05000280/LER-1980-014-01, /01T-0:on 800320,informed by Westinghouse That Incident of Stress Corrosion Cracking in Control Rod Support Pins & Flexures Noted in Foreign Plant.Vendor Testing & Assessment Program in Progress.Appropriate Action Planned

/01T-0:on 800320,informed by Westinghouse That Incident of Stress Corrosion Cracking in Control Rod Support Pins & Flexures Noted in Foreign Plant.Vendor Testing & Assessment Program in Progress.Appropriate Action Planned

ML18139A134
Person / Time
Site:	Surry
Issue date:	04/02/1980
From:	Joshua Wilson VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML18139A132	List: 05000280/LER-1980-002-01, /01T-0:on 800320,insp of Containment Following Type a Leak Rate Revealed Eight 1/4 Inch Holders Drilled Through Containment Liner.Caused by Improper Interpretation of Procedure During Design Change 78-48.Repair Planned 05000280/LER-1980-014-01, /01T-0:on 800320,informed by Westinghouse That Incident of Stress Corrosion Cracking in Control Rod Support Pins & Flexures Noted in Foreign Plant.Vendor Testing & Assessment Program in Progress.Appropriate Action Planned ML18139A131
References
LER-80-014-01T, LER-80-14-1T, NUDOCS 8004080486
Download: ML18139A134 (2)

LER-1980-014, /01T-0:on 800320,informed by Westinghouse That Incident of Stress Corrosion Cracking in Control Rod Support Pins & Flexures Noted in Foreign Plant.Vendor Testing & Assessment Program in Progress.Appropriate Action Planned

Event date:
Report date:
2801980014R01 - NRC Website

text

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e LICENSEE EVENT REPORT CONTROL BLOCK: ~_.___,.____._ _ _._l_.._!~18 6

(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

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LICENSEE CODE 14 U,

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60 61 DOCKET N.UMBER 68 69 EVENT DATE 74 75 REPORT DATE 80

.EVENT DESCRIPTION AND ?ROBABLE CONSEQUENCES@.

[IJIJ !Westinghouse has informed.us that an incident of stress corrosion cracking.in the control I

[£JI] I rod support pins and flexures in a foreign plant has been noted, and although there is no f

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I safety issue in. domesti_c operating plants the event is reportable under Title 10 CFR part I

((]}] I 21.

Should a broken pin develop from this condition, the control rod operation could be [TID I adversely affected.* This event is reportable in accordance with T.S. 6.6.2.A.5.

Since [BI) I these parts did not fail and both units were at cold shut down, the health and safety of * !

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I the public were not affected.

7 8 9 SYSTEM CODE I RI Bl@

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CAUSE

CAUSE COMP.

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. 13 18 19 SEQUENTIAL OCCURRENCE REPORT REPORT NO.

CODE TYPE l.:=J 1011141 1.......-1 lolil LI.J 23 24 26 27 28 29 30 VALVE.

SUBCODE lci 20 L=1 31 PRIME C:OMP.

80 REVISION COMPONENT ACTION FUTURE TAKEN ACTION EFFECT

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43 D:J::§J I The cracked pins identified were all from one heat treatment lot of material used in J:((J I foreign reactors.. A Westinghouse testing an~ an assessment_program is in.progress.to J:ID.I examine this situation more fully and the:.liceusee is prepared take ?P'P,rol?irat~ action JIIJ I based ~pon tlrn results of this rev~ew.

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FACILITY STATUS

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METHOD OF DISCOVERY DISCOVERY DESCRIPTION 32 W@INotification from Westinghouse.

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804.,-357-3184 NAME.OF PRFPAR*FR----.:._ __.;r iL* Wilson

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• e ATTACHMENT, PAGE 1 of 1 SURRY POWER STATION, UNIT 1 DOCKET NO:

50-280; 50-281 REPORT NO:

80-014/0lT-0 EVENT DATE:

3-20-80 TITLE OF EVENT:

CONTROL ROD MECHANISM POSSIBLE DEFECT

1.

DESCRIPTION OF EVENT

Westinghouse has provided information on the stress corrosion cracking of control rod support pins and flexures in an operating PWR plant in a foreign country.

Although Westinghouse state_d_ tll~re __ is no safety issue in domestic operating plants, they reported the event to the NRC under Title 18 CFR part 21.

In so much as the control rod operations could be adversely effected should a broken pin be experienced, the event is reported in accordance with T.S.6.6.2.A.5.

2.

PROBABLE CONSEQUENCES AND STATUS OF REDUNDANT SYSTEM:

Westinghouse has stated that no known cracking of support pins or flexures has been discovered in domestic plants and that on going testing efforts will provide information giving further assurance that this situation will not be a concern for any Westinghouse plant, Under these circumstances the health and safety of the public were not affected.

3.

CAUSE

The failure of Westinghouse supplied support pins noted to date has been limited to pins with solution heat treatment at 1625AF.

It should be noted that the present process for solution heat treatment

( in the.range of 1950°F to 2000°F) gives little indication of potential stress corrosion cracking.

4.

IMMEDIATE CORRECTIVE ACTION

Westinghouse has proposed a support pin inspection program and has recommended no licensee action be taken by Non URI plants until the results have been concluded.

5.

SCHEDULED CORRECTIVE ACTION:

Based upon the conclusion of the Westinghouse testing and assessment program, the licensee will take appropriate -measures to assure the reliability of this system.

6.

ACTION TAKEN TO PREVENT RECURRENCE:

None

7.

GENERIC IMPLICATIONS:

At this time this event is.not considered generic.

Past inspections by Westinghouse have revealed no material failures in the pins or flexures of domestic plants, however, they are pursuing a further inspection program to determine more fully the reliability of the parts used.