ML20052A729

PWR Main Steam Line Break W/Continued Feedwater Addition, Vepco Units 1 & 2, Request for Addl Info

ML20052A729
Person / Time
Site:	North Anna
Issue date:	03/15/1982
From:	Vosbury F FRANKLIN INSTITUTE
To:	Peter Hearn NRC
Shared Package
ML20052A724	List: ML20052A729
References
CON-NRC-03-81-130, CON-NRC-3-81-130 IEB-80-04, IEB-80-4, NUDOCS 8204290084
Download: ML20052A729 (3)

Text

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REQUEST FOR ADDITIONAL INFORh'ATION r

PWR M.AIN STEAM LINE BREAK WITH CONTINUED FEEDWATER ADDITION .

VIRGINIA ELECTRIC AND POWER COMPANY

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NORTH ANNA POWER STATION UNITS 1 AND 2 NRC DOCXET NO. 50-338, 50-339 FRC PROJECT C5506 -

NRC TAC NO. 46845, 46846. FRC ASSIGNMENT S NRC CONTRACT NO. NRC43-81 130 FRC TASK 133 Preparedby Franklin Research Centar . . Authon F. 7osbury 20th and Race Street Ph!!adelphia, PA 19103 FRC Group Leaden R. C. Herrick Prepsted for Nuciaar Regulatory Ccmmission Washington, D.C. 2C555 Lead NRC Engineer: P. Hearn March 15, 1982 P

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1 ~Q BACKGROUND Evaluation of*the information contained in the May 8, 1980 [1] lettdr from Virginia Electric and Power Company (VEPCO) to the Nuclear Regulatory q xumission (NRC) relating to IE Bulletin 80-04, " Analysis of a PWR Main Steam .

Line Break with Continued Feedwater Addition," revealed an item of concern.

l l , Additional information relating to this concern is net.ded before a final evaluation can be made regarding the potential for exceeding containment design pressure. .

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i The concern and the additional information needed to resolve this concern are identified in this Request for Additional Information.

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• ITEM CONCEFS Item 1 of IE Bulletin 80-04 directs the Licensee to review containment l pressure response to a main steam line break (M373) accident to determine the l i= pact of runcut flow frca the auxiliary feedwater (AFW) system and o'ther energy sources at North Anna Units 1 and 2.

'In addition, it directs the bcensee to evaluate the ability of the AIM pumps to remain operable after extended operation at runout flow. Since the containment pressure response analysis contained in Section 6.2.1.3.1 cf the l

Ncrth Anna FSAR [2] indicated that impact of AFW runout flow to the ruptured steam generator was included in the analysis, an evaluation of pump l

operability is requ' ired.

• REQUEST Please provide an evaluation of the ability of the motor-driven and turbine-driven AEW pumps to remain operable for 30 minutes at runout flow.

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REFERENCE

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1. B. R. Sylvia -(VEPCO) .

Letter to d. P. O'Reilly (NRC)

Subject:

Response to IE Bulletin 80-04 May 8, 1980 *

2. Final Sa'fety Analysis'F.eport .

North Anna Power Station Section 6.2.1.3.1 .

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