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, Phillips R
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LR-N970258, NUDOCS 9704220161
Download: ML18102A984 (13)
v • d • e


Text

OPS~G*

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.

Sincerely yours, iYl!f.G General Manager -

Salem Operations RAR:tcp Enclosures C Mr. H. J. Miller Regional Administrator USNRC, Region 1 475 Allendale Road King of Prussia, PA 19046

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  • 95-2168 REV. 6/94 L

10CFR5Q.59 EVALUATIONS DOCKE.0: 50-272 MONTH: MARCH 1997 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 The proposal involves the replacement of a relief valve in the circulating Bearing Safety Evaluation S96- water pump bearing lube water section of the Circulating Water System.

064 Lubrication Pressure Relief The modification is within the Circulating Water System and is not Valve (1SC16) Replacement addressed in the Technical Specifications or "Bases". The effects on the Circulating Water System 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 Design Change Packages DCP These change packages replacethe No. -15 and No. 16 Service Water

  • lEC-3408 and lEC-3409, No. Pumps (1SWE5/1SWE6) with pumps that are manufactured of materials 15&16 Service Water Pump that are more resistant to the corrosive and erosive silt laden brackish river Replacements water than the existing pump materials.

SORC: 97-035 Safety Evaluation #97-088 DCP This proposa1.is to modify Salem Unit 1 emergency lighting inverters lEC-3385, Pkg. 2, Rev. 0, 1INV1A15Y, 1INV1B16Y and 1INV1C2Y to change their normal and Emergency Lighting Inverter back-up power source selections. The 125 VDC source will be changed Modification from the regular or normal to the emergency or back-up power source.

SORC: 97-041

10CFR5'1.59 EVALUATIONS DOCKE-0: 50-272 MONTH: MARCH 1997 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 #S97-066 Section 2.0 (Safety Limits), 3/4.1 (Reactivity Control Systems), 3/4.3 UFSAR Change Notice 97-025 (Instrumentation) and 3/4.4 (Reactor Coolant System) of the Salem Units 1 Clarification of the Reactor & 2 Technical Specifications as well as the bases for each of these sections Vessel Head Vent (Reactor were reviewed. There are no changes to any Technical Specification value Coolant System) 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 Safety Evaluation S97-054 DCP This proposal changes the station air compressor 1SAE2 from the existing lEC-3651, Pkg. 2, Rev. 1, total closure control scheme to a total closure control scheme proposed by Modification to Station Air the air compressor vendor for the reduction of cycling which currently Compressor Controls 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 Safety Evaluation S97-055 DCP This proposal changes the station air compressor 1SAE3 from the existing lEC-3651, Pkg. 3, Rev. 1, total closure control scheme to a total closure control scheme proposed by Modification to Station Air the air compressor vendor for the reduction of cycling which currently Compressors Controls 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 DOCKE.O: 50-272 MONTH: MARCH 1997 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 50.54 (p). All Technical Specifications sections were reviewed.

SORC: 97-041 Safety Evaluation S97-083 DCP The reliefvruve 1CV141 has had a history ofleaking through the seat; lEC-3525, Pkg. 1, Rev. 0 numerous maintenance work requests have been written to correct relief Relocation/Replacement of RV valve 1CVl41 leakage and chattering. This proposal implements some of 1CVl41 and Relocation of the recommendations provided in the root cause analysis for CR 1CV63 960113275.

SORC: 97-039 Safety Evaluation S97-093 DCP This proposal replaces the TDl relays in Train A and B of the SSPS with lEE-0346, Pkg. 1 & 2EE-0293, relays which add a time delay-off feature. The modification does not Pkg. 1, Solid State Protection change the design requirements or function of the Safety Injection initiation (SSPS) Safety Injection Reset or reset circuitry or modify the design basis of the affected circuits.

Modification SORC: 97-043 Safety Evaluations, lEC-3330, These change packages replace the No. 13 & No. 14 Service Water Package 1, CP Rev. 2 and lEC- Pumps (1SWE3/lSWE4) with a-pump manufactured of materials that are 3329, Package 1, CP Revision 2 more resistant to the corrosive and erosive silt laden brackish river water _

NO. 13&14 Service Water Pump than the existing pump materials.

Replacements SORC: 97-035

10CFR5().59 EVALUATIONS DOCKE.O: 50-272 MbNTH: MARCH 1997 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 The proposed changes to the RPS Low-Low Tavg signal are intended for lEC-3306, Pkg. 2, Rev. 0 Low- clarification purposes only. The changes being performed by this Low Tavg. Nomenclature Change 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 Safety Evaluation S97-067 DCP The modifications implemented by this DCP are structural in nature and are lEC-3474, Pkg. 1, Rev. 0, High intended to restore the degraded condition and improve reliability of the Energy Line Break Relief Path pressure relief mechanism associated with postulated HELB events in the Modifications Auxiliary Building. The increased capacity and reliability of the modified pressure relief system will result in an increased and adequate margin of

__ _ , __s~fety. __ _ __ _ _. ___. ____ ~- ___ _

SORC: 97-033 Safety Evaluation 897-068 DCP The proposed change package will restore vent panels and their fasteners lEC-3475, Pkg. 1, Rev. 0, Inner to a more reliable condition and improve reliability of the pressure relief and Outer Penetration Area function of these panels. Implementation of the proposed modifications Blowout Panel Modifications will have no negative impact and hence is not considered to represent a reduction in the margin of safety.

SORC: 97-033 MISCELLANEOUS Safety Evaluation #S97-065 on Because certain single active failures can impact two of the three installed Basis for Technical Specification CCW pumps, three CCW pumps must be operable at the start of an 3.7.3 Component Cooling Water accident to assure the two operable CCW loops required by the technical (CCW) System Operability 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 DOCKE.O: 50-272 MONTH: MARCH 1997 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 The Salem Technical Specification section identified above was reviewed Discrepancy Report 970204195 and determined not to be affected by the proposal. The Emergency Air Utilization of Service water as Compressors and CA system are not addressed in the Technical the principal cooling medium for Specification and the use of Service Water as a cooling medium is an the Unit 1 and 2 Emergency approved operational mode described in procedure Sl/2.0P-SO.CA-Control Air Compressors 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 Steam Generator Level Sensing The proposal authorizes the use of steam generator narrow range Line "Use As Is" Justification instrumentation for Tech Spec 3/4.4.1.3 .3 surveillance under degraded (C~9702J?_1_11)_ .. , _-c_ , _ .*. co114itiol1~* . Ac~ofding to ~a~~l:l!~ti~ns peiformed in respo~se t<? p~,~si~le 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 PROCEDURE Safety Evaluation S97-080 - This is a new temporary Integrated Operating Procedure which will expire Supports procedure TSl.OP- upon Unit 1 transition to operational Mode 6. This procedure provides IO.ZZ-001 l(Q), Rev. 0, Control instructions necessary to verify all required systems and equipment are Room Operability With Unit 1 available (or operable) to ensure Unif 1 CREACS remains operable to Defueled 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:

CONTACT:

Unitl 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 #97-0081 T- This T-mod provides an alternate power source to No. 13 Auxiliary Mod 97-006, Rev. 0, Alternate Building Ventilation (ABV) Exhaust Fan (1VHE47). The proposed Power Source for #13 Aux. Bldg. modification will not change the ability of the Auxiliary Building Exhaust Fan (1VHE47) Ventilation System to satisfy the basic criteria for preventing the uncontrolled release of radioactivity.

SORC: 97-038 Temporary Modification 96-004, This T-Mod inserts a jumper to bypass the vacuum pressure switch in the Vacuum Interlock Removal - 1 lB circulator starting logic. The T-Mod also revises the circulating water 1 lB Circulating Water Pump, pump operating procedure to require that the condenser water boxes are Safety Evaluation S96-012 vented to approximately atmospheric pressure prior to starting the circulator. The T-Mod is being installed to support Unit 2 startup in that Circulating ~ater is ne~essary to p~event 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:

CONTACT:

Unit 1 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 There are two changes being addressed in this evaluation. The first change 960731232 Revision to UFSAR is the clarification of the current note at the bottom ofUFSAR Table 6.2-Table 6.2-13 Note on SW 58 and 13 pertaining the SW58 and SW72 valves being exempted from Type C 72 Valves Not Being Subject to Leakrate testing per I OCFR50 Appendix J. The second change evaluated Type C Leakrate Testing and is a proposed SW system alignment while in Mode 4 with CFCU service Temporary Service Water water lines drain, and with their respective CIV's closed.

System Alignment to CFCU' s vs. SORC: 97-042 Containment Integrity UFSAR Change Notice 96-139 This evaluation covers those changes and Clarification which need to be Containment Isolation System 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

. .

completed by:

  • OPERATING DATA REPORT Robert Phillips Docket No:

Date:

Telephone:

50-272 04/10/97 339-2735 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

AVE~ 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

UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH March 1997 DOCKET NO.: -'5::..:0'°"'"-=-2I.,.2:..,,..,.._..__

UNIT NAME: Salem #1 DATE: 04/10/97 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 6 TO PREVENT RECURRENCE -

3859 2-1-97 F 744 FC 4 ----------- zz zzzz Refueling Schedule Extension 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 CNUREG-0161)

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

~e~ueling Month:

Information March, 1997

  • Docket No.

Unit Name:

50-272 Salem 1 Contact: D.Tisdel Telephone: 609-339-1538 Month: March, 1997

1. Refueling information has changed from last month: Yes: X No:
2. Scheduled date for next refueling: To Be Determined Scheduled date for restart following refueling: To Be Determined
3. 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: 0
b. In Spent Fuel Storage: 953
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: 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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