ML18153A343

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Discusses Completion of Licensing Action for GL 97-04, Assurance of Sufficient NPSH for ECC & Containment Heat Removal Pumps. Info Re GL 97-04 Provided
ML18153A343
Person / Time
Site: Surry  
Issue date: 04/01/1999
From: Edison G
NRC (Affiliation Not Assigned)
To: Ohanlon J
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
References
GL-97-04, GL-97-4, TAC-MA0050, TAC-MA0051, TAC-MA50, TAC-MA51, NUDOCS 9904070170
Download: ML18153A343 (4)


Text

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 1, 1999 Mr. J. P. O'Hanlon Senior Vice President - Nuclear Virginia Electric and Power Company 5000 Dominion Blvd.

Glen Allen, Virginia 23060

SUBJECT:

COMPLETION OF LICENSING ACTION FOR GENERIC LETTER 97-04, "ASSURANCE OF SUFFICIENT NET POSITIVE SUCTION HEAD FOR EMERGENCY CORE COOLING AND CONTAINMENT HEAT REMOVAL PUMPS";

SURRY POWER STATION, UNIT NOS. 1 AND 2 (TAC NOS. MA0050 AND MA0051)

Dear Mr. O'Hanlon:

On October 7, 1997, the U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 97-04, "Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps" requesting that the addressees submit information necessary to confirm the adequacy of the net positive suction head (NPSH) available for emergency core cooling (including core spray and decay heat removal) and containment heat removal pumps. More specifically, the licensees were requested to provide the information outlined below:

1.

Specify the general methodology used to calculate the head loss associated with the emergency core cooling system suction *strainers.

2.

Identify the required NPSH and the available NPSH.

3.
4.

Specify whether the current design-basis NPSH differs from the most recent analysis reviewed and approved by the NRC for which a safety evaluation was issued.

Specify whether containment overpressure (i.e., containment pressure above the vapor pressure of the sump or suppression pool fluid) was credited in the calculation of the available NPSH. Specify the amount of overpressure needed and the minimum

. overpressure available.

5.

When the containment overpressure is credited in the calculation of available NPSH, confirm that an appropriate containment pressure analysis was done to establish the minimum containment pressure.

By letter dated December 29, 1997, you responded to GL 97-04for Surry Power Station (SPS),

Units 1 and 2. Based on the review of your response, the staff questioned whether SPS was within its licensing basis with regard to use of containment overpressure to assure adequate NPSH to the low head safety injection pumps. By letter dated September 1, 1998, the staff requested additional information regarding how the GL 97-04 response compares with the 9904070170 990401

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J.P. O'Hanlon current licensing basis at SPS. You responded to the request for additional information by letter dated October 29, 1998. In a January 19, 1999, meeting with the staff, your staff presented the reference to past licensing documentation and the current methodology of the containment analysis code and how it is used to calculate the available NPSH.

The staff has reviewed the referenced and current documentation of the SPS licensing basis with respect to use of containment overpressure. This combined documentation defines the methodology and analytical process which has been used in the past as well as the present.

The process has remained essentially unchanged since the last major staff review. Based on this finding and the review of the responses, the staff believes that *the required information associated with GL 97-04 has been provided. Therefore, the staff considers TAC Nos. MA0050 and MA0051 closed.

If you have any additional questions regarding this matter, pl~ase contact Dr. G. E. Edison at (301) 415-1448.

Docket Nos. 50-280 and 50-281 cc: See next page Sincerely, G. E. Edison, Sr. Project Manager,*section 1 Project Directorate 11 Division of Licensing Project Management Office of Nuclear Reactor Regulation

J. P. O'Hanlon April 1, 1999 currenf licens.irig basis.at SPS. You responded to the request for additional information by letter dated October 29, 1998. In a January 19, 1999, meeting with the staff, your staff presented the reference to past licensing documentation and the current methodology of the containment analysis code and how it is used to calculate the available NPSH.

The staff has reviewed the referenced and current documentation of the SPS licensing basis with respect to use of containment overpressure. This.combined documentation defines the methodology and analytical process which has been used in the past as well as the present.

The process has remained essentially unchanged since the last major staff review. Based on this finding and the review of the responses, the staff believes that the required information associated with GL 97-04 has been provided. Therefore, the staff considers TAC Nos. MA0050 and MA0051 closed..

If you have any additional questions regarding this matter, please contact Dr. G. E. Edison at (301) 415-1448.

Sincerely, ORIGINAL SIGNED BY:

G: E. Edison, Sr. Project Manager, Section 1 Project Directorate 11 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-280 and 50-281 cc: See next page Distribution

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Mr. J. P. O'Hanlon Virginia Electric and Power Company cc:

Mr. Donald P. Irwin, Esq.

Hunton and Williams Riverfront Plaza, East Tower 951 E. Byrd Street Richmond, Virginia 23219 Mr. E. S. Grecheck Site Vice President Surry Power Station Virginia Electric and Power Company 5570 Hog Island Road Surry, Virginia 23883 Senior Resident Inspector Surry Power Station U.S. Nuclear Regulatory Commission 5850 Hog Island Road Surry, Virginia 23883 Chairman Board of Supervisors of Surry County Surry County Courthouse Surry, Virginia 23683 Dr. W. T. Lough Virginia State Corporation Commission Division of Energy Regulation P. 0. Box 1197 Richmond, Virginia 23209 Robert B. Strobe, M.D., M.P:H.

State Health Commissioner Office of the Commissioner Virginia Department of Health P.O. Box 2448 Richmond, Virginia 23218 Surry Power Station Office of the Attorney General Commonwealth of Virginia 900 East Main Street Richmond, Virginia 23219 Mr. J. H. McCarthy, Manager Nuclear Licensing & Operations Support Innsbrook Technical Center Virginia Electric and Power Company 5000 Dominion Blvd.

Glen Allen, Virginia 23060 Mr. W. R. Matthews Site Vice President North Anna Power Station Virginia Electric and Power Company P. 0. Box 402 Mineral, Virginia 23117