ML18153C259

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Forwards Response to NRC 900524 Request for Addl Info Re NRC Bulletin 88-004, Potential Safety-Related Pump Loss. Engineering Will Initiate Study to Evaluate Enhancements of Cooldown & Possible Heatup Operation
ML18153C259
Person / Time
Site: Surry  Dominion icon.png
Issue date: 06/18/1990
From: Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
88-275D, IEB-88-004, IEB-88-4, NUDOCS 9006250208
Download: ML18153C259 (3)


Text

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e e VIRGINIA ELECTRIC AND POWER COMPANY RICHM:OND, VIRGINIA 23261 June 18, 1990 United States Nuclear Regulatory Commission Serial No. 88-275D Attention: Document Control Desk NURCS 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 UNITS 1. AND 2 REQUEST FOR ADDITIONAL INFORMATION

. NRC BULLETIN 88-04, POTENTIAL SAFETY RELATED PUMP LOSS We have reviewed your letter,* dated May 24,

  • 1990, which requested the status of completed actions and the schedule for completing remaining actions associated with potential safety related pump loss. Our response to your request is provided in Attachment 1.
  • Should you have any furthe_r questions, please contact us.

Very truly yours,

~L~~

  • W. L. Stewart Senior Vice President - Nuclear

_ Attachment(s) 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.

9006250208 900618.

PDR ADOCK 05000280 Q PDC

e. e ATTACHMENT 1 REPLY TO A REQUEST FOR ADDITIONAL INFORMATION .

ON STATUS* OF*. CORRECTIVE ACTIONS FOR NRC BULLETIN 88-04 I POTENTIAL SAFETY RELATED . PUMP LOSS .

I. RESIDUAL HEAT REMOVAL (RHR)

Corrective Actions - . No corrective actions necessary. Engineering will initiate

    • . Origin_aily Proposed .study to evaluate enhancements of cooldown and
  • possible heatup operation which may reduce pump maintenance requirements.

Status - COMPLETE

  • II. LOW HEAD SAFETY INJECTION (LHSI)

Corrective Actions - Small break LOCA scenarios will be conducted by

-Originally Proposed November 1, 1988 on the simulator to verify the EOPs adequately address and therefore minimize o'peration of

  • The LHSI pumps on the recirculation mode.

Status -

  • COMPLETE 111. HIGH HEAD SAFETY INJECTION (HHSI) ..

Corrective Actions - No corrective actions* are deemed necessary.

  • Originally Proposed Status. - COMPLETE.*

IV. AUXILIARY FEED WATER (AFW)

Corrective Actions - Short Term Originally Proposed

. a.

  • Appropriate_ procedur~s will be . reviewed and revised,* as necessary, by November 1, 1988 to minimize operation at' low flow/minimum flow recirculation. *

. Status - COMPLETE

  • b. Operation/Engineering -personnel will be directed to limit: 1.JSe of.

these pumps in leak testing.

  • Status - ** COMPLETE

\ ,.'

IV. AUXILIARY FEED WATER (continued)

Corrective Actions - Long Term Originally Proposed *

a. One auxiliary feedwater pump will be disassembled and inspected for degradation during the 1989 and 1990 refueling outage for each unit. The remaining pumps will be inspected during subsequent outages. Inspection results will determine the required inspection frequency and number of pumps inspected.

Status - INCOMPLETE. The Cycle 1O refueling outages for Unit 1 and Unit 2 (the refueling outages originally referenced above) are currently scheduled for the fourth quarter on 1990 and second quarter of 1991, respectively, during which* this item will be initiated.

b. Larger minimum flow recirculation lines are* scheduled to be .

installed in the 1989 and 1990 refueling outages for Units 1 and 2, respectively.

Status - INCOMPLETE. The Cycle 1O refueling outages for Unit 1 and Unit 2 (the refueling outages originally referenced above) are

  • currently* scheduled for the fourth quarter on 1990 and second
  • quarter of 1991, respectively, during which this item will be completed.

.. ~ I