ML18101A170

LER 94-009-00:on 940715,two Intentional TS 3.0.3 Entries Occurred Due to Deenergizing Arpi Sys for All Control Rods.Caused by Design Manufacturing.Module 2SB2 & Span of Module Were adjusted.W/940803 Ltr

ML18101A170
Person / Time
Site:	Salem
Issue date:	08/03/1994
From:	HAGAN J J, PASTVA M J Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-94-009-01, LER-94-9-1, NUDOCS 9408110265
Download: ML18101A170 (6)

Text

• Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station u. s. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sir:

SALEM GENERATING STATION LICENSE NO. DPR-75 DOCKET NO. 50-311 UNIT NO. 2 LICENSEE EVENT REPORT 94-009-00 August 3, 1994 This Licensee Event Report is bei'.ng 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.

MJPJ:pc Distribution C: ("--; .. -.. , u (.,.. .. t..J '--\/ 9408110265 940803 PDR ADOCK 05000311 S PDR The power is in your hands. Sincerely yours, n General_ Manager -Salem Operations 95-2189 REV 7-92

" lfNRC 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 , LICENSEE EVENT REPORT (LER) INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD 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. FACILITY NAME (1) DOCKET NUMBER (2) PAGE (3) Salem Generating Station -Unit 2 05000 311 1 OF 04 TITLE (4) Intentional Technical Specification (TS) 3.0.3 Entries To Support Correction Of Analog Rod Position Indication

<ARPI) S*stem Drift Affecting Rod 2SB2. EVENT DATE (5) LER NUMBER (6 REPORT NUMBER (7) OTHER FACILITIES INVOLVED (8 SEQUENTIAL REVISION FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBER NUMBER MONTH DAY YEAR 05000 FACILITY NAME DOCKET NUMBER ----05000 07 15 94 94 009 00 08 03 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) POWER 20.405 (a)(1 )(i) 50.36(c)(1}

50.73(a)(2)(v) 73.71 (c) LEVEL (10) 100 20.405(a)

(1)(ii) 50.36(c)(2}

50.73(a)(2)(vii)

OTHER -20.405(a)

(1) (iii) x 50.73(a)(2)(i) 50.73(a) (2) (viii) (A) (Specify in Abstract below and in Text, NRG. 20.405(a}(1)(iv) 50.73(a)(2)(ii) 50.73(a) (2) (viii) (8) 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 CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE CAUSE SYSTEM COMPONENT MANUFACTURER TO NPRDS TO NPRDS SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED MONTH DAY YEAR I YES NO SUBMISSION (If yes, complete EXPECTED SUBMISSION DATE) x 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 7/15/94 due to deenergizing the Analog Rod Position Indication (ARPI) System for all control rods to support correction of ARPI indicator drift for rod 2SB2. 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 2SB2 repair. Internal adjustments were made to the 2SB2 signal conditioning module and the module span, a channel check demonstrated ARPI operability, and TS 3.0.3 was exited. PSE&G will continue participation in the industry _ j 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)

BLOCK NUMBER 1 2 3 4 5 6 7 8

• L 9 10 11 12 13 14 15 *

• REQUIRED NUMBER OF DIGITS/CHARACTERS FOR EACH BLOCK NUMBER OF DIGITS/CHARACTERS TITLE UP TO 46 FACILITY NAME 8 TOTAL 3 IN ADDITION TO 05000 DOCKET NUMBER VARIES PAGE NUMBER UP TO 76 TITLE 6 TOTAL 2 PER BLOCK EVENT DATE 7 TOTAL 2 FOR YEAR 3 FOR SEQUENTIAL NUMBER LER NUMBER 2 FOR REVISION NUMBER 6 TOTAL 2 PER BLOCK REPORT DATE UP TO 18 --FACILITY NAME 8 TOTAL -DOCKET NUMBER OTHER FACILITIES INVOLVED 3 IN ADDITION TO 05000 1 OPERATING MODE 3 POWER LEVEL 1 CHECK BOX THAT APPLIES REQUIREMENTS OF 10 CFR UP TO 50 FOR NAME 14 FOR TELEPHONE LICENSEE CONTACT CAUSE VARIES 2 FOR SYSTEM 4 FOR COMPONENT EACH COMPONENT FAILURE 4 FOR MANUFACTURER NPRDS VARIES 1 CHECK BOX THAT APPLIES SUPPLEMENTAL REPORT EXPECTED 6 TOTAL 2 PER BLOCK EXPECTED SUBMISSION DATE r *

• LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating station Unit 2 DOCKET NUMBER 5000311 PLANT AND SYSTEM IDENTIFICATION:

Westinghouse

-Pressurized Water Reactor LER NUMBER 94-009-00 PAGE 2 of 4 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 2SB2 Event Date: 7/15/94 Report Date: 8/3/94 This report was initiated by Incident Report No.94-196. CONDITIONS PRIOR TO OCCURRENCE:

Mode 1 Reactor Power 100% -Unit Load 1090 MWe DESCRIPTION OF OCCURRENCE:

Two intentional TS 3.0.3 entries occurred on July 15, 1994 (from 1012 to 1014 hours0.0117 days <br />0.282 hours <br />0.00168 weeks <br />3.85827e-4 months <br />, and from 1024 to 1026 hours0.0119 days <br />0.285 hours <br />0.0017 weeks <br />3.90393e-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 2SB2. 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 Unit 2 DOCKET NUMBER 5000311 ANALYSIS OF OCCURRENCE: (cont'd) :J:,.ER NUMBER 94-009-00 PAGE 3 of 4 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 requirement 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 2SB2. 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 2SB2 signal conditioning module and the module span, based on redeveloped secondary AC voltage value to the module. A channel check demonstrated ARP! 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 2SB2 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, and 311/94-003-00).

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 Unit 2 SAFETY SIGNIFICANCE:

DOCKET NUMBER 5000311 LER NUMBER 94-009-00 PAGE 4 of 4 These events did not affect the health and safety of the public and are reportable to the NRC pursuant to Code of Federal Regulations lOCFR 50.73(a) (2) (i) (B). Removing the subject fuses deenergized ARP! 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 2SB2 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 2SB2 module and the span of the module were adjusted, a channel check was performed which demonstrated the 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, in order 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! per bank is inoperable.

Genera nager -Salem Operations MJPJ:pc SORC Mtg.94-062