ML18101B228

Monthly Operating Rept for Jan 1996 for Salem Nuclear Power Plant,Unit 1.W/960215 Ltr

ML18101B228
Person / Time
Site:	Salem
Issue date:	01/31/1996
From:	Heller R, Phillips R, Warren C Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9602220050
Download: ML18101B228 (10)

Text

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• Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit February 15, 1996 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn.: Document Control Desk MONTHLY OPERATING REPORT SALEMNO. 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 report for the month of January is being sent to you.

Sincerely yours,

~:~

General Manager -

Salem Operations RH:vls Enclosures C Mr. Thomas T. Martin Regional Administrator USNRC, Region I 631 Park Avenue King of Prussia, PA 19046

.-.._on._ n _A_ of __ _ _______ _

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9602220050 960131 PDR ADOCK 05000272 R PDR The power is in your hands.

95-2168 REV. 6/94

Completed by:

• OPERATING DATA REPORT Robert Phillips

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Docket No:

Date:

Telephone:

50-272 02/10/96 339-2735 Operating Status

1. unit Name Salem No. 1 Notes

2. Reporting Period January 1996

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) NIA

10. Reasons for Restrictions, if any ~~~~~~~-=N+-=A=---~~~~~~~~~~

This Month Year to Date Cumulative

12. Hours in Reporting Period 744 744 162961

12. No. of Hrs. Rx. was Critical 0 0 104380.5

13. Reactor Reserve Shutdown Hrs. 0 0 0

14. Hours Generator On-Line 0 0 100388.3

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 0 0 318062229.2

17. Gross Elec. Energy Generated (MWH) 0 0 105301000

18. Net Elec. Energy Gen. (MWH) -2461 -2461 100202452

19. Unit Service Factor 0 0 61. 6

20. Unit Availability Factor 0 0 61. 6

21. Unit Capacity Factor (using MDC Net) 0 0 55.6

22. Unit Capacity Factor (using DER Net) 0 0 55.1

23. Unit Forced outage Rate 0 0 22.9

24. Shutdowns scheduled over next 6 months (type, date and duration of each)

We are presently in a scheduled extension of refueling outage.

25. If shutdown at end of Report Period, Estimated Date of Startup:

Under review.

8-1-7.R2

AVEi9E DAILY UNIT POWER LEVEL

• Docket No.: 50-272 Unit Name: Salem #1 Date: 02/10/96 Completed by: Robert Phillips Telephone: 339-2735 Month January 1996 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 0 17 0 2 0 18 0 3 0 19 0 4 0 20 0 5 0 21 0 6 0 22 0 7 0 23 0 8 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 28 0 13 0 29 0 14 0 30 0 15 0 31 0 16 0 P. 8.1-7 Rl

UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH January 1996 DOCKET NO. 50-272 UNIT NAME Salem #1 DATE 02/10/96 COMPLETED BY Robert Phillips TELEPHONE 609-339-2735.

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 5 TO PREVENT RECURRENCE 3824 01-01-96 s 744 c 4 ---------- zz zzzz Schedule Extension of Refueling 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-Refueling 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 1996 UNIT NAME: SALEM 1 DATE: 02/10/96 COMPLETED BY: R. HELLER TELEPHONE: 609-33 9-5162 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-3301, Pkg. 1 "Steam Generator Blowdown Upgrade" Rev. 1 - This DCP replaces Steam Generator Blowdown system valves to improve performance and reliability. It replaces GB185, GB923 &

GB924 in the Turbine Building and GB9 & GB189 valves in the Mechanical Penetration Area. In addition it installs a bypass valve around GB9 valves and replaces the carbon steel piping downstream of GB923 valves with stainless steel. This revision will replace some of the encapsulations near the GB9 valves and revise the safety evaluation to include information regarding the encapsulations. This revision also incorporates the Independent Design Verification, which was not complete at Rev. 0. Some pipe supports are being modified to facilitate installation. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 95-104) lEC-3307, Pkg. 2 "Gaseous Waste Disposal System Piping Reclassification and Modification to Sample Chamber RA-4331" Rev. 0 - This design change package removes the abandoned lRl 4 radiation detector now existing in Sample Chamber RA-4331 and weld a permanent plate in place of the existing fitted shield cap on the chamber. The detector is currently in place only to serve as a piping pressure boundary in order to protect and seal the integrity of the Gaseous Waste Disposal System. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 95-142) lEC-3322, Pkg. 3 "Service Water Pipe Replacement: Auxiliary Building Nuclear Header 11" Rev. 0 - This DCP replaces service water piping in the Unit 1 Auxiliary Building. The scope of the change involves

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10CFR50.59 EVALUATIONS DOCKET NO:

• 50-272 MONTH: JANUARY 1996 UNIT NAME: SALEM 1 DATE: 02/10/96 COMPLETED BY: R.HELLER TELEPHONE: 609-339-.5162 replacement of 24", 20", 8" and 4" supply and return piping and associated branch connections supporting the No. 11 Component Cooling Heat Exchanger (CCHX) to/from Service Water Nuclear Header No. 11. The pipe is currently coal tar epoxy lined or cement lined carbon steel. Replacement piping will be 6% molybdenum austenitic stainless steel. This is part of the Service Water Upgrade Program is identified in the UFSAR.

This change of material is already defined in the UFSAR. This DCP also incorporates a P&ID location change of temperature.

tap, 1TT14726, and root valve, 11SW123. These changes only reflect the as-built condition and are not implemented per this DCP. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 95-128) lEC-3323, Pkg. 1 "Piping Replacement for Service Water Intake Bay # 1 (Blind Flange Installation) Rev. 2 - This design change package replaces service water piping in the Unit 1 Intake Bay #1. This revision to the package installs a 30"blind flange to the turbine header discharge piping upstream of 11 SW20 at the service water header in Intake Bay #1. This is being made as an interim solution due to excessive valve seat leakage through turbine header cross tie isolation valve 13 SW20. Installation of this blind flange will allow service water piping replacement work to continue. There is no reduction in the margin of safety as defined in the basis for any Technical Specification.

(SORC 95-100)

2. UFSAR Change Notices (SCN)

SCN 95-74 "Seismic Evaluation Of Service Water/Circulating Water Discharge Piping" - The original plant design provided a buried 24 inch blank "tee" connection in the yard for each of the two underground nuclear discharge headers. In response to FSAR Question 9.34, PSE&G stated that the above buried tees would be opened to establish an alternate discharge path for the Service Water System in the event of a postulated failure of the

10CFR50.59 EVALUATIONS DOCKET NO:

• 50-272 MONTH: JANUARY 1996 UNIT NAME: SALEM 1 DATE: 02/10/96 COlvlPLETED BY: R.HELLER TELEPHONE: 609-339-5162 (Cont'd) non-seismic circulating water piping during a seismic event.

This action would become necessary if the postulated failure of the circulating water piping resulted in blockage of the service water discharge from the plant. However, a recent Engineering Evaluation, S-C-SW-CEE-0955 concludes that the water discharge function of the circulating water piping will not be

• affected by the postulated seismic event. The evaluation concludes that there is no concern that the circulating water piping would fail during a seismic event and block the service water discharge from the plant. Thus, the buried tees located in the yard do not need to be opened during or after a seismic event as anticipated in the original design. This proposal is intended to revise UFSAR Section 9 .2.1 to document the results of the above engineering evaluation and to acknowledge that the buried tees located in the yard do not need to be opened during or after a postulated seismic event as anticipated in the original design. This proposal does not modify any equipment, component(s), system(s) or station procedure(s).

There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 96-001)

SCN95-42 "Inconsistent Flood Level References For The Service Water Intake Structure" - This UFSAR update incorporates changes made to the Service Water Intake Structure by DCP lEC-1837, which was approved and completed in 1984. The changes were the result of revised flood levels and maximum wave runup.

The changes revised Service Water Intake Structure watertightness up to Elev. 128 ft. Public Service Datum for the air-intake penthouse and watertightness up to Elev. 126 ft.

Public Service Datum with wave runup protection up to Elev.

128 ft. Public Service Datum for the air exhausts. The margins for safety as defined in the Technical Specifications are not changed. The existing Service Water Intake Structure building flood level watertightness and flood wave runup protection satisfies design basis requirements. (SORC 96-002)

10CFR50.59 EVALUATIONS

• DOCKET NO:

• 50-272 MONTH: JANUARY 1996 UNIT NAME: SALEM 1 DATE: 02/10/96 COMPLETED BY: R. HELLER TELEPHONE: 609-339-5162

4. Safety Evaluation (S/E)

ODCM "Offsite Dose Calculation Manual" Rev. 10 - The purpose of this revision is to incorporate updating information from previous releases. The changes are mainly editorial in nature.

Technical Specifications 3.3.8 and 3.11.1.1 are considered the pertinent sections affected by the changes proposed under Revision 10 to the Salem ODCM. The alarm/trip setpoint calculated under the proposed revision will ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20, Appendix B, Table II, Column 2. The changes proposed under Revision 10 to the Salem ODCM do not reduce the margin of safety as defined in the basis for any Technical Specification. (SORC 96-001)

ES-13.010 Rev. 3 "Penetration Overcurrent Protection Coordination Calculation -

ES-13.005 Rev. 4 Salem Unit 1 and Salem Unit 2 - This is an update to the Penetration Protection Coordination Calculations to add Attachment 3 that provides a summary of the electrical devices that provide redundant electrical protection for the electrical containment penetration feed through conductors as required by Reg Guide 1.63. Modifications to this calculation are made by the Design Change Process as outlined in procedure NC.NA-AP .ZZ-0008(Q). This calculation is mentioned in Section 8.3.2.4 of the UFSAR regarding a list of Containment Penetration Protection devices. The addition, deletion or modification of the specific protective devices is controlled by the Design Change Process. All devices listed in the subject calculation have been previously reviewed when the calculation was developed or reviewed as part of a Design Change Package that installed them. Therefore, this calculation revision does not reduce the margin of safety as defined in the basis for any Technical Specifications. (SORC 96-011)

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REFUELING INFORMATION

• DOCKET NO:

• 50-272 MONTH: JANUARY 1996 UNIT NAME: SALEM 1 DATE: 02/10/96 COMPLETED BY: R. HELLER TELEPHONE: 609-339-5162 MONTH : JANUARY 1996 Refueling information has changed from last month: YES . X . NO,,__.-----'-

Scheduled date for next refueling: 09/10/95 Scheduled date for restart following refueling: 06/17/96

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? (to be determined )

Scheduled date(s) for submitting proposed licensing action: . n/a Important licensing considerations associated with refueling:

Number of Fuel Assemblies:

a. Incore 0

b. In Spent Fuel Storage 1005 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

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SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT 1 JANUARY 1996 SALEM UNIT NO. 1 The Unit is in a refueling outage and remained shutdown for the entire period. According to commitments from PSE&G and a subsequent confirmatory action letter from the NRC, the Unit will remain shutdown pending completion of the following actions:

• Appropriately address long standing equipment reliability and operability issues

• After the work is completed, conduct a restart readiness review to determine for ourselves the ability of each Unit to operate in a safe, event free manner

• After the restart review, meet with the NRC and communicate the results of that review