05000289/LER-1980-013-03, /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

/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:	Crane
Issue date:	03/13/1981
From:	Mitchell D METROPOLITAN EDISON CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19347D394	List: 05000289/LER-1980-013, Forwards LER 80-013/03L-1 05000289/LER-1980-013-03, /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
References
L1L-065, LER-80-013-03L, NUDOCS 8103170552
Download: ML19347D398 (2)

LER-1980-013, /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

Event date:
Report date:
2891980013R03 - NRC Website

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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 The unit has not been critical since the valve's J

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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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