ML18102B400

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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


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'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

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

95-2168 REV. 6/94

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  • 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,

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  • 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.

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Other

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

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  • 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.

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  • 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.

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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

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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

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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

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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)

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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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