ML18100A312
| 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.
RH:pc 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 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 R
)C98 95-2189 (10M) 12-89
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:
Date:
Completed by:
Mark Shedlock Telephone:
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)
Report, Give Reason NA 2
- 9.
Power Level to Which Restricted, if any (Net MWe)
- 10. Reasons for Restrictions, if any
- 12. Hours in Reporting Period
- 12. No. of Hrs. Rx. was Critical
- 13. Reactor Reserve Shutdown Hrs.
- 14. Hours Generator On-Line
- 15. Unit Reserve Shutdown Hours
- 16. Gross Thermal Energy Generated (MWH)
- 17. Gross Elec. Energy Generated (MWH)
- 18. Net Elec. Energy Gen. (MWH)
- 19. Unit Service Factor
- 20. Unit Availability Factor
- 21. Unit Car::icity Factor (using MDC Net)
- 22. Unit Capacity Factor (using DER Net)
- 23. Unit Forced Outage Rate N/A This Month Year to Date 744 2160 744 1903.91 0
0 744 1818.35 0
0 2529597.6 5985722.4 854420 2017130 820606 1923882 100 84.2 100 84.2 99.7 80.5 98.9 79.9 0
15.8 50-272 04/10/93 339-2122 since Last N/A Cumulative 138097 91085.89 0
87958.76 0
278184330.8 92391120 87995541 63.7 63.7 57.6 57.1 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
NO.
DATE 0028 03/04/93 0029 03/05/93 0030 03/09/93 0031 03/10/93 0023 03/13/93 0024 03/15/93 0022 03/18/93 0025 03/22/93 0026 03/28/93 0027 03/31/93 1
F:
Forced S:
Scheduled UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH MARCH 1993 METHOD OF SHUTTING LICENSE DURATION DOWN EVENT SYSTEM TYPE1 (HOURS)
REASON2 REACTOR REPORT #
CODE4 F
5.20 A
5 HF F
5.47 A
5 HF F
4.05 A
5 HF F
5.93 A
5 HF F
2.00 A
5 HF F
7.18 A
5 HF F
32.15 5
HH F
6.98 A
5 HF F
4.42 A
5 HF F
2.40 B
5 HF 2
3 Reason A-Equipment Failure (explain)
B-Maintenance or Test C-Refueling D-Requlatory Restriction E-Operator Training & License Examination F-Administrative G-Operational Error (Explain)
H-Other (Explain)
Method:
1-Manual 2-Manual Scram 3-Automatic Scram 4*-continuation of Previous Outage 5-Load Reduction 9-0ther COMPONENT CODE6 PUMP XX PUMPXX PUMPXX PUMPXX PUMPXX PUMPXX PUMPXX PUMPXX PUMPXX PUMPXX 4
DOCKET NO.
UNIT NAME DATE COMPLETED BY TELEPHONE 50-272 Salem #1 04/10/93 Mark Shedlock 339-2122 CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE CIRCULATING WATER PUMPS CIRCULATING WATER PUMPS CIRCULATING WATER PUMPS CIRCULATING WATER PUMPS CIRCULATING WATER PUMPS CIRCULATING WATER PUMPS OTHER HEATER DRAIN SYSTEM PROBLEMS CIRCULATING WATER PUMPS CIRCULATING WATER PUMPS CONDENSER TUBE AND WATER BOX CLEANING 5
Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File Exhibit 1 - same Source (NUREG-0161)
S~FETY~RELATED MAINTE..
CE MONTH: -
MARCH 1993 DOCKE,NO:
UNIT NAME:
50-272 SALEM 1 WO NO UNIT 930215080 1
930306087 1
930311151 1
930328070 1
DATE:
COMPLETED BY:
TELEPHONE:
APRIL 10, 1993 J. FEST (609)339-2904 EQUIPMENT IDENTIFICATION SERVICE WATER HEADER PRESSURE FAILURE DESCRIPTION:
1PAS386 SLOW RESPONSE -
INVESTIGATE RADIATION MONITOR 1R46E FAILURE DESCRIPTION:
MONITOR SPIKES TO WARNING -
INVESTIGATE 1SWE27 FAILURE DESCRIPTION:
FAILED PERFORMANCE EVAL., CLEAN 1SWE27, REMOVE THE SPOOLS OF THE CFCU FOR CLEANING 11 CONTAINMENT FAN COIL UNIT FAILURE DESCRIPTION:
11 CFCU SW FLOW INDICATION ERRATIC -
TROUBLESHOOT
10CFR50.59 EVALUATION~
MONTH: -
MARCH 1993 DOCKEao:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
50-272 SALEM 1 APRIL 10, 1993 J. FEST (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 lEC-3216 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)
"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 /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
e 10~FR50.59 EVALUATIONS MONTH:. -
MARCH 19 9 3 (cont'd)
DOCKE,NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
50-272 SALEM 1 APRIL 10, 1993 J. FEST (609)339-2904
~-------------------------------------------------------
ITEM SC.SA-AP.ZZ-0026{Q)
C.
Safety Evaluations IOP-1, IOP-7,
SUMMARY
designator for the Relay Department from "RLT" to "RLY".
3.) Simplifies surveillance number/department responsibility paragraph in. /2.
There is no reduction in the margin of safety as defined in the basis for any Technical Specification.
(SORC 93-020)
"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)
"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 UNIT NO. 1 SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
UNIT 1 MARCH 1993 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.
e REFUELING INFORMATION DOCKE,NO:
. MONTH: -
M..~CH 1993 UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
MONTH MARCH 1993
- 1.
Refueling information has changed from last month:
YES NO X
- 2.
Scheduled date for next refueling:
OCTOBER 2, 1993 50-272 SALEM 1 APRIL 10, 1993 J. FEST (609)339-2904
- 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