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Latest revision as of 04:19, 3 February 2020

LER 79-004/03L-0 on 790204:setpoints of Seven Main Steam Safety Valves Not within Tech Spec Limits.Caused by Normal Setpoint Drift
ML18113A857
Person / Time
Site: Surry Dominion icon.png
Issue date: 02/21/1979
From: Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML18113A856 List:
References
LER-79-004-03L-01, LER-79-4-3L-1, NUDOCS 7902260398
Download: ML18113A857 (2)


Text

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! During refueling shutdown whj_le conducting a periodic test, it was revealed that the setpoints of seven (7) Nain Steam Safety valves were not within plus .or minus three percent(+/- 3%) of the value required. The maximlIDl deviation experienced was 7%. This event is contrary to Technical Specification 3.6.A and the ASME Code and is reportable per Technical Specification 6.6.2.b.(2). This event had no effect upon the health IJ ':3 I LI------------------------------------------'

and safety of the public.

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-tAttachment, page 1 of Surry Power Station Dockel No:_50-281 Report no: 79-00L1/03L-0 Event Date: 02-04-79 Title of Report: HS Safety Valve Setpoint Drift

1. Description of Event:

During preparations for refueling, Periodic Test 13, Test of Main Steam Safety Valve Setpoints, seven (7) valves (HS-201B, 203B, 204B, 205B, 203C, 20L1C, 205C) were not within plus or minus three percent (+/- 3%) of the setpoint as required. The maximum deviation experienced was 7%. This event is considered contrary to Technical Specification 3.6 and ASME Code, and is reportable per Technical Specification 6.6.2.b.(2).

2. Probable Consequences:

As found, setpoints were conservatively below the established parameters, and valves would have relieved prematurely. This would not have affected the health and safety of the general public.

3. Cause of Event:

Setpoint drift such as experienced is anticipated, thus necessitating verification each refueling. Though the safety valves deviated from these setpoints, the capacity for pressure protection and steam flow relief was not impaired.

4. Immediate Corrective Action:

The safety valves which were out of specification were immediately reset to within plus or minus one percent (+/- 1%) of their setpoin t and retested to confirm proper response.

5. Scheduled Corrective Action:

None required since all valves were reset to "nameplate" pressure.

6. Action to Prevent Recurrence:

None

7. Generic Implications:

None