05000280/LER-1979-040-01, /01T-0:on 791218,pipe Stress Reanalysis of Show Cause Lines Outside Containment Determined That Feed Header to Nonregenerative & Seal Water Heat Exchangers Overstressed Beyond 50% Ultimate Capacity.Mods Initiated

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/01T-0:on 791218,pipe Stress Reanalysis of Show Cause Lines Outside Containment Determined That Feed Header to Nonregenerative & Seal Water Heat Exchangers Overstressed Beyond 50% Ultimate Capacity.Mods Initiated
ML18136A340
Person / Time
Site: Surry Dominion icon.png
Issue date: 12/28/1979
From: Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML18136A339 List:
References
LER-79-040-01T, LER-79-40-1T, NUDOCS 8001020490
Download: ML18136A340 (2)


LER-1979-040, /01T-0:on 791218,pipe Stress Reanalysis of Show Cause Lines Outside Containment Determined That Feed Header to Nonregenerative & Seal Water Heat Exchangers Overstressed Beyond 50% Ultimate Capacity.Mods Initiated
Event date:
Report date:
2801979040R01 - NRC Website

text

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U.S. NUCLEAR REGULATORY COMMISSION

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REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@

I Pipe stress reanalysis of show cause lines outside containment has determined that twal [ill]

supports on line 8 11-CC-61-151, the feed header to the non-regenerative and seal water

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.I heat exchangers, were overstressed beyond 50 percent ultimate caoacity.

This event is reportable in accordance with Tech. Spec. 6.6.2.a.9 and th~ NRC order lifting sus-

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pension of facility operation dated August 22, 1g79.

The health and safety of the

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CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 43 44 47 jStress analysis calculations indicated that initial configuration of the hangers did o:JJJ 1not meet acceotance criteria.

Modifications to the supports were initiated in accord-

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e Surry P~we'r Docket No.:

Station, Unit No. 1 50-280 Report No. :

Event Date:

79-040/0lT-0 12-18-79 Title of Report:

Excessive Stress on Pipe Hangers, Line 8"-CC-61-151

1.

Description of Event

While continuing the program of pipe stress analysis it was revealed that two (2) supports were overstressed (exceeding 50 percent ultimate capacity) on line 8"-CC-61-151 which ties into a CC feed header for the RHR heat exchanger.

This event is reportable in accordance with the NRC order lifting suspension of unit operation dated August 22, 1979 and Technical Specification 6.6.1.9.a.

2.

Probable Consequences and Status of Redundant Systems:

This line is connected to the non regenerative and seal *water heat exchang-ers and, had a rupture occurred due to the overstressed hangers, the possiblility for violating a LCO for the CC system could have existed.

Under the circumstances present, the health and safety of the public were not affected.

3.

Cause of Event

The architect engineer encountered this problem while conducting the pipe stress analysis precipitated by the NRG Show Cause Order.

4.

Immediate Corrective Action

Corrective action taken was to modify the supports in accordance with pre-liminary design drawings.

These modifications were completed prior to identification of overstressed conditions.

5.

Subsequent Corrective Action:

Since modifications have been made to eliminate the overstressed condition, no subsequent action is required.

6.

Future Corrective Action:

Analysis will continue and modifications will be made to relieve any over-stress conditions encountered.

7.

Generic Implications:

Analysis continues on both Unit No. 1 and Unit No. 2 to discover and rectify all overstressed conditions.