Георгій Балакан

Народився 9.06.1962. Українець. Мова: українська, російська - вільно, english-технічний -Інженер-теплоенергетик, атомні станції та установки. Одеський політех -Спеціальний курс навчання в Westinghouse (USA) за функціональною проектування системи SPDS для реакторних установок ВВЕР-1000 -Спеціальний курс навчання в Westinghouse (USA) за функціональною проектування системи SPDS для реакторних установок ВВЕР-1000 International Nuclear Safety Program, SAIС і PNNL USA -Спеціальний курс навчання в компанії Westinghouse (USA) по розробці та обґрунтуванню сімтомно-орієнтованих аварійних інструкцій і аварійних інструкцій управління важкими аваріями

Спеціалізація

• Комплексні інженерні питання, технічна експертиза;

• Аналіз безпеки, досвіду експлуатації АЕС;

• Перемовини з виробниками обладнання, постачальниками робіт та послуг для СВБ АЕС;

Досвід

2019-наст час. Експертні послуги по підтримці проектів ANL USA в ядерній галузі України, та аналізу ліцензування проектів SMR в США та Канаді.

2014-2019 Енергоатом. Радник президента

2013-2014 Державна Інспекція Ядерного Регулювання України. Позаштатний радник голови

2006-2013 ПУАЕС. Головний спеціаліст з енергетичних реакторів-Керівник служби інженерно-технічної підтримки

2004-2006 Заступник головного інженера з технології та інжинірингу ПУАЕС, радник президента Енергоатом

2000-2004 ПУАЕС. Керівник служби інженерно-технічної підтримки

1984-2000 ПУАЕС. Начальник зміни блоку, Начальник зміни реакторного цеху, Старший інженер управління реактором, Старший інженер з експлуатації реакторного відділення, Оператор спеціального водоочищення, оператор реакторного відділення

Навички

• Експлуатація обладнання АЕС;

• Стратегічне планування;

• Управління персоналом;

• Управління проектами модернізації та підтримання експлуатаційної надійності АЕС, інжинірингом та модифікаціями обладнання й систем АЕС;

• Технічні знання по технології легко-водяних SMR;

• Управління міжнародними проектами зі співробітництва та комерційними проектами модернізації АЕС та технічної допомоги;

• Проведення переговорів з вітчизняними та іноземними партнерами;

• Розробка та впровадження програм і проектів модернізації АЕС для підвищення безпеки, підтримання експлуатаційної надійності та ефективності АЕС ;

• Проведення розслідувань причин інцидентів і аварійних подій;

• Аналіз і розробка проектів модифікації АЕС, організаційна робота з проектними та інжиніринговими організаціями і інститутами;

• Управління закупівлями обладнання для АЕС;

• Навчання персоналу, оцінка персоналу, професійний підбір персоналу;

• Розробка та впровадження мотивації персоналу, найм та адаптація співробітника;

• Розробка, аналіз, технічне та аналітичне обґрунтування інструкцій по стратегіям управління аваріями, експлуатаційних керівництв, технічних регламентів та іншої документації експлуатації АЕС;

• Функціональне проектування інформаційно обчислювальних систем і систем аварійної підтримки оператора блочного щита АЕС та центрів управління;

• Обґрунтування і захист в регулюючих органах змін проектних основ АЕС і їх модифікацій, досвід по взаємодії з науково-технічним супроводом експертиз,

• Виконання технічних експертиз для МАГАТЕ;

• Рішучість та наполегливість у впровадженні та управлінні змінами;

• Стресостійкість.

Міжнародні проекти

1. ANL-ARB-04/23.200.ОD.00 Argonne National Laboratory Technical Assistance to ENERGOATOM/ZNPP. Cooling of the reactor core in conditions of loss of power supply to safety systems, April 2023

The need for performing this work arose due to the russia’s unprovoked military invasion of Ukraine, capture of the Zaporizhzhya nuclear power plant (ZNPP) and long-continued shelling of its territory by the military of the aggressor country.

Due to a series of shelling of ZNPP structures and equipment, and external power lines, the Ukrainian operating company SE “NNEGC “Energoatom” was forced to shut down all six power units of the plant. This was caused by the existence of real threat of further shelling by the russian federation, which could lead to a complete loss of off-site power and significant risks to nuclear and radiation safety of the NPP. With these conditions, there is also a threat of complete loss of power supply to NPP safety systems in case of insufficient diesel fuel or loss of service water due to common cause. The SG mobile makeup systems - MNU500 are vulnerable to failures during shelling and may be unavailable for the ZNPP operational personnel if they are stolen by the russian army for transportation purposes.

The existing emergency response strategies did not envisage such sequence of failures or viewed them as impossible. The hostilities, occupation and loss of control by Ukraine have significantly changed our understanding of the principle of a single failure, a common cause failure and a deliberate failure, which can be provoked by the russian military and russian specialists, who are well versed in technology and capable of a crime that overrun equipment capabilities and strategies, applied before the war.

The loss of the Kakhovka reservoir and possible loss of the cooling pond near the ZNPP result in impossibility to ensure water in the spray pools of the safety systems, create new threats and require searching for new sources of water, alternative use of the existing and new equipment, and non-trivial solutions and strategies to maintain the safety functions of the ZNPP power units.

Completely new conditions have occurred for the long-term feeding of steam generators during operation of the ZNPP power units, especially in case of long-term feeding with water, which has a reduced quality of chemical composition. This challenges the integrity of SG tubes being a physical boundary between the primary and secondary coolant. Moreover, the long-term SG feeding with the service water can result in a loss of the safety function - heat removal through the secondary circuit, and even a complete and permanent loss of SGs.

Taking into account that ZNPP reactor facilities were not operated at power for more than 7-12 months, the low level of energy release in the core gives new possibilities for heat removal from the reactor, as well as greater time span before the beginning of uncompensated loss of the primary coolant and beginning of the core damage, with a complete loss of safety systems for removing heat from the reactor core and loss of mobile SG makeup systems.

Under such circumstances, there is an urgent need to evaluate alternative ways to ensure heat removal from the reactor core using more flexible approaches to emergency response strategies. The options for accomplishing the task include cooling the primary coolant in the steam generator by injecting water (from the mobile pump station) or air (through the open hatch manhole of the steam generator) to the SG secondary circuit.

The report presents the results of Stage 2 of the work, consisting of the following tasks:

Task 3: Assessment of the possibility of removing decay heat from the core of the sealed reactor without exceeding the upper limit of the temperature and pressure of the primary circuit in the natural circulation mode with heat removal through the steam generators by air cooling the outer surface (secondary circuit) of the tubes of all SGs using the air from the containment (CTMT) with its further removal through steamlines and steam dump valves to the ultimate heat sink (UHS) - the atmosphere of the external environment;

Task 4: Assessment of the possibility of removing decay heat from the core of the sealed reactor in the natural circulation mode with heat removal through the steam generators in water-to-water mode by injecting water to one steam generator from the MPS or with heat removal through the steam generators in water-air mode by air cooling the tubes of all SGs using the air from the CTMT with its further removal through steamlines and steam dump valves to the ultimate heat sink - the atmosphere of the external environment.

This work is performed in accordance with the “Terms of Reference for Calculation of energy sufficiency for heating the ZNPP and the satellite town of Energodar from main circulation pumps of the ZNPP and assessment of stability of heat removal from the reactor core in the condition of total loss of power supply to the safety systems equipment” under the Contract No. 3F-60028 dated December 2, 2022.

2. ANL-ARB-11/22.100.ОD.00. Argonne National Laboratory Technical Assistance to ENERGOATOM/ZNPP Assessment of providing heating to the plant and the satellite town of Energodar without bringing reactors to criticality. Energy Balance Analysis for Maintaining Parameters for ZNPP House Loads and Providing Heating to Energodar. Dezember 2022.

The need to perform this work is caused by russia’s undisguised military invasion of Ukraine and the shelling of the Zaporizhzhia Nuclear Power Plant (ZNPP), which has been periodically carried out by the military of the aggressor country for a long period of time.

After a series of attacks on the structures and equipment at the ZNPP site and on the external power transmission lines (PTL), NNEGC Energoatom was forced to operate all six ZNPP power units in a shutdown state. This is due to the existence of a real threat of further shelling by russia, which can lead to a complete loss of external power supply to the NPP and the emergence of significant risks for nuclear and radiation safety of the NPP in the event of an attempt to transfer any of the power units to “Operation at power” state.

In such circumstances, there is an urgent need to evaluate the possible ways of providing ZNPP in the winter period of the year with its own needs for thermal energy and heat supply to the city of Energodar. One of the options is to use the heat generated during operation of the main circulation pumps (MCP) in the operating modes that are not associated with bringing the reactor to power. The whole complex of actions required for this is generally well-known and sufficiently experienced by ZNPP personnel, since the use of the heat of the MCP while maintaining the reactor in a subcritical state is carried out, for example, to heat up the reactor facility after the power unit has been shut down for refueling. In addition, there is a good practice of operating in a similar mode one of the power units of another Ukrainian nuclear power plant (of the same type as the ZNPP power units) to supply heat generated by the MCP to the satellite city. Thus, the proposed option of meeting the needs of ZNPP and the city of Energodar in the thermal energy can be considered as principally possible, and the task of the research is to analyze its applicability and effectiveness for the conditions of ZNPP.

This work is performed in accordance with the “Terms of Reference for Calculation of energy sufficiency for heating the ZNPP and the satellite town of Energodar from main circulation pumps of the ZNPP and assessment of stability of heat removal from the reactor core in the condition of total loss of power supply to the safety systems equipment” under the Contract No. 3F-60028 dated December 2, 2022.

3. Development of a Document on Coping Strategies for Long Term Blackout Events at Ukraine NPPs (March 2015-December 2018)

FLEX Procedures complement existing SOIs (Symptom Oriented Instructions) and SAMGs (Severe Accident Guidelines) by enhancing-defense-in-depth for the extended loss of electrical power at NPPs.

Tasks under WO # 0J-30502-0029A involve analytical efforts on development of the list of calculation scenarios that should establish basis for the FLEX procedures development as well as for the definition of FLEX equipment characteristics. The report provides descriptions of the possible FLEX concepts in the case of ELAP for all three types of WWER reactors operated in Ukraine. Report will be distributed among the FLEX meeting participants: NAEK “Energoatom” and its engineering divisions, NPPs and regulatory body with its technical support organization, with the request to provide their opinion on the best concept. 4. Safety Improvement Concept for Ukrainian NPPs with VVER reactors (Dec. 2005 – Dec. 2011)

Author of the list of administrative and technical activities within Safety Improvement Concept for Ukrainian NPPs with VVER reactors (2005), approved by the Decree of the Cabinet of Ministers of Ukraine #515 dated 13.12.05 and accepted for implementation by NNEGC “Enegroatom” and Regulatory Authority. The Concept and list of activities became background documents for safety improvement of Ukrainian NPPs to the end of 2010.

Practically all activities of the Concept were implemented by the end of 2010. In most of the implemented activities I was as the author of the idea so the developer of the concept, organization and justification of its implementation at SUNPP, as well as the developer of the requirements to equipment procurement and reports on implemented activities.

The results of activities implemented at SUNPP Unit 1 were such that for the time of activities accomplished the risk factors of core damage were significantly changed and reduced for more than 160 times. In 2006 the core damage frequency at SUNPP Unit 1 for internal initiators was 1.15*10-4 1/year and at the end of 2010 it was 6.06 10-6 1/year

5. Tacis International Project implemented together with the EU contractor EC-Tractabel #156-01 (soft assistance). (Jan. 2005 – Jan. 2010)

Manager of Tacis International Project implemented together with the EU contractor EC-Tractabel #156-01 (soft assistance) regarding the methodology, development of strategies and severe accident management guidelines for SUNPP Units 1 and 2, but based on the GDF-Suez-Tractebel methodology (from 2005 to 2010);

6. WBS1.01.04.07.04 "Ukraine NPP EOP Project (April 2004 – April 2010)

Project manager (both in the framework of the international project with Westinghouse and separate national project) in development, analytical justification and implementation of symptom-based emergency operating procedures (SBEOPs) for SUNPP Units 1, 2, 3 (from 2005 to 2008). SUNPP was the first plant in Ukraine that implemented EOPs at all power units, although formally the pilot plant in the national project was Zaporizhzhya NPP.

7. Analysis of containment structural integrity at SUNPP Unit 1 for PRA-2 (Jan. 2007 – Dec. 2009)

Project manager for analysis of containment structural integrity at SUNPP Unit 1 for PRA-2 purposes within the contract with GRS (Germany); the project was successfully implemented, the results were used in PRA-2 project, obtained good results in the State Expert Review performed by State Nuclear Regulatory Committee of Ukraine (SNRCU)

8. SAMG SUNPP (Jan. 2008 – Jan. 2009)

By the end of 2008, using Westinghouse methodology, adopted without any help the severe accident management guidelines (SAMGs) to the conditions of SUNPP reactor facility, both with respect to the guidelines and technical background documents.

Developed a special report on accomplishment of activity #6.2 “Development of technical and procedural recommendations on management of accidents with core damage” as per the Safety Improvement Concept for operating power units at SUNPP Unit 1. The report was approved by the Regulatory Authority of Ukraine. Implementation of such severe accident management guidelines (SAMGs) based on Westinghouse methodology is not possible without involvement of Westinghouse.

In my opinion, implementation of the efficient SAMGs is possible only with participation of Westinghouse in this process, like it was accomplished during development and implementation of symptom-based emergency operating procedures for Ukrainian NPPs in 2008.

Ukraine selected another way – development and implementation of severe accident management guidelines based on the methodology which was never implemented and confirmed.

9. Generic Program on Implementation of Risk-Oriented Approaches in Operation and Regulatory Activity at Ukrainian NPPs (Jan. 2002 – May 2006)

Expert–Technologist of the team working of Working Committee of NNEGC “Energoatom” and State Nuclear Regulatory Committee of Ukraine for development of the Generic Program on Implementation of Risk-Oriented Approaches in Operation and Regulatory Activity at Ukrainian NPPs

10. WBS1.02.03.47 Project "SUNPP UL CIS"(Dec. 2004 – May 2006)

Head of Working Group for development of Functional Design of Information Display Means under the framework of the project on replacement of computerized information system at power units 2 of SUNPP into the Westinghouse’s programmed engineering complex WDPF. After that, was the Head of Working Group for development of functional design of computerized information system (CIS) for power unit 3 of SUNPP on the base of Westinghouse’s programmed engineering complex Ovation. All above mentioned CIS replacement (modernization) projects were successfully implemented at power units of SUNPP with further integration of these CISs with SPDS (WBS1.02.03.17 Project) supplied to Ukraine from 1997 to 2000 under the framework of DOE’s International Nuclear Safety Program (INSP);

11. WBS 1.03.01 "NPP Risk and Safety Assessment" (Jan. 1995 – Dec. 2006)

Key Expert – Technologist of the team working in Probabilistic Safety Assessment

12. The pilot SPDS training course for the operators and instructors of the reactor facility VVER-1000 (June 2002 – Dec. 2003)

Expert – Technologist of the team working. Development (under the INSP Program, US DOE) of the training materials for the pilot SPDS training course for the operators and instructors of the reactor facility VVER-1000 (2002);

13. WBS1.01.04.07 "Ukrainian NPP EOP Implementation Project" (2003)

Completed a special training course (under INSP/US DOE Program) in the Belgium branch of Westinghouse Company on the methodology of symptom-oriented management of design-basis and beyond design-basis accidents, including severe accidents, as well as development of symptom-based EOPs, analytical justification and setpoint justification for EOPs

14. Development of normal and abnormal operation procedures for SUNPP

(Jan. 2001 – Dec. 2002)

Key Expert–Technologist of the team working in Tacis International Assistance Project “Development of normal and abnormal operation procedures for SUNPP”

15. WBS 1.01.02.08 Modernization of simulators for SPDS (May 2001 – Dec. 2002)

Provided expert support in SPDS setup on full scope simulators (FSS) at power units 1 and 3 of SUNPP.

16. WBS1.02.03.17 Project "Safety Parameters Display System for Ukrainian VVER-1000 reactors", International Nuclear Safety Programe USA (Jan. 1998 – Dec. 2002)

Head of SPDS functional design at power units 1, 2 and 3 of SUNPP, functional putting of SPDS into trial operation (1998-2000) with further putting into commercial operation (2001);

17. EOPs for VVER reactors (INSP Program, in SAIC Company and PNNL USA)

(Jan. 2000 – Feb. 2002)

Completed the training course on analytical justification of symptom-oriented emergency operating procedures (EOPs for VVER reactors (INSP Program, in SAIC Company and PNNL USA)

18. WBS1.02.03.17 Project "Safety Parameters Display System for Ukrainian VVER-1000 reactors", International Nuclear Safety Programe USA (Oct. 1997 – Dec. 1998)

Under the framework of International Nuclear Safety Program (INSP) of the Department of Energy of the USA (US DOE) took a special training course in Westinghouse Company (USA) on functional design of SPDS system (safety parameters display system) for Ukrainian VVER-1000 reactors

19. WBS1.02.03.17 Project "Safety Parameters Display System for Ukrainian VVER-1000 reactors", International Nuclear Safety Programe USA (Jan. 1998 – Dec. 1998)

Functional design of SPDS video cards for “pilot” SPDS at Khmelnitskiy and Zaporizhzhe NPPs

20. “Lisbon Initiative” Working Group 4: Development of Normal Operation and Abnormal Operation Guidelines for VVER-1000 Reactors (May 1998 – Oct. 1998)

Participated in the International Nuclear Safety Program “Lisbon Initiative” within Working Group 4: Development of Normal Operation and Abnormal Operation Guidelines for VVER-1000 Reactors

21. Tacis project “Establishment of Electricity Market” (Sept. 1996 – Oct. 1996)

Completed the training course in Nuclear Electric Company (England) under the framework of Tacis project “Establishment of Electricity Market”