ML20214D877
| ML20214D877 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 04/30/1987 |
| From: | Jensen H Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML20214D882 | List: |
| References | |
| NUDOCS 8705210521 | |
| Download: ML20214D877 (107) | |
Text
{{#Wiki_filter:c AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 86-354 UNIT Hope Creek Gen. Station DATE 05/06/87 COMPLETED BY H. Jensen TELEPHONE (609) 339-5261 April, 1987 MONTH DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (HWe-Net) (HWe-Not) 935 1 ___ _ __ _ 17 18 935 . 2 925 3 19 929 934 4 20 931 5 _- _ - - _ 21 __ 22 924 6 __ 926 7 23 24 928 8 1032 931 9 25 1020 931 10 _ _ _ _ 26 1024 928 11 __ ______________ 27 28 937 12 _ _ _ _ _ _ 930 13 - _ _ _ 29 _ 923 I 14 _ 30 i
~~~
15 31 j 945 ; 16 1 1 l 0705210521 070530 l PDR ADOCK 05000354 R PDR
OPERATING DATA REPORT DOCKET NO. 86-354 UNIT Hope Creek Gen. Sta. DATE e5/06/87 COMPLETED BY H. Jensen TELEPHONE (6091339-5261 OPERATING STATUS
- 1. REPORTING PERIODApril 1987 GROSS HOURS IN REPORTING PERIOD 719
- 2. CURRENTLY AUTHORIZED POWER LEVEL (MWt) 3 19)
MAX. DEPEND. CAPACITY (MWe-Net) 1967* DESIGN ELECTRICAL RATING-(MWe-Net) 1962 3 POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net)__ None
- 4. REASONS FOR RESTRICTION (IF ANY)
THIS YR TO MONTH DATE CUMULATIVE -
- 5. NO. OF HOURS REACTOR WAS CRITICAL _
719 27 08 2996 i
- 6. REACTOR RESERVE SHUTDOWN HOURS G G 0
- 7. HOURS GENERATOR ON LINE 714 2683.1 29'71.1.
- 8. UNIT RESERVE SHUTDOWN HOURS e 0 0
- 9. GROSS THERMAL ENERGY GENERATED (MWH) 2.174.957 7.999.792 8,920,200
- 19. GROSS ELECTRICAL ENERGY GENERATED (MWH) 730.546 2.693.160 2.990,800
- 11. NET ELECTRICAL ENERGY GENERATED (MWH) 700.197 2.581.221 2.867,045.
12 REACTOR SERVICE FACTOR 100 94.1 94.6
- 13. REACTOR AVAILABILITY FACTOR ,
100 94.1 94.6
- 14. UNIT SERVICE FACTOR ine 93.2 93.8
! 15. UNIT AVAILABILITY FACTOR 1en 43.2 93.8
- 16. UNIT CAPACITY FACTOR (Using Design MDC) 41.3 _ _
&&__ 8 4. E_.
17 . UNIT CAPACITY FACTOF (Using Design MWe) 41.3 84 84.8
- 18. UNIT FORCED OUTAGE RATE G 6.8 6.2 1
i 19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, & DURATION) : Maintenance 09/23/87 -15 Days
' 20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: N/A
'0 Estimated Value. Actual value to be determined in July or August 1987. ! }
d OPERATING DATA REPORT UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET'NO. 86-354' Hope _~ Creek 1 Gen'. Sta. UNIT.NAME-DATE 85/86/87-i COMPLETED BY H. Jensen REPORT MONTH April 1987 TELEPHONE (609)339-5261 - METHOD OF SHUTTING l DOWN THE
-TYPE REACTOR'OR F FORCED DURATION REASON REDUCING CORRECTIVE ACTION /
I NO. DATE S SCHEDULED (HOURS) (1) POWER (2) COMMENTS 4 1 None . i i i l .l i :
- t I
I l-4 !.
, I' i i
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SUMMARY
- See attached i
i
HOPE CREEK GENERATING STATION
, MONTHLY OPERATING
SUMMARY
APRIL 1987 - The Hope Creek Unit entered the month operating at 99% power with this output being the administrative limit established by the Electrical System Operator based on electical- system stability considerations. Varying limits are placed on the output of the Hope Creek and Salem Generating Station as a result of the loss of the Hope Creek /Keeney 500KV transmission line. (See the Monthly Operating. Summary, March 1987 for additional details). The unit operated at essentially.these established limits throughout the month and did not experience any. reportable shutdowns or ' power reductions. On April 39, the unit completed its 61st day of , continuous power operation. f
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f, 1 e t 4-9
j
SUMMARY
OF CHANGES, TESTS, AND EXPERIMENTS FOR THE HOPE CREEK GENERATING' STATION APRIL 1986 THRU APRIL 1987 4
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I l I DCE Description 91 Change / Safety EvaluatioD 504 This DCP added 2 fire alarms to the Administration Building. The fire alarms did not create a new safety hazard to the- plant nor did they affect the safe shutdown of.-the reactor. This. DCP did not change .the plant-effluent releases and did not ' alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 513 This DCP added a temperature switch to the service water pump. This switch alarms when the stuffing box gland overheats. The temperature switch ~ does not affect the-operability of the service water pump and thus did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. This DCP did not change the plant effluent releases and did not alter the-existing environmental impact. -Therefore, no unreviewed safety or environmental questions are involved. ' 565 This DCP provided upgrades to the Post Accident Sampling System. The upgrades improved syst'em , operability and thus did not create a new safety hazard to the' plant nor did they affect the safe shutdown of the reactor. This DCP did not change the plant effluent releases and 'did not alter the existing environmental impact. Therefore, no .unreviewed safety or environmental questions are involved. 652 This DCP added drip trays and tygon tubing to the Auxiliary Building in order to protect ~ safety related components from non-safety grade hazard interactions (e.g. pipe leaks). This was a licensing commitment and did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. The DCP did not change the_ plant effluent releases and did not alter the existing environmental impact.- Therefore, no unreviewed safety or environmental questions are involved. 1 1
1
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I' i 1 IK3!' ' Description 91 chance / Safety Evaluation t . 653
~ ; This_DCP. added tygon tubing to drip trays in ; Diesel Building Rooms 5394~through '5387. .This '
protects safetyL related .equipmentL from: non-- '
- safety . grade. hazard interactions. (e.g.. pipe; R F -leaks). .The- installation 1of Tygon Tubing;_did not create a new safety; hazard'to the plant nor:
did it. affect the safe' shutdown of-.the reactor. The DCP. did not . change.-the. plant _ effluent releases .and - did not . alter' the existing
< environmental impact. Therefore,Lno.unreviewed
- safety _or environmental questions are involved.. l 1 -
DCP added drip. trays and,tygon.itubing 'in t 656 This j Diesel- Building Rooms _5538 through ;5545. 'This i
- protects safety related
- equipment- from' non- i
, safety grade hazard . interactions (e.g. pipe' ! leaks)._ The installation of drip _ trays. and tygon tubing.was a licensing commitment and did: 4 not create a new-safety hazard to the-plant nort l i did it affect the safe shutdown of the reactor.. This DCP did not change 'the plant effluent releases and did not- . alter. the existing- ! < environmental. impact.. Therefore, no unreviewed. j safety or environmental.. questions,are involved. 4 658 This DCP'added splash guards in; Diesel . Building Rooms ~5605, 5697,15612, and 56152 This protects-safety related equipment from non-safety. . grade j;
- hazard interactions- (e~.g. pipe leaks). .The .;
installation of splash _ guards was a. licensing. commitment and did not create;.a' ~ new safety. ' +- hazard _ to the plant nor didvit affect'the safe < shutdown of the reactor. This .DCP did- not change the plant effluent releases and did' not
- . alter the existing environmental ^ impact.
Therefore, no unreviewed. safety or. environmental , questions are involved. l 662 This DCP provided access!controllto a. ~ Turbine i Building . Area (Room- 1515). where radiation l' streaming occurs through a seismic' gap. -
.This
- f. DCP minimizes. radiation-exposure to' personnel-
. and. did not' create a-newfsafety hazard..to .the
!. plant nor did it affect the; safe shutdowntof1the
-{
i reactor. .This -DCP did not change.Lthe plant- effluent releases ~and.did not alter the' existing environmentalLimpact. Thereforejino_unreviewed safety or environmental questions are involved. a > '/ i , 1 I 5 l d- _ -. _ . _ ._ . . . - ~ . _ _ _ _ . _ _ _ .. . _ ... _ __- w _
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[ DCE. Descrintion g[ Chance / Safety Evaluation 1663- This DCP provided radiation shielding .for -the , seismic gap between the South Radwaste Steam Tunnel' (Room 4313)1and Turbine Building ' Room 4 1485. The addition. of the steel- plate as shielding did not create a new safety hazard to the plant nor did'it affect the safe shutdown of the; reactor. This DCP did not change.the plant' effluent releases and did not alter the existing environmental impact. Therefore,.no unreviewed safety or. environmental _ questions are involved. i 665 .This DCP provided shielding for.the; seismic gap in . Turbine . Building Room 1319 to prevent-radiation shine' to Rooms 1392 and 1393. The , addition of a steel plate as shielding.did not. create a new safety hazard.to the plant nor- did
--it, affect the safe shutdown of the reactor.
This DCP did not' change the plant -effluent ~ releases and did not alter- .the : existing environmental impact. Therefore,-no unreviewed safety or. environmental questions are involved. 672 'This DCP added a barrier to protect'line BB-236- . 1" from any jet impingements. This DCP.did not create a new safety hazard to the plant nor did it affect the safe-shutdown of- the ' reactor. This DCP did not-change the plant effluent releases and did. not alter' existing environmental impact. Therefore, no unreviewed. safety or environmental questions are involved. 687 This DCP disconnected Reactor Building Ventilation System (RBVS) Supply. Dampers, RBVS-Exhaust Dampers, Radwaste 1 Supply Dampers, Radwaste Exhaust Dampers, and Radwaste Tank. Vent Dampers from their non lE.' power source and-connected them to-the same class lE power source as their associated fans. This DCP did -not create a new safety. hazard to the plant nor did it affect the safe shutdown of.the reactor. It did not change.the: plant effluent releases -and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. d
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.DCE DescIlRhiDD si fhange/ Safety'EyaluatlDD 691- This DCP added convection;stop. insulation at the Bioshield Wall Doors and 'at other unsealed Bioshield Wall Penetrations to help the Drywell:
cooling system' maintain the temperature in- the area between -the Bioshield and - the Reactor Pressure. Vessel Insulation within the acceptable limits. The additional ~ insulation did .not create a new safety hazard to the plant nor.'did it affect .the safe shutdown of the ' reactor.- This DCP did not change the plant effluent releases and. did. not galter- the existing environmental impact. Therefore, no unreviewed 4 safety or environmental questions are involved. 692. This DCP added~ cables to . support, Radiation
, Monitoring equipment._ The. cables did not ?
create a new safety hazard.to the plant nor did they affect the safe shutdown of the reactor.'
, This DCP did not change the plant effluent.
releases and did not alter the- existing-environmental impact. . Therefore,;no unreviewed safety or' environmental. questions are involved. 696 This DCP installed a jumper across 2 contacts in order to make the existing circuit work with CV-l 22 relays. The relays.will'be. replaced. by a future DCP. The installation of the. jumper did i not create a new safety hazard nor did it affect [ the safe shutdown of the reactor. It did not change the plant effluent. releases and did not
~
alter the . existing environmental -impact. Therefore, no unreviewed safety or environmental ] questions are involved. 791 This DCP added filter units 1for. collecting and concentrating metallic-impurities:and replaced Feedwater Grab Sample Lines with Filter. Lines.
; This DCP did not create a new safety hazard to-the plant nor did it affect the safe shutdown-of-the reactor. .It did not_ change the plant effluent releases and did.not alter the existing; environmental impact. Therefore, no'unreviewed 4-safety or-environnental questions are involved.
~ 792' Tnis DCP added cards and cable to cabinet AC655' to add computer point A7999 and _used' existing - spare points in cabinet DC655 to add computer [ point A7901. - The addition- of the computer points did not create a new safety hazard nor. _ did it affect the safe shutdown of the reactor.. It did not change the plant effluent _-releases , and did not alter the existing. environmental--
- . impact. Therefore, no unreviewed - safety ao r -
environmental questions are involved. i 4:
IK2 Description 21 Change / Safety Evaluation 5012 This DCP revised the wiring to the hot deflection displaceant transducers.to eliminate the need to visually inspect. piping inside the Drywell. This DCP did not create a new safety. hazard nor did it affect the safe shutdown of' the reactor. It did not ' change the plant effluent releases and did not alter.the existing environmental. impact. .Therefore, no unreviewed safety or environmental questions are involved. 5024 This DCP modified the Reactor Recirculation Pump logic to add -runback capability.- This modification did not create a-new safety. hazard nor did it affect the safe shutdown- of the reactor. This DCP did not change -the plant 1 effluent releases and - did not, alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. { 5025 This DCP revised the pipe supports for, the~ Motor-Generator Set Lube Oil Pump Suction and Discharge Lines to eliminate excessive vibration. This DCP did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant. effluent releases-and did not alter the existing _ environmental . impact. Therefore, . no unreviewed safety or environmental questions are involved. I 7031 -This DCP installed a drip shield under a storm drain -line to protect class lE equipment from l pipe leaks. The installation of the drip shield
- did not create a new safety hazard to'the plant i
nor did it affect the safe shutdown of the ! reactor.- It did not change the~ plant effluent' l releases and did - not -alter the existing-environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 7037 This DCP corrected water hammer problems which were being experienced in the . Domestic Water 3 piping in the Auxiliary Boiler Building.- This-DCP did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the-plant effluent releases and did- not alter the existing-environmental impact. .Therefore,.no unreviewed safety or_ environmental questions'are-involved. 5 _ __ , __ _,
LDCE DescriptiRD 91 . Change / Safety Eyaluation 7865 This DCP.provided.a Deep Well Water. Pump feed to existing Fresh-Water Storage Tanks. It also revised- the control wiring logics:to start the-well pump (s) on low water level in either'. - Domestic Water Storage Tank or either Fire Water Storage- Tank. .This DCP did not create a new safety hazard to the plant nor did it affect the-safe shutdown of the. reactor. It did not change the plant effluent releases and.did not . alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 7987 This DCP added an access panel Lin .the-Guardhouse (Room 107). It._ allowed floor penetration F197-1 to be sealed. This panel did not create a new. safety hazard to the plant nor did it affect the safe shutdown of- the. reactor. It did not- alter the- existing. environmental. impact. . Therefore, no unreviewed safety or environmental questions.are involved.- 7090 This DCP relocated 'the Condensate Level switches so that the trip points can be verified. This change did not alter the function of these instruments and thus did .not create a new safety hazard to'the plant nor did 4 it affect the safe shutdown of the reactor. It did not change the plant effluent and did (not alter the existing environmental impact. Therefore, no unreviewed safety or environmental-
; questions are involved.
7106 This DCP provided mounting brackets for Self-
, Contained Breathing Apparatus and Emergency Life
. Support Apparatus. This installation met an FSAR commitment and did not create a new safety 3 hazard to the plant-nor did it affect the safe shutdown.of the reactor. It did not. change the plant effluent releases and did not- alter- the existing environmental impacts. Therefore, no' unreviewed safety or' environmental questions are involved. 7119 This DCP re-routed steam supplies and heat tracing lines and changed steam trap locations to allow for condensate drainage. This DCP did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It .did not change the plant effluent releases
; and did not alter the . existing environmental
- impacts. Therefore,- no unreviewed safety or environmental questions =are involved.
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l DCE Darcriptinn of chance / Safety Evaluation ~ 7122 .This DCP modified the Ultrasonic. Resin LCleaner 3- to permit better operations-and to- reduce -the loss of resin. -Thistmodification~did not create a new safety l hazard-to the-plant.nor did Dit affect the safe shutdown of the reactor. It did
- not change the. plant effluent releases and did.
not. alter the existing environmental' impacts. Therefore, no unreviewed safety or environmental questions are involved. 7141 This DCP added 2 beams to upgrade'the structural' steel framing due to loading on hanger'-1-P-AB-098-HB5. The. beams did.not: create a new: safety. hazard to the plant nor.did they affect the safe shutdown of the.. reactor. This DCP 'did not i change the plant effluent" releases and did -not-alter the existing environmental . impact. Therefore, no safety or environmental, questions , are involved. 7153 This DCP rewired all_. safety-related Tobar instruments. This DCP .did not create a new safety hazard to the plant-nor did.it affect the. safe shutdown of the reactor. It did not change the plant effluent releases and did not;-alter
- the existing environmental impact. Therefore,.
no safety or environmental questions are involved. 7155 This DCP upgraded 12 : pressure indicator-installations to ensure containment. pressure boundary integrity.- This DCP met an NRC Inspection Report commitment and did not create-
! a new safety hazardato the plant nor did it J affect the safe shutdown of'the reactor. 'It- i did not change the plant effluent! releases.and 1 i' did not alter the existing environmental ;
impact. Therefore, no .unreviewed safety .or environmental questions are involved. I 7157 This DCP provided an additional door.in the_ wall' i of the Unit 2 Reactor Building to provide. access 1 to temporary office space in the Diesel' Building. This DCP did not create a new safety, hazard to the plant.nor did it affect the: safe
~
shutdown of the reactor._ Itfdid not change:the= 4 plant effluent releases and did not1 alter the existing environmental impact. Therefore, no unreviewed safety or environmental ~ questions are involved. i L i L 2____ , . . _ ~ - 7- .
.i DCE Description'gf' Change / Safety Evaluation.
7163 This DCP replaced Reactor Building LVentilation System: Exhaust.ductwork. The_ductwork change did not create a,new' safety-hazard to the. -plant-nor did it affect the safe' shutdown of -the' reactor. It _did.not change.the plant; effluent releases and did- not alter the- ' existing:
' environmental impact. -Therefore,.no'unreviewed safety or environmental ~ questions are' involved.
7167 This DCP replaced a. rotating camera with 2 fixed-focus cameras with .wide angle. lenses.. The; cameras did not create a new safety 1 hazard .to the plant nor did-they= affect the safe shutdown of the reactor. .This DCP did not[ change the plant . effluent releases <and'did not alter thel existing environmental impact. Therefore, no unreviewed safety or environmental questions are , involved. 7169 This DCP repaired existing fireproofing_ and added new-fireproofing to beams and columns. in order to meet- an FSAR. commitment. .This . fireproofing did not create a safety hazard. to l the plant nor did it. affect the safe shutdown of. the reactor. This DCP did not change the-plant effluent releases and did not alter-the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 7171 This DCP provided.an access platform ~ for the Service Water Intake Structure Gantry. Crane. The access platform did not- create a safety hazard to the plant nor.did'it affect.the -safe shutdown of the' ~ reactor. This DCP did not-change the plant effluent releases and did' not alter the- existing . environmental impact.; Therefore, no unreviewed safety or environmental questions are involved.. 7175 This DCP provided -support for unrestrained equipment (printer and keyboard / printer) located in the. Control Room. This DCP--met an 'FSARi commitment and did not create a safety hazard to= the plant nor did it_ affect the safe ~ shutdown of-the reactor.- This DCP did not change ~the plant: effluent releases and did.not alter the-existing environmental impact. Therefore, nozunreviewed safety or environmental questions are involved.- 8
5 DCE Description hf Change / Safety Evaluation 7177 This DCP consolidated Condensate- Demineralizer sample ' points and' rewired the transmitters to-send their signals toa different control panel. This DCP.did not' create a new. safety hazard to the plant,nor did it affect ~the safe shutdown of the: reactor. . It did not--change':the . plant effluent releases'and did not alter ~the existing-environmental impact.- Therefore, no'unreviewed. safety or environmental questions:are involved.. 7181 This DCP installed a sampling _ instrument to provide a sample from the Crystalizer Bottom Tank. This DCP did not create a new -safety s hazard to the plant nor did it affect'the- safe shutdown ~of the reactor. It.did not change the-plant : effluent releases and~did.not' alter the ; existing environmental impact.. Therefore, no unreviewed safety or environmental questions. are involved. , 7185 This DCP' added/ changed fire door hardware :to. i meet .NFPA criteria. , This upgrade was Ja j licensing commitment and did not create' a inew. I safety hazard to the'-plant nor'did'it affect'the-safe shutdown of the reactor. It:did not' change the plant effluent releases and did not alter the existing environmental:_ impact. -Therefore, no unreviewed safety or. environmental questions-
- are involved.
7186 This DCP provided _ annunciation for Liquid Radwaste Discharge Isolation' due_ to either Liquid Radwaste High-Flow, Liquid Radwaste High-Rad, or Cooling Tower Blowdown Low Flow. .This annunciation did not create a new safety hazard to thefplant nor did it affect the safe shutdown of the reactor. It did not change 'the plant effluent releases and did-not alter the existing environmental impact. Therefore, no unreviewed safety or-environmental questions are involved. 7199 This DCP added a flow orifice- ~ to a ~ Reactor Recirculation line._ The addition of the flow orifice did_ not create- a new safety: hazard to the plant'nor did it affect 1the safe' shutdown of the reactor. It did not_ change the plant ~ effluent releases and- did not ' alter - the existing environmentalcimpact. Therefore, no
- unreviewed safety or environmental questions.
are involved. 9
~ . _ _ _ _ _ . _ _ . _ _ . __ . _
k DCE -Description pf' Change / Safety Eyaluation 7192 This.DCP replaced trim componentsLinl valves ~ in the Reactor Core. Isolation Cooling and,lHigh; Pressure- Coolant . Injection ' Turbine. Steam systems. This DCP did.not create a new safety: hazard-to~the.plantinor~did it affect the safe shutdown of the reactor. It.did not change the. plant _ effluent releases and did not. alter -the existing environmental impact. .Therefore, no unreviewed safety or' environmental question are involved. 7193 This DCP changed the control logic for several valves-in the Gaseous Radwaste' system. -This DCP did not create a new safety hazard Ltx> the plant nor did- it affect the safe - shutdown- of._ the reactor. It did not. change the plant effluent releases and did not alter the existing environmental' impact. Therefore, no unreviewed-safety or environmental question are involved. 7199 This DCP _provided water tight seals for-(all penetrations through radwaste dikes. This DCP l met an FSAR commitment and did not create ~a :new safety hazard to the plant nor did it affect the-safe shutdown of the_ reactor. It did not change" the plant effluent releases and did not alter-the existing environmental impact. Therefore, no unreviewed safety or environmental questions-are involved. 7201 This DCP installed a drain pot,- level control valves, and controls on the ' Steam Jet Air Ejector Aftercondenser Drains. This DCP did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It: did not_ change che plant effluent _ releases and did not alter the existing' environmental' impact. Therefore, no unreviewed safety or environmental-questions are involved. 7205 This DCP provided an interlock between- doors 4322, 4326, and the receiving bay-door (4323A) , so that they cannot be opened ~ while the receiving bay-door is open. . This DCP did not create a new safety hazard to the plant nor~did it affect the safe shutdown of the reactor.- It. did not change the plant effluent releases ~ and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 18
i DCE , Description di, Change / Safety Evaluation
-7296 This .DCP synchronized the' clocks in the Control _ -
Room .and the Shift Supervisors . office. The
. synchronization' did not. create a_ new-- safety.
, hazard. to the. plant nor did it affect the safe shutdown-of-the reactor. ~_It.did-not change-the-plant . effluent- releases and did not alter--the existing' environmental impact..
~
Therefore, no unreviewed safety or. environmental questions are involved. 7209 The DCP replaced Tobar -transmitters .with Rosemount transmitters.: This'DCP did not create a new safety hazard.to;the plant nor did it affect the safe shutdown of-the reactor. It did not change the plant effluent releases'and. did not alter the existing environmentalf impact. Therefore, no unreviewed. safety or. environmental questions are involved. 7210 This'DCP revised the wiring for.the. control Room Integrated , Display computer system. This DCP: did not create a new safety hazard to the plant nor. did it affect the safe. shutdown of_.the reactor. It did not change the-plant. effluent releases and did not : alter the existing' environmental impact. Therefore, no unreviewed . safety or environmental questions are involved. R 7211 This DCP changed the glycol cooler refrigeration units from continuous to intermittent operation. l This conversion did not create a new safety l hazard to the plant nor did it affect the safe shutdown of the reactor. The DCP did not change the plant effluent releases and.did. not alter the existing environmental impact. Therefore,- no unreviewed safety _or environmental 1 questions are involved. 7212 This DCP replaced the Oily Waste Sump Pump. Impellers with larger ~ impellers._ This DCP did not create a new safety hazard to.the plant nor did it affect the safe shutdown'of the reactor. The DCP did not change; the plant effluent releases and did. not alter the existing environmental impact. Therefore,-no unreviewed -l safety or environmental questions are_ involved. ; l 1 1 1 11
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1 DCE Description gf Change / Safety Evaluation 7214 .This DCP provided permanent power to a~ flow' , indicator in the Station Service Water. system. This DCP did notl create a newLsafety hazard to the plant nor did it affect thel safe shutdown of the reactor. The DCP'did not_ change the ' plant effluent releases and did not alter the existing- L environmental impact. . Therefore, .ru) unreviewed safety or environmental questions are involved. 7461 This DCP replaced the tubing and fittings on the Containment Vent / Purge' Valves. _This DCP did not create a new safety hazard to the plantinor did . it' affect the safe shutdown ~of the reactor. It: 4 did not change the plant effluent releases and , did not alter the existing environmental impact.~. i Therefore, no unreviewed safety or environmental- _ questions are involved. This- DCP added 2 new axial restraints on Ithe 7466 ^ Auxiliary Steam System to alleviate water hammer problems. This DCP-did not create a new safety.
-hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not. alter the '
existing -environmental impact._ Therefore, _no unreviewed safety or environmental questions'are involved.
; 7468 This DCP relocated a hanger to eliminate a thermal interference problem. This DCP did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact.
Therefore, no unreviewed safety or environmental questions are. involved. 1 GH-ZZ-002 This DCP provided coaxial cable to allow the. Guardhouse to access the corporate computer-j systems. The installation of~this cable did not create a new safety hazard to the plant nor did
; it affect the safe: shutdown of-the reactor.- It-did not change the plant effluent' releases and did not alter the existing environmental impact.
Therefore, no unreviewed safety or environmental questions are involved. ,
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r j 12-
-DCE Description of Change / Safety Jil1gluation: This DCP.was used to' install.the -Dechlorination
~
~HC-DF-002 system. This_DCP met a licensing commitment and. did-not create a new safety hazard to the . plant nor did it affectithe safe;. shutdown of- the reactor. It did not change the plant effluent releases .and .did not _alte r - the. existing environmental impact. Therefore, no.unreviewed safety or environmental. questions are involved. HC-KC-004 This DCP provided for the installation of fire barriers inside and'around non-segregated . phase bus ducts.where there were penetrations in the 3-hour-rated floor orJwalls.. This DCP fulfilled. an: NRC commitment- and did not . create a new safety hazard to the plant nor-did it affect the safe shutdown of the reactor. .It did not alter the existing environmental impact. .Therefore, no unreviewed safety or. environmental questions are involved. HC-NA-002 This DCP added support'to the, duct expansion joints on the exterior 4.16KV and 7.2KV :non-segragated phases busses. The added-supportLdid not create a new safety. hazard nor did it affectf the safe shutdown of the reactor. -It did not change the plant effluent releases.and did not alter the existing. environmental impact. , Therefore, no unreviewed safety or environmental questions are involved. HC-QA-003 This DCP replaced l'ight. fixtures in the machine-shop to increase illuminationL levels. The. increased illumination did not create a new safety hazard nor did it affect..the safe shutdown of the reactor.. It did-not change the plant effluent releases'and did not alter -the- l existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. UC-QA-004 This DCP provided 120 volt AC dedicated circuits and outlets-in the Operations 1 Conference Room in. the Control / Diesel Building. This DCP did 1not' create a new safety hazard nor did'it affect the' I safe shutdown ~of the reactor.. It did not change the plant effluent releases and did not alter-the existing environmental impact. Therefore, no unreviewed safety or environmental questions-are involved. 13 j
DCE Descriotion Af Chance / Safety Evaluation HC-QA-005 This' DCP added' a 249 volt ' outlet in -the
- Technical Document-Room.- This outlet'did not create 'a new. safety hazard to-the plant ~nor did e it affect the safe shutdown of'the reactor. lit e did- not~ change the plant effluent releases and did not alter the existing _ environmental impact.
Therefore, no unreviewed; safety or environmental questions are involved.
~ 'HC-QA-006 This DCPrinstalled a 298. volt /28 amp outlet in
- - the . Service and Radwaste Building (Room- 3421)
. for thel Perkin-Elmer Graphite ~ Furnace. This outlet did not create a.new safety-hazard.tc the plant nor did it affect the safe shutdown of the-reactor. -It did'not change the plant effluent releases and .did 'not alter the . existing environmental impact.. Therefore, no!unreviewed ' safety or environmental questions are involved. HC-QJ-002 This:-DCP_ provided heat tracing for! the Steam Supply Piping and the Condensate Return Line between the Auxiliary Boilers and :the Esteam traps. This DCP did not create a new safety _ hazard 'totthe plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the
- existing environmental impact... Therefore,- no
, unreviewed safety or environmental questions are involved.
HC-QL-902 This DCP installed a back-up radio communication- j system in.the control' Room. This-DCP; met an NRC H +- commitment ~ and did not create- a- new ' safety hazard to the plant nor-did it affect the safe-shutdown of the' reactor. It.did not change the i plant effluent releases and did not alter' the
- existing environmental impact. .Therefore, no
; unreviewed safety or environmental questions are involved.
HC-WE-002 The DCP increased.the. space between -conduit. i 14NRMS52 and transformer 19A491. .This DCP did not create a new safety hazard to the-plant nor
~
l did it affect the: safe. shutdown of the reactor. It did not change the plant effluent- releases , and did not alter the existing ' environmental _ , impact. Therefore, no unreviewed ~ safety or- , environmental questions are' involved. i I i 14 R
DCE Description af Chanae/ Safety ~ Evaluation.
~
4-BCM-85-0006 This DCP bypassed portions of-the Solid Radwaste system and provided; an . alternate. method of processing the solid radwaste.- This.DCP did not create a new safety hazard to the plant nor'did it affect the safe shutdown of the reactor. It-did not change.the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed-safety or environmental questions are involved. 4-EMJ-85-00ll This DCP added cable to' provide-plant electric load data to the. load dispatcher.- This DCP did not create a new safety hazard to the plant nor did it affect the safe shutdown of_the reactor.- It did not change the~ plant effluent . releases and did not alter the -existing environmental-impact. Therefore, .no' unreviewed safetyL or environmental questions are involved.- 4-EMP-85-0012 This DCP replaced the leather piston cup seals in the High Pressure Coolant-Injection Turbine Stop Valve Hydraulic Cylinder with Buna-N seals.- This DCP implemented a General Electric recommendation to increase the reliability of the valve and did not not create a new safety hazard to the plant nor did it affect the' safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental _ impact. Therefore, no unreviewed safety or environmental questions-are involved. 4-EMM-86-0001 This DCP modified a hanger and added 3 other hangers in the Demineralized Water system. This DCP did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not- alter the existing environmental impact. Therefore, no -unreviewed-safety or environmental questions are-involved. 4-ECM-86-0003 This DCP replaced the gasket between the outlet relief valve flange-for a Residual Heat Removal u Safety Relief Valve with a'Gask-O-Seal'and'added a test hole in the piping flange. This DCP met a licensing commitment and did not create a new-safety hazard to the plant nor did it affect the safe shutdown of the reactor. 'It did not change the plant effluent releases and did not'-alter the existing environmental-impact. -Therefore, no'unreviewed safety or environmental- questions are involved. 15
DCE Description 2f Change / Safety Evaluation 4-EME-86-0008~ This DCP placed' the Reactor- Core Isolation Cooling. Trip and Throttle-Valve (HV 4282) fuse-and breaker in series to power feed the valve motor._ This DCP met a licensing commitment and did not create a new safety hazard to the plant-nor did it affect the safe shutdown of the reactor. It did not change-the plant-effluent releases and .did not alter- the existing environmental impact. 'Therefore, no unreviewed safety or' environmental-questions are involved. 4-EME-86-0009 This .DCP removed a jumper. from .the Main Generator Overcurrent. Relay.- . Removing the jumper will allow the relay to function .aus designed and did not create a new safety hazard to the plant nor. did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did.not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. i 4-EME-86-0014 This DCP provided 120 -volt /20 amp: outlets for portable fans to ventilate Inverter. Rooms and the Remote Shutdown Panel Room. This DCP met an NRC commitment and did not create a'new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did.not~ change the plant effluent releases and did not alter the existing environmental impact.- Therefore, no unreviewed safety orJenvironmental questions are involved. 4-EME-86-0015 This DCP added switches'to Radiological Control Area Doors to sound a local alarm when the doors are opened. This DCP did not create a new safety hazard.to the plant _nor~did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter-the existing environmental impact.- Therefore, no unreviewed safety or environmental questions are involved. 1 i 16 i
L ' i' DCE' Description 21 Chanoe/ Safety Evaluation 4-EMM-86-0018- This DCP provided for the storage and :tiedown of~ tools and equipmentfin the Reactor Building Tnt the 201 elevation for seismic ~and- missile
-hazard considerations. This DCP did not. create-a new safety' hazard to the plant.nori did. it affect: the' safe . shutdown of the: ~ reactor.- .It ,
did not change the plant effluent releases and '
'did not alter the. . existing. . environmental impact. Therefore,. no 'unreviewed safety or environmental questionszare involved.
4-EMEi 86-0019A This DCP- provide'd an 'uninterruptable . power supply, . with a diesel generator back up, to the Telecommunciations, system. This DCP met- FSAR commitments to . : maintain an Loperating communication system after Loss of . Coolant- or. Loss of Power Accidents and did not create a new-safety. hazard to the plant nor did it affect.the. q safe shutdown.of the reactor. It did not change i the plant effluent releases and.did not ' alter. the existing environmental ~ impact.-. Therefore, no unreviewed safety or environmental questions , are involved. l 4-ECM-86-0025 This DCP installed new valve glands in the Recirculation System Suction and Discharge Valves. These valve glands did not create:a new safety hazard to they plant nor did they affect the safe shutdown of the reactor. .This DCP did not change the plant effluent releases and did not alter the existing environmental ; impact. Therefore, no unreviewed. .. safety or-environmental questions are involved. 4-EME-86-0032B This DCP re-designed the Isolated Phase. Bus Transition Compartment / Generator Termination Compartment. The new design will. lower -the. temperature experienced during power generation ! and did not create a-new safety. hazard: to -the plant nor did it affect >the safe shutdown of the reactor. The DCP did not change the plant-effluent releases and did not alter the existing environmental. impact. Therefore, no unreviewed. safety or environmental questions are involved. 17 . q
i 1 l DCE- Descripti2D 21 Chance / Safety Evaluation l 4-EME-86-0037 This DCP provided emergency- lighting battery power packs in the Diesel _and Control Areas of the plant that are being utilized'as temporary offices. This DCP meets an OSHA regulation and did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor.. It did not-change the plant effluent releases _and did not alter the existing environmental-. impact. Therefore, no unreviewed safety or environmental questions are involved. 4-EMC-86-0040 This DCP provided Lube Oil Storage Cages at various _ plant locations. The addition of _the i storage cages did not create a new safety hazard ' to the plant nor did it affect the' safe shutdown of the reactor. They did not change the plant. effluent releases and did not alter.the existing l environmental impact. Therefore,_no unreviewed i safety or environmental questions are. involved. 4-EMC-86-0043 This DCP provided racks for the storage. of i nitrogen bottles for seismic and missile hazard considerations. This DCP did not create a new safety hazard to the plant nor did .it affect the safe shutdown of the reactor.- It did not change the plant effluent releases and did not alter the existing environmental impact. : Therefore, no unreviewed safety or environmental questions are involved. 4-HMJ-86-0044 This DCP deleted the Main Turbine .High Trip Signal because of spurious trip signals due to i cable - induced noise. This DCP-did not create I a new safety hazard to the plant nor did it l affect the safe shutdown of the reactor. It did 1 not change the plant effluent releases and did l not alter the existing environmental impact. l Therefore, no unreviewed safety or environmental ' questions are involved. 4-EMC-86-0045 This DCP added 2 doors for emergency egress in-the Diesel and Control Area (Room 5227). These doors did not create-a'new safety hazard to the plant nor did they affect the safe shutdown -of the reactor.- It did not change the plant effluent releases and'did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental' questions are involved. I 18
~
, :l Description Af Change / Safety Evaluation
~
'DCE 4-EMM-86-8048 This DCP installed a : spring-loaded, air-operated solenoid to a Pressure Tight Door in the . Diesel Bay to allow it to be' opened on Loss- of Air.
This DCP did not~ create a new safety hazard.- to the' plant nor did it affect the safe shutdown of the reactor. It .did inot change the plant effluent releases and-did;not alter:the existing environmental impact. Therefore,.no unreviewed safety or environmental questions are involved.
.4-HMD-86-9953 This .DCP replaced _a Lunkenheimer gate valve on the Auxiliary Steam-system.with a Hancock ' gate valve.. This DCP didinot: create a new = safety.
hazard to the plant.nor did-itlaffect the safe shutdown of the reactor. .It'did not_ change the plant effluent releases and,did.not alter the. existing _ environmental impact;- Therefore,-. no-unreviewed safety or environmental 1 questions are involved. 4-HME-86-0059 This DCP modified wiring to reflect .the -as designed configuration'and permanently installed. Temporary Modifications._~in .the Reactor Recircuation system. This DCP.did not create a new safety hazard to the plant noridid it affect' the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental- _ impact. Therefore, no unreviewed safety or environmental questions are involved. 4-HME-86-0071 This DCP replaced the circuit breakers.that~ feed' the. receptacles in- the Service and Radwaste Building Rooms 3568 and 3569. This DCP did not create a new safety hazard to:the plant nor did it affect the: safe shutdown of the reactor. It-did not_ change the plant effluent releases and ~ did not alter the existing environmental impact. Therefore, no unreviewed safety-or-environmental questions are. involved. 4-HME-86-0083 This DCP' revised the wiring on Load Sensing Instrumented End Caps. .This wiring change Edid not create a new safety hazard to: the plant nor did it affect the safe shutdown of the reactor. It did not change the plant _ effluent _ releases and did not alter.the- existing environmental impact. Therefore, no unreviewed safety ~ or environmental questions are-involved. 19
l ThCk Description'gI Change / Safety Evaluating .
~4-ECE-86-0084 This DCP reinstalled the wall. and ' electrical' equipment which were removed _ to; -facilitate removal of'thez"D"~ Diesel-Generator. This DCP did not create a new safety-hazard.to the plant nor did it. affect the safe . shutdown. of the-reactor. It- did not_ change the plant _ effluent releases .and did not alter-
- the : existing environmental impact. . Therefore,cno;unreviewed safety or environmental' questions'are involved..
4-BMJ-86-0086A This~ DCP reversed .the condenser Pressure. Interlocks for the Reactor Recirculation. system runbacks_ _to coincide with engineering calculations. This -DCP'did not create: la new safety hazard to the plant nor did'itLaffect-the i safe shutdown of the reactor.- It did not change- l
. the plant effluent releases and did not alter I
the existing. environmental impact. Therefore, no unreviewed safety or environmental-questions j are involved. ! 4-EMJ-86-0088 This DCP contains safeguards information; ; however, it did not create _a new safety hazard- l to the plant nor did it affect the safe shutdown' ! of the reactor. It did not change the -plant l effluent releases and -did not alter -the existing environmental impact. Therefore, no unreviewed safety or environmental-questions are involved. 4-EMM-86-0090 This DCP modified a drain to more ~ efficiently collect water drained- from a process; line. This DCP did'not create-a new . safety piping= hazard to the plant'nor did it affect ~the safe shutdown of the reactor. It did not change the plant effluent releases and.did=not alter -the existing environmental impact. Therefore,. no unreviewed safety or environmental-questions are involved. 4-EMJ-86-0093A This DCP provided Control Room indication of the Reactor Recirculation Pump Speed Output' Demand Signals. This DCP did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not. change the' plant effluent releases and did not' alter the existing environmental impact. 'Therefore, no unreviewed safety.or environmental questions are involved. l
-29: j
DCE Description af Change / Safety Evaluation: 4-EMJ-86-9993B This DCP.provided Control. Room indication'of the? Scoop ~ Tube Lock-up status.- This DCP;.did .not-create. a'new safety hazard-to the plant'nor did it' affect the safe shutdown of1the reactor.- tit did 'not change the plant effluent releases and did not alter.the existing environmental impact. Therefore, no unreviewed safety.or. environmental
-questions are involved.
4-EMM-86-9994 This DCP modified.the air. start tubing- on the
~
Standby Diesel Generators to positively vent the
' air .from' the rack boostLcylinder to prevent overspeed trips of the. Standby Diesel ~ Generator q on engine startup. This DCP.did not create. a new safety hazard-to the plant nor did.it affect the safe shutdown of-the. reactor. It did not change the plant effluent releases and did .not alter the existing environmental. impact.
Therefore, no unreviewed safety or environmental. questions are involved.- 4-EMM-86-9997 This DCP removed the limit switch interlock-from motor- operated gate valve closing circuits to allow the valves to seat properly. This DCP-did' not create a new safety' hazard to the plant.nor ~ did it affect the safe shutdown.of the- reactor. It did not change:the plant effluent releases- : and did not alter the existing environmental impact. Therefore, no: unreviewed safety' or environmental questions are involved. 4-EMJ-86-9998A This DCP' added a. remote reset switch in _.the Control Room for the Fire Protection Status Panel. The DCP.also corrected zone code design. discrepancies.. 'This DCP did not create a ,new safety hazard to the plant nor did it affect the ,
~
safe shutdown of the reactor.- It did not. change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 4-EMM-86-9191 This DCP added a fixed-support to an Electro-Hydraulic Control Oil,Line to reduce vibration.. This DCP did not create a new-safety hazard to. the-plant nor did it affect the safe shutdown of the reactor. It did not change the plant ) effluent releases and did not alter the existing- I environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 1 21 ]
l' DCE Description 91. Change / Safety Evaluation 4-EMJ-86-0193 This :DCP're-wired' limit switches on a' rotor in the Reactor Water, Cleanup system. A previous adjustment affected these limit switches, ,this accomodated.the previous adjustment and did' not. create; a new safety hazard to the plant nor'did it affect the safe shutdown ~of the reactor. It did not change.the plant effluent releases .and did not alter the existing environmental questions ~are involved. 4-HMM-86-0194 This DCP insulated a copper tubing line from the-Blowdown Sample Cooler to' prevent the.line from freezing. This DCP did not create a.new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not' alter. the existing environmental impact. Therefore, no unreview safety or environmental questions are involved. 4-EMM-86-0195 This DCP installed a flow totalizer and a level: transmitter for the Low Volume Oily Waste system. This DCP did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not' change the. plant effluent- releases and did not alter. .the. existing environmental impact. Therefore, no unreviewed safety ortenvironmental questions are involved. 4-EMJ-86-9196 This DCP changed theftimers and/or- the timer-settings for the Condensate storage and Transfer Pumps. This DCP 'did not create a new safety-hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases.and did not alter the existing environmental impact. Therefore, ru) unreviewed safety or environmental questions are involved. 4-EMM-86-0197 This DCP provided temporary air- conditioning units with cooling water from the Domestic Water system. This DCP met a licensing commitment and did not create a new safety hazard to the plant nor did it ~a ffect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no-unreviewed safety or environmental questions are involved. 22
. - . . -. . - .- - .~ . - . - - - .- .- .- - . -
t DCE Description AL Change / Safety Evaluation ' I 4-HME-86-9108 This DCP sealed the Generator. Exciter : Housing Penetrations to prevent.the entry of ' dust and . gas. This DCP did' not create a new . safety-
- . hazard to the. plant ~nor did it affect the safe
- shutdown of the reactor. It did not change the
i plant effluent releases and did not alter the i existing. environmental impact. Therefore, no , unreviewed safety or environmental questions'are ' involved. 4-ECM-86-9113 The DCP disconnected the electric actuator from I electro-pneumatic relays. to avoid undesirable l fire damper closures in. the Carbon Dioxide System Control Panels. .This DCP did not create i a new safety hazard to the plant .nor did it' : i affect the safe shutdown of the reactor. It did not change the plant effluent releases;and did not alter the existing- environmental impact. Therefore, no unreviewed safety or environmental j questions are involved. 4-EME-86-9115 This DCP eliminated the High Speed Turbine l Turning Gear operation. This DCPLdid not create } a new safety hazard to the plant nor. did it affect the safe shutdown of the reactor.- It did . ! not change the plant effluent releases and did 4 not alter the existing . environmental impact. i
- Therefore, no unreviewed safety or environmental j questions are involved. >
4-EMM-86-9117 This DCP added lock nuts and an additional i section of pipe to prevent the loosening of Turbine Control Valve bolts. This DCP did not create a new safety hazard to the plant nor did I it affect the safe shutdown of the reactor. It did not change the plant effluent releases and l did not alter the existing environmental _ impact. Therefore, no unreviewed safety or environmental' questions are involved. 4-EME-86-9134 This DCP provided 129 volt AC power to the Main ] Generator Exciter Housing -lights and receptacles. This DCP -did not create' a new
- safety hazard to the plant nor did it affect the )
i safe shutdown of the reactor. It did not change-l the plant effluent releases and did not- alter
- the existing environmental impact. Therefore,
! no unreviewed safety or environmental questions-are involved. l 23 s
DCE Dgscription 91 Change / Safety Evaluation 4-HME-86-0136 This DCP provided an independent power source to the Station Air Compressor Control Panels. This DCP did not create a'new safety hazard Eto, the. plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases ..and did not- alter. the -existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 4-BMJ-86-8138 This DCP re-classified Temporary Modification' 133 as a permanent design change. It reset :a Lift Pump Discharge Pressure Switch. This DCP did not create a new safety hazard to the plant' nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 4-EMC-86-0152 This DCP replaced a lock on-a door in the Turbine Generator Building to restrict access to the Turbine Bridge Crane. The replacement of the lock did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not ' change the plant. effluent releases and did not alter the existing environmental impact. Therefore, no.unreviewed safety or environmental questions are involved. 4-EMJ-86-0161 This DCP re-wired a MOVATS limit switch. A previous adjustment affected this limit switch, this DCP accomodated the previous adjustment and did not create a new safety hazard to the plant ; nor did it affect the safe shutdown -of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved.- 4-EMJ-86-0162 This DCP added a 1/2 second time delay: to the Control Room Isolate Signal so that the Process Start Inhibit Signal could inhibit the Control-Room Emergency Filtration Fan Start as designed. ) The time delay did not create a new safety hazard to the plant nor did it affect the safe i i shutdown of the reactor. It did not change the plant effluent releases and did not' alter the existing environmental impact. . Therefore, no J unreviewed-safety or environmental questions are ; involved. l l I 24 j
lhWE Description 2L Chanoe/ Safety Evaluation 4-EME-86-B163 This DCP . updated cable . block diagrams .and terminationi cards' to reflect the. .as-built configuration of the plant. This drawing change did not create a new safety hazard to the plant ~ nor did it- affect-the safe . shutdown of :the reactor.: It did not change the~ plant effluent releases, and did. not alter the Lexisting environmental impact._ Therefore, no unreviewed ' safety or environmental questions.are involved.-
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4-EME-86-0164 This DCP permanently 'i nstalled. Temporary Modification 276. It changed the . overlo'ad ~ heater setpoints on the Oil Recycle Pump Motor-in the Oily Wastewater Treatment system.. This' DCP did not create a new safety hazard to the. plant nor did it affect the safe shutdown of.the reactor. It did not change the plant effluent releases and did not. alter the existing environmental' impact. Therefore, no unreviewed safety or environmental questions are involved. 4-EMC-86-0166 This DCP installed exit-only turnstiles in the Guardhouse to prevent. personnel from entering-the . stations without going through the metal / explosive detectors. This DCP_ did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases. and did not alter the existing environmental impact. Therefore, no unreviewed safety or. environmental questions are involved.. 4-EME-86-0167 This DCP installed a 229. volt outlet for a Xerox machine in the Guardhouse (Room 114). .This DCP did not create a new safety hazard'to the plant. nor did it affect the safe shutdown of the. reactor. It did not change.the-plant: effluent: releases and did not alter' the existing environmental impact. Therefore, no unreviewed safety or environmental questions'are involved. 4-EME-86-9173 This DCP re-wired a switch on a Standby . Liquid Control Heater to -maintain the , temperature between 75' degrees and 85 degrees. The heater was running continuously, this DCP allowed the heater to operate as-designed and did not create a new safety-hazard to the plant norndid . affect-the safe shutdown of the reactor. ltt did .not. change the plant. effluent releases and did not' alter ~ the existing environmental impact. Therefore, no unreviewed safety or environmental-questions are involved. 25
DCE Description ~gf Chanae/ Safety Evaluation 4-BMO-86-0178 This DCP replaced a pipe support in the Reactor Auxiliary Cooling system. This new pipe support did not create a'new safety hazard to the plant nor did it affect the safe' shutdown of _the reactor. It did not change the plant effluent releases and. did not . alter the existing environmental impact. Therefore, no unreviewed
-safety or. environmental questions are involved.
4-HMO-86-0186 This DCP added_-pilot. positioners to damper actuators .in the. Turbine Building HVAC system. . This .DCP did not create a new safety hazard to
'the plant nor did it. affect-the safe shutdown of the reactor. It.'did not change. the plant effluent releases and did not alter the existing j
environmental ~ impact. Therefore, no unreviewed ' safety or environmental questions are involved. 4-HMJ-86-0189 This DCP was a document-only change:to show the actual wiring in the Reactor Protection system. This DCP did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change thel plant effluent releases and did not' alter the existing environmental impact. - Therefore, no unreviewed safety or environmental _ questions are involved. 4-ECM-86-0191 This DCP revised the Main Steam Isolation Inboard / Outboard Seal Gas Supply Valve setpoints and replaced 2 valves with blind flanges. These changes allow the-Main Steam : Isolation Valve Sealing' System to made. available . sooner following a Loss of Coolant Accident and did not create a new safety hazard-to theLplant nor did they affect the safe shutdown of the reactor. It did not change the plant _ effluent releases. and did not~ alter-the_ existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved.- 4-EME-86-0210 This DCP was a document only change to reflect the as-built configuration of cable terminations and jumpers. in the Reactor -Core: Isolation Cooling system. This DCP did not' create a new
~
safety hazard to the plant nor did it affect the-safe shutdown of the react.or. It did not change the plant. effluent releases andLdid not alter the existing' environmental- impact. Therefore, no- unreviewed safety or. environmental' questions are involved, v 26
X' y.'te
?t DCE Description.gf Change / Safety Evaluation 4-HCJ-86-0211 This DCP made Temporary . Modification 278 a-permanent design change. It deleted a valve positioner.from the Reactor Water Cleanup System Backwash Water Control Loop._
This DCP did not create a'new' safety hazard to the plant nor did it affect the safe shutdownJof the reactor. It did not change the plant effluent releases ~.and did not alter the~ existing. environmental _ impact. Therefore, no unreviewed safety.or-environmental questions are involved. / 4-HMJ-86-0212- This DCP re-located an'unciators n in the Demineralized Water system. This DCP did not create a new safety hazard to.the plant ~ nor did
, >it affect the' safe shutdown of the rea'ctor. It did not change the plant effluent releases and did not alter the existing environmental impact.
Therefore, no unreviewed safety or environmental questions are involved. 4-EME-86-0215 This DCP added fuses .to the- High Pressure Coolant Injection system _to protect class. lE busses. This DCP met a licensing commitment and' : did not create a new safety hazard to the plant I nor did it affect the safe : shutdown- of the reactor. It did not change the plant effluent I releases and did not! alter the existing environmental impact. Therefore, no unreviewed safety or environmental. questions are involved.. ! 4-ECC-86-0225A This DCP removed acoustical ceilings, drywell i partitions, and concrete' from137 elevation-Control Point area.- It also , temporarily relocated smoke-detectors and . lighting.. This DCP did not create.a new safety hazard -to the plant nor did it affect the safe shutdown of the reactor. This DCP did not change the plant effluent releases and did not alter'the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 4-ECC-86-0225B This DCP replaced the material removed in 4-ECC . l 86-0225B in an improved manner to establish. better controls and flow patterns between the controlled and uncontrolled areas. This DCP did not create a new' safety hazard to the plant nor did it affect the safe shutdown of the reactor. This DCP did not' change the plant effluent releases and did not- alter the existing environmental impact. Therefore, no'unreviewed-safety or environmental questions are involved. I 27 u
n . e
- DCE; Description 121 Change / Safety Evaluation
. (4-HME-86-9289- 1This DCP was a document-only; change to_ reflect- ,
the actual; configuration of a cable (BPIQ9625A).
'ine the Core Spray system. This'DCP. did -not create a new safety hazard.to the plant nor did nor did it' affect the safe- shutdown 'of' the reactor.. It did not change the plant' effluent:
releases and- did not alter the. existing: environmental impact. Therefore,.no unreviewed-safety or. environmental; questions are involved.. , 4-EhC-86-8293 .This- DCP
- sealed penetrations in' the Unit; 2 Diesel Generator and Reactor Buildings. . These
* -penetration' seals met a licensing commitment and.
did not' create ~a new safety hazard to.the plant . nor did it- affect the safe shutdown of- the: ' reactor.- It did not change the plant effluent _ releases and did not alter the existing I
= environmental-impact. Therefore, no unreviewed-safety or environmental questions _are involved.
4-TMM-86-9318 This DCP modified the Solid Radwaste Concentrate Metering Pumps. This modification did' not creato a newisafety hazard to the plant'nor did it affect the safe shutdown'of the reactor. It did not change the plant effluent. releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are. involved. 4-TMJ-86-9319 This DCP provided automatic control for. the Cooling Tower Blowdown Pump which- provides sample flow to a radiation sensor. The DCP also adds an alarm to be sent 'to the Central Radiation Computer on low flow. _This DCP did not' create a new safety hazard to the plant nor nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental' impact. Therefore, no unreviewed safety or environmental questions.are involved. 4-TMJ-86-9322 This DCP modified the Reactor Feed Pump Turbine logic. This modification did not create a new safety hazard to the plant nor did it affect the safe shutdown of the. reactor. It did not change
..~
the plant effluent releases and did not alter-the existing environmental. impact. Therefore, _ no unreviewed safety or environmental questions s are involved.
)
1 1 i 28 _
'l
. . . ~ . , . . . _ = . . .. . . .
, DCE_ Description ji Change /Safet'y Evaluation
.4-TMJ-86-8323. This-DCP' adjusted the Minimum' Flow Recirculation
-Loops and added-a signal'to.the Runback farming-Circuit. This DCP did'not create a new ; safety ~
-hazard to the plant-nor did.it affect:the' -safe shutdown of the reactor. lIt-did not change the plant effluent releases and'did not alter..the existing environmental-impact. Therefore, no unreviewed safety or environmental questions are involved.
4-TMM-86-9327 -This DCP~ changed-out Turbine Coupling _End Pedestal Dowel Pins. -This DCP did not create.a - new safety hazard to the plant nor did it affect the safe shutdown of the-reactor. It did not' change the plant effluent releases and did not-alter the existing environmental- impact. Therefore, no unreviewed safetyLor environmental-questions are involved.- 4-TMM-86-0330 This DCP modified the Auxiliary Building Chilled Water Tanks to satisfy the Seismic. Evaluation Program requirements. This modification did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did- not change the-plant effluent releases and-did not alter the existing environmental impact. Therefore, no unreviewed safety or' environmental-questions are involved. 4-TMM-86-0332 This DCP installed a trap in the- Demineralized , Water Transfer Line to the Chilled Water ' Head Tank to prevent overflow. The installation of this trap did not create a new safety hazard to-the plant nor did it affect the safe shutdown of the reactor. It did not~ change the. plant-effluent releases and did not alter the existing-environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 4-EMJ-86-0336 This. DCP added_ lightning arrestors to seismic instruments' located in the yard area. This DCP-did not create a new safety' hazard to the plant nor did it'. affect the safe shutdown ,of- the reactor. It did not change the' plant- effluent releases and did not alter the existing environmental impact. .Therefore, no unreviewed safety or environmental questions are involved.
;29
DCE Description af Change / Safety Evaluation - 4-HCM-86-93338A This DCP provided a locking pin to maintain the Undervessel ' Platform in the storage position. This DCP did not create'a new safety hazard to the plant nor did it affect the' safe shutdown of
-the reactor.. It did not- change the-. plant effluent releases and did not alter 1the existing; environmental impact.- ..Therefore,.no unreviewed ~
safety or environmental questions.are' involved. 4-HCM-86-9338B This DCP drilled a hole in the! Control Rod Drive Equipment Handling Platform- Rail Support to > accomodate the_ retaining pin provided-in DCP 4-HCM-86-9337A. This hole did not create-a new safety. hazard to the plant nor did it affect.the safe shutdown of the reactor. It did not change. the plant effluent releases and did not alter the existing environmental impact. _Therefore, no unreviewed safety or environmental -questions are involved. 4-HCM-86-0338C This DCP removed portions of the grating supportl located on the~ Control- Rod Drive Equipment Platform Extensions. This DCP did not create a new safety' hazard to the. plant.nor:did it affect ! the safe shutdown of the reactor.. It did not ! change the plant effluent releases and did- not' alter the existing _ environmental impact. j Therefore,.no unreviewed safety or environmental l questions are involved. 4-EMM-86-0349 This DCP added an opening' in ~ the . Chemistry-Laboratory Storage Area to enable the -Post Accident Sampling System Cart to be- stored there. This DCP did not create 'a new - safety - hazard to the plant nor did it~ affect the' safe shutdown of the reacter. It did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no l unreviewed safety or environmental questions are ! involved. 4-EME-86-0353 This DCP modified the Decontamination Facility. This modification'did not create a new safety hazard to the plant.nor did it affect the safe shutdown of the reactor.- It did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety'or environmental questions are involved. 39
DCE- Description gf Change / Safety' Evaluation 4-EME-86-0354A This DCP replaced land relocated the ~Switchover Relay Board in the Fire' Protection-Status Panel. This ~DCP did not create a new safety hazard to
-the plant nor did it affect the safe-shutdown of:
the reactor. It did not . change the- plant-effluent releases-and did not alter 1the existing- > environmental. impact. Therefore, no unreviewed safety or environmental questions are' involved. 4-ECM-86-0355 This DCP replaced .the HighL Pressure Coolant Injection Barometric Condenser; Water Inlet Valve Motori with .a : larger motor ito. meet design requirements. .This. DCP fdid not create _a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It.did not change the plant effluent releases and did not alter the existing environmental impact. Therefore,
.no unreviewed safety or environmental questions-are involved.
4-HME-86-0356 DCP installed a key. cabinet in the Remote This Shutdown Panel Room. The installation of this
, cabinet ~ did not create a new safety hazard to i the plant nor did it affect the' safe shutdown of the reactor. It did not change the . plant- '
effluent releases and did not alter the existing-environmental impact. Therefore, no unreviewed
- safety or environmental questions are involved.
f 4-EMM-86-0359 This DCP replaced a welded check valve on. the discharge side of the.High Pressure Coolant-l Injection Gland Condenser Vacuum Pump with a'
- flanged check valve. This DCP did'not create a new safety hazard to the plant nor did'it: affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact.
Therefore, no unreviewed safety or environmental questions are involved. 4-EME-86-0360 This DCP provided a 120 volt /20 amp outlet for a l Respirator Testing Unit. This DCP did not , create a new safety hazard to-the plant nor edid it affect the safe shutdown of the reactor.
~
It did' not change the plant effluent releases and ~ did not alter the existing environmental impact. i Therefore, no unreviewed-safety or' environmental- l questions are involved. 1 L 31
DCE Description af Change / Safety Evaluation 4-ECJ-86-0369 This DCP was a document-only change thati reclassified some differential pressure indicators as "non-Q". This reclassification did not create a new safety hazard to the plant nor did it affect the safe shutdown of the-reactor. It did-not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed' safety or environmental questions are involved. 4-HMO-86-0371 This DCP corrected-labels on the -control Room Panel. This DCP did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 4-EMM-86-0374 This DCP rerouted piping in the Solid Radwaste system. This DCP did not create a new safety-hazard to the plant nor did it affect the safe shutdown of the reactor. This DCP did not change the plant effluent releases and did not alter the existing environmental 1 impact. Therefore, no unreviewed safety or environmental questions are involved. 4-EME-86-0382 This DCP changed Temporary Modification 352 into a permanent design change. The initial modification revised wiring to a flow indicator in the Reactor Recirculation system. This DCP did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. This DCP did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed-safety or environmental questions are involved. 4-EMM-86-0384 This DCP added hangers to support a portion of pipe in the Demineralized Water Storage and Transfer system. This DCP did not create _a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, l no unreviewed safety or environmental questions 'j are involved. l i I
- 1 l
32
DCE Description af Change / Safety Evaluation 4-BMJ-86-0385 This DCP was a document-only change to reflect the as-built - wiring configuration of the Main Turbine Lubrication Oil system. This DCP did not create a new-safety hazard to the plant nor did it affect the safe shutdown of the reactor. l It_ did not change the plant effluent' releases l and did not alter the existing environmental l impact. Therefore, no unreviewed safety or ! environmental questions are involved. 4-BMM-86-0386 This DCP installed new sample lines for the Fuel Pool and Torus Water Cleanup. systems. This DCP did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent. releases and did not alter the existing i environmental impact. Therefore, no unreviewed safety or environmental questions are involved. l 4-HMJ-86-0392 This DCP changed a setpoint in the Reactor Building Filtration, Recirculation, and Ventilation system to allow all 6 recirculation unit fans to operate on a Loss of Coolant signal. This DCP.did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did'not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 4-ECJ-86-0397 This DCP installed permanent instrumentation to j perform the -Personnel Airlock Seal Leak Rate ! Test. This instrumentation did not create a new ) safety hazard to the plant nor did it affect the ; safe shutdown of the reactor. This DCP did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental 4 questions are involved. 4-EMM-86-0398 This DCP modified the Electro-Hydraulic Control Unit Equipment Drain and the Dike Floor Drain to- ; prevent mixing the hydraulic fluid with oil in' the 011 Separator. This modification did not create a new safety-hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 1 L l l 33
i 5 1 DCE. Description gi Change / Safety Evaluation 4-EMJ-86-9399 This--DCP.-added a filter-Lacross each; Average . Power Range' Monitorj Flow . Unit Square ? Root. Converter Feedback Circuit to.-eliminate noise' 4 from the; flow transmitters inputting into .the > flow units. :The addition:of the filters did not create a new safety hazard to the plant nor did 4 it affect the safe shutdown of.the reactor.- It
- did not change the plant effluent releases and did not alter the existing environmental impact, i Therefore, no unreviewed safety or environmental-
- questions are involved.-
i 4-ECJ-86-9496A This DCP changed the trip point of the_ Diesel-Generator Jacket Water. Temperature Switches .to-alarm at the-desired Jacket Water temperature.
- 'This DCP did not create a new. safety hazard' to
, the plant nor did it affect the safe shutdown of~ ! the reactor. It did not' change the plant effluent releases and did not alter.the existing' environmental impact. Therefore,.no unreviewed ] safety or environmental questions ~are' involved. l 4-ECJ-86-0486B This DCP installed insulation around instruments j in the Emergency Diesel Generator system. The
. insulation did not create a new safety hazard-to l the plant nor did it affect the-safe shutdown of-the _ reactor. It did 'not ' change the' plant
~
effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed
- safety or environmental questions are. involved.
. 4-ECJ-86-0419 This DCP relocated level instruments and added l quick . disconnect . fittings and quick-closing
- drain valves to the- Nuclear. Instrumentation J.
system. This DCP eliminated'inadvertant reactor scrams caused'by disturbances'during' calibration
- and testing. It did not create a new safety hazard to the plant nor did it affect the safe j' shutdown of~the reactor. It did not change ~the plant effluent releases and did not alter the
[ existing environmental: impact. _ Therefore, no unreviewed safety;or environmental questions are- . involved. 4-HMC-86-0412 This DCP installed tile on the floor in .the i Radwaste Control Room. The tile did not create a- new s afety hazard to_the plant nor' did it
- affect the safe shutdown of the' reactor. .It did
. not change the plant effluent releases and did I not- alter the existing . environmental impact. , Therefore, no unreviewed safety or environmental
- questions are involved.
l L 34~
2]E Description 4f fhance/ Safety Evaluation 4-BMC-86-041'4 This DCP modified smallIpipe hangers. in the Nuclear Boiler-and Recirculation. system. This DCP did not create a new . safety- hazard to the plant.nor-did itcaffect the' safe shutdown of the reactor.- It 'did not change the plant effluent releases and did not alter :the- existing environmental impact. Therefore,Lno unreviewed safety or environmental questions are involved. { 4-EMC-86-9416 This DCP replaced. Gantry Trippers in.the Service-Water -Intake Structure Gantry Crane.- :This DCP
~
~
+ did not create'a new safety hazard to the plant nor did it affect the safe shutdown- of -the 4 reactor. It~ did not change the plant effluent and did not alter. releases the . existing environmental impact. Therefore, no.unreviewed safety or environmental questions are involved. 4-HME-86-0421 This DCP added' coaxial cable and routed it to the Operational Support Center to support the . installation- of an IBM terminal and' printer.. The additional cable did not create a new safety hazard to-the plant nor did it affectithe safe shutdown of the reactor.: It did.not change the 4 plant effluent releases and did not. alter the existing environmental impact. Therefore, no. unreviewed safety or environmental questions are involved. 4-EME-86-0424 This DCP added a. Public Address system.
. Handset / Speaker in. the 182 elevation Drywell Airlock. This DCP did not'. create a'new safety .,
hazard to the plant.nor did it affect the ' safe l 2 shutdown of the reactor. It did not change.the I plant effluent releases and did:not alter the i existing environmental impact. Therefore, no unreviewed. safety.or environmental questions are , involved. , i 4-EMM-86-0431 This DCP modified the design for. the lateral restraint of Control Rod Drive system piping. This DCP did nott create a new safety. hazard to the plant nor did it affect the safe shutdown of the reactor. It did- not change the plant effluent' releases and did not alter the existing environmental impact. .Therefore, no unreviewed j safety or environmental questions are involved. l l 35 - -.- ,.a.
. _ , - - -- ,. - - . . . a -~ -.- , - - -
1TJL Descriptiog 91 Change / Safety Evaluation ;
~
BMP-86-0433 This DCP provided additional supports to the 7
. Fuel Pool Cleanup piping._"The additional piping;
'i. did not create a-new safety hazard ~.to the plant nor did it affect the safe' shutdown of the
- reactor. It did not change-the-plant- effluent releases and .did not alter. the- existing-environmental impact. Therefore, no unreviewed safety or environmental questions are involved. ,
4-EMM-86-9434 This DCP modified the Steam Jet - Air -Ejector Intercondenser. This modification did- - not create a new-safety hazard-to:the plant nor:did it affect the safe shutdown of-the reactor. It: F did- not change the-plant effluent releases and did not alter the existing-environmental impact. 4 Therefore, no unreviewed safety or environmental questions are involved. 4-EME-86-9438 This DCP rewired transmitter / receivers in the i. Fire Protection system. This DCP did not create i a new safety- hazard to the plant nor' did it
- affect the safe shutdown of the reactor. It did not change the plant effluent releases and did i not alter the existing environmental impact.
Therefore, no unreviewed safety or environmental questions are involved. . 4-EMJ-86-0439 This DCP provided a method 'for fastening barriers in their designated. location in the f Radwaste Building. This DCP did not create a 4 new safety hazard to the plant nor did it affect 4 the safe shutdown of the reactor. .It--did not ! change' the plant effluent releases and did not alter the existing environmental impact. j Therefore, no unreviewed safety or environmental ! questions'are involved. 4-EMM-86-0440 This DCP relocated 2 braces to'a less congested i area.- This DCP did not create a~ new safety hazard to the plant nor did it affect.the safe-shutdown of the reactor. It did'not change the plant effluent releases and.did not_alterc the' ! existing environmental impact. Therefore, no ' unreviewed safety or environmental questions are involved. 4-EMM-86-9443 This DCP provided for the removal of fill samples from;.the Cooling Tower for . testing. l This DCP did not create a new safety hazard: to- " l the plant nor did.it affect the safe shutdown of the reactor. It did not change the plant-j effluent releases and did.not alter the existing !
- environmental. impact. Therefore, no-unreviewed!
-safety or. environmental questions are involved. i 36' ]
a ? IE3L Description g1 Change / Safety Evaluation
- - 4-TMJ-86-9448 This. DCPLwas a document-only1 change to. reflect actual level setpoints'in the Liquid
- Radwaste system. This DCP'did not create a new -safety .
- hazard ~to the plant nor did it affectLthe . safe
, shutdown of the reactor. -It didinot change the i-plant. effluent releases and did not alter' the~
existing environmental impact.- .Therefore,- no unreviewed safety'or environmental questions are involved. 4-BME-86-9454 :This DCP- provided ~ an interlock'.between: the
- ' Diesel Area-1E. Panel Room Supply l Fans 'and the Chilled Water. Pumps .tcr ensure' proper fan 4 operation during'the switching of the pump / fan- ,
i trains. The. interlock. did not create a new safety hazard to the~ plant nor did it affect the safe shutdown of the reactor. . .It did not-change the plant effluent releases and did not ' alter the existing environmental. impact. Therefore, 4 no unreviewed safety or environmental questions-i are involved. i j 4-BMJ-86-9456 This DcP replaced flowmeters in the Hydrogen- ! Oxygen Analyzer. The new flowmeters did not' create a new safety hazard to the plant nor did-Fl it affect the safe shutdown of the reactor. It i did not change the plant effluent releases and did'not alter the existing environmental impact.=
- Therefore, no unreviewed safety or environmental questions are involved.
l ) 4-EMJ-86-9459 This DCP corrected wiring-in the Control Room-Integrated Display Computer System. This DCP , did not create a new safety hazard to the plant nor did it affect the safe shutdown. of the ! reactor. It 'did not change the plant' effluent releases and did not alter. the existing
- environmental impact.- .Therefore, no unreviewed-l safety or environmental questions are
- involved.
j 4-BME-86-9464 'This DCP modified the internal wiring of .the
- Control Area Supply Fans to eliminate AC
! interference with the DC circuits in HVAC i- control panels. The wiring change did'not create i a new safety hazard to'the plant nor- did it affect the/ safe' shutdown of the-reactor. It did not change the plant effluent releases and did-l not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. l l 37
1 DCE Description 91 Change / Safety Evaluation 4-ECJ-86-8465A This DCP modified. Chiller Compressor . Motor ' Tripping. Circuits. This modification did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did-not alter the existing environmental' impact. Therefore, no unreviewed safety or environmental questions are involved. 4-EMC-86-9468 This DCP ' installed an enclosure .around the Hydrogen-Oxygen Analyzer Bottles located on the Reactor Building Roof to protect the. bottles - from inclement weather. It also provided- an i access ladder. .This DCP did'not create a new j safety hazard to the plant nor did it. affect-the safe shutdown of the reactor. It did not change i the plant effluent releases and did not alter-the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. ); 4-ECC-86-0469 This DCP installed penetration seals in gaps between the Diesel Generator Exhaust Stack and the roof. This DCP did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 4-BMH-86-0474 This DCP added supports to the Centrifuge Feed Tank Recirculation Pump Discharge Piping. The additional pipe supports did not' create a new l safety hazard to-the plant nor did it affect the ' safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental. impact. Therefore, no unreviewed safety ~or environmental questions are involved. 4-BMP-86-0475 This DCP rerouted a drain line that prevented ! 1 the unrestrained thermal and dynamic-movement of j the Main Steam Equalizer Piping. This DCP did 1 not create a new safety' hazard to the plant. nor l did it affect the safe shutdown of the reactor. It did not change the-plant effluent releases and did not alter the existing environmental i impact. Therefore, no- 'unreviewed safety or ) environmental questions are involved. i- [ 38 l
L _ 1 DCE Description 21 Change / Safety Evaluation 3 - 4-EMC-86-0498 This DCP'added'a penetration and~ routed : tubing. through it. This; DCP _did.not: create _ a newz safety hazard to the plant >nor did it affect the > safe shutdown of-the-reactor.- It.did not change
- the plant effluent. releases and did not . alter the~ existing'environmentallimpact. Therefore, no unreviewed safety or environmental questions are involved.
4-HCO-86-0591 This DCP- . relocated' air monitors in~ the Filtration, Recirculation, and Ventilation System 'from 'a wind-affected area-to a Twind-- sheltered area. This DCP did not create a 'new i safety hazard to the plant nor did.it. affect the i safe shutdown of the' reactor. It-did not change
- the plant effluent releases and did not alter 1 the existing environmental impact. _ Therefore, 8
no unreviewed safety.or environmental 1 questions are-involved. 4-HMO-86-9596 This DCP modified the Evaporator Steam Feed
- system to enhance the operation of the system.
l This DCP did not create a new safety hazard to the plant.nor did it affect the safe shutdown'of -
- the reactor. It did not change the -plant I effluent releasen and did not alter the existing 3
environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 4-HMO-86-0587 This DCP replaced a diffuser in a Radwaste Supply
~
Duct in order to maintain air flow from l an area of lesser potential contamination to an j j area of higher potential contamination. This i i DCP did not create a new safety hazard to the l plant nor did it affect-the safe shutdown of the H
.i ! reactor. It did not change the plant effluent j releases and did not alter the~ existing i j . environmental impact. ~T herefore, no unreviewed j
. safety or environmental questions are involved. j < l 4-4-HCO-86-9599 This DCP corrected wiring on a Bailey Logic ' Module. The correction met the original. design intent and did not create a new safety hazard to i the plant nor did it affect the safe shutdown.of > the reactor. It did not- change the plant ! effluent releases and did'not alter the existing l environmental impact. Therefore,'no unreviewed l safety or environmental questions are involved. i i i i L L
- 39 ,
t 4 DCE' Dgscription hi Change / Safety Evaluation. 4-HMO-86-9513 This DCP revised the' wiring- to; provide-'the correct- annunciation for 'the. Residual Heat Removal system._ This DCP did not' create a new-safety hazard to the plant.nor did it affect the safe shutdown.of the reactor. It'did not: change-the plant effluent releases-and did not alter F -the existing environmental impact. .Therefore,- e no'unreviewed safety or environmental questions i~ are-involved. 4-HCO-86-0518 This DCP was a document-only change to reflect that the Service Water Sample . Pump had been changed from a centrifugal pump to a diaphragm pump. This~ . change- was made 'on. Temporary Modification 384 and was-made a permanent design
, change by this DCP. It-did not create a new.
~
li safety hazard to the plant nor did-it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter-the existing environmental impact.
~
Therefore, t no unreviewed safety or environmental questions are involved. j 4-HCO-86-E520 This DCP changed the setpointifor the Chiller i Evaporator Low Pressure ' Switch. The changed i setpoint did not create a new safety hazard to.
- the plant nor did it affect the safe shutdown of 1
the reactor. It did not change the. plant effluent releases and did not alter the existing l environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 4-HMM-86-0522 This DCP increased the Low- Flow Switch Time Delay on 2 Auxiliary Building HVAC Fans to l prevent the fans from' tripping during -fan transfer. This DCP did not create a new~ safety hazard to the plant nor-did it affect the safe It did not change the o shutdown of the reactor.. plant effluent releases and did not alter- the existing' environmental impact. Therefore, no unreviewed safety or environmental questions are ; involved. 4-HMJ-86-0523 This DCP changed the alarm circuit for.3 Main Generator Recorders to prevent recurring alarms. This DCP,did not create a new. safety hazard to the' plant nor did it. affect the safe shutdown of the reactor. It did not change the -plant. effluent releases and did~not alter the existing environmental impact. Therefore, no unreviewed . safety or environmental questions are involved. ! l
-4s _ __ _ .._,--._ _._ _.
4 Li EE Descrintion'91 chanae/ Safety Ryaluating i f4-BMM-86-9524 This DCP- addedia: perforated plate to an 'ITVAC inlet in the_ Reactor Building Ventilation System. This DCP.did not create a new safety hazard to the plant nor did it. affect the safe shutdown of the reactor.. -It-did not change the
; plant effluent releases.and did not alter the y existing environmental impact. 'Therefore, no!
- .unreviewed' safety or environmental; questions are
- involved, i 4-HMM-86-9534 This DCP replaced the flow orifice on the Liqdid ,
Radwaste Sample: Pump. This DCP did not create a-new safety hazard to the-plant nor did'it affect the safe shutdown of the reactor. It did' not: i change the plant effluent releases and did not i alter the existing environmental impact. ! Therefore, no unreviewed safety or environmental
- j. questions are involved.
- 4-HCE-86-9548 This DCP modified the Standby _ Diesel Generator i . Engine Control Panel Circuits'for the Engine Cooling Water Valve. This _ modification eliminated a potentiali Cooling Water Valve closure during initial start of the diesels 'and eliminated- the failure of the valve to reopen 1 after it is manually closed with the diesel' '
1 running. It did not create a new-safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant i effluent releases and did not, alter the existing' t
- environmental impact. Therefore,.no unreviewed l safety or environmental questions are involved.
4-HMJ-86-9558 This DCP corrected the. polarity;of the input to j the Transversing In-Core Probe Recorder.L This j correction did not create'a new safety hazard to the plant nor did it affect the safe shutdown of + the reactor. It did not change the plant-l effluent releases and did not alter the existing l- environmental impact. Therefore, no unreviewed-l safety or environmental questions are involved. ! 4-BME-86-9553 This- DCP provided' additional supports for j conduit- and cables in the Neutron Monitoring i system. This DCP did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change'the-i plant effluent releases and did not alter the , existing environmental. impact. Therefore, no : unreviewed' safety or environmental questions are involved. I , 41 l
l DCE: Description gi Change / Safety Evaluation
.4-BMM-86-9558 .This DCP was a document-only change to'make the cable ' terminations in the- Solid- Radwaste Crystallizer reflect the as-built. configuration.
This. DCP.did not create a new safety. hazard 'to the plant nor'did it affect'the safe shutdown.of-the reactor. . It did not change the plant. effluent' releases and did not alter the' existing environmental impact. .Therefore, no unreviewed safety.or environmental questions are involved. 4-HMM-86-0572 This: .DCPL supplied 119 Volt- AC' power to a Circulating Water-Chemical' Addition Flow Switch. This DCP did not create a new safety hazard to-the plant nor did it affect the safe shutdown of: the reactor. It did not change..the plant-effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed' safety or environmental questions are involved. 4-HMM-86-0573 This DCP changed the Circulating Water Chemical Addition system'from an Acid Addition system to a caustic Addition system. This'DCP did not create a new safety hazard to-the. plant nor. did it affect the safe shutdown of the reactor. This DCP did not change the plant effluent releases and didnot alter the' existing environmental impact. Therefore,uno unreviewed safety or' environmental questions are involved. 4-HCM-86-0574 This DCP modified the lE Panel Room Supply Fan to eliminate' vibration.. This modification-did not create a new safety' hazard to the plant nor did it affect the safe shutdown of the-reactor. It did not change the~ plant effluent ~ releases and did not~ alter the existing environmental impact. Therefore, no unreviewed. safety or. environmental questions.are involved. 4-HMM-86-0582 This DCP changed the location of check' valves-in the Liquid Radwaste system to' prevent radwaste contamination from getting into the Condensate system. . Relocating the check-valves did not create a new safety hazard to the plant.nor 'did it affect the safe shutdown of the reactor. This DCP did not change the' plant effluent releases and did not alter the existing. environmental impact. Therefore, no unreviewed-safety or environmental questions are involved. 42-
w
.DCE~ Description 21 Change / Safety Evaluation 4-HCM-86-8599 This DCP was a document-only change'to reflect:
the flow orifices installed-in the-Core Spray-
-system by Temporary Modification 456. .This DCP-did not create a new safety hazard to the plant nor did it. affect theLaafe- shutdown of the i reactor. It: did not. change the plant effluent; releases' and did not. alter the existing; environmental ~ impact. Therefore,.no.unreviewed -
safety or-environmental questions are involved.. 4-HMM-86-9591 This DCP installed. lugs so-the Control Rod Drive Hatch Rolling Concrete Shield. Block can be moved back and forth.- This DCP did not create a new-safety hazard to the plant nor did it affect.the safe shutdown of the reactor. It did not change the plant effluent releases and did .not . alter
- the existing environmental impact.. Therefore, no unreviewed'safetylor environmental questions-are involved.
4-HMM-86-0592 This DCP relocatedLsteam traps on the Asphalt Storage Tank. The relocation of the steam traps did not create a new safety hazard to the'~ plant nor did it affect the safe . shutdown, of the reactor. It did not. change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 4-BMM-86-8603 This DCP added Carbon Monoxide Analyzers ~to monitor Emergency ~ Diesel, Generator . Stack Emissions. This' DCP did not create a new ; safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did'not change the plant effluent releases and did not R alter the existing environmental impact. l Therefore, no unreviewed safety or i environmental questions are involved. 4-BMM-86-9604 This DCP modified the tubing between the Agitator and the Crystalizer Bottom Tank in the Solid Radwaste system. This DCP did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or-environmental' questions are involved. 43
[
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DCE pgscription of change / Safety Evaluation . 4-BMM-86-8605 This DCP replacedithe Reactor ' Core . Isolation Cooling System Turbine End Coupling Pedestal. Pins. This DCP did'not-create a new safety
- hazard to the plant nor did it affect the safe shutdown of the reactor. ~ It'did not change the'
. plant _ effluent _ releases and did not: alter- the existing environmental impact.- Therefore, no- r t .unreviewed safety or- environmental questions l are involved.
t 4-TME-86-0611 This DCP modified Fuel Pool underwater lights to ' i- be moisture. resistent. >This DCP did not create i a new safety hazard to the plant nor. did it-F affect the safe shutdown of the reactor.It-did j not change the plant effluent releases and fdid + not altet the existing . environmental impact, i Therefc.e, no unreviewed safety or environmental i questions are involved. [ 4-EMM-86-0616 This DCP replaced limit switches'on valves in ! the Liquid Radwaste system. This-DCP did not create a new safety hazard to the plant.nor did i it affect the safe shutdown of- the reactor.
- It did not change-the plant effluent releases' ,
i and did not alter the existing = environmental- i j- impact. Therefore, no unreviewed safety or 1 environmental questions are involved. ' i , 4-EMM-86-0628 This DCP installed a second torque arm to
- support the Polar Crane Bridge Drive Motor and
. Gear Reducer Assembly. This DCP did not. create a new safety hazard,to the plant nor' did .it affect the safe shutdown of the reactor.. It did not change the plant' effluent releases and did } not alter the existing environmental impact. j Therefore, no unreviewed safety ^or. environmental' [ questions are involved. i 4-EMO-86-0621 This DCP installed a Chilled-Mirror. Moisture i Analyzer for the Charcoal Off-Gas Treatment system. The new analyzer is'more accurate and reliable than the previous one, minimizing the possibility' of erroneous' alarms. This DCP did ? not create a new safety hazard to the plant = nor i did it affect'the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing: environmental i impact. Therefore, no unreviewed safety 7 or
- j. environmental questions are involved.
i A i i { I 44
. . . .. . ~. . .. .- - ._- --_ ---
M 4 4 DCE Dgscription 91 Change / Safety Evaluation 4-EMM-86-8622' This DCP removed insulation from 2111nes in the' - . Reactor Core Isolation . System.. ~ Removing - the-insulation allows additional cooling. This DCP did not create a new safety hazard to the plant nor did- it affect the-safe shutdown of the-
. reactor. It did not change the plant ~ effluent.
releases and did not. alter the existing environmental impact. Therefore, no.unreviewed safety or environmental questions are involved. 4-EMM-86-9623 This DCP replaced the. valve springs Land the actuator. springs for several-valves is the Gaseous Radwaste system. This DCP did' not create a new safety. hazard to the plant nor did i_ it affect the safe shutdown of the. reactor. It-did not. change the plant effluent releases and ^ did not alter the_ existing environmental-impact. Therefore, no; unreviewed safety or environmental questions are involved. 4-BMM-86-0630 This DCP was a document-only change to reflect ! the as-built configuration of 4 hangers. This ! DCP did not create a new safety hazard to the plant nor did it affect the safe shutdown of
- the reactor. It did not change the plant 4
effluent releases and did not alter the existing environmental impact. Therefore, ~ ru) -
; unreviewed safety or -environmental questions
- are involved.
- 4-EMM-86-0631 This DCP modified an Electro-Hydraulic Control 4'
Pipe Support. This modification did not r create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It j did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental
- questions are involved.
i 4-BMP-86-0634 This DCP removed U-Bolts t'o reduce pipe support ! stresses. This modification did not create a j new safety hazard to'the plant nor did it affect.
- the safe shutdown of the reactor. 'It did, not change the plant effluent releases and did not .
! alter the existing environmental impact. l l Therefore, no unreviewed safety or environmental 1 questions are involved. l { \ 45
5 DCE- Description 91 chanae/ Safety Evaluation 4-EME-86-0635 This' DCP- changed-thelpower> supply to i1E power
~for-the elevator'used to. transport Post-AccidentL Samples to the Chemistry Laboratory. . This DCP did not create.aTnew safety hazard to the plant-nor did it affect the safe - shutdown of the reactor. It did not change the plant- effluent releases. and did not_ alter _the- existing-environmental impact. Therefore, no unreviewed safety:or environmental questions are involved.-
4-BMP-86-8637 This DCP reworked piping and' hangers at 'various locations _ to. reduce pipe stress. This DCP did-not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It- did not change the plant effluent releases and did not alter the existing environmental-impact. Therefore, no- 'unreviewed safety- or environmental questions are involved. 4-BME-86-9638 This DCP added cables and revised terminations in the Radiation Monitoring System. This DCP did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter- the existing environmental impact. Therefore,~no unreviewed safety or environmental questions are involved. 4-HMP-86-0640 This DCP added pipe.from the Centrifuge Feed Tank Decant Pump Seal to the floor drain. 'The addition of pipe did not create a new' safety hazard to the plant nor did it affect'the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter. the existing environmental impact. . Therefore, no unreviewed safety or environmental questions are involved. 4-EMC-86-9641 This DCP provided additional rigging to enable. the concrete shielding plugs to be moved. The additional rigging did not create a new safety hazard to the plant'nor did it affect the- safe shutdown of the reactor. It did not change the plant effluent releases and did not alter 'the existing environmental impact. Therefore, no unreviewed safety or environmental. questions are involved. 46
. . -- ~. . - . . - - - . - - . -
DCE Description 91 Change / Safety Evaluation 4-EMC-86-9642 This DCP added- safety tag lines- above the
- Turbine Bridge Runway. This DCP did not create a new safety hazard to tha plant nor did it.
affect the safe shutdown oi >.he reactor. It did a not change the plant effluent releases and did not alter the existing environmental -impact. Therefore, no unreviewed safety or environmental ), questions are' involved. 4-EMC-86-0648 This DCP -sealed penetrations in .the Unit- 2
- Turbine -Building, Elevation 137. Sealing _the
( penetrations did not create a new safety- hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing
! environmental impact. Therefore, no unreviewed safety or environmental questions are involved. .
i
! 4-EMC-86-0654 This DCP added a gasket at the inspection port on each Diesel Generator Exhaust silencer. The I addition of these gaskets did not create a new- , safety hazard-to the plant nor did it affect the i safe shutdown of the reactor. It did not change ; the plant effluent releases and did not alter j the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved.
! 4-EMC-86-0655 This DCP provided an airborne radiation seal in ! a gap in the floor of the Auxiliary Building. This DCP did not create a new safety hazard to the plant nor did it affect the safe shutdown of { the reactor. It did not change the plant
; effluent releases and did not alter the existing l environmental impact. Therefore, no unreviewed .
{ safety or environmental questions are. involved. { 4-EMC-86-9657 This DCP provided an entrance into the Chemistry
- offices from the Administration Facility without i
entering the Radiological Control' Area. This DCP did not create a new safety hazard to the j plant nor did it affect the safe shutdown of the
- reactor. It did not change the plant effluent i releases and did not alter the existing i
- environmental impact. Therefore, no unreviewed safety or environmental questions are involved.
i i 47
, , _ . __ _. _ __ . _ . _ . _.. ~ . . __
J f . l DCE Description 21 Chan9e/ safety Evaluation t ! 4-EMC-86-8661 This'DCP provided for the refurbishment and the' ! ! completion of the Unit 2 Turbine Building Crane.- This .DCP met an FSAR commitment- and did not create a new safety; hazard to the plant nor did it affect-the safe shutdown of the reactor. It l- did not change the plant; effluent releases and
- did not' alter the existing
- environmental impact.
! Therefore, no unreviewed safety or. environmental ! , questions are involved. 4-BMP-86-9663 This 'DCP changed the angularity of pipe clamps
- at various locations. This DCP did not create a j new- safety ~ hazard to the plant nor did it i 1 affect the safe shutdown of the reactor. It did !
i not change the plant effluent' releases and did not alter- the existing environmental impact.
! Therefore, no unreviewed safety or environmental !
j questions are involved. 4-EMM-86-9679 This DCP provided for the grouting of the
- foundation bedplate of the Stator Winding-Coolant Pumping Unit. This DCP did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not
- change the plant affluent releases and did not ;
- alter the existing environmental impact. ,
Therefore, no-unreviewed safety or environmental questions are involved.
- 4-EMM-86-9677 This DCP provided 8 duplex outlets. in the j Administration Building Cafeteria. The. addition i of these outlets did not. create a new safety hazard to the plant nor did it affect the safe ;
i shutdown of the reactor. It did not change the l plant effluent releases and did not alter the existing environmental ' impact. . Therefore, no ; J unreviewed safety or' environmental questions are t
- involved. .;
4-HMJ-86-9682 This DCP relocated the electronic modules for 2 l switches in the solid Radwaste system. This DCP l ) did not create a new' safety hazard to the plant ; nor did it affect the' safe shutdown of the reactor. It did not change the plant effluent . i. releases and did not alter the existing environmental impact. Therefore, no unreviewed ! safety or environmental questions are involved. ; 4 i < i 14 8
QCE Description of Change / Safety Evaluatlan 4-ECM-86-0684 This DCP modified the Upper Branch Junction Module Frame Supports. This DCP did not create a new safety hazard-to the plant nor did it affect a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 4-HMM-86-0687 This DCP installed temperature elements on the Asphalt Recirculation Line and the Asphalt Metering Pump Discharge Lines. This DCP did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 4-HMJ-86-0689 This DCP added a solid state function card to the Solid Radwaste Vapor Body Level Loop. This DCP did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 4-BMM-86-0690 This DCP allowed for minor changes to permanent plant piping to eliminate pipe interference discovered during the Power Ascension Test Program. Due to the minor nature of the changes allowed by this DCP, it did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 4-EMJ-86-0691 This DCP replaced the pressure indicators at all of the Breathing Air Stations in the plant. This DCP did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 49
DCE D.eacristisn af _ Change / safety Evaluation 4-BMJ-86-0692 This DCP corrected the documentation of the Reactor Recirculation Motor-Generator Set Fluid Drive Lube Oil Pressure Computer Input Signals. This DCP did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 4-ECM-86-0696 This DCP removed the Station Service Water Pump Cyclone Separators. The removal of the cyclone separators ensured the availability of sufficient lubricating water for the pump bearings and did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 4-EMJ-86-0698 This DCP changed an incorrectly labeled panel in the Control Room. The panel label was changed from "DW Floor Drain Sump BP267" to "Drywell Floor Drain Sump BT267." The correction of this label did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not altor the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 4-EMJ-86-0699 This DCP rewired the Drywell Leak Detection Condensate Cooler Monitor System to provide annunciation of a high, alert, or failure condition on any channel. This DCP did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 4-ilMJ-86-0706 This DCP was a document-only change to reflect the as-built configuration of the Electro-liydraulic Control Panel. This DCP did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 50
DCE DDB9ript19D DL CbDDS9] Safety Evalunk.19D 4-HMM-86-0708 This DCP deleted 2 air actuated valves from the Gaseous Radwaste System. The deletion of the valves did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 4-HMJ-86-0709 This DCP changed the contacts of the relay for the Load Set Raise Inhibit from normally open to normally closed. This DCP did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 4-HMJ-86-0716 This DCP changed the source of computer point A2426 to the "A" River Level Transmitter from the lower of the "A" or "B" River Level Transmitters. This DCP did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 4-HME-86-0725 This DCP replaced limit switches on valves in the Reactor Core Isolation Cooling Steam Turbine system because the vendor supplied limit switches did not meet the Environmental Qualifications requirements. This DCP did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 4-HME-86-0726 This DCP replaced limit switches on a valve in the High Pressure Coolant Injection Turbine system because the vendor supplied limit switches did not meet the Environmental Qualification requirements. This DCP did not create a now safety hazard to the plant nor did it affect the safe shutdown of the reactor. It i did not change the plant effluent releases and , did not alter the existing environmental impact. l Therefore, no unreviewed safety or environmental questions are involved. i 51 l
D.CE DuchpMsn of Change / Safety Ivaluation 4-HCE-86-0727 This DCP delayed the Ramp Switch Initiation on the Steam Supply Motor Operated Valve of the Reactor Core Isolation Cooling Turbine system to control initial turbine speed and help to prevent overspeed. This DCP did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact. ; Therefore, no unreviewed safety or environmental questions are involved. 4-HCM-86-0728 This DCP replaced the oil pressure gauges on the Reactor Core Isolation Cooling Turbine system. This DCP did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 4-HMM-86-0733 This DCP added isolation valves and flow orifices to the Condensate Distribute system. This DCP did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 4-HME-86-0736 This DCP replaced motor overload heaters in the Class 1E Motor Control Centers. This DCP did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 4-HCM-86-0738 This DCP replaced the plug valve in the inlet line to the Centrifuge Feed Tank Recirculation Pump. The replacement of the plug valve did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 52
DCE Description of Change / Safety Evaluatign 4-HMM-86-0739 Thic DCP replaced 2 strainers in the Service Water Hypochlorination system. This DCP did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 4-HMM-86-0746 This DCP was a document-only change to reflect the as-built condition of access panel penetrations. This DCP did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 4-HCM-86-0748 This DCP replaced a globe valve in the Condenser Air Removal system. This DCP did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact. ' Therefore, no unreviewed safety or environmental questions are involved. 4-HMM-86-0752 This DCP added a protective coating to the Service Water Strainer internal steel surfaces. The protective coating did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and.did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 4-HME-86-0753 This DCP corrected the wiring of contacts in the Main Turbine. This rewiring did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. J l 53 g
~
e i-QCE Dagerintion gi-Chanae/ Safety Evaluation L ' 4-BME-86-9756 -This DCP, added function- generators. to the Reactor. Recirculation: Pumps Temperature' Elements o to 'obtain linear-signals to-;a recorder. .The F function generators:did not create a new safety. , hazard.to the plant nor~did they-affect the safe shutdown of the reactor.. This lDCP 'did not change the plant effluenc. releases and did not-alter the existing environmental: : impact. Therefore, no unreviewed-~ safety or' environmental _ questions are involved. i !- 4-HMM-86-9757- This' 'DCP added l auxiliary relays [toL prevent l 1evel elements in the Solid 'Radwaste system i from burnout due to--excessive' temperatures.. l The additional. relays did not create: a new L safety hazard to the plant nor did they affect l the safe shutdown of the' reactor. This DCP did i notLchange-the plant effluent releases and did , ! not alter the existing environmental impact. - 1 Therefore, no unreviewed safety or j environmental questions are involved. I 4-HMM-86-9758 This DCP mounted a mirror to' allow observation } of the mechanical arm and-the barrel swipe
! drawer in the Solid Radwaste Volume Reduction-j system. The mirror'did'not create a new safety hazard to the plant nor did it affect the safe !
- shutdown'of the
- reactor. 'It did not. change the
, plant effluent releases and did not alter the existing environmental-impact. Therefore, no r unreviewed safety. or environmental questions are involved. i
! 4-HMJ-86-9764 This DCP revised the interlock ~ between the l Circulating Water Pumphouse Fans and Dampers to l permit proper ventilation and cooling of the
! Circulating Water Pump Motors. This'DCP did not i create a new safety hazard ~to the plant nor did
; it affect the safe shutdown of the reactor. It i , did not. change the plant effluent releases and i did not alter the existing environmental impact.
I Therefore, no unreviewed safety or environmental ; questions are involved. i l 4-HMM-86-9765 This DCP interchanged instrument sensing lines j in the' Reactor Recirculation system.- .This DCP j did not create a new' safety hazard to the plant nor did it- -affect the safe shutdown of the j reactor. lit did not change the plant effluent j releases and did not alter. the' existing
- -environmental impact. Therefore, no unreviewed~
i safety or environmental questions are involved. L i 54
p. DCE Descriptisn sf.Ch3Dge/ Safety EyAluati9n 4-HMJ-86-0767 This DCP changed the orifice plug arrangement for Intermediate Valve Actuator Solenoid Test Valves in the Main Turbine Control Oil system. This DCP did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change- the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 4-BMM-86-0778 This DCP installed pipe -hangers to provide support to Respiratory Cleaning Facility piping. The addition of the pipe hangers did not-create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the' plant effluent releases ~ and did not alter the existing environmental impact. Therefore, no- unreviewed safety or environmental questions are invclved. 4-HMJ-86-0782 This DCP revised the range and scale of a recorder in the Process Sampling system. This DCP did not create a new safety hazard to the plant nor did it. affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 4-BMM-86-0783 This DCP modified the Safety .and' Turbine Auxiliary Cooling System Accumulator Nitrogen Bottle Storage Racks to eliminate the need to lift the bottles. This-DCP did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 4-HMO-86-0791A This DCP installed cages around level-instrumentation in the Rerctor Building. The-installation of these cages did not create a new-safety hazard to the plant nor did it affect the safe shutdown of the reactor. It'did not change the plant effluent releases and did 'not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. l 1 55
. . .= - . -- .~. - . . - - . . ~. . ~ . ~ .
1< t i i DCE- DADsIlgt;1gn 91 Change / Safety Evaluation i 4-BMO-86-8791B .Th'is DCP- installed' cages aroundL level l Jinstrumentation in the Reactor Building. The i installation of these cages did not' create a new safety hazard .to the plant nor did- it
' affect the safe shutdown of the. reactor. .It did not change.the plant effluent releases. and
- did _not alter the existing environmental o impact. .Therefore, no unreviewed safety or
. environmental questions are involved. ;
4-HMO-86-9791C This DCP installed cages- around level instrumentation in the Reactor Building. .The installation of ~these cages did not create a i ! new safety hazard to'the plant nor 'did it i ~ affect the safe shutdown of-the. reactor. It did not change the plant effluent releases and 4 did not. alter the existing environmental , 4 impact. Therefore, no unreviewed safety or-environmental-questions are involved. 4-HMO-86-9791D This DCP installed cages around level instrumentation. in the. Reactor Building. The installation of these cages did not' create a new safety hazard to the plant nor did it affect the i safe shutdown of the reactor. It~did not change the plant effluent releases and did not . alter i the existing environmental impact. Therefore, no unreviewed safety or environmental questions 4 are involved. r^ 4-EMJ-86-0795 This DCP is a document-only' change to correct discrepancies in the console legend- and a recorder pen legend in the' Neutron Monitoring system. This RDCP did not create a new safety hazard to the plant nor'did.it affect the safe shutdown of the reactor. It did not change the plant ~ effluent releases and did not alter the existing environmental impact.. . Therefore, no unreviewed safety or environmental questions are involved. 4-HMJ-86-8796 This DCP added a jumper to the Main Turbine Control Oil system to facilitate. testing. .This DCP did not create a new-safety hazard to .the plant norLdid it affect the safe shutdown cf the reactor. It did not change the plant effluent releases and. did not . alter the . existing environmental impact. Therefore, no-unreviewed safety or environmental questions are involved. R
'56 . _ .
DEE Dsesription sf Ebance/ safety Eyal11ation 4-HMM-86-0800 This DCP added a sample valve for Generator Stator Cooling Water Deionizer Outlet Flow. This sample valve did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 4-HMM-86-0806 This DCP changed the trim size of the Solid Radwaste Extruder / Evaporator Temperature Control Valves. This DCP did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 4-HCM-86-0813 This DCP replaced the septa in the Fuel Pool Filter Demineralizer. The replaced septa did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 4-HME-86-0817 This DCP was a document-only change that reflected the as-built location of the Post Accident Sampling System Heat Tracing. This DCP did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questicas are involved. 4-HMM-86-0818 This DCP relocated the welded beam attachment on a hanger in the Main Turbine Sealing Steam system. This DCP did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 57
h EE Description of Change / Safety Evaluation-4-HCM-86-0819 This DCP added;new piping to supply Seal. Water
-for the Main Condenser. Vacuum-Breakers from the Condensate Transfer -Pumps,. This . additional-piping did not create a new. safety hazard. to the plant nor did it affect the safe shutdown of. the reactor. It did not change the plant effluent releases .and :did not - alter the-existing environmental impact. Therefore, no unreviewed safety or . environmental questions are involved.
4-HMM-86-0824 This DCP added. tags to identify the cross feed from the Instrument Gas system. The< tags did not' create'a new safety hazard to:the plant nor did they affect' the safe shutdown of the reactor. This DCP did not change the plant effluent' releases and did not- alter the existing environmental impact. Therefore, no
-unreviewed safety ~or- environnental questions are involved.
4-HMC-86-0827 This DCP added jumpers to enable operating the Control Rocm Chillers remote'from the control Room. This DCP met a. Technical. Specification requirement and did not createLa new safety hazard to the plant nor did it affect the safe-shutdown of the reactor. It did not change:the plant effluent impact. Therefore, no unreviewed safety or environmental questions.
~
are involved. 4-HMM-86-0833 This DCP installed a. rail system :and. support facilities for the Solid Radwaste~ system. . This DCP did not create a new safety hazard to the plant nor'did it affect the safe shutdown of the reactor. It did not change the plant effluent: releases and did not alter. the existing environmental impact. . Therefore, no unreviewed-safety or environmental questions are. involved. 4-HME-86-0839 This DCP provided a power supply for internal lighting of a Radwaste: Control Panel. The power supply did not create-a new safety hazard'to the plant nor . did affect the safe. shutdown of the reactor. It did not' change the: plant effluent: releases. and did not alter. the existing environmental impact. . .Therefore, no unreviewed safety or environmental questions are' involved. 58
DCE Description gf Change / Safety Evaluation DChadded=aldoublenutarrangementto .the
~
4-BMM-86-9855 This Service Water Backwash Arm Shaft.. This DCP did-not create a new safety ~ hazard-to the plant nor' did .it' affect the safe shutdown:of the reactor. It' did~not' change the_ plant effluent : releases. , and did not alter.the _ existing environmental impact.- Therefore, ru) unreviewed . safety or
- environmental questions are involved.
4-BMO-86-9879 This DCP added, Isolation. Valves to~ Drywell' Equipment and Floor Drain. Sumps- Discharge ' Piping.- _The ; valves isolate'the drain sumps when' only 1 pump (in 'either group) is running, , eliminating a syphon _effect. The additional l valves- did not create a new: safety haz'ard to' i the plant nor did'they affect.the safe shutdown i of the reactor. This'DCP did not change ~ the'
- plant effluent. releases and did not alter the-existing environmental impact. Therefore,< no
unreviewed safety or environmental questions j- are involved. 4-HMO-86-9871 This DCP utilized a spare Optical' Isolator . Channel for Safety Relief Valve Annunciation. l This DCP did not create a new-safety hazard' .to the plant nor did it-affect the safe shutdown of the reactor. It did not change the plant i effluent releases and did not alter the existing
- environmental impact. Therefore,:no unreviewed 1 safety or environmental-questions are involved.-
4-HMO-86-9872 This DCP replaced the Cooling 1 Tower- Blowdown Sample Pump. This DCP did not create a new safety hazard to the-plant nor'did'it affect'the - safe shutdown.of the. reactor.
.It did not change.
the plant effluent-releases and did not alter: the existing environmental impact.- Therefore, no unreviewed safety or environmental-questions are involved. 4-HME-86-9879 This DCP added resistors at each Beta. ~ input' from . Bailey Communiciation- Modules. The i resistors'did not create a new safety' hazard to the plant nor did they~ affect the safe shutdown 4 of the reactor. This did not change the plant- i effluent releases'.and did not alter -the
- existing environmental impact. Therefore, no unreviewed safety or environmental -questions are involved.
59
]lCE DR21pription of Change / Safety Evaluation 4-BMJ-86-0883 This DCP added' relays and made wiring changes to allow testing of .the Turbine Master Trip Soleno' ids. This DCP did not create a new safety hazard to the plant nor did'it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or. environmental questions are involved.
4-HME-86-0888 This DCP removed a jumper which was erroniously connected, causing' ground fault on the 125 volt DC system. This DCP did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It.did not change the plant effluent releases and did not alter the-existing environmental impact. Therefore, no unreviewed safety or environmental questions are 3 involved. 4-HMM-86-0890 This DCP replaced a double sink in the Decontamination Facility with a single sink. This DCP did not create a new safety hazard to the plant nor did it affect the. safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 4-BMJ-86-0903 This DCP added a booster relay to the Solid Radwaste Crystallizer Compressor. The relay did not create a new safety hazard to the ' plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 4-EMJ-86-0908 This DCP added jumper connections to the Main Generator Instrumentation to provide a signal to the Electric System Operation Center. The jumpers did not create a new safety hazard to the plant nor did they affect the safe shutdown of the reactor. This DCP did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions l are involved. l 60
r DCE Description 91 chanae/ Safety Evaluation BMP-86-8999 This DCP torqued the U-bolt assembly'on a hanger in .the High Pressure Coolant Injection system. This DCP.did not create a new safety hazard to-
, the plant.nor'did it affect the safe shutdown.of the -reactor. It ;did not change the: plant effluent releases and did not alter the existing environmental impact.; Therefore,- no unreviewed'
. safety or environmental questions _are' involved.
4-EME-86-9912 This DCP re-designed the Shunt: Trip Circuit in 480 Volt. Class lE Motor Control-Centers which -- provide back-up power supply to non-class ;1E inverters. :This DCP did not create ainew safety hazard to the plant nor did it affect the ' safe-shutdown of the reactor.- It did not change the plant effluent. releases and did not - alter .the existing. environmental impact. Therefore, no unreviewed safe'ty or environmental questions are involved. 4-EMC-86-0913 This DCP replaced 2"x 2" wire m'esh.with 1" x 1" wire mesh-on' doors used as functional barricades to radiation areas. The smaller mesh prevents personnel from reaching through the mesh to unlock the doors. This.DCP did not create a new
~
safety hazard to the plant nor did it affect.the-safe shutdown of the reactor. It did not. change the plant effluent-releases and did not ; alter the existing environmental impact. Therefore, no unreviewed safety or environmental. questions are involved. 4-EMC-86-0914 This- DCP installed key-lock switches on Radiation. Shielding. Doors leading into the-Moisture Separator -Rooms and added security-gates at the bottom of the. ladders leading to l the roof above the Moisture Separator Rooms._ 1 This DCP prevents unauthorized access and did. not create a new safety hazard to the. plant ~nor did it. affect the safe' shutdown of the: reactor. It did not change the plant effluent releases and did. not alter the' existing . environmental impact. Therefore, no. unreviewed safety or environmental questions are~ involved. 4-EMC-86-9915 This DCP installed a fencefaround the Cooling-Tower, the Circulating Water Pump. Structure, and the Fuel-Oil Storage Tank... The fence did not create. a new-safety hazard?to'the plant nor-did it affect the safe shutdown of the reactor. -It did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental-questions are involved. 61~
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DC2- Description 21 Change / Safety' Evaluation. 4-EMJ-86-0916A This .DCP -provided -zone markings on . Bailey recorders in the Main Control Room to indicate
<their. normal' operating range. This.DCP met ~a licensing _ _ commitment and did not create a -new safety hazard to the plant nor.did it affect i the safe-shutdown of the reactor. It did ~ not change the plant effluent releases-and did not .
alter :the existing . environmental- , impact. i- Therefore, no unreviewed safetyc or environmental questions are involved. 4-EMJ-86-0916B- This DCP provided- zone markings on . Bailey-indicators in the Main Control Room to indicate
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their normal operating range. ThisiDCP met .a licensing commitment: and did not create a new: safety hazard to the plant nor did it affect the
; safe shutdown of the' reactor. It did not change the plant effluent releases and did not alter 4
the existing environmental impact. Therefore, I no unreviewed safety or environmental questions are involved. 4-EMJ-86-0916C This DCP provided zone- markings on Bailey. edgewise indicators in the Main Control Room -to-indicate their normal operating range. This DCP met a licensing commitment and did not_ create.a new safety hazard to the plant - nor did- it affect the safe shutdown of-the reactor.- It did not change the plant eF' ~ent ' releases and did not alter the existing' environmental-impact. Therefore, no unreviewed safety .or environmental-questions are11nvolved.. , 4-EMC-86-0918 This DCP provided restraints for equipment in
. the Main Control Room. The restraints l satisfied seismic and' missile ' hazard :
considerations and did not create.a new safety hazard to the plant nor did they. affect _the
- safe shutdown of-the reactor. This-DCP did not i change the plant effluent releases and'did not l alter the existing environmental impact.
i Therefore, _ no_ unreviewed : safety or-1 environmental questions are involved. 4-EMC-86-0924 This DCP installed steel beams' andJ added stiffeners to existing. beams in- the_' Turbine l' Building. _This DCP did not create a new safety . hazard to the plant nor did.it affect the safe. shutdown of the reactor. It'did not change ~the plant- effluent releases and'did not alter: the existing environmental impact.- Therefore, no i unreviewed safety'or environmental questions are involved.
'62
1 I DCE 'DescriptioD-pf chanae/Safetv Eyaluation 4-EMJ-86-0925A This DCP added' test instrumentation.to monitor
- Narrow and ;WideJRange Reactor Vessel _ Level-Sensing Lines-to determine the magnitude lof~the hydraulic transients that are causing spurious:
logic actuations. The . additional = instrumentation-_ did not create-a -new. safety 4 hazard to the plant nor did it affect'the safe shutdown of.the-reactor. It did not change _the plant ~ effluent. releases _and did not alter the existing. environmental impact. Therefore,_ no , unreviewed. safety or environmental .qu'estions are involved. 4-EMJ-86-9925B This.DCP added test instrumentation to monitor Narrow and Wide Range Reactor Vessel Level Sensing Lines to determine the magnitude of :the i hydraulic transients that are: causing spurious
!' logic actuations.. .The additional instrumentation did not create a new _ safety hazard to the plant nor did it affect-the' _ safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved.
, 4-BMP-86-0926 This DCP added isolation on pipe between; the Reactor Pressure Vessel- and the condensing . Chamber. The insulation did not' create.a new safety hazard to the plant nor did it affect the safe shutdown of the-reactor. It1did not change the plant effluent releases and-did not . alter the existing environmental impact. .Therefore, no unreviewed safety or environmental questions l are involved.
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4-BMP-86-9927 This DCP added insulation at several-Main Steam and Feedwater System Pipe . Whip -Restraint, l location. The insulation did not create a new . safety hazard to_the plant nor did it affect the i safe shutdown of the reactor. It did_not change
'the plant effluent releases and did not' alter the existingLenvironmental impact. lTherefore, no unreviewed safety or environmental questions 4
are involved. l 4-BMP-86-0928- This DCP added insulation _to~2 lines in the 1 l Nuclear' Boiler system. The insulation. did not j '
- . create a new safety hazard to the-plant nor did it affect the safe shutdown of-the reactor._ It did. not change the plant effluent
- releases and.
did not alter' the existing:. environmental
- impact. Therefore, -no unreviewed safety--or.
l environmental questions are-. involved. 63-
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i DOE Descripti9A 21 Chanae/ Safety . Evaluation- 1 BMP-86-0929 .This DCP modified the Reactor Pressure. Vessel insulation. .The insulation did not create a new
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safety hazard to the plant nor did it affect the safe shutdown.ofithe reactor. It did not change i the. plant effluent' releases and did not alter
.the existingsenvironmental impact. . Therefore, no unreviewed safety or environmental questions are. involved.
4-EMJ-86-8930 This DCP labeled applicable recorders and ! indicators " category 1" as. defined by Regulatory Guide 1.97. The labeling met a . licensing l commitment and Edid not create a new' -safety hazard to the plant nor did it affect the safe shutdown'of the reactor. .It did not change the-plant effluent releases and did not _ alter :the existing environmental impact. Therefore, no , unreviewed safety or environmental questions are
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involved. 4-EMJ-86-0939 This DCP was a fsoftware-only change and corrected errors in-the plant' computers.= This DCP- did_ nots create ainew safety hazard txt the
-plant nor.did it affe~ct the safe' shutdown of the reactor. _Its did notichange the plant. effluent releases and did not alter the ' existing environmental impact. LTherefore, no unreviewed safety or environmental questions are involved.
4-EMJ-86-9942 This DCP recalibrated alarm modules- in the1 Reactor Building Atmosphere Control system. This DCP did not create a new safety. hazard ta) l the plant nor did it affect ~the safe shutdown of l the reactor. It did not change- the. plant effluent releases and'did not alterLthe existing environmental impact. Therefore, no unreviewed j safety or environmental' questions are involved. j 4-EMJ-86-0943 This DCP added and relocated multiplexors in the Transient Montoring system.- _This DCP- did not create a new safety hazard to the-plant nor. i did it affect the-safe shutdown of the' reactor. i It did not change the plant effluent releases 1 and did not alter the-existing environmental i impact. Therefore, no unreviewed safety or " environmental questions are involved. o 64L j
~ DCE Dessrintion af Chanae/ Safety Evaluation l
4-EMJ-86-0945- This DCP added~ cables between several cabinets-to complete the grounding integrity for .the Control Room Integrated Display computer system. The: additional cables did.not create a new safety hazard ato the plant nor did they-affect the safe shutdown of the reactor. This
- DCP did not change the plant' effluent- releases and .did not alter the ~ existing . environmental impact. -Therefore, .no unreviewed safety- or environmental questions are involved,.
4-ECM-86-9949 This DCP modified Instrument Air Supply ' Tubing-and- replaced 2; valves in the Containment Atmosphere ~ Control : system. .This DCP did notL create a new safety hazard:to'the_ plant nor- did 4 it affect the safe shutdown.of the reactor. -It did- not change the plant' effluent releases and- ,4 did not alter the' existing environmental impact. Therefore, no unreviewed safety or environmental- ! questions are involved. 1 4-EME-86-9950A This DCP modified the Key Interlock system in the Switchyard to reduce the _ probability. of , grounding the 599KV grid into the 25KV ground switch. This DCP did not create a'new safety hazard .to the plant nor did it affect the. safe shutdown of the reactor.- -It.did not change the-plant effluent releases and.did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions 4 are involved. i.
- 4-EMM-86-0952 This DCP replaced solenoid
- valves in . the Containment -Atmosphere. Control and Safety
- Auxiliary Cooling systems to prevent failure of the valve due to overpressurization.- This>
valve replacement did not create a.new safety hazard to the plant nor did it affect-the' safe , shutdown of the reactor. It did not change the plant effluent releasessand did not alter the , existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 1 4-BMC-86-0953 This DCP removed cables from. Unit 2 Turbine Building Wall penetrations and resealed _the penetrations. This DCP did not_ create a :new j safety-hazard to the plant 1nor did it affect the safe shutdown ofLthe. reactor. It did not change 4- the plant effluent. releases and did:not- alter the existing. environmental impact. Therefore,
- i. no unreviewed-safety or environmental questions l are involved.
f 65
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1
- D2 Deacripti9n 91 Ebgnge/SRfety EMAlR0hlDD 4-BMC-86-0954 This DCP redesigned unsatisfactory penetration seals (and installed the new1 design. -The improved' penetration seals did not create a new safety hazard to the plant nor did they. affect.
the safe ~ shutdown of the' reactor. Th;s DCP did not change the plant effluent releases and.did not alter the existing- environmental impact. Therefore, no unreviewed safety or environnental questions are involved. 4-EMJ-86-0956 .This DCP changed the ControlqRod Drivt Charging Water Header Pressure Switch from a highi pressure switch to a low pressure switch.. This DCP did not create.a new safety hazard to 'the plant nor did it affect the safe-shutdown of the reactor. . It did not_ change:the' plant effluent releases .and did. not -alter the' existing environmental impact.- Therefore, no unreviewed safety or environmental questions are. involved.
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4-BMC-86-0958 .This DCP. resealed penetrations that were. opened-to add new cables. Resealing the penetrations did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant- effluent' releases and did not; . alter the- existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved.- 4-EMJ-86-0959A This DCP replaced electropneumatic transducers-in the Feedwater system. -The transducers did not create a new safety hazard to the plant nor did they affect the safe shutdown of the reactor. This DCP did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed' safety or environmental questions are involved. 4-EMJ-86-0959B This DCP replaced electropneumatic transducers in the Feedwater system. .The transducers did not create a new safety hazard to the plant nor did they affect the safe shutdown of .the reactor. This DCP' did not change =the. plant . effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or _ environmental questions are involved. 66
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RCI. Description 91 Change / Safety EyaluatJgn 4-EMJ-86-0959C This DCP. replaced.electropneumatic transducers in the Feedwater system.- The transducers did not create a new. safety hazard to the plant nor did they affect ,the safe shutdown of the-reactor. ' This- DCP did not change the plant effluent ~ releases and .didnot - alter the existing. environmental impact. Therefore, no unreviewed safety or environmental- questions - ' are~ involved. 4-EMJ-86-0961 'This DCP _conducte'd a test on'the Air--Supply system- to document that the . existing installation meets the design. intent <of the-system. The. test'did not create a new: safety hazard to the plant-nor did'it-affect the safe-shutdown of the reactor. It-did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety orJenvironmental. questions 1are involved. 4-EMJ-86-0962 This DCP modified the Reactor Auxiliary : Cooling-and Chilled Water systems' logic to prevent-_the overflowing of the Chilled _ Water Head Tank and over running the Reactor Auxiliary. Cooling
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System Pumps. This DCP did not create ~ a ; new safety hazard to the plant nor did it. affect the safe shutdown of the reactor. It did_not change the plant effluentireleases and did not: alter the existing environmental impact. Therefore,. no unreviewed safety or environmental questions are involved. 4-ECE-86-0963 This DCP changed the. power supply for the Safety Relief Valve Acoustical Monitors to provide an uninteruptible power supply. This modification met an FSAR commitment and didLnot create a new safety hazard to-the' plant nor-did it affect the. safe shutdown'of the reactor._-It did not. change ; the plant effluent releases.and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 4-ECE-86-0964 This DCP changed the power supply for the. Neutron Monitoring System Drive Motors-to class lE. This DCP met an FSAR commitment and did not ! create a new safety hazard to the. plant nor did it affect the safe shutdown of the reactor. , It did not change the plant effluent releases and did.not alter the existing. environmental impact. l Therefore, no_unreviewed safety or environmental i questions are involved. '
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, 67~
k 'D.CE Dassript.19B 2f . Change / Safety . Evaluation 4-EMJ-86-0966A This ' was'a document-only change to reflect the 11 . programming -of .some Bailey- FPLA. chips. This DCP did.not-create.a new safety hazard to the plant nor did it affect the. safeL shutdown-of the reactor. It did not changeLthe plant -effluent releases and did not alter the existing environmental. impact. :Therefore,' no unreviewed. safety or' environmental questions are involved. 4-EMJ-86-0966B -This DCP . corrected .the programming of. some Bailey FPLA chips. These, programming changes met the original ~ intent of the system and did not-create a new safety hazard to the plant nor did they affect .the safe shutdown of the reactor. This DCP did not change.the plant effluent- releases and ,did not alter the existing environmental impact. Therefore, no unreviewed. safety or. environmental questions are involved. 4- ;MJ-86-0966C This DCP was a document-only change.to reflect the actual FPLA programming on Bailey Logic Modules. This DCP did not create a new safety hazard to the plant nor did it affect.the safe shutdown of the reactor. It did not change the plant effluent . releases and did not alter- the existing environmental impact.. ~Therefore, no unreviewed safety or environmental questions are involved. 4-EMJ-86-0967 This DCP provided an- uninterruptable power supply to the Residual Heat Removal Heat Exchanger Outlet Temperature Recorder. This DCP met an FSAR commitment and did-not create a new safety hazard to the plant'nor did it' affect the safe shutdown of the reactor. It-did not change the plant effluent releases and did not alter the existing environmental impact. . Therefore, no unreviewed safety or environmental questions are involved. 4-ECE-86-0971 This DCP eliminated nuisance alarms on the' main annunciator and eliminated data logging .of those alarms. The-elimination of the alarms-did not create a new safety hazard to the plant nor did it' affect =the safe' shutdown of- the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 68
t J DCE - Description Af ghangs/ Safety Evaluation 4-EMP-86-9982 This DCP addedLgaskets to a pipe support in the Reactor Water Cleanupisystem. _The- additional gaskets. did.not create a new' safety hazard- to the plant nor did-they affect the safe 1 shutdown-of .the reactor. .This DCP'did not. change the~
. plant effluent releases and did not alter the existing ~ environmental" impact. Therefore,- no unreviewed safety .or environmental questions-are involved.
4-EMM-86-9983' - This~DCP relocated'a temperature element.in'the. - Drywell Area .due to its -proximity to -the Reactor Pressure Vessel Refueling Bellows Assembly. Relocating.the temperature element did not create a new safety hazard.to the: plant nor did it affect the safe shutdown of :the reactor.- It did not change :the plant effluent. releases and did not alter .the . existing; environmental impact.. Therefore, no unreviewed safety or environmental questions are involved. 4-EMP-86-9984 This DCP added flanges on vent and. drain lines to facilitate the removal of the' Residual Feat Removal Pump and Motors. The flanges did not-create a new safety hazard-to the plant nor-did they affect the safe shutdown.of the ' reactor. This DCP did not change the plant _ effluent j releases and .did not alter the existing environmental impact. -Therefore, no unreviewed safety or environmental questions are. involved. 4-HME-86-1003 This DCP changed; setpoints on- the' Lube Oil-Centrifuge Inlet. Temperature. Switch.- The setpoint change did.not create a new safety hazard to the plant nor.did it. affect the safe. shutdown of the reactor. It.did not change thet plant effluent releases and did not-alter the' existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 4-HMM-86-1908 This-DCP was a document-only change to show the actual position of-a valve on a discharge 'line from the drain pot to the Main Condenser.: This DCP did not. create a new safety hazard to the plant nor did.it affect.the safe shutdown of the reactor. It did not change the plant effluent . releases. and did not alter the existing environmental impact. Therefore, no-unreviewed safety or environmental ~ questions-are involved.
-69
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\
Description ofEChange/ Safety'EvaluatioD
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DCE 4-HME-86-1999 This DCP changed 1the scale.on the Steam : Seal Feed Pressure. Indicator.'from "%" to' "PSIG". This- DCP did not create a new safety hazard to the plant.nor did it affect the safe shutdown of-
- the ' reactor, fit did not-. change the plant' -
effluent releases and did not alter the existing environmental. impact. fTherefore,.no unreviewed safety or environmental ~ questions:are' involved. 4-BMM-86-1915 ' This DCP modified. wiring soithat . Main _ Steam Drain Line. Temperature and Reactor Head' Vent Temperature indicate _without an alarm.. This was done as'a. human. factors improvement and did : not create a new: safety hazard to the plant nor did it affect the safe shutdown'of the reactor. This DCP did not change _.the; plant ~ effluent releases .and did. not alter _the existing environmental impact. Therefore, no unreviewed safety or environmental questions.are involved.- 4-HMM-86-1919 This DCP; added a capacitor) to' the Source-Selector card in the' Display Memory modale of-the Reactor _ Manual . Control- system. . The capacitor did not create-a new safety hazard -to -- the~ plant nor did it affect the safe. shutdown of the reactor. It did not change .the plant effluent releases and did .not alter'-the existing environmental-impact.. Therefore, no unreviewed safety or environmental questions are involved. 4-HMJ-86-1922 This DCP added a.defuser. baffle on the side of-the Waste Precoat. Tank. The baffle did not i create a new safety hazard'to the plant nor did- l it affect the safe shutdown'of_the reactor. It : did not change the plant effluent releases and did not alter the existing-_ environmental impact.- Therefore, no unreviewed safety or. environmental ' questions are involved. , 4-HMM-86-1932 This DCP added insulation to a line in the Reactor Recirculation system. The insulation l did not create a.new safety' hazard to the plant -< nor- did it affect the safe- shutdown of the l reactor. It did not change the-plant . effluent releases and. did not alter the. existing. environmental impact. Therefore, no'unreviewed-safety or environmental questions are-involved.
- DCE Description 91 Change / Safety Evaluation 4-HME-86-1942 This DCP installed flexible. hoses on valves- in the Condensate 1 system'to supply instrument air.
The installation of the flexible hoses did' noti create.a new safety hazard to;the plant nor: did it affect the safe. shutdown of-the. reactor.. It did not change the plant. effluent. releases .and-did not altersthe existing. environmental impact.- Therefore, no unreviewed safety or environmental questions are involved. 4-HMC-86-1946 This DCP sealed penetrations 11n the. Reactor Building floor. - The. penetration seals.did not create a new safety hazard to the plant nor-did-they affect the safe shutdown. of the reactor. This DCP did- not change the: plant effluent releases and did not alter the existing environmental impact. . .Therefore, no unreviewed-safety or environmental questions are involved. 4-BMM-86-1947 This DCP repaired leaking exterio'r . Wall-penetration seals. This DCP.did not create a. new safety hazard to the plant nor did.it affect the safe shutdown'of the reactor. It did'- not change the plant effluent releases and did -not' alter -the existing . environmental impact. Therefore, no unreviewed safety orienvironmental questions are involved. 4-BMM-86-1952 This DCP re-routed the Resin Dewatering Effluent to the Liquid Radwaste Collection system from the Solid Radwaste Collection system. This DCP did not create a new safety hazard to the plant nor did they affect the safe . shutdown of the reactor. This DCP .did not change Lthe- plant effluent releases and did not alter-the existing
. environmental impact. Therefore, no unreviewed safety or. environmental questions are involved.
4-HMJ-86-1954 This DCP modified the Main Turbine Generator Differential Expansion Recorder and- Alarms. These- modifications did not create a new safety hazard to the plant nor did they affect.the safe shutdown' of .the reactor.. This DCP did not change the plant _ effluent 1 releases-and did not
. alter the- existing. environmental. impact.
Therefore,'no'unreviewed safety or environmental questions are involved. 71
DCE DeacIipt19n 91-Change /SAfaty Eyaluatlan. '4-HMJ-86-1955 This DCP .added- a pump'and automatic' control circuit for the Heating Steam' Condensate Waste-Radiation Monitor Sample Line. 'This DCP.did not create a new safety hazard to'the, plant nor did-it affect the safe shutdown of the reactor. It did not. change the plant effluent releases and did not' alter the existing. environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 4-HMM-86-1964 This DCP installed fencing .for a tool storage area inside the Radiological Control Area. This fencing did not create a.new safety hazard to the plant;nor did it affect the: safe shutdown of the ' reactor. It did not change the plant. effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions-are involved. 4-HCI-86-1965 This DCP replaced the Main Steam-Line and the Offgas. Pretreatment Logarithmic- Radiation-Monitors. This DCP-did not create a new safety hazard ,to the plant nor'did it~ affect the safe shutdown of the reactor. .It did not change the plant , effluent releases'and did not alter the existing environmental -impact. 'Therefore,- no unreviewed safety or environmental questions are involved.- 4-BMJ-86-1967 This DCP . modified a flow meter in the. Circulating Water system.- 'This DCP did not create a new safety hazard to the plant nor did it affect the safe shutdown of the' reactor. .It did not change the plant effluent releases and did not alter.the existing environmental impact. _' Therefore, no unreviewed safety or environmental questions are involved. 4-EMJ-86-1972 This DCP modified the:Drywell HVAC Erhaust_. Ring Header .and Head Area Supply _ Outlets to. reduce q Drywell temperature. This modification did not l create a.new safety hazard to the plant nor did ' it affect the' safe shutdown of the reactor. It did not change the plant. effluent releases and did not alter-the existing environmental' impact. Therefore, no unreviewed safety or environmental questions are involved. 1 72 b
o DC2- Dsasription 91 Change / Safety Evaluation 4-HMM-86-1978 This DCP changed the operating condition aof valve 1KC-V291_from locked closed to normally. . open. This valve' supplies' Temporary Lubrication-
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-Water Make-up 'to- the . Circulating . Water.
- Lubrication Head Tank.. This water is required to start the Circulating Water Pumps._ This DCP did not create a new safety hazard to the . plant nor did it affect the safe shutdown of- the reactor. It. did not change the plant effluent releases land did not alter the 1 existing environmental impact. Therefore, no unreviewed '
safety or environmental questions are involved. 4-BME-86-1982 This DCP was a document-only change to. reflect as-built cable terminations. The. terminations were. changed by Temporary Modification 584. This DCP'did not create a new safety hazard to the plant nor did it affect'the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact. . Therefore, no unreviewed , safety or ervironmental questions are involved. ' 4-HMM-86-1983 This DCP sealed the gaps between the Return Air Plenums and the Drywell Unit Coolers to increase the return air flow. Sealing the gaps did not create a new safety hazard to the plant nor did it affect the safe shutdown of the-reactor. It did not_ change the plant effluent releases. and. ' did not alter the existing environmental' impact. Therefore, no unreviewed safety or environmental questions are involved.- 1 1 4-HMM-86-1992 This DCP relocated Condensate Air Removal Flow Tubes. Thia DCP did not create a new -safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did~not change the plant effluent releases and.did not. alter the existing environmental impact.- Therefore, no unreviewed safety or environmental questions are involved. 4-HME-86-1995 This DCP changed the identification tags on Main Steam Solenoid Valves. Changing the-tags did not create a new safety hazard to the plant nor. did it affect the safe shutdown of the reactor.. It did.not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. '
. 73'
=
t D.CE- Dassriptignigi _Chanae/ Safety . Evaluation .. 4-HMM-86-1999 'This .DCP provided. additional ladders in :the Drywell for' improved access.. The ' additional-ladders did- not createna new safety hazard. to-the. plant nor did.they affect ~thel safe _ shutdown of the reactor. This:DCP did not change the plant effluent . releases and.did not alter the existing _ environmental' impact.- Therefore, no unreviewed safety ~or environmental questions are involved. 4-MMJ-86-1101 This DCP changed an. alarm point termination 'in the Generator Gas. Control system. -This'DCP-did not create a new safety hazard to the plant inor did it affect the safe shutdown of the: reactor. It did not change the plant . effluent releases and did not alter the existing- environmental impact. Therefore, uno .unreviewed safety or. environmental questions are involved. 4-BME-86-1105 This DCP made Temporary Modification 582 -a permanent design change. It corrected. wiring to a Steam _ Seal Evaporator and did~not create a new; safety hazard to the plant nor did it affect the safe shutdown of the reactor. ~This DCP did not-change. the plant effluent. releases and did- not alter the existing: environmental .-impact. Therefore, no unreviewed safety or environmental questions are involved-4-HMJ-86-ll26 This DCP replaced the contact blocks in the Rod ~ Select module of the Reactor Manual' Control; system. This _DCP did not create a new . safety; : hazard to the plant nor did it affect the safe l shutdown of-the reactor. It did not change the: plant effluent releases and did'not alter- the , existing environmental impact._ -Therefore,. no j unreviewed safety or environmental ~ questions are j involved. j 4-HMM-86-1146 This DCP revised the Personnel Access Airlock' Door Control Linkages and Interlocks. This-DCP did not create a new safety hazard to the plant nor did -it affect?the safe shutdown of the reactor. It- did not~ change the: plant effluent releases _ and did not alter the exist'ing environmental impact. Therefore, no.unreviewed. safety or environmental questions are. involved. v i
'74
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-DCE Descriggign 91 Chanae/ Safety EYBlkakiDB 4-HMJ-86-1148 This DCP retubed the, Vacuum. Relief Valve System Differential Pressure _ Transmitters to allow for proper operation. This DCP did not create afnew safety hazard _to the plant norLdid it affectfthe safe shutdown of the. reactor. It did not change the~ plant effluent releases and did not : alter the existing environmental impact. Therefore, no unreviewed safety or~ environmental questions are' involved.
4-HME-86-1169 This DCP increased the' overload heater size for-a motor-operated valve in the Auxiliary Steam-Seal Supply system.to the proper size. Th'is DCP' did not create a new safety hazard.to the-plant nor did it- affect the safe. shutdown of the reactor. It did not change:thefplant effluent-releases ~ and did not alter the existing environmental ~ impact. Therefore, no'unreviewed safety or environmental questions are involved. 4-HCM-86-1162 This DCP replaced _ Hydraulic. Snubbers on the insulation support frame above1the. . Biological Shield in the Drywell. Replacing the 'anubbers did not create a new safety hazard to the, plant nor did it affect the safe shutdown of the reactor. It'did not change-the1 plant - effluent-releases and! did not alter the. existing i environmental impact.' Therefore, no unreviewed safety-or environmental questions are involved. 4-HMJ-86-ll77 This DCP installed a 1 higher capacity flow transmitter for the Dechlorination system to adequately dete';mine the flow'on ther Cooling-Tower Blowdown line.- This DCP did-not create a-new safety hazard to the plant nor.did it affect the safe shutdown of the reactor. It did not-change the plant effluent releases ~and did. not alter the existing environmental- impact. Therefore, no unreviewed safety or-environmental-questions are involved. 4-HMM-86-1178 This DCP tested the time response of. Recirculation -Flow Valves. This test-did not~ create a new safety. hazard to the plant nor did it affect the safe shutdown of the reactor.- It did not change the plant' effluent releases; and ; did not alter the existing environmental impact. l Therefore, no unreviewed safety or environmental ! questions are involved. I H i
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- DCE Description of Change /SAfD.t;y Evaluatign; I
4-HMM-86-1180 This DCP .sealdd penetrations'in..the Radwaste. '! i, Building (Room 3154). .The penetration; seals _ met. J l a licensing' commitment and did not. create a new : safety hazard to the plant:nor did.they ~ affect the. safe shutdovn of the:teactor.. -This DCP did 2 not change-the plant effluent releases.and .did q l not alter the existing environmental impact. i Therefore,-no unreviewed safety or environmental questions are involved. 4-BME-86-ll85 This DCP sealed pen'etrations-in the Radwaste- l
; Building . (Rooms 3298 _ and . 3399). .
The1 penetration seals metLa licensing. commitment [ and did not create a new safety. hazard to the plant nor did theyiaffect the. safe shutdown of the. reactor. . This.DCP.did not change the plant- , effluent releases and- did. not alter the. existing-environmental impact. Therefore, no unreviewed safety or environmental questions are involved. i 4-HME-86-1186 This DCP added. penetration seals in Unit 2 Control and. Diesel Building Stairwells. The penetration seals did not create a -new safety . hazard to the plant.nor did they affect'the-safe shutdown of the reactor. This DCP did .not change the plant effluent releases and did? not alter the existing . environmental impact. Therefore, no.unreviewed safety or environmental questions are involved. 4-HMM-86-1196 This DCP relocated Drywell Area . Temperature Elements. They care currently located: within 6 , inches of the Residual Heat' Removal Head Spray Line. ' Heat from this line affects the indicated temperature. ' Relocating .the temperature elements did not create a new safety hazard to the plant nor did it affect-the safe shutdown of' the reactor. This DCP did not change'the plant effluent releases and did not alter the existing environmental-impact. Therefore, no unreviewed safety or environmental questions are~ involved. 4-HME-86-1292 This DCP provided internal conduit. seals to conduit in the Suppression Pool Temperature Monitoring system. .. This~DCP did not create a, new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the . existing environmental-
' impact. Therefore, no unreviewed safety or-environmental questions are involved..
76
r n. DER Dsasription of Changs/Safsty Eyaluation H-HMJ-86-1299 This DCP clarified the labels on 'the- Chiller Condenser Pressure Interlocks. This DCP~did.not~ create a.new safety hazard toLthe plant nor did - it affect the safe shutdown of the reactor. It did not_ change the plant effluent releases - and. did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 4-BME-86-1215 .This DCP provided 129 volt.AC power' supplies to transducers in the' Reactor. Recirculation system. This DCP"didJnot create a new . safety hazard to the plant.nor did it affect the safe shutdown 1of the reactor. lit did not change the plant effluent releases.and did not alter the existing environmental. impact.. .Therefore, no unreviewed - safety or environmental questions are involved. 4-HME-86-1221 This DCP. changed- the setpoints on1.the. Fire Water Tank Level. Instruments. This DCP did not create a new safety hazard to.the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and-did not alter the existing environmental impact. Therefore, no _ unreviewed safety -or environmental questions are involved. 4-HMO-86-1229 This DCP replaced a disk pack.on the. Radiation Monitoring computer system. . Replacing the disk pack did not create aLnew safety; hazard to the plant nor did it affect the safe _ shutdown i of the reactor. It did not' change _the -plant effluent releases and did not . alter the existing environmental' impact. Therefore,- no unreviewed safety or . environmental questions are involved. 4-HMO-86-1242 This DCP made Temporary Modification '693 a permanent design . change.. 'The initial-modification lifted wires in the Main Generator
~
Alterex -system and did not create a new _ safety-hazard to the plant nor did it affect the safe shutdown of.the reactor. It did.not change the plant effluent releases and did not alter the existing environmental' impact. Therefore, no. unreviewed safety or environmental questions are involved. 77
DCE Description of change / Safety l Evaluation 4-HMO-86-1247 This DCP added a Field Breaker: Auxiliary Switch Interlock with the Generator Field Ground Relay Circuit. This DCP'did not. create'a new' safety hazard: .to the plant nor didLit affect the safe shutdown of the reactor. It did not-change the~ plant effluent releasesfandidid'not alter the
-existing environmental impact. Therefore, no unreviewed safety or environmental' questions are involved.
4-BMJ-86-1256 -This DCP removed the Process Start Inhibit Signal from the Reactor Auxiliary Cooling System Pump _ Motor Start Logic and removed an interlock so both_ pumps automatically start on.. Loss- of Offsite Power. This DCP did not create.a new: safety hazard to the plant nor did it affect the safe-shutdown of the reactor. 'It did not change the plant effluent releases.and did not alter-the existing environmental impact. Therefore, no unreviewed safety or environmental . questions are involved. 4-HME-86-1271 This DCP corrected. wiring for;the_ Control Rod Drive. Stabilizing Valves. The wiring changes did not create a new safety-hazard.to the plant-nor did they affect the safe shutdown of the reactor. This DCP did not change -the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed-safety or environmental questions are involved.. 4-HME-86-1273 This DCP added a jumper between contacts in the Gaseous Radwaste Panels. This DCP did not create a new safety' hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact.; Therefore, no unreviewed safety or environmental-questions are involved.. 4-BME-86-1287 This DCP changed the engraving on marker plates in the Reactor Protection System- Power Distribution Panels. This DCP did not create a new safety hazard to the plant nor did it affect-the safe shutdown of the reactor. It did not change the plant. effluent releases and-did:'not alter the existing : environmental impact. ; Therefore,-no unreviewed safety or environmental
" questions are involved.
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f DCE Description pf, change /Saffig'EyAluatiga
'4-HME-86-1289 This DCP lifted. leads in the Feedwater System. 1 This. DCP did not create _a new safety hazard to the plant.nor did.it affect-the safe shutdown of the reactor. It did not. change the. plant-effluent releases and did not alter the existing environmental impact. ,Therefore,.no unreviewed safety or environmental questions are involved.
l 4-HME-86-1290 This DCP changed the overload heater and the breaker setting for -a Reactor Water Cleanup. , Isolation Valve. This change reflected the as-- designed condition of the plant and did not create a new safety. hazard to the plant nor.did , it affect the safe shutdown of the reactor. l This DCP did _not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 4-HME-86-1291 This DCP rewired the alarm input so an alarm is received when both Secondary Containment Airlock Doors are open. .This DCP did not create a new safety hazard to_the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter. i the existing environmental ~ impact. Therefore,
, no unreviewed safety or environmental questions
] are involved. I 4-HME-86-1297 This DCP rewired Blow-out Panel Switches in the-I Radiation Monitoring System. Rewiring the l switches did not create a new safety hazard to
- the plant nor did it affect the safe shutdown of the reactor. It did not change the plant '
l- effluent releases and did not alter.the. existing environmental impact. 'Therefore, no-unreviewed safety or environmental questions are involved.
- 4-BME-86-1320 This DCP installed ' lifting lugs -above the Hydrogen Recombiner. . .The lifting lugs did not create a new safety hazard to the plant nor did
! they affect the safe shutdown of the reactor. This DCP did- not change the plant effluent ! releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental' questions are involved. I I 79
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- DCE- Description gf Change / Safety Evaluation HCE-86-1331 This DCP provided the correct heater for a-valve; in the High Pressure _ Coolant,LInjection . System Pump Discharge to-Feedwater Line. :This heater
'did not create a new safety hazard to:the. plant nor did it affect the safe: shutdown .of. the-reactor. -It did not change the plant effluent releases and did not alter .the . existing environmental impact. ._Therefore, no unreviewed safety or environmental questions are involved.
4-HM-9995 This DCP added labels to the Rod Select Panel to identify' Intermediate Range Monitor and Source Range Monitor locations to aid ~ operators in determining which monitor to observe during rod maneuvers. The labels did not create a new safety hazard to the-plant nor did they affect the safe shutdown of the1 reactor.' This DCP did not change the plant effluent releases and did not alter the existing environmental _ impact. Therefore, no unreviewed safety.or_ environmental questions are involved. 4-HM-9017 This DCP changed a setpoint on- the Electro-Hydraulic Control Voltage lComparator Lwhich-provides Bypass Jack indication.
~
The setpoint change provided more margin to' reset and did not i create a new safety hazard to'the-plant nor did- I it affect the safe shutdown of .the reactor. This DCP did not change the plant effluent releases and did not alter- the existing environmental. impact. Therefore, no unreviewed safety or environmental questions are involved. 4-HM-9039 This DCP added 2 capacitors to the Voltage-Regulator / Timing Oscillator board in the Strong-Motion Time History Acceleration Recorder. The capacitors filter out transients.and improve the ability to record seismic' monitor outputL onto cassette tapes. This DCP did not-create a- new-safety hazard to the plant nor did it affect the : safe shutdown of the' reactor. It did not change-the plant effluent releases and did not alter I the existing environmental. impact. Therefore, j no unreviewed safety.or environmental questions- q are involved.- l l t 89
DCE Description Df Change / Safety XEnluation ' 4-HM-0043 This DCP was a document-change only to. reflect the as-built _ condition of the. Circulating. Water Caustic Injection Pumps Internal- Parts.. 'This DCP did not create.a.new' safety hazard.to the plant nor did it affect the safe shutdown of.the reactor. It did'not change the plant effluent: releases and did not alter the , existing environmental impact. Therefore, no unreviewed safety.or environmental questions are involved. 4-BM-0046 This DCP added receptacles in the cafeteria to supply power for vending machines and Lvarious kitchen appliances. , This DCP did not. create a new safety hazard to.the plant nor did it affect the safe shutdown of the reactor. -It did not' change _ the plant effluent releases and did not alter. the existing environmental impact. Therefore, no unreviewed safety or. environmental. questions are' involved. 4-HM-0048 This DCP changed the tag number of the -Main Turbine Vibration Recorder and established setpoints for it. This DCP-did not create a new safety hazard to the plant nor did it affect.the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 4-EC-1946 This DCP changed 2 Reactor Building. Filtration, Recirculation, Ventilation System Low Signal Selectors to High Signal Selectors.- -This: DCP , did not create a new safety hazard to the plant- J nor did it affect the safe shutdown of the ; reactor. It did not change'the plant effluent releases and did not alter- the existing environmental impact. Therefore, no unreviewed-safety or environmental questions are involved. 1 1 l l 81
t 6 Safety Evaluation, ' Description 3f 2MB H-l'-SKXX-CSE-0398 The Temporary ' Modification Request > . (TMR) this Safety Evaluation associated with . supported the use of temporary action l packs . in- -the Drywell Leak . Detection --Sump Monitoring. System. The installation of: the action packs :did not: create:a .new ~ safety , i hazard to _the plant nor did it affect the ' safe shutdown of the-reactor. It 'did not change .the- plant effluent. releases and did t not alter the existing environmental . impact. Therefore, no .unreviewed... safety. or-j' environmental questions are' involved. j H-1-SPXX-SSE-0399 ' The Temporary- Modification- Request .(TMR)
- associated with- this- Safety: Evaluation 4 installed temporary Area-Radiation Monitors inLReactor Building. Rooms 4317 and.4318. The installation of-the-Area. Radiation 1 Monitors
.did not create a new safety-hazard: to. the
! plant nor did it affect the1 safe _ shutdown - of the reactor.- It -did not change the -plant i effluent releases. and did not alter .the existing environmental _ impact. Therefore, no i unreviewed safety or environmental _ questions e are involved. H-1-HBXX-MSE-0401 The Temporary Modification Request ~(TMR) associated with. this Safety Evaluation temporarily . installed. ' Positive Closure Springs in.the Drywell Sump Pump' Discharge Check Valves. This TMR did not create-a new safety hazard to the plant nor:did it affect g ) the safe shutdown of the reactor. It did not I change the plant effluent releases and: did- j not ' alter the' existing environmental. impact. H j Therefore, no ..unreviewed safety' or - environmental questions are. involved. H-1-GJXX-NSE-0407 -The Temporary Mo'dification l Request. .(TMR)
- associated. with this Saf ety _. Evaluation' enabled theLControl Area Chilled Water. system l A-loop Chillers to be' controlled from:1the j Control-Room. This TMR-did not create.a-new
- safety hazard to the plant'nor did it -affect the safe shutdown of the. reactor.. It did not change .the plantteffluentl releases'and 'did
[ j not alter the existing environmental impact. 1 Therefore, .no .unreviewed- safety or environmental questions are-involved. i i
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JQ n'; l Safety Evaluation Description ni THE H-1-ZZXX-ESE-9499 The . Temporary Modification Request.~(TMR) associated vith this- -Safety. Evaluation corrected- wi' ring that caused 1 tripping ofithe~ back-upfingsrtor. power supply.- Thefrewiring_
-corrected' this! problem and.did not cre' ate: :a inew -safe'ty : hazard to the plant.nor ~did' it' affect the safe shutdown of the reactor.. hit did' not change.the? plant effluent releases and.fdid not alter the existing' environmental impact.- Therefore,- Hno unreviewed safety or-environmental questions are. involved.
s, H-1-GSXX-CSE-9417 The :Temporaryi Modification , Request -(TMR) associated .w ith 'this ' Safety ' Evaluation - removed a ~ ground jumper:from the Hydrogen
'Recombiner Panel' Power Supply. Removing this jumper did not create a'newosafety hazard to the-plant nor did it affect the' safe shutdown of the reactor.: It did not change the. plant effluent releases ,and did not alter the-existing environmental' impact'. _Therefore, no unreviewed' safety or~ environmental = questions are involved.- ;
.t l H-1-SPXX-CSE-9422 The Temporary Modification Request (TMR)' .l associated 'with- this . Safety: 1 Evaluation _ l disabled the Rate-of-Rise of:the water level 1
in the floor. drain 1 sumps calculation function l of the~ Radiation Monitoring . System. This function was not operating properly cand disabling it:.did not create a new safety-hazard to the plant nor did it- affect the safe ' shutdown of-the reactor. It-did not chsnge .the plant effluent releases and. did not alter the existing environmental impact. Therefore, . no unreviewed ' safety or environmental questions are involved.
)
H-1-SPXX-CSE-9423 The Temporary Modification- Request (TMR) associated with this Safety _ Evaluation added a- recorder and. wiring to the~ _ Radiation
, Monitoring System to provide: additional information to identify potential causes :of spurious drywell sump level readings. 'This TMR did not' create a new' safety hazard to_the plant'nor did it affect-the safe ~ shutdown of the- reactor. It idid not-change the plant-e effluent 1 releases and did not alter the existing environmental' impact. Therefore, ru) unreviewed safety or environmental questions are involved.
2
(Xp O?~ tr < hD Safety Evaluation . Description 21 THE H-1-BHXX-CSE-9425 The . Temporary Modification Request (TMR) associated with this Safety Evaluation added a recorder and wiring to the Standby Liquid Control System to provide additional information- to, identify potential causes of inadvertent actuations. This TMR did not create a new safety hazard to.the plant nor did .it affect' the safe shutdown of the reactor. . It. did not change the plant effluent releases and did not- alter the existing environmental impact.- Therefore, no unreviewed safety or environmental questions are involved. H-1-BHXX-CSE-0426 The Temporary Modification ' Request. '(TMR) associated with this Safety Evaluation added. a recorder and wiring to the Standby Liquid Control System to provide _ additional information to identify potential causes- of i inadvertent. actuations. This TMR. did not create a new safety. hazard to the plant. nor - did it affect the safe shutdown of the i reactor. It did. not change the ' plant t effluent releases 'and did not . alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. H-1-GSXX-CSE-0427 The Temporary Modification Request' (TMR) associated 'with this Safety Evaluation temporarily defeated 2 Inlet Flow Elements and the associated indicating circuitry for the Hydrogen Recombiners. .These changes are to- be in effect only_when containment is not inerted. Considering this . restraint,- this TMR did not create a new safety hazard to.the plant nor did it affect the safe shutdown of
- the reactor.- It did not' change' the plant effluent -releases- and did not alter the
! existing environmental impact. Therefore,uno unreviewed safety or environmental questions are involved. i 4 3
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i 1- .. Safety Evaluation Description sf THE n
- -H-1-VAR-NSE-9428 The Temporary Modification ~ Request -(TMR) associated with- this Safety Evaluation
- corrected wiring in the Residual-Heat Removal
, and -Automatic Depressurization System Annunciator Circuits. An incorrect change authorizing document had.-previously been-incorporated. This TMR restored the ' system. to its as-designed status and did not create-a new safety hazard to the. plant.nor-did it affect.the safe shutdown of the reactor. .It did not change-the. plant effluent releases , and did not alter the existing environmental' l impact. Therefore, no unreviewed safety:or-environmental questions are involved. H-1-QFXX-ESE-0429 The Temporary Modification Request (TMR) associated with this- _ Safety Evaluation allowed temporary testing and troubleshooting; modifications to the Fire Protection Computer Switchover Board Circuitry. This TMR did not create a new-safety hazard to the plant :nor-did it . affect the safe shutdown of the reactor. It did not change the~ plant-effluent releases and did not alter the-existing environmental impact. Therefore, no unreviewed safety or. environmental . questions-are involved. B-1-ZZXX-CSE-0433 The Temporary- Modification Request (TMR) associated with this Safety Evaluation defeated the Door Tamper Switch on a ' Bailey . Panel. The panel locking mechanism was not working properly, resulting in continuous. annunciation to the Control Room. This TMR ! did not create a new safety hazard ' to the l plant nor did it affect the' safe: shutdown of the reactor. It'did not change: the _ plant effluent releases and did' not- alter- the existing ~ environmental impact.- Therefore, no unreviewed safety or environmental! questions ;l are involved.- i H-1-SFXX-NSE-0434 The Temporary -Modification Request (TMR)- associated with this Safety ' Evaluation replaced a Probe Date Processor Card in the Reactor' Manual Control system. This'TMR did not create a new safety hazard to the plant-nor did it affect the' safe shutdown of the reactor. It did' not ' change 'the plant effluent releases 'and- did~ not alter the existing environmental' impact. -Therefore, no unreviewed' safety cn:. environmental questions are involved. 4
Safety Evaluati2D ' Description 21 IRB H-1-BCXX-ESE-0437 The Temporary Modification Request .(TMR) associated with this Safety Evaluation lifted the 120 volt AC' power leads to the operating solenoid of the Residual Heat Removal Testable ' Check Bypass' Valves.- Lifting the leads did not create a new safety hazard to the plant nor did it affect the safe shutdown of the_ reactor. It did not change the plant effluent releases and did not -alter the existing environmental = impact.; Therefore, no unreviewed safety or environmental questions are involved. H-1-ZZXX-CSE-0440 The Temporary Modification Request (TMR) associated with this Safety Evaluation modified Drywell. -Seal Plate Penetrations. Modilying the penetration. seals did- not. create a new safety hazard to the plant nor did it affect the safe- shutdown of- the reactor. This TMR 'did not change the plant-effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. , H-1-SPXX-CSE-0441 The Temporary Modification Request (TMR) associated with this Safety Evaluation replaced Logarithmic Radiation Monitors for the ~ Main Steam Line Radiation Monitoring ~ . System. This TMR did not create a new safety ' hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant' effluent releases and did ! not alter the existing environmental impact. l Therefore, no unreviewed safety or 1 i environmental questions are involved. ) l H-1-SEXX-MSE-0444 The Temporary Modification Request (TMR) ! , associated with this Safety Evaluation temporarily installed a test jack in the High ~ Pressure Coolant Injection System Panel .for-Power Ascension testing. The installation of l this- test jack did not create a new safety .
)
hazard to the plant nor did it affect' -the i safe shutdown of the reactor. It'did not !
- change the plant effluent releases and did '
not alter the existing environmental impact. Therefore, no unreviewed safety- or environmental questions are involved. l
Safety Evaluation ' Description si lHE - LH-1-SEXX-ESE-8450- The Temporary- Modification . Request- .(TMR) I associated with this Safety Evaluation' modified the Filtration, -Recirculation, and= Ventilation System _to agree with.the., vendor
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documentation. .This TMR did not create a new safety hazard to the plant nor-did<it: affect the safe shutdown of'the' reactor. It did~not. change _the plant effluent releases and fdid not alter-the existing environmental impact. Therefore, no unreviewed safety or environmental 1 questions'are involved. H-1-SPXX-CSE-8464 The Temporary Modification Request- _ (TMR) associated _ with this Safety- Evaluation modified the Suppression, Pool Temperature Monitoring System Channel B Multiplexor wiring. .This .TMR allowed' the system. to continue to provide information indicative of the Suppression Pool Ltemperature- until ~a replacement multiplexor card could be obtained. The modified wiring;did not create a new safety hazard to the plant nor did. it-affect the safe shutdown of the reactor. This .TMR did not change the plant . effluent releases and did' not ' alter the existing environmental' impact. Therefore,- no unreviewed safety _or-environmental questions are involved. H-1-SEXX-CSE-0465 The Temporary Modification Request _ (TMR)' associated with this Safety; Evaluation' lifted leads to eliminate interference to Rod Block
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Monitor Recorders. The lifted leads did not create a new safety-hazard to the_ plant -nor ' did they~ affect: the safe shutdown of -the reactor. This TMR did not change the ; plant effluent releases and- did~ not alter' the existing 1 environmental impact. Therefore, no . unreviewed safety or environmental questions are involved. H-1-SEXX-MSE-0466 The Temporary Mcdification Request (TMR) associated with ~this' Safety: Evaluation installed a temporary sample pump in~ the Offgas Vial Sample Panel to-provide. sample flow for the Offgas _Pretreatment. Radiation Monitor. .The- sample pump did'not create a new -safety chazard to' the plant nor- did- it affect .the safe shutdown of 'the- reactor. This TMR did not. change the plant: effluent-releases- and did- not- alter the . existing. environmental- impact. Therefore, Eno unreviewed safety or? environmental questions are involved.
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F Safe'y'.Eva t uation Description Sf THE H-1-KJXX-CSE-0468 .The Temporary ' Modification Request; - (TMR) - associated _with this Safety Evaluation added' temporary' recorders to monitor.the "B" Diesel;
.an Generator- start. circuitry _following unexplained spurious start..The recorders did
, not create.a new safety; hazard to the plant nor did they affect-the. safe shutdown of the i reactor. This TMR-did not' change the plant-effluent ' releases and did not' alter. the existing environmental impact'. _Therefore, no
.unreviewed safety or environmental questions.
are involved. H-1-AKXX-MSE-9476- The Temporary Modification _ Request (TMR) associated with- this Safety. Evaluation-4 removed the internals to the Ultrasonic Resin I Cleaner' Drain Check Valve in the Condensate Polisher system. Removing the valve internals did not create a new safety hazard' to the plant nor did it affect the. safe shutdown of the: reactor. This TMR did not. change the plant effluent releases.and did , not alter the existing environmental impact. 1 Therefore, no unreviewed safety or: environmental questions are involved.- H-1-JEXX-MSE-0478 The Temporary Modification Request (TMR) associated. with this Safety. Evaluation added Tygon Tubing to- provide- a. method .of determining the fuel-oil' level in the Fuel. Day Tank; This TMR did not create a new I safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not ' change the plant effluent' releases and did not alter the existing environmental. impact. Therefore, no unreviewed- safety or i environmental questions are involved.
; H-1-KJXX-ESE-0481 The Temporary Modification Request- (TMR) I l associated' with this Safety Evaluation )
jumpered the phase "C" Emergency . Diesel ; Generator Time: Overcurrent Relay to : provide i "1 out of 3" logic input. An overcurrent on ] either "A" or "B" phase would energize ?the lockout relay. This TMR- did not create fa-
- new safety ' hazard to the plant nor did
- -it affect the safe shutdown of- the- reactor.
~
, It did not change the plant effluent releases ! and did not alter the_-existing environmental j impact. Therefore, no unreviewed safety or environmental questions are involved. 7
Safety Evaluation Description 2HR: H-1-HGXX-MSE-9484 The Tamporcry Modification-Rtquest[ (TMR). associated' with' this Safety- Evaluation temporarily ' replaced then. Turbine Building High Conductivity = Sump Pumps with a ' Chemical Resitent Pump. Replacing the pumps'did'not-create- a-new safety hazard to the plant. nor did it affect- the safe shutdown- of the-reactor. This TMR did not change the plant effluent releases and did-inot - alters the existing ~ environmental impact. Therefore, no unreviewed safety or environmental-questions are involved. H-1-SUXX-ESE-9515 .The- Temporary Modification Request'_(TMR)
. associated with. this Safety _EvaluationL recalibrated the Heat Tracing Temperature Controllers used- for Solid Radwaste Piping-Protection._ This TMR'did not create a new-safety hazard to the plant-nor did it affect the safe shutdown of the reactor. It'did not.
change the plant effluent releases ~-and_- did not alter.the existing. environmental impact.- Therefore, _ no . unreviewed safetyr or environmental questions are involved. H-1-DBXX-ESE-9516 The Temporary Modification Request (TMR) associated with this Safety Evaluation provided a temporary power ' supply 'in the Cooling Tower Blowdown ~ Radiation -Monitoring System. The temporary _ power supply did not ' create a-new safety hazard to.the plant nor did it affect the safe shutdown of the reactor. This TMR did not change the -plant effluent releases and did 'not alter the existing environmental-impact. Therefore, no unreviewed safety-or. environmental questions are involved. H-1-QAXX-ESE-9517 The Temporary Modification Request . - (TKR) associated' with this Safety Evaluation eliminated . induced voltages / currents:in the class A- Supervised Alarm Circuitry of the Fire Protection Computer by adding resistors. This TMR did not create a new safety hazard to the plant- nor did it : affect the . safe-shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed- safety or environmental questions are involved.- 8
m
.h
' Safety Evaluation
. Description'21 33HL
- H-1-ZZXX-ESE-9542. ' The --Temporary Modification- Request 1 (TMR) associated- - with. this Safety. ; Evaluation ~
spliced the Refueling -Platform. Power and Instrumentation Cable.
~
.This splice did 'not create- a new safety hazard to the_ plant nor did it affect' the -safe shutdown - of the '
reactor. -This TMR.did not change the plant' effluent releases and did' not ~ alter- the
. existing environmental ~ impact. Therefore,.no unreviewed safety-or environmental questions.
are involved.-- , H-1-GMXX-SSE-9565 The . Temporary- Modification. Request. (TMR) associated- .w ith. this ; Safety _- Evaluation removed. the cover plate. from the Diesel. Generator ' Exhaust. Hooks. This TMR did not create a new safety hazard to.the plant- nor did it affect the safe 1 shutdown of -the reactor. It did not schange- the- ' plant-effluent releases' and did not alter the existing environmental impact. -Therefore, no unreviewed safety or environmental questions , are involved. H-1-EAXX-SSE-9566 The Temporary Modification = Request . .(TMR) associated with this Safety -Evaluation repaired the Service Water-Strainer. Interior Surface Protective Coating using Belzona , Molecular-Metal. This TMR'did not create a new safety . hazard to'the plant nor~ did it. affect the safe shutdown of the reactor. , It ~did not change the ' plant effluent i releases and did not . alter the existing environmental impact. Therefore, no , unreviewed safety or environmental . questions. J are involved. H-1-BBXX-CSE-9573 The Temporary Modification . Request- .(TMR) : associated- with this Safety Evaluation ) installed- .a test.~ jack .on the -Reactor ' Recirculation, system: to perform. the controller tuneup" procedure. The. test jack did not' create a new safety hazard 'to the plant nor did it affect the safe shutdown of the reactor. This TMR'did not change the plant effluent releases and did not alter the existing environmental-impact.- Therefore, no unreviewed' safety or environmental questions are involved. 9 -
.-.__..-.u__ .
t Safety Evaluation Description 21 THE H-1-BFXX-CSE-9575 _The Temporary- Modification Request. (TMR) associated with this Safety- Evaluation installed a test jack at .the..-Control Rod
~
Drive Flow Controller Unit Setpoint Input to accomodate using attest generator-to' tune the. control loop. The test. jack-did not create-a new safety hazard to the plant nor did-Lit affect the safe shutdown.of the reactor. This .TMR didinot change the plant _ effluent releases and did not alter _ ,the_ existing environmental' impact. Therefore, . no unreviewed safety or environmental questions are involved. H-1-BBXX-CSE-8577 The Temporary _ Modification-. Request. (TMR). ' associated with this Safety Evaluation added' Honeywell Visicorders to 'the. Channel 1 "D" Reactor Vessel Level Instrumentation to provide additional information to- identify potential causes"of inadvertent actuations.- The additional Visicorders did.not create' a new safety hazard to the plant nor did it affect the safe shutdown Hof- the reactor.. This TMR did not change the plant effluent releases and did not alter .the existing-environmental impact. Therefore, - no unreviewed safety or environmental questions are involved. H-1-AKXX-MSE-9592' The . Temporary Modification Request- (TMR) associated with this ' Safety Evaluation temporarily replaced a lE-capacity controller in a Control' Area Water Chiller with a non-1E
~
capacity controller. This'TMR did not create a new safety hazard to the plant nor did it' affect the safe chutdown of the reactor. l It did not change ~the~ plant effluent releases. and did not alter the existing ' environmental . impact. Therefore, no unreviewed safety or I environmental questions are involved.- j H-1-GMXX-MSE-0593 The Temporary Modification Request (TMR) associated with this' Safety Evaluation replaced moisture elements in the Control Room Emergency Filtration Units with lE resistors. This TMR did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not-change the plant effluent releases and- did-not alter the existing environmental impact. Therefore, no unreviewed safety 'or environmental questions are involved, 1B ,
^
7 1
. Safety Evaluation Description 21 THE H-1-GHXX-MSE-9594 The . Temporary Modification Request .(TMR) associated- 'with: this safety' ; Evaluation-replaced the. internals of:al check. valve ;in :
the1radwaste system with a hose. connected to temporary.'demineralizationLequipment. ,This-TMR did not create ainew safety hazard-to thel-plant nor'did it affect the' safe shutdown .of-
.the reactor. 'It did'not change the plant.
effluent releases and did~ not ' alter the-existing environmental-impact. LTherefore, no-unreviewed safetyL or: environmental questions-are involved. H-1-GUXX-MSE-9595 The Temporary Modificat'on i Request (TMR) associated with? this Safety Evaluation temporarily installed a .non-Q Outside. < Atmosphere Static . Pressure Sensing Head ;on I the. Ventilation portion of the Filtration, Recirculation, and. Ventilation system. Thisi TMR did not create a new safety hazard to the plant nor did it affect the safe shutdown.of the reactor. It did not' change the plant effluent releases. and did- not. alter the existing environmental impact.. Therefore,.no unreviewed safety or environmental questions are involved. H-1-HAXX-MSE-0596 The Temporary Modification-_ Request (TMR) associated with 'this Safety Evaluation-removed 2 Manual Isolation Valves from the-Gaseous Radwaste system. Removing the valves did not create a new safety hazard to~.the plant nor.did it affect the safe shutdown of the reactor. This TMR did not change the plant effluent releases and did not alter the existing environmental impact.~ Therefore, no unreviewed safety or environmental questions. are involved. H-1-GMXX-MSE-0597 The Temporary Modification ^ Request (TMR) associated with this Safety . Evaluation removed an actuator'from a damper. in. the Diesel ' Area Battery Room Exhaust system. Removing the actuator did not-create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. Thig TMR did not. change the plant--effluent re:<ases and did not alter the existing environmental impact. 'Therefore, no.unreviewed safety or environmental questions are involved.
.11-
_y 6 Safety. Evaluation De'scription gf THE
~
H-1-HAXX-MSE-9598 The Temporary Modification Request. (TMR) ; associated with- this' Safety Evaluation , installed La- dewpoint meter in the- Gaseous-Radwaste system. The dewpoint meter did not create _a new safety hazard to~the plant- nor
'did it affect .the safe shutdown of -the.
reactor. This TMR did not change the plant-effluent ~ releases and- did not alter' the-existing ~ environmental impact. . Therefore, no unreviewed safety or environmental questions are involved.
'l H-1-EGXX-MSE-9599 The Temporary Modification Request .(TMR)~ i associated with this Safety Evaluation !
changed the . level setpoints for the Safety. Auxiliary Cooling _ System- Expansion: Tanks. The changed setpoints.did not' create a new _ safety hazard to- the plant nor dio they affect the safe shutdown of the reactor. This TMR did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no- i unreviewed safety'or environmental questions ' are involved. H-1-EAXX-MSE-0600 The Temporary Modification Request .(TMR) associated with this Safety Evaluation adjusted the clearance between the Port ' Shoe and the Screen Element of the Service Water i Strainers Adjusting! the clearance did not. create a new safety hazard to the plant- nor did it affect the safe shutdown of the reactor. This TMR did not change the plant effluent releases and did not ' alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. B-1-KJXX-MSE-0602 The Temporary Modification Request (TMR) . associated with -this Safety Evaluation temporarily replaced an electric heater in the standby Diesel Generator Jacket Water system with a non-Q, non-ASME heater. This temporary modification to the Jacket . Water Cooling Loop offthe Standby Diesel Generator does not adversely affect the ability of'the generator to start and accept loads within-19 seconds or less, and therefore,. will not i preclude the safe shutdown of the plant ' following a Loss ~of Coolant or Loss of Power-Accident. This TMR did'not create a new safety hazard to the plant nor did-it affect the safe shutdown of the reactor. It did not L 12
Safety Evaluation Descripidan of TBBL H-1-KJXX-MSE-9692 change- the fplant effluent releases and- did not alterithe existing environmental- impact. Therefore, no . unreviewed . safety or. environmental ~ questions are involved. 87-9997 The . Temporaryf Modification Request (TMR) associated with' this~ Safety- Evaluation removed the overload heaters from the breaker for~ a ; valve in-the Residual Heat. Removal s Suction / Discharge system.1 This TMR' prevented the valve from opening during a fire and _did. not . create a new safety hazard to the. plant nor did it affectithe safe shutdown of the. reactor. It did not . change .the .' plant. effluent releases and did not alter the existing environmental impact. Therefore,.no unreviewed safety or environmental questions are involved. 87-9999 The Temporary Modification Request (TMR) . associated with this Safety Evaluation.11fted' wires in several panels to remove the.~ power source from the Core Spray Testable Check and Bypass Valve Solenoids to comply with 18CFR59 Appendix R. This TMR did not create a new' safety hazard to the plant nor did it affect the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, . no- unreviewed safety or environmental questions are: involved. 87-9919 The Temporary Modification Request . (TMR) associated with thisfSafety-Evaluation lifted wires in several panels toJremove the power source from 'the. Residual' Heat Removal Testable check and BypassLValve Solenoids to comply with 19CFR59fAppendix R. This TMR did not create a new safety hazard to.the--plant nor did it affect the safe shutdown of the reactor. This TMR did.not. change.the plant effluent releases 'and did not alter the existing environmental impact. Therefore,fno unreviewed safety or environmental' questions are involved. I I I 1 13 ;
, 1 i Safety Evaluation Description sdi THE , 87-9010A The Temporary Modification" Request (TMR) . associated with this Safety Evaluation added a capacitor. to .a Rod Data Memory Card to improve the stability -of the Full Core. Display. Adding-the capacitor did not create a new safety-hazard to the plant nor did it
. affect the safe shutdown of- the reactor.
This TMR did not change the. plant effluent releases and did .not alter the existing environmental impact. Therefore, ~ no unreviewed safety or environmental. questions are. involved. 87-8013. The' Temporary 3 Modification. Request (TMR) associated with this Safety: .: Evaluation changed setpoints an increased the range on transmitters for the- chilled Water Head
- Tanks. These changes will prevent the system from continuously -alarming on .high level.
This TMR did not create a new safety . hazard to 'the plant nor did,it affect' the safe shutdown of the reactor. It did not change the plant effluent releases and did not alter the existing environmental impact.
; Therefore, no unreviewed safety or ! environmental questions are involved.
.i l i l l i 1 4 4 l l 1 e
,- , - . ~ . - ,. . . - . .. . .- . , , . - . . . - - _ - - - - _ _ _
r. 4 , ISafety Evaluation -Description gf RE
'H-1-FCXX-MSE-9435 A 3/8% set screw from'a testable checkcvalve-in the Reactor. Core. Isolation' Cooling-i Turbine Exhaust 'Line was, determined to1 be 4.
missing during a_ Power Ascension test. ~This Safety. : Evaluation determined- that .fthe ; missing screw did not create a safety hazard l= to the plant .nor.did it affect - the1 safe shutdown of the; reactor.. The. deficiency did :;
- not change.the plant
- effluent releases- and did not- alter: the existing environmentel'
~ impact. Therefore, no unreviewed safety.or !
j environmental questions'are involved. H-1-BDXX-MSE-9436 During testingsof.the: Reactor Core Isolation-
- Cooling. system, the discharge lines Lwere ;
l overpressurized. This Safety 1l Evaluation--
- determined ethat the overpressurization did j' not create a safety hazard to the ' plant run .
did it affect the safe shutdown Hof! the j reactor. The deficiency did not change'the
; plant effluent releases and did not alter the existing environmental impact.
Therefore,. no_ unreviewed- safety o r. , j environmental questions are: involved. ' l H-1-BJXX-MSE-0438 During testing _ofEthe.High Pressure . Coolant j Injection system, 'the discharge lines'were
! overpressurized. This Safety Evaluation-
, determined that-the-overpressurization .did , F not. create a safety. hazard"to the plant nor
- did- it- affect Lthe safe shutdown of, the-
- reactor.- The deficiency'did not change-the ~!
j plant effluent releases and-did not alter , }' the existing. environmental . impact. j Therefore, _ no unreviewed. safety- or > environmental questions are involved. 2 H-1-BBXX-MSE-0446 ASME Class 2 piping was _ installed in the f Nuclear Boiler' Vessel ~ Instrumentation and~ } Reactor Recirculation systems. _This piping 4 was originally designed as 'ASME ~ Class L1; J however, this Safety Evaluation determined
; that the ASME Class 2 is= acceptable inL this 4
application and design drawings will be
- changed by DCP: 4-BMM-86-9994. The integrity
) of- the excess flow check.. valve piping is unaffected by~.the material change. . The piping did not' create a safety hazard to the
- plant nor.did'it' affect the^ safe shutdown of-i the reactor. It"did not' change' the' plant -
effluent releases and'Ldid not- alter the i existing environmental impact. Therefore, no ! unreviewed safety lor environmental questions j'
; are involved.
I _ - _ _ _ _ 1
.g 3t- . 3 Safety Evaluation Description af DE H-1-ABXX-MSE-9672. While- replacing solenoids'_in the Main Steam Isolation Valve: Assemblies it was.necessary. to re-use some .O-rings._ This Safety Evaluation ' determined that they are reusable and need' not 'ime replaced luntil the; first- - scheduled refueling outage. The 0-rings-did not create a safety hazard to the plant nor-did it affect- the safe shutdown 1 of the. reactor. The deficiency did not changenthe plant effluent releases and did not alter-the' - existing environmental impact. . Therefore, no unreviewed safety or environmental questions i are involved.
'86-9992 A Control Rod Drive Monit'or-. reported a-high temperature condition, potentially affecting scram time. The high temperature normally is caused by a short Uncoupling. Rod, thereby:not.
allowing enough flow through the Control' Rod Valve Disc. _ Technical Specifications allow U up to 3 Control Rod Drives to' exceed normal-scram time, thereforetthis deficiency;did not create a new safety hazard to the plant: nor did it affect the - ' safe shutdown of. the reactor. The deficiency did~not change the ' plant effluent releases and did not alter the existing environmental impact.. Therefore, no unreviewed safety or environmental. questions are involved. 87-9991 A flow element on_the Drywell' Leak Detection' Cooler Condensate Monitor-read ~.9 to 2.1 GPM with no actual flow. ^T he high reading .was caused by air flowing backward through- the flow element. Since this ' reading- was conservative it did not create-a~new safety-hazard to _the plant nor did it-' affect- the safe' shutdown of the reactor. The-deficiency did not change.the plant effluent- releases ~ and did not alter the existing environmental impact. Therefore,- no unreviewed safety ~or environmental questions are involved. i 2
a M i RAfAty Evaluation Description 91 DB- ; 87-9002' It was discovered that basel'ine data obtained; by Startup for a detector in.the North Plant Vent was in error. This Safety Evaluation allowed data._obtained by a Radiation
' Protection Procedure to-be used. The use of the current data did not create a new safety hazard to- the plant nor did it affect the safe shutdown of the reactor. It--did .not- ,
change 'the plant effluent releases and did . not alter.the existing environmental impact. Therefore, no unreviewed safety or environmental questionsfare. involved.. 87-9003 It was discovered that baseline data obtained by Startup for the Low Range Noble Gas-Detectors was 'in - error._ ..This. Safety: Evaluation . allowed data ,obtained Jby a , Radiation Protection Procedure to be used. The use of the correct data did not. create a
.new safety - hazard:to the. plant nor did it affect the safe shutdown of-the reactor.' It did not change the plant: effluent ~ releases and did not alter the existing environmental impact. Therefore, no unreviewed safety,or '
environmental questions are involved.. 87-0904 This DR was written to document a discrepancy involving 2 General Electric drawings. This Safety Evaluation determined which drawing . was correct and-rest'ored the -affected trip ' unit to its. as-designed configuration by removing a jumper. Removing the jumper did not create a new safety hazardito.the plant nor did it affect ~the safe' shutdown of the reactor. Correcting the deficiency.did not I change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety ~ or environmental questions are involved. 87-9005 This Safety Evaluation corrected calibration data for Main ~ Steam Line and Off-Gas Monitors. Using the corrected data did not create a new safety hazard to the' plant nor did it affect the safe shutdown 'of the reactor. It did not change the plant effluent releases and did not change- the plant effluent releases and did not alter the exiscing~ environmental impact. Therefore, no unreviewed safety or environmental questions
.are involved.
T 3
w: ;
-Safetv' Evaluation DescrJption 91 DE 87-9996 It was discovered that baseline-data obtained.
by Startup for Liquid'Radwaste Monitors _was in error. This! Safety: Evaluation. allowed data obtained- tn( a Radidation Protection Procedure-to be used. The use"of the. correct data -did not create a new safety hazard to-the plant.nor did it affect the safe shutdown
! of the reactor. .It did not change the plant effluent releases and =did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved.
87-9998 A non-adjustable temperature, switch on ' a Control Room Chiller was set at 219 degrees . F.- The required setpoint is 291 degrees F + 11 degrees F. .This Safety Evaluation determined that the higher setpoint viscosity than that specified by the vendor and did not-create a new safety hazard to the plant nor-did it affect. the safe shutdown of ;the reactor. The deficiency did not change .the plant effluent releases and did not alter the existing environmental impact. Therefore,:no unreviewed safety.~or environmental questions are involved. 87-9915 The Preoperational Test Procedure for the Solid Radwaste system pump provided for baseline" data to be taken. The data was properly taken and all, data.'is acceptable; however, the data sheets.do not' indicate what data corresponds to each pump. .This Safety Evaluation determined that this data format did not create a new safety. hazard to the plant nor did it affect the safe shutdown of' the reactor. The deficiency did not. change the plant effluent releases and did not alter l the existing environmental impact. Therefore, no . unreviewed safety or environmental questions are involved. ,
4
' Safety Eyaluation Description ni DB-c 87-8816 Cables terminated. atL a Standby 1 Diesel Generator Jacket Water Heater' exhibited outer jacket feracking. fThis Safety _ Evaluation determined ~ thatthe cracking was caused by-the cables. being' bent. The: bending was corrected; therefore this. deficiency.did.not create a new safety hazard to:the-plant. nor-did it- affect the safe shutdown of the reactor; It did not- change .the~ plant-effluent releases and did not alter the existing environmental impact._-Therefore, no unreviewed safety or environmental questions are. involved.
87-9817 A differential pressure switch onia Standby.
~
Diesel Generator was not functioning, nor was-a replacement switch'available.. _The Safety Evaluation determined that the switches sole' function was to operate the Fuel' Oil Filter Differential Pressure 'High Annunciator window, this' deficiency did not create a new-safety hazard to the' plant nor did it-affect the safe shutdown of the reactor. It did not change the plant effluent-releases _and did not -alter the' existing environmental-impact. Therefore, no unreviewed -safety. or-environmental questions are involved. 5
.Safst,y Eypluation Power Assensign Test Ebanges B-1-HPCI-MSE-0474 This Power Ascension Test Change distinguished between the High Pressure Coolant Injection and Reactor Core Isolation Cooling systems controller tuneup and demonstration tests. It also revised the High Pressure Coolant. Injection system performance charts. It did not create a safety hazard to the plant nor did it affect the safe shutdown of the reactor. The test change 'did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. B-1-ZZXX-MSE-0475 This Power Ascension Test Change allowed the performance of the Shutdown from the outside of the Control Room Test in any test condition. This- did not create a safety hazard to the plant nor did it affect the safe shutdown of the reactor. The test change did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. H-1-XXZZ-MSE-0477 This Power Ascension Test Change allowed the performance of- the Loss of Offsite Power Test in Test Condition 2 or 3. This did not create a safety hazard to the plant nor did it affect the safe shutdown of the reactor. The test change did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. H-1-ACXX-MSE-0479 This Power Ascension Test Change allowed the initial Turbine-Generator testing to be conducted at up to 10% power. This did not create a safety hazard to the plant nor did it affect the safe shutdown of the reactor. The test change did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. 1
f ,,
.J r
Safeh Evaluation PsyaI Assensisa Test Changes
~
H-1-BJXX-MSE-9483- This Power-Ascension Test Change delayed the second' High Pressure Coolant- Injection System Cold . Quick Start Test until Test
, , Condition 6.- This:did not' create.a safety
~
. hazard to .the plant nor did it affect;.the safe shutdown of the: reactor. The test' change 'did not change the plant- effluent 3 releases and .did not alter .the existing ~ environmental impact. Therefore, . no 4 unreviewed safety or environmental questions are' involved. H-1-BFXX-CSE-8492 This Power Ascension Test Change allowed the Control Rod Drive Flow Control Valve. Testing - , to be performed by an Operations procedure, than under the Power Ascension
~
rather program. This did not create a . safety-hazard to the plant ^nor did it affect the safe shutdown of the -reactor. The test change did not change the plant effluent j releases 'adn did not alter'.the existing.-
- environmental impact. Therefore, no unreviewed safety or environmental question are involved.
1 1 1 i f I i i 1 3 i A}}