ML20207R317
| ML20207R317 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 03/05/1987 |
| From: | Sieber J DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, RTR-REGGD-01.097, RTR-REGGD-1.097 GL-82-33, NUDOCS 8703170101 | |
| Download: ML20207R317 (4) | |
Text
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Telephone (412) 393-6000 Nuclear Group
[nSpp*7ano,1, PA 15077-0004 March 5, 1987 d
U. S. Nuclear Regulatory Commission Attn:
Document Control Desk Washington, DC 20555
Reference:
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Generic Letter 82-33, Supplement 1 to NUREG-0737, Regulatory Guide 1.97, Revision 2, Response to Interim Review Results Gentlemen:
By letter dated January 7,
- 1987, the NRC transmitted to the Duquesne Light Company (DLC) the Beaver Valley Unit 1 interim review results and request for additional information on instrumentation to follow the course of accidents.
The review results identified items for which the NRC could not conclude that adequate justification was provided and r
uested a
response to those items within 45 days of receipt of the 1 er.
Upon receipt of the NRC interim results, we began evaluating the identified items to determine what additional information is needed.
- However, we have not had sufficient time to prepare all the additional information in support of either compliance with the NRC resolutions to the identified items or the DLC justifications for the plant specific exceptions.
So that we may properly complete our
- effort, we are requesting a
30-day extension period for our response.
The attachment to this letter provides an item for item status summary of our review efforts.
This summary is provided for information only and includes some of our preliminary findings.
If acceptable, we will submit our complete response by April 3, 1987.
If you have any questions regarding this submittal, please contact myself or members of my staff.
Very truly yours, D. Sieber Vice President, Nuclear 8703170101 B70305 PDR ADOCK 05000334 P
PDR 0
g0lh J
o Benver Valley Powsr StOtion, Unit No. 1 Dock 3t No. 50-334, Licents No. DPR-66
. Generic Letter 82-33; Supplement 1 to NUREG-0737 Page 2 cc: Mr. W. M. Troskoski, Resident Inspector U. S. Nuclear Regulatory Commission Beaver Valley Power Station Shippingport, PA 15077 U. S. Nuclear Regulatory Commission Regional Administrator Region 1 631 Park Avenue King of Prussia, PA 19406 Mr. Peter S. Tam U. S. Nuclear Regulatory Commission Project Directorate No. 2 Division of PWR Licensing - A Washington, DC 20555
- Mail Stop 340 Addressee only Director, Safety Evaluation & Control Virginia Electric & Power Company P.O. Box 26666 One James River Plaza Richmond, VA 23261 l
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- 6 A T T A'C H'M E N T Status Summary of DLC Review of Items Identified in Section 4 of.the Technical Evaluation Report Conformance to Reg. Guide 1.97, BVPS-1 J
Additional information is being gathered for 1.
Neutron Flux determining the most appropriate DLC resolution to this item.
2.
Containment Isolation Position
- DLC ha templeted a listing of information for each identified valv Josition indication which is under review.
1 3&4 RHR Flow and Heat Exchanger outlet temperature - Under review.
5.
Accumulator Tank Level and Pressure - Under review.
6.
Low Pressure Safety Injection Flow DLC is considering providing qualified instrumentation for this item.
Our review shows'that Heater 7.
Pressurizer Heater Current current information for each heater bank is available in the control room via computer.
We believe that this information in addition to heater breaker status will adequately resolve this item.
8.
-Quench tank level
- Our review has determined that the level indication range extends to approximately 95% of-total tank volume.
We
- believe, therefore, that the level indication range will be found' adequate.
9.
Condensate Storage Tank Water Level - There is no tank with this designation at BVPS-1.
The primary source of auxiliary feedwater is the primary plant demineralized water storage tank.
Water can also be supplied by the river water pumps on 4
the engine-driven fire pump via one of the river water system headers.
10.
Primary Plant Demineralized Water Storage Tank Level - Under Review.
11.
Heat Removal by Containment fan heat removal system - For BVPS
-1, the containment depressurization system is composed of two groups of subsystems:
the quench spay subsystems and the recirculation spray subsystems.
These systems are designed to provide the necessary cooling and depressurization of the containment after any LOCA.
Information for the subsystem variables was provided under containment spray flow in our l
R.G.
1.97 Report.
We believe that this will be found an acceptable resolution.
4 Attcchment Paga 2 12.
Containment Atmosphere Temperature - Our review shows that the BVPS-1 UFSAR Table 5.5-5 "FSAR Hot Leg DER in Summer" indicates-the peak containment temperature during extended auxiliary feedwater flow through a faulted steam generator is 269.3*F.
Therefore, we believe that the existing containment atmosphere temperature indication range of 0 to 300*F will be found acceptable.
13 & 14 CCW temperature and flow to ESF System - Under review.
- 15. Radioactive gas holdup tank pressure - DLC is evaluating the re-arrangement of this instrumentation according to the NRC recommendation provided in the TER.
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