ML18139B923

Forwards PWR Safety & Relief Valve Adequacy Rept for North Anna Units 1 & 2 & PWR Safety & Relief Valve Adequacy Rept for Surry Units 1 & 2, in Response to NUREG-0737,Item II.D.1

ML18139B923
Person / Time
Site:	Surry, North Anna, 05000000
Issue date:	07/01/1982
From:	Leasburg R Virginia Power (Virginia Electric & Power Co)
To:	Harold Denton, Eisenhut D Office of Nuclear Reactor Regulation
Shared Package
ML18139B924	List: ML18139B923 ML18139B925 ML20054L667
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM 392, NUDOCS 8207080329
Download: ML18139B923 (2)

Text

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e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND~ VIRGINIA. 23261 R. H. LEASBURG July 1, 1982 VICE PRESIDENT NUCLEAll 0PEJIATIONS Mr. Harold R. Denton, Director Serial No. 392 Office of Nuclear Reactor Regulation NO/DWS,JR.:acm Attn: Mr. Darrell G. Eisenhut, Director PSEC/DPB Division of Licensing Commission Docket Nos. 50-338 U. S. Nuclear Regulatory Commission 50-339 Washington, D. C. 20555 50-280 50-281 License Nos. NPF-4 NPF-7 DPR-32 DPR-37 Gentlemen:

RESPONSE TO NUREG 0737 POST-TMI REQUIREMENT-ITEM II.D.1 RELIEF, SAFETY, BLOCK VALVE TEST AND DISCHARGE PIPING ANALYSIS REQUIREMENTS PLANT SPECIFIC REPORT NORTH ANNA 1 & 2 AND SURRY 1 & 2 In accordance with the requirements of Item II.D.1 of NUREG 0737 and North Anna 2 License Condition 2. C. 21 (f) attached are the July 1, 1982 plant specific submittals for the safety and relief valve testing for North Anna 1 and 2 and Surry 1 and 2. Block valve, plant specific information, also scheduled for July 1, 1982 is not available at this time and will be provided as soon as possible but not later than September 1, 1982.

Plant specific pressurizer discharge piping and support evaluation scheduled for July 1, 1982 is incomplete.

We are currently performing two alternate analyses of the North Anna Unit 2 system. The first approach is to analyze the pressurizer safety valve piping with the loop seals drained. This analysis has now been completed and we are evaluating the results.

Due to potential operability problems posed by draining the loop seals, a second analysis has been undertaken in which the loop seals are retained.

Currently, generation of time history thermal hydraulic loads and development of structural modeling are underway based on the North Anna Unit 2 piping configuration. Detailed analysis will commence upon completion of these efforts. We presently anticipate this analysis to be completed in November, 1982. In conjunction with this analysis, a review of both North Anna Units 1 and 2, and Surry Units 1 and 2 is being performed to determine the unit with the worst case loadings for the dynamic analysis based on retention of the loop seals. This information will be utilized to envelope the remaining three units in the event that the North Anna Unit 2 analysis indicates the feasibility of retaining the loop seals on North Anna Unit 1, and Surry Units 1 and 2. Ao..,(,

8207080329 820701 PDR ADOCK 05000280 p- _PDR

,. e e VIRGINIA ELECTRIC AND POWER COMPANY TO Harold R. Denton Based on our evaluation of the results of the two analyses outlined above, we anticipate that a course of action will be established for North Anna Unit 2 by January 1, 1983. The outcome of these analyses will also be reviewed for application to North Anna Unit 1, and Surry Units 1 and 2 by January 1, 1983.

Also at this time we are reviewing with Westinghouse, Crosby, and Dresser the necessity of making ring adjustments to the safety valves based on the EPRI test results and our plant specific inlet piping arrangements. At the present, our consultant, Westinghouse Electric Corporation advises us there is no evidence that changes in ring settings must be made; however, if their review indicates adjustments are required, VEPCO will advise NRC of the magnitude of the changes and provide a schedule for making adjustments.

Very truly yours,

~L.S~

CR. H. Leasburg cc: Mr. James P. O'Reilly Regional Administrator Office of Inspection and Enforcement Region II Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 Division of Licensing Mr. Robert A. Clark, Chief Operating Reactors Branch No. 3 Division of Licensing