ML20245C440

Forwards Revised Proposed Tech Specs Re Low Temp Overpressure Protection Enable Temp.Proposed Enable Temp Revised from 247 F to 261 F to Include Temp Difference Between Water at Vessel Surface & Metal at Stated Locations

ML20245C440
Person / Time
Site:	North Anna
Issue date:	06/19/1989
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20245C442	List: ML20245C440 ML20245C450
References
88-202B, NUDOCS 8906260188
Download: ML20245C440 (3)

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VIRGINIA ELECTRIC AND POWER COMPANY

' RICHMOND, VIRGINIA 23261 June 19, 1989-U. S. Nuclear Regulatory Commission Serial No.

88-202B Attn:. Document Control Desk PES /DMB:cdk Washington, D.C.

20555 Docket No. 338 License No.-

NPF-4 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY MI 1 -

Plf0P55 W TECHNICAL SPECIFICATIONS CHANGE - SUPPLEMENT On November 30,1988. Virginia Electric and Power Company requested an amendment -

to Operating License Number NPF-4. The requested amendment. proposed revised

'heatup and cooldown curves, along with associated setpoint changes, that are valid for a period up' to ten effective ' full power. years (10 EFPY).-

Based on subsequent discussions with the NRC Staff reviewing' the proposed change, one of the proposed Technical Specification changes has been rcvised and is provided as Attachment 1.

Specifically, the low temperature overpressure protection (LTOP) enable temperature. in Technical Specification 3.4.9.3 was determined based on an incorrect interpretation of Revision. 1 to Standard Review Plan ~(SRP), Branch Technical Position RSB 5-2.

The proposed enable' temperature has been revised from 247'F' to 261*F to include.the temperature difference between the water at the vessel surface'and-the metal.at the 1/4 T and 3/4 T locations. The proposed change'is included?Lin' Attachment i

1.

The safety evaluation has also been. revised and is included in Attachment l

2. provides additional information requested by the NRC-during our recent discussions.

This request has been reviewed by the Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control staff.

It has been determined i

that this request does not involve an unreviewed safety' question as defined in 10 CFR 50.59 or a significant hazards consideration as defined in 10 CFR 50.92.

If you have any questions or require additional information, please contact us immediately.

Very truly yours, l

W. L. Stewart Senior Vice President - Power l pol

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1 Attachments 1.

Revised, Proposed Technical Specification Changes 2.

Safety Evaluation In Support Of Revised Heatup And Cocidown Curves Valid To 10 EFPY 3.

Response To NRC Request for Information On The NAPS Unit 1 Heatup And Cooldown Package

]

cc:

U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.

Suite 2900

{

Atlanta, Georgia 30323 j

Mr. J. L. Caldwell NRC Senior Resident Inspector North Anna Power Station i

Cominissioner Department of Health Room 400 109 Governor Street Richmond, Virginia 23219

4-5 ATTACHMENT 1 REVISED, PROPOSED TECHNICAL SPECIFICATION CHANGES l

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