ML18100A970

LER 94-006-00:on 940221,determined That TS 3.0.3 Entries Were Made When Arpi Sys Was Deenergized for All Control Rods.Signal Conditioning Modules 2C4 & 2SA2 Adjusted & TS 3.0.3 Was exited.W/940316 Ltr

ML18100A970
Person / Time
Site:	Salem
Issue date:	03/16/1994
From:	Hagan J, Pastva M Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-94-006, LER-94-6, NUDOCS 9404010021
Download: ML18100A970 (6)

Text

e t'

PS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station March 16, 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 9-4-006-00 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, MJPJ:pc Distribution 9404010021 940316 PDR ADOCK 05000272 5 PDR The pcmer is in your hands.

95-2189 REV 7-92

. NRG FORM 366 .S. NUCLEAR REGULATORY COMMISSION APPROVED 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 (Mf'!BB 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.

FACILITY NAME (1) II DOCKET NUMBER (2) PAGE (3)

Salem Generating Station - Unit 1 05000 272 1OF04 TITLE (4)

TS 3.0.3 Entry: Planned Inoperability Of ARPI System To Support Maint. Troubleshooting.

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

.. FACILITY NAME DOCKET NUMBER SEQUENTIAL REVISION MONTH DAY YEAR YEAR MONTH DAY YEAR NUMBER NUMBER 05000 FACILITY NAME DOCKET NUMBER 02 21 94 94

-- 006

-- 00 03 16 05000 94 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check one or more (11)

MODE (9) 1 20.402(b) 20.405(c) 50. 73 (a)(2)(iv) 73.71(b)

I L:~E~~~O) I 20.405(a)(1 )(i) 50.36(c)(1) 50.73(a) (2)(v) 73.71(c) 97 I 20.405(a)(1)(ii) 50.36(c)(2) 50. 73 (a) (2) (vii) OTHER (Specify in Abstract 20.405(a)(1 )(iii) x 50. 73 (a)(2)(i) 50.73(a)(2)(viii) (A) 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 LER (12)

NAME TELEPHONE NUMBER (Include Area Code)

M. J. Pastva, Jr. ..,. 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 TONPRDS SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED MOt:JTH 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)

Intentional Technical Specification (TS) *3.0.3 .entries were made on 2/21/94 (from 1819 to 1827 hours0.0211 days <br />0.508 hours <br />0.00302 weeks <br />6.951735e-4 months <br />) and 2/22/94 (from 1042 to 1052 hours0.0122 days <br />0.292 hours <br />0.00174 weeks <br />4.00286e-4 months <br />) due to deenergizing the Analog Rod Position Indication (ARP!)

System for all *control rods.* **The 115-volt alternating current (AC) power supply fuses to the ARPI System primary and auxiliary 13-volt direct current power supplies were conservatively removed to support correction of ARP! indication drift affecting rods 2C4 and 2SA2. In each case, rod positions were verified prior to fuse removal and after reinstallation. The root cause of these events isARPI System design that necessitated the TS 3.0.3 entries to avoid possible equipment damage during correction of the 2C4 and 2SA2 indication drift. The 2C4 and _2SA2 signal conditioning modules were adjusted, channel checks demonstrated ARP! operability, and TS 3.0.3 was exited. These modules will be replaced, as required, should recurring indication drift be identified. 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.

NRG FORM 366 (5-92)

REQUIRED NUMBER OF DIGITS/CHARACTERS 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 6TOTAL 7 REPORT DATE 2 PER BLOCK UPTO 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 CONTACT 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 94-006-00 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:

Two Technical Specification (TS) 3.0.3 Entries; Planned Inoperability of Analog Rod Position Indication (ARPI) System to Support Maintenance Troubleshooting

• Event Dates: 2/21/94 and 2/22/94 Report Date: 3/16/94 This report was initiated by Incident Report Nos.94-065 and 94-066.

CONDITIONS PRIOR TO OCCURRENCE:

(2/21/94)

Mode 1 Reactor Power 97% Unit Load 1140 MWe (2/22/94)

Mode 1 Reactor .Power 97.5% - Unit Load 1145 MWe DESCRIPTION OF OCCURRENCE:

Intentional TS 3.0.3 entries were made on February 21, 1994 (from 1819 to 1827 hours0.0211 days <br />0.508 hours <br />0.00302 weeks <br />6.951735e-4 months <br />) and February 22, .1994 (from 1042 to 1052 hours0.0122 days <br />0.292 hours <br />0.00174 weeks <br />4.00286e-4 months <br />) when the ARP! System {AA} was deenergized for*a11 control rods. In each case, the 115-volt alternating current (AC) power supply fuses to the primary and auxiliary 13-volt direct current (DC) power supplies for the ARP! System were removed. This was done as a conservative measure, to support correction of ARP! indication drift affecting rods 2C4 and 2SA2. In each case, rod positions, as compared to the.rod group demand indicator, were verified prior to fuse removal and after reinstallation.

ANALYSIS OF OCCURRENCE:

ARPI operability is necessary 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, the Safety Parameter Display

.System, the main process P250 computer, and locally via digital multimeter.

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER 'PAGE Unit 1 5000272 94-006-00 3 of 4 ANALYSIS OF OCCURRENCE: (cont'd)

TS 3.1.3.2.1 addresses the operability requirement of the "Reactivity Control System's" position indicating systems. The indicators are determined operable by verifying agreement within twelve (12) steps of the group demand counters. If more than one A.RPI 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.

Intentional TS 3.0.3 entries were made to support correction of instrument drift affecting the ARPI of Control Rod 2C4 and 2SA2. The 115-volt alternating current power supply fuses (total of four) to the primary and auxiliary 13-volt direct current negative and positive power supplies for the ARPI system were removed. This was a conservative measure to eliminate potential electrical shorting of the 2C4 and 2SA2 ARPI signal conditioning modules and damage to the 13-volt de power supplies. In each case rod positions, as compared to the rod group demand indicator, were verified prior to fuse removal and after reinstallation. Adjustments were made to the signal conditioning modules, channel checks demonstrated ARPI operability, and TS 3.0.3 was exited.

APPARENT CAUSE OF OCCURRENCE:

The cause of this event is "Design, Manufacturing, Construction/Installation", as classified in Appendix B of .

NUREG-1022. Design.of the ARPI. system necessitated the intentional TS 3.0.3 entries to avoid possible equipment damage during correction of the 2C4 and 2SA2 indication drift.

PREVIOUS OCCURRENCES:

Events requiring TS 3.0.3 entry to address ARPI concerns have previously occurred on both Salem Units (see LERs 272/93-007-00, 272/94-001-00, 272/94-004-00, 311/92-016-00, 311/93-010-00, 311/94-001-00, and 311/94-003-00). As a result, System Engineering has 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 from the system vendors will be used to develop appropriate action.

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 10 CFR 5 0

• 7 3 (a) ( 2 ) ( i) ( B)

• I LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER 'PAGE Unit 1 5000272 94-006-00 4 of 4 SAFETY SIGNIFICANCE: (cont'd)

Removing the subject fuses resulted in no control rod position indication at the Control Room control rod console. In addition, fuse removal did not affect operability of control rod overhead annunciators and RP3 "Rod Bottom" indication or.the ability for the control rods to insert into the reactor core upon receipt of a reactor trip or safety injection signal.

Had a Reactor trip occurred while the fuses were removed, technicians performing the 2C4 and 2SA2 troubleshooting and repair, could have reinstalled the fuses to restore the ARP! system. As such, the removal of the fuses would not have significantly affected the Control Operators' response to a trip.

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 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, the Senior 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 ARP!.

CORRECTIVE ACTION:

The 2C4 and 2SA2 signal conditioning modules were adjusted, channel checks demonstrated ARPI operability, and TS 3.0.3 was exited. These modules are part of the ARP! trending data base and will be replaced, as required, should recurring indication drift be identified.

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

ger -

ions MJPJ:pc SORC Mtg.94-024