ML20247R187

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Discusses 10CFR50,App R High/Low Pressure Interface in Response to Re Protection of Low Pressure Primary Coolant Boundary Piping During or After Postulated Fire Discussed in Insp Repts 50-277/87-30 & 50-278/87-30
ML20247R187
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 03/31/1989
From: Gallagher J
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8904070269
Download: ML20247R187 (2)


Text

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1 10 CFR 50 I

Appendix R

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PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET l

P.O. BOX 8699 PHILADELPHIA, PA 19101 mag 310 (215) 848 5001 l

l JOSEPH W. G ALL AGHER NU LEAR SERVICES Docket Nos.-50-277 i

50-278 j

I i

U.S.

Nuclear Regulatory Commission ATTN:

Document Control Desk l

Washington, D.C.

20555

SUBJECT:

10 CFR 50, Appendix R High/ Low Pressure Interface Peach Bottom Atomic Power Station Units 2 and 3

REFERENCE:

1) NRC Inspection Report Nos. 50-277/87-30; 50-278/87-30, Unresolved Item No. 4
2) May 11, 1988 letter from J. W. Gallagher (PECo) to W.

R. Butler (NRC)

Dear Sir:

i 1

This letter responds to the January 13, 1989 letter from R.

]

l E. Martin (NRC) to G. A. Hunger, Jr. (PEco) concerning the d

protection of low pressure primary coolant boundary-piping during or after a postulated Appendix R fire at Peach Bottom Atomic Power Station.

After reviewing the Company's May 11, 1988 submittal-(reference 2), the NRC found the Company's proposed resolution of the high/Jow pressure interface issue for Residual Heat-Removal System shutdown cooling suction' piping to be unacceptable.

The Company's proposed resolution was based on probabilistic and piping 1

l design margin evaluations, and the Company concluded that the shutdown cooling piping would not fail.

This is a NRC Region I Unresolved Item (reference 1).

To resolve this issue, the Company will remove motive power from the shutdown cooling suction valve inside containment (MO '

18) with the valve in the closed position prior to reactor operation.

The breaker which feeds power to the valve's motor operator will be administratively blocked in the open position when' l

.the reactor is at power.

This will preclude spurious opening of the pgDN 0904070269 890331.

l' ADOCK050g27 PDR 9

0

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MAR 31 m3 Document Control Desk

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valve due to an Appendix R fire scenario.

The procedural controls to implement this measure will be in effect prior to restart.

If you have any questions or require additional information, please do not hesitate to contact us.

Very truly yours, YU's I

cc:

W.

T.

Ruusel], Administrator, Region I, USNRC T.

P. Johnson, USNRC Senior Resident Inspector R.

E. Martin, PB Project Manager, USNRC A.

Krasopoulos, Inspector, Region I, USNRC T.

E.

Magette, State of Maryland J.

Urban, Delmarva Power J.

T.

Iloettger, Public Service Electric & Gas 11.

C.

Schwemm, Atlantic Electric T.

M. Gerusky, Commonwealth of Pennsylvania i

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