ML18096A571
| ML18096A571 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 02/29/1992 |
| From: | SHEDLOCK M Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9203200358 | |
| Download: ML18096A571 (11) | |
Text
'0 Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Dear Sir:
MONTHLY OPERATING REPORT SALEM NO. 1 DOCKET NO. 50-272 March 12, 1992 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 February 1992 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 Sin erely yours, cc: Mr. Thomas T. Martin Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19046 Enclosures 8-1-7.R4 23000 LJ _ The£neray_l?eogle 9203200358 92*0-229 ... _ PDR ADOCK 05000272 R PDR J/j}-4 '\ \ 95-2189 (10M) 12-89 8-1.:...7. "R2 AVERAGE DAILY UNIT POWER LEVEL Completed by: Mark Shedlock Month February 1992 Day Average Daily Power Level (MWe-NET) 1 1096 2 1107 3 1112 4 1116 5 1095 6 1128 7 1091 8 1118 9 1109 10 1115 11 1111 12 1125 13 1101 14 1115 15 1111 16 1102 Day Docket No.: 50-272 Unit Name: Salem #1 Date: 3/10/92 Telephone:
339-2122 Average Daily Power Level (MWe-NET) 17 1102 18 1118 19 1099 20 1123 21 1123 22 1119 23 1110 24 1110 25 1127 26 1112 27 1126 28 1115 29 1115 30 31 OPERATING DATA REPORT Docket No: Date: Completed by: Mark Shedlock* . Telephone:
Operating Status 1. Unit Name Salem No. 1 Notes 2. Reporting Period February 1992 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 Maximum Dependable Capacity (Net MWe) 1106 50-272 03/10/92 339-2122 8. If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give 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 Capacity Factor (using MDC Net) 22. Unit Capacity Factor (using DER Net) 23. Unit Forced Outage Rate This Month 696 696 0 696 0 2377802.4 805140 773967 100 100 100.5 99.7 0 NA Year to Date 1440 1440 0 1302.1 0 4425564.0 1469530 1406652 90.4 90.4 88.3 87.6 9.6 N/A Cumulative 128593 85040.3 0 82350.0 0 259922709.2 86274160 82183225 64.0 64.0 57.8 57.3 21.1 24. Shutdowns scheduled over next 6 months (type, date and duration of each) Refueling outage scheduled to start 4-4-92 and last 67 days. 25. If shutdown at end of Report Period, Estimated Date of Startup: NA NO. DATE 1 2 F: Forced S: Scheduled UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH FEBRUARY 1992 DURATION TYPE 1 (HOURS) REASON 2 Reason A-Equipment Failure (explain)
B-Maintenance or Test C-Refuel ing Restriction METHOD OF SHUTTING DOWN REACTOR E-Operator Training & License Examination F-Acininistrative G-Operational Error (Explain)
H-Other (Explain) 3 LICENSE EVENT REPORT # Method: 1-Manual 2-Manual Scram SYSTEM COOE 4 3-Automatic Scram 4-Continuation of Previous Outage 5-Load Reduction 9-0ther 4 DOCKET NO.: _,5::..;:0:....*=27
..... 2,__ __ _ UNIT NAME: Salem #1 DATE: 03/10/92 COMPLETED BY: Mark Shedlock TELEPHONE:
339-2122 COMPONENT CAUSE AND CORRECTIVE ACTION CODE 6 Exhibit G -Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File CNUREG-0161)
TO PREVENT RECURRENCE 5 Exhibit 1 -Same Source SAFETY RELATED MAINTENANCE MONTH: -FEBRUARY 1992 DOCKET NO: 50-272 UNIT NAME: SALEM 1 WO NO UNIT 910116186 , 1 910729081 1 910729093 1 911010098 1 920102122 1 920117122 1 920129093 1 920327002 1 DATE: MARCH 10, 1992 COMPLETED BY: J. FEST TELEPHONE: ( 609) 339-2904 EQUIPMENT IDENTIFICATION lB DIESEL PRELUBE PUMP FAILURE DESCRIPTION:
PRELUBE PIPING LEAKS -REWORK 14 CONTAINMENT FAN COIL UNIT FAILURE DESCRIPTION:
SERVICE WATER INLET VALVE DID NOT FAIL OPEN -INVESTIGATE lB DIESEL CRANKCASE EXPLOSION DOOR FAILURE DESCRIPTION:
D/G EXPLOSION DOOR LEAKS -REWORK VALVE 14SW24 FAILURE DESCRIPTION:
14 SERVICE WATER STRAINER VALVE -CONTINUOUS BLOWDOWN -INVESTIGATE CONTAINMENT PRESSURE RECORDER FAILURE DESCRIPTION:
1PR948A CONTAINMENT PRESSURE RECORDER WILL NOT ADVANCE -REPAIR RADIATION MONITOR lRlB FAILURE DESCRIPTION:
RADIATION MONITOR lRlB FAILED -INVESTIGATE STEAM LINE RADIATION MONITOR 1RA15604 FAILURE DESCRIPTION:
MONITOR 1RA15604 READS HIGH -INVESTIGATE 11 SERVICE WATER PUMP FAILURE DESCRIPTION:
PULL 11 SERVICE WATER PUMP AND REPLACE WITH REBUILT SPARE
,------------------------------------------------
10CFR50.59 EVALUATIONS MONTH: -FEBRUARY 1992 DOCKET NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:
50-272 SALEM 1 MARCH 10, 1992 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 (DCP) DCP# lEC-3085 Pkg. 1 DCP# lEC-3111 Pkg. 1 "Phase III Annunciator Modifications" -The purpose of this DCP is to make certain modifications to the Unit 1 Control Room Overhead Annunciator System to correct Human Engineering Discrepancies identified during the Detailed Control Room Design Review. This modification is a replacement and an upgrade of the existing annunciator system This modification does not change any existing safety related system and had no effect on Class lE circuits.
Inputs from safety related systems to the annunciator system are through qualified isolation devices or by an independent set of contacts separate from any Class lE circuits.
There is no change to system performance, instrument setpoints or any other operating parameter. (SORC 92-022) "Replacement of Victoreen Radiation Monitoring Equipment" -The existing Victoreen NIMBINs for 1R41A/B/C (Plant vent Particulate, Iodine and Noble Gas) radiation monitors are being replaced with Sorrento Models RM80, RM23L and RM23A. This change is being performed for the purpose of improved equipment reliability, and therefore, increases plant safety. There are no changes in the functions outlined in the SAR or other licensing documents.
Since only one monitor is being upgraded using new microprocessor hardware, the issue of installing inadequate software in redundant equipment is not a concern and not an issue. Also, because equipment using microprocessor technology is already installed in the equipment room and appropriate procedures are used to preclude it being affected by EMI/RFI, the environmental concern is not applicable.
It can be concluded that the conditions presented in the NRC's letter are not applicable to this plant modification and that a replacement under 10CFR50. 59 is appropriate. ( SORC 92-022) 10CFR50.59 EVALUATIONS MONTH: -FEBRUARY 1992 (Cont'd) ITEM DCP# lEC-3054 Pkg. 2 DCP# lEC-3127 Pkgs 1-3 DOCKET NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:
SUMMARY
50-272 SALEM 1 MARCH 10, 1992 J. FEST (609)339-2904 "Service Water System Piping Upgrades" -This DCP involves the replacement of the 10" cement lined carbon steel service water supply/return piping for Fan Coil Units 11, 12, 13, 14 & 15 below elevation 102' down to the break flanges at the penetrations inside containment.
All associated 3/4" drain lines and valves will be eliminated.
The piping will be replaced with new 6% molybdenum stainless steel for corrosion/
erosion resistance.
Routing of the new piping will be identical to the existing piping. The 3/4" drains in the penetration area are of little use as they are on the elbows and would not allow for complete drainage of the piping. Two inch drains are available outside the containment and are normally used to drain the containment piping. Elimination of the 3/4" drains will have no adverse impact on system operation and reliability.
It merely provides for a reduction in the maintenance and testing requirements. ( SORC 92-018) "lA, lB, lC Diesel Generator Modifications" Rev. 1 -The purpose of this design change is to provide two temperature indicators each for the lA, lB and lC Diesel Generators (D/Gs). One of the temperature indicators is to monitor winding and bearing temperatures and the other replaces existing engine pyrometers.
This DCP also replaces the existing obsolete tachometers with Dynalco E.D.G speed switches to reduce D/G unavailability due to lack of spare parts. The prelube oil pump motor breakers and thermal overload heaters will also be replaced.
The safety functions, control and operation of the D/Gs remain unchanged.
The replacement components are identical in function and performance and do not affect the UFSAR Chapters 3 and 15 analyses.
Therefore, the probability of occurrence or consequences of an accident previously evaluated in the SAR is not increased. ( SORC 92-024) l c-------10CFR50.59 EVALUATIONS MONTH: -FEBRUARY 1992 {Cont'd) ITEM DCP# lEC-3048 Pkg. 2 DOCKET NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:
SUMMARY
50-272 SALEM 1 MARCH 10, 1992 J. FEST (609)339-2904 "Service Water room Cooler Pipe Replacement
-12 Header" -The purpose of this design change is to replace the existing cement lined carbon steel piping 6% molybdenum stainless steel. This change encompasses the 12 Room Cooler Header supply and return to the Main Service Water Header. This DCP also eliminates the cooler flow control valves and related instruments.
These are being replaced with manual valves and orifice plates to result in balanced flows. Components are being added to allow flow and temperature control across the coolers. The new pipe material and its installation are designed to be equivalent to or better than the pipe it replaces and will result in a significant reliability improvement.
The configuration changes are enhancements and will result in greater reliability.
The final configuration does not change the normal or emergency operation of the Service Water system with the exception of adding cross connect capability.
The use of this cross connect will be controlled to only those times when one header is out of service, increasing the availability of components. (SORC 92-024) B. Procedures and Revisions
{Proc) TSC.OP-SO.CH-OOOl(Q) "Chilled Water Cross Tie" The purpose of this procedure is to provide the necessary instruction for Chilled Water Cross Tie operation when three (3) chillers are available on Unit 1 and no chillers are available on Unit 2. This procedure also provides the steps to return the Chilled Water System to normal operation when at least two (2) of the Unit 2 chillers become available.
The margin of safety as defined in the Technical Specification Bases remains unaffected.
Sufficient cooling is still available to ensure Control Room air temperature does not exceed the allowable temperature for continuous duty rating for the equipment and habitability. (SORC 92-020) 10CFR50.59 EVALUATIONS MONTH: -FEBRUARY 1992 (Cont'd) ITEM DOCKET NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:
SUMMARY
50-272 SALEM 1 MARCH 10, 1992 J. FEST (609)339-2904 C. Temporary Modifications (TMOD) w.o. 920203092 D. Safety Evaluations (S/E) "Breach of a Penetration Seal" -The purpose of this modification is to breach a penetration seal and secure a watertight door in an open position in the Unit 1 Auxiliary Building barrier for the purpose of routing temporary commodities (i.e., welding leads). The penetration will be resealed and the door closed upon completion of the planned work. If a postulated high energy pipe rupture were to occur during the period that the penetration would not be sealed, the environmental effects on equipment in the Auxiliary Building would not be significant.
Mitigating factors include the following:
- 1) the breaks will typically be isolated within 30 minutes; 2) the maximum postulated compartment pressure is .5 psig, and 3) the auxiliary Building at elevation 100' is open with a substantial volume that would mix with and dilute any steam flow through the penetration. ( SORC 92-024) SCN 92-07 "Ammonium Hydroxide Operations" -The purpose of this safety evaluation is to assess Control Room habitability during a postulated accidental release of ammonium hydroxide in regard to changes to the operation of the Main Steam System chemical Feed System, specifically the ammonium hydroxide system, and the procedures for receipt of bulk tankers. If a postulated release would occur at the storage vessel, the Control Room Operators would have more than two minutes from detection of the fumes to the NRC limit of 100 ppm. During this time, the Operators would have sufficient time to place the Control Area Air Conditioning System (CAACS) in the "Accident-Inside air" mode of operation.
This would prevent further admission of outside air and maintain Control Room habitability. (SORC 92-022)
SALEM UNIT NO. 1 SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
-UNIT 1 FEBRUARY 1992 The Unit began the period operating at full power, and continued to operate at full power throughout the entire period.
' ,. REFUELING INFORMATION MONTH: -FEBRUARY 1992 MONTH FEBRUARY 1992 DOCKET NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:
- 1. Refueling information has changed from last month: YES X NO 2. Scheduled date for next refueling:
APRIL 4, 1992 50-272 SALEM 1 MARCH 10, 1992 J. FEST (609)339-2904
- 3. Scheduled date for restart following refueling:
JUNE 9, 1992 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 636 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