ML19343C454
| ML19343C454 | |
| Person / Time | |
|---|---|
| Site: | North Anna |
| Issue date: | 03/16/1981 |
| From: | Ferguson J VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Clark R, Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19343C455 | List: |
| References | |
| 119A, NUDOCS 8103240240 | |
| Download: ML19343C454 (2) | |
Text
1-gn g k
'O, N g %g ^N f g VIMUINIA Etr:CTRIC AND POWEH COMI%NY OY efM~
A Ricnwoxn, Vinoss A eneet 4
3 3
s.o,, s.w a
Y
)
\\)A
/.
\\O
% l0 N
JAcz H.Famot:now r._,, u.
n......
March 16, 1981 6
.Mr. Harold R. Denton, Director Serial No. 119A Office of Nuclear Reactor Regulation N0/DCW:ms Attn:
Mr. Robert A. Clark, Chief Docket No. 50-338 Operating Reactors Branch No. 3 License No. NPF-4 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Gentlemen:
AMENDMENT TO OPERATING LICENSE NPF-4 NORTH ANNA POWER STATION UNIT NO. 1 SUPPLEMENT TO PROPOSED TECHNICAL SPECIFICATION CHANGE By our letter dated March 13, 1981 (Serial No. 119) we requested changes to the Technical Specifications for North Anna Unit 1.
The proposed changes deleted four hydraulic snubbers and added one hydraulic snubber to Table 3.7-4 of North' Anna Technical Specifications 3/4.7.10.
The proposed changes as described below supplement our license amendment application referenced above.
As a result of the ARS reanalysis, additional modifications were made to the supports of the feedwater piping system in the main steam valve house and the Safety Injection piping in the safeguards building.
These changes involved the replacement of snubbers WFPD-HSS-219, 220 and 221, and snubbers SI-HSS-100A and 100B with rigid supports. As a result of these changes snubbers 219, 220 and 221 at. location WFPD-282-MSVH and snubbers 100A and 100B at location SI-256-SG should be deleted from Table 3.7-4 of North Anna Unit 1 Technical Specifications.
The replacement of these snubbers with rigid supports does not decrease the margin of safety, in that these changes were made to reduce pipe stresses and loading expected on this piping during a seismic event or during accident conditions.
-This request has _been reviewed and approved by 'the Station Nuclear Safety and
~ 0perating Committee and the System Nuclear Safety and Operating Committee.
It has been-determine 6 that this request does not pose an unreviewed safety question.
We have reviewed this request in accordance with the criteria in 10 CFR 170.22.
~ ince this request supplements our license amendment application referenced S
above, no additional license amendment _ fee is required.
f 8108240 p g
VanonutA EtrcTn C AMD PowEW COMPANY TO Since approval of this request is requi+c* 4n order for North Anna Unit 1 *a resume. power operation, we would apprec; e your prompt review of this requ -
Very truly yours, D
J. H. Ferguson Executive Vice President Power Attachments:
1.
Proposed Technical Specification Change cc:
Mr. James P. O'Reilly, Director Office of Inspection and Enforcement Region II
(
s L
%