ML20028B329
| ML20028B329 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 11/16/1982 |
| From: | Phyllis Clark GENERAL PUBLIC UTILITIES CORP. |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20028B330 | List: |
| References | |
| TASK-***, TASK-RR NUDOCS 8211300293 | |
| Download: ML20028B329 (23) | |
Text
GPU Nuclear f
. Ngg gf 100 Interpace Parkway Parsippany. New Jersey 07054 201 263-6500 TELEX 136-482 Writer's Direct Dial Number:
November 16, 1982 4
Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch #5 Division of Licensing U. S. Nuclear Regulatory Commission Washingtion, DC 20555
Dear Mr. Crutchfield:
SUBJECT:
Oyster Creek Nuclear Generating Station Docket No. 50-219 SEP Integrated Assessment In our meeting on September 2, 1982, with the NRC management, we expressed our concern for any additional hardware changes during the next refueling outage due to the very large amount of work already scheduled during that outage.
However, we stated in our letter to you dated September 13, 1982,that we were reassessing the priority of all identified work in light of your July 30, 1982, response to our December 24, 1981, request for deferral of work, the results of the SEP reviews and the available PRA results from the NRC Staff and our own work. We also stated in the letter that we hoped to incorporate in that review consideration of final NRC action on our NUREG 0737 related work. However, we have not yet received the final NRC action on the NUREG 0737 issues.
we arrived at the attached schedules After prioritization, (Attachment I) for hardware changes resulted from the SEP integrated
@ [7 assessment.
As stated in our September 13, 1982, letter we still anticipate that essentially all SEP items will be resolved during the next two (2) refueling outages.
We are also transmitting the revised integrated assessment summary table (Table 4.1 of draf t NUREG 0822) as Attachment II. The revised table provides final status for " Licensee agrees" and
" Completion date" columns. The draft table indicated "Later" under these colun.s. The revised portions of the table are indicated by asterisks.
8211300293 821116 PDR ADOCK 05000219 p
PDR GPU Nuclear is a part of the General Public Utilities System
- Mr$ D. M. Crutchfield Page 2 November 16, 1982 Also attached to this letter is the summary of SEP seismic review to this date (Attachment III). As shown in the sununary, GPU has already completed several modifications by providing seismic supports for control room panels, switchgear, relay racks, etc.,
contrary to the statement made in the draf t NUREG 0822.
Attachment IV describes results of our recent Probablistic Risk Assessment (PRA) of selected Oyster Creek SEP topics.
A copy of the PRA Report was provided to the NRC staff on October 26, 1982, during ACRS subcommittee meeting. As indicated in Attachment I, the findings in the Assessment were used as bases for assigning schedules for some.of the SEP modifications.
Very truly yours P. R. Clark Executive Vice President i
blf i
Attachments cc: Ronald C. Haynes, Administrator Region i U. S. Nuclear Regulatory Commission 631 Park Avenue i
King of Prussia, PA 19406 NRC Resident Inspector Oyster Creek Nuclear Generating Station Forked River, NJ 08731 1
i 4
--a,-.
EQUIPMENT MODIFICATIONS OR ADDITIONS REQUIRED BY NRC DESCRIPTION OF MODIFICATIONS OR SEP TOPIC NO.
TITLE ADDITIONS SCHEDULE S COMMENTS II-3B Hydrology Install automatic water As indicated in Attachment II of our level instrumentation September 13,19S2 letter to the NRC, in the intake canal the water level instrumentation will be installed by the end of Cycle 11 re-fueling outage Install scuppers in As indicated in Attachment II of our parapets of reactor and September 13, 1982 letter to the NRC, turbine buildings the scuppers will be installed within six months following the Cycle 10 refueling outa
______________________________________________________________________.._____ge.
III_5B Pipe Break Provide emergency condenser Before Cycle 10 start-up GPU will revise the Outside Con-steam pipe leakage detection plant inspection procedure to include specific tainment direction to look 6 listen for leakage on the tour of the affected isolation condenser piping area during each shift by the plant operator.
GPU is currently ~ finalizing a report which predicts crack growth rate of the Oyster Creek insolation condenser lines. The report will be transmitted to the NRC by February.28,1984 Dur preliminary evaluation shows an extremely slow growth rate of a crack with sufficiently large leak rate for visual and audio detection.
V5 Reactor Coolant Make operational the existing The monitor will be operational prior to Pressure Boundary containment airborne part-Cycle 10 start-up.
Leakage Detection iculate and gaseous radio-activity monitors
ATTACH;1ENT I EQUIP > LENT >!ODIFICATIONS OR ADDITIONS REQUIRED BY NRC DESCRIPTION OF F10DIFICATIONS OR SEP TOPIC NO.
TITLE ADDITIONS SCHEDULE 5 CO)MENTS VI 1 Organic >!aterials Inspect and repair, if and Post accident necessary, the drywell During Cycle 10 refueling outage Chemistry coating and apply proper protective coating to the tor
_____________________________________________us VI-4 Containment Provide physical locking Isolation System devices on some types The locking devices will be provided by of containment isolation the end of Cycle 11 refueling outage.
PRA valves.
performed by the NRC consultant indicates that this issue is a low contributor to the
__________________.____________________________________________ _______overall risk.
VI-1.C.1 Appendix K -
Provide modifications to prevent automatic bus 11odifications, if needed, will be completed Electrical Instrumentation transfer (ABT) of faulted by the end of Cycle 11 refueling outage.
Our loads between engineered own PRA indicates that the ABT switches in the and Control safety features and vital AC distribution system of Oyster Creek electrical buses.
do not contribute in any significant way to the failure probability of any key mitigation system.
9
-2_
ATTACH?!ENT I EQUIPMET MODIFICATIONS OR ADDITIONS REQUIRED BY NRC DESCRIPTION OF MODIFICATIONS OR SEP TOPIC S0.
TITLE ADDITIONS SCHEDULE 6 COMMENTS VII-1A Isolation of Install Class IE protection The modification will be completed by the end Reactor Protection at the interface of the of Cycle 11 refueling outage.
System From Non-reactor protection systems By letter dated December 4, 1980, we committed Safety Systems, (RPS) power supply and to install Class IE protection at the inter-Including RPS computer system face between the RPS power supply and the RPS.
Qualifications of The system will be identical to that approved Isolation Devices by the NRC for use at Hatch Unit 1.
The NRC has approved deferral of this task from the 1983 refueling outage.
In response to an NRC request at our meeting on September 2, 1982, we confirmed that underfrequency protection is presently provided at Oyster Creek Nuclear Generating Station.
VII_1B Trip Uncertainty Replace existing RPS monitors GPU has scheduled to install analog trip and Setpoint that have inappropriate scale system during Cycle 11 refueling outage.
Analysis Review trip settings with proper PRA performed by the NRC consultant indicates of Operating Data instrumentation.
that this issue is a low contributor to the Base overall risk.
p
ATTACletENT I EQUIP 3fENT MODIFICATIONS OR ADDITIONS REQUIRED BY NRC DESCRIPTION OF MODIFICATIONS OR SEP TOPIC NO.
TITLE ADDITIONS SCHEDULE 6 COMMENTS VIII-2 Onsite Energency Modify diesel generator The modifications will be completed by the end Power System annunciators and bypass of Cycle 11 refueling outage.
(Diesel Generator) two diesel generator Our own PRA indicates that inprovement in trips.
availability and reliability due to the modification would be extremely small since historical performance of diesel generator failure are overwhelmingly dominated by failures other than protective interlock actuations.
i VIII-3B DC Power System Install battery status Due to the number of nodifications already Bus Voltage alarms planned in the control room during the forth-Stonitoring and coming (Cycle 10) refueling outage, the battery Annunciation status alarms are scheduled to be installed during Cycle 11 refueling outage. New cable trays for these alarms will be installed during Cycle 10 outa
ge.
III-10A Thermal-Over Evaluation thermal over-Although PRA performed by the NRC consultant load protection load bypasses for ESF rated this issue of medium importance, our for Abtors of valves and make appropriate recent plant specific PRA indicates that MOVs modifications.
modifying the safety related MOVs to include thermal overload protection bypasses would not significantly improve 30V performance or systen perfornance. This is because system redundancy provides backup valve trains that can actuate to provide the safety functions And the failure rate of HOVs due to thermal overload relay actuation is not a significant contributor to the total POV failure to operate on demand fron all causes. Thus, corrective actions, if necessary, will be made during Cycle 11 refueling outage.
-4
ATTACHMENT I TOPIC RESOLUTIONSpU DID NOT AGREE WITH THE NRC STAFF Biff NOW AGREES SEP TOPIC NO.
TITLE NRC STAFF POSITION GPU POSITION 6 SCHEDULE III-3C Inservice Formalize the existing GPU will formalize the shift turnover Inspection of inspection of the intake procedures to include inspection of the intake Water Control structure water level and structure area for unusual conditions such Structures trask rack screens until as high/ low water level, building of debris water level gages are by the trash racks, etc.
installed.
The shift turnover procedure will be revised by the end of the Cycle 10 refueling outage.
V-12A Water Purity Modify Technical GPU plans to revise Oyster Creek Technical of BWR Primary Specifications to upgrade Specifications to incorporate Reg. Guide 1.56 Coolant requirements on reactor limits for conductivity and chloride concentration coolant chemistry limits.
after examining our Cycle 10 experience.
V_S Reactor Coolant Install a seismically At meetings on October 26 and 27, 1982, with Pressure Boundary qualified (SSE) contain-ACRS subcommittee and on November 4, 1962, Leakage Detection ment leakage detection with full ACRS committee, the NRC position was system.
restated to call for at Icast one (1) reliable leakage detection method. GPU will provide a reliable detection method by the end of Cycle 11 refueling outa
___.._____________________________________________________________________ge.
XV-16 Radiological Adopt General Electric GPU plans to revise Oyster Creek Technical XV-18 Consequences 'of Standard Technical Specifications to adopt General Electric Failure of Small Specification for iodine Standard Technical Specification for iodine lines carrying control (NUREG_0123) liaits after exaaining our Cycle 10 exparience.
primary coolant Action statement will be consistent with the and Main Steam existing plant Technical Specifications.
Lines Outside Containment
-b-
~
ATTACHMENT II lable 4.1 I n t egra ted a s sevaimn t simia... y r+
m' Tech. Spec.
n modificalions SEP Topic Section Coraple-required from Backlit Licensee Lion PRA No.
tio.
Title SEP review requirements y
agrees date rating o
!!-3.B, 4.l(1)
Condensate Transfer Pump tio Provide redundant power yes*
12/82 11-3.B.1, Power supplies for the condensate transfer puc.ps.
11-3. C 4.l(2)
Flooding, Level Procedures tio None 4.1(3)
Canal Water level no Install automat ic water Yes Cycle XI Instrumentation level instrument.stion in the intake casial.
4.l(4)
Isolation Condenser No Flooding Demonstrate minimum quantity Yes Cycle X of water miaisit.aisied in condensate storage tank sufficient for long-term e$
cooling and inclHle minimum inventury in plant procedures.
4.1(5)
Low Water Level Shutdown tio lione 4.1(6) llurricane Flooding of flo Revise emergency procedures Yes Cycle X Pumps to ident ity alternate water sources and Ilow paths should low elevation pumps be fluo. leal.
4.l(7)
Flooding Elevation tio Evaliial. tonseqiiesices of Yes 10/82 otinas leuilding flooding and confism all other entrance levels aliove 23.5 ft.
See footnotes at end of table.
o ATTAClefENT II lable 4:1 (Continned) m n
Tech. Spec.
2 SEP modifications 85 Topic Section Comple-reguired from Backsit Licensee tion PRA
[
No.
No.
Title SEP review requirements agrees date rating rn 11-3.C 4.1(8)
Groundwater Elevation No See item 4.4(2).
4.l(9)
Roof Drains No Install u uppers in the Yes Cycle X reactor 1,uilding and turbine
+6 mo.
building parapets.
111-1 4.2 Classification of Struc-No Evaluate design of specified Yes 10 CFR tures, Compon-ints, and components on a sampling 50.11 Systems basis, upgrade if necessary, (e)(3)(ii) and den.urnent classification in f5AR update.
111-2 4.3.1 Reactor Building Steel No Analyte and identify any
,Yes 11/82 e
Structure Above the needed upgradisig of reactor Operating Floor building upper steel structure for wind loads.
4.3.2 Ventilation Stack No Analyze and identify any Yes
'1/82 needed upgrading of ventila-tion stark for wind loads.
4.3.3 Effects of Failure of No Analy/e turbisse building Yes 6/83 Nonseismic Category I capacity for wind loads, Structures evalu.it e conseipiences of failure and ident ify any needed upgrading.
4.3.4 Components Not Enclosed No None in Qualified Structures 4.3.5 Exterior Masonry Walls No fione u
See footnotes at end of table.
m ATTACHMENT II y
lable 4.1 (Continued) vi n
Tech. Spec.
s SEP modifications Cumple-E Topic Section required from Backfit Licensee Lion PRA F
No.
No.
Title SEP review requirements agrees date rating en mo III-2 4.3.6 Roof Decks No Provide analysis of reactor Yes 11/82 buildings roof.
Analyse c.giacity of turbine Yes 6/83 buildings s unf to withstand wind lo.uts.
4.3.7 Intake Structure, Oil No Analyze capacity to with-Yes 11/82 Ianks, and Diesel Gener-stand wind and tornado ator Building loads aiid ingstiratie, if necessary.
4.3.8 Load Combinations No Submit analyses demon-yes
- stratinig wisid loads were 8
properly combined with other specitied loads.
4.3.9 Soil and Foundation No lione Capacities
!!!-3.A 4.4(1) flydrostatic Loads No None (Combination) 4.4(2) liydrostatic Loads No Evaluate stuert-duration Yes 4/83 '
(Short-Duration) hydrostatic loads on and floalat inii potential of structures essent.ial to safe shuliloun in runjunction with I loodiset) emertjency procedui c> (l tem 4. l(6)).
4.4(3)
Below-Grade Penetration Nu fl uie Flooding
w-
~
ATTACI'IMENT II lable 4.1 (Cont ino.:d)
Tech. Spec.
SEP n
modificalions g
Topic Section Comple-requireil Irom BackIit Licensee Lion PRA to No.
No.
Title w
SEP review requirements agrees d.ite rating jp, Ill-3.C
- 4. 5.1 Intake and Discharge Canals No Nune o
4.5.2 Intake Structure Trash No Racks and Intake Screens formalize existing inspec-Yes*
tion pr.u.tice as part of shif L turnover or inservice inspes.l ion (151) piocedures until w. iter level moslifi-cation is Complete t
(ltem 4.l(3)).
4.5.3 Roof Drains No See item 4.l(2) 4.5.4 Inspection Program No Develop and implement a Yes Cycle X f ormal inspection program f or water control structures.
Ill-4.A 4.6.1 Emergency Diesel No Analyze potential for and Yes 3/83 Generators and Fuel conseipience> of tornado-Oil Day Tank missile d.ouage of the diesel generdtur heliIding.
4.6.2 Hechanical Equipment No Evaluate the potential for Yes I/83 Access Area and consequences of Lornado-missile impact in the reactor insilding access alour region and ident ily any net.essary correclive actions.
4.6.3 Control Room, Reactor Nn None Building, and Turbine Building lleating, Ventilating,-and Air Conditioning (ilVAC)
Systems See footnntes at end of table.
ATTACPTEE II o
lable 4.1 (Continucil) sn E
-5 lech. Spec.
n 2
SEP modifications Conip le-80 Topic Section required from Bactlit Licensee tion PRA 7
No.
No.
litle SEP review requirennents agrees date rating m
III-4.A 4.6.4 Condensate Storage Tank, No Provide protection for No Torus Water-Storage Tank, sufficient systems and and Service Water and components to ensure a safe Emergency Service shutdown in the event of Water Pumps damasje inom toin.ido missiles.
111-4.8 4.7 Turbine Misciles No inspect turbine.nid propose Yes 12/84 inspecLinn frequency based
?
un resuli,.
Justify monitorinq program Yes 2/83*
for m.iin steam and reheat a
control valves.
esn o
111-4.D 4.8.1 Truck Explosion No None 4.8.2 Aircraf t liazards No Ivaluate potent ial for or Yes 3/83 consequen.cs of aircraft impact.
Ill-5.A 4.9(1)
Cascading Pipe Breaks No.
See item 4.16.
4.9(2)
Jet Impingement Effects No None 4.9(3)
Drywell Penetration No None See footnotes at end of table.
1
a ATTACm!ENT II o$
lable 4.1 (r.n,tinu..I) c1 leth. Spec.
2 SEP molitications Comple-Topic Section requireil trism (lad I iI Licensee Lion PRA tio.
tio.
Title sLp review i equ i r. i..en t s aunces date rating m
m 111-5.8 4.10(1) LOCA Outside Containment tio
[ valuate and islentify any Yes 3/83 needed upgreding of the main steam and reactor water cleanup (RWCU) piping outside contaismient to precluile an unisolatable lireak out > inte conialament.
i 4.10(2) Emergency Condenser No I.valisate antil iilent i ty modi-Ye:,
Cycle X Isolation iicat. ion tu provide leakage dete.: Lion to en ure flaws would lie delet.ted before i
pipe break ocuars.
ui III-6 4.11(1) Piping Systems No Analyze on a sampling Yes Cycle X hasis and verily adequacy of support design > for the seismic resist.ince of specilled piping systems.
4.11(2) Mechanical Equipment tio th em.nst rate that the control Ye.
12/82*
ruit drive system.isul vessti internals have 2,ulticient C.ep.ti i t y t o res is t a sa fe
,hutib.uu carthquale or take a.ori ei t ive.u.t inn.
4.11(3) Electrical Equipment No Reevaluate 4160-V switch-Yes Cycle X
! cai le.iner 1.iiicliar.i.j.e and start demon.Irale, on a 2,ampling i U ain, b.isi,, adequ-uy ut electri-cal gianel aippoi is.
See footnotes at end of table.
ATTACllMENT 11 o$
lable 4.1 (Coisit siiiet il) to ID
.~
n lech. Spec.
s SEP nioili! icaI ions Topic Section Cunqile-reipii re.1 1 rom Itu i e i e ii.ensee tion PRA No.
No.
Title SEP review re.ps i s enien t s un a<pye,
ela t e rating o
III-6 4.11(4) Ability of Safety- -
tio 14..u.-
Related Electrical Equipment ta Function 4.11(S) Qualification of Cable No Provide plan tu implement Yes Cycle X Irays s esults of SLP Owners Group Pringrain un a plant-
., pes.itic basis.
111-7.8 4.12 Design Codes, Design No i valuate adespiacy of Yes 6/83 Criteria, Load uriuinal desi pi criteria Combinations and Reactor un a :,angiling basis for Cavity Design Criteria
- .pe. il ical st ros.tural un c li e.ien t,.
to III-8.A 4.13 Loose-Parts Monitoring No linne Low and Core Barrel Vibration Monitoring til-10.A 4.14(1) Thermal Overload Bypass No tvaluate thermal overload Yes 11/82 Medium leyp.e.ses f or engineeret*
3arely f eature> (tSF) valves.
4.14(2) Magnetic Trip Breakers No li.nic IV-2 4.15 Reactivity Control Systems, No lione Low Including Functional Design and Protection Against Single Failures See footnotes at end of table.
e
m ATTACilM5NT II o
s<
Table 4.1 (t:ont inned) un c+
-1 lech. Spec.
Q SEP siodi f icaliotis Comple-lopic Section required from 11attIiI L icensee tion PRA 7
No.
No.
Title SEP review respii rements agrees date rating en V-5 4.16.1 Airborne Particulate and No Provide at least I leikage Yes*
Low Gaseous Radioactivity detection method qualified Monitoring to SSI and evaluate sensi-Livity in conjunction with topic ill-5. A asialysis.
4.16.2 Operability Requirements Yes inclinte leatsue detection N0*
12/82 sysiem Iimiting tondit. ions for operation in lechnical Sperilicalions.
4.16.3 Intersystem Leakage No l{ane i
4.16.4 Reactor Coolant f(o No n.-
g Inventory Balances V-6 4.17 Reactor Vessel Integrity No Sul>mit a plan for the Yes 10/82 material surveillance capsules.
V-10.B 4.18 Residual lleat Removal No Review and upgraile, if Ye>
Before*
Low System Reliability nece:.sary, shut down Cycle 10 proi c lures to specify Startup alternate sources of water for primary and seconilary aiateup, with particular attention to external events.
V-II.A 4.19 Requirements for Isolation No Demonst r.ite set ief capacity
)e>
l/83 Low
- of liigh-and Low-Pressure and acc. pt dele i.on equences, Systems or filent is f. orrect ive action to prol.. I lait il sys t em.
See tootnotes at end of talile.
m ATTACil ENT II o
1able 4.1 (Continucil) enr+g lech. Spec.
Q SEP siodi fications Comple-lopic Section required from Battiit Iicensee tion PRA F
Ho.
No.
Title SCP review requirements aurces date rating w
V-12.A 4.20 Water Purity of BWR Yes implement proposed procedure
.Yes*
Primary Coolant anilnu.dity lectinical Specifi-catiosis to be consistent.
VI-1 4.21.1 Organic Materials No inspect and repair, if Yes Cycle X nete..ary, drywell coatings e 6 nio.
and ret. oat the torus.
4.21.2 Postaccident Chemistry No Hone VI-4 4.22.1 Locked-Closed Valves No Provide sc.hedule to implement Y :s 11/82 Low piro ical locking devices to ensure valves are not y
in.nlvertently opened.
w*
4.22.2 Remote Manual Valves No Provide leakage detection Yes*
dnd, il neCessary, relocate the operating station for isolation valves in the containment spray and core spray systems.
4.22.3 Valve Location No Hone 4.22.4 Instrument Lines No Hon.-
4.22.5 Valve Location and Type No None 4.22.6 Remote Manual Valves No Hone VI-7.A.3 4.23 Emergency Core Cooling Yes include em.:ruency condenser Ho System Actuation System louic t...t ing in t he leclusi...I L.er i t i<.ations.
i See footnotes at end of table.
s
=
canf!J9AkArtnfit Ichte s.1 (Continucil) ung
-s Icch. Spec.
n SEP moditicalions Comple-2 Topic Section reipiired f rom llack r i t
. Licensee tion PRA e
No.
ik,.
Title SEP review requ i rem.rnt s agree:,
date rating VI-7.A.4 4.24 Core Spray Nozzle No tione 5
Etfectiveness VI-7.C.1 4.25(1) AC Automatic Bus Transfers tio tvaluate tiie existing Yes*
12/82 Medium dntufia.it ir bits t rdH>lers and islent ify corrective actions to ensure f aulted loads would not be t i anst en s eil.
4.25(2) DC Automatic Bus Transfers No None VI-10.A 4.26.1 Response-Time Testing No tione Low i
4.26.2 Instrumentation for Reactor No Verify all safety logic Yes 12/u2 Trip System (RTS) lesting channels Lied to the reactor niode 2, witch are tested by procedure.
Yes Incinile logic rhannel No testing in lcciniical SpeciiicaLions.
4.26.3 Dual-Channel Testing No None VII-1.A 4.27(1) flux Honitoring Isolation No Perform tailure m.nle and Yes 12/82 Low c(tes.1.inaly>i:, t u determine wiselher i:.olation elevices dt'e I'Pijtli t'ed ellld ialt'nt i fy any necales! upgr.nlintl.
4.27(2) Reactor Protection System flo -
Ini,t..li ri:c., il pint ~ection Ye,
(.'yd le XI (RPS) Protective Trip at t i... :: - pi.v..r. npp ly
.o..I 1:l". e a t erI.n e See rootnotes at end of table.
m ATTACil?!ENT II y
lohle 4.1 (Continucil) sn n
Tech. Spec.
s SEP moditications E
Topic Section Cou.ple-required from Backlit licen ee Lion PRA No.
No.
litle SLP review requirements agrees date rating
<n5 VII-1.8 4.28 Trip Uncertainty and No Install analog trip system.
Yes Cycle XI Low Setpoint Analysis Review of Operating Data Base VII-2 4.29 Engineered Safety features See item 4.14(l).
Low System Control Logic and Design Vil-3 4.30 Systems Required for Safe No provide minimum inventory Low Shutdown for condensate storage tank as a water source for flood-ing events (liem 4.l(4))
i ditd ident ify non-l hf equip-g ment in couldown procedures (Item 4.18).
Vill-2 4.31 Onsite Emergency Power No Modify.innunciators to Yes Cycle XI tow Systems (Diesel Generator) confoim to IEli Std.
279-19/l and bypass two trips (voltage-ampere reactive and revesse power) during accident conditions.
VIII-3.8 4.32-OC Power System Bus No Schedule installat inn of Yes 11/82 liigh Voltage Monitoring and specified battery status Annunciation alarm,.
VIII-4 4.33 Electrical Penetrations of No
,None Reactor Containment See footnotes at end of table.
L 8
ATTACm!ENT II o
latile 4.1 (Cao.1 inncil) un rt Tech. Spec.
Q SEP modifications Cumple-Topic Section requised from L:octlit Licen.ee tion PRA F
tio.
No.
Title SEP review s equ i n ceuent s autecs sta te rating unQ IX-5 4.34(1) Restoration of Ventilation No tva lo.it e.md rev i:.e. i f Yes 3/83 necess.o r y, the t us s-o f-off3ite power prnredures to en,ine that restoration of vent ilation systems will not overload the aliesels.
4.34(2) Reactor Building No None Ventilation 4.34(3) Core Spray and Containment No Demonstrate subject pumps Yes 3/83 Spray Pump Ventilation can operate with a loss
?
of vent ilation, or identify curres Live at. tion, as yu necessary.
4.34(4) Battery, Hotor-Generator, Nn Ivaluate effects of loss of Yes 12/83 and Switchgear Ventilation ventilation to the subject rooms an.1 islent i ry any neesleal upgrading.
XV-1 4.35 Decrease in feedwater No None lemperature, Increase in 3
Feedwater Flow, and In-crease in Steam Flow and Inadvertent Opening of a Steam Generator Relief or Safety Valve XV-16 4.36 Radiological Consequences Yes Implement BWR Standard No 2/Hi of Failure of Small Lines lechnical Specitication Carrying Primary Coolant limit sur prim ny coolant Outside Containment
.irt iv ii v.
~
ATTAODIENT II o
i<
I.31,le 4.1 (Caesit ihiscill m
G8 SEP lech. Spec.
moditicalions
'o Topic Section Comp le-7e resguired from Bat.t it 11 o.
No.
Title t si. risisi: tinn PRA 5Ep review reigui r ement s m
agrees date rating Q
XV-18' 4.37 Radiological Consequences see item 4. %.
of a Main Steam Line Failure Outside Containment XV-19 4.38 Loss-of-Coolant Accidents tio Resulting From Spectrum Develop and implement a
'Yes Cycle XI of Postulated Pipe Breaks preventive maintenance Within the Reactor Coolant program for the main steam Pressure Boundary isolation valves, or justify existisig siiaintesiatice based on operating experience.
Subseil results of evalua.
Before*
Cycle X i
Lion intluding testing Cycle 10 experience.
Startup
- lligh for other reasons as explained in the referenced section.
NOTES:
Later - the licensee has not yet responded.
Cycle refers to the end of a vecific refueling outape by core cycle.
t O
6 9
ATTAODIENT III OYSTER CREEK SEISMIC REVIEW STRUCTURE, ORIGINAL
- SYSTEM, ANALYSIS REANALYSIS REANALYSIS COMPONENTS REVIEWED BY NRC BY GPUN RESULTS ESW Pumps X
OK' Emergency Condenser X
OK Cont. Spray HX X
X OK Recirc Pump Supports X
OK CRD Hyd. Control Units X
X OK (SSS)
Battery Racks X
Replaced One Emergency Diesels X
OK Intake Crane X
OK f
e e
e e s w em e
ATTACHMENT III 9
0YSTER CREEK SEISMIC REVIEW STRUCTURE, ORIGINAL
- SYSTEM, ANALYSIS REANALYSIS REANALYSIS COMPONENTS REVIEWED BY NRC BY GPUN RESULTS Reactor Building X
X OK Turbine Building X
X OK Ventilation Stack X
X OK Containment Vessel X
X OK Torus Suction Header X
OK Intake Structure X
OK Reactor Vessel and Support Pedastal X
OK Reactor Internals X
OK Electrical Equipment Anchorage X
Modifications (MCC's, Sw. Gr. Control Implemented panels, rel y racks, substations, transfonners, etc.)
Isolated Phase Bus Ducts X
Supports Added Cable / Conduit Raceways X
In Progress
s ATTAO NENT III OYSTER CREEK SEISMIC REVIEW STRUCTURE, ORIGINAL
- SYSTEM, ANALYSIS REANALYSIS REANALYSIS COMPONENTS REVIEWED BY NRC BY GPUN RESULTS PIPING SYSTEMS 0
Recirculation X
X OK O
Emergency Condenser X
X OK O
X OK O
X OK 0
X OK O
Emer. Service Water X
OK 0
Buried Service Water X
X OK O
CRD Return X
X X
OK (SSS)
Eccentric Mass of Yalve X
OK Operators W.
O e
.