ML18102A391

Monthly Operating Rept for Aug 1996 for Salem Unit 1. W/960911 Ltr

ML18102A391
Person / Time
Site:	Salem
Issue date:	08/31/1996
From:	Garchow D, Heller R, Phillips R Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9609180394
Download: ML18102A391 (8)

Text

PS~G *

• Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nucl(;?ar Business Unit September 11, 1996 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 copy of the monthly operating report for the month of August is being sent to you. .

Sincerely yours, ,

QJrµJ David F. Garchow General Manager -

Salem Operations 1*

RH:vls Enclosures c* Mr. H.J. Miller Regional Administrator USNRC, Region I 475 Allendale Road King of Prussia, PA 19046

(~-~~~~~~~~-

/ .9609180394 960831 t PDR. ADOCK 05000272 R PDR The power is in your hands.

95-2168 REV. 6/94

AVE~ DAILY UNIT POWER LEVEL tit Docket No.: 50-272 Unit Name: Salem #1 Date: 09/10/96 Completed by: Robert Phillips Telephone: 339-2735 Month August 1996 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

OPERATING DATA REPORT Docket No: 50-272 Date: 09/10/96 Completed by: Robert Phillips Telephone: 339-2735 Operating Status

1. Unit Name Salem No. 1 Notes

2. Reporting Period August 1996

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.~~~~N0-.1--=A-=-~~~~~~~~~~~~~~~~~~~~~-

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

12. Hours in Reporting Period 744 5855 168072

12. No. of Hrs. Rx. was Critical 0 0 104380.45

13. Reactor Reserve Shutdown Hrs. 0 0 0

14. Hours Generator on-Line 0 0 100388.27

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 0 0 0

17. Gross Elec. Energy Generated (MWH) 0 0 105301000

18. Net Elec. Energy Gen. (MWH) -2440 -18661 100186252

19. Unit Service Factor 0 0 59.7

20. Unit Availability Factor 0 0 59.7

21. Unit Capacity Factor (using MDC Net) 0 0 53.8

22. Unit Capacity Factor (using DER Net) 0 0 53.5

23. Unit Forced Outage Rate 100 100 24.6

24. Shutdowns scheduled over next 6 months (type, date and duration of each)

Refueling extension.

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

Under review.

8-1-7.R2

UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH August 1996 DOCKET NO. 50-272 UNIT NAME Salem #1*

DATE 09/10/96 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 4092 8/01/96 F 744 FC 4 ---------- HJ 2422 Nuclear Steam Generator Systems.

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-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)

10CFR50.59 EVALUATIONS DOCKET NO: 50-272 MONTH: AUGUST 1996 UNIT NAME: SALEM 1 CONTACT: R.HELLER TELEPHONE: 609-339-5162 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.

1. Temporary Modifications (TMODs)96-026 "Chilled Water Supply to Containment Fan Cooler Units for Containment Cooling" Rev. 0 - This TMOD provides chilled water as an independent closed-loop to two of three containment fan cooler units, and uses the fan cooler units to lower the containment temperature for personnel comfort when accomplishing tasks associated with the Salem Unit 1 steam generator replacement project. Use of the TMOD does not result in deviation from the acceptance criteria, nor does it require a change to the Technical Specifications. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 96-108)

2. Evaluations TS2.0P-SO.ABV-000l(Q) "Modified Auxiliary Building Ventilation Operation -

IOCFRS0.59 Evaluation" Rev. 2 - This safety evaluation justifies an interim Auxiliary Building Ventilation operating configuration that establishes ventilation air movement between the Salem Unit 1 and 2 Auxiliary Buildings by blocking "open" interfacing doors between the units. The proposed temporary alignment will only be used when Salem Units 1 and 2 are defueled. There is no reduction in the margin of safety as defined in the basis for any Technical Specification.

(SORC 96-107)

Emergency Plan Section 9 "Emergency Operations Facility Generator Replacement" Rev.

5 - This change significantly improves backup power and HV AC capabilities for the common Emergency Operations Facility and related telecommunications equipment located within the Nuclear Training Center Critical electrical loads associated with the Emergency Operations Facility function are

10CFR50.59 EVALUATIONS DOCKET NO: 50-272 MONTH: AUGUST 1996 UNIT NAME: SALEM 1 CONTACT: R.HELLER TELEPHONE: 609-3 3 9-5162 backed-up by an uninterruptable power supply and/or diesel generator. Not all systems are currently protected by back-up power. Replacing the existing natural gas driven emergency generator located at the Nuclear Training Center (which primarily supplies back-up power to the Emergency Operations Facility) with a larger capacity diesel driver generator constitutes a change in facility by SAR definition, but there is no reduction in effectiveness of the Emergency Plan. The new generator enhances the effectiveness of the Emergency Plan due to its significantly larger load capacity and subsequent ability to handle more critical loads for a longer duration. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 96-108)

SECL 96-029 "Emergency Operating Procedures Setpoint Document" Rev. 3

- This revision addressed and incorporated comments resulting from PSE&G's Station Operations Review Committee review.

Also, updates to setpoints S.08, X.09, and X.12 have been identified. There is no reduction in the margin of safety as defined in the basis for any Technical Specification.

(SORC 96-114)

3. Procedures and Revisions TSC.OP-SO.CAV-OOOl(Q) "Control Area Ventilation Operation to Support Technical Specification Change" Rev. 0 - The purpose of this procedure is

_ to provide the instructions necessary to: 1) Operate the Control Area Ventilation System in Recirculation mode during modifications to the Unit 1 and Unit 2 Emergency Air Conditioning System and 2) Cope with a loss of Battery Room Exhaust Ventilation. There is no reduction in the margin of safety as defined in the basis for any Technical Specification.

(SORC 96-105)

i--

REFUELING INFORMATION DOCKET NO: 50-272 MONTH: AUGUST 1996 UNIT NAl\ffi: SALEM 1 CONTACT: RHELLER TELEPHONE: 609-339-5162 MONTH : AUGUST 1996 Refueling information has changed from last month: YES _._. NO . X .

Scheduled date for next refueling: (to be determined)

Scheduled date for restart following refueling: (to be determined)

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 )

Scheduled date(s) for submitting proposed licensing action: . n/a Important licensing considerations associated with refueling:

Number of Fuel Assemblies:

a. lncore 0

b. In Spent Fuel Storage 989 Present licensed spent fuel storage capacity: 1632 Future spent fuel storage capacity: 1632 Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: September 2008

SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT 1 AUGUST 1996 SALEMUNITNO. 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