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{{#Wiki_filter:\ '0 PSl§Ge
{{#Wiki_filter:\ '0 PSl§Ge Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit March 11, 1997 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn: Document Control Desk MONTHLY OPERATING REPORT SALEM NO. 2 DOCKET NO: 50-311 In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specifications, the original monthly operating report for the month of February is being sent to you.
* Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn: Document Control Desk MONTHLY OPERATING REPORT SALEM NO. 2 DOCKET NO: 50-311 March 11, 1997 In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specifications, the original monthly operating report for the month of February is being sent to you. VS:pc Enclosures C Mr. H. J. Miller Regional Administrator USNRC, Region 1 4 7 5 Allendale Road King of Prussia, PA 19046 -9703240185 970228 PDR ADOCK 05000311 R PDR . \ Sincerely yours, General Manager -Salem Operations
Sincerely yours, General Manager -
----------
Salem Operations VS:pc Enclosures C       Mr. H. J. Miller Regional Administrator USNRC, Region 1 4 7 5 Allendale Road King of Prussia, PA 19046
-----,, The po.ver is in your hands. 111111111111111111111111111111111111111111 111111111 1111
                          -                   . \
* 9 1 -ll ll 4 7 7 1
9703240185 970228 PDR ADOCK 05000311 R                         PDR 111111111111111111111111111111111111111111 111111111 1111 The po.ver is in your hands.
* 95-2168 REV. 6/94
* 9    1    -   ll  ll    4    7    7    1
. .' * * *, lOCFRS0.59 EVALUATIONS DOCKET NO: 50-311 MONTH: FEBRUARY 1997 NAME: UNIT2 CONTACT: N. CONICELLA TELEPHONE:
* 95-2168 REV. 6/94
609-339-2124 The following items were evaluated in accordance with the provisions of the Code of Federal Regulations 10CFR50.59.
 
The Station Operations Review Committee has reviewed and concurs with these evaluations DESIGN CHANGE PACKAGE 50.59 S/E S96-167, 2EC-3590, Pkg. 1, Rev 1 Addition of Thermal Overpressure Device on CFCU Return Piping 50.59 S/E S96-208, 2EC-3590, Pkg. 2, Rev. This DCP installs a relief valve across SW223 & SW76 valves to address the overpressure condition 50.59 S/E S97-042, 2EC-3570, Pkg. 1, Rev. 0 Nitrogen Purge Blanket 50.59 S/E S97-047, 2EC-3590, Pkg. 8, Rev.O Service Water System No. 21 Header Check Valve Installation This design change package installs a relief valve upstream of each of the five SW223 valves in the service water outlet lines from the CFCU s. SORC: 97-022 Engineering Evaluation S-C-SW-MEE-1138 addresses the Westinghouse Nuclear Safety Advisory Letter (NSAL) 96-003 concern that the CFCU coils and the associated piping could be overpressurized due to potential heat transfer to the stagnant service water in the CFCU coils following a postulated LOCA or MSLB and LOOP event. Package 01 of this DCP installs a relief valve across SW223 & SW76 valves to address the overpressure condition as evaluated in the above engineering evaluation.
*, 10CFRS0.59 EVALUATIONS MONTH: FEBRUARY 1997
SORC: 97-022 This modification does not impact the capacity, capability or the response time of the AFST, the AFW system or the AFW equipment.
                                  *
In addition, this modification does not impact any other safety related equipment or system. The modifications implemented by this DCP are intended to improve the system reliability and increase component life by controlling the amount of dissolved Oxygen in the Auxiliary Feedwater System. SORC: 97-024 This design change package modifies the No. 21 Service Water Nuclear Header 16" CFCU supply piping by adding a redundant check valve downstream of existing check valve to prevent backleakage of the header. SORC: 97-026
* DOCKET NO:
* . , 10CFR50.59 EVALUATIONS
NAME:
* DOCKET NO: 50-311 MONTH: FEBRUARY 1997 NAME: UNIT2 CONTACT: N. CONICELLA TELEPHONE:
CONTACT:
609-339-2124 The following items were evaluated in accordance with the provisions of the Code of Federal Regulations 10CFR50.59.
50-311 UNIT2 N. CONICELLA TELEPHONE:     609-339-2124 The following items were evaluated in accordance with the provisions of the Code of Federal Regulations 10CFR50.59. The Station Operations Review Committee has reviewed and concurs with these evaluations DESIGN CHANGE PACKAGE 50.59 S/E S96-167, 2EC-3590,     This design change package installs a relief valve upstream of each of the Pkg. 1, Rev 1 Addition of         five SW223 valves in the service water outlet lines from the CFCUs.
The Station Operations Review Committee has reviewed and concurs with these evaluations DESIGN CHANGE PACKAGE 50.59 S/E S97-048, 2EC-3590, Pkg. 9, Rev. 0 Service Water System No. 22 Header Check Valve Installation MINOR -MODIFICATION This design change package modifies the No. 22 Service Water Nuclear Header 16" CFCU supply piping by adding a redundant check valve downstream of existing check valve, 22SW51 to prevent backleakage of the header. SORC: 97-026 50.59 S/E S97-022, Masoneilan The purpose of this Minor Mod is to enhance the method of assuring the Air Operator, Retainer Clip S-96-manual handwheel declutching pin stays in place and does not accidentally 032, Rev. 0 allow the handwheel to become engaged. MISCELLANEOUS 50.59 S/E S-97-04lon Engineering Evaluation MEE-1175 Rev. 0 50.59 S/E S97-053 on Turbine Bypass Valve Control Loops Test (TS2.SE-SU.RCP-0002(Q).
Thermal Overpressure Device on                                                         SORC: 97-022 CFCU Return Piping 50.59 S/E S96-208, 2EC-3590,     Engineering Evaluation S-C-SW-MEE-1138 addresses the Westinghouse Pkg. 2, Rev. This DCP installs a Nuclear Safety Advisory Letter (NSAL) 96-003 concern that the CFCU relief valve across SW223 &       coils and the associated piping could be overpressurized due to potential SW76 valves to address the       heat transfer to the stagnant service water in the CFCU coils following a overpressure condition           postulated LOCA or MSLB and LOOP event. Package 01 of this DCP installs a relief valve across SW223 & SW76 valves to address the overpressure condition as evaluated in the above engineering evaluation.
Revision 0 PROCEDURE 50.59 S/E TS2.SE-SU.CN-000l(Q), Condensate Pump Performance Test SORC: 97-018 The purpose of this evaluation is to provide engineering support for an Operability Determination in the event that a chillier fails in the Unit 2 Auxiliary Building Chilled Water (CH) system with Salem Unit 2 in modes three and four, and the Unit 1 CH system having at least two chillers and one pump available in mode undefined.
SORC:    97-022 50.59 S/E S97-042, 2EC-3570,     This modification does not impact the capacity, capability or the response Pkg. 1, Rev. 0 Nitrogen Purge    time of the AFST, the AFW system or the AFW equipment. In addition, Blanket                          this modification does not impact any other safety related equipment or system. The modifications implemented by this DCP are intended to improve the system reliability and increase component life by controlling the amount of dissolved Oxygen in the Auxiliary Feedwater System.
SORC: 97-023 The proposed test injects signals into the Hagan Control System, monitors the response of the controllers, and verifies proper operation of the turbine bypass steam dump valves in response to the control signals. SORC: 97-028 This is a one-time test of the condensate pumps to establish their performance curves (total flow vs. differential pump head). SORC: 97-023 _J 
SORC:   97-024 50.59 S/E S97-047, 2EC-3590,      This design change package modifies the No. 21 Service Water Nuclear Pkg. 8, Rev.O Service Water      Header 16" CFCU supply piping by adding a redundant check valve System No. 21 Header Check        downstream of existing check valve to prevent backleakage of the header.
* *, lOCFRS0.59 EVALUATIONS
Valve Installation                                                                      SORC:    97-026
* DOCKET NO: 50-311 MONTH: FEBRUARY 1997 NAME: UNIT2 CONTACT: N. CONICELLA TELEPHONE:
 
609-339-2124 The following items were evaluated in accordance with the provisions of the Code of Federal Regulations 10CFR50.59.
. , 10CFR50.59 EVALUATIONS MONTH: FEBRUARY 1997
The Station Operations Review Committee has reviewed and concurs with these evaluations PROCEDURE 50.59 SIB S96-036 on Procedure S1(2).0P-SO.SF-0005(Q)  
                                  *
& TRIS Operation of Refueling Water Purification System to RWST in Modes 1-6 and 50.59 SIB S97-030, on Procedure Sl.OP.SO-ABV.0001, Rev. 2, Operation of the Unit 1 Aux. Building Ventilation with Loss of Supply Fans 50.59 SIB S97-033,on Procedure S2.0P-ST.SJ-0005(Q), Rev. 7 on Inservice Testing Safety Injection Valves Modes 5-6 50.59 SIB S97-044, on Procedure TS2.SE-SU.SW-0002(Q) 50.59 SIB S97-045 on Procedure TS2. SE-SU.RCP-0004(Q), Rev. 0 Tuning of Letdown Heat Exchanger Temperature The following Technical Specifications and basis were reviewed:3/4.1.2.1 Boration Systems Flow Paths -Shutdown; 3/4.1.2.2 Reactivity Control Systems Flow Paths. SORC: 97-019 This temporary procedure revision is being created as a contingency for the potential loss of ABV exhaust fan 11 (1 VHE45) during the 1 C buss outage exhaust fan 13 ( 1VHE47) is powered by the 1 C buss. SORC: 97-022 The proposed procedure revision will allow for stroke time testing of the SJ45 valves with an operable RHR loop Inservice.
* DOCKET NO:
The proposed procedure revision will reflect installation of jumpers to allow opening of the 21SJ4 5 and 22SJ45 valves without closing the 2RH1 or 2RH2 valves and opening the respective SJ44 valves. SORC: 97-020 Basically, this test involves splitting the operation of Service Water System in two separate headers (the headers are usually cross-tied in the Service Water Intake Structure).
NAME:
SORC: 97-024 This test will be performed to Mode 2. It will test and, if necessary, tune the controller for valve 2CC71. SORC: 97-029 I : * * " 10CFR50.59 EVALUATIONS DOCKET NO: 50-311 MONTH: FEBRUARY 1997 NAME: UNIT2 CONTACT: N. CONICELLA TELEPHONE:
CONTACT:
609-339-2124 The following items were evaluated in accordance with the provisions of the Code of Federal Regulations 10CFR50.59.
50-311 UNIT2 N. CONICELLA TELEPHONE:        609-339-2124 The following items were evaluated in accordance with the provisions of the Code of Federal Regulations 10CFR50.59. The Station Operations Review Committee has reviewed and concurs with these evaluations DESIGN CHANGE PACKAGE 50.59 S/E S97-048, 2EC-3590,      This design change package modifies the No. 22 Service Water Nuclear Pkg. 9, Rev. 0 Service Water     Header 16" CFCU supply piping by adding a redundant check valve System No. 22 Header Check        downstream of existing check valve, 22SW51 to prevent backleakage of Valve Installation                the header.
The Station Operations Review Committee has reviewed and concurs with these evaluations PROCEDURE 50.59 S/E S97-050, on Procedures NC.EP-EP.ZZ-080l(Q), Rev. 0 Emergency News Center Operations and NC.EP-EPZZ-0806(Q), ENC Proposed changes to the Nuclear Business Unit's Emergency Plan, Section 13.3 of the Hope Creek and Salem Final Updated Safety Analysis Reports (SAR), would reduce the initial Emergency News Center (ENC) staffing from 26 to 22 positions.
SORC:     97-026 MINOR - MODIFICATION 50.59 S/E S97-022, Masoneilan The purpose of this Minor Mod is to enhance the method of assuring the Air Operator, Retainer Clip S manual handwheel declutching pin stays in place and does not accidentally 032, Rev. 0                      allow the handwheel to become engaged.
SORC: 97-029 TEMPORARY MODIFICATION 50.59 S/E 97-027 (T/Mod 97-001) Installation ofBlind Spacers in the No. 21 SW Nuclear Header CFCU Supply/Return and the SW Supply/Return to the No. 21, No. 22 CFCUs 50.59 S/E S96-23 l, (T/Mod 96-037) Removal of Valve 1DF126 Internals 50.59 S/E S97-038, (T/Mod 96-020) Rev. 0 Temporary Installation of Surge Monitoring Equipment at 4Kv SWGR Bus 2H (2SWGR2HD)
SORC:      97-018 MISCELLANEOUS 50.59 S/E S-97-04lon              The purpose of this evaluation is to provide engineering support for an Engineering Evaluation S-2-CH-   Operability Determination in the event that a chillier fails in the Unit 2 MEE-1175 Rev. 0                  Auxiliary Building Chilled Water (CH) system with Salem Unit 2 in modes three and four, and the Unit 1 CH system having at least two chillers and one pump available in mode undefined.
Cubical 2H7D Due to the existing configuration of the Service Water (SW) supply and return piping for the Containment Fan Coil Units (CFCUs), the potential exists for water hammer in the SW return lines and drainage of the SW supply lines following a Loss of Offsite Power (LOOP). DCP 2EC-3590 has been initiated to modify the SW piping to address these concerns.
SORC:     97-023 50.59 S/E S97-053 on Turbine      The proposed test injects signals into the Hagan Control System, monitors Bypass Valve Control Loops        the response of the controllers, and verifies proper operation of the turbine Test (TS2.SE-SU.RCP-0002(Q). bypass steam dump valves in response to the control signals.
SORC: 97-019 The 1DF126 pressure regulator is not functioning either because of malfunction of the regulator itself or the feedback loop from the backpressure control tank. This package presented to extend time period from 2/27/97 to 4/1/97. SORC: 97-028 Installation of the voltage monitor and associated voltage probes at cubicle 2H7D IAW this T-Mod will provide the desired voltage surge data for future engineering review. SORC: 97-029 _ __J
Revision 0                                                                               SORC: 97-028 PROCEDURE 50.59 S/E TS2.SE-SU.CN-           This is a one-time test of the condensate pumps to establish their 000l(Q), Condensate Pump          performance curves (total flow vs. differential pump head).
* 10CFR50.59 EVALUATIONS
Performance Test                                                                        SORC:     97-023
* DOCKET NO: 50-311 MONTH: FEBRUARY 1997 NAME: UNIT2 CONTACT: N. CONICELLA TELEPHONE:
_J
609-339-2124 The following items were evaluated in accordance with the provisions of the Code of Federal Regulations 10CFR50.59.
 
The Station Operations Review Committee has reviewed and concurs with these evaluations UFSAR 50.59 SIB 96-122 and UFSAR Change 96-139, Containment Isolation Systems 50.59 SIB S97-002 on UFSAR change Notice 96-207 Revision of table 9.3-6 as a corrective action for PIR 96032155 50.59 S/E S97-035, on UFSAR Section 13.7 Salem & 13.6 Hope Creek, Salem-Hope Creek Security Plan, Revision 9 50.59 S/E S97-040 on UFSAR CN 97-15 for Tables 9.2-3 & 9.2-4 CC System License amendments removed Table 3.6-1, Containment isolation Valves from T.S. and the information from that Table is now maintained in the UFSAR. In support of that change, a review was performed of the existing Tables in the UFSAR for completeness.
*, 10CFRS0.59 EVALUATIONS MONTH: FEBRUARY 1997
The proposed UFSAR change clarifies the double isolation barriers for each of the mechanical penetrations at Salem. SORC: 97-019 This temporary procedure revision is being created as a contingency for the potential loss of ABV exhaust fan 11 (1 VHE45) during the 1 C buss outage exhaust fan 13 ( 1VHE47) is powered by the 1 C buss. SORC: 97-022 This change involves the proposed configuration of the Hand Geometry Reader system in the Security Center, the elimination of badge issue cubicles, and the description of the changed primary use of the auxiliary guardhouse.
                                    *
SORC: 97-025 TIS 3/4.1.2, "Boration Systems" provides analysis for the loss of a charging pump. No credit is taken for the functionality of the PD charging pump during any condition except during normal shutdown conditions, which is bounded by the loss of a charging pump. This UFSAR Change notice allows the reduction of the CCW flow to the PD Charging Pump oil cooler and Fluidic Drive cooler to ensure during PD Charging Pump operation the oil temperatures are within vendor specified tolerances.
* DOCKET NO:
SORC: 97-023
NAME:
CONTACT:
50-311 UNIT2 N. CONICELLA TELEPHONE:      609-339-2124 The following items were evaluated in accordance with the provisions of the Code of Federal Regulations 10CFR50.59. The Station Operations Review Committee has reviewed and concurs with these evaluations PROCEDURE 50.59 SIB S96-036 on Procedure The following Technical Specifications and basis were reviewed:3/4.1.2.1 S1(2).0P-SO.SF-0005(Q) &          Boration Systems Flow Paths - Shutdown; 3/4.1.2.2 Reactivity Control TRIS Operation of Refueling        Systems Flow Paths.
Water Purification System to                                                                SORC: 97-019 RWST in Modes 1-6 and 50.59 SIB S97-030, on              This temporary procedure revision is being created as a contingency for the Procedure Sl.OP.SO-ABV.0001, potential loss of ABV exhaust fan 11 (1 VHE45) during the 1C buss outage Rev. 2, Operation of the Unit 1    exhaust fan 13 ( 1VHE47) is powered by the 1C buss.
Aux. Building Ventilation with                                                              SORC: 97-022 Loss of Supply Fans 50.59 SIB S97-033,on Procedure     The proposed procedure revision will allow for stroke time testing of the S2.0P-ST.SJ-0005(Q), Rev. 7 on    SJ45 valves with an operable RHR loop Inservice. The proposed procedure Inservice Testing Safety Injection revision will reflect installation of jumpers to allow opening of the 21SJ4 5 Valves Modes 5-6                  and 22SJ45 valves without closing the 2RH1 or 2RH2 valves and opening the respective SJ44 valves.
SORC:  97-020 50.59 SIB S97-044, on             Basically, this test involves splitting the operation of Service Water System Procedure TS2.SE-SU.SW-             in two separate headers (the headers are usually cross-tied in the Service 0002(Q)                           Water Intake Structure).
SORC:  97-024 50.59 SIB S97-045 on Procedure This test will be performed to Mode 2. It will test and, if necessary, tune TS2. SE-SU.RCP-0004(Q), Rev. the controller for valve 2CC71.
0 Tuning of Letdown Heat                                                                   SORC: 97-029 Exchanger Temperature
 
I :
" 10CFR50.59 EVALUATIONS MONTH: FEBRUARY 1997
                                *
* DOCKET NO:
NAME:
CONTACT:
50-311 UNIT2 N. CONICELLA TELEPHONE:      609-339-2124 The following items were evaluated in accordance with the provisions of the Code of Federal Regulations 10CFR50.59. The Station Operations Review Committee has reviewed and concurs with these evaluations PROCEDURE 50.59 S/E S97-050, on            Proposed changes to the Nuclear Business Unit's Emergency Plan, Section Procedures NC.EP-EP.ZZ-          13.3 of the Hope Creek and Salem Final Updated Safety Analysis Reports 080l(Q), Rev. 0 Emergency        (SAR), would reduce the initial Emergency News Center (ENC) staffing News Center Operations and        from 26 to 22 positions.
NC.EP-EPZZ-0806(Q), ENC                                                                SORC:    97-029 TEMPORARY MODIFICATION 50.59 S/E 97-027 (T/Mod 97-      Due to the existing configuration of the Service Water (SW) supply and 001) Installation ofBlind Spacers return piping for the Containment Fan Coil Units (CFCUs), the potential in the No. 21 SW Nuclear          exists for water hammer in the SW return lines and drainage of the SW Header CFCU Supply/Return and    supply lines following a Loss of Offsite Power (LOOP). DCP 2EC-3590 the SW Supply/Return to the No. has been initiated to modify the SW piping to address these concerns.
21, No. 22 CFCUs                                                                        SORC:   97-019 50.59 S/E S96-23 l, (T/Mod 96-   The 1DF126 pressure regulator is not functioning either because of 037) Removal of Valve 1DF126      malfunction of the regulator itself or the feedback loop from the Internals                        backpressure control tank. This package presented to extend time period from 2/27/97 to 4/1/97.
SORC:   97-028 50.59 S/E S97-038, (T/Mod 96- Installation of the voltage monitor and associated voltage probes at cubicle 020) Rev. 0 Temporary            2H7D IAW this T-Mod will provide the desired voltage surge data for Installation of Surge Monitoring future engineering review.
Equipment at 4Kv SWGR Bus                                                              SORC: 97-029 2H (2SWGR2HD) Cubical 2H7D
___J
 
10CFR50.59 EVALUATIONS MONTH: FEBRUARY 1997
                              *
* DOCKET NO:
NAME:
CONTACT:
TELEPHONE:
50-311 UNIT2 N. CONICELLA 609-339-2124 The following items were evaluated in accordance with the provisions of the Code of Federal Regulations 10CFR50.59. The Station Operations Review Committee has reviewed and concurs with these evaluations UFSAR 50.59 SIB 96-122 and UFSAR        License amendments removed Table 3.6-1, Containment isolation Valves Change 96-139, Containment        from T.S. and the information from that Table is now maintained in the Isolation Systems                UFSAR. In support of that change, a review was performed of the existing Tables in the UFSAR for completeness. The proposed UFSAR change clarifies the double isolation barriers for each of the mechanical penetrations at Salem.
SORC:   97-019 50.59 SIB S97-002 on UFSAR        This temporary procedure revision is being created as a contingency for the change Notice 96-207 Revision    potential loss of ABV exhaust fan 11 (1 VHE45) during the 1C buss outage of table 9.3-6 as a corrective    exhaust fan 13 ( 1VHE47) is powered by the 1C buss.
action for PIR 96032155                                                                  SORC:  97-022 50.59 S/E S97-035, on UFSAR      This change involves the proposed configuration of the Hand Geometry Section 13.7 Salem & 13.6 Hope    Reader system in the Security Center, the elimination of badge issue Creek, Salem-Hope Creek          cubicles, and the description of the changed primary use of the auxiliary Security Plan, Revision 9        guardhouse.
SORC:  97-025 50.59 S/E S97-040 on UFSAR        TIS 3/4.1.2, "Boration Systems" provides analysis for the loss of a CN 97-15 for Tables 9.2-3 & 9.2- charging pump. No credit is taken for the functionality of the PD charging 4 CC System                      pump during any condition except during normal shutdown conditions, which is bounded by the loss of a charging pump. This UFSAR Change notice allows the reduction of the CCW flow to the PD Charging Pump oil cooler and Fluidic Drive cooler to ensure during PD Charging Pump operation the oil temperatures are within vendor specified tolerances.
SORC:   97-023
* OPERATING DATA REPORT
* OPERATING DATA REPORT
* Docket No: 50-311 Date: 03/10/97 Completed by: Robert Phillips Telephone:
* Docket No:   50-311 Date:       03/10/97 Completed by:     Robert Phillips                     Telephone:   339-2735 Operating Status
339-2735 Operating Status 1. Unit Name Salem No. 2 Notes 2. Reporting Period February 1997 3. Licensed Thermal Power (MWt) 3411 4. Nameplate Rating (Gross MWe) 1170 5. Design Electrical Rating (Net MWe) 1115 6. Maximum Dependable Capacity(Gross MWe) 1149 7. Maximum Dependable Capacity (Net MWe) 1106 8. If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason NA 9. Power Level to Which Restricted, if any (Net MWe) N/A 10. Reasons for Restrictions, if any
: 1. Unit Name                         Salem No. 2     Notes
: 11. Hours in Reporting Period 12. No. of Hrs. Rx. was Critical 13. Reactor Reserve Shutdown Hrs. 14. Hours Generator On-Line 15. Unit Reserve Shutdown Hours 16. Gross Thermal Energy Generated (MWH) 17. Gross Elec. Energy Generated (MWH) 18. Net Elec. Energy Gen. (MWH) 19. Unit Service Factor 20. Unit Availability Factor 21. Unit Capacity Factor (using MDC Net) 22. Unit Capacity Factor (using DER Net) 23. Unit Forced Outage Rate This Month 672 0 0 0 0 0 0 -9429 0 0 0 0 100 Year to Date cumulative 1416 134567 0 78083.6 0 0 0 75229.5 0 0 0 187781005 0 78648898 -15732 74680599 0 55.5 0 55.5 0 49.8 0 49.4 100 31.3 24. Shutdowns scheduled over next 6 months (type, date and duration of each) Refueling extension.
: 2. Reporting Period               February 1997
: 25. If shutdown at end of Report Period, Estimated Date of Startup: Second quarter of 1997. 8-1-7.R2 9:RAGE DAILY UNIT POWER LE"9 Docket No.: 50-311 Unit Name: Salem #2 Date: 03/10/97 Completed by: Robert Phillips Telephone:
: 3. Licensed Thermal Power (MWt)               3411
339-2735 Month February 1997 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 0 17 0 2 0 18 0 3 0 19 0 4 0 20 0 5 0 21 0 6 0 22 0 7 0 23 0 8 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 28 0 13 0 29 14 0 30 15 0 31 16 0 P. 8.1-7 Rl ND. DATE 3859 2*1*97 F: Forced S: Scheduled DURATION TYPE 1 (HOORS) REASON 1 F 744 F C 2 Reason A*Equfpnent F*flure (expl*fn)
: 4. Nameplate Rating (Gross MWe)               1170
B*Mafntenance or Jest C*Refuelfng D*Requletory Restrfctfon 4 UNIT SHUTDOWN AND POlilER REDUCTIONS REPORT MONTH February 1996 METHOO OF SHUTTING DOWN REACTOR LICENSE EVENT REPORT # *----------
: 5. Design Electrical Rating (Net MWe)         1115
zz 3 Method: 1*Manual 2*Manual Scram SYSTEM CODE' E*Operetor Trefnfng & Lfcense Examfnetfon F*Adlfnfstretfve 3-Automatfc Scram 4*Contfnuatfon of Prevfous outage 5-Load Reduction 9*0ther G*Oper*tfonel Error CExplefn>
: 6. Maximum Dependable Capacity(Gross MWe) 1149
H*Other (Explef n) .. DOCKET NO.: ... 5""0..,.*2  
: 7. Maximum Dependable Capacity (Net MWe)       1106
.... 72......,.
: 8. If Changes Occur   in Capacity Ratings (items 3 through 7) since Last Report, Give Reason             NA
__ _ UN IT NAME:
: 9. Power Level to Which Restricted, if any (Net MWe)               N/A
__ DATE: 02f10/9l COMPLETED BY: ..  
: 10. Reasons for Restrictions, if any   ~~~~--=N:..:...J--'A=-~~~~~~~~~~~~~
... fl""'["'""tps-TELEPHONE:
This Month    Year to Date  cumulative
609*339*2735 CeHPONENT CAUSE AND CORRECTIVE ACTION CODE 5 TD PREVENT RECURRENCE zzzz Refuelfng Schedule Extensfon 4 . Exhfblt G
: 11. Hours in Reporting Period               672          1416        134567
* Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File (NUREG-0161) 5 Exhibit 1
: 12. No. of Hrs. Rx. was Critical             0              0      78083.6
* Same Source ' *
: 13. Reactor Reserve Shutdown Hrs.             0              0          0
. ,. * * ** Refueling Information Month: February, 1997 Docket No. 50-311 Unit Name: Salem 2 Contact: D. Tisdall Telephone:
: 14. Hours Generator On-Line                   0              0      75229.5
609-339-1538 Month: February, 1997 1. Refueling information has changed from last month: Yes: No: X 2. Scheduled date for next refueling:
: 15. Unit Reserve Shutdown Hours               0              0          0
Currently in outage. Scheduled date for restart following refueling:
: 16. Gross Thermal Energy Generated (MWH)                             0              0      187781005
To Be Determined
: 17. Gross Elec. Energy Generated (MWH)                             0              0      78648898
: 18. Net Elec. Energy Gen. (MWH)         -9429          -15732      74680599
: 19. Unit Service Factor                       0              0          55.5
: 20. Unit Availability Factor                 0              0          55.5
: 21. Unit Capacity Factor (using MDC Net)                     0              0          49.8
: 22. Unit Capacity Factor (using DER Net)                     0              0          49.4
: 23. Unit Forced Outage Rate                 100           100           31.3
: 24. Shutdowns scheduled over next 6 months (type, date and duration of each)
Refueling extension.
: 25. If shutdown at end of Report Period, Estimated Date of Startup:
Second quarter of 1997.
8-1-7.R2
 
9:RAGE DAILY UNIT POWER LE"9 Docket No.:   50-311 Unit Name:     Salem #2 Date:         03/10/97 Completed by:     Robert Phillips                   Telephone:     339-2735 Month     February   1997 Day Average Daily Power Level               Day Average Daily Power Level (MWe-NET)                                 (MWe-NET) 1             0                             17             0 2             0                             18             0 3             0                             19             0 4             0                             20             0 5             0                             21             0 6             0                             22             0 7             0                             23             0 8             0                             24             0 9             0                             25             0 10             0                             26             0 11             0                             27             0 12             0                             28             0 13             0                             29 14             0                             30 15             0                             31 16             0 P. 8.1-7 Rl
 
UNIT SHUTDOWN AND POlilER REDUCTIONS REPORT MONTH February     1996                                         DOCKET NO.: ...5""0..,.*2....72......,._ __
UN IT NAME: _s;:;;.;a.-l~em~2.,,,..__ _
DATE:   02f10/9l COMPLETED BY: ..R=obe~r.._t....,P-..h...fl""'["'""tps-TELEPHONE:     609*339*2735 METHOO OF SHUTTING        LICENSE                                                                                                      '
DURATION                    DOWN            EVENT            SYSTEM    CeHPONENT             CAUSE AND CORRECTIVE ACTION ND.      DATE      TYPE1      (HOORS)      REASON1      REACTOR          REPORT #        CODE'    CODE5                    TD PREVENT RECURRENCE 3859  2*1*97    F        744            FC          4
                                                                        *----------      zz        zzzz           Refuelfng Schedule Extensfon 2                                                      3                        4               .                 5 F: Forced    Reason                                                  Method:                    Exhfblt G
* Instructions           Exhibit 1
* Same S: Scheduled  A*Equfpnent F*flure (expl*fn)                            1*Manual                  for Preparation of Data           Source B*Mafntenance or Jest                                    2*Manual Scram            Entry Sheets for Licensee C*Refuelfng                                            3-Automatfc Scram          Event Report CLER) File D*Requletory Restrfctfon                                4*Contfnuatfon of        (NUREG-0161)
E*Operetor Trefnfng &Lfcense Examfnetfon                    Prevfous outage F*Adlfnfstretfve                                      5-Load Reduction G*Oper*tfonel Error CExplefn>                          9*0ther H*Other (Explef n)
 
  ** Refueling Information
                              *
* Docket No. 50-311 Month: February, 1997                                              Unit Name: Salem 2
 
==Contact:==
D. Tisdall Telephone: 609-339-1538 Month: February, 1997
: 1. Refueling information has changed from last month: Yes: No: X
: 2. Scheduled date for next refueling: Currently in outage.
Scheduled date for restart following refueling: To Be Determined
: 3. a. Will Technical Specification changes or other license amendments be required?
: 3. a. Will Technical Specification changes or other license amendments be required?
Yes: No: X Not Determined to Date: b. Has the reload fuel design been reviewed by the Station Operating Review committee?
Yes: No: X Not Determined to Date:
Yes: X No: If no, when is it scheduled?
: b. Has the reload fuel design been reviewed by the Station Operating Review committee?
____ _ 4. Scheduled date (s) for submitting proposed licensing action: N/A 5. Important licensing considerations associated with refueling:
Yes: X No: If no, when is it scheduled? _ _ _ __
: 4. Scheduled date (s) for submitting proposed licensing action: N/A
: 5. Important licensing considerations associated with refueling:
: 6. Number of Fuel Assemblies:
: 6. Number of Fuel Assemblies:
: a. lncore: b. In Spent Fuel Storage: 7. Present Licensed spent fuel storage capacity:
: a. lncore:                                                              193
Future spent fuel storage capacity:
: b. In Spent Fuel Storage:                                              584
: 8. Date of last refueling that can be discharged to the spent fuel 193 584 1632 1632 pool assuming the present licensed capacity:
: 7. Present Licensed spent fuel storage capacity:                         1632 Future spent fuel storage capacity:                                   1632
October, 2016
: 8. Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:                 October, 2016
.. SALEM UNIT 2 *
* SALEM GENERATING STATION MONTHLY OPERATING  
* SALEM GENERATING STATION MONTHLY OPERATING  


==SUMMARY==
==SUMMARY==
-UNIT 2 FEBRUARY 1997 The unit remained shutdown for the entire period. According to commitments from PSE&G and a subsequent confirmatory action letter from the NRC, the unit will remain shutdown pending completion of the following actions:
- UNIT 2 FEBRUARY 1997 SALEM UNIT 2 The unit remained shutdown for the entire period. According to commitments from PSE&G and a subsequent confirmatory action letter from the NRC, the unit will remain shutdown pending completion of the following actions:
* Appropriately address long standing equipment reliability and operability issues.
* Appropriately address long standing equipment reliability and operability issues.
* After the work is completed, conduct a restart readiness review to determine for ourselves the ability of the unit to operate in a safe, event free manner.
* After the work is completed, conduct a restart readiness review to determine for ourselves the ability of the unit to operate in a safe, event free manner.
* After the restart review, meet with the NRC and communicate the results of that review.}}
* After the restart review, meet with the NRC and communicate the results of that review.}}

Latest revision as of 05:19, 3 February 2020

Monthly Operating Rept for Feb 1997 for Salem,Unit 2. W/970311 Ltr
ML18102A929
Person / Time
Site: Salem PSEG icon.png
Issue date: 02/28/1997
From: Conicella N, Garchow D, Phillips R, Tisdall D
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9703240185
Download: ML18102A929 (11)
v • d • e


Text

\ '0 PSl§Ge Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit March 11, 1997 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn: Document Control Desk MONTHLY OPERATING REPORT SALEM NO. 2 DOCKET NO: 50-311 In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specifications, the original monthly operating report for the month of February is being sent to you.

Sincerely yours, General Manager -

Salem Operations VS:pc Enclosures C Mr. H. J. Miller Regional Administrator USNRC, Region 1 4 7 5 Allendale Road King of Prussia, PA 19046

- . \

9703240185 970228 PDR ADOCK 05000311 R PDR 111111111111111111111111111111111111111111 111111111 1111 The po.ver is in your hands.

  • 9 1 - ll ll 4 7 7 1
  • 95-2168 REV. 6/94
  • , 10CFRS0.59 EVALUATIONS MONTH: FEBRUARY 1997
  • DOCKET NO:

NAME:

CONTACT:

50-311 UNIT2 N. CONICELLA TELEPHONE: 609-339-2124 The following items were evaluated in accordance with the provisions of the Code of Federal Regulations 10CFR50.59. The Station Operations Review Committee has reviewed and concurs with these evaluations DESIGN CHANGE PACKAGE 50.59 S/E S96-167, 2EC-3590, This design change package installs a relief valve upstream of each of the Pkg. 1, Rev 1 Addition of five SW223 valves in the service water outlet lines from the CFCUs.

Thermal Overpressure Device on SORC: 97-022 CFCU Return Piping 50.59 S/E S96-208, 2EC-3590, Engineering Evaluation S-C-SW-MEE-1138 addresses the Westinghouse Pkg. 2, Rev. This DCP installs a Nuclear Safety Advisory Letter (NSAL)96-003 concern that the CFCU relief valve across SW223 & coils and the associated piping could be overpressurized due to potential SW76 valves to address the heat transfer to the stagnant service water in the CFCU coils following a overpressure condition postulated LOCA or MSLB and LOOP event. Package 01 of this DCP installs a relief valve across SW223 & SW76 valves to address the overpressure condition as evaluated in the above engineering evaluation.

SORC: 97-022 50.59 S/E S97-042, 2EC-3570, This modification does not impact the capacity, capability or the response Pkg. 1, Rev. 0 Nitrogen Purge time of the AFST, the AFW system or the AFW equipment. In addition, Blanket this modification does not impact any other safety related equipment or system. The modifications implemented by this DCP are intended to improve the system reliability and increase component life by controlling the amount of dissolved Oxygen in the Auxiliary Feedwater System.

SORC: 97-024 50.59 S/E S97-047, 2EC-3590, This design change package modifies the No. 21 Service Water Nuclear Pkg. 8, Rev.O Service Water Header 16" CFCU supply piping by adding a redundant check valve System No. 21 Header Check downstream of existing check valve to prevent backleakage of the header.

Valve Installation SORC: 97-026

. , 10CFR50.59 EVALUATIONS MONTH: FEBRUARY 1997

  • DOCKET NO:

NAME:

CONTACT:

50-311 UNIT2 N. CONICELLA TELEPHONE: 609-339-2124 The following items were evaluated in accordance with the provisions of the Code of Federal Regulations 10CFR50.59. The Station Operations Review Committee has reviewed and concurs with these evaluations DESIGN CHANGE PACKAGE 50.59 S/E S97-048, 2EC-3590, This design change package modifies the No. 22 Service Water Nuclear Pkg. 9, Rev. 0 Service Water Header 16" CFCU supply piping by adding a redundant check valve System No. 22 Header Check downstream of existing check valve, 22SW51 to prevent backleakage of Valve Installation the header.

SORC: 97-026 MINOR - MODIFICATION 50.59 S/E S97-022, Masoneilan The purpose of this Minor Mod is to enhance the method of assuring the Air Operator, Retainer Clip S manual handwheel declutching pin stays in place and does not accidentally 032, Rev. 0 allow the handwheel to become engaged.

SORC: 97-018 MISCELLANEOUS 50.59 S/E S-97-04lon The purpose of this evaluation is to provide engineering support for an Engineering Evaluation S-2-CH- Operability Determination in the event that a chillier fails in the Unit 2 MEE-1175 Rev. 0 Auxiliary Building Chilled Water (CH) system with Salem Unit 2 in modes three and four, and the Unit 1 CH system having at least two chillers and one pump available in mode undefined.

SORC: 97-023 50.59 S/E S97-053 on Turbine The proposed test injects signals into the Hagan Control System, monitors Bypass Valve Control Loops the response of the controllers, and verifies proper operation of the turbine Test (TS2.SE-SU.RCP-0002(Q). bypass steam dump valves in response to the control signals.

Revision 0 SORC: 97-028 PROCEDURE 50.59 S/E TS2.SE-SU.CN- This is a one-time test of the condensate pumps to establish their 000l(Q), Condensate Pump performance curves (total flow vs. differential pump head).

Performance Test SORC: 97-023

_J

  • , 10CFRS0.59 EVALUATIONS MONTH: FEBRUARY 1997
  • DOCKET NO:

NAME:

CONTACT:

50-311 UNIT2 N. CONICELLA TELEPHONE: 609-339-2124 The following items were evaluated in accordance with the provisions of the Code of Federal Regulations 10CFR50.59. The Station Operations Review Committee has reviewed and concurs with these evaluations PROCEDURE 50.59 SIB S96-036 on Procedure The following Technical Specifications and basis were reviewed:3/4.1.2.1 S1(2).0P-SO.SF-0005(Q) & Boration Systems Flow Paths - Shutdown; 3/4.1.2.2 Reactivity Control TRIS Operation of Refueling Systems Flow Paths.

Water Purification System to SORC: 97-019 RWST in Modes 1-6 and 50.59 SIB S97-030, on This temporary procedure revision is being created as a contingency for the Procedure Sl.OP.SO-ABV.0001, potential loss of ABV exhaust fan 11 (1 VHE45) during the 1C buss outage Rev. 2, Operation of the Unit 1 exhaust fan 13 ( 1VHE47) is powered by the 1C buss.

Aux. Building Ventilation with SORC: 97-022 Loss of Supply Fans 50.59 SIB S97-033,on Procedure The proposed procedure revision will allow for stroke time testing of the S2.0P-ST.SJ-0005(Q), Rev. 7 on SJ45 valves with an operable RHR loop Inservice. The proposed procedure Inservice Testing Safety Injection revision will reflect installation of jumpers to allow opening of the 21SJ4 5 Valves Modes 5-6 and 22SJ45 valves without closing the 2RH1 or 2RH2 valves and opening the respective SJ44 valves.

SORC: 97-020 50.59 SIB S97-044, on Basically, this test involves splitting the operation of Service Water System Procedure TS2.SE-SU.SW- in two separate headers (the headers are usually cross-tied in the Service 0002(Q) Water Intake Structure).

SORC: 97-024 50.59 SIB S97-045 on Procedure This test will be performed to Mode 2. It will test and, if necessary, tune TS2. SE-SU.RCP-0004(Q), Rev. the controller for valve 2CC71.

0 Tuning of Letdown Heat SORC: 97-029 Exchanger Temperature

I :

" 10CFR50.59 EVALUATIONS MONTH: FEBRUARY 1997

  • DOCKET NO:

NAME:

CONTACT:

50-311 UNIT2 N. CONICELLA TELEPHONE: 609-339-2124 The following items were evaluated in accordance with the provisions of the Code of Federal Regulations 10CFR50.59. The Station Operations Review Committee has reviewed and concurs with these evaluations PROCEDURE 50.59 S/E S97-050, on Proposed changes to the Nuclear Business Unit's Emergency Plan, Section Procedures NC.EP-EP.ZZ- 13.3 of the Hope Creek and Salem Final Updated Safety Analysis Reports 080l(Q), Rev. 0 Emergency (SAR), would reduce the initial Emergency News Center (ENC) staffing News Center Operations and from 26 to 22 positions.

NC.EP-EPZZ-0806(Q), ENC SORC: 97-029 TEMPORARY MODIFICATION 50.59 S/E 97-027 (T/Mod 97- Due to the existing configuration of the Service Water (SW) supply and 001) Installation ofBlind Spacers return piping for the Containment Fan Coil Units (CFCUs), the potential in the No. 21 SW Nuclear exists for water hammer in the SW return lines and drainage of the SW Header CFCU Supply/Return and supply lines following a Loss of Offsite Power (LOOP). DCP 2EC-3590 the SW Supply/Return to the No. has been initiated to modify the SW piping to address these concerns.

21, No. 22 CFCUs SORC: 97-019 50.59 S/E S96-23 l, (T/Mod 96- The 1DF126 pressure regulator is not functioning either because of 037) Removal of Valve 1DF126 malfunction of the regulator itself or the feedback loop from the Internals backpressure control tank. This package presented to extend time period from 2/27/97 to 4/1/97.

SORC: 97-028 50.59 S/E S97-038, (T/Mod 96- Installation of the voltage monitor and associated voltage probes at cubicle 020) Rev. 0 Temporary 2H7D IAW this T-Mod will provide the desired voltage surge data for Installation of Surge Monitoring future engineering review.

Equipment at 4Kv SWGR Bus SORC: 97-029 2H (2SWGR2HD) Cubical 2H7D

___J

10CFR50.59 EVALUATIONS MONTH: FEBRUARY 1997

  • DOCKET NO:

NAME:

CONTACT:

TELEPHONE:

50-311 UNIT2 N. CONICELLA 609-339-2124 The following items were evaluated in accordance with the provisions of the Code of Federal Regulations 10CFR50.59. The Station Operations Review Committee has reviewed and concurs with these evaluations UFSAR 50.59 SIB 96-122 and UFSAR License amendments removed Table 3.6-1, Containment isolation Valves Change 96-139, Containment from T.S. and the information from that Table is now maintained in the Isolation Systems UFSAR. In support of that change, a review was performed of the existing Tables in the UFSAR for completeness. The proposed UFSAR change clarifies the double isolation barriers for each of the mechanical penetrations at Salem.

SORC: 97-019 50.59 SIB S97-002 on UFSAR This temporary procedure revision is being created as a contingency for the change Notice 96-207 Revision potential loss of ABV exhaust fan 11 (1 VHE45) during the 1C buss outage of table 9.3-6 as a corrective exhaust fan 13 ( 1VHE47) is powered by the 1C buss.

action for PIR 96032155 SORC: 97-022 50.59 S/E S97-035, on UFSAR This change involves the proposed configuration of the Hand Geometry Section 13.7 Salem & 13.6 Hope Reader system in the Security Center, the elimination of badge issue Creek, Salem-Hope Creek cubicles, and the description of the changed primary use of the auxiliary Security Plan, Revision 9 guardhouse.

SORC: 97-025 50.59 S/E S97-040 on UFSAR TIS 3/4.1.2, "Boration Systems" provides analysis for the loss of a CN 97-15 for Tables 9.2-3 & 9.2- charging pump. No credit is taken for the functionality of the PD charging 4 CC System pump during any condition except during normal shutdown conditions, which is bounded by the loss of a charging pump. This UFSAR Change notice allows the reduction of the CCW flow to the PD Charging Pump oil cooler and Fluidic Drive cooler to ensure during PD Charging Pump operation the oil temperatures are within vendor specified tolerances.

SORC: 97-023

  • OPERATING DATA REPORT
  • Docket No: 50-311 Date: 03/10/97 Completed by: Robert Phillips Telephone: 339-2735 Operating Status
1. Unit Name Salem No. 2 Notes
2. Reporting Period February 1997
3. Licensed Thermal Power (MWt) 3411
4. Nameplate Rating (Gross MWe) 1170
5. Design Electrical Rating (Net MWe) 1115
6. Maximum Dependable Capacity(Gross MWe) 1149
7. Maximum Dependable Capacity (Net MWe) 1106
8. If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason NA
9. Power Level to Which Restricted, if any (Net MWe) N/A
10. Reasons for Restrictions, if any ~~~~--=N:..:...J--'A=-~~~~~~~~~~~~~

This Month Year to Date cumulative

11. Hours in Reporting Period 672 1416 134567
12. No. of Hrs. Rx. was Critical 0 0 78083.6
13. Reactor Reserve Shutdown Hrs. 0 0 0
14. Hours Generator On-Line 0 0 75229.5
15. Unit Reserve Shutdown Hours 0 0 0
16. Gross Thermal Energy Generated (MWH) 0 0 187781005
17. Gross Elec. Energy Generated (MWH) 0 0 78648898
18. Net Elec. Energy Gen. (MWH) -9429 -15732 74680599
19. Unit Service Factor 0 0 55.5
20. Unit Availability Factor 0 0 55.5
21. Unit Capacity Factor (using MDC Net) 0 0 49.8
22. Unit Capacity Factor (using DER Net) 0 0 49.4
23. Unit Forced Outage Rate 100 100 31.3
24. Shutdowns scheduled over next 6 months (type, date and duration of each)

Refueling extension.

25. If shutdown at end of Report Period, Estimated Date of Startup:

Second quarter of 1997.

8-1-7.R2

9:RAGE DAILY UNIT POWER LE"9 Docket No.: 50-311 Unit Name: Salem #2 Date: 03/10/97 Completed by: Robert Phillips Telephone: 339-2735 Month February 1997 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 0 17 0 2 0 18 0 3 0 19 0 4 0 20 0 5 0 21 0 6 0 22 0 7 0 23 0 8 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 28 0 13 0 29 14 0 30 15 0 31 16 0 P. 8.1-7 Rl

UNIT SHUTDOWN AND POlilER REDUCTIONS REPORT MONTH February 1996 DOCKET NO.: ...5""0..,.*2....72......,._ __

UN IT NAME: _s;:;;.;a.-l~em~2.,,,..__ _

DATE: 02f10/9l COMPLETED BY: ..R=obe~r.._t....,P-..h...fl""'["'""tps-TELEPHONE: 609*339*2735 METHOO OF SHUTTING LICENSE '

DURATION DOWN EVENT SYSTEM CeHPONENT CAUSE AND CORRECTIVE ACTION ND. DATE TYPE1 (HOORS) REASON1 REACTOR REPORT # CODE' CODE5 TD PREVENT RECURRENCE 3859 2*1*97 F 744 FC 4

  • ---------- zz zzzz Refuelfng Schedule Extensfon 2 3 4 . 5 F: Forced Reason Method: Exhfblt G
  • Instructions Exhibit 1
  • Same S: Scheduled A*Equfpnent F*flure (expl*fn) 1*Manual for Preparation of Data Source B*Mafntenance or Jest 2*Manual Scram Entry Sheets for Licensee C*Refuelfng 3-Automatfc Scram Event Report CLER) File D*Requletory Restrfctfon 4*Contfnuatfon of (NUREG-0161)

E*Operetor Trefnfng &Lfcense Examfnetfon Prevfous outage F*Adlfnfstretfve 5-Load Reduction G*Oper*tfonel Error CExplefn> 9*0ther H*Other (Explef n)

    • Refueling Information
  • Docket No. 50-311 Month: February, 1997 Unit Name: Salem 2

Contact:

D. Tisdall Telephone: 609-339-1538 Month: February, 1997

1. Refueling information has changed from last month: Yes: No: X
2. Scheduled date for next refueling: Currently in outage.

Scheduled date for restart following refueling: To Be Determined

3. a. Will Technical Specification changes or other license amendments be required?

Yes: No: X Not Determined to Date:

b. Has the reload fuel design been reviewed by the Station Operating Review committee?

Yes: X No: If no, when is it scheduled? _ _ _ __

4. Scheduled date (s) for submitting proposed licensing action: N/A
5. Important licensing considerations associated with refueling:
6. Number of Fuel Assemblies:
a. lncore: 193
b. In Spent Fuel Storage: 584
7. Present Licensed spent fuel storage capacity: 1632 Future spent fuel storage capacity: 1632
8. Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: October, 2016
  • SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT 2 FEBRUARY 1997 SALEM UNIT 2 The unit remained shutdown for the entire period. According to commitments from PSE&G and a subsequent confirmatory action letter from the NRC, the unit will remain shutdown pending completion of the following actions:

  • Appropriately address long standing equipment reliability and operability issues.
  • After the work is completed, conduct a restart readiness review to determine for ourselves the ability of the unit to operate in a safe, event free manner.
  • After the restart review, meet with the NRC and communicate the results of that review.
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