ML20063M003

Annual Rept for LaSalle County Nuclear Power Station for Jan-Dec 1993

ML20063M003
Person / Time
Site:	LaSalle
Issue date:	12/31/1993
From:	Ray D COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
NUDOCS 9403080261
Download: ML20063M003 (59)

Text

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Commonwealth Edison LaSalle County Nuclear Station 2601 N. 21st. Rd.

Marseillos, Illinois 61341 Telephone 815/357-6761 February 28,1994 d'

Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Mail Station PI-137 Washington, D.C. 20555 Attn: Document Control Desk Enclosed for your information is the annual report covering LaSaSe County Nuclear Power Station for the period covering January,1993 through December,1993.

Very truly yours, D. J. Ray Station Manager LaSalle County Station j'

DJR/mkl Enclosure cc:

Regional Administrator - Reg'on III NRC Senior Resident inspector - LaSalle IL Department of Nuclear Safety - 12Salle NRR Project Manager - LaSalie GE Representative - LaSalle Regulatory Assurance Supervisor - LaSalle Manager of Nuclear Licensing - Downers Grove Nuclear Fuel Services Manager - General Office QA/NS Off-Site Review - General Office INPO Records Center Station File 9403080261 931231

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Introduction l

The LaSalle County Nuclear Power Station is a two-Unit facility owned by Commonwealth Edison Company and located near Marseilles, Illinois. Each i

unit is a Boiling Water Reactor with a designed not electrical output of 1078 Hogawatts. Waste heat is rejected to a man-made cooling pond using i

the Illinois river for make-up and blowdown. The architect-engineer was Sargent and Lundy and the contractor was Commonwealth Edison Company, l

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

I Initial criticality was achieved on June 21, 1982 and commercial power operation was commenced on January 1, 1984.

l 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 was commenced on October 19, 1984.

l This report was compiled by Michael J.

Cialkowski, telephone number (815) 357-6761, extension 2427.

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l TABLE OF CONTENTS I.

INTRODUCTION 1

II.

ANNUAL REPORTABLE DOCUMENTATION FOR UNITS 1 AND 2 A.

Sumnary of Operating Experience B.

Unit Outage or Power Reductions C.

Radiation Exposure D.

Indications of Failed Fuel Elements E.

Tests and Experiments Not Covered in the Safety Analysis Report F.

Changes to Procedures Covered in the Safety Analysis Report G.

Summary of Changes to the Facility Which Are Described in the Safety Analysis Report H.

Summary of Safety Related Modifications I.

Summary of ECCS Outages J.

Survey of Evaluation Results of Chlorine Shipments by Barge on the Illinois River K.

Summary of Events Violating Technical Specification 3. 4.5.

Primary Coolant Iodine Spiking Exceeding Allowable Limits i

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II. Annual Reportable Documentation for Unit 1 and 2 i

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A.

Summary of Operating Experience The summary of the operating experience has been reported monthly in LaSalle's.NRC Monthly Reports (Section II.A) dated January 1993 through December 1993. For safety related maintenance (non-outage related) performed during the period of January-1993 thru December 1993, see Attachment A.

B.

Unit Outages and Power Reductions For unit outages, see Attachment B.

For unit power reductions see Attachment C.

C.

. Radiation Exposure This information is reported annually for 1993 in the respective sections relating to numbers compiled for LaSalle Unit 1 and 2 in

.the 10 CFR 20.407 annual report submitted under a different cover.

D.

Indications of Failed Fuel Elements This section has been reported monthly.in LaSalle's NRC Monthly Reports (Section II F.5) dated January 1993 through December-1993.

E.

Tests and Experiments not covered in the Safety Analysis Report During this reporting period, January 1, 1993 through December 31,1993 there were no tests or experiments conducted.

F.

Changes to Procedures Covered in the Safety Analysis Report LLP-93-026, operation of Unit 2 Feedwater With The Security UPS Deenergized' This special procedure will allow the unit 2 feedwater'to operate while the security UPS is deenergized for maintenance. The security UPS provides the electrical feed to the Lovejoy Feedwater Turbine Control System. This procedure transfers control of the "2A" turbine driven reactor feedwater pump to a manual pressure regulator located at the Lovejoy pneumatic cabinet.

The feedwater system is not a safety-related system and is not required for safe shutdown of the plant nor is it. required during or after accident conditions. The control system will be operated in a manner consistent with its description in UFSAR 7.7.4.

All turbine driven reactor feedwater pump valid trip signals will still trip the "2A" turbine driven reactor feedwater pump if required. All postulated accidents of the-feedwater system are bounded by either the "Feedwater Controller Maximum Demand" analysis in UFSAR 15.1.2A or " Total Loss. of Feedwater Flow" analysis in UFSAR 15.2.7.

The system is returned to normal following the maintenance on the security UPS.

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F.

Changes to Procedures Covered in the Safety Analysis Report-(continued)

I LLP-93-033, Manual Backwash Of The 2A RHR Service Water Strainer This Procedure will be used to specify the method of backwashing the 2A Residual Heat Removal Service Water strainer with the 2E12-F336A valve out-of-service closed.

This procedure is necessary because a temporary system change will install a manual isolation valve on the 2A Residual Heat l

Removal Service Water strainer backwash line in accordance with CHRON #

l 119575.

This is being done so that a hole in the elbow between the strainer and the backwash valve can be repaired by replacing the elbow.

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Automatic backwashing of the strainer will not be possible, nor is it I

required by UFSAR section 9.2.1.

Manual backwashing is acceptable, and can be performed with this temporary system change installed.

The system will I

l be returned to normal upon completion of this work.

LLP-93-046, Reactor Building Overhead Crane (OHC02G)

Cask Mode Of Operation For Spent Fuel Shipping Casks This procedure provides administrative controls to setup and operate the reactor building crane in the Cask Mode with the TN-8L cask.

The i

procedure ensures that the reactor building crane trolley and hoist speeds are within the limitations allowed by the UFSAR and special report #2 to l

the PSAR while in the Cask Mode of operation and to ensure that TN-8L cask I

will not be raised more than 6 inches from the refuel floor. This procedure takes the place of LFP-800-02 and LFS-400-01.

This procedure is required because a temporary system change allows the bypassing of the geared up limit switch on the reactor building overhead crane.

Lifting lead 53 will allow the ULR relay to deenergize.

Lowering the cask onto the cask wash pit floor does not reset the geared limit switch; so as a result, the cask cannot be raised.

Lifting lead 53 will allow the cask to be raised from the cask wash pit in the cask mode.

Cask lift height will be administratively controlled to a maximum of 6 inches above the refuel floor i

(the design basis) when the cask is in the cask wash pit.

This temporary system change will only be installed when a cask is in the cask wash pit.

LLP-93-046, Rev. 1, Reactor Building Overhead Crane (OHC02G)

Cask Mode Of Operation For Spent Fuel Shipping Casks l

This procedure provides administrative controls to setup and operate the reactor building crane in the Cask Mode with the TN-8L cask. Tha l

l procedure is being revised to allow a maximum trolley speed of 30 fpm I

instead of the present 18.5 fpm while in the cask mode of operation.

UFSAR Section 9.1.4.2.3.1 specifies that the trolley speed, while in the

' Critical "L" Path' mode of operation, will be a maximum of 18.5 fpm. The UFSAR goes on to state that this speed was " arbitrarily" chosen.

However, the acceleration and deceleration loads, corresponding with the reduced l

crane speed of 10.5 fpm, result in decreased load swing.

In addition, the l

UFSAR states the maximum speed of 18.5 fpm will limit trolley drift to about 3 inches such that the Critical "L" Path will be about 11 1/4 inches wide. This procedure change will allow a trolley maximum speed of 30 fpm.

At this increased speed, load swing will be a little greater and the Trolley will drift a little more such that the Critical "L" Path will be a little wider. This procedure is required because a temporary system change allows the bypassing of the geared up limit switch on the reactor building overhead crane.

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1 F.

Changes to Procedures Covered in the Safety Analysis Report-(continued)

LLP-93-046, Rev. 1, Reactor Building Overhead Crane (OHC02G)

Cask Mode of Operation For Spent Fuel Shipping Casks (continued)

Lifting lead 53 will allow the ULR relay to deenergize.

Lowering the cask onto the cask wash pit floor does not reset the geared limit switch; so as a result, the cask cannot be raised.

Lifting lead 53 will allow the cask to be raised from the cask wash pit in the cask mode.

Cask lift height will be administrative 1y controlled to a maximum of 6 inches above the refuel floor (the design basis) when the cask is in the cask wash pit.

This temporary system change will only be installed when a cask is in the cask wash pit.

l LLP-93-064, VG WRGM Drying Out Procedure This procedure is to provide direction to dry out the VG WRGM sample i

line and the VG stack. This procedure allows for a pump to be hooked up to l

the VG WRGM in order to blow out the sample lines.

The pump will be hooked up at the grab sample inlet tap.

During this procedure, the VG WRGM will not have any sampling capability.

The use of this procedure will not change any analyzed parameters for this system.

LST-93-029, Troubleshooting lE51-F063 This test procedure will describe the troubleshooting sequence for determining the condition of the RCIC inboard isolation valve after a l

thermal trip. The use of this procedure will not affect any of the safety l

considerations for this valve.

LST-93-046, Temporary Fill For HPCS System Discharge Line This test procedure will provide temporary make-up water to the HPCS system from the clean condensate system (MC) to allow for maintenance of the HPCS water leg pump. This procedure allows the HPCS system to be declared inoperable, but available.

LST-93-076, Temporary Fill For RCIC System Discharge Line This test procedure provided temporary make-up water to the RCIC system from the clean condensate system (MC) to allow for maintenance of the RCIC water leg pump.

This procedure allowed the RCIC system to be available, but not operable.

LST-93-081, Verifying The Delta T Temperature This test procedure was used to determine the reactor vessel steam dome temperature, the reactor recirculation pump suction temperature, and the l

differential temperature seen by the trip card.

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Changes to Procedures Covered in the safety Analysis Report-(continued)

LST-93-149, Time Delay Setting Verification for RPS EPMA's This was a special procedure for installing test equipment on the Reactor Protection System Electrical Power Monitoring Assemblies for use in r.easuring the time delay associated with the overvoltage, undervoltage and underfrequency trips.

The procedure also provided for adjusting the time delay settings, as necessary. The procedure allowed installation of the test equipment on live and dead buses.

LST-93-150, RCIC Vacuum Breaker Test This was a special procedure that provided for monitoring of suppression pool parameters during operation of the RCIC system. This was done in an effort to evaluate a potential leakage path via the RCIC vacuum breaker line to the suppression chamber.

LAP-820-llTA, Plant Specific Technical Guidelines This Administration Procedure provides for a controlled document location for the Emergency Operating Procedures Plant Specific Technical Guidelines (PSTG), and provides for the control of the PSTG.

The revisions made to this procedure included the elimination of typographical errors, clarifications, refined calculations, and the addition of the Reactor Water Cleanup System recirculation mode to the list of allowed Depressurization Systene.

IAP-820-llTA, Plant Specific Technical Guidelines This procedure provides a controlled document for the Emergency operating Procedures Plant Specific Technical Guidelines.

The revision being made will authorize the defeat of the RHR Shutdown Cooling and Head Spray valve isolation signals to provide a means of using RHR as an outside the core shroud injection system during ATWS events.

Because RHR Shutdown Cooling and Head Spray piping is designed for operation below 500 psig guidance is provided to restrict its use to when the reactor vessel pressure is less than 500 psig.

Also included in this revision is the allowance to defeat Reactor Water Cleanup (RWCU) isolation signals when the RWCU system is being used for alternate boron injection.

The use of alternate boron injection is necessary following a ATWS event of significant magnitude when the Standby Liquid Control (SBLC) system fails to perform its design function.

The isolation interlocks that are being defeated are designed to maintain primary containment integrity, prevent filtering out boron while injecting I

with SBLC, and to protect the RWCU demineralize rs from high temperatures.

When the system is operated for alternate boren injection, it is essentially operated the same as that during normal operations with the exception that the demineralizers are bypassed, normal resins are dumped and the system is filled with a concentration of boren chemicals.

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Changes to Procedures Covered in the safety Analysis Report-(continued)

LOA-FX-12T, Repair Procedure For The Reactor Recirculation Pump Discharge valve 1B33-F067B This Abnormal Procedure provides a cold shutdown repair procedure for the Reactor Recirculation (RR) Pump Discharge Valve 1B33-F067B in the event of a fire in the Control Room.

It is a new procedure that will allow closing the RR pump discharge valve locally at its Motor control Center.

This is needed to prevent short cycling water through the non-running RR pump, when using the "B" Loop of Residual Heat Removal Shutdown Cooling Mode from the Remote Shutdown Panel.

LOA-FX-14T, Repair Procedure For The Reactor Recirculation Pump Discharge Valve 2B33-F067B This Abnormal Procedure will provide a cold shutdown repair procedure for the Reactor Recirculation (RR) Pump Discharge Valve 2B33-F067B in the event of a fire in the Control Room.

It is a new procedure that will allow closing the RR pump discharge valve locally at its Motor Control Center.

This is needed to prevent short cycling water through the non-running RR pump, when using the "B" Loop of Residual Heat Removal Shutdown Cooling Mode from the Remote Shutdown Panel.

LOA-1(2)H13-P601 C202, RHR Service Water Strainer 1(2)A Differential Pressure High This Procedure was revised to allow the use of Special Procedure LLP-93-038, Manual Backwash of The 2A RHR Service Water Strainer. This procedure revision was necessary because a temporary system change will install a manual isolation valve on the 2A Residual Heat Removal Service Water strainer backwash line in accordance with CHRON # 119575. This is being done so that a hole in the elbow between the strainer and the backwash valve can be repaired by replacing the elbow. Automatic backwashing of the strainer will not be possible, nor is it required by UFSAR section 9.2.1.

Manual backwashing is acceptable, and can be performed with this temporary system change installed.

The system will be returned to normal upon completion of this work.

LOA-RH-03, Loss Of RHR Service Water This Procedure was revised to allow the use of Special Procedure LLP-93-038, Manual Backwash Of The 2A RHR Service Water Strainer. This procedure revision was necessary because a temporary system change will install a manual isolation valve on the 2A Residual Heat Removal Service Water strainer backwash line in accordance with CHRON # 119575.

This is being done so that a hole in the elbow between the strainer and the backwash valve can be repaired by replacing the elbow. Automatic backwashing of the strainer will not be possible, nor is it required by UFSAR section 9. 2.1.

Manual backwashing is acceptable, and can be performed with this temporary system change installed.

The system will be returned to normal upon completion of this work.

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Changes to Procedures Covered in the Safety Analysis Report-(continued)

LOP-RH-04, Filling, Venting The RHR Service Water System l

This Procedure will be revised to allow the use of Special Procedure l

LLP-93-038, Manual Backwash Of The 2A RHR Service Water Strainer.

This procedure revision is necessary because a temporary system change will install a manual isolation valve on the 2A Residual Heat Removal Service Water strainer backwash line in accordance with CHRON # 119575.

This is being done so that a hole in the elbow between the strainer and the backwash valve can be repaired by replacing the elbow. Automatic backwashing of the strainer will not be possible, nor is it required by UFSAR section 9.2.1.

Manual backwashing is acceptable, and can be performed with this temporary system change installed.

The system will be returned to normal upon completion of this work.

LOP-RH-05, Operation Of The RHR Service Water System This Procedure was revised to allow the use of Special Procedure l

LLP-93-038, Manual Backwash Of The 2A RHR Service Water Strainer.

This procedure revision was necessary because a temporary system change will install a manual isolation valve on the 2A Residual Heat Removal Service Water strainer backwash line in accordance with CHRON # 119575. This is being done so that a hole in the elbow between the strainer and the backwash valve can be repaired by replacing the elbow. Automatic backwashing of the strainer will not be possible, nor is it required by UFSAR section 9. 2.1.

Manual backwashing is acceptable, and can be performed with this temporary system change installed.

The system will be returned to normal upon completion of this work.

LOP-FM-14, Backwash Of The Residual Heat Removal Service Water Strainers This Procedure was revised to allow the use of Special Procedure LLP-93-038, Manual Backwash Of The 2A RHR Service Water Strainer. This procedure revision was necessary because a temporary system change will install a manual isolation valve on the 2A Residual Heat Removal Service Water strainer backwash line in accordance with CHRON # 119575.

This is being done so that a hole in the elbow between the strainer and the backwash valve can be repaired by replacing the elbow. Automatic backwashing of the strainer will not be possible, nor is it required by UFSAR section 9.2.1.

Manual backwashing is acceptable, and can be performed with this temporary system change installed.

The system will be returned to normal upon completion of this work.

LOP-VG-02, Shutdown Of The Standby Gas Treatment System (SBGT)

The revision to this procedure will delete the prerequisite for no auto initiation signal present, to allow the shutdown of the unaffected unit's train when both trains auto initiate due to a valid initiation signal.

It will delete the precaution when both trains are desired to be running, because this is not applicable to this procedure.

It will create steps to shutdown the train on the unaffected unit during a valid initiation signal, to facilitate evaluations performed during transients.

Finally it will rearrange the procedure format to conform to station procedure standards.

G.

Summary of Changes to the Facility which are Deset15ed in the safety Analysis Report Temporary System Change 1-0426-93 The Cycled Condensate (CY) piping which supplies the "A" Drum Processing Unit (DPU) has a 4 to 5 gpm leak. The leak is located in the vertical pipe shaft which routes piping from the upper Radwaste Pipe Tunnel to the "A" DPU.

The temporary system change provides for the installation of an isolation valve in the upper Radwaste Pipe Tunnel to allow for the supply of CY to other Radwaste locations without introducing CY to the leak.

Additionally, the temporary system change provides for the routing of a j

hose from the isolation valve to the pressure regulator valves located in the "A"

DPU.

This will allow for a supply of CY to the "A" and "B" DPU's while bypassing the leak in the vertical pipe shaft.

Temporary System Change 1-0447-93 This temporary system change allowed the installation of a switch jumper and a time delay at panel IPA 03J to prevent spurious nuisance alarms caused by Unit 1 spent fuel pool rerack work. During the fuel pool rerack work, fuel was removed from the fuel pool.

These spurious alarms are the high/ low level alarms at lH13-P601 C207. The fuel pool high and fuel pool low level alarm at 1H13-P601 C207 remained fully operable.

Reference UFSAR section 9.1.3.2.1 for control room alarms. During the fuel pool rerack work, fuel was removed from the fuel pool. The system was returned to normal upon completion of the work.

Temporary System Change 1-0450-93 This Temporary System Change installed a switch jumper to bypass Unit 1 "B" Reactor Recirculation Flow Control Valve Actuator Drain Alarm.

The Unit 1 "B" Reactor Recirculation Flow Control Valve Actuator Drain alarms were up solid and were masking other alarm signals. The actuator 0-rings were degraded, allowing fyrquel to pass through to the drain line.

By bypassing these alarms, the other alarms can initiate the annunciator in the control room identifying other problems.

The alarm signal is initiated from a leaky actuator.

Provisions were made for a special log to be performed daily to verify that the alarm is still present by closing the switch jumper. The system was returned to normal after repairs.

Temporary System Change 1-0486-93 The temporary system change provided for the installation of a jumper l

to allow for Radwaste Crane bridge movement when moving intermediate l

storage area cubicle lids.

The jumper bypassed a limit switch to allow bridge movement with greater than 1 ton load in the high level storage areas.

Temporary System Change 1-0569-93 This temporary system change allowed the bypassing of the geared up limit switch on the reactor building overhead crane.

Lifting lead 53 l

allowed the ULR relay to deenergize.

Lowering the cask onto the cask wash pit floor did not reset the geared limit switch; so as a result, the cask couldnot be raised.

Lifting lead 53 allowed the cask to be raised from the cask wash pit in the cask mode.

Cask lift height was administratively controlled to a maximum of 6 inches above the refuel floor (the design basis) when the cask was in the cask wash pit.

This temporary system change was only installed when a cask was in the cask wash pit.

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Summary of Changes to the Facility Which are Described in the Safety Analysis Report-(continued)

Temporary System Change 1-0789-93 This Temporary System Change was created because the Unit 1 RHR, B-Loop, Testable Check valve (1E12-F041B) position indicator is broken / malfunctioning.

Position indication is being disabled to prevent misinformation to operators regarding valve position.

The position indication of the 1B RHR Injection Line Testable Check valve will be electrically disconnected at the location of the panel terminal block. The position indication is specified as non-safety, non-EQ in the Q-List.

Temporary System Change 1-0925-93 The Temporary System Change installs a temporary skid to add zinc oxide into the reactor feedwater for source term (dose rate) reduction. The zinc l

oxide is injected into the common suction of the Turbine Driven Reactor l

Feed Pumps, utilizing the existing low cobalt sample point.

l Temporary System Change 2-0124-93 This temporary system change installed a manual isolation valve on the 2A Residual Heat Removal Service Water strainer backwash line in accordance with CHRON # 119575. This was done so that a hole in the elbow between the strainer and the backwash valve could be repaired by replacing the elbow.

Automatic backwashing of the strainer was not possible, nor was it required l

by UFSAR section 9.2.1.

Manual backwashing was acceptable, and could be l

performed with this temporary system change installed.

The system was returned to normal upon completion of this work.

Temporary System Change 2-0352-93 I

This temporary system change provided installation of the switched jumpers at panel 2FP04JA and allowed operations to take fire detection zones 2-16, 2-16P, 2-31, 2-32, 2-33, and 2-34 out-of-service during welding, cutting, and grinding operations in the subject detection zones.

Welding, cutting, or grinding in the vicinity of an in-service detector could have resulted in false alarms at the fire protection control panels.

The system was returned to normal upon completion of the work.

Temporary System Change 2-0429-93 This temporary system change provided installation of a switched jumper at panel 2FPO4JA and allowed operations to take fire detection zone 2-30 out-of-service during welding, cutting, and grinding operations in the detection zone. Welding, cutting, or grinding in the vicinity of an in-i service detector could have resulted in false alarms at the fire protection j

control panels. The system was returned to normal upon completion of the work.

l Out of Service 0-0064-92 The Auxiliary Building Office HVAC Humidity Steam Generator will be isclated electrically.

This will prevent it from functioning in order to keep it from altering Auxiliary Building relative humidity.

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Summary of Changes to the Facility Which are Described in the safety Analysis Report-(continued)

Out of Service 0-0896-92 The out of Service will electrically isolate power to the VC/VE Humidifier Steam Generators so they will not function. This will prevent the steam generators from altering Control Room or Auxiliary Electric Equipment Room humidity.

out of Service 0-0351-93 This out of Service isolates the Station Heat make up pump auto start pressure switch OPS-SH132to allow it to be replaced by two new switches, OPS-SH132A and OPS-SH132B under Modification M-1-0-82-043.

With this out of Service in effect, the new pressure switches will not sense changing pressure in their respoctive sensing lines. The auto start /stop function provided by the pressure switch is disabled so the make up pump will not function in the automatic mode, but will function in the manual mode.

Out of Service 1-0324-92 The out of Service isolates the Turbine Building Closed Cooling Water Heat Exchanger 1WT01AB. There are two heat exchangers, each of which will support 100% operation. During normal operation, service water flow is automatically throttled as needed for cooling.

Having the service water completely isolated from the heat exchanger is generally considered to cause less fouling than reduced velocity conditions.

Out of Service 1-0469-92 The out of service isolated the Turbine Lube oil cooler 1T001AB.

Only one cooler is needed for normal operation.

During normal operation, I

service water flow is automatically throttled as needed for cooling.

Having the service water completely isolated from the cooler is generally considered to cause less fouliag then reduced velocity conditions.

Out of Service 1-0610-93 The out of Service isolates the 1TG02AA Stator Cooling Heat Exchanger.

Only one heat exchanger is necessary for normal operation.

During normal operation, service water flow is automatically throttled as eeded for cooling.

Having the service water completely isolated from 1.a heat exchanger is generally considered to cause less fouling than reduced velocity conditions.

Out of Service 1-0880-93 l

This out of service provided the isolation of the 1A Reactor Recirculation (RR) Low Frequency Motor Generator Set for maintenance purposes. The 1A PR pump uas not available for low speed operation.

If an auto downshift signal is received, the 1A RR pump would trip to off instead of to slow speed while the 1B RR pump downshif ts to slow speed.

Single l

Loop Operation is provided for in plant procedures and the Technical Specifications.

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Summary of Changes to the Facility Which are Described in the Safety Analysis Report-(continued)

Out of Service 2-0246-93 The Out of Service electrically determinates the Unit 2 Diesel Fire Pump Fuel Oil Transfer solenoid suction valve (2D0024) for maintenance purposes. This valve is normally closed except when the diesel fire pump fuel transfer pump is operating.

The loss of fuel from the storage tanks due to failure of the diesel fire pump fuel transfer system is prevented by means of this fail-closed valve. The Out of Service will prevent the valve from opening.

Procedures provide a means to use the bypass valve 2D0021 around the 2D0024 valve to fill the Diesel Fire Pump day tank.

Out-of-Service 2-0252-93 This out-of-service allowed the installation of a new supervised fire detection circuit for the "2B" diesel generator room carbon dioxide system.

The unit 2 diesel generator room carbon dica.=S system was inoperable during the entire duration (approximately I saks) of Modification i

M01-2-89-007.

UFSAR sections 9.5.1.2.1, 9.d.A.2.2, H.3.8.3, H.3.8.4, Technical Specification section 3.7.5.3, ard NFPA-12, 1973 Edition section 1453 were evaluated. They describe the unit 2 diesel generator carbon dioxide system's common alarm horn for both "2A" and "2B" diesel generator rooms, and the manual pushbutton in the "2B" diesel generator room, which were both inoperable during this out-of-service. Although the unit 2 diesel corridor common alarm horn was inoperable, an audible and visual pre-discharge alarm was available within the "2A" diese) generator room to warn individuals if the carbon dioxide system were about to discharge.

While this out-of-service was in affect, compensatory measures (i.e.,

fire watches and the use of portable fire suppression equipment) were established to ensure that a fire is rapidly detected and extinguished.

Out of Service 2-0383-93 l

The Out of Service isolates the Turbine Building Closed Cooling Water Heat Exchanger 2WT01AB. There are two heat exchangers, each of which will support 100% operation.

During normal operation, service water flow is automatically throttled as needed for cooling. Having the service water completely isolated from the heat exchanger is generally considered to cause less fouling than reduced velocity conditions.

Out of Service 2-1779-93 i

The Out of Service electrically disables the refrigerated air drying capability of the 2A D/G "A" Air Start Subsystem. This will remove one of l

the non-refrigerated air dryers from service while both air compressors remain on-line.

This will allow maintenance to be performed on the air dryer while still maintaining D/G operability.

Out of Services 1-0393-92 and 2-0261-93 These Out of Services provide for the 1(2)B21-R005 Local Core Plate Differential Pressure Instrument by closing the high and low stop valves.

This will prevent inadvertent HPCS initiation and scrams from this inactive instrument. The isolation of this instrument results in only a loss of local indication. No automatic functions are affected.

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Summary of Changes to the Facility Which are Described in the Safaty Analysis Report-(continued)

Operability Evaluation, Level Instrumentation Affected By Noncondensible Gas This operability evaluation is for level instrumentation that may be l

affected by noncondensible gas in the reference leg.

Noncondensible gas may cause level indication errors during normal or rapid depressurization 1

as described in NRC Generic Letter 92-04 and NRC Information Notice 93-27.

j BWROG Report 92-074 analyzed the effect of noncondensible gas on level l

initiations while the reactor was in the Run Mode.

Level initiations will l

occur prior to vessel pressure reaching 450 psig for accidents in the Run l

Mode.

Degassing occurs in the reference leg at reactor pressures less than 450 psig. At reactor pressures less than 450 psig, then degassing may l

cau.ae level initiations to be delayed.

The following will occur at pressure less than 450 psig:

1. All wide range level isolations and l

initiations will occur before the analytic or design basis limit.

2. The level 3 RPS initiation and RHR shutdown cooling isolation could actuate outside its required accuracy of UFSAR Table 7.2-1 and 7.3-2.

i Operability Evaluation, LPCS Injection Valve This operability evaluation was performed to ensure that the lE21-F005 valve would be operable in light of the potential for the motor to burnout when the valve is secured after a LOCA, which would prevent reopening if re-injection were needed. This concern is only raised in a degraded

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voltage condition. The evaluation determined that the valve would be l

operable because it can be operated n,snually if re-injection were needed.

l It was also determined that the operators are trained to release the switch as soon as the closed indicating light is received so that the potential for loosing the valve motor is reduced during a degraded voltage condition.

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l Operability Evaluation, Unit 1 RCIC on Potential Failure of 250 VDC Breakers to Trip on Fault The inability of the breakers in MCC 121Y to trip on a fault current will not ndtigate the ability to bring the reactor to a hot shutdown condition. The inability of the Westinghouse HFB Molded Case Breakers with magnetic trip capability to trip on fault currents does not introduce a new failure mode.

In order for the breakers to fail, a fault has to occur on the equipment being serviced by the breakers. The failure of this equipment is bounded by single failure of RCIC.

RCIC will function per design since the function of the breakers to support RCIC operation is to remain closed.

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Parts Technical Evaluation L-93-007-0151

?his Parts Technical Evaluation will allow the disc replacements for in- ' '2) E51-F065/66 RCIC Valves.

The new disc design extends the center of gravity and shifts the counterweight of the disc for vertical pipe j

installations.

Based on Anchor Darling Design Report Certification, the counterweight location effects only the calculations for the hinge and i

actuator shaft.

However, the inspection results indicate there are no effects / violations of any design limits. There are no mechanical changes associated with the new disc design. The disc will still perform the original function to assure immediate isolation of the reactor in case of a LOCA, or to prevent leakage greater than 5 gpm in the reverse direction.

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Summary of Changes to the Facility Which are Described in the Safety Analysis Report-(continued)

On-Site Review 93-046 Rev. 1, Reactor Pressure Vessel Reference Leg Backfill Modification Use of Check Valves On Instrument Lines This On-Site Review looked at the revision to On-Site Review 93-046, Rev.

O.

The Reactor Pressure Vessel reference leg backfill modifications require connecting the backfill instrument lines to the instrument reference leg piping inboard of the instrument reference leg isolation valves for those reference legs with active trip functions. The backfill instrument lines will use check valves as the containment isolation boundary for these four reference legs.

The use of check valves will prevent a common mode failure of multiple reference legs.

This revision evaluated extensive changes of the original On-Site Review section titled

" Bases for the Change to the Licensing Basis".

However, these changes were consistent with the original On-Site Review. The revision also changed the requirement to check backfill flow once per shift during operator rounds to once per day.

On-Site Review 93-063 Rev. O and Rev.

1, ITE Breaker Potential Failure due to Grease Hardening Rev. O documented the evaluation and review performed in response to the issue of potential hardening grease due to aging and/or contarination affecting breaker operation associated with ITE Switchgear. The review was initiated due to concerns which arose out of failures of two breakers which appeared to be caused by hardening of grease. An operability evaluation on the ITE breakers was performed and concluded that the Safety Related and Tech Spec Related breakers are operable based on the operational history of the breakers within the recent timeframe and on the identification of the proper preventative maintenance being performed based on recent procedure changes to the ITE breaker surveillance. The On-Site Review details an action plan that will be followed in accordance with the operability recommendations to ensure longterm reliability of the ITE breakers.

Rev. 1 dorarents the evaluation and review of the issue of potential grease hardening in the ITE breakers based on updated information which affected assumptions which were made in the Rev. 0 On-Site Review. A revised action plan to addrean longterm ITE breaker operability was detailed in the on-Site Review.

WR Lll101 and WR L12023, Impeller Replacement For 0FP25P & OPP 26P Fire Jockey Pumps These Work Requests provided an increase in the impeller diameter for the OFP25P fire jockey pump and a decrease in the impeller diameter on the 0FP26P fire jockey pump.

This allows the fire jockey pumps to sufficiently maintain system pressure to minimize surges when the diesel fire pumps start. The recommended impeller will result in a maximum static pressure at the underground fire protection loop of about 175 psig.

The maximum static pressure at the underground loop will be verified to be less than 175 psig upon completion of these work requests.

This was accomplished as a post maintenance test and was documented on the post maintenance test form for the associated work package.

Changing impellers will only change the pressure which the pump produces. The flow on the pump does not change. The pressure produced by 0FP25P and 0FP26P with the 9.125 inch impeller installed, will be less than the design conditions of all the fire protection piping, valves, and instruments.

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Summary of Changes to the Facility Which are Described in the Safety Analysis Report-(continued)

Isolation Of The 26B Heater Drain Emergency Drain Valve This Safety Evaluation allowed Mte isolation of the 26B heater drain emergency drain valve (2HD059B) one to a steam leak at the valve.

The 26B j

heater emergency drain valve will not be available during a high-high level l

condition (+4").

This configuration would cause the operator to isolate the 26B heater at +3" in accordance with LOA-FM-03J-B101.

Isolation of the 26B heater will result in a 40 degree decrease in final feedwater temperature (LOA-FM-03J-B101, step B.1.a).

The plant has been analyzed for a 145 degree Fahrenheit reduction in the final feedwater temperature (OSR 91-48, L2C5 Supplemental Reload License Report Appendix B).

LOA-PM-03J-B101 has been revised to account for the emergency drain valve being taken out of service closed.

Loss of feedwater(s) LOA-FW-01 is in place to describe the actions required during a loss of feedwater heating transient.

LOA-FW-01 is referenced in the revised LOA-PM-03J-B101.

UFSAR Chapter 2 - Site Characteristics Section 2.3.3.2 was revised and Tables 2.3-65(1-7) and 2.3-66 were deleted since the Offsite Dose Calculation Manual contains tables listing sample locations. The UFSAR tables are redundant.

Referencing the ODCII in the UFSAR will ensure that the correct information is used.

Section 2.3.3.1 was revised, Sections 2.3.3.1.1, 2.3.3.1.2, 2.3.3.1.3, 2.3.3.1.4 and Table 2.3-64 were deleted due to changes to the Onsite Meteorological Measurements Program per EPSP letter of 05/27/93.

UFSAR Chapter 3 - Design of Structures, Components, Equipment and Systems Change of main temperature setpoint from 65 F to 70 F, and alarm setpoints of Switchgear Rooms Temperature Indicating Controls from a high temperature alarm of 104 F to a low temperature alarm of 65 F per Setpoint Change Requests92-039, 92-040,92-041, 92-042,92-043 and 92-044 for the following temperature indicating controls:

Division 1 Switchgear Room 1&2 TIC-VX009; Division 2 Switchgear Room 1&2 TIC-VX008; MG Set Switchgear Room 1&2 TIC-VX007.

UFSAR Chapter 4 - Reactor Modifications M01-1-90-009 atd M01-2-90-007 lowered the Control Rod Drive support structures of Unit 1 and 2, respectively, to increase the nominal clearance between it an". the CRD housing from 1 inch to 1.5 inches (measured at ambient temperatute conditions).

The wording of UFSAR Section 4.6.2.3.1.3 and 4.6.3.2.1.5 was revised to agree with Technical Specifications concerning control rod following.

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Summary of Changes to the Facility Which are Described in the Safety Analysis Report-(continued)

UFSAR Chapter 4 - Reactor (continued)

Section 4.5.2.1 was revised to allow the use of either 304L or 316L grade stainless steels as a replacement of damaged tie-bars in the Unit 2 steam separator.

4.5.2.1 describes the materials used to construct the reactor pressure vessel and internals.

4.5.2.1 presently states that all materials used on the steam separators is made of 304 grade stainless steels. NUREG 0313 and Generic Letter 88-01 recognize that "L" grade stainless steels are less susceptible to stress corrosion cracking due to their lower carbon content. These new materials are suitable for replacement, the PFSAR was revised to list them as materials of construction for tac steam separator.

UFSAR Chapter 5 - Reactor Coolant System and Connected Systems Invoke ASME Code Case N-498, " Alternate Rules for 10 Year Hydrostatic Pressure Testing for Class 1 and 2 Systems".

Revision to Section 5.4.7.3.2 to correct an error in the text to reflect that HPCS automatically initiates at reactor water level 2 (as opposed to water level 3, which it now states). This change does not affect any accident analysis because the proposed change is in agreement with UFSAR chapters 6, 7,

and 15.

Removal of the Unit 1 and 2 RCIC Turbine Electronic Overspeed Trips.

Modifications M01-1-91-009 and M01-2-91-009 removed the electronic overspeed trips. They are no longer serving their function and have been discarded.

UFSAR Chapter 6 - Engineered Safety Features Timing Clarification for the RHR Pump Minimum Flow Valves 1(2)E12-F064A/B/C. The RHR pump ndnimum flow valves are in the process of having their gearing ratios changed in order to increase the thrust delivered to the stems of these MOVs.

This is in response to Generic Letter 89-10.

This is being accomplished in accordance with P01-1-91-552, 553, and 554, and P01-2-91-512, 547, and 548. The GE design specificies a maximum stroke time of 8 seconds. The new gearing ratios cause the valves to stroke at approximately 9.2 seconds. The new stroke time is well within the UFSAR requirement of 23.4 seconds. The change to UFSAR is strictly a justification for exceeding the GE specification. There is no change to the facility as result of this change.

Correct the ECCS pumps NPSH requirements in response to an engineering review of the ECCS and RCIC pumps NPSH requirements (Chron #117854).

Modifications M01-0-88-003A and M01-0-88-003B replaced the A and B Systems 1-out-of-4 of the Control Room HVAC Intake Radiation Monitor Detector control logic with a redundant 2-out-of-4 logic. The revised logic provides for 6 combinations of 2-out-of-4 radiation detectors to activate the Control Room HVAC system emergency function. This reduces the susceptibility of the Control Room HVAC system to spurious radiation monitor trips and allows maintenance to be simultaneously performed on two detectors while meeting the requirements for Technical Specification system operability.

h G.

Summary of Changes to the Facility Which are Described in the Safety Analysis Report-(continued)

UFSAR Chapter 7 - Instrumentation and Control Systems Revision of Section 7.8.2.2.2.4 to reflect algorithm changes to SPDS s to average the four drywell temperature elements rather than using the present scheme that typically results in displaying the highest reading temperature element.

Minor Plant Change P01-1-91-519 replaced the flexible wedge gate valve of 1E51-F063 with a double disk gate valve, and removed the leakoff line.

Figure 7.3-3 (2 of 2) is being revised to delete reference to the leakoff line Table 7.7-6 was revised to change the Rod Block Monitor upscale (high) nominal and allowable trip setpoints to read "as defined by the Core Operating Limits Report".

l The UFSAR was updated to reflect the modifications to Division I and II Reactor Fuel Zone Reference Leg Reroutes in response to NRC Bulletin 93-03.

Modification M01-2-93-022 reroutes the reactor fuel zone level transmitter 2B21-N044A reference leg from condensing chamber 2B21-D004D to condensing l

chamber 2B21-D368.

Modification M01-2-93-023 reroutes the reactor fuel zone level transmitter 2B21-N044B reference leg from condensing chamber 2B21-D004B to condensing chamber 2B21-D367.

Low Reactor Water (L2) Division 1 & 2 RCIC Initiation Agastat EGPB relays 1B21A-K710AX/BX/CX/DX were replaced with Agastat ETR series time -

delay relays per Component Replacements92-052 and 92-053.

This time delay will prevent unwanted RCIC initiations due to pressure ringing caused by TSV/TCV fast closure scrane.

Section 7.2.2.4.7 was revised to add drawing M-100 Sheet 4 (Unit 1 control rod drive hydraulic piping P&ID) as a reference document.

A revision to UFSAR Tables 7.1-2 through 7.1-8 was performed to clarify that IEEE-344-1971 was an original design requirement, any new/ replacement components must be qualified to IEEE-344-1975.

A revision to Section 7.6.2.2.6, subsystem function of the Reactor Water Cleanup System Leak Detection, due to the revision of LOA-VR-01, while allows for the installation and removal of keys to bypass the isolation signal for reactor water cleanup.

A revision to UFSAR Section 7.3.4.3.11 to reflect the control room ventilation process radiation monitor upgrades, and LaSalle Parts Evaluation L-93-007-0041.

UFSAR Chapter 9 - Auxiliary Systems 1

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Modification M01-0-89-017B expanded the Public Address (PA) system from a 2-zone to a 5-zone system to provide communications between the south (new) service building, tho north (old) service building, and the new main warehouse.

Revision to UFSAR Section 3.3.5.2 and 9.3.5.3 to clarify the use of natural sodium pentaborate and enriched pentaborate (as it applies to the standby liquid control system), and the insertion of text inadvertently I

ommitted in a previous submittal.

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9 G.

Summary of Changes to the Facility Which are Described in the Safety Analysis Report-(continued)

UFSAR Chapter 9 - Auxiliary Systems (continued)

Update to Section 9.4.5.4.4 due to revision of LOA-VX-01, Switchgear Heat Removal Damper Failure, to state that recirculation dampers may be temporarily wired open to ensure a constant flow of supply air to a fan if a recirculation actuator fails.

Modification M01-1-91-012 removed the previous 1120 storage cells and replaced them with new, high density racks of 4029 storage locations in the unit 1 spent fuel pool.

These consist of 3982 cells for normally discharged fuel bundles, 4 storage spaces for control rod guide tubes / defective fuel containers, and 43 cells for control rods and other miscellaneous items.

Section 9.2.1.1.1 was revised to change the minimum cooling water flow requirement of the southeast cubicle area cooling coil from 240 gpm to 180 gpm.

An update was performed to UFSAR section 9.2.1 and Table 9.4-19 as a result of a review of the design basis flow rates for the VY area chillers and diesel generator coolers.

Modification M01-0-91-002 replaced the VHF main radio with a Motorola 900 MHz SMARTNET Trunking System. This system provides for the use of more channels, eliminating delayed or missed communications.

The UFSAR was revised due to Design Changes on the Reactor Building Overhead Crane per exempt changes93-929 and 93-932.

UFSAR Chapter 11 - Radioactive Waste Management Main Steam Line Radiation Monitor Recorders 1&2D18-R6 were both replaced with a Yokogawa Micro R 100, model 4156, by component replacements93-042 and 92-044, respectively.

Spent Fuel Pool Exhaust Vent Radiation Monitor Recorders 1&2D18-R606 were both replaced with a Yokogawa Micro R 100, model 4156, by component replacements93-043 and 92-045, respectivley.

Reactor Building Vent Radiation Monitor Recorders 1&2D18-R603 were both replaced with a Yokogawa Micro R 100, model 4156, by component replacements93-044 and 92-046, respectively.

The original Bailey models were obsolete, and repair / replacement parts were no longer available.

i Modification M01-0-88-044 installed crosstie piping, check valves and isolation valves between radwaste demineralizers lWE01D and 2WE01D to permit in-series processing of liquid radwaste through the demineralizers.

UFSAR Chapter 13 - Conduct of Operations Change Procedure Review Requirements to UFSAR Section 13.5, Plant Procedures, as a result of defining procedure review requirements per Technical Specification amendment 86 (Unit 1) and 70 (Unit 2).

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Summary of Changes to the Facility Which are Described in the Safety Analysis Report-(continued)

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UFSAR Chapter 15 - Accident Analysis An administrative change to the UFSAR to correct a typographical l

error, " Reference 1" in section 15.7.5.1 should read " Reference 5".

This l

error was not detected before UFSAR Revision 0 was issued.

UFSAR Volumes X and XI An administrative change to the UFSAR to reflect the annual revision of drawings contained in UFSAR Volumes X and XI. Drawing revisions due to component replacements, setpoint change requests, modifications or other design changes (since the Revision 9 update) which proposed a change to the facility as described in the UFSAR were previously evaluated.

UFSAR Chapter 1 - Introduction and General Description of Plant UFSAR Chapter 7 - Instrumentation and Control Systems UFSAR Chapter 15 - Accident Analysis Lowered the Unit 1 and Unit 2 RWM LPSP from 20% to 10% power and the LPAP from 30% to 25% power by replacing relays K2 and Kl,-respectively, on alarm card FS-1C34-K608. A revision to the station's Technical Specification was performed via Ammendment 88 for unit 1 and Ammendment 73 for unit 2.

l UFSAR Chapter 5 - Reactor Coolant System and Connected Systems UFSAR Chapter 6 - Engineered Safety Features UFSAR Chapter 10 - Steam and Power Coiversion System l

An administrative change to the UFSAR to revise sections 5.4.7.3.2,.

6.2.4.2.3, and 10.4.7.2, which were not revised in the Revision 9 update was performed. Modifications M01-1-86-072, M01-2-86-049, M01-1-87-095, and M01-2-87-082 (HPCS and RCIC buried piping mods) did not previously identify these sections as needing to be revised.

UFSAR Chapter 6 - Engineered Safety Features UFSAR Chapter 7 - Instrumentation and Con'.rol Systems Changes to the Division I, II, and III Condensing Chambers that installs new flow panels that will continuously backfill the chambers in response to NRC Bulletin 93-03. A revision to the station's Technical Specification was performed via Ammendment 76.

M01-2-93-024: 2B21-D004D and 2B21-D368 (Div I).

M01-2-93-025: 2B21-D004B and 2B21-D367 (Div II).

M01-2-93-026: 2B21-D004A and 2B21-D004C (Div III).

UFSAR Appendix G - Reactor Recirculation System Installation of Flexible Hoses on Unit 2 RR-FCV Lines per modification P01-2-91-523. Flexible hoses were installed between the existing hard piping and the RR-FCV actuator connections. The flexible hoses minimize vibrational stresses on the actuator connections.

This will help to minimize the possibility of fatigue-induced cracking of a hydraulic line, precluding the resulting forced outage which is required to permit repair of the associated leak.

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Summary of Changes to the Facility Which are Described in the Safety Analysis Report-(continued)

UFSAR Appendix H - Fire Hazards Analysis Administrative change to the UFSAR section H.3.5.1 to clarify structural steel fireproofing requirements.

Modification M01-2-90-013 removed the DG Fuel Oil Transfer Pump Discharge Solenoid valve 2D0014 due to its unreliable performance, and replaced it with a piping spool.

Preparations for Turbine Supervisory Instrumentation Ugrade per modification M01-1-89-003-A to reflect the installation of new TSI conduit and cables, and drilling of main turbine bearing caps.

Modification M01-1-90-012 replaced the 125VDC Division 3 battery charger, associated power cables and output breaker.

This improves l

performance and availability since replacement parts for the previous charger were no longer available.

The lE51-F063 Valve Motor Operator, Starter and Power Cables were replaced per modification M01-1-91-002B.

This increases the thrust provided to the valve stem to ensure that the valve will close under normal plant and blowdown conditions.

Correct ommission of last paragraph on page H.3-1 which occurred during Revision 9, April 1993 update.

Revision to Section H.4.2.46.2; change " Redundant reactor on LR/PR 1B21-R884B and suppression pool..." to " Redundant reactor indication on 1B21-R884B, suppression pool...",

for the sake of continuity.

Replacement of Operator and Associated Equipment on valve 2E51-F063 The SMB-1-25 Limitorque operator was replaced with a Limitorque SB-2-80 operator per modification M01-2-91-002B.

The associated power cables, conduit, and motor control center starter unit were upgraded.

Modification M01-2-90-012 removes the DG Fuel Oil Transfer Pump Discharge Solenoid Valve 2DOOO4 due to its unreliable performance.

It is replaced with a piping spool.

EC 93-953 This exempt change is to repair the 2B21-F010A check valve preventing the recurring local leak rate testing (LLRT) failures.

These LLRT failures are attributed to the seat ring and disc alignment.

Seat alignment is dependant primarily on two conditions; disc bushing / hinge pin clearances and the relationship between the body bores retaining the hinge pins to the disc bushing bores.

During previous valve repairs an additional counterweight to the disc was installed to compensate for the imbalance created during field machining. The replacement disc should not require the additional counterweight providing the disc's center of gravity is not altered upon installation. This will eliminate the secondary soft seat / hardware, disc bushing lock tabs and eccentric bushings providing i

satisfactory disc / seat ring alignment can be accomplished upon repair.

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Summary of Changes to the Facility Which are Described in the Safety Analysis Report-(continued)

EC 93-959 This exempt change permanently removed the lightning arresters on the unit one 4.16Kv and 6.9Kv bus ducts located near the System Auxiliary Transformer (SAT), off the low side windings.

In addition the associated vertical bus duct risers will be removed. The remaining T-connection on the horizontal section of the bus duct will be enclosed using existing parts. This will not impact the existing fire protection system.

This will not affect the operating mode of any equipment or affect any system function.

EC 93-961 l

l This exempt change permanently remove the lightning arresters on the unit two 4.16Kv and 6.9Kv bus ducts located near the System Auxiliary Transformer (SAT), off the low side windings.

In addition the associated vertical bus duct risers will be removed.

The remaining T-connection on the horizontal section of the bus duct will be enclosed using existing l

parts. This will not impact the existing fire protection system.

This will not af fect the operating mode of any equipment or affect any system function.

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Sumary of Safety Related Modifications M01-0-88-003-A This modification involved a revision to the existing one-out-of-four control logic for four radiation monitors (1D18-K751A, B,

C, D) on the outside air intake to the Control Room HVAC "A" Train System to a limited two-out-of-four control logic. The change was due ro the fact that the operating history of the Control Room HVAC Intake Radiation Monitoring System has shown to be susceptible to spurious trips. The Safety Evaluation concluded that there were no unreviewed safety questions.

There were no Technical Specification changes required.

However, changes to the FSAR/UFSAR section 6.4.4, page 6.4-6 required revision to be submitted.

M01-0-88-003-B This modification involved revision to the existing one-out-of-four control logic for four radiation monitors (2D18-K751A, B,

C, D) on the outside air intake to the control Room HVAC "B" Train System to a limited two-out-of-four control logic. The change was due to the fact that the operating history of the Control Room HVAC Intake Radiation Monitoring System has shown to be susceptible to spurious trips. The Safety Evaluation concluded that there were no unreviewed safety questions. There were no Technical Specification changes required.

However, changes to the PSAR/UPSAR section 6.4.4, page 6.4-6 required revision to be submitted.

M01-1-87-095 This modification involved the modification of the Reactor Core Isolation Cooling (RCIC) system so that it can be aligned to the suppression Pool in the event the RCIC suction and return lines to the condensate Storage Tank fall.

This included adding a water leg pump suction from the suppression pool, adding a full flow test return line to the suppression pool, removing the standpipe from the icYO1A line of the CY tank which reserves 135,000 gallons of water for RCIC and HPCS use, and adding a keylock switch and an alarm to the control circuit of Valve 1E51-F022. The new RCIC full flow test line was tied into the LPCS full flow test return line.

The Safety Evaluation concluded that there were no unreviewed safety questions.

Technical Specification changes to 3/4.3.5, 3/4.7.3, B3/4.7.3 and B3/4.5 associated with the RCIC modification are to add containment isolation provisions for the new full flow test return line to the suppression pool.

The UFSAR changes to Chapters ),

3, 5, 6, 7,

8, 9,

12, 13, and 15, also Appendix H, J, and L consist of revising descriptions and tables associated with the RCIC system.

M01-1-91-001-A M01-1-91-001-B These modifications involved the replacement of the motor operator on the Reactor Water Cleanup (RWCU) system 1G33-F001 and 1G33-F004 valves.

The purpose of this change is to increase the thrust available to close the valves under blowdown conditions.

This modification addresses concerns raised by NRC Generic Letter 89-010 and related documents. The new operators will be Limitorque SMD-0-15.

The increased current requirements of the new motors require that the thermal overload relay and circuit breaker be replaced for the new motor operator.

The Safety Evaluation concluded that there were no unreviewed safety questions. There were no Technical Specificaticn or FSAR/UFSAR changes required, i

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Sumary of Safety Related Modifications-(continued) i M01-1-91-002-A l

M01-1-91-002-B These modifications involved the replacement of the motor operator on the Reactor Core Isolation Cooling (RCIC) system 1E51-F008 and 1E51-F063 valves.

The purpose of this change is to increase the thrust available to close the valves under blowdown conditions. This modification addresses concerns raised by NRC Generic Letter 89-010 and related documents. The new operators will be Limitorque SMD-0-25.

The increased current requirements of the new motors require that the thermal overload relay and circuit breaker be replaced for the new motor operator.

The Safety Evaluation concluded that there were no unreviewed safety questions. There were no Technical Specification or FSAR/UFSAR changes required.

M01-1-91-009 This modification involved the removal of the Reactor Core Isolation Cooling (RCIC) Turbine Electronic overspeed monitor from the RCIC turbine control system.

General Electric has admitted of past problems with the electronic overspeed in SIL #382.

This has remove an unnecessary ground from the RCIC turbine system.

The Safety Evaluation concluded that there were no unreviewed safety questions. There were no Technical Specification changes required. The FSAR/UFSAR Chapter 5 will be revised to remove references to the electronic overspeed monitor.

M01-1-91-012 This modification involved the replacement the existing spent fuel racks with new high density spent fuel racks (HDSFRs). The existing design, supplied through the NSSS contract, permits storage of 1080 spent fuel assemblies.

The new racks will provide a total of 3986 spent fuel storage locations, including 4 defective fuel storage cells, and 43 specialty storage locations. This modification involved the design and l

fabrication of the new HDSFRs and miscellaneous storage racks, demolition of the existing racks and interferences inside the spent fuel pool, disposal of the removed racks and the installation of the new racks.

The Safety Evaluation concluded that there were no unreviewed safety questions.

The Technical Specifications required a revision to Section 5.6, Design Feature, Fuel Storage to reflect the new cell pitch dimension and number of fuel storage locations.

The FSAR/UFSAR Paragraph 9.1.2 and Table 3.2-1 required revision to update the description and classification of the spent fuel pool storage facility.

l M01-2-88-050 1

This modification involves the installation of two (2) fuses (in series) for the RHR Pressure Switches 2E12-NO32A/B and 2E12-N033A/B.

During the steam condensing mode of RHR, steam is rerouted from the reactor i

pressure vessel to the RHR heat exchanger via the RCIC system.

During this mode, RHR pressure switches assist in protecting the RHR heat exchanges from over pressurizes by providing a signal to close bypass valves.

If one of the pressure switches were to fail, it would have cause an electrical short to ground at one of the non-safety related components being supplied from the same DC bus.

This could have disable RHR control logic for essential equipment required during and/or after postulated design events.

The Safety Evaluation concluded that there were no unreviewed safety questions.

There were no UFSAR/FSAR or Technical Specification changes required.

H.

Sumary of Safety Related Modifications-(continued)

M01-2-88-053 M01-2-89-007 These modifications involved the upgrade of the existing 2A and 2B Diesel Generator Room Carbon Dioxide Systems from an unsupervised detection system to class "A" supervised detection systems.

This also provides protection of the DG CO2 system against fire / water damage in order to prevent a single fire in the DG Corridor from causing CO2 to be dumped in both the division 1 and division 2 DG rooms. The existing control panels were replaced with seismically qualified NEMA Type 4 CO2 control panels.

The alarms horns, pushbutton stations, and electrol manual pilot cabinets were also replaced. The conduits containing associated cables were fire wrapped so if damaged they would not spuriously initiate a CO2 discharge or adversely affect their respective DG ventilation system.

The Safety evaluation concluded that there were no unreviewed safety questions.

There were no UFSAR/FSAR or Technical Specification changes required.

l M01-2-90-001 This modification involved the upgrade of the 1/4 inch instrumentation tubing connected to the "2A" Diesel Generator.

This modification was initiated in response to the High Pressure Core Spray (HPCS) Safety System Functional Inspection (SSFI) held in 1989.

This modification upgrades any non-stainless steel 1/4 inch tubing and components to stainless steel.

In additions the removal and replacement of crankcase pressure turbine to the new pressure gage 2PI-DG122.

The Safety evaluation concluded that there were no unreviewed safety questions.

There were no Technical Specification changes required.

However, changes to the FSAR/UFSAR section 7.3.6.2 required update to include the crankcase pressure gauge to the list of local instrumentation.

M01-2-90-007 This modification involved increase the nominal clearance between the Control Rod Drive (CRD) housing supports and the lower surface of the CRD flange cap screws from approx. 1 to 1.5 inches.

This will facilitate undervessel maintenance for the removal and reinstallation of the CRD's during outage period.

This will also decrease the dose associated with this naintenance activity.

The Safety Evaluation concluded that there were no unreviewed safety questions. There were changes to the Technical Specification:

Reactivity Control systems, Section 3/4.1.3 Control Rods.

Changes to the UFSAR Section 4.6.1.2.3, 4.6.2.3.1.2.1, 4.6.2.3.1.2.4 and 4.6.2.3.3.1 were required to reflect this modification.

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Sumary of Safety Related Modifications-(continued)

M01-2-90-012 M01-2-90-013 These modifications involved the enhancement of operation for the diesel fuel system by eliminating the unreliable operation of the solenoid valves for the 2A and 2B Diesel Generator.

These valves have had a history of sticking open, requiring excessive maintenance activities, and resulting in down-time for the diesel generators.

In addition to the valve removal work, antisyphoning holes were drilled into the inlet piping inside the day tanks. The antisyphoning holes will replace the intended function of the valves. These holes will break the vacuum created inside the fuel transfer pipe during the fuel transfer operation. _This will eliminate the differential pressure across the Day Tanks and the Storage Tanks thereby preventing backflow from the Day Tanks to the Storage Tanks which was the purpose of the solenoid valves.

The Safety Evaluation concluded that there were no unreviewed safety questions. There were no Technical Specification changes required. However, changes to the UFSAR/FSAR Appendix H.4,

" Safe Shutdown Analysis" required update.

M01-2-91-004A i

M01-2-91-004B l

These modifications involved the replacement of the motor operator on l

the Reactor Water Cleanup (RWCU) system 2G33-F001 and 2G33-F004 valves.

The purpose of this change is to increase the thrust available to close the valves under blowdown conditions.

These modifications address the concerns raised by NRC Generic Letter 89-010 and related documents.

The new operators will be Limitorque SMD-0-15.

The increased' current requirements of the new motors require that the thermal overload relay and circuit breaker be replaced for the new motor operator.

The Safety Evaluation concluded that there were no unreviewed safety questions. There were no Technical Specification or FSAR/UFSAR changes required.

M01-2-91-008 This modification involved the addition of an intermediate /open (IO) contact to the closing circuit of the 2VQO37 and 2VQO38 motor operators.

The function of the additional contact is to de-energize the operator motor when the valve disc has rotated to its fully closed position.

circuit logic used the torque switch to control valve closure. The existing The logic requires the valve disc to torque into its seat, resulting in compression of the operators spring pack, which opens the torque switch, deenergizing the motor.

This modification has removed the mechanism for nuisance trips of the thermal overload.

The Safety Evaluation concluded that there were no unreviewed safety questions. There were no Technical Specification or FSAR/UFSAR changes required.

M01-2-91-009 This modification involved the removal of the Reactor Core Isolation Cooling (RCIC) Turbine Electronic overspeed monitor from the RCIC turbine control system.

General Electric has admitted of past problems with the electronic overspeed in SIL #382.

This has remove an unnecessary ground from the RCIC turbine system.

The Safety Evaluation concluded that there were no unreviewed safety questions. There were no Technical Specification changes required. The FSAR/UPSAR Chapter 5 will be revised to remove references to the electronic overspeed monitor.

O 4

H.

Sumary of Safety Related Modifications-(continued)

M01-2-93-006 i

This modification involved the replacement of the Residual Heat Removal (RH) System Low Pressure Coolant Injection (LPCI) valve 2E12-F042A motor i

operator. The existing operator was a Limitorque SMB-1-40, 40 foot pound, 3600 RPM motor and power feed from MCC 235Y-2 via a three conductor #14 AWG cable, the new operator motor is a 60 foot pound, 3600 RPM motor. The 4

overall actuator gear ratio was changed to 40.15:1. The gear ratio was replaced with motor pinion gear and worm shaft pinion gear set.

In order to increase the terminal voltage at the motor, the power cable was upgraded to a three conductor #6 AWG cable. The Safety Evaluation concluded that there were no unreviewed safety questions. There were no Technical Specification or FSAR/UFSAR changes required.

l MCl-2-90-046 i

This minor plant change involved installation of pressure switch test connection to eight (8) Nuclear Boiler System pressure switches:

2B21-NO39EE, DD, PP, KK and 2B21-N061DD, EE, PP, and KK.

The test connections will facilitate the testing and calibration of pressure switches.

The Safety evaluation concluded that there were no unreviewed safety, questions, j

There were no Technical Specification of FSAR/UFSAR changes required.

l MCl-2-90-047 This minor plant change involved installation of pressure switch test connection to four (4) Nuclear Boiler System pressure switches:

2B21-

N061K, P,

U, and 2B21-N60U.

The test connections will facilitate the a

testing and calibration of pressure switches.

The Safety evaluation concluded that there were no unreviewed safety questions.

There were no Technical Specification of FSAR/UFSAR changes required.

MC1-2-90-062 This minor plant change involved the installation of high temperature wires to replace deteriorated lead wires of the Containment Monitoring Suppression Pool Inlet Purge Isolation Valve, 2CM026B.

The damage field conductors were replaced with #14 AWG Rockbestos Radiation Besistant Firewall SR lead wires.

The spliced connection was insulated with Raychem WCSF-N-115 heat shrink tubing.

The Safety Evaluation concluded that there 3

were no unreviewed safety questions. There were no Technical Specification i

or UFSAR/FSAR changes required.

P01-1-90-029 This ndnor plant change installed a vent to the bonnet for the RHR suppression Pool Valve 1E12-F004B.

This included installation of two (2) manual gate valve (1E12-F428B and 1E12-F429B) to be installed and connecting pipe to the bonnet of valve 1E12-F004B and return to the process i

header, 1RH01AB. Addition of the vent line has relieved the hydraulic locking problems associated with this valve. The Safety Evaluation concluded that there were no unreviewed safety questions. There were no Technical Specification changes required.

However, changes to the UFSAR Table 6.2-21 were revised to add the 1E12-F428B Ive as a containment isolation valve.

i k

i d

d H.

sumary of safety Related Modifications-(continued)

P01-1-90-026 This minor plant change installed a vent to the bonnet for the RHR suppression Pool Valve 1E12-F004A. This included installation of two (2) manual gate valva (1E12-F428A and lE12-F429A) to be installed and connecting pipe to the bonnet of valve 1E12-F004A and return to the process header, 1RH01AA. Addition of the vent line has relieved the hydraulic locking problene associated with this valve.

The Safety Evaluation concluded that there were no unreviewed safety questions.

There were no Technical Specification changes required.

However, changes to the UFSAR Table 6.2-21 were revised to add the 1E12-F428A valve as a containment isolation valve.

P01-1-90-037 (Valve LINO 31).

P01-1-90-046 (Valve ICM023B)

P01-1-90-038 (Valve 1CM021B)

P01-1-90-050 (Valve 1CM017B)

P01-1-90-040 (Valve ICM028)

P01-1-90-051 (Valve ICM018A)

P01-1-90-041 (Valve ICM030)

P01-1-90-057 (Valve 1CM034)

P01-1-90-042 (Valve ICM029)

P01-1-90-058 (Valve ICM033)

P01-1-90-043 (Valve ICM032)

P01-1-90-059 (Valve ICM024A)

These minor plant changes involvnd the installation of high temperature wires to replace deteriorated lead wires of the containment Monitoring Suppression Pool Purge Isolation Valves. The damage field conductors were replaced with #14 AWG Rockbestos Radiation Resistant Firewall SR lead wires. The spliced connection was insulated with Raychem WCSF-N-115 heat shrink tubing.

The Safety Evaluation concluded that there were no unreviewed safety questions.

There were no Technical Specification or UFSAR/FSAR changes required.

P01-1-91-508 P01-1-91-512 4

These minor plant changes replace the existing 2-ft-lbf motor for the Reactor Building Closed Cooling Water (RBCCW) Inboard Isolation valves 2WR180 and 1WR040 with a 5-ft-lbf motor.

The thermal overload setting was reset. Additional actuator thrust is required to ensure the valve's reliability under design basis flow and differential pressure conditions.

This will increase the thrust that the actuator delivers to the valve stem.

The Safety evaluation concluded that there were no unreviewed safety questions.

There were no Technical Specification of FSAR/UFSAR changes required.

P01-1-91-514 This minor plant change reroute the conduit for the RPS cable 1RP034 which interferes with the opening of the hinged cover on the Main Turbine control Valve #1's limit switch enclosure. This reroutes the rigid conduit and sealtitle for the affected cable so that the enclosure's cover can be opened.

This also included installation of a new junction box and installation of conduit and cable between the new and existing junction boxes.

Changes to the existing supports and removal of supports was also required.

The Safety evaluation concluded that there were no unreviewed safety questions.

There were no Technical Specification of FSAR/UPSAR changes required.

i H.

Sumary of Safety Related Modifications-(continued)

P01-1-91-519 This minor plant chenoa replaces the Reactor Core Isolation Cooling (RCIC) lE51-F063 valve. The new valve body and internals will be a double disk gate valve, replacing the existing flexible wedge gate valve. The new valve does not require a leakoff line, thus cutting and capping the leakoff line. The safety evaluation concluded that there were no unreviewed safety questions. There were no Technical Specification changes required.

4 However, Figure 7.3-7 sheet 2 and Section 5.2.5.2.j of the FSAR/UFSAR have been revised to indicate that valve 1E51-F063 no longer has a leakoff line.

1 j

P01-1-91-521 j

This minor plant change replaces the motor operator on the Reactor Water Cleanup (RWCU) System Return to Feedwater System Throttle Valve 1G31-F042. The existing operator SMB-000-5 has been replaced with a Limitorque j

SMB-00-10 operator.

The circuit breaker required resetting due to the increased current requirements of the larger motor. The thermol overload

{

relay was also replaced. The Safety evaluation concluded that there were I

no unreviewed safety questions. There were no Technical Specification of FSAR/UPSAR changes required.

P01-1-91-540 This minor plant change replace the Pacific Scientific snubber for support M09-RI24-1122S with a Lisega hydraulic snubber.

The existing snubber had a significant maintenance problems due to intense heat and other causes.

Support M09-RI24-1122S is located on line 1RI24B-6".

The Safety evaluation concluded that there were no unreviewed safety questions.

There were no Technical Specification of FSAR/UFSAR changes required.

P01-1-92-515 (HPCS Diesel Cooling Water Pump Room Ventilation Fan 1VD07C)

P01-1-92-516 (HPCS Cubicle Cooler Fan 1VD02C)

P01-1-92-517 (HPCS Diesel Generator (DG) 1B Room Ventilation Fan 1VD01C)

P01-1-92-518 (HPCS Diesel Cooling Water Pump lE22-C002)

P01-1-92-520 (Control Room HVAC Emergency Make-up Air Filter Heater OVC01AA)

P01-1-92-521 (Control Room HVAC Emetgency Make-up Air Filter Fan OVC03CA)

P01-1-92-522 (Control Room HVAC Return Fan OVC02A)

These minor plant changes installed an interposing relay between the contractor coil and control circuit and changed the power source for the contractor coil from 120VAC to 480VAC.

This will eliminate the large voltage drop across the control transformer and cables for the contactor coil and will assure that the contactor and the auxiliary relay will have adequate voltage to function properly at the degraded voltage setpoint.

The Safety evaluation concluded that there were no unreviewed safety questions. There were no Technical Specification of FSAR/UFSAR changes required.

o I

i H.

Sumary of Safety Related Modifications-(continued)

I P01-2-91-508 j

This minor plant change replaces the Reactor Core Isolation Cooling (RCIC) 2E51-F008 valve.

The new valve body and internals will be a double disk gate valve, replacing the existing flexible wedge gate valve.

The function of the valve is to provide containment isolation in the unlikely event that the RCIC steam supply line might break or rupture.

This is in responses to NRC Generic Letter 89-10.

The safety evaluation concluded 1

that there were no unreviewed safety questions.

There were no FSAR/UFSAR or Technical Specification changes required.

P01-2-91-523 This minor plant change installed flexible hoses on the Reactor Recirculation Flow Control Valve (RR-FCV) hydraulic lines.

Each RR-FCV actuator is connected to four hydraulic lines that were hard piped up to the connections on the actuator. Vibration of the RR-FCV has caused fatigue-induced cracking of a hydraulic line.

This has caused unit shutdown for repair in the past.

The new flexible hoses will minimize the vibrational stresses on the actuator connections.

New guide supports were installed to support the free end of the hard piping.

The safety evaluation concluded that there were no unreviewed safety questions.

There were no Technical Specification changes required.

However, Appendix G, Section G.3.3.3.6.2.4 of the UFSAR/FSAR required changes.

P01-2-91-534 This minor plent change replaced the Pacific Scientific snubber for support M09-RI24-2803S with a Lisega hydraulic snubber.

The existing snubber had a significant maintenance problems due to intense heat and other causes.

Support M09-RI24-2803S is located on line 2RI24B-6".

The Safety evaluation concluded that there were no unreviewed safety questions.

There were no Technical Specification of FSAR/UFSAR changes required.

P01-2-91-535 This minor plant change replace the Pacific Scientific anubber for support M09-RI24-2807S with Lisega hydraulic snubbers.

The existing snubber had a significant maintenance problems due to intense heat and other causes.

Support M09-RI24-2807S is located on line 2RI24B-6".

The Safety evaluation concluded that there were no unreviewed safety questions.

There were no Technical Specification of PSAR/UPSAR changes required.

P01-2-91-540 This minor plant change replaced the existing 5-ft-lbf motor for the Reactor Core Isolation Supply System Full Flow Test Downstream Stop 2E51-F059 with a 7.5-ft-lbf motor.

The thermal overload setting was reset.

Additional actuator thrust is required to ensure the valve's reliability under design basis flow and differential pressure conditions.

This will increase the thrust that the actuator delivers to the valve stem.

The Safety evaluation concluded that there were no unreviewed safety questions.

There were no Technical Specification of FSAR/UPSAR changes required.

t I

H.

Sumary of Safety Related Modifications-(continued)

P01-2-91-545 P01-2-91-546 These minor plant changes replace the existing 2-ft-lbf motor for the

{

RHR Supply from Fuel Pool Emergency Makeup Downstream Stop valves 2E12-F093 and 2E12-F094 with a 5-ft-lbf motor.

The thermal overload setting was i

reset.

Additional actuator thrust is required to ensure the valve's reliability under design basis flow and differential pressure conditions.

This will increase the thrust that the actuator delivers to the valve stem.

The Safety evaluation concluded that there were no unreviewed safety questions.

There were no Technical Specification of FSAR/UFSAR changes i

required.

P01-2-91-547 P01-2-91-548 These minor plant changes replace the Limitorque gearing overall ratio 4

(OAR) to 82.0 and change the spring pack to model 0301-111 on the 2B RHR l

Pump Min. Flow Valves 2E12-F064B and 2E12-F064C.

This change will increase the thrust that the actuator delivers to the valve stem by replacing the motor pinion gear and the worm abaft gear to increase the operator's overall gear ratio.

This replacement does not alter the actuator weight.

The Safety Evaluation concluded that there were no unreviewed safety questions. There were no Technical Specification of FSAR/UPSAR changes required.

4 P01-2-91-550 This minor plant change replaces the existing 2-ft-lbf motor for the RHR Blowdown To RBEDT Upstream Isolation valve 2E12-F049A with a 5-ft-lbf motor. The thermal overload setting was reset.

Additional actuator thrust is required to ensure the valve's reliability under design basis flow and differential pressure conditions.

This will increase the thrust that the actuator delivers to the valve stem.

The Safety evaluation concluded that d

there were no unreviewed safety questions.

There were no Technical Specification of FSAR/UFSAR changes required.

j P01-2-91-553 l

l This minor plant change involves the addition of a set of piping flanges in the RCIC Head Spray Piping Line (2RI24B) just upsteam of the N-7 RCIC head Spray nozzle on the Reactor Pressure Vessel. The installation is intended to ease the process of RPV disassemble and reassembly for the refueling purposes by alleviating the need to withdraw the " snout" portion of the existing spray nozzle from the RPV during removal of the Head Spray piping.

The existing configuration has resulted in extended reassemble times and unnecessary dose.

It has also introduced the possibility of damaging both the vessel nozzle and the snout due to the difficulties involved in the making up the vessel to snout flange connection.

The Safety evaluation concluded that there were no unreviewed safety questions.

There were no Technical Specification of FSAR/UFSAR changes required.

ie H.

Sumary of Safety Related Modifications-(continued)

P01-2-92-511 This minor plant change installed an undervoltage relay in the ESF Division I degraded voltage protection circuit for 2427-AP270A and B.

The existing relays are ABB ITE-27D undervoltage relays, the replacement are ABB 1TE-27N undervoltage relay. The main function of these undervoltage relays is to monitor the voltage on the Division 1 4KV bus and initiate an

)

automatic transfer from off-site power to the associated diesel generator when a degraded voltage condition is detected.

The Safety evaluation concluded that there were no unreviewed safety questions.

There were no Technical Specification of FSAR/UPSAR changes required.

P01-2-92-512 l

This minor plant change installed an undervoltage relay in the ESF j

Division II degraded voltage protection circuit for 2427-AP271A and B.

The existing relays are ABB ITE-27D undervoltage relays, the replacement are ABB ITE-27N undervoltage relay.

The main function of these undervoltage relays is to monitor the voltage on the Division II 4KV bus and initiate an automatic transfer from off-site power to the associated diesel generator when a degraded voltage condition is detected.

The Safety evaluation concluded that there were no unreviewed safety questions.

There were no Technical Specification of FSAR/UFSAR changes required.

P01-2-92-513 This minor plant change installed an undervoltage relay in the ESP Division III degraded voltage protection circuit for 2427-AP272A and L.

The existing relays are ABB ITE-27D undervoltage relays, the replacenent are ABB 1TE-27N undervoltage relay. The main function of these undervoltage relays is to monitor the voltage on the Division III 4K7 bus and initiate an automatic transfer from off-site power to the associated diesel generator when a degraded voltage condition is detected.

The Safety evaluation concluded that there were no unreviewed safety questions.

There were no Technical Specification of FSAR/UFSAR changes required.

I P01-2-92-516 (HPCS Cubicle Cooler Fan 2VYO2C)

P01-2-92-517 (HPCS Diesel Generator 1B Room Ventilation Fan lVD01C)

P01-2-92-518 (HPCS Diesel Cooling Water Pump 2E22-C002)

P01-2-92-519 (RHR Suction Cooling Inboard Isolation Valve 2E12-F009) l l

P01-2-92-520 (Control Room HVAC Emergency Make-Up Air Filter Heater OVC01AB)

P01-2-92-515 (HPCS Diesel Cooling Water Pump Room Ventilation Fan 2VD07C)

P01-2-92-522 (Control Room HVAC Return Fan OVC02B)

These minor plant changes installed an interposing relay between the contractor coil and control circuit and changed the power source for the contractor coil from 120VAC to 480VAC. This will eliminate the large voltage drop across the control transformer and cables for the contactor coil and will assure that the contactor and the auxiliary relay will have adequate voltage to function properly at the degraded voltage setpoint.

The Safety evaluation concluded that there were no unreviewed safety questions.

There were no Technical Specification of FSAR/UFSAR changes required.

l l

l

j H.

Sumary of Safety Related Modifications-(continued)

P01-2-93-503 P01-2-93-504 These minor plant changes replaced the existing 15-ft-lbf motor for the RHR Drywell Spray Stop Valve 2E12-F017B and the RHR Heat Exchanger Service Water Outlet Stop 2E12-F068A with a 25-ft-lbf motor.

The thermal overload setting was reset. Additional actuator thrust is required to ensure the valve's reliability under design basis flow and differential pressure conditions. This will increase the thrust that the actuator delivers to the valve stem.

The Safety evaluation concluded that there were no unreviewed safety questions.

There were no Technical Specification of FSAR/UFSAR changes required.

P01-2-93-505 This minor plant change replace the Limitorque gearing overall ratio (OAR) to 140.80-1 and change the spring pack to model 0301-111 on the 2A RHR Pump Shutdown Cooling Suction Stop Valve 2E12-F006A.

This change will increase the thrust that the actuator delivers to the valve stem by replacing the motor pinion gear and the worm shaft gear to increase the operator's overall gear ratio. This replacement does not alter the actuator weight.

The Safety Evaluation concluded that there were no unreviewed safety questions.

There were no Technical Specification of FSAR/UFSAR changes required.

ECR 92-904A ECR 92-904B These exempt change requests installed a program module (SFA-703) into position "HA" on panels 1FPO4JA and 2FP04JA to split lamp load during lamp test.

The Safety Evaluation concluded that there were no unreviewed safety questions.

There were no Technical Specification of FSAR/UFSAR changes i

required.

ECR 92-916 This exempt change request rewired the digital point 2497 from rotor 3 contact to 10-10C rotor contact on the RCIC Pump Full Flow Test Return Valve 2E12-F059 to allow closed and open torque switch bypass to be set properly and still provide good control room indication. The Safety Evaluation concluded that there were no unreviewed safety questions.

There were no Technical Specification of FSAR/UFSAR changes required.

ECR 93-004 This exempt change request drilled an 1/8" hole in the upstream disc of the RCIC Steamline Inboard Isolation Valve 1E51-F063 to eliminate pressure locking on the valve.

The Safety Evaluation concluded that there were no unreviewed safety questions. There were no Tachnical Specification of FSAR/UFSAR changes required.

H.

Sumary of Safety Related Modifications-(continued)

ECR 93-983A ECR 93-983B These exempt change requests replaced the existing 3/C #14 motor operator power cables for the "B" LPCI Injection Valve 2E12-F042B and the l

"C" LPCI Injection Valve 2E12-F042C with 3/C #6 power cable. The existing conduit required upgrading and a new junction box near the operator for termination was installed. The Safety Evaluation concluded that there were l

no unreviewed safety questions. There were no Technical Specification of FSAR/UFSAR changes required.

a CR 90-117 (Valve 1B21-F067B)

CR 90-118 (Valve 1B21-F067C)

CR 90-119 (Valve 1B21-F067D)

CR 90-120 (Valve 1B21-F067A)

These component replacements involve the replacement of the existing Anderson-Greenwood bellows sealed globe valve on the Main Steam Drain Valves with an Anchor / Darling double disk gate valve. The existing motor operator were not replaced.

The purpose of this replacement is to install valves that are better able to meet through-seat leakage limits while i

requiring less maintenance than the existing valves.

The Safety evaluation concluded that were no unreviewed safety questions.

There were no Technical Specification changes required.

However, UFSAR Table 6.2-21 was revised to indicate the change in valve type (from globe to gate).

The table also reflects the Technical Specification stroke time limit of 23 seconds, rather than " standard" stem speed.

SPCR 91-005 SPCR 91-006 4

These setpoint changes involved lowering the alarm setpoint for the drywell temperature recorders 1TR-CM037B/38B and 2TR-CM037B/38B to 125 deg.F.

The Safety evaluation concluded that were no unreviewed safety questions.

l SPCR 92-009 This setpoint change involved increasing the setpoint on the 1B Diesel Generator low lube oil temperature alarm lE22-N512 to 90 degF.

The Safety evaluation concluded that were no unreviewed safety questions.

SPCR 92-067 This setpoint change involved increasing the magnetic setting of MCC 135Y-2, Compt G4, for MOV lE32-F003V from 7.5 to 11 and the overload setting from 0.11 to 0.9.

The Safety evaluation concluded that were no unreviewed safety questions.

SPCR 92-069 This setpoint change involved increasing the setpoint for the 1A RHR Pump Room Cooler Fan IVY 0lc from 260 amps to 400 amps.

The Safety evaluation concluded that were no unreviewed safety questions.

H.

Sumary of Safety Related Modifications-(continued)

SPCR 92-070 This setpoint change involved increasing the thermal overload setpoint for the RCIC Steam Supply Inlet Isolation 1E51-F076 Valve from 0.45 to 0.50.

The safety evaluation concluded that were no unreviewed safety questions.

SPCR 92-071 This setpoint change involved increasing the thermal overload setpoint for the Hydrogen Recombiner Suction For Drywell Outboard Isolation Valve 1HG002A from 0.50 to 0.65.

The Safety evaluation concluded that were no unreviewed safety questions.

I.

Summary of ECCS Outages This information has been reported monthly in LaSalle's NRC Monthly Reports (Section II.F.2) dated January 1993 through December 1993.

J.

Survey of Evaluation Results of Chlorine Shipments by Barge one the Illinois River.

Not required for 1993, the survey was last completed in 1991.

K.

Summary of Events Violating Technical Specification 3. 4.5 - Primary Coolant Iodine Spiking Exceeding Allowable Limits.

During this reporting peri od, January 1, 1993 through December 31, 1993, there were no violations of Technical Specification 3.4.5, Primary Coolant Iodine Spikes Exceeding Allowable Limits.

l ATTACHMENT A SAFETY-RELATED MAINTENAN:E COMPLETED (NON-0UTAGE RE8 ATED)

UNIT =0

- -- ------ -- - - ~- ------- ~ ~

~ - " "

WRNUM SYSTEM EPN

.DESC LO6198 DC ODC02E RELAY HOUSE BATTERY LOW SPECIFIC GRAVITY AND LOW ICV LO7091 VC OPL15J VC PANEL SOUTH DOOR HANDLE BROKEN L08293 AP OAP09E RSH SWGR INSTALL MIS $1NG A & C OVERCURRENT RELAYS LO8649 vc OPOS VC011 VC SUPPLY FLOW SET TOO HIGH j

L11131-DC 00C01E SYS I BATTERY REMOVE CORROSION FROM CELL TERMINALS

.l l

L13138 RD 1/2C11-D002A/B FABRICATE ROD EXTENSION TO CRD SUCTION FILTER L15384 VC OVC03M8 VALVE DID NOT CYCLE PER SPECIAL TEST L15559 VC OvC03CB INSTALL EMERGENCY MAKEUP FAN INTERPOSING RELAY-L15571

.vc OVC03CA INSTALL EMERGENCY MAKEUP FAN INTERPOSING RELAY L15637 NR ONR000 LPRM CARD INSTALL 3 TRANSISTORS, REPLACE AN IC CHIP L16081 VC OVCO2SB CLEAN HUMIDIFIER DRA1H TRAPS AND P!P!NG L17179 DC

'ODC01E CLEAN RELAY HOUSE SYSTEM 1 BATTERY CHARCER L17356 VC 0FSY-VC044X REPLACE BROKEN RELAY L17927 VC 0FSY VC043X REPLACE BROKEN RELAY l

L17928 VC OFSY VC045X REPLACE BROKEN RELAY I

L17972 DG ODG09K DIESEL GENERATOR RADIATOR FINS ARE PLUGGED L18052 VC OvC05CB 0:L LEAK AROUND OIL FILTER L18153 DC ODG09K TSC DIESEL BATTERY CHARGER FLOAT VOLTAGE HIGH i

L18527 DC 00C20E CELL #47 TSC 125 VDC BATTERY LOW L19038 DG ODG02JB-0 DG LOCK-0UT RELAY FAILED INSPECTION L19236 DC ODC20E REMOVE TSC 125 VDC BATTERY CORROSION L19260 DG ODC08CA INSPECT AIR COMPRESSOR SUCTION AND DISCHARGE VALVE L19261 DG 00008CB INSPECT AIR COMPRESSOR SUCTION AND DISCHARGE VALVE L19432 DG OTS-DG040 REPLACE IMMERSION HEATER OIL TEMPERATURE SWITCH L19625 VC OVC03YB REPAIR LIMIT SWITCH MOUNTING BOLT L19727 DC ODC18E BATTERY CELLS #7 AND #45 OUT OF SPECIFICATION

{

L19801 VC OXY-VC165A AMMONIA DETECTOR ALARMING L19987 DG ODG01K TIGHTEN PACKING NUT ON #3 CYLINDER TEST VALVE L20088 VC OTZ-VC005 ACTUATOR DAMPER O!L LEAK L20216 VC OVCO2AA REPLACE HVAC A SUPPLY C0ll DOOR GASKET L20217 VC OVCO2AB REPLACE HVAC B SUPPLY C0ll DOOR GASKET L20371 DC DDC18E RSH BATTERY CHARGER VOLTAGE ERRATIC L20801 DG ODG08CB CHECK AIR COMPRESSOR SUCTION DISCHARGE VALVE L20802 DG ODG08CA CHECK AIR COMPRESSOR SUCTION DISCHARGE VALVE L20950 DG ODG01K INSPECT SYNCROSCOPE 0 DEGREE PHASE ANGLE L21485 vc OXY-VC165B CONTROL ROOM HVAC AMMONIA DETECTOR FLOW LIGHT OUT L21698 vc OTZ-VC004 DVC22YA DAMPER ACTUATOR STROKES 1-1/2 L21706 vc OTZ VC003 OVC19YA DAMPER ACTUATOR OIL LEAK AT PLATE L22005 VC OXY VC165B AMMONIA DETECTOR MASTER FAULT, FLOW LIGHT INOPERABLE L22102 DG OLIS-D0008 DIESEL FIRE PUMP DAY TANK LEVEL INDICATOR ERRATIC L22187 vc OVC05CA CONTROL ROOM HVAC DAMPER O!L LEAKS L22251 VC OVC05CB DAMPER OIL LEAK L22532 VC OFR-VCO28 REPAIR EMERGENCY MAKEUP FLOW RECORDER L22700 VC 0XY-VC125B AMMONIA DETECTOR FLOW LIGHT UP L22737 NR OC51 000 IRM/SRM VOLTAGE PREREGULATOR LOW VOLTAGE L22858 VC 0XY-VC125A CONTROL ROOM HVAC AMMONIA DETECTOR CORRODED L22879 VC OXY-VC165A REPAIR IMMONIA DETECTOR FLOW LIGHT

ATTACHMENT A SAFETY RELATED MAINTENANCE COMPLETED (NON-0UTAGE RELATED)

.............................................................. unggao...........................................................

(continued)

WRNUM SYSTEM EPN DESC L22903 VC OVC05CA HVAC RECYCLE TIMER INOPERABLE L22981 VC 0xY-VC1658 REPAIR AMMONIA DETECTOR FLOW LAMP L23489 VC OXY-VC165B HVAC AMMONIA DETECTOR IN ALARM L23740 DG DDG01P INSPECT COOLING WATER PUMP BEARlWG COVERS L23762 AP OAP49E-E1 CIRCUIT BREAKER TRIPS L23763 DC DDC20E CLEAN TSC 125V BATTERY TERMINALS L23983 DG ODG08CA INSPECT AIR COMPRESSOR SUCTION DISCHARGE VALVE L23984 DG ODG08CB INSPECT AIR COMPRESSOR SUCTION DISCHARGE VALVE L24117 DG ODG01P COOLING WATER POMP TRIPPED ON START UP L25081 DG DDG09K TSC UIESEL GENERATOR WILL NOT START L25130 DG ODG034B REPLACE AIR START VALVE GASKET L25228 RD CC11-0301-REPLACE NITROGEN CHARGING HEADER DISC L25637 VG RR D018 R519 MID/HIGH RANGE ERRATIC

.............................................................. ungi,1...........................................................

WRNUM SYSTEM EPN DESC LO8631 DC 1DC000 PERFORM 24/48V BATTERY ICV'S LO9702 RD 1RD000 REACTOR MANUAL CONTROL WILL NOT RUN IN AUTO L10786 RH 11SDR008 DOOR #8 LOOSE ON CENTER PlVOT ROD L10820 DG TI-1E22 R527 REPAIR JACKET WATER DU1LET TEMPERATURE SENSING LINE L10821 DG 1E22-S001 INSTALL IMMERSON HEATER SUPPORT L12710 RD TR-1C11 R018 REPLACE CRD/RX VESSEL TEMPERATURE WlRING TO RECORDER L13071 HP FS-1E22-N006 REPLACE MIN FLOW BYPASS SWITCH L13882 NB 1821-F539 THERMAL OVERLOAD FAILED TO TRIP L15034 RI 1E51 F360 INSPECT COVENOR VALVE L15565 DG 1VD07C REPLACE 120 VAC CONTROL COIL WITH 480 VAC L16769 NR RY-1C51-J600J TIP DRIVE DRAWER INOPERABLE L17900 AP 1AP01E CUBICLE 8 BREAKER CLOSED INDICATION LIGHT BROKEN L17973 AP 1AP65E CUBICLE B3 RIGHT LOCKING TAB BROKEN L18039 NR XY-1C51-J600-5A REPLACE TIP DRAWERS LIGHT BULBS FOR CORE L18258 Dr 1VD000 REPLACE JUNC BOX'S IJB945/999/1000/1001A COVER SCREWS L18421 DC 1DC06E COMPARTMENT 3C TERM BLOCK DIVIDER CRACKED L18579 DG 1DG08CB INSPECT AIR COMPRESSOR SUCTION DISCHARGE VALVE L18580 DG 1DG08CA INSPECT AIR COMPRESSOR SUCTION DISCHARGE VALVE L19355 RH 1AP60E REPLACE BREAKER HANDLE L19390 RI 1HT01J FREEZE PROTECTION PANEL ALARM UP L19595 DG 1E22 S001 REPLACE GENERATOR PERM MAGNET LEADS CONDUlf L19675 DG 1E22 F379A A!R START STOP VALVE LEAKING L19676 DG 1E22-F379B AIR START STOP VALVE LEAKING L19815 DG 1DG08CB AIR LEAK ON TOP OF AIR COMPRESSOR L19850 AP 1AP000 277/480 VAC TRIPS FEED BREAKER L20167 DC 1DC000 250 VDC GRD DETECTOR CHART RECORDER PEN NOT WORKING L20195 MS ZS-1821-CV4 REPLACE MAIN TURBINE CONTROL VALVE LIMIT SWITCH I

L20223 AP 1AP000 REPAIR MCC 132B-1 COMPARTMENT D4 000R l

l I

l

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ATTACHMENT A SAFETY-RELATED MAINTENANCE COMPLETED (NON-0UTAGE RELATED)

.............................................................. UN1T=1 - - ------ *-----~~------- ------ - ---- ---~--==-~ --- -----

(continued)

WRNUM SYSTEM EPN DESC L20367 RM 1E12-F047A HEAT EXCHANGER INLET VALVE COMPUTER PT D609 ALARMING i

L20378 VG 1FS VG009 REPLACE SBGT SYSTEM FLOW ALUMINUM CAP L20398 RH CE-1E12-N001A SEALTITE BROKE AT FITTING L20400 RH 1E12-F074A GROUND STRAP WAS FOUND OFF L20409 NR RY-1C51 K601A 1A IRM NOT RESPONDING L20479 NR RR 1C51-R603A 1RM A/APRM A RECORDER SELECTOR SWITCH NOISY L20480 RI 1E51-C004 BAROMETRIC CONDENSER PUMP DISCHARGE CHECK VALVE STUCK L20633 RI 1E51-C004 BAROMETRIC CONDENSER PUMP MOTOR FAILED l

L20799 DG 10G08CB INSPECT AIR COMPRESSOR SUCTION DISCHARGE VALVE L20800 DG 1DG08CA INSPECT AIR COMPRESSOR SUCTION DISCHARGE VALVE L20953 DG 1E22 5001 INSPECT SYNCROSCOPE O DEGREE PHASE ANGLE j

L20955 DG 1DG01K INSPECT SYNCROSCOPE 0 DEGREE PHASE ANGLE

[

L20956 DG 1E22-5001 INSPECT SYNCROSCOPE D DEGREE PHASE ANGLE L20960 RD 1C11 D001-117 SCRAM PILOT VALVES INOPERABLE L21001 RD 1C11-D001-117 SCRAM PILOT VALVES INOPERABLE l

L21005 NR 1C51-000 CALIBRATE LPRM COMPUTER POINTS FOR APRM A-F L21014 RD 1C11-D001-026 HY')RAULIC CONTROL UNIT 26-39 N2 LEAK L21015 DG 1DG000 ENGINE TRIP POINT ALARM UP L21016 HP 1HP000 4KV BUS 143 BREAKER AUTO TRIPPED L21131 MS PDI-1821 R901 MSR STEAM CONTROLLER AIR LEAK L21220 RI 1R152AB FLANGE BLOWING STEAM AT LOCAL CONTROL PANEL l

L21570 NR RY-1CS1-J600J B TIP DRAWER CHANNEL SELECTOR SWITCH INOPERABLE I

L21707 RY-1C51-K600H IRM H EXCESSIVE NOISE, UNABLE TO ADJUST L21716 AP 1AP76E REPLACE MOTOR CONTROL CENTER 135Y 2 E 6 HANDLE L21938 DG IVD018Y PUMP ROOM SUPPLY FAN DAMPER INOPERABLE l

L22006 VY 11L-VY004 INSPECT INDICATING LIGHT WIRING L22007 VY llL-VYOO1 INSPECT INDICATING LIGHT WIRING L22091 NB UR 1821-R613 JET PUMP FLOW INDICATION LOW l

L22092 RP ZS-1E21 F028C MAIN STEAM 150 VALVE LIMIT SWITCH INOPERABLE L22098 LC 1E32-C001 EXHAUST BLOWER TRIPPED MAGNETICS L22119 DG 1DG08CB STARTING AIR COMPRESSOR MAKING LOUD NOISE L22132 HG 1HG002A SUCTION ISOLATION VALVE FAILS TO SHOW FULL OPEN L22155 HG 1HG002A SUCTION ISOLATION VALVE STEM TURNS j

l L22241 MS FT 1B21-N541 FLOW INSTRUMENT LOOP INPUT INOPERABLE L22290 RI 1E51 C003 WATER LEG PUMP OIL SEAL LEAKING L22351 RD 1C11-D001-068 REPA!R HYDRAULIC CONTROL UNIT 10-19 SHORT L22374 RD 1C11-C0018 INSTALL CRD FEED PUMP BREAKER BANANA PLUG L22423 DG 1TI-DG064A COOLING WATER TEMPERATURE INDICATOR INOPERABLE L22429 DG 1DG049A INSPECT STARTING AIR COMPRESSOR CHECK VALVE L22430 DG 1DG049B INSPECT STARTING AIR COMPRESSOR CHECK VALVE L22431 DG 1DG13MA INSPECT STARTING AIR COMPRESSOR MOISTURE SEPERATOR L22432 DG 1DG13MS INSPECT STARTING AIR COMPRESSOR MOISTURE SEPERATOR L22433 DG 1DG14MA INSPECT STARTING AIR COMPRESSOR TRAP L22434 DG 1DG14MB INSPECT STARTING AIR COMPRESSOR TRAP L22467 LP 1E21 C002 WATER LEG PUMP MOTOR INTAKE CLOGGED l

l

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4 l

l 3

1 4

ATTACHMENT A SAFETY RELATED MAINTENANCE COMPLETED 1

(NON 0UTAGE RELATED) i l............................................................... UNIT.1...........................................................

(continued)

WRNUM SYSTEM EPN DESC 1

4 L22474 PC 1PC000 CRD REMOVAL HATCH DRIVE ASSEMBLY COVER HAkDLE BROKE L22478 VY 1 TIC-VYO22 REPAIR LPCS PUMP CUBICLE ROOM TEMPERATURE INDICATOR L22545 VY 1TI VYO22 REPAIR LPCS AREA VENT TEMPERATURE INDICATOR L22552 MS TR-1821 RB16 TEMPERATURE RECORDER STICKING L22583 NR 1C51-000 REPA!R APRM POWER SUPPLIES DURING SURVEILLANCE TEST L22628 NR RY 1C51 K601A

!RM 'A' READING 50 IN ALL RANGES -

L22634 HP 1E22 F3618 REllEF VALVE INOPERABLE L22635 HP 1E22 F362B AIR START ISOLATION CHECK VALVE INOPERABLE L22695 RH 1E12 F024B FULL FLOW TEST VALVE FAILED TO CLOSE L22710 NR RY 1C51 K600BA.

B SRM MONITOR READS LOW L22735 RD 1RD000 REPAIR RMCS L22769 LC FS-1E32-N653J FLOW SWITCH FAILED TO ALARM.

L22770 RD XY 1C11*K915L-RMCS DATA FAULT L22780 DG 1AP80E A4 REPLACE 136X2-A4 DG1 A AIR COMPRESSOR BREAKER HANDLE L22869 NB 1FWOOO CALIBRATE CHANNEL A/B LEVEL 8 RELAYS L22870 NB 1FW000 CALIBRATE CHANNEL C LEVEL 8 TRIP LOGIC RELAYS L22880 NB TR-1B21 R816 ERRATIC TEMPERATURE RECORDER INDICATION L22884 NB LR 1821 RS84A REACTOR PRESSURE LEVEL RECORDER GEARS GOING BAD L22945 RH Cl 1E12 NO30A REMOTE SHUTDOWN HEAT EXCHANGER LIGHT INOPERABLE L22948 RH Cl-1E12-NO30B REMOTE SHUTDOWN HEAT EXCHANGER LIGHT INOPERABLE L22983 HG 1HG01A HYDROGEN RECOMBlWER, ADJUST PER VENDOR MANUAL L23000 HP 1E22 F361B AIR COMPRESSOR DISCHARGE VALVE INOPERABLE L23090 RD 1C11-000 RMCS TRIPS REPEATEDLY ON CONTROL ROD DRIVE 06 27 L23129 MS TR-1821-R816 TEMPERATURE RECORDER PT 7 READING ERRATIC L23246 RH PI-1E12-R502 PUMP DISCHARGE PRESSURE INDICATOR LEAKING L23302 R!

SI 1E51 R801 CHANGE RCIC TURBINE SPEED INDICATOR GREEN BAND L23310 DG PI-1E22 N530 REPLACE SOAKBACK PUMP DISCHARGE PRESSURE GAUGE L23387 RI 1H13 P618 INSTALL BANANA JACKS ON TERMINAL STRIP EE L23388 RI 1H13 P621 INSTALL BANANA JACKS ON TERMINAL STRIP AA L23472 DG PS 1E22 N506 PRESSURE SWITCH FOR AIR COMPRESSOR STICKING L23557 NB LT 1821-N0260A WIDE RANGE REACTOR WATER LEVEL TRANSMITTER ERRATIC L23678 PC 1821 HK017 GROUP 7 ISOLATION LOGIC SPURIOUS TRIP L23683 NR 1C51-000 APRM D WILL NOT REMAIN ENERGlZED L23734 VG 1FZ VG003 INSPECT SBGT SUCTION DAMPER L23738 DG 1DG01P INSPECT COOLING WATER PUMP BEARINGS L23761 DG TS-1E22 N901B AIR COMPRESSOR DRYER PLUGGED L23815 HP 1E22 C003 ADJUST HPCS WATER LEG PUMP OlLER POSITION L23817 NR RY 1C51-K601B IRM "B" IS BROKEN L23820 VG 1VG01S SBGT FILTER TRAIN LIGHT BULB BURNED OUT L23840 DG 1LS-D0010 DAY TANK HIGH LEVEL ALARM SWITCH BAD L23871 RH TRS-1E12-R601 REPAIR HEAT EXCHANGER EFFLUENT TEMPERATURE INDICATOR L23900 DG IDG22MB INSPECT MolSTURE SEPARATOR L23902 RH 1E12-C3000 REWORK PUMP OILER PIPING L23903 LP 1E21 C002 INSPECT WATER LEG PUMP BEARINGS L23904 RH 1E12-C003 REWORK WATER LEG PUMP OlLER PIPING L23905 RI 1E51 C003 RCIC WATER LEG PUMP BEARINGS ARE DEGRADED

... ~

4 l

l l

ATTACHMENT A SAFETY RELATED MAINTENANCE COMPLETED (NON-0UTAGE RELATED)

... UNITal *-

(continued)

WRNUM SYSTEM EPN DESC L23997 DG 1DG08CB INSPECT AIR COMPRESSOR SUCTION DISCHARGE VALVE L23998 DG 1DG08CA INSPECT AIR COMPRESSOR SUCTION DISCHARGE VALVE L24001 RH 1E12-C3008

-REPLACE PUMP BEARING OILER.

L24009 RD o! 1C11 R9018 CRD PUMP LUBE OIL PRESSURE GAUGE INOPERABLE L24014 RN 1E G C300A REWORK OILER ON OUTBOARD PUMP BEARING L24119 PC 182*, HK001B RELAY CONTACTS 3 AND 4 DO NOT CLOSE L24212 AP 1PA33J HIGH WIND TEMPERATURE ALARM SWITCH UP, NO INDICATION L24337 WR RY-1C51 K601H IRM "H" PRE REGULATOR OUTPUT NOISE L24495 NB LR-1C34 R608 UPSET / NARROW RANGE REACTOR LEVEL RECORDER LIGHT OUT L24642 NR RY-1C51-K601E 1RM E DOWNSCALE WITH NO LIGHT INDICATION L24673 NR RY 1C51-K605GM REPLACE APRM A+F K18'S RELAYS L24692 RP 1C71 S001B RPS MOTOR BAD ON RPS MOTOR / GENERATOR SET L24741 NR RY 1C51 K601G IRM CHANNEL G DRAWER L24885 RD 1C11 000 R00 WORTH MINIM!ZER FAILES DURING TEST L24890 DG iTI-VD005 CALIBRATE HPCS DIESEL GEN ROOM TEMPERATURE INDICATOR L24918 NR RY 1C51 K600AA REPA!R SRM PRE-REGULATOR L24971 NR RY 1C51 K601G REPAIR IRM PRE *REGULATW L25039 NR RY*1C51-K605CSLPRM 16-57A SHOWS DOWNSCALE L25064 NR 1C51 000 REPAIR LPRM/APRM POWER SUPPLY L25073 RD PDl-1C11-N002 HIGH CRD DRIVE FILTER DIFFERENTIAL PRESSURE ALARM UP L25076 NR RY 1C51 J600H REPAIR 'A' TIP DRAWER L25143 RD 1C11 000 RMCS TRIPPING TROUBLESHOOT AND REPAIR L25160 DG 1DG01P COOLING WATER PUMP, KNOCKING kolSE IN MOTOR L25162 DG 1DG01P COOLING WATER PUMP LEAKS L25180 RD PDI 1C11 N015 CRD SUCTION FILTER DIFF PRESSURE SWITCH READS 0 L25216 NB LIS-1821 N702B CHANNEL 81 LEVEL 1 TRIP INDICATES LOW L25231 RI SU 1E51*J901 RCIC TURBINE SPEED DROPPED L25239 HP 1E22-C302A AIR COMPRESSOR HAS LOUD KNOCKING NOISE L25278 RI 1E51 AK049 RCIC TRACKING CONTROL RELAY CONTACTS L25280 RI 1E51-F360 RCIC TRIP & THROTTLE VALVE ACTUATOR INDICATION L25330 RI 1E51 F360 74 RELAY C0ll BURNED L25340 AP 1AP84E HYDROGEN SEAL Oil VACUUM PUMP BREAKER TRIPS L25388 RH PS 1E12 N5128 LOW PRESSURE SWITCH INOPERABLE L25396 DG 1LI D0005 FUEL OIL DAY TANK LEVEL GAUGE ERRATIC L25411 DG 1DG049A REPAIR AIR COMPRESSOR DISCHARGE CHECK VALVE L25489 RD 1C11 000 ROD 18 27, NO FULL OUT INDICATION L25662 AP 1APO4E TRANSFER PUMP iSF01PB REMOVE OPERATOR MECHANISM L25663 NR RY 1C51 K605GS APRM E HIGH ALARM UPSCALE L25676 RD 1C11 000 ROD 30-35, BOTH FULL IN AND FULL OUT LIGHTS ON L25710 AP 1APO4E LUBRICATE RX RECIRC MG SET DRIVE MOTOR OP MECHANISM L25713 AP 1AP06E LUBRICATE SAT MAIN FEED OPERATING MECHANISM L25714 AP 1AP06E LUBRICATE BUS TIE BREAKER OPERATING MECHANISM L25717 AP 1AP06E LUBE RHR PUMP 1E12 C0028 OPERATING MECHANISM L25718 AP 1AP06E LUBE 10G01K DG 1A MAIN FEED OPERATING MECHANISM L25721 AP 1AP06E LUBE CRD FEED PUMP 1C11-C001B OPERATING MECHANISM u5m RP 1C71.$.i A RPS - OR,m m 10R Sei Lo m AMP iNDiC - E m 1,C 3

l ATTACHMENT A SAFETY RELATED MAINTENANCE COMPLETED (NON 0UTAGE RELATED)

.............................................................. ung1,1...........................................................

(continued)

WRNUM SYSTEM EPN DESC L25799 AP 1AP72E INSPECT 1VP01CA/B BACKUP BREAKERS l

L25909 RP 1C71 5003A REPAIR TRIPPING OF RPS BREAKERS EPMA'S l

L25930 RP 1RP000 REPLACE RPS FUSE JUMPER WIRE L26000 NB 1821-K100CX REACTOR VESSEL LOW LEVEL 1+2 RELAY ERRATIC L26038 LC FT-1E32 N053J MAIN STEAM LINE BLEED OFF FLOW ALARM UP L26205 AP 1AP05E REFURBISH 1B PEATER DRAIN MOTOR BREAKER L26209 HP 1E22-F361B AIR COMPRESSOR RELIEF VALVE LIFTING L26256 DG 1E22-F361A AIR COMPRESSOR RELIEF VALVE LIFTING l

l l

............................................................ gggy.2...........................................................

WRNUM SYSTEM EPN DESC LO2766 NR RY-2C51 K601C IRN 2C INSTALL NEW INVERTER CARD L D4644 DG 2VD000 INSTALL SWITCHGEAR AREA ROOM THERMOMETER LO9006 VY 2VY000 REMOVE LPCS PUMP ROOM PIPE CHASE CHECKERED PLATE L12066 DG 2DG049A GROOVE STARTING TO WEAR INTO VALVE BODY L15086 NR RY-2C51-K605EC LPRM 08-33B READS UPSCALE l

L15541 NR RY-2C51 K605EN LPRM 40 33D SIGNAL DRIFTS L15553 DG 2VD07C REPLACE COOLING FAN 120 VAC WITH 480 L15555 DG 2VD01C REPLACE DG VENT FAN 120 VAC WITH 480 L15556 HP 2E22-C002 REPLACE COOLING WATER PUMP 120 VAC WITH 480 L15558 VC 2VC01AB INSTALL INTERPOSE RELAY L15664 DG 2PDS-VD004 SUPPLY DIFFERENTIAL PRESSURE HIGH

)

L16070 DG SI 2E22 M010 LOCAL SYNCROSCOPE STICKS L16431 DG 2DOO4T DG DAY TANK, SMALL LEAK AT MANWAY L16643 DC 2DCO2E REPLACE BATTERY CHARGER HANDLE L16660 RI 2E51-F086 THERMALS TRIPPED WHEN CLOSING L16798 RI 2F51-C002 OIL LEAKING FROM LUBE DIL SAMPLE VALVE L17339 RI 2E51-F025 STEAM LINE !$0LATION VALVE HAS PACKING LEAK L17978 NR XY 2C51 J6005A REPLACE TIP MACHINE INDICATION LIGHTS L18092 AP 2AP82E-F2 REPLACE MCC 236Y 1 COMPT F2 BREAKER L18774 NR RY-2C51-J600H A TIP DETECTOR SPIKED UPSCALE L19402 DG 2DG08CB INSPEC1 AIR COMPRESSOR SUCTION DISCHARGE VALVE L19403 DG 2DGOBCA INSPECT AIR COMPRESSOR SUCTION DISCHARGE VALVE L19462 RD 2C11-D001 151 CRD 42 27 NO FULL DUT LIGHT L19464 DG 20G01K CHECK CIRCULATING O!L PUMP ALIGNMEili L19512 NR RY 2C51 J600H INSERT TIP KACHINE TIMER TRIP ALARM L19577 DC RR-2E22-R542 GROUND WHEN DIESEL GENERATOR STARTED L19579 DG 2E22 S001 REPLACE LOCKOUT RELAYS K1 & K15 COVERS l

L19585 HP LS 2E22-N002A PERFORM SUPPRESSION CHAM 8ER EQ INSPECTION L19586 RD LS-2C11 N013A PERFORM SCRAM DISCHARGE VOLUME EQ INSPECTION L19800 AP 2AP34E ELEVATOR CIRCUlf BREAKER TRIPS L19938 HP 2E22-F3628 AIR COMPRESSOR flTTING LEAKS AIR

i l

l ATTACHMENT A SATETY-RELATED MAINTENANCE COMPLETED (NON-0UTAGE RELATED)

UNIT =2 - - -~ - - - --- - ---- --- --

(continued)

WRNUM SYSTEM EPN DESC i

L20336 DG 2E22 5001 GROUND PRESENT AT RECORDER L20352 RI LSL-2E51-N907 VACUUM TANK LOW LEVEL SWITCH LEAKING L20364 VC DPDS-VC177 REFRIGERANT COMPRESSOR LOW OIL PRESSURE TRIP i

L20390 NR XY-2C51-J600-5E E TIP MACHINE INTERLOCKS CHANNEL TEN I

L20519 NR LR-2821-RB848 REACTOR WIDE RANGE LEVEL RECORDER INDICATION ERRATIC L20522 AP 2AP15E INSPECT COMPARTMENT 3028, 2FC01PA BREAKER L20523 AP 2AP15E INSPECT COMPARTMENT 3010, 2EWO1EB BREAKER L20524 AP 2AP13E INSPECT COMPARTMENT 603A, 2VT02CA BREAKER 5

L20529 AP 2AP11E INSPECT COMPARTMENT 301A, 2VT01CA BREAKER L20861 NB LR-2B21-R884A REACTOR WIDE RANGE LEVEL RECORDER SLUGGISH L20951 DG 20G01K INSPECT SYNCROSCOPE O DEGREE PHASE ANGLE L20952 DG 2E22 S001 INSPECT SYNCROSCOPE O DEGREE PHASE ANGLE L21006 NR 2C51-000 CALIBRATE LPRM COMPUTER POINTS FOR APRM A F L21031 RH 2E12-C3008 MEGGER MOTOR l

L21032 RH 2E12 C300C MEGGER MOTOR L21033 RH 2E12-C3000 MEGGER MOTOR L21035 HP 2E22 C002 MEGGER MOTOR

)

L21036 RH 2E12 C300A MEGGER MOTOR L21040 DG 2DG01P MEGGER MOTOR L21076 RH TE-2E12-R601 TEMPERATURE RECORDER HAS SPORADIC ALARMS

)

L21084 RH PDI-2E12-N029A RHR LPCS INTEGRATION MUNITOR FAILED CALIBRATION L21128 LC 2E32 N650 INSTALL ALARM UNIT BANANA JACKS 7 AT 8 i

a j

L21263 HG 2LSL HG025 REPLACE DRAIN LINE WATER LEVEL SWITCH L21446 AP 2AP81E A3 REPLACE MCC 236X 3/A3 BOTTOM BLOCK SCREW j

L21536 NB LT-2821 N409A REACTOR LEVEL 8 TRANSMITTER INOPERABLE L21599 R!

2E51 000 RCIC CONTROLLER GOVERNOR VALVE INOPERABLE L21642 NR RY-2C51-J600H TIP DRAWER NOT RECEIVING 138 PULSES L21833 RI 2E51-F068 EXHAUST ISOLATION VALVE INOPERABLE L21933 VG 2VG01$

TRAIN DOOR WINDOJ SEAL LEAKS L22049 NR RY-2C51-K605GU REPLACE ROD BLOCK MONITOR CAPACITER L22050 NR RY 2C51-K605GR D APRM NEUTRON FIRST LIGHT Lli L22066 LP FT-2E21 N003 PERFORM LPC* FLOW TRANSMITTER EQ INSPECTION L22104 RD 2C11 D001-018 CONTROL ROD DRIVE 06-47 FULL IN LIGHT INOPERABLE L22105 MS 2E32 8001E P!PE HEATER DE ENERGIZED L22107 RD 2RD000 RMCS TRIPPING ON CONTROL RODS 10 23 AND 30-23 L22256 NB PS 2B?1-N5600 REPLACE SAFETY RELIEF VALVE F0130 PRESSURF SWITCH L22270 DG 2DG01$

MCC 236X-2 CUB A4 74 RELAY INOPERABLE L22273 RH 2AP82E Ei WATER LEG PUMP RELAY INOPERABLE L22302 RD 2C11-C001B REPLACE SWGR 242Y CUB 7 TIME DELAY RELAY L22316 NR RY 2C51-K601H IRM M FAILED FUNCTIONAL TEST L22347 LC 2E32 B001E REPLACE CABLE LUG AT 2AP76E FOR LCS PIPE IlEATER L22349 NB PI 2B21 R818 UNABLE TO RECALIBRATE HIGH PRESS EXHAUST INDICATOR L22350 RD 2C11-000 RMCS TRIPS WHEN ROD 30-11 SELECTED FOR INSERTION L21354 LC 2E32 8001E INBOARD MSIV LC P!PE HEATER INOPERABLE L22377 RD 2C11-C0018 INSTALL BANANA PLUG FOR CRD FEED PUMP 28 BREAKER

l ATTACHMENT A SAFETY RELATED MAINTENANCE COMPLETED j

(NON 0UTAGE RELATED) 1 l.............................................................. ungi.2............... ~............................................

(continued)

WRNUM SYSTEM EPN DESC

~

4 122378 RD 2C11-C001A INSTALL CRD FEED PUMP BREAKER BANANA PLUG L22399 NR RY-2C51-K6000A "D" SRM FAILED DOWNSCALE L22410 VG 2VG001 INSPECT LIMITORQUE ACTUATOR L22411 VG 2VC003 INSPECT LIMITORQUE ACTUATOR L22417 RN 2E12-D300A STRAINER HAS 1 GPM LEAK ON ELBOW L22443 NR RY 2C51 K601G REFLACE IRM "G" PREREGULATOR L22544 NB 2H13 P631 REPLACE REACTOR LOW LEVEL ADS RELAY L22562 VC 0FZ-VC041A OVC52YB AND OVC05YB DAMPER FUSE BLOWING L22620 AP 2APBOE REPALCE 480V 236X ? C1 BREAKER OlL PUMP HANDLE l

L22629 VY 2TI VY020 AREA TEMERATURE INDICATOR DRIFTING HIGH i

L22651 RD 2C11 000 RMCS TRIPPED / ROD 30-11 HAD SINGLE LED LIT

]

L22685 NB LR 2521 R8840 REPAIR WIDE RANGE REACTOR LEVEL RECO'tDER j

L22696 RI 2E51 C005 BAROMETRIC CONDENSOR VACUUN FUMP LICHT INOPERABLE L22748 LP PS-2E21 N005B REPLACE LPCS LOW PRESSURE SWITCH L22779 NR RY-2C51 K605GV B RBM REFERENCE DOWNSCALE L22843 NR RY 2C51 K600CA REPAIR SRM "C" INDICATION L22857 NR RY 2C51 K601H REPLACE IRM H REGULATOR L22868 MS 2821-F418B ISOLATION VALVE NO INDICATION L22874 RD 2RD000 CONTROL ROD 34 39 WHEN SELECTED RMCS TRIPS L22881 NR RY-2C51 K601D D IRM FAILED DOWNSCALE L22905 DC 2DG22MB INSPECT AIR COMPRESSOR MOISTURE SEPERATOR L22907 DG 2DG19MA IN$PECT AIR COMPRESSOR MOISTURE TRAP L22910 DG 2DG22MA INSPECT AIR COMPRESSOR MOISTURE SEPERATOR L22912 DG 2DG14MB INSPECT AIR COMPRESSOR MolSTURE SEPERATOR L22913 DG 2DG19MB INSPECT AIR COMPRESSOR MolSTURE TRAP L22920 RD 2C11-000 RMCS FAILED ON CONTROL ROD 38 55 L22995 RD 2C11 C001B CUNO FILTER INOPERABLE L23008 RD 2C11 000 CONTROL ROD 18-23 FULL IN, NO INDICATION j

L23189 DG 2DG08CB AIR COMPRESSOR AFTER COOLER HAS AIR LEAK l

L23212 DG 2E22 5001 INSTALL AND REMOVE CYLINDER TEST VALVES L23239 DG 20G048A AIR COMPRESSOR DISCHARGE RELIEF VALVE LEAKS I

L23245 NR RY-2C51 K600BA B SRM SPIKING UPSCALE /DOWNSCALE L23262 R1 LSH 2E51-N010 DRAIN POT LEVEL SWITCH ALARM CYCL]NG L23299 RD 2C11-D001-127 CONTROL ROD DRIVE 18 39 DRIFTED L23303 RI SI-2E51 R801 CHANGE TURBlNE SPEED CAUGE GREEN BAND L23339 RI 2E51-D003 STEAM LINE DRAIN TAP VALVE IS CYCLING L23379 DC 20C000 REPAlR 250 VDC BATTERY HIGH DISCHARGE ALARM UNIT L23385 RI 2H13-P618 INSTALL BANANA PLUGS AT TERM STRIP EE L23386 RI 2H13 P621 INSTALL BANANN PLUGS AT TERM $1 RIP AA L23534 NR 2C51-000 1NDICATION AT TIPS CONTROL DRAWER ON 2A DETECTOR L23535 DC 2DC03E 250 VDC BATTERY ALARM AT POINT A108 L23543 AP 2AP01E REPAIR 251 CUB 6 2CD61PA FEED BREAKER L23604 NR RY 2C51-K600AB REPAlR SRM A PRE-REGULATOR L23620 NR RY 2C51 K6000A REPAIR SRM D PRE 4EGULATOR L23674 DG 2Dc08CB REBUILD AIR COMPRESSOR L23679 RD 2C11-000 RMCS ROD SELECT PUSHBUTTON 14-07 BROKEN

_ -.. ~ -

. - ~.

_. ~

e I

ATTACHMENT A SAFETY-RELATED MAINTENANCE COMPLETED (NON 0UTAGE RELATED)

.............................................................. UNIT =2 * *=*- -

• • • -** *=~ **=*- --* - *

-=== *=

(continued)

WRNUM SYSTEM EPN DESC

~L23684 DG 2DG000 CYLINDER #12 TEST VALVE LEAKING EXCES$1VELY l

L23707 DG 2DG01P REPLACE COOLING WATER PUMP BEARING l

L23741 RH 2E12 C3000 INSPECT RHR SERVICE WATER PUMP BEARINGS L23743 RD XY-2C11-K947 SEVERAL CONTROL RODS HAVE LOST POSITION INDICATION L23759 RD 2RD000 REPLACE ROD 22-35 POSITION INDICATION LIGHT HOLDER L23764 DG 2DG01J COOLING WATER PUMP BACKWASH STRAINER PLUGGED L23805 NR RY-2C51-K605GU ROD BLOCK MONITOR METER STICKS L23858 HP 2PL24J DIV !!! HVAC PANEL WINDOW #17 ALARM INOPERABLE L23993 DG 2DG08CA INSPECT AIR COMPRESSOR SUCTION DISCHARGE VALVE L23994 RN 2E12-C300A REPLACE RHR PUMP OUTBOARD PUMP BEARING OILER L24129 DG 2DG090B INSPECT AIR DRYER L24166-DG 2DG011 COOLING WATER PUMP-STRAINER VALVE CYCLES L24167 RP 2C71-000 REPAIR ALTERNATE RPS EPMA BREAKER POWER L24215 NR RR-2C51-R603D IRM/APRM/RBM RECORDER, TWO ' LED'S OUT i

L24247 RI 2E51 C003 REPLACE RCIC WATER LEG PUMP PIPE N!PPLE L24659 VC RlY-2018-K7518 VC RAD MONITOR FAILED UPSCALE L24842 DG 2T! DG099 LUBE CIL COOLER WATER TEMPERATURE lhDICATOR INOP L24865 DG 2 TIS-DG100 STATCR TEMPERATURE MONITOR, REPLACC LUGS 2

L25065 AP 2AP06E-5 242Y CUB 5 FEED BREAKER 236 X,Y MOUNTING BROKEN L25099 HP 2E22 000 REPLACE RELAY K27 COVER L25120 DG 2AP04E O DG OUTPUT BREAKER ACB 2413 525 SWITCH INOPERABLE L25201 RH PZ-2E12 L902A HEAT EXCHANGER LEVEL CONTROL VALVE INOPERABLE L25215 RD 2C11-C001B CONTROL ROD DRIVE PUMP OIL COOLER LEAKS L25238 NB 2B21-F382 VALVE STROKE ERRATIC, UNABLE TO SET LIMIT SWITCH L25305 LP 2E21 F012 FULL FLOW TEST VALVE PINION PROBLEM L25403 RD 2C11 D001-012 REPLACE CONTROL ROD 14 55 DIRECTIONAL CONTROL VALVE L25488 NR RY 2C51-K600BA REPLACE SRM B, RhADS LOW j

L25774 RD 2C11 D006-113 HCU 18 55 CHARGING WATER STOP VALVE INOPERABLE L257/5 RD 2C11 0093-113 HCU 42 59 CHARGING WATER STOP VALVE INOPERABLE L25776 RD 2C11-0130 113 HCU 30-39 CHARGING WATER STOP VALVE INOPERABLE l

L25955 PC 2PCM111 DRYWELL ACCESS HATCH AlRLOCK VALVE / SEAL LEAKING l

L26152 RH 2E12 F0418 RHR TESTABLE CHECK VALVE NO CLOSED INDICATION l

L26235

-RH TRS 2E12 R601 RHR HEAT EXCHANGER INLET /0UTLET TEMPERATURE L26328 RI 2E51 AK049 RCIC TRACKING CONTROL RELAY AND LOOP L26329 RI 2E51 F045 RCIC STEAM SUPPLY VALVE WITH RCIC STARTUP L26369 HG 2HG0028 VALVE FAILED TO CYCLE l

l l

1 e

ATTACHMENT B II.B UNIT SHUTDOWNS (UNIT 1) l l

DATE: 921003 GENERATOR OFF-LINE: 715.2 OUTAGE TYPE:

Scheduled (L1R05)

(YYMNDD)

(Hours)

REASON: Refueling Outage.

CRITICAL ACTIVITY PATH: See Appendix A.

CORRECTIVE ACTIONS (DVR/LER# if applicable): None.

RADIOACTIVITY RELEASE / EXPOSURE OVER 10% ALLOWABLE VALUES: None.

SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED: See Appendix B.

DATE: 930130 GENERATOR OFF-LINE: 7.2 OUTAGE TYPE:

Forced (LIF16)

(YYMMDD)

(Hours)

REASON: Nbnual Nbin Turbine trip due to high vibration levels on bearings 3,

4, 6 and 7.

The Reactor remained critical during the outage.

CRITICAL ACTIVITY PATH: None.

CORRECTIVE ACTIONS (DVR/LER# if applicable): None.

RADIOACTIVITY RELEASE / EXPOSURE OVER 10% ALLOWABLE VALUES: None.

SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED: None.

DATE: 930131 GENERATOR OFF-LINE: 7.2 OUTAGE TYPE:

Forced (LIF17)

(YYMNDD)

(Hours)

REASON: Manual Main Turbine trip due to high vibration levels on bearing 7.

The Reactor remained critical during the outage.

CRITICAL ACTIVITY PATH: None.

CORRECTIVE ACTIONS (DVR/LER# if applicable): None.

RADIOACTIVITY RELEASE / EXPOSURE OVER 10% ALLOWABLE VALUES: None.

SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED: None.

I DATE: 930131 GENERATOR OFF-LINE: 19.6 OUTAGE TYPE:

Forced (L1F10) l

( Y YNt<DD)

(Hours)

REASON: Manual Main Turbine trip due to high vibration levels on bearings 4

6 and 7.

The Reactor remained critical during the outage.

CRITICAL ACTIVITY PATH: None.

CORRECTIVE ACTIONS (D7A/LERN if applicable): None.

RADIOACTIVITY RELEASE / EXPOSURE OVER 10% ALLOWABLE VALUES: None.

SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED: None.

i I-APPENDIX A CRITICAL PATH ACTIVITY REFUEL OUTAGE (L1R05)

DESCRIPTION REPLACE 1CD01PB COND/COND B00 STER PUMP "B" COUPLING 1VP01CB VP CHILLER LEAKING COMPLETE REACTOR REASSEMBLY CLEAN CONDENSATE CHECK VALVE MODIFICATION TEST 1821-1BSFV1 MSR STEAM VALVE DUAL INDICATION WHEN OPEN COMPLETE TURBINE GENERATOR MAINTENANCE COMPLETE REACTOR CORE ISOLATION COOLING MAINTENANCE COMPLETE 1HD059A HEATER DRAIN VALVE MAINTENANCE COMPLETE 1HD056A HEATER DRAIN VALVE MAINTENANCE l

1821 RSDV2 VALVE FAILED TO STROKE I

iPS-FWOS8 OIL LEAK IN FRONT STANDARD COMPLETE REACTOR HYDRO SCRAM TIME SELECTED CONTROL ROD DRIVES POST REACTOR HYDRO SYSTEM RESTORATION 1E12 F004A MODIFICATION LEAK TEST SIGNATURE TRACE VALVE 1833-F023A ESTABLISH PRIMARY CONTAINMENT FOR INTEGRATED LEAK RATE TEST SIGNATURE TRACE VALVE 1821-2BSFV1 SIGNATURE TRACE VALVE 1821-F430A SIGNATURE TRACE VALVE 1821 R$HLV2 SNUBBER REDUCTION TESTING PERFORM AMP CHECK VALVE 1821 1BSFv1 COMPLETE STARTUP AND SYSTEM CHECKLIST PERFORM AMP CHECK VALVE IB21 F4228 VISUAL ANNUNCIATOR GROUND DET FAILURE ALM IS UP ILDS SV018 1 RAVELING SCREEN DIFFERENTIAL PRESSURE ALARM I

1821 RSDV2 DRAIN VALVE WILL NOT OPERATE I

1E51-F026 RCIC STEAM TRAP DRAIN VALVE MAINTENANCE IN62-F085A 0FFGAS HOLD UP LINE DRAIN VALVE MAINTENANCE 1FY-FWOO8C FEEDWATER REGULATOR LEAKING AIR HYDRAULIC CONTROL UNIT 30 11 WITHDRAW TIME TOO FAST 1PA01J 24 VDC HOUSE POWER HIGH/ LOW ALARM PLANT HEATUP l

HAIN GENERATOR ON-LINE l

l l

I

1 2

APPENDIX B REFUELING OUTAGE (L1R05)

SAFETY RELATED CORRECTIVE MAINTENANCE j

i 1

i WRNUM SYSTEM EPN DESC l

i LO5519 MS 1821 F020 MAIN STEAM EQUAL LINE STOP VALVE PACKING LEAK LO6609 MS 1621 RSHLV2 REPLACE FLEXIBLE CONDUIT l

I LO6691 DC 1DC03E 250V BATTERY CHARGER FUSE BURNED 4

LO7018 NR 1NR000 REPLACE TIP TUBING B 8 & C-3 TAGS LO7067 MS 1821-RSLLV-2 MSR REHEATER VALVE WILL NOT CYCLE LO7381 MS 1B21 1BSFV1 MSR STEAM FEED VALVE, DUAL INDICATION WHEN OPEN I

LO7540 MS 1821-MSBPV 5 TURBINE BYPASS VALVE STEAM LEAR AROUND STEM l

LO7541 MS 1821 CIV5 COMBINED INTERCEPT VALVE LEAKING LO7861 MS 1TG027A FLANGE LEAKING LO8317 MS 1821-MSBPV3 TURBINE BYPASS VALVE PACKING LEAK LO9847 MS 1821 F4938 BYPASS VALVE FAULTY MECHANICAL INDICATION L12656 MS 1821 F504A VALVE LEAKING PAST VALVE SEAT L12933 RI 1E51-F019 MIN FLOW VALVE TRIPPED BREAKER WHEN CLOSING L13610 RI 1E51 F019 VALVE FAILS TO MOVE i

L13816 LC FS-1E32 N653J MSIV ALARM UNIT SAFETY DIVIDER BROKEN L14718 DG ODG009 BACKWASH OUTLET VALVE PACKING LEAK 4

L14730 LC PT-1E32-N051A VENT VALVE HARD TO OPERATE L14731 LC PT-1E32-N051A ISOLATION VALVE LEAKS BY j

L14990 MS 1821 F019 DRAIN VALVE PACKING LEAK L15237 RI 1E51-C005 VACUUM PUMP SHAFT SEAL LEAK L15545 HP 1E22 F004 INJECTION VALVE WATER SEEPAGE BETWEEN VALVE L16598 RI 1E51 F004 PUMP DISCHARGE VALVE AIR REGULATOR LEAK I

L16599 RI 1E51 F005 PUMP DISCHARGE STOP VALVE AIR REGULATOR LEAK L17251 RD 1C11-D001 148 REPLACE SCRAM WATER ACCUMULATOR AT HCU 54 27 L17702 NR XY-1C51 J600 5B 18 TIP DRIVE UNIT STRING 3 INOPERABLE L18122 LC 1821 MSBPV3 LEAK 0FF LINE #3 BYPASS VALVE LEAKING L18163 LC 1E32 F009 LEAKAGE CONTROL DISCHARGE VALVE LEAK I

L18176 MS 1821 F514B 1ST STAGE VALVE STEAM PACKING LEAK L18180 MS 1821-RSCV-2 REHEAT STEAM STOP CHECK VALVE PACKING LEAK

)

L18183 MS 1821 F076C DRAIN MANUAL STOP VALVE BONNET LEAK L18184 MS 1821-F302B DOUBLE BLOCK DRAIN VALVE LEAKS r

L18185 MS 1821-F302C DOUBLE BLOCK DRAIN VALVE LEAKS L18186 MS 1821-F306A DOUBLE BLOCK DRAIN VALVE LEAKS L18187 MS 1821-F306D MANUAL DRAIN VALVE LEAK L18211 MS 1E32 F001E ISOLATION VALVE FAILED LOCAL LEAK RATE TEST 4

L18256 LC 1E32 F008 VALVE FAILED TO OPEN L18328 RD 1H13 P800 DEVICE K17A AND K17C FAILED TO SEAL IN L18367 MS 1B21-R$HLV2 REPAIR HEAT CAMAGED LABLE L18382 RI 1E51 F064 STEAM SUPPLY ISOLATION VALVE LEAK L18383 RI 1E51 F028 VACUMM PUMP DIMHARGE CHECK VALVE DOES NOT SEAT L18384 RI 1E51 F084 TURBINE EXHAUST VACUMM BREAKER DID NOT CLOSE L18446 MS 1821-1BSFV1 VALVE STEM LEAK AT PACKING L18661 RI 1E51 F031 SUCTION VALVE MISSikG DUST SEAL L18877 MS 1821-2BSFV1 REPAIR STEAM VENT STOP CHECK VALVE CABLE

+

L18926 RD 1C11 D001 120 CRD 18-15 DIRECTIONAL CONTROL VALVE LEAKING L18954 RI 1E51 F086 TURB EXHAUST VACUUM BREAKER ISOLATION VALVE LEAKING L18960 RI 1E51*F080 TURS EXHAUST VACUUM BREAKER STOP VALVE LEAKING L19067 RD 1C11 D001 132 HCU 54 35 VALVE LEAKING

4 i

i APPENDIX B REFUELING OUTAGE (L1R05)

SAFETY RELATED CORRECTIVE MAINTENANCE l

WRNUM STSTEM EPN DESC L19068 RD 1C11-D001 111 HCU 42-47 VALVE LEAKING L19085 MS 1821-F0130 VALVE SOLEN 0!D CABLE CONNECTOR BROKEN L19132 MS 1821 MSBPV5 BYPASS VALVE GLAND STEAM LEAK OFF LINE LEAKS L19154 RD 1C11-D001-054 REPLACE CRD 02 27 SOLENOID VALVES l

L19162 MS 1821-F513A REPLACE MSR iST STAGE STEAM VALVE CABLE l

L19217 MS 1821 F0228 NORGROM VALVE LEAKS AT FITTING L19365 NS 1NB098 INSTALL WATER LEVEL REFERENCE LEG PIPING INSULATION l

L19371 MS 1DV016C HEATER SHELL STAR (UP VENT VALVE ACTUATDR LEAKING L19406 MS M09 l?SO4-1031C CONSTANT PIPE SUPP0"tT ROD BENT L19433 RD 1C11-D001 074 HCU 18-15 PRE'tVRE RLEEDS DOWN L19450 RI Pl*1E51 R907 TURBINE OIL HEADIR PRESSURE INDICATION INDPERABLE L19477 RP ZS-1C71-N0060 REPLACE TSV #2 LIMIT SWITCH CABLE 1RPO47 L19505 MS 1821*CV1 LOCKNUTS LOOSE ON TIE ROD CLEVIS L19506 NR RY-1C51-K601C C IRM TRENDS OK BUT RECORDER NOISY L19521 NR RY 1C51-K60008 D SRM SHORT PERIOD ALARM / INDICATION ER2ATIC L19522 NR RY 1C51-K601B B IRM ERRATIC AFTER USING SELECTOR SWITCH L19556 RD 1C11-000 ROD 54-43 FULL OUT LIGHT WILL NOT ENERGIZE L19594 MS 1821 F0248 CHECK VALVE LEAK!kG BY L19701 HG 1FI HG022 HYDROGEN RECORDER FLOW INDICATOR OUT OF TOLERANCE L19741 MS MS88-1003C REPLACE MIS $ LNG CONSTANT SUPPORT NUTS l

L19784 MS MS88 1002R REPLACE MISSING RIGID SUPPORT NUTS L19874 PC 1PC000 BOLT MISSING IN ONE OF THE CONNECTIONS L19880 MS 1821 F303A REPAIR DOUBLE BLOCK VALVE WELD L19881 MS 1821-F3030 REPAlR DOUBLE BLOCK VALVE WELD L19890 MS 1821 F022B MAIN STEAM 150 VALVE ACTUATOR LEAKS BY INTERNAL SEALS L19907 MS 1821 1BSFV1 REPAIR 1ST STAGE BLANKET STEAM VALVE FEED CABLE L19920 RD 1C11 D001 118 HCU 46-43 SCRAM OUTLET VALVE PACKING LEAK L15925 NB LT 1821*N402A RX VESSEL LO WATER ISOLAT!DN INSTRUMENT INOPERABLE L20(93 RI 1E51 C005 REPAIR BAROMETRIC COND VACUUM PUMP PIGTAll L20165 HP 1NP000 ALARM B503 FAILS l0 CLEAR j

L20203 kr IC71-AK022D SCRAN RESET RELA 1 kJZZING l

L20225 RH ZSC 1E12 F041A REPAIR LIGHT INDICATION L20235 MS 1E32 F002A LIM 4T SWITCH CHATTERING L20246 RD 1C11 000 HYDRAULIC CONTROL UNIT DRAIN LINE HEADER PIPE BROKEN L20258 MS 1MS000 T!GHTEN MAIN STEAM LINE SNUBBER BOLTING L20260 MS 1821-F069 REPAIR MAIN STEAM LINE DRAIN VALVE ACTUATOR L20365 RD 1C11-D001 078 HCU 30-11 WITHDRAW TIME TOO FAST l

ATTACHMENT B II.B UNIT SHUTDOWNS (UNIT 1)

DATE: 930203 GENERATOR OFF-LINE: 1.5 OUTAGE TYPE:

Scheduled (LIM 04)

(YYMMDD)

(Hours)

REASON: Main Turbine overspeed test.

CRITICAL ACTIVITY PATH: Completion of overspeed testing.

I CORRECTIVE ACTIONS (DVR/LER# if applicable)* None.

RADIOACTIVITY RELEASE /EXPOSUBE OVER 10% ALLOWABLE VALUES: None.

SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED: None.

DATE: 930214 GENERATOR OFF-LINE: 153.7 OUTAGE TYPE:

Forced (LIF19)

(Y Y144DD)

(Hours)

REASON: Manual shutdown to repair an inoperable valve (1E51-F063) on the j

steam supply line from the Reactor to the Reactor Core Isolation j

Cooling system. The shutdown was mandated by the station's l

Technical Specifications.

CRITICAL ACTIVITY PATH: Troubleshooting, repair and post maintenance i

testing of the 1E51-F063 valve.

CORRECTIVE ACTIONS (DVR/LER# if applicable)! DVR# 01-01-93-014 LER# 93-004 RADIOACTIVITY RELEASE / EXPOSURE OVER 10% ALLOWABLE VALUES: None, i

SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED:

WRNUM EPN DESCRIPTION L20750 1821-F072 Main Steam Line drain valve leaking i

L20767 RY-1C51-K601A Intermediate Range Monitor spiking when withdrawn L21013 RY-1C51-K605G No Low Power Range Monitor indication L21075 RY-1C51-K605DN Low Power Range Monitor reading downscale L21086 1B21-RSHLV1 2nd Stage Steam Valve inoperable L21097 1B21-RSSV2 2nd Stage Valve packing leak L21290 1E51-F063 Valve breaker tripped when valve was opened l

l

4 ATTACEMENT B II.B UNIT SHUTDOWNS (UNIT 1) l DATE: 930228 GENERATOR OFF-LINE: 177.7 OUTAGE TYPE:

Forced (LIF20)

(YYMMDD)

(Hours)

REASON: Manual shutdown to repair an inoperable valve (1E51-F063) on the steam supply line from the Reactor to the Resctor Core Isolation Cooling system. The shutdown was mandated by the station's Technical Specifications.

CRITICAL ACTIVITY PATH: Repair and post maintenance testing of the 1E51-F063 valve.

CORRECTIVE ACTIONS (DVR/LERN if applicable): DVRN 01-01-93-023 LER# 93-007 RADIOACTIVITY RELEASE / EXPOSURE OVER 10% ALLOWABLE VALUES: None.

SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED:

WRNUM EPN Description L18164 1E32-F008

' Valve stem leak L21012 RY-1C51-K605DC Low Power Range Monitor reading downscale L21346 1E51-F063 Disassemble and inspect actuator L21547 RE-1B13-D193DT Low Power Range Monitor cables reversed L21565 LIS-1B21-N702B Master trip unit output indicator inoperable L21705 1E51-F063 Motor trips on thermal overload L21813 1E32-F302N Valve packing leak L21857 1H13-P611 Intermittent relay problem L21887 RY-1C51-K601E Intermediata Range Monitor voltage cable damaged DATE: 930423 GENERATOR OFF-LINE: 35.3 OUTAGE TYPE:

Forced (LIF21)

(YYMMDD)

(Hours)

REASON: Manual Reactor scram due to a Feedwater system heater transient which was caused by a high level in the 12A Low Pressure Feedwater Heater.

CRITICAL ACTIVITY PATH: Troubleshooting, repair and post maintenance testing of the #3 NMin Turbine Bypass Valve fast acting initiation limit switch.

CORRECTIVE ACTIONS (DVR/LER# if applicable): DVR# 01-01-93-0032 LERN 93-011 RADIOACTIVITY RELEASE / EXPOSURE OVER 10% ALLOWABLE VALUES: None.

SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED:

\\ g WRNUM EPN Description L22456 ZSc-1C11-F380 Scram Discharge volume vent valve had dual indication l

l 1

ATTACRMENT B II B UNIT SHUTDOWNS (UNIT 1)

DATE: 930914 GENERATOR OFF-LINE: 543.7 OUTAGE TYPE:

Forced (L1F22)

(YYMMDD)

(Hours)

REASON: Reactor scram due to loss of the Station Auxiliary Transformer.

CRITICAL ACTIVITY PA7F: Replacement of the Reactor Recirculation Pump seals Station Auxiliary Transformer Bus Duct repairs Unit Auxiliary Transformer Bus Duct repairs CORRECTIVE ACTIONS (LER# if applicable): LER# 93-015 RADIOACTIVITY RELEASE / EXPOSURE OVER 10% ALLOWABLE VALUES: None.

SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED:

WRNUM EPN Description L21497 MS14-1402R Replace bent clevis and rod L21499 M314-1403R Replace bent celvis and rod L22384 1B21-F422B Valve leakage L23914 ODG01P Repipe oil bubbler L24316 LR-1821-R615 Level recorder, no indication L24702 1AP80E Feed breaker A phase burnt out L24718 1C11-000 Control Rod Drive 34-31, no indication L24728 1E12-F085A Valve leakage L24737 1E51-C002 Drain plug assembly leakage L24738 1NB10A Insulate reference leg pipe L24753 MS33-1006X Replace support lock nuts L24775 PDI-1C11-N015 Suction filter high Differential press alarm L24826 ODG01P Oil bubbler leaking L24936 1B21-F022A No indication L24937 1B21-F022D No indication L24948 1MS01AA Tighten whip restraint locking nut L24902 RY-1C51-K601D Intermediate Range Monitor reads downscale L24995 PDI-1B2.-R902 Low load output inoperable L24999 ODG006 Valve packing leak i

h 4

I i

ATTACHMENT B II.B UNIT SHUTDOWNS (UNIT 2)

DATE: 920529 GENERATOR OFF-LINE: 217.8 OUTAGE TYPE:

Scheduled (L2M07)

(YYM4DD)

(Hours)

REASON: Nbintenance Outage.

CRITICAL ACTIVITY PATH: Replacement of the 2A Reactor Recirculation pump seal, leak checking and plugging of the Main Condenser tubes and modification of the Residual Heat Removal Low Pressure Core Injection valve 2E12-F042A.

CORRECTIVE ACTIONS (DVR/LER# if applicable): None.

RADIOACTIVITY RELEASE / EXPOSURE OVER 10% ALLOWABLE VALUES: None.

SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED:

WRNUM EPN Description L17595 2E51-F054 Replace steam supply valve L19408 2HD140B Valve leakage L22269 2ZI-EH916D Isolation valve indicates closed on EHC panel L22741 RR-2C51-R603B Erratic recorder indication L22799 2C11-000 Insert and withdrawal pushbuttons inoperable L22801 ZS-2E12-F050B Check valve indication inoperable L22808 2E12-F041C Check valve dual indication L22044 ZSO-2E12-F041A Check valve limit switch sticking DATE: 920904 GENERATOR OFF-LINE : 614.4 OUTAGE TYPE:

Scheduled (L2R05)

(YYMMDD)

(Hours)

REASON: Refuel Outage.

CRITICAL ACTIVITY PATH: See Appendix C.

CORRECTIVE ACTIONS (DVR/LER# if applicable): None.

RADIOACTIVITY RELEASE / EXPOSURE OVER 10% ALLOWABLE VALUES: None, SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED: See Appendix D.

DATE: 931226 GENERATOR OFF-L NE: 1.0 OUTAGE TYPE:

Scheduled (L2M00)

( Y Yt44DD)

(Hours)

REASON: M:in Turbine overspeed test.

CRITICAL ACTIVITY PATH: Completion of overspeed testing.

CORRECTIVE ACTIONS (DVR/LER# if applicable): None.

RADIOACTIVITY RELEASE / EXPOSURE OVER 10% ALLOWABLE VALUES: None.

SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED: None.

l APPENDIX C CRITICAL PATH ACTIVITY REFUEL OUTAGE (L2R05)

DESCRIPil0N i

l MAIN TURBINE GENERATOR OFF LINE SHUTDOWN REACTOR INSPECT DRYWELL AT PRESSURE COOL REACTOR TO LESS THAN 135 PSIG I

COOL REACTOR TO COLD SHUTDOWN PLACE MAIN TURBINE ON TURNING GEAR DURING SHUTDOWN l

MAIN TURBINE TURNING GEAR O!L PUMP 2T010P AUTO TRIPPE0 I

MAIN TURBINE TURNING GEAR FAILED TO AUTO-ENGAGE SIGNATURE TRACE VALVE 2E12 F004A PLACE RESIDUAL HEAT REMOVAL SYSTEM IN SHUTDOWN COOLING PURGE GENERATOR OF HYDROGEN MAIN TURBINE GENERATOR OFF TURNING GEAR REMOVE DRYWELL EQUIPMENT HATCH PERFORM MAIN STEAM ISOLATION VALVES LOCAL LEAK RATE TESTS PERFORM GROUP 2 AND 4 ISOLATION FUNCTIONAL TESTING START ELECTRO HYDRAULIC CONTROLS WORK i

START FEEDWATER WORK START TURBINE GENERATOR WORK l

PERFORM MAIN SfsAM ISOLATION VALVES ACTUATOR PISTON LEAK CHECK PERFORM ALTERNATE DEPRESSURIZTION ACCUMULATOR PRESSURE DROP TEST PERFORM 2B21 F032B LOCAL LEAK RATE TEST l

PERFORM 2821 F010B LOCAL LEAK RATE TEST PERFORM 2B21-F0658 LOCAL LEAK RATE TEST START SAFETY RELIEF VALVE WORK l

REMOVE REACTOR HEAD l

PERFORM MAIN TURBINE THRUST BUMP CHECK PERFORM VALVES 2tNO31,21N017 AND 2!N018 LOCAL LEAK RATE TEST REMOVE STEAM DRYER WHILE FLOODING CAVITY I

REMOVE MOISTURE SEPARATOR FROM VESSEL CAVITY FLOOD UP COMPLETED PERFORM VALVE 2G33 F040 LOCAL LEAK RATE TEST DRAIN MAIN STEAM LINES DRAIN O!L TANK 27001S To OT001T RESTART REACTOR WATER CLEANUP SYSTEM REMOVE FUEL POOL GATE UNLOAD REACTOR CORE REMOVE VALVE 2B21 F013R REMOVE VALVE 2B21 F013E l

REMOVE VALVE 2821-F013C REMOVE VALVE 2821 F013G REMOVE VALVE 2B21 F013M CLEAN 01L TANK 27001S REMOVE VALVE 2821 F013s REMOVE VALVE 2821 F013K l

REMOVE VALVE 2821 F013F l

REINSTALL VALVE 2821 F013G REMOVE VALVE 2821-F0130 REMOVE VALVE 2821 F013V

APPENDIX C CRITICAL PATH ACTIVITY REFUEL DUTAGE (L2R05)

DESCRIPTION 2T00BP SUCTION PUM DISASSEhBLE, CLEAN AND INSPECT 2T011P OIL PUMP DISAS$EMBLE, CLEAN AND INSPECT 21002P OIL DRIVEN BOOSTER PUMP DISASSEMBLE, CLEAN AND INSPECT REINSTALL VALVE 2821*F013M REINSTALL VALVE 2B21 F013$

REINSTALL VALVE 2821 F013K REINSTALL VALVE 2821 F013V REINSTAL'l VALVE 2821 F013F REINSTALL VALVE 2B21-F0130 TURBINE LUBE CIL SYSTEM FLUSH DRAIN, CLEAN, INSPECT AND REFILL DIL TANK 2T001S TURBINE LUBE OIL HIGH VELOCITY FLUSH TURBINE LUBE OIL SYSTEM FINAL FLUSH ZT 2B21 N575A INST NEW LVDT"S QUICK OISCONNECT PERFORM SAFETY RELIEF VALVE POSITION INDICAi!ON INSPECTION AUTOMATIC DEPRES$URIZATION SYSTEM RELAY LOGIC TEST PERFORM LOW LOW SETPIONT MATRIX LOGlc TEST PERFORM LOW LOW SETD0!NT FUNCTIONAL TEST PERFORM SAFETY RELIEF VALVE SOLENOID TEST PERFORM MAIN GENERATOR AIR TEST MAIN TURDINE GENERATOR ON TURNING CEAR MODE SWITCH TO STARTUP RX CRiflCAL 2B21 F032A FEEDWATER CHECK VALVE AIR LEAK ON AIR ACTUATOR ADJUST RCIC OVERSPEED TRIP COMMENCE HEATUP AND PRESSURIZATION PULL RODS TO CRITICAL PERFORM RCIC PUMP OPERABILITY TEST REPERFORM RCIC TURBINE OVERSPEED TEST PERFORM RCIC TURBINE OVERSPEED AT 135 PSI

$ TART UP MDRFP (300 PSI)

EMERGENCY CORE COOLING PERMIS$1VES CLEAR AT 500 PSI HEAT UP TO 600 PSIG MODE SWITCH TO "RUN" RECOUPLE RCIC TURBINE AFTER OVERSPEED TEST PERFORM 2E51+F045 DIFFERENTIAL PRESSURE TESTING DURING STARTUP FILL CENERATOR WITH HYDROGEN FOR STARTUP INCREASE POWER TO 20 25%

ROLL MAIN TURBINE SYNCH GENERATOR TO THE CRID

e APPENDIX D

)

l REFUELING OUTAGE (L2R05)

SAFETY RELATED CORRECTIVE MAINTENANCE j

WRNUM SYSTEM EPN DESC L10458 RD 2C11 000 REPAIR CONTROL ROD 18 43 REED SWifCH L13005 AP 2AP07E BUS 243 DIFFICULT TO CLOSE L13184 NB 2B21-F380 EXCESS FLOW CHECK VALVE WOULD NOT CLOSE L13185 HP 2E22*F342 EXCESS FLOW CHECK VALVE WOULD NOT CLOSE L13186 NB 2821-F367 EXCESS FLOW CHECK VALVE WOULD NOT CLOSE L13644 DG TE-2E22 N903 20 DIESEL GENERATOR CYLINDER #20 TEMPERATURE READS LOW L13864 RD 2C11-D001 033 HCU 26 35 CHARGING WATER CHECK VALVE LEAKS L13865 RD 2C11 D001-098 HCU 38-55 CHARGING WATER CHECK VALVE LEAKS L13939 RP 2C71 AK0108 HFA RELAY CONVERT CONTACT L13940 RP 2C71 AK010H HFA RELAY CONVERT CONTACT L14455 MS Ms04-2725C REPA!R CONSTANT SUPPORT LOCKING DEVICE L14505 RD 2RD000 REPAIR SCRAM PILOT VALVES ELECTRICAL BOXES L14517 NB LT-2821 N402C LEVEL TRANSMITTER HARD TO CLOSE L15096 RI 2E51 C005 REACTOR CORE !$0 COOLING VACUUM PUMP SHAFT SEAL LEAK L15147 PC 22$ PC001D VACUUM BREAKER DUAL INDICATION WHEN OPENED L15161 RI 2E51-C001 REACTOR CORE ISO COOLING PUMP SEAL LEAKING L15365 MS 2821-F425A TDRFP DRAIN BYPASS VALVE STEAM LEAK L15452 RD 2H13 P603 HCU 26-35 NO FULL 0UT INDICATION L16056 RD TE 2C11 N795 CONTROL ROD TEMPERATURE ELEMENT READING LOW L16087 MS 2TG02TA VALVE SONNET BLOWING STEAM L16245 RI 2E51-F064 ISOLATION VALVE PACKING LEAK L16300 NR 2C51 000 REPLACE TIP TUBING ASSOCIATED WITH CHANNEL A.7 L16822 RH 2E12 F016A ISOLATION VALVE PACKING LEAK L16905 RH 2E12 F064C MINIMUM FLOW BYPASS VALVE PACKING LEAK L16974 MS 2821 F069 DRAIN VALVE BREAKER TRIPPED ON THERMAL OVERLOAD L17401 MS 2821 Sv2 MAIN TURBINE STOP VALVE HAS STEAM LEAK L17606 RI 2E51 F045 ACCUMULATOR GOVERNOR VALVE LEAKS L17856 NB PS 2821 N413C VENT VALVE LEAKS L18264 NR RY 2C51-K605AT LPRM 16 330 BAD IV PLOT L18269 MS 2821-1BSFV1 MSR VALVE LEAKING

)

L18528 DC 2DG01K JACKET WATER FROM ENGINE FLANGE LEAKING L18894 RD 2C11 0001 063 CONTROL R00 30 19 BAD POSITION INDICATION AT 48 L18953 RH 2E12 F068B HEAT EXCHANGER OUTLET STOP VALVE PACKING LEAKS j

L18961 RD 2C11 D001 047 CRD 30 27 UNCOUPLED, WITHDRAWN TO FULLOUT L18987 MS 2821 F019 ISOLATION VALVE LEAK L18989 MS 2821 F020 STOP VALVE BONNET LEAK j

L19009 MS 2B21 1BSFV2 STEAM FEED VALVE PACKING LEAKING L19028 MS 2TG01TA STEAM LEAK L19062 RI 2E51 F039 ISOLATION VALVE LEAKS L19064 RI 2E51 F038 ISOLATION VALVE LEAKS L19249 RH 2E12 F024A FULL FLOW TEST VALVE PACKING LEAK L19446 RI 2E51 F022 UPSTREAM STOP VALVE LEAKING L19578 DG 2DG01K OIL PUMP FLANGE LEAK L19769 AP 2AP31E INSPECT SWGR 233A/702B FEED TO MCC 233A 1 BREAKER L20194 DG 2E22 F028 INSPECT COOLING WATER PUMP DISCHARGE CHECK VALVE L21212 RD 2C11 000 RMCS REPA!R AS NECESSARY L21224 NR 2C51-000 REPAIR SRM/lRM CONNECTORS

-~

. - - - -. -. - - - - -. - -. -..~

.~

~

j' l'

}e i

)

APPENDIX D REFUELING OUTAGE (L2R05) 4 l

SAFETY RELATED CORRECTIVE MAINTENANCE j

f...................................................................................................................................

WRNUM SYSTEM EPN DESC

]

l L21226 RD 2C11 000 REPAIR RPIS CONNECTORS j

L22824 MS 2B21 F073 MAIN STEAM LINE DRAIN VALVE LEAKING l

L22832 MS 2821 F067A MAIN STEAM ISO 09AIN VALVE PACKING LEAK L22932 RD XY 2C11 K946CH ROD 02 35 HAS NO INDICATION WHEN FULL OUT I

L23397 R1 2E51 F026 RCIC STEAM SUPPLY DRAIN POT VALVE AIR LEAK j

.L23810 NB FY-2B21 K6000 JET PUMP FLOW SQUARE ROOT EXTRACT L23829 RD 2C11 F393A CRD PUMP DISCHARGE STOP VALVE STEM GALLED i

L23830 RD 2C11-F3938 CRD PUMP DISCHARGE STOP VALVE STEM CALLED

}

L23981 NR RY 2C51-K601E IRM E ERRATIC j

L24124 LP 2E21 F012 FULL FLOW TEST VALVE CYCLED OPEN, DUAL INDICATION i

L24133 MS 2B21 F422B HIGH PRESSURE STEAM ISOLATION VALVE PACKING LEAK j

L24216 NB FR 2C34 R607 RECORDER ' LED'S OUT j

L24428 MS 2B21-RSSv2 VALVE HAS DUAL INDICATION j

L24434 MS 2821 F4008 VALVE PACKING LEAK

}

L24438

. MS 2821 RSHLV1 VALVE PACKING LEAK j

L24441 MS 2TT002AA VALVE PACKING LEAK i

L24459 RI RI24 2862X-ADJUST SWAY STRUT ON INJECTION LINE l

L24462 MS 2B21 F016 PUMP ISOLATION VALVE PACKING LEAK j

L24486 RH 2E12 F325A HIGH POINT VENT SEAL WELD LEAK j

L24516 MS 2821 F398A VALVE INOPERABLE j

L24563 MS 2MS000 REPAIR JUCil0N BOX TJB7 FLEX!BLE CONDutT j

L24570 RI 2E51 F357 STEAM LINE UPSTREAM DRAIN VALVE LEAKING i

L24643 RH 2E12 F016A CONT SPRAY VALVE INTERLOCK CONTACT INOPERABLE L24650 NB 2WR179 RELAY FOR VALVE FAILED 10 TRIP L24654 HG 2HG006A STOP VALVE FAILED LOCAL LEAK RATE TEST

{

L24695 DG 2E22 $001 REPA!R COOLING WATER PIPE BROKEN WELD l

L24700 HG 2HG005A RECOMBINER SUMP POOL DISCHARGE VALVE INOPERABLE L24743 MS 2821 F494A BYPASS ISOLATION VALVE LEAKING i

L24799 DG 2E22-5001 REPLACE DIESEL GENERATOR CONTROL POWER FUSE F1/X1 L24814 NB 2B21 F568 INSTRUMENT REFERENCE LEG ISOLAfl0N VALVE LEAKS i'

L24815 PC 2PC003A VACUUM BREAKER ISOLATION VALVE SEAT LEAKING 1

L24820 RD 2C11 0001 179 CONTROL ROD 34 11 DRIFT!NG i

L24854 RD 2C11 0001-014 REPLACE CONTROL ROD 22 47 L24880 DG 200000 REPLACE REVERSE POWER RELAY L24888 RD 2C11 D116 112 HCU 54 43 112 VALVE WILL NOT CLOSE

}

L24931 NR RE-2C51 N002D REPLACE IRM D DRY TUBE i

L24955 PC 2PC002A VACUUM BREAKER ISOLATION VALVE LEAKING l

L24983 DG 200002 COOLING WATER PUMP DISCHARGE CHECK VALVE INOPERABLE l

L25005 MS 2821 F421A REPLACE TURBlNE STEAM DRAIN VALVE DIAPHRAGM L25006 MS 2B21-F421C REPLACE TURBINE STEAM DRAIN VALVE DIAPHRAGM L25034 RH 2E12 F041C TESTABLE CHECK VALVE FAILED TO OPEN L25040 RD 2C11 0094 127 ADJUST SCRAM INLET AND EXHAUST VALVES PACKING l

L25051 DC 20COSE REPLACE MCC 221X COMPARTMENT 3C 74 RELAY j

L25105 RI 2E51 C002 REPLACE OIL FILTER DRAIN PLUGS j

L25125 RH 2E12 F042C REPLACE INJECTION VALVE PACK!NG i

L25134 NB FT 2821 N539 FEEDWATER PUMP TURBINE TRANSMITTER INOPERABLE f

L25144 NB 2B21 HK60CX8

1. EPLACE VR DAMPER ISOLATION LOGIC RELAY i

j i

l' C

APPENDIX D REFUELING OUTAGE (L2R05)

SAFETY RELATED CORRECTIVE MAINTENANCE 4

j.....................................................................................................................................

4 WRNUM SYSTEM EPN DESC L25145 AP 2AP07E 2AP07E SWGR 243 CUB 004 CLOSE FUSE BLOCK BREAKER L25199 NB LIS-2821 N7030 REPLACE MASTER TRIP UNIT FOR LEVEL 3 FUSE L25206 RD 2C11 D136-116 REPLACE HCU 38 35 AIR SUPPLY LINE l

L25219 DC 2DC05E REPAIR 250VDC BUS #2 MCC 221X CIRCUIT BREAKER L25235 RD 2C11 000 HCU 02 43 ACCUMULATOR PRESSURE SWITCH DIDN'T ACTUATE L25237 RN PDS-2E12*N010AA LPCI MIN FLOW BYPASS SETPOINT DRIFilNG 4

L25254 RD 2C11-0114 113 HCU 30 47 VALVE WILL NOT OPERATE L25266 RD 2C11 D043-113 HCU 14-31 VALVE WILL NOT OPERATE L25267 AP 2AP20E 235Y 203C DC GROUND ON DIV I AT TRIP FUSES l

L25302 DG 2E22 S001 REPLACE LUG AT 2HP143 TERMINAL BLOCK #6 L25303 DC 20C02E REPAIR FEED BREAKERS To 221Y/221X I

L25306 RD 2C11-0138 126 HCU 30-35 126 VALVE LEAKS L25307 RD 2C11 D114 113 HCU 30 47 113 VALVE LEAKS L25309 RD 2APO4E 241Y CUB 6 CRD PUMP BREAKER CHARGING MOTOR L25315 RI 2E51 F026 REPAIR RCIC STEAM LINE DRAIN POT VALVE L25320 RD 2C11-0137 107 HCU 34 35 VALVE LEAKS L25327 RD 2C11 D001 079 HCU 26 11 DIRECTIONAL CONTROL VALVE STICKING L25334 DG 2E22 C302A A!R COMPRESSOR AFTER COOLER AIR LEAK L25341 RH ZSC 2E12 F092A MANUAL INJECTION VALVE HAS DUAL INDICATION L25381 NR RY-2C51 K600AA REPAIR

'A' SRM l

L25382 NR RY 2C51 K6008A REPAIR 88' SRM L25399 RH 2E12 F016A VALVE PAChlNG LEAK L25404 RI 2E51 AK049 INSPECT RClc TRACK!NG CONTROL RELAY L25410 DG 2E22 K032 REPLACE HPCS DIESEL GENERATOR K32 RELAY L25415 RH RH85 2979V REPAIR VARIABLE GUPPORT R00 ASSEMBLY L25426 NR RE 2C51 N001A REPAlR

'A' SRM L25437 RD 2C11 D001 012 REPLACE CONTROL R00 DRIVE 14 55 L25453 RH 2E12*F016B ISOLATION VALVE FAILED LOCAL LEAK RATE TESTING L25457 HP 2E22 P3018 REPAIR HPCS DG K32 RELAY MOUNTING BRACKET L25516 MS 2821-F080 MAIN SYEAM EQUALIZING LINE STOP VALVE INOPERABLE

~

L25517 MS 2821 F016 MAIN STEAM 150 VALVE SHOWS EXCES$1VE LEAKAGE L25527 LP 2E21-F006 INSPECT TESTABLE CHECK VALVE SOLEN 0!D L25529 MS 2B21 F016 REPACK MAIN STEAM LINE DRAIN VALVE L25530 NB PS 2821 N063 REPAIR PRESSURE SWITCH l

L25581 VG 2RF04M INSPECT SBGT STACK LOOP SEAL L25585 RD 2C11 0001 045 REPLACE HCU 06 31 DIRECTIONAL CONTROL VALVE L25609 RH 2E12 F0278 REPA!R DAMAGED WIRES L25626 RH 2E12 F041C INJECil0N TESTABLE CHECK VALVE FAILED TEST L25638 MS PTB 2821 MSBPV1 BYPASS VALVE LEAK!NG L25648 MS MS40 2011R REPLACE COMPONENT SUPPORT ROD L25655 MS TD20 2010R REPAIR STEAM SEAL LINE SUPPORT L25656 MS 2821 CV4 REPAIR CONTROL VALVE FLANGE L25702 RH 2E12 F092C MANUAL INJECTION VALVE FAILED TO OPEN L25756 NR 2H13 P603 REPA!R DIV 1 ARI TROUBLE ALARM L25848 RH 2E12 F315 EXCESS FLOW CHECK VALVE FAILED L25898 RI 2E51 D011 WATER LEG PUMP DISCHARGE LINE ORIFICE LEAKING L25910 MS 2821 F069 REMOVE STEAM LINE DRAIN VALVE RESTRAINT i,

le lQ l

APPENDIX D l

l REFUELING OUTAGE (L2R05) l SAFETY RELATED CORRECTIVE MAINTENANCE WRNUM SYSTEM EPN DESC L25927 RD 2C11 000 HCU SCRAM VALVE PACKING LEAKING L25928 RD 2C11 0001 038 HCU 06 35 CHARGING WATER CHECK VALVE LEAKING L26027 RD XY-2C11 K925F 46 07 CRD ACCUM ALARM LIT L26028 RI 2SC 2E51 F025 RCIC STEAM SUPPLY DRAIN POT STOP VALVE L26031 MS 2B21 F020 REPLACE THERMAL OVERLOAD L26043 AP 2AP19E 480V SWGR 235X MAIN FEED BREAKER WILL NOT CLOSE IN l

L26076 AP 2AP03E UAT FD TO 241X REMOVE PRC CHUTE FROM UAT l

L26079 NR RE 2C51 N001B SRM 888 FAILED DOWNSCALE l

L26093 MS 2B21 F424 TEST VALVE HAS AIR LEAK L26102 LP 2VYO4C LPCS/RCIC PUMP CUBICLE FAN AUTO TRIP ALARM ENERGlZED L26111 RD XY 2C11 K917C HCU 22 27 ACCUMULATOR ALARM UP L26116 MS FT 2821 NO33A JET PUMP #5 FLOW INDICATOR SPIKING L26130 MS 2B21 F399 2ND STG MSR PRESSURE CONTR01. ROOT VALVE L26162 NR R!f 2C51 K605G LPRM ANNUNICIATOR WINDOW IS IN ALARM L26184 R1 2E51 F361 INSPECT RCIC GOVERNOR VALVE L26186 RP 2RP000 ALTERNATE RPS SUPPLY CALIBRATE L26190 RI 2E51 C002 TIGHTEN RCIC TURBINE MAGNETIC PICK UP i

L26191 NR RY 2C51 K600AA SRM 'A' READS HIGH L26195 NR RY 2C51 K601H IRM 'N' DOES NOT SHOW INDICAil0N L26196 NR RY 2C51 K601F IRM

'F' ERRATIC SPIKING L26208 RP 2C71 S003F ALT E PMA BREAKER "F" TRIP CONDITION L26233 RI 2E51 F033 RCIC COND REllEF VALVE, CURRENT !$ HlGH L26300 R1 2E51 F361 REPAIR RCIC GOVERNOR VALVE STARTREC SIGNAL CABLE L7MOS RD 2C11 000 REPAIR CR0 ACCUMULATOR ALARM l

L97548 RD 2C11 D001 102 REPLACE HCU 50 51 ACCUMULATOR i

L98682 AP 2AP07E REPLACE BUS 243, CUB 1 SAT BREAKER TERMINAL BLOCK l

L99431 NB 2XX000 REPAlR INNER & OUTER VESSEL CAVITY GRATING L99648 AP 2E22 P3018 BUS 243 SAT FREQUENCY METER CUT OF TOLERANCE l

l 1

i

l ll-lc l

ATTACIDENT C l

II.B FORCED REDUCTIONS IN POWER l

GREATER THAN 20% IN DESIGN POWER LEVEL (UNIT 1)

DATE:

930317 OPERATION AT REDUCED POWER:

6 (YYbNDD)

(Hours)

REASON: Main Steam Isolation Valve 1B21-F028C limit switch repair.

CRITICAL ACTIVITY PATH: Repair lim 4.t switch.

CORRECTIVE ACTIONS (DVR/LERN if applicable): None.

i RADIOACTIVITY RELEASE / EXPOSURE OVER 10% ALLOWABLE VALUES: None.

l SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED:

WRNUM SYS EPN DESCRIPTION L22092 MS 1B21-F020C Inaccurate limit switch indication DATE:

930506 OPERATION AT REDUCED POWER:

6.5 (YYbHDD)

(Hours)

REASON: Loss of the 15A Feedwater Heater Normal Drain Valva 1HD029A.

CRITICAL ACTIVITY PATH: Completion of valve maintenance.

CORRECTIVE ACTIONS (DVR/LER# if applicable): None.

RADIOACTIVITY RELEASE / EXPOSURE OVER 10% ALLOWABLE VALUES: None.

SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED: None.

DATE:

930712 OPERATION AT REDUCED POWER:

12 (YYbHDD)

(Hours) l l

REASON: 14A Feedwater Heater Drain Valve controller problems.

CRITICAL ACTIVITY PATH: Complete level controller repair.

CORRECTIVE ACTIONS (DVR/LERN if applicable): None, RADIOACTIVITY RELEASE / EXPOSURE OVER 10% ALLOWABLE VALUES: None.

I SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED: None.

(

l DATE:

931212 OPERATION AT REDUCED POWER:

99.8 l

(YYbNDD)

(Hours) i REASON: 11C Feedwater Heater Normal Drain Valve 1HD072C, blown diaphragm.

l 14C Feedwater Heater Safety Relief Valve 1DV009C leaking, l

l CRITICAL ACTIVITY PATH: Complete valve maintenance.

CORRECTIVE ACTIONS (DVR/LER# if applicable): None.

(

RADIOACTIVITY RELEASE / EXPOSURE OVER 10% ALLOWABLE VALUES: None.

SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED: None.

l l

l

N ie 4

1 =

3 e

, e ATTACHMENT C II.B FORCED REDUCTIONS IN POWER 1

j GREATER THAN 20% IN DESIGN POWER LEVEL j

(UNIT 2)

J j

DATE:

930710 OPERATION AT REDUCED POWER:

6 4

(YYh80D)

(Hours)

REASON: Scram time control Rod 18-39.

J CRITICAL ACTIVITY PATH: Complete scram timing.

CORRECTIVE ACTIONS (DVR/LER# if applicable): None.

RADIOACTIVITY RELEASE / EXPOSURE OVER 10% ALLOWABIE VALUES: None, i

SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED:

WRNUM SYS EPN DESCRIPTION L23299 RD 2C11-D001-127 Control Rod 18-39 drifting DATE:

930710 OPERATION AT REDUCED POWER:

10 (YYM4DD)

(Hours)

REASON: Feedwater Heater Drain forward valve broken.

CRITICAL ACTIVITY PATH: Complete valve maintenance.

CORRECTIVE ACTIONS (DVR/LERN if applicable): None.

RADIOACTIVITY RELEASE / EXPOSURE OVER 10% ALLOWABLE VALUES: None.

SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED: None.

DATE:

930801 OPERATION AT REDUCED POWER:

7

( Y Ybe4DD)

(Hours)

REASON: Inserted Control Rod 25-35 to 00 due to loss of RPIS indication.

CRITICAL ACTIVITY PATH: Troubleshoot and correct loss of RPIS.

CORRECTIVE ACTIONS (DVR/LERN if applicable): None.

RADIOACTIVITY RELEASE / EXPOSURE OVER 10% ALLOWABLE VALUES: None.

SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED:

WRNUM SYS EPN DESCRIPTION L23743 RD XY-2C11-K947 Control rods lost indication

. _ - - - -.