ML19296C620
| ML19296C620 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 02/25/1980 |
| From: | Stallings C VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, Schwencer A Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19296C621 | List: |
| References | |
| 141, NUDOCS 8002260729 | |
| Download: ML19296C620 (3) | |
Text
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Vinoix A Er.ucrate Asn Pow n u CoxeAav 11rcu.wou n.Vr uora rA unum February 25, 1980 Mr. Harold R. Denton, Director Serial No. 141 Office of Nuclear Reactor Regulation LQA/WRM:rab Attn:
Mr. A. Schwencer, Chief Operating Reactors Branch No. 1 Docket No. 50-338 Division of Operating Reactors U. S. Nuclear Regulatory Commission License No. NPF-4 Washington, D.C.
20555
Dear Mr. Denton:
AMENDMENT TO OPERATING LICENSE NPF-4 NORTH ANNA POWER STATION UNIT NO. 1 SUPPLEMENT TO PROPOSED TECHNICAL SPECIFICATION CHANGE NO. 26 In a letter dated December 28, 1979, we requested a change to the Technical Specifications for North Anna Power Station Unit No.
1 in response to a NRC letter concerning requirements for auxiliary feedwater systems. Attached are proposed Technical Specification changes to supplement our previous application. These supplemental changes, a result of additional study and review of our previous Technical Specification Change application, address operational con-cerns associated with the requirement for verification of auxiliary feedwater flow paths.
In accordance with the NRC recommended action, Specification 4.7.1.2.c will require flow path verification only during unit startup following a cold shutdown for both the motor driven auxiliary feedwater pumps and the steam turbine driven auxiliary feedwater pump.
The previously proposed Specifications 4.7.1.2.c and 4.7.1.2.d have been deleted. Specification 4.7.1.2.d has been deleted to insure that the steam turbine driven auxiliary feedwater pump is flow tested following a unit cold shutdown instead of each time the unit enters MODE 2 from MODE 3.
The provisions for testing all the auxiliary feedwater pumps prior to entry into MODE 3 from MODE 4 following operation in MODE 5 are now incorporated in the revised Specification 4.7.1.2.c.
The deletion in Specification 4.7.1.2.a.1 is necessitated by the fact that during MODE 1, the steam pressure of 835 psig required for performance of the surveillance requirement is not available; therefore, the surveillance requirement cannot be performed.
The proposed change will facilitate station operations by making it possible to more readily perform the surveillance requirements.
By removing the steam pressure requirement, it will be possible to perform the test in MODE I and still meet the acceptance criteria, p
8002260 f,2f
v Vra<m1A Es.zernic AND Powra COMPANY TO Mr. Harold R. Denton 2
The requested exemption in the ACTION statement is necessary because there is insufficient steam pressure in MODE 4 to perfom the steam turbine auxiliary feedwater pump test required by Specification 4.7.1.2.a.1 for entry into MODE 3.
The surveillance requirement for testing the steam turbine auxiliary feedwater pump will be performed once adequate steam pressure is available in MODE 3.
The proposed changes for testing the ar.xiliary feedwater pumps will not decrease the margin of safety associated with the auxiliary feedwater system; indeed, safety will be enhanced by the verificat'on of auxiliary feedwater flow paths prior to commencing unit power operations following a cold shutdown.
This proposed supplemental change has been reviewed and approved by the Station Nuclear Safety and Operating Committee and the System Nuclear Safety and Operating Committee.
It has been detemined that this request does not involve an unreviewed safety question.
Since this proposal is a supplement to our original pro-posed Technical Specification Change No. 26 and does not pose any additional safety questions, an additional license amendment fee is not required.
Very truly yours, bf C. M. Stallings Vice President-Power Supply and Production Operations
Attachment:
Supplement to Proposed Technical Specification Change No. 26 cc:
Mr. James P. O'Reilly Office of Inspection and Enforcement Region II
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COMMONVEALTH OF VIRGINI A
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CITY OF RICHMOND
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Before me, a Notary Public, in and for the City and Common-weal th aforesaid, today personally appeared C. M. Stallings, who being duly sworn, made oath and said (1) that he is Vice President-Power supply and Production Operations, of the Virginia Electric.ind Power Company, (2) that he is duly authorized to execute and file the fore-going Amendment in behalf of that Company, and (3) that the statements in the Amendment are true to the best of his knowledge and belief.
Given under my hand and notarial seal this 25d day of S hri W V
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My Commission expires
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