ML20051M285

Forwards Addl Info Re NUREG-0737 Action Items I.A.2.1, Upgraded Senior Reactor Operator & Reactor Operator Training & II.B.4,training for Mitigating Core Damage,Per NRC 820318 Request

ML20051M285
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	05/10/1982
From:	Withers B PORTLAND GENERAL ELECTRIC CO.
To:	Clark R Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-1.A.2.1, TASK-2.B.4, TASK-TM TAC-44203, TAC-44553, NUDOCS 8205170327
Download: ML20051M285 (6)

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ex 0 wrers Vce Prescer.t May 10, 1982 Trojan Naelear Plant Docket 50-344 License NPP-1 F) c3

. [d Director of Nuclear Reactor. Regulation g

ATTN:

Mr. Robert A. Clark, Chief

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Operating Reactors Branch No. 3 "O

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U. S. Nuclear Regulatory Commission J '$

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Dear Mr. Clark:

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TROJAN NUCLEAR PLANT NUREG-0737, Items I.A.2.1 and II.B.4 Additional Information on Operator Training Please find attached ado.itional information regarding NUREG-0737, Action Item I.A.2.1 " Upgraded SRO and RO Training" and Action Item II.B.4

" Training for Migitating Core Damage".

This information is submitted to you in response to the NRC letter of March 18, 1982.

Sincerely, d

Bart D. Withers Vice President Nuclear Attachment c:

Mr. Lynn Frank, Director State of Oregon

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Department of Energy gh s

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~8205 70 W 1

P' SW Sa'rr,n Sveet, Por !and. Oregon 97204

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Trojtn Nuclear Plant Mr. Rolert A. Clark Docket 50-344 May 10, 1982 License NPF-1 Page 1 of 5 TROJAN NUCLEAR PLANT Additional Information on NUREG-0737 Action Items I.A.2.1 " Upgraded SRO/R0 Training" 3

II.B.4 " Training for Mitigating Core Damage"__

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NRC Question:

Training procedure.TP-2-1 entitled, " Operator Licenaing Calls for classroom instruction in the areas of-heat transfer, fluid flow, thermodynamics, and mitigation of accidents involving a degraded Core".

Do the instructions contain material as or.tlined in enclosures 2 and 3 of Denton's March 28, 1980 letter? Do these instructions involve 80 contact hours?

(A contat.t hour is a 1-hr in which the course instructor is present or available for instructing or assisting student s; lectures, ser41nars, discussions,

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. problem-solving sessions, and examinations are considered contact 2

periods under this definitior.).

PCE Response:

The license training given to SRO and RO at 7rojan covers the areas of heat transfer, fluid flow, thermodynamics, and mitigation of core damage as outlined in Enclosures 2 and 3 of H. Denton's

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letter of March 28, 1980. Your letter of Farch 18, 1982 implied an NRC requirement of 80 contact hours for license training..Although these instructions do not involve 80 contret hours, the Trojan Training Program complies with NUREG-0737 and H. Denton's letter of March 28, 1980.

2.

NRC Question:

1 Are the lectures and quizzes on the subject of accident mitigation given to Shift Technical Advisors and reperating personnel from the Plant Manager through the operations chain to the licensed operators?

If they are, would you please provide the titles of the people who are trained and an organization chart which illustrates their position in the operations chain?

PGE Response:

l The training program for accident nigitation was developed in accord-ance with the NRC criteria in Enclosure 3 of H. Denton's letter of l

March 28, 1980. The training was t.iven to personnel in the chain of Plant Operations (Plant Manager, Manager of Operations and Maintenance, Operations Supervisor, Assistant Operations Supervisor, Shif t Supervi-sors, Assistant Shift Supervisors, Reactor Operators, and Shift i-

. Technical Advisors). The position of each operations personnel in i-the chain of operation is provirled in Figure 6.2-2, " Facility Organiza-tion" of Appendix A Technical Specifications to the Facility Operating License.

Trojtn Nucicar Plant Mr. Robert A. Clark Docket 50-344 May 10, 1982 License NPF-1 Page 2 of 50 3.

NRC Question:

' Does the training program for operators (TP-2-1) contain an increased emphasis on reactor and Plant transients as called for in enclosure 1 of Denton's March 28, 1980 letter? Does the program address both normal transients and abnormal (accident) transients?

PGE Response:

The license training conducted in accordance with the Training Procedure TP-2-1 covers areas of reactor and Plant transient with an increased emphasis. The areas of Plant transients include both normal and abnormal (accident) transients.

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NRC Question:

Training Procedure TP-2-2 entitled, " Licensee Retraining Program",

calls for instruction in the areas of heat transfer, fluid flow, thermodynamics, and mitigation of accidents involving a degraded core. Do the instructions contain material as outlined in enclo-sures 2 and 3 of Denton's letter of March 28, 1980? Do these instructions involve 80 contac.t hours?

PGE Response:

The Trojan Licensee Retraining Prngram TP-2-2 covers the same area as the License Training Program TP-2-1 as discussed in the PGE i

Response 1 above. Please refer to PGE Response 1 egarding a minimum of 80 contact hours.

5.

NRC Question:

Are your instructors enrolled in a requalification program to assure they are cognizant of current operating history, problems, and changes to procedures and other administrative limitations as required by Item A.2.e in enclosure 1 of Denton's March 28, 1980 letter?

PGE Response:

Instructors are on routing for all the Operational Assessment Reviews j

which are forwarded to the Training Department. A staff meeting held every morning at Trojan keeps-instructors appraised of current, past, and potential operational problems. All safety-related procedure changes are routed to all licensed instructors.

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NRC Question:

For Item II.B.4 provide an outline of the training program for mitigating core damage,. including the number of training hours involved. Your outline can-include any training program which relates to the training for mitigating core damage. Follow the

Troj:n Nuclear Plent Mr. Robert A. Clerk Docket 50-344 May 10, 1982 License NPF-1 Page 3 of 5 guidelines given in enclosure 3 of H. Denton's letter of March 28, 1980 and INPO guidelines for Training to Recognize and Mitigate the Consequences of Core Damage (Document No. STG-01, Rev. 1, January-15, 1981). The NRC requires minimum of 80 contact hours of training for mitigating core damage.

PGE Response:

The following is the outline of the' training program for mitigating core damage. Please also refer to PGE Response 1 regarding the NRC requirement of minimum 80 contact hours of training.

A.

Excore Nuclear Instrumentation (1) Review of source range instruments.

(2) Normal response of source range instruments.

(3) Source range indication during accident conditions.

(4) TMI-2 excore detector response.

B.

Incore Instrumentation (1) Movable incore detector system response to neutrons and gammas.

(2) Effects of movable incore detector response during core voiding and fuel damage.

(3) Review of incore themocouples.

Range, accuracy, %cthods to obtain readings.

(4) TMI-2 incore thermocouples response.

C.

Vital Instrumentation (1) Review of basic instruments-(2) Discussion of failure mechanisms.

(3) Review of important post-accident indication and potential problems and/or failures.

(4) Alternate methods of measuring selected parameters.

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(a) Pressurizer pressure.

(b) Pressurizer level.

(c) S/G level.

Trojan Nuclscr Plant Mr. Robert A. Clark Docket 50-344 May 10, 1982 License NPF-1 Pag? 4 of 5 (d) RCS prese re.

(e) ECCS injection flow.

(f) CVCS letdown flow.

D.

Primary Chemistry (1) Effect on chemistry of accident involving fuel damage.

(2) Problems associated with transferring liquid outside of Containment, importance of leak tight systems.

(3) FSAR analysis of radioactive isotopes in coolant following an accident.

(4) Corrosion effects on primary system following an accident.

E.

Radiation Monitoring (1) Review of instruments, location, and type.

(2) Review of Radiological Emergency Plan procedures on use of detectors for determining extent of core damage and radiation levels in Containment.

F.

Gas Generation (1) Methods of hydrogen generation.

1 (2) Methods of hydrogen removal.

(3) Hydrogen flammability.

(4) Sources of other gases.

(5).- Methods of gas removal from primary system.

(6) TMI-2 hydrogen generation and hydrogen burn.

Additional training in relation to mitigation ot a core-damage accident

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is also given _ in other lectures to operations personnel on the following subjects:

A.

Excore Nuclear Instrumentation.

B.

Incore Instrumentation.

C.

Core Subcooling Margin Monitor.

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- Trojtn Nuclear Plsnt Mr. Robert A. Clark

~ Docket 50-344 May 10,-1982 License NPF-1 Page 5 of 5 1

D.

Reactor Plant Chemistry.

E.

Radiological Controls.

F.

Accident Analysis.

G.

Emergency'and Off-Normal Procedures.

H.

Area Radiation Monitors and Process Effluent Radiation Monitors.

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Radiological Emergency Plan.

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