ML18100A550

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Monthly Operating Rept for Jul 1993 for Salem,Unit 1.W/ 930813 Ltr
ML18100A550
Person / Time
Site: Salem PSEG icon.png
Issue date: 07/31/1993
From: Heller R, Shedlock M, Vondra C
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9308190206
Download: ML18100A550 (20)
v • d • e


Text

  • . .e
    • c PSl<<ir Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station August 13, 1993 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sir:

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 copy of the monthly operating reports for the month of July 1993 are being sent to you.

Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Safety Related Maintenance 10CFR50.59 Evaluations Operating Summary Refueling Information Sincerely yours,

~~

General Manager -

Salem Operations RH:pc cc: Mr. Thomas T. Martin Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19046 Enclosures 8-l-7.R4 The Energy People 9308190206 --9-30731-----~ -\ nn 11 95-2189 (10M) 12-89 PDR ADOCK 05000272 :I .J v :t

__ R_ _ PDR iI __

. ~ERAGE DAILY UNIT POWER LE~

Docket No.: 50-272 Unit Name: Salem #1 Date: 8/10/93 Completed by: Mark Shedlock Telephone: 339-2122 Month July 1993 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 1091 17 0 2 1076 18 0 3 1082 19 0 4 1099 20 11 5 1114 21 400 6 1066 22 852 7 1060 23 1048 8 1132 24 1082 9 1049 25 1061 10 1093 26 1092 11 924 27 766 12 0 28 876 13 0 29 1087 14 0 30 1090 15 0 31 1057 16 0 P. 8.1-7 Rl

e OPERATING DATA REPORT e Docket No: 50-272 Date: 08/10/93 Completed by: Mark Shedlock Telephone: 339-2122 Operating Status

1. Unit Name Salem No. 1 Notes
2. Reporting Period July 1993
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 2
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 744 5087 141024
12. No. of Hrs. Rx. was Critical 633.65 4461. 32 93643.30
13. Reactor Reserve Shutdown Hrs. 0 0 0
14. Hours Generator On-Line 531.11 4259.31 90399.72
15. Unit Reserve Shutdown Hours 0 0 0
16. Gross Thermal Energy Generated (MWH) 1713211. 2 13554124.8 285752733.2
17. Gross Elec. Energy Generated (MWH) 558090 4517820 94890810
18. Net Elec. Energy Gen. (MWH) 525855 4297758 90369417
19. Unit Service Factor 71.4 83.7 64.1
20. Unit Availability Factor 71.4 83.7 64.1
21. Unit Capacity Factor (using MDC Net) 63.9 76.4 57.9
22. Unit Capacity Factor (using DER Net) 63.4 75.8 57.5
23. Unit Forced Outage Rate 28.6 16.3 21.3
24. Shutdowns scheduled over next 6 months (type, date and duration of each)

Refueling, 10-02-93 approximately 72 days.

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

NA 8-1-7.R2

UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH JULY 1993 DOCKET NO.: ~5=-'0...,.-~27~2-=---

UNIT NAME: Salem #1 DATE: 08/10/93 COMPLETED BY: Mark Shedlock TELEPHONE: 339-2122 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 0094 6-30-93 F 8.82 B 4 ...................... HF PUMPXX CIRCULATING WATER PUMPS 0099 7-01-93 F 4.5 B 5 ----------- HF PUMP XX CIRCULATING WATER PUMPS 0096 7-03-93 F 3.73 B 5 ----------- HF PUMPXX CONDENSER TUBE & WATER BOX CLEANING 0100 7-06-93 F 6.03 B 5 ...................... HF PUMP XX CONDENSER TUBE & WATER BOX CLEANING 0097 7-07-93 F 24.38 B 5 ...................... HF PUMP XX CONDENSER TUBE & WATER BOX CLEANING 0101 7-08-93 F 13.00 D 5 ----------- HF PUMPXX STM UNITS THERMAL DIS. LIMITS ENVIRONMENTAL 0102 7-08-93 F 48.20 D 5 ----------- HF PUMPXX STM UNITS THERMAL DIS. LIMITS ENVIRONMENTAL 0098 7-08-93 F 4.88 B 5 ----------- HF PUMP XX CIRCULATING WATER PUMPS 0103 7-11-93 F 212.83 B 3 ----------- IB INSTRU NUCLEAR STM GENERATOR CONTROLS 0105 7-27-93 F 7.17 B 5 ----------- HF PUMP XX CIRCULAITNG WATER PUMPS 0106 7-28-93 F 14.65 B 5 ...................... HF PUMP XX. CIRCULATING WATER PUMPS 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)

.. e

  • .SAFETY RELATED MAINTENANCE DOCKET,O: 50-272 MONTH: - JULY 1993 UNIT NAME: SALEM 1 DATE: AUGUST 10, 1993 COMPLETED BY: R. HELLER TELEPHONE: (609)339-2212 WO NO UNIT EQUIPMENT IDENTIFICATION 930106089 1 1 STATION AIR COMPRESSOR FAILURE DESCRIPTION: SAC MAIN OIL PUMP - SEND TO VENDOR TO REPAIR 930112086 1 GRAB SAMPLE PALLET GSP-1 FAILURE DESCRIPTION: VALVES LEAK BY - REBUILD 930417075 1 11 CHILLER COMPRESSOR FAILURE DESCRIPTION: EXCESSIVE RUN TIME - WORN -

REPLACE 930717135 1 lC 125 VDC BUS FAILURE DESCRIPTION: VOLTAGE LOW - ADJUST FLOAT VOLTAGE 930720122 1 FUEL HANDLING BUILDING EXHAUST FAN 1VHE20 FAILURE DESCRIPTION: REPLACE BELTS ON FHB EXHAUST FAN 930729127 1 FUEL HANDLING BUILDING VENT SYSTEM FAILURE DESCRIPTION: FAILED FLOW TESTING - REPAIR

.*: 10CFR50. 59 EVALUATIONS MONTH: - JULY 1993 e DOCKET,O:

UNIT NAME:

50-272 SALEM 1 DATE: AUGUST 10, 1993 COMPLETED BY: R. HELLER TELEPHONE: (609)339-2212 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.

ITEM

SUMMARY

A. Design Change Packages (DCPs) lSC-2298 Pkg 1 "CW-0008 Circulating Water Electrical Upgrade (Non-outage)" - This DCP installs two now 1000 kVA unit substations to provide power for the Circulating Water System auxiliary loads for Salem Generating Station Units 1 & 2. The new substations replace the existing 750 kVA substations. The new unit substations are located near their respective fish houses. The locations of the existing unit substations have led to operation and maintenance problems. The proposed change does not reduce the margin of safety as defined in the basis for any Technical Specification as the Circulating Water System is not specifically covered in the Salem Technical Specifications. (SORC 93-060) lEC-3150 Pkg 1 "Nuclear Header Crossover - Unit 1 11 - This DCP will: 1.) upgrade Service Water Piping; 2.)

eliminate the overpressurization line in the SW valve rooms (delete the SW49 and SW305 valves and ancillary devices); 3.) delete Control Room indication for the SW49 and 305 valves; 4.)

establish set points for 1SW308 and 1SW311 at 130 psig; 4.) provide a means to achieve a minimum 7500 GPM flow single SW pump operation by installing a pump bypass, and 5.) eliminate cavitating conditions at the discharge TEE upstream of the SW79 check valve in the SW valve room. The 11(12)SW50 valves will be replaced with a new design C&S butterfly valve. Pipe flanges will be permanently added in the piping up-stream and down stream of 11CA330. This is a continuation of the service water upgrade project to replace problem area piping with a more corrosion resistant material and to comply with NRC commitments in response to Generic Letter 89-13. There are no safety limits associated with this change, therefore, the change does not reduce the margin of safety as defined in the basis for any Technical Specification. (SORC 93-060)

  • .':1oct~50.59 EVALUATIONS e DOCKET.O:

UNIT NAME:

50-272 MONTH: - JULY 1993 SALEM 1 DATE: AUGUST 10, 1993 COMPLETED BY: R. HELLER TELEPHONE: (609)339-2212 (cont'd)

ITEM

SUMMARY

lSC-2299 Pkg 1 "Replacement of Condenser Manways and Coatings" -

This Design Change Package (DCP) includes the following Unit 1 modifications: a) Install a strainer at each air removal line in the inlet and outlet waterboxes; b) Replace the existing carbon steel condenser manways and covers with stainless steel material; c) Provide new coatings for the six inlet and six outlet waterboxes, associated tubesheets and other internal components for the main steam condenser. The waterboxes will be coated with a thin film (30-35 mils) multilayer coating; the tubesheets will receive a thick film (200 +/- 40 mils) coating; d) Replace 6" waterbox drain valves 11CW31, 11CW131, 12CW31, 12CW131, 13CW31, 13CW131 with stainless steel plug valves.

In addition, all six valves will be relocated to provide better accessibility, and e) Provide a grounding scheme for all twenty-four condenser waterbox manways and covers. The Salem Technical Specifications do not address the Condenser Air Removal System. Therefore, the proposed modifications do not reduce the margin of safety as defined in the basis for any Technical Specification. (SORC 93-060) lEC-3217 Pkg 2 "No.2 Fire Pump Replacement" - This modification replaces the Salem No.2 fire pump, diesel engine driver, battery system, silencer, and controller; relocates the pressure sensing line for the No.2 fire pump to a location between the discharge check valve and discharge control valve; and installs permanent test gauges to perform license required surveillance testing. The proposed modifications do not reduce the margin of safety as defined in the basis for any Technical Specification. (SORC 93-062) lEC-3276 Pkg 1 "Salem Fire Hose House Removals" - This DCP provides for the removal of 15 fire hose houses installed in yard areas around Salem. This will reduce the labor required for conducting annual service pressure testing of the hoses, monthly inventory of contents of each hose house, and general maintenance and upkeep of the hose

,.10C~~50. 59 EVALUATIONS MONTH: - JULY _1993 e DOCKET,O:

UNIT NAME:

50-272 SALEM 1 DATE: AUGUST 10, 1993 COMPLETED BY: R. HELLER TELEPHONE: (609)339-2212 (cont'd)

ITEM

SUMMARY

houses. The proposed modifications do not reduce the margin of safety as defined in the basis for any Technical Specification. (SORC 93-062) lEC-3149 Pkg 1 "Service Water Pipe Replacement for Unit 1 Diesel Generator Piping" - This DCP will upgrade the Service Water supply and.return pipe to the Diesel Generators. The scope of this changeout runs from the 24 11 supply and return pipes which penetrate into the Cardox Storage Tank Room into the Diesel Fuel Oil Storage Tank Rooms and up to the Diesel Rooms. This pipe supplies the Diesel Lube Oil and Jacket Water Coolers. The existing lined carbon/low alloy stainless steel piping has deteriorated as a result of various erosion and corrosion mechanisms. The replacement will be 6%

molybdenum austenitic stainless steel. This package covers all 3 Diesels and will be worked during Modes 5 and 6 and Core Unload - Undefined.

The work will be sequenced so that 2 Diesels and 1 supply and return header will remain operable at all times complying with the Tech Specs for the modes. This DCP also deletes the SW40 valves which originally provided an autodrain function when the Diesels were shutdown; however, this function has been inactive for over 10 years. The proposed modifications do not reduce the margin of safety as defined in the basis for any Technical Specification. {SORC 93-062) lSC-2297 Pkg 1 "CWIS Electrical Installation" - This design change package performs the following plant modifications: 1.) replace the 125 HP Circulating Water No. 14 Screen Wash Pump motor with a 150 HP motor to support increased size pumps installed by an earlier modification; 2.) increase the size of the cables for the Circulating Water No. 11, 12, 13 and 14 Screen Wash Pump motors to accommodate the higher (150 HP) rating; 3.) revise the screen wash header pressure setpoints for the automatic start and stop of the stand-by screen wash pumps; 4.) establish electrical installation of the new 1000 kVA Unit 1 circulating water facility substation and remove the present 750 kVA substation.

..-: lOCt~50. 59 EVALUATIONS e DOCKET,O: 50-272 MONTH: - JULY 1993 UNIT NAME: SALEM 1 DATE: AUGUST 10, 1993 COMPLETED BY: R. HELLER TELEPHONE: (609)339-2212 (cont'd)

ITEM

SUMMARY

This DCP does not reduce the margin of safety as defined in the basis for any Technical Specification. The availability and reliability of the circulating water system is being improved. Therefore, this modification increases the margin of safety by reducing the probability of a challenge to the safety system caused by a reactor trip. (SORC 93-065) lEC-3236 Pkg 1 "Modification to Motor Operated Valve 1SJ135" -

Pursuant to the requirements of Generic Letter 89-10, a MOV capability evaluation of 1SJ135 has been performed (system calculation S-1-SJ-MDC-0908). The results of this analysis and of VOTES testing performed on 1SJ135 indicate that inertia loads associated with the existing 3400 RPM motor will exceed the thrust capability of the operator and valve. The proposed change replaces the existing motor, motor overload heaters and motor gear set for the Limitorque actuator on valve 1SJ135. As presently configured, the 1SJ135 Limitorque Operator has an overall gear ratio {OAR) of 69.6:1 and a measured IST stroke time of =7.4 seconds. This DCP will change the stroke time to =17 seconds by installing a 1700 RPM motor in place of the existing 3400 RPM motor and changing the motor pinion gear and wormshaft gear which increases the overall gear ratio to 78.81:1. This DCP does not reduce the margin of safety as defined in the basis for any Technical Specification. The valve is not specifically mentioned in the Technical Specifications. The safety function to open has been previously assured by administratively controlling the valve in the locked open position in Modes 1-4. (SORC 93-065) lSC-2267 Pkg 3 "Safeguards Equipment Controller - ATI Restoration" - This DCP will install new EPROMs in the ATis of the three SECs and spare chassis. It will activate the ATis for the first time. Output alarm relays will be installed in existing XK-90 and XK-91 sockets. Wires will be terminated, as required to allow annunciation at the Aux and

.... 10CFR50. 59 EVALUATIONS MONTH: - JULY 1993 e DOCKET.:

UNIT NAME:

50-272 SALEM 1 DATE: AUGUST 10, 1993 COMPLETED BY: R. HELLER TELEPHONE: (609)339-2212 (cont'd)

ITEM

SUMMARY

Overhead Annunciator systems. The ATI provides a self checking function of the SEC. No actuation of plant equipment is initiated by the ATI.

Therefore, channel trip accuracy and channel response times are not affected. No channel indication is affected by the ATI restoration.

Therefore, the ATI restoration does not cause a plant parameter for any analyzed event to fall outside of acceptance limits. This DCP does not reduce the margin of safety as defined in the basis for any Technical Specification. The valve is not specifically mentioned in the Technical Specifications. (SORC 93-065) lEC-3243 Pkg 1 "SGFP/Condensate Pump/Feedwater Heaters System Design Press Modification" - The purpose of this DCP is to alleviate the problems concerning the condensate system design pressure. The condensate pump recirculation flow control will then be modified such that the minimum flow recirculation valve would close on condensate pump flow of 5500 gpm increasing. This will ensure that during cold startup, the total pump flow would be 65000 gpm or more, thereby maintaining a maximum sustained nominal pressure of 625 psig. This DCP does not reduce the margin of safety as defined in the basis for any Technical Specification.

(SORC 93-065) lEC-3202 Pkgs 1-3 "Diesel Generator Building Ventilation Upgrade" -

The modifications detailed in this package are summarized as follows: 1.) change the No. 13 Diesel Generator Area safety related ventilation system from the present exhaust type to a positive pressurization supply air system; 2. change the No. 13 Diesel Generator Area outside dampers to fail open on a loss of control air; 3.) change the No. 13 Diesel Generator Control Area ventilation system from the present exhaust type to a positive pressurization supply air system.

The operation of the Diesel Generator Area Ventilation system and the environmental space temperatures in the Diesel Generator

    • .* 10CFR50. 59 EVALUATIONS MONTH: - JULY 1993 e DOCKET~:

UNIT NAME:

50-272 SALEM 1 DATE: AUGUST 10, 1993 COMPLETED BY: R. HELLER TELEPHONE: {609)339-2212 (cont'd)

ITEM

SUMMARY

Building are not addressed in the Technical Specifications. This DCP does not reduce the margin of safety as defined in the basis for any Technical Specification. {SORC 93-065) lEC-3223 Pkg 1 "Platforms, Ladders and Fences" - This design change will: 1.) Install a Self-Supporting Platform with a ladder for access to RHR System Vent Valves 1RH68 and 1RH69; 2.) Install permanent fencing with locking gates at each end of the N16 Decay Tunnel; 3.) Install folding gates at the Bioshield area entrances; 4.) Upgrade existing Bioshield Access Gates and the Gates at the let down Heat Exchanger/Regeneration Exchanger to insure proper locking of Gates; 5.) Install access prevention hinged cover plates on the Steam Generator Access Ladders, similar to plates installed on pressurizer access ladders; 6.)

Install permanent platform over the part of the area above the Reactor Pit; 7.) Install a guardrail with toe boards around the containment Hatch platform; 8.) Install eight platforms, with necessary ladders which will be removable for valve maintenance, two at each of the four MSIV's located in the penetration area. These modifications contribute to or aid in the compliance to the Technical Specifications by providing permanent structures in lieu of temporary structures which are currently in use to accomplish these requirements. There is no reduction in the margin of safety as defined in the basis for any Technical Specification.

{SORC 93-069) lEC-3227 Pkg 1 "Overhead Annunciator Failure Detection" - The purpose of this design change is to provide the operator with enhanced failure detection and operability determination for the overhead Annunciator {OHA} System. The changes are provided to enhance maintenance and troubleshooting. The new alarm design will ensure that all internally identified OHA System malfunctions are alarmed to the Control Room operators. This DCP makes similar changes to Unit

..... 10CF~50. 59 EVALUATIONS MONTH: - JULY 1993 e DOCKET~:

UNIT NAME:

50-272 SALEM 1 DATE: AUGUST 10, 1993 COMPLETED BY: R. HELLER TELEPHONE: (609)339-2212 (cont'd)

ITEM

SUMMARY

1 as were made to Unit 2 in DCP 2EC-3198. A review of the Technical Specifications did not identify any safety limits, limiting safety system settings, setpoints, operational limit or design limit which are impacted by this modification.

There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 93-069) lEC-3256 Pkg 1 "Main steam Flow Instrumentation Sensing Line Modifications" - This modification will: 1.)

replace, reroute and insulate 1 in. carbon steel piping from the steam header connections at the flow elements to respective condensing pots; 2.)

replace and relocate the 1 in. instrument root valves with identical valves to an accessible location clearing interference from polar crane; 3.) replace the existing condensate pots and tees with increased capacity reservoirs and support them; 4.) replace the existing 3/8 in. OD stainless steel instrument tubing from the condensate pots up to the isolation valves at the entry to the respective panels housing the transmitters with 5/8 in. OD.stainless steel tubing, and reroute and support the new 5/8 in. OD tubing in accordance with PSE&G Technical Standards ND.DE-TS.ZZ-1014(Q) for Instrument Piping and Tubing Design; DE-TS.ZZ-1023(Q) for physical separation; and PSE&G Programmatic Standard DE-PS.ZZ-0023(Q) for Pipe Support Design, 5.) delete the existing 3/8 11 block valves at the sensing line tee-offs to the 837 panels. These sensing lines have been rerouted and the distance shortened. In addition, Nuclear qualified block and blow valves were installed at the panel entry, and 6.) provide dirt legs and cleanouts as required for maintenance. The modified sensing line installation is equal to or better than the previous sensing line under all conditions.

Therefore, there is no impact on the margin of safety as defined in the basis for any Technical Specification. (SORC 93-070)

.... 10CFR50. 59 EVALUATIONS MONTH: - JULY 1993 e DOCKET.:

UNIT NAME:

50-272 SALEM 1 DATE: AUGUST 10, 1993 COMPLETED BY: R. HELLER TELEPHONE: (609)339-2212 (cont'd)

ITEM

SUMMARY

lEC-3246 Pkg 1 "Replacement of Degraded Pipe and Fittings with Chrome Alloy steel" - This change package replaces selected carbon steel fitting and pipe segments with chrome alloy steel materials, and in some cases heavier wall materials. The replacement of worn fittings and pipe segments will restore the plant to its analyzed configuration. Therefore, the replacement of the subject fittings and segments does not reduce the margin of safety as defined in the basis of any Technical Specification. (SORC 93-070) lEC-3258 Pkg 1 "Small Bore Piping Replacement" - This DCP entails the replacement of safety related and non-safety related small bore piping (2 inch and smaller) for portions of various plant systems.

In addition, a small quantity of non-safety related large bore piping is also slated for replacement. In general, the existing piping is schedule 40, A-106 carbon steel, which is being replaced with schedule 80, A-335, P22 chrome-moly for severe erosion/corrosion conditions~

Replacement piping will follow the original routing wherever possible, and the existing pipe supports will also be reused wherever possible.

Piping design and pipe supports will only be modified where necessary. Existing carbon steel globe and gate valves in the affected lines will be replaced with new globe valves of improved design, having chrome-moly bodies. Existing insulation on the affected lines will be demolished and scrapped. Replacement piping will be reinsulated using new calcium silicate*material with stainless steel lagging. The details of the small bore piping and components are not addressed in the Technical Specifications. There is no reduction in the margin of safety as defined in the basis for any Technical Specification.

(SORC 93-070) lEC-3245 Pkg 1 "Replace Emergency Lighting Inverters - Salem 1 11 -

This project replaces the three Garret/SCI Emergency Lighting Inverters with higher rated and more efficient Cyberex Inverters and adds a

.... 10CFR50.59 EVALUATIONS MONTH: - JULY 1993 e DOCKET.:

UNIT NAME:

50-272 SALEM 1 DATE: AUGUST 10, 1993 COMPLETED BY: R. HELLER TELEPHONE: (609)339-2212 (cont'd)

ITEM

SUMMARY

redundant Emergency Lighting circuit in the Control Room. Existing Garret/SCI Emergency Lighting Inverters are experiencing end of life and age related fatigue failures. These inverters are also experiencing overloading conditions.

These inverters efficiencies are very low.

Replacement parts are expensive and difficult to obtain. The Technical Specifications do not specifically discuss the Emergency Lighting system. Therefore, the proposed modifications do not affect the margin of safety as defined in the basis for any Technical Specification.

(SORC 93-070) lEC-3219 Pkg 1 "Pressurizer Safety/Relief Valve Piping System Modification" - This modification consists of installation of drain lines and associated manual valves and pipe supports to fully drain the pressurizer Power Operated Valve and Safety Valve loop seals. In addition, existing supports for the SV/PORV piping will be modified as required to be in compliance with code allowable stresses. As part of this modification, the SV internals will be upgraded with steam compatible internals.

Also, appropriate valve modifications will be performed on the PORVs. This DCP is required*to decrease or eliminate the hydrodynamic load effects of the water loop seals at the safety valves (SVs) and power operated relief valve (PORVs) by drainage of both SV and PORV loop seals, thus permitting piping and/or support code compliance. When this DCP is implemented, the Salem Unit 1 plant will be in compliance with Sections 1.2.3 and 1.2.8 of NRC SER TMI Action NUREG-0737 (II.O.l) Relief and Safety Valve Testing Docket Nos. 50-272 and 50-311. This*

modification will not reduce the margin of safety as defined in the basis for any Technical Specification. (SORC 93-070)

.... 10CFR50.59 EVALUATIONS MONTH: - JULY 1993 e DOCKET-:

UNIT NAME:

50~272 SALEM 1 DATE: AUGUST 10, 1993 COMPLETED BY: R. HELLER TELEPHONE: {609)339-2212 (cont'd)

ITEM

SUMMARY

lEC-3274 Pkg 1 "Installation of Secondary Chemistry Lab Readouts in the Control Room" - The purpose of this change is to monitor and alarm chemistry information from the existing Secondary Chemistry Laboratory in the Control Room. A RS-422 data link will be installed between the Chemistry Departments Data Management System (DMS) computer (VAX 4000-300) and two (2) Speedomax 25000 series recorders installed in the 1RP5 panel located in the Control Room. This modification will not reduce the margin of safety as defined in the basis for any Technical Specification. (SORC 93-070) lEC-3249 PKG 1 "Replacement of Spray Valves 1PS1 and 1PS3 Internals" - This modification retrofits the Pressurizer Spray Control Valves 1PS1 and 1PS3 with a new trim package that is designed to provide the reliability required while eliminating the seat leakage problems associated with the existing trim. Also, this modification upgrades the stud bolts and nuts for: 1.) the valve bonnet and the bonnet extension; 2.) the body to bonnet gaskets; 3.) the valve packing; 4.) the actuator spring and 5.) the actuator mounting bolts. The bonnet extension for valve lPSl will also be replaced in kind. The valves will perform all their intended functions in identical fashion as before but with higher reliability. The consequences of a malfunction of equipment important to safety previously analyzed in the SAR have not increased. The reduction in the upper end of the flow rate to its intended value, will reduce the consequences of a stuck open spray valve. This modification will not reduce the margin of safety as defined in the basis for any Technical Specification. {SORC 93-070) lEC-3250 Pkg 1 "Waste Gas Analyzers and Waste Gas Compressors" -

This modification installs a new waste gas analyzer system that meets: a) the requirements of 10CFR50 GDC 67; b) the redundancy requirements of NUREG 0472, and will provide the ability to comply with Technical Specification surveillance

.._.10CFR50.59 EVALUATIONS MONTH: - JULY 1993 e DOCKET.:

UNIT NAME:

50-272 SALEM 1 DATE: AUGUST 10, 1993 COMPLETED BY: R. HELLER TELEPHONE: (609)339-2212 (cont'd)

~

ITEM

SUMMARY

requirement 4.11.2.5. This DCP also modifies the waste gas compressor skids to increase reliability and provide more efficient means to troubleshoot problems when they do occur. These changes will not increase the risk of explosiveness and do not have an effect on the monitoring 0f gaseous effluents. Since no system having a safety function is affected by this modification, the margin of safety is not reduced. (SORC 93-070) lEC-3254 Pkg 1 "Boric Acid Concentration Reduction Modifications"

- This DCP will perform modifications in support of licensing changes being made to the Boric Acid System. These licensing changes are being supported by submittals and recommendations from ABB-CE concerning a reduction of the boric acid concentration in the Boric Acid Tanks (BATs) from 12% to approximately 3.75%. This DCP will provide changes to instruments and components of the Boric Acid System that will incorporate the reduction of concentration of boric acid into the system design basis. Due to the reduction in Boric Acid concentration from 12% to approximately 3.75%,

operational changes in the Boric Acid System are being made. Changing system parameters which will affect boric acid instrumentation include: (a) fluid density, (b) fluid operating temperature, (c) flow rate, (d) tank operating levels ..

Instrumentation associated with the boric acid system which is affected by this DCP will be replaced and/or recalibrated to compensate for the above parameter changes. Where necessary, new calculations have been performed to support any required changes. The ability to keep the boric acid in solution and deliver the required quantity of borated water remains the same. Therefore, the proposed changes do not reduce the margin of safety as defined in the basis for any Technical Specification. (SORC 93-070)

.... 10CFR50.59 EVALUATIONS MONTH: - JULY 1993 e DOCKET.:

UNIT NAME:

50-272 SALEM 1 DATE: AUGUST 10, 1993 COMPLETED. BY: R. HELLER TELEPHONE: (609)339-2212 (cont'd)

ITEM

SUMMARY

B. Safety Evaluations SAR Change 93-26 "Service Water Supply Design Temperature" - The proposed change revises UFSAR Sections 6.1.1.4, 6.2.2.2.2, 9.2, 9.4.2.1, 9.4.4.3.1, 15.4.8.1.2, UFSAR Tables 6.3-13, 9.1-2 and 15.4-22 to reflect the Salem Units 1&2 service water supply design temperature change from 85°F to 90°F. The design limits for systems affected by service water define the acceptable margin of safety. The service water calculation S-C-SW-MDC-1068, shows that this proposal does not exceed the design limits of the systems affected by service water.

It is therefore concluded that this proposal does not reduce the margin of safety as defined in the basis for any Technical Specification.

(SORC 93-070)

c. Temporary Modifications TMOD # 93-055 "Installation of Temporary Filters for Switchgear-Penetration Area Ventilation System" -

This T-MOD will replace existing obsolete roll filter assemblies with new roll filter assemblies. The ventilation system will be run every 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> of system shutdown during T-MOD implementation. The Technical Specification design basis assumption will not be altered, therefore, there is no reduction in the.margin of safety. (SORC 93-062)

TMOD # 93-056 "Installation of Temporary Filters for Control Area Air Conditioning System" - This T-MOD will replace existing obsolete roll filter assemblies with new roll filter assemblies. The Emergency Air Conditioning System will be run during every 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> of Control Area Air Conditioning System shutdown. The Technical Specification design basis assumption will not be altered, therefore, there is no reduction in the margin of safety.

(SORC 93-062)

-~*10CFR50.59 EVALUATIONS MONTH: - JULY 1993 e DOCKET.:

UNIT NAME:

50-272 SALEM 1 DATE: AUGUST 10, 1993 COMPLETED BY: R. HELLER TELEPHONE: (609)339-2212 (cont'd)

ITEM

SUMMARY

TMOD # 93-071 "Cross connect of 12 and 22 BASTs" - This TMOD will cross connect 12 BAST and 22 BAST allowing the transfer of borated water from 22 BAST to 12 BAST utilizing 22 BAT pump. This will support the additional BAST volume needed f.or reactivity control during mode change on Unit 1. The cross connect, located at the discharge of 22 BAT pump and the inlet to 12 BAST, will use a 3/4" a stainless steel flexible hose and pipe as a tie in at valves 12 & 22CV158. The TMOD will be isolated when both sample valves are closed. The temporary pipe will be heat traced and insulated to prevent boron from crystallizing. At all times for both units, the limiting condition for operation will be satisfied per Technical Specification requirements. The refueling water storage tank will not be affected. The Technical Specification design basis assumption will not be altered, therefore, there is no reduction in the margin of safety. (SORC 93-064)

TMOD # 93-062 "Emergency Lighting Inverters Bypass" - The purpose of this modification is to provide temporary power supply to emergency lighting distribution panels lELD-A, lELDOB, and lELC during their inverter replacement. The proposal does not change the function, performance, or operation of the Emergency Lighting System. The temporary cables will be removed after installation of the new inverters and equipment will be returned to normal plant configuration.

The proposal does not reduce the margin of safety as defined in the basis for any Technical Specification. (SORC 93-070)

SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT 1 JULY 1993 SALEM UNIT NO. 1 The unit began the period operating at full power, and continued to operate at full power until July 11, 1993, when a reactor trip occurred due to low level in #12 Steam Generator. Troubleshooting of the feedwater control system was in progress _at the time of the trip.

The return to service was delayed due to problems in the solid state protection system (SSPS). A design change was performed to correct the problems and the unit was returned to service on July 20, 1993. A power increase was performed and the unit achieved 100% power on July 23, 1993. The unit continued to operate at 100% until July 28, 1993, when power was reduced to 58% to*repair a transformer termination at Hope Creek. The repairs were completed and the unit was returned to 100% power on July 28, 1993. Power was reduced to 72% for a brief period on July 30, 1993 to repair a turbine auxiliaries cooling heat exchanger leak. The unit was returned.to 100% power on July 31, 1993, and continued to operate at full power throughout the remainder of the period.

  • *REFUELING INFORMATION DOCKET.: 50-272 MONTH: - JULY 1993 UNIT NAME: SALEM 1 DATE: AUGUST 10, 1993 COMPLETED BY: R. HELLER TELEPHONE: (609)339-2212 MONTH JULY 1993
1. Refueling information has changed from last month:

YES NO X

2. Scheduled date for next refueling: OCTOBER 2, 1993
3. Scheduled date for restart following refueling: DECEMBER 13, 1993
4. 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?:

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

N/A

6. Important licensing considerations associated with refueling:
7. Number of Fuel Assemblies:
a. Incore 193
b. In Spent Fuel Storage 656
8. Present licensed spent fuel storage capacity: 1170 Future spent fuel storage capacity: 1170
9. Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: September 2001 8-1-7.R4
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