ML17250A521
| ML17250A521 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 08/25/1980 |
| From: | White L ROCHESTER GAS & ELECTRIC CORP. |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8009020086 | |
| Download: ML17250A521 (10) | |
Text
R EGULATORYQNFORiNATION DISTRIBUTION SEN (RIDE)
CCESSION NBR:8009020086 DOC ~ DATE: 80/08/25 NOTARIZED:
NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Planti Unit 1~ Rochester G
05000244 AUTH BYNAME AUTHOR AFFILIATION
@HI TE E L. D.
Rochester Gas 8 Electric Corp.
RECIP ~ NAME REC IP IENJ AFFILIATION, CRUTCHFIELDED ~
Operating Reactors Branch 5
SUBJECT:
Forwards documentation of, implementation of NRC 800828 suggestions re ooerato,r licensing requirements'hift ma'nning requirementsEresulting from TMI action plan~will be responded to in separate ltd DISTRIBUTION CODE: Aoois COPIES RECEIVED:LTR ENCL SIZE:
TITLE: General Distribution for after Issuance of Oper ating Lic NOTES:1 copy:SEP Sect.
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05000244 RECIPIENT ID CODE/NAME ACTION!
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. t yszzzzu ysuzszn i) ziiijgg'zii zsez ii uzza8i~ iiIriuu ROCHESTER GAS ANO ELECTRIC CORPORATION LEON D. WHITE, JR, VICE PAESIDENT i
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89 EAST AVENUE, ROCHESTER, N.Y. 14649 TELEPHONE AREA CODE 7ld 546-2700 August 25, 1980 Director of Nuclear Reactor Regulation Attn:
Mr. Dennis N. Crutchfield, Chief Operating Reactors Branch C5 U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
Five Additional TNI-2 Related Requirements R. E. Ginna Nuclear Power Plant Docket 50-244
Dear Nr. Crutchfield:
Darrel Eisenhut's letter dated May 7, '1980 contained licensee action items for operating reactors which are a result of the TMI Action Plan.
We responded on June 13, 1980 to the enclosures of Nr. Eisenhut s letter concerning three of the five additional requirements.
The remaining two requirements concerned shift manning requirements and licensing examinations.
The shift manning requirements had not been published at the time of Nr.
Eisenhut's letter but have recently been received and will be responded to in a separate letter.
Mr. Eisenhut referenced a letter dated March 28, 1980 as giving the requirements for operator licensing.
The March 28 letter did not request a response although we implemented the suggestions in the letter.
Attachment A to this letter documents how we imple-mented the operator licensing requirements.
Sincerely yours, Attachment L.D. White, Jr.
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ATTACHMENT A R.E. Ginna Power Plant Unit No.
1 Rochester Gas 8 Electric Corporation
Response
to NRC letter dated March 28, 1980 (Qualifications of Reactor Operators)
NRC Item A.l.a:
Applicants for senior operator licenses shall have 4 years of responsible power plant experience.
Responsible power plant experience should be that obtained as a control room operator (fossil or nuclear) or as a power plant staff engineer involved in the day to day activities of the facility, commencing with the final year of construction.
A maximum of 2 years power plant experience may be fulfilled by academic or related technical training, on a one for one time basis.
Two years shall be nuclear power plant experience.
At least 6 months of the nuclear power plant experience shall be at the plant for which he seeks a license.
RG&E Response:
Administrative Procedure A-102.13, R.E. Ginna NRC Licensing Training Program was revised on May 2, 1980 to incorporate the above items in step 3.1.2.
NRC Item A.l.b:
RG&E Response:
Applicants for senior operator licenses shall have held an operator's license for 1 year.
Administrative Procedure A102.13, R.E. Ginna NRC Licensing Training Program was revised on May 2, 1980 to incorporate this requirement in paragraph 3.1.2.5.
NRC Item A.2.a:
RG&E Response:
Senior Operator:
Applicants shall have 3 months of shift training as an extra man on shift.
Administrative Procedure A-102.13, R.E. Ginna NRC Licensing Training Program was revised on May 2, 1980 to incorporate this requirement in paragraph 3.2.3.2.1.
NRC Item A.2.b:
RGB Response:
Control Room Operator:
Applicants shall have 3 months training on shift as an extra person in the control room.
Administrative Procedure A-102.13, R.E. Ginna NRC Licensing Training Program was revised on May 2, 1980 to incorporate this requirement.in paragraph
,3.2.3.1.1.
NRC Item A.2.c:
RG&E Response:
NRC Item'A.2.d:
NRC Item A-2e:
Training programs shall be modified, as necessary, to provide:
1)
Training in heat transfer, fluid flow and thermodynamics.
2)
Training in the use of installed plant systems to control or mitigate an accident in which the core is severely damaged.
3)
Increased emphasis on reactor and plant transients.
Administrative Procedure A102.13, R.E.
Ginna NRC Licensing Training Program was revised on May 2, 1980 and the above topics were added to the technical training in step 3.2.1.
Training Center and facility instructors who teach
- systems, integrated responses, transients and simulator courses shall demonstrate their competence to NRC by successful completion of a senior operator examination.
Instructors shall be enrolled in appropriate requalification programs to assure they are cognizant of current operating history, problems, and changes to procedures and administrative limitations.
RGSE Response:
Administrative Procedure'A-102.14, R.E. Ginna Operator Requalification Program was revised May 21,
- 1980, and the requirements of A.2.d and A.2.e are included in step 8.
The program has been submitted to OLB for review.
NRC Item A.3:
RGScE Response:
Facility Certifications Certification completed pursuant to sections 55.10 (a) (6) and 55.33a (4) and (5) of 10 CFR Part 55 shall be signed by the highest level of corporate management for plant operation.
It has always been and will continue to be the policy of R.E. Ginna that all certifications and license renewals be requested and signed by the Vice President of Electric and Steam Production.
NRC Item B:
RG&E Response:
NRC Item C-1:
NRC Examinations No response is required.
These actions are to be taken by the NRC.
Requalification Program Contents of the licensed operator requalification program shall be modified to include instruction in heat transfer, fluid flow, thermodynamics and mitigation of accidents involving a degraded core.
RG&E Response:
NRC Item C-2:
RG&E Response:
NRC Item C-3:
RG&E Response:
NRC Item D:
RG&E Response:
Administrative Procedure A-102.14, R.E. Ginna Operator Requalification Program was revised on May 21,
- 1980, and the above instruction requirements were added to classroom lectures in step 3.
The criteria for requiring a licensed individual to participate in accelerated requalification shall be modified to be consistent with the new passing grade for issuance of a license; 80/ overall and 70/ each category.
Administrative Procedure A-102.14, R.E. Ginna Operator Requalification Program was revised on May 21, 1980 with these new criteria added in s tep 7.
Programs should be modified to require the control manipu-lations listed in Enclosure 4.
Normal control manipulations, such as plant or reactor startups must be performed.
Control manipulations during abnormal or emergency operations must be walked through with, and evaluated by, a member of the training staff at a minimum.
An appropriate simulator may be used to satisfy the requirements for control manipulations.
Administrative Procedure A-102.14, R.E. Ginna Operator Requalification Program was revised on May 21,
- 1980, and the manipulations listed in Enclosure 4 were added in steps 2 and 4.
Iong Range Criteria and/or Requirements These criteria and requirements require additional staff work and/or rulemaking prior to their implementation.
The long range criteria and requirements are being considered for future inclusion in training programs.
The commission's interest in keeping utilities in-formed of future changes is appreciated.
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