ST-HL-AE-1598, Forwards Interim Response to Generic Ltr 85-12,Section a, Determination of Reactor Coolant Pump Trip Criteria. Criteria Will Be Established from Westinghouse Owners Group Recommendations.Final Response Will Be Submitted by 860331

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Forwards Interim Response to Generic Ltr 85-12,Section a, Determination of Reactor Coolant Pump Trip Criteria. Criteria Will Be Established from Westinghouse Owners Group Recommendations.Final Response Will Be Submitted by 860331
ML20137P722
Person / Time
Site: South Texas  STP Nuclear Operating Company icon.png
Issue date: 01/28/1986
From: Wisenberg M
HOUSTON LIGHTING & POWER CO.
To: Noonan V
Office of Nuclear Reactor Regulation
References
CON-#186-943, TASK-2.K.3.05, TASK-TM GL-85-12, OL, ST-HL-AE-1598, NUDOCS 8602050306
Download: ML20137P722 (3)


Text

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The Light COIII f flouston Lighting & l'ower I!O. Box 1700 llouston,'les.n 77001 (713) 2286211 January 28, 1986 ST-HL-AE-1598 File No.: G9.17/G3.8 Mr. Vincent S. Noonan, Project Director PWR Project Directorate #5 U. S. Nuclear Regulatory Commission Washington, DC 20555 South Texas Project Units 1 and 2 Docket Nos. STN 50-498, STN 50-499 TMI Item II.K.3.5 and Generic Letter 85-12 Automatic Trip of Reactor Coolant Pumos

Dear Mr. Noonan:

DSER Item 61K addresses NUREG-0737 Item II.K.3.5, " Automatic Trip of Reactor Coolant Pumps." The Westinghouse Owners Group (WOG) submitted information in response to NRC Generic Letter 83-10c in support of the WOG alternative reactor coolant pump trip criteria. As stated in NRC Generic Letter 85-12 the NRC has determined the information provided to be acceptable on a generic basis.

By letter dated November 6, 1985, Houston Lighting &

Power Company (HL&P) provided a partial response to the plant-specific concerns given in Generic Letter 85-12 Sections B and C; (i.e., potential reactor coolant pmp problems, and operator training and procenares). Final response to Section A (Determination of RCP Trip Criteria) is dependent on completion of plant specific instrment uncertainty analyses. An interim response is provided in the attachment. Final information will be submitted by March 31, 1986.

If you should have any questions on this matter, please contact Mr. M. A. McBurnett at (512) 972-8530.

Very truly yours, M. R.

senburg Manager Nuclear icens rg THC/yd

Attachment:

Interim Response to Genel.: Letter 85-12, Part A

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F ST-HL-AE-1598 Houston Lighting & Power Company File No.: G9.17/G3.8 Page 2 cc:

Hugh L. Thompson, Jr., Director Brian E. Berwick, Esquire Division of PWR Licensing - A Assistant Attorney General for Office of Nuclear Reactor Regulation the State of Texas U.S. Nuclear Regulatory Commission P.O. Box 12548, Capitol Station Washington, DC 20555 Austin, TX 78711 Robert D. Martin Lanny A. Sinkin Regional Administrator, Region IV Christic Institute Nuclear Regulatory Commission 1324 North Capitol Street 611 Ryan Plaza Drive, Suite 1000 Washington, D.C.

20002 Arlington, TX 76011 Oreste R. Pirfo, Esquire N. Prasad Radambi, Project Manager Hearing Attorney U.S. Nuclear Regulatory Commission Office of the Executive Legal Director 7920 Norfolk Avenue U.S. Nuclear Regulatory Commission Bethesda, MD 20814 Washington, DC 20555 Claude E. Johnson Charles Bechhoefer, Esquire Senior Resident Inspector /STP Cnairman, Atomic Safety &

c/o U.S. Nuclear Regulatory Licensing Board Commission U.S. Nuclear Regulatory Commission P.O. Box 910 Washington, DC 20555 Bay City, TX 77414 4

Dr. James C. Lamb, III M.D. Schwarz, Jr., Esquire 313 Woodhaven Road Baker & Botts Chapel Hill, NC 27514 One Shell Plaza Houston, TX 77002 Judge Frederick J. Shon i

Atomic Safety and Licensing Board J.R. Newman, Esquire U.S. Nuclear Regulatory Commission Newman & Holtzinger, P.C.

Washington, DC 20555

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1615 L Street, N.W.

j Washington, DC 20036 Mr. Ray Goldstein, Esquire 1001 Vaughn Building Director, Office of Inspection 807 Brazos and Enforcement Austin, TX 78701 U.S. Nuclear Regulatory Commission i

Washington, DC 20555 Citizens for Equitable Utilities, Inc.

c/o Ms. Peggy Buchorn T.V. Shockley/R.L. Range Route 1, Box 1684 Central Power & Light Company Brazoria, TX 77422 P.O. Box 2121 Corpus Christi, TX 78403 Docketing & Service Section Office of the Secretary H.L. Peterson/G. Pokorny U.S. Nuclear Regulatory Commission City of Austin Washington, DC 20555 P.O. Box 1088 (3 Copies)

Austin, TX 78767 Advisory Committee on Reactor Safeguards J.B. Poston/A. vonRosenberg U.S. Nuclear Regulatory Commission City Public Service Board 1717 H Street P.O. Box 1771 Washington, DC 20555 San Antonio, TX 78296 Revised 12/2/85

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Attachment ST-ML-AE-File No.: G9.17/G3.8 Page 1 of 1 South Texas Project Units 1 and 2 Docket Nos. STN 50-498, STN 50-499 Interim Responses to Generic Letter 85-12, Part A

'A.

Determination of RCP Trip Criteria 1.

Requirement 1

Identify the instrumentation to be used to determine the RCP trip cet point, including the degree of redundancy of each parameter signal needed for the criterion chosen.

Response

STP will establish RCP trip criteria from the three alt 3rnatives recommended by the Westinghouse Owners Group (WOG). The selection will be based on the instrument uncertainties and operating margin associated with each option. Redundant instranentation is already

-provided to implement each alternative.

7 2.

Requirement Identify the instrtsnentation uncertainties for both normal and adverse containment conditions. Describe the basis for the selection of the adverse containment parameters. Address, as appropriate, local conditions such as fluid jets or pipe whip which might influence the instrumentation reliability.

Response

The instrument uncertainties for both normal and adverse containment conditions will be identified once the trip criteria for item 1 above is established. Containment pressure will be used to indicate an adverse containment environment as discussed in the WOG Emergency Response Guidelines (ERGS). Any local conditions which are appropriate will be considered at that time.

3.

Requirement In addressing the selection of the criterion, consideration of uncertainties associated with the WOG supplied analyses values must be provided.

These uncertainties include both uncertainties in the computer program results and uncertainties resulting from plant specific features not representative of the generic data group.

I

Response

Uncertainties associated with the WOG supplied analyses values will be addressed as appropriate.

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