ML17331A759
| ML17331A759 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 06/04/1981 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | Dolan J INDIANA MICHIGAN POWER CO. |
| Shared Package | |
| ML17319A938 | List: |
| References | |
| IEB-79-06A, IEB-79-6A, NUDOCS 8107080587 | |
| Download: ML17331A759 (7) | |
Text
It Docket Nos. 50-5 an 0-31 JUg 0 4 pe~
Hr. John Dolan, Vice President Indiana and Hichigan Electric Company
',Post Office Box 18 Bowling Green Station New York, New York 10004 DISTRIBUTION Dockets NRC PDR PDR TERA NSIC ORBg)
Rdg DEisenhut OELD IE-3 ACRS-10 SVarga SNner CParrish Gray File
Dear fir. Dolan:
ife have qampleted a review of the information you have provided in.
letters dated flay l, 1979, June 6, 1979, June 25, 197)t; Ju'ly 25, 1979, SeptettIher 17. 1979 and October 11, 1979 in response to IE Bulletins79-06A and 79-06A Revision 1 for the Donald C.
Cook Nuclear Plan),
Unit Hos.
1 and 2.
The enclosed Safety Evaluation addresses the complete-ness and acceptability of the responses.
Your responses to IE Bul'tetin 79-06C-; regarding the operation of the reac-tor coolant pumps following a loss-of-coolant accident will be reviewed separately as part of"Task Action Plan Item II.K.3.5.
Sincerely, ppiginal signed SKI S ~ A. Var~~
Enclosure:
Safety Eva)uation cc w/enclosure See next page Steven A. Varga, Chief Operating Reactors Branch 81 Division of Licensing'
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O. C. 20555 June 4, 1981 Docket Nos.
50-315 and 50-316 Mr. John Dolan, Vice President Indiana and Michigan Electric Company Post Office Box 18 Bowling Green Station New York, New York 10004
Dear Mr. Dolan:
We have completed a review of the information you have provided in letters dated May 1, 1979, June 6, 1979, June 25, 1979, July 25, 1979, September 17, 1979 and October ll, 1979 in response to IE Bulletins79-06A and 79-06A Revision 1 for the Donald C.
Cook Nuclear Plant, Unit Nos.
1 and 2.
The enclosed Safety Evaluation addresses the complete-ness and acceptability of the responses.
Your responses to IE Bulletin 79-06C, regarding the operation of the reac-tor coolant pumps following a loss-of-coolant accident will be reviewed separately as part of Task Action Plan Item II.K.3.5.
- cerely,
Enclosure:
Safety Evaluation cc w/enclosure, See next page arga ief C
Operating Reactor Branch 81 Division of Licensing
ndi ara and Mich icon Electric Co~~any CC:
t",r. Robert W-Jurgensen Chief t>uClear Engineer
'American Electric Power Service Corporation 2 Broadway ttew York, New York 10004 C.:raid Cnarnoff, squire Shaw, Pittman, Potzs and Trowbridge 1800 M S.ree;, N.l.
ti'ashinq on',
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20036 ttaude Preston Palehske ttemorial Library 500 itarket Street S. Jose"h, Michigan 49085 Nr. 0. Shaller, Plant t3anager Donald C.
Cook Nuclear'Plant P. 0.
Box 458
- Sridgman, Michigan 49106 U. S. nuclear Reculatory Ccr;..'.ssion Resident inspectors 0 fice 770 P,ed Arrov: Highway Stevensville, Michigan 49127 t'ill'am J.
- Scanlon, Esquire 2034 Paul i ne B ou 1 eva rd Ann Arbor, Michigan
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555
'SAFETY 'EVAL'UATION'BY 'THE "OFFICE 'OF 'NUCLEAR REACTOR REGULATION
'FOR
'NDIANA AND 'MICHIGAN 'EL'ECTRIC 'COMPANY DONALD C.
COOK NUCLEAR PLANT, UNIT NOS.
1 AND 2
'DOCKET'NOS: '50-315 AND '50-316 INTRODUCTION On March 28, 1979 the, Three Mile Island Nuclear Power Plant, Unit 2 (TMI-2) experienced core damage which resulted from a series of events which were initiated.by a loss of feedwater transient.
Several aspects of the acci-dent have generic applicability at operating Westinghouse reactors.
On April 11, 1979, IE Bulletin 79-06 was sent to all We'stinghouse operatiIIg plant licensees.
The purpose of the Bulletin was to provide information concerning the accident at TMI-2 and to request certain actions be taken by licensees to preclude a similar occurence at their facilities.
This bulletin was superseded and expanded by IE Bulletin 79-06A dated April 14, 1979 and by IE Bulletin 79-06A Revision 1 dated April 18, 1979.
By letters dated May 1, 1979, June 6, 1979, June 25, 1979 July.'25,
- 1979, September 17, 1979 and October 11,.1979, the licensee provided responses in conformance with the requirements of the Bulletins.
'EVALUATION In the two year period since the Bulletins have been implemented we have
- observed, in addition to our review of the responses enumerated
- above, that the licensee has complied with all the following provisions of the Bulletins:
- Understanding of the TMI-2 sequence of events.
- Review Plant Procedures for coping with accidents and transients
- By review of procedures and training instructions:
(1} to avowed overriding automatic action of ESF, (2} to keep high pressure injection (HPI) system in operation for,at least 20 minutes and to maintain 50'F subcooling margin, (3} to correlate HPI initiation with reactor coolant pump (RCP) opera-tion, and (4} to train operators not to rely on pressurizer level only, to deter-mine primary coolant inventory.
- Verification of emergency feedwater (EFM) valve positions and all safety-related valve positions to ensure proper operation of EFW arid ESF.
- By review of containment isolation initiation and design for avoidance of isolating lines that are needed to avoid degraded core cooling capability.
- By preparing and implementing procedures for all valves which could defeat or compromise:flow of EFH.
- By reviewing operating modes and procedures to prevent inadvertent pumping of radioactive gasses and liquids out of the primary containment.
- By reviewing procedures related to maintenance and test of safety-related systems to:
0 ) verify operability of redundant system prior to removal of any system from service, (2) verify operability of all systems following maintenance or testing, an'd (3) verification to operating personnel whenever a system is removed from or returned to service.
- By developing procedures and training operators to establish and maintain natural circulation.
- By training operators to take into account reactor vessel integrity con-siderations during any accident or transient.
- By performing analyses and design modifications to reduce the likelihood of automatic PORV actuation during anticipated transients.
/
- By providing procedures and training operators for a prompt manual reactOr trip for transients that result in a pressure increase'in the reactor coolant system.
- By providing for prompt reporting within one hour of the time the reactor is not in a controlled or expected condition of operation.
- By proposing any needed Technical Specification changes to implement any of the above parts of the Bulletins.
CONCLUSIONS Based on our review of the information provided by the licensee in response to IE Bulletins79-06A and 79-06A Revision 1, we conclude that the licensee has acceptably responded to these Bull.etins.
The actions taken by the licensee demonstrate its understanding fo the concerns and implications of the Tt)I'-2 accident as they relate to the Donald C.
Cook Nuclear Plant, Unit Nos.
1 and 2.
These actions have resulted in added assurance for the continued protection of thei~public health and safety during plant operation.
Dated:
t gag 22 Q9'l