ML19247B283
| ML19247B283 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 07/20/1979 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | Finfrock I JERSEY CENTRAL POWER & LIGHT CO. |
| References | |
| NUDOCS 7908080300 | |
| Download: ML19247B283 (5) | |
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' JULY 2 0 n73 Doexet No. 50-219
". I, R. Finfrock, Jr.
Vice President - Generation Jersey Central Power & Light Compar,y "adison Avenue at Punch Bowl Road Marristown, New Jersey 07960
Dear Mr. Finfrock:
D OYSTER CREEK NUCLEAR GENERATING STATION, UNIT NO.1 We are reviewing your submittal dated April 25, 1979 in response to IE Bulletin 79-08. We have detemined that the additional infomation requested in the enclosure is necessary in order to canplete our safety evaluation.
We request tnat responses to the items in the enclosure be forwarded to this office within two weeks of your receipt of the enclosure, which was previously transmitted to you by telecopy. Please contact William F. Kane at (301) 492-7745 if you require additional discussions or clarification regarding the infomation requested.
Si ncerely, Gw DennisZiemann,Chbf Operating Reactors Branch #2 Division of Operating Reactors
Enclosure:
Request for Additional Infomation cc w/ enclosure:
See next page 3 T SQG
- ) \\ J 7908080 M 4
s Mr. I. R.' Finfrock, Jr. JULY 2 0 s 79 CC G. F. Trowbridge, Esquire Shaw, Pittman, Potts and Trowbridge 1A00 M Street, N. W.
Washington, D. C.
20036 GPU Service Corporation ATIN:
Mr. E. G. Wallace Licensing Manager 260 Cherry Hill Road Parsippany, New Jersey 07054 Anthony Z. Roisman Natural Resources Defense Counci 917 15th Street, N. W.
Washington, D. C.
20005 Steven P. Russo, Esquire 248 Washington Street P. O. Box 1060 Toms River, New Jersey 08753 Josenh W. Ferraro, Jr., Esquire Deputy Attorney General State of New Jersey Department of Law and Public Safety 1100 Raymond Boulevard Newark, New Jersey 07012 Ocean County Library Brick Township Branch 401 Chambers Bridge Road Brick Town, New Jersey 08723
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ENCLOSURE OYSTER CREEK REQUESTS FOR ADDITIONAL INFORMATION IEB 79-08 Item No.
1 1.
Provide the date on whien you completed the review of the actions required by item 1 of IEB 79-08.
Item No. 2 1.
Your response did not specify whether you had reviewed citber the design er the procedures for the initiation of containment isolation for all lines penetrating the containment.
Verify that you have completed epch of these actions or provide a schedule for their completion.
2.
Your response indicates that the following lines or systems are not isolated on all automatie initiations of safety injection:
Reactor Water Cleanup Systea Shutdown Cooling System Main Steam Line Crain Line Isolation Condenser Vent Lines Instrument Air Lines Closed Coaling Water Lines Torus Vacuum B r e ak e r Lines Containment Ventilation Exhaust Lines Item No. 2 of IES 73-08 requires isolation of all lines or systems u.41ess it would degrade safety features or cooling capability.
Therefore, provide justification for not isolating these lines or prepare and implement thc necessary changes to isolate these lines as required by the Bulletin.
Provide a schedule for completion of these actions.
Ites No. 4 1.
Describe other redundant information which the operator might have to determine changes in reactor coolant inventory, e.g.,
drywell high pressure, r'dioactivity levels, suppression pool high temperature, containment sump pump operation, etc.
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OYSTE3 CREEK Item No. 4 (Cont) 2.
Clarii ; your response as to waether operators have been instructed to utilize other available in f irmat ion to initiate safety systems.
Provide your schedule for completion of this action.
Item No. 5 1.
Provide a schedule for any actions on item 5 that have not yet been completed.
Item No. 6 1.
Please augment your response to indicate the extent to which position and locking device checks are performed for locked safety systen valves.
2.
Your response indicated that a review of ESF 'nd safety-related procedures, including valve check offs, vill be performed in the future.
Please provide a schedule for the completion of this review.
3.
Your response indicated that maintenance, testing, plant ano system startup, and supervisory periodic surveillance procedures would be reviewed for post-maintenance / surveillance valve position verificatirn.
Please provide a schedule for the completion of this review.
4.
Your response did not clearly indicate that all accessibl> safety-related valves had been inspected to verify proper position.
Nor was a schedule for performing the position verification for all safety-related valves provided.
Please supplement your respoase to provide this information.
Ites No. 7 1.
Provide a complete list of systems designed to transfer radioactive gases or liquids outside of containment.
2.
Provide assurance that inadvertent transfer of radioactive gases or liquids out of containment will not occur oa resettind safety features instrumentation.
3.
Discuss the basis upon which continued operability is assured of the teatures designed to prevent inadvertent transfer of radioactive gases
.ad liquids out of containment.
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OYSTER CREEK Item No.
3, 1.
We understc.nd from your respense that operability tests are performed on redundant safety-related systems prior to removal of any safety =.related system from service.
Since you may be relying on prior operability verification within the current technical specification surveillance interval, operability should be further verified by at least a visual check of the system statua to the extent practicable, prior to removing the redundant equipment from service.
Please supplement your response to provide a commitment that you will reviae your maintenance and test procedures to adopt this position.
2.
It is not clear from your respcase that all involved reactor operational personnel in the oncoming shift are explicitly notified about the status of syst2ms removed from or returned to service.
Please indicate how this information is transferred at shift turnover.
3.
We understand from your response that maintenance, test, and administrative procedures are being reviewed to ferify systems requiring retest are retes;ed prior to the need for operability.
Please provide a schedule for the completion of this review.
Item No. 11 1.
IEB 79-08 required a response to this item by May 15, 1979, and
'> e have
,t o t yet received your assessment.
Please ptopose c'anges, r
as req 2 ired, to chose technical specifications which must be modifiei a; o
result of your implementing i t e ms 1 - 10 of IEB 79-08.
If you nave not identified such changes please indicate that in your response, s
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