ML18096A571

From kanterella
Jump to navigation Jump to search
Monthly Operating Rept for Feb 1992 for Salem,Unit 1. W/920312 Ltr
ML18096A571
Person / Time
Site: Salem PSEG icon.png
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)
v • d • e


Text

'0 PS~G*

Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station March 12, 1992 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 February 1992 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 Sin erely yours, RH:pc cc: Mr. Thomas T. Martin Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19046 Enclosures

/j}-4

~*

8-1-7.R4

_The£neray_l?eogle 9203200358 92*0-229 ~--- ..._

23000 LJ J '\\

95-2189 (10M) 12-89 PDR ADOCK 05000272 R PDR

8-1.:...7. "R2 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-272 Unit Name: Salem #1 Date: 3/10/92 Completed by: Mark Shedlock Telephone: 339-2122 Month February 1992 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 1096 17 1102 2 1107 18 1118 3 1112 19 1099 4 1116 20 1123 5 1095 21 1123 6 1128 22 1119 7 1091 23 1110 8 1118 24 1110 9 1109 25 1127 10 1115 26 1112 11 1111 27 1126 12 1125 28 1115 13 1101 29 1115 14 1115 30 15 1111 31 16 1102

OPERATING DATA REPORT Docket No: 50-272 Date: 03/10/92 Completed by: Mark Shedlock* . Telephone: 339-2122 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 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 NA This Month Year to Date Cumulative
12. Hours in Reporting Period 696 1440 128593
12. No. of .Hrs. Rx. was Critical 696 1440 85040.3
13. Reactor Reserve Shutdown Hrs. 0 0 0
14. Hours Generator On-Line 696 1302.1 82350.0
15. Unit Reserve Shutdown Hours 0 0 0
16. Gross Thermal Energy Generated (MWH). 2377802.4 4425564.0 259922709.2
17. Gross Elec. Energy Generated (MWH) 805140 1469530 86274160
18. Net Elec. Energy Gen. (MWH) 773967 1406652 82183225
19. Unit Service Factor 100 90.4 64.0
20. Unit Availability Factor 100 90.4 64.0
21. Unit Capacity Factor (using MDC Net) 100.5 88.3 57.8
22. Unit Capacity Factor (using DER Net) 99.7 87.6 57.3
23. Unit Forced Outage Rate 0 9.6 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

UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH FEBRUARY 1992 DOCKET NO.: _,5::..;:0:....*=27.....2,___ __

UNIT NAME: Salem #1 DATE: 03/10/92 COMPLETED BY: Mark Shedlock TELEPHONE: 339-2122 METHOD OF SHUTTING LICENSE 1

DURATION DOWN EVENT SYSTEM COMPONENT CAUSE AND CORRECTIVE ACTION 2

NO. DATE TYPE (HOURS) REASON REACTOR REPORT # COOE 4 CODE 6 TO PREVENT RECURRENCE 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-Refuel ing 3-Automatic Scram Event Report CLER) File D-Requl~tory Restriction 4-Continuation of CNUREG-0161)

E-Operator Training & License Examination Previous Outage F-Acininistrative 5-Load Reduction G-Operational Error (Explain) 9-0ther H-Other (Explain)

SAFETY RELATED MAINTENANCE DOCKET NO: 50-272 MONTH: - FEBRUARY 1992 UNIT NAME: SALEM 1 DATE: MARCH 10, 1992 COMPLETED BY: J. FEST TELEPHONE: ( 609) 339-2904 WO NO UNIT EQUIPMENT IDENTIFICATION 910116186 , 1 lB DIESEL PRELUBE PUMP FAILURE DESCRIPTION: PRELUBE PIPING LEAKS - REWORK 910729081 1 14 CONTAINMENT FAN COIL UNIT FAILURE DESCRIPTION: SERVICE WATER INLET VALVE DID NOT FAIL OPEN - INVESTIGATE 910729093 1 lB DIESEL CRANKCASE EXPLOSION DOOR FAILURE DESCRIPTION: D/G EXPLOSION DOOR LEAKS - REWORK 911010098 1 VALVE 14SW24 FAILURE DESCRIPTION: 14 SERVICE WATER STRAINER VALVE -

CONTINUOUS BLOWDOWN - INVESTIGATE 920102122 1 CONTAINMENT PRESSURE RECORDER FAILURE DESCRIPTION: 1PR948A CONTAINMENT PRESSURE RECORDER WILL NOT ADVANCE -

REPAIR 920117122 1 RADIATION MONITOR lRlB FAILURE DESCRIPTION: RADIATION MONITOR lRlB FAILED -

INVESTIGATE 920129093 1 STEAM LINE RADIATION MONITOR 1RA15604 FAILURE DESCRIPTION: MONITOR 1RA15604 READS HIGH -

INVESTIGATE 920327002 1 11 SERVICE WATER PUMP FAILURE DESCRIPTION: PULL 11 SERVICE WATER PUMP AND REPLACE WITH REBUILT SPARE

10CFR50.59 EVALUATIONS DOCKET NO: 50-272 MONTH: - FEBRUARY 1992 UNIT NAME: SALEM 1 DATE: MARCH 10, 1992 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 (DCP)

DCP# lEC-3085 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)

DCP# lEC-3111 Pkg. 1 "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)

l 10CFR50.59 EVALUATIONS DOCKET NO: 50-272 MONTH: - FEBRUARY 1992 UNIT NAME: SALEM 1 DATE: MARCH 10, 1992 COMPLETED BY: J. FEST TELEPHONE: (609)339-2904 (Cont'd)

ITEM

SUMMARY

DCP# lEC-3054 Pkg. 2 "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)

DCP# lEC-3127 Pkgs 1-3 "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)

c-------

10CFR50.59 EVALUATIONS DOCKET NO: 50-272 MONTH: - FEBRUARY 1992 UNIT NAME: SALEM 1 DATE: MARCH 10, 1992 COMPLETED BY: J. FEST TELEPHONE: (609)339-2904

{Cont'd)

ITEM

SUMMARY

DCP# lEC-3048 Pkg. 2 "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 admini~tratively 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 DOCKET NO: 50-272 MONTH: - FEBRUARY 1992 UNIT NAME: SALEM 1 DATE: MARCH 10, 1992 COMPLETED BY: J. FEST TELEPHONE: (609)339-2904 (Cont'd)

ITEM

SUMMARY

C. Temporary Modifications (TMOD) w.o. 920203092 "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)

D. Safety Evaluations (S/E)

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 GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT 1 FEBRUARY 1992 SALEM UNIT NO. 1 The Unit began the period operating at full power, and continued to operate at full power throughout the entire period.

REFUELING INFORMATION DOCKET NO: 50-272 MONTH: - FEBRUARY 1992 UNIT NAME: SALEM 1 DATE: MARCH 10, 1992 COMPLETED BY: J. FEST TELEPHONE: (609)339-2904 MONTH FEBRUARY 1992

1. Refueling information has changed from last month:

YES X NO

2. Scheduled date for next refueling: APRIL 4, 1992
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
Retrieved from "https://kanterella.com/w/index.php?title=ML18096A571&oldid=2409253"