ML19347B673

RO:80-075/01P:on 801008,analysis Revealed Overstress Condition Existed at Pipe Support H-43 on Reactor Coolant Fill Header from High Head Charging Pumps.Cause Not Determined.Mod Will Be Completed Prior to Plant Startup

ML19347B673
Person / Time
Site:	Beaver Valley
Issue date:	10/08/1980
From:	Werling J DUQUESNE LIGHT CO.
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
BVPS:JAW:1002, IEB-79-14, RO-80-075-01P, RO-80-75-1P, NUDOCS 8010150534
Download: ML19347B673 (3)

Text

o

( ** .. .

E. 8 e

• s

• r p 23 4se sooo

. n s. .. . ~

P nsawgn Ps

'** DUQUESNE LIGHT COMPANY Beaver Valley Power Station Post.0ffice Box 4 Shippingport, PA 15077 October 8, 1980 BVPS: JAW:1002 Beaver Valley Power Station, Unit No. 1 l

Docket No. 50-334, License No. DPR-66 LER 80-075/OlP Mr. B. H. Grier, Director of Regulation United States Nuclear Regulatory Commission Region 1 l 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Mr. Grier:

In accordance with Appendix A, Beaver Valley Technical Specifications, Licensee Event Report LER 80-075/0lP, Technical Specification 6.9.1.8, ,

Administrative Controls, is submitted. This occurrence was reported to j

Mr. J. Hegner, the Beaver Valley Resident Inspector, at 0920 hours0.0106 days <br />0.256 hours <br />0.00152 weeks <br />3.5006e-4 months <br /> on l October 8, 1980.

Evaluation and reanalysis required by IE Bulletin 79-14 have shown that the following piping and support has less conservatism than assumed for the safety analysis and, therefore, requires remedial action. .

The overstress condition occurs at pipe support'H-43 on the reactor coolant fill header from the high head charging pumps. Loss of this line at this location would result in a loss of all three charging pumps during a seismic event. This overstress condition has been calculated for the summed loading factors of, deadweight, thermal and design basis earthquake loads.

l 00h 5t \

0 010150.BI.94l r

1 1

i Mr. B. H. Grier l October 8, 1980 .

BVPS

JAW: 1002 Page 2_ l l

l The plant is currently in Operational Mqde 5. A pipe break at this location could be quickly isolat d and t%e low head safety injection pumps

would be available to provide reactor coolant makeup if needed. Therefore, the health and safety of the general public would not be jeopardized.

Modification of the pipe support needed to alleviate this condition will be l done prior to plant startup.

Very truly yours, 7

't 1

J. A. Werling Superintendent i

• cc: Director Of Manage =ent & Program Analysis United States Nuclear Regulatory Commission Washington, D. C. 20555 W. J. Ross, BVP,S Licensing Project Manager w/'

United States Nuclear Regulatory Co= mission Washington, D. C. 20555 .

D. A. Beckman, Nuclear Regdlatory Com=ission, BVPS Site Inspector P. Higgins, Secretary, Prime Movers Committee - EEI Nuclear Safety Analysis Center, Falo Alto, California Mr. John Alford, PA Public Utilities Commission, Harrisburg, PA e

+

m LICENSEE EVENT REPORT i bONTROL BLOCx: l l l l l l 1h (PLEASE FRINT OR TYPE ALL REQUIRED IPJFORMATION) 10 lil I I l l l l l@l15 l l l I l l l l l l 26 l@l;6 l l l LICENSE TYPE JJ l l@l67 i. Al T tol@

7 8 9 UICENSEE CODE 14 LICENSE NUMBEH CON'T IoI1I 7 3 5[$"CE i 60 l@lO l fl 01 61 O ID I 313168Yl@l DOCA ET NUveER 63 T5EVENT l Oi DATE l l Ol Ol (fl@l REPORT 74 75 %I ClDATEi I Ol 8001 fl@

EVENT DESCRIPTION AND PROB ABLE CONSEQUENCES h l

10121 I ,

, 10131 1 IN /. W l l

l 10 l a l 1 I

l l o 151 I I

10161 L I

lo lil l l o is i i 80 7 6 9 SY STE M CAUSE CAUSE COVP. VALVE COCE CCCE SLsCODE CCVPONENT CODE SU8 CODE SUBCODE I l0l9l l l l l l l l l l l l l l l l l 7 8 9 10 11 12 13 18 19 20 SEQUENTI AL OCCURAENCE REPORT REVIS'ON LER AO EVE CAR REPORT NO. CODE TYPE NO.

@ g.g; 1 dT 1 V0 1 1-1 Lol7151 k.] lo l l I LB l-1 I I

't 22 23 24 26 27 23 29 au 31 32 TAK N ACT ON ON

• NT tET HOURS S8 T FOR 1d S. S P LI E MAN FACTURER l 1 l@l34 l@ l l@ l l@ l I I I I I 41 l@ l l@ l l@ l l l j_J@

, J3 35 Jo 3 40 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS li 101 l l I

ITTT 1 1 l l'i21 L I I

i'iai L m1a 7 a so l

STA S N PO AER OTHER STA TUS IS O RY DISCOVERY DESCRIPTION li is i i l@ l I I l@l l I l@l I ACT VITY CONTENT RELE ASED OF RELE ASE AVOUNT OF ACTIVITY LOCATION OF RELEASE l1 l6l l lhI i l l l 1 8 9 10 11 44 45 80 PERSONNE' EXPOSURES NUM9ER DESCRIPTICN li l 71 l l I l@lTYPE l @l i PERSCNNEL INJUR ES NUYeER DESCRIPTION li ia l l I I l@l12 I 7 8 9 11 90 LOSS TYPE OF OR DAVAGE TO FACILITY Q DESCRIPTION v 7 8 9 10 80 DESCRIPTION

• ISSUED l2 l0l l 7 8 9 lhl TO l

68 63 llll]l1lll lllf SO ; 1 NAME OF PREPARER PHONE: