ML19344A372
| ML19344A372 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom |
| Issue date: | 07/14/1980 |
| From: | Gallagher J PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| IEB-80-17, NUDOCS 8008200031 | |
| Download: ML19344A372 (3) | |
Text
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PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET P.O. BOX 8699 PHILADELPHIA. PA.19101 JOSEPH W. G ALLAGM ER stseems e oouc't o$ es, news,
12151 841 50o3
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July 14, 1980 Re: Docket Nos. 50-277 50-270 IE Bulletin 80-17 Mr. Boyce H. Grier Office of Inspection & Enforcement Region I US Nuclear Regulattory Commission 631 Park Avenue King of Prussia, PA 19406
Dear Mr. Grier:
This letter is our second response to IE Bulletin 80-17, forwarded to us on July 3, 1980, concerning the failure of 76 of 185 control rods to fully insert during a scram at a BWR.
This response addresses items 6.c and 7.
The " Actions to be Taken By Licensees" and our responses are treated sequentially.
Actions to be Taken by Licensees 6.
In order to mitigate the consequences of an ATWS event, enhanced operability of HPCI, RCIC, SLCS, RPT/RHR/ pool cooling and main steam bypass is essential.
Accordingly, the following actions are requested:
c.
Perform a 50.59 review of increase SLCS flow to the maximum consistent with safety (2 pumps, unless unsafe).
Response
Philadelphia Electric Company Engineering Department in conjunction with General Electric and Bechtel Power Corporation is performing the required 50.59 review.
8 0 08 2 00 O'S I
Mr. Boyco H. Grior Pago 2 7.
For plants without ATWS related RPT, perform an analysis of the net safety of derating such that, in the event of an ATWS, calculated peak pressures do not exceed the service Level "C"
limit (ev/1500 psig) by taking into consideration the heat removal capability of safety valves, isolation condenser bypass to the main condenser and other available heat removal systems.
Response
Philadelphia Electric Company (PECO) has had previous communication with the Nuclear Regulatory Commission (NRC) concerning Recirculation Pump Trips (RPT) with respect to ATWS.
Our most recent information concerning ATWS related RPT was transmitted by a letter from E. J.
Bradley (PE) to T. A.
Ippolito (NRC), dated July 14, 1978.
In accordance with the information transmitted by this letter, Peach Bottom Units 2 and 3 have ATWS related RPT and therefore an analysis of the net safety of derating is not r.a q u i r e d.
Should you have any questions or require additional information, please do not hasitate to contact us.
Very truly yours, g.w. k u p cc: NRC Office of Inspection and Enforcement Division of Reactor Operations Inspection Washington, DC 20555
COMMONWEALTH OF PENNSYLVANIA :
ss.
COUNTY OF PHILADELPHIA i
J.
W.
Gallagher, being first duly sworn, deposes and says:
That he is Manager of the Electric Production Department of Philadelphia Electric Company; that he has read the foregoing response to IE Bulletin 80-17 and knows the contents thereof; and that the statements and matters set forth therein are true and correct to the best of his knowledge, information and belief.
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Subscribed and sworn to before me this /[#' day l
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