ML18100A312

Monthly Operating Rept for Mar 1993 for Salem,Unit 1.W/ 930414 Ltr

ML18100A312
Person / Time
Site:	Salem
Issue date:	03/31/1993
From:	Shedlock M, Vondra C Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9304190343
Download: ML18100A312 (9)

Text

Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station April 14, 1993 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sir:

MONTHLY OPERATING REPORT SALEM NO. 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 March 1993 are being sent to you.

Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Safety Related Maintenance 10CFR50.59 Evaluations Operating Summary Refueling Information ti~

General Manager -

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

,,,- 9304190343 930331 PDR ADOCK 05000272 )C98 95-2189 (10M) 12-89 R PDR

8-1-7.R2 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-272 Unit Name: Salem #1 Date: 4/10/93 Completed by: Mark Shedlock Telephone: 339-2122 Month March 1993 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 1101 17 1104 2 1119 18 1117 3 1111 19 1105 4 1104 20 1109 5 1112 21 1113 6 1114 22 1088 7 1095 23 1087 8 1119 24 1100 9 1110 25 1116 10 1081 26 1115 11 1102 27 1092 12 1122 28 1130 13 1091 29 1125 14 1051 30 1122 15 1051 31 1102 16 1094

OPERATING DATA REPORT Docket No: 50-272 Date: 04/10/93 Completed by: Mark Shedlock Telephone: 339-2122 Operating Status

1. Unit Name Salem No. 1 Notes

2. Reporting Period March 1993

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 2

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 2160 138097

12. No. of Hrs. Rx. was Critical 744 1903.91 91085.89

13. Reactor Reserve Shutdown Hrs. 0 0 0

14. Hours Generator On-Line 744 1818.35 87958.76

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 2529597.6 5985722.4 278184330.8

17. Gross Elec. Energy Generated (MWH) 854420 2017130 92391120

18. Net Elec. Energy Gen. (MWH) 820606 1923882 87995541

19. Unit Service Factor 100 84.2 63.7

20. Unit Availability Factor 100 84.2 63.7

21. Unit Car::icity Factor (using MDC Net) 99.7 80.5 57.6

22. Unit Capacity Factor (using DER Net) 98.9 79.9 57.1

23. Unit Forced Outage Rate 0 15.8 21.4

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

Refueling. 10-02-93 approximately 72 days.

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

NA

UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH MARCH 1993 DOCKET NO. 50-272 UNIT NAME Salem #1 DATE 04/10/93 COMPLETED BY Mark Shedlock TELEPHONE 339-2122 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 6 TO PREVENT RECURRENCE 0028 03/04/93 F 5.20 A 5 ------------ HF PUMPXX CIRCULATING WATER PUMPS 0029 03/05/93 F 5.47 A 5 ------------ HF PUMPXX CIRCULATING WATER PUMPS 0030 03/09/93 F 4.05 A 5 ------------ HF PUMPXX CIRCULATING WATER PUMPS 0031 03/10/93 F 5.93 A 5 ------------ HF PUMPXX CIRCULATING WATER PUMPS 0023 03/13/93 F 2.00 A 5 ------------ HF PUMPXX CIRCULATING WATER PUMPS 0024 03/15/93 F 7.18 A 5 ------------ HF PUMPXX CIRCULATING WATER PUMPS 0022 03/18/93 F 32.15 5 ------------ HH PUMPXX OTHER HEATER DRAIN SYSTEM PROBLEMS 0025 03/22/93 F 6.98 A 5 ------------ HF PUMPXX CIRCULATING WATER PUMPS 0026 03/28/93 F 4.42 A 5 ------------ HF PUMPXX CIRCULATING WATER PUMPS 0027 03/31/93 F 2.40 B 5 ------------ HF PUMPXX CONDENSER TUBE AND WATER BOX CLEANING 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)

S~FETY~RELATED MAINTE. .CE DOCKE,NO: 50-272 MONTH: - MARCH 1993 UNIT NAME: SALEM 1 DATE: APRIL 10, 1993 COMPLETED BY: J. FEST TELEPHONE: (609)339-2904 WO NO UNIT EQUIPMENT IDENTIFICATION 930215080 1 SERVICE WATER HEADER PRESSURE FAILURE DESCRIPTION: 1PAS386 SLOW RESPONSE -

INVESTIGATE 930306087 1 RADIATION MONITOR 1R46E FAILURE DESCRIPTION: MONITOR SPIKES TO WARNING -

INVESTIGATE 930311151 1 1SWE27 FAILURE DESCRIPTION: FAILED PERFORMANCE EVAL., CLEAN 1SWE27, REMOVE THE SPOOLS OF THE CFCU FOR CLEANING 930328070 1 11 CONTAINMENT FAN COIL UNIT FAILURE DESCRIPTION: 11 CFCU SW FLOW INDICATION ERRATIC - TROUBLESHOOT

10CFR50.59 EVALUATION~ DOCKEao: 50-272 MONTH: - MARCH 1993 UNIT NAME: SALEM 1 DATE: APRIL 10, 1993 COMPLETED BY: J. FEST TELEPHONE: (609)339-2904 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.

ITEM

SUMMARY

A. Design Change Packages (DCPs) lEC-3204 Pkg. 1 "Boiler House Drains Modification" - The purpose of this design change is to redirect the discharge of Salem Generating S~ation's Skimmer Tank #3 from the storm sewer system to the Salem Non-Radioacti ve Liquid Waste Disposal Facility.

• The purpose of the proposed modification is to reduce the potential discharge of a toxic substance to the Delaware River. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. {SORC 93-020) lEC-3216 Pkg. 1 "Replacement of Boric Acid Instrumentation" - The following description applies to both Units, unless otherwise noted. a) Install new pressure indication filled system at the BAT pumps discharge and at the Unit 2 BA filter inlet and discharge to replace existing installation. b)

Install new assemblies as above at the BAT pumps suction. The addition and rework of the instrumentation does not affect the ability of the Boron Injection system to perform its intended function since they are being used for indication only. Therefore, the margin of safety is not compromised. (SORC 93-026)

B. Procedures and Revisions SC.SA-AP.ZZ-0012(Q) "Technical Specification Surveillance Program Matrix" - The limited revision to this procedure is as-follows: 1.) Removes fire protection surveillance numbers 4.3.3.6, Fire Detection Instrumentation 3.7.10, Fire Suppression Systems, and 4.7.11, Penetration Barriers for Unit 1/2 Attachment 1/2) from the matrix. Technical Specification Amendments 139/117 dated January 5, 1993, revised the fire protection license condition and relocated the surveillance and operability requirements relating to fire protection currently contained in the Technical Specifications, to plant periodic test procedures. 2.) Corrects the departments

10~FR50.59 EVALUATIONS e DOCKE,NO: 50-272 MONTH:. - MARCH 19 9 3 UNIT NAME: SALEM 1 DATE: APRIL 10, 1993 COMPLETED BY: J. FEST TELEPHONE: (609)339-2904 (cont'd)

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~-------------------------------------------------------

ITEM

SUMMARY

designator for the Relay Department from "RLT" to "RLY". 3.) Simplifies surveillance number/department responsibility paragraph in.

Attachment 1/2. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 93-020)

SC.SA-AP.ZZ-0026{Q) "Boiler and Machinery Inspection Program Matrix" -

This general revision incorporates the June and October, 1991, and December, 1992 revisions to the

• Nuclear Mutual Limited/Jurisdictional Boiler and Machinery Inspection Program. The crane and rigging requirements which have been added as part of the December, 1992, revision have not been incorporated. The revision to the procedure does not change the intent of the administrative controls for implementation of the inspections.

The revision contains editorial changes to the text, identifies changed inspection requirements, and adds MMIS component identification numbers.

Therefore, the proposal cannot reduce the margin of safety as defined in the basis for any Technical Specification. (SORC 93-023)

C. Safety Evaluations IOP-1, IOP-7, "IOP-1, IOP-7,Sl.OP-AB.RAD-OOOl{Q), lIC-4.1.014, lPD-4.2.005 & lIC-4.5.001 - This change will install jumpers, in Aux Relay Cabinets 58 & 59, to prevent receiving a Containment Ventilation Isolation Signal from the lRllA Containment Particulate Radiation Monitor. These jumpers are to be installed when the Unit is in Mode 5, after exiting Mode 6 per IOP-1, and they are to be removed in Mode 5, prior to entering Mode 6 per IOP-7. The following procedures are affected by this change: IOP-1, IOP-7, Sl.OP-AB-RAD-OOOl(Q),

lIC-4.1.014, lPD-4.2.005 and lIC-4.5.001. The installation of these jumpers, per procedure in Modes 1-5, does not add, delete or alter the equipment of the lRllA radiation monitor in any way. The equipment sensitivity, inaccuracies, response time and setpoints all remain the same.

Therefore, this proposed change does not reduce the margin of safety as defined in the basis for any Technical Specification. (SORC 93-020)

SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT 1 MARCH 1993 SALEM UNIT NO. 1 The Unit began the period operating at 100% power, and, with the exception of minor load reductions for condenser waterbox cleaning and repairs to #11 Heater Drain Pump controls, continued to operate at full power throughout the entire period.

REFUELING INFORMATION e DOCKE,NO: 50-272

. MONTH: - M..~CH 1993 UNIT NAME: SALEM 1 DATE: APRIL 10, 1993 COMPLETED BY: J. FEST TELEPHONE: (609)339-2904 MONTH MARCH 1993

1. Refueling information has changed from last month:

YES NO X

2. Scheduled date for next refueling: OCTOBER 2, 1993

3. Scheduled date for restart following refueling: DECEMBER 13, 1993

4. 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?:

5. Scheduled date(s) for submitting proposed licensing action:

N/A

6. Important licensing considerations associated with refueling:

7. Number of Fuel Assemblies:

a. Incore 193

b. In Spent Fuel Storage 656

8. Present licensed spent fuel storage capacity: 1170 Future spent fuel storage capacity: 1170

9. Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: September 2001 8-1-7.R4