ML20028A387
| ML20028A387 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 11/04/1982 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | Cavanaugh W ARKANSAS POWER & LIGHT CO. |
| References | |
| TASK-2.K.3.25, TASK-TM NUDOCS 8211190360 | |
| Download: ML20028A387 (3) | |
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IM Focket File NRC PDR LPDR Docket flo. 50-368 enhut JHeltemes 0 ELD ELJordan ifr. llilliara Cavanaugh, III Senior Vice President, Energy
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Supply Department PMKreutzer-3 Arkansas Power & Light Company RAClark itle oc Arkansas 72203 7
Dear Mr. Cavanaugh:
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SUBJECT:
REQUEST FOR ADDITIONAL IrlFORMATION - Tl4I ITEM.II.K.3.25, POUER TO PUfP SEALS lie have reviewed your response dated June 28, 1982 regarding TMI Item II.K.3.25, Power to Pump Seals, and find that additional information is r'.cessary in order for us to complete our review. Enclosed is our Request for Additional Information (RAI) regarding this matter which reiterates the staff's position and requests that you identify areas of conformance or deviation from the stated position and provide detailed supporting information regarding the design and operation of the affected cooling-systemsc-Please respond-to the enclosed RAI within 60 days of roccipt of this letter.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than 19 respondents; therefore, OMB clearance under P. L.96-511 is not required.
Sincerely.
Original signed by Robert A. Clark Robert A. Clark, Chief Operating Reactors Branch f3 Division of Licensing
Enclosure:
As stated cc: See next page 8211190360 821104 PDR ADOCK 05000368 P
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- O Arkansas Power & Light Company cc:
Mr. John Marshall Manager, Licensing Arkansas Power & Light Company P. O. Box 551 Little Rock, Arkansas 72203 U.S. Environmental Protection Agency Mr. James P. O'Hanlon Region VI Office General Manager ATTN:
Regional Radiation Arkansas Nuclear One Representative P. O. Box 608 1201 Elm Street Russellville, Arkansas 72801 Dallas, Texas 75270 1
Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 220 -
7910 Woodmont Avenue S. L. Smith, Operations Officer Bethesda, Maryland 20814 Arkansas Nuclear Planning &
Response Program Nicholas S. Reynolds, Esq.
P. O. Box 1749 c/o DeBevoise & Liberman Russellville, Arkansas 72801 1200 Seventeenth Street, N.W.
Washir,Ston, D. C.
20036 Arkansas Polytechnic College Russellville, Arkansas 72801 Mr. Charles B. Brinkman Manager - Washington Nuclear Operations C-E Power Systems 4853 Cordell Avenue, Suite A-1 Bethesda, Maryland 20014 Regional Administrator Nuclear Regulatory Commission, Region IV Office of Executive Director for Operations 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Mr. W. John. son U.S. NRC P. O. Box 2090 Russellville, Arkansas 72801
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REQUEST FOR ADDITIONAL INFORMATION o
TMI ITEM II.K.3.25, POWER TO PUMP SEALS Below is the staff's position on TMI Item II.K.3.25, Power to Pump Seals.
For each item please identify whether or not your plant's design conforms i
to or deviates fra the stated position, In either case, we require that specific design and operating information be supplied in support of your response:
1.' The cooling water supply should be adequate to provide seal cooling and prevent seal failure for a period of two hours during a loss of offsite power event.
2.
RCP seals should be designed such that they are cooled by means of two independent supplies, e.g. seal injection (charging pumps) and thermal barrier heat exchangers (Reactor Building Closed Cooling Water (RBCCW) System).
If plant design consists of only one cooling method, provide detailed design infonnation to. demonstrate that seal integrity is still maintained in the event of a loss-of.-offsite power event.
3.
It is currently our position that automatic loading of the cooling water pumps onto the emergency buses is desirable and should be in-corporated.
The cooling water pumps should be automatically (requiring no operator action) and sequentially loaded onto the diesel generators and aut matically started.
Wrecognize that a number of facilities currently employ manual, 4.
rather than automatic actions, to perform the above functions. In the event that your response deviates from the above position, provide de-tailed justification in support of the position that manual, rather than automatic action, is, sufficient to assure RCP seal integrity.
The system should be designed such that any required operator action complies -
with the draft ANSI-N660, " Time Response Design Criteria for Safety '
~
Related Operator Actions", guidelines.
Justify the acceptablity of the selected time for crediting operator actions.
The response should provide conclusive verification that the integrity of the RCP seals will remain intact during the period of coolant deprivation through the time of coolant restoration,. appropriately accounting for thermal shock to old seals as coolant is reinstated.
If insufficient justification is provided, either additional analyses or applicable. experimental data pertaining to pump seal integrity will be required.
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