ML18102B307

Monthly Operating Rept for Apr 1997 for Salem Generating Station,Unit 1.W/970515 Ltr

ML18102B307
Person / Time
Site:	Salem
Issue date:	04/30/1997
From:	Garchow D, Ritzman R Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9705220281
Download: ML18102B307 (9)

Text

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• Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit MAY 15 7997 LR-N970310 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 April, 1997, is attached.

David F. Garchow General Manager -

Salem Operations

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I RAR:tcp Enclosures c Mr. H. J. Miller Regional Administrator USNRC, Region 1 475 Allendale Road King of Prussia, PA 19046

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DOCKET NO.: 50-272 UNIT: Salem 1 DATE: 05/15/97 COMPLETED BY: R. Ritzman TELEPHONE: (609) 339-1445

SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS FOR THE SALEM GENERATING STATION MONTH APRIL 1997 The following items completed during April 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 April, 1997.

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

Procedures Summary of Safety Evaluations SC.CH-SA.WD-0244(Q), Rev. 18, Plant Vent Sampling. This procedure revision provides a temporary, auxiliary continuous sampling method to meet Technical Specification requirements. This method of meeting these Technical Specification requirements is being used while the normal

I' method is unavailable to support outage activities. This procedure is only intended to be used while the 1R45 sample shed is out of service. This temporary sampling method maintains the ability to continuously sample for radioactive particulate and iodine releases.

Therefore, this design change 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 CN 97-039, Nuclear Business Unit (NBU) Organization Change.

This CN shifts, clarifies, and consolidates responsibilities for NBU organizations, revises the succession of authority and responsibility for Salem station operations, establishes new positions, and corrects editorial errors. The changes provide better control over NBU activities, and do not involve any reduction in the qualifications or training requirements, technical support, management control, commitments, or the quality assurance program.

Therefore, this CN dqes not inc~e~se the probability or consequences of an accident previously described in the UFSAR and does not involve an Unreviewed Safety Question.

CN 97-044, Nuclear Engineering Consolidation. This CN reorganizes the functions within the Nuclear Engineering Department. The description of the entire Nuclear Engineering Department function is now consolidated under the control of the Senior Vice President - Nuclear Engineering. This provides flexibility in transferring responsibilities between direct reports to the Senior Vice President - Nuclear Engineering.

Therefore, this CN does not increase the probability or consequences of an accident previously described in the UFSAR and does not involve an Unreviewed Safety Question.

CN 97-056, Residual Heat Removal Pumps Net Positive Suction Head in Recirculation Modes. This CN clarifies the Net Positive Suction Head (NPSH) design basis for the Residual Heat Removal (RHR) pumps in the post-LOCA recirculation mode. The design basis for RHR pump NPSH in the recirculation mode of operation* is to ensure that adequate NPSH exists to meet the NPSH required for the maximum postulated flows. A new design basis calculation was completed. The calculation evaluated the suction piping pressure drop; and as a result, the design basis has been

updated.

Required.

The NPSH Available continues to exceed the NPSH Therefore, this CN does not increase the probability or consequences of an accident previously described in the UFSAR and does not involve an Unreviewed Safety Question.

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

Other Summary of Safety Evaluation S-C-ZZ-ESE-0841, Rev 2, Safety Evaluation for Separation Distance of Cables in Free Air Installed in Salem Unit 1 and Unit 2 Limited Hazard Areas. This evaluation clarifies the free air separation distance criteria for the Salem Generating Station Limited Hazard Areas. The separation criteria is based on industry testing that was used as the technical basis for the 1992 revision of IEEE 384. IEEE 384-1992 indicates that the specified separation criteria for open to open configurations will establish independence of lE equipment and circuits. Open to open configurations applicable to Salem are free air cable to free air cable and free air cable to open cable trays. This safety evaluation provides additional information and does not result in a reduction in the margin of safety. Compliance with IEEE 384-1992 ensures that faults will not propagate to adjacent cables nor cause a loss of redundant functions.

Therefore, this safety evaluation does not increase the probability or consequences of an accident previously described in the UFSAR and does not involve an Unreviewed Safety Question.

• OPERATING DATA REPORT

• Docket No: 50-272 Date: 05/10/97 Completed by: Robert Phillips Telephone: 339-2735 Operating Status

1. Unit Name Salem No. 1 Notes

2. Reporting Period April 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.~~~~N'-!-L.cA"-"'--~~~~~~~~~~~~~~~~~~~~~~~

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 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 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 -10937 100157788

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.

8-1-7.R2

- I AVE~ DAILY UNIT POWER LEVEL

• Docket No.: 50-2 72 Unit Name: Salem #1 Date: 05/10/97 Completed by: Robert Phillips Telephone: 339-2735 Month April 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 REPORT MONTH April 1997 DOCKET NO. 50-272 UNIT NAME Salem #1 DATE 05/10/97 .

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 4-1-97 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 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-Administrative 5-Load Reduction G-Operational Error (Explain) 9-0ther H-Other (Explain)

"" ~ \ I Refueling Information Month: April, 1997 Docket No.

Unit Name:

50-272 Salem 1

Contact:

D.Tisdel Telephone: 609-339-1538 Month: April, 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

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SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT 1 APRIL 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 unit to operate in a safe, event free manner.

• After the restart review, meet with the NRC and communicate the results of that review.