ML18102B400: Difference between revisions

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=Text=
=Text=
{{#Wiki_filter:"*I .* *' *  
{{#Wiki_filter:"*I
* 'Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit 'JU_N 1 3. 1997 LR-N970381 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn: Document Control Desk MONTHLY OPERATING REPORT SALEM UNIT NO. 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 May, 1997, is attached.
.*
RAR:tcp Enclosures C Mr. H. J. Miller Sincerely Wr: David F. archow General Manager -Salem Operations Regional Administrator USNRC, Region 1 475 Allendale Road King of Prussia, PA 19046 1 ,_ -----cn-062sooa2 970531 -----------\ I PDR ADOCK 05000272 I I R' PDR ,----
      *'
The power is in your hands. I If llll lllll llll{l/lll lllll lllll Jiii if ii I 95-2168 REV. 6/94
OPS~G                        *
-* *
            'Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236
* DOCKET NO.: UNIT: DATE: COMPLETED BY: TELEPHONE:
* Nuclear Business Unit
50-272 Salem 1 06/13/97 R. Ritzman (609) 339-1445  
                                                                    'JU_N 1 3. 1997 LR-N970381 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn:       Document Control Desk MONTHLY OPERATING REPORT SALEM UNIT NO. 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 May, 1997, is attached.
Sincerely Wr:
David F. archow General Manager -
I Salem Operations RAR:tcp Enclosures C       Mr. H. J. Miller Regional Administrator USNRC, Region 1 475 Allendale Road King of Prussia, PA 19046 1,_ - ----cn-062sooa2 970531 -- ----- ----\
I         PDR ADOCK 05000272                             I I         R'                       PDR
                                                      ,--  -    -    --~-------
IIfllll lllll llll{l/lll lllll lllllJiii ifii The power is in your hands.
95-2168 REV. 6/94
 
-*                     *
* DOCKET NO.: 50-272 UNIT: Salem 1 DATE: 06/13/97 COMPLETED BY: R. Ritzman TELEPHONE: (609) 339-1445


==SUMMARY==
==SUMMARY==
OF CHANGES, TESTS, AND EXPERIMENTS FOR THE SALEM GENERATING STATION MONTH MAY 1997 The following items completed during May 1997 have been evaluated to determine:
OF CHANGES, TESTS, AND EXPERIMENTS FOR THE SALEM GENERATING STATION MONTH     MAY 1997 The following items completed during May 1997 have been evaluated to determine:
: 1. If the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report may be increased; or 2. If a possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report may be created; or 3. If the margin of safety as defined in the basis for any technical specification is reduced. The 10CFR50.59 Safety Evaluations showed that these items did not create a new safety hazard to the plant nor did they affect the safe shutdown of the reactor. These items did not change the plant effluent releases and did not alter the existing environmental impact. The 10CFR50.59 Safety Evaluations determined that no unreviewed safety or environmental questions are involved.
: 1. If the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report may be increased; or
Design Changes Summary of Safety Evaluations There were no changes in this category implemented during May, 1997. Temporary Modifications Summary of Safety Evaluations There were no changes in this category implemented during May, 1997. Procedures Summary of Safety Evaluations NC.NA-AP.ZZ-003S(Q), Rev. 7, Nuclear Licensing and Reporting.
: 2. If a possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report may be created; or
This procedure revision deletes the attachment that detailed the description of the station reporting requirements and served as a reference for the station staff to indicate which reports are required by federal, state,
: 3. If the margin of safety as defined in the basis for any technical specification is reduced.
.* .-*
The 10CFR50.59 Safety Evaluations showed that these items did not create a new safety hazard to the plant nor did they affect the safe shutdown of the reactor. These items did not change the plant effluent releases and did not alter the existing environmental impact. The 10CFR50.59 Safety Evaluations determined that no unreviewed safety or environmental questions are involved.
* and local agencies.
Design Changes       Summary of Safety Evaluations There were no changes in this category implemented during May, 1997.
The text of the procedure continues to provide sufficient guidelines for the preparation, review, and submittal of correspondence to the NRC. This is an administrative change only. The pertinent information previously contained in the attachment will be maintained elsewhere.
Temporary Modifications     Summary of Safety Evaluations There were no changes in this category implemented during May, 1997.
Therefore, this procedure revision does not increase the probability or consequences of an accident previously described in the UFSAR and does not involve an Unreviewed Safety Question.
Procedures   Summary of Safety Evaluations NC.NA-AP.ZZ-003S(Q), Rev. 7, Nuclear Licensing and Reporting. This procedure revision deletes the attachment that detailed the description of the station reporting requirements and served as a reference for the station staff to indicate which reports are required by federal, state,
TSl.OP-IO.ZZ-OOll(Q), Rev. 1, Control Room Operability with Unit 1 Defueled.
 
This procedure provides instructions necessary to verify that all required systems and equipment are available (or operable) to ensure the Unit 1 Control Room Emergency Air Conditioning System (CREACS) remains operable to support an operable Control Room Envelope.
.*.-                   *
System alignments and Surveillance Requirements are specified to ensure all systems required to support Unit 1 CREACS operability are available or operable.
* and local agencies. The text of the procedure continues to provide sufficient guidelines for the preparation, review, and submittal of correspondence to the NRC.
This revision allows the use of backup battery chargers to provide increased flexibility.
This is an administrative change only. The pertinent information previously contained in the attachment will be maintained elsewhere. Therefore, this procedure revision does not increase the probability or consequences of an accident previously described in the UFSAR and does not involve an Unreviewed Safety Question.
This revision also identifies additional required operator actions if a Unit 2 CREACS actuation occurs concurrent with a lB 230V Vital Bus failure while in certain specific plant configurations.
TSl.OP-IO.ZZ-OOll(Q), Rev. 1, Control Room Operability with Unit 1 Defueled. This procedure provides instructions necessary to verify that all required systems and equipment are available (or operable) to ensure the Unit 1 Control Room Emergency Air Conditioning System (CREACS) remains operable to support an operable Control Room Envelope.
All electrical alignments specified by this procedure are bounded by Technical Specifications, approved calculations, engineering evaluations, operability determinations, and operating procedures.
System alignments and Surveillance Requirements are specified to ensure all systems required to support Unit 1 CREACS operability are available or operable. This revision allows the use of backup battery chargers to provide increased flexibility. This revision also identifies additional required operator actions if a Unit 2 CREACS actuation occurs concurrent with a lB 230V Vital Bus failure while in certain specific plant configurations.
Therefore, this procedure revision does not increase the probability or consequences of an accident previously described in the UFSAR and does not involve an Unreviewed Safety Question.
All electrical alignments specified by this procedure are bounded by Technical Specifications, approved calculations, engineering evaluations, operability determinations, and operating procedures. Therefore, this procedure revision does not increase the probability or consequences of an accident previously described in the UFSAR and does not involve an Unreviewed Safety Question.
UFSAR Change Notices Summary of Safety Evaluations There were no changes in this category implemented during May, 1997. Deficiency Reports Summary of Safety Evaluations There were no changes in this category implemented during May, 1997.
UFSAR Change Notices     Summary of Safety Evaluations There were no changes in this category implemented during May, 1997.
-* Other *
Deficiency Reports     Summary of Safety Evaluations There were no changes in this category implemented during May, 1997.
* Summary of Safety Evaluation There were no changes in this category implemented during May, 1997.
 
*" .. *
-*
* OPERATING DATA REPORT CORRECTION Completed by: Robert Phillips Operating Status 1. Unit Name Salem No. 1 2. Reporting Period March 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 Report, Give Reason NA
Other
* Docket No: Date: Telephone:
* Summary of Safety Evaluation
Notes through 7) 9. Power Level to Which Restricted, if any (Net MWe) 10. Reasons for Restrictions, if any 11. Hours in Reporting Period 12. No. of Hrs. Rx. was Critical 13. Reactor Reserve Shutdown Hrs. 14. Hocirs 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 NA This Month Year to Date 744 2160 0 0 0 0 0 d 0 0 0 0 0 0 -2987 -8457 0 0 0 0 0 0 0 0 100 100 50-272 04/10/97 339-2735 since Last N/A Cumulative 176565 104380.5 0 100388.3 0 318062229 105301000 100166279 57.5 57.5 51. 8 51. 5 28.1 24. Shutdowns scheduled over next 6 months (type, date and duration of each) Steam Generator replacement.
* There were no changes in this category implemented during May, 1997.
: 25. If shutdown at end of Report Period, Estimated Date of startup: Under review. 8-1-7.R2
 
* OPERATING DATA REPORT CORRECTION Completed by: Robert Phillips Operating Status 1. Unit Name Salem No. 1 2. Reporting Period A:gril 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 Report, Give Reason NA
*"
* Docket No: 50-272 Date: 05/10/97 Telephone:
      ..*
339-2735 Notes through 7) since Last 9. Power Level to Which Restricted, if any {Net MWe) N/A 10. Reasons for Restrictions, if any
* OPERATING DATA REPORT CORRECTION
: 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
* Docket No:
{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 24. Shutdowns scheduled over next 6 Steam Generator replacement.
Date:
This Month 719 0 0 0 0 0 0 -3021 0 0 0 0 100 months {type, Year to Date Cumulative 2879 0 0 0 0 0 -11478 0 0 0 0 100 date and 177284 104380.5 0 100388.5 0 318062229 10530100 100163258 56.5 56.5 51. 0 50.6 29.6 duration of each) 25. If shutdown at end of Report Period, Estimated Date of Startup: Under review. 8-l-7.R2 
50-272 04/10/97 Completed by:       Robert Phillips                 Telephone:    339-2735 Operating Status
*
: 1. Unit Name                         Salem No. 1   Notes
* OPERATING DATA REPORT .. Docket No: 50-272 Date: 06/10/97 Completed by: Robert Phillips Telephone:
: 2. Reporting Period             March       1997
339-2735 Operating Status 1. Unit Name Salem No. 1 Notes 2. Reporting Period May 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 NA This Month Year*to Date Cumulative
: 3. Licensed Thermal Power (MWt)             3411
: 11. Hours in Reporting Period 744 3623 181079 12. No. of Hrs. Rx. was Critical 0 0 104380.45
: 4. Nameplate Rating (Gross MWe)             1170
: 13. Reactor Reserve Shutdow'n Hrs. *O 0 0 14. Hours Generator On-Line 0 0 100338.27
: 5. Design Electrical Rating (Net MWe)       1115
: 15. Unit Reserve Shutdown Hours 0 0 0 16. Gross Thermal Energy Generated (MWH) 0 0 318062229
: 6. Maximum Dependable Capacity(Gross MWe) 1149
: 17. Gross Elec. Energy Generated (MWH) 0 0 10530100 18. Net Elec. Energy Gen. (MWH) -2379 -13857 100160879
: 7. Maximum Dependable Capacity (Net MWe)     1106
: 19. Unit Service Factor 0 0 55.4 20. Unit Availability Factor 0 0 55.4 21. Unit Capacity Factor (using MDC Net) 0 0 50.0 22. Unit Capacity Factor (using DER Net) 0 0 49.6 23. Unit Forced Outage Rate 100 100 31.3 24. Shutdowns scheduled over next 6 months (type, date and duration of each) steam Generator re2lacement.
: 8. If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason       NA
: 25. If shutdown at end of Report Period, Estimated Date of Startup: Under review. 8-l-7.R2 L  
: 9. Power Level to Which Restricted, if any (Net MWe)           N/A
: 10. Reasons for Restrictions, if any                   NA This Month  Year to Date    Cumulative
: 11. Hours in Reporting Period           744          2160          176565
: 12. No. of Hrs. Rx. was Critical           0              0          104380.5
: 13. Reactor Reserve Shutdown Hrs.         0              0              0
: 14. Hocirs Generator On-Line               0              d          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)         -2987        -8457          100166279
: 19. Unit Service Factor                   0              0              57.5
: 20. Unit Availability Factor               0              0              57.5
: 21. Unit Capacity Factor (using MDC Net)                   0                0            51. 8
: 22. Unit Capacity Factor (using DER Net)                   0                0            51. 5
: 23. Unit Forced Outage Rate                 100            100            28.1
: 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
* OPERATING DATA REPORT CORRECTION
* Docket No:
Date:
50-272 05/10/97 Completed by:      Robert Phillips                  Telephone:    339-2735 Operating Status
: 1. Unit Name                          Salem No. 1     Notes
: 2. Reporting Period               A:gril      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             719          2879          177284
: 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                        100388.5
: 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          10530100
: 18. Net Elec. Energy Gen. {MWH)           -3021        -11478        100163258
: 19. Unit Service Factor                     0              0              56.5
: 20. Unit Availability Factor                 0              0              56.5
: 21. Unit Capacity Factor
{using MDC Net)                     0                0            51. 0
: 22. Unit Capacity Factor
{using DER Net)                     0                0            50.6
: 23. Unit Forced Outage Rate               100            100            29.6
: 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-l-7.R2
 
..
* OPERATING DATA REPORT
* Docket No:
Date:
50-272 06/10/97 Completed by:    Robert Phillips                  Telephone:    339-2735 Operating Status
: 1. Unit Name                          Salem No. 1    Notes
: 2. Reporting Period              May        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                  NA This Month  Year*to Date    Cumulative
: 11. Hours in Reporting Period              744        3623          181079
: 12. No. of Hrs. Rx. was Critical            0            0          104380.45
: 13. Reactor Reserve Shutdow'n Hrs.         *O             0             0
: 14. Hours Generator On-Line                 0             0         100338.27
: 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         10530100
: 18. Net Elec. Energy Gen. (MWH)         -2379       -13857         100160879
: 19. Unit Service Factor                     0             0             55.4
: 20. Unit Availability Factor                 0             0             55.4
: 21. Unit Capacity Factor (using MDC Net)                     0               0           50.0
: 22. Unit Capacity Factor (using DER Net)                     0               0           49.6
: 23. Unit Forced Outage Rate               100           100             31.3
: 24. Shutdowns scheduled over next 6 months (type, date and duration of each) steam Generator re2lacement.
: 25. If shutdown at end of Report Period, Estimated Date of Startup:
Under review.
8-l-7.R2
 
AVERA~AILY UNIT POWER LEVEL
* Docket No.:    50-272 Unit Name:    Salem #l Date:          06/10/97 completed by:    Robert Phillips                Telephone:    339-2735 Month        May        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            0 14            0                          30            0 15            0                          31            0 16            0 P. 8.1-7 Rl
 
                                                                                                                                                                  ..'.
                                                                                                                                                                      \
UNIT SHUTDOWN AND POWER REDUCTIONS                                                                        . l REPORT MONTH May          1997                                          DOCKET NO. 50-272 UNIT NAME    Salem #1 DATE  06/10/97 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 5                    TO PREVENT RECURRENCE 3859    5-1-97    F          744          F,C            4              -----------      zz        zzzz            Steam Generator Replacement
                                            -
1              2                                                        3                          4                                  5 F:  Forced    Reason                                                  Method:                    Exhibit G - Instructions          Exhibit 1 - Same S: Scheduled  A-Equipment Failure (explain)                            1-Manual                  for Preparation of Data            Source 2-Manual Scram            Entry Sheets for Licensee
* B-Maintenance or Test C-Refuel ing                                              3-Automatic Scram          Event Report CLER) File D-Requlatory Restriction                                  4-Continuation of          (NUREG-0161)
E-Operator Training & License Examination                    Previous outage F-Administrative                                          5-Load Reduction G-Operational Error (Explain)                            9-0ther H-Other (Explain)


UNIT POWER LEVEL
.
* Docket No.: 50-272 Unit Name: Salem #l Date: 06/10/97 completed by: Robert Phillips Telephone:
.-
339-2735 Month May 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 0 14 0 30 0 15 0 31 0 16 0 P. 8.1-7 Rl NO. DATE 3859 5-1-97 F 1 2 F: Forced S: Scheduled DURATION TYPE 1 (HOURS) REASON 2 744 F,C -Reason A-Equipment Failure (explain)
.*
B-Maintenance or Test C-Refuel ing D-Requlatory Restriction 4 UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH May 1997 METHOD OF SHUTTING DOWN REACTOR '-LICENSE EVENT REPORT # -----------
  ,
zz 3 Method: 1-Manual 2-Manual Scram SYSTEM CODE 4 E-Operator Training & License Examination F-Administrative 3-Automatic Scram 4-Continuation of Previous outage 5-Load Reduction 9-0ther G-Operational Error (Explain)
Refueling Information Month: May, 1997
H-Other (Explain)
                            *
COMPONENT CODE 5 DOCKET NO. UNIT NAME DATE COMPLETED BY TELEPHONE 50-272 Salem #1 06/10/97 .. \ '. Robert Phillips 609-339-2735 CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE zzzz Steam Generator Replacement 4 Exhibit G -Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File (NUREG-0161) 5 Exhibit 1 -Same Source . l *
* Docket No.
. , .* .-Refueling Information Month: May, 1997 Month: May, 1997 *
Unit Name:
* Docket No. Unit Name: Contact: Telephone:
50-272 Salem 1 Contact:  D.Tisdel Telephone: 609-339-1538 Month:    May, 1997
50-272 Salem 1 D.Tisdel 609-339-1538
: 1. Refueling information has changed from last month: Yes:   No: X
: 1. Refueling information has changed from last month: Yes: No: X 2. Scheduled date for next refueling:
: 2. Scheduled date for next refueling:   To Be Determined Scheduled date for restart following refueling: To Be Determined
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: X No: Not Determined to Date: b. Has the reload fuel design been reviewed by the Station Operating Review Committee?
Yes: X No: Not Determined to Date:
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: To be Determined
: 4. Scheduled date (s) for submitting proposed licensing action: To be Determined
: 5. Important licensing considerations associated with refueling:
: 5. Important licensing considerations associated with refueling:
: 6. Number of Fuel Assemblies:
: 6. Number of Fuel Assemblies:
: a. Incore: 0 b. In Spent Fuel Storage: 953 7. Present Licensed spent fuel storage capacity:
: a. Incore:                                                 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
: 8. Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:         April 2012
* SALEM GENERATING STATION MONTHLY OPERATING  
* SALEM GENERATING STATION MONTHLY OPERATING  


==SUMMARY==
==SUMMARY==
  -UNIT 1 MAY 1997 SALEM UNIT 1
  - UNIT 1
* The unit is ln 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:
* MAY 1997 SALEM UNIT 1 The unit is ln 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 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.}}

Revision as of 09:20, 21 October 2019

Monthly Operating Rept for May 1997 for Salem Unit 1. W/970613 Ltr
ML18102B400
Person / Time
Site: Salem PSEG icon.png
Issue date: 05/31/1997
From: Garchow D, Ritzman R
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LR-N970381, NUDOCS 9706250082
Download: ML18102B400 (11)
v • d • e


Text

"*I

.*

  • '

OPS~G *

'Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236

  • Nuclear Business Unit

'JU_N 1 3. 1997 LR-N970381 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn: Document Control Desk MONTHLY OPERATING REPORT SALEM UNIT NO. 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 May, 1997, is attached.

Sincerely Wr:

David F. archow General Manager -

I Salem Operations RAR:tcp Enclosures C Mr. H. J. Miller Regional Administrator USNRC, Region 1 475 Allendale Road King of Prussia, PA 19046 1,_ - ----cn-062sooa2 970531 -- ----- ----\

I PDR ADOCK 05000272 I I R' PDR

,-- - - --~-------

IIfllll lllll llll{l/lll lllll lllllJiii ifii The power is in your hands.

95-2168 REV. 6/94

-* *

  • DOCKET NO.: 50-272 UNIT: Salem 1 DATE: 06/13/97 COMPLETED BY: R. Ritzman TELEPHONE: (609) 339-1445

SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS FOR THE SALEM GENERATING STATION MONTH MAY 1997 The following items completed during May 1997 have been evaluated to determine:

1. If the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report may be increased; or
2. If a possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report may be created; or
3. If the margin of safety as defined in the basis for any technical specification is reduced.

The 10CFR50.59 Safety Evaluations showed that these items did not create a new safety hazard to the plant nor did they affect the safe shutdown of the reactor. These items did not change the plant effluent releases and did not alter the existing environmental impact. The 10CFR50.59 Safety Evaluations determined that no unreviewed safety or environmental questions are involved.

Design Changes Summary of Safety Evaluations There were no changes in this category implemented during May, 1997.

Temporary Modifications Summary of Safety Evaluations There were no changes in this category implemented during May, 1997.

Procedures Summary of Safety Evaluations NC.NA-AP.ZZ-003S(Q), Rev. 7, Nuclear Licensing and Reporting. This procedure revision deletes the attachment that detailed the description of the station reporting requirements and served as a reference for the station staff to indicate which reports are required by federal, state,

.*.- *

  • and local agencies. The text of the procedure continues to provide sufficient guidelines for the preparation, review, and submittal of correspondence to the NRC.

This is an administrative change only. The pertinent information previously contained in the attachment will be maintained elsewhere. Therefore, this procedure revision does not increase the probability or consequences of an accident previously described in the UFSAR and does not involve an Unreviewed Safety Question.

TSl.OP-IO.ZZ-OOll(Q), Rev. 1, Control Room Operability with Unit 1 Defueled. This procedure provides instructions necessary to verify that all required systems and equipment are available (or operable) to ensure the Unit 1 Control Room Emergency Air Conditioning System (CREACS) remains operable to support an operable Control Room Envelope.

System alignments and Surveillance Requirements are specified to ensure all systems required to support Unit 1 CREACS operability are available or operable. This revision allows the use of backup battery chargers to provide increased flexibility. This revision also identifies additional required operator actions if a Unit 2 CREACS actuation occurs concurrent with a lB 230V Vital Bus failure while in certain specific plant configurations.

All electrical alignments specified by this procedure are bounded by Technical Specifications, approved calculations, engineering evaluations, operability determinations, and operating procedures. Therefore, this procedure revision does not increase the probability or consequences of an accident previously described in the UFSAR and does not involve an Unreviewed Safety Question.

UFSAR Change Notices Summary of Safety Evaluations There were no changes in this category implemented during May, 1997.

Deficiency Reports Summary of Safety Evaluations There were no changes in this category implemented during May, 1997.

-*

Other

  • Summary of Safety Evaluation
  • There were no changes in this category implemented during May, 1997.
  • "

..*

  • OPERATING DATA REPORT CORRECTION
  • Docket No:

Date:

50-272 04/10/97 Completed by: Robert Phillips Telephone: 339-2735 Operating Status

1. Unit Name Salem No. 1 Notes
2. Reporting Period March 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 NA This Month Year to Date Cumulative
11. Hours in Reporting Period 744 2160 176565
12. No. of Hrs. Rx. was Critical 0 0 104380.5
13. Reactor Reserve Shutdown Hrs. 0 0 0
14. Hocirs Generator On-Line 0 d 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) -2987 -8457 100166279
19. Unit Service Factor 0 0 57.5
20. Unit Availability Factor 0 0 57.5
21. Unit Capacity Factor (using MDC Net) 0 0 51. 8
22. Unit Capacity Factor (using DER Net) 0 0 51. 5
23. Unit Forced Outage Rate 100 100 28.1
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

  • OPERATING DATA REPORT CORRECTION
  • Docket No:

Date:

50-272 05/10/97 Completed by: Robert Phillips Telephone: 339-2735 Operating Status

1. Unit Name Salem No. 1 Notes
2. Reporting Period A:gril 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 719 2879 177284
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 100388.5
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 10530100
18. Net Elec. Energy Gen. {MWH) -3021 -11478 100163258
19. Unit Service Factor 0 0 56.5
20. Unit Availability Factor 0 0 56.5
21. Unit Capacity Factor

{using MDC Net) 0 0 51. 0

22. Unit Capacity Factor

{using DER Net) 0 0 50.6

23. Unit Forced Outage Rate 100 100 29.6
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-l-7.R2

..

  • OPERATING DATA REPORT
  • Docket No:

Date:

50-272 06/10/97 Completed by: Robert Phillips Telephone: 339-2735 Operating Status

1. Unit Name Salem No. 1 Notes
2. Reporting Period May 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 NA This Month Year*to Date Cumulative
11. Hours in Reporting Period 744 3623 181079
12. No. of Hrs. Rx. was Critical 0 0 104380.45
13. Reactor Reserve Shutdow'n Hrs. *O 0 0
14. Hours Generator On-Line 0 0 100338.27
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 10530100
18. Net Elec. Energy Gen. (MWH) -2379 -13857 100160879
19. Unit Service Factor 0 0 55.4
20. Unit Availability Factor 0 0 55.4
21. Unit Capacity Factor (using MDC Net) 0 0 50.0
22. Unit Capacity Factor (using DER Net) 0 0 49.6
23. Unit Forced Outage Rate 100 100 31.3
24. Shutdowns scheduled over next 6 months (type, date and duration of each) steam Generator re2lacement.
25. If shutdown at end of Report Period, Estimated Date of Startup:

Under review.

8-l-7.R2

AVERA~AILY UNIT POWER LEVEL

  • Docket No.: 50-272 Unit Name: Salem #l Date: 06/10/97 completed by: Robert Phillips Telephone: 339-2735 Month May 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 0 14 0 30 0 15 0 31 0 16 0 P. 8.1-7 Rl

..'.

\

UNIT SHUTDOWN AND POWER REDUCTIONS . l REPORT MONTH May 1997 DOCKET NO. 50-272 UNIT NAME Salem #1 DATE 06/10/97 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 5 TO PREVENT RECURRENCE 3859 5-1-97 F 744 F,C 4 ----------- zz zzzz Steam Generator Replacement

-

1 2 3 4 5 F: Forced Reason Method: Exhibit G - Instructions Exhibit 1 - Same S: Scheduled A-Equipment Failure (explain) 1-Manual for Preparation of Data Source 2-Manual Scram Entry Sheets for Licensee

  • B-Maintenance or Test C-Refuel ing 3-Automatic Scram Event Report CLER) File D-Requlatory Restriction 4-Continuation of (NUREG-0161)

E-Operator Training & License Examination Previous outage F-Administrative 5-Load Reduction G-Operational Error (Explain) 9-0ther H-Other (Explain)

.

.-

.*

,

Refueling Information Month: May, 1997

  • Docket No.

Unit Name:

50-272 Salem 1 Contact: D.Tisdel Telephone: 609-339-1538 Month: May, 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: X No: Not Determined to Date:

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: To be Determined
5. Important licensing considerations associated with refueling:
6. Number of Fuel Assemblies:
a. Incore: 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
  • SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT 1

  • MAY 1997 SALEM UNIT 1 The unit is ln 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 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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