ML18102A984

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Monthly Operating Rept for Mar 1997 for Salem Unit 1.W/ 970415 Ltr
ML18102A984
Person / Time
Site: Salem PSEG icon.png
Issue date: 03/31/1997
From: GARCHOW D F, PHILLIPS R
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LR-N970258, NUDOCS 9704220161
Download: ML18102A984 (13)
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FYublic Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit APR 151997 LR-N970258 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn: Document Control Desk MONTHLY OPERATING REPORT SALEM NO. 1 DOCKET NO. 50-272 In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical specifications, the original monthly operating report for the month of March is being sent to you. RAR:tcp Enclosures C Mr. H. J. Miller Sincerely yours, iYl!f.G General Manager -Salem Operations Regional Administrator USNRC, Region 1 475 Allendale Road King of Prussia, PA 19046 ,,------970422o{6i-97o331

______ ---------1 PDR .ADOCK 05000272 i R PDR The power is in your hands.

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  • L 95-2168 REV. 6/94 10CFR5Q.59 EVALUATIONS MONTH: MARCH 1997 DOCKE.0: 50-272 NAME: Unit 1 CONTACT: R. Ritzman TELEPHONE:

609-339-1445 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 DCP lEE-0349, Pkg. 1, Rev. O Bearing Safety Evaluation S96-064 Lubrication Pressure Relief Valve (1SC16) Replacement Circulating Water System Design Change Packages DCP lEC-3408 and lEC-3409, No. 15&16 Service Water Pump Replacements Safety Evaluation

  1. 97-088 DCP lEC-3385, Pkg. 2, Rev. 0, Emergency Lighting Inverter Modification The proposal involves the replacement of a relief valve in the circulating water pump bearing lube water section of the Circulating Water System. The modification is within the Circulating Water System and is not addressed in the Technical Specifications or "Bases". The effects on the reactor and its associated margins of safety due to postulated pipe breaks is not addressed in the basis of any Technical Specification section. Therefore, the proposed modification does not reduce the margin of safety as defined in the basis for any Technical Specifications.

Technical Specification Sections 2.0, B2.0, 3/4, 3/4. 7, 3/4. 7.1, B3/4, B3/4. 7, B3/4.7.1 and 5.0 were reviewed in making this determination.

SORC: 97-031 These change packages replacethe No. -15 and No. 16 Service Water

  • Pumps (1SWE5/1SWE6) with pumps that are manufactured of materials that are more resistant to the corrosive and erosive silt laden brackish river water than the existing pump materials.

SORC: 97-035 This proposa1.is to modify Salem Unit 1 emergency lighting inverters 1INV1A15Y, 1INV1B16Y and 1INV1C2Y to change their normal and back-up power source selections.

The 125 VDC source will be changed from the regular or normal to the emergency or back-up power source. SORC: 97-041 10CFR5'1.59 EVALUATIONS MONTH: MARCH 1997 DOCKE-0: 50-272 NAME: Unit 1 CONTACT: R. Ritzman TELEPHONE:

609-339-1445 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 Safety Evaluation

  1. S97-066 UFSAR Change Notice 97-025 Clarification of the Reactor Vessel Head Vent (Reactor Coolant System) Safety Evaluation S97-054 DCP lEC-3651, Pkg. 2, Rev. 1, Modification to Station Air Compressor Controls Safety Evaluation S97-055 DCP lEC-3651, Pkg. 3, Rev. 1, Modification to Station Air Compressors Controls Section 2.0 (Safety Limits), 3/4.1 (Reactivity Control Systems), 3/4.3 (Instrumentation) and 3/4.4 (Reactor Coolant System) of the Salem Units 1 & 2 Technical Specifications as well as the bases for each of these sections were reviewed.

There are no changes to any Technical Specification value and no new effect on the margin of safety associated with this change is created. The proposed change is descriptive in nature and is not a hardware change. It will have no effect on the availability, operability (ability to perform safety related function), or performance of systems and components important to safety and does not affect the plant technical specification requirements.

The proposed change does not require a change to the technical specifications and does not prevent inspections or surveillance required by technical specification.

Therefore, the proposed change will not reduce the margin safety, as described in the bases for any technical specification

  • SORC: 97-033 This proposal changes the station air compressor 1 SAE2 from the existing total closure control scheme to a total closure control scheme proposed by the air compressor vendor for the reduction of cycling which currently occurs during low load operation.

The changes in the control scheme require the installation of a control enclosure, an orifice in the 3rd stage discharge piping, and a differential pressure transmitter across the orifice. SORC: 97-039 This proposal changes the station air compressor 1 SAE3 from the existing total closure control scheme to a total closure control scheme proposed by the air compressor vendor for the reduction of cycling which currently occurs during low load operation.

The changes in the control scheme require the installation of a control enclosure, an orifice in the 3rd stage discharge piping, and a differential pressure transmitter across the orifice. SORC: 97-039 10CFR5Q.59 EVALUATIONS MONTH: MARCH 1997 DOCKE.O: 50-272 NAME: Unit 1 CONTACT: R. Ritzman TELEPHONE:

609-339-1445 The following items were evaluated in accordance with the provisions of the Code of Federal Regulations IOCFR50.59.

The Station Operations Review Committee has reviewed and concurs with these evaluations DESIGN CHANGE PACKAGE Safety Evaluation S97-069 DCP This modification does not reduce the margin of safety as defined in the lEC-3622, Pkg. 1, Rev. 0, Liquid basis for Technical Specification 3/4.11.1, Liquid Eftluents, but instead Radwaste System Enhancements increases the safety margin. SORC: 97-043 Safety Evaluation S97-082 DCP The proposal involves no plant equipment, except security hand-geometry 5EC-0008, Pkg. 1, Rev. 0 Hand readers and their interface with the security system, and does not reduce Geometry Security Access Project the effectiveness of the Security Plan or the acceptance criterion of 10 CFR Safety Evaluation S97-083 DCP lEC-3525, Pkg. 1, Rev. 0 Relocation/Replacement of RV 1CVl41 and Relocation of 1CV63 Safety Evaluation S97-093 DCP lEE-0346, Pkg. 1 & 2EE-0293, Pkg. 1, Solid State Protection (SSPS) Safety Injection Reset Modification Safety Evaluations, lEC-3330, Package 1, CP Rev. 2 and lEC-3329, Package 1, CP Revision 2 NO. 13&14 Service Water Pump Replacements 50.54 (p). All Technical Specifications sections were reviewed.

SORC: 97-041 The reliefvruve 1CV141 has had a history ofleaking through the seat; numerous maintenance work requests have been written to correct relief valve 1CVl41 leakage and chattering.

This proposal implements some of the recommendations provided in the root cause analysis for CR 960113275.

SORC: 97-039 This proposal replaces the TDl relays in Train A and B of the SSPS with relays which add a time delay-off feature. The modification does not change the design requirements or function of the Safety Injection initiation or reset circuitry or modify the design basis of the affected circuits.

SORC: 97-043 These change packages replace the No. 13 & No. 14 Service Water Pumps (1SWE3/lSWE4) with a-pump manufactured of materials that are more resistant to the corrosive and erosive silt laden brackish river water _ than the existing pump materials.

SORC: 97-035 10CFR5().59 EVALUATIONS MbNTH: MARCH 1997 DOCKE.O: 50-272 NAME: Unit 1 CONTACT: R. Ritzman TELEPHONE:

609-339-1445 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 REQUEST Safety Evaluation S97-060 DCP lEC-3306, Pkg. 2, Rev. 0 Low Tavg. Nomenclature Change Safety Evaluation S97-067 DCP lEC-3474, Pkg. 1, Rev. 0, High Energy Line Break Relief Path Modifications The proposed changes to the RPS Low-Low Tavg signal are intended for clarification purposes only. The changes being performed by this modification will not affect any functions, operation or setpoints associated with this signal. Therefore, this modification does not reduce the margin of safety as defined in the basis for any Technical Specification.

SORC: 97-033 The modifications implemented by this DCP are structural in nature and are intended to restore the degraded condition and improve reliability of the pressure relief mechanism associated with postulated HELB events in the Auxiliary Building.

The increased capacity and reliability of the modified pressure relief system will result in an increased and adequate margin of __ _ , __

__ _ __ _ _ .. ___ . ____ ___ _ Safety Evaluation 897-068 DCP lEC-3475, Pkg. 1, Rev. 0, Inner and Outer Penetration Area Blowout Panel Modifications MISCELLANEOUS Safety Evaluation

  1. S97-065 on Basis for Technical Specification

3.7.3 Component

Cooling Water (CCW) System Operability SORC: 97-033 The proposed change package will restore vent panels and their fasteners to a more reliable condition and improve reliability of the pressure relief function of these panels. Implementation of the proposed modifications will have no negative impact and hence is not considered to represent a reduction in the margin of safety. SORC: 97-033 Because certain single active failures can impact two of the three installed CCW pumps, three CCW pumps must be operable at the start of an accident to assure the two operable CCW loops required by the technical specifications.

Applying the prior UFSAR guidance that implied only two operable pumps are required, one CCW pump could have been tagged for maintenance at the start* of an accident.

In that case, a single failure could have impacted the two operable pumps and reduced system capability below the minimum safeguards alignment.

SORC: 97-031 lOCFRS0.59 EVALUATIONS MONTH: MARCH 1997 DOCKE.O: 50-272 NAME: Unit 1 CONTACT: R. Ritzman TELEPHONE:

609-339-1445 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 MISCELLANEOUS Safety Evaluation S97-089 Discrepancy Report 970204195 Utilization of Service water as the principal cooling medium for the Unit 1 and 2 Emergency Control Air Compressors Steam Generator Level Sensing Line "Use As Is" Justification

.. , _-c_ , _ .*. PROCEDURE Safety Evaluation S97-080 -Supports procedure IO.ZZ-001 l(Q), Rev. 0, Control Room Operability With Unit 1 Defueled The Salem Technical Specification section identified above was reviewed and determined not to be affected by the proposal.

The Emergency Air Compressors and CA system are not addressed in the Technical Specification and the use of Service Water as a cooling medium is an approved operational mode described in procedure OOOl(Q). Therefore the proposal does not affect the margin of safety defined in any Technical Specification.

Service Water is part of the design basis for ECAC cooling and is listed in the FSAR as a back up source. , . . -SORC: 97-041 The proposal authorizes the use of steam generator narrow range instrumentation for Tech Spec 3/4.4.1.3

.3 surveillance under degraded

..

to peif ormed in t<?

overstress conditions identified in CR 970219114, the steam generator wide and narrow range instrument sensing lines may be subjected to stresses exceeding ANSI B31. l/B31. 7 allowable limits at primary coolant temperatures exceeding 250F. The stresses are a result of steam generator thermal growth and an insufficient sensing line expansion configuration.

SORC: 97-035 This is a new temporary Integrated Operating Procedure which will expire upon Unit 1 transition to operational Mode 6. This procedure provides instructions necessary to verify all required systems and equipment are available (or operable) to ensure Unif 1 CREACS remains operable to support an operable combined Control Room Envelope.

System alignments and Surveillance Requirements are specified to ensure all systems required to support Unit 1 CREACS operability are available or operable.

This procedure also identifies required operator actions should a Unit 2 CREACS actuation occur. SORC: 97-035 lOCFRS0.59 EVALUATIONS MONTH: MARCH 1997

  • DOCKE.O: 50-272 NAME: Unitl CONTACT: R. Ritzman TELEPHONE:

609-339-1445 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 Safety Evaluation S97-092 This proposal supports a revision to the CCHX high flow flush 11(12)(21)(22)

Component procedures--

Sl.OP-PM.CC-001 l(Q) & Sl.OP-PM.CC-0012(Q) and Cooling Water Heat Exchanger S2.0P-PM.CC-0021(Q)

& S2.0P-PM.CC-0022(Q)--

to allow the SW High Flow Flush and Alignment flow through the CCHX to go to 12500 gpm when establishing the CCHX Sl.OP-PM.CC-001 l(Q); SI.OP-SW manual inlet and outlet valve throttle position (11CCHX-11SW121

& PM.CC-0012(Q);

S2.0P-PM.CC-11SW355; 12CCHX-12SW384

& 12SW387; 21CCHX-21SW121

& 002l(Q); S2.0P-PM.CC-0022(Q) 21SW355; 22CCHX-22SW121 & 22SW121 & 22SW356).

This exceeds the nominal operating flow for 10000 gpm stated in FSAR Section 9.2.1, SAR Change Notice 96-109, which is the CCHX design flow. SORC: 97-042 TEMPORARY MODIFICATION Safety Evaluation

  1. 97-0081 Mod 97-006, Rev. 0, Alternate Power Source for #13 Aux. Bldg. Exhaust Fan (1VHE47) Temporary Modification 96-004, Vacuum Interlock Removal -1 lB Circulating Water Pump, Safety Evaluation S96-012 This T-mod provides an alternate power source to No. 13 Auxiliary Building Ventilation (ABV) Exhaust Fan (1VHE47).

The proposed modification will not change the ability of the Auxiliary Building Ventilation System to satisfy the basic criteria for preventing the uncontrolled release of radioactivity.

SORC: 97-038 This T-Mod inserts a jumper to bypass the vacuum pressure switch in the 1 lB circulator starting logic. The T-Mod also revises the circulating water pump operating procedure to require that the condenser water boxes are vented to approximately atmospheric pressure prior to starting the circulator.

The T-Mod is being installed to support Unit 2 startup in that Circulating is to violation of the NJPDES permit requirement limiting thermal discharges to 27.5 F for the unit. Unit 2 Nuclear Service Water discharges into Unit 1 Circulating Water discharge piping. The T-Mod will be removed upon installation of lEC-3537 prior to Mode 4 of Unit 1. The circulator will not be used with the T-Mod installed for normal power operations.

The operation of a circulator with a vented water box has been proven via the installation and the subsequent testing of the Unit 2 DCP. That testing showed that operation of a circulator with the condenser waterboxes vented to atmosphere results in pressures within the design analysis and below the structural design limits. SORC: 97-037 10CFR50.59 EVALUATIONS MONTH: MARCH 1997 *

  • DOCKE.0: 50-272 NAME: Unit 1 CONTACT: R. Ritzman TELEPHONE:

609-339-1445 The following items were evaluated in accordance with the provisions of the Code of Federal Regulations lOCFRS0.59.

The Station Operations Review Committee has reviewed and concurs with these evaluations UFSAR Safety Evaluation, Ref PIRS 960731232 Revision to UFSAR Table 6.2-13 Note on SW 58 and 72 Valves Not Being Subject to Type C Leakrate Testing and Temporary Service Water System Alignment to CFCU' s vs. Containment Integrity UFSAR Change Notice 96-139 Containment Isolation System There are two changes being addressed in this evaluation.

The first change is the clarification of the current note at the bottom ofUFSAR Table 6.2-13 pertaining the SW58 and SW72 valves being exempted from Type C Leakrate testing per I OCFR50 Appendix J. The second change evaluated is a proposed SW system alignment while in Mode 4 with CFCU service water lines drain, and with their respective CIV's closed. SORC: 97-042 This evaluation covers those changes and Clarification which need to be made to the Salem UFSAR so that the licensing basis accurately reflects the design basis for the plants. The changes area result of a review of the UFSAR against the current plarit design and the design requirement of IOCFR50, Appendix A, General Design Criteria 54-57. SORC: 97-035

  • OPERATING DATA REPORT Docket No: 50-272 . . Date: 04/10/97 completed by: Robert Phillips Telephone:

339-2735 Operating Status 1. Unit Name Salem No. 1 Notes 2. Reporting Period March 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 NA This Month Year to Date Cumulative

11. Hours in Reporting Period 744 2160 176565 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
17. Gross Elec. Energy Generated (MWH) 0 0 105301000
18. Net Elec. Energy Gen. (MWH) -2987 -7916 100161350
19. Unit Service Factor 0 0 57.5 20. Unit Availability Factor 0 0 57.5 21. Unit Capacity Factor (using MDC Net) 0 0 51.8 22. Unit Capacity Factor (using DER Net) 0 0 51. 5 23. Unit Forced Outage Rate 100 100 28.1 24. Shutdowns scheduled over next 6 months (type, date and duration of each) Steam Generator replacement.
25. If shutdown at end of Report Period, Estimated Date of startup: Under review. 8-1-7.R2

DAILY UNIT POWER LEVEL tt Docket No.: 50-272 Unit Name: Salem #1 Date: 04/10/97 Completed by: Robert Phillips Telephone:

339-2735 Month March 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 0 14 0 30 0 15 0 31 0 16 0 P. 8.1-7 Rl NO. DATE 3859 2-1-97 F 1 2 F: Forced S: Scheduled DURATION TYPE 1 (HOURS) REASON 2 744 F C Reason A-Equipment Failure (explain)

B-Maintenance or Test C-Refuel ing D-Requlatory Restriction 4 UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH March 1997 METHOD OF SHUTTING DOWN REACTOR LICENSE EVENT REPORT # -----------

zz 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'°"'"-=-2I.,.2:..,,..,.._..__

UNIT NAME: Salem #1 DATE: 04/10/97 COMPLETED BY: Robert Phillips TELEPHONE:

609-339-2735 . CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE

-zzzz Refueling Schedule Extension 4 Exhibit G -Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File CNUREG-0161) 5 Exhibit 1 -Same Source

  • Information Month: March, 1997 Docket No. Unit Name: 50-272 Salem 1 D.Tisdel 609-339-1538 Contact: Telephone:

Month: March, 1997 1. Refueling information has changed from last month: Yes: X No: 2. Scheduled date for next refueling:

To Be Determined

3. Scheduled date for restart following refueling:

To Be Determined

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

Yes: X No: Not Determined to Date: 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

4. Scheduled date (s) for submitting proposed licensing action: To be Determined
5. Important licensing considerations associated with refueling:
6. Number of Fuel Assemblies:
a. Incore: b. In Spent Fuel Storage: 7. Present Licensed spent fuel storage capacity:

Future spent fuel storage capacity:

0 953 1632 1632 8. Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

April 2012

  • SALEM GENERATING STATION . ' MONTHLY OPERATING

SUMMARY

-UNIT 1 MARCH 1997 SALEM UNIT 1 The unit is in a refueling and steam generator replacement 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 the nit 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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