ML20081F546
| ML20081F546 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 06/04/1991 |
| From: | Helwig D PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9106100487 | |
| Download: ML20081F546 (3) | |
Text
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i, l'Illi,ADEll'ill A EIECTillC COMI'ANY NUCl. EAR GROUP llEADQUARTERS 955-65 CilESTERBROOK HIND.
WAYNE, PA 19087 5691 (2153 640 4 650 June 4, 1991 DAVID R. HEuYlO Docket Hos.
50-277 vcr mesotur 50-278 MCUAR UGNrEnm a SUNCrS License Nos.
DPR-44 DPR-56 U.S.
Nuclear Regillatory Commission Attn Document Control Desk Washington, DC 20555 SUlkTECT:
Peach Bottom Atomic Power Station, Units 2 and 3 Additional Response to March 12, 1991 Meeting on Emergency Diesel Generators
REFERENCE:
(1)
Meeting Summary 3ssued by G.
Y. Suh (NRC) dated March 25, 1991 (2)
Letter from D. R. llelwig (PECo) to U.S. Nuclear Regulatory Commission dated April 15, 1991
Dear Sir:
The purpose of this letter is to pro %ide additional information related to a meeting between the NRC and Philadelphia Electric Company (PECo) held on March 12, 1991.
The subject of the meeting was the Emergency Diesel Generator loading for Peach Bottom Atomic Power Station, Units 2 and 3.
The NRC issued a summary of the meeting in Reference (1).
This summary included the ten Action Items to which PECo agreed at the meeting.
In Reference (2), PECo provided a complete response to seven ot the ten Action Items, our initial response to the remaining three Action Items is provided as an Enclosure to this letter.
As discussed in the Enclosure, final closure of these three Action Items will be the subject of future submittals.
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U.S. Nuclear Regulatory Commission June 4, 1991 PBAPS3 Units 2 and 3 Page 2 Additional Response to March 12, 1991 Meeting on Emergency Diosol Generators i
If you require any additional information, please contact very truly yours, lfy, kvf,fr o c1,< c w. u Enclosure cc T. T. Martin, Administrator, Region I, USNRC J.J.
Lyash, USNRC Senior Resident Inspector, PBAPS I
l Page 1 Peach Bottom Atomic Power Station, Units 2 and 3 Additional Response to March 12, 1991 Meeting on Emergency Diesel concrators Action Item (5):
Confirm that the Emergency Diesel Generator (EDG) ratings are based on an appropriate consideration of plant specific installation paramotors such as ambient room temperature, combustion air temperature and cooling water temperature.
Action Item (6):
Confirm with the EDG manufacturer that the EDG ratings are valid given plant specific installation parameters.
Response to Action Items (S) and (6):
We havn performed a comprehensive scarch of our internal records and determined that plant specific parameters such as the design combustion air temperature, cooling water flow rate and temperature, ambient air temperature, etc., have boon considered in the development of the EDG ratings by our EDG manufacturer.
Specifically, the 30-minute rating of 3250 kW has been recently confirmed by the manufacturer for a combustion air temperature of 110*F, a raw water temperature of 90*F, and a raw water flow rate of 700 GPM.
These conditions bound plant design environmental conditions.
The manufacturer has thus far boon unable to provide specific documentation which demonstrates that the continuous, 200-hour, and 2000-hour ratings envelope plant design conditions.
This information will be reconstructed as a part of our design basis reconstitution effort and is expected to be concluded by October 15, 1991.
Action Item (B):
Complete an ongoing reevaluation of EDG testing practices and requirements, with the submittal of an associated Technical Specifications Change Request.
Response to Action Item (8):
In our initial response to this Action Item, we stated that a commitment to a submittal date of the Technical Specifications Change Request (TSCR) resulting from our review of current EDG testing associated Technical Specifications would be provided by May 31, 1991.
Accordingly, we commit to submittal of the appropriate TSCR by December 2, 1991.
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