ML20073M034
| ML20073M034 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 04/12/1983 |
| From: | Carey J DUQUESNE LIGHT CO. |
| To: | Varga S Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20073M038 | List: |
| References | |
| TAC-51308, NUDOCS 8304210396 | |
| Download: ML20073M034 (2) | |
Text
%F Telephone (412) 391-6000 Nuclear Division P.O. Dox 4 April 12, 1983 Shippingport, PA 15077-0004 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Attn:
Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 Division of Licensing Washington, DC 20555
Reference:
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Snubber Technical Specifications Clarification Gentlemen:
This letter is to formally document the April 7, 1983 telephone conversation between members of your staff and K. D. Grada of Duquesne Light Company concerning clarification of snubber technical specifica-tions. The discussion concluded that the suggested clarifications to Section 3.7.12 were acceptabic to your staf f and that we would formally submit the changes for approval. The revised pages identifying the clarification statements are attached for your review. The revisions are as follows:
1.
The applicability statement for Section 3.7.12, to identify snubbers required to be operable in Modes 5 and 6 was revised to incorporate a clarification note "These systems are defined as those portions or sub-systems required to prevent releases in excess of 10 CFR 100 limits."
2.
Surveillance Requirement 4.7.12.f was revised to include a note to clarify the snubber service life baseline "For purposes of establishing a baseline for the determination of service life monitoring, this program will be implemented over three successive refueling periods."
It was determined that no additional fee above the Class III fee previously remitted for Amendment No. 49 is required and that no safety evaluation is required since this is a clarification of an existing Technical Specification.
We are anticipating future licensing action relative to this speci-fication concerning large bore Bergen Patterson snubbers. The maintenance e f fo rts involved in functional testing these units represents significant radiation exposure and capital expenditures, presently estimated at 2.8 million dollars for this outage, fd 8304210396 830412 gDRADOCK 05000334 PDR 1
. _. =. _..
Beaver Valley Power Station, Unit No.1
- Docket No. 50-334, License No. DPR-66 Snubber Technical Specifications Clarification Page.2 i
During the third refueling outage, expected to begin in June, 1983, we will replace the seals in all 36 Bergen Patterson snubbers.
These snubbers are mounted on the steam generator and reactor coolant pump supports. This will be done to establish the baseline reference data for snubber service life monitoring, therefore, these snubbers will not be part of.the sample included in the snubber inspection program for the third refueling outage.
Very truly ours, J. J. Carey Vice President, Nuclear cc:
Mr. P. Tam, Project Manager U. S. Nuclear Regulatory Commission Phillips Building Washington, DC _20555
- Mail Stop 438 -
Mr. W. M. Troskoski, Resident Inpsector U. S. Nuclear Regulatory Commission Beaver Valley Power Station Shippinport, PA 15077 U. S. Nuclear Regulatory Commission c/o Document Management Branch Washington, DC 20555 1
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