ML20207R887
| ML20207R887 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 12/31/1986 |
| From: | Gucwa L GEORGIA POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| SL-2076, NUDOCS 8703180255 | |
| Download: ML20207R887 (79) | |
Text
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i TABLE OF CONTENTS Pyr.L Introduction 1
SRV Challenges for 1996 2
Design Changes and Test or Experiment.
Plant Design Changes (Safety-related) 3 Test or Experiment Request 67 Data Tabulations and Unique Reporting Requirements Occupational Personnel Radiation Exposure Reactor Coolant Chemistry Summary
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INTRODUCTION Edwin I.
Hatch Nuclear Plant is a two unit facility located approximately 11 elles north of Baxley, Georgia on U.S. Highway 1.
The plant consists of two Light Water Reactors licensed to operate at 2436 MW Thereal power each.
Electrical Maximus Dependable Capacities for 1986 were 750 MW for Unit 1 and 761 MW for Unit 2.
General Electric Company furnished the Boiling Water Reactor Nuclear Steam Supply System and the Turbine -
Generator.
The plant was designed by Southern Company Services, Inc.
with assistance provided by Bechtel eower Corporation.
The condenser cooling method employs forced draft cooling towers and circulating water systees with normal makeup drawn from the Altamaha River.
The plant is a co-owned facility with ownership delegated as follows:
Georgia Power Company 50.1%
Municipal Electrical Authority of Georgia 17.7%
City of Dalton, Georgia 2.2%
Oglethorpe Electric Membership Corporation 30.01 Licensing information for the units is as follows.
Unit 1 Unit 2 Docket number 50-321 50-366 License issued 0B/06/74 06/13/78 (DPR-57)
(NPF-5)
Initial criticality 09/12/74 07/04/78 Initial synchronization 11/11/74 09/22/79
. Commercial operation 12/31/75 09/05/79 Georgia Power Company has sole responsibility for overall
- planning, design, construction, operation, maintenance and disposal of the plant.
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3RV Challenges for 1996 UNIT 1 E.Alf.
VALVES ACTUATED 05-21-06 1921-F0134, B, C, D, E,F,6,H,J,K,L UNIT 2 No Challenges l
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D: sign Chcngo R;qu0sts and Tcct er Espcric;nt Rcqucsts Pursuant to 10CFR50.59, the following is a brief description of changes ta Safety Related systees and components, tests of the safety evaluation of each for performed, and a summary
- 1986, This sueeary addresses the three criteria used to determine if a proposed change or test involves an unreviewed safety question, i.e 1.
If the probability of occurrence or the consequences of an accident or ealfunction of equipeent important to safety previously evaluated in the FSAR say be increased.
2.
If a possibility for an accident or salfunction of a different type than any evaluated previously in the FSAR say be created.
3.
If the margin of safety as defined in the bases for any Technical Specification is reduced.
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DESIGN CHANGE REQUESTS78-256 Provide sore reliable timers to be used for load shedding and sequencing during a LOCA or LOSP energency.
1.
The principles of the load shedding and sequencing during a LOCA or LOSP energency remains unchanged.
2.
There are no new modes of failure introduced as a result of this design change.
3.
There are not any safety limits affected by this change.78-345 Modify the logic to IEll-F068A so that the valve will operate when the "A" loop of RHR S.W. is being fed from
'the "B" loop pumps, and so IEll-F0688 mill operate when the "B" loop of RHR S.W. is being fed from the
'A' loop pumps.
1.
This will actually reduce the existing modes of failure since the system would then operate according to the original intent.
2.
This change is covered under the original design analysis.
3.
The margin is increased since the system will now operate properly should the crosstie need to be used.78-359 Modify the interlock on the drywell personnel air lock Rev. I doors to eliminate the possibility of personnel being trapped inside the drywell or the airlock.
Revision I adds the capability to defeat the air lock interlock from inside the airlock and an annunciator to indicate both doors open.
1.
The modification does not change the operation of the airlock doors.
2.
The operation of the airlock doors does not change.
3.
Operation of the personnel airlock is not affected.
4
79-095 Install a saal purge systco on Rcetcr Watcr Cleanup Rev 1.
pecps uhich will provido a continucus cooling catcr supply to the pump seals.
1.
The seal water will be both a clean and a cold source of cooling water.
This saintains cleanliness on the seal rotating
- face, reduces the risk of plugging the seal cooling water
- line, and maintains a stable, low toeperature condition in the seal cavity area under steady state and transient RWCU conditions.
2.
This reduces the possibility of seal failure.
3.
This design change will increase the reliability of the RWCU systes by reducing the potential for RWCU pump seal failures due to inadequate pump seal cooling and unfiltered seal water.79-126 Modify penetrations (25 and X205 to allow leakage l
testing of the contatnment isolation valves in the same
' direction as would be exerted by Post-LOCA containment pressures.
l.
The same type of piping materials as previously used are to be used for this change and the existing mode of failure will not be increased.
2.
No new modes of failure have been introduced.
3.
The same type of material is being used and neither existing node of failure will be increased nor will new ones be introduced.79-134 Modify penetrations X26 and 1220 to allow leakage testing of the containment isolation valve in the same direction as would be exerted by Post-LOCA containment pressures.
l.
The existing modes of failures are not increased due to the fact that the same type piping eaterial is to be used as was previously used.
2.
No new modes of failure have been introduced.
3.
The change is made solely to be able to test valves in the correct direction.
5
80-157 During alert, cccrgcncy or act.ident condittcno, provido Rev. 1 icprovcd canagoccnt inforcotton fer battcr ccerdinatien and response to the plant condtti'q.
1.
These systems are used for monitoring only, and degr'adation of these systees will not effect any safety systems.
2.
These systems are used for sonitoring only, and degradation of these systees will not effect any safety systems.
3.
These systees do not perfore safety functions.80-101 Increase spent fuel storage capacity to allow continued operation without filling the spent fuel pool in the tenediate future.
1.
This change does not vary or affect any esisting
, equipment important to safety.
fatture or accident modes are being imposed on 2.
Now new the plant due to this change.
3.
Based on the response to 1 above, the eargin of safety for the spent fuel racks will be increased due to the sample surveillance programs.81-056 Replace the 0-200ohe btas setting potentiometer with a fixed 2000he resistor for normal operations and re-route the Woodward servo drain from the turbine oil susp to the actuator case drain.
1.
During normal operation at the RCIC turbine the potenticeeter is set at 2000he and " locked" in place, thus replacing the pot.
with a 200ohe fixed resistor does not change the operation of the systes.
By providing a prised hydraulic line there is a reduced chance of systes failure due to air in the line, l
2.
No new modes of failure are introduced, j
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The intent or operability of the RCIC system ts not l
altered.
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7 91-059 Install, ccdtfy, or deleto pipo supp;rts oce IEB 79-014 Rev. 2 d sign rcquiro::nts.
Rcvisten 2 inecepgratcs all 79-014 work for Unit 1.
1.
This change reduces the actual stresses to meet coseitsents in the FSAR.
2.
No new modes of failure have been introduced.
3.
This change increases the margin of safety.81-093 Replace unqualtfied MOV motors and actuators with Rev. 2 qualified ones to meet the requirements of IEB 79-01B.
1.
The replacement sotors and actuators /sotors will be qualified per USNRC IEB 79-OlB requirements for all postulated events.
2.
The operatton of the replacement motors and actuators / motors will not be different from the existing equtpoent.
3.
The replaceeent motors and actuators /sotors will be complying to the same Technical Specifications as the existing equtpsent.91-111 Install switches, transettters, relief valves, solenoid
- valves, additional header and lock to protect against overpressure and to alare low or high pressure in the air supply lines to ADS valves.
Also, provide two
- separate, non-redundant supply lines to all drywell air-operated equipment and provide low pressure and high flow isolations to these lines.
1.
The safety design bases for the drywell pneumatic system are still being eet in the new design.
2.
No new modes of failure are introduced.
3.
The safety function to keep the ADS valve accumulators charged to the proper pressure is actually enhanced by addition of high and low pressure alarms and a relief valve.91-113 Replace actor on main steam line drain valve 921-F019 with a motor that meets all requirements of IEB 79-019 1.
The replacement motor will be qualified for all postulated events.
2.
The operation of the replacement sotor will not be different from the existing motor.
3.
The replacement notor will be subjected to the same Technical Specifications as the existing motor.
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81-124 Prevent nuisanco annunctator 'Cloan-up Syst03 Dischargo Rcv. 1 Pressuro HI/LO' froo +alsoly alarcing in tho esntral race due to normal leakage through 1631-F033 and pressuri:ing the downstrean line.
Install an alare trip relay to lieit the alare to only when a signal is sent to open valve F033.
1.
With the introduction of Alare Trip Unit 1631-N604 to the RWCU system, a nuisance annunciation is elietnated the overall result of which should be a more tieely response to other annunciations by operations personnel and increased safety of the plant.
2.
This modification does not introduce any conditions which could affect system operation or tapair the safe shutdown of the reactor.
3.
No Technical Soecification lietts or considerations will be afiected by the addition of this alare trip unit.91-132 Provide environmentally qualified power f eed source and Rev.2 replacement of power
'eed cable with fully qualified cables.
Provide Ha-On analyzers and recorders to meet IEEE 323, 1974 (NUREG-05BB) and IEEE 344, 1975.
Provide new saeple lines for the Ha-On analyzer to have the same generic arrangement as Unit 2.
The post-accident reactor coolant and containment atmosphere saepling system will tap off the new fission products sonttoring sample lines.
1.
The design and installation of the pipe, tubing and valves will be caesensurate with the piping system in which they are installed.
2.
The systee responds exact!' as before as a result of the change.
3.
The valves will be maintLined in the same way as the existing primary containment isolation valves in the plant.91-139 Replace certain existing Engineering Safeguard Trip instrumentation on the RPS, ECCS, and NSSS systees atth l
new analog transmitter / trip Units.
Applicable to Unit I instruments.
1.
The support modifications / additions all have a margin of safety which substantially etceeds design standards.
2.
This change does not introduce any conditions or new eechanises which are not a part of the original design basis.
3.
No Technical Specification eargin is affected.
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91-139 R; place ccrtain existing Engin cr Sefcquard Trip Rov. I instruC ntatiCn on tho RPS, ECCS, and NSSS systcca cith new analog transeitter/ trip Units.
Applicable to Unit 2 instruments.
1.
The replacement equipment will be qualified for all postulated events and provides the saae function as the existing equipment.
2.
The operation of the replacement equipment will not degrade the evtsting togtes.
3.
The replacement equtoeent will be subjected to the same or additional margin as the existing equipment.81-161 Provide replaceeent valves for lonergan and Kerotest valves on nitrogen tank piping and install SU-2 valve.
1.
Presently the valves freeze up and their operation is unreliable after replacement has been accomplished, the safety and reliability of the Nitrogen inerting Systce will be improved.
i 2.
The replacement valves meet or exceed the design specifications of the valves furnished with the systee.
3.
The nitrogen storage tank can be filled more dependably, the overall reliability of the Nitrogen Inerting System will be improved.91-165 Replace existing primary containeert oxygen and hydrogen analyzers and recorders with qualified equipment.
1.
The replacement equipment will be qualified for all postulated events and provides the same function as the existing equipment.
2.
The operation and power requirements of the replacement equipment will not be different from the existing legtes.
3.
The replacement equipeent will subjected to the same Technical Specifications as the existing equipeent.
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81-168 Add annunctation to the Cire.
WStcr Flu 00 Valvos to ccrrect an idantificd petantial singlo failure thich could cause valve IN71-F201 en Unit I
and velve 2N71-F013 on Unit 2 to close on a seismic event.
A closure of either valve will cause a loss of Plant Service Water to essential components.
1.
The modification is preventing an identified single failure which could cause a closure of the valve.
2.
The change does not modify the normal position of the subject valve.
3.
The cperation of the Service Water Systes is not affected by the change.81-174 Provide transtent sanitoring instrumentation on the HPCI/RCIC systees capable of recording systes parameters and responses during systes start-ups.
1.
This will not alter the logic or affect the operation of the HPCI or RCIC systee as described in FSAR Section 4.7 and 7.4.3.2.
2.
The new circuit design will not introduce any new modes of failure.
3.
This will increase the operability and availability of the HPCI and RCIC sy' stems by minimizing and improving trouble shooting and maintenance operations,81-192 Replace existing motors on RCIC/HPCI MOVs with new Rev. I motors to increase the reliability of RCIC/HPCI MOVs.
1.
The replacement motor will be qualified for all postulated events.
2.
The operation of the replacement motor will not be different from the existing motor.
3.
The replacement motor will be subjected to the same Technical Specification as the existing motor.
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91-196 Provido IEB 79-019 qualifications for various Rev. 4 ccepongnts by replacing, rolecating or cedifying thoto components.
t 1.
The-replacement equipment will be qualified for all postulated events and provides the same function as the existing equipment.
2.
The operation and power requirements of the replacement equipment will not be any different fore the existing logics.
3.
The replacesent equipment will be subjected to the same Technical Specification as the existing equipment.92-009 To replace HPCI electric Turbine Trip Solenoid Valve Rev. 2 with
" Target Rock' qualified solenoid valve MPL No.
2E41-SV-F124 on Unit 2 and MPL No. 1E41-SV-F124 on Unit 1.
As well as replace existing lower limit switch on HPCI turbine stop valve with Nasco limit switch MPL No.
2E41-POS-N074 on Unit 2 and tE41-POS-N074 on Unit 1.
1.
The modification does not change the purpose or performance of the system.
2.
The systen responds exactly as before as a result of the change.
3.
The replacement equipment will be saintained in the same way as the existing equipment, i
82-041 Install insulation on Unit 2 drywell hangers where needed and provide tread pads for Drywell areas of high traffic.
1.
The insulation is
'Q', designed for containment use.
I 2.
The insulation is
'Q*,
designed for containment use.
3.
The insulation is "Q', designed for containment use.
i 82-046 Install an overvoltage protector on the output circuit Rev. 1 of each 24/49 volt power supply in the Reactor Manual Control Systee.
I 1.
It does not affect systes performance or response times.
2.
The modification will not degrade any equipment or prevent any system froe functioning as assumed in the FSAR.
3.
This modification will not affect the systen logic, setpoints or response times.
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92-093 Chango. the backcash piping froo Unit I scevico catar strainGrs to chcre it psnetratG9 the east call of the intake structure to 316 stainless steel.
1.
The replacement equipment is identical to the existing equipment (i.e. Limitorque Operators).
2.
The replacement equipment is identical to the existing equipment.
3.
The replacement equipment is identical to the existing equipment.92-165 Change the set cotnt of the RBCCW Surge tank low level switch N04a to 1/2 inch above the alare set point to prevent unnecessary alare activation.
Also adjust the fill rate so that unacceptable leakage can be detected.
1.
This change adds a timer / counter logic circuit which provides a means of detecting unacce: table systen leaks.
2.
This modification will elieinate an annunciation for normal systee operation and will also provide an annunciation *or leaks of unacceptable sagnitude.
3.
This ites is not addressed in the Tech. Specs.92-171 Replace presently installed HFA relays or relay Coil assemblies with new taproved longer-lif e Century series type HFA relays or Century series coil assemblies as recoseended per SIL No. 44 l
1.
The replacement of cotts in existing relays does not i
change the operation of any existing equipment.
f 2.
No system operation is modified.
3.
After replacement of the coils, the relays will have longer life coils and this will increase system reliability.92-187 Replace the existing Square D RCIC Lube Gil filter differential pressure switch with a ITT Barton or equivalent switch.
1.
No control function is associated with the device that l
could affect the perioreance of safety related equipment.
2.
This does not change the results of any accident 1.
analysis presented in the FSAR.
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A sore reliable seans of sonitoring the RCIC lube oil f
filter differential pressure is provided.
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82-230 Install nscessary intcrlocks to prohibit travol of the Unit 2 reactor building overhsad crano trolley over the Units 1 and 2 spent fuel pools.
1.
The probability of the occurrence of a load drop accident impacting and damaging spent fuel will be reduced.
2.
No new modes of iailure are introduced.
3.
This proposed change will provide interlocks for automatic implementation of Tech. Spec. Safety sargins rather than depend on administrative controls.82-234 Replace the existing NAMCO Maglock proximity switches, located on the Core Spray Testable check valves 2E21-F006 A and 9, with Honeywell proxieity switches.
1.
This design change does not affect the performance of any safety-related systen and therefore does not change the results of any accident analysis presented in the FSAR.
2.
No control function is associated with this device that could affect the performance of safety-related equipment a
3.
A eore reliable means of monitoring the Core Spray testable check valve disk position is provided.82-257 Install, modify, or delete pipe supports per IEB 79-14 Rev. I design requirements for all Unit 2 79-14 work.
1.
This change reduces the actual stresses to meet the j
coseitsents in the FSAR.
2.
No new modes of failure have been introduced.
3.
This change increases the margin of safety.
consercial grade oxygen analyzer for routine 83-043 Install a
containment atmosphere saepling.
Install a single pen recorder in the main control room to provide indication and recording of oxygen concentration.
1.
This modification provides redundant sampling capability and say be isolated in case of equipment malfunction by two class IE isolation valves.
2.
No new failure modes of the sampling system are l
introduced by installation of this modification.
l 3.
The equipment installed for this modification is not safety related beyond systes isolation valves.
This equipment is not required for safe shutdown.
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03-091 Provida isolation dacpgrs in the concan line to the SB6T filtsrs to provido cvsrprossure protcction fer 596T in case of a LOCA.
1.
This change protects equipment important to safety by providing redundant isolation daspers.
2.
The systes design function will not be affected.
3.
This change enhances plant safety.
i 83-105 Add pressure / vacuum compensation enhancement kits to
/
existing Kaman wide range effluent monitors for the
/
main stack and reactor building vent 'plenue.
1.
The modification does not charge the purpose or performance of the system.
7 2.
The system responds exactly as before as a result of the change.
/
3.
This change will ennance the capability of assessing radioactivity levels of gaseous effluents, f
83-106 Add pressure / vacuum compensation enhancement kits to existing Kaman wide range effluent monitors for the main stack and reactor building vent plenue.
1.
The modification does not change the purpose or performance of the system.
2.
The system responds exactly as before as a result of the change.
3.
This change will enhance the capability of assessing radioactivity levels of gaseous effulents93-118 Replace existing 6.E.
' Reactor. Vessel temperature recorder with a L k N 250 Speedonax recorder.
l 1.
The replacement equipment will not alter or affect the system's ability to meet its design conditions.
/
2.
The replacement equipment will perfore the same function as the existing equipment.
I 3.
The equipment is not addressed in the Technical Specifications.
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83-123 P;r Colt Industries recoCC3ndation, PGOSv0 the cylindse relief valvss froa D/G's 1A, 19, 1C and 2A.
Raplace with plugs provided by Colt Industries.
1.
The replacement equipment will be qualified for all postulated events and will be more dependable than the existing equipment.
2.
This change does not affect the perforeacne of any safety related systees.
3.
The replacement equipment will be of a higher quality and dependabtlity than the existing equipment, and the Technical Specifications are not changed.
.83-139 Provide a one hour fire barrier for safe shutdown cableways to cosply with sodifications for 10 CFR 50 Appendix "R*.
1.
The addition of a one hour fire barrier will not change the operation of any essential systems.
2.
No basic design intent has been changed.
3.
No systes operation will be affected.83-140 Provide a one hour fire barrier for safe shutdown cableways to comply with modifications for 10 CFR 50 Appendix "R".
1.
The addition of a one hour fire barrier will not change the operation of any essential system.
2.
No basic design intent is changed.
3.
No system operation will be affected.
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l 83-141 Provide a one hour fire barrier 4or safe shutdown cableways below the 130' elevation of the Reactor j
i Building to comply with modifications for 10 CFR 50 l
Appendix "R".
1.
The addition of a one hour fire barrier will not change the operation of any essential systems.
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No basic design intent has been changed.
3.
No systees operation will be affected.
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83-156 Raplaco pre 2Gnt HPCI/RHR tocosrature escordar with a Le:ds & N:rthrup ccdal 250 olsctronte rsecrdsr.
1.
The recorder replacenent has been reviewed to ensure the structural adequacy of the recorder installation detrils and to ensure the recorder replacement does not affect the seissic qualification of MCR panel 2Hil-P614.
2.
The replacement recorder is of equal quality to the previously installed equipment.
3.
The new equipment is subject to the same Technical Specification as the previously installed equipment.83-167 Provide for autoratic closure of containment atmosphere purge and vent valves on a high radiation signal.
1.
This change will decrease the probability of radiation releases without affecting existing safety features of the system.
2.
The system responds exactly as before as a result of the change.
3.
System reliability ts enhanced by not relying on operator action and indirect isolation signals.83-214 Add a 2 second time delay between the HPCI LOCA initiation signal and the auto closing of HPCI Pump discharge return to CST valve, IE41-F008.
1.
The valve will still close before 30 seconds, the earliest time for which credit is taking for the operation of the systen.
2.
Basic operation of the system will remain the same.
3.
This ensures that the Technical Spec 14ication safety eargins remain unchanged.
A change to the Technical Specifications will provide for the proper functioning l
of the time delay relay.
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83-218 Provida cooling cater piping to the Unit 2 RHRSW pucp cetors that aill not expcricnco floo restricticns duo to rust, siltation, etc.
1.
Changing the piping from carbon steel to stainless steel will help elisinate pipe fouling.
2.
The RHRSW system will not be degraded.
3.
These changes are being implemented to enhance the performance and reliability of the RHRSW and PSW systems.83-219 Branch a partial water riser off of Unit 1
Fire Protection "atn inside of Unit 1 Torus.
This riser is to be used for the new Reactor Building sprinkler systems to casoly with Appendix "R"
coseitsents 1.
This is a seismically supported systes design to preclude damage to any equipment in the Reactor
' Building following a seismic event.
2.
This change constitutes a change to the document titled
" Evaluation of the Hatch Nuclear Plant Fire Protection Program" which is referenced in the FSAR.
this document will be revised to reflect the change.
3.
Overall margin of plant safety will be increased due to the addition of the partial header system.83-220 Install a partial water riser systen for the Unit 2 reactor building sprinkler systen to comply with Appendix "R" commitments.
1.
This is a seiseically supported systes designed to preclude damage to any equipment in the Reactor Building following a seismic event.
t 2.
This change constitutes a change to the ducument titled
" Evaluation of the Hatch Nuclear Plant Fire Protection Program" which is raferenced in the FSAR.
3.
Overall margin of plant safety will be increased due to the addition of the partial header system.
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83-223 This DCR involvco tho additico of safo shutdctn corptncnts IEll-F0179, IE11-F0079, and IE11-N012B to the remote shutdown s'stes to insure compliance with the requirements of 10 CFR 50 Appendix
'R'.
- 1. - The addition of certain safe shutdown components to the remote shutdown system will not change the operation of any existing safety systes.
2.
No basic design intent is changed.
3.
No existing systee operation will be affected.83-224 Make modification to certain components associated atth high h
low oressure systee isolation to insure compliance with 10 CFR 50 Appendix R.
1.
No baste destgn intent has been changed and additional protection is provided against salfunction.
2.
No baste design intent has been changed.
3.
No systen operations will be af f ected.83-226 Protect certain cables located in the Reactor Building Rev. I with a one hour fire barrier.
The raceways to be protected are a follows 2E17421, 2E27469, 2E27473, 2E27473, 2E27475, 2E27476, 1.
The addition of a one hour fire barrier will not change the operation of any essential systees.
2.
No basic design intent is changed.
3.
No systees operation will be affected.83-230 Provide access barriers to control room back panels.
1.
The seismic criteria used for implementing this destqn change is considered adequate.
2.
The installation of the doors will not affect the I
(
l safety of the panels or any other safety related equipment in the area.
3.
The addition of the doors will not present a new hazard to fire protection since they are of a wire mesh type.
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93-234 This c:dificaticn is fer protecticn of certain elcctrical Gquipecnt in tho R2acter Building, froa propas d firo sprink1cr systoco to b3 instclicd into the area.
- 1. - The protection o+ certain electrical equipeent will not change the operation of any essential systems.
2.
No basic design intent is changed.
3.
No system operation will be affected.93-235 This modification is for protection of equtpoent from damage caused by actuation of fire protection systees required to meet the requirements of 10 CFR 50 Appendix
'R".
1.
This change provides protection for safety related and Appendix
- R" required equipeent against sprinkler actuation and thus increases plant safety.
2.
The modification does not have any affect on systen operation and all modifications have been analyzed for all accidents described in the FSAR.
3.
All Technical Specification requirements are being met and systes reliability is being increased.93-236 Install new supports and sodify existing supports for Rev. I conduits and/or cable trays as required due to the installation of fire barrier material and to support any circuits which are rerouted.
Locations per this DCR work are Unit 1 Reactor Building elevation 130*-0" conduits and cable trays.
analyzed / designed to withstand all static 1.
Supports are and seismic loads.
2.
The systee operation is not affected by this scope of work.
i 3.
The margin of safety is not affected as defined in the l
Technical Specifications.
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93-237 Install nco suppcrts and c dify oxisting cupparts fcr ccnduits and/or cablo trays as rcquircd to supp:rt additianal Icad en tha cquipicnt due to tho installation of fire barrier material and to support any circuits which are rerouted.
Unit 1 Control Building elevation 112', 130', 600 volt Seitchgear Room (130')
4160/600 volt Transformer Room (130')
Annunciator Room 130' and RPs Battery Room (130')
conduits and cable trays to insure compliance with the requirements of 10 CFR 50 Appendix R.
1.
These modifications are being implemented to Saintain the margin of safety at the plant due to the increased i
weight of cable wrapping.
2.
The modifications maintain the plant margin of safety as it was before the Appendix R cable wrap.
3.
System operation and design as defined in the Technical Specification is not impacted.83-239 Install new supports and modify existing supports for conduits and/or cable trays as required to support additional load on the equipment due to the installation of fire barrier eaterial and to support circuits which are rerouted in Unit 1 east cableway any conduits and cable trays.
analyzed / designed to withstand all static 1.
Supports are and seismic loads.
2.
The system operation is not affected by the scope of work.
3.
The margin of safety is not affected as defined in the Technical Specifications.93-243 Install a Fire Protection Sprinkler Systee in the east, northwest, and southwest sections of the Reactor Butiding elevation 130' to comply with Appendix R
coseitsents.
1.
The seismic response criteria imposed on this modification meets or exceeds the seismic criteria imposed on existing plant equipeent taking into consideration the location of the modification.
2.
The supports have been analyzed to Seismic ! criteria.
l 3.
Systee operation and design as defined in the Technical Specifications is not impacted.
I 20
83-244 Add a nco firo prottetion sprinklcr systoa to the caot Rev. I arca elevation 158*-0* in tha Unit 91 RGactor Building.
1.
This modification is being implemented to comply with the response to Appendix
'R' to upgrade plant safety.
2.
The structures have been analyzed to ensure the sargin of saf ety is not decreased by the additional loads.
3.
Systes operation and design as defined in the Technical Specifications is not impacted.83-245 Install a Fire protection sprinkler system in the east and west section below (130') elevation Unit 1 Torus area to comply with Appendix R consiteents.
1.
These modifications are being implemented to comply with the response to Appendiu R,
to upgrade Plant safety.
2.
'The structures are analyzed to ensure the eargin of safety is not decreased by the additional loads.
3.
System operation and design as defined in the Technical Specifications is not impacted.83-246 Install new Fire Protection sprinkler systems in the southern and nestern areas of elevation 185*-0' in Reactor Building 41.
1.
This modification is being implemented to comply with the response to Appendix R to upgrade plant safety.
2.
The structures have been analyzed to ensure the margin of safety is not decreased by the additional loads.
3.
System operation and design as defined in the Technical Specifications is not impacted.
i 83-248 Install fire protection sprinkler systees in the east Rev. I and west areas of the 130' elevation of Unit 42 Reactor l
Building.
l l
1.
This modification is being implemented to comply with the response to Appendix
'R' to up-g'rade plant safety.
2.
The structures have been analyzed to ensure the margin of safety is not decreased by the additional loads.
3.
Systee operation and design as defined in the technical specifications is not impacted.
l 21 l
83-249 In tall a fire protcetion sprinklcr systoo in tho ncrthcrn half and cast of the 185* clGvaticn Unit 2 Roactor Building.
1.
This modification is being impleoented to comply with the response to Appendix "R"
to upgrade plant safety.
2.
The structures have been analyzed to ensure the margin of safety is not decreased by the additional loads.
3.
Systee operation and design as defined in the technical specification's is not impacted.93-250 Install a fire protection sprinkler systee in the east Rev. I and west areas of the torus chamber in the Unit 2 Reactor Building.
1.
This modification is being implemented to comply with t
the response to Appendix
'R' to upgrade plant safety.
2.
'The structures have been analyzed to ensure the margin of safety is not decreased by the additional loads.
3.
Systee operation and design as defined in the Technical Specifications is not impacted.
{
03-252 Expand the area protected by the existing sprinkler Rev. 1 system to include the Radwaste Lab and Health Physics Supervisor's office on the 130' elevation of the Unit 2 Control Building.
1.
This modification is being implemented to comply with the response to Appendix
'R' to upgrade plant safety.
2.
The structures have been analyzed to ensure the margin of safety is not decreased by the additional loads.
3.
System operation and design as defined in the Technical Specifications is not impacted.
22
93-253 Expand cev rag 3 of the Centrol Building 130* etcvaticn R v. 2 nrrth ctrrid:r systen and conycrt to ect pipa, and conv:rt tho RPS vcrtical cabic cy to est pipo, and relocate sprinkler head to resolve interference with TSI cabletray wrap in the Turbine Building east cableway.
1.
The modification to the existing sprinkler system will provide improved sprinkler coverage and upgrade the fire protection features already provided in the east cableway of Unit 1, elevation 130*.
2.
The modification to the existing sprinkler system will be installed with setsete I supports such that the margin of safety for the existing structure and equipment in the lasedtate area is not decreased.
3.
The modification to the existing suppression systee will allow tt to become sore reliable and effective, so as to increase the margin of safety.83-273 Install new supports and/or sodify etisting supports for conduits load on the equipment due to the installation of fire barrier material and to support any circutts which are rerouted to insure compliance with the requirements of 10 CFR 50, Appendix R.
1.
The support modifications proposed by this DCR ensure the seismic qualification is maintained for the cable tray and conduits supports which eust be wrapped for protection from fire damage.
2.
No new modes of failure are introduced.
3.
This modification will not affect systee operation of any circuits in Raceway with supports modified by this DCR.
23
93-274 Provida Haloa Extinguish:cnt cyctco and Pheto Eltetric 0:tectitn systco fcr pcn21s 2C82-P001A and 2C82-70018 in Unit 2 R;actcr Building 01cvctica 130' to eccply with 10CFP50 Appendiz R.
1.
It has been determined that the seismic criteria imposed on this modification meets or exceeds the seismic criteria imposed on existing plant equipment taking into consideration the location of the modification.
This design change provides additional fire protection.
2.
The structures have been analyzed to ensure the margin of safety is not decreased by the additional loads imposed by the Halon equipment or the associated pipe addition.
3.
An additional reviewed safety eargin is being added to the system.84-011
' Install new fire detection systee in the Unit i Power Rev. 2 Block to comply with fire codes and 10CFR50 Appendix R.
1.
This modification is being implemented to comply with the response to Appendix R to upgrade plant safety.
2.
The structures have been analyzed to ensure that the margin of safety will not be decreased by the additional loads.
3.
Systee operation and design as defined in the Technical Specifications is not impacted.
Increase of loads on the structure due to the system is negligible 84-012 Install new fire detection systes in the Control Rev. 2 Building to comply with fire codes and 10 C~
50, Appendix
'R".
i 1.
This modification is being implemented to comply with the response to Appendix
'R' to upgrade plant safety.
2.
The structures have been analyzed to ensure that the f
margin of safety will not be decreased by the additional loads.
3.
Systes operation and design as defined in the Technical Specifications is not impacted.
l 24
94-019 Install cest:r cultiplex panol end printer in the ccntrol rcea and inctall sicvo pansls and printcrs in the CDs tank area on the 147' elevation of Control Building.
Interconnect the easter and slave printers and connect the fire detection systees.
1.
This modification is being implemented to cosply with the response to Appendix
'R' to upgrade plant saf ety.
2.
The structures have been analyzed to ensure that the margin of safety will not be decreased by the additional loads.
3.
Systee operation and design as defined in the technical specifications is not impacted.84-020 Install new fire detection systes in the Unit 2 Power Rev. 3 Block to comply wtth fire codes and Appendix
'R".
1.
The modification is being implemented to comply with
'the response to Appendix
'R' to upgrade plant safety.
2.
The supports were designed seisaically.
3.
System operation and design as defined in the Technical Specifications is not impacted.84-060 Replace the carbon steel Plant Service Water pumps with stainless steel pumps on an as needed basis.
The pump
- bowls, wear ring, seal
- rings, discharge case and suction bell will be stainless steel.
The impellers will remain bronze.
1.
The performance rating is the same as the existing pumps evaluated in the FSAR.
2.
There are no changes by this design which could cause a different type of accident or ealfunction other than those analyzed.
3.
The stainless steel bowls will increase the eargin of safety by increasing the service life of the pueps.
l 25
84-065 R:plcco cn an at-n:cded bacis, th3 carbra st001 purp Rev. 1 bt:1 ass 0;blies eith stainlocs ste:1, cnd a transiticn colu;G to allca tho Unit I and Unit 2 RHRSW purp br:1 assemblies to be identical and interchangeable.
1.
This design change allows for the substitution of components capable of meeting the design requirements as described in the FSAR.
2.
No unanalyzed ' allure eodes are being introduced.
3.
The pump performance remains unchanged.84-066 Replace the carbon steel RHRSW pump bowl assemblies with stainless steel assemblies.
1.
This design change allows for the substitution of components capable of eeeting the design requirements as described in the FSAR.
2.
- No changes in the operation or design of the pumps are being introduced that could cause an unevaluated accident or malfunction 3.
The pump performance remains within the requirements of Technical Specifications.84-095 Install a 1 or 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> fire rated barrier around raceways requiring protection in the Control Building RPS Room (elevation 130'), Containment Building (112')
4160/600 volt Transforeer Room (130'), East & West 600 volt Switch 6 ear Room, Annunciator Room (130'), and Oil Conditioner Room (130')
to insure compliance with 10CFR50, Appendix R.
1.
All raceway systees were evaluated and shown to be l
acceptable regarding cable derating due to the use of the fire barrier saterial.
l 2.
The method of systee operation is not affected.
3.
Safety limits are not affected by this modification, and no changes to the Technical Specifications are required.
l 26
84-086 Inctall a
1-hrur firo ratcd barrice around racc:ays rcquiring protcctica in ths East Cabicscy (olcvatten 130')
to insure complict:co cith th3 rcquircCOsts ftr 10CFR50 Appendia R.
1.
All - raceway systees were evaluated and shown to be acceptable regarding cable derating due to the use of the fire barrier eaterial.
2.
The eethod of systee operation is not affected.
3.
Safety limits are not affected by this modification, and no changes to the Technical Specifications are required.84-087 Provide fire protection as required by wrapping cable trays and condutt with a 1-hour fire rated barrier for the Reactor Building elevation E7*.
1.
All raceway systees were evaluated and shown to be
- acceptable regarding cable derating due to the use of the fire barrier eaterial.
All raceway supports have been seismically analyzed and sodified as necessary to satisfy the load requirements imposed by the additional weight added by the fire barrier saterial.
2.
The method of systee operation is not affected.
This change only involves protecting the raceway systees.
3.
Safety Itaits are not affected by this modification, and no changes to the Technical Specifications are requireo.84-098 Remove 50 AMP trip element from Unit 2 switchgear 2R23-S003 Fr.6T and sake necessary adjusteent such that the instantaneous trip point will be equal to that of the present 40 AMP trip element used in the feeder breaker to the RPS MS Set 9 of Unit 1.
1.
The replacement trip element will be set the same and its operating characteristics are the saae as the original element.
2.
The replacement trip element carries the same mode!
number and qualification criteria as the original component.
3.
No Technical Specification limits or lietting safety systen settings are being changed.
27
84-112 R;placo Turbino Building Stcan Leak 0:tcetica cinitcrs cith solitors having built-in tcct cq3ip;cnt capchio cf simulating input signals for each thcrc ccepto and tripping alare logic.
1.
The replaceeent instrueents will not degrade the response of the RPS 6 RPV isolation systee.
2.
This modification will not introduce any failure sechanises which were previously unantteipated or any events not bounded by the FSAR.
3.
No margin of safety is affected.
The bases of Technical Specifications 3/4.3.2 ensures the effectiveness of instrumentation perforetng isolation of reactor systems.84-124 Replace the existing Rectre Pumps temperature recorder with a state-of-the-art design recorder.
1.
The replacement equipment will not alter or affect the
'systees ability to eeet its design conditions.
2.
The replacement equionent will perfore the saae function as the existing equipeent.
The replacement recorder is setseically qualified and is to be sounted seismically.
3.
The equipment is not addressed in the Technical Specifications.04-125 Replace existing Rectre M6 Set, generator and drive actor temperature recorder with a Leeds & Northrup model 250.
1.
The replacement equipment will not alter or affect the systee's ability to meet its design conditions.
2.
The replacement recorders are 1eismically qualified and are to be sounted seismically.
The replacement equipment will perfore the same function as the existing equipment.
3.
The equipeent is not addressed in the Technical Specifications.94-195 Replace esisting SRV Tail pipe temperature recorder eith a Leeds & Northrup model 250.
1.
The replacement equipeent will rot alter or affect the systems' ability to meet its design conditions.
2.
The replacement equipment will perfore the same function as the entsting equipment.
The replacement recorder is seismically qualified and is to be sounted seismically.
3.
The equipment is not addressed in the Technical Specifications.
28
84-200 M;dify tha ADS initiation Icgic in rcspenso to NURES-0737 ites II.K.3.18:
Byp0:3 ef tho high dry;oll pressure per0tssive aftcr a sustaincd Ico reacttr catcr level and addition of a manual inhabit switch.
1.
The same conditions that caused ADS to initiate before (low RPV level
+ high drywell pressure + ECCS pumps running) will initiate ADS.
2.
Ne new eedes for ADS failure have been introduced.
3.
The intent of the ADS systee has not been changed.84-204 Terminate LPCI !nverters (IR44-5002 and Rev. I 1R44-S003) output power cables directly on ector control centers (R24-S0184, R24-S0199) hortrontal bus, thus eliminating the MCC feeder breakers.
Add manual disconnect swttches in circuit for personnel safety.
1.
The circuit breaker being replace is not functionally
- required.
2.
The not effect util not reduce the number of critical components in the motor control center power circuit.
3.
No change relattve to the Technical Specifications is proposed.94-205 Replace entsting narrow range forus level Rosecount l
transmitters with new Rosecount transettters which are qualifted to 24 m 10* R radiation exposure.
1.
The replacement equipeent will be qualified for all postulated events.
2.
The operation and power requirements of the replacement equipment will not be different froe the esisting logics.
l 3.
The replacement equipeent will be subjected to the same Technical Specification as the entsting equipment.
i 1
f i
29
84-219 Replaco th9 felle ing cabico frco iT47-TE-M003:
K104F-ES0-C025 and circs 9A,99,9C,9S cf cablo Hil-F654-ES0-C213 with a cablo ccda N07 using saae tereination points.
For IT47-TE-N009 replace cable Hil-P651-ESS-C232 wires 134,138,13C,13S with a cable code N07 using same tereination points.
1.
The replacement cable has documented evidence of radiation and temperature tolerance better than the material now being used.
2.
The basic destgn intent is not changed.
3.
The replacement cable has a higher documented safety margin than the entstang cable.94-252 Provide a new HVAC system in the CDs tank room using service water oor a heat sink.
This is a requirement of the new multiplex fire detection system installed
,for 10CFR50.48 and Appendix R.
1.
The HVAC unit is seismically sounted and qualified and the service water piptng is setseically supported.
2.
The safety 8 unction of the plant service water systes is not affected by this change.
3.
This change does not affect the Technical Specifications.84-259 Add a wall and set of double doors to contain the air free the HVAC system which will be installed under DCR 84-252.
1.
This modification is being implemented to comply with the response to Appendix R to upgrade plant safety.
2.
The modification maintains the plant margin of safety as it was before the wall addition.
System operation will not be affected by this change.
3.
The margin of safety as defined in the Technical Specification is not impacted.94-277 Modify cable EEE805Cl4 for RCIC MOV 2E51-F007 to meet Rev. I the separation requirements of Appendix R.
1.
The rerouting of certain safe shutdown circuits will not change the operation of any essential systess.
2.
No basic design intent is changed.
3.
No systees operation will be affected.
30
84-322 Change existing MSIV d; sign to rcficct a nco osin ptppet decign eith an elongatcd naso to Iccato tha poppet for proper sealing ar.d additional stoliito en poppet to allow future machine work.
The change also includes a self aligning pilot poppet with stellite #21 on 'the seat and guiding surfaces.
Included in this change is and anti-rotation device.
i 1.
The MSIV design is being improved by providing better guides for the sain and pilot poppets.
2.
The basic MS!V design remains the same.
3.
The basic MSiv design remains the same.
B5-054 Replace the RPS auto and manual scras relays (model Rey. 1 CR105D102 GE contactor) with an improved model.
new contactors are of the same type & size as the 1.
,The existing contactors.
2.
There is no change in any system function.
3.
There is no change in any system function.85-067 Add roofing eaterial to existing roof on Unit 1 Service Building, Unit 1
& Unit 2 Turbine Building, Control Building, Unit 1
% Unit 2 Reactor Building, Unit 1 &
Unit 2 Radwaste Building, and Hot Weld Machine Shop.
1.
The additional roof loads have been checked and were found to be acceptable, therefore plant safety is not affected.
2.
The change does not have any affect on system operation and all changes have been analyzed for all accidents described in the FSAR.
3.
The additional loads have been checked and all Technical Specification requirements are being set.
31
85-072 R place cnisting centrol valvoc en filtcr trein dolugo systco cith c nitcrablo rising stoo valvoc.
1.
These redundant valves are not required by NFPA codes nor discussed in the FSAR.
2.
Indicating valves are provided and these redundant valves are being removed.
3.
Indicating valves are provided and these redundant valves will be removed and replaced with the same class of pipe that is attached to these valves now.95-092 Change setpoints and/or Technical Specification limits as required to facilitate installation of Barton or Rosesount transeitters in ATTS applications on Unit 1.
1.
The trip setting was developed using the criteria of Regulatory Guide 1.105 and.
- thus, also meets the
, criteria of Hatch 1 FSAR.
2.
The high drywell trip function factions resulting from this signal) are the same.
3.
The new trip setting is such that the actual drywell pressure will not exceed 2.0 psig before ESF actuation.
l l
32 e
85-094 Changa s:tpoints and/cr Tcchnical Specificatien licits as rcquircd to facilitato inctallctica of 8:rtcn er Rosecount transeitters in ATTS (pplicatiens en Unit 2.
1.
The change is consistent with the basis for Plant Hatch Analog Transeitter Trip System setpoint calculations that the NRC has previously approved in Technical Specification seendeent 39.
2.
The change does not modify either the function of the instruments nor does it affect the design basis from which the Technical Specifications were developed.
3.
The basis ' rom which the Technical Specifications were developed has not changed.85-095 Change ATTS Barton transeitters to Rosecount transmitters.
Also change originally installed Rosemount to new Rosemont on a case by case basis when
,an original transeitter fails.
1.
The replacement transmitters are environmentally and seismically qualified so the probability or consequences of a malfunction will not be increased.
2.
This modification will not introduce any failure mechanisms which were previously unanticipated or any events not bounded by the FSAR.
3.
The bases for Technical Specifications 3/4.3.1, 3/4.3.2 and 3/4.3.3 ensure the effectiveness of instrumentation that input signals to RPS, isolation of reactor systems and ECCS respectively.
The response time of the high drywell trip function is less than specified in the Technical Specifications.85-100 Provide additional lighting for remote shutdown panels, new post fire pathways and manual action stations to comply with 10 CFR 50 Appendix R.
1.
The lighting branch circuits are fed free circuit breakers dedicated for lighting only, and will not affect equipment important to safety.
2.
No basic design intent is changed.
3.
No systee operation will be affected.
33
85-102 Provido additional lighting fer reesto ehutdcen panols.
N30 post firo pathcays and cacual acticn stationo to ec ply eith 10 CFR 50 App;ndin R.
1.
These modifications are being implemented to comply witk the response to Appendin R to upgrade plant safety.
2.
This change will upgrade plant safety by providing the additional lighting needed in event of loss of power.
3.
The eargin of safety is not affected by the electrical or civil work as defined in the Technical Specifications.85-105 Replace the present Fission Product Monitoring system with the General Electric NUMAC systee.
i 1.
The new NUMAC radiation sonitor is functionally equivalent to the existing sonitor and will perform all
, rocess radiation sonttoring requirements.
p 2.
The NUMAC is an upgraded functional replacement and will not change any operational parameters.
3.
The replacement NUMAC sonitors will provide the same protection as the existing monitors and will not reduce the margin of safety as defined in the Technical Specifications.
t 85-106 Install RTD's in entor stator windings for temperature seasurement.
Upgrade stator winding insulation from IEEE class 9 to IEEE class F.
1.
The proposed modification will improve the entor insulation and provide actor stator temperature indication.
l 2.
No basic design intent has been changed.
3.
No basic design intent has been changed.
Modification improves reliability of the safety system.85-110 Modify existing Main Stack and Reactor Building vent radiation detectors to monitor ganea energies greater l
than 80 Key by installing new detectors with vendor supplied modification kits.
1.
The replacement will be qualified for the same postulated events and provide the same function as the existing equipment.
2.
The replacement is functionally identical to the previously evaluated existing equipment.
3.
The replacement equipment will be subjected to the same Technical Specifications as the existing equipment.
34
T 95-111 Install r:d group 1,2,3 6 4 palet scran ssicacid indicatir.g lights fcr cha:ncis A&8 ca pcnst 1H11-P603.
1.
This will prevent an inadvertent full-scras signal, hence it increases the systes reliability.
2.
There is no change in any systee function.
The lights are only for indication.
3.
There is no change in any system function.85-119 Detereinate circuits 1R24-S022-ESB-C188 and 1R24-5022-ESB-C18A free conductors V15 V17 respectively.
Reroute wiring by pulling new cables 1R24-5022-ES8-C18F and IR24-S022-ES8-C196.
1.
The logic of the RHR shutdown cooling valves remains unchanged.
New wiring routes for Fire Protection will not affect the logic.
2.
- No logic changes are being sade to the plant.
3.
The DCR is implemented in the cold shutdown or re4ueling sode.
Also, proper valve position sust be se:ured when shutdown cooling is required.85-120 Induction Heat Stress leprovement shall be used to eitigate future 16 SCC en unflawed stainless steel welds, or used a a repair eethod on welds with shallow flaws.
Weld overlay repairs will be used on welds with flaws of unacceptable depth.
1.
The application of the weld overlay provides reinforcement of piping at flawed locations, so that design margins are maintained or improved.
Induction Heat Stress leprovement (IHSI) is applied to weldsents in stainless steel piping to convert the residual welding stresses from tension to compression and thereby eliminate one of the critical factors that l
promotes !GSCC, 2.
The application of a weld overlay makes the affected location less susceptible to failure.
3.
Code design margins are maintained or restored by the weld overlay.
i 35 l
85-149 R:placo cuisting sanitors 1011-K601, 2011-K601, 1011-K603A-0, 2Dil-K603A-D cith NUMAC (6:0Cral Electric) log radiation monitors.
1.
The new NUMAC radiation sonitor is functionally
' equivalent to the entsting sonitor and will perfore all process radiation sonitoring requirements.
2.
The NUMAC is an upgraded functional replacement for the INMAC and will not change any operational parameters.
The NUMAC weighs the same as the INMAC and has the same qualifications.
3.
The replacement NUMAC sonitors will provide the saes protection as the entsting monitors and will not reduce the eargin of safety as defined in the Technical Specifications.85-161 Modify all MS!V's to acconnodate a larger 2* diameter
,stee.
1.
Operability of the MS!Vs' will not be altered by this change. Valve service life will be increased.
2.
No new modes of failure will be introduced by this design change.
3.
MSIVs closure time as required by the Technical Specifications remains within the required limits.85-163 Relocate starter for valve 2 Ell-F017A from MCC 2R24-S0ttA to 2R24-9011 and reroute associated cables through protected raceways to comply with Appendin R.
1.
The relocation of starters will not alter the operation of any essential systees.
2.
The system will respond exactly as before the change since no systems operation will be affected.
3.
The system operation will reeain unchanged and the eargin of safety will be increased aDove that which currently entsts in the plant.
1 36 i
95-164 Upgrad] south call of oil condittoatng rosa feto 2-hr Rev. I to 3-hr fire rating to comply cith App;adin R.
1.
These modifications are being implemented to comply with the response to Appendia R to upgrade plant safety.
2.
The walls were analyzed to ensure the additional weight free the fire proofing coating would not cause any structural overstresses during a setseic event.
3.
The margin of safety is not affected as defined in the Technical Specifications.85-165 Provide fusing for the 125/250V station battery 1A 6 18 aseeter circutts in the battery shunt bones to comply with Appendin R.
1.
The installation of Suse holders and fuses in aseeter circuits will not a48ect the systee performance.
2.
'Systee operation and performance are not affected as a result of this change.
3.
Safety lietts are not af8ected by this change.95-173 Replace the cable codes N3-04 and N3-19 for containment ateosphere cooling systen toeperature detection for Unit I with qualified cable code N07.
1.
Replacement cable has docueented evidence of radiation and temperature qualification better than the saterial now being used.
2.
No design basis intent is changed.
3.
No system operation will be affected.85-179 Temporary piping and instruments are installed in and around the Unit i Reactor Building in support of a containment integrated leak rate test.
All plant changes done by this DCR are removed prior to plant restart.
1.
This change is teeperary, and will only be in place while the reactor is in cold shutdown.
2.
This change is toeparary, and in support of a test described in the FSAR, and required by the plant Technical Specifications.
3.
This temporary design change request is in sunport of a test (1.L.R.T) specifically required by the Technical Specifications.
37
85-100 Provide cavironeeatally qualificd procsure suitch;s 2P70-PS-N003, and 2P70-PS-2016 03 tha dry:Oli pnO COtic syste3.
1.
The new pressure switches are class lE, environmentally and seismically qualified.
2.
The replacement of presently unqualified subject pressure switches with qualified ones, to comply with Reg. Suide 1.97, is an enhancement for the reliability of the said :oeponents.
3.
They provide improved reliability for the subject low pressure alare circutts.85-191 Add supports as necessary in order to adequately I
support tubing tray for dP switches 2P41-N304Ab8 at strainers 2P41-000iA49.
1.
The placement of additional tube tray supports for the
' tubing for 2P41-N304A and B is to be in accordance with approved instrument installation details for Seismic Class 1
installation and will not affect systee response or operation.
2.
The addition of the new tube tray supports does not introduce any conditions which could affect systee operation or impair the safe shutdown of the reactor.
3.
The tube tray supports are not referenced in the Technical Specifications and no Technical Specification limits or considerations will be affected by the addition of the new supports.95-196 Add decontamination ports to the Unit 1 RWCU drain lines.
1.
The decontamination ports will be designed and fabricated to the original code (USAS 831.1).
2.
The systes design and operation will not be altered by this modification.
3.
The Technical Specifications are not affected by this modification.
t 18
95-197 Add d:conta3tnation pirts to tho Unit i scran discharge vcluco.
1.
The decontamination ports will be designed and fabricated to the ASME Section III Class II.
Therefore, the integrity of the CRD scran discharge headers eill be maintained.
2.
The systes design and operation will not be altered by this modification.
3.
The Technical Specifications are not affected by this modification.85-202 Modify supports 1V-a4H,
- IV4AJ, IV4AK, IV-4AL, tv-ti, IV-tu, tv-4AM, tv-AN, IV-4AR, IV-4AS, IV-4AT, Unit 1 Reactor Building 158' elevation to comply with FSAR design criteria.
1.
These modifications will increase the safety of the
' cable tray by strengthening the cable tray supports.
2.
These modifications will further increase the safety of the cable tray supports.
3.
The cable tray supports are designed to withstand all appropriate seismic and static loads.95-215 Remove spool piece between RPV head and RHR and install a blank flange on the RPV to reduce reactor pressure vessel disassembly time by deleting the RHR head spray mode and associated flanged-in spool pieces.
1.
The head spray has no safety function and its renoval will not adversely affect any safety systee.
2.
Only a section of piping is being removed, thus disabling a systee which was not used.
This removal would actually slightly reduce the possibility of an accident which is evaluated in the FSAR (primary system pipe break).
The head spray performs no function which would be needed to prevent an accident or salfunction nor provide aid if an accident or salfunction occurred 3.
The head spray has no safety function and no credit has been taken for its use in current safety evaluations or energency operating procedures.
39
85-218 ROplaco cuisting EC-2A ovcrcurrcat trip d;vice oith solid state Ccncral Elcctric cicro v;rca cycrcurrcnt trip device on 6E AK25 600 valt, 600 asp. air circuit breakers located in compartments 3M, 38, 4B, 4M, and 7M of 600 volt switchgear IR23-5003.
1.
The safety related
- function, classification, and application of the circuit breaker will not change.
2.
The Micro Versa Trip device incorporates better design and more up to date technology.
Systee operation and performance are not affected as a result if this change.
3.
The installation of the Micro Versa Trip device will not change the safety classification of the switchgear and breakers.85-219 Replace existing EC-2A overcurrent trip device with solid state General Electric Micro Versa overcurrent
' trip device on GE AK25 circuit breakers located 1 compartments 3M, 38, 4M, 49, and 6M of 600 volt switchgear 1R23-5004.
1.
The safety related
- function, classification, and application of the circuit breaker will not change.
2.
The Micro Versa Trip device incorporates better design and more up to date technology.
System operation and performance are not affected as a result of this change.
3.
The installation of the Micro Versa Trip device will not change the safety classification of the switchgear and breakers.85-221 Modify existing GE EC-2A-18 overcurrent trip elements on the 125/250 VOC switchgear 1R22-S016 & S017 to increasing the trip elements spring tension until the desired instantaneous trip set point is achieved.
1.
The safety related
- function, classification, and application of the circuit breaker will not change.
2.
Systee operation and performance are not adversely affected as a result of this change.
3.
Safety limits are not affected by this change.
40
95-23e Rcplace Licitorque cctors eith environcGntal qualificd (EG)
Licitorqu2 cGtors.
Rcplaco circuit breakcro er cable for Licitorquo estcro if rcquirGd.
1.
The environmental qualification of the motors and circuit breaker is to the same level or greater than that of the existing equipment.-
The proven environmental qualification meets the requirements of the accident environment.
2.
This modification conforms to the design bases of the system involved.
3.
The changes to the motors and circuit breaker are to a level of detail not covered in the Technical Specifications.85-242 Provide overcurrent protection for Diesel Generator Battery Charger aseeter circuits in order to comply with Appendix R coneitsents.
1.
'The installation of fuse holders and fuses in the asseter circuits for the protection of the Energency Station Service Batteries and for the protection of possible conson enclosure associated circuit concerns, will not affect the systes performance.
2.
Systee operation and performance are not affected as a result of this change.
3.
Safety limits are not affected by this change.05-243 Cable Tray supports in Unit 2 Reactor Building and Control 3uilding are to be structurally modified.
1.
These modifications will increase the safety of the cable trats by strengthening the cable tray supports.
2.
These modifications will further increase the safety of the cable tray supports.
1 3.
The cable tray supports are designed to withstand all seismic and static loads.
i 85-246 Protect the circuits for valves 1E51-F029 & F031 so that a fire-induced short in the CST area will not result in a loss of the RCIC systen.
1.
The logic 04 the RCIC systee remains unchanged and the addition of the fuse will decrease the probability of a short causing loss of the RCIC Logic.
2.
No logic changes are being sade to the plant.
l 3.
The RCIC system will operate as it did before since no logic changes are being eade.
41
95-259 Install a firo bcrrier catcrial around racceays in tho, D/6 building that rcquiro protecticn pcr Appcndix R.
1.
All raceway systen were evaluattei and shown to be acceptable regarding cable derating due to the use of the fire barrier eaterial.
All raceway supports are analyzed / designed and sodified as-necessary to withstand all static and seismic load requirements imposed by the additional weight added by the fire barrier eatorial.
The method of systees operation is not af[ected.
2.
3.
Safety limits are not affected by this modification, and no change to tre Technical Specification are required.85-260 Add a backup power feed for the control logic for RHR Rev. I pump IEll-C0020.
1.
'The logic of the RHR systes remains unchanged and the addition of a
backup control power supply for IEll-C002D will decrease the probability of a fire causing the loss of that pump.
2.
The FSAR will be revised to show the new energency load on Diesel Generator IB 125 VDC distribution panel.
3.
The addition of a control transfer switch will increase the reliability of control power to Ell-C0020 by providing an auxiliary control power feed.85-261 Replace existing EC-2A overcurrent trip devices with solid state General Electric Micro Versa overcurrent j
l trip devices on GE AK25 breakers located in compartments 2M, 3M, 4M, 4D, and 6B of 600V switchgear 2R23-5003.
I 1.
The safety related
- function, classification, and application of the circuit breaker will not change.
2.
System operation and performance are not affected as a result of this change.
3.
The installation of the Micro Versa Trip device will not change the safety classification of the switchgear and breakers.
j
(
i I
42 L.95-262 Replace cxisting EC-2A overcurrcnt trip devices cith solid state 6:ncral Electric Micro Vcrse trip ov:rcurrent d viccs on SE AK25, 600 Volt, 600 A p air circuit breakers located in compartments 4T, 5T, 78, 7M, and BB of 600 Volt switchgear 2R23-S004.
1.
The safety related
- function, classification, and appitcation of the circuit breaker will not change.
2.
Systee operatton and perforeance are not affected as a result of this change.
3.
The installation of the Micro Versa Trio Device will not change the safety classification of the switchgear and breakers.85-263 Modify the existing GE EC-2A-1B overcurrent trip
, elements on the breakers in 2R22-S016 h 2R22-S017 by increasing the elements spring tension to the new set points to comply with 4ppendix R.
6 1.
The safety related
- function, classification, and application of the circuit breaker will not change.
2.
System operation,ind performance are not adversely affected as a result of this change.
3.
Safety limits are not affected by this change.85-264 Add fuses to the sin Station Battery aseeter circuits required by Appendir R to prevent the possibility of as a fire induced fault that could blow one of the main
' battery fuses.
1.
The fuses and fuseblocks are seismically qualified and will be seiseically installed so as to adhere to the seismic qualifications.
~2.
The blowing of any of these new fuses will result in lost indication of battery supplied current, but will not' affect actual power distribution to the load.
3.
The addition of the fuses in the anneter circutts e
adjacent, to the shunts will assure isolation of the faulted ' circuit and allow the main Station Battery feeds to remain operational.
e 43
85-265 Provide s;parato fusing for CST Ica lovel logic to prevent tho pessibility of a firo-induced failuro cf levol switches 2E41-N002 er N003, er rolay 2E41-K17, (or associated cabling) having an adverse effect on the balance of the HPCI logic.
1.
The modification improves the availability of the HPCI systee in the event of a fire in the vicinity of the condensate storage tank.
2.
No basic design criteria is changed.
3.
The system will resoond exactly as before the change since systen logic is not affected.95-266 Modify valves 2 Ell-F069A%B position sodulator logic so I
that a fire in D/6 switchgear room 2F cannot cause a failure of this valve to throttle automatically.
This change is required for Appendix R compliance.
1.
'The new circuitry will be safety-related and seismically qualified 50 that the qualifications of existing equipment will not be violated.
2.
The modification will not degrade any equipment or prevent any system free functioning as assumed in the FSAR.
3.
This modification will not af f ect the RHR system logic, setpoints, or response times.85-267 Modify suppression chamber high water level logic so that balance of RCIC logic is not affected by fire induced loss of level switch 2E51-N0629 nor cable EEE701C29.
This change is required for Appendix R compliance.
1.
The modification improves the availability of the RCIC j
systen in the event of a fire in the vicinity of level switch 2E51-N0629, l
2.
No basic design criteria is changed.
3.
The system will respond exactly as before the change since systee logic is not affected.
l r
l l
l 44
85-268 Godify control circuit for PSW valvo 2P41-F316B to that the valvo is not adycrsaly affcetGd by a firo-induced loss of cablo PUE805C04.
This chango is required for Appendix R compliance.
1.
The ability of the Plant Service Water (PSW) system to supply cooling water to equipment required for accident conditions is not affected.
2.
The system will respond exactly as before the change since the systee logic was not affected.
3.
No sargin of safety as defined in the basis for any Technical Specification is affected.85-271 SRM/IRM dry tubes (2B11-D191) will be replaced with a redesigned model.
1.
The dry tube replacement will not alter or affect the
, systems ability to meet ortginal design conditions.
2.
This change will not affect the operation of the source range or intermediate range monitor systes.
3.
This change will not affect the operation of the source range or intermediate range sonitor systems.85-280 Replace Limitorque motors with environmental qualified (EQ) Limitorque notors.
1.
This modification involves only equipment replacement and does not alter the operation or function of plant safety systees.
l 2.
This modif f' 3 tion conforms to the design basis of the RHR system and creates no new failure mechanise.
3.
No sargin of safety specified in the Technical Specifications is affected by this modification.
I 45
86-002 Replaco cxisting cotor pinion coro shaft gear and terque suitch lioiter platGs, to icprova tho stroke tica of the RWCU Inboard Isolatien gato valvo 1631-F001.
1.
The' conversion kit to obtain faster closing valve is certified by manufacturer to meet the original construction requirements.
2.
The conversion hit meets the original manufacturing / construction requirement.
The operability of the valve is not affected.
3.
The faster closing valve will result in an increase in margin of safety to meet Off-site / Plant Boundary radiation release requirements.96-004 Modify the D/G's stop and shutdown circuits to isolate the remote trips without losing either the starting capability or the essential protective functions.
This
' change is required for Appendix R compliance.
1.
The proposed sodification improves the availability of the Diesel Generators in the event of a fire in the Cable Spreading Room and in general.
2.
No basic design or design criteria is changed.
3.
No system logic will change; additional fuses will be provided for electrical circuit separation.86-006 Build up lower guide rib of RHR Torus Return isolation
- valves, IE11-F028 ALB with a shin plate to raise valve disc relative to body seat rings.
1.
The change would restore the alignment of the valve disc to original condition.
2.
The change would not affect valve operability and correct alignment of the disc would allow for a acre leak tight alignment for leak testing.
3.
The change would restore the valve disc alignment to f
the original condition to meet Technical Specification requirements of section 3.7.D.
46
-=
B6-010 Provida annunciation of HPCI and RCIC leak dotsetien tic r initiation so that cp; rater acticn cay be takcn before isolation in the cycnt of an crroncous actuatien due to a fire in the Torus Roos.
Required for compliance with 10 CFR 50, Appendix R.
1.
This modification will enhance the steam leak detection systee by providing status indication and has no bearing on the probability of the occurrence of accidents analyzed in the FSAR.
2.
This modification will not introduce any failure mechanises which were previously unanticipated or any events which are not bounded by the FSAR.
3.
The proposed modiiication will not reduce the effectiveness of the instrumentation and will not adversely affect the prescribed functions.86-012 Add fuses to the two energency station service battery charge ammeter circuits to prevent loss of the 125V DC Energency Station Service Batteries due to failure of the battery charger. ammeter circuits.
Required for compliance with 10 CFR 50, Appendix R.
1.
The ability of the charger to supply power to the Diesel Generator system is not affected.
2.
Blowing of the new fuses in the charger aseeter circuits will only lose the indication of the current by the ammeter but will not affect the operation of the charger or power supply to the 125V DC distribution panel.
3.
This modification will not affect systes logic, system operation, set points or response times.86-019 Add spacer behind hinge pin gasket of Feedwater Check Valves to repair steam cuts on body and provide adequate sealing on the hinge pin gasket seating surface.
1.
By allowing this change, the valve is returned to its normal operable condition.
2.
The safety function of the tilt disc check valve is not affected by this change.
The valve is returned to a normal operating condition.
3.
This change has no effect on the Technical Specifications.
47
86-020 Provido rcplaccesnt Jet Suce uolddorn Baac for boaa chich has crackitke indications.
To facilitato the esplaccccnt of the Jst Pucp Holddern 9349 the rGtaince clip cust b2 cut and not rcplaced.
1.
Renoval of the retainer to allow Jet pump Beas replacement does not change the engineering function of the hold-doen bean itself.
2.
The safety function / operation of the holddown beae itself is not affect by this change.
3.
Jet pump operation as defined in the Technical Specifications is not affected by this change.86-021 Provide additional supports to D/W interior vessel protection plates.
1.
The barriers will continue to protect the primary containment pressure boundary free pipe whip associated
'with postulated pipe breaks.
The proposed sodification will ensure that the existing barriers meet Seismic Category I requirements.
2.
This change will not introduce any failure mechanises which were previously unanticipated or any events which are not bounded by the FSAR.
3.
This change does not affect any eargin of safety as defined in the Technical Specification Bases.86-026 Replace RHR Heat Exchanger Outlet Conductivity indicator, Beckman RA-5, with a Beckman RA-6.
1.
Replacement equipment is qualified for all postulated events and performs the same function as existing equipment.
2.
The replacement equipment performs the same function as the existing equipment.
3.
Ti.i s equipment is not addressed in the Technical Specifications.
48
85-027 Rcplaco Rosocount Rscire flow transcittsrs ll51DP6B22 iib cith Rsss sunt Il51DP6B22T transettters.
1.
The replacement equipment will not alter or affcct the system's ability to meet its design conditions.
2.
The replacement will perform the same function as the existing equipment.
3.
The equipment is not addressed in the Technical Specifications.06-028 Replace Liettoroue motors which were affected during the SE Diagonal Flooding Event.
1.
The DCR replaces existing electrical motors with new
- motors, which are of the same type and size and meet the environmental qualification requirements as the existing motors.
2.
There is no change in systes function.
3.
There is no change in system function.86-029 Replace existing Refueling Bridge load cell system with new system described in SE proposal number 416-6145-HTO.
Mount digital readout unit so it is easily readable from operator's control console.
1.
The change does not change the operation of the R/F bridge grapple.
It only adds a more accurate, reliable load cell systes.
2.
No new modes of operation are introduced.
3.
Tech Specs is not affected.86-034 Seal Weld Seat Ring (nonel) to valve body (carbon steel) of
'A' loop RHR suction valve.
1.
The change would restore the alignment of the valve seat ring to original condition, i
2.
The change would not affect valve operability.
l 3.
The change would restore the valve seat ring to original condition to meet Technical Specification requirements of section 3.7.D.
i 49 I
96-035 Rcplaco dacaged ASCO solsnoid valvos on 1E21-F069A and IE21-F070A.
Alleo uno of atthcr ASCO HB8302C27RF er HBB302D27RF in the Cero Spray jockey pucp systco.
1.
No changes are being made to the FSAR or equipment ref erenced on the FSAR.
2.
This change replaces a component with its current equivalent.
3.
No equipment important to safety as defined by the Technical Specifications is affected by this change.86-036 The existence of crevice corrosion and anaerobic bacteria has been identified in the Plant Service Water system.
It is necessary to obtain samples from selected areas in order to determine the extent of piping deterioration.
All sampled areas are to be repaired.
1.
The weld samples area will be repaired in accordance with ANSI 931.1, with NDE requirements as per ASME Section III, Class !!I.
2.
The weight of the repair parts is considered to be negligible, therefore the seismic integrity of the Seismic Category I system will not be affected.
3.
The requirements as stated in the Technical Specifications for the PSWS will not be a tered due to this change.96-042 Modify the D/6 stop & shutdown circuits to electrically isolate those cables that are routed through either the Main Control
- Roos, Cable Spreading Room, or Computer Room.
Required for Appendix R compliance.
1.
The installation of fuseholders and fuses to electrically isolate fire induced faults in Fire Area 0024 from local circuits required for diesel starting,
- running, metering will not affect systen performance or response times.
2.
The proposed modification will not degrade any l
I equipment or prevent any systee from functioning as assumed in the FSAR.
3.
This modification will not affect Diesel Generator systen logic, setpoints, or response times.
I l
l 50
96-049 R; place ths RHR differGntial transattters chich care ectted during tho diag:nal floed.
(R; place 1E11-N070 (Barton 368-1328) with a Rosemount 1151 transmitter.
Replace 1E11-N071 (GE 555) with a Rosemount 1151 transmitter.
Replace lEll-N028 (SE 50-551) with a Rosesount 1151 transmitter).
1.
The replacement equionent performs the same function as the original equipment.
2.
No new modes of failure are introduced.
3.
The new equipment gerecess the same function as the existing equipment, and it is not addressed in the Technical Specifications96-049 Replace the core spray transmitters which were wetted during the diagonal flood.
(Replace 1E21-4001A (SE 50-556120DAAA1) dith a Rosemount model 1151.
Replace IE21-N001B (GE 50-55-1) with a Rosemount model 1151).
1.
The replacement equipment performs the same function as the ortginal equipment in that it gives an indication of t5e performance of the systen but does not alter the purpose or operation of the system.
2.
No new modes of failure are introduced.
3.
The new equipment performs the same function as the existing equipment.96-055 Add the necessary saepling and test connections on the Feedwater (N21),
Offgas (N62),
Reactor Recirc (931),
and RWCU (631) systess in order to initiate the required test conditions and monitor the applicable plant parameters during the Hydrogen Water Chemistry test.
1.
No hydrogen injection increment into the feedwater system is large enough to result in an unexpected change on any plant parameters.
l 2.
No new modes of failure are introduced.
Industrial l
safety practices and procedures will be followed in the l
- design, construction and operation of the gas handling and injection system.
All persanent piping nodifications to safety systems will be seismically qualified.
3.
A temporary change to the Main Steam Line High Radiation scrae and isolation setpoints is required due to the expected increased steae line radiation.
- However, the only event which takes credit for these setpoints is the Control Rod Drop Accident (CRDA).
Below 20% rated power, where the event is limiting, the setpoints will not be changed.
Consequently, safety margins are not reduced, l
51
96-059 Install junction boxos, butt-splice, and replace cabics as nccessary to recovo the affectGd aroc of cabloc damaged by the Southeast Diagonal Flood.
1.
This change will restore the instrumentation cabling syst'en to its preflood functional level of performance capability and will make no system logic or operational parameter changes.
2.
No new accident or salfunction types will be introduced by this modi'ication.
3.
This change is part of an overall effort to restore the plant to its preflood safety margin.96-053 Remove spool otece between RPV head and RHR and install a blind 'lange on the RPV to reduce RPV disassembly time.
The cur piping will be blanked after 2 Ell-F0lo is removed and ca :ed before 2 Ell-r023.
1.
The Head Spray has no safety function and its removal will not adversely affect any safety system.
2.
The Head Spray performs no function which would be needed to prevent an accident or salfunction nor provide aid if an accident or malfunction occurred.
3.
The Head Spray has no safety function and no credit has been taken for its use in current safety evaluations or emergency operating procedures.96-068 Allow use of either stellite 6 or stellite 21 for hardsurfacing on the following valves:
lE41-F002, IE41-F003, IE21-F004A&B, IE21-F005A&B, and IE21-F007AhB.
1.
The change would restore th< valve disc 5ard facing to original condition.
2.
The change would not affect valve operability and the new hard facing (stellite) would allow ice a tight seating surface.
3.
The change would restore the valve disc hard facing to original conditton for tight seating.
52
36-072 allom uso of Balzona ceracic R Fillse Catal and Csracic S Scaling Matal
'ostional) to rGbuild da agcd dite areas on Plant Service Water butterfly valves 1P41-F310A&B.
1.
By repairing the disc on 1P41-F310 A,B,C,6 D the design
& safety intent of the components will not be altered.
2.
No new modes of failure are introduced because of this design change, in that the valves will be repaired to perfore their design intent.
3.
This change does not affect the operation of valves IP41-F310 A,9,C,& D.36-073 Install junction boxes, butt-splice, and replace cables as necessary to "emove the affected area of cables damaged by the southeast diagonal flood.
1.
This change will restore the power and control cabling systen to its preflood functional level of performance capability and will sake no system logic or operational para.eter changes.
accident or ealfunction types will be introduced 2.
No new by this modi 8tcation.
3.
This change is part of an overall effort to restore the plant to its preflood safety sargin.86-075 Upgrade the Square D float switch of the HPCI barometric condenser, model 9036-661-52, with a Square D float switch sodel 9036-GG2.
1.
The new component will not alter or affect the system's ability to meet its design conditions.
2.
The new component will perfore the same Junction as the existing equipment.
3.
This component is not addressed in the Technical Specifications.
53
86-094 Replace solenoid extenston cabics ratcd at 90 dcgrsos C cith cabics rated in Cxc0ss of 138 dcgross C on tha following valves:
- F122, F124, 2P70-SV-F0019, F004, F005, F066,
& F067.
(HPCI and Drywell Pneumatics) 1.
The proposed modification has no bearing on the probability of an accident.
2.
The replacement cable is environment' ally qualified and will have a tescerature tolerance greater than existing cable thus enhanctng the reliability of the cable and solenoid valve.
3.
The change will enhance the ability of the affected solenoids to functicq properly if required in the mitigation of an accident.
b 86-696 Repair RWCU tsolation valve disc with hard surface stellite 21.
1.
The change would restore the valve disc hard facing to original configuration.
2.
The change would not affect valve operability and new hard facing iroe stellite 6 to stellite 21 would allow for a leak tight seating to meet leak rate test requirements.
3.
The change would restore the valve disc hard facing to original configuration to meet Technical Specification requirements of section 3.7.D.86-103 Upgrade those walls that need to be fire rated for Rev. 1 Appendix R compliance but are not shown as rated in the
" Evaluation of the HNP Fire Protection Program".
Upgrade fire dampers and doors as required, except in the Reactor Buildings, and upgrade floors / ceilings as required.
1.
These modifications are being implemented to comply with the response to Appendix R to ucgrade plant safety.
2.
The modifications saintain the plant eargin of safety as it was before the modifications.
3.
This change does not affect the Technical Specifications.
The modifications increase the targin of safety above that which currently exist in the plant.
54
86-105 Rcconncet the calibration vcnt lines for lovel seitenes (ICll-N013) in the CRD Scran Dischargo Voluco.
1.
This modification will not adversely affect the ability or the response time of the level switches.
2.
The proposed modification will not degrade any equipment or prevent any system from functioning as assumed in the FSAR.
3.
The system lagte and setootnts are not changed.86-107 Install junction botes with terminal blocks so that valves 2E11-ro7aAhB and 2E41-F053 can be sealed.
1.
The change will ennance the ability of the solenoids to function properly even under the postulated accident
-environmental conditions and will not affect the design operation of the salve or its seismic qualification 2.
No basic design intent is changed and no new failure mechanise is introduced as a result of this change.
3.
No sargin of safety is af3ected by the godification.86-108 Provide redundant gear case brake and actor brake operation of the Unit 1
Reactor Building overhead crane.
1.
The only change to the logic of t5e system is the removal of a time delay free the motor brake.
This allows the brake to coerate ismediately and therefore increases the speed with which the oraking action occurs.
2.
The design change does not eliminate any of the original design braking.
3.
The Tech Spec section 3.10.F.1 states the Geactor Building crane will meet single Sailure criteria.
Since the modifications keep one back-up brake powered from another source and the design still actuates all the brakes in the event of brake 3ailure, the single failure criteria is not violated.
l 55
86-113 Add a statnisss steel 1500 slip-on flange to the and of, the Plant Sorvico Water Backmash piping to tha riv:r.
1.
This change does not affect the design or safety intent of the Plant Service Water System.
2.
No new modes of failure are introduced because of the change.
3.
This change does not affect the operation of the Plant Service Water Systes.96-114 Replace obsolete check valves as required with suitable substitute in the Diesel Generator Starting Air System.
Valves to
- e reclaced are IR43-F3034 A,B,&
C.,
IR43-F3035 A,B,k C.,
IR43-F3040 A,B,&
C.,
IR43-F3041 A,B,&
C.,
and 2R43-3024 A&C., 2R43-F025 A&C., 2R43-F029 A&C., 2R43-F005 A%C.
1.
The design or sadety intent as evaluated in the FSAR has not been altered.
2.
No new modes of failure are introduced.
3.
The replacement valves maintain the eargin of safety as required and defined in the Technical Specifications.86-117 Replace the 2A Station Battery (NAX1650) with the 2B Station Battery (NC11650).
1.
The consequences of an accident analyzed in FSAR will not be increased because the sodification will not affect the DC power distribution system which would be used for accident artigation, nor will it alter operation or logic function of plant safety systems.
2.
No new failure mechanism is created as a result of this change.
The changes provide a newer battery of the rating and capacity as the existing one for the DC same
- cwer Distribution Systes.
I 3.
The basis for operability of the battery systems given in Technical Speci4ication Section 3/4.0 does not specify any required sargin in battery capacity above that required for safe shutdown and accident control.
56 l
96-117 RGpl ace the 11' positivo plate-ocr-coll 2B Station Batt:ry cith a
16 positivo plato-per-cell battGry.
Modify associated circuitry as necessary.
Replace existing racks alth new racks'to accommodate the larger battery.
1.
The modification will not affect the DC pcwer distribution system which would be used for accident sitigation, nor will it alter operation or logic function of plant safety systems.
2.
No new fatlure mechants, is created as a result of this change.
The proposeo change provides a new, higher capacity battery 'or the DC power distribution systee.
3.
The basis for a:eractitty of the battery systems given i cation Section 3/4.0 does not in Technical 3cect t
specify any required margin in battery capacity above that required 'or safe snutdown and accident control.86-120 The purpose of the change is to temporarily energize and de-energize DC switchgear 2A (2R22-S016) from DC switchgear 2B (2R22-3017) and vice versa to replace the station service battertes IA (2R42-S001A) and 2B (2R42-5001B) under DCR (96-117) and DCR (86-119).
1.
The changes to DC switchgears 2A & 2B will be temporary and it is ensured by the procedures that all equipsent is restored to its original state after the replacement of station service batteries 2A k 29.
2.
The temporary DCR will be in effect only during plant cold shutdown or refueling conditions.
The total load on both the Switchgear busses will 90t exceed the capacity of the individual battery serving the system.
3.
Technical Specification 3.8.2.4 requires only one DC oower division while in cold shutdown or refueling mode of plant operation This DCR exceeds the required margin because both DC power divisio9s will be energi:ed.
57
86-121 The purpcs3 of this chango is to esdify Fecdcatcr Nszzlo inspection Door 1F51-N4B to Cliotnato the interference which occurs between this door and the feedwater pipe (systes 021) at feedwater nozzle
'9",
when the door is opened to access the nozzle welds duri~ng in-service inspections.
1.
The modification to the existing inspection door will not change the operation of any essential systes.
2.
No basic design intent is changed.
This change will not introduce any 3ailure mechanises which were previously unanticipated or any events which are not bounded by the 5AR.
3.
No systen oceraticos will be affected.
This change does not a43ect any iargin of safety as defined in the Technical Specification Bases.86-126 Re-hang valve disk of W Check Valve (1921-F032A) and Rev. 1 change saterial of bearing insert to allow for proper disk seating 3or LLRT integrity.
1.
This modification will not alter the design or safety _
requirements as stated in HNP-1-FSAR 7.3.
modes of failure are introduced because of this 2.
No new change.
3.
This modification will provide for better seating of IB21-F0324 and thereby support the ILRT requireeents specified in Technical Specification 3.7.
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86-127 Deplaco upper thrust washer do=als (part #16632) and lon r thrust cashgr decole (part #10386) with flathead screws part 4075309A01 and part 0075309A02 for upper and lower thrust washer respectively.
Applicable to RCIC Turbine, IE51-C002.
1.
The change will not affect or change operation of the RCIC system.
It provides an improved method of holding the oil puso shaft thrust washers in place and therefore will arovide teproved reliability.
2.
No new modes of Jailure are introduced as a result of this change.
3.
The operability of the RCIC system as defined in Technical Soecifications is not affected by this change.86-132 Change the normal range effluent monitors (IDil-P001/P002) trip signal and Kasan post accident radiation monitors (IDll-P005/P006) initiation signal so as to recetve high alarm just below the Tech. Spec.
effluent release limit.
Normal range monitor to trip at HI-HI alare and Vaman post accident radiation monitor to initiate at HI-HI alare.
1.
The proposed sodification does not initiate any action other than indication and will not affect the safety function of the Radiation Monitoring Systen.
2.
This modification will not introduce any failure mechanises which were previously unanticipated or any events which are not bounded by the FSAR.
3.
No margie of safety is a43ected.
The proposed modification will not reduce the effectiveness of the instrumentation and will not adversely affect the prescribed functions.
l 96-139 Use stainless steel capscrews, bolts and nuts in place of carbon steel fasteners for bolting the cump bowl assemblies of the Standby Plant Service Water Pump.
1.
Changing the carbon steel capstrews for the Standby Diesel Service Water pump bowl assembly to stainless steel will decrease the degradation of the capscrews j
and thereby reduce the probability of malfunction of equipment important to safety.
2.
No new modes of failure are introduced because of this design change.
I 3.
This change does not alter the safety or design intent l
of the Standby Diestl Service Water Dump.
59
86-141 use stellito 21 en crano valvo disc for 6004 carbon Rev. I steal gato valvos (RCIC Stoao Isolation Valvos, IE51-F007, F000).
1.
The change would restore the valve disc hard facing to original condition.
2.
The change would not affect valve operability and new hardiacing would allow for a sore leak tight seating to meet the leak rate test requirements.
3.
The change would restore the valve disc hard facing to meet Tech. Spec. requirements of Section 3.7.D.86-165 Increase the si:e of the restriction orifice of the Standby Plant Service Water Pump (2P41-C002) to improve pump performance.
1.
This enlargement will result in increased cooling water flow to the Diesel Senerator IB Heat Exchanger to its design condition.
2.
Any increase in pressure to the Heat Exchanger inlet due to the increase in ortfice disseter will be less than the maximue allowed.
3.
This modification will not affect operability requirements of the Standby Service Water systen or of the Standby Diesel Generator as defined in the Technical Specifications.86-166 Build up the lower valve guide rib of the RHR Torus Suction Valve, (IEll-F0049) to allow proper seating of the disc.
1.
The change would restore the alignment of the valve disc to original condition.
2.
The change would not affect valve operability and correct aligneent of disc would allow for a more leak tight seating.
3.
The change would restore the disc alignment to original contition to meet Technical Specificaton requirements of Section 3.7.D.
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86-181 Disconn:ct cablos ABE802i'01 and ABE804M01 froa pan 21 2R25-S130 and re-routo to panol 2R25-S002.
With this modi f ic ati on,
panel 2R25-S002 cill fesd panols 2H11-P926 and 2Hil-P928, and 2R25-S130 will not be required for Appendix R path 2 shutdown.
1.
The operability of the power system is not affected.
The new conduit will be seismically supported.
2.
The circuit breaker coordination study is not affected by removal of two circuits from panel 2R25-S130 and adding them to 2R25-S002.
3.
This modification wtll not affect the system operation.86-184 Modify cable tray supports 2F-28, 2F-4, 2F-2F, 2F-20, 2C-249, 2F-21, h 2 F~- 11 to comply with FSAR design criteria.
1.
These modifications will increase the safety of the cable trays by strengthening the cable tray supports.
2.
These modifications will further increase the safety of the cable tray supports.
3.
The cable tray supports are designed to withstand all seismic and static loads.86-220 Add an isolation switch to 1A & 1C D-B current transformer (CT)/ setering circuit.
This change is required for compliance with 10 CFR 50, Appendix R.
1.
This modi 8ication will not affect accidents analyzed in the FSAR where credit is taken for the Diesel Generators.
2.
The circuit integrity is maint ained since the switch will be safety related with qualifications consistent with that service.
3.
This sodification does not affect systes logic, setpoints, or response times.
No margin of safety as defined in the basis for any Technical Specification will be affected.
61
96-221 Add an isolation soitch to 2A L 2C D/G current Transforccr (CT)/ catering circuit.
This changG is required for compliance with 10 CFR 50, Appendix 4.
1.
This modification will not affect accidents analyzed in the FSAR where credit is taken for the Diesel.
Generators.
2.
The circuit integrity is maintained since the switch will be safety related with qualifications consistent with that service.
3.
This nodi 4 tcation does not affect systee logic, setpoints, or response times.
No cargin of safety as defined in the basis
'or any Technical Specification will be affected.96-232 Use Induction West Stress Improvement to mitigate future IGSCC on stainless steel primary coolant boundary pipiag welds.
1.
. Induction Heat Stress Improvement (IHSI) is applied to weldsents in stainless steel piping to convert the restdual welding stresses from tension to compression and thereby eliminate one of the critical factors that promotes IGSCC.
2.
With improvement sade by IHSI, treated locations are less suscepttble to cracking than prior to repair.
3.
The potential for further 10 SCC initiation or growth at the repaired location is reduced due to the weld residual stress improvement resulting from Induction Heating Stress Improvement (IHSI).96-245 Install compressor system and instrumentation necessary to perform an ILRT on Primary Containment.
1.
This change only provides temporary todt'ications required to support the ILRT and will only be in place during Modes 4 or 5.
2.
This change is temporary and in support of a test described in the FSAR.
- Also, primary containment l
integrity is not required during Modes 4 and 5.
3.
Since all modifications will be removed and the plant returned to its original design configuration prior to entering Mode 3, no eargin of safety is affected.
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86-247 Livo load valves in 2B31, 2E41, 2E51, and 2631 syste s through thG use of 9211Gvillo springs to caintain a proper gland bolt load (i.o.
valve bcconos s91f adjusting).
1.
Through the use of Belleville springs, proper gland bolt loads can be **intained on all valves that are reworked.
This will result in reduced valve stem
- leakage, extended packing life, and increased stroke endurance, making any reworked valve more reliable.
2.
No new modes of failure are introduced.
3.
The Technical Soecifications are not affected by this change.86-248 Live load valves in 2N11, 2N22, 2N36, and 2N38 systems Rev. I through the use of Belleville washers to maintain a proper gland bolt load (i.e. valve packing becomes self adjusting).
1.
Through the use of Belleville springs, proper gland bolt loads can be maintained on all valves that are reworked.
This will result in reduced valve sten
- leakage, extended packing life, and increased stroke endurance, making any reworked valve more reliable.
2.
No new modes of failure are introduced.
3.
The Technical Specification are not affected by this change.86-249 Replace the existing Crosby 1" 1 1 1/2" relief valve (Drywell Pneumatic relief
- valve, 2P70-F100) with a l
Target Rock safety relief valve model 82LL-001, l' X 1 1/2".
l 1.
The replacement Target Rock relief valve eeets the same design parameters and code requirements as the existing Crosby relief valve.
2.
The proposed modification will not degrade any equipment or prevent any systen from functioning as assumed in the FSAR.
3.
No requirement or bases to the Technical Specification is affected.
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1
86-275 Reroute
- circuits, EEE718C34 EEE718C35, RIE701C01, RIE701E02, RIE706C01, RIE700C01, RIE726C02, RIE726C03, RNX701A01, k
RNX702A02 to provida altcenato path reroute for Appendix R compliance.
1, The rerouting of these circuits will have no effect on the operation of any systes since no electrical design has been changed.
Since these circuits will be install in areas to crotect one train of equipment from a Fire Postulated in accordance with the requirements of 10CFR50 Appendix R, system availability is not reduced, but enhanced.
2.
No new modes of failure are introduced.
3.
This modification does not affect system logic, setpoints, or response times.86-291 Remove the fusion line of the weld at sheath-to-handle Rev. I and sheath-to-velocity limiter weld areas of Control Rods.
1.
This control rod sodification effectively restores the configuration of the sheath-to-handle and sheath-to-velocity limiter welds to that of the original equipment.
2.
The structural adequacy, scran perforeance, reactivity worth and envelope dimensions of the control rods are unchanged.
3.
All criteria of the control rods as evaluated in the Technical Specifications are unchanged by this modification.
spectacle orifice in the HPCI full flow test 86-298 Install a
line to enable a more controlled surveillance test to be performed for the HPCI system.
1.
The design change does not alter the original design intent of the systes and does not affect the function of the systee.
2.
This change does not affect the function of the systes.
3.
This change will allow for a more controlled surveillance test to be performed on the system to satisfy the requirements of the Technical Specifications.
64
96-360 Replace cxisting crackcd cell tn Station Battery 1A (6NB NAX 1950) cith GNB NCX 1650.
1.
Station Service Battery 1A with the replacement cell will meet the design load requirements.
The new cell is seismically qualified to.the same specification as the existing cell.
The seismic qualification of the rack is not adversely affected by the slight difference in weight between the cells.
2.
No new failure modes are created by the replacement of the battery cell.
Station Service Battery operation or design is not affected by this change.
3.
The 2-hour load supply period (without recharging) specified in the bases for Technical Specification 3.9.A.2.a will not be reduced by this change.86-363 Increase the tric devtce pick-up setting of the Service Air Compressor 4eeder breakers from 100% to 110% for
~.59 (LP51-C001A),
IR23-S004, Fr.
5B 1R23-5003, r
(IP51-C0019), and 1923-5004, Fr. 6B (IP51-C001C).
1.
The air compressors are not safety related.
The breakers for the feeders to the A/C's are.
Adjusting the trtp settings on these breakers will not reduce their ability to operate, will not cause "upstreas' breakers to trip, and will not exceed the design capabilities of the breaker.
2.
No new design logic or equipment is being introduced and this existing equipment is not betrg pushed beyond its limits of safe operation.
3.
The breakers will not place any safety related equipment in jeopardy.06-373 Hard pipe HPCI h i gh p oi r,t vent line to drain.
The present system configuration is such that when operations vents the systee via 2E41-FV001, steam is discharged into the atmosphere in the vicinity of the oprations personnel.
This creates the possibility of personnel being burned by the steas and airborn activity.
l.
This modification will be designed and fabricated in accordance with the requirements of the original code.
2.
The operation and safety function of the HPCI system will remain unchanged.
3.
This modification will not affect any requirements for the HPCI systee as defined in the Technical Specifications.
l 65 I
I
86-381 Replace existing 1* 15000 Yarcay valv22 2N62-FD001 and FD002 cith'1* 15000 Kcrotect.
1.
The replacement valves will not degrade systee operation.
2.
The subject modification will not affect the operation of the offgas systes.
3.
The sodification will not affect the operation of the offgas system.86-383 To add fittings to RCIC pump suction drain line to facilitate alternate Boron injection.
(To support the energency operating procedures).
1.
This modification will be designed and fabricated in accordance with the original USAS B31.7, class II code.
- Moreover, this destqn change will not affect the operation or safety function of the RCIC systes.
2.
The operation and safety function of the RCIC system will not be affected.
3.
The margin of safety of the Technical Specification requirements for any RCIC systes component will not be reduced after this modification is completed.86-409 Replace the existing Rectre Seal Purge Relief Valves, 2831-F015 A&B, Crosby assembly No. 55299 style JR-SPEC type A 3/4' X
1", with Crosby 3/4" X 1" relief valves style JR-C-A with a 316 - Stainless Steel base and disc.
1.
The replacement valve will not degrade system operation.
2.
This modification will not affect the operation of the recirc system or the recirc seal purge systee.
3.
This modification will not affect the operation of the recirc or recirc seal purge system.
66
TEST or EXPERIMENT REQUESTS86-001 This test is performed to observe and record feedsater Rev. 1 flow oscillation characteristics throughout the feedwater systes during low flow conditions 1.
None of the equipment being used in this test is important to safety.
Recorder connection will not affect the functions and/or performance of any plant equipment.
2.
The installation of the 2 eultichannel portable Honeywell 1858 Visicorders does not affect systes response and/or operation The recorders are connected to instrument test jacks that were featured in the original design and manufacture of the instruments.
3.
This test does not change any limited safety systes settings and/or result in an operating condition which would allow a limiting condition for operation to be
'enceeded as addressed in the Hatch Unit 2 Technical Specifications.86-002 This test provides direction for processing Floor Drain Water which will sanimize the renoval capacity of the Floor Drain Desin.
The improved desin efficiency will increase the recovery of Floor Drain Sample Tanks to the CST and produce longer run-lengths on the Desin.
1.
No changes are being sade in the operation of Radwaste as allowed by current operating procedures.
Only chemistry guidelines have been added to aid in determining the optieue processing path.
2.
No changes are being made in the operation of Radwaste as allowed by current operating procedures.
3.
All Technical Specification requirements are being set.86-004 Run both MSIV Leakage Control Systen blowers Rev. 1 2E32-C002A&E, seasure vacuum, and throttle 2E32-F013 to verify the MSIV LCS outboard blower will develop designed dilution air flow values.
1.
The running of both MSIV LCS blowers simultaneously is proper systee operation and is an analyzed event in the FSAR.
2.
This test places the MSIV LCS outboard blowers in their normal operational mode and does not change systee operation and response.
3.
No safety limits are exceed by running both MSIV LCS blowers simultaneously.
The stese suction valves will remain closed during the operation of the blowers.
67
84-005 Using Hydreg:n injsetion into the Focdeatcr Systco, Rav. I dctcrcino the a: cunt of Hydregcn noedGd to protcet recire pipoo frco Intergranular Stroco Carrcoien Cracking (16 SCC).
1.
He injection into the feedwater systen is limited to a concentration of 2 ppe. Maxieue He injection is 60 scfe. This will result in an expected radiation increase of approximat.ely 5 times noreal background upon He injection.
To sinioite the effects on the offgas systen, On will be injected through a test connection on the coseon line from the stean jet air ejectors.
To insure that the proper amount of Os is added to the offgas systes an 03 sonitor will analyze the recombiner outlet gas.
Maximus 03 injection is 30 scia.
The injection of gases is to be controlled by use of clearances and a special purpose procedure and will be done under the strict supervision of the GE and GPC test engineers.
Therefore no hydrogen injection increment is large enough to result in an unexpected change in any plant parameter.
2.
No new modes of failure are introduced.
Industrial safety practices and procedures will be followed in the design and operation of this systee.
Systes and plant protection is accomplished by a excess flow check valve located at the hydrogen tanks.
This valve cuts off flow at 100 scfm in the occurrence of a severed line.
Also Hs monitors located in the Turbine Building monitor the air for any buildup of Hz.
At a 21 absolute concentration the monitors send a signal to the control panel which shuts off the hydrogen injection.
Protection is also provided for plant op er a ti o,1 by a Cs sonttor after the offgas recombiner.
This sonitor sends a signal to the control panel to shutoff the hydrogen injection at a Os concentration of 5% assuring that all hydrogen is recombined.
3.
A temporary change to the Main Steae Line High Radiation scrae and isolation setpoints is required (An initial value of 10 times normal background will first l
be used) due to the expected increase in steam line l
radiation. Operations will maintain the setpoint in the proper position by an Operations Standing Order.
The only event which takes credit for these setpoints is the control rod drop accident.
Below 20% power, where the event is limiting, the above Operations Standing Order will control operation.
Consequently, safety eargins are not reduced.
68
96-007 Maacura focd purp and FW control respcaso tico with ens RFPT in "ocnual* end the second in " auto
- to dutcraina the nocd fcr changing RFP flon velva epocdc and if additional FW control systen tuning is needed.
1.
The test sonitors the response of the FWC system to nores! control signals generated by controllers in the system.
2.
Loss of Feedwater/High level transients bound the maxieus transients created by this test.
These bounding transients are analyzed events.
3.
The test only operates the FWC systes using its normally used control equipment.
No systes modification / alterations are performed by this test.96-009 Determine the dynamic characteristics of panel 2H11-P614 by performing a dynamic excitation test to develop required response spectra (RRS) for the seismic
' qualification of new equipment in panel 2H11-P614.
1.
The implementation of the test will not produce acceleration levels greater than OBE levels whic-the equipment in the panel was qualified.
2.
The implementation of this dynamic test will be performed while the plant is in a refueling mode or cold shutdown so that the instruments in the panel are not required to be functional.
3.
The implementation of this test does not change or affect the Technical Specifications.96-011 Obtain pressure data on Standby Plant Service Water Pump and associated piping / components to determine cause of low flow rates achieved by the pump.
1.
This modification is temporary in nature, and is only to gather pressure data from the Standby PSW Puep. All instrumentation disconnected in order to perfore this procedure will be reconnected prior to returning the
'B' Diesel Generator to service.
2.
The '9' D/S will be out of service while performing this procedure.
All instrueentation disconnected in order to perfore this procedure will be reconnected prior to returning the
'B' D/8 to service, i
3.
The margin of safety as defined in the Technical j
Specifications will not be reduced since the
'B' D/3 will be out of service during the performance of this procedure.
The
'B' D/6 mill not return to service until all disconnected instruments have been reconnected.
l 69
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OCCUPATIONAL'PERSONNELRADIATIONEXPOSl[RE e
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- 1 OCCUPATIONAL PERSONNEL RADIATION EXPOSURE This section has been compiled to satisfy the requirements of E. I.
Hatch Unit I and II Technical Specifications Section 6.9.1.5 and to assure compliance with the Code of Federal Regulations as set forth
'in the pertinent sections of Title 10.
Special attention was s
afforded to the methods prescribed by the Commission in Regulatory Guide 1.16 in order. that the intent as well as the letter of these laws might be fullfilled with providing meaningful information as to the degree and circumstances of a'.1 exposures of personnel at this facility. An indication of the effectiveness of the plant radiation program may be inferred from the. large number of individuals with no measureable exposure or minimal dose.
The time period covered by this tabulation extended from January 1, 1986 through December 31, 1986. All monitored personnel were included in summary as provided under 10 CFR 20.407. (a) (2).
Individual exposures as indicated by self-reading pocket ion chambers w'ere recorded daily with the use of an ALARA Computer System.,
These exposures were ta' ulated and printed in hard copy on o
a weekly basis and when required, along with the difference between these readings and the most restrictive exposure limit.> The corresponding ion chamber results as recorded on the dis: dosimetry files were supplanted by thermo-luminescent dosimeter measurements made over a period of approximately one month as the TLD data became
. available from a ver1 dor.
Each person listed in the dosimetry disc files was assigned an usual job category based on his expected daily activities. There are six job categories of this nature and are identified in the following table.
Running totals of dose acquired in each of these categories were maintained for each person in his dosimetry file.
Each dosimeter reading, in addition to being retained for individual exposure records, is added to the total representing the cumulative dose in the appropriate job category.
.The implicit assumption involved in this method of accounting for exposure in different tasks is that all exposure acquired in job categories other than the usual will be documented by a radiation work permit.
This circumstance should prevail in all significant Cases.
Further delineation as to the number of persons and amount of exposure of people in different job categories by various personnel categories is indicated by the standard reporting format of Regulatory Guide 1.16.
Each personnel dosimetry disc file contains the personnel category information required to accomplish this compi lation. The individual running dose totals for each job were used by the ALARA Computer to compute the number of man-rem indicated in each group.
Backup disc files were maintained for redundancy in the case of destruction or temporary inaccessability suffered by the main files.
Hard copy records as printed by the ALARA Computer were also maintained.
t
-F.1 By the use of the ALARA' Computer System personnel dosimetry information has been compiled, retained and tabulated in such a manner as to satisfy the pertinent ~ Federal Regulations and Plant Technical Specifications.
The system has been organized to provide this information in the format specified by these requirements and the suggestions of the Regulatory Guides.
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C6ERCIA POUER COMPANY - HUCLEAR"CEHERATION PLHHT E.1. HATCH F.O.90M 439.
SAXLEY, CA 31513 License :
DPR-57 L2 cense :
HPF-5 Regulatory Guide 1.16 Infor.mation END OF YEAR REPORT FOR 1986
, Personnel <>100 mrem >
Total Han-Rem WORK & JOB FUNCTION Utility Station Contret Utility Station Contret Raector Operations & Surveillance Maintenance & Construction 0
17 354
.126 6.086 99.221 Operaticns 0
115 0
.076 59.476
.331 Health Physics & Lab 1
97 60
.116 65.516 46.517 Supervisory & Office Start 4
57 8
1.246 20.306 3.677 Engineering Staff 1
29 30
.401 14.332 11.419 Routine Plant Maintenance Maintenance & Construction 0
170 476
.091 G1.611 142.334 Operations 0
is 0
.008 10.469
.294 H2alth Physics & Lab 0
31 27
.002 13.374 9,644 Supervisger & Office Staff 0
16 13
.058 4.377, 5.537 Engineering Staff 0
10 31
.039 3.470 11.337 Inservice lospection Maintenance & Construction 0
1 359
.065 1.261 100.171 Uperations 0
0 0
.000
.229
.20i Health Physics & Lab 0
9 19
.002 2.666 4.318 Supervisory & Office-Staff 0
t 9
.086 1.209 3.330
. Engineering Staff 0
3 24
.026 1.318 11.451 Special Plant Maintenance Naintenance & Construction 0
125 671
.213 46.207 316.796 Operations 0
8 1
.008 3.066
.324 Health Physics & Lab 0
14 24
.002 5.455 7.608 Supervisory & Office Staff 1
4 24
.245 2.170 14.626 Engineering Staff 0
20 84
.229
?.100 19.746
' Waste Processina Maintenance & Construction 0
1 355
.065
.614 99.450 Operations 0
0 1
.008
.124
.91f Health Physics & Lab 0
10 20
.002 2.683 4.50 Supervisorv & Office Staff C
0 7
.015
.231 2.508 Engineerin'g Staff 0
0 21
.026
.176 S.3?
Refuelina Maintinance & Construction 0
20 356
.065 7.577 99.838 Operations 0
2 0
.000 1.621
.202 Health Physics & Lab 0
11 23
.002 2,941 5.113 Supervisory & Office Staff 0
0 3
.015
.426 2.792 Engineering Staff 0
1 21
.026
.545 3.441 Totals 4
haintenance i Construction 0
334 2571
.625 143.556 557.813 Operations 0
143 2
.114 74.984 2.262 Health Phycics c Lab 1
172 173
.127 92.641 77.701 Supervisorv & Orrice Staff 5
78 69 1.666 29.219 32.467 Engineering Staff 1
63 211
.747 28,942 79.776 i
nd Totals 7
790 3026 3.279 369.341 1050.019 I
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s Personnel Monitoring Report - 10CFR20.407 Final Report for 1986 GEORGIA POWER COMPANY - NUCLEAR GENERATION PLANT E. I. HATCH P. O. 80X 439 BAXLEY, GA.
31513 License DPR License NPF-5 Actual Whole Body Exposure Range Number of individuals (Rem) in each range No measurable exposure 1312 Measurable exposure less than 0.1 1340 1
0.1 to 0.25 696 0.25 to 0.5 516 0.5 to 0.75 274 O.75 to 1 210 I to 2 374 2 to 3 68 3 to 4 7
i 4 to 5 1
5 to 6 0
6 to 7 0
7 to 8 0
8 to 9 0
9 to 10 0
10 to 11 0
11 to 12 0
1 12+
0 Total number of personnel monitored 4798 This report is submitted in accordance with paragraph (a)(2) of 10CFR20.407.
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e O
REACTOR COOLANT CHEMISTRY
SUMMARY
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REACTOR COOLANT CHEMISTRY Tabulations on a monthly basis of values of SJAE Isotopics and Reactor Coolant system parameters as required by Section 4.6.F.1 of the Unit Specifications are found in the following tables.
I Technical Unit 11 values are also shown, although it is not required that they are reported.
Isotope values listed as "0" are less than Ltd for the counting system.
UNIT I 1986 SJAE ISOTOPIC $
uCi/SEC DAIL 1986 m xe.133 x
..............................................e.135 xe.138 Kr-85m Kr.87
...........................................................Kr.88 f.6 g..g..........................................................................................................................
.g.g..........................................................................................................................
g.......................................................................................................................
z..........................................................................................................
' J1n 02 2387 3.00E.1 2.10E+2 1.58E+0 1.12E+1
........................................... 7.30E+0.............................................................6.77E+0 2.37E+2 14 2423 0
1.
..........................................14E+1 2.53E+2 0
2.17E+1
........................................................... 0 2.86E+2 Aug 14 2408 7.92E.1 3.10C+2 2.77E+0 1.69E+1
............................................1.26E+1............................................................1.01E+1 3.53E+2 Sep 08 2433 0
............................................1.24E+1 3.60E+2 2.24E+0 2.13E+1 3.96E+2
............................................................. 0 Oct 09 2436 5.17E.1 2.60E+2 2.30E+0 1.67E+1
............................................9.83E+0...........................................................
8.43E+0 2.98E+2 Niv 07 2428 1.14 E+ 1 1.21E+2 2.31E+0 8.02 6.95E+0 1.73E+2
........................................... 2.32E+1..................................................E+0 Dec 08 2436 5.73E+2 2.83E+3 2.47E+2 6.61E+2 6.24E+3
............................................1.42E+3............................................................5.llE+2 REACTOR CHEMISTRY 10 DINE 5 uti/ml DAIL 1986 MWi 1 131 g.g......................................1132.............................................................OE!
131 I.i))
i.134 I.335 g.g..........................................................................................................................
- ..g..........................................................................................................................
g.g..........................................................................................................................
z.g..........................................................................................................................
an 02 2387 1.79E-5 1.76E.4 1.25E.3 4.08E.4
......................................... 4.96E.4.............................................................1.39E.4 41 14 2423 1.09E.5 1.69E.4 1.59E.3 4.35E.4 1
..........................................5.97E.4.............................................................
42E 4 14 2408 1.54E.5 4
2.26E.4 1.llE.3 5.33E.4 1
i9
....................................... 83C.4............................................................
57E.4 2433 1.82E.5 2.49E.4 1.51[.3 5.09E.4 f
..................................... 5.65E-4..............................................................
74E.4 t 09 2436 1.5lE-5 2.02E.4 1.13E.3 5.89E.4 1
..........................................5.73E.4.............................................................
69E.4
= 07 2428 6.82E.5 2.95E.4 1.38f.)
5.86E.4 I
......................................... 5.46E.4...........................................................2.40E.4 p..=.........mc..............................5.38E.3
- 5. ot. 3 5.mt.3 4.43E.3 3.a6E.3 i.8it.3
UNIT 2 1986 SJAE 150 TOPICS uC1/5EC I
DATE 1986 MWT Xe-333 Xe.135 Ar.85m Ar-81 Kr.58
............................................................Xe.138
.........................................................7.6 Jan 07 2428 6.13E+2 2.75E+3 5.56E+2 1.69E+3 1.2 1.79Et4
...........................................................1.11E+4................................................8E*3 Feb 14 2078 6.14E+2 1.67E+3 2.59E+2 8.69E+2 7.75 8.55E+3
..........................................................4.37E+3..................................................E+2 Mar 18 2066 4.01E+2 1.33E+
3.92E+3 2.06E+2-6.58E+2
..................................................3......................................................6.03E+2 7.12E*3 Apr 08 2071 5.52E+2 1.88E+
5.27E+3 3.12E+2 1.05E+3 3.......................................................9.43E+21.00E+4 May 06 2071 5.72E+2 1.48E+
5.03E+3 2.74E+2 9.28E+2
..................................................3.....................................................
8.46E+2 9.13E+3 l
Jun 13 2052 5.49E+2 1.84E+
5.24E+3 3.12E+3 1.08E+3
................................................. 3.......................................................9.58E+29,98E+3 Jul 11 2071 1.24E+3 4.42E+
9.25E+3 5.89E+2 1.90E+3
.......................................,...........3......................................................1.58E+3 1.89E+4 Aug 01 1554 3.92E+2 1
6.37E+3 2.59E+2 9.24E+2
............................................. 43E+3..........................................................
8.55E+2 1.05E+4 Sep 09 2437 6.61E+2 2
1.19E+4 4.93E+2 1.92E+3 1.92E+4 89E+3...........................................................1.32E+3 Dec 26 2408 7.18E+0 1.54 2.12E+3 2.22E+1 1.53E+2 2.53E+3
.................................................E+2........................................................7.52E+1 REACTOR CHEMISTRY 100lNE5 uCi/ml DAIL 1986 MWT I.131 1 133 1 134 1 lJ5
............................................1132............................................................. DEI 131 Jan 07 2428 4.03E.3 2.43C.2 2.89E.2 2.80E.2
........................................... 2.85E.2.............................................................1.44E.2 Feb 14 2078 3.61E.3 2
1.20E.2 1.20E.2 1.17E.2
............................................. 10E.2...........................................................8.80E.3 Mar 18 2066 3.13E.3 2.1 1.33E.2 1.55E.2 1.59E.2
...............................................5E.2.........................................................9.0E6E.3 Apr 08 2071 1.97E.3 1.78 6.95E.3 1.27E.2 8.22E.3
................................................E.2.........................................................5.39E-3 May 06 2071 2.21E.3 2.23 9.96E.3 1.70E.2 1.36E-2 7
................................................E.2..........................................................
13E.3 Jun 13 2052 2.18E.3 7.63 7.15E.3 6.12E.3 8.13E-3
................................................E.3.........................................................5.17E.3 Jul 11 2071 7.34E.3 4.17E.2 4.51E.2 4.49E.2 2.38E.2
.......................................................... 3.86E.2 Aug 01 1554 1.26E.3 1.71
................................................E.2........................................................3.57E.3 3.96E.3 7.61E.3 5.85E.3 p 09 2437 4.87E.3 2.34E.2
......................................................... 2.17E.2 3.61E.2 2.89E.2 1.46E.2 Dec 26 2408 4
1.26E-3 7.llE-4 5.51E.
51E.5................................................
3 8.61E.3 5.18E.4
Georgia Power Company 333 Piedmont Avenum Atlinta. Georgia 30308
~ Telephone 404 5264526 Mailing Address:
Fbst Office Box 4545 Atlanta, Georgia 30302 Georgia Power L T. Gucwa trie southern elecinc system Manager Nuclear Safety and Licensing SL-2076 1170C l
March 2,1987 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C.
20555 NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNITS 1, 2 ANNUAL OPERATING REPORT FOR 1986 Gentlemen:
Pursuant to Section 6.9.1.5 and 4.6.F.1 of the Plant Edwin I. Hatch Unit 1 Operating License and Section 6.9.1.5 of the Unit 2 Operating License, please find enclosed the Annual Operating Report for 1986.
If you have any questions in this regard, please contact this office at any time.
Sincerely, pg- :- =
L. T. Gucwa MJB/lc Enclosure c: Geort ia Power Company U. S. Nuclear Regulatory Commission Mr. s. P. O'Reilly Dr. J. N. Grace, Regional Administrator Mr. J. T. Beckham, Jr.
Mr. P. Holmes-Ray, Senior Resident Mr. H. C. Nix, Jr.
Inspector - Hatch GO-NORMS Mr. G. Rivenbark, Licensing Project fianager II
-c47 1170C