ML20135D228

Annual Rept for LaSalle County Nuclear Power Station for Jan-Dec 1996

ML20135D228
Person / Time
Site:	LaSalle
Issue date:	12/31/1996
From:	Dacimo F COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9703050138
Download: ML20135D228 (86)

Text

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Commonw caith 1.dium Q>mpany lasalle Generating station 2601 North 2ht Road Marseillen, 11.61341-9757 Tei sis.3sw6i February 28,1997 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555

Subject:

Annual Report Enclosed for your information is the Annual Report for LaSalle County Nuclear Power Station for the period January,1996, through December,1996.

If there are any questions or comments conceming this letter, please refer i

them to me at (815) 357-6761, extension 2212.

Respectfully, b

Fred Dacimo Plant General Manager LaSalle County Station Enclosure cc:

A. B. Beach, NRC Region 111 Administrator k

M. P. Huber, NRC Senior Ree! dent inspector - LaSalle f

/'(,oq[j C. Mathews, IDNS Resident inspector - LaSalle

/

lilinois Department of Nuclear Safety - Springfield, IL D. L. Farrar, Nuclear Regulatory Services Manager, NORS y

Institute of Nuclear Power Operations - Records Center GE Representative - LaSalle D. M. Skay, Project Manager - NRR - LaSalle F. Niziolek, Office of Nuclear Facility Safety - IDNS 050016 DCD - Licensing (Hardcopy:

Electronic:

)

Regulatory Assurance Supervisor - LaSalle Central File 9703050138 961231 PDR ADOCK 05000373

$,IEEfkE,IIkIE un.e,m o,,,,n,

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i Annual Report for LaSalle j

County Nuclear Power Station l

January 1996 j

through i

December 1996 i

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TABLE OF CONTENTS TITLE PAGE I.

Introduction.......................................

............2 II.

Annual Reportable Documentation for Unit 1 and 2........

....3 i

A.

Summary of Operating Experience

............3 B.

Unit Outages and Power Reductions

........3 C.

Radiation Exposure...............................

......3 D.

Failed Fuel Elements..

............3 E.

Tests and Experiments Not Desenbed in the Safety Analysis Report...... 3 F.

Changes to Procedures Described in the Safety Analysis Report.......... 4 G.

Summary of Changes to the Facility Which are Described in the Safety An alysis Report..................................

...............16 H.

Survey of Evaluation Results of Chlorine Shipments by Barge on the Illinoi s Rive r..............................................

....................61 1.

Summary of Events Violating Technical Specification 3.4.5 Primary Coolant lodine Spiking Exceeding Allowable Limits...................... 61 Attachment A - Safety Related Maintenance Completed (Non-Outage Related)........ 62 Attachment B - Unit Shutdowns.

................69 Attachment C - Forced Reductions in Power......................

..............79 Appendix A - Critical Path Activities - L1R07 Refuel Outage...

.. 83 Appendix B - Critical Path Activities - L2R07 Refuel Outage..

................84 Appendix C - Safety Related Corrective Maintenance - L1R07 Refuel Outage.

.85 Appendix D - Radiation Exposure.

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Introduction i[

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

is a Boiling Water Reactor with a designed net electrical output of 1078 Megawatts. Waste heat is rejected to a man-made cooling pond using the Illinois River for make-up and blow-down. The architect-engineer was Sargent and Lundy and the contractor was Commonwealth Edison Company.

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

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

Unit two was issued operating license number NPF-18 on December 16,1983.

Initial criticality was achieved on March 10,1984 and commercial power operation commenced on October 19,1984.

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

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II.

Annual Reportable Documentation for Unit 1 and 2 A.

Summarv of Operatinu Experience The summary of the operating experience has been reported monthly in LaSalle's NRC Monthly Reports dated January 1996 through December 1996. For safety related maintenance (non-outage related) performed i

during the period of January through December 1996, see Attachment A.

B.

Unit Outaaes and Power Reductions For unit outages, see Attachment B. For unit power reductions see Attachment C.

C.

Radiation Exposure i

For the radiation exposure of LaSalle Station personnel for the reporting l

period of January 1,1996 to December 1,1996, see Appendix D.

D.

Indications of Failed Fuel Elements i

l On January 15,1996, Unit 2 had indications of leaking fuel. Flux tilting was completed on January 24,1996 and five rods were inserted to suppress power in the leaking bundle. The cycle was completed with rods a

inserted. During core unload, in-core sipping was performed and determined bundle YJ5835, cell 26-47 to be leaking. The cause was still undetermined after a visualinspection. Reinspection of the bundle will be 1

performed at a later date.

E.

Tests and Experiments Not Described in the Safety Analysis Report During this reporting period, January 1,1996 through December 31,1996, there were no tests or experiments conducted that are not described in

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the Final Safety Analysis Report.

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F.

Chances to Procedures Covered in the Safety Analysis Report I

LaSalle Special Test Procedure LST-96-070 Revision 0, Auxiliary Electric Equipment Room and Control Room Pressure and Flow Rate Verification l

The procedure was written to check and adjust Auxiliary Electric Equipment Room and Control Room differential pressure with the Control Room Emergency Makeup System in operation and to verify compliance l

with the UFSAR.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the procedure.

SpecialProcedure LLP-96-120 Revision 0, Administrative Controls for Unit 1 Scram Discharge Volume Hydrolazing in Condition 4 The procedure specifies administrative controls and operator actions to allow hydrotazing of the Unit 1 scram discharge volume while in Condition 4 (Cold Shutdown). This procedure was performed to reduce general area radiological dose rates in the Unit 1 Hydraulic Control Unit (HCU) area.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the special procedure.

Special Procedure LLP-96-119 Revision 0, Isolation ofinstrument Air to Unit 2 Reactor Building The procedure provides guidance to isolate instrument air to the Unit 2 i

reactor building to allow maintenance to be performed on various valves.

This procedure was performed while the Unit 2 reactor vessel was defueled and the fuel pool gates were installed in the Unit 2 spent fuel pool.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the special procedure.

Procedure LOP-FC-20 Revision 0, Reactor Cavity Grating Area Removal The procedure provides guidance for the setup, coordination, and performance of draining water below the reactor cavity gratings following reactor cavity draindown. This provides for proper handling and l

processing of water.

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The 10CFR50.59 safety evaluation concluded that there was no unreviewed safety questions associated with the procedure.

Procedure LOP-ZZ-07 Revision 0, Miscellaneous Temporary Installations To Support Refuel Outages The procedure provides guidance for the installation of temporary equipment and temporary configurations that are usually installed to support refuel outage activities.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the procedure.

Interim change to Procedure LOP-WF-30 Revision 3, Generic Transfers and Draining / Filling Procedure Underground water has been leaking into the Ice Melting Pit area. The procedure change allows routing leakage to the Fire Sump instead of the Dewater Sump Pit. The water coming off of the wall will be accumulated in a catch container without contacting the floor of the pit.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the procedure change.

Procedure LOA-PF-01 Revision 6, Malfunction and Manual Closure of Water Tight Doors, and Deletion of Procedure LOS-PF-Q1 Revision 7, Quarterly / Water-Tight Door Surveillance Procedure LOA-PF-01 provides contingencies for the replacement of CSCS-ECWS pump room doors D-13, D-15, D-16, and D-17. The procedure was evaluated for temporary arrangements associated with the activities required to replace the doors. Trained personnel will stand flood and fire watches as needed during the replacement activities.

The testing requirements of LOS-PF-Q1 were incorporated in procedure LTS-1000-29.

The 10CFR50.59 safety evaluation concluded that there was no unreviewed safety question associated with the procedure revision and the procedure deletion.

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Evaluation of Procedure LOA-AP-08 Attachment F Revision 11 for Station Blackout Concerns The procedure was evaluated for an inconsistency in UFSAR Table 15.9-2 with regards to the DC load shedding during a Station Blackout Event in a specified time frame. Calculations showed that the batteries have adequate capacity to support either load shedding scheme.

The procedure was revised to agree with the UFSAR Table.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the procedure revision.

Procedures LGA-MS-01 Revision 4, Main Steam isolation Heat Sink, and LGA-VR-01 Revision 4, Reactor Building Ventilation Startup i

Following System isolation l

i The subject procedures were revised to reflect plant changes to Unit 1 as a result of Modification M01-1-9500482, which modified the leak detection logic for Unit 1 main steam tunnel high temperature leak detection and the delta T isolation logic.

The 10CFR50.59 safety evaluations concluded that there were no unreviewed safety questions associated with the procedure revisions.

Procedure LTS-300-5 Revision 20, Local Leak Rate Test 0.6 La Accountability Program The procedure was revised to incorporate Option B of 10CFR50 Appendix J, as well as associated regulatory and technical guidance.

I Allowable Main Steam Isolation Valve (MSiV) leakage was increased based upon approved license amendment numbers 110 and 95 for Units 1 and 2, respectively, for the station Technical Specifications.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the procedure change.

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Procedure LTS-1000-29 Revision 5, Water Tight Doorand Penetration inspection The procedure provides contingencies for the replacement of CSCS-ECWS pump room doors D-13, D-15, D-16, and D-17. The procedure was evaluated for temporary arrangements associated with the activities required to replace the doors. Trained personnel will stand flood and fire watches as needed during the replacement activities.

The 10CFR50.59 safety evaluation concluded that there was no unreviewed safety question associated with the procedure revision.

Procedure LFP-400-6 Revision 2, Installation and Operation of Sipping Equipment The procedure change incorporates instructions for installation and operation of new in-mast sipping equipment. Recent advances have developed means to perform fuel assembly sipping while performing core off-load. This procedure provides the guidance for using this equipment.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the procedure.

Procedure LAP-1300-6 Revision 6, System, Component and Temporary Labeling The proceaure was revised to remove components specific to the practical aspects of system and component labeling such that the procedure provides the administrative guidance / controls for system and component labeling. Practical aspects of label construction and application were placed into an administratively controlled Labeling Guide.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the procedure revision.

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Administrative Procedures LAP-200-1 Revision 32, Operating Department Organization; LAP-200-3 Revision 28, Shift Change; LAP-200-5 Revision 7, Transfer of ControlRoom Command Functions Between the Control Room Unit Supervisors, The Shift Manager and/or WCC SRO; LAP-200-10 Revision 3, NRC Operator License Active Status Maintenance and Reactivation; LAP-1600-2 Revision 51, Conduct of Operations; and update to UFSAR Sections 9.1,13.1, and 13.2 The procedure revisions consisted of changing the title of " Shift Engineer" to " Shift Manager"; the requirement for a Field Supervisor to hold an SRO license was removed; references to the Field Supervisor fulfilling the minimum staffing positions were deleted; references to licensed Field Supervisor were changed to Work Control Center (WCC) SRO; the reference to the Control Room Supervisor was changed to the Unit

}

Supervisor. UFSAR Sections 9.1,13.1, and 13.2 were correspondiFiy J

revised.

These changes were done to make current plant staffing titles consistent, in order to remove confusion related to what positions are qualified to fulfill the minimum manning requirements of the Technical Specifications.

J The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the procedure revisions and the UFSAR change.

l Procedure LLP-96-056 Revision 0, Reactor Water Cleanup Lineup for Heat Exchanger Cleanup i

T he procedure allows for flushing the Reactor Water Cleanup (RWCU) regenerative heat exchangers with hot water to remove resins that may be trapped within the heat exchangers. This process then discharges the water through the non-regenerative heat exchangers to cool the mixture, prior to discharge to the reactor building equipment drain tank.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the procedure.

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1 LLP-96-016 Revision 0, installation / Removal of Temporary 24 Volt j

Battery Charger l

The procedure provides guidance for the installation, operation, and removal of a temporary 24 VDC battery charger with the affected unit on line. The procedure allows for maintenance to be performed on the permanent charger, by connecting a temporary charger to avoid discharging the batteries while the normal charger is de-energized for repairs.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the procedure revision.

l Procedure LLP-96-054 Revision 0, Un t 2 Turbine Control Valve #3 Closure input Signal The procedure outlines steps to install a jumper to simulate a test closure of turbine control valve #3 and to control the removal of the jumper during the test. The jumper inputs a closed signal to the control valve. This was done while the valve was stuck closed. The jumper prevented the valve i

from inadvertently opening and initiating a plant transient event.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the procedure.

Procedure LLP-96-052 Revision 0, Reactor Water Cleanup System (RWCU) - Placing a Filter /Demineralizer in Service with increased System Flow The station increased flow through the RWCU system to not more than 165 gpm per RWCU pump, for a maximum total flow of 330 gpm. The increased flow accelerates cleanup of the reactor coolant in an effort to reduce conductivity values to acceptable levels.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the procedure.

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LLP-96-016 Revision 1, installation / Removal of Temporary 24 Volt i

Battery Charger The procedure provides guidance for the installation, operation, and removal of a temporary 24 VDC battery charger with the affected unit on line. The procedure allows for maintenance to be performed on the i

permanent charger, by connecting a temporary charger to avoid i

discharging the batteries while the normal charger is de-energized for repairs.

4 The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the procedure revision.

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Procedure LLP-96-044 Revision 0, Operational Verification of Unit 1 "A" Pressure Regulator While At Pressure The procedure provides for methodical removal of the 1 A pressure i

amplifier from service to perform a functional verification of the pressure transducer and demodulator circuit while the reactor is at low pressure, i

typically below 25% rated core thermal power.

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The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the procedure.

Procedure LLP-96-098 Revision 0, Temporaryincrease in Flow Through the Rsator Water Cleanup (RWCU) System The procedure outlines the steps necessary to place a filter /demineralizer in service, and operate the RWCU system with increased flow. The flow through the rystem was increased to not more than 165 gpm per pump for a total maximum of 330 gpm menured at the filter flow recorders. The increase was desirable to accelerate cleanup of the reactor coolant in an i

effort to bring reactor coolant chemistry to within specified limits.

i The 10CFR60.59 safety evaluation concluded that there were no unreviewed safety questions associated with the procedure.

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Procedure LLP-94-069 Revision 1, VJ Exhaust and Supply Fan Shutdown i

The procedure provides instructions to shut down the VJ exhaust fan OVJ02C and supply fan OVJ01C to prevent an unmonitored release to the environment. The procedure was revised to conform with current station practice regarding the installation of Temporary Alterations and provided the steps to return the VJ system to normal operation.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with this procedure.

Procedure LLP-96-070 Revision 0 and Temporary Alteration (TALT) 1-0086-96 The procedure provides guidance to line up the 0,1 A, and 2A Diesel Generator (DGs) coolers to the Fire Protection system for a loss of Core Standby Cooling Systems (CSCS) concurrent with loss of offsite power.

The TALT was written to provide the lineup for alternate cooling to the subject DG coolers using the Fire Protection system in conjunction with the procedure.

The 10CFR50.59 safety evaluations concluded that there were no unreviewed safety questions associated with the procedure and the TALT.

Procedure LLP-96-075 Revision 0, Unit 1 Division 1 Battery Charger Troubleshooting and Repair Procedure The procedure administratively controlled troubleshooting, repair, and switching sequences of the Unit 1 Division 1 Battery Charger.

I The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the procedure.

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Procedure LLP-96-094 Revision 0, Manual Control of VR Supply Flow The procedure provides instructions to take manua! control of reactor i

building ventilation (VR) supply flow controller to allow calibration of the supply flow control and indication loop. A test box was installed to manually control the position of the reactor building ventilation supply i

damper. The test box was installed and removed with the reactor building ventilation system shut down.

The 10CFR50.59 safety evaluations concluded that there were no unreviewed safety questions associated with the procedure.

Procedure LLP-96-089 Revision 0, Unit 2 Turbine Control Valve #2 Closureinput Signal The procedure outlines steps to install a jumper to simulate a test closure of turbine control valve #2 and to control the removal of the jumper during the test. The jumper inputs a closed signal to the control valve. This was done while the valve was stuck closed. The jumper prevented the valve from inadvertently opening and initiating a plant transient event.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the procedure.

Procedure LLP-96-089 Revision 1, Unit 2 Turbine Control Valve #2 Closure input Signal 2

The procedure outlines the steps for installation of a jumper to input a close signal to the valve. This was done following observed oscillations 1

in turbine control valve #2. The installed jumper allowed for the continued operation of the Unit 2 turbine generator with the #2 control valve closed, preventing the control valve from opening or closing unexpectedly.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the procedure revision.

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Procedure LLP-96-077 Revision 0, Flushing the Chemical Waste i

Concentrator Prior to WZ Room Recovery The special procedure was written to provide guidance for flushing the WZ evaporator heating element after the WZ evaporator has been shut down. This allows residual contents in the heating element to be flushed to the floor to allow for room recovery in the wake of the heating element failure.

2 The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the procedure.

LLP-96-097 Revision 0, Final Flushing of SH System and Glycol Fill The procedure provides the directions to perform a Snal flush of the entire station heat recovery system (SH), the removal of chemicals from the system, and the filling of the system with glycol.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the procedure.

LP-96-069 Revision 0, Processing of Floor Drain Collector Tanks Through the Unit 2 Floor Drain Domineralizers The procedure provides guidance to operate the Unit 2 floor drain demineralizers, using a temporary setup to process collector tanks while evaporators are unavailable. Floor drain water is typically processed through evaporators. The procedure allows for an alternate processing configuration if the evaporators became unavailable.

i The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the procedure.

Procedure LST-96-040 Revision 1, Reactor Water Level Control Troubleshooting, and UFSAR Section G.2.2.1.3.1 Update The procedure includes steps to bypass, then re-enable cavitation interlocks of the Reactor Recirculation (RR) system pumps. This prevents inadvertent downshifting of the RR pumps during pump testing. UFSAR Section G.2.2.1.3.1 is revised to describe the use of administratively controlled keylock switches to bypass RR pump cavitation interlocks.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the procedure and the UFSAR changes.

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I Procedure LST-96-045 Revision 0, Unit 1 Division 1 Battery Charger Troubleshooting Procedure i

The procedure administratively controlled the troubleshooting and switching sequences associated with the subject battery charger.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the procedure.

Procedure LST-96-046 Revision 0, Unit 1 Division 1 Battery Charger Silicon Controlled Rectifier (SCR) And Other Power Connections Tightening Test Procedure The procedure administratively controlled the crosstie sequencing between Unit 1 Division 1 and Unit 2 Division 1 for tightening accessible power connections on the Unit 1 Division 1 battery charger.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the procedure.

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Summary of Chanaes to the Facility Which are Described in the Safety

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Analysis Report Acceptance of Siemens Power Corporation (SPC) Powerplex Core Monitoring Code The General Electric (GE) Core Monitoring Code (CMC) is being replaced with the SPC Powerplex core monitoring code due to the transition to SPC fuel. Powerplex is the NRC approved Siemens code for monitoring core thermal limits. Powerplex will be instal led for the Unit 2 Cycle 8 core loading, which consists of Siemens and GE fuel assemblies. The code will also be used for Unit 1 startup following the L1F35 forced outage.

UFSAR Sections 7.7.7.1 and 7.7.7.2 are revised to reflect the use of the Powerplex core monitoring code.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the implementation of the i

new core monitoring code.

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l UFSAR Update for Mislocated and Misoriented Fuel Assembly UFSAR Sections 4.4.2 and 15.4 were revised to reflect the Siemens Power Corporation (SPC) misloaded bundle analysis. Other changes are associated with the analysis of misoriented and mislocation of Siemens fuel bundles.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the proposed change.

UFSAR Update to Reflect the Updated Low Power Rod Withdrawal ErrorAnalysis UFSAR Section 15.4.1.2 describes the low power Rod Withdrawal Error (RWE) event, its consequences, and the setpoints assumed in the analysis. Credit is taken for the Avereqe Power Range Monitor (APRM) scram in the startup mode at 15% rated core thermal power (RCTP).

Table 7.3-4 lists the trip setpoint as 15%, the allowable as 0% RCTP, and the analytical limit as 25% RTCP. The change is based on a General Electric analysis dispositioning this event for a setpoint of 25% RCTP.

UFSAR Table 7.3-4 and Section 15.4.1.2 are revised to reflect an allowable scram value of 20% RCTP.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the proposed change.

UFSAR Update for the Evaluation of VesselInternals and Fuel Loadings for Siemens Fuel UFSAR Sections 3.0,3.7, and 3.9 are revised to incorporate the vessel internals and fuel loadings for the introduction of Siemens Power Corporation (SPC) ATRIUM-98 fuel. Siemens evaluated seism;c/LOCA loadings on the fuel and internals, performed a bundle lift analysis, and evaluated structural deformation during a LOCA, with regards to control blade insertability.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the proposed change.

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Deletion of References to UFSAR Section 15.B t

j The references to UFSAR Section 15.B are deleted in Sections 15.1, 15.2,15.4, and 15.6.

The 10CFR50.59 safety evaluation concluded that there were no l

unreviewed safety questions associated with the change.

I Update of UFSAR Associated with the Mechanical Vacuum Pump i

Licensing Amendments Amendment No.101 to Facility Operating License No. NPF-11 (Unit 1) i and Amendment No. 85 to Facility Operating License No. NPF-18 (Unit 2) j resolved an unreviewed safety question related to the operation of main condenser mechanical vacuum pump upon receipt of a main steam line high radiation alarm. UFSAR sections 2.3.4.1,2.3.4.4,10.4.2.2, l

11.5.2.1.4,15.0.5, and 15.4.9 were revised due to the license j

amendments.

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The proposed changes to sections 10.4.2.2,11.5.2.1.4, and 15.4.9 revise the UFSAR to agree with the actual design of the mechanical vacuum pump. Previously, UFSAR sections 11.5.2.1.4 and 15.4.9 incorrectly j

indicated or assumed that the mechanical vacuum pump automatically trips on high main steamline radiation, and UFSAR section 10.4.2.2 incorrectly indicated that the mechanical vacuum pump also trips on high station vent stack radiation. Therefore, these UFSAR sections are revised to reflect the fact that this pump does not automatically trip on a signal from either the main steamline or station vent stack radiation monitors. In addition, UFSAR section 15.4.9 is revised to reflect the change in the consequences of the Control Rod Drop Accident (CRDA) since the original analysis assumed that the mechanical vacuum pump was automatically tripped at the beginning of the accident.

UFSAR sections 2.3.4 (items 1 and 2 above) and 15.0.5 are revised to reflect the changes in the meteorological paremeters used in the new CRDA analysis. The previous CRDA analysis utilized the arbitrary meteorological parameters of Regulatory Guide 1.3. The new CRDA analysis uses more realistic parameters which were calculated in accordance with Regulatory Guide 1.145.

The proposed changes to UFSAR sections 2.1.4 and 15.0.5 are based on the Regulatory Guide 1.145 meteorological analysis performed by S&L and the proposed changes to UFSAR section 15.4.9 are based on the CRDA analyses performed by GE.

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The application for amendment to the Unit 1 and 2 operating licenses was approved by LaSalle Onsite Review 93-043, and submitted to the NRC per letter cated September 10,1993, with supplemental letter dated November 17,1993. The license amendments were approved by the NRC per letter dated July 26,1994. The proposed changes to the UFSAR were approved by Onsite Review 96-037.

The 10CFR50.59 safety evaluation concluded that there was no unreviewed safety question associated with the design change.

UFSAR Clarifications as a Result of Electrical Separation Design Basis Document (DBD) Preparation UFSAR Sections 7.1.3.4.3,8.3.1.4.2, and 8.3.3.1 were revised following the preparation of the subject DBD.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with this activity.

Clarification to the UFSAR with regards to Emergency Core Cooling System / Core Standby Cooling System (ECCS/CSCS) Area Cooling UFSAR Section 9.4.5.3 and Table 9.4-20 were revised in ordar to clarify ECCS/CSCS cooling.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with this activity.

UFSAR Update for Continuous Operation of the Post LOCA H2/02 Monitoring Panels UFSAR Section 6.2.4.2.2, Table 6.2-21 (sheets 6D, 8D, and 9), and Section 7.5.2.2.2.1 are revised to reflect the use of the panels for continuous sampling of primary containment oxygen concentration during normal operation. The post-accident design function of the panels is j

maintained by adhering to vendor recommendations and Environmental Qualification (EO) requirements.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with using the panels for continuous sampling during power operation.

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Temporary Alteration 1-0019-96 Revision 1 The temporary alteration installed a keyed switching jumper to allow the i

Operations department to readily take detector zones 1-16,1-16P,1-30, 31, 32, and 33 out of service (OOS) by placing the switch in the OFF position. Operations used the OOS administrative procedure to control the position of the switch. The keyed switch was installed to provide the ability to remove individual zones from service without lifting leads. This change allowed individual zones to be removed from service operations for the duration of the L1R07.

The 10CFR50.59 safety evaluation concluded that there was no unreviewed safety question associated with the temporary alteration.

Temporary Alteration (TALT) 1-0107-96, Install A Switched Jumper for the 1A(B) Reactor Recirculation (RR) Flow Control Valve (FCV)

ActuatorDrain Alarm The TALT installed a switch jumper in the 1 A(B) RR FCV actuator drain alarm logic to allow clearing of the common alarm to permit monitoring the receipt of other alarms.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the temporary alteration.

Temporary Alteration (TALT) 2-0078-96, WS Supply for Condenser Tube Cleaning The TALT provides for a source of service water (WS) from line 2WS78A-2" to support cleaning of the Unit 2 main condenser tubes during the Unit 2 seventh refuel outage (L2R07).

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the temporary alteration.

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i Temporary Alteration (TALT) 1-0101-96, Install Switch Jumper for the 1B Reactor Recirculation (RR) Flow Control Valve (FCV) Actuator Drain Alarm The TALT installed a switch jumper in the 1B RR FCV actuator drain alarm logic to allow clearing common alarm R0964 to permit monitoring the receipt of other alarms.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the temporary alteration.

UFSAR Update to Reflect the Storage of Siemens Power Corporation (SPC) Fuelin the New Fuel Vault and Spent Fuel Pools UFSAR Sections 3.1.2,4.3.2,9.1.1, and 9.1.2 are revised, and new UFSAR Section 9.1.5 is added to reflect the storage of Siemens fuel in the vault and pools. The Siemens fuel design is compatible with fuel handling equipment, as well as the vault and pool storage areas.

Analyses demonstrate that the higher enrichment SPC fuel may be safely stored in the new fuel vault and the spent fuel pools. Effects on the Unit 2 boraflex racks is independent of fuel design.

The 10CFR50.59 safety evaluation concluded that there were no 4

unreviewed safety questions associated with the storage of SPC fuelin LaSalle's new fuel vault or spent fuel pools.

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1 Update to UFSAR Figure 7.6-3 and Section 7.7 Update to UFSAR Figure 7.6-3 and Section 7.7 are revised to reflect the actual plant configuration of the source range monitors (SRMs) and the j

intermediate range monitors (IRMs).

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The 10CFR50.59 safety evaluation concluded that there were no j

unreviewed safety questions associated with this activity.

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Update of UFSAR to reflect conformance to Regulatory Guides and the Description of the Records Storage Area UFSAR Chapter 17, Quality Assurance Records, and Appendix B, Conformance to Regulatory Guides, were revised to incorporate QA Topical Report CE-1-A, Revision 65a, to reflect the obsolescence of Regulatory Guide 1.88 Revision 2, and to update the description of the records storage areas in the South Service Building.

The ANSI standards previously endorsed by Regulatory Guide 1.88 Revision 2 were incorporated into ANSI /ASME NOA-1-1983, " Quality Assurance Program Requirements for Nuclear Facilities" Maintenance of Quality Assurance records continues to be maintained in accordance with NOA-1-1983, Supplement 17S-1, in accordance with CE-1-A. The requirements of 10CFR50 Appendix B, Article XVil, Quality Assurance Records, and 10CFR71.135, Quality Assurance Records, continues to be met. The proposed revision incorporates changes previously approved by the NRC.

j The 10CFR50.59 safety evaluation concluded that there was no j

unreviewed safety question associated with the design change.

20

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1 Change to UFSAR Section 7.7.14.1.2.1 UFSAR Section 7.7.14.1.2.1 is revised to correct the description of power supply for the offgas post treatment monitors. The actual power source for the monitors is 124-VDC. Accordingly, the description of the power supply is changed to 124-VDC Buses A and B. This is consistent with FSAR Section 11.5.2.1.2. There are no resultant changes to plant systems or components.

The 10CFR50.59 safety evaluation concluded that there was no unreviewed safety question associated with this change.

Revision to UFSAR Section 2.3.3.1, Meteorolog! cal Tower i

Description The UFSAR is amended to state that the tower doesn't meet the siting criteria of Regulatory Guide 1.23 and ANSI /ANS 2.5 (1984) for the 10 i

meter wind direction and wind sp9ed measurements The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the UFSAR change.

Update to UFSAR Section H.4.2.57, Safe Shutdown Analyses for Unit 1 Fire Zone 5C11 and Unit 2 Fire Zone 5C11, and Associated Tables The subject UFSAR Section and associated tables are revised to reflect the new safe shutdown path that has been established for use in the event of a fire in Unit 1 Fire Zone SC11 and Unit 2 Fire Zone SC11.

UFSAR Tables H 4-50, H.4-51, H.4-55, H.4-56, H.4-57, H.4-59, H.4-60, H.4-62, H.4-64, H.4-65, and H.4-66 are revised to reflect the safe shutdown equipment and cabling located in Unit 1 Fire Zone SC11 and Unit 2 Fire Zone SC11.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with this activity.

4 21

Update to UFSAR Section 9.2.2.2 for Service Water (WS) System Strainer Mesh Size UFSAR Section 9.2.2.2 was revised to indicate that the WS strainers will remove suspended matter which is greater than 1/8" in size. This changes the previous text which states that matter greater than 1/16" in size is strained out.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the revision to UFSAR Section 9.2.2.2.

1 UFSAR Update per DCR 94-030, Removal of Abandoned Pipe Whip Restraint 1R-50 The design change removed the abandoned pipe whip restraint. UFSAR Table 3.6-3 and Figure 3.6-14 are accordingly revised.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the change.

Revision to UFSAR Table 3.8-1, Containment Penetrations I

UFSAR Table 3.8-1 was revised to reflect present plant design. It includes the latest information from the Containment Penetration Schedule Drawings (Mechanical, Electrical, Instrument), Electrical Installation Drawings (Reactor Building), and UFSAR Table 6.2-21 (summary of lines penetrating the primary containment).

The 10CFR50.59 safety evaluation concluded that there were no 2

unreviewed safety questions associated with the change.

1 Correction to UFSAR Section 9.1.3.71 l

The wording in Section 9.1.3.1.1 associated with the fuel pool cookng system heat removal capability was corrected. Service water temperature pertains to fuel pool cooling capacity, not Maximum Normal Heat Load.

The change corrected the location of the wording. The addition of the l

service water temperature assumed in the heat removal calculation for i

fuel pool cooling heat exchangers was incorrectly placed in the sentence concerning the Maximum Normal Heat Load to be removed from the fuel pool.

t t

22

i Tha 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with this change.

Diesel Generator 2A Ground Relay Replacement and UFSAR Update, Exempt Change E01-2-94-960E The exempt change replaced DG-2A neutral ground relay 2459-DG012.

The previous neutral ground relay, a Basler type PRV-120 overvoltage relay, was replaced due to obsolescence. Parts and repair services are no longer available. The replacement voltage relay is a GE type IAV, model no.12lAV51D1 A. The new relay performs the same function and meets or exceeds the original equipment specifications.

UFSAR Table 8.3-2 is affected by this replacement, since the table lists -

the relay 'ype for the reverse power relay. However, instead of revising the table to identify the type of the replacement relay, the change consists of replacing the relay type with a note that refers the reader to the Q-List to obtain the relay manufacturer and model number.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the exempt change.

Revision to UFSAR Appendix B, Conformance to Regulatory Guides i

UFSAR Appendix B is revised to reflect license amendments No.109 and 94 for Unit 1 and 2, respectively. The UFSAR change incorporates Regulatory Guide 1.9 Revision 3, and exceptions that LaSalle has taken to the Regulatory Guide.

)

The 10CFR50.59 safety evaluation concluded that there was no unreviewed safety question associated with this change.

Pressere Relief Hole in RHR Suction Cooling Outboard Isolation Valve 1E12-F008 Upstream Disc, Exempt Change E01-1-9500346 i

The design change drilled a 1/4" vent hole in the upstream (reactor recirculation) side disc of the 1E12-F008 valve. The purpose of the hole is to prevent pressure or hydraulic locking of the valve.

UFSAR Table 6.2-21, Summary of Lines Penetrating the Primary Containment, is revised to reflect that the 1 E12-F008 valve has a vent hole drilled in its reactor / upstream side disc.

The 10CFR50.59 safety evaluation concluded that there was no unreviewed safety question associated with the design change.

23

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4 Update of UFSAR for Motor Operated Valve Thermal Overload Settings i

UFSAR Section 6.3.2.2.13 is revised to indicate that the thermal overloads for the Hydrogen Recombiner (HG) system MOVs are not i

required to be bypassed under accident conditions, and to provide the i

design bases for their trip setpoints. UFSAR Section 8.3.1 is revised to delete redundant information, and to refer to 6.3.2.2.13 for information on MOV thermal overload circuit design.

The 10CFR50.59 safety evaluation concluded that there was no unreviewad safety question associated with the design change.

Changes to Correct discrepancies found dunng renew of UFSAR

\\

Chapters 9,10, and 11 The associated safety evaluations for the below change activities concluded that there were no unreviewed safety questions involved with the changes.

Per Onsite Review 96-038, the following sections are revised:

9.2.2.2, Service Water System Description 11.2.1.7.8, Refueling and Maintenance Outages 11.2.1.9.1, Normal Operations 1.2.1.10.b, Tank Level Control 11.2.1.10.c, Tank Level Control i

11.2.2, Radwaste System Description 11.2.2.4, Laundry Waste Subsystem 11.2.2.5.5, Concentrator Waste Tanks i

11.2.2.8, Control and Instrumentation i

Table 11.2-3 sheet 2, Liquid Radwaste System Components and Design Parameters 11.4.1.3, Types of Waste Table 11.4-2, Expected and Design Annual Volumes of Solid Waste i

Management System Output Per Onsite Review 96-040, the following sections are revised:

11.2.2.5, Sludge Subsystems 11.2.2.5.1, Spent Resin Tank 11.2.3.1, Criteria for Recycling 11.4.1.1, Solid Waste Management Power Generation Design Basis 1

11.4.1.2, Safety Design Basis 24

i 11.4.2.2, Decanting Station 11.4.2.3, Drumming Station 11.4.2.4, Drum Handling Equipment 11.4.2.5, Smear Test and Label Station Table 11.4-1, Solid Waste Management System Equipment and Storage Design Capabilities-Radwaste Building Figure 11.4-1, Radwaste Disposal System Flow Diagram Per Onsite Review 96-041, the following sections are revised:

9.3.3.5, Floor and Equipment Drain System, instrumentation Application 10.4.6.5, Condensate Polisher System, instrumentation Application 11.2.1.7.4, Condenser Tube Leakage 11.2.2.3, Chemical Waste Subsystem 11.2.3.2, Release Assumptions Table 11.2-6, Maximum and Expected inputs to Radwaste Systems Table 11.4-2, Expected and Design Annual Volumes of (Units 1 & 2) Solid Waste Management System Output UFSAR Update for Diesel Generator 1A Neutral Ground Relay Replacement per Exempt Change E01-1-94-960-A The exempt changu revised the DG-1 A neutral ground fault trip circuit.

The previous neutral ground relay, a Basler type PRV-120 overvoltage relay, was replaced due to obsolescence. Parts and repair services are no longer available. The replacement voltage relay is a GE type IAV, model no.12lAV51D1 A. The new relay performs the same function and meets or exceeds the original equipment specifications.

The UFSAR Table 8.3-2 lists the relay type for the reverse power relay.

The table was revised to reference the reader to the 0-list to obtain the appropriate replacement relay information instead of documenting it on the table.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the design change.

25

i i

v Unit 2 Diesel Generator A (DG 2A) Reverse Power Relay Replacement and UFSAR Change, Exempt Change E01-2-94-960-F The exempt change replaced DG 2A reverse power relay 2432-DG009.

The previous reverse power relay, Basler type PRP-110, was replaced 4

due to obsolescence, and parts and repair services were no longer available for the relay. The replacement relay is a GE type ICW, model no.12lCW51 A2A, directional power relay. The new relay performs the same function as the previous relay and meets or exceeds the original equipment specifications.

UFSAR Table 8.3-2 is being revised since it lists the type of reverse power relay. However, instead of revising this table to identify the type of the replacement relay, the proposed change replaces the relay type with a note in Table 8.3-2 that refers the reader to the Q-List to obtain the relay manufacturer and model number.

The 10CFR50.59 safety evaluation concluded that there was no unreviewed safety question associated with the exempt change.

Update of UFSAR Associated with the implementation of Hydrogen Water Chemistry on LaSalle Unit 1, Design Change Package (DCP) 9500085 i

Hydrogen Water Chemistry (HWC) is implemented at LaSalle County Station Unit 1 in order to reduce intergranular stress corrosion cracking (IGSCC) rates of reactor recirculation piping and reactor vessel lower internals. Hydrogen injection into the reactor condensate is the primary means of suppressing the concentration of free dissolved oxygen in i

reactor water.

UFSAR Sections 7.7 and 11.3 are revised to reflect the irnplementation of HWC on Unit 1.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the design change.

Generic Evaluation for Replacing 1/2-inch a GouldInstrument Stop Valve with an Anderson Greenwood Valve The evaluation was performed to document the technical acceptance of replacing a 1/2-inch Gould valve (part number 30124400) with an Anderson Greenwood Company valve (part number H7HPS-4QB-XAP) in applications where the Gould valve functions as an instrument stop valve located in a dead-leg instrument line. A dead-leg instrument line is 26

i i

considered an instrument line having no flow. The existing Gould valves are not seating properly, resulting in potential bypass leakage. Operators 4

have to isolate the upstream root valve to perform monthly instrument surveillances, resulting in unnecessary personnel radiation exposure.

The current valve model is no longer available, and a suitable replacement is required.

The 10CFR50.59 safety evaluation concluded that there was no i

unreviewed safety question associated with the generic evaluation.

l Weld Repairs to Fuel Pool Emergency Makeup Pumps 1FC03PA and 2FC03PB The weld repairs involved the use of stainless steel to rapair the carbon steel casings of the subject pumps, in order to restore the original minimum wall thickness. The weld repairs were performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code. UFSAR Section 9.2.1.2 is revised to reflect the use of stainless steel in repairing the carbon steel casings.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the weld repairs.

Laundry Prefilter Assembly 0WY03F Piping Replacement per Modification M01-0-93-001 The subject modification replaced hoses on the prefilter assembly with hard piping. Normal effluent treatment will be accomplished by the prefilter assembly, as opposed to the laundry reverse osmosis (RO) unit.

The RO unit has been out of service for several years due to a rupture caused by bacterial growth. This modification cleared Temporary System Change (TSC) 1-0404-90.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with this modification.

Diesel Generator 0 Underfrequency Relay Replacement per Component Replacement C01-0-94-007-A The design change replaced the O Diesel Generator Underfrequency relay. The previous Basler type PRF-120 relay was replaced due to obsolescence. The replacement is an ABB Type ITE-81, model no. 422C1276-1 frequency relay. The new relay performs the same function and meets or exceeds the original equipment specifications.

27

l UFSAR Table 8.3-2 is revised with a note that refers the reader to the Q-List to obtain the relay manufacturer and model number.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the design change.

Installation of 120 VAC Voltage Regulating Transformer, Design i

Change Package (DCP) 9500025 The design change added a voltage regulating transformer in the 120 VAC distribution circuit for Motor Control Center (MCC) 136X-1, i

Circuit #5, the feed for the Post LOCA Containment Monitoring control circuit. The design change improves the voltages at the loads fed by this circuit during normal and abnormal system conditions.

1 The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the design change.

BUS 242Y Relay Settings Change on 2AP070A, 70B, and 90, Design Change Package (DCP) 9300193 The DCP reset the setpoints for the 4.16 kV side phase overcurrent relays and transformer neutral ground overcurrent relay for transformer 236X.

The setpoints were adjusted to maintain coordination of these relays with the General Electric RMS-9 trip unit installed on the main feed breaker for 480 VAC switchgear 236X.

3 i

The 10CFR50.59 safety evaluation concluded that there was no unreviewed safety question associated with the design change.

Install Spoolpiece On Drum Processing Unit (DPU) Piping Design l

Change Package (DCP) 9300312 The design change installed a removable spoolpiece on the pipe flushing i

line of the "B" DPU. The removable spoolpiece a' lows access to the "A" i

l DPU pipe chase.

The 10CFR50.59 safety evaluation concluded that there was no unreviewed safety question associated with the design change.

i 28

i Unit Auxiliary Transformer (UAT) 141 CO-2, CO-7 & ITH Protective Relay Addition, Design Change Package (DCP) 9300071 (Modification M01-1-93-019)

The DCP modifies the subject relay protection to the level required by the company standard, specified in System Planning Department Memo 4-1.

The following overcurrent relay additions were required:

A transformer low voltage (LV) lead differential scheme (CO-2 relays, ground differential), using high speed overcurrent relays, was installed as l

primary protection for phase to ground faults in the transformer LV l

windings or leads.

j i

A time overcurrent relay (CO-7 relay, transformer low voltage breaker back-up) was installed to provide back-up protection in the event that the Unit Auxiliary Transformer LV breaker fails to interrupt for a LV bus multiphase fault. It also provides back-up protection for transformer internal or LV lead multiphase faults.

The transformers previously used differential relays which could saturate for heavy multiple internal faults. To insure high speed operation for severe saturation, a solid state instantaneous overcurrent (ITH) relay is l

provided for high speed overcurrent back-up protection. The ITH relay addition provides back-up protection to mitigate transformer damage due to heavy internal faults.

The modification also installed new panel 1PA18J, which is located in the Unit 1 Auxiliary Electric Equipment Room (AEER).

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the design change.

Operation of the RHR Pumps 1A/2A Without Cooling WaterFlow to VY Room Cooler-Shutdown Cooling or Test Modes, Design Change Package (DCP) 9600520 l

When Residual Heat Removal (RHR) pump 1 A or 2A run, cubicle cooler fans 1VYO1C or 2VYO1C also run, which blows air over the low temperature coils being supplied by the 0 Diesel Generator (DG) cooling water pump, ODG01P. The DCP temporari!y prevents the water from l

ODG01P from flowing, unless ODG01P is manually started, or, if either a l

high drywell pressure or reactor low water level condition exists that l

initiates 0 DG operation. This DCP assists in maintaining a warm room j

l temperature in the northwest cubicle area of RHR pumps 1 A and 2A.

i f

4 29

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the design change.

Temporary Heating Supply for Turbine Building (VT System) and Reactor Building (VR System) Station Heating Coils, Design Change

\\

Package (DCP) 9600509 The DCP installed a temporary power feed from Unit 2 switchgear 231X to temporary electric heaters and associated ducts as maintenance support for station heat recovery system coil repairs and to prevent further freezing. The heat was needed to support maintenance activities while VT and VR are in operation.

l The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the design change.

Temporary Heating Supply for Turbine Building (VT System) and Reactor Building (VR System) Station Heating Coils, Design Change Package (DCP) 9600503 I

The DCP installed a temporary power feed from Unit 1 switchgear 131X to temporary electric heaters and associated ducts as maintenance support for station heat recovery system coil repairs and to prevent further freezing. The heat was needed to support maintenance activities while VT and VR are in operation.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the design change.

Temporary Heating Supply for Radwaste Building Ventilation System (VW System), Design Change Package (DCP) 9600510 The DCP installed temporary heaters outside of the intake of the radwaste ventilation (VW) system. The heaters were powered by a temporary diesel engine located on the ground elevation (710'). The heaters were installed to provide a heated air supply to prevent freezing of the VW station heat recovery coils.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the design change.

l l

l 30

= - -

t l

Temporary Power Feeds for L2R07 for Drywell Access Equipment, l

Design Change Package (DCP) 9600229 l

The DCP installed a temporary power feed from Motor Control Center l

(MCC) 134X-2 for the Unit 2 drywell access equipment.

The 10CFR50.59 safety evaluation concluded that there were no i

unreviewed safety questions associated with the design change.

l Temporary Power Feeds for L2R07 for Drywell Access Equipment, Design Change Package (DCP) 9600231 The DCP installed a temporary power feed from Motor Control Center (MCC) 235Y-1 to the Unit 2 drywell equipment hatch.

The 10CFR50.59 safety evaluation concluded that there were no j

unreviewed safety questions associated with the design change.

i Temporary Power Feeds for Unit 1 CRD Room Repair, Design Change Package (DCP) 9600232 l

The DCP installed a temporary power feed from Motor Control Center (MCC) 133-2 to provide 25 ampere to the Unit 1 Control Rod Drive (CRD) repair room.

1 The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the design change.

Temporary Power Feeds for L2R07 for Refuel Floor HEPA Filter, Design Change Package (DCP) 9600233 The DCP installed a temporary power feed from power panel 233-3/A5 for the high efficiency particulate air (HEPA) filter on the refuel floor.

i The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the design change.

Temporary Power Feeds for L2R07 for Refuel Floor Duraline Power Panel, Design Change Package (DCP) 9600234 The DCP installed a temporary power feed from power panel 133-3/C5 for j

the refuel floor duratine power panel.

l The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the design change.

l l

31

1 i

Temporary Power Feeds for L2R07 for 237 kW Refuel Floor Head Heaters, Design Change Package (DCP) 9600235 The DCP installed a temporary power feed from power panel 133-3/B3 to head heaters at the refuel floor.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the design change.

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Temporary Power Feeds for L2R07 for Unit 2 Suppression Pool Inspection Equipment, Design Change Package (DCP) 9600237 The DCP installed a temporary power feed from power panel 233-2/D3 for the l-igh efficiency particulate air (HEPA) filter on the refuel floor.

The 10CFR50.59 safety evaluation concluded that there were no l

unreviewed safety questions associated with the design change.

Temporary Power Feeds for L2R07 for Heater Bay 8 Pack Welder, Design Change Package (DCP) 9600240 The DCP installed a temporary power feed from power panel 231B-5/C5 to heater bay 8 pack welder.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the design change.

Temporary Power Feeds for L2R07 for Reactor Building Hydrolazer, Design Change Package (DCP) 9600241 The DCP installed a temporary power feed from power panel 235Y-3/AA5 for the 50 hp hydrolazer unit.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the design change.

Temporary Power Feeds for L2R07 for Back to Back DryweII Bullpen for Welding, Design Change Package (DCP) 9600243 The DCP installed a temporary power feed from power panel 235X-1/A3 for the back to back drywell bullpen for welding.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the design change.

32

Temporary Heating Supply for VR/VT Station Heat (SH) Coils Design Change Package (DCP) 9600541 A temporary power feed was installed from switchgear 231X to a temporary electric heater to support maintenance activities associated with the station heat recovery coils of the turbine building (VT) and radwaste building (VR) ventilation systems.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the design change.

Installation of 120 VAC Voltage Regulating Transformer 1APD1E for Post LOCA Containment Monitoring Ccntrol Circuit, Design Change Package (DCP) 9500023 The design change added a voltage regulating transformer in the 120 VAC distribution circuit for Motor Control Center (MCC) 135X-1, Circuit #5, the feed for the Post LOCA Containment Monitoring control circuit. The design change improves the voltages at the loads fed by this circuit during normal and abnormal system conditions.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the design change.

Motor Operated Valve 1E51-F045 Valve and Gear Set Replacement, Design Change Package (DCP) 9400057 The design change replaced the Reactor Core Isolation Cooling (RCIC) system 1E51-F045 valve in order to improve startup performance of the RCIC system. The valve's operator overall actuator gear ratio (OAR) was increased from 34.96:1 to 51.80:1. This was accomplished by replacing the motor pinion and worm shaft pinion gears. The modified gear reduction increases the available operator torque and thrust.

The 10CFR50.59 safety evaluation concluded that there was no unreviewed safety question associated with the design change.

33

i installation of 120 VAC Voltage Regulating Transformer 2APD7E for the Control Room HVAC Control Circuit, Design Change Packeye (DCP) 9500045 The design change added a voltage regulating transformer in the 120 VAC distribution circuit for Motor Control Center (MCC) 236X-1, Circuit #36, the feed for the Control Room HVAC control circuit. The design change improves the voltages at the loads fed by this circuit during normal and abnormal system conditions.

~

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the design change.

Installation of 120 VAC Voltage Regulating Transformer 2APD2E, ' r Post LOCA Containment Monitoring Circuit, Design Change Packge (DCP) 9500044 The design change added a voltage regulating transformer in the 120 VAC distribution circuit for Motor Control Center (MCC) 236X-1, Circuit # 5, the feed for the Post LOCA Containment Monitoring circuit.

i The design change improves the voltages at the loads fed by this circuit during normal and abnormal system conditions.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the design change.

installation of a Leakoff Line on the Fire Protection (FP) Deluge Header to the Charcoal Filter for Charcoal Adsorber OVS11S, Design Change Package (DCP) 9600158 The DCP installed two additional isolation valves and a leakoff line on the fire protection supply header 0FPD2A-2.0" for the Technical Support Center filter train OVS11S charcoal adsorber. UFSAR Section H.3.9.7 is accordingly revised to reflect the DCP.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the design change.

34

Unit 1 Design Change Packages (DCP) 9500481, Relocate Main Steam Tunnel Thermocouples, and 9500482, Main Steam Tunnel Leak Detection Logic Change DCP 9500481 relocated ten thermocouples in the main steam tunnel i

(MST) leak detection system, and changed their high differential temperature setpoints.

j DCP 9500482 made two significant changes to the MST leak detection system. First, permanent jumpers were installed to eliminate the Group 1 Main Steam Line isolation function associated with high ambient temperature in the MST. Second, key-lock bypass switches were

)

installed in the control room to allow bypassing the Group 1 isolation logic l

associated with high differential temperature in the MST. The switches replace the temporary jumpers previously used.

These design changes significantly reduce the risk of inadvertent reactor scrams related to the MST leak detection system response to Reactor Building Ventilation System (VR) operating transients. These DCPs were installed to implement licensing amendment No.111 to Unit 1 license NPF-11.

UFSAR Chapters 3,5,7,9,15, and Appendix H are revised to refler.t these DCPt The 10CFR50.59 safety evaluations concluded that there were no unreviewed safety questions associated with the DCPs.

Unit 1 Main Steam isolation Valve (MSIV) Leakage Control System (LCS) Abandonment (Phase l} per Design Change Package (DCP) 9500167 The DCP functionally eliminated the Unit 1 LCS during the Unit 1 seventh refuel outage (L1R07). The scope consisted of physically isolating and abandoning the LCS in place, and electrically disabling the LCS instrumentation. This work was associated with the approval of licensing amendment No.112 to Unit 1 license NPF-11.

UFSAR sections 1.0,1.2,3.2,5.4,6.0,6.1,6.2,6.4,6.7,7.3,10.3,15.0, 15.6, and Appendix H (part H.3) are revised. New section 6.8 is introduced.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the DCP.

35

1 Temporary Heating Supply for VR/VT Station Heat (SH) Coils, Design Change Package 9600543 A temporary power feed was installed from switchgear 131X to a temporary electric heater to support maintenance activities associated

)

with the station heat recovery coils of the turbine building (VT) and radwaste building (VR) ventilation systems.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the design change.

Temporary Power Feeds for L2R07 for Leak Rate Rig 710' Elevation, Design Change Package 9600246 A temporary feed from motor control center 236Y-1/F6 was installed to supply power for a leak rate rig on the 710' elevation of the Unit 2 reactor building.

j The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the design change.

Temporary Power Feeds for L2R07 for Local Leak Rate Rig 740' Elevation, Design Change Package 9600247 A temporary feed from motor control center 234X-2/83 was installed to supply power for a leak rate test rig on the 740' elevation of the Unit 2 reactor building.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the design change.

Temporary Power Feeds for L2R07 for Unit 2 Control Rod Drive (CRD) Rebuild Room HEPA Filter, Design Change Package 9600251 A temporary feed from motor control center 233-2/C6 was installed to supply power for the Unit 2 CRD rebuild room during L2R07.

Tho 10CFR50.59 safety evaluation concluded that there were no umeviewed safety questions associated with the design change.

36

t i

l Temporary Power Feeds for L2R07 for Battery Charger 2DC17E, Design Change Package 9600252 t

A temporary feed from motor control center 136X-3/B1 to motor control center 236X-3/B5 was installed to supply power for the Unit 2 Division ll I

battery charger 2DC17E for the 242Y bus outage.

The 10CFR50.59 safety evaluation concluded that there were no

{

unreviewed safety questions associated with the design change.

Temporary Power Feeds for Regular Lighting Cabinet (RLC) #121, i

Design Change Package 9600253 i

l l

A temporary feed from motor control center 134Y-1/C3 was installed for l

temporary lighting power to RLC #121 during the bus 242Y outage. The i

100FR50.59 safety evaluation concluded that there were no unreviewed l

safety questions associated with the design change.

Temporary Power Feeds for Regular Lighting Cabinet (RLC) #216, Design Change Package 9600377 i

l A temporary feed from motor control center 135Y-1/E3 was installed for temporary lighting power to RLC #216 during the bus 242Y outage.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the design change.

Temporary Power Feeds for Regular Lighting Cabinet (RLC) #210, Design Change Package 9600378 A temporary feed from motor control center 233-2/84 to motor control center RLC #210 was installed for temporary lighting power during the bus 242Y outage.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the design change.

Plugging of Floor Drains on Turbine Building Elevation 710', Design Change Package 9600399 The turbine building floor drains at elevation 710' were plugged at the trackway entrance and the condenser tube puil area in support of glycol transfer activities and turbine generator maintenance and inspection.

l 37

This was done to prevent foreign material from entering the turbine building floor drain system.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the design change.

Replacement of Multi-Stage Multi-Path Anti-Cavitation Trim on the 1E12-F021 Valve, per Design Change Package (DCP) 9400436 The DCP installed new multi-stage, multi-path, high pressure drop trim in the 1E12-F021 ("C" RHR Full Flow Test Return) valve. This replacement was done during the recent L1R07 refuel outage. This trim replaces the multi-stage (2 stage), multi-path, high pressure drop trim that was installed in the valve during the previous L1R06 refuel outage, per J

Modification M01-1-93-013. The new multi-stage trim was required to reduce the vibration in the piping system at and around the F021 valve that remained because of the installation of two stage trim. This is observed only when the valve is used to throttle flow through the "C" RHR full flow test loop. The F021 valve, although of the same design as the F024A/B valves, is installed differently, with the normal flow over the seat of the valve. For this application, at least four stages of trim are required to drop the pressure across the valve and reduce the cavitation and its associated vibration. The cavitation results from the large pressure drop that occurs across the valve seat under throttling flow conditions.

The mechanical dial position indicator (MDPI) on the F021 valve was also 4

replaced. During testing activities for Modification M01-1-93-013, it was noted that the MDPl for the F021 valve was no longer reading accurately.

This was due to the installation of the trim and its associated valve stem replacement.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with this design change.

Parallel Conductor on Cable 1LV053 per Design Change Package (DCP) 9500021 The design change was implemented to reduce the voltage drop in Cable 1LV053 by connecting the existing spare (red) conductor in parallel with the line side (tJack) conductor. The affected conductors will be connected at Circuit #30 of the 120 VAC distribution panel at Motor Control Certer (MCC) 136X-2, and at Panel 1PM13J. Tne reduction in voltage drop will s

38

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ensure that adequate voltage is available at the safety related loads, specifically during a degraded voltage condition. This change does not implement a functional design change in that the originally intended function of the affected 120 VAC distribution system circuit, and downstream safety related loads, are reinforced.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with this design change.

Unit 1 Motor Operated Valve (MOV) 1821-F016 Valve and Operator Replacement Design Change Package (DCP) 9400429 The design change replaced the fb

,e gate of MOV 1B21-F016 with double disc parallel slide gates m.

2.or" red by the Anchor / Darling Valve Company. The DCP also replaced the previous Limitorque SMB-000-5 operator with a Limitorque SMB-00-15 operator.

The valve was replaced because the hardfacing on the valve's seats was almost completely removed by extensive machining. The machining was required to refinish the seats so that local leak rate test (LLRT) acceptance criteria could be met.

The valve's operator was replaced because the previous operator was only marginally adequate to open and close the valve under all postulated operating conditions. The new operator was selected to provide adequate design margin between the operator's capability and operational. requirements.

A vent hole was added in the reactor side disc of the new valve. The vent hole is intended to eliminate the potential for pressure locking of the valve's discs. With the vent hole installed, the valve will still seal effectively because the vented side of the valves is always exposed to a higher pressure. The higher pressure on the back side of the non-vented valves discs will force the discs into their seats and provide flow shut-off.

Motor Operated Valve 1G33-F040, Gear Set and Spring Pack Replacement, Design Change Package (DCP) 9400433 The design change improves the reliability and operability of motor operated valve 1G33-F040. Specific requirements relating to operability have been presented in NRC Generic Letter 89-10. Several alternatives were considered to resolve the operability concerns. This design change was selected as the preferred alternative because it has the lowest cost and provides the greatest benefit of improved valve reliability.

39

The 1G33-F040 valve was equipped with a Limitorque SMB-00-10 operator with an overall actuator gear ratio (OAR) of 46.80:1. The design change increased the OAR to 82.00:1. This was accomplished by replacing the motor pinion and worm shaft pinion gears. This enables the operator to provide the required torque and thrust to operate the valve under all postulated operating conditions.

The net effect of the gear set change increases the 1G33-F040 stroke time from approximately 21 seconds to approximately 39 seconds. This new stroke time is outside of the standard operating time range for a motor operated gate valve. A note is being added to UFSAR Table 6.2-21 specifying the approximate operating time for the 1G33-F040 valve.

This design change also replaced the Limitorque operator's spring pack.

The previous spring pack had a torque range of 110-185 ft-Ibs. The replacement spring pack has a torque range of 170-240 ft-lbs. The new spring pack allows a torque setting near the lower end of the range, which is desired.

The 10CFR50.59 safety evaluation concluded that there was no unreviewed safety question associated with the design change.

increase of Magnetic Setpoint for Diesel Generator Supply Fan DVD01C, Design Change Packages (DCP) 9500257 and 9500260 An engineering evaluation was performed for Diesel Generator Room Supply Fans OVD01C,1VD01C,1VD03C,2VD01C, and 2VD03C. The engineering evaluation was performed to determine the impact of the counter-clockwise rotation on the ability of the supply fans to start without tripping the feed circuit breakers or thermal overload relays.

For a reverse rotation of 250 rpm, the previous thermal overload relay setting was found to be acceptable. The fan will start without tripping the overload relay. The previous circuit breaker magnetic setting was found to be marginally acceptable, based on no incidents of nuisance tripping of the magnetic element having occurred to date. In order to provide the intended margin for starting current with worst case reverse rotation, the DCP was implemented to increase the magnetic setting of the circuit breakers. The magnetic setpoint of the Klockner-Moeller thermal-magnetic feed circuit breaker for supply fan OVD01C was increased from 600 to 800 amps. DCP 9500257 incorporated the setpoint change for the feed circuit breaker in Motor Control Center (MCC) 135X-2, Compartment B-4. DCP 9500260 incorporated the setpoint change for the feed circuit breaker in MCC 235X-2, Compartment B-4.

40

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with these design changes.

Design Change Package 9400257, Replacement of Motor Operator and Spring Pack on the 1E12-F016A DryweII Spray isolation Valve The subject valve is a 16" Anchor / Darling flex-wedge gate valve. The design change replaced the valve's yoke and motor operator. The Limitorque SMB-0 motor operator installed on valve 1E12-F016A was replaced with a Limitorque SMB-1 operator with an overall actuator gear ratio of 124.1:1. The valve's thermal overload relays were replaced and its molded case circuit breaker was reset.

The operator change increased the valve's stroke time from approximately 75 seconds to approximately 95 seconds. This new stroke time is outside the standard operating time range for a motor operated gate valve. A note is added to Table 6.2-21 of the UFSAR specifying the approximate operating time for the Unit 1 RHR 16A valve.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the design change.

Design Change Package 9400254, Replacement of Motor Operator and Spring Pack on the 1E12-F017B Drywell Sprayisolation Valve The subject valve is a 16" Anchor / Darling flex-wedge gate valve. The design change replaced the valve's yoke and motor operator. The Limitorque SMB-0 motor operator installed on valve 1E12-F017B was replaced with a Limitorque SMB-1 operator with an overall actuator gear ratio of 124.1:1. The valve's thermal overload relays were replaced and its molded case circuit breaker was reset.

The operator change increased the valve's stroke time from approximately 75 seconds to approximately 95 seconds. This new stroke time is outside the standard operating time range for a motor operated gate valve. A note is added to Table 6.2-21 of the UFSAR specifying the approximate operating time for valve 1E12-F0178.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the design change.

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Traversing in-core Probe (TIP) Isolation Seal-In Modification M01-2-95-00130 The TIP isolation circuit was modified so that automatic isolation actuation instrumentation will be completed once initiated and will not be interrupted if primary containment isolation system isolation is reset prior to i

completion of TIP withdrawal. In addition, return to normal operation after isolation actuation requires deliberate operator action.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the modification.

J Minor Plant Change MC1-1-90-023 Test The test procedure for the subject change consisted of an operability and leakage test on the newly installed drain valve 1SA117. Minor Change MC1-1-90-023 installed the valve at the low point drain connection on line 1SA22A-4" to allow the periodic blowdown of service air (SA) system piping.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the test procedure.

Minor Plant Change P01-2-90-573, Unit 2 CRD HCU Drain Header This Minor Change installed drain hoses at all Unit 2 Control Rod Drive Hydraulic Control Unit Accumulator Drain Valves which are routed to local RF floor drains. This was done to minimize the spread of contamination from water spills which may occur when the accumulators are drained for maintenance or nitrogen charging. The design change was installed in February 1994, applicable changes to UFSAR Section H were previously incorporated.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the minor change.

Diesel Generator 2A Differential Relay Replacement, Component Replacement No. C01-2-94-006 E This design change replaced the DG-2A differential relay 2487-DG008.

The previous Basler type PRC-130 differential relay is obsolete. Parts and repair services are no longer available. The replacement relay is an ABB/ Westinghouse type SA-1, Model No. 290B225A10 differential relay.

The new relay performs the same function as the previous relay and meets or exceeds the original equipment specifications.

42

)

l UFSAR Table 8.3-2 was previously revised by replacing the relay type with a note that refers the reader to the Q-List to obtain the relay manufacturer and model number.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety question associated with the design change.

Changeout ofInternal Parts for Primary Containment Ventilation Chillers per Alternate Replacement L-1996-48-0 l

The alternate replacement changed out the internal parts for the primary containment 400 ton chillers to facilitate the change from refrigerant R-12 to R-134A. The manufacture and use of R-12 is being phased out by the Clean Air Act of 1990. The retrofitting of the machines with the non-CFC based R-134 refrigerant allows for future continued use of the machines.

UFSAR Section 9.2.9.2 is revised to reflect the alternate replacement.

)

l The 10CFR50.59 safety evaluation concluded that there was no unreviewed safety question associated with this activity.

Diesel Generator 1A Differential Relay Replacement, Component l

Replacement No. C01-1-94-007-F This design change replaced the DG-1 A differential relay 1487-DG008.

The previous Basler type PRC-130 differential relay is obsolete. Parts and repair services are no longer available. The replacement relay is an ABB/ Westinghouse type SA-1, model no. 2908225A10 differential relay.

i The new relay performs the same function as the previous relay and meets or exceeds the original equipment specifications.

UFSAR Table 8.3-2 is affected by this replacement, since the table lists the relay type for the generator differential relay. However, instead of revising the table to identify the type of the replacement relay, the change consists of replacing the relay type with a note that refers the reader to the Q-List to obtain the relay manufacturer and model number.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety question associated with the design change.

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Diesel Generator 1A Reverse Power Relay Replacement, Exempt Change No. E01-1-94-960-B

~

The previous reverse power relay, Basler type PRP-110, was obsolete.

Parts and repair services were no longer available for the relay. The replacement relay is a GE type ICW, model no.12lCW51 A2A, directional power relay. The replacement relay performs the same function as the previous relay and meets or exceeds the original equipment specifications.

UFSAR Table 8.3-2 is affected by this replacement, since the table lists the relay type for the reverse power relay. However, instead of revising the table to identify the type of the replacement relay, the change consists of replacing the relay type with a note that refers the reader to the Q-List to obtain the relay manufacturer and model number.

l The 10CFR50.59 safety evaluation concluded that there were no i

unreviewed safety questions associated with the design change.

3 Diesel Generator 1B Reverse Power Relay Replacement, Exempt Change E01-1-94-802-A The exempt change revised the DG-1B neutral ground fault trip circuit.

i The previous reverse power relay, a GE type GGP-53B, was replaced due to obsolescence. Parts and repair services are no longer available.

i The replacement relay is a GGP-53C, model no.12GGP53C1 A. The new relay performs the same function and meets or exceeds the original i

l equipment specifications.

UFSAR Table 8.3-2 was affected by this replacement, since the table lists the relay type for the reverse power relay. However, instead of revising the table to identify the type of the replacement relay, the change consisted of replacing the relay type with a note that refers the reader to the Q-List to obtain the relay manufacturer and model number. This was incorporated in the UFSAR Revision 11 update of April 1996.

The 10CFR50.59 safety evaluation concluded that there was no unreviewed safety questions associated with the design change.

Diesel Generator 0 Neutral Ground Relay Replacement and UFSAR Update, Exempt Change E01-0-94-960-D The exempt change replaced the DG-1 A neutral ground relay. The previous neutral ground relay, a Basler type PRV-120 overvoltage relay, was replaced due to obsolescence. Parts and repair services are no 44

longer available. The replacement voltage relay is a GE type IAV, model no.12lAV51D1 A. The new relay performs the same function and meets or exceeds the original equipment specifications.

UFSAR Table 8.3-2 is affected by this replacement, since the table lists the relay type for the reverse power relay. However, instead of revising the table to identify the type of replacement relay, the change consists of replacing the relay type with a note that refers the reader to the Q-List to obtain the relay manufacturer and model number.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the design change.

Diesel Generator 0 Differential Relay Replacement and UFSAR Update, Exempt Change C01-0-94-007-J The exempt change revised the O DG differential relay. The Basler type PRC-130 relay was replaced due to obsolescence. Parts and repair services are no longer available. The replecement is an ABB/ Westinghouse type SA-1, model no. T.90B225A10 differential relay.

The new relay performs the same function and meets or exceeds the original equipment specifications.

UFSAR Table 8.3-2 is affected by this replacement, since the table lists the relay type for the reverse power relay. However, instead of revising the table to identify the type of the replacement relay, the change consists of replacing the relay type with a note that refers the reader to the Q-List to obtain the relay manufacturer and model number.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the design change.

Motor Operated Valve 1821-F019 Valve and Operator Replacement, Exempt Change E01-1-9400428 The design change replaced the flex-wedge gate valve with a double disc parallel slide gate valve manufactured by the Anchor / Darling Valve Company. The previous Limitorque SMB-000-5 operator for valve 1821-F019 was replaced with a Limitorque SMB-00-15 operator.

l The valve was replaced because the hardfacing on its seats has been almost completely removed by extensive machining. The machining was required to refinish the seats so that local leak rate test (LLRT) acceptance criteria could be met.

45

l The valve operator was replaced because it was only marginally adequate to open and close the valve under all postulated operating conditions. The new operator has been selected to provide adequate j

design margin between the operator's capability and operational requirements.

The new valves have the addition of a vent hole in the reactor side disc.

J The intent of the vent hole is to eliminate the potential for pressure locking of the valve discs. With the vent hole installed, the valve will still l

seal effectively because the vented side of the valve is always exposed to a higher pressure. The higher pressure on the back side of the non-vented valve disc will force the disc into its seat and provide flow shut-off.

UFSAR Table 6.2-21 is revised to indicate the installation of the vent hole in the reactor side disc.

l l

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the design change.

i Diesel Generator 0 Overcurrent Relay Replacement and UFSAR Update, Component Replacement C01-0-94-007-l The design change replaced the 0 Diesel Generator Overcurrent relay.

The previous Basler type PRC-110-108 relay was replaced due to i

obsolescence. The replacement is an ABB/ Westinghouse type CO-6, model no. 264C898A05 relay. The new relay performs the same function and meets or exceeds the original equipment specifications.

UFSAR Table 8.3-2 is affected by this replacement, since the table lists the relay type for the reverse power relay. However, instead of revising the table to identify the type of the replacement relay, the change consists of replacing the relay type with a note that refers the reader to the Q-List to obtain the relay manufacturer and model number.

i The 10CFR50.59 safety evaluation concluded that there were no i

unreviewed safety questions associated with the design change.

l 4

Operability Determination of the 0 Diesel Generator (DG) Cooling Water StrainerODG01F Flow was not initially acoustically measured in the ODG01F Strainer backwash line when the discharge valve was opened to its 10% open position. This condition was identified during the check of backwash flow 4

and led to the concern that the backwash line could be plugged with debris preventing the required 250 gpm flow from being achieved. When i

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e i

i the valve was manually opened to greater than 10% and then back to 10%, measured flow exceeded 300 gpm. The operability determination concluded that the strainer is operable, with manual operation of the valve j

being used if necessary.

l l

l The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the operability determination.

I Installation of Circulating Water Hypochlorite and Bromide Feeds, i

Exempt Change E01-1-9500157 l

i The design change installed a Chemical Feed skid, having air-operated j

pumps and valves, and associated instruments and controls, on an existing concrete pad in the Chemical Feed Building adjecent to the Lake l

Screen House. The skid injects a combination of sodium hypochlorite and j

sodium bromide (biocide) into the Circulating Water system to reduce micro-biological corrosion. This helps to extend the life f condenser tubes and reduces the scope of condenser tube cleaning during outages.

UFSAR Sections 9.2.12 (Chemical Feed System) and 10.4.5.2 (CW System Description) are revised to include the biocide injection into the

]

Circulating Water System.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the design change.

4 Design Change Package 9400255, Replacement of Motor Operator and Spring Pack on the 1E12-F017A Drywell Sprayisolation Valve The subject valve is a 16" Anchor / Darling flex-wedge gate valve. The design change replaced the valve's yoke and motor operator. The Limitorque SMB-0 motor operator installed on valve 1E12-F017A was replaced with a Limitorque SMB-1 operator with an overall actuator gear ratio of 124.1:1.

The operator change increased the valve's stroke time from approximately 75 seconds to approximately 95 seconds. This new stroke time is outside the standard operating time range for a motor operated gate valve. A note is added to Table 6.2-21 of the UFSAR specifying the approximate operating time for valve 1 E12-F017A.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the design change.

47 i

i Operability Evaluation for Motion Restrictor Not Installed An operability and safety evaluation was conducted due to the discovery of a motion restrictor not being installed on a roof / floor drain in Unit 1 Diesel Generator (DG) corridor. The restrictor is required to be installed j

for seismic events.

1 The system and interaction with adjacent equipment were evaluated, yielding the conclusion that all systems will function as designed under accident conditions, and will maintain their structural integrity. The motion restrictor will be installed per Modification M01-1-83-055.

4 The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with this procedure.

Control Rod Drive (CRD) Recirculation Line Addition and Check Valve Replacement, Modification M01-1-92-006 The Unit 1 CRD system previously contained a small recirculation bypass line (1-inch NPS) for each pump. The flow rate through the recirculation bypass line was limited to approximately 20 gpm by the restriction orifice (C11-D007A&B) located in this line. This flow rate is sufficient to prevent i

pump over-heating and abnormal wear during normally expected, short duration, minimum flow rate, operating conditions. During refueling periods, however, there is a period of up to eight weeks when a higher minimum flow requirement specified by the pump manufacturer is not satisfied. During these operating periods the CRD system flow demand is greatly reduced. These operating periods have resulted in a considerable amount of wear, damage, and degradation in pump performance to the point where pump replacement is being performed.

i The modification installed a two-inch diameter recirculation line containing a Severe Service (Manual) Control Valve. This modification provides additional flow paths for the CRD pumps (1C11-C001 A&B) for operation during a unit outage when fuel is in the reactor, but when the CRD system flow demand is greatly reduced. This recirculation line will provide a means of maintaining the pump manufacturer's recommended minimum flow during this reduced flow condition.

The Unit 1 CRD Pump discharge stop-check valves (1C11-F014A&B) were also replaced. The previous valves were free-floating disc type stop-check valves installed in a vertical run of piping. These valves may not have closed properly in reverse flow due to the vertical orientation of the valves. Spring loaded type stop-check valves were installed as a replacement to ensure closure on reverse flow.

48

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l l

UFSAR Section 4.6 is revised to reflect the recirculation line for the CRD pumps.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the design change.

Installation of Circulating Water Hypochlorite and Bromide Feeds, Exempt Change E01-2-9500156 Micro-biological corrosion has been identified as the main reason that causes the pitting and subsequent tube plugging of condenser tubes and lost condenser efficiency. This corrosion is due to sulfate reducing bacteria producing sulfuric acid that attacks the tubes. Injection of the i

combined Sodium Hypochlorite and Sod am Bromide (Biocide) into the Circulation Water will reduce this bio-activity. This helps to extend the life of condenser tubes and reduce the tube cleaning task during outages.

Polyacrylate was previously injected into the Circulating Water to minimize the silting and scaling problems (not the bio-fouling problem) in the main condensers. The design change installed a Chemical Feed skid to inject to Unit 2, consisting of air-operated pumps and valves, and associated instruments and controls in the Chemical Feed Building adjacent to the Lake Screen House.

UFSAR Sections 9.2 and 10.4 are revised to reflect the installation of the chemical injection feeds for Unit 2.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the design change Enhancement of the Unit 1 Rod Worth MinimizerperModification M01-1-94-012, and Post Modification Scram Data Capture Test The modifications revised subsystem B of the Unit 1 Rod Worth Minimizer (RWM) so that new control rod position information will be stored in RWM B memory and displayed on the CRT at control room panel 1H13-P603 after each scan of the Rod Position Information System (RPIS) during a scram. Also, unknown position codes generated by rods which have not activated any of the reed switches on the rod position probe, such as those which have inserted past the full-in reed switches, will not erase previously stored valid position data.

This design change was installed to resolve a problem with rod position indication following a scram. Following a scram, position indication has been lost in several instances for a few control rods. A preliminary i

)

49

- investigation determined that this problem was caused by the control rod inserting past the full-in position indication reed switch. Following the installation of these changes, the last position indication reed switch that is picked up by the control rod is displayed by RWM B during a scram.

The post-modification scram data capture test verified that the RWM performed as required following modification.

i A 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the design change or the post-modification testing.

Diesel Generator 1A Overcurrent Relay Replacement per Component Replacement C01-1-94-007-E, and UFSAR Update The design change replaced the 1 A Diesel Generator Overcurrent relay.

The previous Basler type PRC-110-108 relay was replaced due to obsolescence. The replacement relay is an ABB/ Westinghouse type CO-6, model no. 264C898A05 relay. The new relay performs the same function and meets or exceeds the original equipment specifications.

UFSAR Table 8.3-2 is affected by this replacement, since the table lists the relay type for the reverse power relay. However, instead of revising the table to identify the type of the replacement relay, the change consists of replacing the relay type with a note that refers the reader to the Q-List to obtain the relay manufacturer and model number.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the design change.

System Auxiliary Transformer (SAT) 142, CO-7 Protective Relay Addition, Modification M01-1-93-020 The modification brings the subject relays to the level of protection required by the company standard specified in System Planning Department Memo 4-1.

The CO-2 ground differential scheme relay provides primary protection for phase to ground faults. The Low Voltage (LV) windings of the transformer are resistance grounded, which limits the amount of ground current available for phase to ground faults. The differential and sudden pressure relays may be insensitive for phase to ground faults in the transformer LV windings or leads. A transformer LV lead differential scheme, using high speed overcurrent relays, was installed to provide primary protection for these faults.

50

CO-7 transformer low voltage breaker back-up relay provides back-up protection in the event that the Unit Auxiliary Transformer LV breaker fails l

to interrupt for an LV bue multiphase fault. It also provides back-up protection for transformer internal or LV lead multiphase faults.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with this design change.

Unit 1 Reactor Core Isolation Cooling (RCIC) System Drain Valve Pressure Gauges Installation, Exempt Changes E01-1-94-914A, B, C, and D Exempt changes 94-914A, B, C, and D added pressure gauges to RCIC drain valves 1E51-F026, F025, F004, and F005, respectively (These exempt changes were authorized for operation in June 1994, and were not previously reported due to an administrative error). The pressure gauges allow for leak detection of their air regulators, and facilitate plant operators to properly set air pressure to ensure that the control valves travel through their full range. The pressure gauges also allow determination of air leakage caused by over-pressurization of the air regulators.

The 10CFR50.59 safety evaluations concluded that there were no unreviewed safety questions associated with these exempt changes.

Replacement of Actuator on Reactor Core Isolation Cooling (RCIC)

Valve 1E51-F022, Exempt Change E01-1-9400431 The exempt change modified the overall actuator ratio (OAR) of motor operated valve (MOV) 1E51-F022 from 47.90:1 to 62.50:1. This was accomplished by replacing the motor pinion and worm shaft pinion gears.

This resulted in greater available operator torque and thrust, thus improving the valve's design margin. The gear change also increased the valve's stroke time from approximately 7 seconds to approximately 9 seconds.

The 10CFR50.59 safety evaluations concluded that there were no unreviewed safety questions associated with this exempt change.

51

_. _.... _ _ _ _. _ _.. _. ~

Upgrade Power Supply Feed For Unit 1 Intermediate' Range

. Monitoring (IRM) and Average Power Range Monitoring (APRM)

Recorders 1C51-R603A, B, C, and D, Exempt Changes E01-1-94-927A

\\

and B i

The subject IRM/APRM recorders receive input signals from the Neutron Monitoring System, which is powered from the Reactor Protection System.

The chart recorders are powered from non-redundant and non-Class 1E power sources.

'.These design changes upgraded the power supply to Class 1E and provided redundancy. Recorders 1C51-R603A and C were added to the Engineered Safety Systems (ESS) Division 1 (Instrument Bus A) power supply from Motor Control Center (MCC) 135X-3 per exempt change E01-1-94-927A. Recorders 1C51-R603B and 1C51-R603D were added to ESS Division 2 (Instrument Bus B) power supply from MCC 136X-3 per exempt change E01-1-94-927B.

These upgrades meet the alternate requirements for uninterruptibility as defined in Section 5.0 of General Electric Report NEDO 31558, Position on NRC Regulatory Guide 1.97, Revision 3, Requirements for Post-Accident Neutron Monitoring System. Comed previously committed to the '

NRC that the power supply upgrades would be performed during the L1R07 outage.

The 10CFR50.59 safety evaluations concluded that there were no I

unreviewed safety questions associated with these exempt changes.

Diesel Generator 1A Underfrequency Relay i?eplacement per Component Replacement C01-1-94 907-B i

The subject component replacement consisted of replacing i

underfrequency trip relay 1481-DG014 in the DG-1 A/2A shutdown' control

-l circuit. The previous Basler model PRF-120 relay was replaced with an ABB type ITE-81, model no. 422C1276-L, frequency relay. The PRF-120 relays were replaced because they are obsolete. They are no longer manufactured or repaired by Basler, and spares parts are not available.

The new relay meets or exceeds the original equipment specifications for this application.

i 52

~.

A change was incorporated in UFSAR Table 8.3-2 in the UFSAR Revision 11 update. The table contains a note which refers the reader to the Q-list to obtain the relay manufacturer and model number.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with this design change.

Leak Detection System (LD) Electrical Circuits did not Meet Station ElectricalSeparation Criteria It was identified that the LD control wiring for redundant RPS channels internal to panels was bundled together. This is a non-conforming condition that will be corrected to meet the station electrical separation criteria. The issue of LD thermocouple instrumentation cables being routed as the same electrical division will remain unchanged based on the analysis provided in the associated operability evaluation.

The non-conforming condition has been evaluated in an operability assessment, which concluded that no credible failure mode exists that could create the necessary hot shorts to disable this system. This design is in conformance with IEEE 279-1971. The design will be changed to meet the required station separation criteria for the internal panel control circuits. The LD thermocouple instrumentation cabling will remain unchanged based on its low energy circuitry and routing analysis addressed in the attached operability evaluation.

The 10CFR50.59 safety evaluation concluded that there is no unreviewed l

safety question associated with this operability assessment.

Evaluation of the Unit 1 FuelPool Cooling System to Clarify Full Core Discnarge During Each Refueling Outage The UFSAR was unclear that the removal of the entire core to the fuel pool during refuel outages is a normal practice and not only an emergency condition. This evaluation ensures that the issues related to the normal refueling offload of the Unit 1 reactor core to the fuel pool are consistent with the licensing requirements. UFSAR Section 9.1.3 is revised to allow one to better determine the difference between routine refueling and a design basis emergency condition. Table 9.1-3 was revised to make the Maximum Normal Heat Load (MNHL) consistent with the changes of Section 9.1.3.1.1.

The 10CFR50.59 safety evaluation concluded that there was no unroviewed safety question associated with the evaluation and the changes to the UFSAR.

53

Use of 80 mil thickness Fuel Channels and Modified Channel Fasteners Future reload fuel bundles (starting with L1R07) will utilize 80 mil thickness fuel channels as opposed to those of 100 mil thickness previously used. The fuel channel fasteners are also slightly modified to accommodate the thinner fuel channel:.

The zircaloy channel material is a mild neutron poison and degrades neutron economy. Reducing the amount of material in the channel significantly improves core performance. This results in the need for fewer bundles to be purchased and loaded each cycle. The reduced amount of channel material also decreases the channel cost.

UFSAR Sections 3.9 and 4.2 of the UFSAR Revision 11 update were revised to reflect the modified channels and fasteners.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the changes.

Use of Mobile Vendor System to Process WE, WF, and WZ System i

Water, and Solid Wastes Onsite Review 96-002 evaluated the use of a mobile vendor system to process water collected by the WF (Floor Drain) and WZ (Chemical Floor Drain) systems. The system will also be used to process the concentrated wastes that are generated during the processing of water from the WF and WZ systems. The mobile vendor system may be optionally used to process WE (Equipment Drain) water. The mobile system provides a processing alternative to the evaporators. Utilization of the vendor system is significantly dose efficient and generates significantly less waste. UFSAR Section 11.2.1.1 is being revised to reflect the mobile vendor system.

The 10CFR50.59 safety evaluation concluded that there was no unreviewed safety question.

54

Operability Assessment of Non-seismically Supported i

Humidification Equipment on VC and VE System Operability l

It was determined that the humidification equipment for the control room ventilation (VC) and the Auxiliary Electric Equipment Room (AEER) ventilation (VE) was not seismically supported. This contradicts the UFSAR, which states that they are seismically supported. An operability evaluation was performed in response to this.

The postulated result from this lack of support is that a 1-inch diameter hole could be created in the ductwork whee the pipe enters the duct. It was determined that a section of humidifier piping or assemblies located above the VE and VC system ductwork could rest and settle on top of affected portions of the ductwork upon failure. The entire piping assembly would fall several feet. The integrity of the ductwork ghou!d remain intact. The assessment concluded that there is no effEct on safety related equipment, other than VC and VE, due to the failure of the non-seismically supported humidification equipment, and that VC and VE systems have no affect on the frequency of accident initiators.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the operability assessment.

Unit 0 Diesel Generator (DG) 0 Reverse Power Relay Replacement, Exempt Change E01-0-94-960-C (DCP 9400313)

The previous reverse power relay, Basler type PRP-110, was replaced because it became obsolete, and parts and repair services were no longer available for the relay. The replacement relay is a GE type ICW, model no.12lCW51 A2A, directional power relay. The new relay performs the same function as the previous relay and meets or exceeds the original equipment specifications.

UFSAR Table 8.3-2 is being revised since it lists the type of reverse i

power relay. However, instead of revising this table to identify the type of the replacement relay, the proposed change replaces the relay type with a note in Table 8.3-2 that refers the reader to the Q-List to obtain the relay manufacturer and model number.

The 10CFR50.59 safety evaluation concluded that there was no unreviewed safety question associated with this design change.

l 55

N i

Temporary Removal of Cable Raceway to Support Station Procedure LMP-VQ-05 i

Cable Tray Sections 1100C,1101C,1101R, and associated supports were temporarily removed, per Station Procedure LMP-VQ-05. This 4

permits work to be done on valve 1VQO29, and its motor operator.

The 10CFR50.59 safety evaluation concluded that there was no i

unreviewed safety question associated with the procedure revision and the procedure deletion.

Enhancement of the Unit 2 Rod Worth Minimizerper Modification M01-2-94-009 The modifications revised subsystem B of the Unit 2 Rod Worth Minim!zer i

(RWM) so that new control rod position information will be stored in RWM B memory and displayed on the CRT at control room panel i

2H13-P603 after each scan of the Rod Position Information System (RPIS) during a scram. Also, unknown position codes generated by rod; which have not activated any of the reed switches on the rod position prcbe, such as those which have inserted past the full-in reed switches, will not erase previously stored valid position data.

This design change was installed to resolve a problem with rod position indication following a scram. Following a scram, position indication has been lost in several instances for a few control rods. A preliminary investigation determined that this problem was caused by the control rod inserting past the full-in position indication reed switch. Following the installation of these changes, the last position indication reed switch that is picked up by the control rod is displayed by RWM B during a scram.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the design change.

Installation of Cross-tie between WF and WE systems, Modification M01-0-9500315 The design change installed a cross tie line which connects the floor drain collector discharge line, 2WF05A-4", to the Reactor Water Cleanup (RWCU) Reject to Radwaste line,2WE82A-4". The new line contains a normally closed, locked closed gate valve. The cross-tie line also contains a check valve to prevent the higher pressure RWCU fluid from entering the lower pressure WF system.

56

Downstream of the cross-tie, a new gate valve is installed in the 2WF05A-4"line. This valve is normally locked open. Operation of the new valves is administratively controlled to prevent inadvertent transfer of WF water to WE. The installation of a cross-tie between the WF system (floor drain collector) and the WE system (drain collectors and surge tanks) allows the site operational flexibility by providing a processing i

flowpath. UFSAR Section 11.2.2 is revised to reflect the installation of the i

cross-tie.

The 10CFR50.59 safety evaluation concluded that there were no that were no unreviewed safety questions.

Operability Evaluation On Degrading Response Times For Scram Solenoid Pilot Valves (SSPV) 1 i

Scram Response times for the control rod drives that have the new Viton elastomer diaphragms installed have begun to degrade. This issue has been identified at all nuclear facilities that have installed the Viton style valves.

The degradation of the old BUNA-N style diaphragms necessitated the installation of new Viton designed valves. Subsequent information from other nuclear facilities, as well as data obtained at LaSalle, indicates the Viton valves are experiencing a slowing in their response times. This has been identified to be caused by a molecular adhesion between the Viton elastomer and the brass seating surface.

)

The function of the SSPVs is to open upon receipt. They are not the precursor for initiating the sequence. Upon receipt of ' scram signal for a

RPS, the SSPVs de-energize and cause the air to exhaust from the scram i

valves thus causing the control rod to rapidly insert. The worst case condition is the SSPVs fail to function, thereby preventing some or all the control rods to insert. This consequence has been analyzed in the ATWS event.

Augmented testing will allow the degradation in the scram times to be trended. This trend will be used to replace the valves prior to reaching a point where the Technical Specification required times are exceeded.

Testing and industry experience has lead to the conclusion that the adhesion phenomenon, while causing the start of motion of the control rods on a scram to slow, will not cause the control rod to fail to scram.

This phenomenon is internal to the valve and thus does not affect any other portions of the CRD system from performing their intended functions.

57

Scram insertion times currently are within technical specification requirements. Continued monitoring will verify that these times remain within these requirements.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the operability evaluation.

Amendment to Unit 1 Core Operating Limits Report (COLR)

The Administrative Technical Requirements (ATR) for N subject COLR was revised to support Cycle 8 operation. The reload v a design was found to affect transient response, while the new operating limit minimum critical power ratio (MCPR) accounts for changes to transient response.

The limiting event for Unit 1 Cycle 8 is the Rod Withdrawal Error (RWE).

The results of the analysis for the ASME over-pressurization event were within Technical Specification limits.

The 10CFR50.59 safety evaluation concluded that there were no unreviewed safety questions associated with the revised COLR.

H.

Survey of Evaluation Results of Chlorine Shipments by Barae on the lilinois River Per the UFSAR, every 3 years a survey will be conducted to re-evaluate the use of chlorine, within 5 miles of the control room, to ensure that a chlorine hszard does not exist. The last survey performed was in 1994 and the results were included in the NRC Annual Report for that year.

l.

Summary of Events Violatina Technical Specification 3.4.5 Primary Coolant lodine Spikina Exceedina Allowable Limits 1

During this reporting period, January 1,1996 through December 31,1996, there were no violations of Technical j

Specification 3.4.5, Primary Coolant lodine Spikes Exceeding Allowable j

Limits.

l 58 I

1 i

ATTACHMENT A SAFETY-RELATED MAINTENANCE COMPLETED i

l (NON-OUTAGE RELATED) i WRNUM GYS EPN DESCRIPTION 930047338-01 VE OVE03CB EXCESSIVE VlBRATION; INSPECT FAN FOR DAMAGE AND BALANCING 930047338-02 VE OVE03CB EXCESSIVE VIBRATION; INSPECT FAN FOR DAMAGE AND BALANCING 940059444-01 E12 1E12F097 VALVE IS STUCK OPEN OR WORKING INCORRECTLY i

940059444-02 E12 1E12F097 VALVE DOES CYCLE, SEAT DAMAGE OR CRUD BUILD-UP EVIDENT 940066023-01 W

2WO2C LUBE FAN CSCS EQUIP AREA HPCS PUMP CUBICAL COOLER l

940072541 01 E12 1E12C003 44 DROP PER MINUTE SEAL LEAK ON PUMP 940072541-02 E12 1E12C003 STRESS IN SUCTION BOLT-UP 940074032-02 FC 2FC03PB PERFORM BASE METAL REPAIR ON 6" FLANGE ON LINE 2FC30AH-6" 940078603-01 E12 2E12F021 (CHANGE) VALVE 18 fNCH MOTOR OPERATED GLOB 5 940079753-01 FC 1FC044A CHECK VALVE INSPECTION l

950004511-01 VC OVCO3AB BOTTOM OF OVC03AB HOUSING IS CORRODED AND LEAKS RAIN WATER 950007222-01 PL IPL76J VISUALLY INSPECT VARIOUS PARTS OF THE PANEL SEE EO-LSO 950007231 01 PL iPL77J VISUALLY INSPECT VARIOUS PARTS OF THE PANEL SEE EQ-LSO 950007849-01 DC 1DC14E INSPECT DIV ll 125VDC BATTERY 950007855-01 DC 1DC16E DIV 11125VDC BATTERY CHARGER CAPACITY TEST 950007880-01 DC 1DC16E "JSPECT DIV 11125VDC BATTERY CHARGER 950014069-01 E22 1PS-E22N51r:

HPCS DG LUBE OIL CRANK LOCKOUT 950016330-01 VC OVC01SB MOISTURE SEPARATOR DP NEEDS TO BE VACUUMED TO REDUCE DP 950019472-01 FC 2FC03PB ELIMINATE SOFTFOOT IN MOTOR PER FOLLOWING INSTRUCTIONS 950019472-02 FC 2FC03PB SEND MOTOR OUT FOR WORK NEEDED TO AID IN TASK 01 COMPLETION 950019472-06 FC 2FC03PB FAB PLATE AND HYRDO PUMP CASING 950019812-01 DC 1DC01E INSPECT 250 VDC BATTERY 950031890-01 VC OVC01SB CHARCOAL SAMPLE FROM CONTROL ROOM EMERG MAKEUP TRAIN B 950031896-01 VG 2VG01S CHARCOAL SAMPLE FROM STANDBY GAS TREATMENT TRAIN 2 950031896 02 VG 2VG01S CHARCOAL SAMPLE FROM STANDBY GAS TREATMENT TRAIN 2 950031896-03 VG 2VG01S REPLACE FILTERS 950031903-01 VG 2VG01S STANDBY GAS TREATMENT CHARCOAL FILTER LEAK TEST 950031906-01 VC OVC01SB CONTROL ROOM EMERG MAKEUP TRAIN CHARCOAL FILTER LEAK TEST 950032679-01 HG 1HG027 (CHECK) VALVE 3/4 INCH MOTOR OPERATED GLOBE 950032679-02 HG 1HG027 PERFORM GREASE SAMPLE ON VALVE 1HG027 950035577-01 W

1WO2C MONITOR LINE CURRENT & NOISE ON IWO2C (HPCS PUMP AREA FAN) 950035656-01 W

IVYO3C LUBE FAN CSCS EQUIP AREA RHR PUMP CUBICAL WATER COOLER 950035688-01 E12 2E12C002A PERFORM MOTOR MEGGER (POLARIZATION INDEX) ON 2E12C001 A 95007.689-01 E12 2E12C002B PERFORM MEGGERING ON '28' RHR PUMP MOTOR 950035690-01 E22 1E22C001 PERFORM MEGGERING ON MOTOR 950035695-01 E12 1E12C300D TAKE CURRENT READINGS AND MEGGER 1E12C300D MOTOR 950035701-01 VC OVC01AA PERFORM 'A' TRAIN PORTION OF LES-VC-01 M0035702-01 VC OVC01FB CHARCOAL SAMPLE FROM CONTROL ROOM SUPPLY FILTER 950 0 5707-01 VG 2VG01S STANDBY GAS TREATMENT HEPA FILTER LEAK TEST 9500358 h M B21 2PS-B21N023AB 2PS-B21N023AB-PERFORM U1 RX HIGH PRESS VESSEL ALARM 950035930-01 E12 1E12C300C TAKE CURRENT READINGS AND MEGGER 1E12C300C MOTOR 950036015-01 W

1WO4A WATER FLOWRATE TEST l

t 59

ATTACHMENT A SAFETY-RELATED MAINTENANCE COMPLETED (NON-OUTAGE RELATED)

WRNUM SYS EPN DESCRIPTION 950036039-01 DG 2DG01P MEGGER & OBTAIN CURRENT READINGS ON 2DG01P MOTOR 950036049-01 E22 2E22C002 TAKE CURRENT READINGS AND MEGGER ON MOTOR 950036104 41 VC OVC01AB PERFORM DUCT HTR PERFORMANCE TEST - COORDINATE THIS SU 950036974-01 W

1WD1C LUBE 1WO1C MOTOR, A RHR PP CUBICLE COOLER FAN PER EQ-L3067 95003717S-01 W

1VYO3C PERFORM LES-EO-102 FOR iWO3C TESTING EQ MOTORS (EO-LS073) 950039531-01 VG 2VG01S REMOVE TAPE MARKS AND PAINT BETWEEN CHAR AND HEPA 950040433-01 E22 iPS-E22N514 HPCS DG LUBE OIL CRANKCASE PRESS (S-20) 950041046-01 E12 2E12F336A (CHECK) VALVE 04 IN MOTOR OPERATED GATE 9500436F 01 DC 2DC16E DIV 11125 VDC BATTERY CHARGER CAPACITY TEST 95004444 41 W

1WO2C GREASE HPCS PUMP CUBlCLE COOLER FAN PER EQ-LS067 95005090 -01 E22 2E22C001 MOTOR LUBRICATION USING SHC 624 950051518-01 E22 2E22C003 LUBE 2E22C003 MOTOR, HPCS WATER LEG PUMP PER EQ-LSLO69 950051519-01 E22 2E22C001 PERFORM MEGGERING ON MOTOR (GTD REQUESTED TO BE INSTALLED) 950056631-01 E12 1E12C002A CHANGE OIL ON U1:'1 A' RHR PUMP MOTOR / INSPECT AIR INTAKES 950057287-02 B33 1833C001B INSTALL SHAFT AND BUILD NEW 1B RR PUMP STUFFING BOX 950057287-03 B33 1833C001B MODIFY / MACHINE PARTS ON THE 1B RR PUMP STUFFING BOX 950058012-01 E12 2E120002B PERFORM OIL CHANGE ON '2B' RHR PUMP MOTOR 950058630-01 VG 2VG01C LUBE 2VG01C MOTOR BEARINGS & Ct.EAN AIR INTAKE SCREENS 950058631-01 VG 2VG02C LUBE 2VG02C MOTOR BEARINGS & CLEAN AIR INTAKE SCREENS 950060006-01 E12 1E12C002C MEGGER '1C' RHR MOTOR PER LEP-GM-120 950065076-01 VE OPS-VE108 BAD CONTACTS ON SUCTION PRESSURE SWITCH 950066943-01 E22 1E22C001 CHANGE MOTOR OIL AND CLEAN / INSPECT AIR INTAKE SCREENS 950068421-01 E22 2E22C003 PUMP BEARING DAMAGE 95m68421-02 E22 2E22C003 SHIM DISCHARGE PIPING HANGERS M068718-01 FC 1FCO3PB MEGGER/ CURRENT READINGS ON MOTORS 960068720-01 FC 1FCO3PA MEGGER/ CURRENT READINGS ON MOTORS 950071378 01 VG 2VG01S DOGS NEED TO BE RE-LOCKWIRED -CFM JOB 950072487 01 VG 2VG02C LUBE MOTOR BEARINGS WITH SHC 32 950072488-01 VG 2VG01C LUBE MOTOR BEARINGS WITH SHC 32 950073168-01 PL 2PL33J PERFORM EQ INSPECTION OF 2PL33J PER EQ-LS080-B1 950073529-01 VG 2VG01C MEGGER 2VG01C FAN MOTOR 950073530-01 VG 2VG02C MEGGER 2VG02C MOTOR 950073536-01 PL 2PL32J PER LS080-B1 INSP WIRES CONNECTING PILOT LIGHT + BASE AROUND 950073605-01 E12 1E12C003 T%KE CURRENT READINGS ON RHR WATER LEG PUMP (1E12C003) 950073607-01 W

1WO3C LUBE MOTOR BEARINGS WITH SHC 32 950073608-01 W

2WO2C LUBE MOTOR BEARINGS WITH SHC 32 950073610-01 E12 2E12C002C MEGGER 2E12C002C MOTOR & INSPECT / CLEAN AIR INTAKES 950073612-01 FC 2FC03PB MEGGER/ CURRENT READINGS ON MOTORS 950073621 01 E32 2E32B001J PERFORM 18 MONTH SURV. CHECK CLAMP SCREWS, JUMPER CABL 950075042-01 VG 2FZ-VG003 REPLACE DAMPER ACTUATOR BASED ON EQ LIFE 950076078-01 VD 1VD05C LUBE 1VD05C MOTOR, HPCS DG COOL WTR PUMP RM VENT SUPPLY 60

- -. ~ - - - - _ - -

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

1 ATTACHMENT A SAFETY-RELATED MAINTENANCE COMPLETED

{

(NON-OUTAGE RELATED) l l

I WRNUM SYS EPN DESCRIPTION l

950076079-01 VD.

1VD01C LUBE 1VD01C MOTOR, HPCS DIESEL GEN RM VENT j'

950076080-01 VD 1VD03C LUBE 1VD03C MOTOR, DIESEL GEN RM VENT I

950076081-01 VD 1VD02C LUBE 1VD02C MOTOR, HPCS DG FUEL STORAGE TANK RM VENT 950076082-01 VD 1VD04C LUBE 1VD04C MOTOR, DG FUEL STORAGE TANK RM VENT

.f l

950076085 01 W

1WO60 LUBE 1WO6C MOTOR, FAN CSCS EQ RHR SERVWTR PUMP C+D SUPPLY I

j.

950076168-01 VX 2VXO4C

- LUBE DIVISION ll SWGR ROOM SUPPLY FAN 2VX04C l

l 950076259-01 VX 2VX05C LUBE 2VX05C MOTOR, FAN ESS SWGR DIV-2 BATT ROOM EXH 950076260-01 VX 2VXO7C LUBE 2VX07C RX PROT MG SET RM 1 VENT SUPPLY FAN l

950076269-01 DC 2DC06E PERFORM LES-GM-130 FOR ALL SPARE CUBICLES @ MCC 221Y(2DC06E) h 950076280-01 W

1WO4C MONITOR LINE CURRENT, NOISE LITE STATUS ON EQ MOTORS EQ-LS073

[

3 950076384-01 E22 2E22F362B CHECK VLV LEAKS BY OVERPRESURRIZING COMPR l

}

950078007-01 E21 2E21D003 REPLACE MIN FLOW ORIFICE Si# 772E68 950078864-01 PL 1PL35J INADEQUATE CRIMP ON SEVERAL LUGS 950078881-01 Dia 2RE-D18N009B 2RE-D18N009B-REPLACE SENSOR / CONVERTER PER EQ REQUIREMENTS j

950078885-01 D18 2RE-D18N009D 2RE-D18N009D-REPLACE SENSOR / CONVERTER PER EQ REQUIREMENTS 950080769-01 E12 1E12C002B CHANGE MOTOR BEARING OIL IN '1B' RHR MOTOR j

950082042-01 VG 1VG02C LUBE 1VG02C FAN MOTOR BEARINGS 950100185-01 VE OVE01 AB REPLACE THE DOOR GASKETS. REQ'D BY PADS: M-0045 i

f f

950100191-01 E12 2E12C002A CHANGE UPPER & LOWER BEARING OIL IN 2A RHR MOTOR q

950102094 01 DC 2DC16E PREFORM LES-DC-202J ON 2DC16E (DIV 11 SPARE CHARGER)

{

950102100-03 '

DG ODG023A DG START AIR COMP DISCHARGE CHECK VALVE ACOUSTIC EMISS TEST i

950102101-03 DG ODG023B DG START AIR COMP DISCHARGE CHECK VALVE ACOUSTIC EMISS TEST i

950102823-01 E12 2E12C002C CHANGE OIL IN UPPER & LOWER MOTOR BEARINGS (2C RHR PUMP) 1 950105663-01 VX 2VX19YA LO2VX-009-BOP-SWGR HT RMVL DlV 1 AREA RETURN AIR TEMPERATURE l

950105663-02 VX 2VX19YA DAMPER MOTOR 2VX19YA BROKEN 950105669-01 B21 1PS-B21N560D 1PS-B21N5600-MS SAFETY RELIEF VLV F013-D ADS ACCUM 5

95n105675-02 H13 1H13P631 PERFORM LES-NB-102B U-1 DIV. 2 ADS TIMERS CALIBRATION.

950105676-01 B21 2PS-B21N560V 2PS-B21N560V-MS SAFETY RELIEF VLV F013 V ADS ACCUM 950105687-01 VC OTI-VC106 LOOVC-106--BOP-01-FILTER TRAIN OVC01SA OUTLET TEMP (LCO) 950105692-02 H13 2H13P629 PERFORM EMD UNIT 2 TECH SPEC SURVEILLANCE 950105698-02 H13 2H13P628 PERFORM LES-NB-202A DIV,1 ADS TIMERS CALIBRATION.

950105699-01 B21 2PS-B21N023BB 2PS-B21N023BB-HIGH REACTOR PRESSURE ALARM 950109705-01 VG 2PDI-VG016 CRACKED LENS / REPLACE MAGNEHELIC GAUGE 950109827-01 D18 ORR-D18RS19 SBGT WIDE RANGE NOBLE GAS MONITORING-ORR-D18RS19 950109831-01 C51 1RY-C51K605A LOCAL PWR RANGE MON COMPUTER POINT CAllBRATION (LCO) 950109841-01 CC1 2RY-C51K605A LOCAL PWR RANGE MON COMPUTER POINT CALIBRATION (LCO) 950110130-01 D18 2RlY-D18K751D ERRAT!C BEHAVIOR, SPURIOUSLY TRIPS 950110221-01 E21 2FT-E21N003 INSPECTION OF CONDUIT SEAL WIRES FOR CRACKS, DISCOLORATIONS 950110613-01 VD IVD07C LUBE 1V007tl MOTOR, FAN HPCS DG COOLING WTR PUMP RM 950110619-01 HG 2HG01A VISUALLY inPECT ACCESSIBLE BUTT SPUCE TERMINALS AND CONNEC 950110624-01 E22 2E22C003 PERFORM LES-EQ-102 FOR 2E22C003 TESTING EQ MOTORS (EQ-LS069) 61

i ATTACHMENT A SAFETY-RELATED MAINTENANCE COMPLETED (NON-OUTAGE RELATED) i WRNUM SYS EPN DESCRIPTION 950113296-01 CM 1UY-CM038 DISPLAY SCREEN APPEARS TO BE SLOWLY FAILING 950113560-01 HG 2LSH HG024 2LSH-HG024-HYDROBEN RECOMBINER LOOP SEAL HI LVL ALARM. (LCO) 950113561-01 HG 2LSL-HG025 2LSL-HG025-HYDROBEN RECOMBINER LOOP SEAL LO LVL ALARM. (LCO)

'y 950115565-02 PL.

OPLD2J TASK 1 FAILED PMT CHANNEL STILL ERRATIC 95'J115723C VC OVC01SA CONTROL ROOM EMU "A" TRAIN CHARCOAL FILTER LEAK TEST

]

950116078-01 E21 2E21C001 CHANGE OIL lt' U-2 LPCS MOTOR & CLEAN / INSPECT AIR INTAKES j

950118854 41 VY 1WO2A AIR SIDE FLOWRATE TEST 950118895-01 CM 2PY-CM056 ALARM CAME UP WHEN 2A DG WAS STARTED 950119961-01 E31 1TS-E31N601C RlLEY MODULE WAS USED TO REPLACE 1E31-N601J 950121429-01 E22 1E22C003 FUMP HAS OlL LEAK. REPLACE WITH REBUUT PUMP i

950121625-01 VE OVE09YA DAMPER BLADES ARE CORRODED-REPAIR OR PAINT 950121969-01 E12 1TI-E12R511 GAUGE INDICATlON IS DOWNSCALE i

960000331-01 H13 1H13P629 PERFORM LES-RH-102A DIV i PUMP START TIME DELAY j

960000441 01 E12 1E12C002C CHANGE OIL ON '1C' RHR PUMP & CLEAN / INSPECT MTR AIR INTAKES j

960000556-01 E21 2PS-E21N001 REMAINS ENERGlZED WHEN IT SHCULD NOT BE 960000707-01 DG OPS-DG047 SWITCH TRIPPED DURING LOS DG-SA1 960000738-01 C51 2RY-C51K605GM UPSCALE ALARM LIGHT AT 2H13-P608 DOESN'T ALWAYS LATCH 960001268-01 PL OPLD2J SBGTWRGM LOW RANGE SPIKING AND ALARMING 96000130 S 01 C51 1RY-C51K605DD BROKEN WIRE IN CONNECTOR AT APRM DRAWER 960002435-02 H13 2H13P618 PERFORM LES-RH-202B U-2 DIV. 2 RHR PUMP START TIME DELAY SUR 1

960002443-01 CM 1 RR-CM017 RECORDER INDICATING DOWNSCALE AT 1PM13J. CHECK RECORDER I

960004110-01 C51 2RR-C51R603C 2A RBM RECORDER IN NOT TRACKING I

960004829-01 D18 1EY-D18K614A METER IND DROPPED FROM 600V TO SOV DURING LIP-OG-001 960007690-01 E32 2FT E32N053J DIDN'T GET ANY RESPONSE UNTIL AFTER TOGGLING SW1 (TRIP REF) 960008386-01 VE OVE04CA CANNOT ADJUST UNLOADER VALVE. REPLACE ADJUSTING STEM 960008567-01 DC 1DC09E REPLACE DAMAGED BREAKER AND ASSOCIATED SIS WIRE 960009910-01 B21 2PS-B21N560D RECEIVED LOW PRESSURE ALARMRECAL 960010114-01 DG ODG01A END BELL ON HEAT EXCHANGER IS LEAKING WATER 960010127-01 D18 1RlY-D1BK751 A MODULE ALARMED THEN RETURNED TO NORMAL RAD (<.1) HAPPENED 3X l

960016099-02 H13 2H13P628 PERFORM LES-NB-202A DIV,1 ADS TIMERS CALIBRATION 960016100-02 H13 2H13P629 LES-RH-202A (UNIT 2 DIVISION 1 RHR PUMP START TIME DELAY) 960017188-02 H13 1H13P63)

PERFORM LES-NB-102B U-1 DIV,2 ADS TIMERS CALIBRATION 960017189-01 H13 1H13P618 PERFORM LES-RH-102B U-1 DIV. 2 RHR PUMP START TIME DELAY SUR l

960020499-01 VC OVC05CB CHECK, REPAIR AND/OR REPLACE OIL RETURN CHECK VALVE D6002172101 C51 2RY-C51K605GT U 2 APRM F +/-15VDC REGULATOR CARD Z26 960022085-01 E12 1E12F042A TYPE C APPENDIX J LLRT. RPV BOUNDARY OOS REQUIRED 960022096-01 B21 2PS-B21N560E RECEIVLD ALARM FOR LO PRESS TEST GAUGE SHOWS NORMAL 960022431-01 VG 2FC-VG003 SBGT SYS FLOW VERY ERRATIC DURING OPERABILITY RUN 960024249 01 E22 1E22F362B DG START AIR COMP DISCHARGE CHECK VALVE ACOUSTIC EMISS TEST 960025478-01 H13 1H13P628 PERFORM LES-NB-102A DIV.1 ADS TIMERS CALIBRATION 960025479-01 H13 1H13P629 PERFORM LES-RH-102A DIV 1 PUMP START TIME DELAY d

4 62 l

4

I ATTACHMENT A SAFETY-RELATED MAIN TENANCE COMPLETED i

(NON-OUTAGE RELATED) i WRNUM SYS EPN DESCRIPTION 960025480-02 NB 2H13P631 PERFORM LES-NB 202B U-2 DIV. 2 ADS TIMERS CALIBRATION 960025481-02 RH 2H13P618 PERFORM LES-RH-202B U-2 DIV. 2 RHR PUMP START TIME DELAY SUR 960025779-01 G33 1G33F040 TYPE C APPENDIX J LLRT - RPV BOUNDARY OOS REQUIRED t

960025781-01 B21 1B21F065B TYPE C APPENDIX J LLRT - RPV BOUNDARY 000 REQUIRED l

960027184-01 E22 1E22C003 '

REBUILD SPARE WATERLEG PUMP REMOVED UNDER 950121429 l

960029531-01 E12 1E12F025C REMOVE BOLT ONE AT A TIME / REMOVEWASHERS / RETORQUE I

960029616-01 E12 1E12F025B REMOVE BOLT ONE AT Ai ME / REMOVEWASHERS / RETOROUE 960030611-01 PC 1PC002D.

TYPE B APPENDIX J LLRT l :ESILIANT SEALS AND O-RINGS 960031659-01 C51 1RY-C51K601 A TROUBLESHOOT AND INVESTIGATE PROBLEM WITH IRM'S A AND C 960033085-01 E12 2E12C002C CHANGE OIL IN C RHR PUMP MOTOR UPPER AND LOWER BEARINGS 960034054-01 E31 1TDS-E31N615B CARD FOUND INOPERABLE DURING THE PERFORMANCE OF MOD TEST 960034096-01 D18 2RlY-D18K751B 2018-K751B FAILED TO CLOSE CONTACTS 'T.S. REQUIRED' ON FIRST 960034264 01 VG 1VG02C MONITOR LINE CURRENT, NOISE, LITE STATUS ON EQ MOTORS EQ-LS073 960035314-01 E31 2TDS-E31N614C SWITCH CHATTERS AT RESET POINT i

960038998-01 C51 1C51S302 PENETRATION PRESSURE 14 PSIG, PER LOS-PC-M3, SHOULD BE >15 960039844-01 D18 2RlY-D18K610A DOWNSCALE ALARM DID NOT INITIATE DURING LIS-MS-202 960041619-01 VX 2 TIC-VX009 CORRECT WIRNG PROBLEM AND REPAIR RTD WIRE AT RTD TERMINALS 960042367-01 H13 2H13P655 LUG ON TB-CB TERMINAL 78 IS NOT TERMINATED PROPERLY I

960044179-01 AP 2AP78E WHILE PERFORMING LES-GM-109 T/OL WAS DAMAGED l

960044181-01 AP 2AP81E REPAIR TERMINATIONS 960044293-01 C51 2RR-C51R603B PEN 2 FAILED WHILE PERFORMING LIS-NR-202 960045023-01 DC 1DC09E CHARGER AMPS ARE DROPPING / BATTERY AMPSINCREASING(ERRATIC) 960045202 4 2 RH 2H13P618 PERFORM LES-RH-202B U-2 DIV. 2 RHR PUMP START TIME DELAY SUR 960046691-01 E22 2TS-E22N517 TS 2E22-N517 DG 2B SHUTDOWN TEMP SWITCH WILL NOT CAL 960N7058-01 DC 2DC09E INSPECT FIRE BOARD SPADE CONNECTORS FOR BROKEN SOLDER JNTS 960049623-01 VX 2 TIC-VX009 ROOM RUNNING ABOVE TECH SPEC LIMITS REQ IMMEDIATE FlX 960050677-01 E21 1PS-E21N001 DURING LIS-RH-101 A WHEN PUTTING IN JUMPER TO TEST 1E12-N019A 960051384-01 C51 1RY-C51K605GR D APRM CAUSED 1/2 SCRAM l

960053581-01 DC 1DC09E THE DIV 1125 VDC BATTERY IS ON CHARGE.WE ARE RECEIVING 960054874-01 E22 1TS-E22N517 SWITCH DOES NOT FUNCTION PROPERLY 960057555-01 CM 2LT CM032 TRANSMITTER FAILS TO 2.8 MA OUT WHEN >400"WC (S APPLIED 960059252-01 C51 2RY-C51K605BL LPRM IS DRIFTING 960059769-01 E12 1E12C3008 OUTBD BEARING HOUSING R0TATES 1 TO 2 RPM WHEN PUMP RUNS 960063241-01 C51 2RY-C51K601E IRM DID NOT MEET THE REQUIRED IRM/APRM OVERLAP TESTS 960064874-01 E12 1E12B001B REMOVE / INVESTIGATE / REINSTALL INSULATION /SEE PHOTO /

960064874-02 E12 1E12B001B REPLACE SECTION OF 20" PIPE 960065398-01 C51 2RR-C51R603B DIGITAL DISP!.AY IS VERY DIM 960066087 01 CM 2UY-CM038 ELECTROLUM!NESCENT DISPLAY IS SLOWLY FADING 960067279-02 H13 1H13P631 PERFORM l U, ND-102B U-1 DIV. 2 ADS TIMERS CAllBRATION 960067280 01 H13 1H13P618 PERFOc ^ i LES-RH-102B U-1 DIV. 2 RHR PUMP START TIME DELAY SUR 960067795-01 VC OFR-VC068 PEN STICKS 960068340-01 H22 1H22P076 ALL INSTR'S MUST BE LOCKWIRED PER SECT 7.A.2 & 3 OF THE FSAR 63

i ATTACHMENT A SAFETY-RELATED MAINTENANCE COMPLETED (NON-OUTAGE RELATED)

WRNUM SYS EPN DESCRIPTION 960068340-02 H22 2H22P076 ALL INSTRUMENTS MUST BE LOCKWIRED PER FSAR 960070450 01 H22 1H22P001 APPLY LOCKWIRES TO REMAINING ADS INSTR VALVES 960070450-02 H22 1H22P018 APPLY LOCKWIRES TO REMAINING ADS INSTR VAL */ES 900070450-03 H22 1H22P026 APPLY LOCKWIRES TO REMAINING ADS INSTRUMENT VALVES 960070450-04 H22 1H22P027 APPLY LOCKWIRES TO REMAINING ADS INSTRUMENT VALVES 960070450-05 H22 1H22P075 APPLY LOC VIRES TO REMAINING ADS INSTRUMENT VALVES 960070451-01 H22 2H22P001 APPLY LOCKWIRES TO REMAINING ADS INSTR VALVES 960070451-02 H22 2H22P018 APPLY LOCKWIRES TO REMAINING ADS INSTR VALVES j

960070451-03 H22 2H22P026 APPLY LOCKWIRES TO REMAINING ADS INSTR VALVES 960070451 4 4 H22 2H22P027 APPLY LOCKWIRES TO REMAINING ADS INSTR VALVES l

960070451-05 H22 2H22P075 APPLY LOCKWIRES TO REMAINING ADS INSTR VALVES 960071734-02 NB 2H13P631 PERFORM LES-NB-202B U-2 DIV,2 ADS TIMERS CALIBRATION 960071735-02 RH 2H13P618 PERFORM LES-RH-202B U-2 DIV. 2 RHR PUMP START TIME DELAY SUR 960074881-01 VG IVG003 000 / RESET LIMIT / TORQUE SW AS NEC TO PREVENT HAMMERING 960076215-01 E22 1E22C002 SAMPLE & CHANGE 18 DSL CLG WTR PMP Oil 960076637-01 DC 1DC09E CHARGER VOLTAGE LO/ Fall ALARM UP WITH NORMAL VOLTAGE 960077371-01 H13 1H13P628 PERFORM LES-NB-102A DIV.1 ADS TIMERS CAllBRATION 4

960077904-01 E51 1E51D001 RUPTURE DISC BLEW-REPLACE RUPTURE DISC 960077904-02 E51 1E51D002 RUPTURE DISC BLEW DURING QUARTERLY SURVEILLANCE i

960077904-04 E51 1E51D004 REMOVE / REINSTALL ORIFICE 960077904-08 E51 1E51D010A REMOVE FOR FLUSH AND REINSTALL AFTER FLUSH 960077904-09 E51 1E51D0100 REMOVE FOR FLUSH AND REINSTALL AFTER FLUSH 960077904-10 E51 1E51D008 DISASSEMBLE FLUSH REASSEMBLE FLOW ORIFICE 960077904-12 E51 1E51F040 DISASSEMBLE INSPECT REASSEMBLE CHECK VALVE 960077904-13 E51 1E51D004 CUT-OUT AND REPLACE FLANGES AT 1E51D004 960077904-15 E51 1E51F040 DISASSEMBLE INSPECT REASSEMBLE CHECK VALVE 960077904-17 E51 1E510002 DISC BUCKLED DURING BOLT UP 960078196-01 E51 1PSH-E51N012A FLUSH SENSING LINES OF SWITCHES 1E51-N012A,B.C&D 960079112-02 E51 2E510001 REPLACE RUPTURE DISCS AND INSPECT FOR WATER IN POT 960079127-01 E51 2LSH-E51NC10 RCIC TURB STM INLET DRAIN POT LEVEL-2LSH-E51N010 960079127-03 E51 2LSH-E51N010 RCIC LEVEL SWITCH IS NOT REPEATABLE 960079711-01 E51 2E510002 DISC BUCKLED DURING BOLT UP 960079781-01 ES1 2PSH-E51N009A RETUBE UNIT 2 SWITCHES TO MATCH UNIT 1/ MOVE SNUBBER 960079781-02 E51 2PSH-E51N009B RETUBE UNIT 2 SWITCHES TO MATCH UNIT 1/ MOVE SNUBBER 960081150-01 E51 1E51D001 REPLACE THE 1E51-D001 AND 1E51-D002 RUPTURE DISC'S 960081176-01 E51 2E51D001 REPLACE 2E51-DOO1 AND 2E51-D002 RUPTURE DISC'S 950085204-01 H13 1H13P628 FERFORM LES-NB-102A DIV 1 ADS TIMERS CAllBRATION 960085205-01 H13 1H13P629 PERFORM LES-RH-102A DIV i PUMP START TIME DELAY 960085932-01 B21 2B21F013V SEND SRV TO WYLE LABS FOR TESTING /REFURB 960088043-01 E12 2E12C300A TURN IMPELLER O.D. TO 13-5/8" THEN RETURN TO STORES 960090548-01 H13 2H13P601 SCREW IS STRIPPED REPAIR / REPLACE TERMINAL STRIP 960092212-01 E21 2E21F005 TYPE C APPENDlX J LLRT-RPV BOUNDARY OOS REQUIRED e

64

ATTACHMENT A SAFETY-RELATED MAINTENANCE COMPLETED (NON-OUTAGE RELATED)

WRNUM SYS EPN DESCRIPTION 960094630-01 E12 2E12F005 TYPE B APPENDIX J LLRT RESILIANT SEALS AND O-RINGS 960094631-01 E12 2E12F025A TYPE B APPENDIX J LLRT RESILIANT SEALS AND O-RINGS 960094635-01 E22 2E22F014 TYPE B APPENDIX J LLRT RESILIANT SEALS AND O-RINGS 060095831-01 E12 2E12C300D REMOVE CASING FROM SKID AND SEND OUT FOR REPAIRS BY VENDOR 960099911-01 B21 2B21F032A TYPE C APPENDIX J LLRT - RPV BOUNDARY OOS REQUIRED 960102868-01 E12 2E12F042C TYPE C APPENDIX J LLRT-RPV BOUNDARY OOS REQUIRED 960103492-01 E12 2E12F070 VALVE HANDWHEEL TURNS AND THE VALVE DOES NOT MOVE 960113574-01 C51 1RY-C51K605GP 5 VOLT POWER SUPPLY HAS EXCESSIVE RIPPLE, FOUND DURING CAL 960114219-01 E12 1E12B001 A REMOVE INSULATION ON LINES 1RH37AA AND 1RH38AA 960117590-01 VC OXY-VC086B TROUBLE INDICATION DID NOT LIGHT DURING LES-FP-10A 960117632-01 DC 2DC07E CORROSION ON CELLS 23,27,29,33,38,39,43,50 & 52 1

65

l ATTACHMENT B II.B UNIT SHUTDOWNS l

(UNIT 1)

Date:

Generator Off-Outage Type:

Refuel i

l (YYMMDD) 960125 line (Hours):

2463.8 (L1R07)

REASON: Refuel Outage.

I CRITICAL ACTIVITY PATH: See Appendix A.

j CORRECTIVE ACTIONS (LER# if applicable): None.

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

l SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED: See Appendix C.

l Date:

Generator Off-Outage Type:

Scheduled

(

(YYMMDD) 960507 line (Hours):

0.9 (L1M09)

REASON: Main Turbine overspeed test.

CRITICAL ACTIVITY PATH: Completion of overspeed test.

[

CORRECTIVE ACTIONS (LER#if applicable): None.

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

SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED: None.

l Date:

Generator Off-Outage Type:

Forced (YYMMDD) 960512 line (Hours):

128.3 (L1F33)

REASON: The main turbine experienced high vibration levels on the number 11 and 12 bearing and the unit was subsequently scrammed.

i CRITICAL ACTIVITY PATH: Investigate and repair high vibration on main turbine bearings number 11 and 12.

CORRECTIVE ACTIONS (LER# if applicable): None.

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

SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED: None.

l i

l 1

66 l

i

l ATTACHMENT B ll.B UNIT SHUTDOWNS (UNIT 1) i Date:

Generator Off-Outage Type:

Forced l

q (YYMMDD) 960626 line (Hours):

431.9 (L1F34) l REASON: Automatic scram due to Group 1 Main Steam isolation. Unit remained off-line f.

due to ECCS and CSCS equipment Cooling systems being inoperable due to foreign material in the Service Water system tunnel.

CRITICAL ACTIVITY PATH: Repair neutron monitoring (IRM's), Service water tunnel Cleaning, and DG and RHR strainer repairs.

CORRECTIVE ACTIONS (LER# if applicable): LER# 96-007 and LER# 96-008 RADIOACTIVITY RELEASE / EXPOSURE OVER 10% ALLOWABLE VALUES: None.

SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED:

I WRNUM SYS EPN ~

DESCRIPTION 960038964-01 H13 1H13P622 RECORDER TRACE NOISY PASSES CAL AND FUNCTIONAL.

l 960047383-01 C51 1RY-C51K605H TERMINAL POINT AA-103 HAS BROKEN BANANA JACK 960056232-01 C51 1RY-C51K601 A RECORDER PEN STICKING.

960061971-02 E31 iPDIS-E31N010D CAUSED SPURIOUS Hi-HI 1/2 SCRAM WHILE ON RANGE 1 i

960062998-01 C51 1RY-C51K601H

'A'IRM DET PARTIALLY STUCK IN CORE / FULL OUT LITE STILL LIT 960063002-01 C51 1RR-C51R603A INSPECT SNUBBERS ON BD.90,10D AND 110 l

960064874-01 E12 1E12B001B LPRM 40-57D READS DOWNSCALE AT 33% POWER l

960066183-01 DG 1DG01F INCORRECT GEAR MOTOR DRIVE REASSEMBLY, REASSEMBLE 960066183-02 DG 1DG01F INCORRECT GEAR MOTOR DRIVE REASSEMBLY, REASSEMBLE 960066375-01 E22 1E22F315 REMOVE COVERS INVESTIGATE CAUSE OF LEAKAGE l

960068340-01 H22 1H22P076 VALVE DISC MAY BE SEPARATED FROM THE STEM

}

ALL INSTR'S MUST BE LOCKWIRED PER SECT 7.A.2 & 3 OF THE FSAR i

1 J

)

1 l

4 1

67

ATTACHMENT B i

ll.B UNIT SHUTDOWNS j

(UNIT 1) 1 Date:

Generator Off-Outage Type:

Forced (YYMMDD) 960922 line (Hours):

871.9 (L1F35)

REASON: Manual scram due to problems with the number 4 Main Turbine Control Valve.

CRITICAL ACTIVITY PATH: Repair servo valves for Main Turbine Control Valves number 3 and 4, offgas drain line repairs, and OCB 9-10 repairs.

CORRECTIVE ACTIONS (LER#if applicable): None.

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

SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED:

WRNUM SYS EPN DESCRIPTION 960047851-01 B21 1821F065A INSPECT FUSE HOLDER 960071768-01 DC 1DC17E AMPS SWINGING WHILE THE BAT WAS ON CHARGE 960080846-01 C41 1C41F017 OUTLET FLANGE STUD LOOSE (FINGER TIGHT) 960083498-01 C11 1C11D001037 NITROGEN LEAKS PAST CHARGING CAP 960085717-01 DC 1DC11E BREAKER FAILED TRIP TEST 960093551-01 E12 1 E12F332A INSPECT / REPAIR VALVE 2E12-F332A VALVE j

960093551-02 FC 1FC000 REMOVEllNSTALL M09-FC31-1020X 960100526-01 E22 1HS-E22AS023 DETERM AND REMOVE SWITCH 68 t

ATTAC!iMENT B 11.8 UNIT SHUTDOWNS (UNIT 1)

Date:

Generator Off-line Outage Type:

Scheduled (YYMMDD) 961029' (Hours):

1536 (L1F35)

REASON:

Forced outage status changed to a planned maintenance outage. A management decision was made to keep the unit shutdown to address s number of engineering concems.

CRITICAL ACTIVITY PATH: Plant material condition and engineering concems. The total scope of work to complete L1F35 had not yet been determined at the end of December 1996. The scope will be determined, in part, by the results of ongoing review activities including the System Functional Performance Review program and a thorough review of plant backlogs.

CORRECTIVE ACTIONS (LER#if applicable): None.

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

l i

I 69

.I

ATTACHMENT B 11.B UNIT SHUTDOWNS (UNIT 1)

SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED:

WRNUM SYS EPN DESCRIPTION 960066495-01 DC 1DC09E CHARGER AMPS ARE DROPPING ERRADICALLY 960068530-01 C51 1RY-C51K605S32-49D FAILED DOWNSCALE AND IV PLOT HAD NO CURRENT 960070717-01 C51 1RY-C51K601H 1RM H POSSIBLE SPIKING & 1/2 SCRAM ON RNG 6 7 TRANSFER 960070717-02 C51 1RY-C51K002H REPAIR / REPLACE 1H IRM CONNECTORS AND/OR DETECTOR 960071768-01 DC 1DC17E AMPS FOUND SWINGING WHILE THE BATTERY WAS ON CHARGE.

960074030-01 C51 1RR-C51R603B APRM B READS LOW ON RECORDER ONLY 960078404-01 C51 1RY-C51K605A, CLEAN LPRM CHANNEL MODE SWITCH FOR 40-41D 960084095-01 D18 1RlY-D18K615B INDICATION IS ERRATIC 960092205-02 E51 1E51F065 VALVE DOES NOT OPERATE THROUGH IT'S ENT!RE STROKE 960093551 04 E12 1E12F332A REPAIR DISC.

960093551-05 E12 1E12F332A WELD BUILD UP AND REPAIR OF VALVE BODY PER NDIT LS-0411.

960093552-02 E12 1E12F332B REPAIR VALVE DISC PER NDIT LS-0411 UPGRADE 3.

960093552-03 E12 1E12F332B PERFORM VALVE BODY REPAIRS AND INSTALL NEW GUIDES 960095026-01 CM 1CM026B TROUBLE SHOOT BLOWN FUSE FOR SOLENOID VALVE 1CM026B 960096810-01 PL 1PL77J LOW PRESSURE ALARM IS ON WITH PROPER BOTTLE PRESSURES 960097993-01 E22 1E22F332 NUTS ON TWO U-BOLTS ARE LOOSE ON THE SUPPORT OF VALVE 960100526-01 E22 1HS-E22AS023 DETERM AND REMOVE SWITCH 960100527-01.

E51 1HS-E51 AS003 DETERM AND REMOVE SWITCH 960103401 01 D18 1RR-D18R800 RECORDER ERRATIC 960106811 01 VY 1VYO1Y TROUBLESHOOT, REPAIR / REPLACE DAMPER 1VYO1Y 960106816-01 VY 1VYO4Y DURING WALKDOWN, FOUND 1VYO4Y CRACKED 12 INCHES OPEN 960107671-01 VG 1TE-VG031 TROUBLESHOOT AND REPAIR-PANEL IN PREALARM 960110358-01 C51 1RR-C51R603C SOME LED DISPLAY SEGMENTS NOT WORKING 960112546-01 E12 1E12B001A LINES 1RH37AA AND 1RH38AA HANGERS ARE NOT INSTALLED.

960112546-02 E12 1E12B001A REPLACE THE (8) NUTS ON 1RH37AA AND 1RH38AA HANGERS 960114495-01 DG 1DG01K CYLINDER VALVE ASSEMBLIES ARE LOOSE, MUST BE TIGHTENED.

70

ATTACHMENT B 11.B UNIT SHUTDOWNS (UNIT 2)

Date:

Generator Off-Outage Type:

Forced (YYMMDD) 960202 line (Hours):

149.8 (L2F23)

REASON: Manual reactor scram due to loss of cooling on the '2E' main power transformer and maintenance on the number 4 turbine control valve.

CRITICAL ACTIVITY PATH: Repair cooling to 2E MPT, repair leak on MSIV-LSC valve, and repair TSV and CIV servo and shutoff valves.

CORRECTIVE ACTIONS (LER#if applicable): LER# 96-002.

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

SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED:

WRNUM SYS EPN DESCRIPTION 96001o382-01 E32 2E32F302E PACKING LEAK /FIX IT Date:

Generator Off-Outage Type:

Forced (YYMMDD) 960211 line (Hours):

14.0 (L2F24)

REASON: Generator taken off-line to perform maintenance on the main power transformer disconnect. Reactor remained critical.

CRITICAL ACTIVITY PATH: Main generator manual disconnect repairs.

CORRECTIVE ACTIONS (LER#if applicable): None.

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

SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED: None.

71

ATTACHMENT B ll.B UNIT SHUTDOWNS (UNIT 2) j i

Date:

Generator Off-Outage Type:

Forced i

(YYMMDD) 960521 line (Hours):

85.1 (L2F25) l REASON: Unit shutdown due to problems with the Electro-Hydraulic Control (EHC) system.

CRITICAL ACTIVITY PATH: EHC repairs for bypass valve alid Turbine Control Valves, replacement for 2GS002 motor operated valve (MOV).

CORRECTIVE ACTIONS (LER# if applicable): None.

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

i SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED:

WRNUM SYS EPN DESCRIPTION 950081854-01 C51 2RY-C51K601D WHILE PERFORMING LIS-NR-202 FINISHING UP THE LAST CHANNEL'H' 950081854-02 C51 2RE-C51N002D IRM"D" DETECTOR REPAIR / REPLACE 960049623-01 VX 2 TIC-VX009 ROOM RUNNING ABOVE TECH SPEC LIMITS - REQ IMMEDIATE FIX 960050608-01 C51 2RY-C51K601E FAILED UPSCALE AFTER SCRAM l

l I

l t

72 I

l I

~_

-m 1

ATTACHMENT B ll.B UNIT SHUTDOWNS I

(UNIT 2) e i

Date:

Generator Off-Outage Type:

Forced (YYMMDD) 960629 line (H0urs):

412.2 (L2F26) i j

l REASON: Unit shutdown due to ttie ECCS and CSCS equipment cooling systems being inoperable due to foreign material in the Service Water system tunnel.

J CRITICAL ACTIVITY PATH: Clearing service water tunnel of foreign material.

CORRECTIVE ACTIONS (LERi4if applicable): LER# 96-008.

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

I SAFETY RELATED COR'ECTIVE MAINTENANCE COMPLETED:

)

WRNUM SYS EPN DESCRIPTION 950081854-04 C51 2RY-C51K0010 IRM 'D' FAILED TEST ON STARTUP/ GOING TO RUN7 960000738 41 C51 2RY-C51K605GM UPSCALE ALARM LIGHT AT 2H13-P608 DOESNT ALWAYS LATCH

{

960062799 41 E21 2E21C001 PERFORM INSPECTION OF LPCS MOTOR COOLER 960063624-01 CM 2 AIR-CM048 PEN IS IMMOBILE WITH DIV 2 POST LOCA RUNNING 960063819-01 C51 2RY-C51K601F TROUBLESHOOT / REPAIR ELECTRONICS OR DETECTOR FOR IRM F 960065398 41 C51 2RR-C51R603B DIGITAL DISPLAY IS VERY DIM 960066107-01 E12 2E12F009 RE-TORQUE VALVE BONNET 960066177-02 DG,

2DG01F INVESTIGATE GAP 960066179-01 E22 2E22D300 INCORRECT GEAR MOTOR DRIVE REASSEMBLY

- 960066179-02 E22 2E22D300 INVESTIGATE GAP 1

960068340-02 H22 2H22P076 ALL INSTRUMENTS MUST BE LOCKWIRED PER FSAR 4

4 J

e i

I 4

73

..m_..-._

?

ATTACHMENT B II.B UNIT SHUTDOWNS (UNIT 2) l Date:

Generator Off-Outage Type:

Refuel (YYMMDD) 960922 line (Hours):

2472 (L2R07)

REASON: Refuel outage.

CRITICAL ACTIVITY PATH: See Appendix B.

CORRECTIVE ACTIONS (LER#if applicable): None.

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

e l

l' i

i i

l 74

...__m.

~ _ _.

ATTACHMENT B ll.B UNIT SHUTDOWNS (UNIT 2)

SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED:

WRNUM SYS EPN DESCRIPTION 940060460-03 E22 2E22C002 SEND PUMP BACK TO OEM FOR CASING REPAIR 950026408-02 CM 2CM012 FLUSH AND PRESSURE TEST AND BACKFlLL 950026408-01 CM 2CM012 CLEAN AND INSPECT EFCV DURING L2R07 950026603-02 B21 2B21F380 PRESSURE TEST CHECK VALVE 2B21F380 950041300-01 B21 2B21F485B VALVE HAS20 DROP / MIN PACKING LEAK FOUND DURING HYDRO 950053912-01 B21 2PS-B21N015D D ALARM DID NOT RESET PRIOR TO 932 # CLEARED AT 935 #

950092079-02 E12 2E12F313A REBUILD RELIEF VALVE 2E12F313A (FAILED TEST) 950092086 02 E51 2E51F017 FAILED SET POINT TESTING DISASSEMBLE AND REPAIR IF REQ'D 950099971-03 E12 2E12F332A REPAIR VALVE BODY PER NDIT NO, LS-0411 950099971-04 E12 2E12F332A REPAIR BENT STEM PER NDIT NO. LS-0458 UPGRADE O 960035356-01 B21 2LT-B21N408B ROSEMOUNT TRANSMITTER SHIFTED FROM CAL / RECALIBRATE 960044551-01 B21 2LT-B21N40BA POSSIBLE DEFECTIVE TRANSMITTER 960069764-01 PC 2PC001A DIVISION 2 INDICATION WENT TO DUAL INDICATION 960082665-01 E31 2TE-E31N004A TEMPERATURE READING 121, LOCALLY TEMPERATURE IS 100 960083481-01 E22 2E22F342 CLEAN AND INSPECT VALVE AT A FUTURE DATE 960087621 01 B21 2821F508A PACKING LEAK 960089197-01 E21 2E21F051 HANDWHEEL ON ACTUATOR HARD TO TURN. SHOULD BE FREE SPINNING 960090548-01 H13 2H13P601 SCREW IS STRIPPED REPAIR / REPLACE TERMINAL STRIP 960093362-01 E21 2E21F006 DETERM SOLENOID ON ACTUATOR TO ALLOW MECHANICAL CONNECTION 960093562-05 E12 2E12F332C STEM IS BENT, STRAIGHTEN PER WORK INSTRUCTIONS 960093563-05 E12 2E12F332D STRAIGHTEN STEM PER NDIT LS-0458 UPGRADE 1 960093647-04 E12 2E12F332B REPAIR VALVE STEM PER NDIT LS-0458 UPGRADE 1 960093885 01 C71 2PS-C71N002C PRESSURE TEST OF INSTRUMENT AS REQUIRED BY LIS-NB-216 960095385-01 W

2WO4C HIGH VIBES IN FAN, INVESTIGATE & REPAIR 960101253-01 B21 2B21F032B REPAIR LEAK ON PIPING, FOUND BY OPERATIONS 960101988-01 H13 2H13P608 TERMINAL POINTS 102TO105 AND POINT 111 ON TB-51 ARE BROKEN.

960103492-01 E12 2E12F070 VALVE HANDWHEEL TURNS AND THE VALVE DOES NOT MOVE 960105408-01 DC 2DC03E CRWR 250 VDC BATT CHARGER OUTPUT VOLTAGE ERRATIC 960107667-01 PA 2PA12J GREEN LIGHT FOR POINT #9 WILL NOT L!GHT l

960110394-01 W

2TZ WO23C TROUBLESHOOT, REPAIR / REPLACE DAMPER 2WO3Y/2TZ-WO23C 960112575-01 H13 2H13P603 INADVERTENT ANNUNCIATION OF AN ALARM I

960114493-01 DG 2DG01K CYLINDER VALVE ASSEMBLIES ARE LOOSE. MUST BE TIGHTENED I

l 4

0 i

75 l

i

__.=_______~.______m_.-

?

ATTACHMENT C I

GREATER THAN 20% IN DESIGN PWR LEVEL II.B FORCED REDUCTIONS IN POWER

)

(UNIT 1) l s

i Date:

Operation At Reduced Power j

(YYMMDD) 960619 (Hours):

40.7 j

]

REASON: Power reduction due to service water strainers high differential pressure.

j CRITICAL ACTIVITY PATH: Maintenance on the service water strainers.

q CORRECTIVE ACTIONS (LER# if applicable): None.

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

J i

SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED:

WRNUM SYS EQUIPMENT DESCRIPTION j

960059769 01 E12 1E12C3ooB OUTBD BEARING HOUSING ROTATES 1 TO 2 RPM WHEN PUMP RUNS j

Date:

Operation At Reduced Power (YYMMDD) 960624 (Hours):

6.28 i

1 REASON: Power reduction due to low service water system header pressure.

l CRITICAL ACTIVITY PATH: Maintenance work on the service water system.

d CORRECTIVE ACTIONS (LER# if applicable): None, f

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

i SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED: None, i

a 4

f 1

i t

i 76

I ATTACHMENT C l

11.B FORCED REDUCTIONS IN POWER GREATER THAN 20% IN DESIGN PWR LEVEL i

l (UNIT 2)

Date:

Operation At Reduced Power (YYMMDD) 960105 (Hours):

12.5 i

REASON: Power reduction for repair of the 22 'A' Feedwater Heater Valve and performance of scram time testing.

CRITICAL ACTIVITY PATH: Wom on the 22 'A' Feedwater Heater Valve and scram time testing.

CORRECTIVE ACTIONS (LER# if applicable): None.

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

SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED: None.

l Date:

Operation At Reduced Power (YYMMDD) 960113 (Hours):

46.0 i

REASON: Power reduction for repair of the 22 'A' Feedwater Heater Valve and number 2 Turbine Control Valve (TCV).

CRITICAL ACTIVITY PATH: Completion of maintenance on the 22 'A' Feedwater Heater Valve and number 2 TCV.

CORRECTIVE ACTIONS (LER# if applicable): None.

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

SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED: None, i

Date:

Operation At Reduced Power (YYMMDD) 960122 (Hours):

61.8 REASON: Power reduction for testing to identify a possible fuel failure.

CRITICAL ACTIVITY PATH: Flux tilt testing.

l CORRECTIVE ACTIONS (LER# if applicable): None.

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

SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED: None.

}

r 77 1

i f

ATTACHMENT C II.B FORCED REDUCTIONS IN POWER GREATER THAN 20% IN DESIGN PWR LEVEL (UNIT 2)

Date:

Operation At Reduced Power (YYMMDD) 960126 (Hours):

3.3 REASON

Power reduction to place the '2A' Turbine Driven Reactor Feedpump off-line for maintenance.

CRITICAL ACTIVITY PATH: Maintenance on the *2A' Turbine Driven Reactor Feedpump.

CORRECTIVE ACTIONS (LER# if applicable): None.

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

i SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED: None, Date:

Operation /.t Reduced Power (YYMMDD) 960426 (Hours): _

65.0 REASON: Power reduction due to the number 3 Turbine Con rol Valve failing to reopen after surveillance testing.

CRITICAL ACTIVITY PATH: Maintenance on the nur,ioer 3 Turbine Control Valve.

CORRECTIVE ACTIONS (LER# if applicable): None.

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

SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED: None.

l i

Date:

Operation At Reduced Power (YYMMDD) 960520 (Hours):

3.0 REASON

Power reduction due to the number 1 Turbine Bypass Valve opening.

CRITICAL ACTIVITY PATH: Maintenance on the number 1 Turbine Bypass Valve.

j CORRECTIVE ACTIONS (LER#if applicable): None.

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

SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED: None.

78

ATTACHMENT C ll.B FORCED REDUCTIONS IN POWER GREATER THAN 20% IN DESIGN PWR LEVEL (UNIT 2)

Date:

Operation At Reduced Power (YYMMDD) 960520 (Hours):

9.5 REASON

Power reduction which proceeded forced outage L2F25.

CRITICAL ACTIVITY PATH: Completion of maintenance on the number 1 Turbine Bypass Valve.

CORRECTIVE ACTIONS (LER# if applicable): None.

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

SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED: None.

Date:

Operation At Reduced Power (YYMMDD) 960619 (Hours):

6.0 REASON

Power reduction due to Service Water Strainers high differential pressure.

CRITICAL ACTIVITY PATH: Maintenance on the Service Water Strainers.

CORRECTIVE ACTIONS (LER#if applicable): None.

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

SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED: None.

Date:

Operation At Reduced Power (YYMMDD) 960624 (Hours):

60.5 REASON: Power reduction due to low Service Water System discharge pressure.

CRITICAL ACTIVITY PATH: Maintenance on the Service Water System.

1 CORRECTIVE ACTIONS (LER# if applicable): None.

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

SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED: None.

79

l APPENDIX A CRITICAL PATH ACTIVITIES REFUEL OUTAGE (L1R07) j l

TURBINE GENERATOR OFF LINE REACTOR SHUTDOWN TO COOLDOWN DISASSEMBLY OF REACTOR PRESSURE VESSEL j

CAVITY FLOODUP CORE UNLOAD "0" DIESEL GENERATOR WORK RR/RWCU DECONTAMINATION RHR CHEMICAL DECONTAMINATION i

BUS 142Y OUTAGE

'B' RHR LLRT l

'C' RHR LLRT

'A' RHR WORK

'B' RHR WORK

'C' RHR WORK REFURBISH F027B - B RHR SUPPRESSION POOL SPRAY REFURBISH F0648 - B RHR MIN FLOW BYPASS SHROUD INSPECTION

{

CORE RELOAD REASSEMBLY OF REACTOR PRESSURE VESSEL l

CONTAINMENT PRESSURE TEST REACTOR PRESSURE VESSEL HYDRO 1

MODE SWITCH TO STARTUP MAIN TURBINE GENERATOR ON-LINE l

80

APPENDIX B CRITICAL PATH ACTIVITIES REFUEL OUTAGE (L2R07)

TURBINE GENERATOR OFF LINE REACTOR SHUTDOWN TO COOLDOWN DISASSEMBLY OF REACTOR PRESSURE VESSEL CORE UNLOAD IRM/SRM DRY TUBE INSPECTION 2833-FO67B AND 2B33F023A RX RECIRC DISCHARGE AND SUCTION VALVE REPAIRS i

2G33-F040 RWCU RETURN VALVE REPAIRS j

4 AC TO DC MODIFICATION FOR GROUPS II AND IV FILL AND VENT LPCS VE SYSTEM CHARCOAL CHANGE-OUT l

REPAIR OF THE RT F040 j

d REPAIR OF THE 2E21-F035 DISCHARGE RELIEF VALVE j

SBM SWITCH REPLACEMENT REPAIR OF 2E12-F041 A i

REPAIR OF 2E12F332A AND B 2B21-F032B ACTUATOR REPAIRS REPAIR OF 2DG0112A DG COOLING WATER STRAINER BACKWASH VALVE REPAIR OF VR STATION HEATING COILS i

CORE SHROUD UT AND VESSEL INTERNALS IWI j

LLRT ON 2E12-F041 A I

AT THIS POINT IN THE OUTAGE A MANAGEMENT DECISION WAS MADE TO KEEP THE UNIT DOWN TO ADDRESS PLANT MATERIAL CONDITION AND ENGINEERING a

CONCERNS. THE FOLLOWING ACTIVITIES REPRESENT THE CRITICAL PATH AS OF DECMEBER 31,1996, FOR COMPLETING THE MAJORITY OF THE WORK:

DIVISION 2 WORK

'A' DIESEL GENERATOR WORK AND TESTING I

PLACE B RHR IN SHUTDOWN COOLING DIVISION 1 WORK DIVISION 1 OPERABILITY TESTING ESTABLISH A AND B RHR ALTERNATE DECAY HEAT REMOVAL

. COMMON SHUTDOWN COOLING HEADER WORK BUSSES 141X,142X 151, AND 152 PREP, OUTAGE AND TESTING STATION AUX TRANSFORMER WORK

'O' DIESEL GENERATOR WORK AND TESTING DIESEL GENERATOR TESTING PRIMARY CONTAINMENT FLOOR BYPASS TEST REACTOR PRESSURE VESSEL HYDRO AND CRD SCRAM TIME TESTING J

THE TOTAL SCOPE OF WORK TO COMPLETE L2R07 HAD NOT YET BEEN DETERMINED AT THE END OF DECEMBER 1996. THE SCOPE WILL BE DETERMINED, IN PART, BY THE RESULTS OF ONGOING REVIEW ACTIVITIES INCLUDING THE SYSTEM FUNCTIONAL PERFORMANCE REVIEW PROGRAM AND A THOROUGH REVIEW OF PLANT BACKLOGS.

81

APPENDIX C REFUELING OUTAGE (L1R07) l SAFETY RELATED CORRECTIVE MAINTENANCE WRNUM SYS EPN DESCRIPTION 930046646-02 E12 1E12C300A REMOVE / REPLACE OUT BOARD BEARING 940058261-01 IN 11N095B CROSS THREADED-PIPE WRENCH HAD USED THE WHOLE WAY OFF 940058621-01 H13 1H13P606 BROKEN DIVIDER BETWEEN TERMINALS 940053644-01 E22 ill-E22R621 REMOVE AND INSTALL NEW ONE 940058973-01 E22 1E22F342 WHEN VLV RESET,IND DID NOT RETURN TO "OPEN" WITHOUT TAPPING 940058974-01 E22 1E22F341 WHEN VLV RESET, INDICATION DID NOT RETURN TO "OPEN" 940059008-01 CM 1CM010 CHECKED / FLOW DROPPED OFF + CONTROL ROOM LIGHT CHANGED 940059027-01 E12 1E12F042A MPDI DOES NOT PROVIDE ACCURATE POSITION IND OVER FULL RANGE 940059100-01 C11 1C11F381 APPEARS TO BE BINDING /VLV FAILED TO GO FULL CLOSED DURING LO 940059385-01 E12 1E12F339B VLV DOES NOT OPEN/ INVESTIGATE + REPAIR 940059628 01 E22 1E22S001 DEFECTIVE O-RING REQUIRES REPLACING ON RIGHT SIDE OF LUBE 01 940059873-01 B21 1821F326A CHECKED BUT HAD TO BE PRESSURIZED FROM DWNSTRM TO RE-OPEN 940060033-01 E51 1E51F064 VLV MOVED SLIGHTLY WHILE ATTEMPTING TO CYCLE VLV (ABOUT 1")

940060244-01 CM 1UY-CM038 RTD "R" ELEMENT 2 READS GREATER THAN 5 DEG THAN ELEMENT 1 940060387-01 E12 1E12F042A HAS PACKING LEAK-1 DROP /2-3 SECONDS 940061107-03 C51 1RE-C51N002D REPLACE IRM D DETECTOR AND SHUTTLE / DRIVE TUBE O-RING 940061361-01 DC 1DC11E SMALL 25-50 V GROUND INTERMITTENT 940061856-01 AP 1AP07E SEQUENCE OF EVENT RECORDER DOES NOT WORK 940061857-01 E12 1E12F312A TRIPPED IT'S CONTROL POWER FUSE WHILE LOS-HG-Q1 ATT 1C IN PR 940061868-01 C51 1RY-C51K605BR LPRM 56-25 A ON APRM *A' HAS POOR CONNECTION 940083301-02 B33 1B33F060B REPLACE BONNET GASKET AND REPACK VALVE 1B33-F060B 940083301-03 B33 IB33F060B MACHINE SERRATED FACE IN ACTUATOR CARTRIDGE FLANGE FACE 940083943-02 E51 1E51F082 DISASSEMBLE / INSPECT 1E51F082 DUE TO FAILED LLRT 940085032-02 E12 1 E12F088A REBUILD RELIEF VALVE BECAUSE OF FAILED SET POINT TEST 950002536-01 G33 1G33F106 VALVE PACKING LEAK. BLOWS STEAM 2 FT IN AIR 950002566-01 B21 1PS-B21N056C STOP VALVE LEAKS BY WOULD NOT ISOLATE PER LIS-MS-106 950002566-02 B21 1PS-B21N056C REPLACE VALVE WITH NEW VALVE 950002567-01 ES 1ESO44 VALVE WOULD NOT SEAT DURING PERFORMANCE OF LIS-MS-106 950005681-02 H13 1H13P623 BURNISH CONTACTS ON 1B21KX202 950011206-02 E51 1E51F076 DISASSEMBLE, INSPECT AND REPAIR VALVE FOR LEAKING D50012803-04 DG 1DG01K EXCESSIVE VALVE COVER OIL LEAKAGE. PLEASE REPLACE GASKET.

950012803-06 DG 1DG01K RETORQUE OIL PIPING FLANGE BOLTING 950012807-02 E22 1E22S001 EXCESSIVE OIL LEAKAGE FROM COVER AND SIDE BOLTS 950012807-06 E22 1E22S001 RETORQUE LUBE OIL PIPING FLANGE BOLTING 950014464-01 B33 1B33F023B VALVE PACKING IS LEAKING 950050283-01 IN ilN114 11N114 VALVE LEAKS BY WHEN CLOSED 950055501-01 C71 1ZS-C71N006B INSPECT / FIND THE EXTENT OF AND REPAIR HEAT DAMAGE TO CABLE 950062888-01 C51 1RY-C51K605DR LOCAL DNSCL LIGHT SOCKET IS VERY FLAKY.

950066634-01 E12 1E12F047A MINOR PACKING LEAKAGE / REPACK 950066635 01 E12 1E12F048A MINOR PACKING LEAKAGE / REPACK 950066607-01 E51 1E51F008 SLIGHT PACKING LEAK 950067853-01 E12 1E12F047B VALVE HAS PACKING LEAK, LEAKING DOWN TO 694, NEEDS CATCH BAS 950073706-01 C51 1RY-C51K601G IRM G SPIKING INTERMITTENTLY ON 8/21/95 SH 3-GAVE 1/2 SCRAM 950080546-01 DG 1 DG073 PLUG IS LEAKING OIL 950093616-01 E51 1E51F069 REPACK / REPAIR AS REQUIRED 82

APPENDIX C REFUELING OUTAGE (L1R07)

SAFETY RELATED CORRECTIVE MAINTENANCE WRNUM SYS EPN DESCRIPTION 950107402-01 C71 1ZS-C71N006E IMPROPER LIMIT SWITCH OPERATION ON MAIN STOP VALVE #2 950121931-01 E12 1E12C300A REPLACE SEALS 960007687-01 B21 1B21F437 HP EFCV FAIL TO CHECK DURING LIS-NB-115. DISASSEMBLE DURING 960007855-01 C71 1C71S003C REPLACE BAD LOGIC CARD 1C71-S003C 960008424-01 E51 1E51F028 1E51F028 FAILED LLRT 5.2 SCFH LEAKAGE EXCEEDED ADMIN LIMIT 960008426-01 E51 1E51F084 1E51F084 VALVE FAILED TO SEAT / FAILED TO HOLD PRESSURE 950008427 01 E51 1E51F064 1E51F064 FAILED LLRT. SEAT LEAKAGE MAY BE OVERSEATING 960009525-01 PA 1PA14J RELAY CONTACT R2-M2 DIDN'T CLOSE TO CLOSE 1VOO37 VALVE.

960010922-01 E12 1E12F099A 1E12F099A'A' SDC LOOP TEST CK BYP STP EXCESSIVE SEAT LEAKAGE 960010922-02 E12 1E12F099A 1E12F099A'A' SDC LOOP TEST CK BYP STP EXCESSIVE SEAT LEAKAGE 960011732-01 E21 1E21C002 VIBE ANALYSIS INDICATES IMPACTING IN THE PUMP / COUPLING AREA.

960012880-01 DC 1DC13E REPLACE DAMAGED OR MISSING BOLTING 86 AT 112Y (1DC13E) 960013128-01 C71 1C71S003B BROKEN WIRE TO 3 OHM RESISTOR / REPAIR 960013958-01 H13 1H13P603 HIGH RESISTANCE CONTACTS ON RELAY K3B / REPLACE RELAY 960014306-01 C41 1C41F004A AMPHENOL CONNECTOR BAD ON SQUlB VALVE "A' 960014536-01 B33 1B33F066B LINE 1RR48BB DOWNSTREAM STUB BENT AND CRACKED; REPAIR 960016799-01 E31 1PDIS-E31N011 A SWITCH DID NOT PASS RESPONSE TIME TEST LIS-PC-118 960017281-01 PC 1PC003D 1PC003D OUTBOARD FLANGE LEAKS / REWORK AS NECESSARY 950018159-01 H13 1H13P601 THE CLOSED LIGHT FOR THE 1E12F049A IS BROKEN, REPLACE 960018968-01 H13 1H13P629 WIRE AT CC-9 (FIELD SIDE) NOT PROPERLY LUGGED 960019570-01 VR 1VR05YB BOLT NEXT TO TOP TRAVEL STOP MISSING, REPLACE BOLT 960020762-01 E12 1E12F090A HANDWHEEL DOES NOT MOVE VALVE, APPEARS OPERATOR BROKE 960022466-01 C51 1RR-C51R603A RED PEN DOES NOT RESPOND 960022466-02 C51 1RR-C51R603A

'C' IRM IS NOT RESPONDING CORRECTLY 960022613-01 E12 1512F359B FAILED TO CHECK WHEN TESTED PER LIS-NB-115 960026018-01 H13 1H13P623 RELAY CONTACTS R3 AND M3 HAVE HIGH RESISTANCE 960026024-01 E31 1TDS-E31N613B RCIC EQUIPMENT AREA PIPE TUN Hi AMB/DIFF TEMP RILEY NEEDS R 960026853-01 E31 1TS-E31N601J MODULE CANNOT BE CAllBRATED, ALSO IT CHATTERS EXCESSIVELY.

960028708-01 B13 1813D003 REPLACE / REPAIR JET PUMP #10 HOLD DOWN BRACKET INDICATION 900028708-02 B13 1B13D003 JET PUMP #10 HOLD DOWN BRACKET TACKWELD 960028878 01 B21 1821F013H AIR BLOWING OUT EXHAUST PORT OF AIR VALVE 960029170-01 H22 1H22P026 LUG JJ-14 IS STRIPPED / TAP HOLE AND INSTALL NEXT BIGGER SCREW 960029239-01 LV 1LV99E REPAIR SRM DRIVE FEED CABLE INR418 AT PENETRATION E-7 960029918-01 B33 1B33F317B INSPECT, CLEAN, REPAIR EFCV, VALVE WENT DUAL DURING LIS-NB-115 960030947-01 E22 1E22S001 REPAIR FUEL OIL LEAK ON HPCS DIESEL 960031065-01 C61 1C61P001 24 VOLT POWER IS REVERSED TO THE EG-M FROM REMOTE S/D PANEL 960031082-03 B33 1833F0608 WELD SEAL LEAK-OFF LINE 960031982-01 E22 1E22S001 FUEL LINE LEAK 960032917-01 VQ 1VOO31 1VQO31 VALVE FAILED TO STROKE DURING LTS-400-19 960034261-01 CM 1RE-CM017 DIV 2 GROSS GAMMA IND ON RECORDER AND TRIP UN!T SUSPECT 960036605-01 VT 1VT79YA DAMPER CLOSES WITH NORMAL SYSTEM FLOW / SET SO IT IS OPEN 960036605-02 VT 1VT79YB DAMPER CLOSES WITH NORMAL SYSTEM FLOW / SET SO IT IS OPEN 960036605 4 3 VT 1VT79YC DAMPER CLOSES WITH NORMAL SYSTEM FLOW / SET SO IT IS OPEN 960037242-01 E51 1E51D011 ORIFICE PASSAGE APPEARS TO BE CLOGGED OR RESTRICTED.

960038342-01 PL iPL76)

ERRATIC INDICATION ON 02 RErORDER 83

l I

APPENDIX D I

REGULATORY GUIDE 1.96 REPORT NUMBER OF PER3ONNEL AND PERSON-REM BY WORK AND JOB FUNCTION FOR 1996

-NUMBER OF PERSONNEL-

-QUANTITY OF PERSON-REM--

WORK AND JOB FUNCTION STATION CONTRACTORSI UTILfrY 107 AL STATION CONTRACTOR / UTUTY TOTAL EMPLOYEES OTHERS EMPLOYEES PERSONS EMPLOYEES OTHERS EMPLOYEES PERSON REM REACTOR OPERATIONS AND SURVEILLANCE ENGINEERING 48 6

0 4.220 1.111 0.000 HEALTH PHYSICS 45 24 57 16.547 6.019 1252 MAINTENANCE 10 26 1

4.443 6 824 0.047 OPERATIONS '

121 37 0

29.906 2.427 0.000 SUPERVISORY 74 43 0

5.217 2.037 0.000 298 135 58 491 60 333 18 418 1.300 80.051 ROUTINE MAINTENANCE ENGINEERING 91 247 0

7.898 45.701 0.000 HEALTH PHYSICS 39 76 165 14.511 19 435 3.599 MAINTENANCE 21 0 1487 4fs 96.759 396.442 2.246 OPERATIONS 30 7

0 7.422 0.437 0.000 SUPERVISORY 2M 206 0

14196 9.833 0.000 570 2022 214 2806 140.786 471.849 5.846 618 480 INSERVICE INSPECTION ENGINEERING 8-47 0

0.713 8.754 0.000 HEALTH PHYSICS 0

15 60 0.149 3.897 1.302 MAINTENANCE O

190 0

0 000 50.663 0.000 SUPERVISORY 7

1 0

0.471 0 043 0.000 15 253 60 328 1.333 63.357 1.302 65 991 SPECIAL MAINTENANCE ENGINEERING 0

0 0

0.000 0.021 0.000 i

f HEALTH PHYSICS 0

0 0

0.001 _

0.005 0.000 MAINTENANCE 2

57 10 0.863 15.224 0 458 i

OPERATIONS 0

0 0

0.016 0.000 0.000 SUPERVISORY 1

2 0

0 062 0 072 0 000 3

59 10 72 0942 15 322 0.458 16 722 REFUELING j

ENGINEERING 3

42 0

0.277 7.728 0.000 j

HEALTH PHYSICS 3

0 58 1.287 0.003 1.257 MAINTENANCE 2

34 0

1.085 9.129 0.000 OPERATIONS 9

0 0

2.337 0.000 0.000 SUPERVISORY 20 3

0 1.422 0.162 0 000 39 79 58 176 6 408 17.023 1.257 24.688 NGINEERING 2

0 0

0.137 0.042 0 000 HEALTH PHYSICS 1

0 1

0.378 0 070 0.01 8 MAINTENANCE O

19 0

0.077 4.946 0 000 OPERATIONS 3

97 0

0.734 6.273 0.000 SUPERVISORY 4

0 0

0 317 0 006 0 000 10 116 1

127 1.644 11 338 0 018 13 000 TOTAL BY JOB FUNCTION ENGINEERING 152 343 0

495 13.245 63.358 0 000 76.603 HEALTH PHYSICS 89 115 340 544 32.874 29.429 7.429 69 732 MAINTENANCE 224 1812 60 2096 103.227 483.229 2.752 589 208 OPERATING 164 141 0

305 40 414 9 138 0.000 49.552 SUPERVISORY 306 254 0

560 21.685 12.153 0 000 33 838 j

• • ""GR AND TOTAL"**"

935 2665 400 4000 211.445 597.307 10.181 818 933 l

84