ML20137W993

Requests Addl Info Re Pilgrim Nuclear Power Station,To Credit Containment Overpressure in Net Positive Suction Head Analysis for ECC Pumps Generated as Result of NRC Staff Review of Licensee Info Submitted on 970120

ML20137W993
Person / Time
Site:	Pilgrim
Issue date:	04/17/1997
From:	Wang A NRC (Affiliation Not Assigned)
To:	Boulette E BOSTON EDISON CO.
References
TAC-M97789, NUDOCS 9704210114
Download: ML20137W993 (5)

Text

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[* > April 17, 1997~

Mr. E.' Thomas Boulette, Ph.D .

.. Senior-Vice PresidentJ- Nuclear Boston. Edison Company

- Pilgrim Nuclear Power Station ,

RFD #1 Rocky Hill-Road '

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Plymouth,. MA 02360 .

SUBJECT:

REQUEST FOR-ADDITIONAL INFORMATI'ON ON/ THE PILGRIM NUCLEAR POWER. '

-STATION TO CREDIT CONTAINMENT OVERPRESSURE IN>THE NET POSITIVE- '

SUCTION HEAD. ANALYSIS FOR THE EMERGENCY CORE COOLING PUMPS (TAC NO.-

M97789)

Dear. Mr. Boulette:

Enclosed is a' request for additional' information generated as a-result of NRC staff review, regarding your subject submittal dated January 20, 1997.

The' staff. requests that the response be'provided within 30 days of. issuance of

.this' letter ,

iSincerely,

= Original signed by Alan B. Wang, Project Manager Project Directorate'I-3 Division of Reactor Projects' - I/II Office of Nuclear Reactor Regulation ,

Docket No. 50-293

Enclosure:

Request. for Additional Information

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E. Thomas Boulette Pilgrim Nuclear Power Station j l

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Mr.; Leon J. Olivier Mr. Jeffery Keene Vice President of Nuclear Licensing Division Manager Operations & Station Director Boston Edison coinpany ,

Pilgrim Nuclear Power Station 600 Rocky Hill Road '

IFD #1 Rocky Hill Road ~ Plymouth, MA 02360-5599 Plymouth, MA 02360 Ms. Nancy Desmond Resident Inspector . . .

Manager, Reg. Affairs Dept.

U. S. Nuclear Regulatory Commission Pilgrim Nuclear Power Station Pilgrim Nuclear Power Station RFD #1 Rocky Hill Road Post Office Box 867 Plymouth, MA 02360 Plymouth, MA 02360 Mr. David F. Tarantino Chairman, Board of Selectmen Nuclear Information Manager 11 Lincoln Street Pilgrim Nuclear Power Station Plymouth, MA 02360 RFD #1, Rocky Hill Road Plymouth, MA 02360 Chairman, Duxbury Board of Selectmen Town Hall Ms. Kathleen M. O'Toole ,

878 Tremont Street Secretary of Public Safety Duxbury, MA 02332 Executive Office of Public Safety One Ashburton Place Office of the Commissioner Boston, MA 02108 Massachusetts Department of Environmental Protection Mr. Peter LaPorte, Director One Winter Street Attn: James Muckerheide Boston, MA 02108 Massachusetts Emergency Management Agency Office of the Attorney General 400 Worcester Road One Ashburton Place P.O. Box 1496 20th Floor Framingham, MA 01701-0317 Boston, MA 02108 Chairman, Citizens Urging Mr. Robert M. Hallisey, Director Responsible Energy Radiation Control Program P.O. Box 2621 Massachusetts Department of Duxbury, MA 02331 Public Health 305 South Street Citizens at Risk Boston, MA '02130 P.O. Box 3803 Plymouth, MA 02361 Regional Administrator, Region I U. S. Nuclear Regulatory Commission W.S. Stowe, Esquire 475 Allendale Road Boston Edison Company King of Prussia, PA 19406 800 Boylston St., 36th Floor Boston, MA 02199 Ms. Jane Fleming 8 Oceanwood Drive

.Duxbury, MA. 0233

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Nuclear Matters Committee-Town-Hall 11 Lincoln Street

' Plymouth, MA 02360 .

Mr. William FD. Meinert  :

Nuclear Engineer Massachusetts Municipal Wholesale Electric Company. f P.O. Box 426 .

Ludlow, MA- 01056-0426 2

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1 REQUEST FOR ADDITIONAL INFORMATION INCREASE IN ULTIMATE HEAT SINK TEMPERATURE PILGRIM NUCLEAR POWER STATION In Enclosure 4 to your' January 20, 1997, you provided Safety Evaluation (SE)

No. 2983 which included the results of your analysis of a proposed temperature increase of the ultimate heat sink (UHS) from 65 to 75 degrees Fahrenheit

, (*F). Portions of that evaluation describe the effects of the temperature tncrease on equipment directly cooled by the reactor building closed cooling water (RBCCW) system. In order to complete our review and make an

, acceptability determination regarding this issue, we need the following additional information.

1. On Page 30 of SE No. 2983, you state that the function of the residual heat removal (RHR) pump seal coolers is to prevent flashing at the RHR pump seal faces and adequately explain why this cooling is not necessary for post-accident operation of the pumps. You further described that the

. seal coolers are only necessary when the RHR pumps operate in the shutdown cooling (SDC) mode. However, you did not provide information to verify that RHR pumps will not be damaged by seal flashing when operating

in the SDC mode with the UHS at the increased temperature of 75 *F (corresponding to a peak RBCCW temperature of 98 *F). Please provide additional information to describe why the incretse in RBCCW temperature is acceptable when the RHR pumps are operating in the SDC mode. This additional information should also include verification that safe cold shutdown following a fire can still be achieved within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in accordance with Appendix R to 10 CFR Part 50.

2. On Page 30 of the SE you also discuss the effects of the increased RBCCW

temperature on the operation of the core spray (CS) pumps. In that discussion you state that "The calculated cooling water inlet and outlet temperatures are well within the acceptable range to ensure reliable operation of the Core Spray pump motors with a SSW injection temperature of 75 *F." This general statement implies (but is not explicit) that the temperature of the cooling water RBCCW to the CS pump motor coolers remain within the design range of acceptable cooling water inlet temperatures for the CS pump motors. Verify that the peak RBCCW temperature (98 *F) is within the design limits for CS pump motor cooling, or if it is not, provide the justification for your conclusion that pump operation is acceptable for the duration of design basis accidents.

3. On Page 31 of your evaluation you discuss building compartment cooling and provide the same type of general statements as we discussed in the above Item 2. For the motor control center (MCC) ventilation you state that "the temperature in the enclosures will remain sufficiently-low to ensure reliable operation." On the same page, for the equipment area cooling you state that "the temperature results for building compartments served by equipment area cooling as well as those that were not evaluattd against temperature limits for the local equipment and found acceptable to ensure reliable operation." In neither case did you state Enclosure

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9 that the temperature remains within the equipment design limits. Verify that the area temoeratures and the temperature in the MCC enclosures remain within the equipment design limits at the increased RBCCW temperature, or if they do not, provide justification for your

-determination that the equipment and/or MCCs will remain operable.

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