ML20012A346

1989 Annual Operating Rept for Sequoyah Nuclear Plant.W/ 900301 Ltr

ML20012A346
Person / Time
Site:	Sequoyah
Issue date:	12/31/1989
From:	Wallace E TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9003090292
Download: ML20012A346 (65)

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1 TENNESSEE. VALLEY.. AUTHORITY

- CHATTANOOGA. TENNESSEE 37401 n SN 157B Lookout Place MAR 011990

' U.S.' Nuclear Regulatory Commission ATTN: ' Document Control Desk-Washington, D.C. 20555 Gentlemen:

u In the Matter of, ) Docket Nos. 50-327 Tennessee Valley Authortty. ) 50-328 SEQUOYAH NUCLEAR-PLANT (SQH) - 1989 ANNUAL OPERATING REPORT Enclosed 1s the 1989 Annual Operating Report for SQN. It contains a summary

of.the following items: facillty changes, procedure changes, special tests,.

Land occupational exposure data.

This report is being submitted to satisfy the requirements of 10 CFR 50.59 and-

, cTechnical' Specifications 6.9.1.4, 6.9.1.5, and 6.15.1.

Please direct questions concerning this issue to Russell R. Thompson-at

-(615) 843-7470.'

Very truly yours, TENNESSEE VALLEY AUTHORITY E._G. Hallace, Manager Nuclear Licensing and

' Regulatory Affairs Enclosure cc: See page 2 s

9003090292 891231 PDR

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An Equal Opportunity Employer

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U.S. Nuclear Regulatory Commission I: .

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Ms. S. C. Black, Assistant Director for' Projects TVA Projects Division U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 e

Mr. B. A. Wilson, Assistant Director i for-Inspection Programs TVA Projects Division U.S. Nuclear Regulatory Commission Region 11

'101 Marietta Street, NW,~ Suite 2900 Atlanta, Georgia 30323 NRC Resident Inspector Sequoyah Nuclear Plant i 2600 Igou-Ferry Road

. Soddy Daisy, Tennessee 37379 1

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I TENNESSEE VALLEY AUTHORITY L L NUCLEAR POWER 1 PRODUCT 10N-  ;

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SEQUOYAHJNUCLEAR PLANT l UNITS 1 AND 2 .

'10 CFR 50.59 ANNUAL OPERATING REPORT .

TO-THE NUCLEAR REGULATORY COMMISSION j

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JANUARY -1,1989 - DECEMBER 31,1989 4

DOCKET NUMBER 50-327 AND 50-328 LICENSE NUMBER DPR-77 AND DPR-79 i

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s SEQUOYAH NUCLEAR PLANT 10 CFR 50'.59 NRC ANNUAL OPERATING REPORT 1989 *

.m TABLE OF CONTENTS ,

I Preface

-Acronym List I. Summary of Facility Changes Modifications 1 (

Temporary Alterations - 24 II. Summary ~of Procedure Changes Abnormal Operating. Instructions 27 Emergency Instructions 28 Survelliance~ Instructions =29 SpeciallTest Instructions 34

-Other: Instructions 35

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.t III'. . . Summary of Special Tests 41 ,

IV. Occupational Exposure Data 42 i r

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.a-The' following is - a list of abbreviations and acronyms- common to this report. =]

F -Abbreviations / Acronyms , < Definition ABCTS- Auxilliary Building'Cas Treatment System AESCE

! Auxiliary Building Secondary Containment: Enclosure ac Alternating Current,  ;

ACA . Auxiliary Control' Air j

.AERCW1 Auxiliary Essent'lal' Raw Cooling' Water j AFW Auxiliary Feedwater AFWPT Auxiliary Feedwater Pump Turbine ,

AHU Air-Mandling Unit AI Administrative Instruction ANSI American National Standards Institute '

AOI Abnormal' Operating Instruction cASME- American Society Cf Mechanical Engineers ASTM American Society For Testing"And Materials ATC Automatic Time Control

'ATWS Anticipated Transient Without a Scram ~.

AUO, Assistant Unit Operator AUX Auxiliary.. '{

AWG American Wire cause L AZ Azimuth

• A/C Air-Conditioning BAT Boric' Acid Tank BATP Boric Acid Transfer Pump I BIT- Boron Injection Tank CAM Continuous Air Monitor CAQR' Condition Adverse To Quality Report ,

CATS Commitment Action Tracking System-CCP- Centrifugal Charging Pump CCS Component Cooling System CCW Component Cooling Water CDWE Condensate Demineralizer Waste Evaporator CEB Civil Engineering Branch cfm

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Cubic Feet Per Minute' CFR Code Of Federal Regulations '

CGCS Combustible cas Control System CIS Containment Isolation System CIV Containment Isolation Valve COPS Cold Overpressure Protection System

CP - Crankcaso pressure cpm Counts Per Minute j CRD Control Rod Drive CRDM Control Rod Drive Mechanism CRI Control Room Isolation

'CRVI Control Room Ventilation Isolation CS Containment Spray CSP Containment Spray Pump CSS Containment Spray System CSSC Critical Systems, Structures, and-Components CST Condensate Storage Tank CT Current Transformer k.

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- & j .O Abbreviations / Acronyms- Definition  ;

CV Check Valve -

CVCS Chemical Volume, Control System  !

CVIL Containment Vent ~ Isolation DBA: Design Baseline Accident.

DBE Design Baseline. Event DBVP. Design' Baseline , Verification Program de- Direct Current:

DCA' Design Change Authorization DCN Design Change Notice.

DCR Design Change Request DPM Division Procedure Manuals DWCD Demineralized Water and Cask Decontamination DWST- Demineralized Water Storage Tank D/G' Diesel Generator >

EBR Electrical Board 1 Room ECCS Emergency Core Cooling System ,

ECN Enginesring Change Notice  !

EGTS Emergency Gas Treatment System EHC Electrohydraulic ~ Controller.

el Elevation EMI -Electromagnetic Interference Electrical Maintenance Section Letter EMSL ENS . Emergency Notification System E0I Emergency Operating Instruction E0P Emergency Operating Procedure EQ Environmental Qualification EQIS Equipment Information System

.ERCW Essential Raw Cooling Water ESF Engineered Safety Feature '

FCR Field Change Request- .

FCV Flow Control Valve '

FQE Field Quality Engineering FRG Function Restoration Guidelines FT Flow Transmitter-ft-lb- Foot-Pound +

l- GBCS Generator Bus Cooling System l GCS Gland Steam Condenser

> CCS Cencral-Construction Specification

[. 1GDC . General Design Criteria E GOI General Operating Instruction HCI Hazard Control Instruction High-Energy Line Break HELB l HEPA High-Efficiency Particulate Air HERCW Hanger - ERCW

'HJWT High-Jacket Water Temperature hp- Horsepower HPFP High-Pressure Fire Protection HVAC. Heating, Ventilation. And Air-Conditioning ICF Instruction Change Form IMI Instrument Maintenance Instruction I/P Current to. Pneumatic

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's ' Abbreviations / Acronyms-L ; ' 7, _ Definition.

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• kV~ Kilovoltf .

kW Kilowatt ) '

Limit Control-LC LCO - Limiting Condition of Operation J

LCV Level Control Valve LER. Licensee Event Rcport  !

LLRW Low-Level Radwaste' '

LOCA Loss'of Coolant Accident

LOP' Lube Oil Pressure

• LT Level Transmitter '

MA Milliamperc i MCC Motor-Control Center '

MCR Main Control Room

• MDAFWP1 Motor-Driven Auxiliary'Feedwater Pump I MEB . Mechanical Engineering Branch MFIV(s) Main Feedwater Isolation Valves (s)

MFLB Main Feedwater Line Break MFPTC Main Feedwater Pump Turbine Condenser MFW Main Feedwater MIC Microbiologically-Induced Corrosion

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MOP Main 011 Pump MOV Motor-operated Valve MPC Maximum Permissible Concentration MR Man-Rem / Maintenance Request  !

MS Main Steam . l MSDDT . Main Steam Dump Drain Tank MSIV Main Steam Isolation Valve MSLB Main Steam Line Break MTR Minimum Training Radius MVAR Millivolt Amperes Reactive M&AI M&TE Modifications and Additions Instruction Measuring and Test Equipment NBS National Bureau of. Standards NCR Nonconformance Report-NDE ,

Nondestructive-Examination '

NE Nuclear Engineering NEB Nuclear Engineering Branch NPG Nuclear Power Croup NPSU . Net Positive Suction Head ,

NQAM Nuclear Quality' Assurance Manual NRC Nuclear Regulatory Commission NSSS Nuclear. Steam Supply System O&PS Office and Power Stores OE-MEB

• 0H&S Office of Engineering-Mechanical Engineering Branch Occupational Health and. Safety PCB Power Circuit Breaker PD. Positive Displacement PI Pressure Indicators PM Preventive Maintenance PHP Preventive Maintenance Program PORC Plant Operations Review Committee l

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.g7 , - t Abbreviations / Acronyms Definition'~ '

PORV' fower-Operated. Relief Valve PRO; Potential'Reportabic Occurrence PRT Pressure-Relief' Tank PRV Pressure-Relief Valve PS Pressure Switch.

psil  : Pounds Per' Square Inch psia Pounds Per Square Inch Absolutei i paid. Pounds Per Square Inch Differential

• psig- Pounds Per Square Inch Cauge.

PSO t Power System Operations- ,

PT Pressure Transmitter /Prooperational Test m ' QA Quality Assurance '

QC: Quality Control QE&C Quality Engineering and Control' '[

-QIR. -Quality Information Release / Request QMDS Qualification Maintenance Data Sheet.

R Revis!on RCH Reactor Coolant. Hanger '

RCP Reactor Coolant Pump I RCS Reactor Coolant System RCW Raw Cooling Water RF(I) Radio Frequency (Interference)

RHR -Residual Heat Removal ,

RHV Reactor Head Vent RM Radiation Monitor RPI Rod-Position Indicator rpm- ' Revolutions.Per Minute RSW g Raw Service Water . j RTD Resistive Thermal Detector

-RTV~ Room Treated Vulcanization RWST Refueling Water Storage Tank RX Reactor

.R.G. Regulatory Guide 7 SAR Safety Analysis Report i SCF. Standard Cubic Feet  ;

~ SCFH Standard Cubic Feet Per Hour '

SCR Significant Condition Report SCV Steel Containment Vessel SDM Shutdown Margin SE. Shift Engineer SFPC Spent Fuel Pool Cooling SGBD Steam Concrator Blowdown.

SGTR Steam Generator Tube-Rupture SI Survel'11ance Instruction

=SI Safety - Inj ection SIS Safety injection System SNM Special Nuclear Material  !

SOI Standard Operating Instruction SP Standard Pressure SPDS Safety Paramotor Display System SPTS Sequoyah Procedures Tracking System i

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T.'e 'C' Abbreviations / Acronyms' <

Definition v ,

'SQA 9-  ; pequoyah Administrative Instruction '

<. SQN Sequoyah Nuclear Plant L f SR ' Surveillance Requirement

[ SRO. Senior Reactor Operator <

SSD. Seismic Self-Drilling

, .SSPS Solid State Protection System

=SS Stainless Steel 3 STI' Special Test Instruction' S/D Shutdown j*

S/G- Steam Generator TACF TemporaryLA16a.rntion Control Fo'1m -i T av Average Temperature.

• TDAhW -Turbine-Driven Auxiliary Feedwater ,

TDPU Time-Delay Pickup. ,

TEACP. ' Temporary Exterior Access Control Portal -

TI' Technical Instruction TS Technical Specification (s)

TSC Technical. Support. Center '

UF Underfrequency  !

UHIH Upper-Head Injection Hanger t UHI(S) Upper-Head' Injection (System)  !

UO- Unit Operator

.USQ Unreviewed Safety Question USQD' Unreviewed Safety Question Determination UV Undervoltage U.L. Underwriters Laboratories V Volt VCT' Volume-Control Tank

WC Water Column

'WGDT Waste Gas Decay Tank WOG-ERGS Westinghouse Owners Group-Emergency Response Guidelines WP Workplan -

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Page No. 1 CHANGES IN THE FACILITY - MODIFICATIONS ~

.q ECN/DCR DESCRIPTION SAFETY ANALYSIS DCN E00437 Because the ESF cooter motor shafts had failed at the drive end Removat of the motor / fan belts from'the ESF cooters decreased DCR 2673 bearing shaft shoulder, motor / fan belts were removed as required to excessive forces, which have lead to motor shaft failure. .This ensure excessive forces acting on motor shaf ts were elimirrted. The change did not af fect plant procedures listed in the researched .

excessive forces resulted from extra notor/fsn belts. documents or affect any test or experiment described in the SAR orf any IIcense amendment issued by the NRC to authorize the test or e r

• iment.

CCN E00906C Drawings were revised to specify the correct electrical strike panic TP_ margin of safety as defined in the bests for TS 3/4.7.12 was not DCR 2335 bar lock, strike guard door closer, and to omit unnecessary deadbott reduced.

Iock on Door D33.

DCN M00017 Temorary filters were instat ted on the lower comartment cooters to This change is applicable for Modes 5 and 6 to prevent cooter coits '

DCR 2259 protect the cooters' coits from becoming fouted during Modes 5 from being closged by dust and contaminants during plant cold and 6. shutdown and refueling. Neither the system function nor its. -

operabliity was af fected by the change. ;j DCN M00229A This modification changed the inboard hydrogen analyzer CIVs from Changes made under this DCN restored containment Integrity for Modes DCR 2509 fait open (on toss of air, fait close on toss of power) 4 and 3. The change did not degrade the operability of the system.

electro-pneumatic valves to fait closed solenoid valves. New CIVs These changes did not contribute to the probebility of or-were added inside the annutus, and existing contret air lines inside consequences of any accident. The DCN replaced the inboard CIVs' contaiment were capped because they were no longer required to with more reliable valver. There was no reduction in the margin of provide air to the analyzer CIVs. This also eliminated or minimized safety.

tow points on the hydrogen enalyzer: sample pnd return lines inside the contaiment and the annutus. ,

DCN N00230A The outboard containment isolation valves were added to the hydrogen The hydrogen anal *zer system is not considered as contributing to DCR 2510 anatyrer sample lines to bring SON Unit 1 hydrogen anatyrer system the probability of an accident. The changes made by this DCN did in compliance with 10 CFR 50 Appendix A, and were electricatty not increase the probability of an accident as described in the SAR.

connected to permit the hydrogen anatyrer to function.

DCN M00231 The hydrogen anatyrer Train B calibration panels were retoi.ated to The possibitity for an accident of a different type than any DCR 2511 the Auxiliary Building secondary containment enclosure. Att the evaluated previously in the SAR was not created. The margin of-

. wiring ano tubing was ccanected by DCN M00232. safety as defined in the basis for any TS was not reduced.

I ' DCN M00265C Modifications were made to various pipe supports to qualify these This activity affects safety-related snubbers; therefore, TS 3/4.7.9

! DCR 2293 supports as required by att applicable design criteria as denoted in applies. However, since this activity ensured the design require-l the modification criteria. Additionally, calculatierrs and design ments of the piping systees were met,.the margin of safety was not I drawings were issued to reflect tre seismic qualific-tion cf the reduced.

affected supports.

l DCN M00283C Sections of carbon-steet piping and fittings that were determined to This modification reduced / mitigated erosion / corrosion in areas that

! DCR 2587 have excessive wall thinning were upgraded to stainless-steel were replaced. There was no increase in the probability for or the I material. consequences of an accident. The margin of safety as defined in any..

l TS was not reduced.

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.Page No. 2 CHANGES IN THE FACILITY - MODIFICAi!ONS-i J,

DCN M00374C Tubing supports on either side of SCV Penetrations X-23, X-25A, There was no increase in the probability for or the consequences of  ;;

DCR 2641 x-25D, X-84A, X-85A, X-91, X-92,'x-93, X-96C, X-99, F-100, X-101, an accident. The margin of safety as described in any TS was not. '

X-103, X-106, and X-116A were modified to allow flexibility for the - reduced.

tubing to' take the SCV mvements with existing routing.

DCN M00418 Eight new sprinkler heads were added, and ten existing sprinkter This modification dedreased the probability of a malfunction of the-DCR 2542 heads were relocated inside the Unit 1 annutus to provide KPFP for RCS tetdown beca"3e of fire effects by increasing the fire' .

interactions between eteatrical cables that are required for a suppression system capabilities, and it did not cause a malfunction qualified letdown path. of a type different from that previously evaluated. The margin of safety as defined in TSs 3/4.3 and 3/4.7 was not reduced.

DCN M00419 This was a documentation change only to update the flow data on the The function of the ERCW remains unchanged, and the probability cf a '

DCR 2605 ERCW flow diagrams. new or different kind of eccident fr m any previously evaluated in -

the SAR was not created. There was no reduction in the margin of safety as defined in the basis for any 15.

DCN M00438A This DCN permanently removed the outer-most motor / fan belt from The margin of safety as defined in the basis for any TS was not' DCR 2673 specified ESF cooters to ensure that excessive forces acting on the reduced.

motor shafts were eliminated. The remaining motor / fan belts were aligned and tensioned according to the specificaticns docmented in TVA memorandum B29 880615 010. .,

DCN M00447 Points 0-RE-90-M2 and 0-RE-90-103 were added to the Unit 2 TSCDS. These points were required for the SPDS radioactivity status tree, DCR 2538 Alt software modifications were made under Software Change S0 which is an operator aid onty. The cable installed was property TSC-017 and S0-88-ISC-018. isolated from att safety-grade equipment in accordance with Scu-DC-V-12.2. .

DCN M00450A this modification removed the minimum / maximum circuitry from the; The minimtzn/maximtsu circuits do not provide protection for a f ailed DCR 2321 controt circuits for att Unit 1 D/Gs. The change involved only exciter or voltage regulator and do not provide any funi: tion when inter-panet wiring and did not involve any circuits routed external the D/G is in emergency mode. This modification did not increase to the diesel control panets. All changes were made in the D/G the probability or the consequences of an accident. The margin of buildings with no interface to the plant systems, safety was not reduced.

DCN M00456A Sequoyah's drawings were revised to ettow the use of the Watts Bar The margin of safety was not reduced. It is permissable to use the DCR 2669 RCP motor-lifting device. Nondestructive testing of the critical Watts Bar RCP motor-lifting device on a limited basis in accordance corponents was performed before its use. with OIR MEB SON 88044, R0.

DCN M00458 This DCN instatted Chesterton live-load packing on Valves 2-FCV-3-67 The margin of safety as defined in the basis for TS 3/4.7 was not DCR 2569 and 81 to prevent water from running down the valve stem an.:I into reduced.

the operator.

OCN M00467A ESF cooter motor shafts failed at the drive and bearing shaft The margin of safet/ as defined in the basis for any TS was not DCR 2673 shoulder. Fan belts were removed as required with an option to reduced.

replace motor shafts to prevent motor-shaft failures.

D'CN M005583 This modification added, retocated, and rewired Bahour battery-. This' modification enhanced the emergency tightp3ck system ard did DCR 2694 powered emergency tight packs to operate valves and controts to not change the plant operating characteristics as described in the place the plant in shutdown. SAR.

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Page No. 3 CHANGES IN THE FACILITY - MODIFICATIONS ..

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DCN M00579A Fire hazard analysis determined that additional sprinkler protection This modificatton provided 'concensation for the tack of a heriter'tal

'DCR 2700 was required in the Auxiliary Building to protect the RCS tetdown distance of more than 20 feet free of intervening ccribustibles -

path. This DCN ackfed three sprinkler heads in the Auxiliary between redundant divisions being protected in accordance with ,4 Building,'one in each of tne following rooms: . 734.0- A2, 734.0-A10,- 10 CFR 50, Appendix R, Section 111.G.2.b.. Civil calculations

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and 734.0-24. verified that piping is property supported. This change decreases a the consequences of an accident because of fire by providing i mroved suppression capability. The additional fire protection increases the equipment reliability. This modification did not decrease the margin of safety as defined in the basis for TS 3/4.3l or 3/4.7. '

DCN M00602 This DCN replaced the 1A-A and 18-B containment spray planp bearing The replacement of the tubing did not change'the ftsiction of the DCR 2637 oil and stuf fing box cooling water tubing with 1/2-inch diameter containment spray pums; therefore, the possibility for sn accident staintess-steet tubing with fewer bends and turns, of a different type was not created. The margin of safety as defined in the basis for TS 3/4.6.2 was not reduced.

DCN M00678 valve 2-FCV-1-215 was replaced with a Masoneiten valve specified for This change did not affect the safety function of the MS system or DCR 2713 vacuum service. any other system essential for safe operation of the plant. No TS requirements are identified or required for this nonsafety-related portion of the MS system.

DCN M00738 New power-supply cables and fuses were provided for protection This DCN upgraded th. newage facilities 'to reduce EPA nonconpliances DCR 2348 between existing distribution cabinet DC1 in the Office and Power. in the area. No safety-related function or system was involved.' No Stores Building and the new interfacing disconnect switch for the $AR or TS section applied to this modification.

two 50 hp inotors tocated at the Soddy Daisy Sewage Treatment Facility in the yard just north of the Office and Power Stores '

Building. Grounding terminations were also provided at the sewage treatment facility interface.

DCN M00739 This DCN changed the tap setting on the 18-8 D/G exciter current This chang 6 increased the ability of the standby AC power system to DCR 2715 transformers. This tap change matched the exciter to the generator perform its safety function and did not increase the consequences of so that the D/G transient voltage response was improved. an accident. The voltage response was iPoroved, so the margin of safety was not reduced.

DCN M00761 Electrical intertocks were added to the MOP between MOP A1 and A2 This modification did not increase the probability of an accident DCR 2219 and between MCP 81 and 82 on the main feed pu m turbine for previously evaluated in the SAR. The margin of safety as defined in loss-of-controt power so that there is no decrease in oil pressure the basis for any TS was ret reduced.

on toss of power.

DCN M00803A A new cable-tray support was added to correct the sag of two cable The cable-tray support was added to ensure sieseic design require-DCR 2773 trays. ments and were not required by the SAR.

l DCN M00864A This DCN revised the Emergency Operating Procedure Setpoint Table TS 6.8.1 invokes Regulatory Guide 1.33, which requires the emergency (47E250- 1 and 2) to incorporate the RVtlS setpoints. Instructions t6 be maintained. The Fmergency Operating Procedure Setpoint Table (47E250- 1 and 2) detinentes the EOP setpoints as

-required by WOG-ERGS to ensure design requirements and safety limit are not exceeded.

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..o Page No. 4 CHANGES IN THE FACit.tif - M00lFICATIONS DCN N00874 Curbs were added to the roof of the ERCW ptmping station to keep The addition of curbing to the ERCW pumping station roof did not t DCR 2823 flamable hydraulic oil from the crane from entering the ERCW 2A change the ERCW system as described in the SAR, nor did it change

- ptmp room. the description / analysis of the ERCW punping station as described in .

the SAR.

DCN M00876 The closure botting for the S/G manways and handholes were replaced The margin of safetyJ with respect to RCS pressure, as defined in DCR 2508 with studs, nuts and washers. This will attow torque tightening of the basis of the TS, is provided in part by the safety factors the nuts and will prevent damage to the bott holes because of thread included in the ASME code and was not reduced. TS requirements for gatting. . primary system teakage timits were not altered.' -Therefore, the margin of safety as defined in the basis for TS 3/4.4.1.1 through 3/4.4.10 and 3/4.7.1.1 was not reduced.

DCN M00877A This modification removed rigid conduit Support 1317 from flexible The change corrected an error that had been made during instatta-DCR 2786 conduit. Additional supports were added for the rigid conduit. tion. TSs do not address conduit instattations or supports for conduit. -

DCN M00878A A 3/8-inch steel plate was attached over the existing 1/4-inch plate There was no change to the operating characteristics of the plant.

DCR 2795 that protects the Unit 1 Reactor Building exhaust vent from There was no decrease in the margin of safety as described in any-penetration by a tornado missite. TS.

DCN M008838 This DCN provided an optional botting method for reinstallation of The optional method was reviewed and approved by the Electrical the TDAFP exhaust fan motor dome. Maintenance Conconent Qustification Group and did not adversely impact the seismic Category I qualification of the safety-related fan.

DCN M00887A This DCN authorized the change of the temperature setpoint of Tests performed demonstrated that the operability of the sensitive '

various thermostats of the auxiliary instrument room and conputer instruments and the conputer performed f avorably with colder room HVAC system. Tenperature setpoints were towered to prevent TSC environment in the rooms. The change was within the design envelope computer component and instrt ent f ailure. of environmental design- therefore, the equipment quali.fication was not af fected. ' The teaperature limits for the spaces serviced by the electrical board room HVAC have not been specificatty addressed in TSs. The margin of safety was not reduced.

DCN M008899 The local buzzer of radiation monitoring system of shield building The tocal buzzer was generating a spike in toop 2-RE-90-100. The DCR 2820 vent and the capacitor that were added by TACF 2-80-537-90 were starm is stilt generated in the MCR. The loop's operability, removed. Vendor Drawing ELJ-281 8011 was updated. reliability, and maintainability were improved by removal of the buzzer because it eliminated the spike in the loop.

I DCN M00897 The leaking stand packing on valve.2-1-293A was repaired with This modification did not affect the operating characteristics of

! DCR 2817 formanite. The valve marker tag drawings were revised to reflect the pressure transmitter on this instrument line. The margin of.

the as-built configuration. Safety as defined in TS 3/4.7 was not reduced.'

DCN M00899A Flow Element 0-FE-14-134 (including the orifice) in nonsafety acid The flow element was not essential to the process because there is transfer tine was removed and replaced with a pipe spool to another flow element (0-FE-14-145) and transmitter down stream.

eliminate an acid leak. This was a documentation-only change because the physical work was performed in 1981 by TACF 81-529-14.

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Page No. 4 CHANGES IN THE FACILITY - MODIFICATIONS DCN M00874 Curbs were added te the roof of the ERCW ptmping station to keep The addition of curbing to the ERCW pufping station roof did not :

DCR 2823 flamable hydraulic oil from the crane from entering the ERCW 2A change the ERCW system as described in the SAR, nor did it change ptrnp room. the description / analysis of the ERCW gwping station as described in '

the SAR.

1 DCN N00876 The closure botting for the S/G ranways and handholes were repiaced The margin of safety, with respect to RCS pressure, as defined in .

DCR 2508 with studs, nuts and washers. -This will attow torque tightening of the basis of the TS, is provided in part by the safety factors the nuts and will prevent danage to the bolt holes because of thread included in the ASME code and was not reduced. TS requirements for gatting. primary system teakage limits were not altered. Therefo e, the margin of safety as defined in the basis for TS 3/4.4.1.1 through ~

3/4.4.10 and 3/4.7.1.1 was not reduced.

DCN M00877A This modification removed rigid conduit suppo-t 1317 from flexible The change corrected an error that had been made during instatta-DCR 2786 conduit. Additional supports were added for the rigid conduit. tion. TSs do not address conduit instattations or surports for-conduit. ,

DC4 M00878A A 3/8-inch steel plate was attached 'over the existing 1/4-inch plate There was no change to the operating characteristics of the plant.

DCR 2795 that protects the tJnit 1 Reactor Building exhaust vent from There was ne decrease in the margin of safety as described in any penetration by a tornado missite. TS.

DCN M008839 This DCN provided an optional botting method for reinstattation of The optional method was reviewed and approved by the Electrical the TDAFP exhaust fan motor dome. Maintenance Component Qualification Group and did not adversely impact the seismic Category I qualification of the safety-related fan.

DCN M00SS7A This DCN authorized the change of the te m erature setpoint of Tests performed demonstrated that the operability 4,f the sensitive various thermostats of the auxiliary instrument room and conputer instruments and the conputer performed f avorably with colder room HVAC system. Temperature setpoints were lowered to prevent TSC environment in the rooms. The change was within the design envelope computer component and instrument failure. of envirornnental design; therefore, the equipment qualification was not affected. The te m erature limits for the spaces serviced by the electrical board room HVAC have not been specificatty addressed in TSs. The margin of safety was not reduced.

DCN M008S99 The local buzzer of radiation monitoring system of shield building The local buzzer was generating a epike in Loop 2-RE-90-100. The; DCR 2820 vent and the capacitor that were added by TACF 2-80-537-90 were starm is stilt generated in the MCR. .ine loop's operabitity, removed. Vendor Drawing ELJ-281-8011 was updated. reliability, and maintainability were inproved by removal of the buzzer because it eliminated the spike in the loop.

DCN M00897 The teaking gland packing on valve.2-1-293A was repaired with This modification did not affect the operating characteristics of-DCR 2817 furmanite. The vatve marker tag drswings were revised to reflect the pressure transmitter on this instrunent . tine. The margin of the as-built configuration. safety as defined in TS 3/4.7 was not reduced.

DCN M00899A Flow Element 0-FE-14-134 (including the orifice) in nonsafety acid The flow element was not' essential to the process because there is transfer line was removed and replaced with a pipe spool to. another flow element (0-FE-14-145) and transmitter down strea:s.

eliminate an acid teak. -

This was a docunentation-only change because the physical work was performed in 1981 by TACF 81-529 14

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Page No. 5 CHANGES IN THE FACILITY - MODIFICATIONS Il DCN N00900A TACF 2-84-2046 replaced solenoid Valve FSV-46-36E on the MFWP The system operability, retlability, and performance were i groved DCR 2809 Turbine 2B with a valve having a larger orifice that provided br providing remote reset of the overspeed trip. The subject sufficient olt supply for resetting the overspeed trip. It was then conponent and its operating characteristics are not described in the found that the operating oil pressure was greater than the design- SAR.

differential pressure of either the original valve or its replacement. A new solenoid valve was procured, having a compatible pressure and temperature, as well as a suitable orifice size. ~ _

DCN M00901 The NEPA/charcoat fitter cartridge in the main condenser evactntion Removat of the filter cartridge did not degrade the availability or .

DCR 2402 system was removed. reliability of the radiation monitor or change the limits imposed by the TS. The riargin of safety as defined by the TS basis was not j reduced.

DCN M00909A The Unit 1 Sussman KLC6 fuses were replaced with Bussman KtC3 fuses. There was no increase in the probability for or the consequence of DCR 2780 This replaced a fuse of the same type with one having a lower an accident. The margin of safety as described in any TS was not amperage. TP.e KLC3 fuse provides a 5:1 coordination ratio, which is reduced. -

well above the manuf acturer's recomended minimtn ratio of 3:1.

DCN M00910A The Unit 2 Bussman KLC6 fuses were replaced with Bussman KLC3 fuses. There was no increase in the probability for or the consequences of .

DCR 2780 This replaced a fuse of the same type with one having a tower an accident. The margin of safety as described in any TS was not amperage. The KLC3 fuse provides a 5:1 coordination ratio, which is reduced.

wet 1 above the manufacturer's recorrnended minimum ratio of 3:1.

DCN M00913A As a result of CAQR SOP 880144, this DCN reptsced Unit 1 ERCU There was no increase ir. the probability of or consequences of ars DCR 2624 compartment nameptates with ones having proper color coding and -accident previously evaluated in the SAR. There was no reduction in revised Drawing 35UT36-1 to add a note addressing the nondivisional the margin of safety.

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toads connected to the MCCs.

DCN M00914A As a result of CAQR SOP 880144, this DCN replaced Unit 2 ERCW There was no increase in the probability of or consequences of an DCR 2624 compartment nameplates with ones having proper color coding and accident previously evaluated in the SAR. There was no reduction la revised Drawing 35W736-1 to add a note addressing the nondivisional the margin of safety.

toads connected to the MCCs.

DCN M00915 This DCN plugged teaks in Valves 2-50-519 and S20 with furmanite. This modification did not affect the operating characteristics of DCR 2824 the vatves. The margin of safety as defined in the basis for TSs

' 3/4.7.4 and 3/4.7.5 was not. reduced.

DCN f400928 This DCN replaced the automatic arming feature of the COPS with two This change will pre ~ent the coincidence of a single failure of a DCR 2644 control switches in the MCR on Panet 2-M-5. One control switch arms wide-range temperature channet and an event such as an MSLB or SGTR the COPS Train A, and the other control switch arms the COPS Train from inadvertently causing a PORV to open. Adninistrative proce-B. Also, an alarm window was added to the annunciator panel. dures were written to arm the COPS during tow-temperature operation and to disarm the COPS when the RCS te m erature exceeds 3500F.

DCN M00932 containment step level Transmitters 2-LT-63-176,177,178, and 179 The function of the system or the tevet transmitters was not changed DCR 2306 were replaced with Statham Model PD3200 and retocated to outside the by this modification. These transmitters are qualified for crane watt at et 680'-3", 46' radius at Ar 1760, 40, 2600, and 700 underwater submergence, which allowed them to be mounted at the base of the containment su m and eliminated the need for sensing lines, the margin of safety as defined in the basis for any IS was not reduced.

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Page No. 6 CSMNGES IN THE FACILITY - MODIFICAT1 CMS i k

DCN M00933 The 20 rubber expansion joints in the ice condenser drain lines were The margin of safety as defined in the basis of TS 3.6.5.7 and 6.8 DCR 2670' replaced with Pathway metal bettows. was not reduced.

DCN M00935A The CDWE ~ water heater conductivity probe was bypassed by jtmping The toss of hot water did not jeopardize plant safety because the Contacts 9 and 10. water heater is not needed to mitigate on a SAR Chapter 15 event.

DCR 2849 DCN M00936A This DCN docunented the removal of the light standard at 52 + 28.00 This levet of detait is not described in the SAR. The light was DCR 2348 (see Drawing ISN410-1, Revision 27) that was removed via TACF tocated near the gatehouse and had been removed to attow the 0-87-0013-245 and provided a design for protecting the exposed instattation of a mobile office trailer.

cables that remained t.fter the light was removed.

DCN M00942A 1his modification added relay K6, connected from remote controt K3 There was to increase in the probability for or the consequences of .

DCR 2793 and start terminals to ac neutrat, and added normatty closeo contact an accident. The margin of safety as described in any TS was not K6 in parrattet to flow switch in series with relay Coil K1. This reduced.

changed " Loss of Sanple Flow Alarm" RA-90-2128 to actuate only when loss of sample flow occurs during the time the Turbine Building step -

pwps are pucping.

DCN M00943 This DCN modified cable tray support MK 34 to facilitate instatta- Modification to the cabte tray did not require a change in the TS. .)

DCR 2829 tion of stiffener plates to the penetratien closure plates on Unit 2 Penetrations X-110, X-114, and X-115.

DCN N00952A Drawings 46w454-1 and 9 were revised to specify the correct- Door 033 provides fire and security protection and serves as a electrical strike, panic bar lockset, strike guard, door closer, and life-safety emergency exit for the D/G building. This change did omit the unneccessary deadbott lock on Door D33. not affect the existing seismic 1 (L).reteation requirements cf the door. There was no reduction in the margirt of safety.

DCN M00957A A 3/8-inch steet plate was attached over the existing 1/4-inch plate There was no change to.the operating characterist cs of the p %nt.

i DCR 2795 that protects the Unit 2 Reactor Building exhaust vent from There was no decrease in tne saargin of safety as described in any penetration by a tornado missite. TS.

DCN M00967 An analog isolation board (Westinghousa P/N 232470G01) was instatted The new and crx#fied equiment involved with this change was DCR 2539 in Panet 1-R-105 Located in the Control Building computer room. property isolated from att ecuirment irustunt to safety in This iso 8ation board provides an anplified output signal to both the accordance wit'n MN-DC-V-12.2. Therefore, this change did not TSC computer's input multiplexers located in 1-R-156 and 1-R-157, increase the formauences of a ratfunction of equiment imoortant to and P250's I/O conponents tocated in 1-R-104 safety previously evaiuated in the SAR. " The anargin of safety as defined in the bazis for any TS was not reduced.

DCN M00969B Setpoints for the reactor trip steam dunp control system and the tow the steam dunps Mve no safety function; therefore, the margin of DCR 2763 Tavg main feedwater isotation were optimized. safety was not reduced.

DCN M00971A Nameplates and drawings for the Fifth vital Battery distribution Adding the S designation to the nameplates and drawings had no DCR 2867 Panets A and B were revised to reflect the S suffix for effect on the operability, reliability, or performance of the system identification of the equi ment as safety related with redundant conponent s. The change added the S suf fix to cocoty with design power sources. -

criteria and SAR requirements to reduce the potential for human error during e:sintenance and operation. TS 3/4.8.2 was not affected.

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Page No. 7 CHANGES IN THE FACILITY - MODIFICATIONS g 4

DCN M00982 Westinghouse type AR tatching retsys were replaced with the approved This was a one-on-one reptocement with no wiring changes or DCR 2859 Potter and Brumfield tatching relays.

configuration changes. No change to TSs was regaired. '

DCR 2638 DCN M00983 This was a documentation change only to revise the contairnent spray The safety function of the system was not altered, and this change DCR 2825 system flow Diagraa 47W812-1 to reflect the actual design conditions did not increase the consequences of an accident. The margin of-of the pressure and teeperature boundary. safety as defined in the basis for TS 3/4.6.2 was mt reduced.

DCE M00993 This DCN replaced the packiic, tantern ring, and gland- seat water The exsrgin of. safety as defined in the basis for TS 3/4.7.1 was not DCR 2955 on MS dtsrp vatves 2-FCV-1-103 through 114 with Chesterton live-toad reduced.

packing. Also, the packing for durrp valve isolation Valves 2-627.

through 638 was replaced with Chesterton packing, and the tantern ring and gland-seat water were removed, DCN M00994 inis DCN replaced the packing, tantern ring, and glarv3-seat water on The margin of safety as defined in the basis for TS 3/4.7.1 was'not DCR 2955 MS dump vatves 1-FCV-1-103 through 114 with Chesterton live-toad reduced. -

packing. Also, the packing for dtmp valve isolation Valves 1-627 through 633 was replaced with Chesterton packing, and the tantern ring and gtand-seat water were removed.

DCN M010004 Timing retays in the pressure switch logic in the EGTS automatic This modification ensured that a single failure witt'not irhibit the DCR 2865 train were added to modify and prectode any singte-failure occur- ability of the EGTS system to perform its safety function of rence on the discharge dampers. timiting 10 CFR 100 dose ratr. No increase in accident probability un caused by this activity.

DCN M01001 Because a single-f ailure occurrence causing the discharge modulating This modification ensured that a single f ailure did not inhibit the-DCR 2865 dacper in the EGTS automatic train to f ait open could prevent system ability of the EGTS system to perform its safety function. No '

from performing its design function, the present pressure-switch increase in accident probability was caused by this activity. This togic was modified to add timing relays 'to preclude any single- change did not physicatty alter the operation c,f equip ent but did f ailure occurrence on the discharge danpers. '

change the control circuits so that a failure would be detected in a timely manner and the other train started.

DCN M01004 Two disk-spring washers were added between the actuator stem nut and This modification did not change the f acility frun that described in -

DCR 2609 the diaphragm on 2 tCV-62-118 to prevent stem rotation of the valve. the SAR.

DCN M01006 This DCN added the fot towing to the main generator protective The addition of these relays provided enharred protection to the DCR 2971 relaying: (1) A current transformer to neutral grounding trans- generator. The malfunction of equipment important to safety former secondary to provide input to the overcurrent relay that previously evaluated in the SAR was not increased.

functions as ground overcurrent protection devicc, (2) A 100-percent stator ground fault protection tnit to the neutrat grounding resistor to detect a stator ground fault on the Unit 1 main generator.

DCN M01008 The hydrogen dryer was replaced with an automatic, contineously- The dual-tower dryer eliminated moisture in the hydrogen cooling DCR 2244 operating, dual-tower dryer complete with continuous, dew-point gas, which was detrimental to stator and rotor strands afxf '

monitoring of the hydrogen gas of the turbine generator cooling gas insulation, and reduced stress-corrosion cracking of the hig%

system. Panets 1-L-502 and 503 were addeJ in the Turbine Building, strength steet parts. The radio frequency monitoring system aids in New relief valves were installed on the new hydrogen gas dryers. An monitoring and tracking of f ailure trends and helps prevent ontine diagnostics monitoring system was added to the turbine urotamed turbine trips and costly emergency corrective maintenance n

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Page No. 8 CHANGES IN THE FACILITT - MODIFICATIONS -.

cenerator and auxiliary systems consisting mainty of a radio and repairs. The margin of safety as defined in the basis for any -

frequency monitor and flow detection on the hydrogen auxiliary TS was not reduced.

system.

DCN M01012 This DCN plugged leaks in Valves 1-50-517 and 518 with furmanite. '

This modification did not affect the operating characteristics of DCR 2966 the valves. The margin of safety as defined in the basis for TSs 3/4.7.4 and 3/4.7.5 was not reduced.

DCN M01020 Restraint bars were added in front of each row of modules in Rocks This modification enabled the rocks and penets to meet their seismic DCR 2981 i-R-127, 128, 130, and 131 and Panets 1-L-11A and 118. qualifications. This change did mt involve a change in the facility or the plant operating characteristics.

DCN M01032A An overcurrent relay and a 100-percent stator protection device was the changes were to nonsafety-related aquipment and provided DCR 2990 added to the Unit 2 main generator to detect stator ground faults. enhanced generator protection. This DON did not increase the consequences of a malfunction of equipment i m ortant,to safety

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2 DCN M01040A A 3/8-inch steel plates wcs attached over the existing 1/4-inch There was no change in the operating characte-istics of the plant.

DCR 2915 plates tha; protect the Auxiliary Building exhaust vents from There was no decrease in the margin of safety.as described in any penetration by a tornado missle.

TS.

DCN M01042A This modification was for design and installation of ycrd conduit No TS amties to nonsafety-related conduit instattation or to the DCR 2340' banks dedicated to the telephone system replacement as detailed by potable water system. This modification did not change the facility '

TVA Office of Muclear Power TS for a voice / data telecommuncations or plant operating characteristics from that described in the SAR.

system. This required minor site grading and installation of potable water supply for addition of a remote switch node building. ,

DCN M010829 A fire damer with a 1 and 1/2-hour rating was instatted at each air This change has no adverse affect on system performance during the DCR 2868 supply and air exhaust opening at the suspended ceiling of the normat or emergency modes. Instattation of the fire darpers ~

Control Building, et 732, to provide a fire barrier for the operator imroves the comartmentation of these spaces and redu:es the spread quarters; for fire without adverse af fect on any SAR analysis. TS 3/4.7.7 and-3/4.12.1 were unchanged.

DCN M01092 This DCN furmanited tesking Valve 1-VLV-3-511. This modification did not affect the coerating characteristics of DCR 3033 the valve end was not addressed in the SAR.

DCN M01094A The existing plaster ceiling in the Control Room Buildirg operators' There was no increase in the probability for or the consequences of DCR 2868 quarters was replaced with one that met the 1 and 1/2-hour fire an accident. The margin of safety as described in any TS was not rating required by the SAR. reduced.

i DCN M01099 Supports were deleted and/or modified on the pressurizer-relief _ the changes to the pipe-support scheme did not invlove a change in DCR 3007 piping system to stop leaking safety-retlef valves. the facility from that described in the SAR, but did ensure that the l

piping and supports met the requriements of the SAR.

DCN M01104A The existing nameplate for C-A vent Board 291-B comartment 12C was ' The replacement nameptate accurately describes the load, thereby l

replaced with one engraved " AUX BLOG VENT SAMPLE LINE PUMP.' reducing the probahitity of operator error. The margin of. safety;"'

. was not reduced.

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Page No. 9 CHANGES IN THE FACILITY - MQ)!F10ATIONS -

f DCN M01126 The recirculation piping located inside condenser C, which had The condensate system is not a safety system.' Replacing the piping. a

DCR 3048 ruptured at a 12-inch 900 elbow, was replaced with a stainless steel with stainless steet reduced / mitigated effect; of erosion, and iepingement (target) tee. Tuo elbows downstream of the elbow and.- ~ modifying the supports erhanced the design of the supports. . The the piping in between were replaced with stainless steet. Four margin of safety as defined in the basis for any TS was not reduced.

supports inside the condenser were modified to strengthen and enhance their design. The recirculation piping outside of tFe condenser was restrained to reduce vibration.

DCN M01149 This DCN attowed the use of 316 stainless-steet 20-gauge tubes in this systeer; Ys not described in the SAR or the TS.

C'CR 3057 the stator cooling water Exchanger 2-MEX-35-94A, instead of 18 BWG Admiratty 18 gauge that was previously used.

DCN M01159 This ECN repositioned 16 of the Unit 2 chint>te tubes inspected by this process of capping and/or opositioning of worn thiabte tibes DCR 2881 eddy-current testing showing excessive wear. The worn thiebte tubes decreased the possibility of tube wear-through eruf gave assurance .

were repositioned to new tube-wall surface in the wear area. The that the RCS boundary will be maintained. No other safety ecuipnent most severely worn thimble tubes (L15, R6, and RS) were capped to was affected; therefore, the probability of equipment matfunction ensure that should ttue leakage occur, it will be confined to the was anchanged. The capping and/or repositioning did not redxe the inner tube area and not require isolation valve closure to prevent nuder of thiebtes to less than required by TSs and did not reduce reactor coolant toss into the instrumentatico room. the margin of safety as defined in any TS.

DCN M01192 The ground strap Las removed / isolated for source range Detectors This modification provided isolation between the source range / inter-DCR 3078 2-XE-92-5001 and 5002 at the source range / intermediate range mediate range detectors to reduce the susceptibility to electrical housing. The integrat triaxiat MI cable was insulated from the noise interference with the neutron detector signal. This attews detector housing using fibergtsss tape to' isolate the source range the detectors to function as required. There was no chag e in the ground from the intermediate range ground, facility from that described in the SAR.

DCN M01200 The valve internals for ERCu check valves 2-67-565%, B, C, and 0; This modification did not increase the probability of a ex.tfunction DCR 3083 2-67-658A, B, C, and 0; and 2-67-671a, B, C, and D were removed. of equipment inportant to safety. The margin of safety as defined in the TS was not redu ed.

DCN M01204 Check Valves 2-70-676A and B had damaged internals and were replaced The margin of safety as defined in the basis for any TS was not DCR 3085 with equivalent check valves from Hartsvitte. reduced.

DCN M01250 Grating was removed in the new fuel storage vault. Grating over the new fuel storage vault did not invalidate any SAR DCR 2935 descriptions or plant configuration and/or operating scenario.

DCN M01251 Cable / conduit Contination 2V2733A was damaged when dritted into by No TS requirements were changed or affected by this modification.

DCR 3097 workers who were core dritting in preparation for pipe support anchors. A new Cable 2v2738A and conduit 2v2739A were routed from Penetration 21 to 2-FCv-63-80.

DCN M01270 Pipe support Mark No. 2CSH005 (2-H21-5) was modified fran a welded This modification did not change any ftnetionat configuration. The DCR 3103 connection to a botted connection to atlow item 30 (w5x19) to be margin of safety as defined in the basis fre any TS was not reduced.

removed white maintenance is being performed on Yatve 2-FCV-72-39.

DCN M01271 Pressure Transmitter 2-PT-2-7 was reptaced with a new Rosemount ' The new pressure transmitter has the came functions and qualifica-DCR 3031 1151AP series transmitter. tions as the old one,

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Page No. 10 CHANGES IN THE FACILITY 4 MODIFICATIONS t .

DCN M01304A Defective silicone robber Cable 2PL4826A for CRDM cooting Fan 2C-A The cable was replaced so that it will perform its intended ' ~

DCR 3129 and condait-associated Cables 2v1328A and 2v1346A inside primary ' 1 function.- There was no change in the f acility from that described -

contairunent were replaced. in the SAR. The margin of safety was not reduced. -

DCN M01315A This change abandoned the section of Cabte A3082 in conduit MC2025 The replacement cable was the same size, type, and tength. The=

DCR 3132 and spliced this to existing cable A3082 in Manhole 33 and 56. annunciation fmedon was stitt provided. There was no change in facility from frera SAR description result.

DCN M01323A Handraf ts were added to the south end of the 15-ton Turbine Building The addition of handraits enhanced personnet safety and accessibit-bridge crane as part of the Crane Consistency Program.' ity for routine maintenance. There was no reduction in the margin:

of safety.'

DCN M01345 The defective / obsolete pressuriter transmitter for.1-PT-3-80 (GE-MAC This modification did not alter the original design function or ~

DCR 3080 model 556) was replaced with Rosemount 1151 GP series transmitter, method of performing the intended function that'is described in the.

SAR for main feedwater system or radwaste system.

DCN M01354B This modification repacked a valve, removed a latern ring, anri cut This activity did not alter or reduce any margin of safety as DCR 3171 and capped the stem teakoff line for Valve 2-FCV-62-93. The leakof f defined by any TSs.

drain line at the header was also cut and capped.

DCN M01355A This DCN revised drawings to reflect the assignment of unique This margin of safety as defined in tne basis for TSs 3/4.5,'3/4.10, DCR 3040 identification ntrbers and instatted ID tags on manual valves. and 3/4.3 was not reduced.

DCN M01361A Pipe Supports Mark No. 2AFDH0303 and 2AFDH0291 were modified to make There was no increase in the probabitity for or the consequences of DCR 3174 2AFDH0303 rencvabte from 2AFDH0291 to facilitate valve maintenance. an accident. The margin of safety as defired in any TS was not reduced.

DCN M01379 This modification disconnected the 120Y at internal wiring and The removat of the sanpte s m p from 0-RE-90-212 did not affect the DCR 3191 rerouted the internat sangte line tubing to bypass the sample pump function of the radiation monitor as described in the SAR, but for effluent radiation monitor 0-RE-90-212. It also rewired the deletes a detait that states that the ptro is required. This sample flow switch alarm so that a loss of sanple flow will continue activity did not increase the probability of an accident or have to show a malfunction atarm, 0-RA-90-2129, in the MCR. The sample detrimental ef fects on safety-related equipwnt functions.

p e p, overloads, and associated handswi.tch'were spared in place.

DCN M01309A This modification added seoarate test points in Panet 0-M-12 for RMs The additional test points provide a wett-defined connection poir.t DCR 2876 0-RE-90-102 and 103 and 1-RE-90-106, 112, 130, and 131. for test equiprwt used in the performance of S1-32, "Functionat n Tests for the Radiation Monitoring System - Units 0 and 1." This f reduces the potentist for personnet errors daring the SI performance and, therefore, reduces spurious ESF actuations.

DCN M01t.00A Separate test points were previded foe Panet 0-M-12 for RMs The system capabilities were not cha,ged or adversely af fected. . The DCR 2876 2-RE-90-106, 112. 130, and 131. The test. points were added to new test jacks and wiring and their instattation met att seismic and provide a well-defined connection point for test equipment used in envirorrnental requirements. There was no reduction in the margin of.

the performance of SI-82.2, "Functionat Test for Radiation Monitor- safety.

ing System - Unit 2."

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DCN M0148SA This modification replaced the as-designed nitrogen flow indicating This modification erhenced the system operability and retlebitity.

DCR 2393 system for Loops 0-F-77-423 and 426 to monitor a flow of There was ro increase in the probebility or the consequences of an appaoximately 20 scfm of nitrogen to condensate storage tank?. The accident previously evaluated in the SAR. There was no i g oct on new instruments are inline rotameters, Brooks Modet 130SEZ12 (Range plant TSs, and the mergin of safety was not reduced.

2.4 to 24 scfm).

DCN M01684A This modification instMled EMI/RFI comer-foit shielding tape This modification is to a nondivisionet radiation monitor. The ,

around the 1-cM-90-179 signal cable presently susceptible to EMI/RFI modification was mode to eliminste interference and did not of feet 1 interference. 1-RM-90-119 gives an Indication of an activity tealt the function or operation of the equipment as described in the SAR.

from the primary to the secondary systen.

OCN M0194SA Misceltenevss structural steet ( i.e., six tifting lugs with This redificatien was evolueted by TVA Calculation SCG-1SX279 eM DCR 3390 surface-mounted plates) was installed to the bottom of the concrete was found to be accesirtable. The instattation of the miscellaneous floor stab tel 705) of the ERCW 3xwing station. The lifting lugs structural steet met att applicable design criteria and the will primarity be used during meintenance of the four ERCW requirements specified in the SAR. This acdification did not strainers. Drawing 3N206-9 was revised to chow lif ting lug . adversely i m ect the ability of the plant or plant staff to perform detaits, any required functions. There was no leect on nueteer safety.

DCN M0984A The te m erary power supply to the ASE's office in the Turbine Power supplies for tighting and appliances in the Turbine Building DCR 2856 Building, et 706, from tighting cabinet LC 204 was disconnected and are not addressed in the TS. Therefore, the mergin of safety was a permanent feed was provided from LC 206, et 732. not reduced.

DCN x00001A This modification removed en internet protective ring on the intets The Bettone molecutar metal is designed to be flexible. The FCR 5430 and outlets connected to the condenser water boxes and coated the deformations that occur in the expension joint do not cause the inside of the joint bettows with Bettona. Bettone to crack or degrade. This helps prevent leeks. The eergin of safety was not reduced. .

OCN N0000TE Instrtrnents 2-PDT-65-80, 82, 90, and 97 were reworked to add a There was no increase in the probability of or consequences of an .

DCR 2259 condensate collection chenber. These transmitters are used to actident. No new sccidants or motfunctions dif ferent from those

- automaticatty control EGTS exhaust da9ers for arriulus pressure evaluated in the SAR were crested. The TSs do not address control post accident. Instrunentation tubing and/or fittings used in this modification.

DCN x00023B New instrtrnant idantification tags were fabricated and attached for There was no increase in the probability for or the consequances of those instricents with missing tags discovered during the walkdown en accident. The mergin of safety was not reduced.

in accordance .nith SMI-0-317-61.

DCN x00049D This modification remcved the dxt asbestos insulation the RVAC There was no increase in the probebility for er the consevsence of DCR 2259 system that operates and meintains the temerature in the Contret an accident. Seismic and steport anstysis was provided because of Building computer room. The insulation was replaced with an the ackfitional weight of the dagers and/or registers. Additional approved duct insulation. Also, additional sspply and return air seismic sumort was provided. There was no reduction in the margin was provided and the system air flow was rebatanced to meintain of safety.

design room temerature.

DCN x000844 various siticone rubber cables inside centeinment were replaced with This modification did not affect the function, performance, or DCR 22S? type uCA-3 cable. Junction Box 1109 was reptsced with type Jys eperability of the cables. There was no increase in the probabitity junction and moved lef t four inches to facilitate the opening and or consequences of an accident. The mergin of safety was not closing of the cover. Two supports were attached to conduit reduced.

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Pege. No. 12 'CMA#GES In TPE FACILITY - MODIFICATIONS' DCN KD0087C Low-vottage auxitle power and control Silicon rubber-insuteted The cross-tinked polyethytene IE cables are rated et voltages not DCR 2259 cables were replaced with Ctess IE cross-tinked polyethytene : exceeding 60cv and jacketed with fire-resistance meterlat. The insulated cables. testing requirements for the new cables met thet described in SAR Section 8.3.1.2.3 and IEEE standards. The new cables instetted were of the same tength anei tess or ecuet weight. The selsnicity of the existing conduits was not igerted. Safety-related systems ig eeted by this modificatier, were not adversely af fected, and their funct!on -

was not changad freir that described in the SAR.

DCm 200137' This DCs tack welded the yoke to the bonnet in four places secouse the tack welds were nonpressure retaining end serve es e DCR 2235 approxinately 900 apart en valves 1 and 2-FCV-26-240. This fix backup for the setscrews, the feinction of the valve was not ef fected allowed the valves to pass St-166.6 and 51 158.1. and the possibility of an accident of a different type was not created. The mergin of safety specified in the TS was not reduced.

DCu x00152 The check vatve was reptoced with's needte va in' the M2 anatyrer The hydrogen anetyter system is not considered es contributing to .

FCR 5716 Panets 1-L-448 and 1-L-649 to belance the anatyrer bypass flow at the probebility of an accident white in Modes & end 5 therefore. -

higher pressure tduring wide-range calibration). the probebility of occurrence of an accident was not increased. The.

mergin of safety es defined in the basis for TS 3/4.6.4 was not i affected.

OCN x00184A A nameptate was placed on the AFWPT atternate feeder de breaker t>&x There was no increase in the prebebility for or the consequences of to provide adsinistrative control. If it was pieced in the en accident. The mergin of safety es described in any TS was not atternate position, att DBEs could not be mitigated. reduced.

DCN x00190 Drawing 479625-11, Revision M, was revised to show the correct The mergin of safety as defined in the basis for TS 3/'.6.4 was not tocations for the test connections of the A and 8 train hydrogen reduced. '

anatyrer sagte lines between the isolation contret vatwes and containment liner. Unique valve identification nwbers were assigned, and valve tags were hung in the field.

DCN x00192 Tao voltage on heat-trace transformers was changed from 50 to 60 The subject change is not described in the SAR nor did.it change FCR 6832 volts to maintain a cirunum process temerature of 3000F in the system function operability.

pressuriter loop seats. The heat-trace circuits are 4445-4465 and 444P-446P.

DC4 K00205A The C07 discharge tifes listed on Drawings 1, 2-45#639-1 and I, There was no incresce in the' prubebility for or the cons @ences of DCR 2257 2-45N639-3 were revised to egree with the actuet times listed in the an accident. The mergin of safety was not reduced.

CIR Attachment 1 to satisfy the requirements of CAOR SOP 871399.

DCM N0020TA This DCN revised the tocatien of the 2+4nch RSW supply connection This modification had no effect on any systee s safety function.

FCR 6747 for the War Room air-conditioning unit cooling weter stsspty. There was no increase in probability of or the consequence of en accident. The changes did not effect the desigs basis for any TS; therefore, there was no reduction in the mergin of safety.

DCW N00217 This ECW changed the tiee-delay senoint on ACC 1 from vendor's The security diesel design besis is not in the SAR or the TSs.

FOR 6860 setting of I second to 6 seconds to 4tininete the fiuisance starts of the security D/G.

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Page No. 13 CNANGES IN THE FActLITY - MODIFICATIO45 i

DCN x00227C A toad resistor was added to the instrument' toop for the Foxboro The involved instrtment loops provide an indication of flow in the DCR 2503 E110M transmitters to increase the circuit ispedance. This brought beckup Contret Room onty. There is no control function essociated the total circuit i g adance up to meet the specifications for the. with these loops, and they are non-Class 1E. There was no change in transmitters. A test point was added to provide a means fo the function of any safety-related system. The loops operate monitoring the circuit. exactly as designed fottowing the modification. There was m reduction in the errgin of safety es defined in the besis for TS 3/4.5.2, 3/4.5.3, or 3/4.3.1.5.

DCN x00238 This DCN reptoced Valve 2-70-743 with e new valve ecceptable for the nergin of safety es defined in the bests for TS 3/t.7.3 was not DCR 2383 throttling. reduced.

DCN x00239C ERCW drawings were revised to correctly show the facilities and The deactivation of the originot equipment did not beve an adverse corponents required to safety operate the plant af ter the AERCW and effect on plant safety. The new ERCW ptreing station et the river CCW ptrping stations had been repteced by the current ERCW pwping supptles att the ERCW required for safe operation and shutdown of station. This was a doeurentation-onty change. the plent.

DCN N00279 The old lifting d-vice for lifting the fuel transfer canal gate end ThenewliftingdevicehasahigherfactorofsafetyandmeetsNutiIG DCR 2378 the divider poet gate tocated in the spent fuel poet was reptoced 0612 requirementst therefore, the probebility of equipment metfune-with a new lif ting device with a safety factor of 10 to 1. tion was decreased. The mergin of safety was not reduced.

DCN x00299 Two supply isotation valves, two discharge isolation valves, four This modification did not etter the control logic or function of the DCR 2561 drain valves, arv3 four vent valves were added to the ERCW system. ERCW nor any other nuclear safety-related features. The addition of These vatwes are required to isolate EST cooters and attow repair en these new valves and piping inproved system configuration control MIC-affected welds, during normat maintenance and had no ef fect on safety.

ECM LO363 Drawing discrepancies on the Ret System were cc-rected es a result of the drawing chang *s were not addressed in the TSsf therefore, the FCR 4926R1 the Desim Basetine end Verification Program. margin of safety in the basis for any TS was unaf fected. '

ECN L5200 This modification added the Post Accident Sampling System capebte of This modification was made subsequent to the Three Mite Istend 2 obtaining designated liquid and gas samples during and after e incident. On April 24, 1984, NRC issued Amendment 35 to facility postutated event. The facitity was designed to protect personnet Operating License DPR-77 and Amendnent 26 to facility operating assigned to cetteet end handle the sapples. License DPR-79 for SON to authorire the operation of the Post Accident Saapting Systen. The ECN and essociated FCRs have been verified as field copptete.

ECM L5313 Modifications were made to the east and west steam valve rooms to the new roof is a blowout type like the previous one. The new roof DCR 0859 prevent reisture problems. The plywood thickness was changed, a is seismically gastified. Th* mergin of safety es definad in the vapor barrier and insulation was added to avoid moisture dansge arv3 basis for arry TS was not reduced.

high temperature exposure to the plywood, and the method of application of the roof weather coating was changad for greater flexibility.

ECN L5510 oualified electricat penetrations for personnet airtecks were The cargin of safety as defined in the basis for an TS was not DCR 1058 instatted. redixed.

ECW L5676 The existing 1/2-inch gate vatve that is used to drain the D/G This change replaced the existing watve with a more reliebte erv3 DCR 1234 rir-start tank was replaced with a valve tess prone to teekege. The equally or better-quatified valve. No new accident situation was replacement was equat to or better than the starv$ards used ty the - created. This change ensures that the preper pressure is meintained 1

I

W Page No.14 CHANCES IN TME TACILITY - PODIFICAft04S equipnent manufacturer. In the air-start tanks. The mergin of safety es defined in the -

basis for the TS for the operability of onsite power sources was not reduced.

ECN LST24 This modification revised the support design on mode 986 (1RMWs-503 There was no increase in the probebility for or the conseguances of DCR 1246 in Unit 1 and 2RMen-503 in Unit 2) and deleted the sw port at mode an accident. The mergin of safety as defined in the basis for any 987 (1RHRM-504 at Unit 1 and 2). TS was not reduced.

ECM L5739 The nethod for sa mling the boric acid'eveporator concentrate was with the old method, boric acid clogged the sa gte line. This DCR 1704 changed by adding a root valve to attow a simte local samlet This required persomet to enter the pockege room in order to obtain a was done by ed:fing an 18-inch piece of 3/4-inch pipe between sample samle. This modification eliminated the need to eater the isolation valves 1-43-300 and 1-43-301, and between 2-43-300 and evaporator pockege room, thus reducing radiation harards to person-2-43-301. net. The change was not covered by the basis for any TS: the-efore, the mergin of safety was not reduced.

ECM L5742 This modification retocated main control board Mendswitches 68-341A, The mergin of safety es defined in the basis for any TS wes not -

DCR 0799 68-341F, ard 68-3914 on Penet 2-M-4 in accordance with the penet reduced..

configuration shown on Drawing 47W605-10.

ECM L5827 Power 1ine carrier terminst and microwave channet equipment was This change was not governed by any TST therefore, the mergin of DCR 1705 provided for trensnission of interchenge readings to the atternate safety was not reduced.

Power Service Control Center at the Voltsiteer, Tn 500-kV substation.

ECM L5847 This ECW ached negator springs to gravity-operated fire demers and ' The instat tation of the negetor spring kits comtied with seismic UCR 1835 changad out gravity-oparated fire da m ers that would not accept ami 04 requiremants. Because the fire da m ers will perform the same negator spring kits. safety function, the margin of safety as defined in the basis for any TS was not reduced.

ECM L5865 This modification retocated levet Alarm LA-77-129 atorm override The margin of safety was not reduced because there ware no TS basis DCR 1495 switrh and tight from incere insturent room to outside conteiment. affected.

ECM L5902 This ECM removed the wire from Terminst 9 for Wetay LB459EX8 in The re==:rvat of the autometic beckup centret heater bank cutof f DCR 1633 Panets 1-R 55 and 2-R-55 for the automatic backe control hester signal did not degrade the operability centret or responsiveness of bank cutoff signal. The heaters in the pressurizer backw Grows 1C the pres 3u-irer for att events evetuated in Chapter 15 of the SAR.

and 2C will stitt turn on automaticatty upon pressurizer high tevet This change i m roved the reliability of the relay breaker. The or low pressure but now reouire manual action to turn them of f. The margin of safety as defined in the basis for TS 3/4.4 was not heater breakers were repeatedly opening and closing es conditions in reduced.

the pressure fluctuated, proving very destructive to the breaker.

ECW L5913 tevet Transmitters LT-3-172,173,174, and 175 were retoested from The function of the LTs was not affected. This change did not have DCR 1308 inside the crane watt to outside the crane vatt. any adverse effect on the Lis' response time or eccuracy.

Therefore, the mergin of safety was not affected.

ECm L5935 Security tighting was added in the isolation zone of the reduced. The esegin of safety es defined in the besis for any TS was not DCR 1698 protected area 'ncluding roofs of the Office Service Building and reduced. The probability of occurrence er the conseguences of an the Control Bui! ding. the area inside the Turbine Building adjacent accident or metfunction of equipment imortent to safety peeviously to the Control Building wett, and minimet area lighting on et 763 of evalueted in the SAR were not increased.

the Auxitiary Buitding near Door A207

Page me. 15 CMa#CES IN TwE FACittTY - M001FICATIO4S ECM L6006 Solid plates were removed from the top of the cabinets and were The pergin of safety was not reduced because no TS bests were DCR 1976 replaced with filter-backed gritts. affected.

ECW L6014 This ECN redesigned the actor bearings' cooling lines to be The margin of safety as defined in the basis for TS 3/4.T.6 (ERCW)

,DCR 1910 self-driving. replaced 1-inch SS pipe with 1/2-inch SS pipe, and or any other TS was ret reduced. .

removed the sntine strainer and orifice cap.

~ECM L6098 The whole body count equipment was removed to the clean laundry There is no TS covering the whole body comt ewirrent. The margin DCR 0987 storage aree. of safety was nnt reduced.

ECM L6105 This DCN designed truck access to the plant perimeter road from the These changes did not increase the probability of safety equipment DCR 1698 access road, provided truck access to the Office and Power Stores falture because of flooding caused by site runoff. It did not Building and revised the intersection at the ERCW pt.rping station , af fect any equipment located in the security area. There was no road, and relocated the plant perimeter road north of the 500-kV reduction in the nergin of safety.

switchyard. The temporary road from the office building to the switchyard was added to permanent road drawings, and the origie:at -

access road was restored as it existed prior to the Office and Power Stores Building being built. This DCN also revised the site fence at the north and south ends of the Office and Power Stores Building and revised the site fence north of the 500-kV switchyard. All of the areas where roads were added or relocated were graded art:!

drained as required. The DCu also reworued the area between the south end of the Office and Power Stores Building and the original gatehouse. This was done as peft of the ipplementation of the

" Power Block.*

Etw (6147 A set-screw locking device was instatted on the handwheet shaft- The locking device applies pressure to the side of the packing out DCR 1304 packing gland evt. The packing nut had been backing off slightly, to prevent it from moving. The addition of the locking device did causing a breach of containment, not af fect the seismic qualifications of the handwheel shaf t

. assedly. The change prevents future failures of the airlock leak-rate test. The change did ret alter the function of the handwheet shaft esse +(y. The sergin of safety as defined in TS 3/4.6.1.3 was not reduced.

ECN L61SO Additionet instrumentation required to monitor the air pressure in The edditional instrumentation is high-wality cowrcist grade and DCR 1156 the MCR during a CRI event was instalted. designed to equivalent seismic Category 1(L)B requirecents. The instrumentation is capable of operating following a loss of offsite power. The new instrunentation does not provide any nuclear safety-retated fmetion. The margin of safety as defined in TS 3/4.3.3.7 was not reduced.

ECN L6209 A fire protection blanket was wrapped around the conduit to the 2A There was no increase in the probabitity for or consewences of an FCR 2588 480V transformars as they pass through the 6900v S/D board Room 8. accident. No function or operation of equipnent was affected.

Also, conduit to the is 680V transformers as they pass through the .There was no re wetion in the margin of safety.

6900 S/D board Room A was wrapped, conduit that passes over the counting recre and through the seismic tunnet in the Auxiliary Building was wrapped, and conduit from CCS Pums 14 and 2A above the

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- Page No. 16 CMANGES IN TME TACILITY - PODIFICATIoms O,[

M CCS partiet barrier was wrapped. The 12-foot by 10-foot floor hatch -

between the el 749 2A 480V board room and the s 6900v S/D boerd room -

(et 734) was pyrocreted.

ECW L6231 Piping was rerouted on various systems to avoid interferences and Special requirements ensured that the new piping layout met att the -

FCR 2748 allow instattation of the new valve motor operators required by original design requirements. No functional or operational charac ~

NUREG 0588. Support structure for containment spray piping was teristics of any system we*e affected by this change. The mergin of modified to eliminate interferences with the instattation of the new safety as described in any TS was not reduced.

valve cperators. This change involved moving one structural mefber f rom the topside of the support to the underside. ' The new -

configuration did not invalidate the seismic qualifications of the suppert.

Etw L6235 Activities required to bring sequoyah wuclear Plant into futt Att changes met safety requirements, and no safety systems were DCR 2133 compliance with to CFR 50, Appendix R, were implemented by this EC4. dagraded. The margin of safety was not reduced.

ECM L6287 Setf-contained acgr tighting triits were instatted in areas The margin of safety as defined in the besis for any TS was not DCR 2075 manned for safe shutdown of the plant and for entrance and exit reduced.

routes to all fire areas.

ECW L6318 The fitters from the front and the back door gritts on anntriciators These modtfications did not degrade the function or performance of DCR 1076 cabinets were removed. the annunciators cabinets; therefore, the margin of safety as defined in the basis for any TS was not reduced.

EC4 L6323 This ECW updated hanger drawings for the MPTP piping to show present This doeunentation change did not adversely af fect or degrade any DCR 2079 gipe support rubers and locations. safety-related equipment. The possibility for any new accidents or.

metfunctions was not created. The margin of safety as defined in the basis for TS 3/4.7.71 or any other TS was not reduced.

Erw 16327 A documentation change was made to the RSV piping drawings to delete Thir was a documantation-only change. No physical changes were FCR 3132 the lawn sprinkters indicated by FCR 3132 that were never instatted made.

and show only those actustliy instatted in front of the of fice building. the parking lot, and the gatehouse.

ECM L6334 A locat disconnect switch was instetted in the 480v feed to the The margin of safety as defined in the basis for any TS i.as not DCR 1875 turbogenerator turning the gear drive-motor. reduced.

ECN L6335 The Megan optimac 2-pen trend recorders in the MCR were replaced This nodification did not degrade any safety-related function or DCR 2122 with new Tracor Westronics model 04E2 recorders. We cutting, feature. The new recorders perform the same function as the old welding, or wiring changes were retvired. These recorders are used recordars; therefore, the possibility for any new accidents or by the unit operators when performing trend analysis of various . malfunctions was not created.

plant parameters and systems such as re g erature, and generator and auxiliary power.

ECW L6429 The existing co m onent cooling water heat Enchanger B (tube and The margin of safety as defined in the besis for TSs 3/4.7.3 (CCS)

DCR 2170 shett) was replaced with two plate-type heat exchangars. - or 3/4.7.4 (ERCW) was not redxed.

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Page No.17 Cn44CES IN TME FACILITY - MODIFICATIONS ECW L6452 This ECM provided the 125V de vitat control electrical Penetrations The ftections of the penetrations was not degraded or changed by OCR 1972 30 and 37 with overcurrent protection by adding fuses instatted in' this ECN. The margin of safety as defined in the basis for series with the cirTuit breakers. TS 3/4.6.1 was not reduced.

ECN L6488 Pressure-differential transmitters on EGTS were reptsced with No safety-related function or feature covered by the plant TSs was DCR 0972 qualified transmitters, adversty affected by this ECN. The margin of safety as defined in the basis for any TS was not reduced.

ECW L6495 Valve 1-68-446A (an inline angte valve) was reptsced with a The new configuration should result in increased retlebility of the DCR 2191 straight *through gate valve. This valve is between the condensate instrument and less maintenance. The new valve and configuration pot and one of the pressure transmitters of f the RCS pressurizer meets or exceeds the originst design requirements. The margin of (PT-68-340). safety as defined in the basis of TS 3/4.3.1 and TS 3/4.3.2 was not.

reduced.

ECN L6500 Lower corpartment containnent RMs RE-90-273 and 274 were moved above The margin of safety as defined in the basis foe TS 3/4.3.3 or any DCR 0972 the flood tevet of contairunent. other TS was not reduced. -

ECM L6519 This modification removed the tube-lane blocking devices frem the The mergin of safety defined in the basis cf the TSs is pressure DCR 1967 steam generators and revised the " Mechanical teprovement tinits 1 boundary integrity between the primary and secondary systems in the and 2 Steam Generato- Modifications Manual" to detineate same. steam generator. Removing the tube lane blocking devices did not reduce the margin of safety.

ECM L6521 The existing motor, pinion gea*, and worn shaft gear for TCVs 1 and No safety-related function or feature covered by the plant TSs was DCR 0972 2-FCV-62-61 were replaced. degraded by this modification. The margin of safety as defined in the basis for TS 3/4.6.3 n any other TS was not reduced.

ECM L6540 This modification replaced the motors for limitorque-eperating The margin of safety as definad in the basis for TS 3/4.5.2, DCR 0972 valves 2-FCV-74-1 and 2-FCV-74-2. 3/4.5.3, and 3/4.9.8 was not reduced.

ECN L6544 Drawings changes deleted jurpered-cut limit switches, simplified The margin of safety as defined in the basis for any TS was not FCR 3874 schematics, added design information, corrected drawing discrepan- reduced.

cies. and reduced field wiring for valves being qualified under 10 CFR 50.49.

ECM L6560 This is a documentation-only change. The piping in the ERCW No physical or functional changes were made to the ERCW system under DCR 1124 drawings for the supply piping to the upper containment vent Cooler this modification, and it did not affect flow requirements to other 2B is carbon steel instead of stainless steet. essential cog enents within the ERCu system. The margin of safety as defined in the basis for TS 3/4.7.4 was not reduced.

ECW L6570 The design pressure and temerature for the charging and Si ptry This modification involved docunentation-only changas encept for the FCR 3758 suction piping was revised to 220 psig and 2000F. The o*awings were replacement of the Pis. The systems were not functionalty changed revised to show the correct set point of 220 psig for relief Vatves or adversety af fected. At t af fected emponents were confirwd 1 and 2-62-505 and I and 2-63-511. Pressure Indicators 1 and acceptable for the new design pressure and te g erature. The 2-62-102, 1 2-62-105, and 1 and 2-62-109 were replaced with Pts that probability of an occurrence or the consequences of an accident were are rated for the correct design conditions. not increased. The margin of safety as defined in the basis foe TS 3/4.1.2, 3/4.5.2, and 3/4.5.3 was not reduced.

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Page No.18 CNANGES IN TNE FACILITY - M001FICAft0NS ECN L6582 The motor pinion on valves 1-FCv-63-93 and 94 was replaced with a Tests were performed to verify that no safety-related function DCR 972 23-tooth motor pinion. The worn shaft gear was replaced with a associated with these valves were adversely affected. No safety- ~

37-tooth vorn shaf t gear. The brake coil and friction disc were related function covered by the plant TSs was adversely affected by-

. removeo, and the brake housing was replaced. This modification; this ECN. The margin of safety as defined in the basis for TS

- increased the stroke time from 10 seconds to approximately 15 - 3/4.9.8 was not reduced.

seconds. This eliminated the need for the steam-motor brakes that were not environmentally qualified.

ECM L6589 This ECW replaced temerature Switches 1 and 2-T5-74-43, 44, 45, and This change did not affect any system eperation; therefore, the DCR 0972 46 with qualified switches. margin of safety as described in any TS basis was not reduced.

ECN L6611 The brake colt on limitorque motor-operator valves 1 and 2-FCV-3-33, The margin of safety was increased as the actuators can operate at a DCR 0972 47, 87, and 100 was replaced. tesser voltage than was required before the replacement.

ECN L6651 Terminal blocks inside J9s and tepanst J9s were coated by Riv-3140, The margin of safety tes defined in the basis for TSs 3.6.1.4, DCR 0972 and the terminal block was replaced by a Raychem nuclear-qualified 3.6.1.8, and 3.7.1.1 was not reduced. -

splice for Transmitters 1-PS-3-140A and 2-PS-3-1404.

ECM L6665 The existing motor brakes were removed and the operator was regeared The margin of safety as defined in the basis for TS 3/4.6.3 was not DCR 0972 so that the motor brakes are not required for valves 1 and reduced.

2-FCV-62-063 and 1 and 2-1.CV-62-132 and 133, For 2-FCV-74-033 and 035. the operator was regeared and the motor was replaced with a stower-speed mtor not requiring brakes.

ECM L6676 This changa routed separate cables to the motor-brane coils of the The margin of safety as defined in the basis for TS 3/4.8 or any DCR 0972 MFlvs. other TS basis was not red eed.

ECN L6680 This ECN reputted Cables 1PM64711,1PM64511,1Pm690tl, and 1PM783tt No safety-related systems covered by plant TSs were degredad by this OCR 0972 with cables qualified in binder $0NEG-012, erand-Rex. modification; therefore, the margin of saf ety as dafined in the

- basis for any TS was not reduced.

ECN L6686 This ECM removed the existing motor brakes and regeared the operator Af ter regaaring, the valves were tested for fast closure as defined DCR 0972 so that motor brakes ware not required on Valves 1 and 2-FCV-63 001, in SAR Section 6.3.2. Therefore, the margin of safety as dafined in 005, 006, 007, 003, 011, 047,and 048. And on vatwes 1-FCV-74-33 and the basis for any TS was not reduced.

35, this change regeared the operator end replaced the motors with stower-speed motors that do require brakes.

ECN L6712 The normal feeder cable for the TDAFu pum controt circuit was The margin of safety as defined in the basis of TS 3/4.7.1.2 was not DCR 2246 replaced and the TDAFu pt.rp room de vent fan motor-starter circuit ' reduced.

was receb bd.

1 ECM L6724 This ECN Disconnected electrical power to 1, 2-FSV-67-188 and 1, The associated FCys uitI perforte their safety ftnetion with the DCR 2259 2-FSV-67-190 to prevent short-circuiting solenoid valve frem disab- electrical power renoved. No margin of safety was redsced.

ting RHR ptro room Cooter fan.

ECM L6731 This ECW eodified beam-end comection for Typical 47A056-85 to a No safety-related function covered by the TSs was sdversty af fected DCR 2259 rotter-type connection to permit thermet growth of the beam in the by the new aesign; therefore, the margin of safety as defined in the -

event of an accident, which results in high enviremental tem era- basis for any TS was not reduced.

tures.

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Page No.19 CPANGES IN THE FACILITY - MQ)lFICATICMS

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ECW L6744 variances for typical conduit supports that were identified during The margin of safety as defined ir. the basis for any TS was not FCR 4561 NSRS survey of supports in MOV board rooms for System 363 were reduced.

evaluated and analyzed to docurent their acceptability.

'ECM L6762 This ECM performed en analysis, a stwort evaluation, and documenta- No safety-related system covered by the TSS was adversely of fected DCR 2259 tion of the effects of the correct snubber orientatios of stsverts by this modification. The mergin of safety as defined in the basis listed in SCR SCwCEB8615. Drawings were revised and reissued to for any TS was not reduced.

reflect the correct orientations and toads.

ECu L6779 Norqualified termination blocks were replaced with QJalified termia The mergin of sefety as defined in the besis for acy TS was not DCR 0972 nation blocks as listed in SCR-SONEOP8622. reduced.

ECM L6783 The 10 f t-tb motor en the timitorque SMB-00 motor operator for valve The mergin of safety as defined in Table 3.6-2 was not reduced.

DCR 0972 2-FCv-70-87 was replaced with a 15 ft-tb motor and replaced the spring pack.

ECM L6785 T-drains were instetted in limit switch co m artments of motor- The margin of safety as defined in the besis for any TS was not DCR 0972 operated flow-contret valves listed within Sequoyah Enviremental reduced.

Qualification Binders MOV-001 through 005.,

ECM L6790 The mechanical piping penetrations in the watts and floors between The probability of a fatture because of this change was not DCR 2259 the Turbine Building and the Control Building and between the increased. The new seats were designed and tested to eeet the Auxiliary suitding and the Turbine Building, including the Service requirements to accomplislt all required safety functions. This Building, were seated against a moderate energy line-break flood in modification ensures protection from flooding, pressuritation, and the Turbine Building, et 706. fire. There was no decrease in the mergin of safety.

ECM L6795 Transient suporession networks for FSV-43-201, 202, 207, and 205 The retocation of the transient su m ression networks to a mild DCe 2259 were relocated to MOR Panet M-10. envircrynent prevents the problem of failure because of radiation exposure. This chsnge maintained the operability of the equipet and systems required for the detection of hydrogen gas during -

post-L XA conditiens. The mergin of safety as defined in the basis for any TS was not reduced.

ECW L6808 Conduit fittings and conduits were seated in the Auxitiery Building The mergin of safety as defined in the basis of-eny TS was net DCR D2259 below postulated flood levels and in the main steam valve vaults reduced.

below the maxinn flood level.

EC4 L6811 Cable PS140 was instatted from the 120V CYC distribution Panet A4 to These modifications protect the cable and did not tdversely af 8ect DCR 2259 heat trace Circuit 73P.. The cable was routed in conduit peraltet to system coeration.

the abandoned Cable PS12 in the Auxiliary Building. Sensors in Co m artnent 3C of the 680V S/D boards were replaced with a tower-rated sensor. The circuit breaker trip setting was lowered f rom 300 percent to 125 percent of the futt toed current.

ECM L6817 This ECW replaced the Cottins 516 analog terminal with a new digitat This new equigment at tows for better system performence and DCR 2251 microwave tercrinat en the 8630 link. rettability in terms of mittipteming, signating, nonitoring, and utilizing of channels. No safety-related function covered by the plant TSS was directly or indirectly af fected.

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'Page No. 20 CMANGES In THE FACILITY - MODIFICATI04S ECM L6828 This nradification seated the identified electrical conduit penetra- The margin of safety as defined in the basis for any TS was not DCR 2259 tions up to et 706 to prevent propagation of Turbine Building reduced.

-flooding into the Control or Auxiliary Building.

ECN L6846 Instatted covers and/or solid bottoms on channetized and train trays The margin of safety as defined in the basis for any TS was tvst DCR 2259 tocated in the spreader and auxiliary instrunent rooms. reduced.

ECW L6879 To correct a deficiency identified by SCR SQ4CE88699 and an' The modification was imtemted as'eg a reinforceme*tt pad fabel.

DCR 2259 engineering evaluation by CEB, a reinforcement pad was eMed to the cated from the same materiet as the hse metat. The fabrication ewf fabricated 18-inch laterat located adjacent to Valve 2-70-501. This instattation of the pad conformed to ASME Section Mi reair was done to reietforce the joint area of the lateral, main line requirements. There was no increase in the probability of attachtnent to provide an adequate stress margin to comly with occurrence or the conse7Jences of an accident. The margin of safety seismic Category I r g irements. was not reduced.

ECM L6881 The transient suppression networks associated with 2-FSV-6d-394 and.This modification eliminated.a potentist f ailure of the reactor DCR 2259 395 in the reactor vesset head vent system were relocated from a vessel head vents. Circuit functions remained unchanged, and systet harsh envirorvent (Reactor Building) to a mild environment (MCR). operation was unaffected. The TS 3/4.4 does not a*fress the reactor-vesset head went systeN therefore, the margirt of safety remains the same.

ECW L6890 This modification charmf the fuses on the 480V circuit for the The existing fuses were replaced with higher vettage rated fuses or FCR 5027 centrot room MvAC system and reactor MOV boards from the 300v rating tower ancierage fuses so that the centret circuits are better to 600V rating to provide a better protection for the circuits. The protected. The existing fuse blocks were replaced with a new type fuse-block type was changed to accomodate the new fuses, and the so that the new fuses would fit. The circuits are Class 1E and meet electrical fuse tabulation and other af fected drawings were revised. seismic Category 1 requirements. The TS does cot address the fuses or the fuse t>tecks in this modification. The ourpose of the .  :

modification was to better protect the contret circuits and prevent circuit failure caused by overloads.

ECM L6893 Systen,314 air regulators were replaced with qualified regulators. There was no increase in the possibility of or the consequences of DCR 2259 The originat regulators were Class :t and did not have adaquate cA en accident. The margin of safety was not reduced.

doctrientation.

ECW L7093A Cartm steet piping that had been <ismaged by erosion / corrosion The margin of safety was not reduced by this modification.

FCR 5259 downstream of M N regulator valves was replaced with SS piping.

Also, the 2 1/2-inch piping associated with high-pressure MSR operating vent near vatve 14CV-5-18 was replaced with SS.

ECM L7095 The shield building staeve seats were modified to ensure a boundary the probability of a failure because of this change was not DCR 2259 for fire, water, and pressure retention. Above et 724, water - increased because it did not af fect any comonent capable of retention was not required. initiating an accident evaluated by the SA4 The desigan functions-of the new seats were not changed by this eiodification.

ECm L7098A This modification replaced existing emptosive detectors in personnet the margin of safety as defined in the basis for any TS was not access controt portats with ITI Entry Scan Marit !! Detectors reduced.

Modet 85.

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.x Page No. 21 CnAWGES IN TME FACILITT - MODIFICATIO45 4

ECW L7118 Pulsation dameners were added to pressure Switches 2-PS-3-1214, FCR 5311 1219, 1210, 139AA, 1399, 139D, 1444, 1449, and 1440 in the AFW system.

ECN L7156 Nonqualified MDAFWP discharge pressure Gauges 1-PI 3-1228 and To i mtement this modification, the instatted Pts were removed -

DCR 2259 1-PI-3-1323 were replaced with qualified seismic 1(L) pressure - before the new Pts could be instatted. As a result, the facility as shown in SAR Figure 10.4.7-7 was temorarity changed. There was-gauges to ensure pressure bouridry retention.

also a potential breach of pressure boundary during i mtementation.

This modification was performed, co mteted, inspected, and tested before the plant ascended to Modes 3, 2, or 1. Final plant -

configuration was not changed.

ECM L7185 This ECW replaced cables ard relocated electrical equipment and - The results of these modifications did not change the function of DCR 2295 conduit (containing to CFR 50.49 cables) located in the east and any of the equipment tmst did promote enhanced system reliability.

west MS valve vaults that were identified as being located over or The margin of safety as defined in the basis for TS 3/4.7 eM 3/4.8 near " hot spot" areas. was not reduced. -

EC4 L7208 This ECN reassigned 480V power supply for hydrogen Anatyrers 14-A This mdificat ien enhanced the reliability of the power supply to DCR 2259 and 18-8 from reactor vent Boards 1A-A and 18-8 to 480V reactor Mov the hydregen anatyrers because the reactor MOV beards are becked by Boards 1A2-A and 182-8. the 0/Gs or offsite power. The censequences of a estfunction of equipment i m ortant to safety previevsty evaluated in the SAR was not increased. The margin of safety as defined in the basis for TS 3.6.4.1 or any other TS was not reduced.

ECM L7245A This was one of several ECWs that cettectively served to restore The replacement of the motor and veneaxist fan of the Reactor DCR 2259 test performance to the Reactor Building tower comartment cooting Building tower compartment cooling units results in their perform-units for Unit 1 and upgraded those units to CSSC requirements. As ante being w graded to provide sufficient recirculation of the more corrective action to CACR SOT 870349, these units were reclassified _ dense air of the Reactor Building tower comartment following use of as safety-related equipment with post-accident functions. LCV fan the containment spray system. This change did not increase the

- assenbtles were replaced. The fans had been seismic Category 1(t) probability of an accidnet or increase the consequences of a and driven by a 50 hp non-Class 1E meter. These were replaced with metfunction of equipment. The margin of safety for TS 3.6.1.5 was seismic Category 1 fans driven by 75 hp Class 1E motors. not reduced.

ECW L7269 This modification changad existing feeder and branch circuit fuses The margin of safety as defined in TS 3/4.8.2 was not reduced or on the D/G remote control circuits with different rating such that affected.

the new fuses were property coordinated. It also peevided a new relay for blown-fuse annunciation on applicable circuit.

ECM L7277 Fuses / fuse blocks and circuit breakers were instatted in series with The response time test penetration circuits are not safety related.

DCR 2259 response time test circuits for penetration protection. .'They are not described in the SAR and the addition of fuses did not impact nuclear safety.

ECM L7279 This ECW authorized the performance of physical modifications to This modification did not alter the function of any systcc but-DCR 2293 various pipe supports to qualify these supports, as required by att enhanced the system reliability by ensuring adaquete seismic epplicable design criteria, as designated in the modification qualification. The possibility of an accident or matfunction of a criteria. Calculations and design drawings were issued to reflect different type was not created.. This modification did affect the seismic qualifications of the affected support (s). This work safety-related snubbers, so TS 3/4.7.9 did apply.

was the result of the regeneration of " test" civil calculations.

Snubbers 2-n34-9?? and 2-H47-61 were affected by this ECN.

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_ .L Page No. 22 CHANCES IN THE FACILITY - PODIFICATIONS ECN L7284 This ECN authorized the performance of physical modifications to ' This modification ensured that the seismic requirements of the DCR 2293 various pipe supports in Systems 62, 67, 68, and 74 to qualify these af fected piping systems will be met as required in att applicable supports as required by att applicable design criteria as denoted in design criteria. Overalt system reliability was creanced b/ this .

the modification criteria. Calculations and design drawings were modification. The modifications on the two safety-related snubbers issued to reflect the seismic qualification of the affected were performed in compliance with TS 3/4.7.9.

supnort(s). This ECW modified. safety-related Snihbers, 2-M36-290 and 2-N34-934 ECN L7317A The existing instrtsnentation port cottsun asseety was removed and. The safety function of the instrumentation port cottses assedly (and -

the new Westinghouse design instrumentation port cottori asst +bty was associated thermoccuptes) was smettered. The margin of safety as installed in five places. defined in the basis for TS 3.3.3.7 and 3.4.10 was not reduced.

ECN L7326 This ECN aut.eorized the performance of physical modifications to This modification did not alter the function sf any system and DCR 2293 various pipe supports in System 67 to qualify these supports as ensured the seismic design is in co mtience with the specifications '

required by att applicable design criteria as denoted in the identified in the SAR. Modifications made to safety-related modification criteria. Calculations and design drawings were issued snubbers by this ECN were performed in comtience with TS 3/4.7.9.-

to reflect the seismic qualification of the affected support (s).

These modifications were the result of the regeneration of " tost" civit calculations.

ECN L73318 This modification replaced containment isolation check valves that The probability of the occurrence or consequances of an accident failed to pass containment isolation teak-rate test with motor- were not increased bacouse it did not affect any passive co m onant operated butterfly watves and added pressure check valves between capable of initiating any accid-nt evaluated in the SAR. The margin the new motor-operated valve and the existing motor-operated vatve. of safety as defined la the basis for TS 3.6.1.2 was not reduced.

ECN L7340s The modification added four new supports and modified one existing This modification ensures that the safety function wilt be achieved DCR 2259 support om ducting for the lower co m artment cooling system. This after a seismic event and enhanced the operability of the conters permitted the ductwork to be certified as seismic Category 1 and related to TS 3/4.6.2.2.

environmentatty qualified to function af ter a steam line break.

ECN L7346 The normal feeder cables for Unit 1 TDAFWP control circuit and the The AFU system is not required for plant operation in Podes 4 or 5.

DCR 2246 cables for TDAFUP room de vent fan motor and starter circuit were The final system configuration eesulting from this modification was replaced with larger cables. The enclosure for the fan motor- not diffeeent from the system as described in SAR Section 10.6.7.2 starter was replaced with a larger enclosure to accoerodote the and figure 4.7-7. Therefore, the possibility for an accident or targer cables and their splices. metfunction of a different type than any previously evaluated in the SAR was not created. The margin of safety as defined in the basis for TS 3/4.7.1.2 was not reduced.

ECN L73499 This modification replaced the temporary rthber hose from the CDWE There was no increase in the probebility of or consequances of an DCR 2152 to the floor drain cettector tank. The rthber hose was replaced accident presiously evaluated in the SAR. The change did not affect with hard pipe and improved the reliability of the system. any equipment i m ortant to safety. The margin of safety was not reduced.

ECN L7361C This nodification replaced CCS containment-isolation check valve This modification ensured contairrent integrity was maintained, and DCR 2320 with motor-operated butterfly valve and changed valve rueer from - the margin of safety defined in the basis for the TS was not 1-70-692 to 1-FCV-70-141.- reduced.

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0 Page No. 23 CHANGES IN THE FACILITY - MODIFICATIONS ECN L7363 This ECN authorized the performance of physical modifications to These sodification did not alter the function of any system and witt DCR 2293 various pipe supports in Systems 1, 62, 63, 72, and 74 to e ntify ' ensure the seismic design is in conpliance to the specifications -

these stoports, as required by att applicable design criteria, as identified in the SAR and design criteria. The possibility for an denoted in the modification criteria. Calculations and design accident of a different type than previously evaluated was not drawings were issued to reflect the seismic qualification of the ~ created. This modification may have af fected safety-related effected support (s). This work was the result of the Unit 1 snuthers; therefore, TS 3/4.7.9 would apply.

Rigorous Analysis Program and the regeneration of " lost" civil calculations.

ECM L7378A Containment isolation (Class B) check valves 1-67-562A, B, C and 0 This change provided positive isolation of the ERCW line sg ptying DCR 2333 were replaced with electric motor-operated butterfly valves. A cooling water to lower containment ventilation cooters and set the pressure-retleving check vatve was added between the new motor- seal-teakage test required by 10 CFR 50 Appendix J and TS LCO operated valve. Tag nun 6ers were revised for electric motor- 3.6.1.2. Therefore, the margin of safety as defined in the basis operated valves in the Unit 1 supply lines located in the annutus, for TS 3.6.1.2 was not reduced.

System 67.

ECN L7383 This ECM changed the RCP undervottage relay setpoint from 90V to The new trip setpoint is in the conservative direction, and as such FCR 5819 93.6v to ensure a prisnary voltage setpoint of 5022v. It did not create the possibility for an accident of a different type than any evaluated previously in the SAR. TS Tabte 2.2-1 was revised in accordance with TS change TVA-SON-TS 8T-18 to incorporate a change in the RCP undervottage relays setting from 4830V to 5022v.

The margin of safety as defined in the basis fos the TS was increased.

ECM L7386B Photoelectric fire detectors were added to the annutus. The addition of the fire detectors in the existing fire zones FCR 6866R1 increased the protection in the area monitored. This activity did not have en adverse impact on safety.

ECN L7387A This change replaced and/or repaired the tnacceptable Class 1E The minimum margin of safety as described in the TSs was not FCR 6717R2 10 CFR 50.49 scope Raychem sptices for Unit I restart-required reduced.

electrical equipment in accordance with M&Al-7,

• Cable Terminations, Spticing, ard Repairing of Damaged Cables".

ECN L7394A This modification instatted pressurizer safety-relief valves with .The reliability of the safety valves under this configuration is DCR 1808 steam trim internals and locfted open loop seat drain Valves equal to or better than that of the previous configuration. The 2-68-566, 2-68-567, 2-68-568, and 2-68-4444. margin of safety was not reduced.

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Page No. 24 CMANCES IN THE FACILiff -

TEMo0RARY MODIFICAil045-e TACF DESCRIPi104' SAFETY

SUMMARY

This alteration did not involve a change in' the facility from

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0-89-0005-077 0-PIS-77-422 AND 0-PIS-77-425 The setpoint for 0-PIS-77-422 and 425 was changed from 30 psis that descrit ed in the SAR.

to 38 psig. The setting for 0-PCV-77-428 and 429 was changed to 35 psig. -5 0-89-0032-062 BORIC ACID EVAPORATOR PACKAGE A AND 8 CONCENTR4fE PUMP 1 Amo 2 This alteration did not change the facility from that This alteration replaced concentrate ptrps ard associated described in the SAR or TSs.

motors and electrical connections on evaporator Packages A and 8 with Attis Chalmer ptrps.

0-89-0038-090 0 FS-90 212 LOW FLOW SAMPLE SWITCn this alteration did not involve a change in the facility as this alteration changed the Proteus Industries Modet 100- described in the SAR or a radwaste system.

tow-flow switch to a Fluid Com onents incorporated Model FR72 2 switch.

0-89-0057-317 6.9 KV COM T4 BOARD A LOAD FEEDER TO 480V WATER SUPPLY This alteration did not involve a change.in the facility as TRANSFORMER A described in the SAR or any TS.

This alteration connected the feeder cable for the old ERCW pums to the 6900V bushing on the cepenon Board A water supply 6900/480V transformer and extended the feeder cable to the old ERCW ptrps.

0-89-0059-067 0-67-FMP- A- A, 8-A, C-8, D-8, 2-67-STRw-2A, AND 2-67-STRW-28 Att affected TS LCOs were corptied with; therefore, the margin.

This TACF engaged one of the old ERCW Pupps (A-A or B-A) of safety as defined in the besis of the f5 was not reduceL*.

inservice to stpply ERCW Header 2A and (C-5 or D-8) inservice to supply ERCW Header 28 while maintenance was performed on the A2 A-A or 82 8-8 new ERrW strainers. The change aise removed the flag and note from 1, 2-47W845-1. The TACF instatted the bearing cooting water line to the old ERCW pirps from service water and manual operator on the old ERCW Strainers 2A and 28.

0-89-0060-077 CHECK VALVE 0-VLV-77-687 -

The margin of safety as defined in the bwsis for TS This atteration removed the internals from check Valve 0-vLv- 3/4.11.1.1, 3/4.11.1.2, and 3/4.11.1.3 was not reduced.77-687 0-89-0061-077 CHECK VALVE 0-VLV 77-6704 This alteration did not create the possibility of an accident This alteration removed the valve bonnet and internats,- of a different type than any evaluated previously in the SAR.

instatted a modified bonnet fitted with a 2-inch diameter The margin of safety was not reduced.

nipple, and isolated the valve and 2-inch butt hose.-

0-89-0066-400 PLANT STRUCTURE . The instattation of the fence did not change any system dasign This alteration instatted a fence with a gate at et 706 or functional requirement; therefore, the SAR was not changed railroad bay (column A11X) to enetose radiation demineratirer by this atteration. This alteration was required to leptemmt -

pre-fitters to prevent unauthorized entry. the requirements of TS 6.12.

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Page No. 25 CHANGES IN THE FACILITT - '

. TEMPORARY MODIFICATIONS

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0-87-0069-063 _1, 2-LT-63-50, 51, 52, 53 ..

. . This atteration did not change the facitity f ront that The thereestats and strip heaters for RUST trancmitters 1 and described in the SAR. -

2-tT-63-50, 51, 52 and 53 were reterminated.

0-87-0070-400 EAST VALVE ROOM MISSILE PROTECTION SMIELD, ELEVATION 714 AND This atteration did not affect the operation of the retief-706 UALL OPENINGS; WEST VALVE ROOM WALL OPENINGS ELEVATION . opening; did not af fect methods of ensuring cortptiaxe with 706. .

TS: did tiot ef fect any process or procedure outlined.

This atteration instatted Visqueen (plastic sheets) on the sumarized, or described in the SAR.

exterior f ace of the East valve Room watt missite protection shield and watt opening and en the exterior face of the west ~

valve room watt openings.

0-87-0071-067 PIPING UPSTREAM OF 1-67-702, 1-PIPG-67 Total failure of the 1/2-inch nippte will not pre e t tecu This TACF addad a clanp and piping support on 1/2-inch piping from performing its safety funtion. Therefore, the m.wstn et upstream of the vent valve 1-67-702 on the Train 8 ERCu ~ safety was not reduced. -

discharge header.

1-82-0077-087 1-utS-87-21, 22, 23 AND 24 This alteration did not involve a change in the f acility or This atteration cleared the alarm for 1-NA-55-66-27 and 28. instruction as described in the SAR.

DCRP-1100 was written for a permanent modification.

1-88-0023-030 tNIT 1 LFPER CONTAINMENT SPACE MEATER TPERMOSTATS The contairinent heating requirceents are not devritet m tns A replacement thermostat wee installed for att four of the SAR.

upper containment unit heaters.

1-87-0025-006 1-FT-6-107 . .

This alteration did not change the f acility f rv t r .t - '

This TACF rescaled 1-FT-6-107 to accomodate existing 12 inch described in the SAR.

flow nozzle flow characteristics.

I'-87-0036-063 1-TE-63-25A AND 1-TE-68-37A This at teration did not involve a char 9e in tn - ' . t et, *e for 1-TE-68-25A, field wires 6A-1, 64-2, 6A-3, and 64-4, on that described in the SAR.

terminal Stock A in Rack 6 were removed and retocated. For 1-TE-63-37A, internst Wire 68-4 from 69-4 to 68-3 on terminat -

Stock B in Rack 6 was relocated.

1 87 0 % 0-001 PRESSURE TRANSMITTER SENSING LINES The additien of heat trace to textetter e"#- t Heat tracing and insulation were added to portions of sense not invalidate any SAR de>cript fors ,an t t N . 6 t ines caposed to cold weather. involved were non-CSSC/r m lE.

1-8?-0052 055 wanCI AfoR v1NDou xa 55-SC-1 CIRCUtf .

This etteration did net. change the fxility to t' This TACF removed the fuses in 1-FUZ-30 831Als in Panet described in the SAR.

1-R-75.

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1-8? 0068-006 1-PDIS 6-106B This alteration did not change the fx itity te -

This change revised the setpoint at which 1-PDIS-6-1068 closes described in the SAR.

-1 tCV-6-1069 to prevent HDT 3 purp runout.

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. Page No. 26 -CHANGES IN THE FACILITY .

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TEMPORARY MODIFICATIOgS 1-89-0073-400 ' MISCEttANEOUS STRUCTURE (400) - MAIN STEAM PRESSURE TRANSatIT- The addition of the insulation did not inumet the accident TER SENSING LINE .

analysis of Chapter 15. The SAR and TS were not affected.

This alteration instatted te m erary insulation over the main steam pressure transmitter sensing Lines 1-PT-t-9A, 98, 204, and 20s located in the east valve room near the pressure relief penets.

2-83-2002-068 2-TE-68-56A AND 2-TE-68-568 This atteration did not involve a change in the facility from The shield lead in Junction Box'2928 from Terminals 1085 cnd that described in the SAR.

10311 was lifted and insulated.

2-89-0034-001 PRESSURE TRANSMITTER SENSING LINES The addition of heat trace to transmitter sensing lines did Heat tracing and insulation were added to portions of sense not invalidate any SAR descriptions, and the co m onents lines exposed to cold weather. involved were non-CSSC. -

2-89-0044-068 2-TE-65-14A AND 2-TE-68-148 This alteration did not involve a change in the facility fron This atteration re % internal Wires 28-1, 28-2, 28-4, and that described in the SAR.

shields from Terminals 28 1, 28-2, 28-4, and 28-5. The internal rack wires were relocated to terminal Stock 28 on f eminals 7, 8,10, and 11 in Rack 2-R-2.'

2-89-0047-00o 2-Pcts-6-1068 . The setpoint for PDIS-6-1068 was not specified in the SAR.

This change revised the setpoint at which 2-PDIS-6-1068 closes The function of this switch or resultant ef fects are not 2-LCV-6-1069 to prevent NOTP 3 runout. Safety eetated.

2-89-0049-085 ROD C04 TROL POWER CABINETS - STATIONARY GRIPPER TEST Po!NT The margin of safety as defined in the basis for any TS was This alteration connected Stationary gripper test points to not redaced, the reat-time comuter acquisition data logger recorder.

2-89 0050-053 2-vtv-63-565 .

This alteration did not iepact or redxe the margin of safety The broten packing gland follower on 2-vLv-63-565 was replaced for any TS.

with fabricated split-packing gland follower.

~2-89-0062-007 'GtAND STEA9 CONDENSER DRAINS- .

The Turbine Gland Seating System is a nonsafety-related Class The 2-inch diameter overflow drain line was uncoupled from the N system. The design function of this system was not offected stand steam condenser and a *teca and three 2-inch manual by this activity.

vatves were instatted.

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1-80-0152-079 2-81-2341-087 0-81-0467-062 1-82-0062-002 . 2-81-2342-087 - 82-0258-067 1-82-0103-234 . 2-81-2343-087: 84-0084-059 1-84-0057-085 2-81-2344-087 87-0004-234 1-84-0081-062 2-83-2022-079- 0-87-0023-244-1-85-0070-030 2-84-2016-062- 0-87-0033-014 1-86-0006-068 2-84-2039-003 0-88-0001-012 2-87-2001-030 0-88-0010-245:

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A01/ REY DESCRIPTIO4 SAFETY

SUMMARY

A01-06 SMALL REACTOR COOLANT SYSTEM LEAtt (MODE 1, 2, or 3) OR SMUTDOW4 LOCA The procedure revision did not increase the probability of or conse-REV 024 (MODE 4 OR 5) . quences of an accident. The mergin of safety was not reduced.

This revised the containment rurge shutdown step to refer to SCI-30.2, "Cnntainment Purge System Operation."

A01-07 PRcBABLE MAXIMUM FLOOD The procedure revision did not increase the probebility of or REY 014 This revision was made in conjunction with the bienniet review and consequences of an accident. .The margin of safety was not reduced.

enhanced the procedure, deleted tsinecessary steps, corrected verbose description of various vetves, L.A changed various titles. It also deleted cutting a hole in contairmat in accordance with RIMS 825 881116 007 and NRC Comitment (C.1), added closing Penetration X-54 in accordance with safety Evaluation M!-3.4, R4, and RIMS 825 881024 ~

584, and added a comitment list.

L A0!-14 LOSS OF RMR SHUTDOW4 COOLING .

Various meintenance and inspection activities performed during REV 009 This revision was a generet formet changed from a two-colum format shutdown on RCS require coolant levet in the RCS to be towered below to a standard A01 format and added enhancements for mid-loop the reactor vesset flange. The RMR, which is used to cool the operation contingency action. reactor during the mid-loop operation, is susceptible to air

. ingestion / air binding if the levet in the RCS drops too low. This change did not increase the probability of an accident previously evaluated in the SAR. There was no decrease in the mergin of safety.

A01-15 LOSS OF COMPO4ENT COOLING WATER - 04tf5 1 and 2 CCS heat Exchanger 8 was replaced during the 12C3 refueling outage.

REV 011 This revision provided t'ne necessary procedurest guidance to align- CCS heat Enchanger 8 provides cooling to Train A engineering safety the CCS Pwp 2A-A to the Unit 1 Train A freader. This procedure safeguard equipment. During this heat exchaneer outage, Unit 2 requires nine valves to be locatty operated to perform this Train A CCS toads were cooled by the CCS heat Exchanger A. During alignnent. These actions are required to reinitiate CCS flow to the this configuaation, a design basis LOCA could occur. Aligrenent of spent fuet pit cooling heat exchanger. the CCS to staply spent fuet pit cooling reouires operators to perform tocal valve operations. A01-13 requires nine valves to be positioned. Therfore, to ensure the operators do not exceed their

'10 CFR 50 CDC 19 timit, a specific mission dose calculatier: was performed based on 77 hours8.912037e-4 days <br />0.0214 hours <br />1.273148e-4 weeks <br />2.92985e-5 months <br /> post-LOCA ewposure rates. The results were doew ented in $o4-50S2-0070 (825 890113 900). fnese actions were reviewed to determine if they constituted conpensatory mea-sures. Evatustion doeweats show that there are suf ficient personnel to perform att required actions. The actions do not inpoet minimum shift staffing levels. -The actions will not invalidate So4's ECCS analyses docunented in SAR Sections 6.3 and 15.4.1. The margin of safety was not reduced.

A01-31 ABNORMAL RELEASE OF RAD 104CT:vE MATERIAL This revision did not increase the prebability of or consequences of REY 0% This chang- revised the containment purge shutdown step to refer to any accident previously evaluated. The margin of safety was not 501-30.2, " Containment Purge Systen Operatlon." reduced.

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'Page No. 23 CMA4GES TO PROCEDURES AS DESCRIBED IN TME SAR ES/REV DESCRIPTION SAFEff

SUMMARY

E-0 REACTOR TRIP OR SAFETY INJECT 104 Rearranging the order of steps ensures the opposite tnit's purge REY 006 This revision rearranged the steps and clarified the intent of systam is shut 63n before transitioning to another event-based ,

stopping the opposite unit's purge system. procedare. Clarifying the intent of how to shut down the purge system is consistant with the NE safety evaluation. Based on the evaluations, the change had no effect on the previously established .

mergin of safety.

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E-0 REACTOR TRIP OR SAFETY 14 JECT 104 The DBAs in the SAR evaluated were the spurious SI and the small end REV 008 This procedare was revised to reflect changes in the RRR pwp 'large bresi LOCAs as defined in SAR Chapters 13.2, 15.3, and 15.4.

operability requirements for shutoff head in accordance with The only SAR accident requiring RMR as an ECCs subsystem for P-QIR-NE-MEB-SOP-PM 89042, R0. This P-0!R documents the maxistso . mitigation of the event is the targe break LOCA. The procedare time attowed for RHR pu m operation at shutoff pressure (11 change did not af fect system performance from that described in SAR ^

minutes). Step 15 of EO was revised to allow only are pwp to be Chapter 6.3.2.2. The probability of failure of the RNR system was placed in standby following 51 and added a precautionary statement not increased by this procedurst change since at least one train of that requires the operator to restart the pw p ptoced in stan & y if RPR is irrediately avaltable for injection in accordance with E-0.

operating ptre trips. In addition, Step 29 was revised back to the Since the design pereneters, system functionet reg;irements, and WOG original ERGS. Westinghouse has reviewed and concurred that Chapter 15 analyses were not adversely effected by this proceduret this procedure change protects the RMR punps ahlte providing change, this change did not degrade the performance of the RPR or operator direction to maintain minimum injection capability from the any other safety system.

RHR ptspps.

ES-0.1 REACTOR TRIP RESDONSE. The function of this equipment has not changed. This was a REV 010 This revision changed the S/G pressure controller setpoint to procedural change only and did not involve any change to the percent instead of pressure in accordance with CAOR 880580 815. .

facility. The margin of safety was not reduced.

The low Ta yg setpoint for Unit 2 was revised frera $540F to 55000 in accordance with WP M969-01.

ES-1.2 TRANSFER TO RNR CONTAINMENT $*JMP . There was no increase in the probebility of an accident previously REY 006 This procedure provides the necessary instructions for transferring evaluated in the SAR Section 15.4.1. Doewentation exist to ECCS and containment spray suction to the centainnent stsup. denonstrate that 70 CFR 50.46 and 10 CFR $0 Appendix K requirements Revision 6 added Step 2, "Close RHR Crosstie," snd Step 14. " Check are satisfied. The consequences of an accident were not increased.

CCS Status," in Appendin A because of CCS heat Exchanger B outage The probability of a malfunction of equipment irportant to safety modification. was not increased. Actions req; ired ensure that $34's ECCS analyses remain unaffeeted.

ES-1.2 TRANSFER TO RMe CONTAl wENT SUMP The deletion of Steps 2 and 4 returned the instruction to its REV 007 This revision deleted Steps 2 and 14 that had been added in Revision pre-CCS heat enchanger modification configuration.

6 to accomodate the CCS heat Exchanger B outage. The outage /modifi-cation has been conpleted.

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SUMMARY

1-SI-SXP-062- BORIC ACID TRANSFER PUMP 1A-A QUARTERLY OPERA 8ILITY TEST - (MIT 1 This test will have no adverse i m act on safety.

002.A Revision 0 (swersedes $1-304.1) changed the responsible section REV 000 aM imtemented a new flow path because of CAOR SQP 890385, it incorporated the use of the thit 2A-A BATP to smply recircula-tion flow to Unit 1 BIT. The proposed test line m attows adequate time to test the 1A-A BATP white SIT recircutation is supplied by the Unit 2A-A BATP.

2-St-SXP-062- BORIC ACID TRANSFER PUMP 28-8 00ARTERLY CPERABILITY TEST - U4tT 2 This test will have no adverse i m act on safety.

002.8 Revision 0 (supersedes S1-304.1) changed the responsible section REV 000 and imtemented a new flow path because of CAOR SQP 890385. It incorporated the use of the Unit 2A-A BATP to supply recircula- ,

tion flow to Unit 1 BIT. The proposed test lineup attows -

adequate time to test the 1A-A BATP white SIT recirculation is supplied by the Unit 2A-A BATP.

St-002 SMIFT LOG - tMITS 0,1, and 2 The proposed activity did not adversely imact the safety of the REV 064 This revision changed the method and location of obtaining heat plant.

ICF-89-0752 sink tem erature and deleted rotting everage method of cateuta-tion, using 24-houe average.51-011 REACTIVITY CONTRot. SYSTEMS MOVEABLE C04 Trot. ASSEwSLIES This change in the Si does not affect safety. The testing is done REV 015 This test is performed by placing the futt-tength (shutdown and within the shutdown margin attowed by the TSs. The governing ICF-39-0613 controt) rods on bank seteet,. moving each bank.until the procedures and associated TSs ensure that the consequences of an appropriate movenent has been verified on both the grots 6 3 accident are not increased. The purpose of the testing is to position indicators and the rod-position indicators, and return- identify malfunctions in the futt-length shutdwn aM controt rods.

ing to the original position to verify att futt-tength rods are Any malfunctions are corrected prior to restoring the subject bank operable. The test was modified to attow movement of the to eperable status. The margin of safety as defined in the basis shutdown and control bank reds in Modes 3, 4, and 5 to an for TS 3/4.1 (sorstion Controt) is ensured by the performance of appropriate position white testing the rod control system. St-30, " Shutdown Margin - Units 1 and 2,* in conjunction with this test. Furtherinore, the performance of St-11 ensures comtlance with TS 3/4.1.3 (Moveable Control Assee6 ties), hence the margin of safety

'is maintained.

SI-033 ERCW VALVES SERVIC14G SAFETY RELATED EQUIPMENT (COPMON) - tMITS The new plate-type heat exchangers have significantly more thermet REV 032 0, 1 and 2 capacity than the old tube and shell so that both ERCV and CCS are EC4 L6429 replaced the existing ttbe and shett-type CCS heat capable of fulfitting their design requirements as stated in SAR.

Exchanger B with two plate-type heat exchangers in carattet. The The failure of this co m onent is equivalent to the failure of the new plate-type heat exchanges were tabeled 2A1 and 2A2. The original heat Exchanger 8. There was no increase in the probability procedure was revised to add valves in accordance with WP6429 and for or consequences of an accident. The margin of safety was not WP12742. reduced.

St-135 EGTS CLEANUP SUBSYSTEM AUTOMATIC START TS 3.6.1.8 requires that the EGTS be operable for a mit in % des 1 REV 013 SI-135 was revised to incorporate as Sit requiring test personnet through C. St-135 is performed white the applicable unit is in Mode to irrediately close the fottowing EGTS Air Cleane Subsystem , 5 or 6. - During Mode 3 or 6, the EGTS is not required to perf orm any Valves FCV-65-7, 9, 29, 50, and FCO-65-45 and 46 for Unit 2 in safety-related function and is not required to be operable. .The

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m Mode 5 and 6, up3n a Phase A cont 91 ment isolation signet from instruction change enwres that the ECTS is operable for the Unit 1 white in Modes 1 through 4; or FCV-65-8, 10, 30, 51, and opposite unit in Modes 1 through 4 The change to 51-135 did not FCO-65-26 and 27 for Unit 1 in Mode 5 or 6, upon a Phase A increase the probability of an accident previously evaluated in the containment isolation signal frorn Unit 2 white in Modes 1 ' SAR. There was no increase in the consequences of an accident. The through 4. margin of safety as defined in the basis of TS 3.6.1.8 was not reduced.

St-137.2 REACTOR COOLANT SYSTEM WATER INVENTORY This change will not prevent safety-related systems from performing ICF-89-0758 This change will attow for smalt negative triidentified RCS their intended safety functions.

testages to be recorded and accepted. The minimum testing time requirement of two hours will remain. If unidentified teskage after two hours is negative, an additional hour of testing will be performed.51-164 TESTING SETPOINT OF SAFETY AND RELIEF VALVES (ASME SECTION NI, Mold orders are not required for att valves. The footroom now REV 010 CATEGORY C VALVES) .

performs calibration verification tests. Post calibration verifica-ICF-87-0138 This ICF added *N/A' provisions for hold orders, changed tion test points checked need only to coincide with actual test Instrument Maintenance to Toolroom, changed post-calibration runs. The general revisions were made because of organizational and verification test points checked, and did a generat update of the program changes and new instructions that had been written. There procedure. was no increase in the probability of an accident, and the margin of safety was not reduced.

$1-166

SUMMARY

OF VALVE TESTS FCR ASME SECTION NI ! UNITS 0, 1 and 2 The testing is required by AS84E Section Nt to shew that the REV 020 This revision added requiremmts to allow vatves to be tested in co m onent witI function as required. Stroking of-the valves in ICF-87-0816 Mode 3, made acousticat monitoring mandatory and added necessary Mode 3 witt not degrede the reliability of the watves.

precautions. .

S1-166.32.4 TURBINE DRIVEN At!*ILIARY TEEDuATER PUMP CHECK VALVE TEST DURING The procedure serves to confirm the ability of the plant to remove REV 000 HOT STAND 8Y - UNIT 2 . decay heat in the event of an accident by ensuring the check valves ICF-87-0823 This revision changed the method of testing check Valves 2-3-871, in the AFu wilt pass the minimus flow required by the chapter 2-3-872, 2-3-873, and 2-3-874 frere verifying that they att can anstysis. ' The procedure testing ensures that this test does not pass 220 gattein simultaneously to verifying that two of the four introduce any new challenges to the system comonents that are can pass 220 gat / min white the flow through the other two check outside of the systems design basis by establishing an upper limit valves is approximately 220 gat / min. Then the two check valves on the flow.

previously not tested are tested to verify that they can pass 220 gat / min.51-166.36.1 DIESEL STARit4G AIR VALVE TEST TOR D/G SET 1A-A, TIME FRAME A - Deleting the St requirements to tiae the 0/G during each performance REV 001 UNIT 0 did not affeet safety.

ICF-89-0653 This change deleted the step that verified the D/G started within 10 seconds. This was a result of TS Change 57.51-166.36.2 DIESEL STARTING AIR VALVE TEST FOR D/G SET 1A-A, TIME FRAME B - Deleting the si requirements to time the 0/G during each performance REV 001 UNii 0 did not affect safety.

ICF-89-0647 This change deleted the step that verified the 0/G started within 10 seconds. This was a result of TS Change 57.

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SI-166.36.3 DIESEL STARTING Alt VALVE TEST FOR D/G SET 2A-A, TIME FRAME A - Deleting the SI requirements to time the D/G during each performance 1 REV 001 UNIT 0 .

did not affect safety.

ICF-89-0648 This change deleted the step that verified the D/G started within 10 seconds. This was a result of TS Change 57.51-166.36.4 DIESEL STARTING AIR VALVE TEST FOR D/G SET 2A-A, TIME. FRAME 8 - Deleting the SI requirements to time the D/G during each performance REV 000 tMIT 0 _ ,

did not affect safety.

ICF-89-0643 This change daleted the step that verified the D/G started within 10 seconds. This was a result of TS Change 57.

S1-166.36.5 DIESEL STARTING AIR VALVE TEST FOR D/G SET 18-8. TIME FRAME A - Deleting the 51 requirements to time the D/G during each performance REV 001 tmIT 0 did not affect safety..

ICF-89-0649 This change deleted the step that verified the D/G started within 10 seconds. This was a result of TS Change 57.

St **!.1,.4 DIESEL STARTING AIR VALVE TEST FOR D/G SET 18-8, TIME FRAME 8 - Deleting the $1 requirenents to time the D/G during each performance REV 001 UNIT 0 .

did not affeet safety.

ICF-89-0650 This change deteted the step that verified the 0/G startc3 within 10 seconds. This was a result of TS Change 57.

S1-166.36.7 DIESEL STARTI6s AIR VALVE TEST FOR D/G SET 28-8, TIME TRAME A - Deleting the S1 regairements to time the 0/G during each performance REV 001 UNIT 0 did not affect safety.

ICF-89-0651 This change deleted the step that verified the D/G started within 10 seconds. 'This was a resutt of TS change 57.

S1466.36.8 DIESEL STARTING AIR VALVE TEST FOR D/G SET 28-8, TIME FRAME 8 - Deleting the SI requirements to time the D/G during each performance REY 000 UNIT 0 did not affect safety.

ICF-89-0652 This change deleted the step that verified the D/G started within 10 seconds. This was a result of TS Change 57.51-166.41 REACTOR ttEA3 VENT VALVE STROKE TEST CURING A REFUELING OUTAGE - There was no change in the probability of system failure. The RCS will continue to perform its safety function with the stroke testing REV 002 UNITS 1 and 2 ICF-87-0817 The purpose of this revision was to add requirements to attow . of the head vent valves.

valves to be tested in Mode 3, correct organizational titles and delete CC review on data package sheet in accordance with 51-1 SI-167 FIRE READER VALVE LINEUP INSPECTION .

The safety of the plant was not corpromised by these changes because REV 023 This revision specified a new method of verifying the proper the operability of components ipportant to safety was not degraded, position of Vatwes 1, 2-67-501 A, 8, and C. It revised the valve and the verification procedures necessary to ensure proper valve listing sequance to increase inspection ef ficiency. It listed aligment were enhanced.

isotation Yatve 0-26-1616 to the a .1 M additional D/G build-ing sprinkter system to be seated closed. It aMed 0-26-2114, 0-26-0683, 0-26-2335, and 0-26-2336 to be inspected. -It '

corrected typing errors and added a note to clarify that 1, 2-26-554, 555, 560, and 561 are normatty stosed, since they are not part of the preferred fire punp suction path.

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'Page No. 32 CMANGES TO PROCEDURES AS DESCRIBED IN THE SAR St-172 FIRE SYSTEM TESTABLE VALVE CTCLING The safety of the plant was not coaceomised by these changes because REV 013 This revision deleted testing of Vatves 1, 2-6b501-A, 8, ard C, the operability of corcenents incertant to safety was not degraded, and added testing of 0-26-1616, 2335, and 2336 and the verification procedures necessary to ensure proper valve aligmient were enhanced.

SI-172 FIRE SYSTEM TESTABLE VALVE CYCLING - tJWITS 0,1 ard 2 Alte ng one of the two 12-inch suction valves for each fire pwp to '

REV 014 fnis revision made provision that one of the two 12-inch suction be inoperable tntil an appropriate time to repair / replace the valve valves for each fire punp from condenser circulating water (CCW) wilt not prevent the fire pumps from being able to take suction from ptry wells may be inoperable, provided the inoperable valve is the forebay of the CCW purping station as described in TS 3.7.11.1.b repaired / replaced during the next scheduled or unscheduled outage (Ref. 3). naving one of,two suction valves.to each fire pwp of sufficient duration. inoperable did not alter the fire pwe's ebility to obtain its normal suction path from the ERCW ptro wells behind the CCW pwp -

i.elts. The ntater of available suction flow paths for each fire ptrp would be decreased from three to two during the time period that one of the two valves is inoperable, but this arrangament does not decrease the ruter of flow paths required by the FSA4 or TS. -

St-187 CONTAIN*ENT INSPECTION - tMITS 1 and 2 The effect of storing stuminue inside containment above

• hat which '

REV 010 This revision supports a change to SAR Table 15.4.1-14 and is recognized by the SAR is to create an unknown or unanatyred 15.4.1-97.51-187 cnd S0466 witt be changed to contret transient condition goverfting hydrogen production. -Initial calculations attriinun material in containment and to maintain total aluminum provide a worst-case evaluation of the amount of hydrogen that would inventory to unounts less than those specified in SAR Tabte be given of f from the attnirus corrosion reaction during the 15.4.1-14.

post-LOCA period. This value is added to values from other sources of hydrogen generaticn (plus a safety margin) to develop design basis for the CGCS. The CCCS is still able to perform.its safety function. TS Basis 3/6.6.1.C ensures that the maxinus allowed contairment pressure (12 psis) will not be enceeded. As the reelsed calcotation has shown, the design basis is not exceeded for hydrogen

- mitigat6en. Therefore, no margin of safety was reduced.51-247.900 ENGINEERED SAFETY FEAftJRE RESPONSE TIME YERIFICATION - LMITS 1 The design basis events that ig ese safety-related performance-REY 011 AND 2 requirements on the turbine-driven pJrtions of the AFWS are toss of This revision was made to attew justification for continued main feedwater, feedwater line or steam line rtoture, LCCA, operation since the system TS and SAR requirements ere met if the cooldown, toss of off-site power and less of att ac power (station 3-inch TOAFW LCYs are 50 percent open within 60 seconds even if blackout). For the events that impose the most stringent flow they fait to stroke futt open within 60 seconds. demand on the ArUS, a total of at least &&O gat / min s=>st be delivered within one minute to at least two intact (non fautted) stears generators. The TS requirement can still be met without the 3-inch LCYs being futty opened. The margin of safety was not reduced.

S1-276 AtNILI ART FEEDWATER AUTOMATIC CONTROL VALVES OPERA 8ILITY - (MITS The function of the 4-inch LCVs was not changed and the system REY 015 1 and 2 ~.

requirement of delivering &&D get/ min to two intact S/Gs within one White performing 51-276, the response time of the ESF equipment miinute can still be met. Tenporary renoval of the 2-inch b/ pass LCY actuation for one of the MDAFPs exceeded the manieun time of 60 from the AFW flow path does not prevent the srstem from parforming seconds. This evatustion revid SI-276 to afford justification its safety function. 'This change did not reduce the margin of for continued operation by denonstrating that the system TS and safety.

SAR requirements are met (i.e., &&O gal / min to two intact S/Gs within 60 seconds) if the 4-inch LCVs fait to stroke futt open

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within 60 seconds.: This evetustion justified fifting the teeds_ -

-to the pressure switch of any 2-inch bypess LCV (PS-3-145i 156, w 1M. and 171) that transfers the tevet controt from the 4-inch - ' s-

, ' valve to the 2-inch bypess valve. - 1 SI-304.1 80RIC ACID TRANSFER PUMP 1A-A QUARTERLY OPERAstLITY TEST - tatt 1 - This change bed no adverse ispect on safety. Att actions ete- -

- REV 000 This ICT chen2ed the test method to align 84TP 2A to steply the i consistant with the reQJirement of the TSs. ' -

ICF-89-0602 Unit 1 BIT during performance of the test. This was done to-minimize the amount of time the BIT is without recirculation.

The cancellation of TS Interpretation 74 mode the present. ~ -

procedure inadequete.

S t -673 . REACTOR COOLANT SYSTEM tEVEL YERIFICAft04 USING SIGNTGLASS 04 - There was no increase in the probability of an occurrence er the - ~ '

REV 012 TTG04 MOSE - U41TS 1 and 2 . consequences of an accident. The mergin of safety was not redxed.

ICF-89-0352 This ICF adhd guidance to atlow emintenance on the RCS during <

partial drain doun of the RCS without entering a reduced -

inventory levet.

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'Sil/REV DESCRIPTION . SAFETY SLPMARY ' '

Sit-138- ' COLLECT!the CF TLO'J AND PRESSURE DATA ON COMPONENT COOLING WTER MEAT The effect of the simtated differentist pressure of the plate heat

-REV 000 EXCt' ANGER "B" - UNIT 2 - .

exchangers would decrease the amowit of flow to att A-train Unit 2 :

This STI was written to establish the method of obtaining . . CCS coui;rnent aM reduce.their design capacity only daring periods informational data on the pressure and flow characteristics of the ' 'when CCS is throttled beyond the margin that exists in the system.- -

Unit 2f Train A CCS flow by simtating the expected differentiat- Since the throttled vetves can be reopened, any lost flow can be' pressure of'the plate that Exchangers 2A1 and 2A2 before to their instantaneously regained before the heat toad is recognized by the

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instattation to replace the ttbe aM shett-type heat . Exchanger B.' 3 - system. ' There was no increase in the probability. for or ..

. consequences of an accident. The margin of safety was not reduced. ,

ST1-138 COLLECTION OF FLOfJ AND PRESSURE DATA CN COMPONENT COOLING WTER MEAT This revision was made because the necessary data could not be REY 001 EXCM1EER *B" - tulIT 2 . . .

.cottected using valve 2-FCV-70-15 as the throttle valve. 'This' --

This revision changs! the designated throttle valve identified in ' revision was within the scope of the criginal. safety evaluation that.

the procedure to fatve 2-FCV-70-16.md changed the precaution for was written for 571-135, Rev 0.

7000 gat / min with one pw p operational to a M that this is appl u ble when in LOCA aligment.

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SAFETY SLM".ARY PROCEDURE /R DESCRIPTION EVISION i

This change did not affect the safety function of the CRD or its Al-5 SHIFT AND RELIEF TURNOVER This instruction was changed to require that points associated with ability to interrupt power to CRDM to attow any withdrawn rod to REV 051 the CRDM air temperature be checked once per shif t (Points 1-129 and falt into the cere and thus perform its intended safety function.

1-130, Loop TR-56-1P129,1P130) to ensure that the tmperature does The u rgin of safety was not reduced.

not exceed the design value of 1640F. This was in effect while flow Switch 1-FS-30-83A/B was being repaired.

The margin of safety as defined in the basis for any TS was not C01-1 PLANT START-UP FROM COLD' SHUTDOWN TO HOT STANDBY REV 085 This revision was written to provide operators with the flexibility reduced.

needed to operate the AFW system. It added general operating -

instructions and the system operating instruction (501-3.2) to encourage operators to batch flow to the S/Gs instead of establish-ing steady low flows when rneup was required.

The margin of safety as defined in the basis for any TS was not GO!-2 PLANT START-UP FROM HOT STANDSY TO M!NIMUM LCAD REV 067 This revision was written to provide operators with the flexibility reduced.

needed to operate the AFU system. It added generat operating instructions and the system cperating instruction (S01-3.2) to encourage operators to batch flow to the S/Gs instead of establish-ing steady tow flows when makeup was required.

White equignent~ redundancy and single-f ailure criteria are imacted, C01-3 PLANT SHUTDOW FROM MINIMUM LOAD TO COLD SHUTDOWN REV 44 The procedure was revised to add a new section to attow the stopping the acceptability of these irpacts has been evaluated aM accepted of the RCPs white in Mode 3.

This section gives guidance needed for by the NRC, and thus the plant remains within the licensing basis.

Analyses have been perfonaad in accordance with SAR Section 15.3.4.

na: ural circulation white maintaining Tavg. This was necessary because of repairs to the CCS 3-inch flex hose supplying the RCP 3 .The RCS design parameters are not affected by this activity. The core cooling capability is not degraded in accordance with SAR upper bearing oil cooters. Section 5.5.2.3.2. The reactor coolant pressure boundary is not affected by this activity because operability in Mode 3 is below design limits of the reactor coolant piping. The reactor core parameters are not af f ected since the RCS will be borated to shutdown conditions.

This change only provides for Mode 3 RHV valve calibration and does IMI-68 REACTOR COOLANT SYSTEM .

not affect any system parameters since these valves will be isolated This ICF to IMI-68 changed only the mode in which RHV Valves REV 24 ICF-89-OS24 FSV-68-396 and 397 can be calibrated. This change included frcn the RCS and PRT. The changes do not increase the probability of occurrence of any DBA. The RCS vent paths are futty esintained requirements to close the block and manual isolation (at least one within the constraints of TS 3/4.4.11. The margin o' safety was not manual isolation) valves before stroking for this calibration.

reduced.

The changes made would not cause a failure in the piping pressure M&Al-11 FABRICATION, INSTALLATION,ANDDOCUMENTAT!C[NOFSUPPORTS,P! PING retention bomdary or any damages to system comonents, equigrent, REY 020 SYSTEMS AND STRUCTURES ATTACHED TO SEISMIF CATECORY I STRUCTURES bg

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, d714 Page No. 36 ' CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR _ 3 This revision to Section 5.2 clarified the special requirements / pre- or structures that would prevent safe' shutdown. Therfore, the cautions and the applicability of the special requirements /precau- margin of. safety as defined in the basis for any TS was not reduced.

tiens in order to render a pipe support inoperable for nodification, 8 maintenance, enhancement, or inspection. '

M1-13.3.3 REPLACEMENT OF LOCKOUT SVITC!i 86/8/8 FOR SHUTDOWN BOARD 2A-A - -This i mtementation of the'toekout retay contact Jw pe.~ in accor .:

ICF-SS-0524 This ICF added steps to place a jtrper across toekout relay contact dance M1-13.3.3 with the ICF-0524 changes did not adversty af fect 86/8/8 in the emergency feeder breaker close circuit during the safety, performance of the instruction. This ensured the D/G would be

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available automaticatty to supply 2A-A shutdown board through Breaker 1922 If required daring the performance of the instruction.

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PI-SXX-032- AUX 1LIARY BUILDING CONTROL-AIR QUALITY TEST This instruction provides testing to ensure air quality is main-0020 This procedure was written to perform air quality testing for - tained within the required specifications and did not affect the REV 000 essential and nonessential control air systems in the Aunitiary margin of safety as defined in the basis for any TS. Additionally, Building. This procedure verifies control air quality is within this procedure helps decrease the probability of loss of controt .

manuf acturer's specifications for all pnetnatic equipment 'that is air.

either safety-related or relied upon to perform a safety ftriction.

PI-SXX-032- TURB1kE SUILDING CONTROL AIR QUALITY TEST The margin of safety as defined in the basis for any TS was not 001.0 This revision was written to perform air quality testing for reduced.

REV 000 nonessential control air system in the Turbine Buitding and conpty with NRC Generic Letter 88-4 recomendation to periodically monitor air quality of the Control Air System. 4 SMI-0-317- APPENDIX R - CASUALTY PROCEDURES . There was no increase in the probability of or consequences of an 18 This procedure revision was made to change the text and block accident previously evaluated in the SAR.- This procedure revision .

REV 002 diagrams to reflect how the rerouting of Cables 1PL2601A and was made based on worlt done by ECM L71523 and its safety evaluation.

ICF-89-0708 1PL26044 by ECM L71523, FCR 7693, interact with cable 1PL45129. There was no decrease in the margin of safety.

S01-3.2 AUXILIARY FEEDuATER SYSTEM .

The margin of safety as defined in the basis for any TS was net REV 047 This revision was written to provide operators with the flexibility reduceJ.

needed to operate the AFU system. It added generat operating instructions and the system operating instruction (Sci-3.2) to encourage operators to batch flow to the S/Gs instead of establish-ing steady low flows when makeup was required.

S01-203.1 690v and 480V SkUTDouW BOARD DC CONTROL BUS TRANSTER PROCEDURE This activity did not reduce the margin of safety as defined in the REV 000 This procedure was written to provide conditions for operation basis for any TS. Outage time for safety-related systems is within precautions and instructions for transferring the vital 125V de TS LCOs, and the performance of this Sot did not increase the system supplied control busses (normat and emergency) on the 690V . probability of a matfunction of equipent important to safety.

and 480V shutdown board from its normal supply to atternate supply and back to norrat supply without causing an ESF actuation.

Sot-55-OL4A ANwtMCI ATOR RESPONSE AUtf LI ARY CONTROL ROOM-D/G PA'tEL .There were no adverse effects on safety. The procedure change had xA-55-L4A This safety evaluation was written to establish the minisun jacket'. no unacceptable ef fects on the operation of the D/Gs and in m way -

REV 002 water and tube oil te m erature requireren- for D/G operability. The imedes their ability to perform the rensired safety functions.

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'9 F 'Page No. 37 CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR This procedure change was based on the vendor's recomendation.

ICF-89-0683 procedure changes redefined operability as a function of itbe of t tecperature rather than jacket water tem erature. The procedure revision indicates the correct operability timits.

There were no adverse effects on safety. The procedure change had

$01-55-OL48 ANNUNCI ATOR RESPONSE AUX 1LI ARY CONTROL ROOM'D/G no PANEL unacceptable effects on the operation of.the D/Gs and in no way -

XA-55-L4B This safety water and evatustion tube oft was written temperature to establish requirement for the D/G mininun jacketThe impedes their ability to perform the required safety functions.

operability.

REV 002 This procedure change was based on the vendor's recomendation.

ICF-89-0686 procedure changes redefined operability as a function of tube oft temperature rather than Jacket water temperature. The procedure -

revision indicates the correct operability limits.

There were no adverse effects on safety. The procedure change had S01-55-OL4C ANNUNCI ATOR RESPONSE AUXILIARY CONTROL ROOM D/G PANEL no unacceptable ef fects on the operation of the D/Gs and in no way XA-55-L4C This safety water and evaluation tube oil was written te@erature to establish requirement for the mininun D/G jacketThe impedes their ability to perform the required safety functions.

operability.

REV 002 This procedure change was based on the vendor's reewriendation.

ICF-89-0684 procedure changes redefined operability as a function of tube oil .-

tempera *ure rather than jacket water te@ erature. The procedure' revision indicates the correct operability limits.

There were no adverse effects on safety. The procedure change had S01-55-Ot40 ANNUNCIATOR RESPONSE AUXIL!ARY CONTROL ROOM D/G FANEL no unacceptable effects on the operation of the D/Gs and in no way XA-55-L4D This safety evaluation was written to establish the minicus jacketThe imedes their ability to perform the required safety functions.

water and tube oil tenperature requirement for D/G operability.

REV 002 This procedure change was based on the vendor's recomendation.

JCF-89-0685 procedure changes redefined operability as a function of tube oit tecperature rather than Jacket water tenperature. The procedure revision indicates the correct operability limits.

There were no adverse effects on safety. The procedure change had SOI-55-0M26 ANNUNCI ATOR RESPONSE DIESEL GENERATOR CONTROL This safety evaluation was written to establish the minimum jacket no unacceptable effects en the operation of the D/Gs and in no way XA-55-26A REV 007 water and tube of t tenperature requirement for D/G operability. The lepedes their ability to perform the required safety functions.

This procedure change was based on the vendor's reccurendation.

ICF-89-0679 procedure changes redefined operability as a function of tube oft temperature rather than Jacket water tenperature. The procedure revision indicates the correct operability limits.

There were no adverse effects on safety. The procedure change had i

S01-55-0M26 ANNUNCI ATOR RESPONSE DIESEL GENERATOR CONTROL no unacceptable effects on the operation of the D/Gs and in no way l

XA-55-26B This safety water evaluation and tube was written oit tenperature to establish requirement for the D/Gminimum jacketThe impedes their ability to perform the required safety functions.

operability.

! REV 006 This procedure change was based on the vendor's recomendation.

l ICF-89 0680 procedure changes redefined operability as a function of tube oft temperature rather than jacket water tenperature. The procedure revision indicates the correct operability limits.

There were no adverse effects on safety. The procedure change had S0!-55-0M26 ANNUNCI ATOR RESPONSE OtESEL GENERATOR CONTROL . no unacceptable effects on the operation of the D/Gs and in no way xA-55-26C This safety water evaluation and tube was written oil temperature to establish requirement for the D/Gminimum jacketThe impedes their ability to perform the required safety functions.

operability.

REV 006 This procedure change was based on the vendor's recorriendation.

ICF-89-0681 procedure changes redefined operability as a function of tube ott temperature rather than jacket water temperature. The procedure revision indicates the correct operability Umits.

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Page No. 33 CHANGES TO PROCEDURES AS DESCRIBED IN Tf" $AR

• a So!-55-0M26 ANWNCI ATOR RESPONSE DIESEL CENERATOR CONTROL .

There were no adverse effects on safety. The procedure change had-XA-55-260 This safety evaluation was written to establish the minisun jacket no unacceptabte ef fects on the operation of the D/Gs and in no way REV 005 water and tube oil te m erature requirement for D/G cperability. The imedes their ability to perform the required safety functions.

ICF-89-0682 procedure changes redefined operability as a function of tube oft This procedure change was based on the vendor's recomendation.

temperature rather than Jacket water temperature. The procedure revision indicates the correct operability limits.

501-55-1M5X ANWNCIATOR RESPONSE t mtementation of this change did not degrade the avaltability or A-55-5B This procedure was revised to clarify instructions and give the reliability of the af fected systems or corponents. The margin of REV 012 operators better guidance on when to initiate the shutdown of an RCP safety as defined in the basis for any TS was not reduced. ~

given teakof f rates from the number 1 seat in excess of the alarm .

setpoint of 4.8 gal / min.

501-55-1MSX ANWNC!ATOR RESPONSE This change did not af fect the safety function of the CR0 or its A-55-5C This instruction was changed to indicate that TACF 1-89-52-055 ability to perform its intended safety function. The margin of RGV 010 temerarity removed Fuses 1-FU2-30-83A/B in Panet 1-R-75 to clear safety was not reduced. .

comom alarm annunciator Window XA-55-5C-1 for the CRDM cooters low air flow until 1-FS-30-83A/B was repaired.

S01-55-2M5X ANNUNCIATOR RESPONSE .

Imtementationofthischangedidnotdegfadetheavailabilityor A-55-58 This procedure was revised to clarify instructions and give the rellebility of the af fected systems or corponents. 'The margin of REV 004 operators better guidance on when to initiate the shutdown of an RCP safety as defined in the basis for any TS was not reduced.

given leakof f rates from the nunber 1 seat in excess of the alarm setpoint of 4.8 gat / min.

501-62.1 CHEMICAL AND VOwME CONTROL SYSTEM This activity permits the plant to enter this configuration when REV 045 The procedure was revised to provide the capability to terminate maintenance is required on the normat'RCS tetdown header. While ICF-89-0723 normat RCS tetdown through the CVCS regenerative heat exchanger and i mtementing this procedure, provision will be made to ensure the letdown heat exchanger and use the excess letdown heat exchanger as RCP seat's design parameters are not exceeded in accordance with en alternate tetdown path during normal power operations. Impte- SOls. This activity is within the design basis of the system menting the procedure revision may require the termination of normat components. Westinghouse has evaluated the im act of operating in RCS charging throug5 the regenerative heat exchanger and the use of the proposed configuration in relation to thermal stresses, and the' the alternate charging path via the RCP seal injection. However, thermal stress cyctic limitations have been documented. This the normat charging will remain available for emergency boration to procedure change does not exceed those limitations.

maintain shutdown margin in the event of a reactor trip.

S01-67.1 ESSENTIAL RAW COOLING WATER SYSTEM .

Att affected TS LCOs were comtied with; therefore, the margin of REV 047 This revision was written to allow isolation of either ERCW safety as defined in the basis of the TS was not reduced.

Strainers 2A or 29 to perform maintecance on the strainers. An old ERCW pump, along with its associated strainer and piping, were utilized to supply ERCW to the header with the isolated strainer.

S01-67.1 ESSENT!At. RAW COOLING WATER SYSTEM - Cooting water is maintained to att components required for normat REV 046 This revision was written to attou isolating each ERCW strainer by operation on the inoperable train. The redundant train equipPent utilizing a crosstie at the old puming station. This configuration was unaf fected by this alignment. .The probability of an SAR ensured that a flow path is maintained to both of the inoperable accident was not increased.

headers to support normal plant operation and that equipment is not damaged by inadvertant starts.

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e. "1 Page No. 39 CHANCES TO PROCEDURES AS DESCRIBED IN THE SAR Sol-68.2 ' REACTOR COOLANT PUMPS .

. The coerability requirements of the WDS, CVCS, and RCS are provided ICF-89-0716 This ICF added Appendix B to provide conditions, precautions, and in the TS section 3/4.3, 3/4,4, 3/4.5, and 3/4.11. trptementing inspections for verifying No. 1 seat leakoff during power opera- this activity did not degrade the availability or reliability of the, tions. af fected systems and corponents. - The margin of safety es defined in the basis for any TS was not reduced.

S01-68.2 REACTOR COOLANT PUMPS teptementation of this change did not degrade the availability'or REV 036 This procedure was revised to clarify instructions and give the reliability of the affected systems or corponents. 'The margin of operators better guidance on when to initiate the shutdown of an RCP safety as defined in the basis for any TS was not reduced.

given teakoff rates from the number 1 seat in excess of the alarm setpoint of 4.8 gal / min.

$01-68.2 REACTOR COOLANT PUMPS .

White equipment redundancy and single-faiture criteria are lepseted, REV 037 The procedure was revised to allow the stopping of the RCP cooling the acceptability of these iepacts has been evaluated and accepted water in g 10 minutes. This was necessary because of repairs to the by the NRC, and thus the plant remains within the licensing basis.

CCS 3-inch flex hose supplying the RCP 3 upper bearing oil coolers Analyses have been performed in accordance with SAR Section 15.3.4.,

The RCS design parameters are not affected by this activity. The core cooling capability is not degraded in accordance with SAR section 5.5.2.3.2. The reactor coolant pressure boundary is not affected by this activity because operability in Mode 3 is below design limits of the reactor coolant piping. The reactor core parameters are not affected since the RCS will be berated to shutdown conditions.

SOI-77.1 VASTE DISPOSAL SYSTEM (LIOUID) . The changes made did not af fect the ability to meet any limit on REV 061 This revision aligned 0-77-671A closed on Valve Checklist 77.1B4-1. discharges to the enviroment as specified in the TSs. The In addition, this revision supported TACF 0-89-61-077 by instatting radioactivity limits were not exceeded; therefore, the margin of a butthose t- provide an.additionat recir flow path and the . safety as defined in the basis for TS 3/4.11.1.1, 3/4.11.1.2 and necessary valve alignment to use that flow path. 3/4.11.1.3 was not reduced.

S'0 1-77.1 WASTE D'SPOSAL SYSTEM (L10UID) The interim and final changes did not af fect the CDCT system ICF-89-0730 This partial modification replaced CDCT Ptenp B with a 150 gat / min configuration or affect the ability to meet any limit on discharges REV 004 pump and removed temperature tip-in from Ptro A. This change is in to the enviroment as specified in the TSs. The radioactivity concurrence with ECN 5916. Also, a bypass line was installed around timits were not exceeded, and the margin of safety as defined in the the CDCT pump fitter, and caps were instatted on the intet and basis fer TS 3/4.11.1.1, 3/4.11.1.2, and 3/4.11.1.3 was not r *uced.

outlet of these filters.

S01-77.5 PORTABLE RADWASTE DEM!NERALIZATION SYSTEM -

The change made did not atter the ability to reet any limit on REV 001 This revision was written to add a section A to provide instructions discharges to the environment as specified in the TSs. The margin for operation of the Mobile Fluidization Transfer Demineralization of safety as defined in the basis of TS 3/4.11.1.1, 3/4.11.1.2 and System. 3/4.11.1.3 was not reduced.

SOI - 77.5 PORTABLE RADWASTE DIMERALIZATION SYSTEM .

The margin of safety as defined in the basis for any TS was not REV 000 This revision provided operating information for use of a new mobile reduced.

demineralization system replacing the one currently described in the SAR (Ref. 19 and 20).

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4 Page No. 40 CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR S01-82.1 DIESEL GENFRATOR 1A-A- . There were no adverse effects on safety. The procedure change had!

REV 034 This safety evaluation was written to establish the minimum jacket no unacceptable effects on the operation of the 0/Gs and in no way ICF 89-0675 water and tube oit te merature requirement for D/G operability. The imedes their ability to perform the required safety functions.

procedure changes redefined opersbility as a function of tube oit This procedure change was based on the vendor's recomendation.

temperature rather than Jacke. water temperature. The procedure revision indicates the correct operability limits.

S01-82.2 DIESEL GENERATOR 18-B .

There were no adverse effects on safety. The procedure change had-REV 033' This safety evaluation was written to establish the minirma jacket no unacceptable effects on the operation of the D/Gs and in no way ICF-89-0676 water and tube oit temperature requirement for D/G orvrability. The impedes their ability to perform the required safety functions.

procedure changes redefined operability as a funct'as of tthe oit This procedure change was based on the vendor's recomendation.

temperature rather than jacket water temperature. The procedure revision indicates the correct cperability t bnits.

S01-82.3 DIESEL GENERATOR 2A-A - There were no adverse effects on safety. The procedure change had REV 037 This safety evaluatinn was written to establish the minimtm Jacket no unacceptable ef fects on the operation of the D/Gs and in no way-ICF-89-0677 water and tube oil tenperature requirement for D/G operability. The imedes their ability to perform the required safety functions.

procedure changes redefined operability as a function of tube oit this procedure change was based on the vendor's recomendation.

tes!perature rather than Jacket water temperature. The procedure revision indicates the correct operability limits.

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SOI-82.4 DIESEL GENERATOR 28-B There were no adverse effects on safety. The procedure change had REV 034 This safety evaluation was written to e<tablish the minimum Jacket no unacceptable effects on the operation of the D/Gs and in no way ICF-89-0678 water and tube oil temperature requirement for D/G operability. The' impedes their ability to perform the required safety functions.

procedure changes redefined operability as a function of tube oit This procedure change was basad on the vendor's recomendation.

temperature rather than jacket water te@ erature. The procedure -

revision indicates the correct operability limits.

SCA-187 SON ORGANIZATION AND RESPONSIBILITIES - The margin of safety as defined in the basis for any TS was not REV 002 This revision provided the new SON organizational structure and reduced.

defined the overall responsibilities of att organizations reporting directly or indirectly to the SON site director.

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Page No. 41 PF".FCRMANCE OF TESTS / EXPERIMENTS AS DESCRIBED IN THE SAR , _.

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STI/REV DESCRIPTION SAFETY

SUMMARY

STI-2 ' ICE CONDENSER LOWER -!NLET 000R LEAKAGE - UNITS 1 and 2 . There was no change in the operation of plant systens. -There was no ;

REV 001 The purpose of this special test was to quantify the tower intet increase in the probability of an accident. The c:argin of safety' door air leakage. - The data collected by this test was " baseline" - was not reduced.

~

data for evaluation of future corrective efforts. This test may be ~

conducted again at a later date to determine the effects of . .

corrective measures taken.' It is hoped that the data cettected by

^

. :d this test will be useful in gaining better. insight into leproving --

the operation of tte ice condenser in generat.

STI-132 CYCLING OF UNIT ONE POWER CIRCU1T BREAKER (PCB) 5034 AND 5038 The test is conynon PCB cycling required for preparation to tie the .

REV 000 The performance of this instruction cycled PCB 5038 verifying proper generator online to the yard, The test does not affect or inpact - .

t breaker operation and correct position indication before placing the nuclear safety based on its isolation from offsite power sources.

PCB in service.

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'$1Afl0N UI'ILITY CONTRACT 4

EMPLOYEES . EMPLOYEES T O T A L' STAi!0N 'Uf!E17Y COMtRACf TOTAL AND ofMERS PERSONS EMPLOYEES EMPLOYEES -AND OfMERS M-REMS

' M A!"AT E N ANC E PERSONNEL 626 17 22

- DPERATINC PERSONNEL 665 22 061 1.496 1.702 25.239-107 2 'O 109 MEALfM PHYSICS PERSONNEL 18.6a1 0.805 0.000 19.4a6.

42 0 51 93 9.659 SUPEkvaS0*Y PE NSONNE L 71 0.000 3.148 12.807.

27 17 115 2.508 0.668 ENGINEER!NC PERSONNEL 76 18 0.698 3.87a 59 153 6.610 1.862 2.713 11.185.

MO 922 64 149 1135 59.479 4.831 .8.261 72.571

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MosROUI!NE MAINIENANC[ --..----.-.- ..-..--------=--.- --- --.---....------.-

CROUP STATION Uf!LITY CONTRACT TOTAL STAT 10N UIILITY EMPLOYEES CONTRACT TOTAL EMPLOVEES. AND OTHERS PERSONS EMPLOYEES EMPiOYEES. AND OTHERS M. REMS MAINTENANCE PERSONNEL 626 14 38 OPERATINC PfRSONNEL 678 121.065 1.554 4.038 126.657 96 2 3 101 HEALTH PHYSICS PERSONNEL 2.513 0.025 0.029 2.567 42 0 50 92 9.986 SUPERYISORY P[ws0NNEt F4 0.000 10.577 20.563 22 16 112 7.e99 0.686 ENGINEER 1NC PERSONNEL 67 16 1.260 9.aa5 47 130 4.243 0.759

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11.726 16.728 MD 905 54 154 1113 145.306 3.024 27.630 175.960

...........----................. -..... MO 3N. SERVICE INSPECTION ........--...--..-- --....--..--..........-........--

C20ue STA110N UllLITY CONTRACI IDIAL STATION Uf1LitY CONTRACT TOTAL EMPLOVEES EMPLOYEES AND OTHERS PERSONS' EMPLOYEES EMPLOYEES AND OfMERS M.RENS MAINTENANCE PERSONNEL 251 4 3 258 OPERA!!NC PLkdONNEL 9 0 C 67.625 0.799 "0.015 68.439 9 0.!19 0.000 0.000 0.119-MEALIM PHYSICS PERSONNEL 31 0 45' 76 SUPERYIs0NY Ptn50NNEt 10.672 0.000 19.81e 30.488-28 24 26 78 6.696 ENCIN[ERING,PEASONNEL 10.870 17.983 35.557 10 13 22 45 0.920 17.346 28.658 46.932 MO 329- 41 96 466 86.0a0 '29.023 --66.472 181.535

.-.....---.--------.----------...-.----..--.------..-- M0=SPECIAL MAINIENANCE ----==---.....-...--..-...-... ......-..............-.

C"00P STAT!DN UTILITY CONTR2Cf- TOTAL STAIION Uf!LITY CONTRACT. TOTAL EMPLOYEES EMPLOYEES AND OTHERS PERSONS EMPLOYEES EMPLOYEES AND OTHERS M. REMS MAINTfNANCE PERSONNEL 482 7 20 509 OPERAI!NC PEhSONNEL 80.155' O.863 0.969 81.987 16 0 0 16 0.096 MEALIM PHYSICS PERSONNEL 0.000 0.000 0.096 39 0 35 74 2.314 SUPERTISchY PEhSONNEL 0.000 0.859 3.173 49 8 6 63 4.195

' ENGINEER!NC PERSONNEL .0.a03 0.060 e.658 48 5 35 88 3.948 0.040 19.616 23.604 MD 634 20 96 730 90.708 1.306 21.50s .113.518

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