ML18096B265

LER 93-001-00:on 930111,TS 3.0.3 Intentionally Entered Twice Due to Removal of Main & Auxiliary 115-volt Power Supply Fuses.Caused by Equipment Failure.Design Change Will Be Installed to Relocate flange.W/930209 Ltr

ML18096B265
Person / Time
Site:	Salem
Issue date:	02/09/1993
From:	Pollack M, Vondra C Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-93-001, LER-93-1, NUDOCS 9302170235
Download: ML18096B265 (5)

Text

.. e PS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station -

February 9, 1993 U. s. Nuclear Regulatory Commission Docu~ent Control Desk Washington, DC 20555

Dear Sir:

SALEM GENERATING STATION LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT NO. 1 LICENSEE EVENT REPORT 93-001-00 This Licensee Event Report is being submitted pursuant to the requirements of the Code of Federal Regulations lOCFR 5 0

• 7 3 (a) ( 2) ( i) ( B)

• This report is required to be issued within thirty (30) days of event discovery.

sincerely yours,

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. c. A Vondra General Manager -

Salem Operations MJP:pc Distribution 17004i 9302170235 930209

~DR ADOCK 05000272 PDR

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U.S. NUCLEAR REGULATORY COM.MISSl.ON (6-891 APPROVED OMB NO. 3150.-0104 EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD LICENSEE EVENT REPORT (LERI COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS.

AND REPORTS* MANAGEMENT BRANCH (P-5301. U.S. NUCLEAR

• ~ . REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3150-01041, OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.

FACILiTY NAME (11

- Unit 1 TITLE (41 Inooerabiiit 7 of Analoo Rod Position Indication: for Maintenance.Troubleshooting.

EVENT DATE (51. LEA NUMBER (61 REPORT DATE (71 OTHER FACILITIES INVOLVED (81 MONTH DAY YEAR YEAR I>< SEQUENTIAL NUMBER kt REVISION NUMBER MONTH DAY YEAR FACI LIT)' NAMES , DOCKET NUMBERISI .

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OPERATING

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I . I. I I I I I SUPPLEMENTAL REPORT EXPECTED 1141 MONTH DAY YEAR EXPECTED n

SUBMISSION DATE 1151 YES (If yes, complete EXPECTED SUBMISSION DATE) , I I I ABSTRACT (Limir to 1400 sps~es, i.e., approximately fiftetm single-space typewritten lines) (16)

On 1/11/93, from 1038 to 1039 hours0.012 days <br />0.289 hours <br />0.00172 weeks <br />3.953395e-4 months <br /> and from 1041 to 1043 hours0.0121 days <br />0.29 hours <br />0.00172 weeks <br />3.968615e-4 months <br />, Technical Specification (T/S) 3.0.3 was entered for action beyond T/S

.3.1.3.2.1, due to removing the main and auxiliary 115.;.:volt alternating current power.supply fuses to the 13-volt direct current power supply for the Analog Rod Position Indication (.ARPI) system.* Fuse removal eliminated the possibility of electrically shortfng the ARP! signal conditioning module.of control rod 204 and damaging* the 13-volt de

- power supply during troubleshooting of erratic 204 indication.

Nuclear Shift Supervisor (NSS) approval was obtained prior to removing the fuses and he was advised of the consequences of removing the fuses. In each case, the fuses were reinstalled, a channel check showed the ARP! system operable, and T / s *3 . o. 3 was exited~ Upon *a Reactor trip, I&C technicians, performing the troubleshooting, could have reinstalled the fuses restoring the ARP!. The 2D4 ARP! erratic indication resulted from failure of the 204 ARP! connector at the Reactor vessel head. Pipe flange leakage, immediately upstream of the Reactor head vent manual isolation valve, corroded the connector wire. The leakage was stopped through a temporary modification and*

the connector was repaired, restoring proper indication for 2D4.

During the next unit refueling, a design chan~e will be installed to relocate the.involved flange to eliminate a potential leak path that could affect ARP! connections.

NRC Fo~m 366 (6-891

---~--

".

LICENSEE EVENT REPORT Salem Generating Station (LER~

DOCKET NUMBER

• TEXT CONTINUATION LER NUMBER PAGE Unit 1 5000272 93-001-00 2 of 4 PLANT AND SYSTEM IDENTIFICATION:

Westinghou~e - Pressurized Water Reactor Energy Industry Identification System (EIIS) codes are identified in the text as {xx}

IDENTIFICATION OF OCCURRENCE:

Technical Specification (T/S) 3.0.3 entries; Inoperability of Analog Rod Position Indication (~PI) for Maintenance Troubleshooting Event Date: 1/11/93 Report Date: 2/9/93 This report was initiated by Incident Report No.93-022.

_CONDITIONS PRIOR TO OCCURRENCE:

-Mode*1 Reactor Power 100% Unit Load 1155 MWe DESCRIPTION OF OCCURRENCE:

Ori January 11, 1993, T/S 3.0.3 was interitionally entered twice (from 1038 to 1039 hours0.012 days <br />0.289 hours <br />0.00172 weeks <br />3.953395e-4 months <br /> and from 1041 to 1043 hours0.0121 days <br />0.29 hours <br />0.00172 weeks <br />3.968615e-4 months <br />). These events occurred due to removal of the main and auxiliary 115-volt alternating current power supply fuses (total of two)_ to the 13-volt direct current negative and positive power supply for the ARPI system

{AA}. The fuses were removed to support troubleshooting the ARPI of

• control rod 2D4 to determine the cause of _erratic position indication problems. * * *

• Fuse removal_ eliminated the possibility of electrically shorting the .

2D4 ARP! signal conditioning module and damaging the 13-volt de power supply during the 2D4 ARPI troubleshooting. This required removal and reinsertion of the 2D4 module. Nuclear Shift Supervisor (NSS) approval was obtained prior to removing the fuses .. The Maintenance Department Supervisor aQ.vised the NSS of the consequences of removing the fuses for ARPI (see Analysis of Occurrence section).

Troubleshooting was performed using procedure SC.IC-GP.ZZ-0006(Q),

"CONTROLS EQUIPMENT*- TROUBLESHOOTING".

TI s 3 o'l. 3. 2. 1 addresses the operability. requirement of the .

"Reactivity Control System's" {AA} position indicating systems. The indicatdrs are determiried oper~ble by verifying the rod position indication system agrees within twelve (12) steps of the group demand counters. Actions required, if more than one ARP! per _bank is inoperable, exceed the Limiting Condition For Operation and associated ACTION requirements of T/S 3.1~3.2~1. As such, the required ~ctions associated with T/S 3.0.3 apply.

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 1 5000272 93-001-00 3 of 4 DESCRIPTION OF OCCURRENCE: (cont'd)

T/S 3.0.3 states:

"When a Limiting Condition for Operation is not met, except as provided in the associated ACTION requirements, within one hour action shall be initiated to place the unit in a MODE in which the specification_ does not apply by placihg it, as applicable, in:

1. At least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,

2. At least HOT SHUTbOWN within the following 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />sj and

3. At least COLD SHUTDOWN within th.e subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Where corrective measures are completed that permit operation under the ACTION requirements, the ACTION may be taken in accordance with the specified time limits as measured from the time of failure to meet the Limiting Condition of Operation.

Exceptions to these requirements are stated in th~ individual specifications."

This event is reportable per Code of Federal Regulations ,

lOCFR 50.73(a) (2) (i) (B).

APPARENT CAUSE OF OCCURRENCE:

The root cause of this e~ent is equipment failure. The T/S 3.0.3 entries were necessary to s~pport investigation of 2D4 erratic indication. On January 14, 1993, it was determined the 2D4 ARPI erratic indi~ation resulted f~om failure of the 2D4 ARPI connector at the Reactor vessel head. Boric acid f~om pipe flange leakage, immediately upstream of the Reactor.head vent manual-isolation valve, 1RC900_ {AB}, corroded the connector wire.

ANALYSIS OF OCCURRENCE:

Operability of the ARPis is required to determine control rod positions. This ensures compliance with control rod alignment and insertion limits assumed in the accident analyses.

Upon any known or suspected complete/partial loss of ARPI, in accordance with procedure Sl.OP-AB.ROD-0004 (Q), "ROD POSITION INDICATION FAILURE", the Control Operator will notify Reactor Engineering, to ensure shutdown margin is maintained, and the Maintenance Controls Department, to investigate and correct the cause of the problem. Reactor Operators utilize alternate monitoring systems; i.e. Nuclear Instrumentation,.Reactor Power Range channels, Intermediate and Source Range channels to confirm a Reactor trip coincident with unavailability of the ARPI.

• e LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER. PAGE Unit 1 . 5000272 93-001-00 4 of 4 Removing the subject fuses de-energized ARPI and resulted in no control rod: position indication at:

1) The Control Room*control rod console;

2) The,plant process P250 computer; and I,-*

3) The Safety Parameter Display System computer.

I However,. fuse removal did not affect operability of control rod overhead annunciators (OHAs) and RP3 "Rod Bottom".indication.

Wh~n the 2D4 ARPI signal conditi9ning module was removed, in addition to the lost indications as described above, the 2D4 "Rod Bottom" OHA -

indicator light.lit, as expected. The "Rod Bottom" OHA indicator lights for the remaining control rods remained operable. -

Had-a Reactor trip occurred.while the fuses were removed,.Maintenance I&C technicians performing the 2D4 troubleshooting, could have reinstalled the fuses restoring the ARPI. This would not.have hindered the.Control Operators' response to a trip. Therefore, the health or safety of the public was not affected by this 'event.

CORRECTIVE ACTION:

• In each case, the fuses were reinstalled, a channel check was performed which showed the ARPI operable, and T/S 3.0.3 was exited.

The flange leak, affecting the 2D4 ARPI connector, was stopped through installation of a leak repair clamp in accordance .with a

• temporary modification. Periodic monitoring of the clamp will be performed.

During the next unit refueling outage, a design change will be installed to relocate the flange. The new location will eliminate a potentiai leak path that _could affect ARPI .connections. A similar design change will be installed on Salem Unit 2, during its next refueling outage.

The:2D4 ARPI connector was repaired restoring proper indication for the control rod.

a7'a General Manager -

Salem Operations MJPJ:pc SORC Mtg.93-013