ML18100A422
| ML18100A422 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 05/31/1993 |
| From: | Heller R, Shedlock M, Vondra C Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9306220209 | |
| Download: ML18100A422 (13) | |
Text
PS~G*
Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station U.S. Nuclear Regulatory Cornmissio Document Control Desk Washington, DC 20555
Dear Sir:
MONTHLY OPERATING REPORT SALEM NO. 1 DOCKET NO. 50-272 1993 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 May 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
~ely;g_
Gener~r -
Salem Operations cc:
Mr. Thomas T. Martin Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19046 Enclosures 8-1-7.R4
~
§~jjgt{J People_
,,----9306220209 I
PDR ADOCK R
930531 05000272 PDR ftM
'/I 95-2189 (10M) 12-89
~ERAGE DAILY UNIT POWER LE'4t.
Docket No.:
50-272 Unit Name:
Salem #1 Date:
6/10/93 Completed by:
Mark Shedlock Telephone:
339-2122 Month May 1993 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET)
(MWe-NET)*
1 816 17 969 2
919 18 777 3
1044 19 878 4
993 20 1076 5
1117 21 1059 6
1116 22 1074 7
1034 23 1003 8
1134 24 1099 9
1049 25 1057 10 1120 26 1078 11 1096 27 1079 12 1127 28 1082 13 1079 29 1112 14 1099 30 1111 15 1103 31 1076 16 976 P. 8.1-7 Rl
'1~
e OPERATING DATA REPORT e Docket No:
50-272 Date:
06/10/93 completed by:
Mark Shedlock Telephone:
339-2122 Operating Status
- 1.
Unit Name Salem No. 1 Notes
- 2.
Reporting Period May 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_~N--=A~----------------------~
2
- 9.
Power Level to Which Restricted, if any (Net MWe)
N/A
- 10. Reasons for Restrictions, if any _______ N___,_~A~-----------
- 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 Capacity Factor (using MDC Net)
- 22. Unit Capacity Factor (using DER Net)
- 23. Unit Forced Outage Rate This Month 744 744 0
744 0
243949.4 810900 776465 100 100 94.9 93.6 0
Year to Date.
Cumulative 3623 3366.91 0
328*1. 35 0
10383912.0 3477610 3318387 90.1 90.1 82.8 82.1 9.4 139560 92548.89 0
89421. 76 0
282582520.4 93851600 89390046 64.1 64.1 57.9 57.4 21.1
- 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 8-l-7.R2
NO.
DATE 0072 04-30-93 F
0073 05-04-93 F
0074 05-05-93 F
0075 05-06-93 F
0076 05-07-93 F
0077 05-16-93 F
0078 05-16-93 F
0082 05-17-93 F
0079 05-17-93 F
0083 05-17-93 F
0080 05-18-93 F
0081 05-19-93 F
1 2
F:
Forced S:
Scheduled DURATION TYPE 1 (HOURS)
REASON 2 61.00 A
27.58 A
3.92 A
10.67 A
3.45 A
5.93 A
10.00 B
4.68 A
19.52 A
19.52 A
9.28 A
9.40 B
Reason A-Equipment Failure (explain)
B-Maintenance or Test C-Refueling D-Requlatory Restriction UNIT SHUTDOWN AND POWER REDUCTIONS 5
5 5
5 5
5 5
5 5
5 5
5 REPORT MONTH MAY 1993 METHOD OF SHUTTING DOWN REACTOR LICENSE EVENT REPORT #
HF HF HF HF HF HF HF HF HF EG EG HF 3
Method:
1-Manual 2-Manual Scram SYSTEM CODE 4
E-Operator Training & License Examination F-Administrative 3-Automatic Scram 4-Continuation of Previous outage 5-Load Reduction 9-0ther G-Operational Error (Explain)
H-Other (Explain)
COMPONENT CODE5 FILTER PUMPXX FILTER PUMPXX PUMP XX PUMPXX PUMPXX PUMPXX PUMP XX xxxxxxx xxxxxxx PUMPXX 4
DOCKET NO.
UNIT NAME DATE COMPLETED BY TELEPHONE 50-272 Salem #1 06/10/93 Mark Shedlock 339-2122 CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE TRAVELING SCREENS/TRASH RACKS CIRCULATING WATER PUMPS TRAVELING SCREENS/TRASH RACKS CIRCULATING WATER PUMPS CIRCULATING WATER PUMPS CIRCULATING WATER PUMPS CONDENSER TUBE & WATER BOX CLEANING CIRCULATING WATER PUMPS CIRCULATING WATER PUMPS SW IT CHY ARD OR HIGH VOLTAGE SYSTEM PROBLEM SWITCHYARD OR HIGH VOLTAGE SYSTEM PROBLEM CIRCULATING WATER PUMPS 5
Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Exhibit 1 - Same Source Event Report CLER) File (NUREG-0161)
UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH MAY 1993 (CONTINUED)
METHOD OF SHUTTING LICENSE DURATION DOWN EVENT NO.
DATE TYPE 1
(HOURS)
REASON 2 REACTOR REPORT #
0084 05-23-93 F
11.17 A
5 0085 05-28-93 F
4.25 B
5 SYSTEM COMPONENT CODE4 CODE 5 HF PUMP XX HF PUMP XX DOCKET NO.
UNIT NAME DATE COMPLETED BY TELEPHONE 50-272 SALEM #1 6-10-93 Mark Shedlock 339-2122 CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE CIRCULATING WATER PUMPS CONDENSER TUBE AND WATER BOX CLEANER
SAFETY RELATED MAINTENA'E MONTH: -
MAY 1993 DOCKET.:
UNIT NAME:
50-272 SALEM 1 WO NO UNIT 870905048 1
871003047 1
87121205966 1
880401166 1
880428104 1
921219063 1
DATE:
COMPLETED BY:
TELEPHONE:
JUNE 10, 1993 R. HELLER (609)339-2212 EQUIPMENT IDENTIFICATION VALVE 1MS924 FAILURE DESCRIPTION:
MAIN STEAM LEAK UPSTREAM OF 1MS924 UNDER INSULATION -
INVESTIGATE AND REPAIR 13 MOISTURE SEPARATOR REHEATER FAILURE DESCRIPTION:
13MSR BEZEL ALARMS ARE FLASHING AND WILL NOT ACKNOWLEDGE -
INVESTIGATE VALVE 12CS48 FAILURE DESCRIPTION:
12CS48 FAILED LEAK RATE TEST -
TROUBLESHOOT VALVE VALVE 1RH26 FAILURE DESCRIPTION:
1RH26 BONNET LEAK -
INSPECT AND CLEAN VALVE 12CV150 FAILURE DESCRIPTION:
12CV150 BONNET LEAKS/REPLACE 12 SERVICE WATER PUMP FAILURE DESCRIPTION:
PUMP SHAFT SLEEVE LEAK, BLOWN 110 11 RING -
REPAIR
10CFRS0.59 EVALUATIONS e MONTH: -
MAY 1993
'DOCKET":
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
50-272 SALEM 1 JUNE 10, 1993 R. HELLER (609)339-2212 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-3216 Pkg 2 lEC-3213 Pkg 1 "Boric Acid Evaporator Upgrades" - This DCP upgrades Boric Acid Evaporator (BAE) control panels 301-1 & 301-2.
Five pneumatic indicating controllers and a dual indicator per panel will be replaced with functionally equivalent devices.
Nameplates and scales will be replaced.
In addition, the concentrates pumps discharge pressure gages are reinstalled essentially the same as the original design (Unit 2 only), and the boric acid filter inlet and outlet gages are replaced by gages with ~ sealed capillary system (Unit 1 only).
The BAE instrumentation and controls provide only local indication and control of non-safety related equipment.
The affected boric acid filter gages provide only local indication.
There is no effect on the functionality or operation of the Chemical and Volume Control System.
There is no reduction in the margin of safety as defined in the basis for any Technical Specification.
(SORC 93-041)
"Station Air Compressor Coolers" -
The purpose of this DCP is to replace the Lube Oil Coolers, Intercoolers and Aftercoolers on the 11,12 & 13 Service Air Compressors for the Salem Generating Station common Service Air system.
Drain tanks will also be provided in the condensate drain piping.
This modification will upgrade cooler materials from carbon steel shells with copper nickel tubes to stainless steel shells with 6%
moly tubes.
The drain tanks and piping will also be stainless steel.
The coolers will be fabricated in accordance with ASME VIII requirements.
The piping will be fabricated in accordance with ANSI B31.1.
The operation of the Station Air Compressors is not addressed in the Technical Specifications.
There is no reduction in the margin of safety as defined in the basis for any Technical Specification.
(SORC 93-041)
10CFR50.59 EVALUATIONS~
MONTH: -
MAY 1993 (cont'd)
ITEM 3EE-0001 Pkg 1 lSC-2300 Pkg 1 lEC-3221 Pkg 1 DOCKET.:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
SUMMARY
50-272 SALEM 1 JUNE 10, 1993 R. HELLER (609)339-2212 "Salem Unit 3 Secondary Leakage & Spill Containment" - This change adds a concrete slab and drain around the Salem Unit 3 Gas Turbine, to contain any oil spillage and to divert it to the oil/water separator for processing.
Additionally, fuel oil piping is being rerouted from underground to above ground and the air/control cabinet is being raised to keep it above the maximum water level.
There is no reduction in the margin of safety as defined in the basis for any Technical Specification.
(SORC 93-041)
"CW Air Ingress Monitors, Loop Seal and Vacuum Pumps" - This DCP replaces the #11 condenser Vacuum Pump with a single stage pump which does not require an air ejector stage; adds a heat traced loop seal to the system to replace the (12) float valves; replaces extraneous boundary valves with blind flanges; installs air ingress monitors on the system; changes the controls on No. 11 Vacuum Pump; changes the Control Room bezel nameplates and removes spare relays in the relay cabinets.
The Salem Technical Specifications do not address the Condenser Air Removal and Priming System.
Therefore, the proposed modifications do not reduce the margin of safety as defined in the basis for any Technical Specification.
(SORC 93-042)
"Drain Pipe Additions" - This DCP includes component drain lines located at both Salem units 1 and 2.
This DCP proposes the installation of hard piped equipment drains to replace the temporary tygon tubing currently in use.
There are no Technical Specifications directly applicable to the proposed modifications.
The proposed modification does not perform any safety related function and does not affect any safety related system required for the safe shutdown of the Salem Unit.
The proposed modification does not reduce the margin of safety as defined in the basis for any Technical Specification.
(SORC 93-042)
10CFR50.59 EVALUATIONS tt MONTH: -
MAY 1993 (cont'd)
ITEM 5EC-3030 Pkg 1 lSC-2269 Pkg 6 DOCKET.:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
SUMMARY
50-272 SALEM 1 JUNE 10, 1993 R. HELLER (609)339-2212 "Low Level Radwaste Storage Facility" -
The proposed Low Level Radwaste Storage Facility (LLRSF) will provide safe and secure space for temporary storage of low level radwaste generated by both Salem and Hope Creek Generating Stations during a period commencing when access to operating low level radwaste disposal facilities becomes unavailable and ending when an approved disposal facility becomes available to Public Service Electric & Gas.
The new LLRSF is functionally and physically isolated from all systems, structures, components and cables which could affect reactor safety or be used to mitigate the consequences of an accident.
There is no reduction in the margin of safety as defined in the basis for any Technical Specification.
(SORC 93-042)
"Modification to Salem Unit lE Distribution System
& Circulating Water Switchgear" - This package will provide the final connections between the two new offsite power sources between the offsite transmission network and the Salem Unit 1 Class lE distribution system (Vital Busses lA, lB & lC) and Unit 1 new CW switchgear.
This change will increase voltage recovery on vital and group busses during bus transfer, provide load growth capacity, improve voltages in the plant, provide margin for short circuit capability and improve plant reliability.
The modifications will improve the voltage profile on the vital and group busses.
This has resulted in a change of the trip setpoint for the second level of undervoltage protection on the vital busses.
This will increase the margin of safety between the setpoint value and the minimum allowable value and ensure safe operation of the vital equipment.
There is no reduction in the margin of safety as defined in the basis for any Technical Specification.
(SORC 93-042)
10CFR50. 59 EVALUATIONS e MONTH: -
MAY 1993 (cont'd)
ITEM lEC-3170 Pkg 1 B.
Safety Evaluations S-C-RC-CSE-0821 DOCKET.:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
SUMMARY
50-272 SALEM 1 JUNE 10, 1993 R. HELLER (609)339-2212 "Replace Containment Isolation Valves" - This DCP replaces pressure regulator 1NT31 with a higher range regulator, modify high pressure nitrogen containment isolation valve 1NT32 internals, and modify control air containment isolation valves 11CA330, 12CA330 and high pressure nitrogen containment isolation valves 1NT34 to accept soft seats. All changes are confined to component and do not affect component function. They also remove the external control pressure connection on the 1NT31 nitrogen pressure regulator. Valve 1NT901 will be deleted and valve 1NT54 will be replaced with a higher pressure class valve.
There is no change in the function of the valves and the Technical Specification requirements will still be met.
Therefore the proposal does not reduce the margin of safety as defined in the basis for any Technical Specification.
(SORC 93-046)
"Steam Generator Keeper Plates" -
The Steam Generators (S/G) at both Salem Units are supported by hinged frames.
Each of the eight hinges on each S/G is formed by structural steel members connected by a steel pin.
Keeper plates slip into milled slots on the pins.
These plates are bolted to a structural member.
The design intent of the keeper plates was to restrict pin rotation and axial movement.
However, further evaluation of these plates shows that they are unnecessary during any design basis event.
A Unit 2 DR (No.
SMD 93-089) identified two keeper plates as discrepant because of missing (No. 21 S/G) or bent (No. 22 S/G).
These discrepancies make the keeper plates non-functional Six keeper plates were identified as missing on Unit 1 S/G supports in previous DRs.
The proposed change is to accept the as-is condition of the S/G support pin keeper
~OCFR50.59 EVALUATIONS MONT.H: -
MAY 1993 (cont'd)
ITEM SMD 92-775 DOCKET I:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
SUMMARY
50-272 SALEM 1 JUNE 10, 1993 R. HELLER (609)339-2212 plates at both Unit 1 and Unit 2.
The keeper plate does not change the function or operability of the S/G or its support system.
Therefore, the proposal does not reduce the margin of safety as defined in the basis for any Technical Specification.
(SORC 93~041)
"Evaluation of the Thermal Performance of 12 Component Cooling Heat Exchanger" - the purpose of this evaluation is to assess the thermal performance of 12 Component Cooling Heat Exchanger (CCHX).
As demonstrated in Calculation S-1-SW-MDC-1247 Rev. 1, "Maximum Service Water Temperature and Minimum flow for Operation of 12 CCHX", the design heat removal of 12 CCHX is maintained provided the Service Water Temperature is maintained below 88.5°F with both sides of 12 CCHX in service and 82.9°F with just 12A CCHX in service.
The operating procedures will reflect the new temperature until the present situation can be remedied by removing the fouled plates from 12B CCHX and installing clean ones.
This will maintain the heat removal capacity in the SAR.
There is no reduction in the margin of safety as defined in the basis for any Technical Specification.
(SORC 93-041)
SALEM UNIT NO. 1 SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
UNIT 1 MAY 1993 The Unit began the period operating at reduced power due to heavy grass conditions at the circulating water inlet.
On May 3, 1993, the Unit achieved full power, and with the exception of several minor load reductions due to heavy grass conditions, continued to operate at full power until May 16, 1993.
Power was reduced on May 16, 1993 to clean condenser water boxes, repair # llB Circulating Water Pump and repair the isophase bus for the cooling unit.
The Unit was restored to full power on May 19, 1993, and, with the exception of two minor load reductions due to heavy grass conditions, continued to operate at essentially full power throughout the remainder of the period.
. FEFUELING INFORMATION MONTH: -
MAY 1993 MONTH MAY 1993 DOCKET I:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
- 1.
Refueling information has changed from last month:
YES NO X
50-272 SALEM 1 JUNE 10, 1993 R. HELLER
{609)339-2212
- 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
- a.
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