ML20216J943

Addendum 7 to Mnps,Unit 3 Annual Rept,

ML20216J943
Person / Time
Site:	Millstone
Issue date:	02/28/1998
From:	NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20216J853	List: B17083, Forwards Addendum 5 to Rev 10 to FSAR in Form of Replacement Pages as Required & Addendum 7 to Annual Rept.Commitments Made by Util,Provided ML20216J943
References
NUDOCS 9803240127
Download: ML20216J943 (80)

Text

1 Docket No. 50-423 B17083 Attachment 2 Millstone Nuclear Power Station, Unit No. 3 Addendum 7 - February 26,1998 to Millstone Nuclear Power Station Unit No. 3 Annual Report dated February 28,1997 February 1998 9903240127 900226 PDR. ADOCK 05000423 K PDR

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Docket No. 50-423 B17083 Attachment 2 Millstone Nuclear Power Station, Unit No. 3 Addendum 7 - February 26,1998 to Millstone Nuclear Power Station Unit No. 3 Annual Report dated February 28,1997 l

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February 1998

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l Docket No. 50-423 B17083 INTRODUCTION l

None of the plant design changes described herein constitute, nor constituted, an unreviewed safety question per the criteria of.10CFR50.59.

PLANT DESIGN CHANGES DCR Number Title (FSAR Sections. Tables, and Fiaures Affected)

M3-97025 Safety Related Buses (7.6.9, 8.3.1, T8.3-3; processed with l

l FSARCR 97-MP3-185) l M3-97030 Degraded Grid Modifications (8.3.1,8.3.2; processed with FSARCR 97-MP3-315) l l Bvoass Jumper Number Title (FSAR St.ctions. Tables, and Fiaures Affected) 3-86-100 & Water Treating System Demineralizer Bypass and System 3-94-042 Isolation (9.2.3 T9.2-15; processed with FSARCR 97-MP3-542) 3-95-109 Boron Evaporator Reboiler Pump Disconnect (9.3.5; processed with FSARCR 97-MP3-540)

FSARCR Number Title (FSAR Sections. Tables. and Fiaures Affectedi 97-MP3-42 Feedwater Line Break Analysis Changes (6.3.3,10.4.9,15.2, T15.2-1, F15.2) 97-MP3-53 Steam System Piping Failure and increase in Heat Removal by the Secondary System Clarifications (6.3.3,15.1, T15.1-1, F15.1-14) 97_-MP3-91 Accident Analyses Changes and Clarifications (T7.2-4,15.0, T15.0-1, T15.0-2, T15.0-3, T15.0-4, T15.0-6, F15.0)

' 97-MP3-125 Reactor Coolant Piping Changes (5.4.3) 97-MP3-156 Residual Heat Removel System - Safety Grade Cold Shutdown Operations - Failure Modes and Effects Analyses (T5.4-9)

V 97-MP3-244 ' Pressure and Flow Indication Changes (6.3.5) 4 l'

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i Docket No. 50-423 B17083  !

l 1 37-MP3-294 Chemical and Volume Control System Component Description Changes (9.3.4) 97-MP3-320 Measurement and Calculation of Integrated Fast Neutron Flux Clarifications (5.3.1) 97-MP3-357 Piping and instrumentation Diagrams and Accumulator Valves and Controls Clarifications (6.3.2, 7.3.1, 7.6.4, 7.6.6) 97-MP3-367 Shoroline Slope Clarifications (2.5.5, F2.5.5-1, F2.5.5-4)

. 97-MP3-383 Steam Jet Air Ejectors Tests and Inspections (10.4.2) 97-MP3-388 Auxiliary Steam Control Valve Clarification (10.4.10) 97-MP3-389 Radiation Protection Design Features Changes (12.3, T12.3-5, l T12.3-6, T12.3-7, T12.3 8) i 97-MP3-402 Control Room Area Blockwall Clarification (F3.8-64, F6.4-1) l 97-MP3-403 Containment Penetrations and Valve Closure Time Changes (6.0, 6.2.4, T6.2-65) 97-MP3-421 Containment Vacuum System Changes (6.2.5, 9.5.10)'

97-MP3-429 Parameters for Ultimate Sump Percent Hydrogen (pH) Calculation Changes (6.1.1, T6.1-2) f 97-MP3-432 Reactor Vessel Stud Handling Changes (9.1.4) 97-MP3-433 Missile Shield Handling Changes (9.1.4) 97-MP3-439 Major Component Support Calculation Changes (T3.98-16, T3.9B-17, T3.9B-18, T3.9B-19, T3.9B-20, T3.9B-21, 97-MP3 440 Control Rod Drive Mechanism Clarifications (F3.9N-4, F3.9N-6, F3.9N-7) 97-MP3-446 - Unidentified Leakage Sump Pump Clarification (9.3.3) 97-MP3-453 Component Cooling Cross Connect and Level Signal Changes (7.3.1, 9.2.2) 2

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l Docket No. 50-423 B17083 97-MP3-457 Tank Overflow Protection Changes (T11.2-3) 97-MP3-460 Control Room Envelope Description Changes (6.4.2) 97-MP3-465 Neutron Shield Tank Design Clarifications (T9.2-9) MP3 466 Fire Protection Program Manual Changes (9.5.1, FPER 3.2, F3-1) 97-MP3-467 Containment Enclosure Siding Thickness Change (T6.2-63, T6.2-64) 97-MP3-470 Containment Systems Tables and Figures Changes (6.2.1, T6.2, F6.2-19, F6.2-23, F6.2-25, F6.2-26) 97-MP3-472 Inservice inspection Program Changes (6.6, T6.6-1, T6.6-2) 97-MP3-474 Chilled Water Flow Rate Change (T9.2-8) 97-MP3-477 Condensate Storage and Surge Tank Makeup Valves Location Clarification (9.2.6) 97-MP3-480 Miscellaneous Building Heating and Ventilation Changes (9.4.12) 97-MP3-484 Nitrogen System Major Component Design Data Changes (T9.5-6, T9.5-7) 97-MP3-486 Circulating Water and Associated Systems Changes (10.4.5) 97-MP3-489 Emergency Diesel Engine Lubrication System Change (9.5.7) MP3-490 Anticipated Transient Without Scram Mitigation System Actuation Circuitry Changes (7.8.1) 97-MP3-491 Pressurizer inspection Areas Change (F5.2-3) 97-MP3 496 Compressed Air Systems Instrumentation Requirements Clarifications (9.3.1) -

97-MP3-498 Liquid Waste Management Systems Changes (9.3.5,11.2,11.2.1, 11.2.2, T11.2-2, F11.2-3) 3

Docket No.' 50-423 -

B17083 97-MP3-503 Control Building Ventilation System Changes (9.4.1, T9.4-2)

I97-MP3-505 Environmental Design Conditions' Changes (Appendix 3B)

~ 97-MP3 508 Fire Hazards Analysis Update (FPER 5) 97-MP3-509 Auxiliary Boiler Fuel Pressure Change (T3.6-3)'

97-MP3 510 Reactor Vessel Integrity Change (5.3.3, F5.4-6 Notes)

' 97-MP3-512 Waste Neutralization Sump Clarification (11.5.1) 97-MP3-515 Organic Materials Clarification (T6.1-4) 97-MP3-516' Boron Recovery System Changes (T9.3-7) 97-MP3-518 Reactor Internals Construction Materials Clarifications (T3.2-1) 97-MP3-521 Gaseous Waste Systems Changes (9.3.3,11.3,11.3.1,11.3.2) 97-MP3-523 Spent Fuel Pool Demineralizer Clarification (3.1.2) 97-MP3-525 Ultimate Heat Sink Clarifications (9.2.5) 97-MP3-530 ' Containment isolation System Changes (T6.2-65) 97-MP3-531 Emergency Filtration Units Changes (T1.8-1, 6.2.3, 6.4.2, T6.5-1, 9.4.3, 9.4.7) 4 97-MP3-532 Effects of Local Intense Precipitation Changes (2.4.2, T2.4-11) 97-MP3-533 Containment Structure Ventilation System Changes (9.4.7, T9.4-12)

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. 97-MP3-548 Reactor Water Storage Tank Description Changes (6.3.2)

. : 97-MP3-551 Refueling Procedure Changes (9.1.4) 97-MP3-558  : Reactor Coolant Pump Malfunction Indications Clarifications (5.4.1, .T5.4-8).

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Docket No. 50-423 B17083 97-MP3-563 Emergency Core Cooling System Relief Valve Data Changes (6.3.2) 97-MP3 564- Cable Separation Criteria Clarifications (T1.8-1, 8.3.1) 97-MP3 567 Probable Maximum Precipitation Change (2.3.2) 97-MP3-571 Liquid Waste and Turbine Building Floor Drains Monitors Changes (11.5.2) 97-MP3-572 Solid Waste Management Changes (11.4,11.4.1,11.4.2)

' 97-MP3-573 Auxiliary Building Ventilation System Changes (9.4.3) 97-MP3-576 Effect of Local Intense Precipitation Clarification (2.4.2, T2.4-9, T2.4-12)-

97-MP3 580 Location of Power Range Nuclear instrumentation Clarification (4.4.6) 97-MP3-589 Class 1E Equipment Test Results Clarification (3.10B.5, T3.108-1, T3.10B-2) 97-MP3-591 Environmental Design Conditions (3.118.2)

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- DCR Number Title M3-97025 Safety Related Buses Connections Description of Change The table of nonsafety-related equipment' connected to safety-related buses was changed to add two heat tracing isolation transformers.

Reason for Channe This change was implemented to provide isolation from the safety related bus in the event that a high energy line break in an adjacent room creates a harsh environment.

. Safety Evaluation This change does not degrade the design, operation, qualification, or performance of the safety related

- bus. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

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DCR Number .. Title M3-97030 Degraded Grid Modifications Descriotion of Chance The degraded grid voltage protection relays were restored by incorporating transformer tap changes, undervoltage relay setpoint changes, overvoltage alarms, and miscellaneous circuit modifications.

Reason for Channe This change was implemented to restore the operability of the degraded grid voltage protection relays.

Safety Evahiation This change assures that adequate vol: age is supplied to certain loads during a postulated accident with a f-~

) coincident degraded grid voltage condition. Therefore, the change is safe and does not constitute an Unteviewed Safety Question.

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th nass Jumper Number Title 34-100 and 3-94-042 Water Treating System Dcmineralizer Bypass and System Isolation Description of Channe A direct path was provided from the Water Treating System filtration skids to the final filtration and demineralization equipment. A blank flange was installed to provide positive isolation to the unused portion of the Water Treating System.

Beason for Channe . .

This change was implemented to reficct actual plant configuration.

Safety Evaluation This change does not have an adverse affect on the reactor coolant boundary, fuel cladding protection, nor

. the containment boundary. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

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Ihpass Jumper Number Title 3 95 109 Boron Evaporator iteboiler Pump Disconnect

. Description of Chance The low seal water flow alarm and interlock switch were disconnected for the boron evaporator reboiler pump.

itcason for Chance This change was implemented to reduce the amount ofliquid radioactive waste to process.

Safety livaluation This change does not adversely affect the Boron Evaporator system or plant safety systems. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

FSARCR Number - ' Titig 97-MP3-42 Feedwater Line Break Analysis Changes Descrintion of Change Several sentences were deleted and others reworded in the descriptions of Loss of Electrical Load, Turbine :

Trip, Loss of Condenser Vacuum, Loss of Nonemergency AC Power, Loss of Normal Feedwater Flow, and Feedwater Line Break.

Reason for Chance This change was implemented to clarify potentially confusing sentences and document new Feedwater Line Break analyses.

Safety Evaluation -

The change in auxiliary feedwater flow rate has no impact on the consequences of the Feedwater Line Break. Long term cooling is still assured with the reduction in the assumed auxiliary feedwater flow rate.

- Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

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FSARCR Nunty . Title 97-MP3-53 Steam System Piping Failure and increase in licat Removal by the Secondary System Clarifications

&scription of Chance The description of the steam dump interlock was corrected and analyses to support increased stroke times for the Main Steam isolation Valves were incorporated.

Reason for Chance This change was implemented to add clarification and reflect actual plant configuration. Modifications to assumptions and results of design basis accidents were also incorporated.

Safety Evaluation This change is primarily editorial in nature and the acceptance criteria for all increases in heat removal accidents continue to be met. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

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FSARCR Number Title 97-MP3-91 Accident Analyses Changes and Clarifications Description of Chang The discussion section and associated tables for various accident conditions were revised and clarified.

Changes were also incorporated to correct editorial inaccuracies throughout the accident analyses section.

Reason for Chanee

- This change was implemented to clarify and accurately represent current accident analysis of records and to reflect new analysis and evahiations.

Safety Evaluation This change is editorial in nature and the acceptance criteria for the accidents analyzed continue to be met. Therefore, the change is safe and does not constitute an Unresiewed Safety Question.

l FSARCR Number Title 97-MP3-125 Reactor Coolant Piping Changes Description of Chance Several editorial and sentence numbering changes were incorporated and the description of the pressurizer -

surge line attachment was changed.

Reason for Chance This change was implemented to provide clarification and to reflect actu:d plant conditions.

Safety Wahiation Changing the pipe branch connection location does not result in a change to the specifications, materials, operating parameters or analyses. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

l FSARCR Numbg Titic 97-MP3-156 Residual Heat Removal System - Safety Grade Cold i Shutdown Operations - Failure Modes and Effects Analyses Descrintion of Chance The table which describes the components, failure modes and detection methods, function, and effects on system operation was revised to incorporate various editorial comments.

Reason for Chanze This change was implemented to reflect actual plant configuration and to be consistent with licensing and design documents.

Safety Evaluation -

This change does not alter equipment design specifications for material, operating parameters or methodology. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

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FSARCR Nurnber Title 97-MP3 244 Pressure and Flow Indication Changes Description of Chance The descriptions of the types and locations of pressure and flow indication for the Residual licat Removal Pumps, Containment Recirculation Putnp, Charging Purnp injection, and Safety injection Pump were changed.

Reason for Chance This change was implemented to add clarification and to reflect actual plant configuration.

Safety Evaluation This change is editorial in nature and is consistent with licensing and design documents. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

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FSARCR Number Title 97-MP3-294 Chemical and Volume Control System Component Description Cimnges Description of Changg The description of the charging pumps was changed to indicate that cach pump has a relief valve on the suction line as well as a relief valve on the suction header.

Reason for Channe This change was implemented to add clarification and reflect actual plant configuration.

Safety Evaluation ,

This change is editorial in nature and is consistent with design and licensing documents. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

FSARCR Nurnber Title 97-MP3-320 Measurement and Calculation of Integrated Fast Neutron Flux Clarifications

. Description of Chance The descriptions of the measurement and calculation methods ofintegrated fast neutron flux at irradiation -

samples were rewritten.

Reason for Chance This change was implemented to reflect the data obtained frorn surveillance capsule analyses avd to be consistent with approved analytical methodology.

Safety Evaluation Tins change only reflects the change in description of methodology and does not change fluence estimates.

Operational limits based on fluence estimates are adequately conservative. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

FSARCR Number ' __ Tltig 97-MP3-357 Piping and Instrumentation Diagrams and Accumulator Valves and Controls Clarifications Description of Channe The descriptions of accumulator isolation valves, charging pump mini-flow, and the signal for steam

_ generator blowdown and sample valves were revised.

Reason for Chance -

This change was implemented to reficct actual plant configuration and provide clarification to be consistent with design documents.

Safety Evaluation This change does not alter performance of a safety system nor change significant loads on safety systems.

Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

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FSARCR Nurnber Titic 97-MP3 367 Shoreline Slope Clarifications pescriotion or Chance The description of the underlayrnent stone weights for slope protection were changed and a typographical error was corrected.

itcason for Chance This change was impleniented to reflect actual plant configuration and to be consistent with design and licensing documents.

Safety Evahiation The change to the weight of the underlayment does not inipact the ability to afford adequate crosion protection. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

FS ARCR Number Titic 97-MP3-383 Steam Jet Air Ejectors Tests and inspections Description of Channe The description of the inspection process for the steam jet air ejectors was reworded for clarification. A statement regarding alternating equipment to equalize wear was deleted.

Reason for Chance This change was implemented to reflect that the actual testing and inspection method for the equipment is performed in accordance with applicable station procedures.

Safety I' valuation This change is editorial in nature and does not affect the operation or performance of the steam jet air ejectors. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

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FS ARCR Number Title 97-MP3 388 Auxiliary Steam Control Valve Clarification Description of Chance The description of the trip signal for the auxiliary steam supply to various components was changed from high radiation to high conductivity.

Reason for Channe This change was implemented to reflect actual plant configuration.

Safety Evaluation This change is editorial in nature and is consistent with design and licensing documents. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

FSARCR Number Title 97.MP3-389 Radiation Protection Design Features Changes Description of Chance The intent of the shielding description was clarified and various other descriptions of design features were reworded for clarity.

Reason for Chance This change was implemented to reflect actual plant conditions and to be consistent with design documents.

Safety Evaluation This change is editorial in nature and does not result in any physical or operational changes to plant equipment. Therefore, the change is safe and does not constitute an Unresiewed Safety Question.

FSARCR Number Title 97-MP3-402 Control Room Arca Blockwall Clarification Description of Chaare The description of the masonry block wall within the instrument rack room was changed to indicate it is in a safety related area.

Reason for Chance This change was implemented to accurately reflect actual plant configuration.

Safety Evaluation This change is editorial in nature and does not physically alter any equipment. The masonry wall is seismically qualified and continues to provide the primary function as a fire barrier. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

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FSARCR Number ~ . Titic 97-MP3-403 Containment Penetrations and Valve Closure Time Changes Description of Chance The description and associated tables of operation of containment isolation valves were changed by incorporating correct valve closure times, and penetration types and classification.

Reason for Chance This change was implemented to reflect actual plant configuration.

Safety Evaluation This change is editorial in nature and the changes in closure times of the isolation valves remain bounded by existing accident analyscs. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

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FSARCR Number Title 97-MP3-421 Containment Vacuum System Changes

' Description of Channe This section of the Final Safety Analysis Report was changed by clarifying pump capabilitics, correcting a reference to limusing documents, deleting incorrect statements and revising pump discharge temperature.

itcason for Channe This change was implemented to reflect actual plant configuration and to be consistent with design and licensing documents.

Safety Evaluation This change is editorial in nature and does not result in any operational or design changes. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

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FSARCR Number Title 97-MP3-429 Parameters For Ultimate Sump Percent 11ydrogen (pII)

Calculation Changes Descriotion of Chance The column titled Maximum pli was deleted and the value used as input to calculate the amount of trisodium phosphate required to maintain minimum pH was updated.

Reason for Chance This change was implemented to reficct the most recent calculation uhich sized the trisodium phosphate system to assure an ultimate sump pit.

Safety Evaluation This change is editorial in nature and is consistent with design and licensing docmnents. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

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. FSARCR Nmnber Title 97-MP3-432 Reactor Vessel Stud Handling Changes Description of Chance The description of the head stud removal process was changed to agree with the maintenance procedure.

Reason for Chance This change was implemented to reficct the actual approved process for head stud removal and storage.

- Safety Evaluation This change is editorial in nature and is consistent with design and licensing documents. Therefore, the change is safe and does not constitute an Unreviewed Safety Questiort i

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I 9 FSARCR Number - , i T_ille 97-MP3-433 Missile Shield Handling Changes

' Description of Chance The sequence of steps performed to transfer and temporarily store the missile shield during preparatiorts for fuel handling were rearranged.'

. Reason for Chance -

- This change was implemented to reflect actual plant conditions and be consistent with approved procedures.

Safety Evaluation This change is editorial in nature and is consistent with design and licensing documents. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

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FSARCR Number Title 97-MP3-439 Major Component Support Calculation Changes Description of Chance i This section of the Final Safety Analyses Report was revised to incorporate current results of the major equipment support calculations.

Reason for Chance This change was implemented to reflect actual plant configuration and to be consistent with design documents. I Safety Evaluation This change is editorial in nature and is consistent with licensing and design documents. Therefore, the change is safe and does not constitute an Unresiewed Safety Question.

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FS ARCR Number Title

- 97 MP3 440 Control Rod Drive Mechanism Clarifications Description of Chance The assembly drawing and figures of the control rod drive mechanism latch clearance were changed to incorporate the latest available pertinent information.

! Reason for Chance This change was implemented to tellect actual plant configuration and to be consistent with design and licensing documents.

l Safety Evaluation This change is editorial in nature and does not physically change any plant equipment. Therefore, the l .

change is safe and does not constitute an Unresicued Safety Question.

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l FSARCR Number Title 97-MP3-446 Unidentified Leakage Sump Pump Clarification Description of Chance

- The description of the sump pump activation <q;nals and alanns was changed to clarify the unidentified leakage sump pump alarm activates upon anning time and not level indication.

itcason for Chance This change was implemented to reflect actual plant configuration.

Safety I! valuation This change is editorial in nature and does not alter the function or operation of the pump. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

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FSARCR Number Title 97-MP3-453 Component Cooling Cross Connect and Level Signal Changes Description of Chance The description that the component cooling headers are cross connected was clarified to reflect that they can be cross connected and the low-level alarm and signals logic was clarified.

Reason for Chanee This change was implemented to be consistent with design documents and to tellect actual plant configuration.

Safety Evahiation This change is editorial in nature and does not change the design function of the plant component cooling system. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

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fj ARCR Number Titic 97-MP3-457 Tank Overflow Protection Changes Descrintion of Channe The low level alarm for various tanks were deleted from the table of tank overflow protection information and all the batch dewatering tank information was deleted.

Reason for Chance This change was implemented because the low level alarm warning annunciation does not provide any overflow protection and the batch dewatering tank does not exist.

Safety Evaluation This change is editorial in nature and does not change tank overflow protection. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

FSARCR Number Title 97-MP3-460 Control Room Envelope Description Changes Description of Chance The description of the control room envelope mis changed by deleting ref:rences to equipment that was not installed and adding references to instrument air lines, loose parts monitoring and distributed control system console equipment.-

. Reason for Chance This change was implemented to tellect actual plant configuration and to be consistent with design documents.

Safety Evaluation This change is editorial in natuic and is consistent with design documents. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

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97-MP3-465 ' Neutron Shield Tank Design Clarifications Description of Channe ne design temperature for the Neutron Shield Tank, the design temperature for the Neutron Shield Tank Surge Tank, and the design pressure for the Neutron Shield Tank Cooler were changed.

~ Reason for Channe

" This change was implemented to reflect actual plant configuration and to be consistent with design documents.-

' Safety Evaluation This change is editorial in nature and the changes to the design parameters are within the current design

envelope. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

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FSARCR Number Title 97-MP3-466 Fire Protection Program Manual Changes Description of Chang; The Fire Protection Program Manual was changed to reflect the individual responsibilities for the -

elements of the Fire Protection Program.

Reason for Chance This change was implemented to document the philosophy used in the application of fire protection features to preclude / limit fire damage.

Safety Evaluation This change is editorial in nature and is consistent with design and licensing documents. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

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- FSARCR Number Titig 97-MP3-467 Containment Enclosure Siding Thickness Change Description of Change The description of the siding pancis of the containment enclosure from the implied single panel of 0.08 inches thickness to the double panel of 18 gauge steel.

Reason for Chance This change was implemented to reflect actual plant configuration.-

Safety Evaluation

- Changing the siding thickness does not affect the ability to provide containtnent leak tightness.

' Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

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FSARCR Nnmber Title .

97-MP3 470 Containment Systems Tables and Figures Changes -

Description of Change-

- The mass and energy release analysis assumptions and results were resised and incorporated in the appropriate tables and figures.

Reason for Chance This change wasimpl emente p ant confi gurati on andtobe cons it d to reflect actuall s entwith design

- documents. ,

Safett Evaluation

-. This change is editorial in nature and the protection functions and normal plant functions of the containment systems remain unchanged. Therefore, the change is safe and does not constitute an

- Unreviewed Safety Question..

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FSARCR Number Ihlt 97-MP3-472 Inservice Inspection Program Changes Description of Chanee The description of the Inservice Inspection of Class 2 and 3 Components was deleted and replaced with a general description of the Inservice inspection Program.

Henson for Chance This change was implemented to climinate information that is contained in the Inservice Inspection Manual u hich is periodically updated and approved.

Safety Evaluation This change is editorial in nature and does not change the previously approved Inservice inspection Program. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

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' FSARCR Number Ijtig 97-MP3-474 - Chilled Water Flow Rate Change

' Description of Change The chilled water system evaporator design flow rate was changed from 2,100 gallons per minute to 2,250 l gallons per minutec Reason for Changg .

This change was implemented to tellect actual evaporator design flow rate of the chilled water system water chillers.

Safety Evaluation

.This change is editorial in nature and'is consistent with design and licensmg documents. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

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FSARCR Number Title 97 MP3-477 Condensate Sterage and Surge Tank Makeup Valves Location Clarification Description of Chance The description and location of the controls for the condensate storage and surge tank makeup valves were changed.

Reason for Chance This change was implemented to reflect actual plant configuration and to be consistent with design documents.

Safety Evaluation This change is editorial in nature and does not result in any physical change to the plant. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

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FSARCR Number Ijigg 97-MP3-480 Miscellaneous Building IIcating and Ventilation Changes Description of Chance The descriptions of various components were changed by making the descriptions consistent with design logic drawings, design setpoint calculations, and piping and instruinentation drawings.

Reason for Channe This change was implemented to tellect actual plant configuration and to be consistent with design and licensing documents.

Safety Evaluation This change is editorial in nature and is consistent with design and licensing documents. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

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. FSARCR Number Title 97-MP3-484 Nitrogen Systern Major Component Design Data Changes DescriDtion of Chance The nitrogen pump operating flow rate was deleted and the flow rate through the high pressure vaporizer was increased to agree with the latest specification addenda.

Reason for Chance

. The nitrogen pump operating flow rate was deleted because no documentation could be found to substantiate the value. The remaining change was implemented to reflect actual plant configuration.

Safety IIvaluation The flow rate change does not change the physical characteristics of the pump. The pump capacity remains the same and will continue to provide the required flow rate based on pump speed. Therefore, the

change is safe and does not constitute an Unresiewed Safety Question.

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FSARCR Number Title 97-MP3-486 Circulating Water and Associated Systems Changes Description of Chance The description of the instrumentation and controls for the condenser circulation water system were changed.

Reason for Chance

- This change was implemented to reflect actual plant configuration and to be consistent with design documents.

Safety Evaluation This change is editorial in nature and does not alter the capability or capacity of the auxiliary feedwater pump. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

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- PSARCR Number Titic 97-MP3-489 Emergency Diesel Engine Lubrication System Change Descrintion of Channe ~

The description of the lubricating oil used in the rxkcr arm lubrication system was changed to reflect the pour point of the oil in use.

Reason for Chance This change was implemented to reflect actual plant configuration.

Safety Evaluation The change of the lubricating oil pour point has no effect on the operability of the emergency diesel

. generator. The oil in the rocker arm lubricating system is maintained wil above the pour point.

Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

FSARCR Nurnber Title 97-MP3-490 Anticipated Transient Without Scram Mitigation System Actuation Circuitry Changes Description of Chance The description of the function of the Steam Generator level and Turbine Impulse Pressure Transmitters was changed. Additional system descriptions were clarified and incorporated.

Reason for Chance This change was implemented for clarification and to reflect actual plant configuration.

Safety Evaluation This change is editorial in nature and is consistent with design and licensing documents. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

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' FSARCR' Number Title MP3-491 Pressurizer Inspection Arcas Change Description of Change The distance between the upper head to shcIl weld and the upper shell to upper intermediate shell weld was changed from 107.06 inches to 137.06 inches.

Reason for Chanze This change was implemented to be consistent with design documents and to reficci actual plant configuration.

Safety Evaluation ~

This change is editorialin nature and does not alter the pressurizer design specifications. Therefore, the chang;c is safe and does not constitute an Unreviewed Safety Question.

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FSARCR Number Title 97 MP3-496 . Compressed Air Systems Instrumentation Requircir.ents Clarifications Description of Chance The description oflocal pressure and temperature indicators, control switches and indicating lights were corrected.

Reason for Chance This change was implemented to reflect actual plant configuration.

Safety Evaluation This change is editorial in nature and is consistent with design and licensing documents. Therefore, the change is safe and aces not constitute an Unreviewed Safety Question.

FSARCR Number 71119 97-MP3-498 Liquid Waste Management Systems Changes Description of Chance The description, design data, tables and figures were changed by incorporating requirements for reporting effluent relcases, operated flows and capacitics for various tanks and filters in the radioactive liquid waste system.

Reason for Chanec

. This change was implemented to reflect regulatory requirements and actual plant configuration.

Safety Evaluation This change is editorial in nature and does not make any physical change to plant equipment. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

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FS ARCR Number Title 97-MP3-503 Cor. trol Building Ventilation System Changes Description of Channe

- The description of s arious components, test frequencies, and performance characteristics were changed by adding clanfication and editorial corrections.

Reason for Chance This change was implemented to be consistent with design and licensing documents and to reflect actual plant configuration.

Efety Evaluation This change is editorial in nature and is consistent with licensing and design documents. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

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FSARCR Nuneber Tilla 97 MP3 505 Environmental Design Conditions Changes 12pserintion of Chance The control buildmg Accident Radiation Dose and the Radiation Dose - 40 Year Life Plus Accident values were changed to values which are traccable to calculations.

Reason for Chance This change was innplemented to provide clarity and to be consistent with design and licensing documents.

Safety Evaluation

' This change is editorial in nature and decreasing the accident dose calculation does not alter the mild environment conclusion. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

J FSARCR Nuniber Title 97 MP3-508 Fire Huards Analysis Update Description of Chance The Fire Protection Evaluation Report was revised to include changes to the Combustible L,oading Section of each Fire Area and Zone description. Changes to the types of cornbustible materials, relative Dre severity, and zone ditoensions were also made as necessary.

Reason for Chance This change was implemented to reficct actual plant conGguration.

Safety Evaluation This change is editorial in nature and is consistent with licensing and design documents. Therefore, the change is safe and doer not constitute an Unresiewed Safety Question.

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FSARCR Number Title 97-MP3 509 Auxiliary Boiler Fuel Pressure Change Description of Chance The auxiliary boiler fuel oil system maximum pressure was changed from 130 to 150 pounds per square inch gauge.

Reason for Chante This change was implemented to reflect operating irstructions provided try the manufacturer and to reflect actual plant operating conditions.

Safety Evaluation This change is editorial and is consistent with design documents. Therefore, the change is safe and does not constitute an Unresiered Safety Question.

r FS ARCR Number Title 97-MP3-510 . Reactor Vessel Integrity Change Descrirstion of Chance The reactor vessel heatup and cooldown rate and the primary water temperature transient for normal operating conditions were changed.

Reason for Chance This change was implemented to clarify the heatup/cooldown rate design limit and to be consistent with other design and licensing documents.

Safety Evahiation This change is editorial in nature and is consistent with licensing documents. The design and function of the reactor vessel and other plant equipment is unaffected by the change. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

FS ARCR Number Title 97-MP3-512 Waste Neutralization Sump Clarification Description of Chance The description of the waste neutralization sump effluent discharge to the circulating water discharge tunnc! was changed.

Reason for Channe This change was implemented to reficct actual plant configuration.

S.afety Evaluation This change is editorial in nature and is consistent with design and licensing documents. Therefore, the change is sale and does not constitute an Unreviewed Safety Question.

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FSARCR Number  : Title 97-MP3-515 . Organic Materials Clarification

' Description of Chance

The table that lists the Other Organic Materials Used inside Containment was updated to incorporate current actual values used in associated analysis.

Reason for Chance This change was implemented to reDect actual plant conGguration and to be consistent with design and licensing documents.

Safety Evaluation This change is editorial in nature and the increase in organic materials is consistent with the amount that is previously analyzed and acceptable. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

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l FS ARCR Number Title 97 MP3 516 Boron Recovery System Changes Descriotion of Chance The table w hich lists the characteristics of various components of the boron recovery system was changed to incorporate design basis information.

Re^ son for Chance This change was implemented to reflect actual plant configuration and to be consistent with design doeurnents.

Safety livaluation This change is editorial in nature and does not change the operation or performance of the boron recovery j system. Therefore, the change is safe and does not constitute an Unresiewed Safety Quc< tion.

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i FSARCR Number Title 97 MP3-518 Reactor Internals Construction Materials Clarification t

Description of Chance l

l The design code for materials used in the fabrication of the reactor vessel internals was identified and clarified.

Reason for Chanec This change was implemented to be consistent with licensing and design documents.

! Epfctv Evaluation This change is editorial in nature and the materials used are comparable to those currently listed in design and licensing documents and meet the intent of the code. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

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l FSARCR Number Title 97-MP3-521 Gascous Waste Systems Changes Description of Chance The description of the operation and performance characteristics of various components in the reactor plant vent and drain systems were changed for clarity and accuracy, Reason for Chance This change was implemented to reficct actual plant configuration.

Safety Evaluation This change is editorial in nature and is consistent with design and licensing documents. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

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r FSARCR Number Titic 97-MP3 523 Spent Fuci Pool Dcmineralizer Clarification Description of Chance .

The description of fuel pool demincrlizer effluent specific conductivity monitoring and high conductivity corrective actions was changed to reflect the current level of conformance to established design criteria.

Egason for Chance This change was implemented to reconcile the differences in the current commitment and the current design.

Safety Evaluation This change is editorial in nature and does not change the assumptions and conclusions of any accident analyses. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

FSARCR Nuniber Titic 97-MP3 525 Ultiinate Heat Sink Clarifications Description of Chance The description of the circulating water discharge tunnel capabilitics was reworded and the reference to the heat reinoval capability of the quarry outlet was clarified.

Reason for Changq This change was iniplernented to reflect actual plant configuration, Safety Evaluation This change is editorial in nature and is consistent with design and licensing docuinents. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

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FSARCR Number Title 97-MP3-530 Containment isolation S;, stem Changes Descrintion of Chance The category of the containment leakage monitoring open taps penctrations. the main steam penetrations, and the main steam to auxiliary feedwater pump turbine penetrations was changed. The penetration designation of essential /non-essential was deleted u here the information was superfluous.

Reason f or Chance This change was implemented to reficet actual plant conditions and to be consistent with design and licensing documents.

Safety Evaluation This change is editorial in nature and the change in category does not impact the systems ability to isolate the containment and mitigate the consequences of any accident. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

FSARCR Number Title 97-MP3-531 Emergency Filtration Units Changes Description of Chance The emergency filtration unit charcoal filter face velocity and residence time design values were changed.

Reason for Chance This change was implemented to incorporate clarifications, provide additional information, and correct editorial inaccuracies.

Safety Evahtation This change is editorial in nature and has no affect on the operation of the emergency filtration units.

. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

fjARCR Number Title 97-MP3-532 Effects Of Local Intense Precipitation Changes Description of Chance The discussion of the Dcmineralized Water Storage Tank and the Refueling Water Storage Tank was changed by clarifying the site ground clevation surrounding the buildings.

Rg;ison for Cluinne This change was implemented to reflect actual plant configuration and to be consistent with design drawings.

Safety Evaluation This change is editorial in nature and is consistent with design and licensing documents. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

FS ARCR Number Title 97-MP3-533 Containment Structure Ventilation System Changes Description of Chance The values for the Control Rod Drive Mechanism cooling system flow rates were restored to the original design now rates and the value for total fan pressure was reduced.

Reason for Chance This change was implemented to reflect actual plant conGguration and to be consistent with design documents.

Safety FIvaluatjpon . .

This change is editorial m nature and is consistent with licensing and design documents. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

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FSARCR Number Title 97-MP3 548 Reactor Water Storage Tank Description Changes Description of Chance The discussion of the Reactor Water Storage Tank minimum volume requirements and level measurement were changed.

Reason for Chance This change was implemented te reflect actual plant configuration.

Safety Evaluation This change is editorial in nature and there is no change to the capability or capacity to cool the rescior.

Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

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FSARCR Number Titic 97-MP3-551 Refueling Procedure Changes Description of Chanec The refueling procedure was changed to permit the completion of the reactor vessel head lift before flooding the upper cavity and draining the upper cavity before installing the reactor vessel head.

Reason for Chance This change was impicmented to reduce the time required to completc the lift and reduce the resulting radiation exposure to personnel.

Safety Evahiation This change reduces the risk involved with heavy load movement and reduces worker radiation exposure.

The clumge is editorial in nature and is consistent with design and licensing documents. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

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FSARCR Number Title 97-MP3-558 Reactor Coolant Pump Malfunction Indications Clarifications Description of Chance The discussion of operator action to monitor Reactor Coolant Pump vibration levels u hen the anmmciator alarm (s) for high or low seal leakoff rates and/or increasing Reactor Coolant Pump bearing /No. I seal inlet temperature are sounded was deleted.

Reason for Chance This change was implemented to tellect actual plant configuration and because operator response instructions are provided in other documents.

Safety Evaluation This change is editorial in nature and is consistent with design and licensing documents. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

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FSARCR Number Title j 97-MP3-563 Emergency Core Cooling System Relief Valve Data Changes 1

Description of Chance Discrepancies between the description of various Emergency Core Cooling System valves and the design specifications and features of the valves were corrected.

Reason for Chance This change was implemented to reflect actual plant configuration and to be consistent with design documents.

Safety Evaluation This change is editorial in nature and is consistent with design and licensing documents. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

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FSARCR Nurnber Title 97-MP3-564 Cabic Separation Criteria Clarifications Description of Chance The electrical separation criteria internal to control roorn panels was changed.

ILeason for Change This change was implemented to reflect actual plant configuration and to reflect results of actual tests performed to demonstrate the flame retardant characteristics of the wiring.

Safety Evaluation This change is editorial in nature and the tests demonstrated that under worst case conditions, the target cables retain their functional capability. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

FS ARCR Number Title 97-MP3-567 Probabic Maximum Precipitation Change Description of Chance The design maximum rainfall rate, used for site flooding estimate and roof drainage design, was changed.

Reason for Channe This change uns implemented to reflect the actual design value for estimated rainfall and to incorporate current roof drainage and flooding analysis.

Safety Evaluation This change is editorial in nature and the results of the flooding analysis indicates no impact to equipment imponant to safety. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

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FSARCR Number Title 97 MP3-571 Liquid Waste and Turbine Building Floor Drains Monitors Changes

. Description of Chance The discussion regarding closure of discharge valves was changed to clarify the valve action prevents discharge to the environment in excess of dose limits.

Reason for Chance This change was implemented to reficct a small time delay prior to alarm which may allow discharge of some radioactivity.

Safety Evaluation

This change is editorial in nature and the consequences of the alarm response delays are inconsequential.

Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

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FSARCR Number Title 97-MP3 572 Solid Waste Management Changes Description of Chance Alternative solidification and packaging methodologies and approved transportation alternatives were incorporated into the Solid Waste Management discussions.

Reason for Channe This change was implemented to demonstrate compliance with presiously approved regulatory commitments.

Safety Evahiation This change is editorial in nature and is consistent with design and licensing documents. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

FSARCR Nurnber T!1}ls 97-MP3-573 - Auxiliary Building Ventilation System Changes

. Descrintion of Changg The text in the design bases discussion was resised to ensure charging putnp cubicle area design teinperature is within licensing limits.

Beason for Channe This change was implernented to reflect actual plant configuration.

Safety Evaluation This change is editorial in nature and is consistent with design and licensing doctanents. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

FSARCR Number Title 97-MP3-576 Effect of Local Intense Precipitation Clarifications

' Description of Chance Discrepancies, contradictions, and inaccuracies in the tables and discussions of roof ponding due to -

intense precipitation were corrected and clarified.

Reason for Chance This change was implemented to reflect actual plant configuration and to be consistent with design documents.

Safety Evaluation .

This change is editorial in nature and all the involved structures remain fully qualified for the revised roof .-

loadings. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

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FSARCR Number T 97-MP3 580 P wer Range Nuclear Instrumentation Clarification Descrintion of Channe A change was incorporated by clarifying the location of the detectors in the reactor neu_ an shield tank.

1 i s cliange , incorporated to ref1cci actual plant configuration and to be consistent with design documents.

Safety Evaluation This change is editorial in nature and is consistent with design and licensing documents. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

FSARCR Number Title

. 97-MP3-589 - Class 1E Equipment Test Results Clarification Description of Channe

' The text which describes the results of testing and analyses was revised by deleting tables and rewording .

' the description to state where the data is maintained and available for retrieval.

Reason for Change

- This change was implemented to accurately describe where the qualification test data and analyses is maintained.

Safety Evahiation This change is editorial in nature and is consistent with design and licensing documents. Therefore, the change is safe and does not constitute an Unresiewed Safety Question.

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FSARCR Number Title 97-MP3-591 Environmental Design Conditions Descriotion of Chance A statement was added to clarify that mild environments are not within the scope of 10CFR50.49 and

- therefore not part of the Electrical Equipment Qualification program.

Reason for Chance This change was implemented to define the scope of the Electrical Engineering Qualification program and to provide consistency with licensing documents.

Safety Evaluation This change is editorial in nature and does not alter the ability of the equ i pment to perform its design function under normal and accident conditions. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

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