ML20203H033

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Addendum 5 to Mnps,Unit 3 Annual Rept
ML20203H033
Person / Time
Site: Millstone Dominion icon.png
Issue date: 11/21/1997
From:
NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20203H004 List:
References
NUDOCS 9712180286
Download: ML20203H033 (58)
v • d • e


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Docket No. 50-423 -j B16874 -j

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1 Attachment 2 -

Millstone Nuclear Power Station, Unit No. 3

- Addendum 5 - November 22,1997 to Millstone Power Station Unit No. 3 -

Annual Report dated February 28,1997 O

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Docket No. 50-423  ;

B16874 q n)TRODUCTION' l

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

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

M3 97017 On Site Meteorological Measurements Program Changes (2.3.3; processed with FSARCR 97-MP3-244)

M3 97053 Modifications for Safety Re!ated Valves and Nonsafety Related Controls (Appendix 7.5A, T7.51; processed with FSARCR 97 MP3-458)

FSARCR Number Title (FSAR Secticns. Tables, and Fiaures Affected) o b 97 MP3169 Fire Protection Eveluation Report Changes (FPER 5) 97 MP3173 Service Water System Changes (9.2.1)

- 97 MP3-178_ Water System Changes (T9.2-4) 97-MP3184 Reactor Plant Component Cooling System Changes (T9.2-5) 97 MP3 200 Reactor Trip System Changes (7.2) 97-MP3 203 Engineered Safety Features and Essential Auxiliary Support Systems Changes (7.3.1) 97-MP3-207 Emergency Core Cooling System Component Interlock Changes (6.3.2) 97 MP3 217 Reporting Type A Teste to NRC Clarification (6.2.6)

. 97-MP3 218 Containment Penetration Leakage Rate Test Clarification (6.2:6) 97 MP3-221 - Reactor Trip System Instrumentation Changes (7.1, T7.2 3) 97-MP3-223 Valve Position Indication Changes (6.3.5) 97-MP3 225 Pump Vibration Monitoring Changes (9.2.1, 9.2.2, 9.4.1) 97-MP3 228 Instrumentation for Detection of inadequate Core Cooling Changes (4.4.6, F4.4-13, F4.4-17) 97-MP3 229 ' Thermal and Hydraulic Design Changes (4.4.6, T4.4-3) 97-MP3 232 Primary and Auxiliary Components Material Specifications Changes (T5.2-2) 97-MP3 234 '- Reactor Vessel Testing Clarification (5.3.1, T5 3-1) p 97-MP3 235 Reactor Vessel Insulatio. Change (5.3.3, T5.3-6) .

V 97-MP3-236 Reactor Coolant Pump Low Motor Lube Oil Level Alarm Change (5.4.1) 1

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Docket No. 50-423 B16874 97 MP3 237 Reactor Coolant System Components Code Change (T5.2-1) 97-MP3 238 Reactor Vessels Internal Material Specifications Changes (TS.2-3) 97-MP3 243 Reliability Tests and Inspections Clarifications (6.3.4) 97-MP3 249 Reactor Materials Changes (4.5, 4.5.1, 4.5.2) 97-MP3 252 . Equipment Supports, Loading Combinations, and Design Allowable Stresses Format Changes (T5.4-18) 97 MP3 255 Containment Mass and Energy Analytical Assumptions

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Clarifications (6.2.1)

'7 97-MP3 261 Mass and Energy Release Data (6.2.1)

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97-MP3 263 Containment Systems Changes (T6.21, T6.2-3, T6.2 4, T6.2-7, T6.2-17, T6.218, T6.2-19, T6.2-27, T6.2-28, T6.2 29, T6.2-30, T6.2-32A, T6.2 35, T6.2-58, T6.2 59, T6.2-77, F6.2-12, F6.2-13) 97 MP3 285 Analysis of Engineered Safety Features Actuation System Clarifications (T1.8-1, T1.8N 1, 7.3.2, T7.3-4) 97-MP3 287 Control Systems Not Required for Safety (7.7, T7.7-1, F7.7-1, F7.7-14. F7.715) 97 MP3 324 Reactor Materials Change (4.5.1, 4.5.2) 97 MP3 325 Emergency Core Cooling System Component Parameters Change (T6.3-1)

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97-MP3 327 Refueling Water Storage Tank Water Levels Change (F6.3 6) 97-MP3 332 Ventilation System Temperatu.e Control Change (9.4.5,9.4.7, 9.4.8) 97-MP3 334 Steam Generator Blowdown System Change (10.4.8, T10.1-1) 97-MP3-358 Area Radiation and Airborne Radioactivity Monitoring Changes (12.3.4, T12.3 2) 97-MP3 361 Emergency Core Cooling System Relief Valve Data Change (T6.3 2) 97 MP3 366 Habitability Systems and instrumentation Requirements Changes (6.4.1,6.4.6) 97-MP3-390 Turbine Bypass Valve Description Change (10.4.4) 97-MP3 407 Fire Protection Program Manual Changes (FPER 4, 5, 6,7, Appendix B) 97-MP3-410 Fuel System Design and Functional Design of Reactivity Control System Changes (4.6.2, 4.6.6, F4.2-1, F4.2-5, F4.2-9, F4.211, F4.2-14) 97-MP3-418 Domestic Water and Sanitary System Change (9.2.4) 97-MP3-419 Condensate Surge Tank Level Clarification (9.2.6) 97-MP3-436 Service Water Cubicles interconnecting Door Clarification (F3.4-1, F3.8-69) 97-MP3-437 Components Reauiring inelastic Analyses Change (T3.98-2) 97-MP3-444 Auxiliary Building Ventilation Changes (T9.4-4) g 97-MP3 461 Deviations to the Electrical Separation Criteria Outside Panels (8.3.1, T1.8-1) 2

Docket No. 50-423 O ,

B16874

-- 97 MP3-478 -

Control Building Ventilation System Change (9.4.1) 97-MP3-479 Control Building Ventilation System inspection and Testing ,  !

Requirements Changes (9.4.1, 9.4.2, 9.4-10) 97-MP3-485 Hydrogen Supply System Description Clarification (9,5.9) 4 J

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DCR Number - Tillt M3 97017 = - On Site Meteoretogical Measurements Program Changes .

Description of Channe - .

A new data link was installed between the meteorological tower instruicentation and directly to a new -

transmitter, The information is then transmitted in a digital format to a ree-h*r snd comcrted to an analog signal for input to the Unit 3 Plant Proess Computer,

= Reason for Channe This change was implemented to Cminate data access problems associated with the Emironmental Data Acquisition Network computer by transmitting directly to the Unit 3 Plant Process Computer. -

Safett Evaluation

. This change does not alter safety related equipment and prmides a more reliable method of obtaining meteorological data. Therefore, the change is safe and does not constitute an Unresiewed Safety Question.

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M3 97053 Modifications for Safety Related Valves with Nonsafety ,

Related Controls .

3 Description of Channe

  • This change upgraded controls for various valves by replacing in-containment terminal blocks with qualified splices and replacing certain valve position 1imit switches and solenoid operated valves.

Reason for Channe This change was implemented to upgrade the controls for various valves to be consistent with the design _

basis and provide reasonable assurance of their post accident operation.

Saferv Evaluation - .

This change ensures the valves do not spuriously open as result of a harsh environment and is consistent '

with licensing and design bases documents. Therefore, the change is safe and does not constitute an Unresiewed Safety Question.

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97 MP3169 . Fire Protection Evaluation Report Changes

.. Description of Channe':

l The maintenance shop fire zone analyses were mised to correct barrier construction information and fire. -  !

ratingsJ The fire area analyses for the turbine and service buildings were revised to identify the fire rating :

of the block walls. The Fire Area Hazards Analyses was revised to add fire detection and floor ifrain _.

information to the Condensate Polishing Enclosure fire areas,-  ;

Reason for Channe  ; . .

This change was implemented to correct barrier construction design descriptions which were determined to contain incorrect or contain incomplete information, and to include fire detection and building drain -

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information previously omitted from the applicable turbine building analyses.

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Safety Evaluation This change dxs not alter any safety limit or reduce the margin of safety of any protective boundaries .

which separate safety-related areas or ponions of redundant systems important to safe shutdown within any fire area. Therefore, the change is safe and does not consutute an Unreviewed Safety Question.

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Service Water System Changes-Descrintion of Channe '- l The design pressures for certain components of the Service Water System, including the shutoff head for g

  • the booster pumps, were changed and clarified to accurately reflect design parameters.

Reason for Change >

This change was implemented to eliminate conflict between actual plant configuration and design ,

documentation.- '

Saf1tLEYplpation ,  !

This citange does not alter any assumptions or conclusions of any accident analysis All the design paranw.1 cts required to assure the affected equipment is maintained in a safe and reliable configuration s remain within acceptable limits. Therefore, the change is safe and does not constitute an Unresiewed Safety Question?

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97 MP3178 Ihlt Water System Changes Description of Chance The reference to seismic Category 1 pipe . 26 inch and Category Il pipe . 2 inch was deleted from the .,

consequence of component failures table.

Reason for Chance This change was implemented to reflect actual plant conditions and ensure the tables contain complete and correct information.

SafetyISt ;dign This change is editorial in nature and does not alter system design, operation not function. Therefore, the

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

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('j ES 'ACR Nunihi Ijik 97 MP3184 Reactor Plant Component Cooling System Changes Description of Ch'ince The Component Coolmg Heat Exchanger design temperature was changed from 200 degrees F to 125 degrees F on the tube side and 150 degrees F on the shell side.

Reason for Chance This change was implemented to reflect actual plant configuration and to reflect design information provided in the vendor's drawing.

Safety Evaluation The bounding fluid operation temperature of the system is not affected by this changa and the heat removal capabilities assumed for safety grade cold shutdown are not affected. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

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97-MP3-200 Reactor Trip System Changes Descriotion of Change The desenption of the Reactor Trip System was changed to incorporate additional information and clarify, ambiguous information.  ;

I Reason for Channe .

This change was implemented to reflect actual plant conditions and correct the system description -

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Safett Evaluation r

This t.hange does not affect any analyzed accident or malfunction. The change does not affect the
operation of the plant or the ability to mitigate an accident. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

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- Support Systems Changes

- DescrMon of Ch=ana ._

The descriptions of the containment isolation system and the reactor plant component cooling water .

system were changed to add additional annunciation signals, delete certain testing requirements, and ,

clarify certain alarm conditions.

Remmn for Chanae

_TE change was implemented to add clarification and reflect actual plant configuration.

! Safety Evaluatiert

~ This change is cohorial in nature and does not create any physical changes to the plant equipment. The ,

change is consistent with licensing and design bases documents. Therefore, the change is safe and does

. not constitute an Unresiewed Safety Question.

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Emergency Core Cooling System Component Interlock Changes Description of Chanc.t The desenption of the interlocks associated with opening the safety injection pump ana charging pump recirculation suction isolation vahts was changed.

4 Reason for Chance This change was implemented to provide additional descriptive information and to reflect actual plant -

configuration.

.- - Safety Evaluation

_ _ _ This change is editorial in nature and does not create any physical changes to plant equipment. The change is consistent with licensing and design bases documents. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

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Reporting Type A Tests to NRC Clarification Descnouon of Chanac

--De reporting requirements for Type A test was changed to clanfy that only failed tests be reported and -

other tests be filed and made available upon request.

Reason for Chance This chanBe was implemented to update the procedure described in the Final Safety Analyses Report for reporting results of periodic Type A tests.

Safety Evaluation This change is editorial and administrative in natere and does not create any physical changes to plant -

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

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k't~ FSARCR Nurnber Ig!g 97 MP3 218 Containment Penetration Leakage Rate Test Clarification Description of Chance The number of electrical penetration requiring Type B leak rate testing was changed from 81 to 80.

Reason for Chance This change was implemented to reflect the actual plant configuration because the additional penetration had been prniously plugged and no longer requires this testing.

- Safety Evaluation This change does not degrade the functional design of the penetrations nor containment integrity.

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

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' V- . 97 MP3 221 Reactor Trip System Instrumentation Changes Description of Chance The Reactor Trip System Instrumentation table was revised by replacing typical values for range, accuracy and time response with specific values for the unit.

J Reason for Chance This change was implemented to incorporate more specific, descriptiw and accurate information into the description of the reactor trip system instrumentation.

Safety Evaluation This change removes vague information and replaces it with specific design bases information. The change does not alter any conclusions of existing safety evaluations, Therefore, the change-is safe and does not constitute an Unreviewed Safety Question. .

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\_l FSARCR Number Inig 97 MP3 223 Valve Position Indication Changes Descrit3 tion of Chance The annunciator window terminology and window colot were clarified and the reference to the pressure for w hich the safety injection actuation signal is unblocked was corrected Reason for Chance This change was implemented to reflect actual plant configuration and an.nunciation terminoloEy, Safetv Evaluation This change is editorial in nature and does not ueate any physical changes to the piant and is consistent with licensing and design bases dxuments. Herefore, the change is safe and does not constitute an Unresiewed Safety Question.

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FS ARCR Number (L') 97.MP3 228 1111t Pump Vibration Monitoring Changes pescrirition of Chance The wording that calls for computer inputs to monitor vibration or differential pressure on the Senice

. Water, Charging Pump Cooling, Safety injection. and Circulating Water pumps was deleted.

Reason for Chance This change was implemented to reflect actual plant configuration because the monitoring equipment was not installed.

Saferv Evaluation This change does not alter systern design, operating paran.eters or methodology. The information that would have been monitored by this equipment is being collected and recorded by other means. Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

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Descrintion of Channe The reference to a dedicated trend recorder to monitor reactor vessel water level was deleted and use of the '

plant computer system for trending and display was clarified.

Reason for Channe

. This change was implemented to incorporate a highly reliable system to trend and display reactor vessel .

level and to allow the plant operator to monitor reactor status during abnormal plant conditions.

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This change provides the same fimetions and information with very high reliability and does not adversely .

' affect any safety system design limits or functions. Therefore, the chahge is safe and does not constitute

- an Unreviewed Safety Question?

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- 97 MP3 229 ' Thermal and Hydraulic Design Changes Descrmuon of Channe The description of the Heated Junction Thermocouples was changed by correcting certain descriptive .

- details and incorporating specific equipment locations Reason for Channe -l This change u as implemented to incorporate additional, specific information and to reflect actual plant '- J configuration.

l Salav Evaluation This change does not alter how the plant is operated nor impact the plant response to design basis >

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

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TS ANCR Nurnber Il1}g 97.htP3 232 Prunary and Auxiliary Components hiaterial Specifications Changes Description of Chance The table of anaterial specificauons was changed by deleting a reference that does not exist. The material identification and wcid metal analysis identification were mrrected to agree with vendor provided information and codes in effect at the time of manufactur Reason for Chance This change was implemented to clarify information and reficci actual plant configuration.

Safety Evaluat;on This change is editorielin nature and the technical content of the information is not changed Thereforc.

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

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Description of Chance Ihe allowable method of testing of the final support weld buildups was doeurnented in the Reactor Vessel, Non Destructive Examination table.

' Reason for Chance This thange was irnplemented to document the allowable, optional use of ultrasonic inspection in heu of  ;

magnetic particle testing for the vessel support welds, i Stlett Evaluatu This change does not degrade the quality of the weld. The optional method provides a 100 percent volumetric inspection of the weld. Therefore, the change is safe and does not constitute an Unreviewed Safety Question -

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FS ARCR Number ,Q11g 97-MP3 235 Acactor VesselInndation Change Description of Chance The desenption of the reactor vessel insulation was changed to clarify the,ase of canned stainless steel panels of fibrous, powdered and reflective insulation.

Reason for Chance This change was implemented to clarify term.nology and reflect the actual plant cordiguration.

Safety Evahiation This change is editorial in nature and does not alter the reacto. vessel insulation design specifications, materials, operating parameters or methodo'ogies. Therefore, the change is safe and does not constitute ,

an Unteviewed Safety Question.

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i TS ARCR Naratsi 11tig i 97 MP3 236 Reactor Coolant Pump Low Motor Lute Oil Level Alarm (

Change  ;

Description of Chang ,

The action to be fAken following a low oil level alarm Wal changed from shutting down the reactor coolant pump to monitoring tearing temperature and then tripping the reactor, followed 17 the reactor coolant pump if any betting temperature exceeds the manufacturer's recommended maximurn limit.

Epson for Chance .

This change was implementa! to conect the m erly conservath e action ofinpping the pump w hen the low lute oil sump level alarm is actuated.

53fett Evaluation Using temperature indication instead of low in el alarm to provide the trip point for the pumps does not '

affect ans equipment rnalfanction nor increase the challenges to any plant safety system. Therefore the change is safe and does not constitute an Unrnicued Safety Question.

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Reason for Chance This change was implemented to reflect actual plant design criteria specified during procurement of the valves uhich ovuned over a period of time. ,

Safett Evalugliga 1 n- This change is editcrial in nature and all the valves met the design requirements. Therefore, the change is

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b FS ARCR Nuniber Ijlig 97.MP3 238 Reactor Vessels internal Material Specifications Changes Descrir. tion of Chance Additional materials of construction used in the fabrication of the reactor vessel internals was -

incorporated into the table of specifications.

Reason for Chance This change was irnplemented to provide additional infonnation and to reflect the actual plant s configuration.

Safett Evaluation 1 This change is editonal in nature. The added runterials are equivalent to the snaterials prniously listed and the pliysical properties are ecmparable. Therefore, the change is safe and does not constitute an Untniewul Safety Question.

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FS APCR Number M 97.Mp3 243 Reliability Test: and Inspections Clanfications  :

pmgjption of Chang The desenption of the periodic testing of Emergency Core Cooling System components was clanfied to ,  ;

state the testing is perfortned in accordance with applicable plant procedures ,

Enrn for chang This change was implemented to accurately reflect in what Modes the components are tested.

Safety Evaj alim This change is editorial in nature and does not modify plant components nor change plant surveillance procedures Therefore, the change is safe and does not const tute an Unteriewed Safety Question.

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  • actor Materials Changes Description of Chance The desenption of the detailed evaluation of the reactor internals was clarified by directing the reader to '

Chapter 1.ft and incorporating additional editorial changes.

Beason for Chance This change was implernented to chminate irrelevant infonnation and to be consistent with applicable -

quality assurance procedures.

Safety Evaluation This change is editorial in nature and does not change the way the plant is operated not change any plant equipment or design pecifications. Therefore, the change is safe and does not constitute .tii Unreviewed Safety Quettion. -

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f.16ECR Number lhlt 97 MP3 252 Equipment Suppons.1.cadmg Combinations, and Design Allowable Stresses Format Changes  ;

i' Desenotion of Chance , ,

The table of Equipment Suppons, Loading Combinations, and A.llowable Stresses was reformatted.

Reason for Chanet This change was implemented to avoid any confusion u hen resiewing the information, and to be consistent with design documents., l Safety Evaluation This change is editorial in nature and does not alter system design specifications, operating parameters or methodologies. Therefore, the change is safe and does not constitute an Unteviewed Safety Question.

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l (j TS ARCR Number M I 97 MP3 255 Containment Mass and Energy Analpical Assumptions Clanfications i

Deeriotion of Chance '

The containtnent mass and energy analytical assumptions were corrected by incorporating various editorial cortections-Reason for Chance "Ihis change was implemented to derme the in'ent of statements and reficc1 analytical assumptions and results.

Safett INaluation This change is editorial in nature and does not modif

  • plant components. Operation of the containment systems is not changed. Therefore, the change is safe and does not constitute an Unteviewed Safety Question. ,

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i 97 MP3 261 Mass and Energy Release Data pngription of Chance The Mass and Energv Release Data was changed to indicate that the steamlme isolation signal is generated in high containment pressure and the feedwater isolation signal is generated by the safety injection signal.

Renon for L hance This change was implemented to tellect actual plant configuration.

Safety Evaluation

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_._' plant components or system. Therefore, the change is safe and does not constitute an Unteviewed Safety

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b FS ARCR Number Lik I 97 MP3 263 Containment Systems Changes l l

Description of Chante Correct and accurate information was incorporated into the tables and figures to clattfy analyses, -

assumptions and results.

i Reason for Chante This change was implemented to reflect actual plant configuration and to be consistent with design documents, Safety Evaluation This chan,ge is editorial in nature and does not create any physical changes to the plant equipment. The chanac is cont'~~' with design basis doeurnents. Therefere, the change is safe and does not constitute an Unreviewed F . . ,

,uestion.

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97 MP3 285 Analysis of ESFAS Clarifications Desenotion of Chance Additional information w hich was part of the original plant design was incorporated and various -

grammatical inconsistencies and typographical enors were corrected in the analyses for ESFAS.

Reason for Clw >

Tids change was incerporated to seflect actual plant configuration, correct enors and clarify terminology, Safety Evaluation This change is editorial in nature and does not alter any plant equipment. The change is consistent with licensing and design bases documents. Therefore, the change is safe and does not constitute an Unteviewed Safety Question.

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FS ARCR Nutats.t Iglg 97 MP.) 287 Control Systems Not Required for Safety Desenotion of Chance Various editorial changes were incorporated into this section to correctly desenbe functions and ,

operations of the various systems not required for safety.

Reason for Chance This change was implemented to correct discrepancies and to reflect desenptions found in other design documents.

Safety Evalua.li20 This change is editorial in nature and does not involve modtfications to system design, operation or equipment. Therefore, the change is safe and does not constitute an Unreviewed Safety Qu'estion.

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FS ARCR Number Ij,tk 97 MP3124 Reactor Materials Change l Description of Chance ,

The list ofinsterials used in the fabrication of the vessel internals u;as changed by deleting the re.ference , l to materials and documents not used and adding materials that wev, used. l l

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

Safety Evaluation This change is editorial in nature and does not introduce any parameters w hich impact plant design. The materials used are comparable to the original design specihcations and will perform as originally designed. Therefore, the change is safe and does not constitute an Unreviewed Safety Question. ,

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FS ARCR Number Illig ,

97 MP3 325 Emergency Core Coolmg System Component Parameten  !

Change Description of Chance The accumulators operating tempersture was changed and the nominal water volume and nitrogen gas tolume u ere conected in accordance with previously approved analyses and calculations. The section describing anotor operated valves was deleted.

Bguenfor Chance This change was implemented to reflect actual plant operating parameters based on design base analysis  !

data inputs and to be consistent with other design documents. The motor operated valve design parameters w hich were deleted are found in other controlled design documents.

Safety Evaluation This chante is editorialin nature tnd does not modify ( - wise any plant components or design base analyses. Therefore, the change is safe and does not constitute an Unteriewc4 Safety Question. l i

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FS ARCR Number Illjs 97.htP3 327 Rrefueling Water Storage Tank Water Levels Change Resermtion of Clungg The figure uNch shows the refueling water storage tank water levels was changed to reflect the center of, the Emergency Core Cooling System suction line and to indicate the Low Low. Low level is *cmpty".

hason for Chance This change was implemented to reficct the actual configuration of the tank.

i Safety Evaluation '

This change is editorial in nature because the correct value for the suction hne elevation was used in the

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

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97. hip 3 332 Ventilation System Temperature Control Change Description of Chance The description of the Engineered Safety Features Building emergency ventitation air supply ternperature in the machinery tooms was changed to clarify that the minimum temperature is based on the air supply '

ternperature and not on the area temperature. The air temperature sensing element was also relocated.

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

l Safett Evaluation This change does not affect the summer mode of operation and the winter mode of operation is made ,

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

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FSARCR Number 1 i11 . {

97.hD'3 334 Steam Generator Blowdown System Change Desertotion of Channe  !

The description of the steam generator blowdown system flow rate was changed to reflect a lower flow ,  !

rate.  !

Reason for Chanze . .

[

This change was implemented to reflect actual plant configuration based on current plant life conditions. l Safets Evaluation  !

This change is editorial in nature and does not affect the occurrence or probability of an erosion / . j corrosion failure in the blowdown system. Therefore, the change is safe and does not constitute an  :

. Unreviewed Safety Question.

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FS ARCR Nun :er Iith 97 hU'3 358 Aru Radiation and Airborne Radioactinty Monitoring Changes Description of Cham -

The description and associated tables of the area radiation and airborne radioactnity monitoring equipment were clarified by incorporating various edito-ial changes that resulted from presious equipment and procedure changes.

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

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

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i FSARCR Number Igt]g 97 MP3 361 Emergency Core Cooling System Relief Valve Data Change Description of Chance . -

The table of relief valve data was changed to reflect present terminology and values for set pressure, back pressure and capacity.

BIason for CFuga This change ,as impic.nented to be consistent with actual design and set point of the pressure relief vahes.

Sg ,uation T. tis . 'nge is editorial in nature and does not change the design or operability aspects of the valves.

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

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p i FSARCR Number IE]s 97 MP3 366 Habitability Systems and instrumentation Requirements i Changes j l

Destnotion of Chance .

i The description of the habitabihty systems design bases and instrumentation requirements was revised in j the Final Safety Analyses Report.

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

Safett Evaluation This change is consistent with heensing and design bases documents. Therefore, the change is safe and ,

does not constitute an Unreviewed Safety Question.

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\ FSARCR Nunnber Ink V7.MP3 390 Turbine Bypass Yaht Description Change i.

Description of Chance The description of the procedure for snanual operation of the turbine bypass valves during normal plant ,

shutdown was changed.

Reason for Chance This change was implemented to clarify incomplete infonnation and provide a general description of the entire manual control of the turbine bypass vah es during shutdown and cooling.

Saf-tv Evaluation ,

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- This change is editonal in nature and does not create any physical changes to '.he valve or its controls.

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

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FS ARCR Number liik 97 MP3407 Fire Protection Program Manual Changes Dngjption of Change i The Fire Protection Program Manual uas incorporated into the Fire Protection Evaluation Report to enhance the esisting fire protection program. Additional clarincation was provided for specific five protection features controlled by the Fire Protection Prograin.

Reason for Chante This change y as implemented to enhance the fire protection program and assure that all aspects of the fire protection program are presented in a unified rnarmer and accurately documented.  !

Safety Evaluation This change documents current fire protection features and is consistent with licensing and design bases documents. Therefore the change is safe and does not constitute an Unreviewed Safety Question.

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97.hU'3-410 Fuel System Design and Functional Design of Reactivity .

Control System Changes l Descriotion of Chagg The descriptit .) of various components of the fuel assembly, control rod, bumable absorber assembly, secondary source assembly and control rod drive system were changed by correcting dimensions and configuration information.

Reason for Chance This change was implemented to reflect actual plant configuration and be consistert with design  !

documents.

Safety Evaluation This change is editorial in nature and does not cret te any physical changes to plant equipment. _ The -

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

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TS ARCR Number 11tk 97 MP3418 Domestic Water and Sanitary Sys1em Change Description of Chance The desenption of the sanitary system was changed to state that noncontaminated drainage is directed to ,

the town sewer system and a correction of the domestic water flow rate was incorporated.

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

Safety Evalggnon Tids change is editorial in nature and does not impact any safety related systems or plant operations.

Therefore, the change is safe and does not comtitute an Untniewed Safety Question.- .

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("3) EQCR Number 97 MP3-419 18].E Condensate Surse Tank Level Clarification Qt,5cription of Chanct The reference to a normally maintained surge tank inventory of 73,000 ga:lons was changed to state a less specific inventory.

Reason for ClaDER This change was implemented to reflect actual plant conditions which do not recuire or support a specific surge tank inventory.  ;

Sn(sg Evaluation This change is editorial in nature and the w- Je tank inventory is normally maintained at a level that will allow for surges from the Condensate syste : n the event ofload transients. Therefore. the thange is safe and does not constitute an Unreviewed Safety Questiott t

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l FS APCR Number ljik 974tP3436 Senice V/ater Cubicles Interconnecting Door Clarification ,

Description:

oLChange The figures that indicated a door t*tueen the service unter pump cubicles were changed to remove the door from the figure Reason for Chan,gt This change was implemented to reflect actual plant configura lon because the door was not installed.  ;

Safett Evaluation  ;

Tids change is editorial in nature, is consistent with design documents and does not create any physical change to plant equipment Therefore, the change is safe and does not constitute an Unreviewed Safety Question. ,

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f'y V ESARCR Number 974fP3-437 11]h Components Requiring inelastic Analyses Change Description of Chance The table which lists the components requiring incalastic analyses was changed to include additional components and their analyzes.

  • Reason for Changg TI'is change was implememed to reflect, actual plant configuration.

Safety Evalusti2D This change is editorial in nature and does not alter rystem design specifications, operating parameters or methodology The change is consistent with licensinE and design bases documents. Therefore, the

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

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FSARCR NuWt ljlig .

97 MP3-444 Auxiliary Building Ventilation Changes Description of Chance The design parameters of the auxiliary building heating / ventilating supply fans and ventilation exhaust ,

fans were changed to correspond to the flow and fan blade settings mac'e during startup testing.

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

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

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- fSARCR Nnmher . 3 !

= 97 MP3-461 - _

Desistions to the Electrical Separation Criteria Outside -

Panels Descrintion of Channe - -

The discussions of electrical separation and egulatory guides were changed to incorporate documentation :

which allows deviations based on tests, Reason for Channe This change was implememed to retlect actual piant configuration.

Saferv Evaluation The test results show that these deviations still maintain the single failure enteria between redundant

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

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(}j f1ARCR Number Ig]s V 97 MP3-478 Control Building Ventilation System Change Description of Changg The description of the control building purge exhaust fan was changed to indicate that it is manually staned from a control switch at Ventilation Panel 1 (VP1).

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

Safety Evaluation This change is editorial in nature and does not affect the design function of the control building purge ventilation system Ther ore, the change is safe and does not constitute an Unreviewed Safety Question.

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FS ARCR Number ~. Iit]g __

- 97 MP3-479 Control Building Ventilation System inspection and - -;

Testing Requirements Changes Description of Channe , _, . . _,

The reference to perform monthly component inspections was deleted and replaced with sun'eillance -

  • requirements imposed by Technical Specifications. The references to
  • Chapter * <" were also deleted.

Reason for Channe This change was implemented to reflect actual surveillance performance and clarify the basis for the ,

surveillance.

Safety Evaluation The change assures system operability by imposing the suntillance requirements contained in Technical Specifications. Therefore, the change _is safe and does not constitute an Unreviewed Safety Question.

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FSARCR Number
3- _. .

-%:4P3 485 - Hydrogen Supply System Description Clarification-

- Dese .aion of Chance

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The reference to the maximum amount of hydrogen required as make up due to leakage for the turbine _ i generator was deleted.

Reason for Chugg ,

This change was implemented to reflect the established make up rate which is monitored by the Operations Department.

- Safety Evaluation Deletion of the make up value does not change the operation of the plant and current monitoring .

procedures assure that sufficient hydrogen is maintained in the turbine generator Therefore, the change is safe and does not constitute an Unreviewed Safety Question.

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