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:
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ML18101A550	List: ML18101A549 ML18101A551
References
NUDOCS 9502210290
Download: ML18101A551 (10)

Text

~RAGE DAILY UNIT POWER LE'41 Docket No.: 50-272 Unit Name: Salem #1 Date: 02/10/95 Completed by: Mike Morroni Telephone: 339-2122 Month January 1995 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 1124 17 1121 2 1096 18 1121 3 1098 19 1121 4 1127 20 1112 5 1127 21 1100 6 640 22 1106 7 1124 23 1120 8 1113 24 1112 9 1117 25 1120 10 1120 26 1118 11 1120 27 1119 12 1118 28 1103 13 1118 29 1123 14 1103 30 1122 15 1099 31 1108 16 1121 P. 8.1-7 Rl

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9502210290 950214 PDR ADDCK 05000272 R PDR

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 ~~~~~~~N~~A'--~~~~~~~~~~~

This Month Year to Date cumulative

12. Hours in Reporting Period 744 744 154201

12. No. of Hrs. Rx. was Critical 744 744 102463.6

13. Reactor Reserve Shutdown Hrs. 0 0 0

14. Hours Generator On-Line 744 744 98500.2

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 2508588 2508588 312560490.8

17. Gross Elec. Energy Generated (MWH) 850890 850890 103462040

18. Net Elec. Energy Gen. (MWH) 818199 818199 98500363

19. Unit Service Factor 100 100 63.9

20. Unit Availability Factor 100 100 63.9

21. Unit Capacity Factor (using MDC Net) 99.4 99.4 57.8

22. Unit capacity Factor (using DER Net) 98.6 98.6 57.3

23. Unit Forced Outage Rate 0 0 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

UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH JANUARY 1995 DOCKET NO. :-'5:::..;:0:....*=27:....:2.___ __

UN IT NAME: ....:.:Sa:::..:l:..:e~m._#::...1,__-'--

DATE: __.2=,..-_,_10~*....:.9=-5-...,--

COMPLETED BY: Mike Morroni TELEPHONE: -'3=3:..:.9-'-5"-1:....:4=2_ __

METHOD OF SHUTTING LICENSE DURATION DOWN EVENT SYSTEM COMPONENT CAUSE AND CORRECTIVE ACTION NO. DATE TYPE 1 (HOURS) REASON 2 REACTOR REPORT # CODE 4 CODE 6 TO PREVENT RECURRENCE 2291 1-6-95 F 5.0 A 5 ------------ IB INSTRU 1A SEC PWR SUPPLY FAILURE 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-Requlatory Restriction 4-Continuation of (NUREG-0161)

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

10CFR50.59 EVALUATIONS DOCKET NO: 50-272 MONTH: JANUARY 1995 UNIT NAME: SALEM 1 DATE: 02/10/95 COMPLETED BY: R.HELLER TELEPHONE: 609-339-5162

• 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 1TL92 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. Th~ 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 DOCKET NO: 50-272 MONTH: JANUARY 1995 UNIT NAME: SALEM 1 DATE: 02/10/95 COMPLETED BY: R.HELLER TELEPHONE: 609-339-5162 (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 1VHE125" Rev. 0 - 1VHE125, 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 DOCKET NO: 50-272 MONTH: JANUARY 1995 UNIT NAME: SALEM 1 DATE: 02/10/95 COMPLETED BY: R. HELLER TELEPHONE: 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 DOCKET NO: 50-272 MONTH: JANUARY 1995 UNIT NAME: SALEM 1 SUPPLEMENT DATE: 02/10/95 COMPLETED BY: R.HELLER TELEPHONE: 609-339-5162 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 ~n.argin 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 DOCKET NO: 50-272 1\1:0NTH: JANUARY 1995 UNIT NAME: SALEM 1 SUPPLEMENT DATE: 02/10/95 COMPLETED BY: R. HELLER TELEPHONE: 609-339-5162 90-076 "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

• DOCKET NO: 50-272 MONTH: JANUARY 1995 UNIT NAME: SALEM 1 DATE: 02/10/95 COMPLETED BY: R.HELLER TELEPHONE: 609-339-5162 MONTH : JANUARY 1995 Refueling information has changed from last month: YES _ _NO x Scheduled date for next refueling: April 8. 1995 Scheduled date for restart following refueling: June 6. 1995

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 _193 _ _

b. In Spent Fuel Storage 732 Present licensed spent fuel storage capacity: _1632_

Future spent fuel storage capacity: _1632_ _

Date oflast refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: September 2008 8-l-7.R4

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.