ML20046B490

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LER 93-008-00:on 930701,discovered That During Previous Surveillance Testing on 910515,pump Differential Pressure Entered IST Required Action Range Due to Personnel Error. Plant Procedure AP 0164 Will Be revised.W/930730 Ltr
ML20046B490
Person / Time
Site: Vermont Yankee Entergy icon.png
Issue date: 07/30/1993
From: Wanczky R
VERMONT YANKEE NUCLEAR POWER CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-93-008, LER-93-8, NUDOCS 9308040281
Download: ML20046B490 (5)
v • d • e


Text

Vii1MONT YANKEE  ;

NUCLEAR POWER CORPORATION ,

i N /

h-- P 0. Box 157, Governor Hunt Road vernon, Vermont 05354-0157

,) (802) 257-7711

' ~j y.-.-p(+ r 3,

..' f..)

July 30, 1993 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555  ;

REFERENCE:

Operating License DPR-28 Docket No. 50-271 Reportable Occurrence No. LER 93-008 Dear Sirst As defined by 10 CFR 50.73, we are reporting the attached Reportable i Occurrence as LER 93-008. ,

Very truly yours, ,

VERMONT YANKEE NUCLEAR POWER CORPORATION ob W Robert J anczyk Plant Manager j l

~

cc Regional Administrator USNRC ,

Region I '

475 Allendale Road King of Prussia, PA 19406 i

0300C0 }Y ' I 9309040281 930730 P' - '

PDR ADOCK 05000271 S PDR j$;3 f

Wic foro 366 U.S. CUCLEAR REGULATC3Y COMMISSION APPROJED OMS No. 3150-0104

. (640) EXPIRES 4/30/02

. ESilMATED BURDEN PER RESPONSE TO COMPL7 C3ITH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS RECARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANACEMENT BRANCH (P-350), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3160-0104), CFFICE OF MANAGEMENT AND BUDCET, WASHINGTON, DC 20603.

FACILITY NAME (1) DOCKET Wo. (2) PAGE (3)

VERMONT YANKEE NUCLEAR POWER STATION Ol5l0l0l0l2l7l1 0 1 0F 0 4 TITLE (4)

"A" RHRSW purrp was not declared inoperable as required by the Inservice Testing (IST) Prograra.

EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8)

C:ONTH DAY YEAR YEAR SEQ # REV # MONTH DAY YEAR FACILITY NAMES DOCKET NO. (S) 0 5 0 0 0 0 7 0 1 9 3 9 3 -

0 0 8 -

0 0 0 7 3 0 9 3 0 5 0 0 0 C?ERATING THIS REPORT IS SUEMITTED PURSUANT To REQ'MTS OF 10 CFR i: CHECK ONE OR MORE (11)

MODE (9) N 20.402(b) 20.405(c) 50.73(a)(2)(Iv) 73.71(b)

POWER 20.405(a)(1)(1) 50.36(c)(1) 50.73(a)(2)(v) 73.71(c)

LEVEL (10) 1l0l0 20.405(a)(1)(li) X 50.36(c)(2) 50.73(a)(2)(vil) OTHER:

.................. 20.405(a)(1)(iii) 50.73(a)(2)(1) 50.73(a)(2)(viii)(A)

.................. 20.405(a)(1)(iv) 50.73(a)(2)(li) 50.73(a)(2)(viii)(B)

.................. 20.405(a)(1)(v) 50.73(a)(2)(ill) 50.73(a)(2)(x)

LICENSEE CONTACT FOR THIS LER (12)

NAME TELEPHONE NO.

AREA CODE ROBERT J. WANCZYK, PLANT MANAGER 8l0l2 2l5l7l-l7l7l1l1 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

CAUSE SYST COMPONENT MFR REPORTABLE CAUSE SYST COMPONENT MFR REPORTABLE TO NPRDF .... TO NPRDS ....

A BlI Pl l l Bl5l8l0 Yes ....

l l l l l l l I I I I I I I I I I I I I I SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED M0 DAY YR SUBMISSION DATE (15)

YES (If yes, conplete EXPECTED SUBMISSION DATE) X NO l l l ABSTRACT (Limit to 1400 spaces, i.e., approx. fif teen single-space typewritten lines) (16)

During technical specification surveillance testing performed on May 15,1991, the *A* RHRSW (P-8-1 A) pump was not declared inoperable when the differential pressure entered the IST Required Action Range. The relevant technical specification LCO (Limiting Condition of Operation) was not entered. However, a review of system operability testing performed on 5/15/91 reveals the LCO requirements were satisfied. Also, a review of testing data both prior to and following the 5/15/91 test indicates that the "A" RHRSW pump was able to provide the required cooling water flow. Thus, there was no impact to the safe operation of the plant.

The root cause of this event is attributed to a cognitive personnel error. The shift engineer who evaluated the surveillance data failed to correctly identify that the pump's differential pressure had entered the IST Required Action Range. The lack of independent review of the resultant test data has been identified as a contributing cause.

The Plant procedure (AP 0164) which is used to evaluate pump IST data is being revised to address these identifier 1 problems.

N3C Form 366 (6 89)

1 NRC Foro 366A U.S. NUCLEAR REGULATC37 CoMMISSIC3 APPROVED OMS No. 3150-0904

. (6-87) EXPIRES 4/30/92 ESTIMATED BCBDEN PER RESPC3SE To CoMPL7 tjlTH THIS INFoRMATIoN COLLECT!oW REQUEST: 50.0 HRS. FORWARD LIDENSEE EVENT REPORT (LER) COMMENTS RECARDING BURDEN ESTIMATE To THE RECORDS AND TEXT CoWTINUAT!oN REPORTS MANAGEMENT BRANCH (P 350), U.S. NUCLEAR REGULATORY ,

CoMMISSloN, WASHINGTON DC 20555, AND To THE PAPERWORK REDUCTION PROJECT (3160-0104), OFFICE oF MANAGEMENT AND BUDGET, WASHINGTON, DC 20603.

FACILITT NAME (1) DOCKET No (2) LER NUMBER (6) PAGE (3) ,

YEAR SEQ # REV #

UERMONT TANKEE NUCLEAR POWER CORPoRATloN 0l5l0l0l0l2l7l1 9 3 -

0l0 8 - 0 0 0 l2 oF 0 l4 TEXT (If more space is required, use additional NRC Form 366A) (17) l QfjCRIPTION OF EVENT On 7/1/93, while reviewing historical pump test data for the *A* RHRSW pump P-8-1 A (Ells = BI), it was discovered that during previous surveillance testing on 5/15/91, with the plant at 100% power, the pump's differential pressure had entered the IST ,

Required Action Range. Due to a cognitive personnel error, it was incorrectly logged in the IST Alert Range. '

When a pump parameter enters the IST Required Action Range, AP 0164 requires that the pump be declared inoperable and the 7 relevant Technical Specifications LCO entered to perform altemate operability testing. The relevant technical specification LCO was not entered.

CAUSE OF EVENT l

Vermont Yankee has performed a Root Cause Analysis for this event. The root cause of the failure to enter the Required Action l Range has been determined to be a cognitive personnel error. Using the correct procedure form (VYAPF 0164.02), the Shift ]

Engineer (SE) failed to correctly log the test data. The SE inadvertently placed a

  • check" mark in the procedure's ' ALERT
  • box '

instead of the

  • REQUIRED ACTION
  • box. Since the individual is no longer employed by the company, an interview with his supervisor indicates the individual received adequate training and his performance both prior to and following the event was satisfactory.

i A contributing cause has been determined to be lack of a meaningful independent review of the test data. A comparison of the two plant procedural forms (VYAPF 0206.02 and VYAPF 0164.02) which are used to assess IST test results, indicates that VYAPF 0164.02 lacks an independent review.

ANALYSIS OF EVENT Operability testing of the RHRSW Pumps is performed in accordance with Technical Specifications Section 4.5.C.1. This Section states that such testing shall be performed in accordance with Section 4.6.E.

Technical Specifications Section 4.6.E.2 states that:

l

  • Operability testing of safety-related pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g), except where written relief has been granted by the NRC pursuant to 10 CFR 50, Section 50.55a(g)(6)(i).*

Technical Specifications Section 4.5.C.1 also states that:

Pump hydraulic data, including differential pressure, is measured, recorded, and analyzed in accordance with Subsection IWP of ASME Section XI and Relief Request No. GP-1 of the Vermont Yankee Inservice Testing (IST) Program. Paragraph IWP-3100 of ,

ASME Section XI states.. *The resistance of the system shall be varied until either the measured differential pressure or the I measured flow rate equals the corresponding reference value." For the *A* RHRSW pump a reference technical specification flow of 2700 gpm is established and the resulting differential pressure compared to the established baseline value (169 psid).

NRC Form 366 (6-89)

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n NRC Form 366A U.S. NUCLEAR REGULATORY A A,n%wew--3W"NN..

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1 OtMPLY WITN TNis irm.a -QgignWSM " 'd.0 HRS. ~ FORWARD f

-LICENSEE EVENT REPORT (LER)- tin * - **%****** '467 ' 70 THE RECORDS AS -- . l TEXT CONTINUATION  :. -

U.S.' NUCLEAR REinfLATCutf -

- . .h;HEMAs:Nf32fM 7A C L 410 THE PAPERWORK '  ;

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1CE.OF MANAGEMENT AND , .1 w ::- -

FACILITY NAME (1) ggyn PM (3)( i 3.yaw :; 3.x.qWWy:o-s em ~ . - 2g VERMONT YANKEE NUCLEAR POWER CORPORATIPP hN];p.% . '~ , f Aj '. TW .:%. -

J]4 0F 0)l 4L TEXT (if more space is requiredi use additie W~P y

e CORRECTIVE ACTIONS (Continued) , ,

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Long Term-- - -

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1). Recent self-assessment activities ,

M anificant Correctivel Action Report (CAR). Th.is CAR w5 A_,-

't al ' Address the effects of cop pea *pu:, '

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g'g b) :- Introduce improvements k eponding to equipment -

performance in IST action - A ply l!., M c) ' Evaluate the validity of cu- s y,.;ifff4 M "" pra w "!

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. This CAR and the appropriate IST i .

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a). Additional training will be provided importance of attention to detail 6 -

[gsa5 wew&* cribed above and theJ apaMy  ;

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j Any significant recommendations from thi 1ans desenbad -

herein will be addressed in a supplement to

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ADDITIONAL INFORMATION

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24, and LER 89.

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NRC Fors 366 < 'l I

(6-89) t

C'RE Form 366A U.S. L'UCLEAR REGULATo2Y CcMMissio3 APPROVED OMS ko. 3150-0104

. (6-89) EXPIRES 4/30/92 ESTIMATED BURDEN PER CEsPo'1SE To COMPLY WITH TH!$

IkFoRMATION COLLECTION REQUEST: 50.0 hrs. FORWARD LICENSEE EVENT REPORT (LER) COMMENTS RECARDING BURDEN ESTIMATE To THE RECoRcS AND TEXT CONTINUAT10N REPORTS MAKAGEMENT BRANCH (P-350), U.S. NUCLEAR REGULATORY COMM1sS!oN, WASHINGTON DC 20555, AND To THE PAPERWORK REDUCT!oW PROJECT (3t60-0104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20603 FACILITY NAME (1) DOCKET No (2) LER NUMBER (6) PAGE (3)

YEAR SEQ # REV #

VERMONT YANKEE NUCLEAR POWER CoRPORATloW 0l5l0l0l0l2l7l1 9 3 -

0 0 8 -

0 0 0 l3 oF 0 l4 TEXT (if more space is required, use additional NRC Form 366Al (17)

ANALYSIS OF EVENT (Continued) i i

The Required Action Range per IST Relief Request No. GP-1 was clearly established as: less than 152 esid or creater than 183 niid. The 5/15/91 surveillance test resulted in a pump differential pressure of 151 psid which placed it in the IST Required Action Range. The Shif t Engineer responsible for the data entry and evaluation incorrectly logged the data in the IST Alert Range. .

+

I Although technically inoperable, the "A" RHRSW pump was able to provide the required cooling water flow based on the following acceptable performance indicators: j

1) Technical Specifications Section 4.5.C.1 requires that each RHRSW pump provides at least 2700 gpm with at least 70 psia being maintained at the RHR heat exchanger service water outlet. The outlet pressure assures that a higher tube side than shell side heat exchanger pressure exists to prevent the release of radioactivity from the RHR system into the RHRSW system. On 5/15/91, the "A" RHRSW pump provided 2700 gpm with greater than 260 psia maintained at the heat exchanger outlet. As such, the pump hydraulic requirements of Technical Specifications were satisfied. -
2) As indicated on the 5/15/91 surveillance data sheet, the vibration levels for "A" RHRSW pump were within acceptable limits.

When one of the RHRSW pumps is made or found to be inoperable, Technical Specifications Section 4.5.C.2 states that the operable RHRSW pumps shall have been or shall be demonstrated to be operable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Although Section 4.5.C.2 was not entered, a review of system operability testing indicates that the required alternate testing was in fact performed. The 5/15/91 data on the remaining three RHRSW pumps indicates acceptability as an attemate test. All four RHRSW pumps were being surveillance tested on 5/15/91 since the surveillance procedure had just been revised from monthly to quarterly and the plant had just retumed on line from an unplanned shutdown.

Technical Specifications Section 3.5.C.2 also states that when one of the RHRSW pumps is made or found to be inoperable, reactor operation is permissible only during the succeeding thirty days unless such pump is sooner made operable. On 5/28/91 and 8/14/91, altemate testing was performed on the "A" RHRSW pump with differential pressure out of the IST Required Action Rar.ge.

CORRECTIVE ACTIONS ,

Short Ter-

1) A copy of this LER will be distributed to the appropriate Operations Department personnel to re-emphasize the importance of attention to detail when evaluating test data.
2) Plant Procedure AP 0164 will be revised to require an independent review of the Shift Engineer's determination. This ,

procedure revision will be completed by 9-1-93.

NRC Form 366 (6-80)

WRC Foro 366A U.S. NUCLEAR REGULATOY COMMISSIC APPROL'ED OMS NO. 3150-0104

, * ('649) EXPIRES 4/30/93 ESTIMATE 9 BURDEN PER RESPONSE TO COMPLY UIVH THIS i INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD l LICENSEE EVENT REPORT (LER) COMMENTS RECARDING BURDEN ESTIMATE TO THE RECORDS AND ,

TEXT CONTINUATION REPORTS MANAGEMENT BRANCH (P-350), U.S. NUCLEAR REGULATORY j COMMIS$10N, WASHINGTON DC 20555, AND TO THE PAPERWORK i REDUCTION PROJECT (3160-0104), OFFICE OF MANAGEMENT AND '

BUDGET, WASHINGTON, DC 20603. I FACILITT WAME (1) DOCKET NO (2) LER NUMBER (6) PAGE (3)

YEAR SEQ # REV # ,

tfERMONT YANKEE NUCLEAR POWER CORPORATION 0l5l0j0l0l2l7l1 9 3 -

0 0 8 -

0 0 0 l4 0F 0 l4 TEXT (If more space is required, use additional NRC Form 366A) (17) ]

l f0RRECTIVE ACTIONS (Continued)

I Long Term: 1 l

1) Recent self-assessment activities involving the IST Program have resulted in the initiation of a significant Corrective Action Report (CAR). This CAR will:

a) Address the effects of cognitive personnel errors on the remaining pumps in the IST Program.

b) Introduce improvements in establishing new IST reference values and recognizing and responding to equipment performance in IST action ranges, c) Evaluate the validity of current reference values with respect to test results trending. i This CAR and the appropriate IST Program and procedure revisions will be completed by 12-31-93.

2) Additional training will be provided as a result of this LER to emphasize the procedure changes described above and the importance of attention to detail when evaluating test data.

l Any significant recommendations from the Corrective Action Report which would change the corrective actions described ,

herein will be addressed in a supplement to this LER. i ADDITIONAL INFORM ATION Previous similar events have been reported to the Commission, in the last five years, as LER 92-016, LER 89-24, and LER 89-  ;

20.  !

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i kRC Form 366 (6-89) l

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