ML18101B103

Monthly Operating Rept for Oct 1995 for Salem,Unit 1.W/ 951114 Ltr

ML18101B103
Person / Time
Site:	Salem
Issue date:	10/31/1995
From:	Phillips R, Warren C Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9511200078
Download: ML18101B103 (10)

Text

e PS~G Public* Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit November 14, 1995 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn.: Document Control Desk MONTHLY OPERATING REPORT SALEMN0.1 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 October are being sent to you.

Sincerely yours,

~~

C. Warren 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 8-l-7.R4 9 (:

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9511200078 951031 95-2168 REV. 6/94 PDR ADOCK 05000272 R PDR

AVE. DAILY UNIT POWER LEVEL e Docket No.: 50-272

' . Unit Name: Salem #1 Date: 11/10/95 Completed by: Robert Phillips Telephone: 339-2735 Month October 1995 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

OPERATING DATA REPORT Docket No: 50-272 Date: 11/10/95 Co~pleted by: Robert Phillips Telephone: 339-2735 Operating Status

1. Unit Name Salem No. 1 Notes

2. Reporting Period October 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~~~~N"'"'""""'A~~~~~~~~~~~~~~~~~~~~~~~

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 745 7296 160753

12. No. of Hrs. Rx. was Critical 0 2660.9 104380.4:7

13. Reactor Reserve Shutdown Hrs. 0 0 0

14. Hours Generator On-Line 0 2632.1 100388.3

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 0 8010326.4 318062229.2

17. Gross Elec. Energy Generated (MWH) 0 2689850 105301000

18. Net Elec. Energy Gen. (MWH) -2112 2527390 100209554

19. Unit Service Factor 0 36.1 '62. 4

20. Unit Availability Factor 0 36.1 62.4

21. Unit Capacity Factor (using MDC Net) 0 31. 3 56.4

22. Unit Capacity Factor (using DER Net) 0 31.1 55.9

23. Unit Forced Outage Rate 0 56.3 22.9

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

Scheduled refueling outage.

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

Under review.

8-1-7.R2

UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH October 1995 DOCKET NO. 50-272 l

UNIT NAME Salem #1 DATE 11/10/95 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 3642 10-1-95 s 745 c 4 --------- zz zzzzzz Refueling outage 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)

lO<;F:R50.59 EVALUATIONS DOCKET NO: 50-272 MONTH: OCTOBER 1995 UNIT NAME: SALEM 1 DATE: 11/10/95 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)

The reporting ofDCP related 10CFR50.59 evaluations is being modified to address these items only after they have been implemented and turned over to Operations. For the next several months, during this transition phase, we anticipate few new DCPs to report.

lEE-0151, Pkg. 1 "Protection of Condensate Piping from Overpressurization" Rev. 0 - The purpose of this DCP is to install a l" x l" relief valve set at 15 psig on the 1 1/2" threaded connection on the suction strainer (1CNE28) located between the suction nozzle of condensate pump No. 12 (1CNE6) and gate valve (12CN5).

The relief valve installation should be typical for strainer (1CNE27) of condensate pump No. 11 (1CNE5) and strainer (1CNE29) for condensate pump No. 13 (1CNE7). The relief valve is required to protect equipment from over pressurization during condensate pump isolation mode. The relief valve is sized to pass back leakage flow for the check valve located downstream of the condensate pump. A lift in the relief valve would visually alert the operator that leakage is occurring and isolation of the system should stop before an over pressure condition occurs in the piping system. These modifications do not reduce the margin of safety because the condensate system is not addressed in the Technical Specifications or their bases.

(SORC 95-122)

2. Safety Evaluations (S/E)

W/O 940921184 "Freeze Seal Of The Component Cooling Water Supply To The Boric Acid Evaporator Condenser Safety Relief Valve Discharge Piping (1CC40)" - The purpose ofthis proposal is to install a freeze seal on the 1-1/2" discharge piping of the boric acid evaporator condenser safety relief valve, 1CC40, in the

10v~50.59 EVALUATIONS DOCKET NO: 50-272 MONTH: OCTOBER 1995 UNIT NAME: SALEM 1 DATE: 11/10/95 COMPLETED BY: R.HELLER TELEPHONE: 609-339-5162 Component Cooling Water (CCW) System. The freeze seal is needed to allow replacement of the 1CC40 relief valve for testing. The installation of a freeze seal will prevent "back leakage" of CCW from the CCW supply line through the relief valve discharge line while the valve is being replaced. A freeze seal failure is unlikely because its installation is controlled by a procedure which has been successfully performed several times at Salem and throughout the industry. In the unlikely event that the procedure fails (which causes the freeze seal to fail), the result would be a minor loss of CCW inventory. This would quickly be mitigated since the written contingency plan requires personnel to be present and instructs them on corrective actions to be taken. Loss of Spent fuel Pool Cooling was considered.

The event is not considered to be plausible due to the following barriers: Operators are stationed at the 1CV40 and in communication with the Control Room for the duration of the freeze seal evolution; Ability to cross connect to the Unit 2 Spent Fuel Pool Cooling System; and Alarm Response and Abnormal Operating procedures. There is no reduction in the margin of safety as defined in the bases for any Technical Specifications. (SORC 95-122) .

3. Procedures SC.CH-SA.WG-023 l(Q) "Waste Gas Decay Tank Sampling" Rev. 2 - Chemistry procedure SC.CH-SA.WG-023 l(Q), Rev. 2, directs Chemistry personnel to sample the Waste Gas Decay Tanks (WGDTs) at Unit 1 and Unit 2, Auxiliary Building elevation 64', Panel 108.

There are two primary reasons that samples are drawn at this location. One, samples must be drawn and analyzed prior to release from the WGDTs to the environment to verify release limits as prescribed in Tech Spec are not exceeded. Two, samples are taken to determine if there are explosive gas mixtures in the WGDTs when the Waste Gas Analyzer is out of service. The sample location in this procedure is different than the sample location described in Sections 11.3.2 and 11.3.4 in the UFSAR. Samples taken at the Waste Gas Analyzer as

lOCER.50.59 EVALUATIONS DOCKET NO: 50-272 MONTH: OCTOBER 1995 UNIT NAJ\.ffi: SALEM 1 DATE: 11/10/95 COMPLETED BY: R. HELLER TELEPHONE: 609-339-5162 described in the UFSAR, present the possibility of being cross contaminated by other gasses being drawn into the analyzer.

Therefore, representativeness of activity from the respective WGDT may not be obtained. However, sampling for oxygen (explosive gas mixture) is not affected by sampling at the WGA.

This procedure describes sampling each individual Gas Decay Tank separately by using the specific vent valve 11, 12, 13, 14, 21, 22, 23or 24WG132 stemming off the pressurized instrument line. Each vent has two isolation valves downstream from the respective WGDT. A pressure regulator is connected to the vent valve using quick disconnects. A sample apparatus is then connected to the outlet of the regulator and the sample is purged into a 5 gallon bottle partially filled with DM water with particulate and iodine filters on the vent side. The design and operation of the WGDTs is not affected. The only change is to the location of the sample points. There is no reduction in the margin of safety as defined in the bases for any Technical Specifications. (SORC 95-124)

4. UFSAR Change Notice (SCN.

SCN 91-35 "Containment Penetrations - Over Current Protection Devices"

- The proposed change to the UFSAR is to remove the tables listing the containment penetration/conductor over current protective devices (Tables 8.3-4A and 8.3-4B) from the UFSAR and to revise UFSAR Section 8.3.2.4 to include references to Engineering Calculation Numbers ES-13.0lO(Q)

& ES-13.00S(Q) for Salem Units 1and2 respectively. These calculations contain information with regard to the size, equipment power, setpoint settings, etc. And include references to the location for each device. These calculations are controlled and any revisions to the calculations will be .

accompanied with a 10CFR50.59 evaluation. This change to the UFSAR is to avoid having to change the UFSAR each time the information in the calculations change. In this proposed UFSAR change notice, no changes are being made to the devices or their descriptions. The only change is the location of

10CER50.59 EVALUATIONS DOCKET NO: 50-272 MONTH: OCTOBER 1995 UNIT NAME: SALEM 1 DATE: 11/10/95 COMPLETED BY: R.HELLER TELEPHONE: 609-339-5162 the infonnation with regard to the devices. This change notice also addresses revision to the description of these devices in the Technical Specifications Bases Section 3/4.8 "Electrical Equipment Protective Devices." This revision provides references to the UFSAR for discussions of these devices, and the UFSAR will now provide a discussion as well as references to the Engineering Calculations for details with regard to the devices. There is no reduction in the margin of safety as defined in the bases for any Technical Specification.

(SORC 95-127}

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~FPELING INFORMATION DOCKET NO: 50-272 MONTH: OCTOBER 1995 UNIT NAME: SALEM 1 DATE: 11/10/95 COMPLETED BY: R. HELLER TELEPHONE: 609-339-5162 MONTH : OCTOBER 1995 Refueling information has changed from last month: YES X. NO _ _

Scheduled date for next refueling: 09/10/95 Scheduled date for restart following refueling: 2nd quarter 1996

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 X If no, when is it scheduled? (to be determined)

Scheduled date(s) for submitting prpposed 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 of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: September 2008 8-1-7.R4

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SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT 1 "NeVBMB:BR. 1995 "c+1hlf SALEMUNITNO. 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, both Units 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