ML18102A187

Monthly Operating Rept for May 1996 for Salem Unit 2. W/960615 Ltr

ML18102A187
Person / Time
Site:	Salem
Issue date:	05/31/1996
From:	Garchow D, Heller R, Phillips R Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9606200227
Download: ML18102A187 (14)

Text

PS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit June 15, 1996 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn.: Document Control Desk MONTHLY OPERATING REPORT SALEMNO. 2 DOCKET NO: 50-311 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 May is being sent to you.

QZ;u~. tJ David F. Gar91!::.

General Manager - .

Salem Operations RH:vls Enclosures C Mr. Thomas T. Martin Regional Administrator USNRC, Region I 475 Allendale Road King of Prussia, PA 19046

-~9606200227 9650005303111

~DR ADOCK 0 PDR The power is in your hands.

95-2168 REV. 6/94

~RAGE DAILY UNIT POWER LE~

Docket No.: 50-311 Unit Name: Salem #2 Date: 06/10/96 Completed by: Robert Phillips Telephone: 339-2735 Month May 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

OPERATING DATA REPORT Docket No: 50-311 Date: 06/10/96 Completed by: Robert Phillips Telephone: 339-2735 Operating Status

1. Unit Name Salem No. 2 Notes

2. Reporting Period May 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) N/A 1o~Reasons for Restrictions, if any NA This Month Year to Date Cumulative

11. Hours in Reporting Period . 744 3647 128280 l2o 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 187781005.0

17. Gross Elec. Energy Generated (MWH) 0 0 78648898

18. Net Elec. Energy Gen. (MWH) -2623 -14759 74726295

19. Unit Service Factor 0 0 58.6

20. Unit Availability Factor 0 0 58.6

21. Unit Capacity Factor (using MDC Net) 0 0 52.7

22. Unit Capacity Factor (using DER Net) 0 0 52.2

23. Unit Forced Outage Rate 100 100 27.1

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

Forced Outage extension of a refueling outage.

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

August 27, 1996.

8-l-7.R2

UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH May 1996 DOCKET NO. 50-311 UNIT NAME Salem #2 DATE 06-10-96.

COMPLETED BY Robert Phillips TELEPHONE 609-339-2735 METHOD OF SHUTTING LICENSE DURATION DOWN EVENT SYSTEM COMPONENT CAUSE AND CORRECTIVE ACTION 1 2 NO. DATE TYPE (HOURS) REASON REACTOR REPORT # CODE 4 CODE 5 TO PREVENT RECURRENCE 3859 05-01-96 F 744 F c 4 ---------- zz zzzz Refueling Schedule Exceeded 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 (LER) 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)

IOCFR50.59 EVALUATIONS DOCKET NO: 50-311 MONTH: MAY 1996 UNIT NAME: SALEM2 DATE: 06/10/96 COMPLETED BY: R.HELLER TELEPHONE: 609-339-5162 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.

1. Design Change Packages (DCP) 2EC-3467, Pkgs. 1&2 "Package 1 - Modification to SJ1&2 Valve Disks I Package 2 - Modification to SJl 13 Valve Disks" - This DCP drills 1/8" weep holes in the valve disc of valves 2SJ1, 2SJ2 and 2SJ113. The margin of safety as defined in the bases for the Technical Specifications will not be reduced. The Safety Injection System reliability will be enhanced by providing an internal relief path for any fluid trapped in the valve bonnets, thus ensuring valve operability. (SORC 96-041) 2EC-3403, Pkg. 3 "EDG 2C Fuel Oil Day Tank Level Switch Setpoint Changes" Rev. 1 - This DCP raises the EDG 2C Fuel Oil

. Day Tank low level alarm and back-up pump start setpoint on 2LD 7064 from 18" to 27". It also lowers the primary stop setpoint for the transfer pumps on switch 2LD 7065 from 46" to 43" and lowers the secondary stop setpoint for the transfer pumps/high tank level alarm switch 2LD 7067 from 47" to 45". All MMIS ICD tolerances will be 1/2 inch for consistency. These changes are in the conservative direction for the back-up pump start and low level alarm setpoint so the margin of safety will be increased.

(SORC 96-041) 2EC-3468, Pkg. 1 "Resolving SW Control Valves 2SW308/311 Issues" Rev. 0

- This modification addresses the two Unit 2 SW Pump Recirc lines in the SW Intake Structure Bay No. 2 (Valve 2SW308) and Bay No. 4 (Valve 2SW3 l l). This DCP raises the SW Recirc Valve setpoint from 130# to 150#. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 96-024)

10CFR50.59 EVALUATIONS DOCKET NO: 50-311 MONTH: MAY 1996 UNIT NAME: SALEM2 DATE: 06/10/96 COMPLETED BY: R.HELLER TELEPHONE: 609-339-5162 (Cont'd) 2EC-3478, Pkg. 1 "Relief Valve Replacement and Relocation" Rev. 0 - This modification replaces the existing safety relief valve (2CV141) with a Crosby model JRAK-BS bellows style safety relief valve. The modification also relocates 2CV141 and check valve 2CV63 further away from the slow oscillations caused by the pulsation dampener and elbow.

The new configuration places the check valve downstream of2CV141 to eliminate the starvation potential (and subsequent flow oscillation) caused by the check valve being located upstream of the relief valve. This modification does not reduce the margin of safety as defined in the basis for the Technical Specifications. (SORC 96-050) 2EE-0142, Pkg. 1 "Valve 2HY15 Replacement" Rev. 0 - This DCP replaces (2HY15), the Hydrogen Pressure Regulator for the Volume Control Tank (VCT). A new control air line is being run from the control air supply through an existing penetration on the Auxiliary Building roof. The design change involves replacement of a non safety related valve with a more reliable component. This component is not directly a part of a Technical Specification system and does not support the function of any other safety related systems. The proposed modification does not affect the emergency boration paths or flow rates assumed in the design bases section of the Technical Specifications. The required rapid boration flow rates from the boric acid tanks are not affected by fluctuations in the VCT cover gas pressure. Therefore, this modification does not reduce the margin of safety as defined in the basic for any Technical Specifications.

(SORC 96-025) 2EC-3266 Pkg. 1 "DIG LIO Temperature Low Alarm Setpoint" Rev. 0 - This change accomplishes three tasks. First, 2A Emergency DG (EDG) lube oil pump heater failure alarm temperature switch and lube oil heater control switch (0-400°F) are replaced with similar, 0-250°F range switches.

10CFR50.59 EVALUATIONS DOCKET NO: 50-311 MONTH: MAY 1996 UNIT NAME: SALEM2 DATE: 06/10/96 C01\1PLETED BY: R. HELLER TELEPHONE: 609-339-5162 Temperature sensor locations on 2C EDG will be rearranged to facilitate consistent physical arrangement of both the heaters and heater failure alarm. Following the switch replacement and sensor rearrangement, the low temperature alarm setpoint will be raised from 80°F to 100°F for all three Diesel Generator Lube Oil Heater Failure Alarm low temperature setpoints. Neither the high temperature setpoint nor the heater on and off setpoints will be affected. This change does not affect the margin of safety. (SORC 96-034) 2EC-3287, Pkg. 2 "Service Water Large Bore Pipe Replacement" Rev. 0 -

This DCP replaces service water piping in the Unit 2 Auxiliary Building. The change involves replacement of 20" and 24" supply and return piping and associated 16", 1O" and 6" branch connections supporting service water nuclear header no. 22. Replacement piping will be 6% molybdenum austenitic stainless steel. An inspection port will be added to a new spool on the return header per Generic Letter 89-

13. The DCP includes the replacement of temperature indicator and restriction orifices 2R01, 15, 16 and 20, the addition of a full open flow orifice, 2R0263 in the no. 22 CCHX supply line and the removal/deletion of valve 22SW928. Associated with the pipe replacement, wall anchors 2P-SWA-WS10 and 2P-SWA-WS102 have been modified to accommodate the new pipe material. These changes do not affect the margin of safety. (SORC 96-018) 2EC-3288, Pkg. 2 "Piping Replacement for Service Water Intake Bays# 3 and

1. 4" Rev. 0 - The DCP replaces service water piping in the Unit 2 Intake Bay 4 and Unit 1Bay3. The change replaces 24" and 30" piping, including the nuclear header supply piping, main header crosstie piping, turbine crossconnect header piping and the discharge piping from service water pump No. 25. Ultrasonic flow computers 2FL14762 and 2FL14763 will be modified for compatibility with the

10CFR50.59 EVALUATIONS DOCKET NO: 50-311 MONTH: MAY 1996 UNIT NAME: SALEM2 DATE: 06/10/96 COMPLETED BY: R. HELLER TELEPHONE: 609-3 3 9-5162 (Cont'd) replacement piping due to the differences in the ultrasonic characteristics between the existing cement lined carbon steel pipe and the new stainless steel pipe. (SORC 96-018) 2EC-3309, Pkg. 1 "Service Water Large Bore Pipe Replacement" Rev. 0 -

This DCP replaces the existing service water piping with a 6% molybdenum stainless steel material as part of the ongoing service water pipe replacement effort. These modifications upgrade the pipe material from cement or epoxy lined carbon steel to 6% molybdenum austenitic stainless steel. The new material provides superior corrosion resistance relative to the existing material. The piping material, fabrication, installation and configuration has been designed to meet or exceed the original design basis. Therefore, the modifications do not reduce the margin of safety. (SORC 96-001) 2EC-3338, Pkgs. 5&6 "Group Bus UV Protection - Condensate Pumps" Rev. 0 -

This change package modifies the control circuit of the Unit 2 Condensate Pump No. 21 by adding wiring (2 conductors) in the 2H 4160 Volt Group Bus Auxiliary Relay Cubicle from the 27X/CIRC Relay to terminal block "B" within the Auxiliary Relay enclosure. The modifications do not reduce the margin of safety. (SORC 96-047) 2EC-3349, Pkg. 3 "2C EDG Starting Air & Turbo Boost System Upgrades" Rev. 0 - This DCP upgrades the existing carbon steel piping and components in both safety related and non-safety related portions of the 2C Emergency Diesel Generator (EDG) starting air and turbo boost systems. New piping and valves (safety related and non-safety related) will be stainless steel to the extent practicable. These modifications upgrade the starting air and turbo boost systems to decrease their susceptibility to corrosion and improve their performance and reliability. There is no reduction in the margin of safety as defined in the bases for any Technical Specification. (SORC 96-040)

10CFR50.59 EVALUATIONS DOCKET NO: 50-311 MONTH: MAY 1996 UNIT NAME: SALEM2 DATE: 06/10/96 COMPLETED BY: R.HELLER TELEPHONE: 609-3 3 9-5162 2EC-3390, Pkg. 1 "Annular Steel Column and Surface Channel Modifications" Rev. 0 - This change modifies annular steel columns in eight (8) locations by bracing the columns to the crane wall with W6 members. The surface mounted channels will be modified by the addition of an angle bracket to reduce their span length. One light fixture will be relocated to facilitate this modification. This modification increases the margin for the annular steel columns and surface mounted channels.

Consequently, this proposed modification is not considered a reduction in the technical specification margin of safety.

(SORC 96-033) 2EC-3404, Pkg.3 "Modify 2B Emergency Diesel Generator to Increase Vibration Tolerance" Rev. 0 - This DCP increases the vibration tolerance characteristics of the 2B Diesel Generator and associated equipment by hardening the diesel against vibration related degradation. Modifications involve adding and replacing flex hoses, isolating components from sources of vibration, providing additional flexibility between components, providing additional supports and bracing and removing the engine and generator mounted vibration switches. These modifications will mitigate the problems associated with the vibration of safety related components, thus, increasing the reliability of the EDG. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 96-029) 2EC-3442, Pkg. 3 "DIG Crankcase Exhaust Piping Modification" Rev. 0 - This modification involves the removal of the Temporary Modification and rerouting the Emergency Diesel Generator (EDG) crankcase exhaust vent piping in order to provide a permanent corrective modification. This modification will reroute the crankcase exhaust fumes at a location and elevation remote from the EDG control room ventilation intake to prevent recirculation of the fumes. Additionally, the piping will be provided tornado missile protection in accordance with Regulatory Guides 1.117 and 1. 9.

10CFR50.59 EVALUATIONS DOCKET NO: 50-311 MONTH: MAY 1996 UNIT NAME: SALEM2 DATE: 06/10/96 COMPLETED BY: R.HELLER TELEPHONE: 609-339-5162 There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 96-043) 2EC-3396, Pkg. 1 "Installation of Transfer Switches for Appendix R Alternate Shutdown" Rev. 0 - Motor Control Center (MCC) and control panel circuits for 36 components (3 chillers, 17 valves, 4 vent fans, 8 room coolers and 4 pumps) will be modified to include local switches which isolate component wiring from the Control Room, Relay room and ceiling area of the 460-230 Switchgear Room, thus precluding the necessity of electrical wiring modifications and jumpers to operate the subject equipment to achieve Hot Standby in the event of a fire in these areas. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 96-046) 2EE-0248, Pkg. 1 "No. 22 Centrifugal Charging Pump Outboard Mechanical Seal Housing Replacement" Rev. 0 - This DCP replaces the No. 22 Centrifugal Charging Pump outboard mechanical seal housing with a seal housing of a later design which is air cooled. The existing component cooling water connections to the seal housing will be removed. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 96-056)

2. Procedures and Revisions S2.MD-FR.DG-000l(Q) "Temporary Power for the Emergency Diesel Generator 22 Fuel Oil Transfer Pump" - This change affects the basic design of the Diesel Fuel Oil Transfer System in that the 22 Fuel Oil Transfer Pump will be temporarily powered from a portable diesel generator. This alternate feed will provide an additional "Defense-in-Depth" measure that will ensure that 2A and 2C Diesels will have both transfer pumps available for their respective diesel day tank fuel oil supply.

The portable diesel generator will be required to supply the correct horsepower and current that normally feeds the 22

IOCFR50.59 EVALUATIONS DOCKET NO: 50-311 MONTH: MAY 1996 UNIT NAME: SALEM2 DATE: 06/10/96 COMPLETED BY: R.HELLER TELEPHONE: 609-3 3 9-5162 Fuel Oil Transfer Pump. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 96-069)

TS2.MD-CM.CAV-0001(Q) "Temporary Blank Installation for Control Area Supply Fan" Rev. 0 - The Unit 2 SPAVS supply fans are described in the UFSAR. In order to support maintenance (motor removal) on 1 of3 system supply fans, this proposed procedure will install a blank plate to isolate a supply fan from the rest of the system. The upstream and downstream plenums for Switchgear and Penetration Area Ventilation System (SP AVS) must be isolated to prevent short circuiting of the air flow pattern. Only 1 supply fan will be in service during the blank installation/removal. While 2 supply fans are out of service, the SP AVS areas will be monitored for temperature. This proposal does not reduce the margin of safety as defined in the basis for any Technical Specifications. (SORC 96-068)

3. Safety Evaluations DR 960508069 "Freeze Seal of the Service Water supply to the 21 Containment Spray Pump Room Cooler" The proposal is to install a freeze seal on the 1-1 /2", austentic stainless steel, service water cooling supply line to the 21 Containment Spray Pump Room Cooler. The freeze seal is necessary to allow a gasket repair and orifice plate replacement to the 2F16055 flow orifice as the existing service water room cooler isolation valve, 21SW464, is leaking by preventing full system isolation. The contingency plan includes provisions for minimizing the amount of leakage from the service water system in the event of a failed freeze seal.

There is no reduction in the margin of safety as defined in the bases for any Technical Specifications. (SORC 96-060)

10CFR50.59 EVALUATIONS DOCKET NO: 50-311 MONTH: MAY 1996 UNIT NAME: SALEM2 DATE: 06/10/96 COMPLETED BY: R.HELLER TELEPHONE: 609-3 3 9-5162 2-IOP-7 "Fuel Handling Area Ventilation System Interim Design Basis Condition" Rev. 10 - This safety evaluation changes certain accident assumptions to conform to actual plant conditions for this interim design basis. In particular, the assumption on time since reactor shutdown is changed from the design basis case of 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> to the actual decay time since shutdown of Unit 2. Hence, the proposal constitutes a change to the facility as described in the UFSAR. Since this safety evaluation documents analyses which show filtration of potential radioactive releases is not required under current plant conditions, the margin of safety has not been reduced. (SORC 96-066) 2-IOP-10 "Fuel Handling Area Ventilation System Interim Design Basis Condition" Rev. 1 - PR Number 950908540, CRCA

1. 12, identifies the need to address the design basis for FHB area radiation monitors. This issue is related to both automatic start-up of the system and automatic initiation of flow through HEP A filters and charcoal adsorbers on receipt of a high radiation signal. With regard to automatic switch-over of flow trains, a future analysis will be required to demonstrate potential releases prior to transfer of flow to the filter path do not exceed allowable limits. In addition, PR Number 960125282, CREV #01, indicates one FHA ventilation exhaust fan must be in-service to maintain spent fuel pool temperature below 180 degrees F in the event of loss of forced cooling, until various design basis issues are resolved related to fuel pool boiling. This safety evaluation demonstrates that regardless of the impact of these issues with respect to the design basis case, under current plant conditions, they have no significant safety impact. Fuel handling activities may safely proceed under the restrictions contained herein until these issues are finally resolved. The margin of safety, as defined in the bases of the applicable Technical Specifications, has not been reduced.

(SORC 96-071)

REFUELING INFORMATION DOCKET NO: 50-311 MONTH: MAY 1996 UNIT NAME: SALEM2 DATE: 06110196 COMPLETED BY: R. HELLER TELEPHONE: 609-339-5162 MONTH: MAY 1996

1. Refueling information has changed from last month: YES . X . NO ""-"_ _...

2. Scheduled date for next refueling: (currently in refueling)

Scheduled date for restart following refueling: 8/27/96

3. 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)

5. Scheduled date(s) for submitting proposed licensing action: . n/a

6. Important licensing considerations associated with refueling:

7. Number of Fuel Assemblies:

a. lncore 0

b. In Spent Fuel Storage 777

8. Present licensed spent fuel storage capacity: 1632 Future spent fuel storage capacity: 1632

9. Date oflast refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: March 2012 8-l-7.R4

SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT 2 MAY 1996 SALEM UNIT NO. 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 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