05000295/LER-1997-009-01, :on 970114,1FCV-CS0002 Was Inoperable Between 970115 & 0208.Caused by Failure to Verify That Acceptance Criteria for Return to Service Was Met.Disciplined Unit Supervisor & Will Cover Event in Licensed Operator Training

:on 970114,1FCV-CS0002 Was Inoperable Between 970115 & 0208.Caused by Failure to Verify That Acceptance Criteria for Return to Service Was Met.Disciplined Unit Supervisor & Will Cover Event in Licensed Operator Training

ML20141E366
Person / Time
Site:	Zion File:ZionSolutions icon.png
Issue date:	05/14/1997
From:	Brennan N COMMONWEALTH EDISON CO.
To:
Shared Package
ML20141E352	List: 05000295/LER-1997-009, Forwards LER 97-009-00 IAW 10CFR50.73(A)(2)(i)(B) Which Requires Listed Corrective Actions 05000295/LER-1997-009-01, :on 970114,1FCV-CS0002 Was Inoperable Between 970115 & 0208.Caused by Failure to Verify That Acceptance Criteria for Return to Service Was Met.Disciplined Unit Supervisor & Will Cover Event in Licensed Operator Training
References
LER-97-009-01, LER-97-9-1, NUDOCS 9705200417
Download: ML20141E366 (3)

LER-1997-009, on 970114,1FCV-CS0002 Was Inoperable Between 970115 & 0208.Caused by Failure to Verify That Acceptance Criteria for Return to Service Was Met.Disciplined Unit Supervisor & Will Cover Event in Licensed Operator Training

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(x)
2951997009R01 - NRC Website

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e LICENSEE EVENT REPORT (LER)

FACILITY NAME J0CKET NUMBER PAGE 0l5l0l0l0l2l9l5 1 l0Fl 0 l 3 ZION NUCLEAR POWER STATION UNIT TITLE IFCV-C50002 was inoperable between January 15. 1997, and February 8. 1997, because of failing to verify that the acceptance criteria for the return to service of IFCV-C50002 was met.

j EVENT DATE LER NUMBER REPORT CATE OTHER FACILITIES INVOLVED MONTH DAY YFAR YEAR SEO.

REV.

MONTH DAY YEAR FACILITY NAMt5 DOCKET N'JMBER(5) 7f0N UNIT 2 0 l 5 l 0 l 0 l 0 l 3 l 0 l4 olo ois 114 al7 I I I I I I I c13 114 9 !7 917 01019 THIS REPORT 15 5UBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR 6: (CHECK ONE OR MORE OF THE FOLLOWING)

OPERATING MODE 1

20.402(b) 20.405(e) 50.73(a)(2)(iv) 73.71(b)

P(kER 20.405(a)(1)(1) 50.36(c)(1) 50.73(a)(2)(v) 73.71(c) 0l9l9 LEVEL 20.405(a)(1)(11) 50.36(c)(2) 50.73(a)(2)(v11)

OTHER (Specify in 20.405(a)(1)(111) x 50.73(a)(2)(1) 50.73(a)(2)(viii)(A)

Abstract below 20.405(a)(1)(iv) 50.73(a)(2)(11) 50.73(a)(2)(vi11)(B) 20.405(a)(1)(v) 50.73(a)(2)(iii) 50.73(a)(2)(x)

LICENSEE CONTACT FOR THIS LER NAME TFtEPHONF NUMBFR N M. Brennan Reg Assurance Ext. 2380 slalv 7141si-lzinlele s fLETE ONE LINE FOR EACM COMPONENT FAILURE DESCRIBED IN THIS REPORT

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CAUSE

SYSl(M COMPONENT MANUFACTURER

CAUSE

SYSTEM COMPONENT MANUFACTURER TO NPRDS TO NPRDS I

I I I I I I I

I I I I I I I

I I I I I I I

I I I I I I SUPPL EMENTAL REPORT EXPECTED EXPECTED MONTH DAY YEAR SUBMISSION YES (if yes complete EXPECTfD SUBMISSION DATE)

NO DATE l

l l

ABSTRACT (limit to 1400 spaces. 1 e.

approa mately fifteen single-space typewritten lines).

Operating personnel failed to meet Technical Specification (TS) 4.0.5 " Inservice Inspection Surveillance Requirements." Ouring his review of PT-6B ST " Containment Spray B Pump Tests and Checks." a Unit Supervisor (US) mis-interpreted the partially e

performed Technical Staff Group Procedure (TSGP) T5GP-31, " Setting minimum flow stops for FCV-C50001. 2. 3" as meeting the operabiltty requirements of IFCV C50002. The US assumed that T5GP 31 had been completely performed, but did not review TSGP-

31. Therefore ICFV C50002 was inoperable between January 15 and February B. 1997. On February S. 1997. IFCV-C50002 was successfully " Fail Open" proven operable. Although not correctly documented, the valve was operated during the performance of T5GP-31 suf ficiently to provide assurance that following maintenance to the valve. it would fall open. When first reviewed.

It was considered that operability of the 1FCV-C50002 had been shown during the maintenance activity and this event was not reportable. Upon further evaluation it was determined on April 14. 1997 that because PT-6B ST was not performed on 1FCV-C50002. TS 4.0.5 requirements were violated. The Cause of this event is the practice which allows a single License Shift Supervisor to determine what sections of a prescribed Post Maintenance Test will be performed. A contributing cause of this event was the Unit Supervisor f ailing to verify that the acceptance criteria for the return to service of 1FCV-C50002 was met. Corrective actions include 1) Unit Supervisor has been counselled. 2)This event will t>e covered in Licensed Operator current events tratning 3) Deletion of a sections of prescribed Maintenance Test will require concurrence of two License Shift Supervisors.(NUREG Code 1022 code E) 9705200417 970514 PDR ADOCK 05000295 S

PDR ZtER\\97009 ler(1)

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LICENSEE EVENT REPORT (LER) TEXT C0NTINUATION FACILITY hME DOCKET NUMBER LER NUMBER PAGE YEAR SEO.

REV.

ZION NUCLEAR POWER STATION 0l3 0l5l0l0l0l2l9l5 9l7 0l0l9 0l0 0l2

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0F TEXT Energy Industry Identification System (EIIS) codes are identified in the text as [XX) l A.

PLANT CONDITIONS PRIOR TO EVENT j

Unit 1 MODE 1-power operations RX Power 99.6 RCS[AB] Temperature / Pressure SS9 deg F/2235 PISG l

l B.

DESCRIPTION OF EVENT

1.

3 On' January 14, 1997, at 0501 hours0.0058 days <br />0.139 hours <br />8.28373e-4 weeks <br />1.906305e-4 months <br /> the 18 Containment Spray (CS) [BE] pump was made inoperable to perform corrective maintenance. Part of the work package was the replacement of the valve actuator on IFCV-CS0002 [BE] "CS Pump B Recirculation Flow Control Valve." The work package contained requirements to perform Technical Staff Group Procedure (TSGP) TSGP-31 i

" Setting Minimum Flow Stops for FCV-CS0001, 2, 3" and Periodic Test (PT) PT-6B-ST l

" Containment Spray B Pump Tests and Checks." Both of these tests contain sections to perform

" Fail Open" tests on 1FCV-CS0002. TSGP-31 also contains a section that strokes 1FCV-CS0002 for setting minimum flow by removing the power from the wpply air solenoid, thus failing

]

1FCV-CS0002 open. The " Fail Open" test is required to meet Inservice Test (IST) requirements of Technical Specification (TS) 4.0.5.

l 4

1 TSGP-31 and PT-6B-ST were started at 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br />. TSGP-31 was completed at 0615 hours0.00712 days <br />0.171 hours <br />0.00102 weeks <br />2.340075e-4 months <br />. PT-68-ST testing continued through the 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> Operating Shift turnover and was completed at 0945 hours0.0109 days <br />0.263 hours <br />0.00156 weeks <br />3.595725e-4 months <br />. The applicable section on TSGP-31 was not used to test the " Fail Open" requirements and was marked "N/A" because of PT-6B-ST was specified in the work package to be performed to prove operability. Interviews with the System Engineer indicated that he requested flow readings from the Unit 1 Nuclear Station Operator (NS0) while setting the mechanical stops, but this was not documented. IFCV-CS0002 [BE] was failed open 10 times during the setting of the minimum flow stop. After test TSGP-31 was completed, the System j

Engineer performing the test notified the Unit One Unit Supervisor (US) and left the site.

The oncoming US. during his review of PT-68-ST. mis-interpreted the multiple stroking of 1FCV CS0002 performed in TSGP 31. The PT-68-ST section that tests the " Fail Open" requirements of IFCV-CS0002 was mistakenly marked "N/A" by the US. The US assumed that the entire TSGP-31 has been performed the preceding shift without verification. This resulted in j

IFCV-CS0002 being returned to service without being proven operable. On February 8. 1997.

IFCV-CS0002 was successfully " Fail Open" tested and proven operable. Therefore. 1FCV-CS0002 was inoperable between January 15. 1997, and February 8. 1997. When first reviewed, it was considered that operability of the 1FCV-CS0002 "CS Pump B Recirculation Flow Control Valve" had been demonstrated during the maintenance activity and this event was not reportable.

Upon further evaluation, it was determined on April 14. 1997. that because PT-6B-ST was not performed on IFCV-CS0002. the event violated 1S 4.0.5 requirements.

2LER\\97009.ler(2) 2

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LICENSEE EVENT REPORT (LER) TEXT CONTINUATION i

FACILITY NAME.

DOCKET NUMBER LER NUMBER PAGE I

YEAR sEO.

REV.

ZION NUCLEAR POWER STATION 0l3 f

0lSl0l0l0l2l9ls 9l7 0l0l9 0l0 0l3

~

~

0F TEXT Energy Industry Identification System (E!!S) codes'are identified in the text as [XXI

- C.

CAUSE OF EVENT

j The Cause of this event is the practice which allows a single License Shift Supervisor to.

determine what. sections of a prescribed Post Maintenance Test will be performed. A contributing cause of this event was the Unit Supervisor failing~to verify that the acceptance criteria for the return to service of 1FCV-CS0002 was met, i

D.

SAFETY ANALYSIS

Although.not correctly documented the valve was operated during the performance of TSGP-31.

l 1

." Setting Minimum Flow Stops For FCV CS0001.2.3." sufficiently to provide assurance that following maintenance the valve would fail open following a loss of instrument air. When s

adjusting the valve to meet its upper mechanical stop, the controller supplies zero current l

to the air supply solenoid which vents the control air from the valve actuator. This has the same effect as a loss of air. TSGP-31 step 7.2,13 records that at the upper mechanical stop the flow rate reads 145 gpm which is essentially full open. The valve came to this position by the engineer electrically opening the solenoid valve, venting the air from the actuator, and allowing the spring to force open the valve. The work performed replaced the valve diaphragm actuator. No work was performed on the actuation circuitry and therefore the

- l actuation circuitry function was not affected. The safety significance of the event is i

minimal arid the risk to the health and safety of the public was not affected J

E.

CORRECTIVE ACTIONS

j 1.

Unit Supervisor has been counselled.

2.

This event will be covered in Licensed Operator current events training.

3.

Plant procedures will be revised to require concurrence of two Licensed Shift Supervisors to delete sections of prescribed Post Maintenance Tests.

F.

PREVIOUS EVENTS SEARCH AND ANALYSIS A review of Zion's Nuclear Tracking System database has revealed a previous occurrence in which Licensed Shift Supervisors performed an inadequate review; refer to LERs 95-0006, 96 007 and 96-009. Zion Station has identified that problems exist in this area of surveillance compliance and is taking steps to elimirete this problem.

G.

COMPONENT FAILURE DATA

None J

I ZLER\\97009.ler(3)