ML18096B279
| ML18096B279 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 01/31/1993 |
| From: | Shedlock M, Vondra C Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9302220401 | |
| Download: ML18096B279 (12) | |
Text
.,
Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station February 12, 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 January 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 Sincerely yours,
~(}:!7oLo?
v A_...
~heral Manager -
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 The Energy People 9302220401 PDR ADOCK R
930131 05000272 PDR 95-2189 (10M) 12-8
8-1-7.R~
AVERAGE DAILY UNIT POWER LEVEL Completed by:
Mark Shedlock Month January 1993 Day Average Daily Power Level (MWe-NET) 1 1119 2
1129 3
1114 4
1118 5
1118 6
1118 7
1123 8
1111 9
1126 10 1112 11 1128 12 1102 13 1022 14 839 15 525 16 96 Day Docket No.:
50-272 Unit Name:
Salem #1 Date:
2/10/93 Telephone:
339-2122 Average Daily Power Level (MWe-NET) 17 0
18 0
19 0
20 0
21 0
22 0
23 0
24 269 25 978 26 1119 27 1105 28 1106 29 1120 30 1131 31 1131
OPERATING DATA REPORT Docket No:
50-272 Date:
02/10/93 Completed by:
Mark Shedlock Telephone:
339-2122 Operating Status
- 1.
Unit Name Salem No. 1 Notes
- 2.
Reporting Period January 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-1-=-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 744 604.1 0
560.1 0
1771291. 2 598030 567133 75.3 75.3 68.9 68.4 24.7 Year to Date 744 604.1 0
560.l 0
1771291.2 598030 567133 75.3 75.3 68.9 68.4 24.7 Cumulative 136681 89786.1 0
86700.5 0
273969899.6 90971020 86638792 63.4 63.4 57.3 56.8 21.5
- 24. Shutdowns scheduled over next 6 months (type, date and duration of each)
None.
- 25. If shutdown at end of Report Period, Estimated Date of Startup:
NA
NO.
DATE 0010 01/14/93 F
0011 01/16/93 F
0012 01/24/93 F
1 2
F:
Forced S:
Scheduled DURATION TYPE 1 (HOURS)
REASON 2 35.1 183.9 4.8 Reason A-Equipment Failure (explain)
B-Maintenance or Test C-Refueling D-Requlatory Restriction B
A B
UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH JANUARY 1993 METHOD OF SHUTTING DOWN REACTOR 5
2 5
LICENSE EVENT REPORT #
3 Method:
1-Manual 2-Manual Scram SYSTEM CODE4 CH CH HH 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 CODE 6 DOCKET NO.
UNIT NAME DATE COMPLETED BY TELEPHONE 5D-272 Salem #1 D2/1D/93 Mark Shedlock 339-2122 CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE PUMP XX
- 11 STEAM GEN. FEED PUMP PUMPXX
- 12 STEAM GEN. FEED PUMP TRIP PUMP XX
- 13 CONDENSATE PUMP 4
Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File (NUREG-0161) 5 Exhibit 1 - Same Source
e SAFETY RELATED MAINTENANCE DOCKE,NO:
50-272 SALEM 1 MONTH: -* JANUARY 1993 UNIT NAME:
WO NO UNIT 920325118 1
921103174 1
921217184 1
DATE:
COMPLETED BY:
TELEPHONE:
FEBRUARY 10, 1993 J. FEST
{609)339-2904 EQUIPMENT IDENTIFICATION lA DIESEL GENERATOR FAILURE DESCRIPTION:
START AIR PRESSURE REGULATOR -
LOW OUTPUT -
INVESTIGATE 11 ACCUMULATOR FAILURE DESCRIPTION:
CONSOLE LEVEL ALARM DID NOT REFLASH -
INVESTIGATE PRIMARY WATER STORAGE TANK FAILURE DESCRIPTION:
HIGH LEVEL ALARM IN -
TROUBLESHOOT AND REWORK
~----------------------------
921228150 1
930103075 1
930111085 1
930111161 1
930113061 1
930117052 1
930117058 1
VALVE 12MS10 FAILURE DESCRIPTION:
MANUAL/AUTO STATION WILL NOT SWAP TO AUTO -
INVESTIGATE RADIATION MONITOR 1R41A FAILURE DESCRIPTION:
MONITOR NORMAL LIGHT ERRATIC -
INVESTIGATE BORATE FLOW BEZEL 1FI113A FAILURE DESCRIPTION:
RAPID BORATE FLOW BEZEL READS HIGH -
INVESTIGATE RADIATION MONITOR 1R41C FAILURE DESCRIPTION:
MONITOR NORMAL LIGHT OFF -
INVESTIGATE 15 CONTAINMENT FAN COIL UNIT FAILURE DESCRIPTION:
INDICATION OFF SCALE IN LOW SPEED INVESTIGATE 1LT112 & 114 VCT LEVEL FAILURE DESCRIPTION:
NO AUTO SWAP -
INVESTIGATE VALVE llMSlO FAILURE DESCRIPTION:
VALVE FAILED OPEN IN AUTO -
REWORK
SAFETY RELATED MAINTE.CE MON~H: -* JANUARY 1993 DOCKE,NO:
UNIT NAME:
50-272 SALEM 1 (cont'd)
WO NO UNIT 930123054 1
930123059 1
930128058 1
DATE:
COMPLETED BY:
TELEPHONE:
FEBRUARY 10, 1993 J. FEST (609)339-2904 EQUIPMENT IDENTIFICATION VALVE 11BF40 FAILURE DESCRIPTION:
VALVE NOT OPENING FULLY -
INVESTIGATE & CORRECT VALVE 13BF40 FAILURE DESCRIPTION:
VALVE NOT OPENING FULLY -
INVESTIGATE & CORRECT PLANT VENT FLOW RECORDER FAILURE DESCRIPTION:
FLOW RECORDER READING HIGH -
INVESTIGATE
10CFR50.59 EVALUATION, MONTH: -* JANUARY 1993 DOCKE,NO:
so-212 UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
SALEM 1 FEBRUARY 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) lSM-0103 Pkg. 1 lEC-3197 Pkg. 1 "Installation of Service Water System Material Test stand" - This design change is to address the installation of the Service Water System Material Test stand as a permanent arrangement.
This stand was installed by DCP lSM-0103 Rev. O as a temporary installation to evaluate the performance of various materials being considered for use in the Service Water System.
The original plan called for this evaluation to last two years.
At
-the conclusion of the two year study it was determined that it would be beneficial to continue evaluating the performance of the materials selected for use in the system.
It was decided to revise the Design Change Package to make the test stand a permanent installation.
It also adds document changes to add the test stand to the P&IDs and arrangement drawings as well as add the valves to MMIS database.
The test stand is located in a non-nuclear, non-safety related portion of the Unit 1 turbine building.
It uses approximately 100 GPM which is diverted from the normal flow to the TAC heat exchangers.
This is an insignificant flow in this area.
This installation does not alter the design intent of the Service Water System.
This installation does not affect the independent service water loops described in the Technical Specifications.
There is no reduction in the margin of safety as defined in the basis for any Technical Specification.
(SORC 93-002)
"Steam Generator Feed Pump Independent Control Oil System" -
The purpose of this change is to install two (2) Woodward High Pressure Hydraulic Power Units (11PLE40, 12PLE40) to provide an independent supply of control oil to the SGFP&T governor hydraulic actuators.
In order to provide an emergency source of oil to the new units, connections will be made between the existing low
10CFR50.59 EVALUATION~
MoNrH:
~ JANUARY 1993 (cont'd)
ITEM DOCKE-NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
SUMMARY
50-272 SALEM 1 FEBRUARY 10, 1993 J. FEST (609)339-2904 pressure lube oil system and the new reservoirs to the SGFP&T lube oil storage tank.
Control of the new HPU's will be from control switches located inside of the new HPU auxiliary equipment cabinets which will be mounted to the end of the respective SGFP local panels (362, 363) and a normal hinged door with a handle will provide quick access to the switches.
By mounting these switches inside the panels, they are made less visible and less prone to inadvertent operation.
Abnormal HPU operation will be alarmed on the overhead annunciator (SGFP trouble) and similarly at the local SGFP panels 362 (363).
At a pressure of 350 PSI decreasing, the standby pump will start.
At a pressure of 300 PSI decreasing, the HPU will trip the SGFP.
During the installation of a cable through penetration seal, flood protection will be compromised.
If at anytime during this installation, the Delaware River water level, as monitored by Operations, rises above 99.5 feet, the work will be stopped and a temporary barrier will be installed.
There is no reduction in the margin of safety as defined in the basis for any Technical Specification.
(SORC 93-008)
B.
Procedures and Revisions NC.NA-AP.ZZ-0058(Q)
"Corrective Action" Program" -
The following changes have been made in this revision: 1) The title Vice President - Nuclear Engineering in Section 3.4 was changed to General Manager -
Engineering and Plant Betterment.
Also, deleted responsibility for procurement of nuclear fuel which is now responsibility of VP -
Nuclear Operations; 2) Section 3.5 was completely revised;
- 3) Revised 3.7 to describe responsibilities for the General Manager - Nuclear Operations Support;
- 4) Section 3.7 changed to Section 3.8.
Revised responsibilities for the General Manager -
Nuclear Services; 5) Section 3.8 changed to Section 3.9.
The title General Manager -
Procurement and Material Control changed to the General Manager -
Material Control; 6) Section 3.9 changed to Section 3.10 and describes responsibilities for the GM - Nuclear Human Resources; 7) Section 3.10 and 3.11 changed to Section 3.11 and 3.12;
10CFR50.59 EVALUATION~
MONTH:
~ JANUARY 1993 (cont'd)
ITEM DOCKE,NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
SUMMARY
50-272 SALEM 1 FEBRUARY 10, 1993 J. FEST (609)339-2904
- 8) Added "NC" designator to VP-PO.ZZ-OOlO(Q) is section 3.1 and 9.1.5; 9) Revised Exhibit 1 to reflect current Forms, Procedures and Organizations, and 10) Miscellaneous typographical and editorial corrections~
There is no reduction in the*margin of safety as defined in the basis for the Technical Specifications.
(SORC 93-004)
- c.
Temporary Modification Requests T-Mod #
93-012 T-Mod #
93-010 "lPSl Bonnet Leak Repair" -
The purpose of this modification is to eliminate the bonnet leak on lPSl.
The modification will involve drilling two small holes in the valve bonnet and injecting a leak sealing compound into the void space.
The valve will be rendered inoperable by this modification since the compound will fill the bonnet and it will no longer be po~sible to open the valve.
This modification will remain in place until the next refueling outage, at which time the valve will be repaired.
The only valves that provide a safety function.for the pressurizer are the PORVs and the safety valves, and these valves will not be affected by this T-Mod.
The only affect will be the reduction of spray flow because of the loss of one of the spray lines.
This may cause the pressurizer pressure to reach the setpoint of the PORVs in the event of a 10% step power reduction.
_However, the setpoint of the PORVs and therefore the margin of safety will remain unchanged.
(SORC 93-006)
"Unit 1 and Unit 2 BAST Cross Connect" -
The purpose of this TMOD is to cross connect 12 BAST and 22 BAST, allowing the transfer of borated
- water from 22 BAST to 12 BAST utilizing 22 BAT pump.
At all times, for both Units, the following limiting condition for operation will be satisfied per Technical Specification requirements: a boric acid storage system and one associated heat tracing system with a minimum contained volume of 5106 gallons; between 20~000 and 22,500 ppm of
10CFR50.59 EVALUATION, MONTH: -
JANUARY 1993 (cont'd)
ITEM T-Mod #
92-111 T-Mod #
93-015 DOCKE,NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
SUMMARY
50-272 SALEM 1 FEBRUARY 10, 1993 J. FEST (609)339-2904 boron; and a minimum solution temperature of 145 deg. F.
The refueling water storage tank will not be affected.
The Technical Specification design basis assumption will not be altered, therefore, there is no reduction in the margin of safety.
(SORC 93-007)
"Portable Temporary Station Air Supply to SWIS" -.
This temporary modification connects a temporary supply of compressed air to maintain service air and control air supply to the No. 1 & 2 Units Service Water Intake Structure during the installation of DCP lEC-3210.
The lack of impact on safety systems and equipment and review of the Technical Specifications indicate this modification dries not have any adverse effect on the margins of safety that are the bases for the Technical Specifications.
(SORC 93-007)
"Radiation Monitoring System" - This TMOD allows the check source for the 1Rl5 to be removed from the monitor until design issues can be resolved.
The Check Source assembly does not affect the operability of the monitor.
Its only function is to provide a means of checking channel operability.
There is no reduction in the margin of safety as defined in the basis for any Technical Specification.
(SORC 93-008)
SALEM UNIT-NO. 1 SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
UNIT 1 JANUARY 1993 The Unit began the period operating at full power and continued to operate at full power until January 15, 1993, when power was* reduced to repair 11 Steam Generator Feed Pump coupling.
A reactor head vent leak required a shutdown on January 16, 1993, to evaluate boric acid damage to an individual rod position indicator housing.
The Reactor was manually tripped during the shutdown due to the failure of the main steam bypass system controls.
Following completion of the shutdown activities a reactor startup began and the Unit was synchronized on January 24, 1993.
The Unit returned to full power on January 25, 1993, and continued to operate at full power throughout the remainder of the period.
RE~UE~~NG INFORMATIONtt MON~H: ~ JANUARY 1993 MONTH JANUARY 1993 DOCKE-NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
- 1.
Refueling information has changed from last month:
YES NO X
- 2.
Scheduled date for next refueling:
OCTOBER 2, 1993 50-272 SALEM 1 FEBRUARY 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