ML20027D950

LER 82-097/03L-0:on 821008,HPCS Pump Declared Inoperable Based on Engineering Review of 821002 Incorrect Valve Lineup.Caused by Insufficient Retesting Following Valve Position Indicator Mod & Failure to Remove Info Tag

ML20027D950
Person / Time
Site:	Grand Gulf
Issue date:	11/05/1982
From:	Chenault W MISSISSIPPI POWER & LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20027D945	List: ML20027D944 ML20027D950
References
LER-82-097-03L, LER-82-97-3L, NUDOCS 8211100436
Download: ML20027D950 (4)

Text

NRC FORM 366 U. S. NUCLEAR REGULATCY COMMISSION LICENSEE EVENT REPORT Attschm nt to AECM-82/530 Page 1 of 4

, COrtTROL BLOCK: l l l l l l l (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6 lo li 8l l9 n l sLICENSEE 7

i c i cCODE l S I i 14l@l15o l o l _ l o LICENSE l o l oNUMBER l o l o l _ I n i25n l@l 26 aLICENSE l i l i lTYPEi l iJOl@l67 CAT I

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DOCKET NU. BER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h o 2 l With the plant in Cold Shutdown, the HPCS Pump was declared inoperable due to an I lo lal l engineering review of an incident which occurred on October 2,1982. This incident l lo l4 l l involved an incorrect valve lineup during the performance of a routine surveillance l l o l 5 I l on the HPCS System. This left only one ECCS pump, LPCS, operable. T.S.3.5.2. requires l l 0 l6 l l two ECCS Systems to be operable. This had no effect on the health and safety of the l

- l 0 l 7 l l public and did not constitute a threat to plant safety. This event is reported as l loia, ccquired by T.S.6.9.1.13.b. l 7 e .

80 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUSCODE l0l01 7 8 bdh Wh l B l@ lV l A lL lV lE lX l@ l Bl@ ]@

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43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h l 1 l 0 l l Tncorrect valvo linoun in the incident on october 2. 1982 van caused by insufficient l 1 1 l roresting following vnive nosition indientors modifiention nnd fn 41 tiro to romnvo nn I 1 7 l information tae on the valve which told the onerator to not rely on th'e position _ -l Iil3l Qudicator. The information_ tag was removed-and the Retest Control Proegdg e was l 1114I gavised. The system was tested and returned to service. I 7 8 9 80 A S  % POWER OTHER STATUS IS O RY DISCOVERY DESCRIPTION l1 l 5 I [_.C,.jh h) 1010lhl NA I [B_jhhperatorObservation/RoutineSurveillaned ACTIVITY CO TENT RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE 7

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LOSS OF OR DAMAGE TO FACILITY TYPE DESCHlPTION 1 9 (Jjhl NA I

, a 9 iO PUBL ICi f Y 8211100436 821105 80 PDR ADOCK 05000416 O NRC USE ONLY

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Attachment to AECM-82/530 Page 2 of 4 SUPPLEMENTAL INFORMATION TO LER 82-097/03 L-0 Mississippi Power & Light Company Grand Gulf Nuclear Station - Unit 1 Docket No. 50-416 Technical Specification Involved: 3.5.2 Reported Under Technical Specification: 6.9.1.13.b Event Narrative:

On October 2, 1982, with the plant in Cold Shutdown, Operations attempted to perform the HPCS Pump monthly surveillance test to prove operability of the system. The HPCS Pump was 911gned to take suction from the Condensate Storage Tank (CST) and pump thru the HPCS test return line back to the CST (See Figure 1). When the pump was started, the operator at the HPCS Pump noticed a waterleak from check valve F216. He immediately informed the control room operator of the leak and requested that the HPCS Pump be stopped. The control room operator, who had opened the F010 and F011 valves and established a flow of 5000 gpm, stopped the HPCS pump and closed the F010 and F011 valves.

A walkdown of the system piping was initiated to determine the cause for the leakage at valve F216. The walkdown revealed the top gasket of valve F216 leaking, possibly due to high pressure. Further inspection revealed valve F070 (at the CST) had a stem seal leak. The local position indicator for valve F070 indicated the valve was closed. The operator, who had verified the valve in the OPEN position prior to starting the HPCS Pump, was questioned about the discrepancy. He stated that when he went to valve F070 to verify the valve was open, he found the valve locked and the indicator showing closed. He notified the control room that the valve was indicating closed but there was an Information Tag (#821063) on the valve handle stating that the

" Indicator May Indicate Incorrectly, Do Not Rely On Indicator Pointer". He unlocked the valve and attempted to OPEN the valve. The valve opened about 1/4 turn and stopped. He backed the valve off 1/4 turn and tried to open the valve again. The valve stopped at the same position. With the information tag stating not to rely on the position indicator and his inability to open the valve any further, the operator informed the control room operator that the valve was OPEN but indicated CLOSED.

After the HPCS Pump was shutdown and valve F070 discovered leaking, two operators using a lever arm opened valve F070. The valve had been closed as indicated by the position indicator when the HPCS pump was started.

Previous Similar Events:

Further investigation revealed a Design Change (DCP 82/486) had been incorporated on valve F070 under a Maintenance Work Order (MWO M28924) on August 24, 1982 to correct the indicator problem. However, the information tag which was hung on July 28, 1982 stating "Do Not Rely on Indicator Pointer" was not removed following the indicator modification per the design change.

The information tag was verified removed on October 5, 1982. In addition to valve F070, an additional 60 valves with the Pratt Type MDT-5 Manual Valve Operators supplied with Pratt Butterfly Valves, were modified by the same

Attcchm:nt to 4 AECM-82/530 Page 3 of 4 design change. Each of the 60 valves had information tags hung on July 28, 1982, stating "Do Not Rely on Indicator Pointer". All the tags were verified removed on October 5, 1982. Administrative Procedure Protective Tagging System (01-S-06-1) states that any operations personnel may request that an information tag be removed when conditions no longer warrant the need for the information tag, however, the retest requirements should have specified tag removal.

Af ter valves F070 and F216 were found to be leaking, Maintenance Work Orders (MWO M2A695 and M2A696) were issued to correct the leaks. The F070 valve was replaced and the gaskets on F216 were replaced. In addition to the work orders issued, Operations initiated an Incident Report (82-10-07) documenting "An event happening out of the ordinary which is not a violation of plant operating procedures or Technical Specifications but is important for its historical significance or to prevent future incidents" (Section 5.1.1 and 5.2.4 of Administrative Procedure 01-S-06-5 "Iv.cident Reports / Reportable Events"). This incident was not considered reportable because the section of piping involved was the HPCS Test Line and therefore the HPCS system was still operable.

When the incident report was evaluated by the Engineering Department, Engineering recommended that the HPCS System be declared inoperable until certain additional checks could be completed.

The HPCS system was declared inoperable at 1720 on October 8, 1982 pending the results of the inspection previously described. Declaring the HPCS system inoperable required placing the plant in a Limiting Condition for Operation.

T.S.3.5.2 requires two operable ECCS systems during shutdown. LPCS remained the only operable ECCS System. LPCI "A" was considered inoperable due to being in the shutdown cooling mode. LPCI "B" and "C" were inoperable due to the associated Diesel Generator being out of service. This LC0 (82-0128) resulted in incident report 82-10-14 which required this LER per T.S.6.9.1.13.b.

At 1430 on October 10, 1982, the HPCS system was declared operable following the satisfactory completion of the required tests and inspections.

This event had no ef fect on the health or safety of the public and did not constitute a threat to plant safety.

The root causes of this event are attributed to the lack of adequate retest requirements by the Maintenance Work Order following the work on the F070 valve and improper valve position verification by the operator.

Since the performance of the Maintenance Work Order on August 24, 1982, Technical Section Procedure " Control of Retest Requirements" (09-S-07-6) has been revised to give better guidance to Maintenance Planners on what type of activities require retests and what type of retest are required.

Pratt valves with this type of position indication problem have all been modified and the information tags removed. This is a final report.

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