ML18141A306
| ML18141A306 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 01/09/1984 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, Varga S Office of Nuclear Reactor Regulation |
| References | |
| 754, NUDOCS 8401130314 | |
| Download: ML18141A306 (2) | |
Text
e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND_. VIRGINIA 23261
- w. L. STEWA.RT VICE PRESIDENT NUCLEAR 0PERATI01'f8 January 9, 1984 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attn:
Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Gentlemen:
SUPPLEMENTAL INFORMATION TO Serial No. 754 NO/WDC:jab Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 AMENDMENT TO OPERATING LICENSE DPR-32 AND DPR-37 SURRY POWER STATION UNIT NOS. 1 AND 2 In our letter dated October 28, 1980 (Serial No. 862), the Virginia Electric and Power Company requested an amendment, in the form of changes to the Technical Specifications, to Operating Licenses DPR-32 and DPR-37 for Surry Power Station Unit Nos.
1 and 2.
The proposed changes pertain to the auxiliary ventilation system, total dynamic head of the fire pump, and break points to be incorporated in the High Energy Pipe Break Inspection Program.
Additional information concerning the fire pump has been requested by the NRC to aid in the review of our proposed change.
By letter dated June 16, 1977, the NRC provided sample fire protection Technical Specifications for guidance.
In the NRC guidance letter, the specification for fire pump flow testing, Specification 4.7.11.1.3.2, stated, "By verifying that each pump develops at least (2500) gpm at a system head of (250) feet."
The amount for gpm and feet were to be provided by each licensee.
In accordance with the NRC guidance letter, we revised our fire protection Technical Specifications.
Due to error and oversight in our revise.cl submittal of August 1, 1977, we proposed the guidance specification verbatim instead of providing the gpm and feet to correspond to Surry's pump design criteria.
During periodic tests, the fire pumps failed to meet the acceptance criteria of 250 feet of head at 2500 gpm.
The NRC was notified of the failure in our letter dated April 22, 1980 (Serial No. 370).
The pump was inspected at that time, and it was determined that the pump showed no sign of significant or abnormal wear, nor did its performance deviate significantly from the original test data.
Subsequently, a representative of the pump manufacturer inspected Surry' s fire pump and verified these conclusions.
Further review revealed that Specification 4.18.B.l.f.(2) exceeds both the original design criteria of 244.9 feet at 2500 gpm and the FSAR requirement of 100 psi discharge pressure at 2500 gpm.
Based on this review, a request to change the specification was
~401130314 840109 PDR ADOCK 05000280 P
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e V1n0INIA ELECTRIC AND PowER CoMPANY To Mr. Harold R. Denton submitted requiring that each pump develop a flow equal to or greater than 2500 gpm at a total dynamic head of 231 feet (100 psi).
In subsequent periodic tests of the fire pumps, the pumps have failed to meet the existing Technical Specification requirement, but exceeded the specifications as proposed in our pending change.
We conclude that the fire pumps are capable of providing adequate fire protection and meet the requirements of the FSAR and the proposed Technical Specification change.
cc:
Mr. James P. O'Reilly Regional Administrator Region II Mr. D. J. Burke NRC Resident Inspector Surry Power Station Mr. Charles Price Department of Health 109 Governor Street Richmond, Virginia 23219 Very truly yours, W. L. Stewart