ML20090A178

Annual Report Covering LaSalle County Nuclear Power Station for 1991

ML20090A178
Person / Time
Site:	LaSalle
Issue date:	12/31/1991
From:	Diederich G COMMONWEALTH EDISON CO.
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 9203020175
Download: ML20090A178 (74)

Text

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Commonwasith Edison

.* LaSalle County Nuclear Station 2601 N. 21st. Rd.

Marseilles, Ilhnois 61341 Telephone 815/3!,7 6761 February 24, 1992 Director of Nucleat Reactor Regulation U.S. Nuclear Regulatory Commission Mail Station PI-137 Nashington, D.C. 20555 Gentlernen:

Enclosed for your information is the annual report covering LaSalle County Nuclear Power Station for the period covering January, 1991 through December, 1991.

Very truly yours, .

,. N O

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G. J. Diederich t IStation Manager LaSalle County Station GJD/MJC/djf Enclosure cet A. B. Davis, NRC, Region III D. E. Hills, NRC Resident Inspector, LaSalle J. L. Roman, IL Dept. cf Nuclear Safety B. Siegel, NRR Project Manager D. P. Galle, CECO.

D. L. Farrar, CECO.

INPO Records Center D. R. Eggett, NED P. Doverspike, GE Resident T. J. Kovach, Manager of Nuclear Licensing W. F. Naughton, Nuclear Fuel Services Manager J. E. Lockwood, Regulatory Assurance Supv.

J. W. Gieseker, Technical Staff Supv.

M. M. Servoss, OA/NS Offsite Review Station File 9203020175 911231 PDR ADOCK 05000373 \/. 1 R

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l .' I. INTRODUCTION The LaSalle County Nuclear Power Station is a two-unit facility owned by-Commonwealth Edison Company and located near Marsellies, Illinois. Units 1-and 2 are Lolling water reactors with a designed net electrical output of 1078 megawatts. Wa:Le heat is rejected to a man-made cooling pond using the Illinois River for make-up and blowdown. The architect-engineer was Sargent and Lundy and the primary construction contractor was Commonwealth Edison Company.

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

Initial criticality was achieved on June 21, 1982 and comme rcial operation was commenced on January 1, 1984.

Unit ? was issued operating licanse number NPF. 8 on December 16, 1983. 4 Initial criticality was achieved on March 10, 1984 and commercial  ;

operation was commenced on June 19, 1984.

This report was compiled by Michael J. Cialkowski, telephone number (815)357-6761, extension 2427.

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• TABLE OF CONTENTS ,

I. INTRODUCTION II. ANNUAL REPORTABLE DOCUMENTATION FOR UNITS 1 AND 2 _

A. Summary of Operating Experience l B. ' Unit Outage or Power Reductiot.s C.' Radiation Exposure

-D. Indications of Failed f uel Elements E. . Tests and Experiments Not Covered in the Safety Analysis Report

. F,. Changes to Procedures Covered in the Safety Analysis Report G. Summary of Changes to the Facility Which Are Described in the Safety Analysis Report H. Swmnary of Safety Related Modifications 1

I. Summary of ECCS Outages J. Survey of Evaluation Results of Chlorine Shipments by Darge on the Illinois' River K. Summary of Events Violating Technical Specification 3.4.5 Primary Coolant Iodine Spiking Exceeding Allowable Limits a

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II. Annual Reportable . Documentation 'for Un' t I and 2 s .

A.' Eumar.y.,_D.L_QpAIALinge,IspeIlance The summary of the operating experience has been reported monthly in-LaSa11e's NRC Monthly Reports (Section II. A) dated January 1991-through December 1991. For safety related maintenance (non-outage related) performed during the period of January 1.991 thru December 1991, see Attachment A.

B. U n11__QRtAg e_ar_.favar__ReJinctioA s For unit outages, see Attachment B. For unit power reductions see

• Attachment C.

C, End1ALinn., Exposure This information is reported annually for 1991 in the respective sections relating to numbers compiled for LaSalle Unit I and 2 in  ;

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

D. Indications _gf_IAllgd fuel Elements 4

This section has been reported monthly in LaSa11e's NRC Monthly Reports-(Section II.F.5) dated January 1991 through December 1991. i E. .Tetts and Experiments not covgred in the Safety Analysis _Repati s

LaSalle Special Procedure 91-001 LaSalle Special P*ocedure LLP 91-001, " Condenser Tube Leak with Sulfur Hexafluoride", wac performed to determine which side of the condenser contained tube leakage.-This procsdure consisted of temporary installation of the Science Applications International Corporation Sulfur Hexaflouride injection and detection equipment to the Amertap and Off Gas pretreatment Process Radiation Monitor system. The margin of safety was not reduced since both the Circulating Water.and Process Radiation Monitoring systems are equipped with isolation boundaries to prohibit injection into the Circulating Water system or process air through the vendors detection equipment. The Sulfur Mexaflouride did not impact reactor chemistry or degrade any reactor components. This process is a standard industry practice.

LaSalle Special Test 91-003 LaSalle Special Test LST 91-003, " Unit 1 feedwater Check Valve 1B21-F032A Troubleshooting Procedure" provided a method for determining the failure mode of the 1B21-F032A opening circuit logic. The special test also attempted to fully open the valve per circuit alterations. The purpose of the change was to eliminate an undesired feedwater A/B branch flow mismatch of about 10% at full power when the valve is 15% closed. The valve opening circuitry was modified to energize the open solenoids in the reverse direction. Since these are AC solenoids this did not affect their overall function. Because one of the two close solenoids remained connected throughout the test, tae mechanical ability of the check valve to isolate was not affected and rechnical Specifications were maintained.

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LaSalle Special Test 91-054 LaSalle Special Test LST 91-054 "Special Measuros for Secondary ii Containment Leak Rate Test (SCLRT) On-Line" outlined methods / controls to bypass Main Stenm Line Tunnel (MST) High Ambient Temperature and High Ventilation System Differential Temperature trips while the Reactor Building Ventilation HVAC System (VR) was shutdown. The purpose of this change was to ensure compliance with Technical Specification 3.3.2.2. The bypass actions change the isolation of Group I from automatic to manual action (for small leaks only). The major effects of this were analyzed and reviewed in the justification for amendment 62 to Unit 2 Technical I Specification (LOSR 90-40, 90-41, License submittal for unendment 77 to Unit I license and snendment 62 to Unit 2 license). The special test bypasses the automatic trips only and does not affect temperat re indicators for the MST. Should unexpectedly high te' reratures vecur in the MST which could be indicative of a staam leak a manual isolation could be performed. However, a manual isolation does not bypass the valve motor thermal overload protective devices of the Main Steam Line (MSL) drain valves. Therfore in the event that a manual isolation is required the thermal overload protective devices on the MSL drain valves would not be lk bypassed. This was not specifically addressed in the License amendment submittal and is therefore the subject of this safety evaluation. The UFSAR will be updated to reflect this test mode. Since this procedure collected response indications, this will be evaluated and the evaluation results were sent to engineering to verify compliance with the pretest Environmental Qualification calculations for components in the MST.

The jumpers installed by this procedure did not change the facility as described in the UFSAR because the isolation bypassed is reviewed and approved. The Division 1 jumpers at P632 also bypasc the loss of power interlock to K3A and C. This interlock causes a trip but is not contained in the Technical Specifications or the UFSAR.

LaSalle Special Test 91-069 LaSalle Special Test LST 91-069 " Unit 1 250V Battery "DITE" Test" approved the measurement of individual cell impedance by passing a 1 amp 25 Hz AC signal through the battery. This change allowed battery capacity to be quantitatively evaluated based on cell impedance. This procedure attached an AC signal source to a safety related battery. This is not addressed in the UFSAR. Unit I was shut down during this test. The 250V battery is not required to mitigate the consequences of any accident in the shutdown mode. The failure analysis of this battery bounds this test. The 250V DC system is not required to be operable by Technical Specifications with the Unit in shutdown, therefore this change did not reduce the safety margin.

LaSalle Special Test 91-089 LaSalle Test Procedure, LST-91-089, Unit-1 High Pr essure Core Spray Water Leg Pump Performance Test, allowed 1E22-F033, the Water Leg Pump Recirc Stop Valve to be throttled from a closed position to a partially open position to increase pressure and thereby prevent water hammer to the system during the performance of this test. Based on a safety evaluation, that was performed as required by 10CFR50.59, it was concluded that this Test Procedure had an insignificant affect on the plant.

E. Tests _andlxperiments_not_ coveted.in_the.Satoty_ Analysis Jeport (continued)

LaSalle Special Test 91-121 LaSalle Procedure LST 91-121 "Startup, Testing, and Shutdown of Unit 1 Turbine Building Ventilation System (VT) Evaporative Coolet Bank A" provided guidelines for the startup, testing and shutdown of the Unit 1 Turbine Building Evaporative Cooler (lVT03AA) to evaluate the feasability of operating this system during warm weather. The UFSAR Section 9.4.4.2 indicates that the evaporative coolers are supplied with domestic water, since clean Condensate System (MC) will be used, the UFSAR is affected.

This is not a technical specification change. The evaporative coolers have no impact on plant safety. The use of MC in place of domestic water for operating the evaporative coolers does not affeet the saf ety of t.he plant. The likelyhood for an accident affecting plant safety was not increased.

LaSall: Special Test 91-123 and Temporary Syste.n Change 1-1286-91 LaSalle Special Test LST 91-123 " Chemical Cleaning of IVYO3A Southeast Area Cooler" isolated IVYO3A from Core Standby Cooling System CSCS) for chemical cleaning. The purpose of this change was to achieve a higher flow. ate through the cooler, which will restore the heat exchanger to the normal level of efficiency. This caused theD' and 'C' Residual Heat Removal (RHR) area cooler to be inoperable as described in the UFSAR for plant operation. There was no change to the Technical Specifications (TS). Worst case is total loss of Division 2 Emergency Core Cooling System (ECCS) function, which is already bounded by the UFSAR by single failure criterion. TS allow ECCS to be inoperable for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, thus the margin of safety was within TS limiting condition for operation. During the chemical cleaning process Divisions 1 and 3 were operable and available to mitigate the consequences of all UFSAR evaluated accidents. In conjunction with this special test, Temporary System Change 1-1286-91 installed a blank flange in Service Water Supply Line 1DC' % 4" downstream of IDG008 and upstream of IDG007 so that lA Diesel Generator (DG) Cooling Water Pump could be returned to service while the cooler was inoperable due to cleaning.

Lasalle Special iest 91-141 LaSalle Specia? Test LST 91-141 " Chemical Cleaning of Core Standby Cooling System (VY) Northear,t (NE) and Northwest (NW) Area Coolers" approved taking the Engineered Safety Feature (ESF) Division 1 'O' Diesel

' Generator (DG) Cooling Water Pumps Out Of Service (OOS) to isolate Unit 1/2 VY NE and NW coolers for chemical cleaning. This was accomplished by cleaning each unit separately within a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> timeclock and returning 'O' DG Cooling Water Pwnp to service with adjusted flow to 'O' DG cooler of 1,000 GPM plus or minus 25. The purpose of this change was to achieve higher flow rates through the coolers. ESF Division 1 was inoperable during the cleaning process on the unit being cleaned, Divisions 2 and 3 were operable during the process and mitigate all UFSAR evaluated accidents. The worst case condition is a total loss of ESF Division 1 Emergency Core Cooling System (ECCS) functions. This case is bounded in the UFSAR analysis by single failure criterion. Technical Specifications allows ECCS Division 1 to be inoperable for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, thus the margin of safety is within technical specification limiting condition for operation.

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r. Ch ang es_to_froceslu r e s_Cov e r e d_in the_l e tely_A n a l ys i a lero tt On-Site Review 91-014 LPSalle On-Site Review OSR 91-014 "Helocation of the Radioactive Effluent Technical Specifications (TS) to the Off-Site Doce Calculation Manual (ODCM)" rpproved the relocation of the Radioactive Effluent TS to the ODCM. This amendment involves changes to the TS controls for licensee initiated revisions to the ODCM. The UFSAR in Appendix 1 indicates that the programmatic controls and requirements for control of radioactive effluents are included in the TS's. This amendment along wit h the change submitted in On-Site Review 89-038 will relocate the procedural details of the Radioactive Effluent Technical Specifications (RETS) to the ODCM and Process Control Program (PCP). These changes will not affect the initial a s s umpt ions for, or increase the probability of the occurrence of the initiators for, any previously analyzed events. Nor does this change affect the radiation dose previously calculated for any event either on site or off site at the site boundaries. These amendments are administrative in nature and do not alter 'l= evel of control for plant radiological effluents. The necessary cont. , for radiological effluents, will be provided in the ODCM and PCP.

Emergency Operating Procedure Format Guidelines To make procedures easier to manage, the format used to write Abnormal Operating Procedures has been revised. This resulted in changes to the UFSAR. Changes to the UFSAR included deleting a description of the procedure f o rr..at and a list of typical Abnormal Operating Procedures.

Reference to the BWR Owners Group quide'ines and ariters flowchart .

guideline was added to provide direction to individuals writing nr.

Abnormal Operating Procedure. By changing the guidelines for the preparation of Abnormal Operating Procedures, these procedures will be easier to manage.

Procedure LFS-100-1 LaSalle Fue1 handlers Survel? lance LFS-100-1 " Refuel Platform Main Holst Interlock Check for Core Alterations" Revision 5 corrects typographical errors, revises a note, adds a note on performing surveillances with the Reactor Mode Switch in SHUTDOWN and adds a reference. UFSAR Section 7.7.13.2.2 requires interlocks only with Mode Switch in REFUEL position. However, 7.7.13.2.4 states that (loaded) bridge travel over the core is stopped any time rods are withdrawn, disabling the Core Limit Switches defeats this. This condition was evaluated ( LOSR 87-2 6 ) . Inadvertant criticality is avoided by constant rod block in shutdown and administrative controls. Technical Specifications contain previsions for core alterations with the Mode Switch in SHUTDOWN. The limit switches defeated to do this are required only with the Mode switch in REFUEL.

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F. Changenta_Pfacedures_coyatedds_thq_fic&nly.Analysia_ Resort

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Procedure LOA-l'2)H13-P603

( A403 1

-Procedure LaSalle Abnormal Procedure LOA-1(2) H13-P603 A403'has been .

-revised-and LaSalle Special procedure LLP-91-058.was written. In the LOA procedure, operator-actions have been added to direct that once all possible corrective actions have been identified and' initiated, the individual alarms may be patched-out.- For. Unit I this will be done by having the Instrument Maintenance Department reprogram the individual Control Rod Drive (CRD) channel on the new IC11-R018 recorder so that the alarm output relay is deactivated. This will-deactivate the alarm for this CRD but will allow trending to continue. For these Unit 2 CRDs, th 4. s will be.done under LLP-91-058, "Bjpassing CRD Thermocouples at 2C11-R018 Recorder". The procedure directs the Instrument Maintenance Department to lift the leads from the CRD thermocouple at the recorder, anu to install a jumper across the recorder terminals so that this CRD point will actually be reading room te 'erature. All bypass CRD temperature points will be monitored weekly I the Technical Staff Engineer and any CRDs that are no longer." hot" will be reactivated. When the new recorder is installed on Unit 2, the LLP will be closed.

Procedure LOA 1(2)PM10J A103 LaSalle Abnormal Operations Procedure LOA 1(2)PM10J A103 " Reactor Building Closed Cooling Water (RBCCW) Expansion Tank Level High-Low" provides for action when the automatic level control valve falls to operate normally. The purpose of this procedure change is to provide for proper tracking of the condition and provide proper control of off-normal

' valve poritions. Section 9.2.3.5 of the UTSAR states the RbutW Expansion Tank level is controlled automatically, manual operation is not discussed. The RBCCW System does not have a safety design basis, and

-proper level control will be monitored via the Control Room Annunciators.

The RBCCW System is not addressed in the Technical Specifications.

Procedures LOA-RH-06, LOA-RI-04, LOA-RI-05 l' LOA-VP-02, LOP-CM-02 and LOP-RT-14 LaSalle General Abnormal Operating (LGA) -support procedures which were developed as revisi a O's were initiated to provide instructions for

111ning up miscellaneous plant systems to facilitate actions necessary to-l_ . support operation under the scope of Emergency Operating Procedures.

l Revisions to existing support procedures were made to. resolve-various procedural deficiencies identified during proceduro walkdowns.

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F. Changes l o_Prortdnea Covered lJLthel Die _ty_Analysla leS M1 (continued)

Procedure LOA-VX-01 Throughout the year, it-is not unusual for the outside air damper actuators to fall on the switchgear heat removal system. When an outside air damper actuator falls, the damper is moved to its f all-saf e position of fully opened. If a failure occurs during periods of cold weather, large amounts of cold air will enter the room. As a result, and if counter measures are not taken, the temperature of the switchgear room and the battery cell electrolyte would fall below the allowable Technical Specification limits for operation. Technical Specification 3.7.7 states that the switchgear room temperature will be maintained between 50 and 104 degrees Fahrenheit and Technical Specification 4.8.2.3.2 states that battery electrolyte temperature be maintained above 60 degrees Fahrenheit.

The newly developed LaSalle Operational Abnormal procedure LOA-VX-01, "Switchgear Heat Removal Damper Failure", allows the use of a permanent procedure to replace the need to create a temporary proceduto each time the threat of cold outside temperatures appears. This procedure outlines ,

steps to manually operate the dampers, and if necessary, temporarily wire closed the outside air dampers until outside air is needed or repairs to the actuator can be completed. In the cases where the damper is temporarily wired closed, the intent of the UFSAR, to be able to automatically adjust the dampers, is no longer porsible. The UFSAR states, "Each heat removal system is designed to admit 100% outside air, but outside- air dampers- and return air dampers are modulated to maintain temperatures within limits," section 9.4.5.2.2.d. With the dampers temporarily wired closed, outside air would not be able to < .ar the rooms and the omnper would not be able to modulate automatically to control temperature.

The purpose of LOA-VX-01, "S*itchgear Heat Removal Denper Failure" is to provide guidance to prevent the switchgear room temperature from decreasing below Technical Specification limits when the switchgear heat removal dampers f all . In the event of switchgear room temperature decreasing below 65 degrees Fahrenheit, the procedure directs the Operating Department to monitor room temperature.

The possibility of an occurrence or the consequence of an ac cident, or malfunction of equipment important to safety as previously evaluated in the Safety Analysis Report is not increased. The switchgear end battery room temperatures are monitored and if they begin to approach Technical Specification Limits, the drapers will be adjusted manually to compensate. Also, the battery room is vented to the much lorger volume of I the-switchgear room to prevent the build-up of hydrogen in the battery room, A small amount of air flows out of the switchgeer room and into the

turbine building also preventing any build up of hydrogen in the switchgear room.

The possibility for an accident or malfunction of a different type than any previously evaluated in the Safety Analysis Report is not created. The monitoring and adjustment to the switchgear room temperature j will be done manually and the dilution of hydrogen in the switchgear room creates no new unanalyzed situations.

The margin of safety, as. defined in the basis for any Technical Specification, is not reduced. The room temperature will be monitored during each shift to verify that the room is within Technical Specification limits for temperbture and will be adjusted accordingly if necessary. The large switchgear room air volume and the venting of air out of the battery room will prevent the buildup of hydrogen in those i

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i Procedure LOP-HP-01, LOP-HP-02, LOP-HP-03, LOP-HP-04 and LOA 1(2)H1.3-P601 A205 LaSalle High Pressure Core Spray (HPCS) Operating Procedures were revised to reflect actual plant conditions: LOP-IIP-01 " Pilling and Venting 3- The High Pressure Core Spray' System";.' LOP-ilP-02 " Draining the liigh Pressure Core S,nray System"; LOP-HP-03 " Preparation for Standby Operation of High Pressure Core Spray System"J' LOP-HP-04 " Shutdown for High Pressure Core Spray System Afer An Automatic Initiation"; and LOA 1(2)li13-P601 A205 "lligh Pressure Core Spray System Actuation". These procedures have been revised to reflect the permanont alignment of the HPCS System to the Suppreasion Pool (SP), and to reflect the permanent isolation of connections between the HPCS System and the Cycled Condensate (CY) System. The Cycled Condensate System has no safety design basis and eliminating the capability for the HPCS System to access the water volume in the Cycled Condensate Storage Tank (CST) has no' impact on the plant

. accident analysis. Isolation of tbe CST as a water source for the llPCS System will not significantly reduce the calculated margins of safety since the CST is not considered in the safety analysis for the design basis accident or transient.

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G. S umm a ry_nLChange rdo_the_.fmility_Mhish_a r e_De ac1.ibeLin_the-Safe _ty_Analym1LReport LaSalle Special Procedure 91-061 LaSalle Special Procedure LLP 91-061 "Depressurising Across Unit 1

-Instrument Nitrogen (IN) 1000 Supply Header" provided direction for isolation of IN to Main Steam Isolation Valves (MSIV). The purpose was to provide guidance for performing MSIV maintenance during Hot Shutdown. The probability of the occurance of an accident was not affected. This procedure did not perform any action that could cause a loss of the pressure boundary. Consequences of an accident are bounded by accidents from power operation. The procedure did not affect any equipment operating modes. Unit was in shutdown, therefore, margin to protective functions were conservative. System availability was maintained within Technical Specification requirements.

LaSalle On Site Review 90-011 LaSalle Onsite Review LOSR 90-011, Unit 1, Division 2, 125V Battery ,

Replacement, was performed to provide support for a temporary battery supply arrangement that was required to replace the Unit 1 Divison 2, 125V DC batteries. Based on a safety evaluation, that was performed as required by 10CFR50.59, the NRC concluded that even though the duration of this temporary arrangement exceeded Limiting Conditions for Operation, that an adequate basis for this duration was provided and that the proposed temporary battery supply arrangement for division 2 was acceptable, LaSalle On Site Review 91-006 LaSalle Onsite Review LOSR 91-006 " Unit 1 Cycle 5 Reload and Core Operating Limits Report" was approved to ensure Unit 1 operates within the design basis by complying with the results of the reload licensing submittal and other analyses performed by GE which will affect future unit operations. The probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the UFSAR is not increased nor is the probability for an

,- accident or malfunction of a different type than any evaluated previously in the UFSAR created and the margin of safety is not reduced as i demonstrated in analyses using NRC approved methods. The NRC has previously approved GE9B fuel for use as a reload fuel type. Limiting l

postulated occurences have been analyzed for LlCS to ensure that safety

{ limits are bounded and that acceptable fuel performance is maintained.

The reload fuel in no way affects the performance of any safety relateds equipment. Analysis also demonstrated that fuel design and licensing criteria will be met during normal and abnormal operating conditions.

L Since operation during LICS is bounded by the limits established in the L reload analyses and associeted generic analyses performed by GE and specified in the LICS COLR. '

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G. S ummary_oLChange s_to_thalacility_.Mhish_arLDescribed__lothe Safety _ Analysis _ Report (continued)

Work Request LO4753 LaSalle Work Request LO4753 to repair Control Room Door'609 included the temporary removal of the door. This door is an elt' ment of the Control-Room envelope as defined in the UFSAR 6.4.2.4. The "B" VC Emergency Make-Up Filter Train remained operable during the removal of door 609 by closing doors 296 and 298 as demonstrated by testing. Continuous monitoring of doors 296 and 298 during the repair ensured the probability of failure of the "B" VC Emergency Make-Up Filter Train to meet the Control Room pressurisation requirement did not increase. Therefore, the consequences of a design basis accident was mitigated by the operation of the "B" VC Emergency Make-Up Trains. The only parameter important to reactor safety that was affected by the temporary removal of door 609 was control room pressure. This has already been evaluated in the UFSAR. The ,

basis for the applicable Technical Specification 3.7.2 is to limit radiation exposure to Control Room personnel during a design basis accident. This margin of safety was ensured by the operation of the "B" VC Tilter Train.

Out Of Service 1-D701-90 LaSalle Out of Service OOS " Valve 1E51-T064 Out Of Sevice Closed During Operational Conditions 1, 2 and 3", approves IE51-F064 being left OOS Closed during conditions 1,2 and 3 following LaSalle Unit 1 Fourth Refuel (L1R04). The valve motor is undersized and therefore the valve cannot meet design basis opening / closing requirements. The valve will be closed to meet isolation condition requirements of the Technical Specifications. This is a change to the UFSAR as the valve is normally in service-during conditions 1,2 and 3 but closed. The valve is used (cycled ,

open) to initiate the steam condensing mode of operation which is not required by the Emergency Operating procedures. The valve is normally closed during plant operation and would only be used (cycled open) after a

. shutdown if the steam condensing mode were to be used.

Out Of Service 0-244-91 and Out Of Service 0-246-91 LaSalle Out Of Service's DOS 0-244-91 "O Diesel Generator Air Compressor ODG08CA" and OOS 0-246-91 "O Diesel Generator Air Compressor ODG08CB" approved opening the air crosstle between subsystems, (ODG032).

This eliminated the two separate subystems as described in Section 9.5.6.1

-of the Safety Evaluat an Report (SER). This change also deviated from the definition of 2 subsystems as described in the USAR Section 9.546.1.- The purpose of this_ change was to take the 0 DG 'A' air compressor (ODGOBCA) and 'B' Air Compressor (ODGOBCB), respectively, OOS for planned maintenance. The air pressure remained above 200 psig per Technical Specification (TS) 4.8.1.1.2.a.7. This allowed the DG to be considered operable. The probability that an accident would occur was nut affected as UTSAR section 9.5.6.3 assumes the failure of the Diesel Generator when both subsystems fall. Consistent with the basis of TS 3/4.8.1 and 3/4.8.2, in that, no degradetion to the receiver supply for the DG was made, the margin of safety was not reduced.

G. Summary _oLQ1ang es__tolheJ acility.Jhic1Latelc antib eLin_the

. Safety _Analyslaleport (continued) l Out Of Service 0-2020-91 LaSalle Out Of. Service (OOS) "A and B Auxiliary Electric Equipment Room Ventilation (VE) Cooler Condenser Fan" approved removing the'A and B VE Cooler Condenser Fans from service to perform breaker inspections. The ,

purpose of this DOS was to perform breaker inspections for the Electrical-Distribution System Functional Inspection (EDSFI). Section 9.4 of the UFSAR states that the Control Room HVAC System (VC) Emergency.Make-Up (EMU) train must monitor the habitability of the Control Room and Auxiliary Electric Equipment Room (AEER)s le. a positive pressure.and low dose. Removing the VE Cooler Condenser Fan from service wtald not affect either of these parameters, and it would not affect the operation of VE EMU train. Section 7.3.4.2.a and 0.4.1.2 state that the AEER refrigeration unit is required to maintain AEER temperatures less than 80 degrees F. Even with these fans DOS low temperature outside air (less than 30 degrees F) was avn11able to maintain AEER temperatures less than 80 degrees F. VC EMU train opera

• ion as required by Technical Specifications Section 3.7.2 was not affected and AEER temperatures as required by section 3.7.7 were maintained between 50 and 104 degrees F during the DOS so that the margin of safety was not reduced.

Out Of Service 0-2055-91 LaSalle Out Of Service OOS 0-2055-91 "O Diesel Generator (DG) Air Compresser ODGOBCB" approved opening the air cross tie between subsystems, (ODG032,'. This did not provide the 2 separate subsystems as descr~ bed in the Safety Evaluation Report (SER) in section 9.5.6. This change also j deviated from the definition of 2 subsystems as described in the UFSAP section 9.5.6.1. The purpose of this change was to take the O DG 'A' air compressor (ODG08CA)OOS for maintenance on the discharge check valve. The air pressure remained above 200 psig per Technical Specification 4.8.1.1.2.a.7 for the DG to be considered operable. The UFSAR section 9.5.6.3 assumes the failure of the DG when both. subsystems fall, therefore the probability that an accident will occur was not affected. Consistent with the basis of Technical Specification 3/4.8.1 and 3/4.8.2, in that, no degradation to the receiver supply for the DG was made, the margin of safety was not reduced.

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G. Summe rE.0 LQiang e n_ to__the_f ac il1Ly_.Mh irtL ate _ Ile s c r ib c Li ttihe Saf e ty_ Analysis _ Report (continued)

I Out Of Service 1-28-91 LaSalle Out Of Service (00S) " Opening of the 1E32-r008 Valve in Operational Condition 1 (Run) and Leaving The Valve Out Of Service Open" approved opening the Main Steam Isolation Valves Leakage Control System (MSIV-LCV) valve (1E32-F008) and placing the valve DOS while the unit was in the run mode. The purpose of this change was to allow backseating of the valve to prevent steNu leakage from the packing. The purpose of this valve is to blowdown stemn to lower Main Steam Line pressure o aring outboard MSIV-LCV operation. This valve is in series with anot her valve with the same function (3E32-F009) which will remain operable '.o per form the design function. In the event that the second valve (1E3.-F009) were to fall, the steam would blowdown into the steam tunnel . The steam tunnel is controlled access only, which provides for personnel safety. The Leak Detection System is designed to detect significant leaks in the steam tunnel providing automatic mitigation by isolating the MSIV's. There is no impact on the Technical Specifications as the cystem will be able to function as designed. This change will not affect any accident analysis of the UFSAR.

Out Of Service 1-135-91 LaSalle out of service DOS 1-135-91 " Unit 1 Division I 12bv Battery Room Exhaust ran DOS" approved the Division I 125 V battery room exhaust fan (1VX02C) being shut down and taken out of service to allow the IVX02C fan breaker to be inspected. Battery room ventilation is specified in Section 8.3.2.1 of the UFSAR as being required to purge the battery room of hydrogen liberated from the batteries to prevent an explosive mixture, limit room temperature to 65-104 r, and maintain battery room at normal plant pressure. Battery ventilation is also indirectly Technical Specification related through battery electro:yte temperature requirements. With the fan shut down these are affected. The battery room door remained open during the period the fan was DOS. This allowed the pressures in the Division 1 Switchgear and 125 VDC Battery Room to equalize and allowed the switchgear ventilation system to maintain proper battery room temperature. A special log was initiated to monitor battery room hydrogen concentration to ensure an explosive mixture was prevented-from occuring. The battery was not equalized charged during the time when the fan was OOS so hydrogen production was minimited. In addition, a portable fan was situated in front of the open battery room door to exhaust air from the battery room to the Division 1 Switchgear Room. The battery was considered fully opetable during this change. Also an hourly fire watch was in effect while the battery room fire door was propped open.

. . . _ . _ _ ___._. _._._________.~__.__m..___.-.__._

4 G. S wnma rLoLCh angattoahe_In cilityJhi ch_arn_De actib e d_.inJ.he SMaty_Analys.is RepnLt -

(continued)

Out Of Service 1-463-91 LaSalle Out Of Service.OOS 1-463-91 " Isolate The Unit-1 VY System I While Unit 2 Room Coolers And The Unit 2 Low Pressure Core Spray (LPCS)

Motor Cooler Remains Operable" epproved as the title describes the isolatloa of the Unit 1 VY System to perform Maintenance. The safety

- evaluation states that adejuate pump flow would exist through Unit 2 LpCS room cooler, Unit 2 RHR A room cooler, and 0 Diesel Generator (D/G) cooling water pump. This ensured that the O D/G cooling water pump would be able to perform it's intended function during an accident and therefore does not change existing accident analyses. All actions were controlled by the Technical Specifications and therefore all Technical Specification margins of safety remain unchanged.

Out Of Service 1-1070-91 LaSalle Out Of Service DOS 1-1070-91 " Unit 1 'B' Diesel Generator-(DG) Air Compressor 1E22-C302B" approved the opening of the air cross tie '

between subsystems (1E22-F368). This did not provide the two separate subsystems described in section 9.5.6 of the Safety Evaluation Report (SER). This change also deviated from the definition of 2 subsystems as described in the UFSAR 9.5.6.1. The purpose of this change was to take the Unit 1 B Diesel Generator Air Compressor B (1E22-C302B) OOS for preventative maintenance. The air compressor remained above 200 psig as

, required per Technical Specifications (TS) 4.8.1.1.2.a.7 for the DG to be considered operable. The probability that an accident would occur was not affected as UFSAR Section 9.5.6.3 assumes the failure of the DG when both subsystems fall. Consistent with the basis of TS 3/4.8.1 and 3/4.6.2, in that, no degradation to the receiver supply for the DG was made the margin of-safety was not reduced.

Out Of Service 1-1297-91 LaSalle Out Of Service DOS 1-1297-91 " Unit 1 'A' Diesel Generator (DG) Air Compressor 1DG08CA" approved the opening of the air cross tie between subsystems, (IDG058). This did-not provide the 2 separate subsystems as described in the Safety Evaluation Report (SER) Section 9.5.6. This change also deviated from the definition of 2 subsystems as l

described in the UFSAR Section 9.5.6.1. The purpose of this change was to take the Unit 1 'A' DG.Alr Compressor A (IDCOBCA) OOS for planned maintenance. The air pressure remained above 200 psig per Technical Specification (TS) 4 . 8.1.1. 2. a . 7 for the diesel to be considered operable. The UFSAR section 9.5.6.3 assumes the f ailure of the DG when j- both subsystems fail, therefore the probability that an accident would

~

occur was not affected. Consistent with the basis.of TS 3/4.8.1 and 3/4.8.2, in that, no degradation to the receiver supply for the DG was made, the margin of safety was not reduced.

l l

l L

\, . - . -. __ - .- .-- . . - .- . -

G. Sa' mary o LCh ange a._L9_thelacili tyJihi c1Lat e. De a c Libe d._in_the SaInty_Analys.iruEmport (continued) out Of Service 1-1339-91

~

LaSalle Out Of Servlce 005 1-1339-91 " Unit 1 'B' Diesel Generator (DG) Air Compressor IE22-C302A" approved the opening of the air crosstle between subsystems, (IE22-F368). This eliminated two separate subsy*tems as described in section 9.5.6 of the Safety Evaluation Report (SER). This change also deviated from the definition of 2 subsystems as described in the UFSAR Section 9.5.6.1. The purpose of this change was to take the Unit 1 'B' Diesel Generator Air Compressor A (1E22-C302A) OOS for required maintenance. The air compressor remained above 200 psig as required per Technical Specification (TS) 4.8.1.1.2.a.7 for the DG to be considered operable. The probability that an accident would occur was not affected as UFSAR section 9.5.6.3 assumes the failure of the DG when both i

subsystems fall. Consistent with the basis of TS 3/4.8.1 and 3/4.8.2, in that, no degradation to the receiver supply for the DG was made the margin of safety was not reduced.

Out Of Service 1-1379-91 LaSalle Out Of Service DOS 1-1379-91 " Unit 1 Division 2 125V Battery l

Exhaust Fan" approved the shutdown and OOS of the Unit 1 Division 2 125V t Battery Exhaust Fan (IVX0SC). The purpose of this change was to allow the IVXOSC f an fire damper to be inspected. Battery room ventilation is specified in UFSAR section 8.3.2.1 as being required to purge the Battery i Room of hydrogen liberated from the batteries to prevent an explosive mixture, limit room temperature to 65-104 degrees F, and maintain the

• Battery Room at normal plant pressure. With the fan shutdown and OOS, the previous UFSAR section is affected. Battery Room ventilation itself is not Technical Specification (TS) related, however, it is tied to the TS indirectly through battery electrolyte temperature requirements. The Battery Room Door remained opened during the period the fan was OCS. This ,

allowed the-pressures in the Division 2 Switchgear and 125VDC Battery Room to equalize and allowed the Switchgear Ventilation System to maintain proper Battery Room temperatures. 11ydrogen concentration was not a concern unless the fan was shutdown longer than 2 shifts.

The battery was not equalized charged during this time when the fan was OOS so hydrogen production was minimized. In addition, a portable fan was situated in front of the open Battery room Door to exhaust air to the Division I Switchgear Room. The battery was considered fully operable during this change. If the fan was to be shutdown longer than the expected 2 eight-hour shifts hydrogen concentration in the Battery Room would have been monitored shiftly to ensure an explosive hydrogen mixture was prevented f rom- accumulating. An hourly fire watch was in effect while the Battery Room Fire Door was propped open, as required by the TS,

.he: s fore , the margin of safety was not reduced.

1

!~

, ,- .m . ~ _ _ = ,,_,

G. S wwn ary._o LCh anec a_t o_thcla cil.ityJhich_a reJe s cribeLinJ.he Safety _Analy11s l epor.t (continued)

Out Of Service 1-1390-91 LaSalle Out Of Service 005 1-1390-91 " Unit 1 'B' Diesel Generator (DG) Air Compressor IE22-C302A" approved the opening of the air crosstle between-subsystems, (1E22-F368). This eliminated two separate subsytems as described in section 9.5.6.1 of the Safety Evaluation Report (SER).

This change also deviated from the definition of 2 subsystems as described 4

in the UFSAR Section 9.5.6.1. The purpose of this change was to take the Unit 1 'B' Diessel Generator Air Compressor A (1E22-C302A) OOS for required maintenance. The air compressor remained above 200 psig as required per Technical Specification (TS) 4.8.1.1.2.a.7 for the DG to be considered operable. The probability that an accident would occur was not af fected as UFSAR section 9.5.6.3 assumes the f ailure of the Diesel Generator when both subsystems fail. Consistent with the basis of TS 3/4.8.1 and 3/4.8.2, in that, no degradation to the receiver supply for i

the DG was made the margin of safety was not reduced.

Out Of Service 1-1604-91 i

LaSalle Out Of Service 005 1-1604-91 " Unit 1 'B' Diesel Generator (DG) Air Compressor 1E22-C302A" approved opening the air cross tie between subsystems, (1E22-F368). This did not provide the 2 separate subsystems as described in the Safety Evaluation Report (SER) in section 9.5.6. This change also deviated from the definition of 2 subsystems as described in the UFSAR Section 9.5.6.1. The purpose of this change was to take the

Unit 1 B DG 'A' air compressor (IE22-C302A) DOS to repair / replace the discharge relief valve. The air pressure remained above 200 psig per Technical Specification (TS) 4.8.1.1.2.a.7 so that the DG was considered operable. The probability that an accident would occur was not affected as UFSAR section 9,5.6.3 assumes the failure of the DG when both subsystems fail. Consistent with the basis of TS 3/4.8.1 and 3/4.8.2, in that, no degradation to the receiver supply for the DG was made, the margin of safety was not reduced.

Out Of Service 2-174-90 LaSalle Out Of Service DOS 2-174-90 " Isolation of the 2C Residual Heat Removal (RHR) Pun.p Seal Cooler" approves the isolation of the cooling water supply to the Unit 2 RHR Pump Seal Cooler. The purpose of this change in to isolate the pump Seal Cooler since the Cooler has a cracked baseplate. This change requires clarification to the UFSAR 9.2.1.1.1. The C RHR pumps do not require seal cooling because the process fluid which it purps is not expected to exceed 176 degrees F during a LOCA requiring LPCI actuation, thus this change does not affect the operation of the system.

G. Samary_oLfhangentolhe_lacility_Nhic1L a t e_ Des cI.ibe d_in_th e

. SeCely_Analytisleimit (continued)

Out Of Service 2-186-91 LaSalle Out Of Service DOS 2 186-91 " Unit 2 ' A' Diesel Gener ator (DG)

Air Compressor 2DG05CB" appoved tke opening of the air cross tie between

-subsystems (IDG058). This eliminated the twoLseperate subsytems as described in section 9.5.6 of the Safety Evaluation Report (SER). This also deviated from the definition of 2 subsystems as described in the UFSAR Section 9.5.6.1. The purpose of this change was to take the Unit 2 A DG Air Compressor B (2DG08CB) 005 for- planned maintenance. The air pressure remained above 200 psig per Technical Specification (TS) 4.8.1.1.2.a.7 so that the DG was considered operable. Section 9.5.6.3 of the UFSAR assumes the failure of the DG when both subystems fall. The probability that an accident would occur was not affected. Consistent with the basis of TS 3/4.8.1 and 3/4.8.2 in that no degradation to the receiver supply for the DG was made, therefore, the margin of safety was not reduced.

Temporary System Change 1-43-91 LaSalle Temporary System Change TSC 1-43-91 " Defeating Radioactive Waste (RW) Control Room Alarms" appoves the defeating cf alarms resulting from various-RW tank level instruments to remove nuisance alarms. The level indication for these tanks is unreliable, resulting in sporadic alarms. The indicators and recorders will remain operable. Radweste levol instrnmante are not importent to safety as defined in the UFSAR, except to

-the extent that off-site releases are tept te within 10 CFR limits. This change will not affect off-site releases. Tank overflows are discussed in the b7SAR: and there are hard piping overflows to contain them.

Radioactive level alarms are not the basis of any margins of safety from the Technical Specifications.

l l Temporary System Change 1-211-91 l

LaSalle Temporary System Change TSC 1-211-91 " Remove Off Gas (OG)

Filter Building Dam" was approved to eliminate the personnel safety concern of a potential tripping hazard during LaSalle Unit 1 fourth refuel

, outage (L1R04) activities. Pump requirements f rom UFSAR 2.4.2. 3/ Questions 371.14-16 requires existing temporary curb / dam due to Facility Improvemont Program (FIP). The only. potential consequences from this change is 1 flooding. Flooding will not initiate an accident. Flood damage, as calculated by Engineering, would not occur for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. Monitoring and-

~

administrative controls would have re-installed the dam if flooding became possible. The margin of safety was not reduced.

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.. G.1 Sw; nary _oLChanges_to_the_IAcilityJihich_are Described _la_the

1. ' '- Salaty_Analysls_Repott -

, (continued)

Temporary System Change 1-469-91 and Temporary System Change 1-476-91 LaSalle Temporary System Changes TSC 1-469-91 and 1-476-91 " Unit 1 Fuel Pool Cooling System (FC) and Reactor Dullding Ventilation HVAC System (VR) Process Radiation Monitors (PRM)" approved jumpering around the VR and FC ventilation PRM's". The purpose of this change was to bypass isolation trip signals during calibration and testing of the VR and FC Ventilation PRM's. Per the UFSAR section 7.6.1.2 and 3, the PRM's provide protection against the consequences of Rod Drop and Fuel Handling

-accidents. Per Technical Specification 3.3.2, no core alterations, operations with a potential to drain the reactor, og movement of irradiated fuel was allowed while this TSC was in effect. Unit 2 monitors remained oper able and capable of initiating Stand By Gas Treatment (SBGT)

, and Group IV isolations. The action statement of Technical Specification '

3.3.2 was adherred to, and the jumpers were removed prior to fuel load so the safety margin was not reduced.

Temporary System Change 1-480-91 LaSalle Temporary System Change TSC 1-480-91 " Repair of the Unit 1

'A' Residual _ Heat Removal (RHR) Heat Exchanger Baffle Plate" approves two pieces of bar stock being welded to the top of the heat exchanger baffle plate, and.Furmanite being injected between these pieces. This  ;

repair is being made_to improve the heat exchanger performance by elimination of baffle bypass flow.- The steam condensing mode of RHR is affected by this change, and will not be used with this TSC in place. It does not affect the seismic qualification of the RHR Heat Exchanger ,

discussed in UFSAR.3.9.2.2.2.11, and is being added to restore adequate operation of the heat exchanger. The added material is compatible with the heat exchanger internals. This repair does not change any of the saf ety design bases of the RHR system ao specified in UFSAR 5.4.7.1.

I_ Failure of a s'ngle RHR Heat Exchanger is bounded by the Loss of Shutdown

( Cooling accident analysis of UFSAR 15.2.9. The Operational characteristics of the RHR system are not changing from the system design parameters, thus no Technical Specifications are affected by this repair.

Temporary System Change 1-535-91 LaSalle Temporary System Change TSC 1-535-91 "To Defeat 'A' Residual i

Heat Removal (RHR) Pump Trip From Suction Valve- Closed Signal" approved the lifting of lead AA-64 In panel 1H13-P629 to defeat the " suction valves closed" trip. "A" RHR pump (1E12-F004 A closed and any of IE12-F006A, 8.or 9 closed). The purpose.of this change was to_ allow running the "A" RHR pmnp for surveillances'with a malfunction associated with the IE12-F004A valve that causes the RHR pump to trip even though the valve is open. 'This interlock is not Technical Specification related. However, the pump trip interlock associated with the "A" RHR pump suction valves la discussed in the UFSAR Section 7.4.3.2.3 and defeating this trip is a change to the facility as described in the UFSAR.

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

G. Swant,y_cLChanget.lo_the_.Eac.1111y_Whictuate_Ilescr.1hed in the - -

I.' '

- Safety _Analysia_ Report (continued)

Temporary System Change 1-535-91

, (continued)

The"A" RHR subsystem is not required with the Reactor defueled and this TSC was cleared prior to Core reload. Defeating the trip interlock

-for no suction path to pwnp will not- make the RHR System inoperable because the Interlock is not required by the Technical Specificatlons and 4 a normal lineup la verified by the Technical Specifications. The "A" RHR subsystem is not required for backup fuel pool cooling. With the reactor defueled, there la no possibility for an accident or malfunction important to safety. Therefore the margin of safety was not reduced.

Temporary System Change 1-705-91 LaSalle Temporary System Change TSC 1-705-91 " Primary Containment (PC) Group 6 and 7 Level 3 Jumper Installation" approved the jumpering out i of the Primary Containment Isolation System (PCIS) Group 6 and 7 Level 3 i isolation inputs. The purpose of this change was to allow lowering of reactor pressure vessel level for testing of new wide range level l transmitters without isolating shut-down cooling, which is used as a means to lower level. This change was performed while the Unit was defueled with fuel pool gates installed. The isolation signals are only required for conditions 1,2 and 3. The UFSAR addressos a loss of fuel pool level and therefore no unanalyzed conditions existed. Since the Unit was ,

defueled and manual isolation capability existed there was no decrease In the margin of safety.

Temporary System Change 1-1338-91 To improve on the margin of safety, the diesel generator (DG) carbon Edioxide (CO2) control panels have been replaced with panels that can provide supervised detection. The cables have been wrapped in c>ndult and an enclosure with a one hour fire rating covers the DG CO2 cabinet.

While this modification was being performed, the following items were inoperable during certain parts of the installation A. the emergency manual push-button in the "0" and "lA" DG room B. the local' bell alarms, annunciator alarms, and trouble lights at the IFP04JA and IFPO4JB panels for the sprinkler system l

associated with valve's IFP030 and IFP031 C. the bell alarms for the "1D" diesel oil day tank room, "0" diesel fuel storage tank room, "1A" diesel fuel storage tank room, "lB" diesel fuel storage tank room, and the Unit I reactor building

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i

.e. )

i 0.. = Eumary mLChangen to thnJac.111tyJhic1 Late _Denctibed_in_the l Safety _Analytis_ Report.

(continued)

Temporary System Change 1 1338-91 (continued) i The suppression system was not affected by the inoperability of any of the_ items stated above. Automatic detection and actuation was still available within the room with an emergency manual and manual push-button

actuation available in the DG corridor. Additionally, the diesel day tank

?

. rooms are separated from the DG rooms and the rest of the plant by a 3-hour rated barrier. An hourly fire watch wan provided for the day tank .l rooms. If the sprinkler system within the day tank room had actuated, the  !

intermediate jockey pump and if necessary one or both diesel fire pumps would start thereby providing indication and annunciation in the control room. At,this point, an operator would have been sent to investigate the diesel oil day tank rooms.

l Temporary System Change 1-1405-91 ,

i LaSalle Temporary System Change, 1-1405-91, was used to plug and seal l floor drLins, clean outs, and the Tendon Tunnel access plug at various elevations in the reaclor building to reduce the chance of getting an incompatible cleaning solution into the radwaste system. Based on a safety evaluation, that was performed as required by_10CTR50.59, it was concluded that this Temporary System Change had an insignificant affect on the plant. The relatively small amounts of cleaning fluid used (500

, gallons) did not pose a flooding hazard and the drains could have easily been unplugged in the event of another source of flooding in the area.

Temporary System Change 1-1414-91 LaSalle Temporary System Change, 1-1414-91, was used to isolate the Unit 1 NE/NW Core Standby Cooling System Coolers for chemical cleaning.

~This Temporary System Change installed blind flanges on the down stream side of 1DG019, IDG023 and on the upstream side of IDG032 to isolate the IVY 01A and l 'YO4 A coolers . Based on a safety eraluation, that-was performed as required by 10CTR50.59, it was concluded that this Temporary System Change had an insignificant affect on the plant. The "0" Diesel Generator' Cooling Water Pump was operable during the time this Temporary System Change was installed. In addition, the Low Pressure Core Spray, Reactor Core Isolation Cooling, and "A" Residual Heat Removal pump room temperaturer were continuously monitored in the event Residual Heat Removal would have been required during this time.

G. Sggnary of CllRAges to the Facility Whleh aud2ein.lhedAthe Enf<ely Analysis _RePRLt (continued)

Temporary System change 2-077-91 LaSalle Temporary System Change TSC 2-077-91 " Manual Control of

- 2RE02PA" which-approves bypass of the DWEDS Sump Temperature and Level Interlock to allow continued operat'on of the sump pwnp. This would be accomplished by the installation of a switch junper across contacts .2-21 in the control-logic of 2RE02PA. The purpose of this change is to f acilitate better system control with increased sump temperatures and imputs. Section 9.3.3 of the UFSAR states that the sump pump autostart on high sump level. This will not be true when the switch jumper is installed and closed. However,-with the switch in that configuration the pump will run continuously anyway. Therefore-the probability of an accident is not increased since the leakage monitoring function of this system is not impaired. These pumps are not addressed in the Technical Specifications, therefore this change will not reduce the margin of safety.

t Temporary System Change 2-164-91 LaSalle Temporary System Change TSC 2-164-91, " Cross Connection Of Domestic Nater With Service Water At The Inlet To The Unit 2 Alterex Cooler" approves the injection of domestic water into the service water inlet to the alterex cooler through the alteret water inlet test tap.

During normal plant operation using service water as a cooling media in the alterex cooler, the heat exchanger surfaces tend to become fouled.

, During the summer months when the lake is at elevated temperatures heat transfer in the alterex cooler can be severely restricted. This change i will provide a source of cool clean water for the alterez cooler in order l to obtain a better heat transfer rate. This will lower machine air temperatures. The connection of domestic water and service water is a facility change. The UFSAR section 9.2.5 restricts the connection of potable water to a radioactive system. Service water is monitored for radiation and the TSC isolates domestic water from service water backflow through a double check valve. The Generator Alternator-Exciter is not required for safe shutdown of the reactor. The domestic water and service >

water systems are not required by any safety system for operation. If the generator-field excitation is lost, the corresponding turbine trip has already been analyzed. This TSC does not affect'any .achnical Specification items and the safety margin is not reduced.

l-l l

Temporary System Change 2-332-91 LaSalle Temporary System Change TSC 2-332-91 " Defeat Annuciator For Unit 2 'C' Residual Heat Removal-(RHR) pump Discharge Pressure High Alarm" approved lifting R-Point 1352 in order to clear a Division 2 ground. Due to steam cleaning in the RHR Room various equipment became wet. Pressure

!- Switch 2E12-N022C became wet and started to give a 110V ground on g -Division 2. The annunciator had to be defeated in order to clear this ground. UFSAR Section 7.6.2.2.5 states that high discharge pressure is a monitored parameter and chall provide annunciators for indication of a RHR leak. The high discharge pressure interface function was maintained by way of local pressure indication once a shif t while this TSC was in effect-. Technical Specification 3.4.3.7 actions were complied with by way of a 30 day timeclock and a special log to monitor pressure locally, therefore the margin of safety was not reduced.

G. Sumary_nLChanges._to lhelacilityJhtch_arcJescribed in_.the Snie.ty l nalysis_ Report (continued) r Temporary System Change 2-360-91 LaSalle Temporary System Change TSC 2-360-91 " Defeating Control Rod Drive (CRD) Hydraulic Temperature High Annunciator - 2H13-P603-A403" was written to defeat the Unit 2 CRD Hydraulic Temperature High Annuociator ,

(A403) at control room panel 2H13-P603. The purpose of this change is to j eliminat9 false / nuisance alarms. The CRD temperature recorder which

, supplies the alarm signal to this alarm is broken and causes false alarms on all CRDs. The recorder cannot be replaced until LaSalle Unit 2 Fourth Refuel (L2R04) at which time the recorder will be replaced with a new more

, reliable model. (Component Replacement 89-079, work request L88983) The CRD temperature recording, trending and annuciator alarm function are mentioned several times in the UFSAR Sections 7.7.2.2.3, 4.6.1.1.2.4.2.4, 4.6.2.3.1.2.2.1, 2, 3 and 4.6.2.3.1.2.6. The primary purpose. as described in the UFSAR, of this instrument and alarm function is to help  ;

the reactor operator identify accidents or equipment malfunctions which have occurred. The probability of any related accidents or equipment malfunctions occurring is In no way increased by loss of CRD temperature i alarms. The. consequences of all these accidents are bounded usually l causing a choked-flow small line break vessel leakage rate, limited rod  ;

withdraw (one notch) and or rod drift-in or scram. As CRD high temperature alarm is only one of several indications which will be received (and CRD temperature indication is not defeated), the event will not go on t

undetected. Shiftly monitoring per existing operating department curveillances, will allow the loss of cooling water flow to the CRDs to be detected by downscale flow indication and indication at the temperature recorders. Technical Staff will continue weekly monitoring of all hot CRDs. The CRD temperature recorders and alarm are not used as a basis for any Technical Specifications and-therefore can have no affect on aay matgin of safety.

Temporary System Change 2-374-91 LaSalle Temporary System Change TSC 2-374-91 " Temporary Defeating of Unit 2 Main Turbine Bearing #6 High Vibration Trip" approves lifting the vibration probe amplifier output f rom bearing 86 f rom the Turbine

- Supervisory Instrumentation (TSI) high vibration trip module. The purpose of this chango is to prevent a turbine trip caused by a spurious trip signal from the 66 Turbine bearing amplifier card while testing is being performed following installation. The bearing 36 high vibration trip will be bypaJsed. The UFSAR section 10.2.2 states that the turbine trips on high vibration. This will remain valid for all bearings except 96.

l

j. Administrative controls will be implemented to monitor vibration readings and alarms toitrip the turbine should a high vibration condition occur-on 46 bearing. .The. vibration trip is not for reactor safety purposes, it is

-for-aquipment preservation. The Main Turbine overspeed trip remains operable. A turbine trip on high vibration is not included in the Technical Specification accident analysis, therefore, the safety margin is not reduced.

l' i

e'y +e

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G. EnonryJ2LChGnges to thelad11ty WhictLMfLDeAndhed_.iLthe Sate _ty_Analys.ls_Regott -

(continued)

Temporary System Change 2-397-91 LaSalle Temporary System Change, 2-397-91, was used to isolate the Unit 2 NE/NW Core Standby Cooling System Coolers for chemical cleaning.

This Temporary System Change installed blind flanges on the down stream side of 2DG019, 2DG023.and on the upstream side of 2DG032 to isolate the 2VY01A and 2VYO4A coolers. Based on a safety evaluation, that was performed as required by 10CTR50.59, it was concluded that this Temporary System Change had an in11gnifjcant affect on the plant. The "0" Diesel Generator Cooling Water Pump was operable during the time this Temporary System Change was installed. In addition, the bow pressure Core Spray, Reactor Core Isolation Cooling, and "A" Residual Heat Removal pump room temperatures were continuously monitored in the event Residual Heat Removal would have been required during this time.

Technical Specification 3/4.8.2 Technical specification amendments to the engineered safety feature Division 3 125 Volt DC battery specific gravity requirements. This change-will update the technical specifications to reflect the manufacturer's recommendations for nominal specific gravity values for the replacement  ;

batteries to be installed under Modifications M1-1-90 011 and M1-2-90-009, These amendments are required as a result of the upcoming replacement of the Units 1 and 2 engineered safety feature (EST) Division 3 125 Volt DC batteries. The sC-distribution system and the batteries are designed to provide control power for bath normal and emergency operation of plant equipment and to provide power for automatic operation of the engineered l- safety feature protection systems during abnormal and accident conditions l (UFSAR Section 8.3.2.1). The technical specification 11mits for battery specific gravity are based on the manufacturer's nominal full charge specific gravity rating for a particular battery type, The replacement batteries are of a different type and are rated with a higher nominal full charge specific gravity value than are the currently installed batteries.

Raising the technical specification specific gravity limits for the Division 3 batteries will help to ensure that they are maintained in an operable condition capable of meeting their design function. This amendment does not affect the initial assumptions for any accident evaluated in the UTSAR.

The proposed snendment reflects the change in nominal full charge ,

specific gravity rating between the currently installed battery and the replacement batteries. The proposed amendment does not bring about any changen to the facility or to the-operation of.the facility as described in-the UTSAR.

The bases for Technical Specification 3/4.8.2~provides the criteria for establishing the battery specific gravity limits based on the manufacturer's. ratings.- The limits currently provided in the technical specifications for the Division 3 batteries if left unchanged would be non-conservative for the replacement batteries. Therefore, the technical specification specific gravity limits for the Division 3 batteries must be raised accordingly in order to maintain the current margin of safety.

i l

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G. Summ a ry_m LChar.ge n_to_t he_1.acili tyJihi ch _a f dc a c tib ed._in_the i Safaty_Analysia_Itepott

.. (continued)  ;

.UFSAR Chapter 8 - Electric Power  :

The UFSAR will be revised to reflect the setpoint changes of relays 1427-AP270A/D, 1427-AP271A/B, 2427-AP270A/B, and-2427-AP271A/D. The relays' trip setpoints will be changed from 3814 volts to 3885 volts, plus or minus 4 volts. Analysis of degraded voltage relay setpoints shows that the current relay settings are too low for all possible conditions at minimum switchyard voltages. A higher setpoint will cause the under voltage relays to trip at a higher, more conservative voltage but will not affect the way in which the undervoltage relay operates. The relay and >

lts designed function will not be changed.

UFSAR Chapter 8 - Electric Power -

, UFSAR Appendix H - Fire Hazards Analysis 4

Section 8.3.2 of the UFSAR will be revised to reflect the replacement of the Unit 2 non-1E 24/48V batteries. The old batteries are obsolete and have reached the end of their life cycle. Replacement cells for the o13 batteries are not available. The new batteries have a larger capacit y and their installation has required modifications to the racking system. The new batteries and modified rack meets all requirements specified by the UFSAR.

UFSAR Chapter 9 - Auxiliary Systems The UFSAR will be revised to reflect the changes made by modification M01-0-89-021. This modification: 1) removed the non-operational hypochlorite system, 2) installed equipment capable of injecting a hypochlorite/ sodium bromide mixture into the water tunnel inlet lines, and

3) installed equipment capable of injecting polyacrylate. The new chemical feed system will minimize biological fouling in the Core Standby Cooling System. Also, the new system will minimize biological fouling, silting, and scaling of all heat exchangers and piping that uses water from the. water tunnel. The installation was in response to a commitment made to the NRC in regards to Generic Letter 89-13.

This modification involves the addition of a non-safety related system with no direct control or interaction with ar.y other plant system.

Construction of this system does not interface directly with any plant systems which control reactivity, assure pressure boundary integrity, or provide core-cooling.

UFSAR Chapter '10 - Steam And Power Conversion System l: -The UFSAR will be' revised to reflect the addition of a test tap line l- on the Unit 2' condenser outlet dewatering line. This line will be used to provide warm water for the Unit I condenser chemical cleaning. When chemical cleaning is not in progress, the line will be isolated by an

! isolation valve and a blind flange.

l

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G. - Swnraagy oLChanges _tosthe_Iacj21ty_Which. art.leacribed An the Salely_AnalyA11JeP2il ~l (continued) ,

UFSAR Chapter 11 - Radioactive Waste Management During review of.UFSAR section 11.5.5, "High Radiation Sampling _ {

-System", __it was determined that this section needed to be revised to reflect:the actual plant conditions and to provide an enhanced description of the system. A past modification to the plant installed an in-line dissolved- oxygen probo in the nigh radiation sampling system panel to measure dissolved oxygen concentration. Another modification installed  ;

gas partitioners, capable of separating gaseous, lodine, and particulates. The gas partitioners replaced the'need to obtain an air smnple f rom containment. These changes were included in the revision to the UFSAR. To clarify the. location of where the analysis for boron would oce . the chemistry laboratory was specified. Finally, a section was ,

adveu to the UFSAR to describe the backup off site chemical analysis capabilities _that-the plant has in place. l Since the changes to the plant were evaluated separately and found not to affect plant safety as described by the UFSAR, by including these changes in_the UFSAR, plant safety will also not be adversely aff3cted.

The enhancements to_the UFSAR will only provide a more descriptive analysis of plant operations.

UFSAR Chapter 11 - Gaseous Waste Management Systems The offgas hydrogen analysars require a minimum offgas flow of 35 scfm. If the offgas flow rate is less than 35 scfm, then the hydrogen analyser must be considered inoperable. The offgas purge piping, originally used to add service air to the offgas system when a unit wcs shut down, will now be opened up to allow service air to enter the offgas l system continuously. By adding service air to the offgas system, the offgas flow _ increases from 20 to 80 scfm. The offgas system was designed  ;

to operate with flows up to 250 scfm and the offgas post treatment radiation monitors will isolate the offgas system in the event of high radiation doses. The UFSAR will be revised to' reflect these changes in the 1992 revision.

UFSAR Appendix G - Reactor Recirculation System The reactor recirculation differential temperature circuit has been modified. The reason for the modification was to reduce the number of downshifts. experienced by the reactor recirculation pwmp due to spurious low voltage. noise in the differential temperature circuitry. The new instrumentation provides signal conditioning between existing transmitters, resistive temperature devices, and existing-logic relays.

The new instrumentation has a signal range.of 1-5 Vdc opposed to e range l-of 0-1 mVdc thtt was used previously. This change does not functionally change the circuitry, l

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G. S umm ary_o LCh a nse a_to_thelatilit y_.Which_arLDe.s crib e d _in_1he

' Satelylnalysislepari (continued)

UFSAR Appendix 11 - Tire Hasards Analysis The walls'of the main steamline tunnel that extend-from elevation 736 feet-7 inches to 768 feet-0 inches at column 11 and rows G.5 to H.8, and column 12.7 and rows G.5 to-H.8 have been re-classified au non fire barrier walls. It was determined in a letter to G. Liederich, LaSalle Station Manager, from R. Bishop, production Services Manager, that these walls did not need to be classified-as fire barr16rs since they do not separate safety shutdcwn cables, safety shutdown equipment, and associated non-safety circuits of redundant traint.. The UFSAR will be revised to reflect this evaluation.

I UFSAR Volume X - Drawings The UTSAR drawing M-82 sheet I has been revised to reflect the installation of differential pressure gauges across the service air dryer afterfilters.- The gauges have been . installed in the three service air trains to measure differential pressure across the afterfilters. The gauge does not affect the operation of the filter. The service air system i is not safety or ASME code related therefore the installation of the gauge will not affect the safe shutdown of the units.

l.

I

l H. Suma ry_qlgalcly_Re l at eLMo dific ailo ns Modification M01-0-82-065

.This modification involved providing a logic _ change for-the Control Room Emergency Makeup Fans so the dampers OVC05YA/B and OVC5;YA/B would close upon manual start of-the emergency makeup fans. This change was installed as to prevent scavenging of the air to the Emergency Makeup Fans from the normal supply fans.- This will ensure that the Emergency Makeup Fans are supplied air from an outside source. The Safety evaluation concluded that there were no unreviewed safety questions.

Modification M01-0-82-084 This modification involved providing the permanent disability of the OVC01YA/B Tornado Pampers installed in the minimum outside air intake duct for the Control Room / Auxiliary Clectrical Equipment Room HVAC (VC) ,

system. This work entailed removal of control room indication lights and i hwitches for both sets of tornado dampers, removal of the tornado damper blades from the duct work, and the removal of the instrument air supply f rom the damper solenoid valve. A change to the U)SAR was required to support the removal of the 1ornado Dampers. The Safety evaluation concluded that there were no unreviewed safety questions.

Modification M01-0-06-014 This modification involved the physical removal / abandonment of the HVAC System VC Chlorine Detectors and associated equipment such as temperature switches, heaters, probes and sample lines. The control room HVAC chlorine detection system is no longer required at LaSalle County Station due to the absence of chlorine shipments around the plant. This analysis was performed in accordarce with the requirements of Reg. Guide 1.78, Guide 1.70 (Section 2.2.3.1) which iustified the removal / abandonment of the chlorine detection system. A chenge to the Technical Specification had been previously issued to eliminate all chlorine detection requirements-(section 3/4.7.2 and 3/4.3.7.8). However, changes to the UFSAR were required to support the removal / abandonment of the HVAC System VC Chlorine Detectors. The Safety evaluation concluded that there were no unreviewed safety questions.

Modification M-0-90-004 This modiffne*19n involved the installation of the required mechanical.ano el' t ilcal components for the IDNS Facility. The existing

• IDNS_SBGT and Main 5ts;k Effluent Monitoring System was demolished and only the SBGT Fenetrat ',2 was used for the- new equipment. This installation j also included additional tubing, heat tracing and supports from the plant stack to the new IDNS Facility. Connections to existing plant system were completed nder this modification. The Safety Evaluation concluded that there-were no unreviewed safety questions.

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2 II . S unna r y_o LS af e ty_ Re l ate dEodl il c at i o n s (continued)

Modification M01-1-82-273 This modification invclved replacing the esistina plvision Ill. 125V J DC Ground Detector with an Esterline Angus Ground Detector The

( replacement detector was mounted on the Division 111 125V DC Instr umentation Panel 1PLH2J. The ground detector was renlaced in order to meet the production instruction specification of alarming at 125K ohms to ground. The eulsting ground detector was alarming at 40K ohms which resulted in an alarm setpoint too ciose to the nornial operating voltage.

. The Ester 11ne Angus ground detector is capable of recording an.d dotection of a ground condition on both sides of the bus. A change to the UFSAR was required to support the new dround Detector. The Safety evaluation concluded that there were no unreviewed shfety questions.

t

' I Modiffration M01-1-03-062 This modificatlun involved relocation of the "B" RHR valve 1RE043 and orifice IE12-D310 from line 1RE17AD to 1RE37AA. Relocating the IRE 043 J valve will poimit warm-up flow from both "A" and "B" RHR loops to be sent  !

to the condenser rather than to the reactor building equipment drain tanks. This modification will also allow the line-up of the "B" RHR system l In a more timely manner for_ Shutdown Cooling Operatica. There were no '

UTSAR or Technical Specifications changes required. The Safety evaluation ,

concluded that there were no unreviewed safety questions. l t

i Modification M01-1-84-018 This modification involved the modif) cation of the control circuitry for the 1A Diesel Generator Circuit Breaker Close Circuit IDG01K. This  !

has involved the closure of the diesel generator 1423 breaker onto the 142Y bus if the bus is. faulted. This change would also trip the breaker upon the bus fault Indication as long as an ECCS signal is not present.

This benefits the diesel generator from supplying excessive currents to a faulted bus. There were no UrSAR or Technical Specification changes required. The Safety evaluation concluded that there were no unreviewrd safety questions.

Modification M01-1-87-078 This modification involved the replacement of the Petter dierel engine in the starting air system for the llPCd Diesel Generator la with an AC motor. This was necessary since the diesel engine starting motor load was not included in the battery service test and secondly the diesel '

engine is a high maintenance item and was not reliable. There were no Technical Specification changes required for this modification. However, i

changes to the.UTSAR section 9.5.6.2 were required to delett references to l the diesel engine from the system description. Also information on the new motors was inserted in the section as required. The Safety evaluation concluded that there were no unreviewed safety questions.

H. ."Enm ary.mLS al e ty_ Rela te L Ho di f ic at i on s (continued)

Modification H01-1-87-089 This modification involved revision of the 1A Diesel Generator to pr event a f all-to-st art t rip unless the air st art solenolds have been energised, allow continuous cranking of the diesel englne f or t he ent ire time delay t.etting of crank limit timer K39, and reduce electrient noise in the speed sensing signal. Thls change has improved the reliability and avallabllity of the 1A Dlesel Generator by correctlng a pntential problem with the stant circuit. The crank ar.d rest relays K37 e ad K38 were removed and changes to the permlsslve for the S6 lube oil pfessure switch in interlock the alt start solenolds. No changes to the Technical Speelfication or UFSAR were requited. The Safety evaluation concluded that t there were no unreviewed safety questions.

Hodification M01-1-87-097 a

, This modificatlon involved s eplacement of the reactor water IcVel Static-O-Ring (S-O-R) switches on the ECCS Systems, Low Presh4re Core Spray (LPCS), Residual Heat Removal (RHR), Automatic Depressurleation System (ADS), High Pressure Core Spray (HPCS) and the Reactor Core Isolation Cooling (RCIC) with an analog trlp system conslating of l Rosemount level transmitters, trip unlts, and control relays. This modificatlon was installed as a result of the NRC Bulletin 86-02. Changes to both the Technical apecificatlon and the UrSAR were completed. The Safety evaluation concluded that there were no unreviewed safety questions.

Hodification H01-1-88-001 This modification involved the replacement of the existing 250 Voll battery IDC01E ard rack and revising the current monitoring Instrumentation of the batt ery and it's associated charger. This was j

accomplirhed by removal of the existing Plante type FPS-13 battery and racks ~and installing the new GND Lead Calcium type NCX-27 battery and rack. This included the installation of inter-coll, inter-row, inter-rack i and main feed connections, and addltional and reconnection of all grounding cable. The bettery's rack have been r

hanged f rom a two stop to a two tier design to facilitate t.he battery's larger physical site. No 3 Technical Specification changes were required. A revisson to the UFFAR Section 8.3 was required. The Safety evaluation concluded that there were ,

no unreviewed safety questions. I i

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4 II . S um e t LoLS af e ty_.Re l a te d3c di f i c at le ria (continued) g Modification M01-1 88-002 This modification involved adding a 125 Volt Divls'on !! Ilattery 4

changer, IDC17E, rateu at 200 amps. This change is required to accommodate the new 125 volt, Division II, GND type NCX+17, batterles which are to also be Inst alled under H01-1-88-003. The new 1DC170 charges will be the primary charget and the existing change IDC16E will remain as a back up changer and may be used in the event of a primary chniger failure. The scope of this modification included the addition of instrument ation cables, new conduit f or *he charger, addition of AC n'.d DC cables f or t he new charger, addition of the AC breaker for the new charger, and addition of the DC breaker and a new 300 arnp shunt in the 2D cubleal. No Technical Specification changes were required. A revision to the UFSAR Section B.3 was required, The Safety evaluation concluded that there were no unteviewed safety questions.

Modificotton H01-1-88-003 L

This modification involved the replacement of the 60 lead-antimony '

Plante type FPS-15, 125 VDC_ Division 11 batteries with $8 GND Lead-calcium NCX-17 type batteries, and also replaced the hattery sack with one of a two-tier design so as to fit the new, larger batteiles in the existing battery room. This also revised the current monitoring instrumentation of i the batterles. No Technical Specification changes were required. A ,

revision to the UFSAR Sset.lon 8.3 was required. The Safety evaluation concluded that there were no unreviewed safety questions.

Modification M01-1 88-049  :

This inodification involved the upgr ade of the existing "1A" Diesel Generator Room Carbon Dioulde System from a unsupervised detection system to a Class A supervised detection system as speelfled in NFPA 72D-197$.

i The replacement of the existing control panals with selsmically qualified HEMA Type 4 CO2 control panels. Alarm horns, pushbutton stations, and electrol manual pilot cabinets weic also installed. There were no ,

Technical Specification or UFSAR changes required. The Safety evaluation i concluded that there were no unreviewed safety questions.

Modification M01-1-09-010 This modification involved the installation of four instantaneous Agastat time delay relay at 11113-F621 innel to prevent an erroneous tilp ,

of the RCIC Main and Feedwater Turbines. This time delay has provided a ,

four minute span for the operators to determine if the start of the RPlc system was spurious and secure RCIC If the' system is not needed to maintain vessel inventory to shutdown the RCIC Trip. The installation of new annunciator and labels, new HCR annunciator window, SER print.out message. relay labels, and selector switch and indicating lights were also

included with this modification. There were no Technical Specification and j UFSAR changes required. The Safety concluded that there were no unreviewed safety questions.

l

II . Sumny_oLS af e tLitelatedJiodific ations J .

(continued)

A l

1 Modifications M01-1-89-026 This modification involved the changes in logic to Anticipated l Transient Without Scram (ATNS) f r om one-out-of-two t o one-out-of-two t aken

, twice using the Alternative Rod Insertion (ARI) level and ptessure i instrw;Jntations for tripping the Reactor Recir culation pumps. The removal j of the calsting A7WS, pressure and level instruments, rewire AEER parts to f use ARI pressure and level logle telays, change selector switch at AEER panels, and additional reset pushbutton at MCR panel. This change has becu made to comply wit h the ATWS Rule 10 CFR50.62. The Technical Specifications ,

required changes to Table 3.3.4.1-1 to change the minimum number of l operable trip channels from one to two, since the new logic tequired bot.h channels of a divlelon (ttip system) to be operabic in order for the  ;

division to be operable. The UFSAP also required changes to be made to  !'

Section 15.8, Appendia G.3.1.2.2. The Safety evaluation concluded that there were no unreviewed safety questions.

Mod!fleation M01-2-87-052 This modification involved the replacement of the Petter diesel engine in the starting air system for the IIPCS Plesel Generator 20 with an AC motor. This was necessary since the diesel engine startleg mot-< load was not included in the battery service test. and secondly the diesel

, engine is a high maintenance item and was not reliable. There were no Technical Specification changes required for this modi ficat ion. Ilowever, changes to the UFSAR section 9.5.6.2 war required to delete references to the diesel engine from the system description. Also infor ntion on the new motors was inserted in the section as required. The Safety evaluation concluded that-there were no unreviewed safety questions.

1 Minor Plant Change P01-1-90-019 R

This Minor Plant Change involves the permanent installation of the temperature sensors in the Drywell t o menitor temperature of selected safety-reinted equipment. This change will abandon five (5) tempet at ur e i sensors (ITr.-VPO41, 042, 076, 081, and 082) and associated cables in place. It will however, install five (5) now temperature sennors

( 1 TE -V P- 113, 114, 115, 116, and 117) and cables witn associated junction l

boses and condult. This will allow all required temperature data for the drywell to be collected from the CM and the IPH05J panel in the Control Room. Changes to Technical Speelfication and UrSAR were required. The '

Safety evaluation concluded t hat there were no unreviewed saf ety quest ions.

Minor Plant, Change P01-1-90-020 This Minor Plant Change involves the installation of a small drain line to the upper and lower motor hearing oil reservoir of the "A" RilR pump motors. This drain line replaced the existing oil plug. The drain line consists of 3/4" line and a globe valve in order to facilitate oil sampling and dralning of the pump. There were no changos to Technical Specification or UTEAR. *ine Safety evaluation concluded that there ssre no unreviewed safety questions.

11 . S umm ar y . 9 t_ S af e ty.. Relate d .Hedi tic ations .

. (continued)

. ' w ,.:

Mino: Plant Change P01-1-90-021 1>

This H!nor Plant Change in.olves the inst allation of a small drain line t o F- ~ '

the upper and lower motor bearing oil resenvolt of the Low Pressure Core Spray (LPCS) pump motor s. This drain line t eplaced the existing oil plug.

The drain line consists of 3/4" line and a globe valve in orden to faellitate oil sampling and dralning of the pump. There were no changes to Technical Speelfication or UFSAR. The Saf ety evaluat 1o.. concluded t hat there were no unreviewed safety questions.

Hinor Plant Change P01-l-90-022 This Minor Plant Change involves the Installation of a small drain line to the upper and lower motor bearing oil reservoir of the liigh P essure Core Spray (llPCS) pump motors. This drain line replaced the existing oil plug. The drain line consists of 3/4" line and a globe valve in order to facilitate oil snmpling and draining of the pump. There were no changes to Technical Specification or UFSAR. The Safety evaluation concluded that there were no unreviewed safety questions.

Hinor Plant Change P01-1-90-028 This Minor Plant Change involves the addition of a clamp assembly to the Jet Pump sensing lines ($$ and $15) which are susceptible to failure by the r) circulation pump vane passing f requency induced vibrational ef fects.

Addition supports and reinforcement to existing supports were added to the sensing lines. This change will lucrease the natural frequency of the unsupp rted length of the sensing line resulting in lower alternating stresses acting on the welded attachments. There were no Technical Specification changes, floweve r , changes to the UFSAR were require to provide clarity and completeness of the as-built condition. The Safety evaluation concluded that there were no unreviewed safety questions.

Hinor Plant Change P01-1-90-033 This Minor Plant change involves installation of transient suppressors or varistors across the line and neutral of the 120 VAC feeds to the GE HUMAC power supplies for the main stemnline radiation monitors, 1D10-K610A, B, C, and D. The varlstor was installed in the control room panels Ill13-P635 and Illl3-P636. This change was recommended by GE in SIL No. 499 to protect the power supplies from low energy transients, There were no Technical Specification or UrSAR changes involved. The Safety Evaluation concluded that there were no unreviewed safety questions.

y _ , _ _ _ _ - _______ _ _ - -

F i H. Smnary_o tlo f e ty_Ite l at e d.Ho di fic ation s

i. '

(wantinued; i

L Hinor Plant Change P01-1-90-064 l This Minor Plant Change involves the installation of a small drain line to the upper and lower motor bearing oil reservolt of the "1C" RHR I

pump motors. T.is draln line replaced the existing oil plug. The drain line consists of 3/4" line and a globe valve in order to feel 11 tate oli sampling and draining of the pump. There were no changes to Technical Specification or UFSAR. The Safety evaluation concluded that those were no

unreviewed safety questions.

l l

Minor plant Changen P01-1-90-065

, This Minor Plant Change involves the Installation of a small drain line to the upper and lower motor bearing oil reservoir of the "1B" RHR pump motors. This drain line replacet,the esisting oli plug. The drain line consists of 3/4" lino and a globe valve in order to facilitate oli sampling and draining of the pwep. There were no changes to 7tschnical l Specification or UFSAR. The Safety evaluation cor4cluded that there we.e no unreviewed safety questions.

l l

Minor Plant Change P01-1-91-501 This Minor Plant Change involves the replacement of the motor pinion gear and worm shaft gear for the RHR 1E12-F064A Motor Operator. This motor i pinion gear will increase the operator's overell gear ratio from 31.9 to j 52.2. The springpack has also been replaced as part of a Technical parto l Evaluation. This change is in response to NRC Generic hetter 89-10 which requires that nuclear plant licensses evaluate the ability of certain motor operated valves to be repositioned when subjected to design basis conditions of flow and differential pressure. There were no changes to the Technleal Specifications or the UFSAR. The Safety evaluation concluded that there were no unreviewed safety questions.

Minor-Plant Change P01-1-91-503 This Minor plant Change involves the replacement of the existing 2 i ft-lbf motor with a 5 ft-lbf motor for the Reactor Building Closed Cooling I Water (RBCCW) IWR179 valve. To accommodate this new motor the magnetic circuit breaker setting'is being lowered from 12.6 to 11.0. The thermal overload is belt.g changed from 1.0 to 1.1. This change will increase the thrust that the actuater delivers to the IWR179 valve stom. This change la in rekponse.to NRC Generic Letter 89-10 which requires that nuclear plant licensees evaluate the ability of certain motor operated valves to be repositioned when subjected to design basis conditions of flow and differential pressure. There were no changes to the Technical Specifications or the UFSAR. The Safety evaluat.lon concluded that there were-no unreviewed safety questions.

- . - ~ . _

H. S weatro L S cle ty_it e lat e LHo d111 c at l u n s (continued)

Minor Plant change P01-1-91-505 This Minor Plant enange involves the replacement of the estating 15 i it-lbf motor with a 25 ft-lbf motor for the RHR 1E12-TQ08 valve. To accommodate tiis new motor the thermal cverload setting la being increased l from 4.0 to 6.6. The circuit breaker setting la being changed from 52 to {

70. This change will lucrease the thrust that the actuator delivers to the  :

1WR179 valve stem. This change is in response to NRC Generic Letter 89-10  !

which requires that nuclear plant Ilcens6es evaluate the ability of certain motor operated valves to be repositic. sed when subjected to design basis conditions of flow and differential pressure. There were no changes to the Technical Specifications or the UTSAR. The Safety evaluation [

concluded that there were no unreviewed safety questions. j Minor Plant Change P01-1-90 507 This Mlnor Plant Change involves the replacement of the motor pinion gear and worta shaf t gent for the Low Pressure Core Spray (!PCS) IE21-r012 Motor Operator. This motor pinion gear will increase the operator's overall gear ratlo from 138.4 to 186.4. This change is_In response to NRC l Generic Letter 89-10 which requires that nuclear plant licenseee evaluate the_ ability of _ certain motor operated valves to be repositioned when '

subjected to design basis conditions of flow and differential pressure.

There were no changes to the Technical Specifications or the UFSAR. The ,

Safety evaluation concluded that there were no unreviewed safety questions.

t i

Minor Plant Change P01-1-91-511 i This Minor plant Change involves the replacement of the esisting 2 ft-lbf motor with a 5 ft-lbf motor for the Reactor Dullding Closed Coollng Water (RBCCW) 1WR029 valve. To accommodate this new motor the magnette circuit breaker setting ls being lowered from 12.6 to 11.0. The thermal l overload is being changed from 1.0 to 1.1. This-change will increase the tnrust that the actuator delivers to the IWR029 valve stem. This change is in response to NRC JJneric Letter 89-10 which requires that nuclear plant licensees evaluate the ability of certain motor operated i

valves to be repositioned when subjected to design basis conditions of flow and differential pressure. There were no changes to the Technical Speelfications'or the UFSAR. The Safety evaluation concluded that these were ne,unreviewed safety questions.

Minor Plant Change P01-2-90-022 ,

Thls Minor Plant Change involves t.he installation of a small drain line to the upper and lower motor bearing oil reservoir of the "2A" RHR pump motors. This o.31n line replaced the existing oil plug. The drain line consists of 3/4" line and a globe valve in order to faellitate oli sampling and draining of the pump. There were no changes to Technical '

Specification or UFSAR. The Safety evaluation concluded that there were no

• l unreviewed safety _ questions.

l l

I l

II . SumteryJLSaf ety_Related Hodifications (continued)

Hlnor Plant Change P01-2-90-024 This Minor Plant Change involves the Installation of a small drain line to the upper and lower motor bearing oil reservoir of the lilgh Pressum Cote Spray (HPCS) pwep motors. This drain line replaced the esisting oli plug. The drain line consists of 3/4" line and a globe valve in ordor to f acilitate oli sampling and draining of the pump. There were no changes to Technical Specification or UrSAR. The Safety evaluation concluded that there were no unrevic.ed safety questions.

Minor Plant Change P01-2-90-044 This Minor Plant Change involves the installation of a small drain

, line to the upper and lower motor bearing oil reservolt of the "2B" RilR pump motors. This drain line repInced the existing oil plug. The drain line consists of 3/4" line and a globe valve in order to facilitate oli sampling and draining of the pump. There were no changes to Tschnical ,

Speelficatlon or UFSAR. The Safety evaluallon concluded that t5ere were no unreviewed safety questions.

l Minor Plant Change P01-2-90-055 This Hlnor Plant change involves installation of high temperature wires to replace deteriorated lead wires of the Containment Monitoring Isolation and Drywell Pnewnatic Valcor solenoid valve 2CM020A. The damaged  ;

fleid conductors were replace with 014 AWG Rockbestos Radiation Resistant Firewall SR lead wires. The spliced connection was insulated with Raychem WCST-N-115 heat shrink tubing. There are no Technleal Speelfication or UFSAR changes required. The Safety evaluation concluded that there were no unreviewed safety questions.

Minor Plant Change P01-2-90-056 l This Minor Plant change involves installation of high temperature wires to replace deteriorated lead w1tes of the Containment Monitoring Isolation and Drywell Pneumatic Valcor solenoid valve 2CM0200. The damaged fleid conductors were replace with 414 AWG Rockbestos Radiation Resistant rirewall SR lead wires. The spliced connection was insulated with Raychem WCSF-N-115 heat shrink tubing. There are no Technical Specification or UFSAR changes required.-The Safety evaluation concluded that there were no unreviewed safety questions.

Minor Plant Changes P01-2-90-060 This Minor Plant change involves installation of high temperature wires to replace deteriorated lead wires of the Contalnhent Monitoring Isolation and Drywell Pneumatic Valcor solenoid valve 2CM024A. The dnmaged fleid conductors were replace with 514 AWG Rockbeston Radiation Resistant Firewall SR lead wires. The spliced connection was insulated with Raychem WCST-N-115 heat chrink tubing. There are no Tect.nical Specification or UTSAR changes required. The Safety evaluation concluded that there were no unreviewed safety questions.

11 . Senary oLSaf ety_.Related3odi!1 cations

• (continued)

Minor Plant Change P01-2-90 067 This Minor Plant change involves installation of high temperature wires to replace deteriorated lead wires of the Containment Monitorlug Isolation and Drywell Pnewnetic Valcor solenold valve 2CM0180. The danaged field conductors were repInce with 114 AWG Rockbestos Radiation Resistant Firewall SR lead wires. The spliced connection was insulated with Raychem WCSF-N-115 heat shrink tubing. There are no Technical Specification or UFSAR changes required. The Safety evaluation concluded that there were no unreviewed safety questions.

Minor Plant Change P01-2-90-Ob8 This Minor Plant change involves installation of high temperatute wires to replace deteriorated lead wires of the Containment Monitoring Isolation and Drywell Pneumatic Valcor solenoid valve 2CM019A. The damaged field conductors were replace with 514 AWG Rockbestos Radiation Resistant Firewall SR lead wires. The spitced connection was insulated with Raychem WCSF-N-13 5 heat shrink tubing. L ere are no Technical Specification or UFSAR changes required. The Safety evaluation concluded that there were no unreviewed safety questions.

Mino: Plant Change P01-2-90-069

.This Minor Plant changa involves installation of high temperature wires to replace deteriorated lead wires of the Containment Monitoring Isolation and Drywell Pneumatic Valcor solenoid valve 2CM019B. The damaqed field conductors were replace with 514 AWO Rockbestos Radiation Resist ant Firews11 SR lead wires. The spliced connection was insulated with Raychem WCSF-N-115 heat shrink tubing. There are no Technical Specification or UFSAR changes required. The Safety evaluation concluded that there were no -

unreviewed safety questions.

Component Replacement 90-140 This Component Replacement involves the replacement of the obsolete N AMCO 7 50-7000 limit switch on the 84 Main Turbine Stop Valve IC71-N006G with a 740-00001 model. The new switch required the mounting to be changed to horisontally in a blister box attached to the side of the EHC cabinet that houses the existing switch. There were no Technien1 Specification on UFSAR changes required. The Safety evaluation concluded that there were no unreviewed safety questions.

Component Replacement 90-141 This Component RepIncoment involves the replacement of the obsolete NAMCO 750-7000 limit switch on the $2 Main Turbine Stop Valve IC71-N006E with a 740-80001 rnodel. The new switch required the mounting to be changed to horizontally in a blister box attached to the side of the EllC cabinet that houses the existing switch. There were no Technical Speelfication or UFSAR changes required. The Sately evaluation concluded that there were no unreviewed safety questions.

- - ~-

3 h Sursnar y_.0LS af e ty_Ite l ate diodific ations i . (continued) a Component Replacement 90-142 This Component Replacement involves the replacement of the obsolete NAMCO 750-7000 limit switch on the el Main Turbine Stop Valve IC71 H006A with a 140-80001 roodel . The new switch required the mounting to be changed to horisontally in a blister boa at tached to the side of the EllC cabinet j that houses the esistlng switch. There were no Technical Specification or tirSAR changes required. The Safety evaluation concluded that there were no unreviewed safety questions.

1 Component Weplacement 91-026 This Component Replacement involves the replacement foi the "A" Rilk l Pump Room 2TS-VY001 tempe:ature switch. The United Electsle temperatute i switches Model C402 120 has been determined to be an accept able  ;

r e pl acerne nt for the enfating switch Model C30: 103. There was no change to  ;

the mounting configuration or electrical conne.tlons. There were no Technical Specification or UFSAR changea requlted. The Safety evaluation concluded that t.here were no unteviewed safety questions.

a 1

L l

f 1

4 3

a 4

-w+,-w,tts-.,,v,-w-mm--wri- -w-e ar -we-,enw-car.-+--.-. . e ,ww , . ,- + y,ww w ny-%, ,#p r-, y ,. ,w- -e e,w,-g~. ++w,,y-+y,,wy-y e,-,-+y-me- ,-w ee v- g- vww t

1. Sumery_ of ECCG _Oute lea This inf ormation has been r epor t ed monthly in LaSalle's HRC Honthly Reports (Section 11.F.2) dated January 1991 through December 1991.

J. Su1Yey_91 Evaluation.llesults._OLChlorinc Shipments by llegge en.the Illinels live 14 ros r. copy of t he evaluation t hat was coinpleted in 1991 see Attachment D.

K. Summaty_cLEventsJiulating_ Technical. Spe;1tication. 3.4.L _Pt imary CoolanL10 dine _Spiklog.Ixceeding_ Allowable. Limits.

During this teporting period. January 1, 1991 thtough December 31, 1991, there were no vlointions of Technlen1 Specification 3.4.5, Primary Coolant lodine Spikes T. acceding Allowable Limita.

t 6 ATTACIIMENT A SATETY-RPLATED MAINTENANCE COMPLETED (HQi. OUTAGE RELATED)

.............. .__.. _.......... .............. UNIT.0 .... .. .. ___...........................

WRNUM SYS EPN DESCRIPTION l LO3081 AP OWH09T 1AP28E DUS 131H 104D KNOB BROKt I LO3811 DC ODC21E TSC BATTERY CilARGER VOLTHETER READS 130V LO4331 DC ODC19E RSil BATTERY CllRGR TRIPPED WilEN RESTARTED i LO5921 DC ODC20E TSC D/G 24 VDC BATT CELLS I 1 & 8 4 LOW SPECIFIC GRAV LO6219 DC ODC20E TSC DATTERY CELL 4 47 FAILED LOS-DC-Q3 LO7869 DC ODC19E RSil DATTERY CllARGER HOT WOREING L08563 DC ODC36E TSC 24 VOLT BATTERY HIGH FLOAT VOLTAGE LO9273 DC ODC19E RSH 125V CHARGER WON'T ADJUST LOW ENOUGH L11132 DC ODC02E SYS 11 BATT RMV CORROSION TRW CELL TERM CONNECTION L89124 DC ODC22E 125V CELL I47 ICV or 2.19 LO4067 DG ODGOBCA 0 DG A A/C SUCT/DISCilllOLD-DOWN SCREW LOOSE LO4068 DG ODG08CD 0 DG fl A/C SUCT/DISCH ll0LD.DOWN SCREW LOOSE LO4596 DG ODG08CA 0 DG A AIR COMPRESSOR SECURE OIL LEVEL L04597 DG ODG08CB 0 DG-D AIR COMPRESSOR SECURE OIL LEVEL LO4764 DG OPDS-VD004 OVD01r DG RON VENT SUPPLY AIR TILTER llIGil LO5249 DG ODG000 ODG SPACE IICATER NOT WIRED PER WIRING DIAGRAM LO5320 DG ODG00CB 0 DG D A/C RELIEr VALVE LITTING LO543w DG 00D01PB 0 DO TK ROOM SUMP PUMP H NOISE /VI!! RATION LO5453 DG ODG01K 0 D/G POWER PACK REBUILD POWER PACK LO5766 DG ODOO1P DG TUEL OIL TRANS PUMP REPLACE LO6093 DG OPS.DG047 DG CRANKCASE PRESS SW WILL NOT RESET 006600 DG ODG01K 0 DG WIRING VERITIED L08256 DG OLS.D0004 0 DG TOTP VLV INDICATED CLOSED L10678 DG OTIS-DG100 0 DG REPLACE ROSEHONT PROCESS MON COVER L10698 DG OLIS-D0008 B DrP DAY TANK LEVEL IND ERRATIC L11393 DG OLE.DOO0d DTP TUEL DAY TANK LEVEL IND LOCAL ll0RN INOP L08823 NR 1C51-000 ION CilAMBER LLW OUTPUT VOLTAGE L11829 NR lill 3.P603 A307 Ill13-P603 LIGilTS RESET ON BACK, ALARM STAYED I LO5864 RD OC11-F099 CRD N2 CllARGING HEADER BOTTLE DANK PR REG LO5971 RD OC11 9437 REBUILD CRD PER LMP-RD-01 DRIVE SPUD DAMAGED LO6184 RD OC11-T350 CRD H2 FilARGING RELIEF LEAKS AIR LO1800 VC .OPL15J VC CONTROL PANEL DOOR HANDLE BROKEN OFF LO2812 VL ors-VC002 VC AUX RELAY CilATTERING LO3816 VC OVC27YA VC SUPPLY DAMPER MOTOR DOESN'T WORK LO4412 VC OTZ-VC043 OVC19YB DAMPER DOES NOT RESPOND TO TEMP CllANGE

• LO4593. VC OVC05CD VC COMPRESSOR DISCH PINilOLE FREON LEAK LO4836 VC OXY-VC165B NH3 DET POST'S WORN CASSETTE CARRIER LO4837 VC OXY-VC165A NH3 DET POST'S WORN CASSETTE CARRIER-LO4838 VC OXY.VC125B N!!3 DET POST'S WORN CASSETTE CARRIER LO4839 VC OXY-VC125A NH3 DET POST'S WORN CASSETTE CARRIER LO5073 VC OPDS.VC013 CR M/U FAN REPLACE MICRO.SWITCil LO5088 VC OPDI-VCO29 EMERG M/U FAN UNABLE TO CALIBRATE INDICATOR LO5089 VC OFS-VC005 CR HVAC MIX DAMPER FLOW UNABLE TO CALIDRATE LO5090 VC OFS.VC006 CR HVAC FLOW SWITCH UNABLE TO CALIBRATE i LO5331 VC OTIC.VC003 MIXING TEMP CONTROLLER METER STICKS LO5379 VC 0FS-VC002 MIXING DAMPER WOULD NOT CALIBRATE LO5898 VC )VC22YD VC TEMP CONTROL DAMPER LEAKING OIL

ATTACID4ENT A SATETY-RELATED MAINTENANCE C04PLETED I

(NON-OUTAGE RELATED) i

---

------------------------------------ UNIT =0 -----------------------------------------  :

l WRNUM SYS EPH DESCRIPT!Of  !

f,- c LO6001 VC Ort-VC101 OVC52YA OUTSIDE AIR ISOLATION DAMPER DOES NOT CLOSE LO6002 VC OrZ-VC009C OVC14YA PURGE ISO DAMPER DOES NOT CLOSE TIGHTLY L06083 VC OXY-VC125B AMMONIA DCTECTOR WILL NOT RESET  ;

LO7069 VC OrSY-VC004X VC RELAY BURNED ,

LO7667 VC OXY-VC165A AMMONIA DETECTOR TAPE DOESN'T ADVANCE  !

L08177 VC Orz-VC001A OVC05YA & OVC52YA DAMPERS FUSE KEEPS BLOWING LO8192 VC OXY-VC125A A Hii3 DET MAG DRIVE MECilANISM PROBLFM LOB 331 VC OXY-VE087A

)

VC DUCT DETECTOR DID NOT RESPOND '

LOB 666 VC OVC01YB SECURE OUTBOAkD SET Or DAMPER BLADE 8  ;

LOB 692 VC OXY-VC165B AMMONIA DETECTOR FILTER PAPER DRIVE NOT WORKING LO8987 VC OXY-VC125A AMMOilA DETECTOR TAPE KEEPS TEARING LO8994 VC OVC05CB (B) VC EVAP C(X) LING COILS NOT OPERATING LO9118 VC OXY-VC12 5f? A>0 G IA DETECTOR REEL NOT TUNCTIONING

- LO9275 VC OXY-VC16$A- AMMONIA DETECTOR TLOW LIGilT IHOP L11277 VC OVC11YA INLET DAMPER DOES NOT OPEN L11633 VC OXY-VC1258 AMMONIA DETECTOR PEGGED DOWNSCALE L11723 VC OXY-VC165A B VC A NH3 DET READING 17 PPM, ALARM UP L12047 VC OXY-VC165A DETECTOR RECIEVED ALARM TAPE NOT ADVANCING ,

L99459 VC OrZ-VC007A OVC11YA ODOR-EATER INLET DAMPER DUAL INDICATIQi L99961 VC OVCS2YA CR OUTS!DE AIR ISOLATION DAMPER L99962 VC OVC52YB CR OUTSIDE AIR ISOLATION DAMPER r

b i

v-e .--emy-%_ w _.-,e., ..,___,...om._ . ,, .,, -

. . , . , , - + _ ,_e-w .,,_m...., .--,.r . . , _ .. _ ~ . . . - - .rm,, , ,.-,.,.__-me,-_

. _ -- . . - - - - - - . , - - - . - - - - - . - - - ..= _.

i

. ATTACl! MENT A S'(ETY-RELATED MAINTENANCE COMPLETED (NON-OUTAGE RELATED) +

---

UNIT=1-------------------------~~~~~--~--

WRNUM SYS EPN DESCRIPf!ON LO3167 AP IVT01CA 1AP11E GE BKR Bt!Sil!NG HISSING IDENT. AS REF 105 L05474 AP 1AP01E 151 CMPT 3 BRKR TOR SAT MAIN TEED 4-PT TB BROKEN LO6308 AP 1AP75E-G1 MCC 135Y-1 IIANDLE BROKEN ON BREAKER G-1 LO6505 AP 1AP75E-El MCC 135Y-1 El BREAKER IIANDLE INOP [

LO8590 AP 1AP63E MCC 133-3 COMP B-5 PilASE-PHASE TAULT L11356 AP 1AP80E MCC 136X-2 B2 DOOR WILL NOT OPEN ,

LO9249 APRM INR000 1r APRM RECEIVED IIALT SCRAM L10803 APRM RY-1C51-K605GT APRM SPIKING CAUSING 1/2 SCRAMS L12009 APRM RY-1C51-K60$GT APRM SPURIOUS 1/2 SCRAMS LO1741 DC 1DC33E 24/48 BATT CELLS 11&12 NAVE LOW SPEC GRAVIT)

LO2194 DC 1DC12E 125 VDC BUS 112X/112Y 10V GROUND INDICATE LO3781 DC 2DC03E 250VDC BATTERY CHARGER OUTPUT VOLTAGE LO4217 DC IPA 08J ANNUNCIATOR PANEL 90V POS GROUND EXISTS LO4428 DC 1DC09E DIV 1 BATT CilARGER ALARM CllATTERING ON TYPER LO5130 DC 1DC11E DIST PANEL 111Y BROKEN DOOR LATCH LO6108 DC 1DC000 DC EMERG LIGitT REPLACE FIXn!RE AND CONDUIT BOX LO7022 DC 1PA03J BAY 4 SCREW STRIPPED OUT R-POINT 507/508 L07028 DC 1DC000 U1/2 250V BUSSES MON FOR BASELINE VOLT READINGS LO8107 DC 1PA03J IER-DColb DIV 1 125V GROUND L08220 DC 1DC000 DIV 2 GROUND DETECTOR METER DOOR GLASS BROKEN LO9838 DC RR-1E22-R542 DIV 3 GROUND DET PEN NOT INKING LO9970 DC 1DC16E DIV II CilARGER AMPS OSCILLATING 10-15 AMP L10798 DC 1rl'EL63 EMERG LIGliTING ENERGIZED EMERG LIGilTING CilARGER L10800 DC ITPEL67 EMERG LIGHTS ARE ON WITH NORMAL LIGHTING ON '

L11067 DC 1E22-8001 125 VDC BATTERY LOOSE CABLE ON CELL 11 LO4441 DG 1E22-8001 IB DG COUPLER LOOSE LO4598 DG IDGOBCA DG A AIR COMPRESSOR SECURE OIL LEVEL LO4599 DG IDG08CB DG B AIR COMPRESSOR SECURE OIL LEVEL LO4605 DG 1E22-C302B llPCS DG AIR COMP "B" FAN GUARD REPAIR LO4823 DG 1DG011 STRAINER BACKWASil LOCAL INDICATION READS 75%

LO5051 DG 1E22-S001 IB DIESEL GENERATOR WELDED TO CLOSE TO FLYWilEEL LO5167 DG IPLG7J WHITE CONDUCTOR Of CABLE IVD132 CUT IN JACKET LO5952 DG 3DG08CA D/G AIR COMPRESSOR (A)! REPAIR LO7537 DG 1PA08J DG IIVAC TROUBLE ALARM CilATTERING NUISANCE LO8288 DG IE22-F316A DG AIR COMP DISCllARGE RELIEr VALVE LIFTING L00540 DG 1E22-C302B DG B AIR COMP BLOWN HEAD GASKET L08816 DG 1DGK008 1A D/G K-8 TDDE RELAY, REPLACE K-8 AGAETAT RELAY LO9151- DG IDGOBCD D/G AIR COMPRESSOR LEAKING AIR AT llEAD -

L09285 DG TS-1E22-N901B AIR DRYER IDG09DB REL 1E22-T361B LIr'!

LO9353 DG 1D0021 SUCTION STOP LEAKING TUEL OIL LO9354 DG 1D0062 TEST TAP LEAKING L10822 DG IE22-5001 CIRC OIL PUMP LEAK ON FITTING L10823 DG IE22-S001 OIL LEAK AROUND SOAKBACK OIL FILTER DRAIN PLUG L94404 DG IVD17Y 1TCU-VD013 NPCS DG COOL WTR PP RM TEMP UP L98231 DG IDGOIK DG TILTER INLET SCREENING BROKEN ON VENT INTAKE I,01335 IIP 2E22-C302B la DG AIR COMPRESSOR la REINSTALL PIPING LO4773 IIP IE22-r028 IIPCS DG COOLING WATER PUMP DISCll CilECK VALVE

. ATTACID4ENT A SATCTY-RELATED MAINTENANCE CC44PLETED (NON-OUTAGE RELATED)

..-- ----.. ------.-.-------------------.------- UNIT =1 -----------------------------------------

WRNUM SYS EPN DESCRIPTION L08291 IIP IE22-C302A IIPCS DG COMPRESSOR ll!Gli PRESS GASKET BLOWN L08805 IIP 1E22-r36111 D/G STARTING AIR C04P DISCll PRESS REL LO9088  !!P 1E22-C003 IIPCS WATER LEG PUMP llAS A 5 DPH LEAK LO9119 IIP 1E22-C003 IIPCS WATER LEG MACil1NE HOTOR BASEPLATE LO6630 IRM 1C51-K601C C 1RM NO DOWNSCALE INDICATION LO5269 LP PIS-1E21-H005D LPCS PUMP LOW DISCll PRESS RETORQUE LO4724 LPRM RY-1C51-K60$DZ LPRM A METER INDICATES DETECTORS IN DYPASS MODE LO8239 LPRM AY-1C51-K605AJ LPRM 40-41D DOWNSCALE RECEIVED L08984 LPitM 1C51-000 PERFORM COMPLETE SET Or IV PLOTS ON 01 LPRM'S LO9052 LPRM RE-1B13-D193L LPRM 16-49C RECEIVED LPRM DOWHSCAL LO4886- MS 1E51-D011 RCIC MIN TLOW ORIr1Cf INCREASE FLOW L05271 MS PS-1821-N056A COND LOW VAC MSIV ISOL RETORQUE LO6552 MS T1-1D21-R865 BLANKET STM SUPPLY TLOW INDICATION L10355 -MS F1-1821-R865 DLANKET STM SUPPLY FLOW INDICATION RECAL LO5110 ND TR-1821-R006 RX VESSEL TEMP RECORDER ERRATIC LO5124 NB -TR-1B21-R816 MSR TEMP RECORDER POINT DAD LO7985 NB LR-1B21-R615 RX TUEL ZONE RECODER LED DAR GRAPil L08174 ND 1821-000 TUEL ZONE LEVEL READS ONSCALE; S110VLD DE Orr L08541 NB LT-1B21-N044A FUEL ZONE LEVEL XMTR LOSS Or 01L LO9479 NH LT-1B21-N406C RX VESSEL LEVI:L LEAKS TOUND LO9480 ND LT-1D21-H406A RX VESSEL LEVEL LEAKS TOUND LO9481 NB LT-1B21-N406D RX VESSEL LEVEL LEAKS TOUND LO9482 NB LT-1D21-N4098 RX VESSEL LEVEL LEAKS TOUND LO9679 NB 1D21-N403A RX VESSEL LEVEL TRANSHITTER OUT OF TOLERANCE LO3569 RD IC11-D001-107 ACCUMULATOR WATER SIDE VENT LEAKS LO5000 RD IC11-000 CRD DLOCK STOP VLV LEAK H2 DY STEM WilEN OPEN 005418 RD 1AP06E IB CRD TD PP TRIP CIRCUIT RELAY DAD 6 LES-RD-104 LO7045 RD 1011-C001B CRD PUMP DIRTY SPEED CHANGER LO8160 RD IC'.1-D001-161 IICU 50-19 TilREADS ROUGil; N2 LEAKS SLOWLY L00335 RD IC11-C001B CRD PHP LEAK ON LUBE OIL COOLER TLNG LO8669 RD PI-1C11-R022 IICU 18-59 NITROGEN LEAK ON PIPE LO8995 RD 1C11-D001-023 IICU 10-4 3 CHAMING NIPPLE LEAKS LO9005 RD- IC11-D001-023 HCU 10-43 INST-BLOCK ISOL VLV LEAKS PAST STEM LO9127 RD 3C11-r379 SDV VENT & DRAIN SnlCK CLSD LO9156 RD 1C11-r023A CRD DRIVE FLTR DROKEN DRN VLV STEM LO9195- RD IC11-r022A CRD TILTER VENT VLV N/D BROKL Orr LO9197 RD IC11-C001A CRD PUMP llIGN LUBE Olb INLET TEMP LO9331 RD IC11-D001-071 HCU 30-15 DUZZING 118 AIR SOLENDID VLV LO9415 RD IC11-D001-126 CRD ACCUMULATOR LEAKS AT INSTRUMENT LO9945 RD 1C11-D001-111 06-35 LEAKS DY UNLESS DACKSEATED L10254 RD IC11-D001-107 ACCUM 30-51 GAS NIPPLE & CAP LEAKS L11428 RD IC11-D001-111 CRD 4 50-35 REPAIR L80365 RD IC11-C001B 10 CRD PUMP CAS1HG EROSION LO3526 Rii 1E12-P094 TUEL POOL EMERG M/V LEAKS PAST SEAT LO3899 F.!! TDS-1E31-N614A RilR EQ AREA VENT TRIPS INTERM.

LO4681 RN 1E12-r052A STEAM LINE ISOf' TION VALVE INOP LO4755 R'l 1E12-r052A STEAM LINE ISOLATION VALVE INOP

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

4 ATTACllMENT A SAFETY-RELATED MA!!!TENANCE COMPLETED (NON-OUTAGE RELATED)

---

UNITal -----------------------------------------

WRNUM SYS EPN DESCRIPTION LO4769 Ril 1E12-r331C WS PUMP DISCil CllECK VLV INSTALL ACCESS LOS280 Hit PS-1E12-N512A RHR PUMP DISCil PRESS LOW SW RETORQ L05614 Ril IE12-r094 T.P. EMU TO B RilR DE/RETERM FOR LO3526 LO6543 RH 1E12-r004C IC RilR PUMP SUCT STEM IND HISSING LO6548 Rll TI-1E12-R509 RHR SERV WTH SUCTION TMP OUT Or TOL LO7870 Ril PDI-1E12-N029A D1V 1 LINE INTERGRITY ALARM (!P LOB 117 RH 1E12-r336D B WS STRNR B/W STOP VLV PACK 1HG LEAK L08268 RH PT-1E12-H034C RHR DIScil PRESS COVER SIEZED/ LOOSE LO9348 Ril PS-1E12-H01611 1E12-C002D RilR PP 90 VOLT NEGATIVE GROUND ON 112 LO9845 RH IE12-r332A RilR SW PP DIScil STOP PACKIN3 I.EAK L09932 Hil 1E12-r074D HCC 136Y-1 TRIPPED C RCUIT HER FOR VL L10791 RH 1E12-KX60D O/L DYPASS CRACKED GLASS COVER L11990 Ril PI-1E12-R528 RilR SW PP 1C SUCT GAGE !! LOCKED LO2989 RI 1E51-C003 RCIC WTR LEG PUMP USES EXCESSIVE 01L LO4832 RI 1E51 C003 RCIC WTR LEG PUMP LEAKED OIL LO4907 R1 1E51-R604 RCIC PUMP SUC PRESS IND ERRATIC I,05272 RI PSL-1E51-H006 RCIC LO SUCTION PRESS SW RETOROUE LO7046 R1 PI-1E51-R907 RCIC ElRD OIL FACE PLATE IS MISSING L10085 RI 1E51-r358 RCIC WLP REPLACE VLV llANDWHEEL L11033 R1 IE51-C002 RCIC TURD TRIPPED ON MECH OVERSPEED LO7606 RM IC11-000 RMCS TRANSPONDER CARD TAILED L07628 RM 1C11-000 RMCS TRIPPED ON ROD 34-31; OPER !!YPASSED L08807 RM 1C11-000 RMCS KEEPS TRIPPING SUSPECT BJM LO9601 RM 1C11-000 RMCS TRIPS L11535 RM 1RD000 RMCS TRIPPED AND WILL NOT STAY RESET L08885 RP 1C71-AK10r $3 TSV SCRAM RELAY CHATTERING / HUMMING LO8294 SRM R1-1C51-R601C SRM METER IND DRIFTS UP SCALE LO9051 SRM RR-1C51-R602 SRM REC VTRY ERRATIC W/ STABLE 10HZ LO8261 TIP RY-1C51-J600ll IE TIP FUSE #5-FLICKERS; REPL TUSE L10888 TIP RR-1C51-R904 TIP X-Y PLOTTER OUT OF TOLERANCE LO9232 VG 1rR-VG009 VG FLOW RECORDER DOES NOP ADVANCE LO9419 VY 1rE-DG030 REMOVE FLOW ELEMENT FRth IVYO3A DIScil LO9663 VY ITIC-VY023 SRV WATER PUMP WILL NOT 00 CLOSE L11418 VY 1 TIC-VYO17 IIPCS ROOM DUCT TEMP RECALIDRATE l

l-

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

ATTACNMENT A SAFETY-RELATED MAINTENANCE COMPLI:TED (Nai-0UTAGE RELATED)

---

. .------------------------- UNITm2 -----------------.-----------------------

WRNUM SYS EPN DESCR7PTION 005817 AP 2AP72E MCC 235X-2 C1 BURNED CONTACTS LO8194 AP 2VYO10 MCC 235Y-2/E4 RELAY CONTACTS FOR AUTO TRI LOB 195 AP 2VYO4C HCC 235Y-2/E3 74 RELAY CONTACTS LO820$ AP 2APO4E 2Sr01PB MCC 241Y CMPT 8 TRIP LATCil ROLLER LO964C AP 2AP03E OVERCURRENT RELAY HELTED INSULATION L10231 AP 2AP82E-D4 MCC 236Y-1 CUB D4 TD TO 2E12-r064B REPL CIRCUIT BRK L10580 AP 2AP74E TRACKWAY DMR TRIPPING BREAKER j L96547 AP 2APOSE TERMINAL B .CK CRACKED '

L98399 AP 2AP19E 480V SuGR 235X ORDER & RPLC 2 TUSE BLOCKS LO3859 APRM AY-2C51-K605CW LPRM 32-57 NOT TEEDING APRM CURRENT [

LO5120 APRM RY-2C51-K60$GN APRM SPURIOUS r!XED NEUTRON UPSCALE 1/2-SCRAM LO5547 APRM 2NR000 APRM C WILL NOT AtJ1 UPSCALE N1 21113-P608 005662 APRM 2NR000 2E APRM NO TIIERMAL TRIP OCCURRED e LIS-NR-403 LO9750 RR-2C51-R603A APRM APRM SPUR 1006 UPSCALE NEUTRON TRIP L03994 DC 2AP03E DIV I 125 VDC GROUND EXISTS OH 125 VDC BUS PLUC LO5923 DC 211 DC054 DIV 2 CNRGR AMMETER IN CR NEEDLE STUCK L06066 DC 2EI-DCO$$ 250VDC BUS VOLT INDICATION LOW LO9560 DC 2DC15E DIV 11 125 BUS GROUND Or 8 VOLTS ON DIV !! 125 V L10509 DC 2DC000 OBTAINED 60 V GROUND IND ON DIV 2 125 VDC L10521 DC 2DC14E DIV 11 BATTERY VER1rY SPACING BET JATT L96969 DC 2DC31E 24 VDC BATTERY LOW ICV CELL $7 LO2103 DG 2DGOBCB 2A DG STARTING AIR COMP CilK SUCTION LO3061 DC 2VD19Y llPCS CWP RM EXil FAN OUTL PAILED CLOSED LO3323 DG 2DG006 A DG COOLER OUTLET VLV VIBRATES EXCESS.

LO4166 DG 2E22-S001 .28 DG SOAKDACK PUMP BULB BROKEN Orr LO4317 DG 2PDS-VD004 2PL24J ALARM WILL NOT RESET DG VENT SPLY TILTER LO4557 DG 2DG08CB DG B AIR COMPRESSOR SECURE OIL LEVEL LO4558 DG 2DG08CA DG A AIR COMPRESSOR OIL LEVEL '

L04795 DG 2PL24J DEV 27/2PL74J UNDER VOLTAGE RELAY STICKS LO4803 DG 2DG08CA COMPRESSOR 2A DIESEL CHECK SUCTION LO484d DG 2PDS-DG051 FUEL TILTER RESTRICTED ALARM LO4896 DG 2PDI-VD004 DG ROOM VENT D/P ALARM UP DN 2PL24J LD5254 DG 2AP72E 235X-2 NICK IN MOTOR LEAD Orr 71 RELAY LO5356 DG 2E22-C3028 AIR COMP REPLACE PRESS RELIEr VALVE LO5492 DG 2VD19Y DIV 3 SWGR VENT DAMPER REBUILD /REPA!R LOS654 DG 2PDS-VD004 2PL24J ALARM UP W1 Tit NO HIGil D/P LO6171 DG 27Z-VD013B 2VD17Y DAMPER ACTUATOR LEAKING OIL LO6197 DG 2DG01K 2A DG REPL COOLING WTR RUBBER 110SES ON 110LD TANK LO6330 DG 2rl-DG029 IIEAT EXCllANGER TLOWMETER READS 200 LO6847 DG 2E22-C302A DG AIR COMP A CLNG COIL LEAKS AIR LO7153 DG 2PM01V COMP PT D292 DG CWP CONTROL POWER UP SPORADIC LO7527 DG 2TS-DG040 DG NTR TEMP REPL DG IMMERSION llEATER '

L08676 DG 2E22-S001 DIV 3 BATT CORROSION ON CELLS 4,7 & 13 LO8762 DG OSI-DG028B D/G FREO METER READS NIGHER ON 2PM01J LO8817 DG 2DGK008 K-8 TDDE RELAY REPLACE K-8 TDDE AGASTAT L09128 DG 2DGOBCB DIESEL CilECK SUCTION & DISCllARGE V!N L09129 DG 2DG08CA DIESEL CliECK SUCTION & DISCllARGE VLV

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

ATTACllMENT A SAFETY.RELATED MAINTEllANCE C04PLETED (NON.0UTAGE RELATED)

................... ........................... UNIT.2 ..........................-.~.~ ....~.

WRNUM SYS EPH DESCRIPT!Of l LO9587 DC 2D002P DO TUEL XPER PUMP MOTOR MOllITOR CURREllT e OPS ,

L10095 DG 2D0011 2A DG CLNG WTR STRNR B/W OUT PACKING LEAK l L10315 DG 2D0000 CAL f. DOCUMENT CAL OT 2D DIESEL OENERATOR I

L10643 DO 2E22.T302A 2D DO A AIR RECCIVER DRA1H VLV LEAKS-L10647 DG 2D0000 2A DO STORAGE TANK SAFETY CllA1H 700 Sil0RT L10648 DG 2D0000 2A DO TUEL STORAGE INSTALL SAFETY CllAIN AT TOP L10683 DC 2E22.T302A 2D DG AIR DRYER CLAMP NEEDS TIGHTENED L10684 DO 2E22.C302A 2B DG A COMP DRAlti LEAKING 1/2" CAP L106118 DG 2E22 0001 2D DO TUEL OIL TLANGE TIGitTEN TLEX ll0SE FLANGE L10828 DG 2DG000 TIGitTEN LOOSE AC SOAK!)ACK PUMP MOTOR TERM DOX L10835 DG 2DG02JB ALARM HORN INLTALL PROTECTIVE COVER L11662 DC 2D008DD DG AIR DRYER CHECK VLV 2D00498 HAS WATER L11696 DO 2PDS-VD004 2VD01r 2D DO RM r!LT D/P 111 ALARM UP L11776 DO II.2E22.M005 RECAL DG AMMETER TO CONFIRM CERT 787 INSTR L03308 IIP 2E22.C302A PETTER DIESEL REPLACE W/ AC MOTOR LO4774 HP 2E22.r028 HPCS DG CLNG WTR PHP DIScil CK VLV INST >

LO4887 IIP 2E22-r023 HPCS INLL FLOW TEST VALVE ll/WilEEL Orr LO5070 llP PDS.2E22.N009 LOW SIDE VENT HARD TO REMOVE LO8248 IIP LS-2E22.N002A 21113.P601 A307 fiUPP CllAMBER LVL 111 LO8818 IIP 2E22.BK008 K-8 TDDE RELAY REPLACE Tile K.8 TDDE LO9012 ilP 2E22.P301B llPCS ANNUNCIATORS ALARMS SPUI.foUS LO9028 HP 2AP079E MCC 243 1 BROKE Orr; TAB OH 0/ LOAD DEVICE LO9874 IIP HC.2E22.K015 LOCKOUT RELAY NOT CRIMPED TO TERM 1HAL LO4955 IRM #".2C51.K601D IRM D CilATTERSI DOWNSCALE TRIP LOS446 IRM RY.2C51.K00211 IRM (11) LOCAL PRE AMP ll!Gil LO6827 IRH RY 2C51.K601D IRM D BAD PRE-REG (NEG); REPL L11350 IRM RY.2C51.K6010 20 IRM ll!Gli VOLTAGE CONNECTOR ON DRAWER J7 BAD LO6476 LC E32.D001J llEATERS PERT EQ 18-M0 SURV CilK LO9282 LC PI.2E32.R651E MSIV.LCS WON'T CAL 6 LIS.LC.201 LO9947 Ls: 2LL000 FIX LIGIIT DOES NOT llAVE PROPER VOLTAGE L10191 LC PT.2E32.N058 REPLACE LUCS AT PNL 21122.P027 LOS268 LP PS-2E21.N005B LPCS PUMP LOW DISCH PRESS RETORQUE LOS2P3 LP - 21113.P601 - C508 LPCS INJ TLOW III ALARM UP LO57* LP TE.2E21.C001AB PUMP MTR UPPER TilRUST BRNO ALARM LO6807 LP 2E21-R002 LPCS PUMP DISCll IND 120 CR IND 600 L11444 LP 2E21.C001 REPLACE (D) CONTACTS LO1842 LPRM RY.2C51.K605DK LPRM 24 25D FAILED UPSCALE /DYPASSED LO6223 LPRM RY.2Cil.K605CF LPRM 48 17C INSTALL AN OMNILIGilT Hl: CORDER LO5270 MS PS.2 BM -N056 A COND LOW VAC MSIV ISOL RETOROUE LOB 671 MS 2B21 1433A TDRFP DAMPER SOCKET S*lVCK ON VALVE L11678 MS TR.2B11.R816 MSR TEMP RECORDER DOES NOT PRINT LO3564 NB FR.2C34-R607 FEED / STEAM FLOW RECORDER HISMATCil LO4628 ND PT.2B21.N051A SPDS RX PRESS IND I.EADING lif GH; WIDE RANGE LOS276 PC PS.2D21-N048A DRYWELL HIG'ir PRESS SW RETOROUE LOS278 PC PS.2B21-N047A DRYWELI. PRESS SW RETORQUE LO5367 PC 2PL15J A*n40SrilERE CONT MON PANEL NO LOW FLOW ALM LO9627 PC 2ZL-PC001A VAC DRKR REPL DIV 2 LIGirl SOCKET

i ATTACitMENT A

, SAPETY-RELATED MAINTENANCE COMPLETED (NON. OUTAGE RELATED) 1

................. .............................. UNIT.2 ...................................... ...

WRNUM EYS EPN DESCRIPT!O4 L06177 RIH RR-2051-R603C RhM/APRM/1RM RECOPDER PEN $2 L02496 RD 2C11-C001D 2ll CRD PP I/D SEAL LEAK L05237 RD 2C11-D001-107 11C0 $0-31 DRAIN LEAKS DY L05369 RD 2C11.D001-079 CulTROL ROD 26-11 N2 LEAK ON INST 11 LOCK PR SW LO5388 RD 2C11-D001 121 NCU 34-43 N2 LEAK 6 CHARGING CAP LO5793 RD 2C11-D001-064 26-19 BCRAM OUTLET VIN LEAKING AIR LOB 313 RD 2RD000 CRD DRIVE PLTR VLV LEAKE BY APPROX 1/2 GPM ,

LOB 436 RD 2C11-C001B CRD PUMP O/D BRNG USING OIL l LO9153 RD 2C11-C001B CRD PUMP LEAK 1HG CASING SEAL CROSSTIE J L10459 RD r!-2C11-R003 CRD llDR TLOW REPLACE GE180  ;

L10555 RD TR-2C11-R018 CRD TEMP recon 0ER NOT PRINTING-L10854 RD PI-2C11-R007 CRD PRESS PEGGED TO MAX OR SnfCK L11279 RD 2C11-000 21113-P603 CORP DISPLAY L1tillTS ALL LITE AT 04CE /

L96487 RD 2C11-D001-113 REDUILD CRD LO3293 Rif 2D18-J005 D & C RilR SERV WTR PRM 1/4 GPM LEAK LO4770 Rif 2E12-P331A WS PUMP DISCllARGE Cl!ECK VLV LO493' Ril 2E12-C300D RilR SW PUMP OILER P! PING LEAKING LO5279 Ril PS-2E12-N512A Ri!R PUMP DISCll PRESS LCM SW RETORQ LOS663 Ril PI-2E12-RS29 2D RilR WS PUMP PRESS IND ZERO SillPT LO6063 Ril PS-2E12 N413D HilR INJ VIN TilREADS STRIPPED  ;

LO6433 Rif TRS.2E12.R601 RilH TEMP REC CAUSES P601 C302 ALMS LO9220 Ril 2E12-l'048D Ril llEX HYPASfi TRIPPED ON T/0 CLOfi1NG '

L09493 RH TRS.2E12-R601 RilR llX INLET /0UTLET TEMP RCDR IND L10119 Rif 27tC-VY016 RilR A CUB TEMP CQiT DOWNSCALE L10695 Rif PIS-2E12-N022C 2C RilR PP DIScil PRESS 111 ALARM ,

L11627 Ril CI.2E12-NO308 -RilR I!X COND TRANS CURRENT OUTPUT L11660 RH PS-2 E12-N 51211 PP DISCil PRESS 1AM ALARM UP L98760 RH 2E12-r332C RilR SERV WTR PP DISCII VLV PACKING LO5188 R1 LSil-2E51-H010 RCIC TURBINE OPEN W/O 2ill3-P601

-L05201 RI LSil.2E51-N010 RCIC DRAIN POT LEVEL INiiTALL NEW LO5448 RI PSH-2E51-N009A RCIC TURD STM EXil TO SUP POOL LO5449 R1 PSL-2E51-N006 RCIC PUMP SUC PRESS RETORQUE PRESS LU5775 .R1 2E51-C005 RCK BAR CCND VAC PUMP ALM WillLE ItDNNING LO9206 R1 2E51.D306 RCIC INJ SIGHTGLASS CRACKED 111G11 POINT LO6806 RM 2C11-000 RMCS TR11'S ON ACTIVITY ERROR ON ROD'46-35 L08026 RM 2C11-D001 135 ROD 46-35 TRIPPED RMCS Oli DIFT.

LO5273 RP PS-2C71-N002A PRI CONT PRESS SW RETORQUE L11349 RP 2C71-K101A CRD CHRG WTR IIDR PRESli TDR DUT OF CAL L94227 RP 2C71-8003E RPS M6 SET LOCALLY CKT BKR RPLC W/NFW LO6737 TIP RY-2C51-J600K TIP MACll1NE DOES NOT ENERJIZE L08657 TIP RY.2C51.J60CK TIP DRAWR OUTPUT INL NOT WORKING L08814 TIP RE-2C51-N003A TIP DETECTOR TAILED UPSCALE L10607 TIP RY-2C51-J600 TIP CNTL LIG!!T GOES OUT WilEN MACil!NES IN AUTO L10130 VC 2rSY-VC002X VC !! EATER & IfUMIDITY RELAY llURNED L02926 VG 2VG01C PRIMARY SBGT PAN VIDES 1110'l >

.LO7784 VG 2FE-VG003 SDGT DAMPER PERT INSP/CilANGE-0UT PER EQ >

L10220 VY 2 TIC-VYO18  !!PCS PP TEMP A!J4 2H13-P601 A408 CYCLE

_ . _ _ . _ _ . u.u_._.__u___._._.___._~._..-. _ . , _ . . _ . _ , _ _ _ . _ , , _ _ _ _ -

ATTACl! MENT H r

!! .B UNIT SITUTDOWHS  !

(UNIT 1)  !

DATEl_31021t_ GENERATOR Orr-LINEl_1980al. OUTAGE TYPE ScheduledJL11t04)

(YYMMDD) (llou r s ) -

REASON: Refueling Outage CRITICAL ACTIVITY PATill See Appendia A CORRECTIVE ACTIONS (DVR/LER$ if applicable): N/A RADIDACTIVITY RELEASE / EXPOSURE OVER 10% ALLOWABLt VALUES: None SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED See Appendia B DATE: 31011P_ GENERATOR Orr LINEl_62.1, _, OUTAGE TYPE: _LOIcedJL1f12)

(YYMMDD) (flour s)

REASON: Control f ailure of the 1 A Turbine Driven Reactor reed Pump. ,

CRITICAL ACTIVITT PATil Investigation of the f eed pump f ailure.

CORRECTIVE ACTIONS (DVR/LER$ Af applicable):

DVRO 1 1 91 0062 LER$ 91 006 00 RADIDACTIV17T RELEASE / EXPOSURE OVER 10% ALLOW 1.BLE VALUES: None SATETI RELATED CORRECTIVE MAINTENANCE COMPLETED MENUK. SYS _EMi- MSCRIP112 i LO9964 LC 1E32.r008 Blowing stenm from valve packing LO7352 DC 1ER.DC015 Divlslon 1 125V ground detector

• LO7582 MS ID21-r022D inboard MSIV blowing air from norgan valve LO7951 LC 1E32-r008 Valve packing leah LO7952 LC 1E32.r006 Valve packing leak 007605 MS ES.1B21.MSDPv1 G1 Bypass valve improper indication LO7634 RD 3C11.D001 030 HCU 10 39 replace scram pliot sol valve LO7642 RD IC11.D001 034 HCU 22 35 replace sermn pilot sol valve LO7658 MS 1D21-HCVCA.3 Drain valve packing leak LO7659 HS 1821.MOVCA-2 Drain valve packing leak LO7666 AS IB21.r511 Blowing steam at packing LO7723 MS 1B21.r049A Valve ' packing leak LO7860 MS 1821-r408A Valve packing leak LO7941 FW ZS.1B21-r032A Adjust check valve limit switches

.LO7982 1RH R1-1C51-N002D 1RH inserts improperly L08002 TW 1rWOO5 riow control valve leaks oil L96946 TG 1B21.CIV.1 11 valve leaks oil i

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

• APPENDIX A I CRITICAL PATil ACTIVITY '

RETUEL OUTAGE (L1R04) {

)

i DESCR1PTION i

COMMENCE POWER REDUCTIQi j MAIN TURBINK GENERATOR Orr LINE 1 PERTORM TURDINE OVERSPEED TEST i PERFORM STATOR COOL 1HG PUMP LOGIC TEST i SAMPLE DRYWE!,b TOR DE1HERT1HG '

PLACE MAIN TURBINE GENERATOR Qi TURNING GEAR l DE-!HERT DRYWELL OBTAIN DATA ON REACTOR REC 1RC TLOW CONTROL VALVES PURGE GENERATOR Or !!YDROGEN

' MAIN WRDINE GENERATOR Orr WRNING GEAR El!UTDOWN REACTOR .

COOL REACTOR TO LESS TilAN 135 PSIG l

! COOL RT.ACER TO COLD Sl!UTDOWN l

TURD 1HE GENERATOR FIRE PROTECTION SYSTEM, OUT OF SERVICE MAIN TURBINE, REMOVE HEAT DETECTORS l REACE R WATER CLEANUP llEAT EXCilANGER CAPACITY TEST DEWATER EAST CONDENSER WATERBOX DEWATER WEST CONDENSER WATERilOX Sl!UTDOWN llEATER DRAIN SYSTEM

.IDENT1rY HEATER DRAIN. CONDENSATE,rEEDWATER O!L LEAKS PRE TLUSit-SURVEY, LOW PRESSURE CORE INJECTION 'A' '

PERFORM PRE MAINTENANCE !!YDROGEN COOLER LEAK CilECK UNIT AUX 1LIARY TRANSTORMER OUT Or SERVICE REMOVE MAIN GENERATOR LINKS

• MA1H POWER SYSTEM MAINTENANCE DIVISION 111 OPEN '

EXTRACTION STEAM MAINTENANCE PERTORM MAIN POWER TRAN$rORMER 1E & IW DELUGE TEST PERFORM LOW PRESSURE COkt 1HJECTION ' A' TLUSit PERTORM REACTOR CORE ISOLATION COOL 1HG llEAD SPRAY TLUSil SIRJTDOWN CIRCULATING WATER SYSTEM ,

PULL VACUUM TO PLUG WDE LEAKS S!!UTDOWN WRBINE DRIVEN REACTOR TEED PUMP PLACE MOTOR DRIVEN REACTOR TEED PUMP IN 110T STANDllY TEEDWATER SYSTEM MAINTENANCE--

WRBINE DRIVEN REACER TEED PUMP B MAINTENANCE SHUTDOWN Orr GAS SYSTEM.

Orr GAS SYSTEM MAINTENANCE TRANSTER A RHR SifUTDOWN COOLING TO D Ri!R TURDINE LUBE OIL SYSTEM,.!!ANG PARTIAL 005 REMOVE DRYWELL llATCilES

. PRIMARY CONTAINMENT MAINTENANCE REACTOR RECIRCULATION SYSTEM MA1HTENANCE REACTOR DUILDING CLOSED COOLING WATER MAINTENANCE REMOVE Sil! ELD WALL REMOVE TURBINE GENERATOR VIBRATION DETECTORS CIRCULATING WATER SYSTEM MAINTENANCE ,

i

,,- a, - , - ~ . . - , _ - . , , , - _ . ~ - , . , - - - - ... _ ,- . ,--,n,-,.r,,,,-n~

,-,a . - - - . , , - , .

l APPENDIX A CRITICAL PATil ACTIVITY REFUEL OUTAGE (LIR04)

DESCRIPTICE CONDENSER TUDE LEAK PLUG / INSPECTION OUT or SERVICE LOCATE & PLUG C04DDISER TUBE LEAKAGE OPEN WEST CONDENSER WATERBOX MANWAY OPEN EAST CONDENSER WATERBOX MANHAY PIN llEATER DRAIN SYSTEM llANGERS SIIUTDOWN CONDENSATE, CQ4DENSATE D00 STER SYSTEM CONDENSATE, CONDENSATE BOOSTER SYSTEM MAINTENANCE DIESEL GENERATOR D MAINTENANCE MAIN TURBINE GENERATOR OUT OP SERVICE TAGGING COMPLETE l WRBINE GENERATOR MAINTENANCE MAIN TURBINE GENERATOR POST CONDENSER. VACUUM MAINTENANCE REMOVE THE A LOW PRESSURE TURBINE A & D COUPLING COVERS REMOVE MAIN WRBINE GENERATOR DELUGE PIPING DRAIN REACTOR WATER CLEANUP SUCTION REMOVE I 3 & 4 TURBINE BEARING COVERS A LOW PRESSURE TURBINE. BREAK A & B COUPLINGS FAB AND INSTALL TrMPORARY PIPING, REACTOR WATER CI.EANUP SYS CONDD4SER TUBE INSPECTION BREAK VACUUM ATTER CONDENSER TUBE INSPECTION LOCAL LEAK RATE TEST VALVES 1G33.r001/IG33.r004 RESTART REACTOR WATER CLEANUP USING TEEDWATER INJECTION REACTOR RECIRCULATION SYSTEM LOOP 'A' MAINTENANCE f

A LOW PRESSURE AIRBINE. A & D COUPLINGS ALIGNMENT CllECKS A LOW PRESSURE TURBINE.RD40VE EXilAUST llOOD 25KV ISO PNAS*. BUS DUCT MEGGER ATTER LINK REMOVAL REMOVE TURBINE GENERATOR INSTRUMENTATION A LOW PRESSURE TURBINE. REMOVE UPPER INNER SIIELL l DRAIN CONDENSATE BOOSTER SYSTEM TOR MAINTENANCE LOW PRESSURE HEATER STRING OUT Or SERVICE DRAIN LOW PRESSURE HEATER STRING CONDENSATE SYSTEM OUT Ol' SERVICE CONDENSATE BOOSTER SYSTEM OUT Or SERVICE

. DRAIN llEATER DRAIN SYSTEM llEATER STRINGS IIEATER DRAIN SYSTEM MAINTENANCE A LOW PRESSURE TURDINE.HEMOVE UPPER DIAPilRAGMS A LOW PRESSURE TURBINE. ROTOR CLEARANCE CllECKS DRAIN !! EATER DRAIN SYSTEM TANK IIEATER DRAIN SYSTEM OUT OF SERVICE A LOW PRESSURE TURBINE. REMOVE ROTOR A LOW PRESSURE TURBINE. REMOVE LOWER DIAPNRAGM PIN CONDENSATE BOOSTER SYSTEM NANGERS PRIOR TO DRAINING A LOW PRESSURE WRBINE. LOWER DI APilRAGM REPAIRS DRAIN CONDENSATE SYSTEM REMOVE PRONT S*?ANDARD INSTRUMENTATION REMOVE WRNING GEAR COVER A LOW PRESSURE TUR111NE. LOWER CASE INSPECTION / REPAIR A LOW PRESSURE WRBINE.I:1 STALL LOWER DIAPilRAGMS I A BUS DUCT FAN CUT Or SERVICE

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

• APPENDIX A CRITICAL PATil ACTIVITY RETUEL OUTAGE (L1R04)

................................................................................................ l DESCRIPT104 1$C LOW PRESSURE NEATER LEAKAGE 1CWOO6A CW PUMP DISCllARGE VALVE IIYDROLAZE SOFT SEATS IUR.TS002 WRDINE EXilAUST/TEMPERAWRE RECORDER READING 111G11 i SilATT VOLTAGE DETECTOR ERRATIC MAIN WRl11NE GENERATOR ON WRNING IEAR ALT COLLECTOR RING REFURillSIIED BY VENDOR PILL CIRCULAT1HG WATER SYSTEM ICWOObB CW PUMP DISCllARGE VALVE, ifYDROLAZE Sort SEATS PIN CONDENSATE SYSTEM llANGERS PRIOR TO DRAINING SYSTEM ALT COLLECTOR RING RETURBISil, INSTA1.L COMPLETE CIRCULATING WATER SYSTEM MAINTENANCE STARWP & OPERATION OF CONDENSATE SYSTEM REPLACE EXCITER tlEAT SENSOR i WRBINE BEARING AREA TIRE PROTECTION SYSTEM TUNCTIONAL TEST STARWP CIRCULATING WATER SYSTEM 1HR179 RBCCW SUPPLY TO DRYWELL FAILED AIR LEAK RATE TEST COMPLETE WRDINE DRIVEN REACTOR TEED PUMP B MAINTENANCE ,

COMPLETE REACTOR RECIRCULATION SYSTEM LOOP 'A' MAINTENANCE COMPLETE REACTOR RECIRCULATION SYSTEM MAINTENANCE COMPLETE REACTOR BUILDING CLOSED C1 jig WATER SYS MAINTr.NENANCE RESTART REACTOR RECIRCULATION SYSTEM PUMPS DRYWELL CLOSEOUT REPLACE IPCM111 DRYWELL PERSONNEL ACCESS HATCl!

. ICD 002A 1A CONDENSATE PUMP DISCilARGE VALVE TAILED TO CLOSE ,

SERVICE AIR O. RING LOCAL LEAK RATE TEST CLEAN CONDENSATE O. RING LOCAL LEAK RATE TEST LOCAL LEAK RATE TEST VALVES ISA042/ISA046

. LOCAL LEAK- RATE TEST VALVj:S 1MC027/1HCO33 DRYWELL TO SUPPRESSION POOL BYPASS LEAK TEST DRYWELL PERSONNEL AIRLOCK LOCAL LEAK RATE TEST REMOVE DRYWELL CLEAN CONDENSATE SPOOL PIECE REMOVE DRYWELL STATION AIR SPOOL PIECE REACTOR REC 1RC SYS TLOW CONTROL VALVE OPERABILITY TEST ALTEREX CO2 FLOW TEST ICB018D ID PUMP MTV AIR DIAPilRAGM BLOWING AIR 1CR-GC001 GC COND METER NOT ADVANCING & INKING '

IES001 A EXTRACTION STEAM TO ll!GH PRESSURE IIEATER 16A PROBLEMS IB DIESEL GENERA'10R TRIP DIVISION 3 GROUND DETECTION PROBLEM IDV060A 16A HIGli PRESSURE IIEATER VENT VALVE PACKING LEAK DRYWELL PERSONNEL ACCESS !!ATCH LOCAL LEAK RATE TEST DRYWELL PERSONNEL ACCESS !!ATCil INTERLOCK TEST-DRYWELL CLOSEOUT AFTER OUTAGE j 1 A BUS DUCT FAN AND DAMPER INSPECTION HODE SWITCil TO STARWP PULL CONTROL RODS TO CRITICAL COMMENCE HEATUP AND PRESSURIZATION

^

START UP GLAND STEAM AND llOGGER

-1LT-TE004 OFT GAS PRESS DRAIN TANK LEVEL TRANSMITTER PRODLEMS

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

+

APPEND 1X A CRITICAL PATil ACTIVITY REf~UTL OUTAGE (L1R04)

DESCRIPT!Q1 PDT.1N62-NO31 Orr GAS ATTER r!LTEk DP TRANSMITTER READS ll!GN ILT.llD0lb AIR SUPPLY TO LEVEL TRANSMITTER, AIR LEAK 1rWO1KB WRB DRIVEN REAC FEED PUMP WRNING GEAR ENGAGED 1rWOIKB TURB DRIVEN REAC TEED PUMP UNCOUPLE FOR OVERSPEED TEST REACTOR CORE ISOLATION COOLING WRBINE OVERSPEED 6 150 PSI DRYWELu PERSONNEL ACCESS IIATCil LOCAL LEAK RATE TEST  ;

VER1rY SATISTACTORY CQiD17101 Or CONDENSATE POLISitER BEDS  ;

RECOUPLE REACTOR CORE ISOLATION COOLING TURBINE l CLEAR OUT Or SERVICE ATTER RCIC WRBINE IS RECOUPLED 1 START UP MOTOR DRIVEN REACTOR TEED PUMP (300 PSI)

$00PS1 EMERGENCY CORE COOLING SYTEMS PERMISSIVES CLEAR MAIN STEAM ISOLAT104 VALVE SCRAM TUNCTIQ4AL TEST REACTOR CORE ISOLATION COOLING PUMP OPERAli1LITY TEST REACTOR PRESSURE >600 PSIG ON STARWP SAFETY RELIEr VALVE MANUAL CYCL 1HG TEST PROCESS COMPUTER NUCLEAR PROGRAM CllECK REACER CORE ISOLATIQi COOLING INSERVICE TESTING SYNCHRONIEE GENERATOR TO THE GRID CONTROL ROD DRIVE SCRAM TIME TESTING INCREASE POWER ADOVE 25'.

t

APPEN01X B RETUELING OUTAGE (L1R04)

SAFETY RELATrD CORRECTIVE MAINTrNANCE

---

UNIT =0 --------- -----------------------------

WRNUM SYS EPH DESCRIPTION L01987 DG ODOO2T 0 DG TUEL DAY TANK MANWAY COVER LEAKING L01994 DG ODG01P Si1M CNTROL SWITCH CLEAN AND INSPECT 9 iPM01J LO3661 DG OD001P O DG TOTP 11 EARING REPLACED LO5752 DG OTSil-DG048 DG LUDE OIL TF.MP LEAKING FLU 1D LO5762 DG OTI-D0062 DO O ENG JACKET WATER TEMP WILL NOT CALIBRATE

---

UNITal-----------------------------------------

WRNUM SYS EPH Dr.SCRIPTION L00533 RH 1E12-706BA RIIR WS llX OUTLET FAILED 'IT) CLOSE LOO 931 PC LS-1E22-H002A SUPP POOL LEVEL 111 ALARM NOT UP L00932 MS 1D21-r421C VALVE AIR LEAK AT DIAPHRAGM LO1063 RI IE51-r008 RCIC SfEAM VAINE PACKING LEAK L01436 RD 1C11-D001-026 RF. PLACE HCU 26-39 PER LMP-RD-14 001437 RD IC11-D001-075 REPLACE IICU HAN!roLD 11 RIVE WTR SilPPLY r!LTER LO1438 RD 1C11-D001-010 REPLACE IICU HAN!rOLD DRIVE WTR SUPPLY FILTER

. 001624 RD 1C11-C001A A CRD PUMP REBUILD LO1767 DG 1E22-8001 -N 1D DG COOLER ADD PROTECTIVE COATING LO1959 Ril 1E12 r085D WATER LEG DISCllARGE CHECK VALVE STICK!i LO2041. RD IC11-D001-103 110U 54-47 LEAKS EXCESSIVELY AT N2 CilARGING N1PPLE LO2046 AP 1AP21E 136X COMPT 302A INSULATION DAMAGE LO2098 Ril IE12-B001A RilR NX DP IS LOW MAY IND DAFFLE PLATE LO2122- RD 1C11-D001-108 HCU 54-47 REPLACE ACCUMULATOR LO2123 RD: 1C11-D001-053- IICU 06-27 REPLACE ACCUMULATOR LO2124 RD 1C11-D001-184 HCU 38-07 REPLACE ACCUMULATOR

• LO2125 RD IC11-D001-183 IICU 42-07 REPLACE ACCUMULATOR

- LO2126 RD 1C11-D001-060 11CU.10-23 REPLACE ACCUMULATOR '

L02127 RD 1C11-D001-059 IICU 14-23 REPLACE ACCUMULATOR LO2128 RD IC11-D001-048 HCU 26-27 REPLACE ACCUMULA'IVR ,

- LO2354 MS 2D21-1DSrV-2 1B 2ND STAGE MSR-STEAM LEAK LO2079 LP 1AP04E LPCS TEED PUMP DREAKER CRACKS -

LO2802 RI PDS-1E31-N013BA RCIC ISOL DP SW MANITOLD REPLACE g LO3118 RD IC11-D001-017 HCU 10-47 EXCESSIVE TIME TO DRAIN AND CHARGE LO3176 MS IB21-MOVCA-4 MSR DRAIN STOP VALVE PACKING LEAK L03215 AP 1AP83E 1833-r023 D DACKUP DKR 136Y DROKEN INTERLOCK LO3550 RD 1C11-38-35 CRD REPLACE DRIVE

-LO3551 RD - 1C11-34-55 CRD REPLACE DRIVE LO3552 RD IC11-30-47 CRD REPLACE DRIVE LO3553 RD 1C11-30-43 CRD REPLACE DRIVE LO3554' RI 1E51-r045 RCIC STEAM SUPPLY LEAKING DY WilILE SYS ,

LO3610 RD IC11-D001-039 'llCU 02-35 2 ALARMS IN LESS TilAN ONE WEEK LO3933 1RM RY-1C51-K601r F IRM CilATTERING OFF Or DOWNSCALE LO3953 MS FZ-ID21-L903 ID21-RSHL V-1 2ND STG HIGil LOAD itEGAN CYCLING O/C LO4008 MS- Ill13 -P64 2 MS TUNNEL DT RELAY IH21-K38 DID NOT TIME OUT b

r-.-r,-.m-r.,,w_--.,m-, m y- - -,,,,,.c. ,,_c,- .,y..,_,.-n.,.._.,,.,,,,, ,,.n,%w-wv...%..r, -., , . * --w -ry,rew w e- v-

AFPENDIX T1 RETUELING OUTAGE (L1R04)

SAFETY RELATED CORRECTIVL MAINTENANCE

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~~---------- UNIT =1 -------------- --- ----------------------

WRNUM SYS EPH DESCRIPT104 L04194 MS ID21-T418B MS TO AS ALARM SiloWS NOT OPrN L04232 RD 1C11-D001-006 NCO 30-59 EXCESSIVE WATEd ALARMS LO4233 RD 1C11-D001-091 IICU 22-03 EXCESSIVE WATER A1, ARMS LO4243  !!G 1110001B 112 RECOMB INDD INLET REPLACE SPRING PACK 004424 MS PS-1821-H015C MS LINC LOW PRESS SW LEAKS DY LO4477 RD 1C11-D001-175 REPLACE WATER ACCUMULATOR LO4478 RD 1C11-D001-178 REPLACE WATEk ACCUMULA*1VR LO4479 RD 1C11-D001-052 REPLACE WATER ACCUMULATOR LO4480 RD JC11-D001-168 REPLACE WATER ACCUMULATOR LO4481 RD ICAJ-D001-129 REPLACE WATER ACCUMULA7VR LO4482 RD 1C11-D001-080 REPLACE WATER ACCtfMul.ATOR LO4483 RD 2C11-D001-011 REPLACE WATER ACCUMULATOR LO4484 RD 1C11-D001-135 REPLACE WATER ACCUMULATOR LO4485- RD 3C11-D001-050 -REPLACE WATER ACCUMULATOR ,

i LO4655 LC 1E32-r008 OUTBOARD MSIV t,GS NO CONTROL POWCH LO4885 MS RIY-1D18-K610A MS 111 RAD MONITOR KEY 110ARD 1,0CKED  ;

LO4892 HP 1C71-AK0100 14 TSV SCRAM RELAY !!UMMING NOISE l LO4929 DC IJY-DC040 POWER SUPPLY 250 VDC INST NO OUTPUT LO4976 RD 1C11-34-23 CRD REMOVE CRD MECilANISM TROM 34-23 LO4977 RD IC11-46-31 CRD REMOVE CRD MECilANISM FROM 46-31  ;

, LO4978 RD 3C11-54-35 CRD REMOVE CRD MECllANISH r't0M $4-35 LO5245 DC 1E22-S001 DIV 111 DATI CELT,3 9 AhD 16 LOW GRAVITY l LO5380 RD IC11-D001-107 ACCUM 38-11 DRAIN VALVE LEAK 1HG BY  ;

, LO5408 RD TR-1C11-RO18 CRD 34-55 POS IND PRODE T/C OUTPUT !!AD LO5460 RN 1 E'L 2 -T05 2 A STEAM LINE 150L VALVE INSTALL SEAL-IH TSC LO5490 DG. 1.E2 2 -r 377 A 1B DG PRESS .'EG REPAIR TUBE r!TTING LO5520 MS IB21-F019 MSIV LINE DRAIN OUTBOARD PACKING BLOWING LO5541 LPRM 1HR000 LPRH 16-57A NO DOWNSCALE LITE UP ON BACK PANEL 005543 PC IPC001C PC VACUUM DifKR TAILED LLRT OUTBOARD FLANGE 7 L05553 RD IC11-0 7 -4 3 02-43 CRD MECilANISM REMOVE / REPLACE /REDUILD LO5558 MS IB21-T067h MSL DRAIN VALVE FAILED LLRT L05559 MS 1821-r067A MSL DRAIN VALVE TA! LED LLRT L05571 RH TRS-1E12-R601 RNR TEMP RECORDER ALARMING AT 140 DEG r '

L05599 RP 1C71-S003B RMS MG tiET REPLACE CIRCUIT 110ARD IN RELAY L05619 MS 1821-T019- MSL DRA1H VALVE (OUT!i0ARD) ADJ LIMITS .

L05633 RD 11113-P801 RELAY IC22 K1' DEFECTIVE LOS684 RI 1E51-r084 RCIC TURD VACbOM BREAKER LEAKS BY SEAT LOS685 RI- 1E51-r028 HCIC VAC PUMP DIScil ISOL VALVE FAILED LLRT

( LOS686 1RM RY-1C51-K69 d IRM C REPLACE TAULTY IHOP INHIBIT SWITCH ,

l- -LOS693 MS MS01-1314S MISSING NUT THOH P!PE CLAMP LOAD DOLT

[ LD5695 MS MS01-1240S MISS!NG NUT FROM PIPE CLAMP LOAD BOLT LO5717 Ril 1E12-r041A EllR TEST CIIECK VALVE WILL N0'I OPEN & CLOSE l LO5755 HP 1AP07E 1E22-C001 HPCS PUMP BREAKER CilARGING MTR DAMAGED L05756 RN 1H13-P629 1E12-K98A1 DEGRADED VOLTAGE RELAY LEADS REVERSED L05776 R' 1E51-l'004 BARO CONDENSER COND PUMP llAD OPEN IND LO5777 .. 8 1821 f381 EXCESS rLOW CilECK WOULD NOT OPEN OR CLOSE LO5778 NH 1821-r367 EXCESS Ft,0W Cl!ECK WOULD NOT OPEN OR CLOSE l

a APPENDIX 11 RErVELING OUTAGE (LIR04)  !

SAFETY RELATED CORRECTIVE MAINTENANCE

---

UNIT =1 ------------------ ----------------------

WRNUM SYS EPN DESCRIPTION i

LO5780 RI Ill13.P601 1E51-C004 ItARD CONDENSER COND PUMP HEPLACE LIGitT [

L05786 AP 1AP07E DOS 143 RUSE IIOLDERS REPLACE IN CUD 1 & 3 LO5798 IIP 1E22-r341 IIPCS LEVEL SWITCil CllECK DID NOT RESET  ;

LD5799 NP 1E27-r342 SUPP POOL LEVEL CllECK DID NOT RESET LO5813 RI FIC-1C61-R001 RCIC FLOW CONTROLLER LOOSE LO5847 PC 1PC001C PRI CONTAINMENT VACCUUM BKR DETERM AND REMOVE L05855 AP 1AP75E-E5 MCC 135Y-1 CUD E5 DOOR INTERLOCK DROKE L05858 11 0 ING001A DH UPSTREAM INLET STOP VALVP. FAILED LLRT LO5859 AP 1AP75E 135X-3 Cull D3 FITTED L DURNED MOLDED CASE IIREAKER LD5869 AP 1APO4E AO OVERCURRENT RELAY TAILED TO TULLY DROP TRIP l LO5879 MS 1021-000 D MSR REPAIR DOTTOM OF PANEL '

LO5887 DG ITSil-DG04 8 DG LUBE OIL TEMP CAPILLARY WDC BROKE L05888 DG 2DG01K 1A DG DROKEN WELDS ON COVER TOR EXCITER  ;

LO5889 DG 1TS-DG041 DG HIGil WATER TEMP SWITCil CANNOT CALIDRATE LO5903 DG IDG01K DG MANITOLD COVER WELD TRONT EXil MANITOLD L05904 Ril 1E12-T041D (D) RilR TESTABLE CllECK VALVE LEAKING LO5908 DG 175-D0040 DG IMMERSION llEATER SWITCil WOULD HOT WORK LO5909 Ril 1E12-r0$0D SDC RE7 URN TEST CllECK VALVE LEAKS LO5910 Ril 1E12-T099B SDC RETURN TEST CllECK EQUAL VALVE SEAT LO5934 MS MSO4-1391S REPLACE SNUUllER DUE TO filGli DRAG LO5938 RH 1E12-r359B EXCESS FLCH CllECK VALVE TAILED l

L05939 Ril 1E12-7359A EXCESS FLOW LuK VALVE FAILtD i LO5951 RD LT-11121-N400D RX WATER ARI LEVEL XMITTER LEAKING LO5970 PC 1AP96E DW ElEC PENE E6 PRESS DECREASED 11ELOW ALERT LIMIT L05972 DC 1DC06E MCC 121Y CUD 7B INSULATION NOT CRIMPED L05973 DC IDC00E MCC 121Y CUD 3C INSULATION NOT CRIMPED

- LO5976 MS MS01-1329S SNUDDER ON LINE IMS01DA CLAMP LOOSE l -LO5977 MS MS01-1320S SNUDDER FOR LINE IM501DD28 IIEX NUT l LO5979 MS MS01-133BS SNUDDER FOR LINE IMS01Dil MISSING llEX NUT LO5999 DO TS-1E2*oN516 IIPCS D/G ENGINE TEMP SWITCll FAILED LO6034 RD LS-1C11-N211 IICU 10-51 LOOSE SEALTITE LO6069 RH 1AP83E 1E12-r004C POWER CABLE 1Rl1037 SLICED INSULATION L06073 AP 1AP11E SWGR 131X FAULTED DUE TO MELTING SNOh DRIPPING L06088 Ril 1E12-r011A IIX DRAIN VALVE CYCLE IN 21.7 SECONDS LO6089 NA 1D13-D003 RX STEAM DRYER CRACKED WELDS ON DRYER LO6107 DC ILL28E ELC I 142 BATTERY GROUND CAME UP WilEN AC WAS Orr

i. LO6125 MS 1D21-r016 MSL DRAIN VALVE LOOSf: PACKING GLAND 006148 RD IC11-D001-073 11C0 22-15 AIR BLOWING OUT OF 1/4" llOSE LO6151 PC ILV94E D/W PENETRATION READS 0 PSIG, SilOULD READ > 15 ,

LO6160 Rll IE12-B001D RilR IIEAT EXCllANGER CORRODED LO6166 TIP INR000 TIP TUBE SUPPORT EEOKEN WEl,D 006168 RD IC11-D006- SCRAM AIR SUPPLY TILTER LEAKING AIR LO6170 RD IC11-000 NCU 18-15 DIRECT CONTROL SOLENOID COVER HISSING L06178 AP IEl-AP038A RELAY DUS UV PROTECTION SETPOINT DRIFT LO6189 RI 1E51-r361 RCIC EG-R ACTUATOR INSPECT & CLEAN L06191 DG 1E22-S001 1D DU COOLING WATER !!X WATER LEAK AT FLANGC LO6192 PC 1PC000 U1 DRYWELL ELECT PENE RECilARGE E-20, E-11 & E-4

, - . _ . - _ - - _ , . _ .,._ -,w-- -.-.- - , . . . . - .a

APPENDIX B REf'UELING OUTAGE (L1R04)

SAFETY RELATED CORPECTIVE MAINTENANCE ,

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. UNIT =1 ----------------------------------------- .

WRNUM SYS EPH DESCRIPTION LC6213 DG 1D0000 DEVICE K-33 TIMER CONT \ CTS FAILED; REPLACE K-33 LO6216 Ri! 1E12-B001A Ri!R ltX REPAIR ERODED BArrLE PLATE LO6218 RH FC13-1401A REMOVABLE SECTION INTERFS W/STUrrING BOX LO6246 AP 1AP12E SWGR 131Y CUH 204B LEAKING OIL  !

LO6247 AP 1AP12E SWOR 131Y CUB 204C CRACKED CONTACT BLOCK LO6266 RD IC11-000 11C0 38-31 CilARJE WTR VALVE LEAKS BY LO6301 DC IDC14E CHARGE CELL 642 DIV 11 BATTERY LO6311 RH 1E12-r049B LEAKGE TOUND i LO6333 RD 1C11-000 llCU 38-23 STUCK OPEN 006360 DC IDC06E HCC 121Y CRACKED INSULATOR IN BACK PANEL LO63be RH 1E12-r090A BROKE, H/W SPINS BUT NO MOVEMENT 3 LO6377 DG 1E22-r361B D/G BYPASS RELIEF LEAKS LO6378 DG 1E22-C302B D/G AIR COMPRESSOR ADJUST SET POINTS LO6379 DG 1E22-C302B D/G (B) AIR COMPRESSOR LEAKS

- LO6392 RD 2C11-D001-122 L'U 58-31 LITTLE FLOW WilEN VENTING LO6393 RD IC11-000 HCU 38-31 LEAKS N2 AROUND STEM INST BLOCK VALVE =

LO6394 RH IE12-r004A RHR SUP POOL SUCTION VALVE NO INDICATION LO6406 RH 1E12-AS003A RHR PUMP START LOGIC BAD LO6411 RH IE12-r027A SUPP POOL SPRAY PACKING LEAK WHEN OPEN  !

L06412 Rif PS-1E12-NO32A RHR REC 1RC PRESS REPAIR OR REPLACE

• LO6426 VY ITI-VYO15 1A RHR DUCT TEMP INDICATION READS ABNORM HIGH LO6431 Ril 1E12-r074B 1B RX VENT VALVE POSITON INDICATION SPORADIC -

LO6434 NB IC22-N701D MASTER TRIP UNIT Cil 1D WIRE LOOSE LO6435 RP 1RP000 CABLE 1RPO42, 44 & 43 DAMAGED AND BRITTLE CABLES LO6441 Ril 1E12-r009 SDC INBOARD ISOL VALVE WON'T CLOSE LO6443 MS 1821-r067D D MSL DRAIN VALVE TORQUE SW SETTING LO6502 -RD IC11-D001-044 IICU 10-31 REPLACE AIR LINE CONNECTION I LO6519 HP 1E22-r004 HPCS INJ VALVE OPEN SEAL-IN RELAY BROKEN I

LO6520 DG 1E22-S001 IB DG BINDS UP FUEL RACK ON START LO6524 Ril 1E12-r009 SDC SUCT INBOARD ISOL TRIPPED LO6526 RH IE12-r053A SDC RETURN SET LIMS Orr BACKSEAT LO6532 MS 1821-r019 INBD MSIV DRAIN ISOL VALVE FAILED LLRT LO6541 MS IMS93AB PIPE SUPPORT NEAR U1 MSV-1 ilANGING LOOSE LO6546 RD 1C11-D001 IICU 14-07 N2 LEAK AROUND STEM ON 111 VALVE l LO6550 HG 1HG018 HG CROSS-TIE RETURBISH LIMITORQUE OPERATOR L LO6551 MS ZS-1821-r022B (B) I/B MSIV LIMIT NOT RESETTING LO6552 MS - 1B21-r016 MSL DRAIN VALVE INSPECT OPERATOR, TEST SPRING PACK LO6564 HG 1821-r028D OUTBOARD HSIV AIR LEAKS AT FITTING LO6568 IRM RY-1C51-K60111 IRM H IND READING llIGHER THAN NORM LO6569 MS 1821-r028A OUTBOARD MSIV CLOSURE SCREW BROKE Orr LO6570 MS 1821-r022B INBOARD MSIV INDICATION LOST WilILE OPENING B MSIV LO6571 MS IB21-r022D INBOARD MSIV AIR LEAK DETWEEN SOL l LO6572 MS 1821-r022B (B) IB MSIV AIR LEAKAGE BETWEEN SOL LO6573 MS 1821-r022C (C) IB MSIV AIR LEAK BETWEEN SOL LO6576 DG 1E22-5001 DG SOAKHACK PUMP FAILED TO START LO6591 RD IC11-000 CRD ACCUMULATOR PACKING LEAK, REPL V. LVE PACKING LO6594 RH IE12-r090B RilR SPC RETURN WILL NOT OPEN

+'s - - - -

.c,,,,ev- ym,,w,-,r-n,,v--,--.-,..----w-.. w .-v.w.w..n-.w,w -~w-rr-w,-,-,w.-,,--,:,-e-.-m-,-m, ---------,m._, --,,*-ce-im,.v.y+- , ,

. . APPENDIX D REFUELING OUTAGE (L1R04)

SAFETY RELATED CORRECTIVE MAINTEN ANCE

---

...------------.----.,-.-----.----------- UNITal -----------------------------------------

WRNUM SYS EPN DESCRIPTION L06597 RH TE-1E12-NO31 RHR FLUSH TO RW BROKEN FLEX CONDUIT LO6598 MS IB21-F028 OUTBOARD MSIV ACTUATORS LEAK LO6633 RD IC11-D001-080 22-11 SCRAM AIR SOL MOUNTING BOLTS LOOSE LO6677 RI 1E51-F045 RCIC STEAM SUPP STOP VALVE WILL NOT DECLUTCH LO6682 RD IC11-D001-171 HCU 42-15 CRD INSTR BLOCK STOP 111 ' f LEAKS LO6683 RD. IC11-000 ACCUM 50-31 All VLV LEAKS BY WHEN BACKSEA~ED LO6746 DC 1PA03J DIV I GROUND COMING FROM 2PA03J IN AEER LO6808 VY l'fS-VY004 LPCS/RCIC CUB COOLER FAN LOOSE CONNECT LO6844 DC 1EY-DC044 250 VOLT CHARGER AMMETER DOES NOT WORK LO6855 RP IC71-K8B IC71-K88 TCV FAST CLOSURE RELAY FAILED LO6952 RI 1E51-C004 1E51-C004 RCIC COND CONDENSATE PUMP BRUSHES WORN LO6956 RM .1C11-D001-013 HCU 26-47 TRIPS RMCS LO7000 RI TI-1E51-R904 RCIC TURBINE VAC TANK UNABLE TO CALIBRATE LO7006 NR INR000 ROD BLOCK MON FAILS WHEN SETTING FROM LO ROD BLK LO7015 RP 1RP000 RPIS FULL CORE DISPLAY COOLING FAN LO7016 RI 1E51-F063 INBCARD STEAM ISOL VALVE CAL C-CLAMP DAMAGE LO7060 MS IB21-2BSFV-2 MSR BLANKETING VALVE DUAL INDICATION LO7061 MS IB21-?BSFV-1 MSR BLANKETING VALVE DUAL INDICATION LO7062 MS IB21-1BSTV-2 IST STAGE MSR DUAL INDICATION LO7084 .LC FT-1E32-N053E LC BLEED OFF INSTALL, NEW FLOW TRAN LO7087 HP 1E22-C003 HPCS WATER LEG PUMP HIGH VIBES, REPLACE BEARINGS LO7104 AP 1AP27E SWG R l'a h BENT METAL BRACKFT ON SLIDING BREAKER LO7118 RH 1E12-F047B RHR HEAT EXCHANGER INLET PACKING LEAK LO7123 DG 1E22-8001 REPL 1B DG K1 HFA. RELAY & K8 AGASTAT TIMER LO7189 RD IC11-D001-143 CRD 42-31 SCRM VLVS OPENED RPS CH B TRIPPED LO7190 RI 1E51-F045 RCIC STEAM SUPP INLET ISOL BULB SHORTED LO7197 MS 1B21-F507 TEST VALVE FOR NDH-RET CK BLOWING AIR LO7200 .NB LPR-1821-R884 RX WIDE RANGE PRESS / LEVEL REC INOP LO7227 HG IHGFV1 H2 RECOMB INLET MOV NO FULL' OPEN IND i LO7228 DG 1E22 R001 IB DG ENGINE TRIP /DIV 3 GRND DET PROBLEM LO7266 RI 16I000 RCIC 1 URB TRIP LOGIC LOW RX PRESS RCIC ISOLATION LO7289 DG 1E22-S001 IB DG GOVENOR RUN SOL OUT OF ADJUSTNENT l

LO7305 DG 1E22-S001 IB D/G SPEED GENERATOR, VERIFY OPERATES LO7311 RH PDI-1E12-N029B RHR 18/1C LINE INTER MON SW ALARM L LO7366- RD 1C11-D001 HCU 54-23. LEAKING TUBE FITTING ABOVE 116 AIR VLV LO7408 RI 1E51-F045 STEAM SUPPLY VALVE PACKING LEAK LO7555 MS IB21-F022B INBOARD MSIV B CLOSED INDICATION

< L74194 RD IIA 000 AIR STOP TO 1C11-K001 308 REGULATOR.

L79939 RH 1E12-F369A RHR SUCT H.P. VENT VALVE DOESN'T OPEN L80708 LPRM RE-1B13-D193AJ LPRM 40-41D FAILED TEST L88969 RH 1E12-F076B IB EHR HX DRAIN UPSTREAM STOP VALVE LEAKS L91552 RP 1C71-8001B OVERVOLTAGE RELAY RPS M-G EET B RESET L93018 RP 1C71-S001B OVERVOLTAGE RELAY, B RPS MG INOP L93019 RP IC71-5001A OVERVOLTAGE RELAY, A RPS MG INOP l L93883 AP 1AP21E SWGR 136X CLAMP BOLT IS DIGGING INTO CABLE JACKET L93932 .t H 1E12-F021 1C RHR TEST RETURN VLV DECLUTCH LEVER L94071 RH 1E12-F053B RHR S/D INJECTION VALVE DECLUTCH LEVER INOP

i 9 APPENDIX B.

REFUELING OUTAGE (L1H04).

SAFETY RELATED CORRECTIVE MAINTENANCE I

---~~------------------------------------------ UNITal -----------------------------------------

WRNUM SYS EPN DESCRIPTION L94596 AP 1AP01E BUS.151 0.V. RELAY FAILED CAL L94730 LPRM RY-1C51-K605DY LPRM 48-41B BENT L95093 NB 1H13-P628 SW 534A WRONG ESCUTCllEON PLATE L95103 NB 1H13-P631 CONTROL SWITCH 1823C-S34B ESCUTCHEON PLATE L95408 LP - 1E21-F005 LPCS INJECTION VALVE LEAKS L95457 NB 1PC000 DRYWELL llEAD REPLACE DRYWELL HEAD BOLTS 36,3',40 L95863 RH' 1E12-C300D RHR SERVICE WATER PUMP INBOARD SEAL LEAK L95909 DC 1ER-DC009 250 VDC GROUND DET TEST CHART PEN IRRATIC L95954 RD 1C11-D001-009 HCU 18-51'OUT ENTIRELY L95982 MS 1821-F076C STEAM LINE DRAIN STOP uALVE PACKING LEAK L95991 LC IE32-F001E VALVE PACKING LEAK L95992 LC IE32-F001J VALVE PACKING LEAK L95995 RD XY-1C11-K946BG CRD 46-19 NO POSITION IF ICATION ,

L96002 MS ITD20C MAIN STEAM CONTROL VALVE LEAK OFF LINE STEAM LEAK

.L96143 TIP IXX000 TIP TUBE SUPPORT REPLACED

- L96246 RI 1E51-F063 RCIC INBOARD-ISOL VALVE STEM LEAKOFF L96249 RH. 1E12-F041C LPCI INBOARD TESTABLE CHECK STEM LEAK L96298 LPRM RY-1C51-K605GH LPRM 48-09A READING DOWNSCALE L96684' MS 1821-MOVCA-3 MSR CROSS-AROUND DRAIN VALVE DUAL INDICATION L97115 RD- IC11-D001-027 CONTROL ROD 22-39 OUT LIGilT. WON'T ILLUMINV!:

L97265 RD XY-1C11-K946EC- CONTROL ROD 18-51 IND HAS NO POS AT 46 (IND XX) l L97274 MS 1B21-F0228 I/B MSIV llIGH TEMP; STEAM LEAKOFF 9200 L97735 RD 1C11-D001-110 HCU 46-47 WATER ALARMS l'REQUENT L98141 DG. 1E2?-S001 IB DG KVAR METER ADD DECIMAL PTS NUMBER L98475 RD IC11-D001-123 HCU 58-39 HAS HISTORY OF WATER ALARMS

= L99021 'RH 1E12-F011B B HX S*D4 COND STOP TO S.P. SLOW L99126 RH IE12-F085C RHR WATER LEG PUMP STOP CHECK VALVE STICKS L99338 MS IB21-F022B INBOARD MSIV OPENED TOO QUICKLY L99435 RD 1RD000 FULL CORE DISPLAY FULL OUT IND FOR ROD 26-39

. L99772 RD IDC13E REPLACE EXISTING INSTALLED BKR ARI LOGIC L99773 RD 1DC11E REPLACE EXISTING INSTALLED BKR ARI LOGIC L99775- HP 'IAP79E REPLACE EXISTING INSTALLED BKR 1E22-F004 L99842 RD 1011-34-59 REPLACE CRD MECHANISM 34-59 L99843 'RD IC11-22-51 REPLACE CRD MECHANISM'22-51 I

l l

l.

i l

l l

1 i

a . . . , -, - . ~ - -

s -, -- ~~-- , ., ,..,.~..,.,_w. ,,.m_.,, -

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

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

DATE _9.lQ52L_ GENERATOR OFF-LINE _L 5 OUTAGE TYPE: .. Scheduled J LlRQl)

(YYMMDD) (Hours)

REASON: Performance of Turbine Overspeed Trip Test.

CRITICAL ACTIVITY PATHi- Suceerstul completion of overspeed trip test.

CORRECTIVE ACTIONS (DVR/LERI if applicable): N/A RADIOACTIVITY RELEASE / EXPOSURE OVER 10% ALLOWARLE VALUES: None j

SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED: None l

DATE 91101L GENERATOR OFF. LINES 8 hl___ OUTAGE TYPE: _f oIce d_.lLif_141 (YYMMDD) ( flours )

REASON: Manual reactor shutdown due to hydraulle control fluid leakage used for positioning of the IB Reactor Recirculation Flow ,

Control Valve. i CRITICAL ACTIVITY PATil Replacement of the Flow Control Valve actuator.

Calibration of the Electro-Hydraulic valve positioning system.

CORRECTIVE ACTIONS (DVR/LERI if app 1icable):

DVRI 1 2-91-045 LERl 91.f42-00 RADIOACTIVITY RELEASE / EXPOSURE OVER 10% ALLONABLE VALUES: None SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED:

MENUli SYL EPH _DESCRIPlION __

LO7172 MS 1821 2BSFV1 MSR blanket valve control switch loose LO7531 MS IB21-F5038 Valve leakage L10787 RD IC11-C001A Change pump oil L10942 APRM 1C51.R603D APRM/IRM recorder erratic L10953 PC IPCM111 . Personnel access hatch failed to operate

-L10978 NB 1B21-L904 MSR control valve, blown diaphragm L10979 NB IB21.L903 MSR blown diaphragm regulator

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

ATTACHMENT B II.B UNIT SilUTDOWNS (UNIT 1)

DATES._S1101 L GENERATOR OFF-LINE E,l__. OUTAGE TYPE _En tted._1LlII.41 (YYMMDD) (Hours)

REASON: Manual reactor shutdown due to hydraulle control fluid leakage used for the positioning of the IB Reactor Recirculation Flow Control Valve.

CRITICAL ACTIVITY PATil Replacement of the Flow Control Valve actuator Calibration of the Electro-Hydraulle valve positioning system CORRECTIVE ACTIONS (DVR/LERI if applicable): None RADIOACTIVITY RELEASE / EXPOSURE OVER 10% ALLOWABLE VALUES:

DVR4 1-2-91-045 LERI 91-012-00 SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED:

HR_ HUM SYE_ IPR DICCRIPIION LO7172 MS 1821-2BSFV1 MSR blanket valve control switch loose LO7531 MS IB21-F503B Valve leakage L10787 RD 1C11-C001A Change pump oil L10942 APRM 3C51-R603D APRM/IRM recorder erratic L10953 PC 1PCM111 Personnel access hatch failed tc operate L10978 NB IB21-L904 MSR control valve, blown diaphragm L10979 NB 1821-L903 MSR blown diaphragm regulator

-r- .--__m -._m - -*_ - e

ATTACIIMENT D II.B UNIT SHUTDOWNS (UNIT 2)

DATE _.910901_ GENERATOR OFF-LINE _12012_ OUTAGE TYPE _IntredjLZfil).

(YYMMDD) (Hours)

REASON: Manual reactor scram due to Turbine Electro-Hydraulic Control leakage at the 42 Turbine Control Valve.

CRITICAL ACTIVITY PATH: Inspect EHC piping and supports, repair / replace damaged supports and leakage Non-Destructive examination to insure that incipient damage to the system was not present beyond the ident.ified leaks Replace insulath on the Main Steam piping soaked by hydrau'ic fluid

" Jest and replace siesmic supports on the Main Steam system damaged by hydt a::lic fluid CORRECTIVE ACTIONS (DVR/LERI if applicable):

DVR8 1-2-91-0038 LERI 91-010-00 RADIOACTIVITY RELEASE / EXPOSURE OVER 10% ALLOWABLE VALUES: None SATETY RELATED CORRECTIVE MAINTENANCE COMPLETED:

NENUtL SYS LEN __.DEECMP110N LO9907 IRM RY-2C51-K60lH IRM, No -15 VDC from regulator LO9910 MS 2EH000 MSL piping remove and replace main steam line insulation LO9958 MS 2B21-MOVSV-5 Main Steam Line drain valve will not open

'99961 MS 2MS000 Stroke test mechanical snubber LO9962 MS 2MS000 Stroke test mechanical snubber LO9963 MS 2MS000 Stroke test mechanical snubber LO9964 MS 2MS000 Stroke test mechanical snubber LO9991 MS 2ZI-EH920B I4 intercept valve fast acting solenoid LO9998 MS MS01-2869S Replace snubber clamp bolt LO9999 MS MS01-2877S Replace snubber clamp bolt L1000" MS MS01-2856S Replace snubber clamp bolt L1002b IRM EL-2C51-AZOO9D IRM apscale alarm high

4 ATTACHMENT B II.B. UNIT SHUTDOWNS (UNIT 2)

DATE: 910924 GENERATOR OFF-LINE _21hL OUTAGE TYPE: . forsed_.f L2E12)

(YYMMDD) (Hours)

REASON: A reactor scram resulted when an erroneous Turbine Electro-Hydraulic Control overspeed signal caused the Main Turbine Control Valves to close.

CRITICAL ACTIVITY PATH: Investigation into the cause of the scram Repairs to the Electro-Hydraulle Control system Replacement of the Main Turbine Master Trip Scienoid assembly with an improved model CORRECTIVE ACTIONS (DVR/LERI if applicable):

DVR4 1 2 91-0045 LERI 91 012-00 RADIOACTIVITT RELEASE / EXPOSURE OVER 10% ALLOWABLE VALUES: None SAFETY RELATED . CORRECTIVE MAINTEN ANCE COMPLETED:

WRNUM_ SXS EPN DIECRIETlON LO4264 IRM RY-2C51-K6010 2G IRM erratic on ranges 1,2 LO9972 RD 2C11-D001-006 Rod 18-55, sticking 120 or 122 valve after driving L10329 RP 2H13-P603 Reactor mode switch loose L10358 RP 2C71-S003F EPM alternate feed breaker failed L10440 RP 2C71-S003E RPS alternate power supply, unable to set underfrequency L10464 MS 2B21-F022A nboard MSIV limit switch L97868 RP 2C71-S003B MG Set, trouble resetting breaker DATE t_.911Q2L GENERATOR OFF-LINES.31.J_,._ OUTAGE TYPE _.Eorced__(LIE 131 (YYMMDD) (flours)

REASON: A reactor scram was initleted when the Main Turblue tripped due to high vibrations on bearing 86. The cause was attributed to a failed turbine vibration card.

CRITICAL ACTIVITY PATH

Investigation into the cause of the sermn l Replacement of the' Turbine Vibration Card I:

l CORRECTIVE ACTIONS (DVR/LER4 if applicable):

DVRO 1-2-91-0056 LERI 91-014-00 RADIOACTIVITY RELEASE / EXPOSURE OVER 10% ALLOWABLE VALUES: None SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED: None

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ATTACID4ENT C

= i II.B FORCED REDUCTIONS IN POWER GREATER THAN 20% IN DESIGN POWER LEVEL (UNIT 1)  !

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DATE: 910113 OPERATION AT REDUCED POWER: _1(11.4 (YYMMDD) (Hours)

REASON: Air leakage of the 4.Way air valve on the Main Steam Isolation l Valve 1821-F022B. l CRITICAL ACTIVITY PATH: Replace air valve and completion of operational testing.

CORRECTIVE ACTIONS (DVR/LERI if applicable): None i

RADIOACTIVITY RELEASE / EXPOSURE OVER 10% ALLOWABLE VALUES: None SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED:

HENUM_ SYS_ . .EEN DESCRIET10N l LO7582 MS- IB21.F022B-_4 way air valve leaking

=

DATE: _9.11021 OPERATION AT REDUCED POWER: _2443_

-(YYMMDD) (Hours)

REASON: Turbine Control Valve #4 failed to fast close during testing.

. CRITICAL ACTIVITY PATH: Resolution of the Turbine Control Valve problem and completion of operational testing.

CORRECTIVE ACTIONS (DVR/LERI if applicable): None RADIOACTIVITY RELEASE / EXPOSURE OVER 10% ALLOWABLE VALUES: None SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED:

ERNUR_ SYS _.JrN DESCRIEIl0LL L11018 MS IB21-CV4 Turbine Control Valve failed testing l

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ATTACl! MENT C

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

DATE : '._91012.R OPERATION AT REDUCED POWERi 1419.

(YYMMDD) (Hours)

REASON: Scram outlet valve air diaphragm for hydraulle control unit 26-19 was laaking air. The control rod was declared inoperable and was fully inserted.

CRITICAL ACTIVITY PATH: Replacement of air diaphragm and operational testing.

CORRECTIVE ACTIONS (DVR/LERI if applicable): None RADIOACTIVITY-RELEASE / EXPOSURE OVER 10% ALLOWABLE VALUES: None SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED:

NILHUM SYS EPN DESCRIETION LO5793 RD 2C11-D001 064 HCUt 26 19 scram outlet valve leaking air DATE: 910601 OPERATION AT REDUCED POWER: ._15 d_.

(YYMMDD) (Hours)

REASON: Reduced reactor-power level due to reactor coolant high-conductivity caused by maintennnce error.

CRITICAL ACTIVITY PATH: None CORRECTIVE ACTIONS (DVR/LERI if applicable): DVRt 1-2-91 0020 RADIOACTIVITY RELEASE / EXPOSURE OVER 10% ALLOWABLE VALUES: None SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED: None ATE: ._91R9D.6 OPERATION AT REDUCED POWER: 0.8 (YYMMDD) ( flours )

REASON: At 0525, due to a Turbine Electro-Hydraulle Control leak, a unit.

shutdown commenced. At 0615 a manual scram of the unit was initiated,

--CRITICAL ACTIVITY PATH: None

' CORRECTIVE ACTIONS (DVR/LERI if applicable):

DVRI 102091-0038 LERI 91 010-00 RADIOACTIVITY RELEASE / EXPOSURE OVER 10% ALLOWABLE VALUES: None SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED: Nonc i

ATTACitMENT C e

II.B FORCED REDUCTIONS IN POWER GREEATER TH di 20% IN DESIGN POWER LEVEL (UNIT 2',

DATE: .211012 OPERATION AT REDUCED POWER: _2210_

(YYMMDD) (Hours)

REASON: Reduced power level to 650 Mwe due to low suction pressure on the 2B Condensate Booster Pump.

CRITICAL ACTIVITT PATH: Clean suction strainers.

CORRECTIVE ACTIONS (DVR/LERS If applicable)t None RADIOACTIVITY RELEASE / EXPOSURE OVER 10% ALLOWABLE VALUES: None SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED: None DATE: _211R2D OPERATION AT REDUCED POWER: _31,Q_

(YYMMDD) (Hours)

REASON Reduced power level to 730 Mwe due to broken valve stems on Heater Drain Valves 2HD045A,2HD045B and 2HD045C.

LRITICAL ACTIVITY PATH: Replace valve stems and operational testing.

CORRECTIVE ACTIONS (DVR/LERI if applicable): None D

RADIOACTIVITY RELEASE /KXPOSURE OVER 10% ALLOWADLE VALUES: None SAFETY RELATED CORRECTIVE MAINTENANCE COMPLETED: None s

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ATTACHMENT D ot SVRVEY OF CHLORINE SHIFMENT IN.TME VIC1HITY Of LA SALLE COUNTY STATION j l

A. IMIAODUCTION 1- .The 1991 survey of chlorine shipments was conducted during June and July, The discussion which follows updates previous surveys performed in 1975, 1986, and 1988. Potential or actual users of bulk quantities of chlorine within a five mile radius of La Salle station are identified. Also included are the shippers and sodes of transportation of chlorine shipment.

The purpose of the survey is to review the shipment of chlorine by barge on the Illinois River near La Salle station. This information is used to evaluate the need for special protective amasures against chlorine to ensure control roca habitability. The information collected during the 1991 survey is consistent with the previous surveys, and supports the conclusion that no special protective provisions against chlorine are required at La Salle County station.

B. PIGULAT.OEI G21212 The ' applicable regulatory guide is 1.78, " Assumptions f or Evaluat ing the Habitability of a Nuclear Power Plant Control Room During a Postulsted Hazardous Chemical Release." Regulatory Guide 1.95, " Protection of a Nuclear Power Plant Control Room Against an Accidental Chlorine Release," describes types of chlorine releases and methods of protection against those releases.

Position 1 cf Regulatory Guide 1.78 states that chlorine stored or situated at distances greater than five miles f rom the station does not have to be considered in the analysis of control room habitability.

C. CAIGINAL SURVEY f.XELANATIQti The location of the plant and the transportation routes in the vicinity of the site are described in section 2.1.1 of the La Salle County Station Final Safety Analysis Report (TSAR). TSAR section- 2.2.2 describes the industrial facilities, products and materials, pipelines, waterways-located nearby and projections of industrial growth. There are no industries or bulk users of chlorine within a five mile radius of the plant. TSAR section L 2.2.4 briefly describes the uses of the Illinois River in the vicinity of the plant as a waterway.

TSAR section 2.2.3.1 states that the Illinois River is the only I transportation route carrying hazardous material within 5 alles of the plant.

Section 2.2.3.2.c requires that this survey be performed every three years to ensure that a chlorine hasard does not exist. TSAR table 2.2-4 listed the commodities shipped on the Illinois River in 1974. There was no- breakdown on chemical shipments to provide data on chlorine shipments The original survey showed that small quantities of chlorine were .being used by the Illinois Nitrogen Corporation, approximately 5 miles north of the station. There was not enough information available to determine that Illinois Hitrogen was not receiving chlorine shipments by barge. Therefore, in order to expedite the station licensing process, chlorine detectors were installed in the outside air intake of the control room ventilation system.

D. C'lP21HI SURVEY

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ATTACHMENT D e

A current list of active chictine barges in the United States and Canada was obtained f r am the Chlorina Institute, a national trade organisation in the chlorine industry. This is included as Table 1. The Institute is not awars of any bulk users or producers which would utillie the Illinois River as a route of t r ans pc r t ing chlorine. According to the Institute's Vice-President of Storage and Transport, there are no chlorine barges operating on the Illinois River.

Illinois Hit rogen Corpor ation f acilitie s at river mile 248.7 have been taken over by Ra i s e r-E st e ch, Inc. This company was contacted, and it was stated that chlorine is neither shipped nor received by barge at their location. Review of La Salle County records showed no new industries within a five alle radius of the plant. The five mile radius includes a small portion of we ste rnmost Grundy county. Grundy County had no similar records to review, but a physical survey of the area did net show that eny industries were in the area.

Table 0 lists the government agencies contacted. The ne a re st water treatmant facilities, in Marseilles and Seneca, were not contacted in this survey, because a representatve of a larger f acility in H?*ris, which was contacted, stated that a barge shipment of chlorine would be f ar too large a quantity ter t he Mor ris f acility to use or keep on hand. Table 3 shows the baige terminals located between the Mar seilles and Dresen locks. Table 4 lists the potential bulk user s of chlorine that can conceivably receive chlorine by barge.

Pepresentatives of two of the companies listed in Tabl- 4 stated that they .

do not use any appreciable amounts of chlorine in their proce sses. These companies are Jefferson Smurfit Corporation and Sponge-Cushion, Inc. A third company, Akro Chemie, is not located on the river, and has no capability of receiving a barge shipment. There is no need for these three companies to be cont act ed in future surveillances. Federal Paperboard Co., located in Marseilles, was not contacted, as it was in previous surveillances, because it produces the same type of products as Jef f erson Smurfit.

The results of the 1991 survey are identical to the 1988 survey, and are summarized below: _

- the Uni *.ed States Coast Guard records did not show any new barge docking facilities constructed between the Marseilles and Dresden locks since 1988; the government agencies contacted (U.S. Army Corps of Engineers, U.S.

Coast Guard, and the lockmaster at the nearest upstream dam) do not track chlorine shipments on the Illinois River;

- the Chlorine InJtitute is not aware of any chlorine shipme nt s on the Illinois River, and a representative of the Institute has stated that there are no such shipments, to the best of his knowledge;

- no chlorine barges operate on the Illinois River;

- none of the barge terminals between the upst rema and downstream dams ship or receive chlorine;

ATTACID4ENT D e '

E. CONCLUSION Qt FtweiNcs .

The 1991 survey did not turn up any significant amount s of chlorine shipped on the Illinois River. There are no chlorine producers located on the river, nor are there any bulk users of chlorine that receive the chemical between the Marseilles and Dresden locks on the river. No chlorine is known to pass through the Dresden locke. The conclusion of t he 1991 survey is t hat chlorine is not shipped on the Illinois River in signif! cant amount s within 5 miles of La Salle station, and that chlorine detectors on the outside air intake of the control room ventilation system are not necessary.

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ATTACHNDfT. D -

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• 4 l

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TASt.E 1

- ACTIVE CHLORINE BARGES IN THE U,$. AND CANADA gy m Reoortina Marks /Name Barme Noi- liQm.Cl2.CADatihlD Canadian Occidental (3)- Metla k a tla' 900 (3 x 300)

LCP (3) ~ LCP 4, 5, & 6 900 (3 x 300)

Georgia Pacific (1) Elaine D* - 1200 (4 x 300)

Occidental (11) DACO 3106 1109 1100 (4 x 275)

DCS 1103 1105 1100 (4 x 275)

EIDC 202 & 204 1100 (4 x 275)

Griffinip* 400 (2 x 200)

Chet Roberts' 600 (2 x-300) .

Olin (7) SBl 601 603 1110 (6 x 185)

OMCC - 651 A 652 100 (4 x 275)

OL 654 A 655- 1050 (4 x 262+)

4 Pennwalt (2) Tyee' 1200 (4 x 300)

Totem * .1200 (4 x 300)

PPG Industries (14) PPG 150,'151, 152 600 (4 x 150) 153,155,158 PPG 400-407 1100 (4 x 275) 1'

• Coast wise barges, operate in Pacific Northwest, rest on intercoastal waterways.

i W -yy.' p-'wgy--4gg-yg=y.-g-e+e.-4,+y-ety-e. w -ne qt--pm-s--r--- ya+.,..,.e-%-re.e--p,-m---asz,- y*.g g r m sew-ary-y-_--- ,gm.i-y-_--.r. y- > op pp e g-q ,g, q 9 g--y m-m,> y- g

ATTACIO(ENT D 3_,,=- ,

e TABLE 2 GOVERNMENT AGENCIES AND TRADE ORGANIEATIONS CONTACTED INFOPMATION THAT CHLORINE IS TRANSPORTED ON gantuititiost tur ftttweis m1vra

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

2. Illinois Dept. of Transportation, Hasar-' Mone dous Materials Div., Springfield, IL.

3. Lockmaster, Dresden Lock and Dam, Mone

4. U.S. . Artny Corps .of Engineers, Rock Is- None land, IL.

5. U.S. Coast Guard,. Chicago, IL. None J

.-rw%,c, - .I _ 4 --~ ., . m,,,,m- .~ u. .,w..-,.. . - . _ . , - - -,y 53.., .%e'..-. #%-. .

.rw_. -3 , .-_ . - ,mw <xe..

l i ATTACHMENT D

, , . -i TABLE-3 BARGE TERMINALS LOCATED ON THE ILLINOIS RIVER BETWEEN THE DRESDEN DAM AND THE MARSEILLES DAM RIVER CHLORINE COMPANY KILE SHIPMENTS

1. Kai s e r-E s t e ch, Inc., Marseilles, IL. 248.7 Hone

2. Texasgulf Chemical Co., Marseilles, IL. 249.9 None

3. Continental Grain Co., Seneca, IL. 252.6 None

4. Black Marine Inc.,-Seneca, IL. 253.0 None

5. Shipyard Terminal and Industrial Park, 253.6 Hone Seneca, IL.

6. Seneca Port operating Co., Seneca, IL. 253.6 None

7. Material Service Corp., Morris, IL. 262.0 None

8. ADM/Growmark, Marris, IL. 262.9 None 263.1

9. Cargill, Inc.,-Morris, IL. 263.1 None

10. Continental Grain Co.,- Morris, IL. 263.2 None i

11. Cessnonwealth Edison, Co. , Collins 265.8 None Station, Morris, IL.

12. Quantum Chemical Corp., USI Div., 269.9 None *

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l ATTACHMENT'D n( c,,

TABLE 4

-POTENTIAL BULK CHLORINE USERS BETWEEN THE DRESDEN AND MARSEILLES DAM CHLORINE RIVER ,

COMPANY PP_ODUCTS SHIPMENTS

1. Texasgulf Chemical Co., Industrial Chemicals None Marseilles, IL 2.- Asco Chemie America, Morris, IL. Industrial Chemicals None

3. ETI Company, Morris, IL. Industrial Chemicals None

4. Jefferson Smurfit Corp., rolding Cartons None Morris e IL.

5. Quantum Chemical Corp., Indust rial Chemicals None USI Div., tberia IL.

6. Reichhold Chemicals, Inc. . Synthetic Resins None Morris, IL.

-7. -Sponge-Cushion, Inc. Sponge Rug Cushions None Morris, IL

-8, water and wastewater Treatment Drinking Neter and None Facility, Morris, IL. Sewage Treatment

9. water and wastewater Treatment Drinking water and None Facility, Marseilles IL. Sewage Treatment 10, water and wastewater Treatment Drinking water and None Facility, Seneca, IL. Sewage Treatment l

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e ATTACHMENT D l

g 4 .

F11 E P.LECLS

1. Mr. Michael Leyden, Chlorine Institute, h a s h i n gt on, D.C. (202)?75-2790.

Personal communication.

2. Mr. Tom Crawford, Illinois Depa rtment of T r a n sport a t ion, Hazardous Materials Division, Springfield, IL, (217)785-3064. Personal communication.

3. Loc kma s t e r, Dresden Dam, IL. (815)942-0040, est. 6732. Personal communication.

4. Miss Donna Jones, U.S. Army Corps of Engineers, Rock Island, IL. (309)788-6361. Personal communication.

5. Mr. Tem Manier, U.S. Army Corp of Engineers, Rock Island, IL. (309)788-6361, ext. 6416. Per sonal communication.

6. Mr. Bob Nedro, Ka i s e r-E s t e ch, Inc., Marseilles, IL. (815)795-4151. Personal communication.

7 Miss Janet Armstrong, Texasgulf Chemical Company, Marsellies, IL. (815)795-5111. Personal communication.

8. Mr. Brian Leydens, Continental Grain Co., Seneca, IL. (815)942-0932.

Perscnal communication.

9. Hu s s Paula Halbur, ADM/Growmark, Morris, IL. (815)726-5227 Personal cocmunication.

10. Mis s Di 'rus Black, Black Marine, Inc., Seneca, IL. (815)357-6666. Personal commun ;ation.

11. Mr. Ge or ge Lamb, Shipyard Te rminal and Industrial Park, Seneca, IL.

(815)357-6721,

12. Mr. Glenn Mcdonald, Seneca Port Operating Company, Seneca II. (815)357-8811. Personal communication.

13. Miss Peggy weber, Material Services Corp., Morris, IL. (815)942-1830.

Personal communication.

14. Mr. Kevin Grudem, Cargill, Inc., Morris, IL. (815)838-1153. Personal ccamunication.

15. Mr. Curt Strong, Continental Grain Company, Morris, IL. (815)838-1801.

Personal ccanunication.

16. Mr. Larry Banas, Commonwealth Edison, Collins Station, Morris, Illinois.

f.815) 9 4 2-4 500, ext. 600. Personal communicat ion.

17 Mr. Jerry Starkey, Quantum Chemical Corporation, USI Division, Morris, IL.

(815)942-7201. Personal communication.

• ATTACHMENT D o 3, .>

18. Petty Officer Gilbert, U.S. Coast Guard, Chicago, IL. (312)353-1226.

Personal communication.

19. Miss Cathy Rollins, Akso Chemie, Morris, IL. (815)942-6200. Personal communication.

20. Mr. Wes Geisert, ETI Company, Horris, IL. (815)357-8711. Persons 1 communication.

21. Jefferson Smurfit Corp., Morris, IL, (815)942-1520,

22. Mr. Jim Basil, Reichhold Chemicals, Inc., Horris, IL. (815)942-4600.

Personal communication.

23. Mr. Jerry Toddern, Sponge-Cushion, Inc. Morris, IL. (815)942-2300.

Personal Communication.

24. Miss June Fox, Water and Wastewater Treatment racility, Morris, IL.

(815)942-5063. Personal communication, l

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