ML19347D398

LER 80-013/03L-1:on 800715,pressurizer Code Safety Valve, RC-RV1B,lifted Below Tech Spec Limits.Cause Not Determined. Addl Testing Planned to Verify Site Heated Nitrogen Test Procedure Yields Results Comparable to Steam Pop Test

ML19347D398
Person / Time
Site:	Three Mile Island
Issue date:	03/13/1981
From:	Mitchell D METROPOLITAN EDISON CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19347D394	List: ML19347D393 ML19347D398
References
L1L-065, LER-80-013-03L, NUDOCS 8103170552
Download: ML19347D398 (2)

Text

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EVENT DESCRIPTION AND PMoSASLE CONSEQUENCES @. .

l I o i 21 1 During performance of the Pressurizer Code . Safety Valve Setpoint Verification  !

fo TTl I procedure, it was determined that RC-RVlB lif ted at 2330 psig, which is not within 1 J

Ioi.1Ilimits of 2500 psig t 1%. The unit has not been critical since the valve's T,T) i installation. Therefore, the health and safety of the public was not affected. l l

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l the seccific probable 1 li6oilInvestination of past testing history could not Additional testing of Code Safetv Valves is ]

Ii Ii 1 Icause for RC-RV1B low pop setpoint.

I m I olanned to verifv the site heated nitrocen test orocedure vields res  ;

,,,3j gble to actual steam pop test.

1 so IiIel l 7 a e DiSCCvtav 0ESCmiPTION DeSCO my j QTWEm 3TATUS A  % #04Wim l l B j@l Surveillance 80 W7-W@ 8 9 l 01 O ! 0l@l NRC Order 12 11 ee 46 46 LOCATION OF mtLEASE AadoyNT ca 4CTIVITY N/A l mtLEAsto 08 atLEAst

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, Attachm:nt 2

. . , , LiL 065 In accordance with the long ter= corrective action per LER 80-13, the Plant Engineering Staff has completed its investigation into the possible cause of RC-RV1B's low liftpoint. This investigation included a careful review of past THI-l testing data of the pressur-izer code safety valves including the test in question. This investi-gation could not identify any specific probable cause for low RC-RV1B pop setpoint.

To allow future analyses to be more conclusive in determining trends of possible setpoint drift, the Surveillance Procedure 1303-11.2 will be revised to require documentation of all intermediate and final valve adjustments by April 17, 1981.

The investigation for cause of this event raised questions about the validity of the site " heated nitrogen" test method results correlation with actual steam pop tests. Since these questions could not be conclusively answered; additional off-site tests are planned to definitely establish a steam-to-heated nitrogen test correlation for each code safety valve.

RC-RV1B was successfully reset in accordance with Surveillance Procedure SP 1303-11.2 to its proper "as-lef t" setpoint by simple adjustment of the spring compression screw and is reinstalled.

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