ML18101A892

Monthly Operating Rept for Jul 1995 for Salem Unit 1.W/ 950814 Ltr

ML18101A892
Person / Time
Site:	Salem
Issue date:	07/31/1995
From:	Phillips R, Warren C Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9508180004
Download: ML18101A892 (10)

Text

e PS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236.

Nuclear Business Unit August 14, 1995 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 reports for the month of July are being sent to you.

Sincerely yours, 4~~

C. Warren General Manager -

Salem Operations RH:vls Enclosures C Mr. Thomas T. Martin Regional Administrator USNRC, Region I 631 Park Avenue King of Prussia, PA 19046 8-l-7.R4

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PDR ADOCK 05000272 R PDR The power is in your hands.

IERAGE DAILY UNIT POWER LE'I Docket No.: 50-272 Unit Name: Salem #1 Date: 08/10/95 Completed by: Robert Phillips Telephone: 339-2735 Month JULY 1995 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 Po 8.1-7 Rl

OPERATING DATA REPORT Docket No: 50-272 Date: 08/10/95 Completed by: Robert Phillips

• Telephone: 339-2735 Operating Status

1. Unit Name Salem No. 1 Notes

2. Reporting Period July 1995

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

12. Hours in Reporting Period 744 5087 158544 1a. No. of Hrs. Rx. was critical 0 2660.9 104380.5

13. Reactor Reserve Shutdown Hrs. 0 0 0

14. Hours Generator On-Line 0 2632.1 100388.3

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 0 8010326.4 318062229.2

17. Gross Elec. Energy Generated (MWH) 0 2689850 105301000

18. Net Elec. Energy Gen. (MWH) -7985 2538135 100220299

19. Unit Service Factor Q_ 51. 7 63.3

20. Unit Availability Factor 0 51. 7 63.3

21. Unit Capacity Factor (using MDC Net) 0 45.1 57.2

22. Unit Capacity Factor (using DER Net) 0 44.7 56.7

23. Unit Forced Outage Rate 100 48.3

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

To be determined.

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

To be determined.

8-1-7.R2

UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH JULY 1995 DOCKET NO.: -'5~0"'"*=27~2~--

UNIT NAME: Salem #1 DATE: 8-10 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 2671 7-1-95 F 744 D 4 ----------- SH CKTBRK TECH. SPEC. 3.0.3 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) .Fi le 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: JULY 1995 UNIT NAME: SALEM 1 DATE: 08/10/95 COMPLETED BY: R.HELLER TELEPHONE: 609-339-5162 The following items were evaluated in accordance with the provisions of the Code of Federal Regulations 10CFRS0.59. The Station Operations Review Committee has reviewed and concurs with these evaluations.

1. Design Change Packages (DCP)

The reporting ofDCP related 10CFRS0.59 evaluations is being modified to address these

, items only after they have been implemented and turned over to Operations. For the next several months, during this transition phase, we anticipate few new DCPs to report.

lEC-3430, Pkg. 1 "The objective of this DCP is to provide the control room with loss of flow indication (indirect but reliable) for radiation monitors lRl l/12's that will allow the operator(s) to take appropriate actions. "Normally closed" contacts off of the sampling line isolation valves' (1 VC7, 1VC8, 1VCl1 and 1VC12) "closed when valve is closed" limit switch auxiliary relays and "normally open" contacts off of the loss of 125VDC control voltage relays associated with the aforementioned valves' control circuits will be wired in series with AAS Point 919 to provide an audible control room alarm whenever one or more of the valves 1VC8 and 1VC12 are closed. This will be done using spare contacts and conductors of existing relays and cables; no new equipment/cable will need to be installed. This design change will only create a non-safety related indication circuit and will not prohibit/alter the required operation of the affected CIVs or of the lRl 1/12 radiation monitors (which are not considered in the accident analysis). Equipment sensitivity, inaccuracies, response time and setpoints will all remain the same, and no equipment will be added, deleted or modified.

There is no reduction in the margin of safety as defined in the bases for any Technical Specification. (SORC 95-079)

IOCFR50.59 EVALUATIONS DOCKET NO: 50-272 MONTH: JULY 1995 UNIT NAME: SALEM 1 DATE: 08/10/95 COMPLETED BY: R.HELLER TELEPHONE: 609-339-5162

2. Temporary Modifications (T-Mod)95-047 "Installation of Blind Flange on Downstream Side of Process Stream of Spent Fuel Pit Heat Exchanger" Rev. 0 - This T-Mod is for installation of blind flange on downstream side of process stream of spent fuel pit heat exchanger to allow isolation of No.

1 spent fuel pit heat exchanger to allow maintenance to be performed. The downstream piping does not have a means of isolation when the cross-tie is in operation. 1SFE12 and 2SFE12 (No. 1 and 2 spent fuel pit heat exchangers) will be isolated by installation of the blind flange on the downstream piping and by closing upstream isolation valves. The required minimum depth of water above the top of the irradiated fuel assemblies (23 ft) will be maintained during implementation or use of the T-Mod. The location of anti-siphon holes on the return piping will limit the loss of pool water inventory by gravity for any gross failures. Similarly, the basis for the fuel handling area ventilation system or margins of safety will not be altered by the isolation of the Unit 1 SFP heat exchanger.

There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 95-077)

3. Procedures Sl(2).0P-ST.ssp.:0002,3,4 "Procedure Revisions for DG Steady State Operation" Rev. 0 -

This proposal modifies the basis for technical specification acceptance criteria for frequency and voltage in technical specifications 3/4.8.1.1.2.d.3 .b and 3/48.1.1.2.d.6.b. The basis for the frequency revision is the SGS Emergency Diesel Generator Loading Calculation, ES-9.002(q) Revision 2. The basis for the voltage revision are calculations ES-15.004(Q)

(interim) Load Flow Analysis for 4160, 480 and 230 volt buses and ES-15.008 (interim) degraded grid. Existing technical specifications allow the DG to be considered operable in the frequency range from 58.8 to 61.2 HZ. The referenced calculation concludes that for frequencies greater than 60.5 HZ the DG will be overloaded. This is the basis for the technical

10CFR50.59 EVALUATIONS DOCKET NO: 50-272 MONTH: JULY 1995 UNIT NAME: SALEM 1 DATE: 08/10/95 COMPLETED BY: R.HELLER TELEPHONE: 609-339-5162 specification revision to a more restrictive range of 58.8 to 60.4 HZ. The existing technical specifications allow the DG to be considered operable in the voltage range from 3950 to 4580 volts. The referenced calculations conclude that for voltages lower than 3910 volts steady state, motors connected to the bus will experience an under voltage condition and could be damaged. Likewise, for voltages greater than 43 80 steady state, the motors connected to the bus will experience an overvoltage condition and could be damaged. This is the basis for the technical specification revision to a more restrictive range of 3950 to 4330 volts. This proposal will provide a better margin of safety. (SORC 95-080)

NC.NA-AP.ZZ-0014(Q) "Training, Qualification and Certification" Rev. 3 - The purpose of this revision is to reflect recent changes in the Nuclear Business Unit, clarify roles and responsibilities and conform the procedure to comply with current requirements. The changes being made by this revision only deal with training administrative issues. There is no reduction in the margin of safety as defined in the bases for any Technical Specification (SORC 95-083)

4. Safety Evaluations SC--HHB-NSE-0852 "Design Change Exclusion Zone for House Heating Boiler House" Rev. 0 - The activity described in this evaluation is to justify that the House Heating Boilers and the House Heating Boiler Building as being outside the scope of Nuclear jurisdiction. Therefore, NC.NA-AP.ZZ-0008(Q) would not apply to modifications performed in this structure. Upon approval, the building and systems described will be added Attachment No. 2 of the Technical Standard NC.DF-TS.ZZ-5426(Z), Exclusion Zone Modifications.

10CFR50.59 EVALUATIONS DOCKET NO: 50-272 MONTH: JULY 1995 UNIT NAME: SALEM 1 DATE: 08/10/95 COMPLETED BY: R. HELLER TELEPHONE: 609-339-5162 This facility and the equipment installed in this facility do not have any impact on any operating point, analysis assumption setpoint or acceptance limits as defined in the bases for any Technical Specification. There is no reduction in the margin of safety as defined in the basis for any Technical Specification.

(SORC 95-081)

REFUELING INFORMATION DOCKET NO: 50-272 MONTH: JULY 1995 UNIT NAME: SALEM I DATE: 08/10/95 C01\.1PLETED BY: R. HELLER TELEPHONE: 609-339-5162 MONTH : JULY 1995 Refueling information has changed from last month: YES_X_NO ~--

Scheduled date for next refueling: 07/10/95 Scheduled date for restart following refueling: 1st quarter 1996

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. Incore 0

b. In Spent Fuel Storage 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 assl1ming the present licensed capacity: September 2008 8-1-7.R4

SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT 1 JULY 1995 SALEMUNITNO. 1 The Unit remained shutdown for the entire period. According to commitments from PSE&G and a subsequent confirmatory action letter from the NRC, both Units 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 each Unit to operate in a safe, event free manner

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