ML18101A169

LER 94-012-00:on 940718,two Intentional TS 3.0.3 Entries Occurred 940718 Due to Deenergizing Arpi System for All Control Rods.Module 2C4 & Span of Module Were Adjusted & License Change Request Will Be submitted.W/940803 Ltr

ML18101A169
Person / Time
Site:	Salem
Issue date:	08/03/1994
From:	Hagan J, Pastva M Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-94-012, LER-94-12, NUDOCS 9408110258
Download: ML18101A169 (6)

Text

() PS~G e

Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station August 3, 1994

u. s. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sir:

SALEM GENERATING STATION LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT NO. 1 LICENSEE EVENT REPORT 94-012-00 This Licensee Event Report is being submitted pursuant to the requirements of Code of Federal Regulation 10CFR50.73(a) (2) (i) (B).

Issuance of this report is required within thirty (30) days of event discovery.

Sincerely yours, ag n General nager -

Salem Operations MJPJ:pc Distribution The power is in your hands.

r 9408110258 940803 PpR ADOCK 05000272 S PDR 95-2189 REV 7-92

NRC FORM 366 . NUCLEAR REGULATORY COMMISSION ~PPROVED BY OMB NO. 3150-0104 (5-92) EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD LICENSEE EVENT REPORT (LER) COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH (MNBB 7714), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF (See reverse for required number of digits/characters for each block) MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.

FACILl.TY NAME (1) DOCKET NUMBER (2) II PAGE (3)

~"'1 om r'.ono..-.qf";ncr St::tt; nn Unit 1 05000 272 1 OF04 TITLE (4) Intentional Technical Specification (TS) 3.0.3 Entries To Support Correction Of A-~1ncr 'Rn~ 'Pnc"j'";nn TnrHf'.::ttinn (ARPI) s,stem Drift AffectinQ: Rod 2C4.

EVENT DATE (5) LEA NUMBER (6 REPORT NUMBER (7) OTHER FACILITIES .INVOLVED (8\

FACILITY NAME DOCKE'( NUMBER SEQUENTIAL REVISION DAY YEAR MONTH DAY YEAR MONTH YEAR NUMBER NUMBER 05000 FACILITY NAME DOCKET NUMBER

-- -- 05000 n1 1A Q/, Qli. n12 00 08 03 94 I

I I OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check one or more 111)

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

I L:~E~~~O) I 002 I 20.405(a)(1 )(i) 50.36{c)(1) 50.73{a)(2)(v) 73.71 {c) 20.405 (a) (1) {ii) 50.36{c)(2) 50.73{a) {2) {vii) OTHER 20.405 (a) (1) (iii) 50.73(a)(2)(i) 50.73{a) (2) (viii) (A) (Specify in Abstract x below and in Text, NRG 20.405{a) (1) (iv) 50.73(a)(2)(ii) 50.73{a) (2) (viii) (B) Form 366A) 20.405 (a)(1 )(v) 50.73(a)(2)(iii) 50.73{a)(2)(x)

LICENSEE CONTACT FOR THIS LEA 12)

NAME TELEPHONE NUMBER (Include Area Code)

M .T p"'" f-'11'1 .Tr_ - .LER Coordinator (609) 339-5165 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

REPORTABLE REPORTABLE CAUSE SYSTEM COMPONENT MANUFACTURER CAUSE SYSTEM COMPONENT MANUFACTURER TO NPRDS TO NPRDS SUPPLEMENTAL REPORT EXPECTED 14) EXPECTED MONTH DAY YEAR I YES (If yes, complete EXPECTED SUBMISSION DATE) x NO SUBMISSION DATE (15)

ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16)

Two intentional Technical Specification (TS) 3.0.3 entries occurred on 7/18/94 due to deenergizing the Analog Rod Position Indication (ARP!)

System for all control rods to support correction of ARP! indicator drift for rod 2C4. Rod positions, as compared to the rod group demand indicator, were correct prior to and following the TS 3.0.3 entries.

Design of the ARPI System necessitated the TS 3.0.3 entries to avoid possible equipment damage during the 2C4 repair. Internal adjustments were made to the 2C4 signal conditioning module and the module span, a channel check demonstrated ARP! operability, and TS 3.0.3 was exited.

PSE&G will continue participation in the industry Rod Control User's Group and will utilize User's Group and vendor recommendations regarding ARPI System drift. A license change request will be submitted to more closely align with the recommendations of NUREG-1341, Vol. 1, by providing a time frame within the TS Action Statement to restore Operability when more than one ARPI indicator per bank is inoperable.

NRG FORM 366 (5-92)

e REQUIRED NUMBER OF DIGITS/CHARACTERS e

FOR EACH BLOCK BLOCK NUMBER OF TITLE NUMBER DIGITS/CHARACTERS 1 UP TO 46 FACILITY NAME 8 TOTAL 2 DOCKET NUMBER 3 IN ADDITION TO 05000 3 VARIES PAGE NUMBER 4 UP TO 76 TITLE 6 TOTAL 5 EVENT DATE 2 PER BLOCK 7 TOTAL 2 FOR YEAR 6 LER NUMBER 3 FOR SEQUENTIAL NUMBER 2 FOR REVISION NUMBER 6 TOTAL 7 REPORT DATE 2 PER BLOCK UP TO 18 FACILITY NAME 8 OTHER FACILITIES INVOLVED 8 TOTAL- DOCKET NUMBER 3 IN ADDITION TO 05000 9 1 OPERATING MODE 10 3 POWER LEVEL 1

11 REQUIREMENTS OF 10 CFR CHECK BOX THAT APPLIES UP TO 50 FOR NAME 12 LICENSEE CONT/>,.CT 14 FOR TELEPHONE CAUSE VARIES 2 FOR SYSTEM 13 4 FOR COMPONENT EACH COMPONENT FAILURE 4 FOR MANUFACTURER NPRDS VARIES 1

14 SUPPLEMENTAL REPORT EXPECTED CHECK BOX THAT APPLIES 6 TOTAL 15 EXPECTED SUBMISSION DATE 2 PER BLOCK

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 1 5000272 94-012-00 2 of 4 PLANT AND SYSTEM IDENTIFICATION:

Westinghouse - Pressurized Water Reactor Energy Industry Identification system (EIIS) codes are identified in the text as {xx}

IDENTIFICATION OF OCCURRENCE:

Intentional Technical Specification (TS) 3.0.3 Entries To Support Correction Of Analog Rod Position Indication (ARPI) System Drift Affecting Rod 2C4 Event Date: 7/18/94 Report Date: 8/3/94 This re~ort was initiated by Incident Report No.94-198.

CONDITIONS PRIOR TO OCCURRENCE:

Mode 2 Reactor Power 2% Unit Load -o- MWe DESCRIPTION OF OCCURRENCE:

Two intentional TS 3.0.3 entries occurred on July 18, 1994 (from 1051 to 1054 hours0.0122 days <br />0.293 hours <br />0.00174 weeks <br />4.01047e-4 months <br />, and from 1058 to 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br />) due to deenergizing the ARPI System {AA} for all control rods. These events occurred due to removing the 115-volt alternating current (AC) power supply fuses to the primary and auxiliary 13-volt direct current negative and positive power supplies for the ARPI System. This was done, as a conservative measure, to support correction of ARPI indication drift affecting rod 2C4. Rod positions, as compared to the rod group demand indicator, were correct prior to fuse removal and following fuse reinstallation.

ANALYSIS OF OCCURRENCE:

ARPI operability is required to determine individual control rod position and ensure compliance with control rod alignment and insertion limits assumed in the accident analyses. ARPI provides actual rod position to the following locations: the Control Board dual channel position indicator modules (supplied by Dixon), the Safety Parameter Display System (SPDS), the main process P250 computer, and locally via digital multimeter (DMM) .

In response to any known or suspected complete/partial loss of ARPI, the Control Operator will notify Reactor Engineering and the Maintenance Controls Department, in accordance with procedure

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 1 5000272 94-012-00 3.of 4 ANALYSIS OF OCCURRENCE: (cont'd)

Sl.OP-AB.ROD-0004(Q), "ROD POSITION INDICATION FAILURE", to ensure that shutdown margin is maintained and to investigate and correct the cause of the problem. In addition, Reactor Operators utilize alternate monitoring systems; i.e. Nuclear Instrumentation, Reactor Power Range channels, and Intermediate and Source Range channels to confirm a Reactor trip coincident with unavailability of the ARPI.

TS 3. 1. 3 . 2. 1 addresses the operability requir-ement of the "Reactivity Control System's" position indicating systems. The indicators are determined operable by verifying that the rod position indication system agrees within twelve (12) steps of the group demand counters.

If more than one ARPI per bank is inoperable, the Limiting Condition For Operation and associated ACTION requirements of TS 3.1.3.2.1 are not met and TS 3.0.3 therefore applies.

Two intentional TS 3.0.3 entries occurred to support correction of instrument drift affecting the ARPI of control rod 2C4. The 115-volt alternating current power supply fuses (total of four) to the primary and auxiliary 13-volt direct current negative and positive power supply for the ARPI system were removed. Internal adjustments were made to the 2C4 signal conditioning module and the module span, based on redeveloped secondary AC voltage value to the module. A channel check demonstrated ARPI operability, and TS 3.0.3 was exited.

APPARENT CAUSE OF OCCURRENCE:

These events are attributed to "Design, Manufacturing, Construction/Installation", as classified in Appendix B of NUREG-1022. Design of the ARPI System necessitated the TS 3.0.3 entries to avoid possible equipment damage during correction of the 2C4 indication drift.

PREVIOUS OCCURRENCES:

Events, attributed to ARPI design concerns, have occurred on both Salem units (see LERs 272/93-007-00, 272/94-001-00, 272/94-004-00, 272/94-006-00, 272/94-010-00, 311/92-016-00, 311/93-010-00, 311/94-001-00, 311/94-003-00, and 311/94-009-00). As a result, System Engineering developed an ARPI trending data base and identified problem electronic modules are being replaced as required. In addition, the industry Rod Control User's Group has recognized an industry-wide problem with ARPI System drift. Recommendations from this group and system vendors will be used to develop appropriate action.

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 1 5000272 94-012-00 4 of 4 SAFETY SIGNIFICANCE:

These events did not affect the health and safety of the public and are reportable to the NRC pursuant to Code of Federal Regulations 10CFR 50. 73 (a) (2) (i) (B).

Removing the subject fuses deenergized ARPI and resulted in no control rod position indication at the Control Room control rod console.

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

Had a Reactor trip occurred while the fuses were removed, technicians correcting the 2C4 indication drift, could have reinstalled the fuses to restore the ARPI System. As such, the removal of the fuses would not have significantly affected the Control Operators' response to a trip.

CORRECTIVE ACTION:

The 2C4 module and the span of the module were adjusted, a channel check was performed which demonstrated the ARPI operability, and TS 3.0.3 was exited. -

PSE&G will continue participation in the industry Rod Control User's Group and will utilize User's Group and vendor recommendations regarding ARPI System drift.

A license change request will be submitted, to more closely align the Salem TSs with the recommendations of NUREG-1341, Vol. 1, "Standard Technical Specifications - Westinghouse Plants", issued November 1992. This change will provide a short time frame within the TS Action Statement to restore Operability when more than one ARP!

indicator per bank is inoperable.

General a ger ~

Salem Operations MJPJ:pc SORC Mtg.94-062