ML18101A551

Monthly Operating Rept for Jan 1995 for Salem Unit 1

ML18101A551
Person / Time
Site:	Salem
Issue date:	01/31/1995
From:	MORRONI M Public Service Enterprise Group
To:
Shared Package
ML18101A550	List: ML18101A549 ML18101A551
References
NUDOCS 9502210290
Download: ML18101A551 (10)

Text

DAILY UNIT POWER LE'41 Completed by: Mike Morroni Month January 1995 Day Average Daily Power Level (MWe-NET) 1 1124 2 1096 3 1098 4 1127 5 1127 6 640 7 1124 8 1113 9 1117 10 1120 11 1120 12 1118 13 1118 14 1103 15 1099 16 1121 P. 8.1-7 Rl

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9502210290 950214 PDR ADDCK 05000272 R PDR Docket No.: 50-272 Unit Name: Salem #1 Date: 02/10/95 Telephone:

339-2122 Day Average Daily Power Level (MWe-NET) 17 1121 18 1121 19 1121 20 1112 21 1100 22 1106 23 1120 24 1112 25 1120 26 1118 27 1119 28 1103 29 1123 30 1122 31 1108 OPERATING DATA REPORT Docket No: 50-272 Date: 02/10/95 Completed by: Mike Morroni Telephone:

339-2122 Operating Status 1. Unit Name Salem No. 1 Notes 2. Reporting Period January 1995 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 9. Power Level to Which Restricted, if any (Net MWe) N/A 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 744 744 0 744 0 2508588 850890 818199 100 100 99.4 98.6 0 Year to Date 744 744 0 744 0 2508588 850890 818199 100 100 99.4 98.6 0 cumulative 154201 102463.6 0 98500.2 0 312560490.8 103462040 98500363 63.9 63.9 57.8 57.3 21.2 24. Shutdowns scheduled over next 6 months (type, date and duration of each) Refueling outage scheduled to start 4/8/95 and last 60 days. 25. If shutdown at end of Report Period, Estimated Date of Startup: NA 8-l-7.R2 NO. DATE 2291 1-6-95 F 1 2 F: Forced S: Scheduled DURATION TYPE 1 (HOURS) REASON 2 5.0 A Reason A-Equipment Failure (explain)

B-Maintenance or Test C-Refuel ing D-Requlatory Restriction UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH JANUARY 1995 METHOD OF SHUTTING DOWN REACTOR 5 LICENSE EVENT REPORT # ------------

IB 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 CODE 6 DOCKET NO. :-'5:::..;:0:....*=27:....:2.__

__ _ UN IT NAME:

DATE:

COMPLETED BY: Mike Morroni TELEPHONE:

-'3=3:..:.9-'-5"-1:....:4=2

__ _ CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE INSTRU 1A SEC PWR SUPPLY FAILURE 4 Exhibit G -Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File (NUREG-0161) 5 Exhibit 1 -Same Source 10CFR50.59 EVALUATIONS MONTH: JANUARY 1995 DOCKET NO: UNIT NAME: 50-272 SALEM 1 02/10/95 R.HELLER 609-339-5162 DATE: COMPLETED BY: TELEPHONE:

• 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.

1. Design Change Packages (DCP) lEA-1086, Pkg. 1 "Deleted 3/4" Vent Valve 1 TL92 from Required Documentation" Rev. 0 -This DCP deleted 3/4" vent valve 1TL92 from drawings (205218, 218706, 226947) to agree with current field conditions.

The only system in this document update is the Lube Oil Filtration System. None of the parameters associated with this system will be affected by this documentation change. There are no credible failure modes affected by the deletion of this valve from the engineering documentation. (SORC 95-001) 2. SAR Change Notice (SCN) UFSAR Section 2.3 "UFSAR Section 2.3 (Meteorology)

Change" -The change includes the removal of detailed information provided in Table 2.3-16 of the Salem UFSAR. Specifically, the change involves removal of meteorological instrumentation and strip chart manufacturer, model specifics from the UFSAR. This change will make this section more consistent with other sections. meteorological monitoring system does not perform any safety related function.

The Technical Specification bases specifies that, "The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere.

This required capability to evaluate the need for initiating protective measures to protect the health and safety of the public is not reduced. (SORC 95-001) 10CFR50.59 EVALUATIONS MONTH: JANUARY 1995 DOCKET NO: UNIT NAME: 50-272 SALEM 1 02/10/95 R.HELLER 609-339-5162 DATE: COMPLETED BY: TELEPHONE: (Cont'd) 3. Safety Evaluations (S/E) SC.MD-CM.RC-OOOI(Q) "Reactor Coolant Pump Seal Disassembly, Inspection, Repair and Reassembly

Rev. 0 -The purpose of this evaluation is to assess the use of the RCP backseat during maintenance while circulating coolant through the core. The RCP is provided with a backseat that can be used during maintenance to form a boundary against RCS leakage during seal work. The RCP internal design specifications detailed in the UFSAR do not include the intricacies of the backseat design. The licensing requirements of the RCP design are not altered by the use of the backseat.

However, the boundary against RCS leak paths is not normally provided by the RCP backseat.

This maintenance evolution will incorporate the sealing capability of the backseat while RHR is in service circulating coolant throughout the core. The proposal changes the facility as described in SAR with respect to RCS boundaries and RCP seal function.

The maintenance of the RCP seal while on the backseat in Mode 5 will not result in RCS level going below the elevation of the seal injection line. Therefore, the margin of safety will not be reduced since the RCS level will be adequate to maintain the RHR system functioning. (SORC 95-007) 4. Temporary Modifications (T-Mods)95-008 "Temporary Blank for 1 VHE125" Rev. 0 -1 VHE125, 13 Control Area Ventilation supply fan and motor are to be removed for maintenance.

To support this activity, the filter plenum, 1VHE125, must be isolated.

There is no isolation point on the upstream side of the fan. There is only one on the downstream side. Therefore, the upstream side is to be blanked off. No Technical Specification is directly related to the fan. However, Section 3/4.7.6, "Control Room emergency Air Conditioning System," is indirectly related.

IOCFR50.59 EVALUATIONS MONTH: JANUARY 1995 DOCKET NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

50-272 SALEM 1 02/10/95 R. HELLER 609-339-5162 This requires certain dampers upstream of the fans within the control area air conditioning system to be operable, in order to isolate the control room during an emergency.

The proposal to install the blank has no effect on this Technical Specification, since it is beyond the boundary of the dampers. (SORC 95-009) 10CFR50.59 EVALUATIONS MONTH: JANUARY 1995 SUPPLEMENT DOCKET NO: UNIT NAME: DATE: 50-272 SALEM 1 02/10/95 R.HELLER 609-339-5162 COMPLETED BY: TELEPHONE:

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.

1. Design Change Packages (DCP) lEC-3016, Pkg. 1 "Security System SWIS Ground Plane Upgrade" Rev. 1 -this modification is a result of Public Service Electric & Gas Company response to the NRC report of the Hope Creek Generating Station Regulatory Effectiveness Review/(T AC No. 72711) Docket No. 50-354 Attachment 1, Section 2.2.1: Weakness in Perimeter Intrusion Detection System. This proposal does not reduce the of safety as defined in the bases for the Technical Specifications since no parameters involving security are documented in the Technical Specifications. (SORC 90-118) 2. Temporary Modifications (T-Mods)90-071 "#3 Station Air Compressor (SAC)" Rev. 0 -This T-Mod involves disabling No. 3 Station Air Compressor's (SAC) automatic High/Low Lube Oil Temperature and High Air Temperature Third Stage Inlet compressor trips. The trip functions will be augmented by continuously monitoring other local temperature gages and performing a manual compressor trip, if required.

This will make No. 3 SAC available as an emergency air compressor while No. 2 SAC is unavailable.

There are no Technical Specifications associated with the SAC. Therefore, there is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 90-060)

. .

• IOCFR50.59 EVALUATIONS 1\1:0NTH:

JANUARY 1995 SUPPLEMENT DOCKET NO: UNIT NAME: DATE: 50-272 SALEM 1 02/10/95 90-076 COMPLETED BY: TELEPHONE:

R. HELLER 609-339-5162 "Unit 1 Condensate Polishing MCC Temporary Power" -the purpose of this modification is to provide a temporary power jumper from a temporary 300KW 480V diesel generator, located on the north side of the Unit 1 Condensate Polishing Building, to the 480V section of the Unit 1 condensate polishing motor control center (MCC). There are no Technical Specifications associated with the Condensate Polishing System. Therefore, there is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 90-088)

• REFUELING INFORMATION MONTH: JANUARY 1995 DOCKET NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

MONTH : JANUARY 1995 Refueling information has changed from last month: YES __ NO Scheduled date for next refueling:

April 8. 1995 Scheduled date for restart following refueling:

June 6. 1995 50-272 SALEM 1 02/10/95 R.HELLER 609-339-5162 x a. Will Technical Specification changes or other license amendments be required?

YES NO --NOT DETERMINED TO DATE ____A_ b. Has the reload fuel design been reviewed by the Station Operating Review Committee?

YES NO_A_ Ifno, when is it scheduled?

March 1995 Scheduled date(s) for submitting proposed licensing action: ___ _j'N'-"1-=-A=

___ _ Important licensing considerations associated with refueling:

Number of Fuel Assemblies:

a. Incore b. In Spent Fuel Storage Present licensed spent fuel storage capacity:

Future spent fuel storage capacity:

Date oflast refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

8-l-7.R4 _193 __ 732 _1632_ _1632 __ September 2008

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• SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

-UNIT 1 JANUARY 1995 SALEM UNIT NO. 1 The Unit began the period operating at full power, and continued full power operations until January 6, 1995, at 09: 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />, when a load reduction was initiated due to IA Safeguards Equipment Control (SEC) cabinet being declared inoperable due to a failed power supply. The repairs were completed and a power increase began at 14:15 hours the same day. The Unit achieved 100% power on January 7, 1995, and continued to operate at essentially full power throughout the remainder of the period.