ML20067B616

Forwards Schedules & Resolutions for SEP Topics II-5.B,V-5, VIII-3.B,V-12.A,XV-16,XV-18,III-4.A,VI-7.A.3,VI-10.A, II-3.B,II-3.B.1,II-3.C,III-1,III-2,III-3.A,III-3.C, III-4.A,III-4.B,III-4.D,III-5.A,III-5.B & III-6

ML20067B616
Person / Time
Site:	Oyster Creek
Issue date:	11/29/1982
From:	Phyllis Clark GENERAL PUBLIC UTILITIES CORP.
To:	Crutchfield D Office of Nuclear Reactor Regulation
References
RTR-NUREG-0822, RTR-NUREG-822, TASK-***, TASK-RR NUDOCS 8212060247
Download: ML20067B616 (17)

Text

,

GPU Nuclear NUh Q[ 100 Interpace Parkway Parsippany, New Jersey 07054 201 263-6500 TELEX 136-482 Writer's Direct Dial Number:

November 29, 1982 Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch #5 Division of Licensing U. S. Nuclear Regulatory Commission Washington, DC 20555

SUBJECT:

Oyster Creek Nuclear Generating Station Docket No. 50-219 SEP Integrated Assessment Our recent letter dated November 16, 1982, provided our schedules for equipment modifications and additions resulting f rom SEP integrated assessment. The letter also provided GPU Nuclear Corporation (GPUNC) positions concerning resolutions of some of the SEP topics proposed by the NRC staff with which we disagreed.

Subsequently, the NRC staff requested a meeting for further discussion of the schedules and topic resolutions in order to reach agreement between GPUNC and the NRC staf f. That meeting was held on November 18, 1982 and we were able to reach ageement on all items.

ATTACHMENT I to this letter lists schedule and resolution agreed at our meeting for each of the topics.

o37 8212060247 821129 PDR ADOCK 05000219 P PDR GPU Nuclear is a part of the General Public Utihties System

Mr. D. M. Crutchfield .

Page 2 ,

November 29, 1982 We are also transmitting the revised integrate.J assessment summary table (Table 4.1 of draft NUREG 0822) as ATTACHMENT II. The revised table reflects the agreements reached during our November 18, 1982, meeting with the NRC staff. The revised portions of the table are indicated by double asterisks (**).

Very truly yours,

, ok P. R. Clark Executive Vice President bif Attachments cc: Ronald C. Haynes, Administrator Region 1 U. S. Nuclear Regulatory Comnission 631 Park Avenue King of Prussia, NJ 19406 i NRC Resident Inspector j Oyster Creek Nuclear Generating Station

! Forked River, NJ 08731 i

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ATTACHMENT I SEP TOPIC SCHEDULES AND RESOLUTIONS AGREED ON NOVEMBER 18,1982 BETWEEN GPUNC AND THE NRC STAFF TOPIC NO. III-5E Pipe Break Outside Containment 4

As stated in our November 16, 1982 letter, GPUNC will prepare and

! transmit a report to the NRC by February 28, 1983, which predicts crack growth rate in the Oyser Creek isolation condenser lines. Based on our findings GPUNC will propose .an appropriate leakage detection method with adequate sensitivity. Our preliminary evaluation indicates the extremely j slow growth rate will allow the use of a crack with suf ficiently large

leak rate for visual and audio detection TOPIC NO. V-5 Reactor Coolant Pressure Boundary Leakage Detection CPUNC will perform a '_' leak before break" analysis for the most j limiting piping to justify the sensitivity of the current leak detection systems available in the containment sump. Results of the analysis will be transmitted .to the NRC by June 30, 1983. GPUNC will also propose Technical Specification change before Cycle 10 startup to include operability requirement of the leakage detection systems inside containment. GPUNC will prepare action statements in Technical Specifications.

TOPIC NO. VIII-3B DC Power System Bus Voltage Monitoring and Annunciation Our November 16, 1982 letter stated that the battery status alarms will be installed during Cycle 11 refueling outage due to the number of modifications already planned in the control room during the l forthcoming (Cycle 10) outage. However, the NRC ' staff requested an intermediate resolution of this issue since PRA performed by the NRC consultant rated this issue of high risk importance. GPUNC will provide an intermediate resolution which consists of periodic inspections of the i

safety related battery systems such as verification of battery breaker position, battery current, charger current, etc. Plant inspection procedure will be revised to include the periodic inspection of the battery systems before Cycle 10 starup. The intermediate resolution will be in effect until the installation of the battery status alarms during Cycle 11 outage.

TOPIC NO. V-12A Water Purity of BWR Primary Coolant Our November 16 1982 letter to the NRC stated that GPUNC will revise Oyster Creek Technical Specifications after examining our Cycle 10 experience. However, during our meeting on November 18, 1982, the NRC staf f requested GPUNC to revise Technical Specifications before Cycle 10 startup. GPUNC agreed to revise Technical Specifications prior to Cycle

10 startup incorporating Reg. Guide 1.56 limits for conductivity and chloride concentration. Action statements will be proposed by GPUNC.

The NRC staff concluded in the meeting that an issuance of a special report rather than an LER by GPUNC would be acceptable following a violation of the Reg. Guide limit for conductivity. The existing limit for conductivity will still remain as an upper bound for the plant operation.

TOPIC NO. XV-16, XV-18 Radiological Consequences of Failure of Small Lines Carrying Primary Coolant and Main Steam Lines Outside Containment GPUNC will revise Oyster Creek Technical Specification adopting General Electric Standard Technical Specifications for iodine limits before Cycle 10 startup. GPUNC will propose action statements.

TOPIC NO. III-4A Tornado Missiles GPUNC will provide a portable pump and hoses for shutdown heat removal during a postulated tornado missile incident. The pump and hoses will be housed in the area of Reactor Building which is protected from the tornado missiles and flooding (the pump will also be used as a redundant pump to the existing condensate transfer pump during a postulated maximum hurricane flood -See SEP Topic II-3B in ATTACHMENT II). Since placing of the pump and hoses is not outage related, GPUNC will complete the project by the end of 1984. The project also include revising the plant emergency procedure for tornado incidents.

TOPIC NO. VI-7.A.3 Emergency Core Cooling System Actuation System TOPIC NO. VI-10A Testing of Reactor Trip System and ESF, Including Response Time Testing Before Cycle 10 startup GPUNC will revise Technical l Specifications to include the emergency condenser logic testing and the i

reactor trip system testing in accordance with the instruction provided I

in our current surveillance procedures for both systems.

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ATTACilMENT II yvi lohle 4.1 Int egra ted 4>>ev.ni.-ut simni.o y n Tech. Spec.

g SEP modifications so Topic Sect,on i Comple-

• required from llat ti a t Litensee tion No. 11 o . Title SEP review requirements PRA en agree > date rating S 11-3.8, 4.1(1) Condensate Transfer P4mip 11-3.8.1, Power flo See SEP Topic No. III-4A** yes* 12/84** -

Section No. 4.6.4 I l- 3. C 4.l(2) Flooding' Level Procedures flo None - - -

4.1(3) Canal Water tevel 11 o Install antumatic water Instrumentation Ye> Cycle XI -

level instramu nt.stion in the intate canal.

4.1(4) Isolation Condenser No Demonstrate minimum quantity Flooding Yes Cycle X -

of water maintained in condensate storage t .sk

• ,s sufficient for long-term

1. cooling and inclinie minimum m

inventory in plant procedures.

4.l(S) Low Water Level Shutdown No lione - - '

4.1(6) llurricane Flooding of flo Revise escrgency procedures Pumps Yes Cycle X -

to ident ily alternate water sources anel Ilow paths shoulil Icw elevation pumps be -

f luo.leil.

4.1(7) Flooding Elevation tio Evalisat.t e onseiginences of Yes 2/83** -

ofigas tenilding flooding and confirm all other entrance

. levels .ibuve 23.S IL.

<ee footnotes at end of table.

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@m lable 4;l (Continued) s n _ _ -

Tech. Spec.

2 SEP modifications

• Topic Section Comple-required from Backlit No. No. Title Licensee Lion g

T SEP review require:aents agrees date PRA rating Il-3.C 4.1(8) Groundwater Elevation No See item 4.4(2). .

4.1(9) Roof Drains No Install scarppers in the Yes Cycle X -

reactor building and turbine +6 mo.

building par.spet s.

111-1 4.2 Classification of Struc- No tures, Compon1nts, and Evaluate design of specified Yes 10 CFR -

Systems compontuts on a sampling 50.71 basis, opgrade if necessary, (e)(3)(ii) and din.ument classification in FSAH update.

, 111-2 4.3.1 Reactor Building Steel No a

Structure Above the Analyse and identify any Yes 12/82** -

0 Operating Floor needed upgrading of reactor building upper steel structure for wind loads.

4.3.2 Ventilation Stack No Analyte and identify any Yes 12/82** _

needed ig. grading of ventila-tion start for wind loads.

4.3.3 Effects of Failure of No Nonseismic Category I Analyic turbine building Yes 6/83 -

Structures capacity for wind loads, evaluate consequences of failure end idiniify any needed upgrading.

4.3.4 Components Not Enclosed No None -

in Qualified Structures - -

4.3.5 . Exterior Hasonry Walls No fione - - -

See footnotes at end of table.

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ATTACWfENT II y lable 4.1 (Centinued) n Tech. Spec.

-s SEP modifications Comple-E Topic Section required from Backtit

• No. No. Title Licensee Lion PRA vi SEP review requirements agrees date rating 5 III-2 4.3.6 Roof Decks No Provide analysis or reactor 12/82** -

Yes buildinig roof.

• Analyze capacity of turbine Yes 6/83 -

building; s ont to withstand wind lo.nis.

4.3.7 Intake Structure, Oil N(, Analyte tapacity to with- Yes -

,, lanks, and Diesel Gener- stand winni and tornado 12/82**

ator Building loads arid upstratie, if necessary.

+ 4.3.8 toad Combinations No Submit analyses demon- yes * ,6/83** ,

strat feig; wisi(I goa,l> were 8 properly combined with other specified loads.

4.3.9 Soil and foundation No tione - - -

Capacities III-3.A 4.4(1) lifdrostatic Loads No None - - -

(Combination) 4.4(2) liydrostatic Loads No Evaltiati short ilureition Yes 4/83 -

(Short-Duration) hydrostatic loacts on and floatat ioni giotential of structures essent.ial to sale shuliluun in rauijunction with I lui..lis.;; emerijency procedin c3 (liem 4.l(6)).

4.4(3) Below-Grade Penetration No ll uic - - -

Flooding r

$, latile 4.1 (Continued) o e

@ Tech. Spec.

n SEP s Topic Section modificalions required from Dacilit Comple-

$ No. No. Title Licensee Lion PRA x SEP review iequircuents agrees d.ite rating

$o III-3.C 4.5.1 Intake and Discharge Canals No Itune - - -

4.5.2 Intake Structure Trash No Racks and Intake Screens formalize existing inspec- Yes* Cycle X** -

tion pr.n.tice as p.u t of shifL tin nuver or inservice

- inspet.t. ion (ISI) procedures nutil w. ster level moslifi- '

cdtiola ib Complete (ltene 4.1(3)).

4.5.3 Roof Drains No See item 4.l(2) - - -

4.5.4 Inspection Program No fievelop .nnt implem.:nt a Yes Cycle X -

, formal inspection program s

for water control structures.

@ III-4.A 4.6.1 Emergency Diesel No Analyze potential for and Yes 3/83 Generators and fuel co, sequence > of tornado-Oil Day Tank siissile damage of the diesel generator insilding.

4.6.2 Hechanical Equipment No Access Area Evaluate the potential for Yes I/83 -

and consequences of tornado-missile impact in the reactor fusilding access alour region and ident ily any ni<essary correct ive attinns.

4.6.3 Control Room, Reactor No None Building, and Turbine - - -

Building Heating,

.VentilatinD, and Air Conditioning (HVAC)

Systesis See footnotes at end of table. '

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ATTACHME.Vr II o

m lable 4.1 (Continuseil)

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lech. Spec.

2 8*

SEP modificalions

• Topic Section Comple-required from BackIit

• No. No. Title SEP review I.icensee tion PRA rn requirements agrees d.ste rating T

III-4.A 4.6.4 Condensate Storage Tank, No Provide protection tcr Yes** .12/84** -

Torus Water Storage Tank, suffic.ient systems and and Service Water and compon. nt > to ensure a safe Emergency Service Water Pumps shutdown in the event of damaije tioin torn.iilo missiles. 6 flooding III-4.B 4. 7 Turbine Missiles No inspee.t turbine .n d propose Yes 12/84 -

inspection frequency based on results.

Justif y nionitorin!; program Yes 2/83* -

1. for m.iin ste.im anit reheat e , control valves.

o III-4.D 4.8.1 Truck Explosion No tione - - -

4.8.2 Aircraf t llazards No fvaluate potenti.il for or Yes 3/83 -

consequen.es of aircraf t impat. t .

III-5.A 4.9(1) Cascading Pipe Breaks No , See llein 4.16. - - -

4.9(2) Jet Impingement Effects No tivne - - -

4.9(3) Drywell Penetration No flune - - -

See footnotes at end of table.

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ATTACHMENT II o

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un I 8181c 4.1 (l'.,nt inn. .I) et m

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n lesh. Spec.

2 SEP Topic modifications Section requireil trom II.n l i i t Comple-No. No. Title Str revieu Licensee Lion PRA m requ i r. i ..ni , agrees date rating 111-5.B 4.10(1) LOCA Dutside Containment No Evalu.ite and iilentify any Yes 3/83 -

sieeded upgrading of the main steam and reactor water cleanup (RWCU) piping outside containment to precluile an unisolatable break out s i<te cont ainment.

4.10(2) Emergency Condenser No

! Isolation , t. valuate and itlent ity modi- Ye:. Cycle X -

. ic.ition to provide leakage dele.:liuss in enstere flaws

' woulillie detected before

.n. .

pipe fireak occurs.

s m 111-6 4.11(1) Piping Systems H No Analyze on a sampling Yes Cycle X -

l> asis and verity ailequacy ut support desiipis for the

,eismic resist.ince of speciIled pipinig systems.

4.11(2) Mechanical Equipment No llem..n,trate th.it the control Ye. 12/82* -

rod ih ive sysicm .nni vesse 1 >

intern ils h.sve :,ull icient - ,

c.ip.u i t y t o re . is t a sa fe

~

.,butlown earthquate or take c.orr..Isve attinn. ~

4.11(3) Electrical Equipment No

• Reevalu.ite 4160-V switch- Yes Cycle X -

gear p.ini!! .eli hdreig ? and sI dl*l ilesnon.Ir.ite, on a sampling 83 an).

b.isi . .nlequ.ny of electri-e . I p.o e i .ppori3. .

See footnotes at end of table.

ATTACFBIENT II y Table 4.1 (Contimacil) m n fech. Spec.

s SEP n.oilii icai ions

[$ Topic Section reiguireil f rom u.n l i t Ces.ep t e-

• Ii.ensee Linn No. No. Title SCP eview re.peir er.. n ts PRA m .

a!pye , elo t e rating

$ III-6 4.11(4) Ability of Safety- No (ti n i.-

Related Electrical -

Equipment to Function 4.11(5) Qualification of Cable No Provide plan to implement Yes 1

Trays Cycle X -

results of $LP Owners

(;roup Program on a t-lant-

, pes. i t ic bas is.

111-7.8 4.12 Design Codes, Design tio Criteria, Load I v.sluate arte.pucy of Ye:, 6/83 -

original design criteria Combinations and Reactor un 4 :,aniplinig basis for Cavity Design Criteria T.

un

.I.e. e l ic.I st rot.tural ele ent,.

1. 9 III-8.A 4.13 Loose-Parts Honitoring No

>  !!.ine - -

i and Core Barrel Low Vibration Monitoring Ill-10.A 4.14(1) Thermal Overload Bypass No tvaluate theraul overload Ye> Mediumi leyp.e.scs for engineered 12/82**

astty scatures (tSt) valves.

4.14(2) Magnetic Trip Breakers No flun.- - - -

IV-2 . 4.15 Reactivity Control Systems, No it..ne Including Functional Low Design and Protection -

A0 ainst Single Falinres ,

J .

See footnotes at end of table.

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• < Table 4.1 (Continneil)

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Tecli. Spec.

Q SEP modi fications Cumple-

$ Topic Section required from liai.t ! i t -

F No. . No. Title Licensee Lion .PRA vi SEP review rerin i n en.en ts a jrees date rat.ing

$ V-5 4.16.1 Airborne Particulate and No Make these monitors yes*

Cycle X** tow Gaseous Radioactivity operational Honitoring

. topic lil-5.A analysis.

4.16.2 Operability Requirements Yes include lealage iletection Yes** 12/82 -

.ytt.:m IimiLing t.ondif.lons N for operation in lechnical

• SpeniiicaLinn>. "

( N.. Intersystem Leakage No None - - -

t 4.16.4 Reactor, Coolant N.o Non.-

.- y Inventory Balances .

V-6 4.17 Reactor Vessel Integrity No Submit a plan for the Yes 12/82**

material surveillance Caphilles. -

V-10.8 4.18 Residual lleat Removal x No

% +

Review and upgraile, if Yes Before* Low System Reliability nete:.sary, shutdown Cycle 10 proi c lures to specify - Startup _

" alternate sources of '

'. f-C =

a water for primary and -

~ secon.l.ory mateop, with -

partioilar at tention to ', r.

cxternal event:.. '

• a V-II: A 4.19 Requirements 'foir Isolation No

• Demonstr.ile selief capacity Ye:,- 1/83 ' '

, of Hign- and Low-Pr' essure and arr. i.t.il.le i unsequences , '

. tcf Systems l or filent s i.. . orrec t ive action 4

to p ru t . . i R.! il ,y , t em.

> ~

See f ootnotes at end of tafale.

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.7 lable 4.1 (Cont iemeil) f' '

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lech. Spec.

9 SEP modifications Comple-

@ lopic Section required from Backlit l icensee tion PRA x No. No. Title SEP review m

renguirements aurec> i.a t e rating E V-12.A 4.20 Water Purity of BWR Yes implement propused procedure Yes* Cycle X** -

l Primary Coolant unit mi,ility lecluiical Specifi-I cdliutts to be consistent.

VI-1 4.21.1 Organic Materials No In31 ert and repair, if Yes Cycle X -

nec essar y, drywell coatings '6 me.

and secoat the torus.

l ,,

4.21.2 Postaccident Chemistry No None - - -

VI-4 4.22.1 Locked-Closed Valves No Provide ><.hedule to implement Yi: . 11/82 Low physical lockinig devices to ca,ure valves are not y in.sdvertent ly opened. .

4.22.2 Remote Manual Valves No Yes. Cycle X**

Provide leakaue ifetection ,

dild, il nece: sary, relocate the operating station for i>olat ion valves in the coniainment spray and core spr.sy systems.

4.22.3 Valve Location No lione - - -

4.22.4 Instrument Lines No Non.- - - -

4.22.5 Valve Location and Type No None - - -

4.22.6 Remote Manual Valves No None - - -

VI-7.A.3 4.23 Emergency Core Cooling Yes includ. em.:ry.ncy condenser Yes** Gycle X** -

System Actuation System logic ..iis,9 in t rie lechoi. ..I Lpei i t i4.itions.

See footnotes at end of tahle.

ATTACllMENT II 5< lable 4.1 (Corit inie.il) sn

. . . . . . - ~ - - - - ~ ~ - -

s tech. Spec.

n SEP -

nindifications Topic Section Comple-2 required froni llack t i t Licen,ce Lion PRA

1. D No. No. Title SEP review 7e requirem..nt, ' agree:. state rating T

VI-7.A.4 4.24 Core Spray Nozzle No None - - -

Effectiveness VI-7.C.1 4.25(1) AC Automatic Bus Transfers No tvalu.ite the exi, ting Yes* 12/u2 Hediuin dtituinJt ir. httb I I*ettid fers ant! islent ify currecLive action:, to ensnre f aulted loads would sent lie t ran>l en reil.

4.25(2) DC Automatic Bus Transfers No flune - - -

VI-10.A 4.26.1 Response-Time Testing No lione - -

tow -

i 4.26.2 Instrumentation for Reactor No

• $ Verity .sti salety logic Yes 12/02 -

Trip System (RTS) lesting channels tied to the reactor ainde switch are tested by proceifure. .

Yes - luclule logic channel Yes** Cycle X** -

Lestinel in Icchnical Specilications.

4.26.3 Dual-Channel Testing No tione - - -

Vil-1.A 4.27(1) flux Monitoring Isolation No Perten m solinre m.. le and Yes 12/u2 tow

, cfici.I .indlysi:, t o <!etermine whether i:.olation elevices dt'e t's sjtlires! .48141 iali fility any vecih a! ul.sgr.nlinti.

4.27(2) Reactor Protection system flo ~ 1...,i .. l l r i c. il (RPS) Protective Trip 1.. ..tec t i on Yes rycle XI -

,, i t i.. I:.

i.ou.r upply

.o..! 1;l", a ,1 cr t .u e See f ootnotes at end of table.

ATTACHEVT II y ui lable 4.1 (Continued)

C+

q _ _ . _ . . _ . _ _ . _ _ . . . . . _ - -

n Tech. Spec.

s SEP

@ moditicaLions lopic Section requirect trom Backiit I:omisle-

• No. No. licen,ee tion PRA litle un SEP review requi reroent s agrees date rating

$ Vll-1.8 4.28 Trip Uncertainty and Setpoint Analysis Review No Install analog trip system. . Ye:, Cycle XI Low of Operating Data Dase

. Vil-2 4.29 Engineered Safety features -

System Control Logic and See Item 4.14(1). - -

Low Design Vll-3 4.30 Systems Required for Safe No Shutdown Provide minimum inventory - -

Low f or condensate storage tank

. as a water source for flood-ing event s (lien: 4.l(4))

i asid ident iry non-I SF equip-g ment in couldown procedures (Item 4. It!).

Vill-2 4.31 Onsite Emergency Power No Hodify annunciator > to Yes Cycle XI Low Systems (Diesel Generator) conform to IEt t Std.

279-19/l and hypass two trips (voltage-ampere reactive and reverse power) durinig accident conditions.

Vill-3.B 4.32- DC Power System Bus No Voltage Monitoring and Scheduh in>tallation of Yet, 12/82** liigh Anaunciation specified hattery status alarm,.

Vill-4 4.33 Electrical Penetrations of No

.None - - -

Reactor Containment See footnotes at enr1 of table.

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ATTACHMENT II o-

• < Iafile 4.1 (Cor.: isumil) us

' --- - ~ ~ - -

Tech. Spec.

Q SEP modificaLions

% Topic Section Comple-7t- reignired irom IM:t it L icen:.ce t it,n tio. No. Title SEP review PRA v> i ci:n ii .-n..-n t > aurces state rating Q IX-5 4.34(1) Restoration of Ventilation tio tvain.it e .niit i ev ine, i f . Ye:, 3/83 -

nece.s..ry, the lo w-o f-ofisite poveer pnn:edures to en:, ore that restoration of ventilJtion sy*,tems Will not overload the aliesels.

4.34(2) Reactor Building No None Ventilation - - -

4.34(3) Core Spray and Containment No Spray Pump Ventilation llemonstrate subject pumps Yes 3/83 -

can operate with a loss

? of vent ilation, or identify y corrn Live act iosi, as nece n.iry.

4.34(4) Battery, Motor-Genarator, No and Switchgear Ventilation Ivalo.ite eltect > of loss of Yes 12/83 -

ventilation to the subject room , anil islent ify any needed upgrading. .

XV-1 4.35 Decrease in feedwater Ho Itone Temperature, Incrsase in - - -

Feedwater Flow, and In- .

crease in Steam Flow and Inadvertent Opening of a Steam Generator Relief or Safety Valve .

XV-15 4.36 Radiological Conseituences Yes in.plement BWR Standard Yes** Cycle X**

of failure of Small Lines lechnii:al Specif ication Carrying Primary Coolant Outside Containment limit 1.n prim.iry toolant

.ir i i v i t f.

o 5<

un I.d,le 4.1 (G.nt inue.Il d

m a fec.h. Spec.

Q SEP modificotions Topic Section Cinnple-

$ 11 o . No. Title required from Udt.k r i t Licen.cc Iinn PRA

-. SEP review requireu.ents aurces date rating g XV-18 4.37 Radiological Consequences -

of a Main Steam Line see llem 4.36. .

Failure Outside Containment XV-19 4.38 Loss-of-Coolant Accidents tio Develop and implement a Resulting from Spectrum Yes Cycle XI -

of Postulated Pipe Breaks preventive maintenance program for the main steam

': Within the Reactor Cnolant Pressnre Boundary isolation valves or justify existing maintenance based on operating experience.

~

Sibmit results of evalua- Before* Cycle X -

' i Lion int luding testing Cycle 10 g experieni:e. 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 outage by core cycle.

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