ML18153B491

Application for Amends to Licenses DPR-32 & DPR-37,revising Tech Spec Re Reactor Vent Path Manual Isolation Valves.Fee Paid

ML18153B491
Person / Time
Site:	Surry
Issue date:	07/29/1988
From:	Cruden D VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML18153B492	List: ML18153B491 ML18153B493
References
88-403, NUDOCS 8808080083
Download: ML18153B491 (5)

Text

10 CFR 50.90 VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 July 29, 1988 D.S.CRUDEN VICE PRESIDENT-NUCLEAR United States Nuclear Regulatory Commission Serial No.88-403 Attention: Document Control Desk NO/ETS: vl h Washington, D. C. 20555 Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT NOS. I AND 2 PROPOSED TECHNICAL SPECIFICATION CHANGE REACTOR HEAD VENT PATH MANUAL ISOLATION VALVES Pursuant to 10 CFR 50. 90, Vi rgi ni a Electric and Power Company requests an amendment, in the form of changes to the Technical Specifications, to Operating License Nos. DPR-32 and DPR-37 for Surry Power Station Unit Nos. 1 and 2. Manual isolation valves have been added downstream of the solenoid operated valves in the redundant reactor vent p~ths for maintenance and testing. This Technical Specification will change the demonstration of operability from verifying the upstream manual isolation valve is locked open to verifying the manual valves in each vent path are locked open.

The proposed change has been reviewed and approved by the Station Nuclear Safety and Operating Committee and by the Safety Evaluation and Control Staff.

As indicated in the attached Safety Evaluation, it has been determined that this request does not involve an unreviewed safety question as defined in 10 CFR 50.59 nor does it pose a significant hazards consideration as defined in 10 CFR 50.92.

We have evaluated this request in accordance with the criteria in 10 CFR 170.12. A voucher check in the amount of $150 is enclosed as an application fee.

Attachments

1. Discussion of Proposed Change

2. Proposed Technical Specification

3. Voucher Check

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PDR ADOCK 05000280

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

Suite 2900 Atlanta, Georgia 30323 Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station Mr. Charles Price Department of Health 109 Governor Street Richmond, Virginia 23219 Mr. Chandu P. Patel NRC Surry Project Manager Project Directorate II-2 Division of Reactor Projects - I/II

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COMMONWEALTH OF VIRGINIA)

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CITY OF RICHMOND )

The foregoing document was acknowledged before me, in and for the City and Commonwealth aforesaid, today by D. S. Cruden who is Vice President - Nuclear, of Virginia Electric and Power Company. He is duly authorized to execute and file the foregoing document in behalf of that Company, and the statements in the document are true to the best of his knowledge and belief.

Acknowledged before me t h i s ~ day of ~~ , 19 ~ -

My Commission expires: ..It,~ .26", , 19 "JI)

(SEAL)

ATTACHMENT I Discussion of Proposed Change

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e DESCRIPTION OF CHANGE In accordance with NUREG 0737, Item II.B.1, reactor vessel head high point vents were installed on each unit. This vent system design was submitted for review and approval in our December 15, 1980 response to NUREG 0737. In your September 12, 1983, Safety Evaluation Report you approved our vent system design which included a common manual isolation valve upstream of the two parallel trains of series remote operating Solenoid Operated Valves (SOV).

Since the SER was issued, a manual isolation valve has been installed in each parallel train downstream of the SOVs. These ~anual isolation valves will be used to determine which train of SOVs is leaking, in the event of a SOV leakage problem. To ensure operability of the reactor head vent paths, the manual isolation valves are* locked open and placed under administrative control during power* operation. Accordingly; Technical Specification 4.1.B.5.a has been changed to include the downstream manual isolation valves in the demonstration of operability of the reactor head vent path. In addition, to avoid confusion the words remote operating have been included to modified the reactor head vent valves in Technical Specifications 4.1.4 and 4.1.5.b.

SIGNIFICANT HAZARDS DETERMINATION The proposed change does not involve a significant hazards consideration because operation of Surry Unit Nos. 1 and 2 in accordance with this change would not:

1) Involve a significant increase in the probability or consequences of an accident or malfunction of equipment previously evaluated. The proposed change does not alter pl ant design function or system operation. The probability of failure of a downstream manual isolation valve is an insignificant contributor to the overall core melt frequency. The downstream manual valves will allow for testing and maintenance of the solenoid operated valves when the reactor is shutdown.

2) Create the possibility of a new or different kind of accident from any accident previously identified in the UFSAR. It has been determined that a new or different kind of accident will not be possible due to this change. The addition of the manual isolation valves will not create the possibility of a new or different accident. Failure of a manual downstream isolation valve would at most, only render one train of the vent path inoperable, which is similar to one SOV failing closed.

3) Involve a significant reduction in a margin of safety. With the manual downstream isolation valves open both vent paths remain operable. The head vent paths are not assumed to operate for accident mitigation in any design base accident discussed in the UFSAR.

Therefore, pursuant to 10 CFR 50. 92 based on the above construction, it has been determined that this change does not involve a significant safety hazards consideration.