05000338/LER-1980-002-01, /01T-0:on 800107,S&W Informed Util That Stress on Vertical Supports RH-R-19 & WS-R-316 & Snubbers SI-HSS-101B,101C & 107A Exceeded Allowable Design Values. Caused by Wrong Valve Weights Used in Design Calculations

/01T-0:on 800107,S&W Informed Util That Stress on Vertical Supports RH-R-19 & WS-R-316 & Snubbers SI-HSS-101B,101C & 107A Exceeded Allowable Design Values. Caused by Wrong Valve Weights Used in Design Calculations

ML19257C012
Person / Time
Site:	North Anna
Issue date:	01/18/1980
From:	Cartwright W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19257C003	List: 05000338/LER-1980-002, Forwards LER 80-002/01T-0 05000338/LER-1980-002-01, /01T-0:on 800107,S&W Informed Util That Stress on Vertical Supports RH-R-19 & WS-R-316 & Snubbers SI-HSS-101B,101C & 107A Exceeded Allowable Design Values. Caused by Wrong Valve Weights Used in Design Calculations
References
LER-80-002-01T, LER-80-2-1T, NUDOCS 8001220563
Download: ML19257C012 (2)

LER-1980-002, /01T-0:on 800107,S&W Informed Util That Stress on Vertical Supports RH-R-19 & WS-R-316 & Snubbers SI-HSS-101B,101C & 107A Exceeded Allowable Design Values. Caused by Wrong Valve Weights Used in Design Calculations

Event date:
Report date:
3381980002R01 - NRC Website

text

U. S. NUCLEAR REGULATORY COMMISSION NRC FORM 366 17 77)

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8 60 61 DOCKET NUM9EH fA 63 EVENT OATE 14 15 REPOR T D ATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h lo l2l l On January 7,1980 Stone & Webster informed Vepco that they had discovorod tho 1

l stress on vertical supports RII-R-10 and hS-R-316 and snubbers SI-HSS-101B.101C.

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Virginia Electric and Power Cmpany North Anna Power Station, Unit #1 At tachnent :

Page 1 of 1 Docket No. 50-338 Report No. LER 80-002/01T-0

Description of Event

On January 7,1980, Stone & Webster infomxxl Vepco that vertical supports Ril-R-19 and WS-R-316 and snubbers SI-11SS-101B, 101C and 107A were stressed over the design allowable. 'Ihese nonconformances in pipe support design af fected the suction line to the residual heat renoval pmps, the discharge line of "B" safety injection acemulator, and the screen wash ptnp tie-in line to the discharge of the auxiliary service water pmps.

Probable Consequences of Occurrence Because the pipe supports were overstressed, it was possible that the suction and discharge of the residual heat raroval pmps, the discharge of "B" acctmulator, and the service water makeup fran the screen wash pmps could have failed during a seisnic event. 'Ihe health and safety of the general public were not affected by this occurrence. 'Ihere are no generic inplications associated with this event.

Cause of Occurrence The pipe supports were stressed over design allowable because of the following valve weight changes:

Hil-R-19 h W -1701_

Old Weight (Ibs.)

New Weight (lbs.)

Support Valve (s) 5562 3543 1-Ril-1 and 1-Ril-9 1862 2900 1-RII-8 and 1-RH-16 992 574 1-PJi-7 and 1-Ril-15 706 346 SI-IISS-101B 1-SI-142 and 1572 2100 1-SI-144 SI-IISS-101C SI -IISS-107A hS-R-316 P W -SW219 593 360 1-SW-24 500 190 Inmediate Corrective Action Vertical supports Ril-R-19 and WS-R-316 and snubbers SI-IISS-101B,101C, and 107A were modifiod or reinforced as detennined necessary.

Scheduled Corrective Action No scheduled corrective action is required.

Actions Taken to Prevent Recurrence No further actions are required.

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