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{{#Wiki_filter:l OPS~G                      -
Puolic 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  
Puolic Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station March 2, 1994
: u. s. Nuclear Regulatory Commission Document Control Desk Washington, DC             20555


==Dear Sir:==
==Dear Sir:==
SALEM GENERATING STATION LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT NO. 1 LICENSEE EVENT REPORT 94-004-00 March 2, 1994 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.
SALEM GENERATING STATION LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT NO. 1 LICENSEE EVENT REPORT 94-004-00 This Licensee Event Report is being submitted pursuant to the requirements of Code of Federal Regulation 10CFR50.73(a) (2) (i} (B).
MJPJ:pc Distribution 9403090246 940302 PDR ADOCK 05000272 S PDR The power is in your hands. Sincerely yours, nager -Operations 95-2189 REV 7-92 l 1--NRC FORM 366 U.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 1 05000 272 1 OF 04 TITLE (4) .. T/S 3.0.3 Entry: Planned Inop. Of ARPI System To Support Maintenance Troubleshooting.
Issuance of this report is required within thirty (30} days of event discovery.
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 01 31 94 94 --004 --00 03 02 94 05000 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check one or more (11 MODE (9) 2 20.402(b}
Sincerely yours, nager -
20.405(c) 50.73(a}(2}(iv) 73.71 (b} POWER 20.405(a)
Operations MJPJ:pc Distribution 9403090246 940302 PDR ADOCK 05000272 S                         PDR The power is in your hands.
(1) (i) 50.36(c)(1) 50.73(a) (2) (v) 73.71 (c) LEVEL (10) 000 20.405(a}(1)(ii) 50.36(c)(2}
95-2189 REV 7-92
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 20.405(a)
NRC FORM 366                                           U.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 (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.
(1) (iv) 50.73(a)(2)(ii) 50.73(a) (2) (viii) (8) below and in Text, NRG Form 366A) 20.405(a)(1)(v) 50.73(a)(2}(iii) 50.73(a)(2)(x)
FACILITY NAME (1)                                                                                             DOCKET NUMBER (2)                                     PAGE (3)
LICENSEE CONTACT FOR THIS LER (12l 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) CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE CAUSE SYSTEM COMPONENT MANUFACTURER  
Salem Generating Station - Unit 1                                                                                         05000 272                             1 OF 04 TITLE (4)                                                                   ..
'REPORTABLE 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) An intentional Technical Specification
T/S 3.0.3 Entry: Planned Inop. Of ARPI System To Support Maintenance Troubleshooting.
{TS) 3.0.3 entry was made on 1/31/94 (from 0422 to 0443 hours) 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 ARP! System primary and auxiliary 13-volt direct current power supplies were conservatively removed to support correction of .ARP! indication drift affecting rod 2SA4. Rod positions were verified prior to fuse removal and after reinstallation.
EVENT DATE (5)                         LER 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 01             31       94       94
The root cause of this event is ARP! System design that necessitated the TS 3.0.3 entry to avoid possible equipment damage during correction of the 2SA4 indication drift. The 2SA4 signal conditioning module was adjusted, *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 ARP! System drift. NRG FORM 366 (5-92)
                                            --     004
BLOCK NUMBER 1 2 3 4 5 6 7 8 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 I LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 1 DOCKET NUMBER 5000272 PLANT AND SYSTEM IDENTIFICATION:
                                                              --     00           03           02                                                       05000 94 OPERATING                     THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check one or more (11 MODE (9)               2       20.402(b}                                 20.405(c)                               50.73(a}(2}(iv)                     73.71 (b}
Westinghouse  
POWER                         20.405(a) (1) (i)                         50.36(c)(1)                             50.73(a) (2) (v)                   73.71 (c)
-Pressurized Water Reactor LER NUMBER 94-004-00 PAGE 2 of 4 Energy Industry Identification System (EIIS)* codes are identified in the text as {xx} IDENTIFICATION OF OCCURRENCE:
LEVEL (10)           000         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)
Technical Specification (TS) 3.0.3 entry; Planned Inoperability of Analog Rod Position Indication (ARP!) system to Support Maintenance Troubleshooting Event Date: 1/31/94 Report Date: 3/2/94 This report was initiated by Incident Report No. 94-033. CONDITIONS-PRIOR TO OCCURRENCE:
-
Mode 2 Reactor Power 2% Unit Load -o-MWe DESCRIPTION OF OCCURRENCE:
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 (12l 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                                                                                         TO NPRDS I
SUPPLEMENTAL REPORT EXPECTED 14                                                               EXPECTED         MONTH       DAY   YEAR YES SUBMISSION NO (If yes, complete EXPECTED SUBMISSION DATE)                         x                                                         DATE (15)
ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16)
An intentional Technical Specification {TS) 3.0.3 entry was made on 1/31/94 (from 0422 to 0443 hours) 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 ARP! System primary and auxiliary 13-volt direct current power supplies were conservatively removed to support correction of .ARP! indication drift affecting rod 2SA4. Rod positions were verified prior to fuse removal and after reinstallation. The root cause of this event is ARP! System design that necessitated the TS 3.0.3 entry to avoid possible equipment damage during correction of the 2SA4 indication drift. The 2SA4 signal conditioning module was adjusted, *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 ARP!
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 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 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
 
I                 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station       DOCKET NUMBER    LER NUMBER        PAGE Unit 1                           5000272         94-004-00      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:
Technical Specification (TS) 3.0.3 entry; Planned Inoperability of Analog Rod Position Indication (ARP!) system to Support Maintenance Troubleshooting Event Date:   1/31/94 Report Date:   3/2/94 This report was initiated by Incident Report No. 94-033.
CONDITIONS-PRIOR TO OCCURRENCE:
Mode 2   Reactor Power 2%     Unit Load -o- MWe DESCRIPTION OF OCCURRENCE:
An intentional TS 3.0.3 entry was made on January 31, 1994 (from 0422 to 0443 hours) when the ARP! System {AA} was deenergized for all control rods. 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 rod 2SA4. Rod positions, as compared to the rod group demand indicator, were verified prior to fuse removal and after reinstallation.
An intentional TS 3.0.3 entry was made on January 31, 1994 (from 0422 to 0443 hours) when the ARP! System {AA} was deenergized for all control rods. 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 rod 2SA4. Rod positions, as compared to the rod group demand indicator, were verified prior to fuse removal and after reinstallation.
ANALYSIS OF OCCURRENCE:
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 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 (SPDS), the main process P250 computer, and locally via the digital multimeter.
ARPI provides actual rod position to the following locations:
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 ARPI per bank is
the Control Board dual channel position indicator modules, the Safety Parameter Display System (SPDS), the main process P250 computer, and locally via the digital multimeter.
 
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.
,                     LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station                   DOCKET NUMBER LER NUMBER  PAGE Unit 1                                       5000272     94-004-00  3 of 4 ANALYSIS OF OCCURRENCE:             (cont'd) 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.
If more than one ARPI per bank is
An intentional TS 3.0.3 entry was made to support correction of instrument drift affecting the ARPI of Control Rod 2SA4. 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 ARP! system were removed. This was a conservative measure to eliminate potential electrical shorting of the 2SA4 ARP!
, LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 1 DOCKET NUMBER 5000272 ANALYSIS OF OCCURRENCE: (cont'd) LER NUMBER 94-004-00 PAGE 3 of 4 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. An intentional TS 3.0.3 entry was made to support correction of instrument drift affecting the ARPI of Control Rod 2SA4. 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 ARP! system were removed. This was a conservative measure to eliminate potential electrical shorting of the 2SA4 ARP! signal conditioning module and damage to the 13-volt de power supplies.
signal conditioning module and damage to the 13-volt de power supplies. Rod positions, as compared to the rod group demand indicator, were verified prior to fuse removal and after reinstallation. Adjustments were made to the 2SA4 signal conditioning module, a channel check was made to demonstrate ARPI operability, and TS 3.0.3 was exited.
Rod positions, as compared to the rod group demand indicator, were verified prior to fuse removal and after reinstallation.
APPARENT C~USE      OF OCCURRENCE:
Adjustments were made to the 2SA4 signal conditioning module, a channel check was made to demonstrate ARPI operability, and TS 3.0.3 was exited. APPARENT 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 entry to avoid possible equipment damage during correction of the 2SA4 indication drift.
The cause of this event is "Design, Manufacturing, Construction/Installation", as classified in Appendix B of NUREG-1022.
PREVIOUS OCCURRENCES:
Design of the ARPI System necessitated the intentional TS 3.0.3 entry to avoid possible equipment damage during correction of the 2SA4 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, 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 to identify problem electronic modules.     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.
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, 311/92-016-00, 311/93-010-00, 311/94-001-00, and 311/94-003-00).
SAFETY SIGNIFICANCE:
As a result, system Engineering has developed an ARPI trending data base to identify problem electronic modules. 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:
This event did not affect the health and safety of the public and is reportable to the NRC pursuant to Code of Federal Regulations 10 CFR 5 0
This event did not affect the health and safety of the public and is reportable to the NRC pursuant to Code of Federal Regulations 10 CFR 5 0
* 7 3 (a) ( 2 ) ( i) ( B)
* 7 3 (a) ( 2 ) ( i) ( B)
* 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
* 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
,t LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 1 SAFETY SIGNIFICANCE: (cont'd) DOCKET NUMBER 5000272 LER NUMBER 94-004-00 PAGE 4 of 4 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 2SA4 troubleshooting and repair, 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. 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) I "ROD POSITION INDICATION FAILURE" I 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 ARPI. CORRECTIVE ACTION: The 2SA4 signal conditioning module was adjusted, a channel check was performed to demonstrate ARPI operability, and TS 3.0.3 was exited. 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.
~
,t LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station         DOCKET NUMBER     LER NUMBER       PAGE Unit 1                              5000272        94-004-00       4 of 4 SAFETY SIGNIFICANCE:    (cont'd) 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 2SA4 troubleshooting and repair, 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.
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) I "ROD POSITION INDICATION FAILURE" I 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 ARPI.
CORRECTIVE ACTION:
The 2SA4 signal conditioning module was adjusted, a channel check was performed to demonstrate ARPI operability, and TS 3.0.3 was exited.
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.
* MJPJ:pc SORC Mtg. 94-020}}
* MJPJ:pc SORC Mtg. 94-020}}

Revision as of 10:31, 21 October 2019

LER 94-004-00:on 940131,intentional TS 3.0.3 Entry Made Due to Deenergizing Analog Rod Position Indication (Arpi).Signal Conditioning Module 2SA4 Adjusted & Channel Check Performed to Demonstrate Arpi operability.W/940302 Ltr
ML18100A917
Person / Time
Site: Salem PSEG icon.png
Issue date: 03/02/1994
From: Hagan J, Pastva M
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-94-004, LER-94-4, NUDOCS 9403090246
Download: ML18100A917 (6)
v • d • e


Text

l OPS~G -

Puolic Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station March 2, 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 94-004-00 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, nager -

Operations MJPJ:pc Distribution 9403090246 940302 PDR ADOCK 05000272 S PDR The power is in your hands.

95-2189 REV 7-92

NRC FORM 366 U.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 (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 1 05000 272 1 OF 04 TITLE (4) ..

T/S 3.0.3 Entry: Planned Inop. Of ARPI System To Support Maintenance Troubleshooting.

EVENT DATE (5) LER 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 01 31 94 94

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-- 00 03 02 05000 94 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check one or more (11 MODE (9) 2 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) 000 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)

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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 (12l 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 TO NPRDS I

SUPPLEMENTAL REPORT EXPECTED 14 EXPECTED MONTH DAY YEAR YES SUBMISSION NO (If yes, complete EXPECTED SUBMISSION DATE) x DATE (15)

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

An intentional Technical Specification {TS) 3.0.3 entry was made on 1/31/94 (from 0422 to 0443 hours0.00513 days <br />0.123 hours <br />7.324735e-4 weeks <br />1.685615e-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 ARP! System primary and auxiliary 13-volt direct current power supplies were conservatively removed to support correction of .ARP! indication drift affecting rod 2SA4. Rod positions were verified prior to fuse removal and after reinstallation. The root cause of this event is ARP! System design that necessitated the TS 3.0.3 entry to avoid possible equipment damage during correction of the 2SA4 indication drift. The 2SA4 signal conditioning module was adjusted, *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 ARP!

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 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 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

I LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 1 5000272 94-004-00 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:

Technical Specification (TS) 3.0.3 entry; Planned Inoperability of Analog Rod Position Indication (ARP!) system to Support Maintenance Troubleshooting Event Date: 1/31/94 Report Date: 3/2/94 This report was initiated by Incident Report No.94-033.

CONDITIONS-PRIOR TO OCCURRENCE:

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

An intentional TS 3.0.3 entry was made on January 31, 1994 (from 0422 to 0443 hours0.00513 days <br />0.123 hours <br />7.324735e-4 weeks <br />1.685615e-4 months <br />) when the ARP! System {AA} was deenergized for all control rods. 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 rod 2SA4. 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 (SPDS), the main process P250 computer, and locally via the digital multimeter.

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 ARPI per bank is

, LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 1 5000272 94-004-00 3 of 4 ANALYSIS OF OCCURRENCE: (cont'd) 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.

An intentional TS 3.0.3 entry was made to support correction of instrument drift affecting the ARPI of Control Rod 2SA4. 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 ARP! system were removed. This was a conservative measure to eliminate potential electrical shorting of the 2SA4 ARP!

signal conditioning module and damage to the 13-volt de power supplies. Rod positions, as compared to the rod group demand indicator, were verified prior to fuse removal and after reinstallation. Adjustments were made to the 2SA4 signal conditioning module, a channel check was made to demonstrate ARPI operability, and TS 3.0.3 was exited.

APPARENT C~USE 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 entry to avoid possible equipment damage during correction of the 2SA4 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, 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 to identify problem electronic modules. 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:

This event did not affect the health and safety of the public and is reportable to the NRC pursuant to Code of Federal Regulations 10 CFR 5 0

  • 7 3 (a) ( 2 ) ( i) ( B)
  • 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

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,t LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 1 5000272 94-004-00 4 of 4 SAFETY SIGNIFICANCE: (cont'd) 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 2SA4 troubleshooting and repair, 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.

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) I "ROD POSITION INDICATION FAILURE" I 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 ARPI.

CORRECTIVE ACTION:

The 2SA4 signal conditioning module was adjusted, a channel check was performed to demonstrate ARPI operability, and TS 3.0.3 was exited.

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.

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