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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  
* Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station October 12, 1994 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC                     20555


==Dear Sir:==
==Dear Sir:==
SALEM GENERATING STATION LICENSE NO. DPR-75 DOCKET NO. 50-311 UNIT NO. 2 LICENSEE EVENT REPORT 94-010-00 October 12, 1994 This Licensee Event Report is being submitted pursuant to the requirements of Code of Federal Regulation 10CFR50.73(a)
 
(2) (i) (A). Issuance of this report is required within thirty (30} days of event discovery.
SALEM GENERATING STATION LICENSE NO. DPR-75 DOCKET NO. 50-311 UNIT NO. 2 LICENSEE EVENT REPORT 94-010-00 This Licensee Event Report is being submitted pursuant to the requirements of Code of Federal Regulation 10CFR50.73(a) (2) (i) (A).
MJPJ:pc Distribution  
Issuance of this report is required within thirty (30} days of event discovery.
':: ;_'-J ['" ,,... :... :1:1_; "* '-' 9410250120 941012 PDR ADOCK 05000311 S PDR The power is in your hanis. Sincerely yours, -1£11';, y 95-2189 REV I I NRC FORM 366 .:::.. NUCLEAR REGULATORY COMMISSION  
Sincerely yours, MJPJ:pc Distribution
*' 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) II PAGE (3) Salem Generating Station Unit 2 05000311 1 Of()4 TITLE (4) Controlled Reactor Shutdown uue To :n Centri:tugal Charging Pump Inoperable Greater Than 72 Hours EVENT DATE (5) LER NUMBER (6 REPORT NUMBER (7) OTHER FACILITIES INVOLVED 18\ REVISION FACILITY NAME DOCKET NUMBER SEQUENTIAL MONTH DAY YEAR MONTH DAY YEAR YEAR NUMBER NUMBER 05000 FACILITY NAME DOCKET NUMBER 09 22 94 94 --010 --00 10 12 94 05000 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  
          ':: ;_'- J ~ ['" ,,... '~
)(i) 50.36(c)(1) 50.73(a)(2)(v) 73.71 (c) LEVEL (10) 100% 20.405(a)
:... :1:1_; ~ "* '-'
(1) (ii) 50.36(c)(2) 50.73(a) (2) (vii) OTHER -20.405(a)
9410250120 941012 PDR ADOCK 05000311 S                               PDR The power is in your hanis.                                                               -1£11' y
(1) (iii) x 50. 73 (a)(2)(i)
95-2189 REV -92
* 50.73(a) (2) (viii) (A) (Specify in Abstract below and in Text, NRC 20.405(a)
 
(1) (iv) 50.73(a)(2)(ii) 50.73(a) (2) (viii) (B) Form 366A) 20.405(a)(1  
I NRC FORM 366                                             .:::.. 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.
)(v) 50.73(a)(2)(iii) 50.73(a)(2)(x)
FACILITY NAME (1)                                                                                           DOCKET NUMBER (2)
LICENSEE CONTACT FOR THIS LEA {12) NAME TELEPHONE NUMBER (Include Area Code) M. J. Pastva, Jr*' Licensee Event Reuort Coordinator 609-339-5165 CAUSE SYSTEM COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)  
II PAGE (3)
"""'"°'""'  
Salem Generating Station Unit 2                                                                                           05000311                             1 Of()4 TITLE (4) Controlled Reactor Shutdown uue To                                   :n   Centri:tugal Charging Pump Inoperable Greater Than 72 Hours EVENT DATE (5)                           LER NUMBER (6                     REPORT NUMBER (7)                     OTHER FACILITIES INVOLVED 18\
';;;",';':,"°  
FACILITY NAME                           DOCKET NUMBER SEQUENTIAL           REVISION MONTH           DAY       YEAR     YEAR                                          MONTH         DAY   YEAR NUMBER             NUMBER                                                                           05000 FACILITY NAME                           DOCKET NUMBER 09           22         94         94     --     010           -- 00           10           12                                                     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)
"'"""
POWER                           20.405(a)(1 )(i)                           50.36(c)(1)                           50.73(a)(2)(v)                   73.71 (c)
REPORTABLE TO NPRDS x BO SC N402 N llJliilll SUPPLEMENTAL REPORT EXPECTED 114) EXPECTED MONTH DAY YEAR I YES SUBMISSION X (If yes, complete EXPECTED SUBMISSION DATE) NO DATE (15) 01 31 95 ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced tfPewritten lines) (16) At 0108 hours, on 9/19/94, 21 Cen rifugal Charging Pump (CCP} was removed from service for scheduled preventive maintenance.
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, NRC 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. J. Pastva, Jr*' Licensee Event Reuort Coordinator                                                             609-339-5165 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
CAUSE        SYSTEM
                            ~~~*            """'"°'""' ';;;",';':,"° *                             ~"'° "'""" ffiM~"ITT """'"°'"~                          REPORTABLE TO NPRDS x
llJliilll BO         SC                 N402                 N I                                    SUPPLEMENTAL REPORT EXPECTED 114)                                                           EXPECTED       MONTH       DAY   YEAR YES                                                                                                                         SUBMISSION NO X     (If yes, complete EXPECTED SUBMISSION DATE)                                                                                   DATE (15) 01         31     95 ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced tfPewritten lines) (16)
At 0108 hours, on 9/19/94, 21 Cen rifugal Charging Pump (CCP} was removed from service for scheduled preventive maintenance.
Post-maintenance testing results satisfied ASME operability criteria.
Post-maintenance testing results satisfied ASME operability criteria.
Increased axial vibration readings in 21CCP speed increaser were measured however, the vibration was not felt to impact pump operability and it was returned to service, at 2100 hours on 9/21/94. Additional vibration readings showed unstable and increasing speed increaser vibration and at approximately 0100 hours, on 9/22/94, 21CCP was declared inoperable (effective from prior removal from service on 9/19/94).
Increased axial vibration readings in 21CCP speed increaser were measured however, the vibration was not felt to impact pump operability and it was returned to service, at 2100 hours on 9/21/94.
At 0108 hours (same day) the Technical Specification (TS) action time expired and at 1222 hours (same day) the Unit was placed in MODE 4 (HOT SHUTDOWN).
Additional vibration readings showed unstable and increasing speed increaser vibration and at approximately 0100 hours, on 9/22/94, 21CCP was declared inoperable (effective from prior removal from service on 9/19/94). At 0108 hours (same day) the Technical Specification (TS) action time expired and at 1222 hours (same day) the Unit was placed in MODE 4 (HOT SHUTDOWN).                                     Identification of the cause of the high vibration in the 21CCP speed increaser, Nuttal Gear Corp., Model No.
Identification of the cause of the high vibration in the 21CCP speed increaser, Nuttal Gear Corp., Model No. SU-1023-SX, is pending results of root cause analysis by the vendor, with assistance from PSE&G. No problems were identified as contributory to this occurrence.
SU-1023-SX, is pending results of root cause analysis by the vendor, with assistance from PSE&G. No problems were identified as contributory to this occurrence. The 21CCP speed increaser was replaced, the pump was satisfactorily tested; and, at 2241 hours on 9/25/94, the TS action was exited.                                               It is anticipated that by 1/31/95 a supplement to this report will be submitted detailing the results of the root cause analysis of the 21CCP speed increaser high vibration.
The 21CCP speed increaser was replaced, the pump was satisfactorily tested; and, at 2241 hours on 9/25/94, the TS action was exited. It is anticipated that by 1/31/95 a supplement to this report will be submitted detailing the results of the root cause analysis of the 21CCP speed increaser high vibration.
NRC FORM 366 (5-92)
NRC FORM 366 (5-92)
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 *l
                                                                        *l 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
* LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 2 DOCKET NUMBER 5000311 PLANT AND SYSTEM IDENTIFICATION:
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
Westinghouse  
14                                      SUPPLEMENTAL REPORT EXPECTED CHECK BOX THAT APPLIES 6 TOTAL 15                                      EXPECTED SUBMISSION DATE 2 PER BLOCK
-Pressurized Water Reactor LER NUMBER 94-010-00 PAGE 2 of 4 Energy Industry Identification System (EIIS) and Institute of Electrical and Electronics Engineers (IEEE) Component Function Identifiers codes are identified in the text as {xx/xx} IDENTIFICATION OF OCCURRENCE:
 
Controlled Reactor Shutdown Due To 21 Centrifugal Charging Pump Inoperable Greater Than 72 Hours Event Date: 9/22/94 Report Date: 10/12/94 This report was initiated by Incident Report No. 94-271. CONDITIONS PRIOR TO OCCURRENCE:
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station       DOCKET NUMBER      LER NUMBER      PAGE Unit 2                           5000311         94-010-00      2 of 4 PLANT AND SYSTEM IDENTIFICATION:
Mode 1 Reactor Power 100% Unit Load 1080 MWe At 0108 hours on September 19, 1994, 21 Centrifugal Charging Pump (CCP) {BQ/P} was removed from service for scheduled preventive maintenance (PM). One of the activities was to investigate unusual noise from the speed increaser
Westinghouse   - Pressurized Water Reactor Energy Industry Identification System (EIIS) and Institute of Electrical and Electronics Engineers (IEEE) Component Function Identifiers codes are identified in the text as {xx/xx}
{BQ/P/SC}
IDENTIFICATION OF OCCURRENCE:
during pump operation.
Controlled Reactor Shutdown Due To 21 Centrifugal Charging Pump Inoperable Greater Than 72 Hours Event Date:   9/22/94 Report Date:   10/12/94 This report was initiated by Incident Report No. 94-271.
An adjustment was made to the motor shaft to speed increaser coupling.
CONDITIONS PRIOR TO OCCURRENCE:
Following post-maintenance testing, the pump, motor, and speed increaser vibrations were satisfactory and testing results satisfied ASME criteria for pump operability.
Mode 1     Reactor Power 100%     Unit Load 1080 MWe At 0108 hours on September 19, 1994, 21 Centrifugal Charging Pump (CCP) {BQ/P} was removed from service for scheduled preventive maintenance (PM). One of the activities was to investigate unusual noise from the speed increaser {BQ/P/SC} during pump operation. An adjustment was made to the motor shaft to speed increaser coupling.
Increased axial vibration readings were measured in the speed increaser.
Following post-maintenance testing, the pump, motor, and speed increaser vibrations were satisfactory and testing results satisfied ASME criteria for pump operability. Increased axial vibration readings were measured in the speed increaser. After Engineering review and consultation with the vendor, it was determined that the increased axial vibration did not impact pump operability. The pump was determined to be operable and returned to service, at 2100 hours on September 21, 1994. Additional vibration readings were recommended to verify that the axial vibration remained stable and that the consequences of the coupling adjustment were negligible.
After Engineering review and consultation with the vendor, it was determined that the increased axial vibration did not impact pump operability.
The pump was determined to be operable and returned to service, at 2100 hours on September 21, 1994. Additional vibration readings were recommended to verify that the axial vibration remained stable and that the consequences of the coupling adjustment were negligible.
DESCRIPTION OF OCCURRENCE:
DESCRIPTION OF OCCURRENCE:
At 2330 hours (same day), additional vibration readings indicated unstable and increasing axial vibration in the 21CCP speed increaser.
At 2330 hours (same day), additional vibration readings indicated unstable and increasing axial vibration in the 21CCP speed increaser. This condition challenged pump operability and at approximately 0100 hours, on September 22,1994, it was declared inoperable (effective from prior removal from service on September 19th) .
This condition challenged pump operability and at approximately 0100 hours, on September 22,1994, it was declared inoperable (effective from prior removal from service on September 19th) . Insufficient time remained to restore the pump to Operable status
Insufficient time remained to restore the pump to Operable status
* LICENSEE EVENT REPORT (LER} TEXT CONTINUATION Salem Generating Station Unit 2 DOCKET NUMBER 5000311 DESCRIPTION OF OCCURRENCE: (cont'd) LER NUMBER 94-010-00 PAGE 3 of 4 prior to expiration of the 72-hour action time of Technical Specification (TS} 3.5.2.a, which occurred at 0108 hours (same day}. At 0230 hours (same day} a controlled shutdown was initiated.
 
At 0300 hours (same day}, the NRC was notified of the initiation of the controlled shutdown, in accordance with lOCFR50.72(b} (i} (A}. At 0509 hours (same day} the Unit was placed in MODE 3 (HOT STANDBY} and, at 1222 hours (same day} was placed in MODE 4 (HOT SHUTDOWN}, as required by TS 3.5.2.a. ANALYSIS OF OCCURRENCE:
LICENSEE EVENT REPORT (LER} TEXT CONTINUATION Salem Generating Station       DOCKET NUMBER    LER NUMBER        PAGE Unit 2                           5000311         94-010-00        3 of 4 DESCRIPTION OF OCCURRENCE: (cont'd) prior to expiration of the 72-hour action time of Technical Specification (TS} 3.5.2.a, which occurred at 0108 hours (same day}.
In MODES 1 through 3, operability of two (2) independent Emergency Core Cooling Systems subsystems ensures sufficient emergency core cooling capability in the event of a Loss-Of-Coolant Accident assuming the loss of one subsystem through any active single failure consideration.
At 0230 hours (same day} a controlled shutdown was initiated. At 0300 hours (same day}, the NRC was notified of the initiation of the controlled shutdown, in accordance with 10CFR50.72(b} (i} (A}. At 0509 hours (same day} the Unit was placed in MODE 3 (HOT STANDBY} and, at 1222 hours (same day} was placed in MODE 4 (HOT SHUTDOWN}, as required by TS 3.5.2.a.
Whenever a single CCP is unavailable, the redundant CCP will provide high head injection flow for the mitigation of any design base accident.
ANALYSIS OF OCCURRENCE:
In MODES 1 through 3, operability of two (2) independent Emergency Core Cooling Systems subsystems ensures sufficient emergency core cooling capability in the event of a Loss-Of-Coolant Accident assuming the loss of one subsystem through any active single failure consideration. Whenever a single CCP is unavailable, the redundant CCP will provide high head injection flow for the mitigation of any design base accident.
APPARENT CAUSE OF OCCURRENCE:
APPARENT CAUSE OF OCCURRENCE:
Upon measuring high vibration in the 21CCP speed increaser it was conservatively determined that the pump was inoperable from when it was previously removed from service on September
Upon measuring high vibration in the 21CCP speed increaser it was conservatively determined that the pump was inoperable from when it was previously removed from service on September 19. As such, there was insufficient time to restore the pump to Operable status prior to expiration of the action time constraints of TS 3.5.2.a.
: 19. As such, there was insufficient time to restore the pump to Operable status prior to expiration of the action time constraints of TS 3.5.2.a. Identification of the cause of the high vibration in the 21CCP speed increaser, Nuttal Gear Corp., Model No. SU-1023-8X, is pending results of root cause analysis by the vendor, with assistance from PSE&G. No problems were identified as contributory to this occurrence.
Identification of the cause of the high vibration in the 21CCP speed increaser, Nuttal Gear Corp., Model No. SU-1023-8X, is pending results of root cause analysis by the vendor, with assistance from PSE&G. No problems were identified as contributory to this occurrence.
PREVIOUS OCCURRENCES:
PREVIOUS OCCURRENCES:
Based upon review of documentation, the high vibration of 21CCP pump speed increaser, as presently understood, is an isolated occurrence.
Based upon review of documentation, the high vibration of 21CCP pump speed increaser, as presently understood, is an isolated occurrence.
Line 72: Line 77:
SAFETY SIGNIFICANCE:
SAFETY SIGNIFICANCE:
This occurrence is reportable pursuant to the requirements of
This occurrence is reportable pursuant to the requirements of
* r
 
* LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 2 SAFETY SIGNIFICANCE: (cont'd) DOCKET NUMBER 5000311 LER NUMBER 94-010-00 PAGE 4 of 4 10CFR50.73(a)
r
(2) (i) (A), due to completion of a TS-required shutdown.
* LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station         DOCKET NUMBER     LER NUMBER       PAGE Unit 2                            5000311        94-010-00       4 of 4 SAFETY SIGNIFICANCE:  (cont'd) 10CFR50.73(a) (2) (i) (A), due to completion of a TS-required shutdown.
During this occurrence 22CCP was available, if required, to provide high head injection flow for the mitigation of any design base accident.
During this occurrence 22CCP was available, if required, to provide high head injection flow for the mitigation of any design base accident.
CORRECTIVE ACTION: The 21CCP speed increaser was replaced, the pump was satisfactorily tested; and, at 2241 hours on September 25, 1994, the Action of TS 3.5.2.a was exited. It is anticipated that by January 31, 1995 a supplement to this report will be submitted detailing the results of the root cause analysis of the 21CCP speed increaser high vibration.
CORRECTIVE ACTION:
The 21CCP speed increaser was replaced, the pump was satisfactorily tested; and, at 2241 hours on September 25, 1994, the Action of TS 3.5.2.a was exited.
It is anticipated that by January 31, 1995 a supplement to this report will be submitted detailing the results of the root cause analysis of the 21CCP speed increaser high vibration.
MJPJ:pc SORC Mtg. 94-078}}
MJPJ:pc SORC Mtg. 94-078}}

Latest revision as of 10:14, 23 February 2020

LER 94-010-00:on 940922,controlled Reactor Shutdown Occurred.Caused by Centrifugal Charging Pump 21 Being Inoperable for Greater than 72 H.Speed Increaser Replaced & Pump Satisfactorily tested.W/941012 Ltr
ML18101A293
Person / Time
Site: Salem PSEG icon.png
Issue date: 10/12/1994
From: Hagan J, Pastva M
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-94-010-00, LER-94-10, NUDOCS 9410250120
Download: ML18101A293 (6)
v • d • e


Text

OPS~G

  • Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station October 12, 1994 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 94-010-00 This Licensee Event Report is being submitted pursuant to the requirements of Code of Federal Regulation 10CFR50.73(a) (2) (i) (A).

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

Sincerely yours, MJPJ:pc Distribution

':: ;_'- J ~ ['" ,,... '~

... :1:1_; ~ "* '-'

9410250120 941012 PDR ADOCK 05000311 S PDR The power is in your hanis. -1£11' y

95-2189 REV -92

I NRC FORM 366 .:::.. 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)

II PAGE (3)

Salem Generating Station Unit 2 05000311 1 Of()4 TITLE (4) Controlled Reactor Shutdown uue To :n Centri:tugal Charging Pump Inoperable Greater Than 72 Hours EVENT DATE (5) LER NUMBER (6 REPORT NUMBER (7) OTHER FACILITIES INVOLVED 18\

FACILITY NAME DOCKET NUMBER SEQUENTIAL REVISION MONTH DAY YEAR YEAR MONTH DAY YEAR NUMBER NUMBER 05000 FACILITY NAME DOCKET NUMBER 09 22 94 94 -- 010 -- 00 10 12 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)

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, NRC 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. J. Pastva, Jr*' Licensee Event Reuort Coordinator 609-339-5165 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

CAUSE SYSTEM

~~~* """'"°'""' ';;;",';':,"° * ~"'° "'""" ffiM~"ITT """'"°'"~ REPORTABLE TO NPRDS x

llJliilll BO SC N402 N I SUPPLEMENTAL REPORT EXPECTED 114) EXPECTED MONTH DAY YEAR YES SUBMISSION NO X (If yes, complete EXPECTED SUBMISSION DATE) DATE (15) 01 31 95 ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced tfPewritten lines) (16)

At 0108 hours0.00125 days <br />0.03 hours <br />1.785714e-4 weeks <br />4.1094e-5 months <br />, on 9/19/94, 21 Cen rifugal Charging Pump (CCP} was removed from service for scheduled preventive maintenance.

Post-maintenance testing results satisfied ASME operability criteria.

Increased axial vibration readings in 21CCP speed increaser were measured however, the vibration was not felt to impact pump operability and it was returned to service, at 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br /> on 9/21/94.

Additional vibration readings showed unstable and increasing speed increaser vibration and at approximately 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />, on 9/22/94, 21CCP was declared inoperable (effective from prior removal from service on 9/19/94). At 0108 hours0.00125 days <br />0.03 hours <br />1.785714e-4 weeks <br />4.1094e-5 months <br /> (same day) the Technical Specification (TS) action time expired and at 1222 hours0.0141 days <br />0.339 hours <br />0.00202 weeks <br />4.64971e-4 months <br /> (same day) the Unit was placed in MODE 4 (HOT SHUTDOWN). Identification of the cause of the high vibration in the 21CCP speed increaser, Nuttal Gear Corp., Model No.

SU-1023-SX, is pending results of root cause analysis by the vendor, with assistance from PSE&G. No problems were identified as contributory to this occurrence. The 21CCP speed increaser was replaced, the pump was satisfactorily tested; and, at 2241 hours0.0259 days <br />0.623 hours <br />0.00371 weeks <br />8.527005e-4 months <br /> on 9/25/94, the TS action was exited. It is anticipated that by 1/31/95 a supplement to this report will be submitted detailing the results of the root cause analysis of the 21CCP speed increaser high vibration.

NRC FORM 366 (5-92)

  • l 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

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 2 5000311 94-010-00 2 of 4 PLANT AND SYSTEM IDENTIFICATION:

Westinghouse - Pressurized Water Reactor Energy Industry Identification System (EIIS) and Institute of Electrical and Electronics Engineers (IEEE) Component Function Identifiers codes are identified in the text as {xx/xx}

IDENTIFICATION OF OCCURRENCE:

Controlled Reactor Shutdown Due To 21 Centrifugal Charging Pump Inoperable Greater Than 72 Hours Event Date: 9/22/94 Report Date: 10/12/94 This report was initiated by Incident Report No.94-271.

CONDITIONS PRIOR TO OCCURRENCE:

Mode 1 Reactor Power 100% Unit Load 1080 MWe At 0108 hours0.00125 days <br />0.03 hours <br />1.785714e-4 weeks <br />4.1094e-5 months <br /> on September 19, 1994, 21 Centrifugal Charging Pump (CCP) {BQ/P} was removed from service for scheduled preventive maintenance (PM). One of the activities was to investigate unusual noise from the speed increaser {BQ/P/SC} during pump operation. An adjustment was made to the motor shaft to speed increaser coupling.

Following post-maintenance testing, the pump, motor, and speed increaser vibrations were satisfactory and testing results satisfied ASME criteria for pump operability. Increased axial vibration readings were measured in the speed increaser. After Engineering review and consultation with the vendor, it was determined that the increased axial vibration did not impact pump operability. The pump was determined to be operable and returned to service, at 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br /> on September 21, 1994. Additional vibration readings were recommended to verify that the axial vibration remained stable and that the consequences of the coupling adjustment were negligible.

DESCRIPTION OF OCCURRENCE:

At 2330 hours0.027 days <br />0.647 hours <br />0.00385 weeks <br />8.86565e-4 months <br /> (same day), additional vibration readings indicated unstable and increasing axial vibration in the 21CCP speed increaser. This condition challenged pump operability and at approximately 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />, on September 22,1994, it was declared inoperable (effective from prior removal from service on September 19th) .

Insufficient time remained to restore the pump to Operable status

LICENSEE EVENT REPORT (LER} TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 2 5000311 94-010-00 3 of 4 DESCRIPTION OF OCCURRENCE: (cont'd) prior to expiration of the 72-hour action time of Technical Specification (TS} 3.5.2.a, which occurred at 0108 hours0.00125 days <br />0.03 hours <br />1.785714e-4 weeks <br />4.1094e-5 months <br /> (same day}.

At 0230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br /> (same day} a controlled shutdown was initiated. At 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> (same day}, the NRC was notified of the initiation of the controlled shutdown, in accordance with 10CFR50.72(b} (i} (A}. At 0509 hours0.00589 days <br />0.141 hours <br />8.416005e-4 weeks <br />1.936745e-4 months <br /> (same day} the Unit was placed in MODE 3 (HOT STANDBY} and, at 1222 hours0.0141 days <br />0.339 hours <br />0.00202 weeks <br />4.64971e-4 months <br /> (same day} was placed in MODE 4 (HOT SHUTDOWN}, as required by TS 3.5.2.a.

ANALYSIS OF OCCURRENCE:

In MODES 1 through 3, operability of two (2) independent Emergency Core Cooling Systems subsystems ensures sufficient emergency core cooling capability in the event of a Loss-Of-Coolant Accident assuming the loss of one subsystem through any active single failure consideration. Whenever a single CCP is unavailable, the redundant CCP will provide high head injection flow for the mitigation of any design base accident.

APPARENT CAUSE OF OCCURRENCE:

Upon measuring high vibration in the 21CCP speed increaser it was conservatively determined that the pump was inoperable from when it was previously removed from service on September 19. As such, there was insufficient time to restore the pump to Operable status prior to expiration of the action time constraints of TS 3.5.2.a.

Identification of the cause of the high vibration in the 21CCP speed increaser, Nuttal Gear Corp., Model No. SU-1023-8X, is pending results of root cause analysis by the vendor, with assistance from PSE&G. No problems were identified as contributory to this occurrence.

PREVIOUS OCCURRENCES:

Based upon review of documentation, the high vibration of 21CCP pump speed increaser, as presently understood, is an isolated occurrence.

LER 272/89-033-00, reported the inoperability 12CCP due to equipment failure of the pump speed increaser, attributed to inadequate Service Water System cooling flow through the speed increaser lube oil cooler. However, the cause of the inadequate flow could not be determined.

SAFETY SIGNIFICANCE:

This occurrence is reportable pursuant to the requirements of

r

  • LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 2 5000311 94-010-00 4 of 4 SAFETY SIGNIFICANCE: (cont'd) 10CFR50.73(a) (2) (i) (A), due to completion of a TS-required shutdown.

During this occurrence 22CCP was available, if required, to provide high head injection flow for the mitigation of any design base accident.

CORRECTIVE ACTION:

The 21CCP speed increaser was replaced, the pump was satisfactorily tested; and, at 2241 hours0.0259 days <br />0.623 hours <br />0.00371 weeks <br />8.527005e-4 months <br /> on September 25, 1994, the Action of TS 3.5.2.a was exited.

It is anticipated that by January 31, 1995 a supplement to this report will be submitted detailing the results of the root cause analysis of the 21CCP speed increaser high vibration.

MJPJ:pc SORC Mtg.94-078

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