ML20045G939

Lr 93-017-00:on 930616,containment Hydrogen Analyzer Heat Trace Channel Calibration Not Performed on Staggered Test Basis Due to Inadequate Implementation of TS Amend.Test Procedure Satisfactorily performed.W/930708 Ltr

ML20045G939
Person / Time
Site:	North Anna
Issue date:	07/08/1993
From:	Kane G VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-93-017, LER-93-17, NUDOCS 9307160166
Download: ML20045G939 (4)

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l VIRGINIA ELECTRIC ANO POWER COMPANY NO RTH AN NA POWE R S TATIO N P. O. B O X 4 02 MIN E RAL, VIRGINI A 23117 10 CFR 50.73 July 8,1993

'U. S. Nuclear Regulatory Commission NAPS:MPW l Attention: Document Control Desk Docket Nos. 50-338  !

Washington, D.C. 20555 50-339 License Nos. NPF-4 NPF-7

Dear Sirs:

The Virginia Electric and Power Company hereby submits the following Licensee Event Report applicable to North Anna Units 1 & 2.

Report No. 50-338/93-017-00 This Report has been reviewed by the Station Nuclear Safety and Operating Committee and will be forwarded to the Corporate Management Safety Review Committee forits review.

Very truly yours, G. E. ne Station Manager

Enclosure:

cc: U.S. Nuclear Regulatory Commission 101 Marietta Street, N.W.

Suite 2900 Atlanta, Georgia 30323 Mr. R. D. McWhorter, Jr.

NRC Senior Resident Inspector I North Anna Power Station 1

9307160166 93070s n PDR ADOCK 05000338 EI [1/1d b l S PDR y D .

NE FORM D8 US NUCLEAR REGULATORY COMMsSO APPROVED OMB NO. 315M104 See) . EXPIRES: 692 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATON COLLECTON REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN UCENSEE EVENT REPORTILERI ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT CRANCH (P-530L U.S.

NUCLEAR REGUL ATORY COMMISSION. WASHINGTON. DC 20555. AND TO THE PAPERWORK REDUCTON PRO 8ECT (3150 0104). OFFICE OF MANAGEMENT AND BUDGET WASHINGTON,DC 20503.

F ActuTY NAME (1) DOCAET NUMBLR (2) MGE m North Anna Power Station Units 1 and 2 al Q0l010l3l318 1IOFl013 W I'I CONTAINMENT HYDROCEN ANALY2ER HEAT TRACE CHANNEL CALIBRATION NOT PERFORMED CN A STAGCERED TEST BASIS AS REQUIRED BY TECHNICAL SPECIFICATIONS DUE TO INADEQUATE IMPLEMETATION OF TECHNICAL SPECIFICATION AMENDMENT EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER F ACILITIES INVOLVED (8)

MONTH DAY YEAR YEAR SEOUENTIAL REVSON MONTH DAY YEAR NUMBER NUMBER North Anna Unit 2 0l5l010l0131319 LXX.KET NUMBERC4

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0 6 1 6 9 3 9 3 0 1 7 0 0 0 7 0 8 9 3 gg gl g g g g g ; ; ;

OPE RA TING THIS HEPORT IS SuisMtT1ED PUHSUANT TO THE REOut4EME NTS OF to CF A l' (Checa one or mye W the kHowmg) 016 MODE (9) 1 20.402(b) 20.405(o 50.73(a(2)(iv) 73.71(b)

POWER 20@aH1)0) 50.36(cH1) 50.73(a)(2)(v) 73.71(c)

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LEVEL j OTHER is,=4 e anees 20.405(ax1)(if) 50.3C(c)(2) 50.73(a)(2)(vli)

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20.405(a)(1)9) 50.73(aX2)M 50.7' max 2)(vuiHA) 20.405:aK1)(iv) 50.73(a)(2501) 50.73(aX2)(vii)(B) 20.405(a)(1)(v) 50.73(a)(2)(ik) 50.73faK2)(x)

LICE N5EE CONI AOl FOR Tens lek 02)

NAME TELEPHONE NUMBER G. E. Kane aaEAccog 7l0l3 8l9l4l-l2l1l0l1 COMPLE TE ONE LINE FOR E ACH COMPONENT Fa1 LURE DESCRIBED IN THIS REPORT 03)

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l l i Ill llibuPPLEMENT AL hi POH1 Ex-ECTE D 04 l lil ll EXPECTED MONTH DAY YEAR SUBM!SSON YES tu res eam uPECTED SUBMSLON DATO NO DATE (15) l l l ABSTRACT pem = 14ao es=ee e e . moommew, waan mae. epa. ween m p 6) on June 16, 1993, with Units 1 and 2 in Mode 1, 100 percent power, the continuing evaluation of Technical Specification (TS) surveillance requirements, being performed as a corrective action reported under LER 50-338/92-007-00, identified that the containment hydrogen analyzer channel heat tracing calibration was not scheduled and performed in accordance with TS 4.6.4.1. The TS 92 day Staggered Test Basis requires that one train of heat trace be tested at least every 46 days in an alternating fashion. However, the periodic test procedure was not being performed on a Staggered Test Basis.

The condition is prohibited by TS and is reportable pursuant to 10CFR50.73 (a) (2) (1) (B) .

The cause of the event is inadequate implementation of TS Amendment No. 64 and No. 49 associated with the Three Mile Island (TMI) action item concerning Containment Hydrogen Monitor.

This event posed no significant safety implications because the periodic testa verified operability of both trains of heat tracing. The previous scheduling frequency of every 92 days had minimal safety implications.

, Therefore, the health and safety of the public were not affected at any time.

kEC Form Jbe Seen

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, NRC FORM 386A US WCLEAR REGULATORY COMMSSION APPROVED oMB No. 31fjkO104

!8-89) , EXPIRES: 46S2 ESTIMATED BURDEN PER RESPONSE To COMPLY wtTH THIS INFORMATON

, UOENSEE EVENT REPORT (LER) CoLLECTON REoVEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN TEXT CONTINUATION ESTIMATE To THE RECORDS AND REPORTS MANAGEMENT BRANCH (P-54 U.S.

NUCLEAR REGULATORY CoMMISSloN. WASHINGTON. DC 20555. AND TO THE l PAPERWORK REDUCTON PROJECT (31500104). OFFICE OF MANAGEMENT AND BUDGET.W ASHINGToN,DC 20503.

FCCluTY hAME (1) DOCKE T WMBLA (2) LER HUMBER (B) PAGE (3) gg SiOvEhl4 RE WISION 1

North Anna Power Station WuacR wuwiER Units 1 and 2 913 Of2 Ol3 nl;lnlelnl31318 --

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I 1.0 Descriotion of the Event On June 16, 1993, with Units 1 and 2 in Mode 1, 100 percent power, the continuing evaluation of Technical Specification (TS) surveillance requirements, being perforemed as a corrective action reported under LER 50-338/92-007-00, identified that the containment hydrogen analyzer (EIIS System IP, Component AA) channel heat tracing (EIIS Component EHTR) calibration was not scheduled and performed in accordance with TS 4.6.4.1. The TS 92 day Staggered Test Basis requires that one train of heat trace be tested at least every 46 days in an alternating fashion. However, the periodic test procedure was not being performed on a Staggered Test Basis. The condition is prohibited by TS and is reportable pursuant to 10CFR50.73 (a) (2) (1) (B) .

In response to Generic Letter 83-37, which provided guidance on the scope of TS for all TMI Action Plan Items, TS change requests were submitted. Upon approval of Amendment No. 64 and No. 49, June 25, 1985, a periodic test procedure was developed and implemented to verify operability of each hydrogen analyzer heat trace channel. The initial test procedure and subsequent revisions provided directions for operability verification at least every 92 days of Train A and Train B heat tracing in the same work evolution. As such, the definition of Staggered Test Basis as define in TS was not correctly implemented. Since there are two trains of heat tracing, the test must be performed on one train every 46 days to meet the TS requirement.

2.0 Significant Safety consequences and Irelications This event posed no significant safety implications because the periodic tests verified operability of both trains of heat tracing. The previous scheduling frequency of every 92 days had minimal safety implications.

Therefore, the health and safety of the public were not affected at any time.

3.0 Cause of the Event The cause of the event is inadequate implementation of TS Amendment No. 64 and No. 49 associated with the Three Mile Island (TMI) action item concerning Containment Hydrogen Monitor.

4.0 I m diate Corrective Actions The test procedure was satisfactorily performed of June 25, 1993 for the heat tracing of both Trcin A and B.

5_0 Additional Corrective Actions The periodic test procedure was revised to provide separate procedures for each train. The tests have been scheduled to be performed in an alternating fashion every 46 days such that both trains are tested within the 92 day interval.

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. NRC FORM 360A Us huctEAR R(.GULATORY COMMSSION APPROVED OMS NO,31504104 M 9 EXPIRES: 4CM2 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATON

. UCENSEE EVENT REPORT (LER) COLLECTON REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN EsmATE TO THE HECoROS AND REPORTS MANAGEMENT BRANCH (P-530). U.S. ,

• TEXT CONTINUATION NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20$55. AND TO THE PAPERWORK REDUCTON PROJECT (3150 0104). OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON,QC 20503.

F ACUTY NAME (1) DOCKEI NJMbLR(2) LER NUMBER (6) PAGE(3 g EQUENTAL REviSON North Anna Power Station NUMBER NUMBE R Units 1 and 2 ni s l a l n l n l 31318 913 -

0 l 1 l7 0 l0 013 OF Ol3 TEXT te mee apem a resumM ime emetenes NRC Fem sr.saw (17) 6.0 Actions to Prevent Recurrence Revision of the surveillance test procedures and schedule ensuring testing of one train every 46 days satisfies the surveillance requirement and will prevent recurrence.

7.0 Similar Events None 0_0 Additional Information The systematic review of the surveillance program was initiated to ensure full compliance with the TS at North Anna. The reviews involved a line-by-line examination to verify that TS surveillance requirements are completely addressed by station procedures. The reviews were completed on June 30, 1993 and included the following chapters: Chapters 1 Reactivity Control, 2 Power Distribution Limits, 3 Instrumentation (RPS, ESF, and Radiation Monitoring), 4 Reactor Coolant System, 5 Emergency Core Cooling System, 6 Containment, 7 Plant Systems, 8 Electric Power, 9 Refueling, 10 Special Test Exceptions, and 11 Radioactive Storage.

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