ML18059A367

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LER 93-006-00:on 930804,determined That Reg Guide 1.97, Category 1,pressurizer Level Indicator Powered from non- Safety Related Power Supply.Caused by Personnel Error. Indicator LIA-0102A Powered from Ac source.W/930903 Ltr
ML18059A367
Person / Time
Site: Palisades Entergy icon.png
Issue date: 09/03/1993
From: Hillman C, Slade G
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RTR-REGGD-01.097, RTR-REGGD-1.097 LER-93-006-01, LER-93-6-1, NUDOCS 9309130261
Download: ML18059A367 (5)
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Text

consumers Power GB Slade General Manager POWERIN&

. MICHl&AN'S PRO&RESS Palisades Nuclear Plant:

  • 27780 Blue Star Memorial Highway, Covert,* Ml 49043 _*

September 3, 1993 Nuclear Regulatory* Commission Document Control Desk

LICENSEE EVENT REPORT 93-006 - REGULATORY GUlDE 1.97,' PRESSURIZER lEVEL INDICATOR POWERED FROM A NON-CLASS IE POWER SUPPLY Lic~nsee Event Report (lER)* 93-006 is attached. This event is reportable in accordance with 10CFR50.73(a)(2)(ii)(B) as a condition outside the design basis of the p1ant.

  • Gerald B Slade General Manager
  • CC Administrator, Region III, USNRC NRC Resident Inspector - Palisades Attachment 1nnn0r; 9309130261 930903 PDR ADOCK 05000255 S PDR I -

. ACMSENER~COMPANY

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NRC Form 366 U.S. NU.CLEAR REGULATORY. COMMISSION:

19-83!

APPROVED Ol\llB NO. 3160-0104 EXPIRES: 8131186 LICENSEE EVENT REPORT (LERI*

FACILITY NAME 11! DOCKET NUl\llBER 121 PAGE 131 Palisades Plant 1 I OF 0 I4 TITLE 14 1 . REGULATORY GUIDE .1. 97, *PRESSURIZER LEVEL INDICATOR POWERED FROM A NON-CLASS lE POWER SUPPLY

  • EVENT CATE 16} LER NUMBER 161 REPORT DATE 161 OTHER FACILITIES INVOLVED 181 SEQUENTIAL REVISIO':' FACILITY NAl\llES MONTH DAV YEAR VEAR NUMBER. NUMBER MONTH DAY 'VEAR N/A ols ol4 9 3 ol o o.19 *ob N/A 0 1 1°1°1°1 I*

6 THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR I: !Ch.ck 0n. or mCNY ol tn. following/ 111 l 20.4061cl 60.3111cll11 -- 60. 7 31111211ivl 60.7311112lM 20,.406ioll1 lliiil -

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60.36ic1121 60.731*11211il -- 60.731111211viil

60. 7 31111211viiil1Al below end in i ext.

- 20.40611111 llivl 20.4061*111 }(vi 60.731*11211iil 60.731*11211iii}

60.731111211viiil1Bl 60.731*11211xl NRC Form 366AI LICENSEE CONTACT FOR THIS LER 1121 I

NAME TELEPHONE NUMBER AREA CODE Cris T. Hillman, Staff Licensing Engineer s I ., I s 1 I s I 4 I . I *a *1 9 I , I 3*

COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 113!

MANUFAC- REPORTABLE MANUFAC* REPORTABLE CAUSE SYSTEM COMPONENT TUR ER TO NPRDS CAUSE SYSTEM COMPONENT TUR ER TO NPRDS I I I I I I I I I I I I I I I .1 I I .I I I .I I I I I I n

SUPPLEMENTAL REPORT EXPECTED 1141 l\llONTH DAY YEAR EXPECTED YES~/ yH, compl*;. EXPECTED SVBMISSION.DATEI* rxi NO SUBl\lllSSION .

DATE 1161

  • 1 I I ABSTRACT !Limit to 1400 .,,.CH, i.*.. IPJNO*imor.ly lihffn liftg#--* .typewritten linHI 1161 On August 4~ 1993, at approximately 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br />, with the plant in cold shutdown for refueling, it was determined that a Regulatory Guide 1.97, Category 1~ pressurizer level indicator was powered from a non-safety related power supply. This condition was discovered during the review of electrical prints in support of the ongoing Configuration Control Program (CCP} drawing review. Field verification of the electrical print crinfirmed that the pressurizer level indicator was powered from a non-safety related power supply.

The cause of this event was personnel error and inadequate post modification testing.

Corrective action for this event includes powering indicator LIA-0102A-from

  • the correct power source pd or to the *e~d *or the -1993 refueling outage, training personnel on the.confusion that -may result when dealing with wire labeling associated with panels of similar alpha-numeric designation, and evalua~ing the* need for changes to procedures.*

NRC Form 388A U.S. NUCLEAR REGULATORY COMMISSION lt-83) APPROVED OM8 NO. 3160-010*

EXPIRES: 8/31186

. LICENSEE EVENT REPORT (LERI TEXT CONTINUATION FACILITY NAME 111 DOCKET NUMBER 121 PAGEi'!

SEQUENTIAL. REVISION YEAR NUMBER NUMBER Palisade*s Plant* ' 0 5 .o 0 0 2 5 5 9 3 0 0 6 0 Q Q 2. OF 0 4 EVENT DESCRIPTION On August 4, 1993r at approximately 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br />, with .the plant in cold shutdown for refueling, it was determined that the Regulatory Guide 1.97, Category 1, pressurizer *level indicator [AB;LI] LIA-0102A was powered from a non-safety related AC power supply. This condition* was di~covered during the review of electrical print~ in support of the ongoing Configuration Control Prbgram (CCP) drawing review.

  • Field verification of the electrical print

. confirmed. that LIA-0102A was powered from.a non-safety related AC power supply, panel Y-01.

  • This event is reportable to the NRC in accordance with 10CFR50.73(a)(2)(ii)(B) as a condition outside the design b~sis of the plant.

CAUSE OF THE EVENT The cause of this event was personhel error and inadequate post modification testing. The modification engineer mistakenly supplied Y-01 power to the instrument. Post modificatiOn testing was inadequate in that it did not verify that power for_ the indicator was supplied from Y-10 ..

This event did not involve the failure of any equipment important to safety.

ANALYSIS OF THE EVENT Facility Change FC~73J, "Upgr~d~ H~Sl/LPSI Flow Indication Instrument Loops,"

performed in 1988, replaced,. removed, or relocated many instruments. Among the instruments affected by this modification were the safety related pressurizer level transmitter LT-0102 and indicator LIA-0102A.- Three of the four previously installed safety related transmitters and indicators for the pressurizer were *removed under FC-731. *The fourth pressurizer transmitter and*

indicator, LT-0102A and LIA-0102A respectively; were replaced with instruments that met Regulatory Guide 1.97, Category 1, requirements. In addition, indicator LIA-0102A was moved from the EC~l2 panel located in the control room to the EC-02 panel,*also located in the control room, and re-powered.

It was the docum~nted intention of the modification engineer to* use a preferred AC power source from panel Y-10, breaker 5, for the relocated

. i iidi c*ator-trA-..oro*2A.**-rhEf'eng1 neer ap*p*arenl'1y mi sl aoe*nea- the ..Y.:11> wire terminations as Y-01 wire termination~~" the wiring diagrams thereby mistakenly supplying Y-01 power to LIA-0102A; however, the transmitter instrument loop (LT-0102) was correctly powered from a preferred AC power supply. This conclusion was reached after. consultation.with the modification i

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NRC Form 399A U.S. NUCLEAR REGULATORY. COMMISSION ~

lll-831 APPROVED OMB NO. 3160~10.

EXPIRES: 8/31 /86 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITY NAME 111 DOCKET NUMBER 121 LER NUMBER 131 PAGE 1*1 SEQUENTIAL REVISION YEAR NUMBER NUMBER Palisades -Plant

  • 0 5 0 0 Q 2 5 5 9* 3 - . Q Q 6 - Q Q. Q 3 OF Q 4
  • engineer and examination of the facility change packa~~. Items examined in
  • the facility change package were the modification plan, engineering analyses,
  • correspondence, engineeri.ng design changes, drawings, the test procedure, and review comments. The review of the facility change package also determined that testing performed as part of the modification did not check to verify that the power supply for indicator LIA-0102A was fed from Y-10.

Other instrument changes made in the facility change w~re exami~ed for discrepancies in their power sourc~. The examination consisted of reviewing the electrical schematic diagrams and the wiring diagrams to verify that the designated sources of power were correct. No discrepancies were found ..

Electrical loads identified on.the panel schedule for Y-iO were examined to verify that the wiring diagrams were powered from Y-10 and not Y-01. *No discrepancies, other than that. identified for LIA-0102A, were :found.*

Two other panels, Y-02 and Y-03, have a similar potential for .

misinterpretation of the labeling convention and might be confused with preferred electrical panels Y-20 and Y-3.0 respectively. The .probability of this similar confusion is very small since Y-02 and Y-03 are associated with the Critical Functirin Monitoring System (CFMS) and provide power to tnstruments located primarily in the tu~bine building. No instruments in the contr*o 1. room are fed from, panels Y-02 and Y:-03.

This i~cident is an isolated occurrence of an engineer mistaking one power source for ~nether due tb the similarities between their alpha-numeric designations. Modificatton testing did not uncover this mistake. The .I' modification testing program* has made significant improvements since the time of this modificatibn and it is unlikely that a similar .situation would occur under the current modification process.

Safety.Significance The safety significance of .this event is minor. LT-0103 is redundant td LT-0102 and would have provided control room ihdic~tion (via LIA~Ol03A) for .-

operator monitoring;* however, in 1992, as described in LER 92005, dated February i4, 1992, the LT-0103 circuit was fou*nd to be connected to a non-class_lE power iupply without adequate circuit isolation. In LER 92-005 we stated that, 11 * *

  • The. first instrwpe_nt 1oQp, LT-0.102, meets ap the _

"requirements of RG 1.97~ "-.*As* a. result *of this determination, it was conClijded a qualified pressurizer level indication instrument was available between the time of installation of the RG 1~97 qualified instruments iD 1988 and the discovery of the inadequate isolation of-LT-0103 from the non-class lE critical functions monitor system (CFMS) computer in 1992.

~ ~ ...

NRC Form 388A U.S. NUCLEAR REGULATORY COMMISSION 19-83) APPflOVEO OMB NO. 3160-010' EXPIRES: 8/31186

~-

LICENSEE EVENT REPORT (LERI TEXT CONTINUATION FACILITY NAME Ill DOCKET NUMBER 121 LER NUMBER 131 SEQUENTIAL REVISION YE.AR NUMBER NUMBER Palisades Plant. 0 *5 . 0 0 0 2 5 5 9 3 - 0 Q 6 - , 0 Q Q 4 OF 0 4 During the period between 1988 and 1992 both LT-0103 and LT-0102 were environmentally qualified and both were properly powered from class lE power supplies; however, the LT-0103 circuit was connected to the non-class 1E input from the CFMS ~omputer without ~dequate isolation, and LIA-0102A, the indicator for LT-0102, was *improperly powered from a non-class lE power supply (Y-01). Even with these inadequacies, it is highly unlikely that a single event would effect a simultaneous loss of indication of both channels of level indication, and, therefo~e, at least one of the instrument loops would have been available to provide the operators with pressurizer level indication ..

CORRECTIVE ACTION Corrective action for this event includes:

1. Power indicator LIA-0102A from the correct AC power sourte prior to the end of the 1993 refueling outage.
2. Train personnel on the confusion that may result when dealing with wire labeling associated with panels Y-10 and Y-01. Also, train personnel on the consideratiqns that should be given to the testing of modifications for the correct power source.
3. *Evaluate the need for chatiges to EGAD PMC&T-02, "Guideline for Preparing Modification Test Pr~c~dure," with respect to including instructions for the test procedure writer to check for proper power sources during a modification.
  • ADDITIONAL INFORMATION LER 92005, dated February 14, 1992,. identified a similar .Regulatory Guide 1.97 *'

concern for the opposite channel of the pressurizer level instrumentation

.. LT-0103.

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