ML20203L289

Annual Rept for LaSalle County Station for Period Jan-Dec 1997

ML20203L289
Person / Time
Site:	LaSalle
Issue date:	12/31/1997
From:	Dacimo F COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9803050433
Download: ML20203L289 (77)

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\larwillir 11. 614 e l 9T icisi u s 4, ni February 28,1998 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555

Subject:

Annual Report for LaSalle County Station LaSalle County Station, Units 1 and 2 Facility Operating License NPF-11 and NPF-18 NRC Docket Nos. 50-373 and 50-374 Enclosed is the Annual Report for LaSalle County Station for the period Januan/,1997, through December 1997 If there are any questions or comments conceming this letter, please refer them to Perry Bames, Regulatory Assurance Manager, at (815) 357-6761, extension 2383.

Pespectfully,

[

Fred Dacimo Site Vice President LaSalle County Station Enclosure r

cc: A. B. Beach, NRC Region Ill Administrator M. P. Huber, NRC Senior Resident inspector - LaSalle C. Mathews, IDNS Resident inspector - LaSalie D. M. Skay, Project Manager - NRR - LaSalle '

s F. Niziolek, Office of Nuclear Facility Safety - IDNS /LL '/

D. L. Farrar, Nuclear Regulatory Services Manager, NORS .I, F l Institute of Nuc!sar Power Operations - Records Center GE Representative - LaSalle

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9803050433 971231 l$hllhlllhlhl i FDR ADOCK 05000373 **' hl hhll l R PDR l

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ANNUAL REPORT FOR LASALLE COUNTY NUCLEAR STATION JANUARY 1997 THROUGH DECEMBER 1997 1

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Table of Contents Section Title Page j l. Introduction 3 11, Annuai Reportable Documentation for Units 1 and Unit 2 4 1

II. A Summary of Operating Experience 4

11. B Unit Restart Activities ( AdditionalInformation on Att. A and B ) 4 Radiation Exposure (AdditionalInformation on Att. C )

11.C 4-ll. D Indications of Failed Fuel Elements 4 II, E Tests and Experiments not Described in the Safety Analysis Report 4 ll. F Summary of Changes to the Facility Described in the Safety 4 Analysis Report ll. G Summary of Changes to Procedures Described in the Safety 16 Analysis Report 11.H Survey of Evaluation Results of Chlorine Shipments by Barge on the 26 Illinois River ( Additional Information on Att. D )

ll. I Summary of Even s Violating Technical Specification 3.4.5 Primary 26 Coolant lodine Spiking Exceeding Allowable Limits-2

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l. Introduction The LaSalle County Nuclear Station is a two-unit facility owned by Commonwealth Edison Company and located near Marseilles, Illinois. Each unit is a Boiling Water Reactor with a designed net electrical output of 1078 Megawatts. Waste heat is rejected to a man-made cooling pond using the Illinois River for make-up and blow-down. The Architect Engineer was Sargent and Lundy and the contractor was Commonwealth Edison Company.

Unit one was issued operating license number NPF 11 on April 17,1982. Initial criticality was

- achieved on June 21,1982 and commerclal power operation commenced on January,1984.

Unit two was issued operating license number NPF-18 on December 16,1983. Initial criticality-was achieved on March 10,1984 and commercial power operation commenced on October 1984.

This report was compiled by Lyle E. Calfa, telephone number (815) 357-6761, extension 2620.

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11. Annual Reportable Documentation for Unit 1 and Unit 2 A. Summarv of Operatina Exoerience The summary of the operating experience has been reported mor,thly in LaSalle's NRC Monthly Reports dated January 1997 throgh December 1997. Both units were shutdown for the entire 1997 year. Unit 1 was in a maintenance outage due to management and engineering concerns. Unit 2 was in an extended refueling outage and remained down also due to management and engineering concerns.

B ,- Unit Restart Activities

- For units restart activities see Attachment A. For safety related corrective maintenance performed for the units restart activities see Attachment B.

. C. Radiption Exposure For the radiatior exposure of LaSalle Station personnel for the reporting period of January 1997 through December 1997, see Attachment C.

D. Indications of Failed Fuel Elements During this reporting period, January 1,1997, through December 31,1997, there were no indications of failed fuel elements.

E. Tests and Experiments Not Described in the Safety Analysis Report During this reporting period, January 1,1997, through December 31,1997, there were no tests or experiments conducted that are not described in the Final Safety Anclysis Report.

F. Summarv of Chanaes to the Facility Described in the Safety Analysis Report The 10CFR50.59 safety evaluations concluded that there were no unreviewed safety questions associated with the following facility changes:

ADDITION 07 DRAIN CONNECTION TO PIPELINE 1RH83AA 20" PER DESIGN CHANGE PACKAGE (DCP) 9700147 The design change installed a 4" drain connection to pipeline 1RH83AA-20", This pipeline was used b dewater the piping to permit repairs to Residual Heat Removal (RHR) valve 1E12-F068A. UFSAR drawing M-87 Sheet 2 was revised to reflect the

_ design change.

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UPDATE TO UFSAR TABLES 7.3 5 AND 7.7 4 TO REFLECT DESIGN CHANGE PACKAGE (DCP) 9700562 Design change 9700562, "SRM Retract Permissive and Downscale Trip Setpoint Revision", revised the Unit 1 Source Range Monitor (SRM) retract permit and downscale trip setpoint. The retract setpoint was revised to 306 counts per sec (CPS) from 100 CPS, whereas the downscale trip setpoint was revised to 1.51 CPS from 1.18 CPS.

UFSAR Tables 7.3-5,

• Control Rod Block Instrumentation Setpoints", and 7.7-4, "SRM System Trips", were revised to reflect engineering setpoint calculation L-001343.

UNIT 1 DIVISION 2 RESIDUAL HEAT REMOVAL - SERVICE WATER KEEP FILL CROSS TIE, DESIGN CHANGE PACKAGE 9600195 The detign change added two cross-ties to Division 2 of the Unit 1 Residual Heat Removal (RHR) - Service Water (WS) system to ensure that it is kept filled and pressurized. One cross-tie is from the service water system, the other is from the Diesel Generator Cooling Water (DGCW) system. The cross-tie from WS will keep the RHR-WS system filled during normal operation, while the cross-tie from the DGCW will keep it i filled in the event of an accident, Loss of Offsite Power (LOOP), or seismic event.

UFSAR Sections 7.3.3.3.1,9.2.1.2,9.2.1.5,9.2.2, and 9.2.2.2 were revised to include a discussion of the keep fili for Division 2 RHR-WS, addressino an overview of the keep fill system, interfaces with DGCW, and alarm annunciation, ECCS SUCTION STRAINER REPLACEMENT PER DFSIGN CHANGE PACKAGE (DCP) 9600290 The design change replaced the Emergency Core Cooling System (ECCS) suction strainer on the Unit 1 "A" Residual Heat Remeval (RHR) system suction line in the ruopression Pool. The replacement strainer increased capacity to reduce pump net positive suction head (NPSH) loss due to the accumulated strainer debris that results from a design basis leak or Loss of Coolant Accident (LOCA). The strainer installation partially addresses the actions required by NRC Bulletin 96-03. UFSAR Drawing M-96 Sheet 2 for the Unit 1 RHR system was revised to reflect the strainer replacement.

MACHINING OF BASE PLATE FOR THE 1DG01P COOLING WATER PUMP PER DESIGN CHANGE PACKAGE (DCP) 9700154 Pump / motor shaft alignment of the 1 A Diesel Generator Cooling Water Pump 1DG01P was found to be out of tolerance following maintenance. The design change provided details for grinding or machining the baseplate of 1DG01P in order to achieve proper shaft alignment.

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MACHINING OF THE 1DG01P DIESEL GENERATOR COOLING WATER PUMP CASE TO RESTORE CONCENTRIC BORE PER DESIGN CHANGE PACKAGE (DCP) 9700534 During maintenance activities on the 1DG01P Diesel Generator Cooling Water Pump, machining and weld buildup was performed. As a result of the repairs, the casing halves were warped and st.rinkage of components occurred. The dimensions were found to be less than those listed on the vendor drawing following repairs for the casing flange thickness, bearing cap wall thickness, and seal gland end-to-end dimensions.

The design change accepted the reduced dimensions -

MODIFICATION OF TIE BM LATE FOR ACTUATOR 1TZ VX008B PER DESIGN CHANGE PACKAGE (DCP) sr00460 The tie back plate for actuator 1TZ VX0088 for ventilation damper 1VX08Y was modified to support the replacement of the actuator.

PRESSURE LOCKING OF T HE 1E12-F003B VALVE PE.: 9ESIGN CHANGE PACKAGE (DCP) 9600167 The design change authorized the drilling of a 1/4" vent hole in the reactor vessel side disc of the "B' Residual Heat Removal (RHR) Heat Exchanger outlet valve 1E12-F0038.

The hole connects the process piping with the valve bonnet to prevent pressure or hydraulic locking of the valve.

PRESSURE LOCKING OF THE 1E12-F003A VALVE PER DESIGN CHANGE PACKAGE (DCP) 9600166 The design change authorized the drilling of a 1/4" vent hole in the reactor vessel side disc of the 'N Residual Heat Removal (RHR) Heat Exchanger outlet valve 1E12-F003A.

The hole connects the process piping with the valve bonnet to prevent pressure or hydraulic locking of the valve.

REPAIRS TO VALVE 1E12 F068B PER DESIGN CHANGE PACKAGE (DCP) 9700144 The design change repaired the internals of Residual Heat Removal (RHR) valve 1E12-F0688 which included, replacing the carbon steel valve disc with a stainless steel disc, replacing the carbon stee! disc guides with stellite faced carbon steel disc guides, replacing the stainless steel valve stem with a stem of differing grade of stainless steel; replacing the spiral wound stainless steel asbestos bonnet gasket with a spiral wound stainless steel graphite filled gasket, replacing the stem nut, bonnet studs, and bonnet nuts like-for-like.

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MODIFY TIE BACK PLATES FOR ACTUATOR 2TZ VD003C PER DESIGN CHANGE PACKAGE (DCP) 9700333 Actuator 2TZ VD003C for the Unit 2 high pressure core spray (HPCS) Diesel Generator (DG) ventilation exhaust control damper 2VD03YA was replaced with an approved alternate replacement. The design change modified the tie back plate to support the replacement of the actuator.

SEISMIC RESTRAINTS FOR MON-SEISMIC EQUIPMENT IN UNIT 2 SWITCHGEAR ROOMS, DESIGN CHANGE PACKAGE (DCP) 9700386 The design change installed seismic restraints in Unit 2 Division 1 and Division 2 switchgear rooms. The restraints were installed to ensure that the non-seismic equipment does not impact safety related equipment in the area during a seismic event.

ADDITION OF HOLE TO REACTOR BUILDING EQUIPMENT DRAIN LINE 1RFb1 AA-4" PER DESIGN CHANGE PACKAGE (DCP) 9700448 4

The design change installed a 0.5" drain hole in the discharge piping associated with and immediately downstream of Residual Heat Removal (RHR) relief valve 1E12-F313A. The drain hole is to prevent water from accumulating in the discharge piping which may affect the setpoint of the relief valve. UFSAR drawing M-91 Sheet 3 for the Unit 1 Reactor Building Equipment Drain system will be revised to reflect the installaticn of the drain hole.

UNIT 2 STATION HEAT SUPPLY AIR COILS REPLACEMENT PER DESIGN CHANGE PACKAG2 (DCP) 9600548 The design change replaced Unit 2 Station Heat Supply Air Coils 2VT02AA and 2VT02AB in the ventilation supply of the Turbine Building and rerouted associated

piping. The previous coils were freeze-damaged. The installation allows for complete draining and venting of the coik, and headers. The UFSAR Tables 9.4 5,9.4-11, and 9.4-13 were revised to reflect the changes.

UNIT 1 STATION HEAT SUPPLY AIR COIL REPLACEMENT PER DESIGN CHANGE PACKAGE (DCP) 9600549 The design change replaced Unit 1 Station Heat Supply Air Coil 1VR02A in the ventilation supply of the Reactor Building and rerouted associated piping. Th previous coil was freeze-damaged. The installation allows for complete draining and venting of i the coil and header. The UFSAR Tables 9.4-5,9.4-11, and 9.4-13 were revised to reflect the change.

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UNIT 0 STATION HEAT SUPPLY AIR COIL REPLACEMENT PER DESIGN CHANGE PACKAGE (DCP) 9600551 The design change replaced supply air coil OVR03A in the ventilation supply of the Radwaste Building and rerouted associated piping. The previous coil was freeze-

, damaged. The installation allows for complete draining and venting of the coil and header. The UFSAR Tables 9,4-5,9.4-11, and 9.4-13 were revised to reflect the i change. ,

UNIT 1 SOURCE RANGE MONITOR (SRM) AND INTERMEDIATE RANGE MONITOR (IRM) SIGNAL CABLE REPLACEMENTS, AND SEAL CABLE GUARDS PER DESIGN CHANGE PACKAGES (DCPS) 9600032,9600034,9600036, AND 9600038 The design changes reduced noise in the Unit 1 SRM and IRM channels of the neutron monitoring system. Raychem triaxial cables for the SRMs and IRMs were replaced with Rockbestos triple shielded cables and the SRM and IRM cables were rerouted in conduits dedicated solely for these signals, in addition,0-rings were installed at the SRM and IRM cable guards. Holes were drilled in the cable guards to prevent moisture from collecting and potentially affecting the detectors. The UFSAR Subsections

7.6.3.2.2 and 7.7.6.1.2 were revised to reflect these changes.

l ADDITION OF DRAIN CONNECTION TO PIPELINE 1RH83BB FOR DEWATERING 1E12-F968B, DESIGN CHANGE PACKAGE (DCP) 9700148 The design change installed a 4-inch drain connection to pipeline 1RH83BB used for dewatering the piping to support repairs to the internals of Residual Heat Removal (RHR) valve 1E12-F0688. UFSAR Druwing M ' 34 Sheet 1, " Core Standby Cooling System Equipment Cooling Water System", was revised to reflect the installation of the

- drain connection, MODIFICATION OF VOLTAGE REGULATION CIRCUlT FOR THE UNIT 1 HIGH PRESSURE CORE SPRAY (HPCS) DIESEL GENERATOR (DG) PER DESIGN CHANGE PACKAGE (DCP) 9600568 The design change revised the Unit 1 HPCS DG (DG-1B) voltage regulating circuit to correct a problem with the generator raise and lower voltage circuit, ard to increase the stability of the DG when paralleled with the grid.

TEMPORARY ALTERATIONS (TALTS) 1-0005-97 AND 2-0002 97, TF.MPORARILY BLOCK AUXILIARY BUILDING HVAC EQUIPMENT AREA VENT SYSTEM RELIEF HOODS The TALTs were installed to block off the relief hoods. This was done to support station heat conservation activities by preventing the escape of warm air from the relief hoods, and the entrance of cold air into the relief hoods.

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REPLACEMENT OF SPEED INSTRUMENTATION CABLES ON THE HIGH "RESSURE CORE SPRAY (HPCS) DIESEL GE5'.:.dATOR (DG) 1B SKID PER DESIGN CHANGE PACKAGE (DCP) 9700446 The design change replaced Engineered Safety Features (ESF) Division 3 diesel generator 1B skid cabling and added portions of conduit. The replacement was done to reduce the susceptibility of cables to noise.

TEMPORARY ALTERATION (TALT) 10053 97, TEMPORARY PLACEMENT OF SANDBAGS FOR FLOOD PROTECTION ON TOP OF TURBINE BUILDING WALL in March 1997 the lake elevation was approximately 701.6'. Internal flood protection is based on an elevation of 701.0'. With the lake elevation higher than 701.0', a postulated 4

leak in the circulating water piping or boot could result in a gravity fed flow which could go over the existing wall and enter the Turbine / Auxiliary Building complex. A temporary placement of sandbags on top of the concrete wall at an approximate elevation of 702' (above the lake level of 701,6') was implemented to contain the postulated flood water within the condenser pit.

TEMPORARY ALTERATIONS (TALTS)1-012197 AND 2-0029 97 The temporary alterations provided a means to drain the Residual Heat Removal (RHR) l Service Water lines for maintenance on heat exchanger outlet valves 1E12-F068A and 2E12-F068A. This was done to support piping repairs and inspections of the safety-related caoling water system.

TEMPORARY ALTERATION (TALT)1-0206 97 The TALT gagged open the 1E12-F090A Residual Heat Removal shutdown cooling header manual stop valve by installing a seismically qualified clamp on the valve stem

, above thc packing gland. The manual operator had been disassembled and removed as parts were available for it.

SPECIAL PROCEDURE LLP 97-009 REVISION 0, SPECIAL OPERATING MODE FOR VCNE HVAC AIR COOLED CONDENSER UNITS; AND TEMPORARY ALTERATION (TALT)1-0029-97, OPENING OF ACCESS DOORS OF VC AND VE AIR COOLED CONDENSERS TO PREVENT FILTER ICING TALT 1-0029-97 allows for opening of the VC (control room ventilation) and VE (auxiliary electric equipment room ventilation) air cooled condenters to prevent icing of filters during the winter season. This TALT is only valid while VCNE is inoperable.

Special procedure LLP-97-009 installs and tracks the installation of the TALT during potential ambient snowfall conditions.

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l STORAGE OF RADIOACTIVE WASTE IN OUTBUILDINGS, AND UFSAR CHANGE l

t The impact of storing radioactive waste and/or material in any of the station's outbuildings was evaluated. The evaluation did not apply to the interim or temporary 4

storage of radioactive waste. UFSAR Section 11.4.2.7 was revised to reflect the subject storage in varioua station outbuildings.

DIESEL GENERATOR 2A OVERCURRENT RELAY REPLACEMENT PER COMPONENT REPLACEMENT C01-2 94-006 D, AND UFSAR UPDATE The design change replacas the 2A Diesel Generator Overcurrent relays 2451-DG011 A and B. The previous Basler type PRC-110-108 relays were replaced due to

, obsolescence. The replacement relays are ABB/ Westinghouse type CO-6, Model No, 264C898A05 relays and perform the same function and meets or exceed the original equipment specifications.

UFSAR Table 8.3-2 is affected by thir, replacement, since the table lists the relay type for tne reverse power relay. The rr, vision to the UFSAR consists of replacing the relay type specified in the table with a note that refers the reade to the Q-List to obtain the relay manufacturer and model number.

WELD REPAIRS TO RHR SERVICE WATER STRAINER 2E12-D300B 3 The previously completed stainless steel weld repair to restore the flange mating surface wall thickness, on strainer 2E12 D3008, was originally considered a

maintenance enhancement to reduce corrosion effects. Subsequent to the repair, it was

- determined to be a design change.

, The subject strainer is safety related and conforms to the ASME Boiler and Pressure Vessel Code, Section Ill, Class 3 requirements. The weld repair consisted of machining the strainer mating flanges to remove corrosion and Non-Destructive Examination (NDE), we! ding to restore wall thickness. Carbon steel filler material was used to restore wall thickness and a thin layer of stainless steel metal was added to inhibit corrosion in the high corrosion areas. However, UFSAR Section 9.2.1.2 stated that strainers are carby, steel.

Vendor drawings for the affected strainer will be revised to show that carbon steel and stainless steel weld repairs have been made. In addition, UFSAR Section 9.2.1.2 is being revised to indicate that strainers are AEME Code Section lli components. The reference to " carbon steel

• has been removed.

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REPLACEMENT OF SElSMIC MONITORING PANEL OPA11J PER DESIGN CHANGE PACKAGE (DCP) 9400128 The seismic monitoring instrumentation in Panel OPA11J (with the exception of the SWP 300 annunciator panel) is being replaced with new instrumentation. Spare parts for the previous seismic monitoring instrumentation are no longer available and have a history of spurious failures, especially during thunderstorms. This change improves system reliability and availability. Relocation of the instrumentation from the Technical Specifications to the UFSAR (Generic Letter 95-10) was approved by Licensing 6

Amendments 117 and 102 for Unit 1 and Unit 2 respectively. UFSAR Section 3.7.4, Seismic Instrumentation, was revised to reflect the change.

UNIT 1 RHR HEAT EXCHANGER BYPASS VALVE 1E12 F048B CONTROL CIRCUlT CHANGE PER DCP 9600461 The design change modified the interlock (from a 10 minute timer interlock to a permissive interlock) that prevents closure of the RHR Heat Exchanger Bypass Valve 1E12-F0488 during a LOCA. The interlock requires the bypass valve to be full open at the start of a LOCA. The thermal overload bypass arrangement for the motor operated valve (MOV)is bypassed continuously as long as a LOCA signalis present. UFSAR Section 7.3.1,2.4.6 was revised to reflect this design change.

UNIT 1 RHR HEAT EXCHANGER BYPASS VALVE 1E12 F048A CONTROL CIRCUlT CHANGE PER DCP 9600460 The design change modified the interlock (from a 10 minute timer interlock to a permissive interlock) that prevents closure of the RHR Heat Exchanger Bypass Valve 1E12-F048A during a LOCA. The interlock requires the Bypass Valve to be full open at the start of a LOCA. The thermal overload bypass arrangement for the motor operated valve (MOV) is bypassed continuously as long as a LOCA signalis present. UFSAR Section 7.3.1.2.4.6 was revised to reflect the design change.

UFSAR CHANGE FOR LAKE BLOWDOWN FLOW MONITOR INSTRUMENTATION MODIFICATION PER DCP 9700194 The design change provides an alternate flow measurement of lake blowdown flow during radwaste discharge that will not be subject to fouling from the fluid stream.

UFSAR Sections 2.4.8.4

• Blowdown Waterline",7.7.11.3 " Liquid Radwaste System Instrumentation and Control", and 11.2.2.6 " Operating Procedures"" Liquid Radwaste Systems", were revised to reflect this design change.

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UFSAR CHANGE TO REFLECT UNIT 1 CIRCULATING WATER PUMP GLAND WATER MODIFICATION PER DCP 9600455 The modification changed the source of the gland water supply from the Circulating Water (CW) pumps to cool the lower bearing and provide lubrication to the stuffing box from the Clean Gland Water Head Tank (located at Aux. Building. 786 feet) to being supplied from the discharges of the existing Service Water Strainers located in the Lake Screen House. The Service Water is further strained through a new automatic backwash strainer to ensure cleanliness of gland water to the packing and lower bearing of the CW pumps. UFSAR Sections 1.2.3.6.3 and 9.2.2.2 were revised to reflect this design change.

REVISION TO UFSAR DRAWING M-124 SHEET 2, TURBINE BUILDING CLOSED COOLING WATER SYSTEM, PER DCP 9600323 4

The design change increases the reliability of station air compressor (SAC) 2SA01C by modifying the cooling water supply to the compressor's inter /aftercooler and oil cooler.

Relief valve 2WT124 on the station air comprestor inter /aftercooler cooling water supply line was replaced. The new relief valve has a setpoint of 75 psig instead of the original 65 psig. Pressure regulator 2WT087 was installed on the WT supply line,2WT02D, upstream of the inter /aftercooler for the Unit 2 station air compressor. The regulator l serves to establish a water supply pressure of 55 psig to the inter /aftercooler Relief j valve 2WT125 was deleted. UFSAR drawing M 124 Sheet 2, Turbine Building Closed Cooling Water System, was appropriately revised. i REVISION TO UFSAR DRAWING M-67 SHEET 2, TURBINE BUILDING CLOSED COOLING WATER SYSTEM, PER DCP 9600321 t

The design change increases the reliability of station air compressor (SAC) SA01C by modifying the cooling water supply to the compressor's inter /aftercooler and oil cooler.

The setpoint for relief valve 0WT016 was raised from 65 to 75 psig and the discharge pipe reconfigured, relief valve 0WT017 was deleted, and the bronze pressure regulator OWT002 for the Turbine Building Closed Cooling Water System (TBCCW) cooling water supply line upstream of the station air compressor inter /aftercooler was replaced with a cast iron pressure regulator. UFSAR drawing M-67 Sheet 2 was revised to reflect these changes.

REVISION TO UFSAR TABLE 6.2-21 PER DESIGN CHANGE PACKAGE (DCP) 9400437, INSTALLATION OF ANTI-CAVITATION TRIM IN THE 1E21-F012 VALVE Anti-cavitation trim was installed in 1E21-F012 valve, (Low Pressure Core Spray (LPCS) full flow test return), to reduce or eliminate severc cavitation that was observed when the valve is used to throttle flow through the LPCS full flow test loop. UFSAR Table 6.2-21, Note 47, was revised to clarify the stroke time of the 1E21-F012 valve.

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UFSAR UPDATE FOR INSTALLATION OF HOT TAP UPSTREAM OF 2E12 F068A FOR DEWATERING, DESIGN CHANGE PACKAGE (DCP) 9700149 The design change installed a 4" drain connection to pipeline 2RH083AA-20' used for dewatering the piping to support repairs to the internals of Residual Heat Removal (RHR) valve 2E12 F068A. UFSAR Drawing M 134 Sheet 2," Core Standby Cooling System Equipment Cooling Water System" was revised to reflect the installation of the drain connection.

ADDITION OF DRAIN CONNECTION TO PIPELINE 1RH59AB 16" PER DESIGN CHANGE PACKAGE (DCP) 9400406 The design change was implemented to prevent pressure locking of valve 1E12-F017B as described in NRC Information Notices 92-26 and 95-14. The design added a drain lina assembly to the Residual Heat Removal (RHR) Loop B Drywell Spray Header Line 1RH59AB 16" downstream of valve 1E12 F016B to drain the line between valves 1E12 F016B and 1E12 F0178, Therefore, pressure locking of valve 1E12-F0178 will be prevented with the bonnet of the valve drained and downstream line empty. UFSAR drawing M-96 Sheet 2 for the Unit 1 RHR System will be updated to reflect the change.

1 ECCS SUCTION STRAINER REPLACEMENT PER DESIGN CHANGE PACKAGE (DCP) 9700300 The design change _ replaced the Emergency Core Cooling System (ECCS) suction strainer on the Unit 1 B Residual Heat Removal (RHR) system suction line in the suppression pool. The replacement strainer has increased capacity to reduce pump net-positive suction head (NPSH) loss due to accumulated strainer debris resulting from a

- design basis leak or Loss of Coolant Accident (LOCA). The strainer surface area is increased as is the available flow area of the strainer. The strainer installation partially addresses the actio1s required by NRC Bulletin 96-03. UFSAR drawing M-96 Sheet 2 for the Unit 1 RHR system was revised to reflect the strainer replacement.

ECCS SUCTION STRAINER REPLACEMENT PER DESIGN CHANGE PACKAGE (OCP) 9700301 The design change replaced the Emergency Core Cooling System (ECCS) suction strainer on the Unit 1 C Residual Heat Removal (RHR) system suction line in the suppression pool. The replacement strainer has increased capacity to reduce pump net.

. positive suction head (NPSH) loss due to accumulated strainer debris resulting from a hsign basis leak or Loss of Coolant Accident (LOCA). The strainer surface area is increased as is the available flow area of the strainer._ The strainer installation partially addresses the actions required by NRC Bulletin 96-03. UFSAR drawing M-96 Sheet 3 for the Unit 1 RHR system is revised to reflect the strainer replacement.

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ADDITION OF HOLE TO REACTOR BUILDING EQUlFMENT DRAIN LINE 1RF61 AB.

4" PER DESIGN CHANGE PACKAGE 9700449 The design change installed a 0.5" drain hole in the discharge piping associated with and immediately downstream of Residual Heat Removal (RHR) relief valve 1E12 F313B to prevent water from accumulaung in the discharge piping. Water accumulation may affect the setpoint of the relief valve UFSAR drawing M 91 Sheet 3 for the Unit 1 Reactor Building equipment drain system is being revised to reflect the installation of the drain hole.

REPLACEMENT OF LIQUID PROCESS RADIATION MONITOR PROBE 1E12 N511

. PER DESIGN CHANGE PACKAGE 9700522 The design change replaced the probe for monitoring the Division 2 Residual Heat Removal (RHR) Heat Exchanger 1B Service Water Discharge, the previous probe failed due to flow induced vibration. UFSAR drawing M-87 Gheet 1 is revised to reflect the probe replacement.

DIESEL GENERATOR 2A t)NDERFREQUENCY RELAY REPLACEMENT PER COMPONENT REPLACEMENT C012-94-006 A The design change replaced the 2A Diesel Generator Underfrequency relay. The previous Basler type PRF-120 relay was replaced due to obsolescence. The replacement is an ABB Type ITE-81, Model No. 422C1276-L frequency relay and performs the same function and meets or exceeds the original equipment specifications, INSTALLATION OF VOLTAGE REGULATING TRANSFORMER (VRT) 2APD4E, DESIGH CHANGE PACKAGE (DCP) 9500046 The design change added a voltage regulating transformer in the 120 VAC distribution circuit for Motor Control Center (MCC) 236X-3, Circuit #19, the feed for the Unit 2 ,

Division 2 leak detection control circuit. The design change improves the voltages at the loads during normal and abnormal system conditions, specifically during a degraded voltage condition.

3 REPLACEMENT OF SPEED INSTRUMENTATION CABLES ON THE HIGH PRESSURE CORE SPRAY (HPCS) DIESEL GENERATOR (DG) 1B SKlD The design change replaced Engineered Safety Features (ESF) Division 3 DG 1B skid cabling and added portions of conduit. The replacement was done to reduce the susceptibility of cables to noise.

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REPAIRS TO VALVE 1E12 F068A PER DESIGN CHANGE PACKAGE (DCP) 9700143 The design change repalrod the internals of Residual Heat Removal (RHR) valve,1E12-F068A. This included rep %cing, the carbon steel valve disc with a stainlest steel disc to minimize corrosion, the carbon steel disc guides wHh stellite faced carbon scsl disc guides in order to minimize wear; the stainless steel valve stem with a stem of differing grade of stainless stect, the spiral wound stainless steel asbestos bonnet gasket with a spiral wound stainless steel graphite filled gasket, the stem nut; bonnet stude, and bonnet nuts like-for-like.

REVISION OF THE THERMAL OVERLOAD BYPASS SCHEME OF RESIDUAL HEAT REMOVAL / LOW PRESSURE CORE SPRAY MOTOR OPEF'ATED VALVES PER DESIGN CHANGE PACKAGE (DCP) 9700025 The design change implemented the corrective actions identified in Licensee Event 4

Report (LEP)96-022, Rev, 0, for the thermal overload bypass logic of the Engineered Safety Features Division 1 motor operated valves (MOVs). The control circuits of MOVs,1E12 F024A,1E12-F027A,1E12 F042A, and 1E21-F005 were revised to ensure

, that the thermal overicads are bypassed whenever a Loss of Coolant Accident (LOCA) l signalis present. The thermal overload bypass signalwas previously removed when l the manual override feature for these valves was enabled by the operator.

MODIFICATION OF TIE BACK PLATES FOR ACTUATOR OTZ VD003C, DESIGN CHANGE PACKAGE (DCP) 9700363 i- The tie back plates for common actuata- OTZ-VD003C for diesel generator ventilation dampers OVD03YA and OVD03YB were modified to support the replacement of the ,

f actuator.

DIESEL GENERATOR BACKWASH VALVE OPENING POSITIONS, DESIGN CHANGE PACKAGE (DCP) 9600371 As a result of special tests, it was determined that adjustments needed to be made to the limit switch settings of diesel generator (DG) cooling water strainer backwash valves ODG009,1DG011,2DG011,1E22-F319, and 2E22-F319. The limit switch settings of the strainer backwash valves were revised to meet the UFSAR required flow of 250 gpm while maintaining adequate flow to other system components. This design change permanently changes the backwash vo'ves full open positions as adjusted during testing and documented in Temporary Alterations 1-0087-96,1-0088-96,1-0089-96,2-0018-96, and 2-0019-96.

15

UPDATE TO UFSAR TABLES 7.3 5 AND 7.7-4 TO REFLECT DEGIGN CHANGE PACKAGE (DCP) 9700562 The Unit 1 Source Range Monitor (SRM) retract permit and downscale trip setpoint was revised per DCP 9700562, "8RM Retract Permissive and Downscale Trip Setpoint Revision". The retract setpoint was revised from 100 counts per sec (cps) to 30S cps and the downscale trip setpoint was revised from 1.18 cps to 1.51 cps. UFSAR Tables 7.3-5, " Control Rod Block instrumentation Setpoints," and 7.7-4, "SRM System Trips,"

was revised to reflect the sctpoint cc'culation L-001343.

UPDATE TO UFSAR SECTION 8.3.2.1.1 TO REFLECT DESIGN CHANGE PACKAGES (DCPS) 9400250,9400251,9400252, AND 9400253 Tne design changes removed the equalize interval timer from battery chargers 2DC03E (250 VDC Division 1),2DC09E (125 VDC Division 1),2DC17E (125 VDC Division 2),

and 2DC19E (125 VDC Division 3). The timers were experiencing a high rate of failure.

The battery charging mode will be switched manually by way of the existing equalize / float switch. UFSAR Section 8.3.2,1.1 was revised to reflect this change.

G. Summary of Ohannes to Procedures Described in the Safetv Analysis Report The 10CFR50.59 safety evaluations concluded that there were no unr6 viewed safety questions associated with the following procedure changes:

LASALLE SPECIAL PROCEDURE LLP 97-007 REVISION 1, ADDING CARBON (CHARCOAL)TO AN EQUIPMENT DRAIN DEMINERALIZER, AND UFSAR CHANGE The procedure was revised to provide the steps necessary to add carbon (charcoal) to Waste Mixed Bed Demineralizer 1(2)WE010. The charcoal overlay serves to protect the ion exchange resins from organic foul'ng. The UFSAR, Section 11.2.2.5 was revised to reflect the use of charcoal in the spent resin tank.

PROCEDURE LRP-5000 7 REVISION 6, UNESCORTED ACCESS TO AND CONDUCT IN RADIOLOGICALLY POSTED AREAS The limitations and actions section of the procedure was revised to reflect the establishment of the radiologically posted areas ingress and egress points by the Radiation Protection Manager, and, to include language from the UFSAR concerning the principal access control point on the ground floor between the new Service Building and Turbine Building.

10

CORPORATE PROCEDURES NEP 18-04 REVISION 0 AND APPENDIX NEP 18 04LA REVIS!ON G ASSOCIATED WITH ENGINEERING REVIEW OF DYNAMIC QUALIFICATIONS

Corporate Procedures NEP 18-04 Revision 0 and appendix NEP 18-04LA Revision 0 associated with Engineering Review of Dynamic Qualifications were reviewed and approved for station use. These re standard procedures for use throughout Commonwealth Edison. The procedure identifies responsibilities and the process for the review of equipment dynamic (seismic) qualification reports. UFSAR Section 3.7.3.2.2 was revised to be consistent with paragraph 6.6.5 of IEEE-374-1375 regarding the duration of seismic qua!ification tests.

1 UFSAR REVISION ASSOCIATED WITH PROCEDURE LCP 310 33 REVISION 3, SAMPLING AT THE JET PUMP FLOW TRANSMITTERS USING A BECKMAN SOLU COMP CONDUCTIVITY CELL MODULE The procedure was revised LCP-310-33 to allow attemate sampling locations from the Jet Pump Number 5 flow transmitter 1(2)B21 N034), and Jet Pump Number 15 flow transmitter 1(2)B21 N034K with concurrence from the Operations and Chemistry Departments. The UFSAR Section 9.3.2.3 was revised to reflect these specific sampling locations.

PROCEDURE LOA RX-101 REVISION 1, UNIT 1 CONTROL ROOM EVACUATION ABNORMAL The procedure revision consisted of the fcilowing:

• Deleted steps B.1.18 and B.1.19 which provided the option to allow for NOT opening RPS breakers CB2A end CB2B if MSIV closure, vesselisolation, and .

containment isolation was NOT desired. In addition, the change deleted logic which involved the MSIVs open, Steps B.1.28,31, and 34, since actions will now always be taken based on the MSIVs closed.

. Changed step B.1.23.4 (RNO) to state, " operate one SRV" for maintaining less than 1000 psig and Step B.1.34 (AER) to state " operate two SRVs as necessary" for cooldo'un. This change was done to be consistent with UFSAR Section 7.4.4.3.

. Changed step B.136 (AER) and B.1.36.16 9) from "135 psig" to "100 psig" to be consistent with Step B.1.34 and agree with 1.,e wording in UFSAR Section 7.4.4.3. 3

. UFSAR Section 7.4.4.3 paragraph I was changed to comp!y with Emergency Operating Procedures (EOPs). UFSAR Section 7.4.4.3 paragraph p was updated to reflect current operating practice.

i/

PROCEDURE LOP VR-01, REVISION 14, REACTOR BUILDING VENTILATION SYSTEM STARTUP The procedure outlines the steps needed to start the Reactor Building Ventilation (VR) system. The revision to the procedure reflects tha installation of Desion Change Packages (DCP) 95004897 and 9500488, which are associated with the main steam pipe tunnel leak detection syttem, and makes editorial and clarification enhancements.

PROCEDURE LOP-RX-08 REVISION 7, START OF SHUTDOWN COOLING FROM a THE REMOTE SHUTDOWN PANEL l

The procedure outlines the steps necessary to start Shutdown Cooling from the Remote Shutdown Panel. Toe proccdure reflects an installed plant modification on the Residual Heat Removal (RHR) Service Water Keep Fill System per Design Change Fackages 9600195 and 9600198. UFSAR Se cons 7.3.3.3.1, 9.2.1.2, 9.2.1.5, 9.2.2, and 9.2.2.2 were revised to reflect the ,:hange.

PROCEDURE LOA RX-201 REVIGION 1 UNIT 2 CONTROL ROOM EVACUATION ABNORMAL The procedure revision consisted of the following:

i . Deleted Steps B.1.18 and B.1.19 that allowed for NOT opening RPS breakem CB2A and CB2B if MSIV closure, vessel isolation, and containment isolation were NOT desired. The logic related to having the MSIVs open, Steps B.1.28,31, and

34. was deleted since actions will now always be taken based on having the MSIVs closed. This change was not consistent with the piecedure actions stated in UFSAR Section 7.4.4.3.c. The UFSAR specifically discusses the opening of these breakers as a bacl<up means of semmming the reactor and closing the containment and reactor vesselisolation valves. The MSIVs will now always be closed by toe opening of the RPS breakers.

• Step B.1.23.4 was modified to state, " operate one SRV" for maintaining less than 1000 psig pressure, and Step B.1.34 to state, " operate two SRVs as necessary" for cooldown. This change was made to be consistent with UFSAR Section 7.4.4.3.

• Step's B.1.36 (AER) and 8.1.36.1 (RNO) were changed to read from, "135 psig" to "100 psig" to be consistent with Step B.1.34 and agree with UFSAR discussion Section 7.4.4.3.

. UFSAR Section 7.4.4.3 paragraph I was changed to comply with Emergency Operating Procedures (EOPs). UFSAR Section 7.4 4.3 paragraph p was updated to reflect current operating practice.

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PROCEDURE LOA FX-101 REVISION 1 UNIT 1 SAFE SHUTDOWN WITH A LOSS OF OFFSITE POWER AND A FIRE IN THE CONTROL ROOM GR AUXILIARY ELECTRIC EQUIPMENT ROOM The procedure reflects the installed plant modification on the Residual Heat Removal (RHR) Service Water Keep Fill System per Design Change Packages 9600195 and 9600198. It provides guidance for a reactor shutdown for the following scenarios: 1) a fire in the control room which renders the control room inaccessible, and a concurrent loss of o# site power and 2) a fire in the Division 1 or Division 2 Auxiliary Electric Equipment Room (AEER) and a concurrent loss of offsite power.

PROCEDJRE LOA FX-201 REVISION 1, UNIT 2 SAFE SHUTDOWN WITH A LOSS OF OFFSITE POWER AND A FIRE IN THE CONTROL ROOivl OR AUXILIARY ELECTRIC EQUIPMENT ROOM The procedure reflects the installed plant modificadon on the Residual Hut Removal (RHR) Service Water Keep Fill System per Design Change Packages 9600195 and 9600198. The procedure provides guidance for a reactor shutdown for the following scenarios: 1) a fire in the control room which renders the control room inaccessible and a concurrent loss of offsite power and 2) a fire in the Division 1 or Division 2 Auxiliary Electric Equipment Room (AEER) and a concurrent loss of offsite power.

PROCEDURE LOP RX 06 REVISION 4, STARTUP OF SUPPRESSION POOL COOLING FROM THE REMOTE SHUTDOWN PANEL The procedure reflects the installed plant modification on the Residual Heat Removal (RHR) Service Water Keep Fill System per Design Change Packages 9600195 and 9600198. It outlines the steps necessary to start Suppression Pool Cooling from the Remote Shutdown Panel.

LASALLE SPECIAL TEST PROCEDURE LST-96-070 REVISION 1, AUXILIARY ELECTRIC EQUIPMENT ROOM AND CONTROL ROOM PRESSURE AND FLOW RATE VERIFICATION The procedure was written to verify the Auxiliary Electric Equipment Room and Control Room differential pressure with the Control Room Emergency Makeup System in operation, complied with the UFSAR.

PROCEDURE LRP 5721-6 REVISION 1, CONSTRUCTION OF RADIOLOGICALLY POSTED AREAS AND STEP OFF PAD AREAS The limitations and actions section of the procedure was revised to make this procedure agree with procedure LRP-5000-7 Revision 6 which allows the Radiation Protection Manager to establish radiologically posted areas ingress and egress points.

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.- _ .. - -. - -. . - - - ~- .-.- - -. . . - - - . -

PROCEDURE LAP 200-3 REVISION 29, SHIFT CHANGE The administrative controls specifying the conduct of Shift Change activities w9te clarified and strengthened by the procedure revision. The following is a summary of the changes:

4

• Log keeping activities are not defined within the shift change procedure and the procedure only references the cppropriate administrative procedure.

• Log book initialing for the Nuclear Station Operator (NSO) and Radwaste Operator .

was eliminated. Shift turnover attachments were provided to document required reviews.

• Unit Supervisor panel walkdown checklists were removed to reduce cdministrative burden.

• Directions on shift change were included 'or the Work Control Center SRO and Shift Technical Advisor. In addition, procedure attachments related to shift designations were revised to reflect the current Operating Shift Schedule.

. Correcting mis-spelled words and improve procedure readability.

UFSAR Section 13.5.1.3.6 (Procedures for Logbooks) was revised to reflect these changes.

LASALLE SITE SPECIFIC OFFSITE DOSE CALCULATION MANUAL (ODCM)

REVISION 1.9 The generic section of the ODCM, Chapter 12, LaSalle specifies a minimum requirement of one control milk sample location whereas the the LaSalle specific section of the ODCM, Chapter 12, specifies two. The owner of the Burton farm formally requested to be removed from the LaSalle milk sample program, and therefore, the L-41, Burton Farm milk sample point was removed. An alternate controllocation will not replace this sample point. Since the generic section requires one controllocation, the requirements of the ODCM are still met.

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4

. y- - -

4 PROCEDURE LOP VR-02 REVISION 17, SHUTDOWN OF THE REACTOR BUILDING j VENTILA flON SYSTEM LOP-VR-02 Revision 17 incorporates the following changes:

• Relocation and isolation logic changes to Unit 2 Main Steam (MS) pipe tunnel leak detection system per design changes 9500487 and 9500488.

. Adding an option to use a blank flange for reactor building elevator equipment room fire damper to reflect design changes 9600385 and 9600386.

. Establishment of secondary containment integrity with the Standby Gas Treatment (SBGT) system operating prior to reactor building ventilation system (VR) shutdown.

PROCEDURE LLP 97-025 REVISION 0, FUEL POOL CLEANOUT PROJECT Movement of loads over the fuel pool is prohibited with the following systems inoperable:

Standby Gas Treatment, Reactor Building Ventilation, Reactor Building and Fuel Pool Cleanup System Radiation Monitors, Control Room Ventilation, and AEER Ventilation.

The procedure establishes control N NUKEM vendor procedures for processing and

. shipping radioactive components in the fuel pool. This allows movements of loads less 4

than 1290 pounds over the fuel pool.

PROCEDURE LST-97-406 REVIS:ON 0 The procedure was implemented to provide guidance for adjusting the Turbine Building Ventilation System (VT) supply flow to obtain negative pressure in the Turbine Building, Units 1 and 2, relative to outside atmospheric pressure. It also provides guidance on how to obtain dat ' to develop a permanent modification that will ensure the Turbine Building is at negative pressure relative to atmospheric pressure whenever the VT system is in operation.

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2'

4 REVISIONS TO LASALLE GENERAL ABNORMAL (LGA) PROCEDURES The procedures (Units 1 and 2) listed below were revised to be to be consistent with Revision 4 of the BWROG Emergency Procedure Guidelines (EPGs; NEDO-31331, March 1987):

LGA-01 Revision 15, RPV Control, RPV Pressure Control Leg I LGA-02 Revision 13, Secondary Containment Control LGA-03 Revision 18, Primary Containment Control, Drywell Temperature Control Leg LGA-04 Revision 14, Emergency Depressurization LGA-05 Revision 11, RPV Flooding, Non ATWS Condition LGA-06 Revision 9, ATWS Emergency Depressurization LGA-07 Revision 9, Steam Cooling LGA-08 Revision 9, Primary Containment Flooding LGA-09 Revision 8, Radioactivity Release Control i LGA-10 Revision 10, Failure to Scrain EVALUATION OF THE MAIN STEAM TUNNEL DELTA-T LEAK DETECTION THERMOCOUPLE CABLE ELECTRICAL SEPARATION, AND UFSAR CHANGE The leak detection main steam tunnel delta T thermocouple cables, although functionally redundant, are assigned to the same electrical division and are not separated. The cable routing deviates from the description of electrical separation in UFSAR Chapter 8. L1e UFSAR states that Class 1E components with redundant safety functions are assigned to separate divisions. Based on analysis, electrical separation of the thermocouple cables is not required to ensure functionality of the main steam tunnel delta-T circuit. The routing of the thermocouple cables in the the same raceway does not affect the operability of the circuit or the safety margin. UFSAR Section 8.3 and Appendix B were revised to reflect the evaluation of the as-built configuration.

(Reference Onsite Peview 97-019),

OSR 97 062 REV. O, UNITIZATION OF LASALLE COUNTY NUCLEAR STATION ORGANIZATION The organizational functions and responsibilities of the Operations, Maintenance, and Work Control organizations at LaSalle County Station were unitized. Unitizing these areas created a " Plant General Manager". The unitized organization's respective department heads for the Operations, Mainte..ance, and Work Control departments report directly to the Plant General Manager. .

Unitization provides additional management focus to facilitate performance 4

improvements on both LaSalle units. UFSAR Sections 9.5,11.5,12.1,13.1,13.2,13.5, 13.6, and Appendix L are revised to reflect various titles and responsibilities unique to the unitized organization.

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REVISION TO UFSAR TABLE 8.31 FOR AUXILIARY ELECTRIC EQUIPMENT ROOM (AEER) CONDENSER FAN OVE03CA/B UFSAR Table 8.3-1, " Input Loading on 4160 SWGR 141Y,142Y and 242Y", was revised to reflect the increase in brake horsepower (BHP) of the AEER Condenser Fan OVE03CA/B.

RHR SERVICE WATER F'JMPS AND DIESEL GENERATOR COOLING WATER PUMPS 1E12 C300A/B/CID,2E12 C300A/B/C/D, ODG01P,1DG01P, AND 2DGMP VENT VALVES The pump casing vent valves provide an additional system vent that can be used during system filling or draining. However, t.'e vent valves did not appear on piping and instrumentation drawings, equipment part numbers (E'Ns) were not associated with these valves, and they were not referenced in the fill and vent or pump test procedures.

Therefore, P&lDs M 87 Sheets 1 & 2, and M 134 Sheets 1 & 2, associated line and valve iists, and the applicable UFSAR drawings were revised to reflect these changes.

REVISION TO DRAWING M-1450

. Drawing M-1450 was revised to reflect the as-built condition of the plant which includes l the removal of references to specific devices serviced by machine shop ventilation

! exh;ust filter package units OVJ02S and OVJ04S, DELETION OF THE DECONTAMINATION FACILITY IN THE NORTH SERVICE BUILDl"G FROM THE UFSAR Egress is no longer allowed from the Turbine Building to the north Service Building. The flow of traffic is toward the south end of the Unit 1 Turbine Ruilding with only one controlled entr;r ce and exit from the radiologically protected area (RPA). As a result, the decontamincon facility is no longer used. UFSAR Section 12.3.1.f I was revised to reflect this change.

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REVISION TO UFSAR SECTIONS 7.3.9.1.4 AND TABLE 8..t1 The UFSAR Section 7.3.9.1.4 for RHR Service Water was revised to correct the l description of the start of RHR Service Water System for Containment Spray. UFSAR Table 8.3-1, Diesel Generator Loading, was revised to document Division 1 RHR Servin Water Pumps operate in post-accident mode and to update the load totals in Unit 1 Divi $ns 1 and 2 per the current calculation. Editorial changes were also made to clarify infoimation in UFSAR Sections 5.4.7.1, 5.4.7.2.2.2, 5.4.7,3.1, 6.3.2.8, 9.2.1.3, and 9.2.1.5.

I UFSAR Sections 7.3.9.1.4.c and 7.3.9.1.4.d state that the RHR Service Water Pumps start automatically and RHR Heat Exchanger Service Water Discharge Valves 1(2)E12-F068A and B open automatically in the containment spray mode of RHR. These sections were revised to be consistent with other sections in the UFSAR which indicate manual operation of the pumps and valves.

REVISION TO UFSAR SECTION 12.1.1.3.K TO REFLECT INFORMATION FROM HEALTH PHYSICS INFORMATION PAPER-071 UFSAR Section 12.1.1.3.k was revised to reflect the policy which allows personnel other than Radiation Protection Technicians the ability to survey hand-carried personal effects. This provides for increased worker efficiency.

REVISION TO UFSAR SECTIONS 1.1, 7.3, 7.6, AND 7.7 UFSAR Section 1.1, and Tables 7.3-4,7.3-5,7.6-2, and 7.7-6 were revised to be consistent with the requirements of 10CFR50.71(e) and Unit 1 and Unit 2 Technical Specifications.

UPDATE TO NEUTRON MONITORING DISCUSSION IN UFSAR SECTION 7.7.6.1.3 UFSAR Section 7.7.6.1.3 was re;; sed to remove the statement that during startup at least one control rod adjacent te all Source Range Monitors (SRMs) and neutron sources is fully withdrawn prior to reaching criticality. Reference to " sources" was correspondingly deleted. This revision reflects that LaSalle no longer has neutron sources in the core. A discussion of shadowing was revised as the reduction in source and delector shadowing is no longer applicable.

REVISION TO UFSAR SECTION 15.6.6 UFSAR Section 15.6.6 was revised to delete the reference to particulate filtration by the Turbine Building Ventilation (VT) system for the Feedwater Line Break Accident. The change deletes the implication in UFSAR Section 15.6.6 that the VT system contains high efficiency particulate air (HEPA) exhaust filters.

4 1

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UFSAR REVISION TO REFLECT THE REPLACEMENT OF THE  ;

ANDERSONIGREENWOOD 2" DOUBLE BLOCK VALVES E21-F331 AND 1E21- l F332, DESIGN CHANGE PACKAGE (DCP) 9700374 The block valves located on the Low Pressure Core Spray (LPCS) pump suction line were replaced with a single valve assembly. This was done due to through-seat leakage and the Anderson / Greenwood doubic block va!ve being obsolete. A gate valve replaced the dout,le block valve since it is less susceptible to becoming a crud trap.

UFSAR drawing M-94, "LPCS" was revised to reflect this change.

REVISION TO UFSAR SECTION 12.5.3.3.1, " PERSONNEL INTERNAL EXPOSURE PROGRAM DURING ACCIDENT CONDITIONS" UFSAR Section 12.5.3.3.1 was revised to remove specific reference to Corporate Procedure CEPIP-3103-1 and added a reference to corporate implementing procedures.

REVISION TO UFSAR SECTION 13.3, " EMERGENCY PLANNING" UFSAR Section 13.3 was revised to more accurately describe the description of the Generating Station Emergency Plan (GSEP).

REVISION TC UFSAR SECTION 9.2.1.3 PER OPERABILITY EVALUATION 97-058 UFSAR Section 9.2.1.3 states the maximum flow velocity to be 5 feet per second (fps) in the 54" bypass line, which provides an emergency source of water to the service water tunnel, in the event of complete failure (blockage) of the traveling screens. However, calculation L-000671 concluded the actual flTv velocity to be 9.49 fps with the line free of sediment, and 18.9 fps with the line 20% blocked with sediment. The specific flow velocity is not relevant to the issue of debris blockage. UFSAR Section 9.2.1.3 was revised to reflect the increased flow veloc;ty. The operation of the 54" bypass line and the systems which take suction off of the service water tunnel, including interfaces, remain unchanged.

REVISION TO UFSAR CHAPTERS 15.0, ACCIDENT ANALYSES, AND 15.A, CYCLE SPECIFIC SAFFTY ANALYSES UFSAR Sections 15.0.8,15.A.4,15.A.5,15.A.6, and Table 15.A-1 were revised to update docurr.ents referenced in these sections. The referenced documents consist of the Core Operating Limits Report, Reload Licensing Package, and station Administrative Technical Requirements.

25 P'

UPDATE TO UFSAR SECTION 4.6.1.1.2.4.2.6 TO REFLECT THE INSTALLATION OF THREADED JOINT HYDROLAZING PORTS TO THE UNIT 1 AND 2 SCRAM DISCHARGE VOLUME (SDV) HEADERS The threaded ports were installed per modifications M01-1-84-059 and M01-2-84-094.

The safety evaluations for these modifications failed to identify the threaded joint issue with respect to Commonwealth Editon LaSalle County Station Safety Evaluation Report (SER) NUREG 0519, Supplement 4, and NUREG-0803. The threaded hydrolazing ports allow for flushing and hydrolazing of the SDV piping during plant outages for dose reduction.

REVISION TO UFSAR APPENDIX B LSCS-FSAR, Appendix B, states that Regulatory Guide (RG) 1.16, Revision 4, is an acceptable program for meeting the reporting requirements of the Technical Specifications. It further states that the reporting of operating information for LaSalle county Station will comply with the applicable requirements as set forth in the reporting requirements section of the Technical Specifications operating license. NKC GL 97-02,

" Revised Contents of the Monthly Operating Report", allows for reduction in the information reported in the NRC Monthly Operating Report. Irrplementation of this l Generic Letter guidance is voluntary provide the licensees take whatever means are l appropnate to negate any prior commitments to RG 1.16. As a result of our review of l applicable operating license documents, the LSCS-UFSAR will have to be revised to reference the GL as acceptable guidance for documenting the monthly operating information to the NRC.

H. Survey of Evaluation Results of Chlorine Shioments by Barae on the lilinois River For the 1997 survey of chlorine shipment inine vicinity of LaSalle County Station, See Attachment D.

I.' Summary of Events Violatina Technical Specification 3 4.5 Primary Coolant lodine Soikina Exceedina Allowable Limits During this reporting period, January 1,1997 through December 31,1997, there were no violations of Technical Specification 3.4.5, Primary Coolant lodine Spikes Exceeding Allowable Limits.

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ATTACHMENT A Unit 1 and Unit 2 Restart Activities Maintenance Activities for Unit 1 Division 2 Window:

. Residual Heat Removal (RHR) Systems Work

. SBM Testing

. "A" Diesel Generator Work

. Div 2 Operability Testing Division 1 W3ndow: )

. Residual Heat Removal System Work

. Low Pressure Core Spray (LPCS) Work RHR Service Water (WS) Work

. 141Y Bus Drop

. Div 1 Post Maintenance Testing and Operability Testing Common Shutoown Cooling Window:

. Common Shutdown Cooling Header Maintenance Work

. Post Maintenance Testing CD-10 Window:

. Condensate Work e Main Condenser Work

. Feedwater System Work

. "0* Diesel Generator Work and Testing

. Auxiliary Power Work Bus 141X

. 151 Bus Drop

. 152 Bus Drop Division 1 Window:

• RHR Service Water Work (pipe inspection and valve work)

. EHC Work

. System Testing

. B Diesel Generator

. - High Pressure Core Spray (HPCS) Pump Division 2 Window:

. Safet'. Relief Valve System Work

. RHR Service Water Valve Repairs

. OPRM Installation and Testing

. Divisional Testing 27

ATTACHMENT A CD 10 Window:

e Reactor Water Cleanup System Work

. EHC Tet ting and Flushing Improve Operator Performance e implemented ' Scorecard" monitoring system

. Monitoring of completed surveillances for accuracy and completeness e Monitoring operator rounds for accuracy and completeness

• Monitoring operator logs for completeness, legibility and conformance e Monitoring of out of service problems including type and nurnber e Monitoring proceoure use and compliance e Monitoring 3 way communication in the Main Control Room and the plant e Monitoring locked valve program

. Improved operating training (completed High Intensity Training)

• Reduced operator challenges (operator work arounds, e.g. temporary alterations) e Review atrj revise operating procedures as necessary e Impl7 ment labeling upgraces to plant equipment for Units 1 and 2 Improve Human Performance to Sapport Safe Plant Operation

. Provided clear expectatlons to site workers; communicated site direction e Coach and mentor workers during job performance e Performed self assessments to identify problems and implemented corrective actions to establish expectations e Benchmarking at other Commonwealth Stations on

• Manage 6nent by Walking Around" e Establish clear expectations e improve Organizational Communications e Plant Material Conditions e Reduce maintenance backlog Improved Plant Matsrlai Co;sdition

. Main Control Room Environment e Review of the Nuclear Work Request (NWR) Corrective backlog to define that level which provides acceptable plant material condition L

Improved Gutage Management and Work Control Processes

. Outage scope additions reviewed by Senior Mar, agers to assure proper prioritization

. Seven day Scope Control concept implemented

. Realignment of discipline tw as and schedulers under the Outage Management Organization

. " Ten Day Look AM , e og objectives and expectations formally documer.ted e implementation of forrn3 .cking and trending of schedule movement 28

ATTACHMENT A Restart and Power Ascension Plan e Established roles and responsibilities of the Senior Management Oversight function.

• Determined key systems to validate the out of service positioin.

Engineering Issues ,

Major Plant Design Changes:

. Turbine Driven Reactor Feed Pump work e Motor Driven Reactor Feed Purnp Seal modification e Electro Hydraulic Control Oil Trip Logic e Heater Bay Cooling

• Switchgear Heat Removal Damper Replacement e Loose parts monitoring system

. Reactor Water Cleanup volding issue e Control Room enhancements e GL 96 06 issue resolution ,

e Primary containment penetration

. HELB e Hydrogen Water Chemistry implementation improve Engineering Capability:

. Establish personnel qualifications e Establish Engineering Assurance Group e SyMem Functional Performance Review and Functional Testing e Design Reviews e Configuration Control Evaluation e Vendor Information cnd Operating Experience Reviews e System Readiness Reviews Process Developmant e Corrective Action and Self Assessment Reviews l e Regulatory reviews

(

• Conducted programmatic assessments e Selected Engineering processes Enhanced (50.59, operability evaluations, and minor modifications) e Establish a Rapid Response Team, System Readiness Recovery Teams.

e implemented a Joint Test Group to process ana facilitate test procedure preparation, review, implementation and results review e Identified functional testing requiremants including overall integrated testing and selected ECCS response demonstration testing 29 l

l l

ATTACHMENT A RegulatoryIssues; l

e Feedwater/ Main Turbine Reactor Vessel Water Level High Trip logic change

. Control Room HVAC Rad Monitor logic

. Control Room HVAC, AEER ventilation, SBGT filter testing

. Leak Detection Isolation for RWCU e Post LOCA Hydrogen improve Site Quelity Verification (SQV) Effectiveness

. Conduct programmatic assessments and implement corrective action program improvements

e identify problems requiring resolution, implement oversight and review of root cause determinations and complete improvements to the corrective actin screening.

i e improve SQV ability to diagnose Nuclear Safe'v and Quality concerns and effectively communicate those issues to the line management.

. Assess technical, operational and managerial experience of SQV personnel.

. Assign functional area responsibility to assessment personriel.

. Perform departmental self assessments to identify problems early in the developmental stages.

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O ATTACHMENT B UNIT 1 l

i WR No. Cystem EPN Equipment Description ,

No. Name 970044390 AP 1AP01E Instr Medium Voltage Replace thumb screws and receivers.

Switchgear 960111322 AP 1AP02E 1 Unit Auxiliary Transformer Main Replace L/C/S for unit Aux transfer l Feed 1 AP02E 1 on switchgear 152, Cubicle 1.

970070096 AP 1APO4E 1 APO4E-4.16 KV Bus Replace all holddown thumb screws and receivers in Cubicle doors.

900110379 AP 1 APO4E 8 Primary Containment Water Replace local control SW at 141Y 8 Chiller 1 A for i A VP Chiller Bkr.

970002004 AP 1AP06E 3 Diesel Generator 1 A Main Feed RPL 1 AP06E 3 (DG 1 A Main Feed L/C/S) A Switchgear 142Y.

960120913 AP 1AP07E Switchgear 143 4160 VAC Evaluate whetner bolts are needed on cubicle doors.

970080106 AP 1 AP07E 003 Switchgear 143 Feed from DG 1B Breaker failed to close during mod (ACB 1433) test Troubleshoot breaker.

960102301 AP 1AP19E 103A DG 0 cooling water pump 0 Problem with tacking mechanism on DG01P (U1 Feed) breaker cubicle.

970093945 AP 1AP21E 3030 Auxiliary equip room supply fan improper gap / clearance on breaker OA. trip mechanism.

900102293 AP 1AP22E-402C 1D RHR Service Water pump Repair racking mechanism on breaker 1E12 C3000. cubicle.

970041209 AP 1AP76E F3 0 DG fuel oil transfer pump OD001P fails to run when feed from (OD001P) U-2 235Y 2 comp F 3.

970001529 AP 1 AP82E-A5 RHR heat exchanger shell side Close contactor binds and doesn't bypass ,atve spring back to normal position.

960010784 AP 1AP83E A5 DW penetrations cooling inboard 1WR180 MCC Feed Breaker cubicle isolation 1WR180 wiring repair.

9700t3403 C21 1821-F022C Operator, air valve ast,embly Junction box cover is missing screw.

9700 0405 B21 1821 F022D Operator, air valve assembly Junction box cover is missing screw.

970002063 B21 1821 HS014 tE12 F0408 0 RHR HX BD Replace SW 1821 HS014,IE12-downstream isolation F040B B RHR.

900120504 B21 1821-HS023 1E12-F053B B RHR shutdown RPL 1821 HS023 (1E12 F0538 RHR cooling discharge isolation stop shutdown injection valve) 1H13-P601.

970023410 B21 1821-NO39PP Low low set point SRV 1821 Replaced missing vent line support F013P clip fastener.

970023407 821 1821 N039UU- Low low set point SRV 1821 Tightened loose vent line support clip F013U fastener.

970090635 B21 1821 N413A LPCS/RHR A injection valves Replaced defective instrument vent reactor pressure interlock test tap cap.

31

I f #5 f$ EI,' $d' Mb%*, L t M d'J G -

k.

ATTACHMENT B UNIT 1 WR No. System EPN Equipment Description No. Name 970027115 021 1021 N413A LPCS/RHR A injection valves ' Replaced damaged test tap plug.

reactor pressure interlock 970099634 B21 1021 N413C LPCS/RHR A injection valves Replaced defective instrument vent reactor pressure interlock test tap cap.

970027110 B21 1021 N413C LPCS/RHR A injection valves Replaced defective test tap plug. ,

reactor presture interir"k 060110875 021 1821HK075 Relay panel Tro'ubleshoot noise, vibration in relay.

970012216 B33 1033-N0180 Reactor Recirculation pump 1B Missing screw from junction box cover suction pressuro-RHR interlock for this pressure switch 9700321 3 CM 1CM002 Valve 3/4' excess flow check Cap for drain / vent.

960031432 CM 1CM002 Valve 3/4" excess fic w check 1CM002 excess flow check valve checks but does not reopen.

970100978 CM 1LT CM030 Suppression pool wide range Disassemble and clean or replace level transmitter 1LT CM030 valve stems.

970098860 CM 1LT CM030 Suppression pool wide range Failed functional test during LIS-CM-level transmitter 301.

970058539 CM iPY-CM05b Suppression pool Alarm function did not work. Unit appears to have power.

970040351 CM 1RR CM011 Post LOCA gross gamma Recorder display is defective, missing recorder segments.

l 970012914 CM 1T R-CM037A Suppression pool water bulk Red pen did not respond, (but display temperature did), during LIS-CM-304.

970070157 CM 11R-CM037A Suppression pool water bulk Pen did not respond dunng temperature performance of LIS-CM-304 970012062 C11 1C11 CRD accumulator wate: side HCU 34-43107 valve quick D001121 10) drain stop valve disconnect leaking through cap 970006308 C11 1C11-N107 Pressure Switch for HCU 18 03 Accumulator alarming intermittently.

970021101 C11 1C34-R603D MSL D Flow Flow indicator indicates flow wi,hout flow conditions.

970015023 C41 1C41 C001A Motor, SBLC pump Secure ground cable with tie wraps.

960109535 C41 1 H S- SBLC stnng tank valve B Rep 1HS C41 AS005 (SBLC sinng C41AS005 tank valve, C41 F001B, in 1H22P011.

97000u363 C51 1C51 tiG05GP Average power range monitor Cable clamp loose at J60 or APRM C channel C 970077880 C51 1C51 K60$GP Average power range monitor Meter mounting screw hole threaded channelC insed is loose 32

O ATTACHMENT B UNIT 1 l

WR No. System EPN Equipment Description  ;

No. Name 97004B447 C61 iC61 AS010 Switch at 1C61P001 for Emergency Switch contact 6-6C en 8-1E12F009/4DD _

BC have high resistance.

970002058 C61 1C61 AS031 1B RHR pump IE12-C002B Replace switch 1C61 AS031, RHR remote shutdown panel pump remote shutdown panel 970002001 C61 1C61 AS036 1E12 F011B B RHR heat Replace switch 1C01 AS036 for exchanger stm cond stop to 1E12-F011B RHR valve in 1C61 remote control switch P001.

900120484 C01 1C01 AS038 1E12 F026B B RHR heat Replace 1E12-F026B (B RHR heat exchanger now to RCIC-remote exchanger flow to RCIC 1C61 AS038; control switch in 1C61 P001.

970001008 C61 1C61 AS040 1E12 F003B B RHR heat Replace switch 1C61 AS040 for exchanger remote control switch 1E12 F0038 RHR heat exchanger.

970002004 C61 1C61 AS041 1E12 F052B B RHR HX inlet stop Replace switch 1C61 ASO41 for remote control switch 1E12 F0528 RHR va've

, 970001265 C61 1C61 AS042 1E12 F0420 0 RHR LPCI Replace 1C61 AS042 in panel 1C61-Injection remote control swit:h P001.

970001266 C61 1C61 AS045 1E12 F048B B RHR HX bypass Replace 1C01 AS045 in panti1C61-stop. remote control switch P001.

970001267 C61 1C61 AS046 1E12 F047B B RHR HX inlet Replace 1C61-AS046 in panel 1C61-stop remote control switch P001.

970001268 C61 1C61 AS056 1E12-F0168 8 RHR containment Replace switch 1C61 AS056 in panel spray upstream isol-remote 1C61 P001.

control switch 970001271 C61 1C61 AS058 1E12 F0270 B RHR suppression Replace 1C61 AS058 in panel 1C61-chamber spray isol stop-remote P001, control switch D6111324 C61 1HS- 1E12-F024B B RHR pump full Replace 1HS-C61 AS037 in panel C61AS037 flow test stop-remote control 1C61 P001.

switch 970023722 C71 1C71 S003-A 1 A RPS MG set electnc power Replace breaker in accordance with monitoring assembly bkr A GE SIL No. 606 970023723 C71 1C71 S003-C 1 A RPS MG set electnc power Replace breaker in accordance wito monitoring assembly bkr C GE SIL No. 606.

970057341 DC 1DC01E 250 VDC battery Cell #103 has excessivt. corror, ion.

970095575 DC 1DC01E 250 VDC battery Several cells have corrosion present.

970083900 DC 1DC07E Assy 125 VDC battery Div 1 Cells 4,9,18,19,29 and 43 have corrosion present, clean and greased 33

u j .

2 i

ATTACHMENT B

UNIT 1 i

WR No. System EPN Equipment Description i

No. Name 970095573 DC 1DC07E Assy 125 VDC battery Div-1 Cells 5,15,16,17,27, and 33 need

to cleaned, greased, and checked.

970093899 DC 1DC11E CB13 0 DG control panel ODG02JA When the breaker was tumed on caused a +55 Volt ground.

970026998 DC 1DC17E Charger,125 VDC battery Div-2 Ground connection AY charger is loose.

960106788 DG 1DG006 1 A DG cooler upstream stop Valve has packing leak of 1 drop per 10 sec.

970012415 DG 1DG01A Heat exchanger, DG Cooling inner portion of divider plate on HX Water leaks.

970012415 DG 1DG01A Heat exchanger A DG Weld repair required on 1DG1 A HX C channel divider.

970012415 DG 1DG01 A Heat exchanger, A DG install channel once repaired.

970023283 DG 1DG01 A Heat exchanger, A DG Disassemble, repair, and reassemble.

970023283 DG 1DG01A Heat exchanger, A DG Weld defect area on channelinside diameter.

970026566 tfG 1DG01F Strainer, standby ENG cooling 80 DPM leak around backwash shaft, water 960075105 DG 1DG01F Reducer, speed cooling water Small air vent on side of gearbox for strainer basket drive missing cap.

970024980 DG 1DG01K DG 1 A Bolt 1 ose on base, tighten.

970026367 DG 1DG01K DG 1 A Terminal voltage would not come up to normal.

960085746 DG 1DG011 DG 1 A cooling water strainer Valve play beyond acceptable limits.

backwash 970065930 DG 1DG014A SE cubicle area cooler flow One packing follower nut is missing.

Instrument low side pressure test ennnection stop 970065939 DG 1DG0414B Cubicle area cooler flow One packing follower nut is missing.

Instrument high side pressure test connection stop 970012918 DG 1DG02JA DG-1 A, A-phase CO-6 overcurrent Existing relay operating relay,1451 DG011 A inconsistently, replace with a new one.

970008328 DG 1DG02JB Assy, panel, DG control Make winng changes as directed by system engineer.

900116251 DG. 1DG03J Assy, panel, DG control Amber light socket for 1 A DG air compressor is broken. y 960069047- OG- 1DG043 1 A DG cooling water strainer Valve leaks by approximately 1/4 to 1DG01F drain stop 1/2 gpm.

970023477 DG 1DG0498 Valve, DG air start comp Acoustical testing has shown valve discharge check degraded.

34

l ATTACHMENT B UNIT 1 l l

WR No. System EPN Equipment Description No. Name 970009033 DG 1DG005 1 A DG cooling water strainer 1/4 gpm of water leaks past seat 1DG01F vent stop when valve is closed.

970023481 DG 1DG08DA Dryer, standby DG refrigerated air Dryer is not operating. check power.

900041337 DG 1DG082 1 A DG engine lube oil drain stop Drain valve la ser. ping oil.

970074146 DG 1DG23B Pipe Internal pipe pitting and wall thinning.

900118246 DG 1HS-DG001 DG 1 A cooling water pump Replace 1HS DG001 in panel 1DG01P 1PM01).

,960118259 DG 1HS-DG038 Replace SBM switch 1HS-DG038.

142Y feed from DG1 A (ACB 1423) 970093675 DG iSI DG028 Meter, frequency 1PM01J A DG Indicated frequency did not reach 60 Hz within 13 sec limit.

900121275 DG 1T S-DG040 DG immersion htr cont Heater not controlling properly, should be 110120 not 140-15.

970086078 D18 1D18 J009 Assy, panel, service water incorrect piping materialinstalled, effluent replace 970052023 D18 1018-K609A Reactor building vent monitor Verify correct fuses are installed in K609A.B,C.

970029737 D18 1 D18-K610D Main steam line D monitor Possible loose connection, alarmed downscale.

970067079 D18 1D18 K6148 Reactor building vent power Wrong screws holding power cable supply connector or comes loose.

970067081 D18 1D18-K614C Reactor building vont power Wrong screws holding power cable supply connector or comes loose.

970067682 D18 1D18 K614D Reactor building vent power Wrong screws holding power cable supply connector or comes loose.

970044712 E12 Relay 1E12A-K95A Relay has high resistance across contacts.

970002023 E12 1E12 AS013 1E12 F0498 8 RHR HX BD Replace 1E12-AS013 SBM for RHR upstream isolation to RBEDT valve 1E12 F049B in panel 1H13 P601.

D60118953 E12 1E12 AS041B Air supply isolation to valves Replace 1HS-E12AS041 B (for 1E12 1E12 F0518 and 1E12-fua5B F051B/1E12-F065B) on 1H13-P601.

960119928 E12 1E12-AS058B 1E12-F0878 B RHR HX steam Replace 1HS E12AS0588 on 1H13-inlet PCV bypass stop P601.

960120079 E12 1E12-AS0648 1E12 F099b B RHR loop testable Replace 1E12-AS064B in panel check bypass valve 1H13P601.

970036325 E12 1E12 C002A Cooler, RHR pump A seal Existing mounting bracket bolts are lastalled incorrectly, 35

ATTACHMENT B UNIT 1 WR No. System EPN Equipment Description No. Name 970002930 E12 1E12 C002B Motor, RHR pump Motor heater elements deteriorating, ceramic insulator crumbling.

970027671 E12 1E12-C002B 1B RHR pump Remove and replace insulation associated with seal cooier.

970032508 E12 1E12 C002B Cooler, RHR pump B seal Mounting bolts installed from the bottom without washers.

970002932 E12 1E12 C002C Motor, RHR pump Motor intake screen is loose and falling off.

970027673 E12 1E12 C002C 1C RHR pump Remove and replace insulation associated with seal cooler, 970031243 E12 1E12-C002C Cooler, RHR pump C seal Tighten the mounting bolts to seal cooler.

970015639 E12 1E12-C003 RHR water leg pump Pump has been venfied filled and vented by a special procedure.

970093662 E12 1E12 C300A RHR service water pump 1E12 C300A, replace pump outboard bearing end cover.

970068570 E12 1E12 C300D D RHR service water pump Broken tie straps need to be replaced.

970073644 E12 1E12 F003A Vatve, RHR HX SHl>SD out Valve cannot close fully to prevent pressure lock / thermal bind.

970092231 E12 1512-F041 A Actuator, air, RHR testable check Unable to cycle valve using actuator.

viv 970002928 E12 1E12-F0418 B RHR injection testable check. Dualindication when closed.

30' 970034383 E12 1E12 F049B B RHR HX BD upstream isolation 1E12-F0498 has packing leak to RBEDT soproximately 30-40 gpm.

970034383 E12 1E12 F049B Actuator, RHR discharge RW t/B 1E12 F0498 pull and test springpack, isolation valve 960120891 E12 1E12 F064A A RHR pump min flow bypass Valve leaking by.

stop 960120891 E12 1E12 F064A . Actuator, RHR pump min flow Valve leaking by, bypass viv 970096602 E12 1E12 F065A Actuator, air steam initiate Actuator positioner has a hair line crack and is blowing air.

970038999 E12 1E12 F092A A RHR LPCI injection line man Handwheel nut is loose on 1E12 stop F092A.

970007822 E12 1E12 F330A A RHR service water pump Handwheelis loose on TJE pinion suction stop shaft.

970005960 E12 1E12 F330C C RHR service water pump . Handwheelis loose.

suction stop 4

36 e-

.w,.- gy,v-,--ww- -me, , - - , - - . my- , + , . g pier p - ,- y9 'og--jy yi-,---#-w,g.-- -s- -m+% w gr- +- p .yey.,y<'- ----- g p- .-

ATTACHMENT B UNIT 1 WR No. System EPN Equipment Description No. Name I

960093553 E12 1E12 F3320 C RHR service water pump Repair bent stem per NDIT No. LS-discharge stop 0458 up grade 1.

960093554 E12 1E12-F332D D RHR service water pump Repair bent stem per NDIT No. LS-discharge stop 0458 up grade 1. l 970008705 E12 1E12 F336B Valve, RHR service water strainer Replace elbow attached to valve ,

1 E12-F3368. j 970092315 E12 1E12 F343A A RHR pump discharge pressure Nuts that hold packing bracket are l instrument stop missing i 970003126 E12 1E12-F430A Ball valve Replace lower bearing oil drain valve.  !

970064854 E12 1E12 N010BA RHR flow 1B pressure diff Equalizer valve leaking by when -

closed.

970064854 E12 1E12-N010BA RHR flow 1B pressure diff 1E12 N010BA failed the diaphragm integrity test.

970080581 E12 1E12 N010CA RHR flow 1C pressure diff Screw missing from Junction box on back of rack.

970003732 E12 1E12-N016B RHR pump 1B discharge Backfill B and C RHR instruments pressure after maintenance.

970073076 E12 1E12 N019B RHR pump 18 discharge Utility box is missing screw, pressure 960120891 E12 1E12 N034A RHR pump 1 A discharge Backfill the following instruments:

pressure 1 E12-R002A, NO34A, N016A.

970027117 E12 1E12 N413A RHR injection valve reactor press 1E12-N413A test tap is stripped, interlock replace.

970080317 E12 1E12 R601 Temperature recorder Switch for noimal position 1 is in backwardo.

970066225 E12 1E12 R603B RHR pump 18 discharge flow to CRWR B RHR discharge pressure reactor indication out of calibration.

960120487 E12 1E12 S500 RHR service water pump 1C Replace 1E12 S500in C61 P001, remote chtdn pnl cont switch 960120493 E12 1E12 S502 1D RHR service water pump Replace 1E12-S502 in C61.P001.

~

remote shtdn pnl cont switch 970002002 E12 1E12 S504 1C61P001 Div 2 instrument Replace 1E12 S504 in C61 P001.

transfer switch 960121506 E12 1E12-000 Misc. work requests Support FRH-1224 H07 not installed.

970042684 E12 1E12 000 Misc. work requests Upgrade or replace reducers downstream of the 1E12 F068A.

960104149 E12 1E1200028 Cooler, RHR pump B seal Design pressure is to low, replace seal cooler.

960104149 E12 1E12C002B Cooler, RHR pump B seal Rework cooler piping 960104791 E12 1E12C002C Cooler, RHR pump C seal Rework cooler piping.

37 l

ATTACHMENTB UNIT 1 WR No. System EPN Equipment Description No. Name 960104791 E12 1E120002C Cooler, RHR pump C seal Design pressure is to low, replace seal cooler.

960107804 E12 1E12F018A A pump minimum flow bypass Valve is hard to operate. Operator is man stop loose.

940083992 E12 1E12F049A Actuator, RHR dischar9e RW t/B Perform dynamic votes test on isolation valve 1E12F049A in L1R07P.

960093553 E12 1E12F332C C RHR service water pump Repair valve disc.

discharge stop 960093553 E12 1E12F332C C RHR service water pump Repair valve body based on discharge stop engineering examination.

960093553 E12 1E12F332C C RHR service water pump Inspect or repair valve based on discharge stop findings on 2E12 F332A valve.

960093554 E12 1E12F332D D RHR service water pump inspect or repair valve based on discharge stop findings on 2E12 F332A valve.

960093554 E12 1E12F332D D RHR service water pump Disc repair 1E12 F332D, discharge stop 960093554 E12 1E12F3320 D RHR serv 6ce water pump Repair valve body based on discharge stop engineering examination.

960086860 E12 1E12F336B Valve, RHR service water strainer Valve play beyond acceptable limits.

960086860 E12 1E12F3368 Valve, RHR service water strainer Freeze seal.

960086860 E12 1E12F336B Actuator, RHR service wat6r Determ, remove, and reinstall, test sp-strainer pack, sig trace.

960118273 E12 1HS- 1B RHR pump 1E12 C002B Replace 1HS E12AS003B in panet E12AS0038 1H13-P601.

960118277 E12 1 HS- 10 RHR pump 1E12-C002C Replace 1HS-E12AS003C SBM E12AS003C switch in panel 1H13-P601.

960118498 E12 1HS- 1E12 F0168 B RHR containment Replace 1HS E12AS0098 for 1E12 E12AS009B spray upstrm isol F016B on panel 1H13-P601.

960118501 E12 1HS- 1E12-F042B B RHR LPCI Replace 1HS-E12AS010B on panel E12AS010B injection line 1HS13-P601, 960118503 E12 1HS- 1E12-F042C C RHR LPCI Replace 1HS E12AS010C on panel E12AS0100 injection line 1HS13-P601.

960118504 E12 1 HS- 1E12-F021 C RHR pump full flow Replace 1HS-E12AS011 on panel E12AS011 test stop 1HS13-P601.

960118507 E12 1 HS- 1E12 F024B B RHR pump full Replace 1HS-E12AS0128 on panel E12AS012B flow test stop 1H13-P601.

960118510 E12 1HS. 1E12 F0178 B RHR cnmt spray Replace 1HS-E12AS014B on panel E12AS014B dwnstrm isol stop 1H13-P601.

960105410 E12 1 HS- 1E12-F064B B RHR pump Replace 1HS-E12AS0160 on panel E12AS016B minimum flow bypass stop 1H13-P601, 38

. l ATTACHMENT B UNIT 1 WR No. System EPN Equipment Description l No. Name l 960118957 E12 1 H S- 1E12 F064C C RHR pump Replace 1HS E12AS0160 on panel E12AS0160 minimum flow bypass stop 1H13-P601.

960118959 E12 1HS. 1E12 F047B RHR heat Replace 1HS E12AS034B on panel E12AS0340 exchanger intet stop 1H13-P601.  ;

960118942 E12 1HS- 1E12 F003B e RHR heat Replace 1HS-E12AS035B on panel E12AS035B exchanger outlet stop 1H13 P601.

960118946 E 12 1HS- 1E12 F0268 B RHR heat Replace 1HS-E12AS0360 on panel E12AS036B exchanger flow to RCIC 1H13-P601.

. 960118948 E12 1 HS- 1E12 F011B B RHR Hz stm cond Replace 1HS-E1 AAS0378 on panel E12AS0378 stop to sup chamber 1H13 P601.

960105409 E12 1H S- 1E12 F048B B RHR Hx bypass Replace 1HS-E12AS0398 on panel

. E12AS0398 stop 1H13-P601.

960105413 E12 1 HS- 1E12 F073B B RHR Hx vent Replace 1HS-E12AS040B on panel E12AS040B downstream stop 1H13 P601.

960105574 E12 1HS- 1E12 F074B B RHR Hx vent Replace 1HS E12AS054B on panel E12AS054B upstream stop 1H13-P601.

960105412 E12 1 HS- 1E12 F0528 8 RHR Hx steam Replace 1HS-E12AS069B on panel E12AS059B inlet stop 1H13-P601.  ;

970045175 E12 1RH000 Constant snubber above 1E12 Constant snubber above 1E12 F092A F092A contacts strut RH-40,1561. ,

960023862 E12 1 21 RHR heat exchanger A vent to Indicates 5% when closed and 88%

E12R608A sup pool viv pos when open.

, 970050809 E21 1E21 F005 Actuator, LPCS injection valve SMB2, replace position indicator and 3 adjust.

970096938 E21 1 E21.F312 LPCS water leg pp doch press ind Valve missing 1 of 4 bonnet to body 1E21 R500 root valve bolts.

970006293 E21 1E21 N413 LPCS inj viv rx press intik Backfill 1 A RHR instruments after maint if required.

970027073 E21 1E21 N413 LPCS inj viv rx press intik Vent valve packing is leaking.

970080319 E21 1E21 N413 LPCS inj viv rx press intik Stop valve leaks by and packing leaks when closed.

970008566 E21 1E21000 misc. work requests 1LP246B-1/2" rework U-bolt support.

I 960078722 E21 1E21 LPCS inj viv rx pressure interlock Repair wire terminations on terminal ,

E21N413 block BB. pts 1 and 2.

970025339 E22 1E22-C002 Pp HPCS diesal cooling water Filt and vent the suction and discharge pressure gages, 960111710 E22 1E22-C002 HPCS diesel cooling water pp Open and repair pump as deemed necessary by system engineering.

960111710 E22 1E22-C002 HPCS diesel cooling water pp Send pump back to OEM for casing repair.

? 900111710 E22 } 1E22-C002 HPCS diesel cooling water pp Reinstall rebuild pump.

4 a

5 39

ATTACH 4ENT B UNIT 1 WR No. System EPN Equipment Description No. Name 970006249 E22 1E22 D306 Onfice HPCS water leg pump While performing LOS-HP-Q1 the min flow line water leg pump discharge.

970007639 E22 1E22 F310 1B DG cool wtr pp suct stop Packing leak, needs to be repacked not much adjustment.

970020630 E22 1E22-F313 18 DG cooler inlet valve 1E22-F313 needs repack, leaking ,

970045168 E22 1E22 F322A SW(HPCS) cubicle area cooler The follower gland nuts are loose, flow test instr lo leg stop 970045169 E22 1E22-F323 SW(HPCS) cubicle area cooler The follower gland nuts are loose, init press test conn root stop 970070628 E22 1E22 F345 1B DG cooler inlet header relief inlet flange studs have improper valve thread engager,ent.

970031482 E22 1E22 F351 1B DG cooling water strainer inlet Downstream pipe nipple and cap hl point t ent stop need to be extended.

970002819 E22 1E22 K072 Relay, cont local cont pnl K72 relay is buzzing very loud.

soakback oil 910017854 E22 1E22 N006 HPCS pump d:Scharge min flow 1E22 N006, install missing pipe bypass interlock clamp, 970034956 E22 1E22 N012A HPCS pump discharge pressure Test tap fitting is difficult to remove, replace fittings.

970034958 E22 1E22 N012B HPCS pump discharge pressure Test tap fitting is difficult to remove, replace fittings.

97044465 E22 1E22 N504 HPCS DG air start press A Replace missing screw and install end of chain on screw.

970044462 E22 1E22-N509 HPCS DB eng dnven fuel oil Replace missing screw on bottom of pressure pressure switch 1E22-N509.

970045056 E22 1E22 N511 HPCS DG lube oil hi temp Missing conduit fitting on bottom of pressure switch 970044460 E22 1E22-N513 HPCS DG lube oillo press Replace missing screw in bottom of pressure switch.

970044461 E22 1E22 N520. LPCS DG wtr cool ws lo press Replace missing screw on bottom of l

pressure switch 1E22 N520.

970044463 E22 1E22 N521 HPCS DG water cooljacket water Install other end of chain under screw.

Iow pressure 970083064 E22 1E22-P301B Assy, panel, HPCS DG engine All annunciators remain dimly lit after control reset P/B pushed.

970078254 E22 1E22-R623 Meter, speed 1H13P601 HPCS Speed indicator fluctuated during DC dieset run.

i 970057342 E22 1E22 S001 Engine HPCS DG Two relays functioning erratically.

970078254' E22 1E22-S001 18 diesel generator 18 diesel generator inpped.

l 970046280 E22 1E22-S001B Pump, DC turbo soakback Replace pump to motor shaft coupling and roll pin on mtr shft.

l l

40

o ,

ATTACHMENT B  :

UNIT 1 WRNo. System EPN Equipment Description No. Name 970026630 E22 1E22 S001N HX, diesel cooling water Heat exchanger is leaking on inside }

Joint on west end, 970020030 E22 1E22 S001N HX, diesel cooling water Require additional weld repair to floating channel.

970020630 E22 1E22 S001N HX, diesel cooling water 1E22 S001N wbid repair on new channel piece.

970026630 E22 1E22 S001N HX, diesel cooling water Perform preliminary leak test on heat exchancer.

970026630 E22 1E22 000 Misc. work requests 1E22 S001N repair corroded intemals of heat exchanger, 960038071 E22 1E22-D318A Lubncator, air start system 1E22 D318A rebuild 1B DG air start olier needle valve. i 960085747 E22 1E22 F319 DG 1B cooling water strainer Valve play beyond acceptable limits, backwash outlet 960074278 E22 1E22- HPCS DB MD pump fuel oil Rewere 1PS E22N508 and N509 to E22N508 pressure match as built piping prints.

970049636 E31 1E31 N009D B MS line high flow Screw is missing from junction box c.n back of rack.

970051603 E31 1E31 N010A MSL C high flow switch Conduit fitting is loose at junction box.

970021142 E31 1E31 N010A MSL C high flow switch Condurt fi' ting is loose at Junction box.

970049642 E31 1E31 N0118 MSL D high flow switch Screw is missing from Junction box on back of rack.

970040977 E31 1E31 N012AA RHR water supply high flow Backfill SDC header insts after LLRT detection 970012206 E31 1E31 N013BA RCIC stm supply high flow Vent test taps are not at tne same detection height.

970085504 E31 1E31 R620 RWCU diff flow With system on. frequent spikes in detta flow indication-970009034 E51 1E51 R606 RI pp discharge flow Instrument nonrepeatable due to sensitivity to static. ,

970096849 FC 1FC000 Pipe downs?eam of 1FC155 RHR Remove fittings and ,nstall pipe cap.

to FC high point vent 970039001 FC_ 1FC069B B filter / demon outlet stop Valve leaks by it's seat, requires minor adjustment.

940058095 FC 1FC133 Assy, valve, globe Leaks by approximately 1 gptn.

970081363 FC 1FE FC038 Fuel pool emergency pump 1 A Venty flow orifice size.

discharge 970081363 FC' 1FE FC038 Fuel pool emergency pump 1 A Repair flange faces per edit.

discharge 41

._ _ - - . _ - - _ ,_ _ _ _ _ _ , _ - . . _,-___ _ _~

i r

ATTACHMENT B UNIT 1 1 ,

WR No. System EPN Equipment Description No. Name  !

4 970089359 FP 1FP000 Misc, work requests 1F P000-dry-pack abandoneYtlirL-bolt holes.

l 970026630 HP 1HP53A Pipe 1HP53A-6*/1HP 528-6' refurbish inlet i

and outlet flange faces.

970024064 H13 1H13-P622 Assy, panel, l/B valve relay Replace broken glass on relay cover.

, 910012259 H22 1H22 P001 Assy, panel, LPCS instr rack Remove piece of wood that is wired to top of panel.

970045052 H22 1H22 P001 Assy, panel, LPCS instr rack Wire showing through insulation on

, vhe lugs AA-2 and AA-4.

970013896 IN ilN095A Compressor, D/W pneumatic air Vent valve missing pipe cap; replace 1 cap.

! 970014811 IN 1PSIN015 Accum 1821 A003D vent stop, Missing 1 mounting bott. 2 cover ho;d 120' down nuts not engaged

, 970025034 PL 1PL25J N2 bottle bank south side header Local audio alarm sounds weak and

! pressure cuts out, i 970044401 PL 1PL29J Assy, panel, DB room vent Push-button will not actuate alarms, l.

system Div 2 i l 970010913 PM 1PM05J Assy, panel, SWGR heat removal CRWR repaint 1PM05J on areas

, Div i where labels were removed. '

t 970080669 PP iPP000 Misc. work requests Electncal penetration E 26 below minimum pressure.

970015572 RH 1E12 C003 Div 2 water leg pump Request IMD vent pump 1E12 C003 at gage line for PI 1E12 510 J

970045173 RH 1RH000 Misc. work requests Whip restraint locking nuts were found to be loose.

970073644 RH 1RWJ3-1541X 1RH03AA 18 subsystem 1RH24, Remove and replace LISEGA strut to rigid selsmic restraint accommodate valve repairs ,

970074147 RH 1RH00AA Pipe internal pipe pitting and wall thinning 960108571 SH iSH000 Misc. wa k requests Add lifting lugs for the unit 1 VR and VT SH coils.

900086643 VC 1VC000 Misc. wo k requests J clip on Junction box 10' off floor is missing 970032995 VD 11CU VD003 DG01K room damper Venfy that a 1/10 emp fuse is in the ,

IVD17Y/18Y controller.

970052644 VD iTCU VD013 DG01K room damper Venfy that a 1/10 amp fuse is in the -

IVD17Y/18Y controller.

970023222 VD 1TYC VD008 DG01K room damper 1TYC VD008 found with no output, IVD11YA/YB failed dampers 1VD11YA and YB.

l 1

f 42 +

I i

- _ . - - . _ ~ _.. - _ _ _ , _ _ _ . . _-_ _ _ . _ _ - , ~ , . . . - - . . . . - _ . . _ _ _ _ _ _ _ _ _ _ - _ _ _

ATTACHMENT 8 UNIT 1 WR No. System EPN Equipment Description No. Name 970022904 VD 1TZ-VD008C DG room 1DG01KDPR 1VD11YA Actuator appears to have failed to and 11YB open, check actuator.

970052644 VD 112 VD0138 DG room 1DG01PMDD DPR HPCS DG cooling water pump cubicle 1VD18Y vent dampers defective 970017805 VD 1VD000 Misc. work requests Replace missing cover screws

~

Sl#664152.

960108325 VD iD000 Misc. work requests Troubleshoot, repair VD system duct work.

970075387 VD 1VD020 Assy, tan, HPCS DG fuel storage Take duct air flow data on F.O.S.T tank room vent exh fans.

970075388 VD 1VD02C Assy, fan, HPCS DG fuel storage Take duct air flow data on F.O S.T tank room vent erb tans.

970087405 VG 1FR VG009 Recorder SBOT train out flow Indicates 380 CF M flow with system shutdown.

970015502 VG 1FT VG003 SBGT train inlet flow transmitter 2 cover screws not flush with surface, check all screws.

970015507 VG 1FT VG009 SBGT train outlet flow transmitter Screws on front of enclosure need to be replaced.

970014594 VG IVG02C Fan, SBGT system cooling Bolt missing screw or, valve handle. ,

970015504 VG 1VG021A SBGT influent flow transmitter Replace missing screw on valve high side instrument stop handle.

960071049 VQ 1VQ068 DW vent / purge outlet downstream Troubleshoot and repair, isolation bypass 960069079 VX 1VX01F Filter essential switchgear Div i 1VX01F seal Div 1 switch gear room vent supply air train access dcors 960111275 VY 1HS VY003 RHR pumps B and C cubicle Replace 1HS-VY003 (RHR pump B/C /

cooler fan 3 cub cir 1VYO3C) on iPL33J.

960080619 VY iTIC VYO23 RHR WS pump A/B temp cont Received cubicle high temp alarm at mod damper 96F room temp, recalibrate.

970052646 VY 1 TIC VY023 RHR WS pump A/B temp cont Venfy that a 1/10 amp fuse is in the mod damper controller.

960097065 VY 1 TIC VYO24 RHR W1 pump C/D temp cont Alarm comes in with normal room mod damper temperatures.

960082000 VY 1VY01A Coil, cooler, CSCS equipment Cooler DP is high. Cooler needs to RHR A pump cubicle be chemically cleaned.

900082609 VY 1VYO4A Coil, cooler, CSCS equipment Cooler DP is high Cooier needs to LPCS pump cubicle be chemically cleaned 970029241 ZZ 1ZZ000 Misc. work requests Remove hat rack.

960106762 ZZ 1ZZ000 Misc. work requests Threaded rod (3) coming thru wall, cutoff and seal.

970101678 AP 1AP000 Misc. work requests Loose screws on junctioa box 1JB298C.

43

ATTACHMENT B UNIT 1 WR No, System EPN Equipment Description No. Name 970106714 AP 1AP000 Misc work requests Cover missing bolts.

960102299 AP 1AP21E 302B Switchgear 136X min feed from Troubleshoot and repair rocking 142Y mechanism problem.

970108543 AP 1 AP22E 4928 Switchgear 146Y main feed inspect racking pin gap and adjust.

970101995 AP 1AP75E B2 CRD cooling water pressure MCC breaker handle is broken.

throttle valve Replace handle.

970089972 AP 1 AP76E E5 1B RHR shutdown cooling return Breaker handle must be pushed in it)

Isolation breaker engage shaft to operate breaker, 970050922 AP 1 AP76E E5 1E12 F053B B RHR shutdown Broken external reset button on cooling discharge isolation switchgear 135%2.

970011782 AP 1AP79E 480 VAC MCC Thumbscrew does not engage.

970092393 AP 1 AP82E C2 RHR heat exchanger flow to intemal winng interferes with thermal suppression poolvalve PB operation.

950008345 AP 1AP83E A2 Spare Dunng LES-GM 109 breaker failed to

~ close 970106713 B21 1B21 F013M- SRV M IMF 2 solenoid valve *C" Metal flex sealtite bent and frayed at C junction box.

970101706 B21 1B"41 N004N Temperature element well Flexible conduit pulled out of fitting, wire exposed.

970102048 B21 1B21 NO34A Reactor core jet pump 1 flow One of the low side stop valves is leaking by its seat.

970099635 B21 1821 N413A LPCS/RHR A injection valves instrument vent test tap cap is reactor pressure interlock defective and needs replacement.

970027115 021 1821 N413A LPCS/RHR A injection valves Test tap cap / plug is damaged replace reactor pressure interlock with ntw plug.

970099034 B21 1821 N4130 LPCS/RHR A injection valves Instrument vent test top cap is reactor pressure interlock defective and needs replacement.

970027116 B21 1B21 N4130 LPCS/RHR A injection valves Test tap cap / plug is damaged replace reactor pressure interlock with new plug.

970108357 B21 1821 N7058 Reactor vessel water level 8 Calibration unit did not insert cal RCIC inp input.

970050931 CM 1CM000 Misc. work requests Cable tray support disconnected and junction box cover is off.

960031432 CM 1CM002 Valve 3/4' excess flow check Excess flow check valve checks but will not reopen.

970133464 CM 1 AIR CM012 Post LOCA H2/02 volume Stop screwis missing on inside front cc ,.r or 1 AIR CM012.

970100978 CM 1LT CM030 Suppression-pool wide range Disassemble and clean or replace level transmitter valve stems.

44

.=

_ __ _______.._____.._d

ATTACHMENT B UNIT 1 WR No. System EPN Equipment Description No. Name 970098860 CM 1L1-CM030 Suppression pool wide range Failed functional test dunng LIS-CM.

level transmitter 301.

970058539 CM iPY CM055 Suppression-pool pressure Alarm function did not work. Unit appears to have power 970101676 CT 1CT000 Misc. work requests Cover plate screw loose on 1C1016.

970108488 C34 1C34 R606C Reactor water level control Indicator span not adjustable to within limits 970100939 C34 1C34 000 Misc. work requests Reactor level instrument line supports not in tension 970015023 C41 1C41 C001 A Motor. SBLC pump Secure ground cable with tie-wraps.

970078495 C41 1C41 N003 SBLC tank temperature Failed LIP SC 503 replaced switch 970077903 C51 1C51 BS003 APRM bypass selector switch Rubber dust boot is broken.

970020049 C51 1C51 K601 A IRM Channel A monitor *A* IRM caused a spunous half scram.

960117567 C51 1C51 K601B IRM CN :) B monitor Ground strap on *B' IRM drawer needs to be replaced. Cable clamp loose at J4 on chassis.

970130449 C51 1C51 K601E IRM Channel E monitor Spunous 1/2 scrams dunng LIS-NR-306.

970078491 C51 1C51 APRM Channel A Right side of APRM *A* 20V power K60$GM supply pushed in past stop.

970007251 C51 1C51 K901B LPRM Channel B All LPRM lights on panel are de-energized.

970098910 C51 1C51 N002C IRM Channel C detector IRM *C" failed pressure test.

970096584 C51 1C51 N002E IRM Channel E detector IRM *E' has degraded shield to ground resistance.

970105748 C51 1C51 S001K Detector nye module. 'RM F IRM *F* failed leak test LIP NR 905.

970005023 C51 1C51 S302 Penetration, neutron monitor elect Penetration E12 cover has loose and/or cross threaded bolt.

970005624 C51 1C51 S304 Penetration, neutron monitor elect Penetration E11 cover is missing screws.

970134815 C51 1C51 R603D IRM/APRM channel recorder IRM H benchboard downscale light socket is worn.

900117567 C51 1RY. IRM Channel *B* monitor IRM *B' spiked when under vessel C51K601B cables were moved. ,

970095575 DC 1DC01E Battery 250 VDC Several cells have corrosion.

970079336 DC 1DC07E Assy, battery,125 VDC DIV 1 Cells 6,16,23,30, and 31 have corrosion present.

45

a

)

• I ATTACHMENT B i UNIT 1

! WR No. System EPN Equipmeni Description No, Name

970028578 DC 1DC11E Assy, panel,125 VDC distnbution Vanous bolts are missing and others i 111Y are loose.

l' 970061797 DC 1DC13E DIV 2125 VDC distnbution panet Bus inspection cover missing, screws

. 112Y missing

) 970100918 DC 10C14E Assy, battery,125 VDC DIV 2 Cell #5 has black corrosion on j terminal gnd bar. _ .

! 970114477 DC 1DC14E Assy, battery,125 VDC DIV 2 Mild corrosion on various cells 970037174 DC 1El DC060 1PM01J, charger 125 VDC DIV-2 indicated 128 VDC when multiple voltage indicator redundant indicator read 131 VDC.

970112323 DC 151-DC002 Battery charger 1DC17E DC 1DCt&E U 1 DIV 2 charger voltmeter i

voltmeter has broken indicator.

i 970031395 DG 1DG003 1 A DG cooling water pump Perform weld repairs to disc.

l discharge valve j 970031395 DG 1DG003 1 A DG cooling water pump outlet inspect / repair valve internals.

l stop_

l 970031395 DG 1DG003 1 A DG cooling water pump Repair guides on valve.

discharge valve .

} 970031527 DG 1DG006 1 A DG cooler outlet throttle valve Replace valve due to excessive

corrosion.

970056844 DG 1DG01F 1 A DG cooling water strainer Strainer backwash shaft seal leaking continuously.

970110567 DG 1DG01K 1 A DG Erratic variable indication during >

diesel generator loading 970110308 DG 1DG01K 1 A DG Replace missing bolt and fix stnpped

! out thread on DG panel.

970045242 DG 1DG01K 1 A DG Replace oil dipstick and remark with 1 sper oillevel marks.

960085704 DG 1DG01P DG engine cooling water pump dutboard pumo sealleaks approximately 20 drops per min while

running.

970085202 DG 1DG049B 1 A DG B starting air compressor 1DG0498 valve failed test.

~

discharge check valve Disassemble, inspect and repair.

970025142 DG 1PI DG098A DG 1 bank A starter air supply Matenal on inside of gauge face.

970117069 DG iSTS-DG076 DG tachometer transmitierl switch The 1 A DG failed to start dunng surveillance.

970081492 DG 1STS-DG076 DG tachometer transmitter / switch inspect and/or repair speed signal wiring in 1 A DG.

S70081492 DG 1STS-DG076 DG tachometer traTsmitter/ sw'tch Spee,1 tach winng cable may be defective.

2 4

46 4

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l ATTACHMENT B l UNIT 1

.WR No. System EPN Equipment Description i No. Name i

"970117057 DG iSTS-DG076 DG tachometer transmitter / switch Troubleshoot / repair 1 A signal speed 4

tach i 970048455 DG 1TS-DG040 DG immersion htr cont Temp switch does not maintain temp within the required tolerance.

, 'WDi08(f53- DO 1LSL DOOO9 Diesel HPCS fuel storage tank Storage tank lowlevel alarm came in

, at 18 8'instead of 18.5'.

i ,F/0003331 D18 1D18 K61re Main steam line B monitor Touching the outside of draw causes the downscale alarm. .

9730I0f89 D18 1D18 K614C Reactor Bldg vent power supply Power supply 24V neg failed when checking during surveillance.

970021197 E12 1E12 8001A RHR heat exchanger 1 A Weld plug in RHR HX 1 A tubes.

970092318 E12 1E12 D3000 8 RHR service water strainer Open and inspect strainer.

) 970073644 E12 1E12 F003A Valve, RHR HX Valve cannot close fully to prevent pressure lock / thermal bind.

2 970073667 E12 1E12 F003B W o, RHR HX Valve cannot close fully to prevent

- pressure lock.

970101572 E12 1E12 F009 Valve, RHR suction cing 1/B iSol Downstream of this valve in drywell, support jam nuts loose. ,

970048042 E12 1E12-F0490 Actuator, RHR discharge RW t/B Troubleshoot breakerinp. Tnp test isolation valve breaker.

970021120 E12 1E12 F0538 Actuator, RHR SDC inject valve Grease relief valve broke.

970096602 E12 1E12 F065A Actuator Air steaminitiate Actuator positioner has a hair line

erack and is blowing air.-

i 970039751 E12 1E12 F068A A RHR heat exchanger outlet Disassemble and reassemble valve. ,

stop valve 970039772 E12 1E12 F068A B RHR heat exchanger outlet Disassemble and reassemble valve.

stop valve Remove electricalinterference in support of disc / guide.

970031391 E12 1E12 F073B Actuator, RHR HX vent valve Strut support 1RH52H07S skewed, pipe clamp rotated.

970031392 E12- 1E12 F074B Actuator, RHR HX vent valve Strut support 1RH52H03S skewtsd, pipe clamp rotated.

970092303 E12 1E12-F313B Velve, RHR HX channel relief Rebuild relief valve.

! 970049537 E12 1E12 F3530 C RHR service water pump Valve leaks by excessively when discharge pressure indicator (PI- closed:

1E12 R503) stop -

970049541 E12 1E12 F3530 D RHR service water pump valve leaks by excessively when

discharge pressure indicator (Pl. closed.

1E12 R503) stop i.

47

.4 4

ATTACHMENT B UNIT 1 WR No. System EPN Equipment Description No. Name 970019770 E12 1E12 F4088 RHR . stvece water strainer 1B Repack and replace as needed.

drain 970006979 E12 1E12 N006A RHR heat exchanger 1A serv 6ce Remove and inspect for erosion and water inlet flow corrosion.

970098384 E12 1E12 N0008 Flow onfice assy Venfy 300# onfice installed and replace if not 300#.

970081603 E12 1E12 N010CA RHR flow 1C pressure diff Sealtite is loose in connector on switch.

970021151 E12 1E12 N010CB RHR flow 10 pressure diff Sealtite is loose in connector on switch.

970111879 E12 1E12-N511 1B RHR service water rad Sample probe broken and loose in monitor probe pipe, needs to be replaced-970080317 E12 1E12 R601 Temp recorder Switch for normal position is in backwards.

970042684 E12 iE12-000 Misc. work requests Repair gouges on 90 degree elbow, Remove foreign material downstream of 1E12 F068A.

970042685 E12 1E12 000 Misc. work requests Remove foreign matenal downstream of 1E12 F0688.

970042685 E12 1E12 000 Misc. work requests Upgrade / replace reducer downstream of the 1E12 F0688.

900034215 E12 .1E12F072C C RHR pump discharge drain C RHR pump discharge drain stop stop leaks by.

970096956 E21 1E21.F003 LPCS pump discharge check 1 stud on check valve has improper valve thread engagement.

970123746 E01 1E21 N009 LPCS pump discharge pressure Black flex conduit has outer Jacket torn.

970091558 E22 -1E22 D3188 1B DG B/D starting air motors in- Not lubncating air start motors as line oiler required.

960115480 E22 1E22 F023 Suppression pool min flow Handwheel key missing.

bypass valvo 970063289 E22 1E22 F033 HPCS water leg pump min flow Inspect intemals of valve, possible line stop flow blockage.

970081a90 E22 1E22-J901 HPCS DG engine tach Pull new CA. for speed tach and transmitter / switch generator switch on 1B HPCS diesel.

inspect speed signal wiring 970104857 E22 1E22 J901 HPCS DG engine tach inspect and replace incorrect terminal transmitter / switch lugs with correct lugs.

970092305 E22 1E22-F342 Suppression poollevel LP excess Contingency to repair dunng L1F35 check valve DIV lit window.

L 48

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vy w -- quea-ww 4, 9 meagy w y ewg---'Nmigr----p-y4-my<a++rp+W-ameq- p-OS# r-ey-'w' f y7 'w

. T I

1

, ATTACHMENT B UNIT 1 l

WR No. System EPN Equipment Description I No. Name BOO 79372 E22 1E22-R$42 Recorder, HPCS DC MCC ground Positive alarm struck while performing

, det test.

970045241 E22 1E22 S001 Diesel dnven generator HPCS Replace oil dipstick and remark with proper oillevel marks.

970045056 E22 1E22 N511 HPCS DG lube oil high Missing condutt fitting on bottom of temperature pressure switch.

970104820 E22 IE22 S001 Misc. elect Relay not changing states.

i 970104674 E22 1E22 S001 Misc, elect Set time delay on K47 relay in panel 1E22 P3018.

! 970091854 E22 1E22 S001 Engine, HPCS DG 2 out 4 mounting screws on module front face are loose.

970122074 E22 1E22 S001 18 DG Kiene valve packing gland needs 4

replaced 4

970104848 E22 1E22B K014 Relay,1H13P625 HPCS manual Relay contact looks burnt or corroded, override.

4 970021142 E31 1E31 N010A MSL C high flow switch Conduit fitting is loose at junction box. l i

970012206 E31 1E31 N013BA RCIC steam supply high flow Vent test taps are not at the same detection. height.

970000849 FC 1FC000 Pipe downstream of 1FC155 RHR Remove fittings and install pipe cap.

! to FC high point vent 970081363 FC 1FE-FC038 Fuel pool emergency pump 1 A Venfy flow onfice size.

discharge I I

970081363 FC 1FE-FC038 Fuel pool emergency pump 1 A Repair flange faces per endit.

discharge j 970047118 FP 1FP000 Misc. work requests Grout through wall opening or install '

round strap supports.  ;

970047118 FP 1FP000 Misc. work requests Grout holes in Unit 1 battery room. i 970136822 G33 1G33 N025 RWCU sr. tem inlet flow low Test taps are not at equallevels. l 970074479 H13 1H13-P608 - Assy, cabinet, power range Missing vanous hardware for all neutron monitor APRMs, LPRMs. and RBMs.

970050820 H13 1H13-P612 Assy, panel, feed Term board BG term #2 broken,

, water / recirculation replace or repair as needed.

970038362 _

H13 1H13-P618 Assy, panel. Div 2 RHR relay - Lugs on terminal block are bent.

970063566 H22 1H22 P027 Assy, panel, B reactor Flex conduit connection at tray 1153C level / pressure local to panel broke.

970108344 H22 1H22 P030 Assy, panel, SRM/lRM preamp Remove grd lugs and clean under to enclosure A 1 insure good contact.

970108349 H22- 1H22-P031 Assy, panel, SRM/lRM preamp Remove grd lugs and clean under to 4 enclosure B 1 insure good contact.

970108350 H22 1ri22-P032 Assy, panel. SRM/lRM r'eamp Remove grd lugs and clean under to

, enclosure A 2 insure good contact.

970112400 IN 1tN000 Misc. work requests Multiple SRV accumulator drai:Vvents d

have CS caps 970112393 IN ilN005C SRV ads accumulator 1821 U-bolt missing on 1* line upstream of A003S vent valve valve.

970100943 IN ilN097C SRV accumulator 1821 A004C Stub found on end of pipe in place of drain valve plug-not per design.

970100940 IN 11N097H SRV accumulator 1821 A004H Stub found on end of pipe in place of 49

i ATTACHMENT B UNIT 1 WR No. System EPN Equipment Description

No. Name l drain valve pluglot per design.

970080668 PP 1PP000 Misc work requests Electrical penetration E 23 below minimum pressure.

970044963 PL 1PL30J Assy, panel, switchgear heat Annunciator alarm windows and horn removal Div 2 cycle on and off when testing 970107061 RF 1RFA3A Pipe The U 1 SBGT drain line 1RFA3A is 3 plugged 970073644 RH 1RH031541X Rigid seismic restraint Remove and replace strut to accommodate valve repairs.

970054608 VD 1TCU VD003 DG01K room damper Controller setting different from 1VD17Yl18Y setting specified 9700$2641 VD 1TCU VD008 DG01K room damper 09YA/YB, Venfy love controller for 1 A DG vent 10YA/YB has correct fuse _

970107164 VD 1TCU VD013 HPCS DG cooling water pump Controller to not maintaining room room temperature controller temperature at sJ point.

970115001 VD 1UAl VD021 DG toom vent annunciator Alarm windows 21 and 2 3 failed lamp check.

970019207 VG IVG002 SBGT train flow control valve Thread engagement poor, replace bolts on lower mounting block.

970014601 VG 1VG003 Valve, butterfly Actuator mount bolts improperly lockwired.

970052652 VY iTIC VYO24 RHR WS pump C/D temp cont Venfy that a 1/10 amp fuse is in the mod damper controller.

970099321 WR 1WR000 Containment chilled water piping Replace non-conforming aluminum insulation lagging lagging with SS lagging 970099334 ZZ 122000 Misc. work requests Rm 385 at vessel at 260 degrees on 700 missing 1 screw. i 970101561 ZZ . 1Z2000 Misc work requests Drywell 740 elevation,165 degrees, 2* diameter lie rod jam nut loose.

970101664 ZZ t 1ZZ000 Misc. work requests 340 degrees, drywell 777 elevation, i' tie rod tumbuckle loose.

970101571 ZZ 12Z000 Misc work requests 340 degrees, drywell 777 elevation,2" tie rod tumbucklo loose.

970101077 ZZ 1ZZ000 Misc work requests Screw missing from box on inside containment wall.

50

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,..,,,.,w w.w. ,.yp , ,,,p, ,. _ -w # _,,,.m,,m,_ _ _ , , , . . . ,_,,w__,.,, y.7_,,..,-,.g,y.ry,-_. .,, _ . _.,, - . _ . ___ _ . _

. ATTACHMENT B ,

UNIT 2 WR No. System EPN Equipment Description No. Name ,

970032520 AP 2AP01E 1 Spare Hear area of cubicle missing knockout plug.

970101- AP 2APO4E Instrument medium voltage Troubleshoot and repair per LAP.

switchgear 1300-1.

960120 k AP 2AP07E Switchgear,243 4160 VAC Evaluate whether bolts are needed on cubicle door near top.

970070098 AP 2AP08E Switchgear P.51 16900 VAC 2 thumbscrews on bottom of door 1 [

missing threaded retainers.

960102296 AP 2AP20E- Primary containment vent supply Repair racking mechanism and 202C fan 2A 2VP02CA position nbbon, swg 235Y/202C 970011790 AP 2AP65E D6 Spare Brkt handle operator mechanism has separa;ed from bkr. t 960116432 B21 2LR- Recorder, reactor pressure / level Recorder struck at 42' dunng LIS NU.

• B21R884A 202.

960111157 CM 2 AIR CM012 Post LOCA H2/02 volume Digital display needs to be replaced.

970087342 CM 2LR-CM027 Suppression pool water level wide Wide range suppression poollevel

+ narrow range indicator is slowly increas,ing 970045494 CM 2LT CM030 Suppression pool wide range Shows slow increase in level, Div 1 level transmitter indication does not respond.

970031993 CM 2PT CM032 Suppression pool pressure Adjustment cover is bent and missing transmitter a screw.

970031994 CM 2PT CM055 Suppression pool pressure Test tap fitting is very difficult to transmitter remove.

960116433 CM 2TE CM060 D/W air temp thermocouple Alarming, Div 2 emergency range temp downscale.

970031287 DC 2DC06E Div 1259 VDC MCC 221Y Fasteners aren't property secured.

970008054 DC 2DC07E Assy, batt,125 VDC Div 1 - Several cell posts need corrosion removed and greased.

970032515 DC 2DC08E Assy, panel,125 VDC distnbution Rear panel access covers missing bus 2A bolts. ~

970023714 DG 2DG01P Motor, DG a cooling water pp Ground wire strand broken.

960118093 DG 2DG037 2A DG cooler inlet high point vent Chicago fitting instal!ed, M 134 S 1 stop shows a pipe cap.

970012522 DG 2DG038 2A DG cooler outlet high point Remove quick couple and install pipe vent stop cap per drawing M 134.

970015513 DO 2LS D0004 DG day tank 2 Level switch cover missing hold down nut.

970085667 D18 2D18-R800 Recorder, VC air intake rad Take-up reel not working, steel spnng gone, 970012205 E12 2E12 B001A 2A RHR heat exchanger HX drain line has Chicago fitting / replacement with pipe cap.

970023713 E12 2E12 C300D Motor, RHR service water pump Ground wire not secure to seal tite, 51

~ - _ . - _ _ . _ . _ _ _ . - ~ , _ _ _ _ . - _ _ . _ _ . _ . . _ _ , , _ _ _ - - . _ .- ,_ ~..__ _ _ _ .. _ ,_ _ ,_ _

. \

, ATTACHMENT B UNIT 2 WR No. _ System EPN Equipment Description No. Name 970011339 E12 2E12 F3300 B RHR service water pump Stem and yoke / gland area dirty; clean suction stop and lutse stem 970012870 E22 2E22- Relay,2H22P028 Relay cover broken in upper left BK035C corner and missing bolt.

970043996 E22 2E22 BK350 Over current relay Relay cover is cracked in upper left corner.

970012521 E22 2E22 F321 28 DG cooler outlet press test Mis;ing cap on pipe, install pipe cap.

connection valve 970012520 E22 2E22 F353 28 DG cooler outlet h gh point Quick coupler on pipe, drawing M 134 vent stop shows a pipe cap.

970032017 E22 2E22 N004 HPCS pump discharge press Point now in LRL status, computer transmitter point A807.

970090248 E22 2E22 N507 HPCS DG air start receivers B improper thrend engagement on two pressure mounting screws.

970011755 E22 2E22D300 Strainer HPCS diesel cooling The handle used for manual backwash water will not fit on shaft.

960117606 E22 2 PIE 22R$10 HPCS DB air receiver B pressure Missing glass face cover.

970131593 E31 2E31 N008A MS line A high flow detection Missing glass face cover.

970131604 E31 2E31 N0088 MS line A high flow detection Missing glass face cover.

970131606 E31 2E31 N0098 MS line B high flow detection Missing glass face cover, 970131607 E31 2E31 N0108 MS line C high flow detection Missing glass face cover.

~970131610 E31 2E31 N0118 MS line D high flow detection Missing glass face cover.

( 970131611 E31 2E31 N022A RCIC steam line pressure Missing glass face cover.

970003836 H13 2H13-P642 Assy, panel, Div 2 leak detection 4 Cover plates are missing screws and are unsecured.

960050218 H13 2H13P603 Assy, panel, reactor control 2E22 TS4 protective cover missing -

hold down bolts.

970023699 H13 2H13 P628 Assy, panel, ADS chamber A Knockout plugs on south end of panel relay, are missing.

970026401 H13 2H13-P655 Assy, panel, MSIV leakage Missing 13/4" knockout plug.

control DIV 1 970018291 H22 2H22 P028 Assy, panel, HPCS DG protection Perform freeze seal to support LLRT, relay '

960100541 M5 2MS25AA pipe Perform freeze seal to support LLRT, 960100540 MS 2MS25AB pipe Perform freeze seal to support LLRT.

$2 i

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, ATTACHMENT B  !

UNIT 2 WR No, System EPN Equipment Description l No. Name 900100539 MS 2MS25AD pipe Perform freere seal to sus aort LLR' 970013490 PL 2PL30J Assy, panel, switchgear heat Replace annunciator hom, not loud removal Div 2 enough to be heard 970028600 PL 2PL31J Assy, panei, M/G set room vent Annunciators alarm windows covers ,

plastic hinges are broken.

970044958 PL 2PL33J Assy, panel, RHR B/C cube vent Gnnd top two mounting hitties to permit UT of bolt.

970022397 PM 2PM06J Assy, panel, HVAC console Missin0 plastic collars that hold annunciator horns in place.

970032997 VD 2TCU VD003 Temperature Venfy a 1/10 AMP fuse controller for 2A DG.

970032998 VD 21CU VD008 DG01K room damper 09YA/YB, Venfy 1110 AMP fuse controller for 2A 10YA/YB DG.

960113396 VD 2VD03YA Damper Damper actuator leaking oil. l 960100224 VE 2VE000 Misc. work requests Air leaks around the frame.

970016505 VG ""T.VG009 SBGT train out flow transmitter Screws on front of enclosure need to be replaced.

970032563 VG 2PDl VG030 SBGT train fan D/P andicator Fan inlet static tube track support clamps loose.

97009M30 VG 2VG02Y Damper flow changes erratically dunng VG run 9701200ba VG 2POR VG016 Recorder, SBGT train HEPA fdter Broken plastic pop nvet, replace.

D/P 970004076 VX 2TZ VX019 Actuator, valve Appears to be letting cold air in even

~

in the closed position.

970004743 Vi 2VYO6Y Damper Remove spot welded grating to allow damper to be wired shut. ,

970108745 B21 2B21 N026E Reactor water level Plug missing on transmitter conduit connection.

970108749 B21 2021 N4000 Reactor water level (APl/RPT) Plastic plug not acceptable for EQ, replace with stainless.

970108750 B21 2B21 N402C Reactor waterlevel(MSIV) Plastic plug used to sealconduit connection.

970087342 CM- 2LR CM027 Suppression poolwater level wide Wide range suppression poollevel plus narrow range - indication is slowly increasing.

9/0109245- CM 2TR-CM038B Drywell and suppression chamber Stop screw missing.

air temperature 970109704 C11 2C11 N012C CRD scram discharge level Pressure transmitter is loose and will spin.

970108747 C34 2C34 N004B Reactor level B tron pipe plug appears to have been used to seal transmitter.

970108623 DC 2DC01E Assy, battery, 250 VDC Found corrosion on the cells.

970108423 DC 20C0)E A sy, battery,125 VDC Div-1 Found corrosion on cells.

970106069 DG 2DG08TA 2A DG A starting pir receiver Union leaking needs repair.

970109221 VG 2FR-VG009 Recorder, SBGT train out flow Recorder can be pulled out of panel, stop broken.

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ATTACHMENT B UNIT 0 WR No. System EPN- Equipment Description No. Name 970068960 DG 0DG000 fasc. work requests Diesel trapped on failure to start lollowing maintenance.

960069048 DG ODG004 DG 'O' cooling water strainer Requires excesta a force to close, outlet stop 960016696 DG ODG01A *0" DG cooler 1DG01 A move tube bundle to install new gasket.

970022646 DG ODG01F Strainer, stand-by eng cookng Repair keyway of gear reducer diesel water cooling water strainer.

970347113 DG ODG01F *0* DG coohng rater strainer Packing gland cracked.

970047113 DG ODG01F Strainer, stand by eng coohng Water leaks about i drop /30 sec.

water around shaft for B.W motor.

970044119 DG ODG01K 'O' DG New DC pump / motor couphng requires inspection.

970069020 DG ODG01K Engine, DG Diesel failed to start, troubleshoot.

970068950 DG ODG01K *0* DG Dieselinpped on failure to start

, following maintenance.

970070419 DG ODG0iK Governor, DG Air hne has been crimped.

960075068 DG ODG01K Engine, DG Replace cyhnder #3 fuelinjector.

960076068 DG ODG01K "0* DG Replace cylinder #11 fuel injector on ODG01 K.

960075068 DG ODGG1K *O' DG Replace lash adjusters.

970102489 DG ODG01K 'O' DG Install test equipment to monitor diesel engine start.

970122068 DG ODGOW *0"00 Replace klone valve packing gland.

970044119 DG ODG01K B Pump, DC turbo soakback Lost discharge pressure while pump was running 970090299 DG ODG01K-N Heat exchanger DG coohng Repair floahng end and channel end of water the heat exchanger.

960016696 DG ODG01K.N Heat exchanger, DG cookng Excavate the spool piece for repair water program.

960016696 DG ODG01K N Heat exchanger, DG coohng Reassemble the heat exchang?r at water completion of the repairs.

960016690 DG ODG01K N Heat exchanger DG coohng Service water leak at the inlet / outlet water end cover platet 960016696 DG ODG01K N - Heat exchanger, DG coohng Remove polymer from the flange faces water - of the heat exchanger.

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$4  :

ATTACHMENT B UNIT 0 WR No. System EPN Equipment Description No. Name 900010696 DG ODG01K N Heat exchanger, DG cooling Repair of end covers on tha ODG01 A.

water 900016696 00 ODG01K N Heat exchanger, DG cooling Replace grease plug in coupling cover water during next tube.

950094799 DG ODG01P Coupling, DG cooling water pump Rebuild pump, repair lower casing stud hole.

970047145 DG ODG01P Pump. DG engine cooling water Repair casing to allow nut to sit flat against pump.

970047145 DG ODG01P *0' DG A generator control panel Common suction valve for the l soakback and clic oil pumps.

970094329 DG ODG047 'O' DG lube oil soakback and circ inspect s[ eed signal winng.

pumps suction valve 970081493 DG OSTS-DG076 DG speed (M13) Investigate winng problems with speed tach.

970081493 DG OSTS-DG076 DG speed (M13) Perform speed loop cat. again. Use older, lighter accuracy's.

970098011 DG OSTS DG076 DG speed (M13) Neatly tie down slack cables on DG.

970039554 DG OTI-DG054 DG main lube oil temperatuto Neatly tie down stack sensor cable on DG.

970039553 DG OTI DG058 DG fuel oli temperature Neatly tie down slack sensor cable on DG.

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970039555 DG OTI DG062 DG engine jacket water temp Nectly tie down slack sensor cable on DG.

970039557 DG OTS DG041 DG hot engine temp S/D Neatly tio down slack sensor cable on DG.

970039658 DG OTSH-DG048 DG lube oil Neatly tie down stack sensor cable on DG.

970011309 DO Ot.S-D0004 DG day tank Pertoim visualinspection of switch wirina.

970070669 018 OD18-N524 SBGT vent winng monitor flow Replace flow element / transmitter, element unable to calibrate.

970017117 D18 OD18-R$19 Recorder, S3GT wide range Mid-range pen occuionally sticks noble gas monitor after source check.

970033534 PA OPA10J Assy, panel, auxiliary equip room Some annunciator window riastic A/C system B hinges are broken.

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ATTACHMENT B UNIT 0 WR No. System EPN Equipment Description No. Name 970057402 PL OPLD2J Assy, panel, SBGT wide range Flow did not drop to zero.

gas monitor 970000295 PL OPL18J Assy, panel, CR HVAC syst B OPL16J, alarm window S 15 and 21 came in and are incorrect.

970012254 VA OTT.VA003 A temperature transmitter . Nut missing on the bottom support for OTT VA003. ~

970001457 VC OPDS-VC011 D/P switch Recalibrate switch.

960098545 VC OTIC-VC003 CR MVAC mix damper 19YA The controller for OVC19YA is failing upscale.

960086644 VC OVC000 Misc. work requests One screw missing, one loose, both on top row of box.

9700'54812 VC OVC01CA Assy fan, CR HVAC supply 0A A VC train did not start correctly.

970099354 VC OVC01CA Assy, fan CR HVAC supply OA OVC01CA, OVCO2CA, & OVC05CA tripped without any alarms, 960119639 VC OVC01CB Assy fan, CR HVAC supply 0B Fan inpped on thermals after about 20 min running.

960119522 VC OVC01FA Filier unit CR HVAC supply air Replace inlet filters.

950106285 VC OVC05CA OA CR HVAC refer Copper tubing is worn and needs to be replaced.

940049823 VC OVC05CA- OVC05CA comp suct valve Suction and discharge valves did not SUCT isolate all the way.

960090704 VC OVC66Y Damper, CR HVAC One thumb catch on access door broken.

970110145 VC 0FR-VCO28 Recorder, filter train OVC15A air fteplace broken plastic pop rivet.

flow 970133535 VC 0FR-VC028 Recorder, filter train OVC15A air Pen sticks.

flow 970')32927 VD OTCU-VD003 DG01K room damper Venfy that a 1/10 amp fuse isin the VD01YA/YB, VD02YA/YB controller.

970065084 VD OTZ VD003C DG room ODG01K vent damper OTZ-VD003C may have hydraulic leak, DVD03YA and MYB difficult to see.

970092704 VD OVD03YA Damper DG vem room vent Broken tack weld on the security

. e ier to OVD03YA.

960106729 VE OTS-VE101 Compressor, OVE04CA high oil , emperature controller gauge out of -

temperature calibration.

~6

ATTACHMENT B

, UNIT 0 WR No. System EPN Equipment Description No. Name 970098868 VE OXY-VE086B - Aux equip room A/C system A RA Power indication hght is out.

ionization monitor 960098533 WS OWS015A A service water lake to water Pipe and bolting corroded, some tunnelinlet stop bolting questionable.

960098534 WS OWS0158 B service water lake to water Pipe and botting corroded, some tunnelinlet stop bolting questionable.

960098538 WS OWS015C C service water lake to water Pipe and bolting corroded, some tunnel inlet stop ,

bolting questionable.

960098540 WS OWS015D D service water take to water Pipe and bolting corroded, some tunnelinlet stop bolting questionable.

I 960098542 WS OWS015E E service water take to water Pipe and bolting corroded, some tunnelinlet stop bolting questionable.

960098544 WS OWS015F F service water take to water Pipe and bolting corroded, some tunnel talet stop bolting questionable.

960118448 XX OXXDR003 Door,003, watertight, aux to DG Middle lug on hinged side is broken, pump room 970000681 XX OXXDR015 Door. 015, watertight Door latch interlock is brc' ten off.

4 970021503 XX OXXDR010 Door,016, watertight The interlock mechanism to door #16

can bind and lock door.

970108143 DG ODG01F Reducer, speed coohng water Remove handwheel and attach to strainer strainer lifting eye bolt.

970106121 DG ODG01K 0DG Between diesol and generator, bent

! conduit, broken conduit clamp 970119536 DG ODG01K 0DG Cylinder 15 test valve unattached to diesel cylinder.

970115616 DG ODG01K-A 0 Gli Increcsing vibrations.

, 970121539 D18 OD18-N511 SBGT effluent low range gas rad Repair / replace stripped screw on the t

detector low range detector.

970091135 D18 OD18-R510 SBGT wide range RM-23 module SBGT WRGM mid range indicating abnormally high.

970115620 FP OFP000 Misc. work requests Rep! ace cracked hose reels.

970084413 IS OlSDR020 Door an?n. Rx Bldg trackway Missile door pin will not open.

970111773 PL OPLD1J Assy, oanel, SBGT vent sample Install separator between particulate

conditioner. and lodine.

970058289 VC- OVC05CB Refng compressor OB Inboard motor bearing dust shield has moved on shaft.

970112749 VD OVD01F Fitter SB DG room vent supply 0 DG supply filter is dirty and needs to be changed.

970000679 XX- OXXDR013 Door. 013, DG pump room B Door latch interlock is broken off.

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1 Attachment C Page 1 of 3 e

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4 Radiation Exposure i.

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e. < .

• REOULATORT GUIDE 1.16 REPORT NLMBER OF PERSONNEL AND PERSON REM SY WORK AND JOB FUNCTION FOR 1997

......... NUMBER OF PERSONNEL ***.... .....

QUANTITY OF PERSON REM **.*

{ STAfl0N CONTRACTORS / UTILITY TOTAL l

WORK AND JOS FUNCTION STATION CONTRACTORS / UTILITY T3TAL EMPLOYEES OTHERS EMPLOYEES PERSONS EMPLOYEES OTHERS EMPLOYEES PERS TEN REACTOR OPERATIONS AND SURVEILLANCE ENGINEERING 48 67 0 1.695 NEALTN PHYSICS 0.779 0.000 4 0 17 1.092 0.001 0.132 MAINTENANCE 10 16 0 3.057 OPERATIONS 1.871 0.016 128 12 0 17.512 0.711 0.000 SUPERVISORY 61 42 0 1.964 0.763 0 250 000 ................

136 17 403 25.340 4.124 0.148 29.613 ROUTINE MAINTENANCE ENGINEERING 153 176 0 5.401 KALTN PHYSICS 2.046 0.000 74 32 326 20.717 3.311 2.600 MAINTENANCE 186 1203 58 59.678 OPERATIONS 144.217 8.412 44 1 0 SUPERVISORY 5.%9 0.030 0.000 235 282 0 7.685 5.1 73 0 691 1693 000 ................

384 2769 99.450 INSERVICE INSPECTION 154.778 11.012 265.240 ENGINEERING 0 0 0 0.013 CALTH PHYSICS 0.000 0.000 0 0 0 0.089 0.000 0.004 MAINTENANCE 3 10 0 0.963 CPERATIONS 1.224 0.000 0 0 0 0.003 0.000 0.000 SUPERVISORY 2 0 0 0.052 0.000 0 5

000 ................

10 0 16 1.119 1.224 0.004 2.347 SPECIAL MAlhTENANCF.

ENGINEERING 3 30 0 0.093 NEALTN PHYSICS 0.354 0.000 0 5 2 0.009 0.570 0.013 MAINTENANCE O 43 1 0.070 5.161 0.133 OPERATIONS 0 0 0 SUPERVISORY 0.048 0.000 0.000 0 4 0 0.001 0.065 0 3 82 000 ................

3 88 0.220 REFUELING 6.150 0.146 6.516 ENGINEERING 0 6 0 0.003 CALTM PHYSICS 0.068 0.000 1 0 0 0.225 0.000 0.000 MAINTENANCE 0 9 0 OPERATIONS 0.050 1.073 0.000 0 0 0 0.052 0.000 0.000 SUPERVISORY 0 1 0 0.014 0.012 ' '30 2 15 0 17 0.345 1.153 WASTE PROCES$!NG 0.000 1.498 ENGINEERING 1 0 0 0.025 NEALTN PHYSICS 0.001 0.000 1 0 0 MAINTENANCE 3.228 0.000 0.002 O 18 0 CPERAfl0NS 0.041 2.124 0.000 4 134 0 SUPERVISORY 0.507 7.809 0.000 6 0 0 0.193 0.005 0 11 000 ................

152 0 164 0.995 9.939 0.002 10.936

o e REGULATORY QUIDE 1.16 REPORT NUMBER OF PERSONNEL AND PEtt0N REM SY WORK AND JOB FUNCTION.FOR 1997

. . . . . . . . . NWBE R OF PER $0NNEL . * . . . . . ..... auANTITY OF PERSON REM * ..

STAfl0N CONTRACTORS / UTILITY TOTAL STATION CONTRACTORS / UTILITY TOTAL WORK AND JOS FUNCTION EMPLOYEES OTHER$ EMPl0YEES PERSONS EMPLOYEES OTHERS EMPLOYEES PERSON REM TOTAL BY J00 FUNCTION ENGINEERING -205 279 0 484 7.229 3.248 0.000 10.477 NEALTN PNYllCS 80 37 345 462 22.361 3.882 2.751 28.994 MAINTENANCE 199 1299 59 1557 63.859 155.670 8.561 228.090 GPERATING 176 147 0 323 24.091 8.550 0.000 32.641 suPEnvis0RT 303 328 0 631 9.929 6.018 0.000 15.947

• • • GRAND TOTAL *** 963 2090 404 3457 127.469 177.368 11.312 316.149 o

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+ _ _ _ w g-r .-grpgs.c 3-eq y g-y, w*-.r - nm..

Number of Personn:1 Execeding 100 MREM ct LaSalle County Station During 1997 Shift Manager, Staff Supenisor, License Training, 3 Staff, Unit Supervisor, Field Supervisor, Fin Manager Radwaste Manager, Radwaste Staff 4 Nuclear Station Operators 3 Equipment Operators Equipment Attendants 4l Auxiliary Operators and Operators in Training 8 Equipment Operators IIVS I Fuct flandler Supervision i Fuel llandlers 6 Mechanical Maintenance Supervision b Mechanical Maintenance Senior "A" 12 Mechanical Maintenance "A" 56 Mechanical Maintenance "B" 12 Electrical Maintenance Supervision I Electrical Maintenance "A" 40 Electrical Maintenance "B" 13 Instrument Maintenance Supervision 2 Instrument Maintenance " CST's" 18 Instrument Maintenance "A" 21 Instrument Maintenance "B" 5 Quality Control 7 Site Construction i Ilealth Physics, EA's Operational 4 Radiation Protection Supervision, Scheduler, Planner 1 Radiation Protection Technicians "A" 37 Radiation Protection Technicians "B" i Chemistry Technicians "A" 7 Systems Engineering NSSS Group 3 Systems Engineering BOP Group i Systems Engineering Radwaste Group 2 Systems Engineering Electrical Group i Systems Engineering Performance Monitoring 2 Systems Engineering Common Group i Systems Engineering Fire Protection i MIS CECO I i 7-Feb-98 I of2

Design Engineering (Physical Design) 1 Support Engineering (Valve & Pump) 3 Support Engineering (Support Programs) 4 4

Work Control Supervision, Work Analyst. StafT, 2 Planner, Scheduler, Work Week Manager Off Site CECO 7 s

Substation Construction 20 Numanco Senior llP Technician 12 Sargent and Lundy 8 Richardson and Estes 11 Raytheon Office 10 Supervision / Clerical' Engineers' Technicians Raytheon Pipe Fitters 113 i Raytheon Carpenters 35 Raytheon iloilermakers 19 Raytheon Ironworkers 12 Eytheon Electricians 1 Raytheon Millwrights 8 Raytheon QC Inspectors 1 Raytheon Sheet Metal Workers 15 Raytheon Laborers 74 Raytheon insulators 25 Miscellaneous Contractors 3 The Atlantic Group i Pow er Cutting Inc. 4 Transco 2 Underwater Engineering Services Inc. (Divers) 5 Chemical Nuclear Services 10

.i ilMS 5 ConAm Inspection 3 GD Staff 2 Sea Inc. I Sun Technical 5 J.L. Manta 13 Anchor Darling 6 Molten Metal Technologies i Duke Engineering Services 1 NuKem Nuclear Technologies 4 17-Feb-93 2 of2

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ATTACHMENT D

, PAGE 1 OF 15 4

)

SURVEY OF CHLORINE SHIPMENTS IN THE a

VICINITY OF LASALLE COUNTY STATION 1

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I Table of Contents '

Page i 1.0 Exec u tive S u m m a ry . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 2.0 I n t rod u c tio n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 3.0 Regulatory G uides . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 4.0 Enriier Surveys of Chlorine Shipments . . . . . . . . . . . . . . . . . . . . . . . . 5 5.0 1997 Survey of Chlorine Shipments . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 6.0 Co n clu sio ns . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 7.0 Disc u s sio n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 8.0 Refe re n c es . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 9.0 A t tac h m e n t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 Table 1 - Government Agencies, Public Officials and Trade Organizations Contacted . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 Table 2 - Barge Terminals Located on the Illinois River Between The Dresden Island Dam and the Marseilles Dam . . . . . . . . . . . 9 Table 3 - Chemical Ccmpanies, Water Treatment Plants, and Other Potential Chlorine Users in Towns on the Illinois River Between the Dresden Island Dam and t h e Ma rs eilles Da m . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 Table 4 - Potential Chlorine River Shipments Handled . . . . . . . . . . . . . .

12 Appendix A - Telephone Memorandums . . . . . . . . . . . . . . . . . . . . . . . . .

Appendix B - Confirmation Letters . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

Appendix C - Tier I and H Reports . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

Appendix D - 1996 Barge Trame Past Mile Point 252. . . . . . . . . . . . . . . .

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l Page 2 of 15

1.0 EXECUTIVE

SUMMARY

1.1 A survey of potential sources ofliquid chlorine that are stored or transported on-site or within a 5-mile radius of the La Salle Station to update the surveys of 1975, 1986,1988,1991, and 1994 was performed. This survey is to ensure compliance -

with 10CFR50, Appendix A," General Design Criteria for Nuclear Power Plants,"

Criterion 19," Control Room" and Regulatory Guide 1.78," Assumptions for Evaluating the Habitability of a Nuclear Power Plant Control Room During a Postulated Hazardous Chemical Release."

1.2 As pan of this survey, an initial screening of E site sources was performed based on information collected from the offices of the Emergency Services and Disaster Agency (ESDA) of Grundy and La Salle Counties. Facilities were identified that were within and without the 5-mile radius of La Salle Station. As a result of this screening, chemical inventories for 10 facilities in Grundy Cotmty and 12 facilities in La Salle County were obtained from the Tier Two Reports (Emergency and Hazardous ChemicalInventory).

1.3 The survey data collected as part of the Control Room Habitability Study is documented in this engineering evaluation.

1.4 Suppliers and transporters of chlorine referenced in previous surveys were contacted, and other controlling authorities were contacted, and no new sources of chlorine or transporters were identified within the five mile radius of the phnt.

1.5 The results of this survey indicates that chlorine is not a hazard at LaSalle, and chlorine detectors are still not needed at the site.

Page 3 of 15

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2.0 : INTRODUCTION 2.1 Licensing of the La Salle County Station required a survey ofindustries and transportation routes in the site vicinity that may use, store, and/or transport hazard >us chemicals. The information collected was then used to evaluate the -

- control room habitability at the La Salle County Station. This survey, which was conducted in 1975, revealed that anhydrous ammonia and probably chlorine were transported by barge on the Illinois River. The information gathered was not -

complete enough to conclude that chlorine was not shipped in large quantities by barge on the Illinois River.

'2.2 A new survey was conducted in January-February 1986 to supplement the information obtained from the 1975 survey. The purpose of the new survey was to determine whether chlorine is a hazard to the control room habitability. Based on the information collected by this survey, it was concluded that no special protection provisions were required for chlorine at the La Salle County Station. In the safety evaluation supporting Amendment No. 38 to Facility Operating License-No. NPF-11 and Amendment No. 20 to Facility Operating License No. NPF-18, the staff of the U.S. Nuclear Regulatory Commission (NRC) agreed with this conclusion but recommended that the survey ofIllinois River shipment be updated every three years. Commonwealth Edison Company committed to doing this in a letter to the NRC dated March 5,1986. Such surveys were conducted in 1988,-

1991, and 1994 which supported the conclusion that chlorine is not shipped on the Illinois River in sufficient qua.ntities to present a hazard to La Salle Control Room.

In accordance with this commitment, a new survey was conducted in July-August 1997, c' 2.3 The following sections describe the regulatory guides that form the basis of the control room habitability evaluation, the results of the earlier surveys, the methods and results of the 1997 survey, and the conclusion regarding chlorine as a hazard.

The results of the 1997 survey and the 1988,1991, and 1994 surveys fully support the 1986 conclusion that no special protection measures are required for chlorine

- at the La Salle County Station.

3.0 REGULATORY GUIDES 3.1 Regulatory Guide 1.78, " Assumption for Evaluating the Habitability of a Nuclear Power Plant Control Room during a Postulated hazardous Chemical Release" .

' identi6es chlorine as a hazardous chemical and requires a control room habitability analysis in case there is an accidental chlorine release from stationary or mobile sources near the plant. Regulatory Guide 1.95, " Protection ofNuclear Power Plant control Room Operators Against an Accidental Chlorine Release" specifically addresses onsite accidental chlorine release. However, it can also be Page 4 of 15

used in analyzing effects of an offsite chlorine release.

3.2 Regulatory Position 1 of Regulatory Guide 1.78 states that chlorine stored or situated at greater distances than five miles from the control room need not be considered in evaluating habitability of the nuclear power plant control room -

during a postulated chlorine release. Regulatory guide 1,78 also specifies frequency, distance, and quantity of chemicals transported or stored with respect to the control room that require a control room hab.it ability analysis. The Regulatory Guide also specifies three modes of transportation that must be considered for chlorine manufactured, stored or used by the industries in the vicinity of the control room: ralhoads, highways, and waterways.

4.0 EARLIER SURVEYS OF CHLORINE SHIPMENT 4.1 The La Salle County Final Safety Analysis Report (FSAR) Section 2.1.1 describes the location of the plant site and the transpostation routes near the site. FSAR Section 2.2.2 describes the nearby industrial, transportation, and military facilities.

All industrial facilities are located outside of a five-mile radius of the plant; therefore, chlorine used or stored at these facilities need not be considered in evaluating control room habitability. A survey of these industries was conducted in 1975 to determine the shipment of chlorine by three modes of transportation, U.

S. Highway 6 and State Highway 47, the nearest highways to the station used by j these industries and the Chicago Rock Island and Pacific, the nearest railroad, cre alllocated farther than five miles from the station. Therefore, transportation of chlorine by these two modes of transportation need not be considered in the control room habitability analysis.

4.2 FSAR Section 2.2.2.4 describes the river traffic i ae Illinois River passing the site. Section 2.2.3.1.c concluded tha. Se only transportation route potentially carrying chlorine within five miles of the station was the Illinois River, which is located approximately 4.7 miles north of the station. However, the available data on commodities transported on the Illinois River (FS AR Table 2.204) did not differentiate barge shipments ofchlorine from other chemicals. In addition, the survey found that although small quantities of chlorine were being used by the Illinois Nitrogen Corporation, located at river mile 248.7 approxin r.ely five miles north of the station, sufficient information was not available to determine that it was not receiving its chlorine supply by barges. Therefore, in order to expedite the licensing process, chlorine detectors were provided in the control room HVAC system intake air ducts.

4.3 To supplement the 1975 survey and to obtain additional specific information on chlorine shipment, a survey was conducted during January-February 1986 to determine whether chlorine was, in fact, transported in barges on the Illinois River.

Page 5 of 15

l For this survey, infonnation was collected from the U.S. Army Corps of Engineers, the U. S. Coast Guard, the lockmasters for the closest upstream and downstream dams. None of these sources had any information to suggest that chlorine is transponed on the Illinois River Because none of the barge operators, barge terminals, or chemical companies reported chlorine shipments on the Illinois .

River and neither of the lockmasters were aware of any chlodne passing through their locks, it was concluded that chlorine was not shipped on the river in significant quantities.

5.0 1997 SURVFN OF CHLORINE SHIPMENTS 5.1 The closest regularly traveled railroad to La Salle Station was formerly known as Atchison, Topeka and Santa Fe Railroad. It has recently been purchased by the Burlington Railroad and is now called Burlington Nonhern Santa Fe Railroad.

j_ This railroad is outside the 5-mile radius of La Salle Station. No chlorine tank cars are reponed to be shipped on this railroad line.

5.2 A ponion of the Illinois River is within the 5-mile radius of La Salle Station. This river is regularly used for commercial barge transportation of many commodities.

To update the survey of possible chlorine shipments on the Illinois River, contacts

initially were made using the same sources ofinformation used in 1986. In

addition, active chlorine barge operators were contacted for their potential shipments on the Illinois River, barge terminals, and chemical companies in the vicinity of the La Salle County Station, and all of the companies on the attached list were contacted. Specifically, information was obtained from the following contacts revealed that chlodne does not need to be considered a hazard as per Regulatory Guide 1.78:

5.2.1 Ten Fovernment agencies, public officials, and trade organizations, as shown in Table 1:

, 5.2.2 Four companies that had operated and presently operate chlorine barges in -

North America, References 8.7,8.8,8.9, and 8.35.

4 1

~

5.2.3 .Founeen barge terminals located on the Illinois River between the Dresden 4

Island Dam and the Marseilles Dam, the upstream and downstream dams

^

closest to the La Salle County Station, as shown in Table 2

and 1

5.2.4 Nineteen chemical companies, water treatment plants, or other potential chlorir.e users located in towns on the Illinois River between the closest upstream and downstream dams, as shown in Table 3.

5.2.5 According to HAZMAT Coordinator at the LaSalle Station, there is no i'

Page 6 of 15 J.

r  :,

chlorine ps used at the LaSalle Station. Sodium hypochlorite is used at

the lake inlet; Calculation S&L 90-0095, Rev 0, 7/10/95, concluded that accidental handling of sodium hypochlorite will not result in chlorine being ,

4 a hazard as per Reg Guide 178.

l 5.3 The results of these contacts can be summarized as follows:

I 5.3.1 The CNorine Institute is not aware of any chlorine being transported on the

, Illinois River, or of any chlorine producer or distributor located on the i river:

t

?

5.3.2 The lockmasters for the closest upstream and downstream dams are not aware of any chlorine passing through their locks

5.3.3 The government agencies contacted do not have any information on chlorine shipments on the Illinois River: "

5.3.4 None of the companies that currently operate chlorine barges in North j America transport chlorine on the Illinois River (References 8.7, 8.8, 8.9,

• 8.35):

5.3.5 None of the barge terminals located between the closest upstream and 4

a downstream dams handle chlorinei and j 5.3.6 None of the chemical companies, water treatment plants, or other potential

! chlorine users send or receive chlorine shipments on the Illinois River.

5.3.7 The Corps of Engineers verified that no chlorine shipments in 19% went

^ past mile point 252 on the Illinois River Mile Point 252 is located within -

the 5-mile radius of La Salle Station.

5.3.8 The US Coast Guard verified there are no authorized marine transfer facilities for chlorine in Chicago Captain of the Port Chicago Zone. This include from Lincoln, IL (about 170 milage marker) to Wisconsin border to '

Iowa border to Michigan, IN.

5.4 Overall, no indication was received that any chlorine is transported on the Illinois River, and several sources volunteered the opinion that chlorine is not transported

. on the river.

6,0 CONCLUSION OF FINDINGS 6.1 In accordance with the NRC staff recommendation made in 1986, a new survey .

was conducted of potential chlorine shipment on the Illinois River. The results of .

Page 7 of 15

the 1997 survey conclude that chlorine is not transported in significant quantities on the Illinois River and within a five mile radius of La Salle Station. No new sources of chlorine were identified, and no increased transportation shipments were noted. Therefore, the 1997 survey concludes that chlorine detectors are not required for the La Salle County Station. .

7.0 DISCUSSION 7.1 minais River 7.1.1 Mr. Jack Carr, US Army Corps ofEngineers, Rock Island Planning Division, (309) 794-5396, was contacted. He provided a list of all the different chemicals being moved on the Illinois River past Mile Point 252 i

for 1996. No chlorine was being shipped on the Illinois River. A copy of this list is in Appendix D.

Table 1 Government Agencies, Public Officials and Trade Organizations Contacted Information That Chlorine Is Transported on the Orennintion Illinois River

1. Chlorine Institute, Washington, D.C. None

2. Illinois Depanment of Transportation,

Chicago, Illinois None

3. Lockmaster, Dresden Island, Illinois, Lock and Dam None

4. Lockmaster, Marseilles, Illinois, Lock and Dam None

5. U. S. Army Corps of Engineers, Rock Island, Illinois None

6. U. S. Army Corps of Engineers, Planning Division, Rock Island, Illinois None

7. Illinois Department of Transportation, Division of Traffic Safety, Springfield, IL None

8. US Coast Guard, Washington, DC None

9. US Coast Guard, Marine Safety, East Peoria, IL None

10. US Coast Guard, Marine Safety Burr Ridge, IL None Page 8 of 15

Table 2 Barge Terminals Located on the Illinois River Between The Dresden Island Dam and the Marseilles Dam Mile Chlorine Comnany Point Shipments Handled

1. IMC Agribusiness, Marseilles,IL 248.7 None (formerly Kaiser-Estech, Inc. and formerly lilinois Nitrogen Corp.)

2. PCS Phosphates, Marseilles, IL 249.9 None (formerly Texasgulf Chemical Co.)

3, Commonwealth Edison, Seneca, IL 251.8 None

4. Continental Grain Co., Seneca, IL 252.6 None

5. Black Marine, Inc., Seneca, IL 253.0 None

6. Shipyard Terminal and Industrial Park, Seneca, IL (fonnerly Conti Carriers) 253.6 None

7. CF Industries, Seneca, IL 253.8 None (formerly Seneca Port Operating Co.)

8. Material Service Corp., Morris, IL 262.0 None 9 ADM/Growmark, Morris, IL 262.9 None

10. ADM/Growmark, Morris, IL 263.0 None

11. Cargill, Inc., Morris, IL 263.1 None

12. Continental Grain Co., Morris, IL 263.2 None

13. Commonwealth Edison, Co., Morris, IL 265.8 None

14. Millennium Petrochemicals, Inc, Morris, IL (formerly Quantum Chemical Corp.,

USI Division), 269.9 - None Page 9 of 15

.. J

e Table 3 Chemical Conepanies, Water Treatnient Plants, and Other Potential Chlorine Users in Towns on the Hlinois River Between the Dresden Island Pane and the Marseilles Dasa Ceespany Ceesty Address Pinese Distence to La SeNe SInseW TMs Facilley Be (senes) ConsWered le flee im SeIIe Centrol Reese HeWeeWitty Aeolysis (Yes/No)

Akzo Nobel Chemical (formerly Grundy N Tabler Road (815) 942 4 200 > 5 miles No Akzo Chemie America) Morris Black Marine Inc La Salle E duPont Road (815) 357-6666 <5 miles Yes Seneca Biewer Company ofIllinois la Salle 524 East Union Street (815) 357 4 792 <5 miles Yes Seneca Burlington Northern Sante Fe La Salle 262 W Madison (RIS) 434-0690 ' >5 miles No Ottawa Continental Grain Company La Salle S Main Street (815)357-874i <5 miles Yes Seneca Continental Grain Company Grundy Calhoun & Griggs Street (SIS) 942-0932 >5 miles No Morris DresdenIsland Locks Grundy P. O. Box 2004 (309) 794 4 200 >5 miles No Rock Island IMC Agribusiness (formerly La Salie 210:1 E Droadway (815) 7954 15I >5 miles No Kaiser-Estech,Inc) Marseilles JefTerson Smurfit Corp Grundy 1000 East Armstrong Street (815) 942-1520 >5 miles No Morris Marseilles locks and Dam La Salle Rock Island District (815) 795-2593 >5 miles No Marseilles .

Material Service Corp. Grundy 3450 W Southmor Road (815) 942-1830 >5 miles No Morris Page 10 of I5 9

. Conspeny Ceesty ' Address Phase D6stence se La selle ShouM TMs Factuey Be (aslies)' CaesMered in eine im same f Cameos me== n maamme>y

~

A sy*(ve nse Millenenen PW, Inc Gnsndy 8:105 N. Tabier Road (815) 942-7627 >5 smiles No (fannerty Quantum Chenucal) Morns Morris Sewage Treatment Plant Grundy N River Raed (SIS)942443 >5 miles No Morris PCS .7-- , " - -(formerly Texas b Selle P. O Box 88 (815) 795-5111 >5 miles No GulfChenucal Co) Marseilles Reichhold Chenucals,Inc Grundy 6350 East Collins Road (815) 942-4600 >5 nailes No Morris "Shepyard Tennmal and Industnel La Salle P. O. Box 380 (815)357-6721- <5 miles Yes Park Seneca Weseeweser Treatment Facility 14 Salle #2 Spicer Lane (815)795-2150 >5 uniles No Marseilles Water / Wastewater Trenenrot la Selle W Williones (815) 357-8406 <5 nailes Yes-Facility Seneca Water Tr*=e-w Facildy : La Selle 209 I h Street (815) 795-4000 >5 iniles No Marseilles

. Page 11 of 15

Table 4 Potential Chlorine River Shipments Handled Chlorine River Comnany Products Shipments Handled .

1. Water and Wastewater Treatment Drinking water Facility, Marseilles, IL sewage treatment None 2 PCS Phosphates (formerly Texasgulf Chemical Co.) . Industrial chemicals None (formerly Maker Industries Corp.),

Marseilles, IL Industrial chemicals None

3. Biewer Co. ofIllinois, Lumber processing Seneca,IL And treatment None

4. Water and Wastewater Drinking water and Trt. ment Facility, sewage treatment Seneca,IL None

5. Arzo Chemie America, Industrial chemicals Morris, IL -

None

6. EIT Company, Morris, IL Industrial chemicals (Formerly duPont) None

7. Jefferson Smurfit Corp. Folding cartons Morris, IL None

8. Quantum Chemical Corp. Industrial chemicals USI Division, Morris, IL (Formerly Norchem, Inc.) None

9. Reichhold Chemicals, Inc. Synthetic resins Morris, IL None

10. Sponge-Cushion, Inc., Sponge rug cushions Morris, IL None

11. Water and wastewater Drinking water and Treatment Facility, sewage treatment Morris, IL None Page 12 of 15

8,0 REFERENCES 8.1. Chlorine Inmtute, Washington, D.C., Mr. Gisy Troj:1, Personal Communication with Sargent & Lundy, July 14,1997.

8.2 Illinois Department of Transportation, Chicago, IL, Mr. Bob Baldone, Personal Communication with Sargent & Lundy, July 1,1997.

8.3. Lockmaster, Dresden Island, IL, Lock and Dam, Mr. Roy Chapman, Personal Communication with Sargent & Lt.ndy, June 30,1997.

8.4. Marseilles, IL, Lock and Dam, Mr. Bumey Smith, Personal Communication with Sargent & Lundy, July 15,1997.

8.5. U. S. Army Corps of Engineers, Rock Island, IL, Mr. Jack Carr, Personal Communication with Sargent & Lundy, July I and 7, 1997.

8.6, Chlorine Institute, Washington, D.C., Mr. Michael E. Lyden, Fax Communication, July 14,1997.

8.7. Occidental Chemical Corp., Dallas, TX, Mr. Larry Shield, Personal Communication with Sargent & Lundy, August 22,1997.

8.8. Elf Atochem., Philadelphia, PA, Mr. Tony Catoia, Personal Communication with Sargent & Lundy, August 21,1997.

8.9. PPG Industries, Pittsburgh, PA, Mr. Glenn Zeak, Personal Communication with Sargent & Lundy, July 14,1997, 8.10. IMC Agribusiness, (formerly Kaiser-Estech, Inc.), Marseilles, IL, Mr. John Moyer, Personal Communication with Sargent & Lundy, June 30,1997.

8.11. PCS Phosphate (formerly Texasgulf Chemical Co.), Marseilles, IL, Mr. Don Jackson, Personal Communication with Sargent & Lundy, June 30,1997.

8.12. Continental Grain Co., Seneca, IL, Mr. Lynn Howard, Personal Communication with Sargent & Lundy, July 16,1997.

8.13. Black Marine, Inc., Seneca, IL, Ms. Diane Tucker, Personal Communication with Sargent & Lundy, July 10,1997.

8.19. Shipyard Terminal and Industrial Park, Seneca, IL, Mr. George Lamb, Personal Communication with Sargent & Lundy, June 30,1997.

Page 13 of 15

8.20, . CF Industries (formerly Seneca Port Operating Co.), Seneca, IL, Mr. Joe Lamb, Personal Communication with Sargent & Lundy, August 21,1997.

8.21. ADM/Growmark, Morris, IL, Mr. David Muffler, Personal Communication with Sargent & Lundy, July 10,1997.

8.22. Cargill, Inc., Morris, IL, Mr. Tim Hutchcraft, Personal Communication with

, Sargent & Lundy, August 21,1997.

8.23. Continental Grain Co., Morris, IL, Mr. Dan Mehochko, Personal Communication with Sargent & Lundy, July 10,1997.

8.24. Millennium Petrochemicals, Inc (formerly Quantum Chemical Corp., USI Division), Morris, IL, Mr. Mark Betozynski, Personal Communication with Sargent & Lundy, June 30,1997.

3.25. Biewer Co. ofIllinois, Seneca, IL, Ms. Brenda Christensen, Personal Communication with Sargent & Lundy, July 16,1997.

8.26. Water Treatment Facility, Mr. Gary Fleming, Personal Communication with Sargent & Lundy, August 12,1997, S.27 Commonwealth Edison, Mr. Mike Martinovich, Personal Communication with Sargent & Lundy, August 25,1997.

8.28. Water and Wastewater Treatment Facility, Seneca, IL, Mr. Jerry Lowell, Personal

- Communication with Sargent & Lundy, July 16,1997.-

8.29. Akzo Nobel Chemical, Mr. Richard Stobbs, Personal Communication with Sargent

& Lundy, July 16,1997.

8.30. Jefferson Smurfit Corp., Morris, IL, Mr. Wendell Darling, Personal Communication with Sargent & Lundy, July 16,1997.

8.31. Reichhold Chemicals, Inc., Morris, IL, Mr. James Manlove, Personal

.Commumcation with Sargent & Lundy, July 16,1997.

8.32. Sponge-Cushion, Inc., Morris, IL, Mr, David Schierenbesk, Personal Communication with Sargent & Lundy, August 21,1997.

8.33. Water and Wastewater Treatment Facility, Morris, IL, Mr. Greg Christensen, Personal Communication with Sargent & Lundy, July 15,1997.

Page 14 of 15

8.34. Burlington Nonhern and Sante Fe, Aurora, IL, Mr. John Linquist, Personal Communication with Sargent & Lundy, June 30,1997.

8.35. Olin Corporation,- Charleston, TN, Mr. Dennis Holgerson, Personal Communication with Sargent & Lundy, August 21,1997. .

8.36. Burlington Nonhern Sante Fe, Ottawa, IL, Foreman Bailey, Personal Communication with Sargent & Lundy, July 30,1997.

8.37, Water Treatment Facility, Marseilles, IL, Mr. Larry Cowie, Personal Communication with Sargent & Lundy, July 16,1997.

8.38. Material Service Corp, Morris, IL, Mr, Dick Stevens, Personal Communication with Sargent & Lundy, August 26,1997.

8.39 US Coast Guard, Washington, DC, Lt Commander John Fanhing, Letter from Sargent & Lundy, August 27,1997, l 8.40 .US Coast Guard, Marine Safety, Petty Officer Pandt, Letter from Sargent &

i Lundy, August 27,1997.

8.41 HazMat Coordinator, Fred Bevinton, LaSalle Station, Personal Communication with Sargent & Lundy, December 9,1997,

' 9,0 ATTACHMENTS 9.1 Tier II Repon, Evenson Explosives, LLC 9.2 Tier II Report, Depanment of Army, Rock Island District 9.3 Tier II Repon, Reichhold Chemicals, Inc.

9.4 Tier I Repon, Quantum Chemical Corp.

9.5 ' Tier 11 Repon, Explosives Technologies, International.

9.6 Tier II Repon, CF Industries 9.7 Tier 11 Repon, CF Industries.

9.8 Tier II Report, Jefferson Smurfit Corp.

9.9 Tier I Repon, SCI, Sponge Cushion.

. Page 15 cf 15