ML20236B769
| ML20236B769 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 10/12/1987 |
| From: | Sieber J DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| GL-83-28, TAC-53901, TAC-62955, NUDOCS 8710260341 | |
| Download: ML20236B769 (2) | |
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}VL USNRc-os 7f 2 007 h A 9 38 A
gmg 1,epseee m mee Nuclear Group October 12, 1987 l
P.O. Box 4 Shippingport, PA 15077 0004 U. S. Nuclear Regulatory Commission Attn:
Document Control Desk l
Washington, DC 20555 I
Reference:
Beaver Valley Power Station, Unit No. 1 and No. 2 i
BV-1 Docket No. 50-334, License No. DPR-66 BV-2 Docket No. 50-412, License No. NPF-73 Beaver Valley-Salem ATWS Items 4.2.3 and 4.2.4, Breaker l
Preventative Maintenance (TAC Nos. 53901 and 62955) l J
Gentlemen:
In your letter dated September 4, 1987 you requested additional information related to the Beaver Valley Unit 2 response to items 4.2.3 and 4.2.4 of Generic Letter 83-28..This letter requested that we provide a commitment to qualify our reactor trip breakers through a
life testing program.
This issue was discussed at the Westinghouse-l Owners Group (WOG)
General Session which was held September 24, 25, 1987.
At that meeting, it was decided to refer this matter to the WOG Technical Specification Subcommittee.
The Subcommittee will be meeting later this fall.
Following this meeting, we will provide you with a more specific action plan.
A similar request for additional information was received for Beaver Valley Unit 1
in a
After receiving this ' letter, the basis for requiring life cycle testing on 1
the reactor trip breakers was discussed with the Staff.
10 CFR
.I 50.55a(h) was provided as the basis.
10 CFR 50.55a(h) is applicable only to plants with construction permits issued after January 1, 1971.
We therefore questioned why this requirement is applicable to l
)
Beaver Valley Unit 1
since Unit l's construction permit was issued prior to this date.
The Staff stated that this would be reviewed further.
The Unit 1
response to this item has therefore not been I
prepared until further clarification on the basis and applicability to Beaver Valley Unit 1 for this requirement is provided.
If you have any questions on this subject, please contact my i
office.
)
l Very truly yours, 1
2 l
8710260341 871012-Vice President, Nuclear J
I PDR ADOCK 05000334 pC[-
P PDR
7-,--____.
l Beaver Valley Power Station, Unit No. 1 and No. 2 I
BV-1 Docket No. 50-334, License No.-DPR-66 BV-2 Docket No. 50-412, License No. NPF-73 Beaver Valley-Salem ATWS Items 4.2.3'and 4.2.4, Breaker Preventative Maintenance (TAC Nos. 53901 and 62955)
Page 2 l
cc:
Mr. F.
I. Young, Sr. Resident Inspector (Unit 1)
Mr. J.
Beall, Sr. Resident Inspector (Unit 2)
Mr. W. T. Russell, NRC Region I Administrator Mr. P. Tam, Project Manager Director, Safety Evaluation & Control (VEPCO) 1
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