ML18102A929

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Monthly Operating Rept for Feb 1997 for Salem,Unit 2. W/970311 Ltr
ML18102A929
Person / Time
Site: Salem PSEG icon.png
Issue date: 02/28/1997
From: Conicella N, Garchow D, Phillips R, Tisdall D
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9703240185
Download: ML18102A929 (11)
v • d • e


Text

\ '0 PSl§Ge Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit March 11, 1997 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn: Document Control Desk MONTHLY OPERATING REPORT SALEM NO. 2 DOCKET NO: 50-311 In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specifications, the original monthly operating report for the month of February is being sent to you.

Sincerely yours, General Manager -

Salem Operations VS:pc Enclosures C Mr. H. J. Miller Regional Administrator USNRC, Region 1 4 7 5 Allendale Road King of Prussia, PA 19046

- . \

9703240185 970228 PDR ADOCK 05000311 R PDR 111111111111111111111111111111111111111111 111111111 1111 The po.ver is in your hands.

  • 9 1 - ll ll 4 7 7 1
  • 95-2168 REV. 6/94
  • , 10CFRS0.59 EVALUATIONS MONTH: FEBRUARY 1997
  • DOCKET NO:

NAME:

CONTACT:

50-311 UNIT2 N. CONICELLA TELEPHONE: 609-339-2124 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 DESIGN CHANGE PACKAGE 50.59 S/E S96-167, 2EC-3590, This design change package installs a relief valve upstream of each of the Pkg. 1, Rev 1 Addition of five SW223 valves in the service water outlet lines from the CFCUs.

Thermal Overpressure Device on SORC: 97-022 CFCU Return Piping 50.59 S/E S96-208, 2EC-3590, Engineering Evaluation S-C-SW-MEE-1138 addresses the Westinghouse Pkg. 2, Rev. This DCP installs a Nuclear Safety Advisory Letter (NSAL)96-003 concern that the CFCU relief valve across SW223 & coils and the associated piping could be overpressurized due to potential SW76 valves to address the heat transfer to the stagnant service water in the CFCU coils following a overpressure condition postulated LOCA or MSLB and LOOP event. Package 01 of this DCP installs a relief valve across SW223 & SW76 valves to address the overpressure condition as evaluated in the above engineering evaluation.

SORC: 97-022 50.59 S/E S97-042, 2EC-3570, This modification does not impact the capacity, capability or the response Pkg. 1, Rev. 0 Nitrogen Purge time of the AFST, the AFW system or the AFW equipment. In addition, Blanket this modification does not impact any other safety related equipment or system. The modifications implemented by this DCP are intended to improve the system reliability and increase component life by controlling the amount of dissolved Oxygen in the Auxiliary Feedwater System.

SORC: 97-024 50.59 S/E S97-047, 2EC-3590, This design change package modifies the No. 21 Service Water Nuclear Pkg. 8, Rev.O Service Water Header 16" CFCU supply piping by adding a redundant check valve System No. 21 Header Check downstream of existing check valve to prevent backleakage of the header.

Valve Installation SORC: 97-026

. , 10CFR50.59 EVALUATIONS MONTH: FEBRUARY 1997

  • DOCKET NO:

NAME:

CONTACT:

50-311 UNIT2 N. CONICELLA TELEPHONE: 609-339-2124 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 DESIGN CHANGE PACKAGE 50.59 S/E S97-048, 2EC-3590, This design change package modifies the No. 22 Service Water Nuclear Pkg. 9, Rev. 0 Service Water Header 16" CFCU supply piping by adding a redundant check valve System No. 22 Header Check downstream of existing check valve, 22SW51 to prevent backleakage of Valve Installation the header.

SORC: 97-026 MINOR - MODIFICATION 50.59 S/E S97-022, Masoneilan The purpose of this Minor Mod is to enhance the method of assuring the Air Operator, Retainer Clip S manual handwheel declutching pin stays in place and does not accidentally 032, Rev. 0 allow the handwheel to become engaged.

SORC: 97-018 MISCELLANEOUS 50.59 S/E S-97-04lon The purpose of this evaluation is to provide engineering support for an Engineering Evaluation S-2-CH- Operability Determination in the event that a chillier fails in the Unit 2 MEE-1175 Rev. 0 Auxiliary Building Chilled Water (CH) system with Salem Unit 2 in modes three and four, and the Unit 1 CH system having at least two chillers and one pump available in mode undefined.

SORC: 97-023 50.59 S/E S97-053 on Turbine The proposed test injects signals into the Hagan Control System, monitors Bypass Valve Control Loops the response of the controllers, and verifies proper operation of the turbine Test (TS2.SE-SU.RCP-0002(Q). bypass steam dump valves in response to the control signals.

Revision 0 SORC: 97-028 PROCEDURE 50.59 S/E TS2.SE-SU.CN- This is a one-time test of the condensate pumps to establish their 000l(Q), Condensate Pump performance curves (total flow vs. differential pump head).

Performance Test SORC: 97-023

_J

  • , 10CFRS0.59 EVALUATIONS MONTH: FEBRUARY 1997
  • DOCKET NO:

NAME:

CONTACT:

50-311 UNIT2 N. CONICELLA TELEPHONE: 609-339-2124 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 PROCEDURE 50.59 SIB S96-036 on Procedure The following Technical Specifications and basis were reviewed:3/4.1.2.1 S1(2).0P-SO.SF-0005(Q) & Boration Systems Flow Paths - Shutdown; 3/4.1.2.2 Reactivity Control TRIS Operation of Refueling Systems Flow Paths.

Water Purification System to SORC: 97-019 RWST in Modes 1-6 and 50.59 SIB S97-030, on This temporary procedure revision is being created as a contingency for the Procedure Sl.OP.SO-ABV.0001, potential loss of ABV exhaust fan 11 (1 VHE45) during the 1C buss outage Rev. 2, Operation of the Unit 1 exhaust fan 13 ( 1VHE47) is powered by the 1C buss.

Aux. Building Ventilation with SORC: 97-022 Loss of Supply Fans 50.59 SIB S97-033,on Procedure The proposed procedure revision will allow for stroke time testing of the S2.0P-ST.SJ-0005(Q), Rev. 7 on SJ45 valves with an operable RHR loop Inservice. The proposed procedure Inservice Testing Safety Injection revision will reflect installation of jumpers to allow opening of the 21SJ4 5 Valves Modes 5-6 and 22SJ45 valves without closing the 2RH1 or 2RH2 valves and opening the respective SJ44 valves.

SORC: 97-020 50.59 SIB S97-044, on Basically, this test involves splitting the operation of Service Water System Procedure TS2.SE-SU.SW- in two separate headers (the headers are usually cross-tied in the Service 0002(Q) Water Intake Structure).

SORC: 97-024 50.59 SIB S97-045 on Procedure This test will be performed to Mode 2. It will test and, if necessary, tune TS2. SE-SU.RCP-0004(Q), Rev. the controller for valve 2CC71.

0 Tuning of Letdown Heat SORC: 97-029 Exchanger Temperature

I :

" 10CFR50.59 EVALUATIONS MONTH: FEBRUARY 1997

  • DOCKET NO:

NAME:

CONTACT:

50-311 UNIT2 N. CONICELLA TELEPHONE: 609-339-2124 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 PROCEDURE 50.59 S/E S97-050, on Proposed changes to the Nuclear Business Unit's Emergency Plan, Section Procedures NC.EP-EP.ZZ- 13.3 of the Hope Creek and Salem Final Updated Safety Analysis Reports 080l(Q), Rev. 0 Emergency (SAR), would reduce the initial Emergency News Center (ENC) staffing News Center Operations and from 26 to 22 positions.

NC.EP-EPZZ-0806(Q), ENC SORC: 97-029 TEMPORARY MODIFICATION 50.59 S/E 97-027 (T/Mod 97- Due to the existing configuration of the Service Water (SW) supply and 001) Installation ofBlind Spacers return piping for the Containment Fan Coil Units (CFCUs), the potential in the No. 21 SW Nuclear exists for water hammer in the SW return lines and drainage of the SW Header CFCU Supply/Return and supply lines following a Loss of Offsite Power (LOOP). DCP 2EC-3590 the SW Supply/Return to the No. has been initiated to modify the SW piping to address these concerns.

21, No. 22 CFCUs SORC: 97-019 50.59 S/E S96-23 l, (T/Mod 96- The 1DF126 pressure regulator is not functioning either because of 037) Removal of Valve 1DF126 malfunction of the regulator itself or the feedback loop from the Internals backpressure control tank. This package presented to extend time period from 2/27/97 to 4/1/97.

SORC: 97-028 50.59 S/E S97-038, (T/Mod 96- Installation of the voltage monitor and associated voltage probes at cubicle 020) Rev. 0 Temporary 2H7D IAW this T-Mod will provide the desired voltage surge data for Installation of Surge Monitoring future engineering review.

Equipment at 4Kv SWGR Bus SORC: 97-029 2H (2SWGR2HD) Cubical 2H7D

___J

10CFR50.59 EVALUATIONS MONTH: FEBRUARY 1997

  • DOCKET NO:

NAME:

CONTACT:

TELEPHONE:

50-311 UNIT2 N. CONICELLA 609-339-2124 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 UFSAR 50.59 SIB 96-122 and UFSAR License amendments removed Table 3.6-1, Containment isolation Valves Change 96-139, Containment from T.S. and the information from that Table is now maintained in the Isolation Systems UFSAR. In support of that change, a review was performed of the existing Tables in the UFSAR for completeness. The proposed UFSAR change clarifies the double isolation barriers for each of the mechanical penetrations at Salem.

SORC: 97-019 50.59 SIB S97-002 on UFSAR This temporary procedure revision is being created as a contingency for the change Notice 96-207 Revision potential loss of ABV exhaust fan 11 (1 VHE45) during the 1C buss outage of table 9.3-6 as a corrective exhaust fan 13 ( 1VHE47) is powered by the 1C buss.

action for PIR 96032155 SORC: 97-022 50.59 S/E S97-035, on UFSAR This change involves the proposed configuration of the Hand Geometry Section 13.7 Salem & 13.6 Hope Reader system in the Security Center, the elimination of badge issue Creek, Salem-Hope Creek cubicles, and the description of the changed primary use of the auxiliary Security Plan, Revision 9 guardhouse.

SORC: 97-025 50.59 S/E S97-040 on UFSAR TIS 3/4.1.2, "Boration Systems" provides analysis for the loss of a CN 97-15 for Tables 9.2-3 & 9.2- charging pump. No credit is taken for the functionality of the PD charging 4 CC System pump during any condition except during normal shutdown conditions, which is bounded by the loss of a charging pump. This UFSAR Change notice allows the reduction of the CCW flow to the PD Charging Pump oil cooler and Fluidic Drive cooler to ensure during PD Charging Pump operation the oil temperatures are within vendor specified tolerances.

SORC: 97-023

  • OPERATING DATA REPORT
  • Docket No: 50-311 Date: 03/10/97 Completed by: Robert Phillips Telephone: 339-2735 Operating Status
1. Unit Name Salem No. 2 Notes
2. Reporting Period February 1997
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:..:...J--'A=-~~~~~~~~~~~~~

This Month Year to Date cumulative

11. Hours in Reporting Period 672 1416 134567
12. No. of Hrs. Rx. was Critical 0 0 78083.6
13. Reactor Reserve Shutdown Hrs. 0 0 0
14. Hours Generator On-Line 0 0 75229.5
15. Unit Reserve Shutdown Hours 0 0 0
16. Gross Thermal Energy Generated (MWH) 0 0 187781005
17. Gross Elec. Energy Generated (MWH) 0 0 78648898
18. Net Elec. Energy Gen. (MWH) -9429 -15732 74680599
19. Unit Service Factor 0 0 55.5
20. Unit Availability Factor 0 0 55.5
21. Unit Capacity Factor (using MDC Net) 0 0 49.8
22. Unit Capacity Factor (using DER Net) 0 0 49.4
23. Unit Forced Outage Rate 100 100 31.3
24. Shutdowns scheduled over next 6 months (type, date and duration of each)

Refueling extension.

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

Second quarter of 1997.

8-1-7.R2

9:RAGE DAILY UNIT POWER LE"9 Docket No.: 50-311 Unit Name: Salem #2 Date: 03/10/97 Completed by: Robert Phillips Telephone: 339-2735 Month February 1997 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 14 0 30 15 0 31 16 0 P. 8.1-7 Rl

UNIT SHUTDOWN AND POlilER REDUCTIONS REPORT MONTH February 1996 DOCKET NO.: ...5""0..,.*2....72......,._ __

UN IT NAME: _s;:;;.;a.-l~em~2.,,,..__ _

DATE: 02f10/9l COMPLETED BY: ..R=obe~r.._t....,P-..h...fl""'["'""tps-TELEPHONE: 609*339*2735 METHOO OF SHUTTING LICENSE '

DURATION DOWN EVENT SYSTEM CeHPONENT CAUSE AND CORRECTIVE ACTION ND. DATE TYPE1 (HOORS) REASON1 REACTOR REPORT # CODE' CODE5 TD PREVENT RECURRENCE 3859 2*1*97 F 744 FC 4

  • ---------- zz zzzz Refuelfng Schedule Extensfon 2 3 4 . 5 F: Forced Reason Method: Exhfblt G
  • Instructions Exhibit 1
  • Same S: Scheduled A*Equfpnent F*flure (expl*fn) 1*Manual for Preparation of Data Source B*Mafntenance or Jest 2*Manual Scram Entry Sheets for Licensee C*Refuelfng 3-Automatfc Scram Event Report CLER) File D*Requletory Restrfctfon 4*Contfnuatfon of (NUREG-0161)

E*Operetor Trefnfng &Lfcense Examfnetfon Prevfous outage F*Adlfnfstretfve 5-Load Reduction G*Oper*tfonel Error CExplefn> 9*0ther H*Other (Explef n)

    • Refueling Information
  • Docket No. 50-311 Month: February, 1997 Unit Name: Salem 2

Contact:

D. Tisdall Telephone: 609-339-1538 Month: February, 1997

1. Refueling information has changed from last month: Yes: No: X
2. Scheduled date for next refueling: Currently in outage.

Scheduled date for restart following refueling: To Be Determined

3. a. Will Technical Specification changes or other license amendments be required?

Yes: No: X Not Determined to Date:

b. Has the reload fuel design been reviewed by the Station Operating Review committee?

Yes: X No: If no, when is it scheduled? _ _ _ __

4. Scheduled date (s) for submitting proposed licensing action: N/A
5. Important licensing considerations associated with refueling:
6. Number of Fuel Assemblies:
a. lncore: 193
b. In Spent Fuel Storage: 584
7. Present Licensed spent fuel storage capacity: 1632 Future spent fuel storage capacity: 1632
8. Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: October, 2016
  • SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT 2 FEBRUARY 1997 SALEM UNIT 2 The unit 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 the unit to operate in a safe, event free manner.
  • After the restart review, meet with the NRC and communicate the results of that review.
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