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| issue date = 08/20/1993
| issue date = 08/20/1993
| title = LER 93-014-00:on 930722,concern Raised Re 4 Kv Vital Bus Second Level Undervoltage Protection Dropout Setpoint (Both Units).Caused by Design,Mfg,Const/Installation,Per NUREG-1022.Design Changes Will Be implemented.W/930820 Ltr
| title = LER 93-014-00:on 930722,concern Raised Re 4 Kv Vital Bus Second Level Undervoltage Protection Dropout Setpoint (Both Units).Caused by Design,Mfg,Const/Installation,Per NUREG-1022.Design Changes Will Be implemented.W/930820 Ltr
| author name = PASTVA M J, VONDRA C A
| author name = Pastva M, Vondra C
| author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY
| author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY
| addressee name =  
| addressee name =  
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=Text=
=Text=
{{#Wiki_filter: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  
{{#Wiki_filter:Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station August 20, 1993 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 93-014-00 August 20, 1993 This Licensee Event Report is being submitted pursuant to the requirements of the Code of Federal Regulations lOCFR 50.73(a) (2) (ii) (B). This report is required to be issued within thirty (30) days of event discovery.
 
MJPJ:pc Distribution  
SALEM GENERATING STATION LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT NO. 1 LICENSEE EVENT REPORT 93-014-00 This Licensee Event Report is being submitted pursuant to the requirements of the Code of Federal Regulations 10CFR 50.73(a) (2) (ii) (B). This report is required to be issued within thirty (30) days of event discovery.
... ) -. 0 Ii r--: "-'"' '-* Ju' The EnerQY People 9308300321 930820 PDR 05000272 S PDR Sincerely yours, C. A Vondra General Manager -Salem Operations 95-2189 ( 10M) 12-89 NRC F0RM 366 (6-89) U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMB NO. 3150-0104 LICENSEE EVENT REPORT (LERI FACILITY NAME 11) Salem Station -Unit 1 TITLE 141 EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH IP-530). U.S. NUCLEAR REGULATORY COMMISSION.
Sincerely yours, C. A Vondra General Manager -
WASHINGTON.
Salem Operations MJPJ:pc Distribution
DC 20555. AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104).
        . . )~ -. 0 Ii'-* r--Ju'*~ :
OFFICE OF MANAGEMENT AND BUDGET. WASHINGTON.
The EnerQY People 9308300321 930820                                                                 95-2189 ( 10M) 12-89 PDR ADOC~ 05000272 S                                PDR
DC 20503. I DOCKET NUMBER 12) I PAGE 13} 01s101010121712 1joFOl5 4KV Vital Bus Second Level Undervoltage Protection Dropout Setpoint Concern (both Units). EVENT OATE (5) LER NUMBER (6) REPORT DATE 17) OTHER FACILITIES INVOLVED IB) MONTH DAY YEAR YEAR rt j(
 
MONTH DAY YEAR FACILITY NAMES OOCKET NUMBERISl Salem Unit 2 o 1s1 o Io Io 13 1111 o I 1 2 I 2 9 3 9 I 3 -a I 1 .14 -a I o o I s 21 a 9 I 3 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE Rl:QUIREMENTS OF 10 CFR §: (Ch*ck on* or mor* of th* following) 111) MODE 19) 1 20.402lb) 20.405lcl 50.731*)12Hiv)
NRC F0RM 366                                                                     U.S. NUCLEAR REGULATORY COMMISSION (6-89)                                                                                                                                      APPROVED OMB NO. 3150-0104 EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD LICENSEE EVENT REPORT (LERI                                                              COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH IP-530). U.S. NUCLEAR REGULATORY COMMISSION. WASHINGTON. DC 20555. AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104). OFFICE OF MANAGEMENT AND BUDGET. WASHINGTON. DC 20503.
POWER I 0 18 I 0 .....__ --,_ 20.4061*111 Hil 50.3Slcll1)
FACILITY NAME 11)                                                                                                                      DOCKET NUMBER 12)                     I     PAGE 13}
IX 50.73l*H2llvl
Salem TITLE 141 Generatin~            Station - Unit 1                                                                                I01s101010121712                        1joFOl5 4KV Vital Bus Second Level Undervoltage Protection Dropout Setpoint Concern (both Units).
..__ ,....__ 20.4051aH1lliil 50.38(cll2) 50.731*1121 Mil ..__ -20.40tilall1 Hiiil 50.731*ll2)(i) 50.73l*ll2HvlllHAI  
EVENT OATE (5)                       LER NUMBER (6)                           REPORT DATE 17)                         OTHER FACILITIES INVOLVED IB)
..__ ....__ 20.4061*>11  
MONTH       DAY       YEAR     YEAR   rt SE~~~~~~AL        j( ~~~~~~        MONTH       DAY   YEAR               FACILITY NAMES                     OOCKET NUMBERISl Salem Unit 2                           o 1s1 o Io Io 13 1111 o I1        I 2 2       9 3 9       I3 -       a   I 1 .14 -         a Io oIs 21 a               9 I3 OPERATING                 THIS REPORT IS SUBMITTED PURSUANT TO THE Rl:QUIREMENTS OF 10 CFR             §: (Ch*ck on* or mor* of th* following) 111)
)(Iv) x 60.73l*ll2llii) 50.73lall2HvlllHBI
MODE 19)
--20.4061*)11 )lvl 50.73l*ll2lliiil 50.73lall2Hxl LICENSEE CONTACT FOR THIS LER 112) NAME M. J. Pastva. Jr. -LER Coordinator AREA CODE .....__ .....__ ....__ 73.71lb) 73.71lc) OTHER (SP1Jcify in Abst,.ct b*low *nd in TDxt. NRC Form 366AJ TELEPHONE NUMBER b 1019* 313*19 1-1511 1615 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 113) CAUSE SYSTEM COMPONENT I I I I I I I I I I I I I I SUPPLEMENTAL REPORT EXPECTED 114) r:-i YES (If y*s, EXPECTED SUBMISSION DATE) ABSTRACT (Limit to 1400 spaces, i.e .* approKimtJtely fifteen single-space typewritten lines) (16) I I I I I I I I I I I I I I EXPECTED SUBMISSION DATE (151 MONTH DAY YEAR *110 ?1'1 ql':l On 7/22/93, it was determined that the present 91.6% dropout setpoint for second level undervoltage (UV) protection of the 4 kilovolt (KV) vital buses (both Salem Units), may not fully protect motors should the bus voltage degrade to less than 93.2% but greater than 91.6%. This is contrary to Branch Technical Position (BTP)-PSB-1 and the Updated Final Safety Analysis Report (UFSAR). However, engineering calculation shows, given the postulated worst case design basis event, vital bus recovery voltage will not degrade to less than 93.2%. The 91.6% dropout setpoint _was based on the lowest voltage the 4.16 KV motors could be allowed to operate (i.e. 90%) due to voltage drops in the *motors' cables and relay inaccuracy considerations.
I
The revised recovery voltage of 93.2% will now maintain all motors operable under degraded voltage conditions.
---------L-=-i~ 20.402lb) 1 20.4061*111 Hil                      -
During the next refueling outage on each Unit, design changes will be implemented to change the relay setpoint to meet the requirements of BTP-PSB-1.
20.405lcl 50.3Slcll1)
In the interim, administrative controls are being implemented.
IX 50.731*)12Hiv) 50.73l*H2llvl 73.71lb) 73.71lc)
Technical Specifications and the UFSAR will be reviewed and revised as appropriate.
POWER L~~~L        0 18 I 0 .....__   20.4051aH1lliil                      ..__   50.38(cll2)                         50.731*1121 Mil                   ....__ OTHER (SP1Jcify in Abst,.ct b*low *nd in TDxt. NRC Form 20.40tilall1 Hiiil                         50.731*ll2)(i)                       50.73l*ll2HvlllHAI                         366AJ 20.4061*>11 )(Iv) 20.4061*)11 )lvl                     -x    60.73l*ll2llii) 50.73l*ll2lliiil           -
Conditions necessary for the design concern coincident with a prerequisite plant transient have not occurred.
LICENSEE CONTACT FOR THIS LER 112) 50.73lall2HvlllHBI 50.73lall2Hxl NAME                                                                                                                                                     TELEPHONE NUMBER AREA CODE M. J. Pastva. Jr. - LER Coordinator                                                                                                       b   1019* 313*19 1-1511 1615 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 113)
As such, the health and safety of the public has not been affected by this concern. Analysis of this event is continuing.
CAUSE   SYSTEM       COMPONENT I         I  I    I          I    I    I                                                  I            I    I    I        I    I    I I          I   I   I         I     I   I                                                 I           I   I   I       I     I   I SUPPLEMENTAL REPORT EXPECTED 114)                                                                                 MONTH      DAY      YEAR EXPECTED SUBMISSION r:-i   YES (If y*s, com~lot* EXPECTED SUBMISSION DATE)
Upon completion of this effort, a supplement to this LER will be submitted.
DATE (151
                                                                                                                                                                    *110        ?1'1    ql':l ABSTRACT (Limit to 1400 spaces, i.e .* approKimtJtely fifteen single-space typewritten lines) (16)
On 7/22/93, it was determined that the present 91.6% dropout setpoint for second level undervoltage (UV) protection of the 4 kilovolt (KV) vital buses (both Salem Units), may not fully protect motors should the bus voltage degrade to less than 93.2% but greater than 91.6%. This is contrary to Branch Technical Position (BTP)-PSB-1 and the Updated Final Safety Analysis Report (UFSAR). However, engineering calculation shows, given the postulated worst case design basis event, vital bus recovery voltage will not degrade to less than 93.2%. The 91.6% dropout setpoint
_was based on the lowest voltage the 4.16 KV motors could be allowed to operate (i.e. 90%) due to voltage drops in the *motors' cables and relay inaccuracy considerations. The revised recovery voltage of 93.2% will now maintain all motors operable under degraded voltage conditions.
During the next refueling outage on each Unit, design changes will be implemented to change the relay setpoint to meet the requirements of BTP-PSB-1. In the interim, administrative controls are being implemented. Technical Specifications and the UFSAR will be reviewed and revised as appropriate. Conditions necessary for the design concern coincident with a prerequisite plant transient have not occurred. As such, the health and safety of the public has not been affected by this concern. Analysis of this event is continuing. Upon completion of this effort, a supplement to this LER will be submitted.
NRC Form 366 (6-89)
NRC Form 366 (6-89)
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 1 DOCKET NUMBER 5000272 PLANT AND SYSTEM IDENTIFICATION:
 
Westinghouse  
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station       DOCKET NUMBER                                  LER NUMBER                PAGE Unit 1                           5000272                                       93-014-00
-Pressurized Water Reactor LER NUMBER 93-014-00 PAGE
* 2 of 5 PLANT AND SYSTEM IDENTIFICATION:
* 2 of 5 Energy Industry Identification System (EIIS) codes are identified in the text as {xx} IDENTIFICATION OF OCCURRENCE:
Westinghouse - Pressurized Water Reactor Energy Industry Identification System (EIIS) codes are identified in the text as {xx}
4 KV Vital Bus Second Level Undervoltage Protection Dropout Setpoint Concern (both Salem Units) Event Discovery Date: 7/22/93 Report Date: 8/20/93 This report was initiated by Incident Report No. 93-320. This event is reportable per 10CFR50.73(a)
IDENTIFICATION OF OCCURRENCE:
(2) (ii) (B) and 10CFR50.73(a)
4 KV Vital Bus Second Level Undervoltage Protection Dropout Setpoint Concern (both Salem Units)
(2) (v) (D). CONDITIONS PRIOR TO OCCURRENCE:
Event Discovery Date:   7/22/93 Report Date: 8/20/93 This report was initiated by Incident Report No. 93-320. This event is reportable per 10CFR50.73(a) (2) (ii) (B) and 10CFR50.73(a) (2) (v) (D).
Unit 1: Mode 1 Reactor Power 80% -Unit Load 815 MWe Unit 2: Mode 1 Reactor Power 100% -Unit Load 1140 MWe DESCRIPTION OF OCCURRENCE:
CONDITIONS PRIOR TO OCCURRENCE:
On July 22, 1993, it was determined.that the *present 91.6% dropout setpoint for second level undervoltage (UV) protection of the 4 kilovolt (KV) vital buses {VJ} (both Salem Units), will not fully protect motors at the 230 and 460 volt level should the 4KV bus voltage degrade to less than 93.2% but greater than 91.6%. This is contrary to Branch Technical Position (BTP)-PSB-1 and the Updated *.Final Safety Analysis Report (UFSAR). However, engineering calculation shows, given*the postulated worst case design basis event, vital bus recovery voltage will not degrade to less than 93.2%. The Nuclear Regulatory Commission was notified of this event per Code of Federal Regulations lOCFR50.72(b)
Unit 1: Mode 1   Reactor Power             80% - Unit Load                               815 MWe Unit 2: Mode 1   Reactor Power 100% - Unit Load 1140 MWe DESCRIPTION OF OCCURRENCE:
(1) (ii) (B). ANALYSIS OF OCCURRENCE:
On July 22, 1993, it was determined.that the *present 91.6% dropout setpoint for second level undervoltage (UV) protection of the 4 kilovolt (KV) vital buses {VJ} (both Salem Units), will not fully protect motors at the 230 and 460 volt level should the 4KV bus voltage degrade to less than 93.2% but greater than 91.6%. This is contrary to Branch Technical Position (BTP)-PSB-1 and the Updated
Availability of minimum redundant alternating current (A.C.) power sources and distribution systems ensures sufficient power will be available to safety-related equipment for safe shutdown of the facility and the mitigation and control of accident conditions.within the facility, as required by General Design Criteria 17 of Appendix "A" to lOCFR Part 50. Per BTP-PSB-1, the plant licensing basis requires a second level of undervoltage protection for 4KV vital buses to ensure minimum motor terminal voltage for all safety-related
  *.Final Safety Analysis Report (UFSAR). However, engineering calculation shows, given*the postulated worst case design basis event, vital bus recovery voltage will not degrade to less than 93.2%.
**, *---*-.,.
The Nuclear Regulatory Commission was notified of this event per Code of Federal Regulations 10CFR50.72(b) (1) (ii) (B).
-*---*
ANALYSIS OF OCCURRENCE:
--*----*---*
r :****
r :****
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 1 DOCKET NUMBER 5000272 ANALYSIS OF OCCURRENCE: (cont'd) LER NUMBER 93-014-00 PAGE 3 of 5 motors *. At Salem, when vital bus voltage drops below the dropout setpoint for relays providing this protection for greater than 13 seconds, vital bus loads are automatically transferred to their respective emergency diesel generators.
Availability of minimum redundant alternating current (A.C.) power sources and distribution systems ensures sufficient power will be available to safety-related equipment for safe shutdown of the facility and the mitigation and control of accident conditions.within the facility, as required by General Design Criteria 17 of Appendix "A" to 10CFR Part 50. Per BTP-PSB-1, the plant licensing basis requires a second level of undervoltage protection for 4KV vital buses to ensure minimum motor terminal voltage for all safety-related
                                  **, *---*-.,.  -*---* --~..-- --*- -- -*---*  ****-----*~*.
 
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station       DOCKET NUMBER      LER NUMBER      PAGE Unit 1                           5000272         93-014-00      3 of 5 ANALYSIS OF OCCURRENCE:   (cont'd) motors *. At Salem, when vital bus voltage drops below the dropout setpoint for relays providing this protection for greater than 13 seconds, vital bus loads are automatically transferred to their respective emergency diesel generators.
As part of the self-initiated Electrical Engineering Self-Assessment Program, electrical calculations are being reviewed to ensure guidelines of BTP-PSB-1 are met. On July 1, 1993, review of Revision 1 of ES-15.00S(Q), "Salem Units 1 and 2 Degraded Grid study" identified a potential concern with the 91.6% dropout setpoint of the Units' 4KV vital buses (lA, lB, lC, 2A, 2B, and 2C). On July 22, 1993, further analysis of this concern determined the recovery vital bus voltage is 93.2% of 4.16KV following transfer of the Auxiliary Power Transformers (APTs) to the Station Power Transformers (SPTs). This voltage could result should a group bus transfer to the SPTs occur coincident with a Loss-of-Coolant Accident (LOCA) and the unaffected unit in startup or shutdown.
As part of the self-initiated Electrical Engineering Self-Assessment Program, electrical calculations are being reviewed to ensure guidelines of BTP-PSB-1 are met. On July 1, 1993, review of Revision 1 of ES-15.00S(Q), "Salem Units 1 and 2 Degraded Grid study" identified a potential concern with the 91.6% dropout setpoint of the Units' 4KV vital buses (lA, lB, lC, 2A, 2B, and 2C). On July 22, 1993, further analysis of this concern determined the recovery vital bus voltage is 93.2% of 4.16KV following transfer of the Auxiliary Power Transformers (APTs) to the Station Power Transformers (SPTs). This voltage could result should a group bus transfer to the SPTs occur coincident with a Loss-of-Coolant Accident (LOCA) and the unaffected unit in startup or shutdown.
UFSAR Section 8.3.1.2 describes the setpoint as being determined using the 90% minimum.motor terminal voltage as the starting point. Since 93.2% bus voltage is required to ensure the minimum motor terminal voltage, the existing 91.6% dropout setpoint is not in compliance with the UFSAR or the BTP. However, because ES-15.00S(Q) calculations also show that vital bus recovery voltage will not
UFSAR Section 8.3.1.2 describes the setpoint as being determined using the 90% minimum.motor terminal voltage as the starting point.
* degrade to a level at which actual motor degradation could occur, the intent of the UFSAR and BTP is still met. These calculations take credit for operation, prior to the event, of the load tap changers which are set to* maintain a_ minimum initial bus voltage of 4.3KV. Following event discovery, an evaluation to justify continued operation of both Salem Units, concluded the present dropout setpoint of the relays does not meet the intent of the BTP. However, Revision 1 of Engineering Calculation ES-15.00S(Q) determined there is not a significant safety concern with the present dropout setpoint provided the 4.16KV vital buses are maintained at 4.3KV or greater. Design changes will be implemented during the next refueling outage on each Unit to change the dropout setpoint to meet the intent of the BTP. * * * * *
Since 93.2% bus voltage is required to ensure the minimum motor terminal voltage, the existing 91.6% dropout setpoint is not in compliance with the UFSAR or the BTP. However, because ES-15.00S(Q) calculations also show that vital bus recovery voltage will not
* For the interim, 4.16KV vital bus voltages are being monitored to assure load tap changers are operating properly to maintain a minimum bus voltage of 4. 3KV. In addition, bus voltages below 4. JKV will be. *r:'::* adjusted between 4.JKV and 4.5KV and restrictions concerning vital bus lineup will be in_effect (see "CORRECTIVE ACTIONS:" section).
* degrade to a level at which actual motor degradation could occur, the intent of the UFSAR and BTP is still met. These calculations take credit for operation, prior to the event, of the load tap changers which are set to* maintain a_ minimum initial bus voltage of 4.3KV.
Analysis of this event is continuing.
Following event discovery, an evaluation to justify continued operation of both Salem Units, concluded the present dropout setpoint of the relays does not meet the intent of the BTP. However, Revision 1 of Engineering Calculation ES-15.00S(Q) determined there is not a significant safety concern with the present dropout setpoint provided the 4.16KV vital buses are maintained at 4.3KV or greater. Design changes will be implemented during the next refueling outage on each Unit to change the dropout setpoint to meet the intent of the BTP. * * * * *
Included will be a historical assessment of the effect of the revised assumptions at vital bus levels below 4KV. Upon completion of this effort, a supplement to this LER will be submitted.
* For the interim, 4.16KV vital bus voltages are being monitored to assure load tap changers are operating properly to maintain a minimum bus voltage of 4. 3KV. In addition, bus voltages below 4. JKV will be. *r:'::*
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating station tinit 1 . --APPARENT CAUSE OF OCCURRENCE:
adjusted between 4.JKV and 4.5KV and restrictions concerning vital bus lineup will be in_effect (see "CORRECTIVE ACTIONS:" section).
DOCKET NUMBER 5000272' LER NUMBER 93:...014-00 PAGE 4 of s The cause of this event is "Design, Manufacturing, Construction/Installation", per NUREG-1022.
Analysis of this event is continuing. Included will be a historical assessment of the effect of the revised assumptions at vital bus levels below 4KV. Upon completion of this effort, a supplement to this LER will be submitted.
The 91.6% dropout setpoint was based on the lowest voltage the 4.16 KV motors could be allowed to operate (i.e. 90%) due to voltage drops in the motors' cables and relay inaccuracy considerations.
 
The revised dropout setpoint, based upon the revised recovery voltage of 93.2%, will now maintain all motors operable under degraded voltage conditions.
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating station         DOCKET NUMBER    LER NUMBER        PAGE tinit 1   .-   -                 5000272'       93:...014-00   4 of s APPARENT CAUSE OF OCCURRENCE:
The cause of this event is "Design, Manufacturing, Construction/Installation", per NUREG-1022. The 91.6% dropout setpoint was based on the lowest voltage the 4.16 KV motors could be allowed to operate (i.e. 90%) due to voltage drops in the motors' cables and relay inaccuracy considerations. The revised dropout setpoint, based upon the revised recovery voltage of 93.2%, will now maintain all motors operable under degraded voltage conditions.
PRIOR SIMILAR OCCURRENCES:
PRIOR SIMILAR OCCURRENCES:
No prior. similar.occurrences of this event were identified.
No prior. similar.occurrences of this event were identified.
SAFETY SIGNIFICANCE:
SAFETY SIGNIFICANCE:
Engineering is. currently completing its evaluation of the safety significance of past operation with the non-conservative second level. UV setpoint *. With the current interim controls, the health and safety of the public is not affected by this event. Upon completion of this evaluation this LER will be
Engineering is. currently completing its evaluation of the safety significance of past operation with the non-conservative second level.
* CORRECTIVE ACTION: Design Changes will be implemented to change the relay setpoint on both Units to meet the requirements of BTP-PSB-1 and be in accordance with the plant design basis. This will be done during the upcoming Unit 1 refueling outage and the next Unit 2 refueling outage. A License Change Request will *be implemented to revise Technical Specifications in accordance with the second level UV relay setpoint concern. The UFSAR will be reviewed*and revised as appropriate.
UV setpoint *. With the current interim controls, the health and safety of the public is not affected by this event. Upon completion of this evaluation this LER will be supplemented~
Administrative controls are being implemented to ensure the following restrictions are employed as interim action until implementation of design changes: 1. 4.i6KV vital bus voltages will be logged hourly to assure a minimum vital bus voltage of 4.3KV. Bus voltages less than 4.3KV will be adjusted to between 4.3KV and 4.SKV. ' 2. '_.,;..:'.
* CORRECTIVE ACTION:
-Only two vital buses may be energized from their operating . , .. transformer if both the-corresponding buses are on -their respective APT. 3a. Three.vital buses may be energized from the operatingtransf armer if one of the corresponding group *** *
Design Changes will be implemented to change the relay setpoint on both Units to meet the requirements of BTP-PSB-1 and be in accordance with the plant design basis. This will be done during the upcoming Unit 1 refueling outage and the next Unit 2 refueling outage.
* buses is transferred to the operating SPT or LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 1 CORRECTIVE ACTION: (cont'd) DOCKET NUMBER 5000272 LER NUMBER 93-014-00 PAGE 5 Of 5 3b. Three vital buses may be energized from the operating transformer if the load which can be transferred from the APTs is reduced by 5 mega volt amps. MJPJ:pc SORC Mtg. 93-077 General Manager -Salem Operations
A License Change Request will *be implemented to revise Technical Specifications in accordance with the second level UV relay setpoint concern.
' . . . ' ,.  
The UFSAR will be reviewed*and revised as appropriate.
'.:,'F '-. . .; . . .,:_*' .
Administrative controls are being implemented to ensure the following restrictions are employed as interim action until implementation of design changes:
I}}
: 1. 4.i6KV vital bus voltages will be logged hourly to assure a       '  *~.
minimum vital bus voltage of 4.3KV. Bus voltages less than 4.3KV will be adjusted to between 4.3KV and 4.SKV.
: 2. Only two vital buses may be energized from their operating .,.
transformer if both the-corresponding gro~p buses are on -
their respective APT.
3a. Three.vital buses may be energized from the operatingtransf armer if one of the corresponding group       ** *
* buses is transferred to the operating SPT or
 
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station     DOCKET NUMBER     LER NUMBER       PAGE Unit 1                          5000272          93-014-00     5 Of 5 CORRECTIVE ACTION:  (cont'd) 3b. Three vital buses may be energized from the operating transformer if the load which can be transferred from the APTs is reduced by 5 mega volt amps.
General Manager -
Salem Operations MJPJ:pc SORC Mtg. 93-077
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Latest revision as of 10:25, 23 February 2020

LER 93-014-00:on 930722,concern Raised Re 4 Kv Vital Bus Second Level Undervoltage Protection Dropout Setpoint (Both Units).Caused by Design,Mfg,Const/Installation,Per NUREG-1022.Design Changes Will Be implemented.W/930820 Ltr
ML18100A557
Person / Time
Site: Salem PSEG icon.png
Issue date: 08/20/1993
From: Pastva M, Vondra C
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RTR-NUREG-1022 LER-93-014, LER-93-14, NUDOCS 9308300327
Download: ML18100A557 (6)
v • d • e


Text

Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station August 20, 1993 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 93-014-00 This Licensee Event Report is being submitted pursuant to the requirements of the Code of Federal Regulations 10CFR 50.73(a) (2) (ii) (B). This report is required to be issued within thirty (30) days of event discovery.

Sincerely yours, C. A Vondra General Manager -

Salem Operations MJPJ:pc Distribution

. . )~ -. 0 Ii'-* r--Ju'*~ :

The EnerQY People 9308300321 930820 95-2189 ( 10M) 12-89 PDR ADOC~ 05000272 S PDR

NRC F0RM 366 U.S. NUCLEAR REGULATORY COMMISSION (6-89) APPROVED OMB NO. 3150-0104 EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD LICENSEE EVENT REPORT (LERI COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH IP-530). U.S. NUCLEAR REGULATORY COMMISSION. WASHINGTON. DC 20555. AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104). OFFICE OF MANAGEMENT AND BUDGET. WASHINGTON. DC 20503.

FACILITY NAME 11) DOCKET NUMBER 12) I PAGE 13}

Salem TITLE 141 Generatin~ Station - Unit 1 I01s101010121712 1joFOl5 4KV Vital Bus Second Level Undervoltage Protection Dropout Setpoint Concern (both Units).

EVENT OATE (5) LER NUMBER (6) REPORT DATE 17) OTHER FACILITIES INVOLVED IB)

MONTH DAY YEAR YEAR rt SE~~~~~~AL j( ~~~~~~ MONTH DAY YEAR FACILITY NAMES OOCKET NUMBERISl Salem Unit 2 o 1s1 o Io Io 13 1111 o I1 I 2 2 9 3 9 I3 - a I 1 .14 - a Io oIs 21 a 9 I3 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE Rl:QUIREMENTS OF 10 CFR §: (Ch*ck on* or mor* of th* following) 111)

MODE 19)

I

L-=-i~ 20.402lb) 1 20.4061*111 Hil -

20.405lcl 50.3Slcll1)

IX 50.731*)12Hiv) 50.73l*H2llvl 73.71lb) 73.71lc)

POWER L~~~L 0 18 I 0 .....__ 20.4051aH1lliil ..__ 50.38(cll2) 50.731*1121 Mil ....__ OTHER (SP1Jcify in Abst,.ct b*low *nd in TDxt. NRC Form 20.40tilall1 Hiiil 50.731*ll2)(i) 50.73l*ll2HvlllHAI 366AJ 20.4061*>11 )(Iv) 20.4061*)11 )lvl -x 60.73l*ll2llii) 50.73l*ll2lliiil -

LICENSEE CONTACT FOR THIS LER 112) 50.73lall2HvlllHBI 50.73lall2Hxl NAME TELEPHONE NUMBER AREA CODE M. J. Pastva. Jr. - LER Coordinator b 1019* 313*19 1-1511 1615 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 113)

CAUSE SYSTEM COMPONENT I I I I I I I I I I I I I I I I I I I I I I I I I I I I SUPPLEMENTAL REPORT EXPECTED 114) MONTH DAY YEAR EXPECTED SUBMISSION r:-i YES (If y*s, com~lot* EXPECTED SUBMISSION DATE)

DATE (151

  • 110 ?1'1 ql':l ABSTRACT (Limit to 1400 spaces, i.e .* approKimtJtely fifteen single-space typewritten lines) (16)

On 7/22/93, it was determined that the present 91.6% dropout setpoint for second level undervoltage (UV) protection of the 4 kilovolt (KV) vital buses (both Salem Units), may not fully protect motors should the bus voltage degrade to less than 93.2% but greater than 91.6%. This is contrary to Branch Technical Position (BTP)-PSB-1 and the Updated Final Safety Analysis Report (UFSAR). However, engineering calculation shows, given the postulated worst case design basis event, vital bus recovery voltage will not degrade to less than 93.2%. The 91.6% dropout setpoint

_was based on the lowest voltage the 4.16 KV motors could be allowed to operate (i.e. 90%) due to voltage drops in the *motors' cables and relay inaccuracy considerations. The revised recovery voltage of 93.2% will now maintain all motors operable under degraded voltage conditions.

During the next refueling outage on each Unit, design changes will be implemented to change the relay setpoint to meet the requirements of BTP-PSB-1. In the interim, administrative controls are being implemented. Technical Specifications and the UFSAR will be reviewed and revised as appropriate. Conditions necessary for the design concern coincident with a prerequisite plant transient have not occurred. As such, the health and safety of the public has not been affected by this concern. Analysis of this event is continuing. Upon completion of this effort, a supplement to this LER will be submitted.

NRC Form 366 (6-89)

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 1 5000272 93-014-00

  • 2 of 5 PLANT AND SYSTEM IDENTIFICATION:

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

IDENTIFICATION OF OCCURRENCE:

4 KV Vital Bus Second Level Undervoltage Protection Dropout Setpoint Concern (both Salem Units)

Event Discovery Date: 7/22/93 Report Date: 8/20/93 This report was initiated by Incident Report No.93-320. This event is reportable per 10CFR50.73(a) (2) (ii) (B) and 10CFR50.73(a) (2) (v) (D).

CONDITIONS PRIOR TO OCCURRENCE:

Unit 1: Mode 1 Reactor Power 80% - Unit Load 815 MWe Unit 2: Mode 1 Reactor Power 100% - Unit Load 1140 MWe DESCRIPTION OF OCCURRENCE:

On July 22, 1993, it was determined.that the *present 91.6% dropout setpoint for second level undervoltage (UV) protection of the 4 kilovolt (KV) vital buses {VJ} (both Salem Units), will not fully protect motors at the 230 and 460 volt level should the 4KV bus voltage degrade to less than 93.2% but greater than 91.6%. This is contrary to Branch Technical Position (BTP)-PSB-1 and the Updated

  • .Final Safety Analysis Report (UFSAR). However, engineering calculation shows, given*the postulated worst case design basis event, vital bus recovery voltage will not degrade to less than 93.2%.

The Nuclear Regulatory Commission was notified of this event per Code of Federal Regulations 10CFR50.72(b) (1) (ii) (B).

ANALYSIS OF OCCURRENCE:

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Availability of minimum redundant alternating current (A.C.) power sources and distribution systems ensures sufficient power will be available to safety-related equipment for safe shutdown of the facility and the mitigation and control of accident conditions.within the facility, as required by General Design Criteria 17 of Appendix "A" to 10CFR Part 50. Per BTP-PSB-1, the plant licensing basis requires a second level of undervoltage protection for 4KV vital buses to ensure minimum motor terminal voltage for all safety-related

    • , *---*-.,. -*---* --~..-- --*- -- -*---* ****-----*~*.

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 1 5000272 93-014-00 3 of 5 ANALYSIS OF OCCURRENCE: (cont'd) motors *. At Salem, when vital bus voltage drops below the dropout setpoint for relays providing this protection for greater than 13 seconds, vital bus loads are automatically transferred to their respective emergency diesel generators.

As part of the self-initiated Electrical Engineering Self-Assessment Program, electrical calculations are being reviewed to ensure guidelines of BTP-PSB-1 are met. On July 1, 1993, review of Revision 1 of ES-15.00S(Q), "Salem Units 1 and 2 Degraded Grid study" identified a potential concern with the 91.6% dropout setpoint of the Units' 4KV vital buses (lA, lB, lC, 2A, 2B, and 2C). On July 22, 1993, further analysis of this concern determined the recovery vital bus voltage is 93.2% of 4.16KV following transfer of the Auxiliary Power Transformers (APTs) to the Station Power Transformers (SPTs). This voltage could result should a group bus transfer to the SPTs occur coincident with a Loss-of-Coolant Accident (LOCA) and the unaffected unit in startup or shutdown.

UFSAR Section 8.3.1.2 describes the setpoint as being determined using the 90% minimum.motor terminal voltage as the starting point.

Since 93.2% bus voltage is required to ensure the minimum motor terminal voltage, the existing 91.6% dropout setpoint is not in compliance with the UFSAR or the BTP. However, because ES-15.00S(Q) calculations also show that vital bus recovery voltage will not

  • degrade to a level at which actual motor degradation could occur, the intent of the UFSAR and BTP is still met. These calculations take credit for operation, prior to the event, of the load tap changers which are set to* maintain a_ minimum initial bus voltage of 4.3KV.

Following event discovery, an evaluation to justify continued operation of both Salem Units, concluded the present dropout setpoint of the relays does not meet the intent of the BTP. However, Revision 1 of Engineering Calculation ES-15.00S(Q) determined there is not a significant safety concern with the present dropout setpoint provided the 4.16KV vital buses are maintained at 4.3KV or greater. Design changes will be implemented during the next refueling outage on each Unit to change the dropout setpoint to meet the intent of the BTP. * * * * *

  • For the interim, 4.16KV vital bus voltages are being monitored to assure load tap changers are operating properly to maintain a minimum bus voltage of 4. 3KV. In addition, bus voltages below 4. JKV will be. *r:'::*

adjusted between 4.JKV and 4.5KV and restrictions concerning vital bus lineup will be in_effect (see "CORRECTIVE ACTIONS:" section).

Analysis of this event is continuing. Included will be a historical assessment of the effect of the revised assumptions at vital bus levels below 4KV. Upon completion of this effort, a supplement to this LER will be submitted.

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating station DOCKET NUMBER LER NUMBER PAGE tinit 1 .- - 5000272' 93:...014-00 4 of s APPARENT CAUSE OF OCCURRENCE:

The cause of this event is "Design, Manufacturing, Construction/Installation", per NUREG-1022. The 91.6% dropout setpoint was based on the lowest voltage the 4.16 KV motors could be allowed to operate (i.e. 90%) due to voltage drops in the motors' cables and relay inaccuracy considerations. The revised dropout setpoint, based upon the revised recovery voltage of 93.2%, will now maintain all motors operable under degraded voltage conditions.

PRIOR SIMILAR OCCURRENCES:

No prior. similar.occurrences of this event were identified.

SAFETY SIGNIFICANCE:

Engineering is. currently completing its evaluation of the safety significance of past operation with the non-conservative second level.

UV setpoint *. With the current interim controls, the health and safety of the public is not affected by this event. Upon completion of this evaluation this LER will be supplemented~

  • CORRECTIVE ACTION:

Design Changes will be implemented to change the relay setpoint on both Units to meet the requirements of BTP-PSB-1 and be in accordance with the plant design basis. This will be done during the upcoming Unit 1 refueling outage and the next Unit 2 refueling outage.

A License Change Request will *be implemented to revise Technical Specifications in accordance with the second level UV relay setpoint concern.

The UFSAR will be reviewed*and revised as appropriate.

Administrative controls are being implemented to ensure the following restrictions are employed as interim action until implementation of design changes:

1. 4.i6KV vital bus voltages will be logged hourly to assure a ' *~.

minimum vital bus voltage of 4.3KV. Bus voltages less than 4.3KV will be adjusted to between 4.3KV and 4.SKV.

2. Only two vital buses may be energized from their operating .,.

transformer if both the-corresponding gro~p buses are on -

their respective APT.

3a. Three.vital buses may be energized from the operatingtransf armer if one of the corresponding group ** *

  • buses is transferred to the operating SPT or

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 1 5000272 93-014-00 5 Of 5 CORRECTIVE ACTION: (cont'd) 3b. Three vital buses may be energized from the operating transformer if the load which can be transferred from the APTs is reduced by 5 mega volt amps.

General Manager -

Salem Operations MJPJ:pc SORC Mtg.93-077

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