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{{#Wiki_filter: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 SALEMNO. 1 DOCKET NO: 50-272 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  
{{#Wiki_filter: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 SALEMNO. 1 DOCKET NO: 50-272 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.
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,! /.., L V '--C Mr. H.J. Miller Regional Administrator USNRC, Regionl 4 7 5 Allendale Road King of Prussia, PA 19046 ---9703240182 970228 PDR ADOCK 05000272 R PDR The pOtVer is in }Dllf hands. (jjy;ms, David F.
David F.
General Manager -Salem Operations
General Manager -
,,..------
Salem Operations Gare~
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VS:pc Enclosures               <:.;  'i .>"\!lll',..1q i"',!
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* 95-2168 REV. 6/94 e e , 10CFR50.59 EVALUATIONS DOCKET NO: 50-272 MONTH: FEBRUARY 1997 NAME: UNITl CONTACT: N. CONICELLA TELEPHONE:
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609-339-2124 The following items were evaluated in accordance with the provisions of the Code of Federal Regulations 10CFR50.59.
C       Mr. H.J. Miller Regional Administrator USNRC, Regionl 4 7 5 Allendale Road King of Prussia, PA 19046
The Station Operations Review Committee has reviewed and concurs with these evaluations DESIGN CHANGE PACKAGE (No 50.59 S/E) lEA-1134 Pkg. 1, Rev. 0 on addition of Station Air Valves 1SA549 and 1SA550 in Auxiliary Building and Valves 1 SA541 through 1 SA548 50.59 S/E S97-026, lEA-1126, Pkg. 1, Rev. 0 As-Built SGFP Suction Strainer Cleanout Valves, 11CN926 & 12CN926 50.59 S/E S97-032, lEC-3486 Pkg. 2, Rev. 1 OCFR50 Appendix R alternate Shutdown Methodology
                -- -
-Installation of Transfer Switches 50.59 S/E S97-043, lEC-3495, Rev. 2 on Steam Trap Replacement Project This modification provides as-built documentation for the non-safety related portion of the station air in the auxiliary building, turbine building and in the clean facilities building.
9703240182 970228 PDR ADOCK 05000272 R                                   PDR
SORC: 97-022 This DCP provides as-built documentation for valves 11 CN926 and 12CN926. The valves provide for controlled manual blowdown of strainers at the suction of both Unit 1 SGFP's. SORC: 97-021 This modification addresses concerns regarding the Alternate Shutdown Methodology at Salem in the event of a Control Room evacuation due to fire in the Control Room, Relay Room, or ceiling area of the 460/230 Volt Switchgear Room, which calls for the use of electrical wiring modifications and jumpers. SORC: 97-019 In order to enhance system performance and eliminate high maintenance components, twenty seven steam traps (1MSE21through1MSE35 and 1MSE38 through 1MSE49) and associated bypass orifices (where presently installed), bypass valve(s), drain valves and isolation valves will be removed (except four isolation valves required by procedure for Steam Generator Tube Rupture) and are being replaced.
                                                        ,,..------
SORC: 97-025 
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. ' e e , lOCFRS0.59 EVALUATIONS DOCKET NO: 50-272 MONTH: FEBRUARY 1997 NAME: UNITl CONTACT: N. CONICELLA TELEPHONE:
* lllll llll 9    7 llllll 111111111111111111111111111111111
609-339-2124 The following items were evaluated in accordance with the provisions of the Code of Federal Regulations 10CFR50.59.
                                                                              ~    &   Iii 4   7   1   5
The Station Operations Review Committee has reviewed and concurs with these evaluations DESIGN CHANGE PACKAGE 50.59 SIB S97-049, lEC-3620, Pkg. 1, Rev. 0 on Letdown Isolation Valve Bypass Key switch 50.59 SIB S97-058, lEC-3648, SSPS Phase A and containment Ventilation Isolation Modification PROCEDURE 50.59 SIB S97-023, SU.CC-0003(Q), Rev. O "Component Cooling Pump Performance with 11CC16 & 12CC 16 Throttled" SAFETY EVALUATION This proposal will revise Section 5.6.4 and Figure 7.2-5 of the UFSAR to describe the new bypass circuitry of the low pressurizer level isolation signal so that operator control of the letdown isolation valves is possible during steam generator tube rupture conditions.
* The pOtVer is in }Dllf hands.
SORC: 97-025 This modification adds relays and additional Main Control Room pushbuttons to both Train A and Train B to allow manual initiation of Containment Ventilation Isolation separately from Phase A Containment Isolation.
95-2168 REV. 6/94
SORC: 97-028 This procedure describes an "experimental" test which will demonstrate if the CC system is capable of reaching pump run-out flow and also whether the CC pump and motor are capable of surviving at maximum pump flow. SORC: 97-017 50.59 SIB S96-047, S.C.ZZ-ESE-This safety evaluation addresses separation of the free air cables installed in 0841 Rev. 1 Separation distance the Salem Relay Rooms. of cables in free air installed in SORC: 96-099 Salem U/1 and U/2 relay rooms 1*
-----OPERATING DATA REPORT Docket No: 50-272 Date: 03/10/97 Completed by: Robert Phillips Telephone:
339-2735 Operating Status 1. Unit Name Salem No. 1 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
: 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 -2446 0 0 0 0 100 Year to Date 1416 0 0 0 0 0 0 -5470 0 0 0 0 100 Cumulative 172417 104380.5 0 100388.3 0 318062229 105301000 100169266 58.2 58.2 52.5 52.1 27.0 24. Shutdowns scheduled over next 6 months (type, date and duration of each) Steam Generator replacement.
: 25. If shutdown at end of Report Period, Estimated Date of startup: Under review. 8-1-7.R2 


DAILY UNIT POWER LEVEL tt Docket No.: 50-272 Unit Name: Salem #1 Date: 03/10/97 Completed by: Robert Phillips Telephone:
, 10CFR50.59 EVALUATIONS e                                          e  DOCKET NO:        50-272 MONTH: FEBRUARY 1997                                                          NAME:              UNITl 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. The Station Operations Review Committee has reviewed and concurs with these evaluations DESIGN CHANGE PACKAGE (No 50.59 S/E) lEA-1134 Pkg.      This modification provides as-built documentation for the non-safety 1, Rev. 0 on addition of Station  related portion of the station air in the auxiliary building, turbine building Air Valves 1SA549 and 1SA550      and in the clean facilities building.
339-2735 Month February 1997 Day Average Daily Power Level (MWe-NET)
in Auxiliary Building and Valves                                                          SORC:    97-022 1SA541 through 1SA548 50.59 S/E S97-026, lEA-1126,      This DCP provides as-built documentation for valves 11 CN926 and Pkg. 1, Rev. 0 As-Built SGFP      12CN926. The valves provide for controlled manual blowdown of Suction Strainer Cleanout        strainers at the suction of both Unit 1 SGFP's.
Day Average Daily Power Level (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 NO. DATE 4092 2-1-97 1 F: Forced S: Scheduled DURATION TYPE 1 (HOURS) REASON 2 F 744 F.C UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH February 1996 METHOD OF SHUTTING LICENSE DOWN EVENT REACTOR REPORT # SYSTEM CODE 4 4 -----------
Valves, 11CN926 & 12CN926                                                                  SORC:    97-021 50.59 S/E S97-032, lEC-3486      This modification addresses concerns regarding the Alternate Shutdown Pkg. 2, Rev. 1OCFR50 Appendix    Methodology at Salem in the event of a Control Room evacuation due to R alternate Shutdown              fire in the Control Room, Relay Room, or ceiling area of the 460/230 Volt Methodology - Installation of    Switchgear Room, which calls for the use of electrical wiring modifications Transfer Switches                and jumpers.
2422 2 3 Reason A-Equipnent Failure (explain)
SORC:    97-019 50.59 S/E S97-043, lEC-3495,      In order to enhance system performance and eliminate high maintenance Rev. 2 on Steam Trap              components, twenty seven steam traps (1MSE21through1MSE35 and Replacement Project              1MSE38 through 1MSE49) and associated bypass orifices (where presently installed), bypass valve(s), drain valves and isolation valves will be removed (except four isolation valves required by procedure for Steam Generator Tube Rupture) and are being replaced.
B-Maintenance or Test C-Refueling D-Requlatory Restriction E-Operator Training & License Examination F-Adninistrative G-Operational Error (Explain)
SORC:    97-025
H-Other (Explain)
 
Method: 1-Manual 2-Manual Scram 3*Automatic Scram 4-Continuation of Previous Outage S*Load Reduction 9*0ther 4 DOCKET NO.: _,s,,.,o..,.-3:.1...,1:.,,....---s*  
    . '
*-* UNIT NAME: _s,..a .... l""em"-""#""'l
, lOCFRS0.59 EVALUATIONS e                                        e  DOCKET NO:      50-272 MONTH: FEBRUARY 1997                                                            NAME:            UNITl 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. The Station Operations Review Committee has reviewed and concurs with these evaluations DESIGN CHANGE PACKAGE 50.59 SIB S97-049, lEC-3620,        This proposal will revise Section 5.6.4 and Figure 7.2-5 of the UFSAR to Pkg. 1, Rev. 0 on Letdown            describe the new bypass circuitry of the low pressurizer level isolation Isolation Valve Bypass Key          signal so that operator control of the letdown isolation valves is possible switch                              during steam generator tube rupture conditions.
__ _ DATE: ....;0::.:2:,...-..:..;10::...-..;.9""'7_,..,...
SORC:  97-025 50.59 SIB S97-058, lEC-3648,        This modification adds relays and additional Main Control Room SSPS Phase A and containment        pushbuttons  to both Train A and Train B to allow manual initiation of Ventilation Isolation Modification Containment Ventilation Isolation separately from Phase A Containment Isolation.
__ COMPLETED BY: Robert.Phillips TELEPHONE:
SORC:  97-028 PROCEDURE 50.59 SIB S97-023, TS1.SE-          This procedure describes an "experimental" test which will demonstrate if SU.CC-0003(Q), Rev. O                the CC system is capable of reaching pump run-out flow and also whether "Component Cooling Pump              the CC pump and motor are capable of surviving at maximum pump flow.
609-339-2735 COMPONENT CAUSE AND CORRECTIVE ACTION CODE 6 TO PREVENT RECURRENCE Steam Generator Replacement Exhibit G
Performance with 11CC16 &                                                                  SORC:  97-017 12CC 16 Throttled" SAFETY EVALUATION 50.59 SIB S96-047, S.C.ZZ-ESE- This safety evaluation addresses separation of the free air cables installed in 0841 Rev. 1 Separation distance the Salem Relay Rooms.
* Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File (NUREG*0161) 5 Exhibit 1
of cables in free air installed in                                                          SORC: 96-099 Salem U/1 and U/2 relay rooms
* Same Source _J Refueling Information Month: February, 1997 Month: February, 1997
 
* Docket No. 50-272 Unit Name: Salem 1. Contact: D.Tisdall Telephone:
          ---~~-    -----
609-339-1538
OPERATING DATA REPORT Docket No:    50-272 Date:        03/10/97 Completed by:    Robert Phillips                  Telephone:    339-2735 Operating Status
: 1. Refueling information has changed from last month: Yes: No: X 2. Scheduled date for next refueling:
: 1. Unit Name                        Salem No. 1    Notes
To Be Determined Scheduled date for restart following refueling:
: 2. Reporting Period              February 1997
To Be Determined
: 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+-=A=------------
This Month  Year to Date    Cumulative
: 11. Hours in Reporting Period            672          1416          172417
: 12. No. of Hrs. Rx. was Critical          0              0          104380.5
: 13. Reactor Reserve Shutdown Hrs.          0              0              0
: 14. Hours Generator On-Line                0              0          100388.3
: 15. Unit Reserve Shutdown Hours            0              0              0
: 16. Gross Thermal Energy Generated (MWH)                          0              0        318062229
: 17. Gross Elec. Energy Generated (MWH)                          0              0        105301000
: 18. Net Elec. Energy Gen. (MWH)        -2446        -5470          100169266
: 19. Unit Service Factor                    0              0              58.2
: 20. Unit Availability Factor              0              0              58.2
: 21. Unit Capacity Factor (using MDC Net)                  0                0            52.5
: 22. Unit Capacity Factor (using DER Net)                  0                0            52.1
: 23. Unit Forced Outage Rate              100            100            27.0
: 24. Shutdowns scheduled over next 6 months (type, date and duration of each)
Steam Generator replacement.
: 25. If shutdown at end of Report Period, Estimated Date of startup:
Under review.
8-1-7.R2 1*
 
AVE~    DAILY UNIT POWER LEVEL   tt Docket No.:   50-272 Unit Name:     Salem #1 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 POWER REDUCTIONS REPORT MONTH February 1996                                             DOCKET NO.: _,s,,.,o..,.-3:.1...,1:.,,....---s**-
* UNIT NAME: _s,..a....l""em"-""#""'l_ __
DATE: . . ;0::.:2:,. .-. :. ;10::.. -. ;.9""'7_,. ,. .__
COMPLETED BY:     Robert.Phillips TELEPHONE:     609-339-2735 METHOD OF SHUTTING        LICENSE DURATION                      DOWN            EVENT          SYSTEM    COMPONENT             CAUSE AND CORRECTIVE ACTION NO.        DATE    TYPE 1 (HOURS)      REASON 2 REACTOR        REPORT #        CODE 4    CODE 6                   TO PREVENT RECURRENCE 4092    2-1-97    F          744          F.C            4              -----------      2422                    Steam Generator Replacement 1            2                                                        3                        4                                  5 F: Forced      Reason                                                  Method:                  Exhibit G
* Instructions           Exhibit 1
* Same S: Scheduled  A-Equipnent Failure (explain)                            1-Manual                for Preparation of Data           Source B-Maintenance or Test                                      2-Manual Scram          Entry Sheets for Licensee C-Refueling                                            3*Automatic Scram        Event Report CLER) File D-Requlatory Restriction                                  4-Continuation of        (NUREG*0161)
E-Operator Training & License Examination                    Previous Outage F-Adninistrative                                        S*Load Reduction G-Operational Error (Explain)                          9*0ther H-Other (Explain)
 
Refueling Information
* Docket No. 50-272 Month: February, 1997                                              Unit Name:   Salem 1.
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: To Be Determined 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: Not Determined to Date: X b. Has the reload fuel design been reviewed by the Station Operating Review committee?
Yes: No: Not Determined to Date: X
Yes: No: X If no, when is it scheduled?
: b. Has the reload fuel design been reviewed by the Station Operating Review committee?
To be Determined
Yes: No: X If no, when is it scheduled? To be Determined
: 4. Scheduled date (s) for submitting proposed licensing action: N/A 5. Important licensing considerations associated with refueling:
: 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: 0 b. In Spent Fuel Storage: 953 7. Present Licensed spent fuel storage capacity:
: a. lncore:                                                                 0
1632 Future spent fuel storage capacity:
: b. In Spent Fuel Storage:                                               953
1632 8. Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
: 7. Present Licensed spent fuel storage capacity:                         1632 Future spent fuel storage capacity:                                   1632
April 2012 I I I _ _J SALEM UNIT 1 SALEM GENERATING STATION MONTHLY OPERATING  
: 8. Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:                     April 2012 I
I I
__J
 
SALEM GENERATING STATION MONTHLY OPERATING  


==SUMMARY==
==SUMMARY==
-UNIT 1 FEBRUARY 1997 The unit is in a refueling and steam generator replacement outage and 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 1 FEBRUARY 1997 SALEM UNIT 1 The unit is in a refueling and steam generator replacement outage and 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 nit 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 nit 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.}}

Revision as of 09:26, 21 October 2019

Monthly Operating Rept for Feb 1997 for Salem,Unit 1. W/970311 Ltr
ML18102A928
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 9703240182
Download: ML18102A928 (8)
v • d • e


Text

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 SALEMNO. 1 DOCKET NO: 50-272 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.

(jjy;ms, ~~

David F.

General Manager -

Salem Operations Gare~

VS:pc Enclosures <:.; 'i .>"\!lll',..1q i"',!

/.., L V '--

i(\

C Mr. H.J. Miller Regional Administrator USNRC, Regionl 4 7 5 Allendale Road King of Prussia, PA 19046

-- -

9703240182 970228 PDR ADOCK 05000272 R PDR

,,..------

Illllll

  • lllll llll 9 7 llllll 111111111111111111111111111111111

~ & Iii 4 7 1 5

  • The pOtVer is in }Dllf hands.

95-2168 REV. 6/94

, 10CFR50.59 EVALUATIONS e e DOCKET NO: 50-272 MONTH: FEBRUARY 1997 NAME: UNITl 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. The Station Operations Review Committee has reviewed and concurs with these evaluations DESIGN CHANGE PACKAGE (No 50.59 S/E) lEA-1134 Pkg. This modification provides as-built documentation for the non-safety 1, Rev. 0 on addition of Station related portion of the station air in the auxiliary building, turbine building Air Valves 1SA549 and 1SA550 and in the clean facilities building.

in Auxiliary Building and Valves SORC: 97-022 1SA541 through 1SA548 50.59 S/E S97-026, lEA-1126, This DCP provides as-built documentation for valves 11 CN926 and Pkg. 1, Rev. 0 As-Built SGFP 12CN926. The valves provide for controlled manual blowdown of Suction Strainer Cleanout strainers at the suction of both Unit 1 SGFP's.

Valves, 11CN926 & 12CN926 SORC: 97-021 50.59 S/E S97-032, lEC-3486 This modification addresses concerns regarding the Alternate Shutdown Pkg. 2, Rev. 1OCFR50 Appendix Methodology at Salem in the event of a Control Room evacuation due to R alternate Shutdown fire in the Control Room, Relay Room, or ceiling area of the 460/230 Volt Methodology - Installation of Switchgear Room, which calls for the use of electrical wiring modifications Transfer Switches and jumpers.

SORC: 97-019 50.59 S/E S97-043, lEC-3495, In order to enhance system performance and eliminate high maintenance Rev. 2 on Steam Trap components, twenty seven steam traps (1MSE21through1MSE35 and Replacement Project 1MSE38 through 1MSE49) and associated bypass orifices (where presently installed), bypass valve(s), drain valves and isolation valves will be removed (except four isolation valves required by procedure for Steam Generator Tube Rupture) and are being replaced.

SORC: 97-025

. '

, lOCFRS0.59 EVALUATIONS e e DOCKET NO: 50-272 MONTH: FEBRUARY 1997 NAME: UNITl 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. The Station Operations Review Committee has reviewed and concurs with these evaluations DESIGN CHANGE PACKAGE 50.59 SIB S97-049, lEC-3620, This proposal will revise Section 5.6.4 and Figure 7.2-5 of the UFSAR to Pkg. 1, Rev. 0 on Letdown describe the new bypass circuitry of the low pressurizer level isolation Isolation Valve Bypass Key signal so that operator control of the letdown isolation valves is possible switch during steam generator tube rupture conditions.

SORC: 97-025 50.59 SIB S97-058, lEC-3648, This modification adds relays and additional Main Control Room SSPS Phase A and containment pushbuttons to both Train A and Train B to allow manual initiation of Ventilation Isolation Modification Containment Ventilation Isolation separately from Phase A Containment Isolation.

SORC: 97-028 PROCEDURE 50.59 SIB S97-023, TS1.SE- This procedure describes an "experimental" test which will demonstrate if SU.CC-0003(Q), Rev. O the CC system is capable of reaching pump run-out flow and also whether "Component Cooling Pump the CC pump and motor are capable of surviving at maximum pump flow.

Performance with 11CC16 & SORC: 97-017 12CC 16 Throttled" SAFETY EVALUATION 50.59 SIB S96-047, S.C.ZZ-ESE- This safety evaluation addresses separation of the free air cables installed in 0841 Rev. 1 Separation distance the Salem Relay Rooms.

of cables in free air installed in SORC: 96-099 Salem U/1 and U/2 relay rooms

---~~- -----

OPERATING DATA REPORT Docket No: 50-272 Date: 03/10/97 Completed by: Robert Phillips Telephone: 339-2735 Operating Status

1. Unit Name Salem No. 1 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+-=A=------------

This Month Year to Date Cumulative

11. Hours in Reporting Period 672 1416 172417
12. No. of Hrs. Rx. was Critical 0 0 104380.5
13. Reactor Reserve Shutdown Hrs. 0 0 0
14. Hours Generator On-Line 0 0 100388.3
15. Unit Reserve Shutdown Hours 0 0 0
16. Gross Thermal Energy Generated (MWH) 0 0 318062229
17. Gross Elec. Energy Generated (MWH) 0 0 105301000
18. Net Elec. Energy Gen. (MWH) -2446 -5470 100169266
19. Unit Service Factor 0 0 58.2
20. Unit Availability Factor 0 0 58.2
21. Unit Capacity Factor (using MDC Net) 0 0 52.5
22. Unit Capacity Factor (using DER Net) 0 0 52.1
23. Unit Forced Outage Rate 100 100 27.0
24. Shutdowns scheduled over next 6 months (type, date and duration of each)

Steam Generator replacement.

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

Under review.

8-1-7.R2 1*

AVE~ DAILY UNIT POWER LEVEL tt Docket No.: 50-272 Unit Name: Salem #1 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 POWER REDUCTIONS REPORT MONTH February 1996 DOCKET NO.: _,s,,.,o..,.-3:.1...,1:.,,....---s**-

  • UNIT NAME: _s,..a....l""em"-""#""'l_ __

DATE: . . ;0::.:2:,. .-. :. ;10::.. -. ;.9""'7_,. ,. .__

COMPLETED BY: Robert.Phillips TELEPHONE: 609-339-2735 METHOD OF SHUTTING LICENSE DURATION DOWN EVENT SYSTEM COMPONENT CAUSE AND CORRECTIVE ACTION NO. DATE TYPE 1 (HOURS) REASON 2 REACTOR REPORT # CODE 4 CODE 6 TO PREVENT RECURRENCE 4092 2-1-97 F 744 F.C 4 ----------- 2422 Steam Generator Replacement 1 2 3 4 5 F: Forced Reason Method: Exhibit G

  • Instructions Exhibit 1
  • Same S: Scheduled A-Equipnent Failure (explain) 1-Manual for Preparation of Data Source B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3*Automatic Scram Event Report CLER) File D-Requlatory Restriction 4-Continuation of (NUREG*0161)

E-Operator Training & License Examination Previous Outage F-Adninistrative S*Load Reduction G-Operational Error (Explain) 9*0ther H-Other (Explain)

Refueling Information

  • Docket No. 50-272 Month: February, 1997 Unit Name: Salem 1.

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: To Be Determined Scheduled date for restart following refueling: To Be Determined
3. a. Will Technical Specification changes or other license amendments be required?

Yes: No: Not Determined to Date: X

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

Yes: No: X If no, when is it scheduled? To be Determined

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: 0
b. In Spent Fuel Storage: 953
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: April 2012 I

I I

__J

SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT 1 FEBRUARY 1997 SALEM UNIT 1 The unit is in a refueling and steam generator replacement outage and 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 nit 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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