Text

Systematic Evaluation Program Status Summary Report.Data as of October 31,1982.(Buff Book)
	ML20069M552
Person / Time
Issue date:	11/30/1982
From:	; NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
To:	;
References
	NUREG-0485, NUREG-0485-V04-N10, NUREG-485, NUREG-485-V4-N10, NUDOCS 8212010138
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'238 l$h!

NUREG-0485 1 %

Vol. 4, No.10 g

October 31,1982 1, ;

8 l SYSTEMATIC EVALUATION PROGRAM STATUS

SUMMARY

REPORT i

l lINITED STATES NUCLEAR REGULATORY COMMISSION v* "%,

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1 Available from NRC/GPO Sales Program -

Superintendent of Docun.ents Government Printing Office Washington, D. C. 20402 A year's subscription consists of 12 issues for this publication.

Single copies of this publication are available fros., National Technical information Service, Springfield, VA 22161.

- Microfiche of single copies are avai!able from NRC/GPO Sales Program Washington, D. C,20555 L

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NUREG-0485 l

Vol. 4, No.10 1

October 31,1982

.i I

i SYSTEMATIC EVALUATION PROGRAM i

STATUS

SUMMARY

REPORT i

i Prepared for: 0FFICE OF MUCLEAR REACTOR REGULATION Prepared By: 0FFICE OF RESOURCE MANAGEMENT I

UNITED STATES NUCLEAR REGULATORY COMMISSION

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William T. Russell, Chief Dennis M. Crutchfield, Chief Systematic Evaluation Program Branch Operating Reactors Branch 5 i

f u ar Reactor Regulation O

e of u ear Reactor Regulation

TABLE OF CONTENTS 1

l SECTION I SECTION !!

SECTION lli SEP TOPIC LIST '

1-2!n1-3 BIG ROCK POINT 2-2 to 2-5 PALISADES 3-2 to 3-3 DRESDEN 1 2-6 GINNA 3-4 to 3-5 DESIGN BASIS EVENT 1-4 DRESDEN 2 2-7 to 2-10 DRESDEN 2 3 6 to 3-9 GROUP DESCRIPTION GINNA 2-11 to 214 OYSTER CREEK 3-10 to 3-12 DEFINITIONS OF STATUS 1-5 HADDAM NECK 2-15 to 2-18 MILLSTONE 1 3-13 to 3-16 LACROSSE 2-19 to 2-22 SAN ONOF,RE 3-17 to 3-20 SEP TOPIC

SUMMARY

1-6 MILLSTONE 1 2-23 to 2-26 BIG ROCK POINT 3-21 to 3-24 STATUS REPORT OYSTER CREEK 2-27 to 2-30 HADDAM NECK 3-25 to 3-28 ALISADES 2-31 to 2-34 PROGRESS TOWARD 1-7 YANKEE 3-29 to 3-32 COMPLETION (Graph)

SAN ONOFRE 2-35 to 2-38 LACROSSE 3-33 to 3-36 YANKF.E 2-39 to 2-42 INTEGRATED PLANT 1-8 SAFETY ASSESSMENT SCHEDULE SEP TOPlc STATUS BY 1-9 REVIEW DIVISION (Summary Table)

SEP topic STATUS BY 1-10 to 1-11 REVIEW DIVISION (Graphs)

I SEP -f0PIC SUBMITTAL'.;

1-12 thru 1-13

- BY LICENSEES (Graphs) 7_

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SYSTEMATIC EVALUATION PROGRAM TOPIC LIST 1

It'IC 8 IIIII foega fiftt TWIC P 117tl IV.2 weacttutty Control Systens including Functional

!!.1 A. lac tusion Area Autnority aad r..et rol ggg.g a,

y,,,,49 w,gg,ges Vestgm and Prctectten Against Stagte f attures H. conviat son Distritmt.9n

,14 3 SaR Jet Pumps Operating Indications

. Potential waaards or (manges te Dotential g, y,rtin, p,ssiles v.1 Cogitance with Codes and Standards (ID CFh parares D e to Tran% ort at toa. i nst it ut iona l

$g, Industr'at aad 4tlitary tacilities ggg.4 C. Internally Gecerated misst es l

It.2 A. Severe seather Pheno.ena 12 Applicable Code Cases m teorological measureairats Progra, V.3 Dwerpressertsation Protection

8. uns tte e

(. Atwnpneric Transport and Dif fusion (fiarac.

W.4 Piptag and Safe Cnd Integrity teristics for Accident Analysis o, 5,te Prostetty missiles (including Aircraf t)

V.5 Reactor Coolant Pressure Boundary (RCP8)

' D.

Avat laot tity of Meteorological Data in the 111 5 A. Ef fects of Pipe Sreen on Structures. Syste'is teakage. Detection Control Room and (oionents iestae Containment g

11 3

. Hydrologic Descriptior.

8. Pipe Breat Dutside Containrent g

g W.8 Steam Generator ($G) Integrity

8. Ilooding Potential and Protect ton Pequire.

cent s V-9 Reactor Core Isolation Cooling System (SWN) til.1 A. Inservice lespection, including Prestressed t

Cas. ability of Opersting Plant to Cove Concrete Contatncents with tither Grauted V.

. RH at E nchangn allums eith Dest e Basis f f ooding Condit tons or tingrouted Tendons j

t. La* ety-related water hoply (Ultimate Heat

8. Destgn Codes. Design Criteria. Load S. #HR Re16 ability S i na tuM5))

Conetnations. and kcactor Cavity Desip g

y g p, t!.4

.cology a%t '.eismoloqv Pmssum Systems C. Delastnation of Prestressed Concrete Con.

. Tect aitc Province tatnnent 5tructuren j

B. P rosioit r of Capable f ectonic *.t ru6tu es D. Contatnpe.nt 5tructural Integrity Tests V-12 A. Water Purity of Boiling Water Reettor r

in I'lant 5 it init,

Primary Coolant

!!l.d A. A t ose Parts Monitoring and Core Sarrel W 1 ),

Water Hammer j

L. Mist s.rital Seiwit et y site a.1 Miles of vibration Monitoring Plant 8L Control Rod Drt ve perhaatse Integrity VI.)

Organic Matertals and Post Accident l

( hemistry I

St at>i t i t y of Slees C. Irradiation Dansgr. Use of Sensitised Stainless 5 teel and I atigue Restst a%,

VI.2 A. Pressure. Suppression Type SidR Containments t. Dam latr9r ity

8. Subcoapartment Analysts

, D. Core Lup.. orts and f uel l ategrity I. '.ett le=nt of Ioundet ions and Ituried C. Ice Condenser Containment 111 9

Sut' port lategrity (quip.,.t D. Mass and Energy Release f or Possible Pipe 1 ] ]. i t'.

A. Thersel.0verload Prot ect ton f or Fotors M Break Inside Containnerat

!!!.1

' l essif ic at ion of St ruttu es twe eent s and Mot or-operated valves r

. st ean l '. i wi c 4~4 Nality)

8. Pus lyencel Integrity VI.3 Containment Pressure and tiest Rene,al

!!!./

n'ad and f ornado t uao ngs Capabtlity

!!!.3 A. I f f ect s of Hiep h.ef er tevel on S truct ureg t i CP %s and DistnAr Jr Valves Vl*4 Containment Isolation System

!!!.11' ors oncat I nt egrit y VI.5 Costustible Gas Control I

81. St ruttural and Ut me' C onsequee< es (e.g.

VI4 Contatnnent Leak Testing 6 iwd.ny of saf et74 elate.1 I quipment ic P ee eat g) nf I a e lure of p e.dredra i n 5,. t eug

! ! !.1/

tevironwat al QualitiCat tom of Saf ety Pelated i

t outparnt leservit e I nvect ion.it aiater t.ont rol %t ruc-IV-l b (!& eratio's with t r.s Than All Loops In-%ervice t u res 12

SYSTEMATIC EVALUATION PROGRAM TOPIC LIST YnPIC a flTit 7"PIC #

f!TLt TOPf C #

TifLE W l-7. A

1. (CC5 Re-evaluation t o Account i eessed y g g.g lestruments f or Monttoring Radiation and Process IV-5 Loss of storaal Fee *ater Flow Vessel Head Teas eratu e y artables Durin, Acct ornt s IV-6 Fechater System Pipe 8reats Inside and Outside

2. Upper Plen m inject mn Vll-6 f requency Decay Contatnnent (Pldit) u

3. ECC5 Actuation System Vll-7 Acceptabt tity of Swing Bus Design on 8#-4 g y. 7 Reactor Coolant Pump Rotor Setture and Plants Reactor Coolant Pump $haf t Break

4. Core Spray horrie i f f ectiveness Vill-l A. Potential Equipment Failures Associated with IV-8 Control Rod Nisoperation (System Malfunction V !- 1. 5 F 55 Swit chover f rom injection to Recirculation a Degraded Grtd Volta 9e or Operator Error) m de ( Autoawtic LCC5 Realign =nt) o V i t t-2 Costte E sergency Power Systems - Diesel IV-9 Startup or an inactive toop or Rectrculation W l-1.C f CC5 S t agie 5 a t te m ert on and Require-Generat o" toop at an Incorrect Terperature, and Flow meets f or t ort mq *

=ec t o Valves Controller Malfunction Causing an increase in including Ince6 *a w l aterloct s on Vill-3 A. Station Battery Capacity fest Requiremrnts ga gor, y]nu gate IV-10 Chemical and volene Control System Malfunction

8. DC Power System Bus Voltage Monitoring and that Results in a Decrease in the Boron Concen-

1. Appendi a IL E lettrical lastrumentation Annu nci at ion tratton in the Reactor Coolant (Piat) and Controi (110) Re-reviews Vill-4 Electrical Penetrations of Reactor Containcent IV-Il Inadvertent toadtag and Operation of a Fuel

2. F a 6 fare Mo e Analysis - ECC5 Assenely in an leproper Postllon g,

3. The if f ect of PW t oop Isolat 6on Valve IV-12 Spectrum of Rod Ejectton Accidents (Piet)

Closure Durteg a tur A on (005 Perf orsunce 11-2 Overhead Handitag Systems - Cranes

1 - 7. 13 Long Term Cocieng - Passive f allures (e.g..

IV-13 Spectrum of Rod Drop Accidents (Stat)

Flooding of Redundant Corponcats) 13-3 Statton Service and Cooling ilater Systems IV-14 Inadvertent Operation of ECC5 and CheatC41 V I-F E ICC5 Sum Design and Test for Rectrculation II-4 Boron Addition System and Volume Control System Malfunction that increases Resctor Coolant inventory 11-5 Ventilation Systems V. 7.F Accuse,lator Isolation Valves Power and Control IV-15 Inadvertent Opening of a Past Pressortaer Safety-

System Design

11 6 Fire Protection Relief Vee or a $d SafetWief Vh V'-8 Coetrol Room Habitability I

Aunittary f eedwater System IV-16 Radtological Consequences of Failure of Small Lines Carrying Primary Coclant Outside Contain-V !- 9 Pain Steam Line Isolation Seal System - Bd 11-1 Appendia I ment VI-10 A. Testing of Reactor irtp System and En9ineered Il-2 Radiological (Ef fluent and Process) Monitortng gy.l y Steam Generator Safety Features inetuding Response f ew Systems Tube Failure (PA)

Testing 1111-1 Conduct of Operat nos IV-18 Radiological Consequences of Main Steam

b. Shared E ngineered 5af ety Features. On-site Line Fatture Outside Containment (8ast)

Emerge cy Power, and ServtC2 Systems f or Ill!-y Saf eguards/in&stetal Security n

Mult tale Unit f acilities IV-19 Loss-of-Coolant Accidents Resulting f rom I V-1 Decrease in F ee4.at er f ewerature, increase in Spectrum of Postulated Piping Sreaks Idtthin V i l-1 A. Isolat ton of Reactor Protect ton System f rom icensater F Inw. Increase in Steam Flow and the Reactor Coolant Pressert Soundary

%on-Saf et y Systems. Including Qualifications inadvert ent Openeng of a Steam benerator Reitef of Isolation Devices af ety Valve IV-20 Radtological Consequences of Fuel Damagtag or >

Accidents (Inside and Outside Containment)

8. Trip Uncertatnty and Setpoint Analysts Reutem IV-2 se(t rum of Steam System Piping f ailures Inside IV-21 5 pent Fuel Cask Crop Accidents of Operating Data Base

.nd Uuts 6de of Containaent (P=k)

Vil-2 tagineered Saf ety Features ([5F ) System Control IV-3 toss of E nternal Load. Turtnne irtp, toss of A"

L ogic a nd Des t gn Condenser vacuum. Closure of Main Steam isola-IV-23 Multiple Tube Failures in Steam Generators t ton valve (BA). and Steam Pressure Regalator Vil-3

',ystees Required f or *>af e %utdown tailure (Closed)

IV-24 Loss of All A-C Power I os

-tmergency A-C P wer to the St ation Vll-4 I f f ects of f ailure en hon-Saf ety aclated g

IVI Techatcal Spectf tcations system on Selected t agineered Saf ety f eatures IVil Operattonal QA Program

Topic deleted from SEP program due to duplication by Three Mile Islar.d (TMil NRC Action Plan. Unresolved Safety issue or other SEP Topic per May 7,1981 letter from G. Leines to all SEP Leconeses 1-3

DES GN BASIS EVENT REV EWS THIS SECTION DEFINES DESIGN BASIS EVENT (DBE) REVIEWS FOR THE ELEVEN SEP FACILITIES N

_8 !C L 5' Bea D8E TFf;,J!$7 Bue 4 e's* DRE TOPIC 115T Trameet Groon Acc idet and Traasteet Groups D.t. f..TQt:C

'!Ta t-Cet vic TITLE

~~

broot I s u-6 Cecrease ta feed ater targerature 6 t 0005 p e-1 Lecrease ir 'eehate. torperatare (8=L t v-1

!acrease ta feed =ater flo=

' t 0005 1;-3.A 47...

p drologic descrtettoa y

s *. s ab' lacrease in feto. ster fin fe1

!acrease ta stea*. fim I l - 3. 8 Floodtag potectlet and protec tica s.-

lat resse ta stea-81o.

se 9 S tart-up cf inactive 1000 and flow require =*ats (caraotlity of operattag so-Imae.erteet crealag o' stear coetroller malfs ction plant to cope with deston bests floodtag a

gee ator relief / safety val.,

s o-3 laadverteat closure of osin stea-condition) s*-4 S tart..

u' inactive loc; 1 solation valve 11-3.C Safety related water supply (ultteate E.l' Sys ter mal'.vt toa c a.g i a; hea t s ent )

Gra g~!!

s. 3 Loss of asternal load G a,

'~

'h-3 se i Los e r.' esternal load Tu ttae trip

41 Ai r3

? roiae tets s v-3 Loss of conde*ser escuur

' ~

!! a. A Tectonic province r

e

!!.a.g Prontelty of capable tectoats structores i

so-3 L as o* coede-ser v ac uwe as-3 Steam pressure reg.1stor f atle e near Elsat r

ne-3 S teav p r es s ore regulat:r f ailu e a*-S Loss of feedaster flow II a.C esistorical seismicit3 withtr 200 otles r

au-

.oss o' f eed.ater f i o.

of plaat E. -t teamster syster stpe eresa Gro.3 s.- 1c nadiotopcal Coaseovences of a 14 -

Stattitty of slopes e ta 5ter Line Failere Outs tde s

i, I n-2 S teer f i r:e t res* ieu se t or ts wee t Coa tainrent pel55tE GatkA!!04 I t !-a Tornado etssiles 3.-?

S tear 1

r. creas outside cortairricat A't? PROTEG:0N~ ~ - ~ Ill-a t Turbine missiles Grcq_ !.

a b-a Loss c' A power t : sta tion

"- ' ~

!!!-a t latercally generated =1ssiles

*. 4 3.-a Lou of AC p;mer to statioe a=e tI 8 eries 111-4,0 5tte premietty missiles (incivding a.e i1 + a se.

aircraf t)

(

QD5

11-2 wind and toccado loadiae Gro a n.-7 Loss of forted coolaat f to"

.c W

tras of f arc es (talaat flo.

sk 7 Prowery pu s rotor setzu e a

r s.-

Pr n y prs rotor seizure Iv-7 Primary pu p snaf t treak m

s. 7 Friors puas saa't breah Gro.p; s h-e Uacoetrolled rod assuetly attedrawal a

e.-f woetrclied rod assertly a tta-at po=er dramal at go.er a s-F Unco trolled rod assertly eithdrawal La.oetrolle1 rod csserely mita-loa power start-up a

drawal low pwer start-up at-6 Coetrol rod sisoperation s.

Coet r, ' rod misoperation tv 13 Spectre of rod drop accideats

$&e;ter of rod ejec tice accideets Gro.p vil a s 19 Spectre of less of coolaat accidents 4" N, Spectre of loss of coolset acctocets Group ~V l l 1

~

sv D Itadiological Coasequemes cf Feel

.ru,.,w 8.- h Radiological ConsegseMes of Fuel Dama; tag Accideats ( t*s iSe sad Car ag t a3 Accidents (las tde and outside contrinrem outside containrect)

Gro.L.*

s e-12 1 a:.ertert opeaiac cf Bd safets' t

e s.-l.

laad.ertent opecing cf Pp rettaf valve orns arizer ret tef valve Groug a s 14

.e4J.eettet operat ic* Cf [lCS so- -

le.ed.erteet operat ion cf ECC5 or EvCL malfu ctica that canes an Gro4 El Eh 13 l'ad*erteat loadiaq a.d operation of n

tac rease ta coolaet teventory a fuel assesely ta sa incesper ret it toa Gr,q.si ha t akslicable to P ks w

Group nJI Isot apos tcaele to Bah

.-, _s :j 3,1" 5 tea-T.**eratoe

d. f ai te-,

1-4 o

STATUS DEFINITIONS G - Generic da-Draf t SE Received From Review Branch These topics are being evaluated as part of on-going NRC generic review effort. The ongoing This status is used for internal NRC tracking of generic review and the SEP topic review will be topic review progress. The status indicates that closely integrated to improve the effectiveness a draft topic safety evaluation es under mange-and efficiency of these efforts and to minimize ment review.

any impact on licensees. The status and conclu-4 sions of generic SEP topics will be incorporated in the final safety assessment for each plant.

4b - SAR Received from Licensee Licensee has submitted a Safety Analysis Report X - Deleted (SAR)in accordance with SEP redirection. (See Eisenhut letter to SEP owners of January 14,1981)

These topics have been verified as not applicable The SAR is under review and a Final NRC safety to the design of a specific plant or ar being evaluation (status 7)is being prepared. Draf t SE duplicated by the N RC TMI Action Plan, will not be issued for topics with licensee SAR submittal.

Unresolved Safety issue or another SEP Topic per the May 7,1981 letter from G. Lainas to all SEP licensees.

5 - Draf t SE Sent to Utility i

O - Topic Not Started A draft topic safety evaluation has been formally transmitted to the licensee for their review and This status indicates that the review of the topic certification of the accuracy of the described has not started.

f acility. Licensees may comment upon NRC conclusions or propose alternatives to NRC posi-tions.

1 - Questions Received From Review Branch 6 - SE Response Received This status is used for internal NRC tracking by NRC of topic review progress. The status indicates that all information necessary to perform a The draft SE has been reviewed and licensee topic evaluation is not available and that ques-comments if any have been formally transmitted tions have been developed and sent to the SEP to the N RC.

branch.

7 - Topic Complete 2 - Questions Sent to U tility The NRC topic evaluation has been completed and a final safety evaluation issued. A topic is completed The questions developed in the previous status in several ways: (1) The licenses has responded have been formally transmitted to the licensee that the N RC draft safety evaluation (i.e. status 5) as a request for additional information.

is correct, or (2) the licensees comments on the NRC draf t safety evaluation (i.e. status 6) have been re-3 - Question Response viewed and if appropriate incorporated into the Received by NRC final safety evaluation, or (3) the licensee has not responded in the time requested, thus concurring The licensee has formally responded to the informa-that the draft safety evaluation is correct.

tion request issued by NRC regarding the topic.

1-5 s

2 SEP TOPIC STATUS

SUMMARY

REPORT M d

\\

NUMBER OF QUESTIONS QUESTION DRAFT SE SAR SE A

TOPICS TOPIC RECEIVED QUESTIONS

RESPONSE

RECEIVED RECEIVED DRAFT SE

RESPONSE

TOPIC

\\

GENERIC DELETED NOT FROM SENT TO RECEIVED FROM FROM SENT TO RECEIVED COMPLETE N

(G)

(X)

STARTED REVIEW UTILITY BY NRC REVIEW LICENSEE UTILITY BY NRC (7)

PLANT NAME

\\

(0)

BRANCH (2)

(3)

BRANCH (4b)

(5)

(6)

\\

(1)

(4a)

\\

PALISADES O

47 0

0 0

0 90 GINNA 0

45 0

0 0

0 92 OYSTER CREEK 0

54 0

0 0

0 83 4

DRESDEN 2 0

49 0

0 0

0 88 MILLSTONE 1 0

51 0

0 0

0

'86 HADDAM NECK 0

47 0

0 0

0 2

0 8

3 77 YANKEE 1

48 0

0 0

0 1

0 6

0 81 LACROSSE 1

54 0

0 0

0 15 1

6 5

55 BIG ROCK POINT 2

52 0

0 0

1 7

1 6

4 64 SAN ONOFRE 2

48 2

0 1

5 7

3 7

6 56 9

DRESDEN 1 TOTALS THIS MONTH 6

495 2

0 1

6 32 6

38 18 772 TOTALS LAST Mi1 NTH 6

495 2

0 1

6 53 8

33 25 741 N NOTE: Totals do not include Dresden 1, see page 2-6.

Also included is May 7, 1981 deletion letter to all SEP licensees, see footnote page 1-3.

I i

1-6 4

I

SYSTEMATIC EVALUATION PROGRAM GOAL PHASEIIF

-1/ Not including Dresden 1 Progress Toward Complet. ion ACTUAL 100%

100

!7 1-82 l

p p/

g 96.5% 97%

9%

90

/

92%

/

88%

/

85%

80 1 m nth 3% /

83%

75 %

/

79%

70%

76 %

70 67 72%

61 %

p/

' Note: Prior to November 30,1981 the 60 60 %

b weighted percent did not include 30-81 p/

generic topics in the progress g

l w

p toward completion.

o 50

/

54%

y p/

50 %

47%

I

/

44%

O W

40 42%

5 40 %

30 The plant topic overall completion status (percent complete) is calculated Status Weighting Factor -

based upon the number of topic reviews to be performed (not including X

Not included deleted topics) and a weighted average of current topic review status.

20 The calculation is performed using the following formula:

G,0 0%

4a 4b 80%

Percent Complete = Sum of Topics in Status x Weighting Factor of Status 5,6 90 %

7 100%

10 Sum of Topics i

0 12 1

2 3

4 5

6 6

7 8

9 10 11 12 1

2 3

4 5

6 7

8 9

10 11 FY-81 FY-82 1-7

i j

INTEGRATED PLANT SAFETY ASSESSMENT REPORT (IPSAR) SCHEDULE 4

TOPIC ALL TOPIC ISSUE IPSAR IPSAR PLANT HAME TECHNICAL FOR ACRS TO EDO AND i

COMPLETE REVIEUS REVIEW COMMISSIDH TO DL 1/

I 1

i PALISADES 100 02/26/82C 04/01/82C 06/30/82 t

f GINHA 100 02/24/82C 05/27/82C 07/30/82 i

i OYSTER CREEK 100 05/31/82 09/30/82 11/30/82 I

DRESDEN 2 100 06/30/82 10/29/82 12/30/82 i

MILLSTONE 1 100 06/30/82 11/30/82 01/31/83 i

1 l

YANKEE 99 08/30/82 01/31/83 03/31/83 1

i 1

LACROSSE 94 09/30/82 01/31/83 03/31/83 HADDAM HECK 98 08/31/82 02/28/83 04/29/83 l

BIG ROCK POINT 94 09/30/82 04/29/83 06/30/83 SAN ONOFRE 87 12/30/82 2/

04/29/83 06/30/83 i

1/ Schedule for each topic for each plant is specified.

l OVERALL COMPLETION : 97%

2/ All topics except Seismic and High Energy Line Breaks are to be completed by 09/30/82.

l 1-8 i

I.

I

4 SEP TOPIC STATUS by REVIEW DIVISION i

SUMMARY

TABLE PLANT PALISADES GINNA OYSTER DRESDEN MILLSTONE HADDAM YANKEE LACROSSE BIG SAN TOTAL CREEK 2

1 NECK ROCK ONOFRE POINT (IAPM) J/

Michaels Wang Fell Cwalina Persinko Brown Boyle Michaels Scholl McKenna NO. OF TOPICS 137 137 137 137 137 137 137 137 137 137 1370 1

DELETED 2/

47 45 54 49 51 47 48 54 52 48 495 APPLICABLE 90 92 83 88 86 90 89 83 85 89 875 57

/

39

/

35

/

36

/

37

/

38

/

38

/

35

/

38

/

37

/

390 /

DL

/

/ 57

/ 39

/ 35

/ 36

/ 37

/ 38

/ 35

/ 38

/ 40

/ 393 TECHNICAL

/

17

/

20

/

19

/

22

/

20

/

20

/

20

/

19

/

15

/

9

/

181 /

REVIEW DOE

/

/ 17

/ 20

/ 19

/ 22

/ 20

/ 17

/ 192 ASSIGNMENT 1/

/

16

/

33

/

29

/

30

/

29

/

32

/

30

/

27

/

28

/

30

/

284 /

DSI

/

/ 16

/ 33

/ 29

/ 30

/ 29

/ 32

/ 31

/ 28

/ 30

/ 32

/ 290

/

90

/

92

/

83

/

88

/

86

/

90

/

88

/

81

/

81

/

76

/

855 /

COMPLETE

/

/ 90

/ 92

/ 83

/ 88

/ 86

/ 90

/ 89

/ 83

/ 85

/ 89

/ 875

/

TARGET DATE -

ALL TOPICS JAN 82 JAN 82 MAY 82 JUN 82 JUN 82 AUG 82 AUG 82 SEP 82 SEP 82 DEC 82 TECHNICAL REVIEWS TO DL l/ Division of Licensing Integrated Assessment Project Manager

'2/

Deleted as not applicable, or duplicated by USI, TMI Action Plan, or another topic.

1/ These schedules and assignments are consistent with HRR FY 1982-1984 Operating Plan.

/l

No. Completed / No. Assigned i

/

l 1-9 STATUS AS OF OCTOBER 31, 1982 I

i

PROGRESS OF TOPIC REVIEWS TOPICS DIVISION OF LICENSING 450 TARGET 400 350 ACTUAL 250 200 150 100 50

~~

l l

l I

l l

l g

SEP OCT NOV DEC JAN FEB MAR APF MAY JUN JUL AUG EEP OCT/DEC

~

PER MONTH ACTUAL 4

7 9

11 7

5 8

7 13 6

8 11 0

^

~

CUMULATIVE ACTat 298 305 314 325 332 337 345 352 365 371 379 390 390 8

7 PROGRESS OF TOPIC REVIEWS 0

TOPICS DIVISION OF ENGINCrRING 22b TARGET 200 175 s

ACTUAL g

p 125

/

100 75 50 25 l

l l

l g

SEP OCT NOV DEC JAN FEB MAR APR MAY JUN JUL AUG SEP OCT/DEC

~

PER MONTH ACTut 0

0 3

6 7

8 1

5 38 9

16 13 3

~

l CUMULATIVE i

ACTUAL 72 72 75 81 88 96 97 102 140 149 165 178 181 l

4 PROGRESS OF TOPIC REVIEWS TOPICS OlVISIONOFSYSTEMSINTEGRATION 350 TARGET 300

~-

ACTUAL 250 f

200

/

i 150 100 50 1

I I

i i

l I

I g

SEP OCT NOV DEC JAN FEB MAR APR MAY JUN JUL AUG SEP OCT/DEC

~

PER MONTH ACTE 14 27 28 13 17 13 13 27 25 6

10 17 0

Imi 197 223 253 275 283 286 288 290 ACIE 88 115 143 156 173 186 199 226 251 257 267 284 284

^

T PROGRESS OF TOPIC REVIEWS O

TOPICS TOTALPROJECT

ggg TARGET 900

~~

800 ACTUAL 7gg ggg 500 400 300 200 100 1

I I

I g

i SEP OCT NOV DEC JAN FEB MAR APR MAY JUN JUL AUG SEP OCI/DEC

~

PER MONTH

~

ACTE 18 34 40 30 31 26 22 39 76 21 34 41 3

CUMULATIVE 6

E 817 836 848 E

ACTE 458 492 532 562 593 619 641 680 756 777 811 852 855

LICENSEE TOPIC SUBMITTALS 1

OlVISIONOFLICENSING SUBMITTALS 4g TARGET 35

__. /

30

/

ACTUAL p

/

25 20 5

i 1

I I

i i

l I

I I

I g

JUN JUL AUG SEP OCT NOV DEC JAN FEB MAR APR MAY JUN JUL/DEC

~

PER MONTH ETUAL 0

3 1

1 4

6 1

0 5

2 2

3 3

TARGET 22 24 28 29 32 32 35 EEAL 0

3 4

5 9

15 16 16 21 23 25 28 31 T

LICENSEE TOPIC SUBMITTALS O

TOPICS DIVISION OF ENGINEERING 80 TARGET 78 ACTUAL g

60 50 40 30 i

20 la 1

I I

g JUN JUL AUG SEP OCT NOV DEC JAN FEB HAR APR MAY JUN JUL/DEC

~

PER MONTH ETUAL 1

8 1

5 7

15 5

1 13 0

3-2 0

TARGET 56 59 61 62 63 64 65 ETuAL 1

9 10 15 22 37 42 43 56 56 59 61 61

LICENSEE TOPIC SUBMITTALS SU8MITTALS DIVISION OF SYSTEMS INTEGRATION 120 II0 TARGET 100 00 ACTUAL 80

/

70 60 50 40 30 20 l

I l

l l

JUN JUL AUG SEP OCT NOV DEC JAN FEB HAR APR MAY JUN JUL/DEC

~

PER MONTH ETE 1

10 3

31 3

2 7

12 7

6 6

4 1

l TARGET 76 84 87 93 96 97 97 A

ETE 1

11 14 45 48 50 57 69 76 82 88 92 93 S

T LICENSEE TOPIC SUBMITTALS O

TOPICS TOTALPROJECT 225 TARGET 200 175 ACTUAL 150 125 100 75 50 25 1

I I

I

.I i

I i

l I

I g

JUN JUL AUG SEP OCT NOV DEC JAN FEB HAR APR MAY JUN JUL/DEC

~

PER MONTH ETE 2

21 5

37 14 23 13 13 25 8

11 9

4

~

CUMULATIVE ETE 2

23 28 65 79 102 115 128 153 161 172 181 185

..1

l Z

O

>0 u.i 0) l l

l l

BIG ROCK POINT FACILITY: BIG ROCK POINT 1 TOPIC NO.

REVIEW STATUS REMARKS DIV/BR LICENSEE: CONSUMERS POWER II-1 A.

DL/SEPB 7

CPCo to NRC 09/02/80 REGION / LOCATION: 4 MILES NORTH EAST OF CHARLEVOI, MICH.

II-1 B.

DL/SEPB 7

CPCo to NRC 09/02/80 DOCK!T N0.2 05000155 II-1 C.

DL/SEPB 7

HRC to CPCo 05/13/81 PONER CAPACITY: 0240(THERMAL) 067(ELECTRICAL)

II-2 A.

DSI/AEB 7

NRC to CPCo 08/03/81 OL NUMBfP: DPR-6 II-2 B.

X HRC to CPCo 05/07/81 N.S.S.S.: GE.

II-2 C.

DSI/AEB 7

HRC TO CPCO 10/26/82 A/E FIRN: BECH.

II-2 D.

X NRC to CPCo 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL II-3 A.

DE/HGEB 5

NRC TO CPCO 10/26/82 OPERATING REACTORS BRANCH CHIEF:

D. CRUTCHFIELD II-3 B.

DE/HGEB 5

HRC TO CPC0 10/26/82 OPERATING REACTORS PROJECT MANAGER: R.

EMCH II-3 B.

1 DE/HGEB 5

HRC TO CPCD 10/26/32 INTEGRATED ASSESSMENT PROJECT MANAGER:

R. SCHOLL /

II-3 C.

DE/HGEB 5

NRC TO CPCO 10/26/82 II-4 DE/GSB 7

NRC to CPCo 06/08/81 KEY FOR STATUS CODES II-4 A.

DE/GSB 7

NRC TO CPCO 10/12/82 G - GEHERIC 4a-DRAFT SE RECEIVED II-4 B.

DE/GSB 7

HRC TO CPCO 10/12/82 FROM REVIEW BRANCH X - DELETED II-4 C.

DE/GSB 7

HRC to CPCo 06/08/81 4b-SAR RECEIVED FROM 0 - TCPIC NOT LICENSEE II-4 D.

DE/HGEB 7

HRC TO CPCO 07/06/82 STARTED 5 - DRAFT SE SENT II-4 E.

X NRC to CPCo 11/16/79 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.

DE/HGEB 7

NRC TO CPC0 07/20/82 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY HRC III-1 DL/SEPB 7(SYS)

HRC TO CPCO 04/16/82 TO UTILITY DL/SEPB 7(ELEC) Part of VII-3 08/19/81 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 4A 09/21/82 RECEIVED BY HRC (2-2)

BIG ROCK POINT TOPIC NO.

REVIEW STATUS REMARKS TOPIC NO.

REVIEW STATUS REMARKS DIV/BR DIV/BR 111-3 A.

DE/SEB 4A 09/30/82 III-10 8.

X NRC to CPCo 11/16/79 III-3 B.

X NRC to CPCo 12/26/80 III-10 C.

X HRC to CPCo 11/16/79 1

(

III-5 C.

DE/AGEB 7

HRC TO CPC0 10/12/82 III-11 X

HRC to CPC0 05/07/81 III-4 A.

DSI/ASB 4A 09/28/82 III-12 X

NRC to CPCo 05/07/81 III-4 B.

DE/MT EB 4B CPCO TO NRC 06/09/82 IV-1 A.

DL/SEPB 7

HRC to CPCo 10/08/81 III-4 C.

DSI/ASB 7

NRC TO CPC0 10/14/82 IV-2 DSI/ICSB 7

CPCo to NRC 12/22/81 III-4 D.

DE/SAB 7

HRC TO CPC0 08/12/82 IV-3 X

HRC to CPCo 05/04/81 III-5 A.

DL/SEPB 4A 10/27/82 V-1 X

NRC to CPCo 11/27/81 III-5 B.

DL/SEPB 7

NRC TO CPC0 09/16/82 V-2 X

HRC to CPCo 11/16/79 III-6 DL/SEPB 5

NRC TO CPC0 10/18/82 V-3 X

HRC to CPCo 05/07/81 III-7 A.

X NRC to CPCo 05/07/81 V-4 DE/MTEB 3

CPCO TO HRC 05/28/82 III-7.B DL/SEPB 5

HRC TO CPCO 09/30/82 V-5 DL/SEPB 6

CPC0 TO HRC 09/30/82 III-7 C.

X NRC to CPCo 11/16/79 V-6 DL/SEPB 7

HRC to CPCo 03/05/80 III-7 D.

DE/SEB 7

NRC TO CPCO 03/17/82 V-7 X

NRC to CPCo 11/16/79 III-8 A.

DSI 7

HRC TO CPCO 03/02/82 V-8 X

HRC to CPCo 05/07/81 III-8 B.

X NRC to CPCo 09/26/80 V-9 X

HRC to CPCo 11/16/79 III-8 C.

DL/SEPB 7

NRC TO CPCO 06/23/82 V-10 A.

DL/SEPB 7

NRC to CPCo 10/09/79 III-8 D.

X NRC to CPCo 05/07/81 V-10 B.

DL/SEPB 7

HRC TO CPCO 09/10/82 III-9 X

HRC to CPCo 05/07/81 V-11 A.

DL/SEPB 7(ELEC) HRC TO CPC0 08/12/82 III-10 A.

DL/SEPB 7

NRC TO CPC0 03/30/82 V-11 B.

DL/SEPB 7(SYS)

HRC TO CPCO 09/10/82 7(Elec) HRC to CPCo 08/12/82 (2-3)

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1 9 8 2 98 5 5 9 1

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DRESDEN1 FACILITY: DRESDEN 1 LICENSEE: COMMONWEALTH EDISON REGION / LOCATION: 9 MILES EAST OF MORRIS, ILL.

DOCKET NO.: 05000010 POWER CAPACITY: 700(THERMAL) 200(ELECTRICAL)

OL NUMBER: DPR-2 H.S.S.S.: GE.

A/E FIRM: BECH.

SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD OPERATING REACTORS PROJECT MANAGER: P. O'CONNOR By letter dated December 31, 1980 Commonwealth Edison indi-cated that Dresden 1 was undergoing an extensive modifica-tion and was not scheduled for restart until June, 1986.

Also, by letter dated April 4,

1981, in response to the NRC's January 14, 1981 letter on SEP redirection the lican-see stated that the Dresden 1 SEP review is not being actively pursued, i.e. defered.

(2-6)

DRESDEN 2 FACILITY: DRESDEN 2 TOPIC NO.

REVIEW STATUS REMARKS DIV/BR LICENSEE: COMMONWEALTH EDISDN II-l A.

DE/SAB 7

NRC to Ceco 10/06/81 REGION / LOCATION: 9 MILES EAST OF MORRIS, ILL.

II-1 B.

DE/SAB 7

NRC to Ceco 10/06/81 DOCKET NO.

05000237 II-1 C.

DE/SAB 7

HRC TO CECO 08/20/82 POWER CAPACITY: 2527(THERMAL) 0794(ELECTRICAL)

II-2 A.

DSI/AEB 7

HRC to CECO 04/24/81 OL NUMBER: DPR-19 II-2 B.

X NRC to Ceco 05/07/81 N.S.S.S.

GE.

II-2 C.

DSI/AEB NRC to CPCo 08/26/81 A/E FIRM: S8L.

II-2 D.

X NRC to Ceco 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL II-3 A.

DE/HGEB 7

NRC TO CECO 09/16/82 OPERATING REACTORS BRANCH CHIEF:

D. CRUTCHFIELD II-3 B.

DE/HGEB 7

HRC TO CECO 09/16/82 OPERATING REACTORS PROJECT MANAGER:

P. O'CONNOR t, '

II-3 B.

1.,

DE/HGEB 7

NRC TO CECO 09/16/82 CW A L IN A w/(( -

INTEGRATED ASSESSMENT PROJECT MANAGER: G.

II-3 C.

DE/HGE7 7

HRC TO CECO 09/16/82 KEY FOR STATUS CODES II-4 DE/GSB 7

NRC to Ceco 07/09/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 A.

DE/GSB 7

HRC to CECO 06/08/81 FROM REVIEW BRANCH X - DELETED II-4 B.

DE/GSB 7

HRC to Ceco 07/09/81 4b-SAR RECEIVED FROM 0 - TOPIC NOT LICENSEE II-4 C.

DE/GSB 7

NRC to CECO 06/08/81 STARTED 5 - DRAFT SE SENT II-4 D.

DE/HGEB 7

HRC TO CECO 06/30/82 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 E.

DE/HGEB 7

HRC TO CECO 09/03/82 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC II-4 F.

DE/HGEB 7

HRC TO CECO 06/30/82 TO UTILITY 7 - TOPIC COMPLETE III-1 DL/SEPB 7(SYS)

HRC TO CECO 09/02/82 3 - QUESTION RESPONSE DL/SEPB 7(Elec) Part of VII-3 07/07/81 RECEIVED BY NRC III-2 DL/SEPB 7

NRC TO CECO 09/21/82 (2-7)

DRESDEN 2

TOPIC HO.

REVIEW STATUS REMARKS TOPIC NO.

REVIEW STATUS REMARKS DIV/BR DIV/BR III-3 A.

DE/SEB 7

NRC TO CECO 06/04/82 111-10 B.

X NRC to Ceco 11/16/79 III-3 B.

X HRC to CECO 11/16/79 III-10 C.

DL/SEPB 7

HRC to Ceco 05/22/79 III-3 C.

DE/HGEB 7

NRC TO CECO 06/30/82 III-11 X

NRC to Ceco 05/07/81 III-4 A.

DSI/ASB 7

NRC TO CECO 06/28/82 III-12 X

NRC to CECO 05/07/81 III-4 B.

DE/MT EB 7

HRC TO CECO 09/16/82 IV-1 A.

DL/SEPB 7

NRC to Ceco 10/26/81 III-4 C.

DSI/ASB 7

HRC TO CECO 06/28/82 IV-2 DSI/ICSB 7

CECO to HRC 12/04/81 III-4 D.

DE/SAB 7

NRC to Ceco 02/22/82 IV-3 DE/MTEB 7

HRC to Ceco 01/22/82 III-5 B.

DL/SEPB 7

NRC TO CECO 09/21/82 V-1 X

HRC to CECO 11/27/81 III-5 B.

DL/SEPB 7

HRC TO CECO 08/20/82 V-2 X

HRC to Ceco 11/16/79 III-6 DL/SEPB 7

HRC TO CECO 06/30/82 V-3 X

HRC to Ceco 11/16/79 III-7 A.

X HRC to CECO 11/16/79 V-4 DE/MTEB 7

HRC TO CECO 06/29/82 III-7 B.

DL/SEPB 7

HRC TO CECO 09/21/82 V-5 DL/SEPB 7

NRC TO CECO 06/23/82 III-7 C.

X NRC to CECO 11/16/79 V-6 DL /SEPB 7

HRC TO CECO 09/03/82 III-7 D.

DE/SEB 7

HRC TO CECO 04/13/82 V-7 X

HRC to Ceco 11/16/79 III-8 A.

DSI 7

HRC to Ceco 02/26/82 V-8 X

HRC to Ceco 11/16/79 III-8 8.

X HRC to CECO 09/11/80 V-9 X

NRC to Ceco 11/16/79 III-8 C.

DL/SEPB 7

HRC TO CECO 06/29/82 V-10 A.

DL/SEPB 7

NRC to CECO 11/08/79 III-8 D.

X HRC to Ceco 05/07/81 V-10 B.

DL/SEPB 7

HRC to CECO 04/24/81 III-9 X

NRC to Ceco 05/07/81 V-11 A.

DL/SEPB 7

HRC to Ceco 07/10/81 III-10 A.

DL/SEPB 7

HRC to CECO 06/26/81 V-11 B.

DL/SEPB 7(Sys)

HRC to Ceco 04/24/81 DL/SEPB 7(Elec) HRC to Ceco 07/10/81 (2-8)

DRESDEN 2 TOPIC NO.

REVIEW STATUS REMARKS TOPIC NO.

REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.

DL/SEPB 7

NRC to Ceco 04/16/81 VI-7 D.

DL/SEPB 7

HRC to CECO 10/18/78 V-13 X

NRC to CECO 05/07/81 VI-7 E.

X NRC t'o Ceco 05/07/81 VI-1 DE/ CEB 7

NRC TO CECO 06/30/82 VI-7 F.

X HRC to Ceco 11/16/79 VI-2 A.

X HRC to CECO 05/07/81 VI-8 X

nKC to Ceco 05/07/81 VI-2 B.

X NRC to CECO 05/07/81 VI-9 X

NRC to Ceco 11/16/79 VI-2 C.

X HRC to Ceco 11/16/79 VI-10 A.

DL/SEPB 7

HRC to Ceco 09/02/82 VI-2 D.

DSI/CSB 7

NRC TO CECO 08/19/82 VI-10 B.

DL/SEPB 7(Sys)

CECO TO HRC 11/03/81 DL/SEPB 7(Elec) HRC TO CECO 09/24/82 VI-3 DSI/CSB 7

HRC TO CECO 08/19/82 VII-t A.

DL/SEPB 7

NRC t.' Ceco 08/05/81 VI-4 DSI/CSB 7(SYS)

HRC TO CECO 09/24/82 DL/SEPB 7(ELEC) NRC TO CECO 06/23/82 VII-1 B, DL/SEPB 7

NRC to CECO 10/18/78 VI-5 X

NRC to CECO 05/07/81 VII-2 DL/SEPB 7

Ceco to NRC 11/03/81 VI-6 DSI/CSB 7

NRC TO CECO 06/25/82 VII-3 DL/SEPB 7(Sys)

HRC to Ceco 04/24/81 DL/SEPB 7(Elec) NRC to CECO 07/07/81 VI-7 A.

1.

X NRC to Ceco 11/16/79 VII-4 X

NRC to Ceco 05/07/81 VI-7 A.

2.

X NRC to Ceco 11/16/79 VII-5 X

NRC to Ceco 05/07/81 VI-7 A.

3.

DL/SEPB 7

Ceco to NRC 11/03/81 VII-6 DL/SEPB 7

NRC to Ceco 08/26/81 VI-7 A.

4.

DSI/RSB 7

NRC to CECO 04/23/82 VII-7 X

NRC to Ceco 11/16/79 VI-) B.

X NRC to CECO 11/16/79 VIII-1 A.

DSI/PSB 7

HRC TO CECO 06/15/82 VI-7 C.

DL/SEPB 7

NRC to Ceco 03/13/81 VIII-2 DL/SEPB 7

NRC to Ceco 06/26/81 VI-7 C.

1.

DSI/PSB 7

HRC TO CECO 02/05/82 VIII-3 A.

DL/SEPB 7

NRC to Ceco 07/07/81 VI-7 C. 2.

DL/SEPB 7

NRC to Ceco 03/13/81 VIII-3 B.

DL/SEPB 7

NRC to CECO 06/26/81 VI-7 C.

3.

X NRC to CECO 11/16/79 VIII-4 DL/SEPB 7

NRC to Ceco 11/30/81 (2 -9)

1

= _

DRESDEN 2 i

TOPIC NO.

REVIEW STATUS REMARKS

'0PIC HD.

REVIEW STATUS R EMA RKS DIV/ER DIV/BR i

r IX-l DSI/ASB 7

NRC TO CECO 05/05/82 XV-10 X

NRC to CECO 11/16/79 IX-2 X

NRC to Ceco 05/07/81 XV-11 DSI/CPB 7

HRC to Ceco 02/08/82 IX-- 3 DL/SEPB 7

CECO to HRC 11/03/81 XV-12 X

NRC to Ceco 11/16/79 IX-4 X

NRC to Ceco 11/16/79 XV-13 DSI/CPB 7(Sys)

HRC to Ceco 02/08/82 DSI/AEB 7(Doses) HRC to CECO 12/28/81 l

IX-5 DL/SEPB 7

HRC TO CECO 09/02/82 XV-14 DSI/RSB 7

NRC to Ceco 12/15/81 j

IX-6 DE/CEB 7

HRC TO CECO 06/23/82 XV-15 DSI/RSB 7

HRC to Ceco 01/04/82 X

X HRC to Ceco 11/16/79 l

XV-16 DSI/AEB 7

CECO to NRC 10/20/81 XI-1 X

NRC to Ceco 12/04/81 XV-17 X

NRC to Ceco 11/16/79 XI-2 X

NRC to Ceco 12/04/81 XV-18 DSI/AEB 7

NRC TO CECO 09/02/82 1 XIII-1 X

NRC to Ceco 05/07/81 XIII-2 DL/SSPB 7

HRC to CECO 04/14/82 XV-19 DSI/RSB 7(Sys)

HRC to Ceco 12/07/81 DSI/AEB 7(DOSES) CECO to NRC 01/05/82 XV-1 DSI/RSB 7

HRC to Ceco 12/29/81 XV-20 DSI/AEB 7

NRC So Ceco 11/20/81 2

XV-2 X

NRC to Ceco 11/16/79 XV-21 X

HRC to Ceco 05/07/as XV-3 DSI/RSB 7

HRC to CECO 12/07/88 XV-22 X

HRC to Ceco 05/07/81 XV-4 DSI/RSB 7'

HRC to CECO 12/07/81 XV-23 X

NRC to Ceco 11/16/79 XV-5 DSI/RSS 7

HRC to Ceco 12/15/81 XV-24 X

NRC to Ceco 05/07/81 3

XV-6 X

HRC to Ceco 11/16/79

^

XVI X

HRC to Ceco 11/05/80 i

XV-7 DSI/RSB 7

HRC to Ceco 01/04/82 XVII DL 7

NRC to Ceco 11/20/79 XV-8 RSI/CPB 7

HRC to Ceco 02/08/82 XV-9 DSI/RSB 7

HRC to Ceco 12/15/81 2

i 1

l 4

(2-10)

GINNA FACILITY: GINNA TOPIC NO.

REVIEW STATUS REMARKS DIV/BR LICENSEE: ROCHESTER GAS & ELECTRIC 11-1 A.

DE/SAB 7

NRC to RGE 07/17/81 REGION / LOCATION: 15 MILES NORTH EAST OF ROCHESTER. NY.

II-1 B.

DE/SAB 7

HRC to RGE 07/21/81 DOCKET NO.6 05000244 II-1 C.

DE/SAB 7

HRC to RGE 09/29/81 POWER CAPACITY: 1520(THERMAL) 3490(ELECTRICAL)

II-2 A.

DSI/AEB 7

NRC to RGE 1/03/81 OL NUMBER: DPR-18 II-2 B.

X N

05/07/81 N.S.S.S.-

WEST.

II-2 C.

DSI/AEB 7

ORE

/24/81 A/E FIRM: GIL.

II-2 D.

RGE 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL II-

/HGED NRC TO RGE 05/27/82 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIFLD II B

7 NRC TO RGE 05/27/82 OPERATING REACTORS PROJECT MANAGER: J.

LYONS DE/HGEB 7

NRC TO RGE 05/27/82 INTEGRATED ASSESSMENT PROJECT MANAGER: A. jf b 7-

' II-5 C.

B 7

NRC TO RGE 05/27/82

\\

JL "

I -4 DE 7

NRC to RGE 07/09/81 KEY FOR STATPT'ko

,,4 p

'hqRCtoRGE 06/08/81

-4 A E

B 7

T L G - GEN D FT SE RECEIVED I

DE/GSB N kC to RGE 07/09/81 FROM REVIEW Hjbl II-4 C Dd G NRC to RGE 06/08/81 X-D E

lM 4b-SAR RECEIVED RO y

DE EB 7

NRC to RGE 02/19/82 0 - TO OT LICENSEE STARTED 5 - DRAFT SE SENT X

NRC to RGE 11/16/79 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.

DE/HGEB 7

HRC to RGE 02/19/82 2 - QUESTIONS SENT B

R III-1 DL/SEPB 7(Sys)

NRC to RGE 12/17/81 TO UTILITY i

DL/SEPB 7(Elec) NRC to RGE 04/02/81 7 - TOP E

3 - QUESTION RESPONSE III-2 DL/SEPB 7

NRC TO RGE 04/21/82 RECEIVED BY NRC w - DATA OR NEXT MONT!i (NOVEMBER)

(2-11)

GINNA TOPIC NO.

REVIEW STATUS REMARKS TOPIC NO.

REVIEW STATUS REMARKS DIV/BR DIV/BR III-5 A.

DE/SEB 7

NRC TO RGE 03/03/82 III-10 B.

DL/SEPB 7

NRC to RGE 06/22/81 III-3 B.

X NRC to RGE 12/31/80 III-10 C.

X NRC to RGE 11/16/79 III-3 C.

DE/NGEB 7

NRC TO RGE 05/27/82 III-11 X

NRC to RGE 05/07/81 III-4 A.

DSI/AEB 7

NRC TO RGE 04/16/82 III-12 X

NRC to RGE 05/07/81 III-4 B.

DE/MTEB 7

HRC to RGE 02/19/82 IV-1 A.

DL/SEPB 7

NRC to RGE 05/29/79 III-4 C.

DSI/ASB 7

NRC to RGE 02/17/82 IV-2 DSI/ICSB 7

NRC to RGE 05/26/81 III-4 D.

DE/SAB 7

NRC to RGE 07/21/81 IV-3 X

NRC to RGE 05/07/81 III-5 A.

DL/SEPB 7

NRC to RGE 02/22/82 V-1 X

NRC to RGE 11/27/81 III-5 B.

DL/SEPB 7

HRC to RGE 09/04/81 V-2 X

NRC to RGE 11/16/79 III-6 DL/SEPB 7

NRC to RGE 02/17/82 V-3 X

NRC to'RGE 05/07/81 III-7 A.

DL/SEPB 7

NRC TO RGE 04/16/82 V-4 X

NRC to RGE 05/07/81 III-7 B.

DL/SEPB 7

NRC TO RGE 04/21/82 V-5 DL/SEPS 7

NRC to RGE 02/08/82 III-7 C.

DE/SEB 7

RGE to NRC 07/07/81 V-6 DL/SEPB 7

NRC to RGE 03/05/80 III-7 D.

DE/SEB 7

NRC to RGE 05/08/80 V-7 DSI/ASB 7

NRC to RGE 02/17/82 III-8 A.

DSI 7

NRC to RGE 02/17/82 V-8 X

NRC to RGE 05/07/81 III-8 B.

X NRC to RGE 02 12 51 V-9 X

NRC to RGE 11/16/79 III-8 C.

DL/SEPB 7

RGE to NRC 12/07/79 V-10 A.

DL/SEPB 7

NRC to RGE 02/02/79 III-8 D.

X NRC to RGE 05/07/81 V-10 B.

DL/SEPB 7

RGE to NRC 09/29/81 III-9 X

NRC to RGE 05/07/81 V-11 A.

DL/SEPB 7

NRC to RGE 11/07/81 III-10 A.

DL/SEPB 7

NRC to RGE 08/03/81 V-11 B.

DL/SEPB 7(Sys)

RGE to NRC 09/29/81 DL/SEPB 7(Elec) HRC to RGE 04/24/81 (2-12)

GINNA TOPIC NO.

REVIEW STATUS REMARKS TOPIC NO.

REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.

X NRC to RGE 11/16/79 VI-7 D.

DL/SEPB 7

HRC_to RGE 08/17/78 V-13 X

NRC to RGE 05/07/81 VI-7 E.

X NRC to RGE 05/07/81 VI-1 DE/CEB 7

NRC to RGE 02/19/82 VI-7 F.

DL/SEPB 7

NRC to RGE 06/24/81 VI-2 A.

X NRC to RGE 05/07/81 VI-8 X

NRC to RGE -

05/07/81 VI-2 B.

X NRC to RGE 05/07/81 VI-9 X

NRC to RGE 11/16/79 VI-2 C.

X NRC to RGE 11/16/79 VI-10 A.

DL/SEPB 7

NRC to RGE 11/27/81 VI-2 D.

DSI/CSB 7

HRC TO RGE 04/12/82 VI-10 B.

X NRC to RGE 11/16/79 VI-3 DSI/CSB 7

HRC TO RGE 04/12/82 VII-1 A.

DL/SEPB 7

HRC to RGE 07/30/81 VI-4 DSI/CSB 7(SYS)

HRC TO RGE 04/12/82 VII-1 B.

DL/SEPB 7

NRC to RGE 08/17/78 DL/SEPB 7(ELEC) NRC TO RGE 03/19/82 VII-2 DL/SEPB 7

NRC to RGE 12/28/81 VI-5 X

HRC to RGE 05/07/81 VII-3 DL/SEPB 7(Sys)

HRC to RGE 09/29/81 VI-6 DSI/CSB 7

HRC to RGE 05/06/81 DL/SEPB 7(Elec) HRC to RGE 03/25/82 VI-7 A.

1.

DL/SEPB 7

NRC to RGE 02/20/81 VII-4 X

NRC to RGE 05/07/81 VI-7 A.

2.

DL/SEPB 7

HRC to RGE 08/17/78 VII-5 X

NRC to RGE 05/07/81 VI-7 A. 3.

DL/SEPB 7

NRC to RGE 11/27/81 VII-6 DL/SEPB 7

NRC to RGE 06/24/81 VI-7 A. 4.

X NRC to RGE 05/07/81 VII-7 X

HRC to RGE 11/16/79 VI-7 B.

DSI/RSB 7(SYS)

NRC TO KGE 03/09/82 VIII-1 A.

DSI/PSB 7

NRC to RGE 03/26/81 DL/SES 7(Elec) NRC to RGE 09/18/81 VIII-2 DL/SEPB 7

MRC to RGE 06/24/81 VI-7 C.

DL/SEPB 7

NRC to RGd 02/20/81 VIII-3 A.

DL/SEPB 7

NRC to RGE 07/31/81 VI-7 C.

1.

DL/SEPB 7

NRC to RGE 11/27/81 VIII-3 B.

DL/SEPB 7

HRC to RGE 06/09/81 VI-7 C. 2.

DL/SEPB 7

NRC to RGE 02/20/81 VIII-4 DL/SEPB 7

RGE to NRC 10/08/81 VI-7 C. 3.

X HRC to RGE 11/16/79 t

t (2-13)

9 GINNA 4

TOPIC NO.

REVIEW STATUS REMARKS TOPIC NO.

REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 fa.'ASB 7

NRC to RGE 11/24/81 XV-10 DSI/RSB 7

NRC to RGE 09/04/81 IX-2 X

NRC to RGE 05/07/81 XV-11 X

NRC to RGE 10/01/80 IX-3

'O rf.'

7 NRC to RGE 11/03/81 XV-12 DSI/CPB 7(Sys)

HRC to RGE 09/04/81 DSI/AEB 7(DOSES) NRC TO RGE 03/03/82 IX-4 7

NRC to RGE 08/26/81 XV-13 X

NRC to RGE 11/16/79 IX-5 Pl./ S EP5 7

RGE to NRC 03/29/82 XV-14 DSI/RSB 7

NRC to RGE 09/04/81 IX-6 7

NRC TO RGE 05/07/82 XV-15 DSI/RSB 7

NRC to RGE 09/04/81 X

X NRC to RGE 05/07/81 XV-16 DSI/AEB 7

NRC TO RGE 03/01'82 4

XI-1 X

HRC to RGE 12/04/81 XV-17 DSI/RSB 7(Sys)

NRC to RGE 09/04/c

XI-2 X

NRC to RGE 12/04/81 DSI/AEB 7(DOSES) NRC TO RGE 03/03/8-NIII-1 X

NRC to RGE 05/07/81 XV-18 X

NRC to RGE 05/11/80 XIII-2 DL/SEPB 7

NP" to RGE 03/26/81 XV-19 DSI/R$5 7(Sys)

NRC to RGE 10/02/81 XV-1 DSI/RSB 7

Nk ; to RGE 09/04/81 XV-20 DSI/AEB 7

NRC TO RGE 03/03/82 XV-2 DSI/RSB 7(Sys)

HRC to RGE 09/04/81 DSI/AEB 7(DOSES) HRC TO RGE 03/03/82 XV-21 X

NRC to RGE 05/07/81 XV-3 DSI/RSB 7,

NRC to RGE 09/04/81 XV-22 X

NRC to RGE 05/07/81 XV-4 DSI/RSB 7

NRC to RGE 09/04/81 XV-23 X

NRC to RGE 05/07/81 XV-5 DSI/RSB 7

NRC to RGE 09/04/81 XV-24 X

NRC to RGE 05/07/81 XV-6 DSI/RSB 7

NRC to RGE 09/04/81 XVI X

NRC to RGE 11/05/80 XV-7 DSI/RSS 7

NRC to RGE 09/04/81 XVII DL 7

NRC to RGE 08/17/78 XV-8 DSI/CPB 7

NRC to RGE 09/04/81 XV-9 DSI/RSB 7

RGE to NRC 10/16/81 1

1 (2-14)

HADDAM NECK FACILITY: HADDAM HECK TOPIC NO.

REVIEW STATUS REMARKS DIV/BR LICENSEE: CONNECTICUT YANKEE ATOMIC POWLR II-l A.

DE/SAB 7

NRC 10 CYAPC0 04/22/82 REGION / LOCATION: 13 MILES EAST OF MERIDEH, CT.

II-1 B.

DE/SAB 7

NRC TO CYAPC0 04/22/82 DOCKET NO: 05000213 II-1,C.

DE/SAB 7

NRC TO CYAPCO 06i28/82 POWER CAPACITY: 1825(THERMAL) G575(ELECTRICAL)

II-2 A; DSI/AEB 7

CYAPCo to NRC 01/22/81 OL NUMBER: DPR-61 II-2 B.

X NRC to CYAPCo 05/07/81 N.S.S.S.

WEST.

A/E FIRM: 51W II-2 C.

DSI/AEB 7

NRC TO CYAPCO 04/26/82 II-2 D.

X NRC to CYAPCo 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL II-3 A.

DE/HGEB 5

NRC TO CYAPC0 09/11/82 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD II-3 B.

DE/HGEB 5

HRC TO CYAPCU 09/11/82 GPERATING REACTORS PROJECT MANAGER: J. LYONS II-3 B.

1 DE/HGEB 5

HRC TO CYAPCO

.09/11/82 f,-

INTEGRATED ASSESSMENT PROJECT MANAGER: S. BROWN II-3 C.

DE/HGEB 5

HRC TO CYAPCO 09/11/82 II-4 DE/GSB 7

NRC to CYAPCo KEY FOR STATUS CODES 06/04/82 II-4 A.

DE/GSB 7

NRC to CYAPCo 06/08/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.

DE/GSB 7

NRC TO CYAPCO 06/04/82 FROM REVIEW BRANCH X - DELETED II-4 C.

DE/GSB 7

NRC to CYAPCo 06/08/81 4b-SAR RECEIVED FROM 0 - TOFIC HOT LICENSEE II-4 D.

DE/HGEB 7

NRC TO CYAPCO 07/13/82 ST8RTED 5 - DRAFT SE SENT II-4 E.

X NRC to CYAPCo 04/16/79 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.

DE/HGEB 7

NRC TO CYAPCO 07/06/82 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY HRC III-1 D'. / S EP 8 5(SYS)

HRC TO CYAPC0 08/12/82 TO UTILITY DL/0EPB 7(Elec) Part of VII-3 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 7

HRC TO CYAPCD 09/02/82 RECEIVED BY NRC l

1 (2-15)

HADDAM NECK TOPIC HO.

REVIEW STATUS REMARKS TOPIC HO.

REVIEW STATUS REMARKS DIV/BR DIV/BR III-3 A.

DE/SEB 7

NRC 10 CYAPC0 08/26/82 III-10 B.

DL/SEPB 7

NRC 10 CYAPCO 03/36/82 III-3 B.

DE/HGEB 5

HRC TO CYAPCO 09/10/82 III-10 C.

X HRC to CYAPCo 04/16/79 III-3 C.

DE/HGEB 7

NRC TO CYAPCO 06/28/82 III-11 X

NRC to CYAPCo 05/07/81 l

III-4 A.

DSI/ASB 7

NRC TO CYAPCO 08/02/82 III-12 X

HRC to CYAPCo 05/07/81 l

III-4 B.

DE/MTEB 7

HRC TO CYAPCO 07/13/82 IV-1 A.

DL/SEPB 7

CYAPCo to NRC 06/25/79 l

III-4 C.

DSI/ASB 5

NRC TO CYAPCO 05/10/82 IV-2 DSI/ICSB 7

HRC to CYAPCo 02/22/82 III-4 D.

DE/SAB 7

NRC TO CYAPCO 04/22/82 IV-3 X

HRC to CYAPCo 05/07/81 III-5 A.

DL/SEPB 5

NRC TO CYAPCO 10/04/82 V-1 X

NRC to CYAPCo 11/27/81 III-5 B.

DL/SEPB 7

NRC TO CYAPCO 05/10/82 V-2 X

MRC to CYAPCo 04/16/79 III-6 DL/SEPB 5

NRC TO CYAPCO 10/12/82 V-3 X

NRC to CYAPCo 05/07/81 III-7 A.

X NRC to CYAPCo 05/07/81 V-4 X

NRC to CYAPCo 05/07/81 III-7 B.

DL/SEPB 5

NRC TO CYAPCO 08/27/82 V-5 DL/SEPB 7

NRC to CYAPCo 02/22/82 III-7 C.

X HRC to CYAPCo 04/16/79 V-6 DL/SEPB 7

NRC to CYAPCo 03/05/80 III-7 D.

DE/SEB 7

NRC to CYAPCo 10/16/81 V-7 DSI/ASB 7

NRC TO CYAPCO 06/21/82 III-8 A.

DSI 7

HRC TO CYAPCO 06/21/82 V-8 X

NRC to CYAPCo 05/07/81 III-8 B.

X HRC to CYAPCo 10/01/80 V-9 X

HRC to CYAPCo 11/16/79 III-8 C.

DL/SEPB 7

NRC to CYAPCo 01/29/82 V-10 A.

DL/SEPB 7

NRC to CYAPCo 01/13/81 III-8 D.

X NRC to CYAPCo 05/07/81 V-10 B.

DL/SEPB 7

NRC to CYAPCo 12/28/81 III-9 X

NRC to CYAPCo 05/07/81 V-11 A.

DL/SEPB 7

NRC to CYAPCo 11/03/81 III-13 A.

DL/SEPB 7

CYAPCo to NRC 09/21/81 V-11 B.

DL/SEPB 7(Sys)

HRC to CYAPCo 12/28/81 DL/SEPB 7(Elec) NRC TO CYAPCO 03/03/82 (2-16)

HADDAM NECK TOPIC NO.

REVIEW STATUS REMARKS TOPIC NO.

REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.

X NRC to CYAPCo 11/16/79 VI-7 D.

DL/SEPB 7

NRC to CYAPCo 08/17/78 V-13 X

NRC to CYAPCo 05/07/81 VI-7 E.

X NRC to CYAPCo 05/07/81 VI-1 DE/CEB 7

NRC TO CYAPCO 07/15/82 VI-7 F.

X HRC to CYAPCo 04/16/79 VI-2 A.

X NRC to CYAPCo 05/07/81 VI-8 X

NRC to CYAPCo 05/07/81 VI-2 B.

X NRC to CYAPCo 05/07/81 VI-9 X

NRC to CYAPCo 11/16/79 VI-2 C.

X HRC to CYAPCo 04/16/79 VI-10 A.

DL/SEPB 7

NRC TO CYAPCO 07/22/82 VI-2 D.

DSI/CSB 7

NRC TO CYAPCO 09/i6/82 VI-10 B.

X HRC *o CYAPCo 04/16/79 VI-3 DSI/CSB 7

HRC TO CYAPC0 09/16/82 VII-1 A.

DL/SEPB 7

NRC 1d CYAPCO 10/20/82 VI-4 DSI/CSB 6(SYS)

CYAPCO TO HRC 08/18/82 VII-1 B.

DL/SEPB 7

NRC to CYAPCo 08/17/78 DL/SEPB 7(Elec) NRC to CYAPCo 09/21/81 VII-2 DL/SEPB 7

HRC TO CYAPCO 03/05/82 VI-5 X

NRC to CYAPCo 05/07/81 VII-3 DL/SEPB 7(Sys)

NRC to CYAPCo 12/28/81 VI-6 DSI/CSB 7

NRC TO CYAPCO 05/07/82 DL/SEPB 7(Elec) HRC to CYAPCo 08/28/81 VI-7 A.

1 DL/SEPB 7

NRC to CYAPCo 02/20/81 VII-4 X

NRC to CYAPCo 05/07/81 VI-7 A. 2.

X NRC to CYAPCo 05/07/81 VII-5 X

NRC to CYAPCo 05/07/81 VI-7 A. 3.

DL/SEPB 7

NRC TO CYAPCO 10/27/82 VII-6 DL/SEPB 7

HRC to CYAPCo 08/28/81 VI-7 A.

4.

X NRC to CYAPCo 05/07/81 VII-7 X

HRC to CYAPCo 04/16/79 VI-7 B.

DSI/RSB 7(SYS)

HRC TO CYAPCO 08/12/82 VIII-1 A.

DSI/PSB 7

HRC TO CYAPCO 07/22/82 DL/SEPB 7(Elec) HRC to CYAPCo 05/21/81 VIII-2 DL/SEPB 7

NRC to CYAPCo 08/28/81 VI-7 C.

DL/SEPB 7

NRC to CYAPCo 03/13/81 VIII-3 A.

DL/SEPB 7

CYAPCo to NRC 02/16/79 VI-7 C.

1 DL/SEPB 7

CYPACO to NRC 01/11/82 VIII-3 B.

DL/SEPB 7

HRC to CYAPCo 08/28/81 VI-7 C. 2.

DL/SEPB 7

NRC to CYAPCo 03/13/81 VIII-4 DL/SEPB 7

HRC TO CYAPC0 05/17/82 VI-7 C. 3.

DL/SEPB 7

CYAPCo to NRC 02/12/82 (2-17)

HADDAM NECK TOPIC NO.

REVIEW STATUS REMARKS TOPIC NO.

REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 7

NRC TO CYAPCO 03/01/82 XV-10 DSI/RSB 7

NRC 10 CYAPCO 04/12/82 IX-2 X

HRC to CYAPCo 05/07/81 XV-11 X

NRC to CYAPCo 10/01/80 IX-3 DL/SEPB 7

NRC TO CYAPCO 06/07/82 XV-12 DSI/CPB 7(SYS)

HRC TO CYAPCO 03/23/82 DSI/RSB 7(DOSES) NRC TO CYAPCO 06/29/82 IX-4 DSI/RSB 7

NRC TO CYAPCO 04/26/82 XV-13 X

NRC to CYAPCo 11/16/79 IX-5 DL/SEPB 7

HRC TO CYAPCO 08/27/82 XV-14 DSI/RSB 7

NRC TO CYAPCO 04/26/82 IX-6 DE 7

NRC TO CYAPC0 06/27/8282 XV-15 DSI/RSB 7

NRC TO CYAPCO 04/16/82 X

X NRC to CYAPCo 05/07/81 XV-16 DSI/AEB 6

CYAPCo to NRC 09/28/81 XI-1 X

NRC to CYAPCo 12/04/81 XV-17 DSI/RSB 7(SYS)

NRC TO CYAPCO 08/19/82 XI-2 X

NRC to CYAPCo 12/04/81 DSI/AEB 7(DOSES) NRC TO CYAPCO 08/19/82 XIII-1 X

NRC to CYAPCo 05/07/81 XV-18 X

HRC to CYAPCo 10/01/80 XIII-2 DL/SSPB 7

HRC TO CYAPCO 06/10/82 XV-19 DSI/RSB 7(Sys)

HRC to CYAPCo 12/02/81 DSI/AEB 7(DOSES) HRC TO CYAPCO 08/27/82 XV-1 DSI/RSB 7

NRC TO CYAPCO 06/18/82 XV-20 DL/SEPB 7

NRC to CYAPCo 06/09/81 XV-2 DSI/RSB 7 (SYS) HRC TO CYAPCO 05/20/82 DSI/AEB 6(DOSES) CYAPCO TO NRC 09/08/82 XV-21 X

HRC to CYAPCo 05/07/81 XV-3 DSI/RSB 7,

NRC TO CYAPCO 03/17/82 XV-22 X

NRC to CYAPCo 05/07/81 XV-4 DSI/RSB 7

HRC to CYAPCo 12/17/81 XV-23 X

NRC to CYAPCo 05/07/81 XV-5 DSI/RSB 7

H2C TO CYAPCO 04/16/82 XV-24 X

HRC to CYAPCo 05/07/81 XV-6 DSI/RSB 7

NRC TO CYAPCO 05/20/82 XVI X

NRC to CYAPCo 11/05/80 XV-7 DSI/RSB 7

NRC TO CYAPCO 05/25/82 XVII DL 7

NRC to CYAPCo 08/17/78 XV-8 DSI/CPB 7

NRC TO CYAPCO 03/25/82 XV-9 DSI/RSB 7

HRC TO CYAPCO 04/26/82 4

(2-18) i

LACROSSE FACILITY: LACROSSE TOPIC NO.

REVIEW STATUS REMARKS DIV/BR LICENSEE: DAIRYLAND POWER l

11-1 A.

DE/SAB 4A 10/29/82 REGION / LOCATION: 19 MILES SOUTH OF LACROSSE, WISC.

11-1 B.

DE/SAB 7

HRC TO DPC 09/13/82 DOCKET NO.: 05000409 II-1 C.

DE/SAB 7

NRC TO DPC 08/30/82 POWER CAPACITY: 0165(THERMAL) 0050(ELECTRICAL)

II-2 A.

DSI/AEB 7

NRC to DPC 12/15/80 OL NUMBER: DPR-45 II-2 B.

X HRC to DPC 05/07/81 N.S.S.S.

AC.

II-2 C.

DSI/AEB 4A 09/28/82 A/E FIRM: SIL II-2 D.

X HRC to DPC 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W.

RUSSELL II-3 A.

DE/HGEB 4A 09/30/82 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD II-3 B.

DE/HGEB 4A 09/30/82 OPERATIt;G REACTORS PROJECT MANAGER: D. DUDLEY II-3 B.

1.

DE/HGEB 4A 09/30/82 INTEGRATED ASSESSMENT PROJECT MANAGER: T. MICHAELS

.U II-3 C.

DE/HGEB 4A 09.'30/82 II-4 DE/GSB 7

NRC to DPC 07/20/82 KEY FOR STATUS CODES II-4 A.

DE/GSB 7

HRC to DPC 06/05/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.

DE/GSB 7

NRC TO DPC 07/20/82 FROM REVIEW BRANCH X - DEL ETED II-4 C.

DE/GSB 7

NRC to DPC 06/08/81 4b-SAR RECEIVED FROM 0 - TOPIC HOT LICENSEE II-4 D.

DE/HGEB 5

HRC TO DPC 08/27/82 STARTED 5 - DRAFT SE SENT II-4 E.

DE/HGEB 7

NRC TO DPC 08/16/82 1 - QUESTIONS RECEIVED TO UTILITY FROM RE'/IEW BRANCH II-4 F.

DE/HGEB 7

NRC TO DPC 07/29/82 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC III-1 DL/SEPB 6(SYS)

DPC TO NRC 08/26/82 TO UTILITY DL/SEPB 6(ELEC) DPC TO NRC 08/26/82 7 - T0?IC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 4A 08/16/82 RECEIVED BY NRC (2-19)

LACROSSE TOPIC NO.

REVIEW STATUS REMARKS TOPIC HO.

REVIEW STATUS REMARKS DIV/BR DIV/BR III-5 A.

DE/SEB 4B DPC 10 NRC 05/12/82 111-10 B.

X NRC to DPC 10/29/79 III-3 B.

X NRC to DPC 03/10/81 III-10 C.

X NRC to DPC 10/29/79 III-3 C.

DE/HGEB 4A 09/10/82 III-11 X

NRC to DPC 05/07/8L III-4 A.

DSI/ASB 4A 09/23/82 III-12 X

NRC to DPC 05/07/81 III-4 B.

DE/MTEB 4A 10/19/82 IV-1 A.

DL/SEPB 7

NRC to DPC 04/19/79 III-4 C.

DSI/ASB 7

NRC TO DPC 07/19/82 IV-2 DSI/ICSB 7

NRC TO DPC 09/10/82 III-4 D.

DE/SAB 7

HRC TO DPC 08/23/82 IV-3 X

NRC to DPC 05/07/81 III-5 A.

DL/SEPB 4A 08/06/82 V-1 X

HRC to DPC 11/27/81 III-5 B.

DL/SEPB 7

NRC TO DPC 08/12/82 V-2 X

HRC to DPC 10/29/79 III-6 DL/SEPB 4A 09/30/82 V-3 X

HRC to DPC 05/07/81 III-7 A.

X NRC to DPC 05/07/81 V-4 X

HRC to DPC 05/07/81 III-7 B.

DL/SEPB 4A 09/23/82 V-5 DL/SEPB 7

NRC TO DPC 07/19/82 III-7 C.

X NRC to DPC 10/29/79 V-6 DL/SEPB 7

HRC to DPC 03/05/80 III-7 D.

DE/SEB 7

HRC TO DPC 04/13/82 V-7 X

NRC to DPC 05/07/81 III-8 A.

DSI 5

HRC TO DPC 02/22/82 V-8 X

HRC to DPC 05/07/81 III-8 B.

X HRC to DPC 09/26/80 V-9 X

NRC to DPC 10/29/79 III-8 C.

DL/SEPB 7

DPC to NRC 03/03/81 V-10 A.

DL/SEPB 7

HRC to DPC 01/07/80 III-8 D.

X NRC to DPC 05/07/81 V-10 B.

DL/SEPB 6

DPC TO HRC 08/26/82 III-9 X

HRC to DPC 05/37/81 V-11 A.

DL/SEPB 7

HRC to DPC 02/22/82 III-10 A.

DL/SEPB 7

HRC to DPC 09/22/81 V-11 B.

DL/SEPB 6($YS)

DPC TO HRC 08/26/82 DL/SEPB 7(ELEC) HRC TO DPC 03/04/82 (2-20)

LACROSSE TOPIC NO.

REVIEW STATUS REMARKS TOPIC NO.

REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.

DL/SEPB 7

NRC to DPC 04/30/79 VI-7 D.

DL/SEPB 7

HRC to DPC 08/17/78 V-13 X

HRC to DPC 05/07/81 VI-7 E.

X HRC to DPC 05/07/81 VI-1 DE/CEB 4A 09/13/82 VI-7 F.

X NRC to DPC 10/29/79 VI-2 A.

X HRC to DPC 05/07/81 VI-8 X

HRC to DPC.

05/07/81 VI-2 B.

X HRC to DPC 05/07/81 VI-9 X

NRC to DPC 10/29/79 VI-2 C.

X NRC to DPC 10/29/79 VI-10 A.

DL/SEPB 7

NRC TO DPC 09/20/82 VI-2 D.

DSI/CSB 7

HRC TO DPC 08/27/82 VI-10 B.

X NRC to DPC 10/29/79 VI-3 DSI/CSB 7

NRC TC 9PC 08/27/82 VII-1 A.

DL/SEPB 7

HRC TO DPC 03/09/82 VI-4 DSI/CSB 6(SYS)

DPC TO NRC 10/08/82 VII-1 B.

DL/SEPB 7

NRC to DPC C8/17/78 DL/SEPB 7(Elec) NRC to DPC 01/05/82 VII-2 DL/SEPB 7

HRC TO DPC 03/11/82 VI-5 X

HRC to DPC 05/07/81 VII-3 DL/SEPB 6(SYS)

DPC TO NRC 08/26/62 VI-6 DSI/CSB 7

NRC TO DPC 08/24/82 DL/SEPB 6(ELEC) DPC TO NRC 08/26/82 VI-7 A.

1.

X HRC to DPC 10/29/79 VII-4 X

NRC to DPC 05/L~/81 VI-7 A. 2.

X HRC to DPC 05/07/81 VII-5 X

NRC to DPC 05/07/81 VI-7 A.

3.

DL/SEPB 7

NRC to DPC 02/17/82 VII-6 DL/SEPB 7

NRC to DPC 09/21/81 VI-7 A. 4.

X NRC to DPC 05/07/81 VII-7 X

HRC to DPC 10/29/79 VI-7 B.

X HRC to DPC 10/29/79 VIII-1 A.

DSI/PSB 7

HRC TO DPC 10/14/82 VI-7 C.

DL/SEPB 7

NRC to DPC 03/13/81 VIII-2 DL/SEPB 7

HRC to DPC 12/18/81 VI-7 C.

1.

DL/SEPB 7

NRC to DPC 09/21/81 VIII-3 A.

DL/CEPB 7

NRC to DPC 06/05/79 VI-7 C. 2.

DL/SEPB 7

NRC to DPC 03/13/81 VIII-3 B.

DL/SEPB 7

HRC to DPC 08/28/81 VI-7 C.

3.

X NRC to DPC 10/29/79 VIII-4 DL/SEPB 7

NRC to DPC 09/09/81 (2-21)

LACROSSE TOPIC NO.

REVIEW STATUS REMARKS TOPIC HO.

REVIEW STATUS ret 1 ARKS DIV/BR DIV/BR IX-1 DSI/ASB 4A 09/23/82 XV-10 X

NRC to DPC 10/29/19 IX-2 X

NRC to DPC 05/07/81 XV-11 DSI/CPB 7

NRC TO DPC 04/05/82 IX-3 DL/SEPB 7

HRC TO DPC 07/20/82 XV-12 X

NRC to DPC 10/29/79 IX-4 X

NRC to DPC 10/29/79 XV-13 DSI/CPB 7(DOSES) NRC TO DPC 07/20/82 DSI/AEB 7(SYS)

HRC TO DPC 04/05/82 l

IX-5 DL/SEPB 7

NRC TO DPC 10/28/82 XV-14 DSI/RSB 7

NRC TO DPC 08/06/82 IX-6 DSI/ASB G

NRC TO DPC 05/10/82 XV-15 DSI/RSB 7

HRC to DPC 09/21/81 X

X NRC to DPC 05/07/81 XV-16 DSI/AEB 5

NRC TO DPC 10/14/82 XI-1 X

NRC to DPC 12/04/81 XV-17 X

NRC to DPC 10/29/79 XI-2 X

NRC to DPC 12/04/81 XV-18 DSI/AEB 7

NRC TO DPC 08/06/82 XIII-1 X

NRC to DPC 05/07/81 XV-19 DSI/AEB 5(DOSES) HRC TO DPC 10/14/82 XIII-2 DL/SSPB 7

HRC to DPC 03/11/81 DSI/RSB 7(SYS)

HRC TO DPC 10/29/82 XV-1 DSI/RSB 7

NRC TO DPC 09/29/82 XV-20 DSI/AEB 5

NRC TO DPC 10/14/82 XV-2 X

HRC to DPC 10/29/79 XV-21 X

NRC to DPC 05/07/83 XV-3 DSI/RSB 7

HRC to DPC 11/13/81 XV-22 X

NRC to DPC 05/07/81 XV-4 DSI/RSB 7

NRC to DPC 11/03/81 XV-23 X

NRC to DPC 05/07/81 XV-5 DSI/RSB 7

NRC TO DPC 08/24/82 XV-24 X

NRC to DPC 05/07/81

~

XV-6 X

NRC to DPC 10/29/79 XVI X

NRC to DPC 11/05/80 XV-7 DSI/RSB 7

NRC TO DPC 08/06/82 XVII DL 7

NRC to LPC 08/17/78 XV-8 DSI/CPB 7

HRC TO DPC 09/10/82 XV-9 DSI/RSB 7

NRC TO DPC 10/12/82 (2-22)

MILLSTONE 1 FACILITY: MILLSTONE 1 TOPIC NO.

REVIEW STATUS REMARKS DIV/SR LICENSEE: NORTHEAST NUCLEAR ENERGY II-1 A.

DE/SAB 7

NRC to NU 07/31/81 REGION / LOCATION: 5 MILES SOUTH WEST OF HEW LONDON. CONN.

II-1 B.

DE/SAB 7

NRC to NU 11/27/81 CCCKET N3.

05000245 II-1 C.

DE/SAB 7

HRC to NU 08/04/82 P0t!ER CAP ACITY: 2011(THERMAL) 0660(ELECTRICAL)

II-2 A.

DSI/AEB 7

NRC to NU 03/30/81 O L NL'MB ER : DPR-21 II-2 B.

X HRC to NU 05/07/81 II-2 C.

DSI/AEB 7

HRC to NU 12/23/81 II-2 D.

X NRC to NU 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL II-3 A.

DE/HGEB 7

NRC Til NU 06/30/82 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD II-3 B.

DE/NGEB 7

NRC TO NU 06/30/82 OPERATING REACTORS PROJECT MANAGER:

J.

SHEA II-3 B.

1.

DE/HGEB 7

HRC 70 NU 06/30/82 ik INTEGRATED ASSESSMENT PROJECT MANAGER: D. PERSINKO II-3 C.

DE/HGEB 7

HRC TO HU 06/30/82 II-4 DE/GSB 7

NRC to NU 06/08/81 KEY FOR STATUS CODES II-4 A.

DE/GSB 7

NRC to NU 06/08/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.

DE/GSB 7

NRC TO HU 05/11/82 FROM REVIEW BRANCH X - DELETED II-4 C.

DE/GSB 7

NRC to NU 06/08/81 4b-SAR RECEIVED FROM 0 - TOPIC NOT LICENSEE II-4 D.

DE/HGEB 7

NRC TO NU 06/30/82 STARTED 5 - DRAFT SE SENT II-4 E.

X HRC to NU 11/16/79 1 - CUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.

DE/HGEB 7

NRC TO NU 06/15/82 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC III-1 DL/SEPB 7(Elec) NRC TO NU 09/16/82 TO UTILITY DL/SEPB 7(SYS)

HRC TO NU 09/01/82 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 7

NRC TO HU 09/30/82 RECEIVED BY NRC (2-23)

MILLSTONE 1 TOPIC NO.

REVIEW STATUS REMARKS TOPIC HD.

REVIEW STATUS REMARKS DIV/BR DIV/BR III-3 A.

DE/SEB 7

NRC 10 HU 09/15/82 111-10 B.

X NRC to NU 11/16/79 III-3 B.

X NRC to NU 12/26/80 III-10 C.

DL/SEPB 7

NU to NRC 08/29/79 III-3 C.

DE/HGEB 7

NRC TC HU 06/23/82 III-11 X

HRC to HU 05/07/84 III-4 A.

DSI/ASB 7

NRC TO NU 05/25/82 III-12 X

NRC to HU 05/07/81 III-4 B.

DE/MTEB 7

NRC TO HU 06/29/82 IV-1 A.

DL/SEPB 7

HU to NRC 02/12/79 III-4 C.

DSI/ASB 7

NRC TO NU 06/09/82 IV-2 DSI/ICSB 7

HRC TO HU 06/03/82 III-4 D.

DE/SAB 7

HRC to NU 11/27/81 IV-3 DL 7

HRC to NU 02/22/82 III-5 A.

DL/SEPB 7

HRC TO NU 06/24/82 V-1 X

NRC to NU 11/27/81 III-5 B.

DL/SEPB 7

NRC TO NU 09/09/82 V-2 X

NRC to NU 11/16/79 III-6 DL/SEPB 7

NRC TO HU 06/33/82 V-3 X

HRC to HU 05/07/81 III-7 A.

X NRC to NU 05/07/81 V-4 X

NRC to NU 05/07/81 III-7 B.

DL/SEPB 7

HRC TO NU 08/11/82 V-5 DL/SEPB 7

HRC to HU 08/28/81 III-7 C.

X NRC to HU 11/16/79 V-6 DL/SEPB 7

NRC to NU 09/29/82 III-7 D.

DE/SEB 7

HU to NRC 02/17/81 V-7 X

HRC to NU 05/07/81 4

III-8 A.

DSI 7

HRC TO NU 03/03/82 V-8 X

NRC to NU 05/07/81 III-8 B.

X HRC to NU 09/26/80 V-9 X

NRC to HU 11/16/79 III-8 C.

DL/SEPB 7

NRC TO NU 06/24/82 V-10 A.

DL/SEPB 7

HU to NRC 03/05/79 III-8 D.

X NRC to NU 05/07/81 V-10 B.

DL/SEPB 7

HU to HRC 07/22/81 III-9 X

NRC to NU 05/07/81 V-11 A.

DL/SEPB 7

HRC to NU 07/08/81 III-10 A.

DL/ SERB 7

NRC to NU 04/07/82 V-11 B.

DL/SEPB 7(Sys)

HU to NRC 07/22/81 DL/SEPB 7(ELEC) NRC TO HU 09/16/82 1

(2-24)

MILLSTONE 1 TOPIC HD.

REVIEW STATUS REMARKS TOPIC HO.

PEVIEW OTATUS REMARKS DIV/BR DIV/BR V-12 A.

DL/SEPB 7

NRC to NU 12/17/79 VI-7 D.

DL/SEPB 7

NRC to NU 08/17/78 V-13 X

NRC to NU 05/07/81 VI-7 E.

X NRC to NU 05/07/81 VI-1 DE/CEB 7

HRC to NU 02/26/82 VI-7 F.

X NRC to NU 11/16/79 VI-2 A.

X NRC to NU 05/07/81 VI-8 X

HRC to NU 05/07/81 i

VI-2 B.

X NRC to NU 05/07/81 VI-9 X

NRC to NU 11/16/79 VI-2 C.

X NRC to HU 11/16/79 VI-10 A.

DL/SEPB 7

NRC to NU 10/08/81 VI-2 D.

DSI/CSB 7

NRC TO HU 09/15/82 VI-10 B.

DL/SEPB 7

NU to NRC 08/05/81 VI-3 DSI/CSB 7

NRC TO NU 09/15/82 VII-1 A.

DL/SEPB 7

NRC to NU 07/23/81 VI-4 DSI/CSB 7(SYS)

NRC TO NU 10/08/82 DL/SEPB 7(ELEC) NRC TO NU 06/24/82 VII-1 B.

DL/SEPB 7

HRC to HU 08/17/78 VI-5 X

NRC to NU 05/07/81 VII-2 DL/SEPB 7

NU TO HRC 06/25/82 VI-6 DSI/CSB 7

NRC TO NU 10/22/82 VII-3 DL/SEPB 7'Sys)

HU to NRC 07/22/81 DL/SEPB

! ELEC) HRC TO HU 09/16/82 VI-7 A.

1 X

NRC to NU 11/16/79 VII-4 X

HRC to NU 05/07/81 VI-7 A.

2.

X NRC to HU 05/07/81 VII-5 X

HRC to NU 05/07/81 VI-7 A. 3.

DL/SEPB 7

NRC to NU 10/27/81 VII-6 DL/SEPB 7

NRC to NU 08/26/81 VI-7 A.

4.

DSI/CPB 7

NRC TO HU 03/11/82 VII-7 X

NRC to NU 11/16/79 VI-7 B.

X NRC to NU 11/16/79 VIII-1 A.

DSI/PSB 7

NRC TO HU 06/30/82 VI-7 C.

DL/SEPB 7

NRC to HU 03/29/81 VIII-2 DL/SEPB 7

NRC to NU 09/30/81 VI-7 C.

1.

DL/SEPB 7

HU to NRC 11/02/81 VIII-3 A.

DL/SEPB 7

HRC to NU 08/26/81 VI-7 C. 2.

DL/SEPB 7

HRC to NU 03/29/81 VIII-3 B.

DL/SEPB 7

NRC to NU 07/23/81 VI-7 C.

3.

X NRC to NU 11/16/79 VIII-4 DL/SEPB 7

HRC to NU 07/07/81 I,

(2-25)

MILLSTONE 1 TOPIC HO.

REVIEW STATUS REMARKS TOPIC HO.

REVIEW STATUS REMARKS DIV/BR DIV/SR IX-1 DSI/ASB 7

NRC TO HU 03/09/82 XV-10 X

NRC to NU 11/16/79 IX-2 X

HRC to NU 05/07/81 XV-11 DSI/CPB 7

NRC to NU 10/14/81 IX-3 DL/SEPB 7

NRC TO HU 07/16/82 XV-12 X

NRC to NU 11/16/79

-IX-4 X

NRC to NU 11/16/79 XV-13 DSI/CPB 7(Sys)

HU to NRC 09/09/81 DSI/AEB 7(Doses) HRC to HU 11/03/81 IX-5 DL/SEPB 7

HRC TO HU 09/14/82 XV-14 DSI/RSB 7

NRC to NU 09/18/81 IX-6 DE 7

NRC TO HU 06/15/82 XV-15 DSI/RSB 7

NRC to NU 10/28/81 X

X HRC to NU 05/07/81 XV-16 DSI/AEB 7

HU to NRC 01/13/82 XI-1 X

HRC to NU 12/04/81 XV-17 X

NRC to NU 11/16/79 XI-2 X

NRC to NU 12/04/81 XV-18 DSI/AEB 7

HU to NRC 01/13/82 XIII-1 X

HRC to NU 05/07/81 XV-19 DSI/RSB 7(Sys)

HRC to NU 08/26/81 XIII-2 DL/SSPB 7

NRC TO NU 06/09/82 DSI/AEB 7(DOSES) HRC TO HU 01/13/82 XV-1 DSI/RSB 7

NRC to NU 12/31/81 XV-23 DSI/AEB 7

NRC to NU 11/03/81 XV-2 X

HRC to HU 11/16/79 XV-21 X

NRC to HU 05/07/81 XV-3 DSI/RSB 7

NRC to NU 09/18/81 XV-22 X

NRC to NU 05/07/81 XV-4 DSI/RSB 7

NRC to NU 09/18/81 XV-23 X

NRC to HU 05/07/81 XV-5 DSI/RSB 7

NRC to NU 01/07/82 XV-24 X

NRC to HU 05/0.' 41 XV-6 X

NRC to NU 11/16/79 XVI X

NRC to NU 11/15/80 XV-7 DSI/RSB 7

NRC to NU 12/04/81 XVII DL 7

NRC to NU 08/17/78 XV-8 DSI/CPB 7

NRC to NU 08/26/81 XV-9 DSI/RSB 7

NRC to NU 01/12/82 (2-26)

0YSTER CREEK 1

FACILITY: OYSTER CREEK 1 TOPIC NO.

REVIEW STATUS REMARKS DIV/BR LICENSEE: JERSEY CENTRAL POWER 3 LIGHT II-1 A.

DE/SAB 7

NRC to JCPL 02/04/82 REGION / LOCATION: 9 MILES SOUTH OF TOMS RIVER, NJ.

II-1 B.

DE/SAB 7

HRC to JCPL 0E/04/82 DOCKET NO.

05000219 II-1 C.

DE/SAB 7

NRC to JCPL 02/04/82 POWER CAPACITY: 1930(THERMAL) 0650(ELECTRICAL)

II-2 A.

DSI/AEB 7

NRC to JCPL 11/16/81 OL NUMBER: DPR-16 II-2 B.

X NRC to JCPL 05/07/81 N.S.S.S.: GE.

II-2 C.

DSI/AEB 7

NRC TO JCPL 03/16/82 A/E FIRM: BIR II-2 D.

X NRC to JCPL 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL II-3 A.

DE/HGEB 7

NRC TO JCPL 08/27/82 OPERATING REACTORS BRANCH CHIEF:

D. CRUTCHFIELD II-3 B.

DE/HGEB 7

NRC TO JCPL 08/27/82 OPERATING REACTORS PROJECT MANAGER: J. LOMBARDO II-3 B.

1.

DE/HGEB 7

HRC TO JCPL 08/27/82 FELLjf INTEGRATED ASSESSMENT PROJECT MANAGER: R.

7.1-3 C.

DE/HGEB 7

NRC TO JCPL 08/27/82 II-4 DE/GSB 7

NRC to JCPL 08/03/81 KEY FOR STATUS CODES II-4 A.

DE/GSB 7

NRC to JCPL 06/08/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.

DE/GSB 7

NRC to JCPL 08/03/81 FROM RdVIEW BRANCH X - DELETED II-4 C.

DE/GSB 7

NRC to JCPL 06/08/81 4b-SAR RECEIVED FROM 0 - TOPIC NOT LICENSEE II-4 D.

DE/HGEB 7

HRC TO JCPL 06/28/82 STARTED 5 - DRAFT SE SENT II-4 E.

X HRC to JCPL 11/16/79 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.

DE/HGEB 7

NRC TO JCPL 06/15/82 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC III-1 DL/SEPB 7(SYS)

HRC TO JCPL 08/30/82 TO UTILITY DL/SEPB 7(Elec) NRC to JCPL 07/09/81 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 7

NRC TO JCPL 06/15/82 RECEIVED BY NRC (2-27)

OYSTER CREEK TOPIC H0.

REVIEW STATUS REMARKS TOPIC HO.

REVIEW STATUS REMARKS DIV/BR DIV/BR III-5 A.

DE/SEB 7

NRC TO JCPL 05/14/82 111-10 8.

X NRC to JCPL 11/16/79 III-3 B.

X HRC to JCPL 12/26/80 III-10 C.

X NRC to JCPL 11/16/79 III-3 C.

DE/HGEB 7

NRC TO JCPL 08/27/82 III-11 X

HRC to JCPL 05/07/85 III-4 A.

DSI/ASB 7

NRC TO JCPL 08/27/82 III-12 X

NRC to JCPL 05/07/81 III-4 B.

DE/MTEB 7

HRC TO JCPL 06/28/82 IV-1 A.

DL/SEPB 7

HRC to JCPL 05/30/79 III-4 C.

DSI/ASB 7

NRC TO JCPL 06/15/82 IV-2 DSI/ICSB 7

HRC TO JCPL 06/18/82 III-4 D.

DE/SAB 7

NRC TO JCPL 06/21/82 IV-3 X

HRC to JCPL 05/07/81 III-5 A.

DL/SEPB 7

NRC TO JCPL 06/29/82 V-1 X

HRC to JCPL 11/27/81 III-5 B.

DL/SEPB 7

HRC TO JCPL 06/22/82 V-2 X

HRC to JCPL 11/16/79 III-6 DL/SEPB 7

HRC TO JCPL 05/12/82 V-3 X

HRC to JCPL 05/07/81 III-7 A.

X NRC to JCPL 05/07/81 V-4 X

NRC to JCPL 05/07/81 III-7 B.

DL/SEPB 7

HRC TO JCPL 08/27/82 V-5 DL/SEPB 7

NRC to JCPL 02/22/82 III-7 C.

X HRC to JCPL 11/16/79 V-6 DL/SEPB 7

HRC to JCPL 03/05/80 III-7 D.

DE/SEB 7

HRC TO JCPL 03/08/82 V-7 X

NRC to JCPL 05/07/81 III-8 A.

DSI/CPB 7

NRC TO JCPL 02/29/82 V-8 X

HRC to JCPL 05/07/81 III-8 B.

X NRC to JCPL 09/26/80 V-9 X

NRC to JCPL 11/16/79 III-8 C.

DL/SEPB 7

NRC to JCPL 10/30/80 V-10 A.

DL/SEPB 7

JCPL to NRC 05/15/79 III-8 D.

X HRC to JCPL 05/07/81 V-10 B.

DL/SEPB 7

HRC to JCPL 09/25/80 III-9 X

HpC to JCPL 05/G7/81 V-11 A.

DL/SEPB 7

HRC to JCPL 07/08/81 III-10 A.

DL/SEPB 7

HRC to JCPL 06/29/81 V-11 B.

DL/SEPB 7(Sys)

HRC to JCPL 09/25/80 DL/SEPB 7(Elec) HRC to JCPL 07/09/81 (2-28)

0YSTER CREEK TOPIC NO.

REVIEW STATUS REMARKS TOPIC NO.

REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.

DL/SEPB 7

NRC TO JCPL 03/16/81 VI-7 D.

DL/SEPB 7

HRC to JCPL 08/17/78 V-13 X

NRC to JCPL 05/07/81 VI-7 E.

X NRC to JCPL 05/07/81 VI-1 DE/CEB 7

NRC TO JCPL 06/29/82 VI-7 F.

X NRC to JCPL 11/16/79 VI-2 A.

X NRC to JCPL 05/07/81 VI-8 X

HRC to JCPL 05/07/81 VI-2 B.

X HRC to JCPL 05/07/81 VI-9 X

NRC to JCPL 11/16/79 VI-2 C.

X HRC to JCPL 11/16/79 VI-10 A.

DL/SEPB 7

NRC to JCPL 08/18/81 VI-2 D.

DSI/CSB 7

NRC TO JCPL 04/30/82 VI-10 B.

X NRC to JCPL 11/16/79 VI-3 DSI/CSB 7

NRC TO JCPL 04/30/82 VII-1 A.

DL/SEPB 7

NRC to JCPL 07/30/81 VI-4 DSI/CSB 7(SYS)

HRC TO JCPL 06/15/82 VII-1 B.

DL/SEFB 7

NRC to JCPL 12/28/81 DL/SEPB 7(Elec) NRC to JCPL 08/05/81 VII-2 DL/SEPB 7

HRC TO JCPL 06/29/81 VI-5 X

HRC to JCPL 05/07/81 VII-3 DL/SEPB 7(Sys)

HRC to JCPL 09/25/80 VI-6 DSI/CSB 7

NRC TO JCPL 03/04/82 DL/SEPB 7(Elec) HRC to JCPL G7/09/81 VI-7 A.

1 X

HRC to JCPL 11/16/79 VII-4 X

NRC to JCPL 05/07/81 VI-7 A. 2.

X NRC to JCPL 05/07/81 VII-5 X

NPC to JCPL 05/07/81 VI-7 A.

3.

DL/SEPB 7

NRC to JCPL 07/30/81 VII-6 DL/SEPB 7

NRC to JCPL 08/29/81 VI-7 A.

4.

DSI/RSB 7

NRC TO JCPL 08/27/82 VII-7 X

NRC to JCPL 11/16/79 VI-7 B.

X NRC to JCPL 11/16/79 VIII-1 A.

DSI/PSB 7

NRC to JCPL 03/03/82 VI-7 C.

DL/SEPB 7

NRC to JCPL 03/13/81 VIII-2 DL/SEP3 7

NRC to JCPL 06/29/81 VI-7 C.

1 DL/SEPB 7

NRC to JCPL 06/29/81 VIII-3 A.

DL/SEPB 7

HRC to JCPL 06/29/81 VI-7 C. 2.

DL/SEPB 7

NRC to JCPL 03/13/81 VIII-3 B.

DL/SEPB 7

NRC to JCPL 05/29/81 VI-7 C.

3.

X NRC to JCPL 11/16/79 VIII-4 DL/SEPB 7

NRC TO JCPL 08/26/81 (2-29)

OYSTER CREEK TOPIC NO.

REVIEW STATUS REMARKS TOPIC NO.

REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 7

NRC IO JCPL 06/01/82 XV-10 X

NRO to JCPL 11/16/79 IX-2 X

NRC to JCPL 05/07/81 XV-11 DSI/CPB 7

NRC TO JCPL 05/17/82 IX-3 DSI/ASB 7

NRC to JCPL 11/13/81 XV-12 X

NRC to JCPL 11/16/79 IX-4 X

NRC to JCPL 05/07/81 XV-13 DSI/AEB 7(DOSES) HRC TO JCPL 09/02/82 DSI/CPB 7(SYS)

NRC to JCPL 05/17/82 IX-5 DL/SEPB 7

NRC TO JCPL 06/28/82 XV-14 DSI/RSB 7

NRC to JCPL 07/16/81 IX-6 DE 7

HRC TO JCPL 06/15/82 XV-15 DSI/RSB 7

NRC to JCPL 12/04/81 X

X NRC to JCPL 05/07/81 XV-16 DSI/AEB 7

NRC TO JCPL 09/02/82 XI-1 X

NRC to JCPL 12/04/81 XV-17 X

NRC to JCPL 11/16/79 XI-2 X

NRC to JCPL 12/04/81 XV-18 DSI/AEB 7

NRC TO JCPL 09/02/82 XIII-1 X

NRC to JCPL 05/07/81 XV-19 DSI/AEB 7(DOSES) NRC TO JCPL 09/02/82 XIII-2 DL/SSPB 7

NRC to JCPL 09/25/80 DSI/RSB 7(Sys)

HRC to JCPL 09/04/81 XV-1 DSI/RSB 7

NRC to JCPL 12/07/81 XV-20 DSI/AEB 7

NRC TO JCPL 09/02/82 XV-2 X

NRC to JCPL 11/16/79 XV-21 X

NRC to JCPL 05/07/81 XV-3 DSI/RSB 7

NRC to JCPL 07/16/81 XV-22 X

NRC to JCPL 05/07/81 XV-4 DSI/RSB 7

NRC to JCPL 07/16/81 XV-23 X

NRC to JCPL 05/07/81 XV-5 DSI/R$B 7

NRC to JCPL 12/07/81 XV-24 X

NRC to JCPL 05/07/81 XV-6 X

NRC to JCPL 11<16/79 XVI X

HPC to JCPL 11/05/80 XV-7 DSI/RSB 7

NRC to JCPL 12/04/81 XVII DL 7

NRC to JCPL 08/17/78 XV-8 DSI/CPB 7

NRC TO JCPL 05/17/82 XV-9 DSI/RSB 7

NRC to JCPL 01/07/82 (2-30)

PALISADES FACILITY: PALISADES TOPIC NO.

REVIEW STATUS REMARKS DIV/BR LICENSEE: CONSUMERS POWER II-l A.

DL/SEPB 7

CPCo to NRC 12/28/79 REGION / LOCATION: 5 MILES SOUTH OF SOUTH HAVEN, MI.

II-1 B.

DL/SEPB 7

CPCo to NRC 12/28/79 DOCKET NO: 05000255 II-1 C.

DL/SEPB 7

CPCo to NRC 05/13/81 POWER CAPACITY: 2530(THERMAL) 0805(ELECTRICAL)

II-2 A.

DSI/AEE 7

HRC to CPCo 6430/81 OL NUMBER: DPR-20 II-2 B.

X 05/07/81 H.S.S.S.: C-E II-2 C.

DSI/AEB H

4/23/81 A/E FIRM: BECH.

II-2 D.

CPCo 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL II E/H EB NRC to CPCo 02/19/82 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD I

GEB 7

HRC to CPCo 02/19/82 OPERATING REACTORS PROJECT MANAGER: T. WAMBACH I

1 DE/HGEB 7

HRC to CPCo 02/19/82 I

INTEGRATED ASSESSMENT PROJECT MANAGER: T.

II-3 C.

/

B 7

NRC to CPCo 02/19/82 KEY FOR STAT M 0

)

Tl I-4 DE/GSB 7

4RC to CPCo 06/08/81 O

lPCo to NRC 07/22/81 G-G I

D FT SE RECEIVED B.

DE/GS L

I i

j%CH l

II-4 C D

NRC to CPCo 06/08/81 FROM REVIEW L-V s

X - D LE E ld 4b-SAR RECEIVED FRO.

0-T OT LICENSEE DE GEB 7

CPCo to NRC 06/01/81

~

STARTED 5 - DRAFT SE SENT 1 - QUESTIONS RECEIVED TO UTILITY X

NRC to CPCo 11/16/79 FROM REVIEW BRANCH II-4 F.

DE/HGEB 7

CPCo to NRC 06/01/31 2 - QUESTIONS SENT III-1 DL/SEPB 7(Elec) NRC to CPCo 11/12/80 TO UTILITY i

DL/SEPB 7(Sys)

HRC to CPCo 02/08/82 7 - T0fEC P TE 3 - QUESTION RESPONSE

\\

RECEIVED BY NRC (2-31)

PALISADES TOPIC NO.

REVIEW STATUS REMARKS TOPIC NO.

REVIEW STATUS REMARKS DIV/BR DIV/BR III-2 DL/SEPB 7

NRC to CPCi ~ 02/08/82 III-10 B.

DL/5EPB 7

NRC to CPCo 02/02/82 7

III-3 A.

DE/SEB 7

HRC to CPCs 08/26/81 III-10 C.

X HRC to CPCo 11/16/79 III-3 B.

X HRC to CPCo 12/26/80 III-11 X

NRC to CPCo 05/07/81 III-3 C.

DE/HGEB 7

NRC to CPco 02/22/82 III-12 X

HRC to CPCo 05/07/81 III-4 A.

DSI/AEB 7

NRC to CPCo 02/02/82 IV-1 A.

DL/SEPB 7

CPCo to NRC 02/06/79 III-4 B.

DE/MTEB 7

hRC to CPCo 02/08/82 IV-2 DSI/ICSB 7

NRC to CPCo 02/08/82 III-4 C.

DSI/ASB 7

NRC to CPCo 09/21/81 IV-3 X

NRC to CPCo 05/07/81 III-4 D.

DE/SAB 7

CPCo to NRC 08/03/81 V-1 X

HRC to CPCo 11/27/81 III-5 A.

DL/SEPB 7

hPC to CPCo 02/08/82 V-2 X

NRC to CPCo 11/16/79 III-5 B.

DL/SEPB 7

NRC to CPCo 02/19/82 V-3 X

NRC to CPCo 05/37/81 III-6 DL/SEPB 7

CPCo to NRC 12/16/81 V-4 X

NRC to CPCo 05/07/81 III-7 A.

DL/SEPB 7

NRC to CPCo 02/10/82 V-5 DL/SEPB 7

HRC to CPCo 02/04/82 III-7 B.

DL/SEPB 7

NRC to CPCo 02/12/82 V-6 DL/SEPB 7

NRC to CPCo 03/05/80 III-7 C.

DE/SEB 7

NRC to CPCo 10/19/81 V-7 DSI/ASB 7

NRC to CPCo 11/16/81 III-7 D.

DE/SEB 7

CPCo to NRC 08/17/81 V-8 X

HRC to CPCo 05/07/81 III-8 A.

DSI 7

HRC to CPCo 11/18/81 V-9 X

NRC to CPCo 11/16/79 III-8 B.

X HRC to CPCo 10/01/80 V-10 A.

DL/SEPB 7

HRC to CPCo 09/26/81 III-8 C.

DL/MTEB 7

CPCo to NRC 12/28/79 V-10 B.

DL/SEPB 7

CPCo to NRC 12/23/81 III-8 D.

X NRC to CPCo 05/07/81 V-11 A.

DL/SEPB 7

NRC to CPCo 11/09/81 III-9 X

HRC to CPCo 05/07/81 V-11 B.

DL/SEPB 7(Sys)

iRC to CPCo 12/23/81 DL/SEPB 7(Elec) NRC to CPCo 12/24/81 III-10 A.

DL/SEPB 7

NRC to CPCo 05/19/81 (2-32)

PALISADES TOPIC HO.

REVIEW STATUS REMARKS TOPIC NO.

REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.

X NRC to CPCo 11/16/79 VI-7 D.

DL/SEPB 7

NRC to CPCo 08/17/78 V-13 X

NRC to CPCo 05/07/81 VI-7 E.

X HRC to CPCo 05/07/81 VI-1 DE/CEB 7

NRC to CPCo 08/03/81 VI-7 F.

DL/SEPB 7

HRC to CPCo 10/29/81 VI-2 A.

X HRC to CPCo 05/07/81 VI-8 X

NRC to CPCo 05/07/81 VI-2 8.

X NRC to CPCo 05/07/81 VI-9 X

NRC to CPCo 11/16/79 i

VI-2 C.

X NRC to CPCo 11/16/79 VI-10 A.

DL/SEPB 7

HRC to CPCo 10/16/81 VI-2 D.

DSI/CSB 7

NRC to CPCo 11/16/81 VI-10 B.

X HRC to CPCo 11/16/79 VI-3 DSI/CSB 7

HRC to CPCo 11/16/81 JII-1 A.

DL/SEPB 7

HRC to CPCo 08/28/81 VI-4 DL/SEPB 7(Elec) CPCo to NRC 08/18/81 :

VII-1 B.

DL/SEPB 7

HRC to CPCo 08/17/78 DCI/CSB 7(Sys)

NRC to CPCo 02/08/82 VII-2 DL/SEPB 7

NRC to CPCo 05/19/81 VI-5 X

NRC to CPCo 05/07/81 VII-3 DL/SEPB 7(Sys)

CPCo to NRC 12/23/81 VI-6 DSI/CSB 7

NRC to CPCo 12/11/81 DL/SEPB 7(Elec) CPCo to HRC 12/31/81 VI-7 A.

1.

X HRC to CPCo 11/16/79 VII-4 X

NRC to CPCo 05/07/81 VI-7 A. 2.

X-NRC to CPCo 05/07/81 VII-5 X

NRC to CPCo 05/07/81 VI-7 A.

3.

DL/SEPB 7

NRC to CPCo 12/18/81 VII-6 DL/SEPB 7

NRC to CPCo 05/19/81 VI-7 A. 4.

X HRC to CPCo 05/07/81 VII-7 X

NRC to CPCo 11/16/79 VI-7 B.

DL/SEPB 7(Elec) HRC to CPCo 05/19/81 VIII-1 A.

DSI/PSB 7

NRC to CPCo 12/22/81 DSI/RSB 7(Sys)

NRC to CPCo 06/30/81 VIII-2 DL/SEPB 7

HRC to CPCo 10/29/81 VI-7 C.

DL/SEPB 7

NRC to CPCo 02/20/81 VIII-3 A.

DL/SEPB 7

HRC to CPCo 05/22/81 VI-7 C.

1.

DL/SEPB 7

NRC to CPCo 10/14/81 VIII-3 B.

DL/SEPB 7

HRC to CPCo 08/05/81 VI-7 C. 2.

DL/SEPB 7

NRC to CPCo 02/20/81 VIII-4 DL/SEPB 7

NRC to CPCo 07/31/81 VI-7 C.

3.

X CPCo to NP.C 12/12/79 (2-33) 1

PALISADES TOPIC HO.

REVIEW STATUS REMARKS TOPIC HO.

REVIEW STATUS REMARK 3 DIV/BR Did/BR IX-1 DSI/ASB 7

NRC to CPCo 02/08/82 XV-10 DL/SEPB 7

NRC to CPCo 11/05/81 IX-2 X

NRC to CPCo 05/07/81 XV-11 X

NRC to CPCo 10/01/80 IX-3 DL/SEPB 7

NRC to CPCo 02/22/82 XV-12 DL/SEPB 7(Doses) NRC to CPCo 12/04/81 DL/SEPB 7(Sys)

HRC to CPCo 11/03/81 IX-4 DSI/RSB 7

NRC to CPCo 02/08/82 XV-13 X

HRC to CPCo 11/16/79 IX-5 DL/SEPB 7

NRC to CPCo 02/11/82 XV-14 DL/SEPB 7

NRC to CPCo 11/03/81 IX-6 DE 7

NRC TO CPC0 04/07/82 XV-15 DL/SEPB 7

NRC to CPCo 11/03/81 X

X NRC to CPCo 05/07/81 XV-16 DL/SEPB 7

NRC to CPCo 11/03/81 XI-1 X

NRC to CPCo 12/04/81 XV-17 DL/SEPB 7(Doses) NRC to CPCo 11/03/81 XI-2 X

NRC to CPCo 12/04/81 DL/SEPB 7CSys)

NRC to CPCo 11/03/81 XIII-1 X

NRC to CPCo 05/07/81 XV-18 X

NRC to CPCo 10/01/80 XIII-2 DL/SSPB 7

NRC to CPCo 10/01/80 XV-19 DL/SEPB 7(Doses) NRC to CPCo 11/03/81 DL/SEPB 7(Sys)

NRC to CPCo 11/03/81 XV-1 DL/SEPB 7

NRC to CPCo 11/03/81 XV-20 DL/SEPB 7

HRC to CPCo 11/03/81 XV-2 DL/SEPB 7(Doses) NRC to CPCo 11/03/81 DL/SEPB 7(Sys)

NRC to CPCo 11/05/81 XV-21 X

NRC to CPCo 05/07/81 XV-3 DL/SEPB 7

NRC to CPCo 11/03/81 XV-22 X

NRC to CPCo 05/07/81 XV-4 DL/SEPB 7

HRC to CPCo 11/03/81 XV-23 X

NRC to CPCo 05/07/81 XV-5 DL/SEPB 7

HRC to CPCo 11/03/81 XV-24 X

NRC to CPCo 05/07/81 l

XV-6 DL/SEPB 7

NRC to CPCo 11/03/81 XVI X

NRC to CPCo 11/05/80 XV-7 DL/SEPB 7

NRC to CPCo 11/03/81 XVII DL 7

NRC to CPCo 08/17/78 XV-8 DL/SEPB 7

HRC to CPCo 11/03/81 XV-9 DL/SEPB 7

NRC to CPCo 11/03/81 (2-34)

SAN ON0FRE FACILITY: SAN ONOFRE 1 TOPIC NO.

REVIEW STATUS REMARKS DIV/BR LICENSEE: SOUTHERN CALIFORNIA EDISON II-1 A.

DL/SEPB 7

HRC to SCE 11/07/79 REGION / LOCATION: 5 MILES SOUTH OF SAN CLEMEHTE, CA.

II-1 B.

DL/SEPB 7

HRC to SCE 11/07/79 DOCKET NO.

05000206 II-1 C.

DE/SAB 4b SCE to NRC 11/12/81 POWER CAPACITY: 1347CTHERMAL) 0430(ELECTRICAL)

II-2 A.

DSI/AEB 7

HRC to SCE 04/27/81 OL NUf1BER: DPR-13 II-2 B.

X HRC to SCE 05/07/81 H.S.S.S.-

WEST.

II-2 C.

DSI/AEB 7

HRC to SCE 11/18/81 A/E FIRM: BECH.

II-2 D.

X HRC to SCE 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRAH;H CHIEF: W.

RUSSELL II-3 A.

DE/HGEB 3

SCE TO HRC 09/13/82 OPERATING REACTORS BRANCH CHIEF:

D. CRUTCHFIELD II-3 B.

DE/HGEB 3

SCE TO HRC 09/13/82 CPERATING REACTORS PROJECT MANAGER: W. PAULSON II-3 B.

1 DE/HGEB 3

SCE TO HRC 04/12/82 INTEGRATED ASSESSMENT PROJECT MAnauta: E. MCKENH A ( / ?l 'h (

II-3 C.

DE/HGEB 2

HRC to SCE 01/07/82 KEY FOR STATUS CODES 03/15/81 II-4 DE/ GSB 5

HRC to SCE II-4 A.

DE/GSB 7

HRC TO SCE 09/16/82 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.

DE/GSB 5

HUREG-0712 12/80 FROM REVIEW BRANCH X-DELETED II-4 C.

DE/GSB -

7 HRC TO SCE 09/16/82 4b-SAR RECEIVED FROM 0 - TOPIC NOT LICEHSEE II-4 D.

DE/HGEB 4A 10/28/82 STARTED 5 - DRAFT SE SENT II-4 E.

X HRC tv SCE 11/16/79 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRAHUI II-4 F.

DE/HGEB 4b SCE to HRC 11/02/81 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC III-1 DL/SEPB 5(SYS)

HRC TO SCE 06/25/82 TO UTILITY DL/SEPB 7(Elec) Part of VII-3 11/18/81 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 4A 09/03/82 RECEIVED BY HRC (2-35)

SAN ONOFRE TOPIC NO.

REVIEW STATUS REMARKS TOPIC NO.

REVIEW STATUS REMARKS DIV/BR DIV/BR 111-3 A.

DE/SEB 3

SCE to NRC 09/68/80 III-10 B.

DL/SEPB 7

NPC to SCE 11/08/79 III-3 B.

X NRC to SCE 11/16/79 III-10 C.

X NRC to SCE 11/16/79 III-3 C.

DE/ HGEB 7

NRC to SCE 11/27/81 III-11 X

HRC to SCE 05/07/86 III-4 A.

DSI/ASB 4A 09/30/82 III-12 X

NRC to SCE 05/07/81 III-4 B.

DE/MTEB 5

HRC TO SCE 06/24/82 IV-1 A.

DL/SE4B 7

NRC to SCE 11/13/79 III-4 C.

DSI/ASB 7

HRC TO SCE 10/12/82 IV-2 DSI ICSB 5

NRC TO SCE 09/14/82 III-4 D.

DE/SAB 4b SCE to NRC 10/23/81 IV-3 X

NRC to SCE 05/07/81 III-5 A.

DL/SEPB 0

V-1 X

NRC to SCE 11/27/81 III-5 B.

DL/SEPB 0

v-2 X

htC to SCE 11/16/79 III-6 DL/SEPB 3

SCE to NRC 12/08/81 V-3 X

N K C

.o SCE 05/07/81 III-7 A.

X HRC to SCE 05/07/81 V-4 X

NRC to SCE 05/07/81 III-7 B.

DL/SEPB 5

HRC TO SCE 09/21/82 V-5 DL/SEPB 5

HRC to SCE 06/03/81 III-7 C.

X NRC to SCE 11/16/79 V-6 DL/SEPB 7

HRC to SCE 03/05/80 III-7 D.

DE/SEB 7

NRC TO SCE 04/23/82 V-7 DSI/ASB 7

NRC to SCE 12/04/81 III-8 A.

DSI 7

NRC to SCE 12/21/81 V-8 X

NRC to SCE 05/07/81 III-8 B.

X HRC to SCE 10/01/80 V-9 X

HRC to SCE 11/16/79 III-8 C.

DL/SEPB 7

NRC to SCE 01/29/80 V-10 A.

DL/SEPB 7

NRC to SCE 01/07/81 III-8 D.

X NRC to SCE 05/07/81 V-10 B.

DL/SEPB 6

SCE TO NRC 04/26/82 III-9 X

HRC to SCE 05/07/81 V-11 A.

DL/SEPB 7

HRC to SCE 08/03/81 1

III-10 A.

DL/SEPB 7

SCE to NRC 07/24/81 V-11 B.

DL/SEPB 6(SYS)

SCE TO HRC 04/26/82 DL/SEPB 7(Elec) HRC to SCE 02/04/82 (2-36)

SAN ON0FRE TOPIC NO.

REVIEW STATUS REMARKS TOPIC NO.

REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.

X NRC to SCE 11/16/79 VI-7 D.

DL/SEPB 7

HRC to SCE 08/17/78 V-13 X

NRC to SCE 05/07/81 VI-7 E.

X NRC to SCE 05/07/81 VI-1 7

NRC TO SCE 07/13/82 VI-7 F.

X NRC to SCE 11/16/79 VI-2 A.

X NRC to SCE 05/07/81 VI-8 X

NRC to SCE 05/07/81 VI-2 B.

X HRC to SCE 05/07/81 VI-9 X

NRC to SCE 11/16/79 VI-2 C.

X NRC to SCE 11/16/79 VI-10 A.

DL/SEPB 7

NRC to SCE 08/28/81 VI-2 D.

DSI/CSB 7

NRC TO SCE 05/27/82 VI-10 B.

DL/SEPB 7

HRC to SCE 11/15/79 VI-5 DSI/CSB 7

NRC TO SCE 05/27/82 VII-1 A.

DL/SEPB 7

HRC to SCE 09/09/81 VI-4 DSI/CSB 7(SYS)

NRC TO SCE 09/16/82 DL/SEPB 7(Elec) NRC to SCE 09/03/81 VII-1 B.

DL/SEPB 7

NRC to SCE 08/17/78 VI-5 X

NRC to SCE 05/07/81 VII-2 DL/SEPB 7

HRC to SCE 11/17/81 VI-6 DSI/CSB 7

NRC TO SCE 08/12/82 VII-3 DL/SEPB 6(SYS)

SCE TO HRC 04/26/32 DL/SEPB 7(Elec) HRC to SCE 06/04/82 VI-7 A.

DL/SEPB 7

NRC to SCE 02/20/81 VII-4 X

NRC to SCE 05/07/81 VI-7 A.

2.

X HRC to SCE 05/07/81 VII-5 X

NRC to SCE 05/07/81 VI-7 A.

3.

DL/SEPB 7

NRC to SCE 11/18/81 VII-6 DL/SEPB 7

HRC to SCE 08/28/81 VI-7 A.

4.

X NRC to SCE 05/07/81 VII-7 X

HRC to SCE 11/16/79 VI-7 B.

DSI/RSB 6(SYS)

SCE TO NRC 01/26/82 DL/SEPB 7(Elec) NRC TO SCE 09/15/82 VIII-1 A.

DSI/RSB G

NRC to SCE 05/07/81 VI-7 C.

DL/SEPB 7

NRC to SCE 06/01/81 VIII-2 DL/SEPB 7

HRC to SCE 07/31/81 VI-7 C.

1 DL/SEPB 7

NRC to SCE 08/03/81 VIII-3 A.

DL/SEPB 7

HRC to SCE 11/07/79 VI-7 C.

2.

DL/SEPB 7

NRC to SCE 06/01/81 VIII-3 B.

DL/SEPB 7

NRC to SCE 07/24/81 VI-7 C.

3.

X HRC to SCE 11/16/79 VIII-4 DL/SEPB 6

SCE TO NRC 05/26/82 (2-37)

SAN ON0FRE TOPIC HO.

REVIEW STATUS REMARKS TOPIC NO.

REVIEW STATUS REMARKS DIV/BR DIV/DR IX-1 DSI/ASB 4A 09/29/82 XV-10 DSI/RSB 7

NRC 10 SCE 04/20/82 IX-2 X

NRC to SCE 05/07/81 XV-11 X

NRC to SCE 10/01/80 IX-3 DL/SEPB 4A 09/30/82 XV-12 DSI/RSB 7(Sys)

HRC to SCE 04/05/82 DL/SEPB 7(Doses) HRC to SCE 01/29/80 IX-4 DSI/RSB 7

NRC to SCE 07/16/81 XV-13 X

NRC to SCE 11/16/79 IX-5 DL/SEPB 4A 08/24/82 XV-14 DSI/RSB 7

NRC to SCE 02/22/82 IX-6 DE G

NRC to SCE 05/07/81 XV-15 DSI/RSB 7

NRC TO SCE 04/20/82 X

X HRC to SCE 05/07/81 XV-16 DSI/AEB 7

NRC to SCE 04/05/82 XI-1 X

HRC to SCE 12/04/81 XV-17 DSI/RSB 7(Sys)

SCE TO NRC 03/12/82 XI-2 X

NRC to SCE 12/04/81 DSI/AEB 7(Doses) HRC to SCE 01/29/80 XIII-1 X

HRC to SCE 05/07/81 XV-18 X

HRC to SCE 10/01/80 XIII-2 DL/SSPB 7

NRC to SCE 01/22/81 XV-19 DSI/RSB 7(Sys)

SCE TO HRC 03/12/82 DL/SEPB 7(Doses) NRC to SCE 01/29/80 XV-1 DSI/RSB 7

NRC TO SCE 07/22/82 XV-20 DL/SEPB 7

NRC to SCE 03/28/80 XV-2 DSI/RSB 6(Sys)

SCE to NRC 03/12/82 DL/SEPB 7(Doses) HRC to SCE 01/29/80 XV-21 X

HRC to SCE 05/07/81 XV-3 DSI/RSB 7

NRC TO SCE 03/12/82 XV-22 X

NRC to SCE 05/07/81 XV-4 DSI/RSB 7

NRC to SCE 04/05/82 XV-23 X

NRC to SCE 05/07/81 XV-5 DSI/RSB 7

NRC to SCE 02/01/82 XV-24 X

NRC to SCE 05/07/81 XV-6 DSI/RSB 7

NRC TO SCE 03/03/82 XVI X

HRC to SCE 11/05/80 XV-7 DSI/RSB 4A 09/29/82 XVII DL 7

NRC to SCE 11/20/79 XV-8 DSI/CPB 7

SCE TO NRC 03/12/82 XV-9 DSI/RSB 7

NRC to SCE 02/24/82 (2-38)

YANKEE FACILITY: YANKEE NUCLEAR F0WER STATION TOPIC NO.

REVIEW STATUS REMARKS DIV/BR LICENSEE: YANKEE ATOMIC ELECTRIC 11-1 A.

DE/SAB 7

NRC TO YAEC 07/13/82 REGICH/ LOCATION: 25 MILES HORTH EAST OF PITTSFIELD, MASS.

II-1 B.

DE/SAB 7

NRC TO YAEC 07/13/82 DOCKET NO.

05000029 II-1 C.

DE/SAB 7

NRC TO YAEC 07/13/82 POWER CAPACITY: 600(THERMAL) 165(ELECTRICAL)

II-2 A.

DSI/AEB 7

NRC to YAEC 08/03/81 OL NUMBER: DPR-3 II-2 B.

X NRC to YAEC 05/07/81 H.S.S.S.

MEST.

II-2 C.

DSI/AEB 7

HRC to YAEC 09/04/81 A/E FIRf1: StW II-2 D.

X NRC to YAEC 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL II-3 A.

DE/HGEB 7

NRC TO YAEC 09/30/82 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD II-3 B.

DE/HGEB 7

HRC TO YAEC 09/30/82 OPERATING REACTORS PROJECT MANAGER:

R. CARUSO II-3 B.

1.

DE/HGEB 7

NRC TO YAEC 09/30/82 BOYLEfh II-3 C.

DE/HGEB 7

NRC TO YAEC 09/30/82 INTEGRATED ASSESSMENT PROJECT MANAGER: M.

II-4 DE/GSB 7

NRC to YAEC 07/15/82 KEY FOR STATUS CODES II-4 A.

DE/GSB 7

NRC to YAEC 06/08/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.

DE/GSB 7

HRC TO YAEC 07/15/82 FROM REVIEW BRANCH X - DELETED II-4 C.

DE/GSB 7

HRC to YAEC 06/08/81 4b-SAR RECEIVED FROM 0 - TOPIC HOT LICENSEE II-4 D.

DE/HGEB 7

HRC TO YAEC 09/02/82 STARTED 5 - DRAFT SE SENT II-4 E.

DE/HGEB 4A 08/31/82 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.

DE/HGEB 7

HRC TO YAEC 09/16/82 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY HRC III-1 DL/SEPB 7(Elec) HRC to YAEC 09/14/82 TO UTILITY DL/SEPB 7(SYS)

HRC TO YAEC 06/18/82 7 - TO?IC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 7

HRC TO YAEC 08/31/82 RECEIVED BY NRC (2-39)

YANKEE TOPIC HO.

REVIEW STATUS REMARKS TOPIC NO.

REVIEW STATUS REMARKS DIV/BR DIV/BR j

III-5 A.

DE/SEB 7

NRC TO YAEC 10/13/82 II' 10 B.

X 14RC to YAEC 11/16/79 III-3 B.

X hRC to YAEC 12/26/80 III-10 C.

X NRC to YAEC 11/16/79 III-3 C.

DE/NGEB 7

NRC TO YAEC 10/04/82 III-11 X

HRC to YAEC 05/07/81 III-4 A.

DSI/ASB 7

NRC TO YAEC 08/31/82 III-12 X

HRC to YAEC 05/07/81 III-4 B.

DE/MTEB 7

HRC to YAEC 02/08/82 IV-1 A.

DL/SEPB 7

HRC to YAEC 04/18/79 III-4 C.

DSI/ASB 7

NRC TO YAEC 09/29/82 IV-2 DSI/ICSB 7

HRC to YAEC 12/23/81 III-4 D.

DE/SAB 7

HRC TO YAEC 07/13/82 IV-3 X

NRC to YAEC 05/07/81 i

III-5 A.

DL/SEPB 7

NRC TO YAEC 08/20/82 V-1 X

NRC to YAEC 11/27/81 III-5 B.

DL/SEPB 7

NRC TO YAEC 06/29/82 V-2 X

HRC to YAEC 11/16/81 III-6 DL/SEPB 5

HRC TO YAEC 10/04/82 V-3 X

NRC to YAEC 05/07/81 III-7 A.

X NRC to YAEC 05/07/81 V-4 X

HRC to YAEC 05/07/81 III-7 B.

DL/SEPB 5

NRC TO YAEC 09/01/82 V-5 DL/SEPB 7

HRC TO YAEC 07/13/82 s

III-7 C.

X NRC to YAEC 11/16/79 V-6 DL/SEPB 7

HRC to YAEC 03/05/80 III-7 D.

DE/SEB 7

NRC TO YAEC 03/18/82 V-7 X

HRC to YAEC 12/14/81 III-8 A.

DSI 7

NRC to YAEC 12/29/81 V-8 X

NRC to YAEC 05/07/81 III-8 B.

X NRC to YAEC 10/01/80 V-9 X

HRC to YAEC 11/_16/79 III-8 C.

DL/SEPB 7

NRC 'm YAEC 11/15/79 V-10 A.

DL/SEPB 7

NRC to YAEC 11/05/79 III-8 D.

X NRC to YAEC 05/07/81 V-10 B.

DL/SEPB 7

HRC to YAEC 02/01/82 III-9 X

HRC to YAEC 05/07/81 V-11 A.

DL/SEPB 7

HRC to YAEC 07/27/82 III-10 A.

DL/SEPB 7

NRC to YAEC 09/22/81 V-11 B.

DL/SEPB 7(Sys)

HRC to YAEC 02/01/82 DL/SEPB 7(Elec) HRC to YAEC 07/27/82 a

4 (2-40) 1 4

YANKEE TOPIC NO.

REVIEW STATUS REMARKS TOPIC NO.

REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.

X NRC to YAEC 11/16/79 VI-7 D.

DL/SEPB 7

NRC to YAEC 08/17/78 V-13 X

NRC to YAEC 05/07/81 VI-7 E.

X NRC t'o YAEC 05/07/81 VI-1 DE/CEB 5

HRC TO YAEC 09/09/82 VI-7 F.

DL/SEPB 7

HRC to YAEC 08/28/81 4

VI-2 A.

X HRC to YAEC 05/07/81 VI-8 X

HRC to YAEC 05/07/81 VI-2 B.

X NRC to YAEC 05/07/81 VI-9 X

HRC to YAEC 11/16/79 VI-2 C.

X HRC to YAEC 11/16/79 VI-10 A.

DL/SEPB 7

NRC to YAEC 06/10/82 VI-2 D.

DSI/CSB 7

HRC TO YAEC 08/20/82 VI-10 B.

X NRC to YAEC 11/16/79 VI-5 DSI/CSB 7

NRC TO YAEC 08/20/82 VII-1 A.

DL/SEPB 7

NRC to YAEC 02/22/82 i

VI-4 DSI/CSB 5(SYS)

HRC TO YAEC 09/01/82 VII-1 B.

DL/SEPB 7

NRC to YAEC 08/17/78 DL/SEPB 7(Elec) NRC to YAEC 03/05/82 YII-2 DL/SEPB 7

NRC to YAEC 02/01/82 VI-5 X

NRC to YAEC 05/07/81 VII-3 DL/SEPB 7(Sys)

HRC to YAEC 02/01/82 VI-6 DSI/CSB 7

NRC TO YAEC 09/02/82 DL/SEPB 7(Elec) HRC to YAEC 09/14/82 VI-7 A.

1 DL/SEPB 7

NRC to YAEC 02/20/81 VII-4 Y

NRC to YAEC 05/07/81 VI-7 A.

2.

X HRC to YAEC 05/07/81 VII-5 X

HRC to YAEC 05/07/81 i

VI-7 A.

3.

DL/SEPB 7

NRC to YAEC 02/08/82 VII-6 DL/SEPB 7

NRC to YAEC 08/28/81 VI-7 A.

4.

X HRC to YAEC 05/07/81 VII-7 X

NRC to YAEC 11/16/79 VI-7 B.

DSI/RSB 7(Elec) NRC to YAEC 06/04/81 VIII-1 A.

DSI/PSB 7

HRC TO YAEC 09/27/82 7(SYS)

NRC TO YAEC 07/13/82 VI-7 C.

DL/SEPB 7

NRC to YAEC 03/13/81 VIII-2 DL/SEPB 7

NRC to YAEC 09/03/81 VI-7 C.

1 DL/SEPB 7

NRC to YAEC 09/04/82 VIII-3 A.

DL/SEPB 7

NRC to YAEC 11/07/79 VI-7 C. 2.

DL/SEPB 7

NRC to YAEC 03/13/81 VIII-5 B.

DL/SEPB 7

HRC to YAEC 08/28/81 VI-7 C.

3.

DL/SEPB 7

NRC to YAEC 07/24/80 VIII-4 DL/SEPB 7

NRC TO YAEC 08/13/82 4

1 (2-41) 1 4

YANKEE J

TOPIC H0.

REVIEW STATUS REMARKS TOPIC NO.

REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 7

NRC 10 YAEC 09/16/82 XV-10 DSI/RSS 7

HRC 10 YAEC 04/26/82 4

IX-2 X

HRC to YAEC 05/07/81 XV-11 X

NRC to YAEC 13/01/80 IX-3 DL/SEPB 7

HRC (0 YAEC 06/11/82 XV-12 DSI/CPB 7(SYS)

HRC TO YAEC 04/16/82 i

DSI/AEB 7(Doses) HRC to YAEC 12/29/81 IX-4 DSI/RSB 7

NRC TO YAEC 06/15/82 XV-13 X

HRC to YAEC 11/16/79 IX-5 DL/SEPB 7

HRC TO YAEC 06/14/82 XV-14 DSI/RSB 7

HRC TO YAEC 07/14/82 IX-6 DE G

HRC to YAEC 05/07/81 l

XV-15 DSI/RSB 7

HRC TO YAEC 05/10/82 X

X HRC to YAEC 05/07/81 XV-16 DSI/AEB 7

H.tC TO YAEC 08/31/82 XI-1 X

HRC to YAEC 12/04/81 XV-17 DSI/RSB 7(SYS) hRC TO YAEC 08/31/82 XI-2 X

HRC to YAEC 12/04/81 DSI/AEB 7(DOSES) HRC TO YAEC 03/30/82 i

XIII-1 X

HRC to YAEC 05/07/81 XV-18 X

NRC to YAEC 10/01/80 XIII-2 DL/SSPB 7

NRC to YAEC 08/31/82 XV-19 DSI/RSB 7(SYS)

HRC TO YAEC 07/13/82 DSI/AEB 7(DOSES) HRC TO YAEC 09/01/82 XV-1 DSI/RSB 7

HRC TO YAEC 07/19/82 XV-20 DL/SEPB 7

NRC to YAEC 09/06/81 XV-2 DSI/RSB 7(SYS)

HRC TO YAEC 07/13/82 DSI/AEB 5(DOSES) HRC TO YAEC 09/01/82 XV-21 X

HRC to YAEC 05/07/81 XV-3 DSI/RSB 7*

HRC to YAEC 01/25/82 XV-22 X

NRC to YAEC 05/07/81 XV-4 DSI/RSB 7

HRC TO YAEC 07/21/82 XV-23 X

NRC to YAEC 05/07/81 a

XV-5 DSI/RSB 7

HRC to YAEC 02/10/82 XV-24 X

HRC to YAEC 05/07/81 XV-6 DSI/RSB 7

NRC TO YAEC 07/13/82 XVI X

HRC to YAEC 11/05/80 XV-7 DSI/RSB 7

NRC TO YAEC 06/29/82 XVII DL 7

NRC to YAEC 11/20/79 XV DSI/CPB 7

HRC TO YAEC 03/05/82 XV-9 DSI/RSB 7

NRC TO YAEC 06/25/82 (2-42) 4

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PAllSADES EL PALISADES Eil 8

SAR 1/

SER R/

SAR 1/

SEP 2/

TOPIC NO. TITLE SCHEDULE SCHEDULE TCPIC NO. TITLE SCNEDULE SCHEDULE 111-1 Classitication of NChE 12/15/81C III-8.A Looso Parts M.m.itoring and NONE 11/03/81C (SYS)

Structures Cenponents and Core Barrel Vibration Systers (Seismic and Monitoring (NRR B-60. C-12)

Quality)

IV-2 Reactivity Control Systems 07/31/81R 10/16/81C III-5.A Effects of Pipe Break on 08/13/81R 12/04/81C Including Functional Design Structures, Systems and and Protection Against Components Inside Single Failures Containment V-7 Reactor Coolant P NONE 11/16/81C III-S.B Pipe Break Outside 08/25/81R 12/23/81C Overspeed (N Containment VI-6 C

m n Lea Test g NONE 08/05/81C III-7.A Inservice Inspection.

NONE 08/15/81C (M

4 Including Prestressed Concrete Containments with V

T-

.A t

la quipment E

12/22/81C Either Grouted or Ungrouted

'\\

F res Associate i

,)

Tendons

" Degraded Grid t e III-7.B Design Codes. Design N.~

/16 1C Criteria, Lead IX-1 S

a NONE 12/11/81C Combinations, and Reactor 1

("i

")

IX-4l Cavity Design rit1ria ror A

e on System 10/09/81R 11/18/81C I

L 1

1 i

-m IX-6

% / Fire Protection (MP B-41)

NDHE 03/05/82C j, k -

S S

(

XI-1 Appendix I(MP A-02)

NONE DELETED TOPIC NO. TITLE S

HE L L

L XI-2 Radiological (Effluent NONE DELETED III-3.C Inscrosco inspecti of

/21M IR,kC2/12/82C and Process) Monitoring Water Control - ruct res A

Systems (NRR B-67)

'~

III-4.B T-n e'Mi-s le MP B NONE 12/02/81C J/ SAR : Licensee Safety Analysis Report-Scheduled or Actual III-7.D e niai reni 5 uctural NONE 08/17/81C (Actual (status 4b) when date is followed by R) t cri Ly l,ests 2/ SER : Staff Safety Evaluation Report -Scheduled or Actual V-1 ompliance with Codes and NONE DELETED (Actual (status 4a. 5, 7) when date is followed by C)

Standards (10 CFR 50.55a)

(MP A-01,A-14) 1/ Desiginated number of days from receipt of licensee SAR (Note: if Licensee SAR is received then date is from receipt of additional information requested)

(3-2)

LICENSEE TOPIC SUBMITTALS PALISADES TOPICS 40 TARGET 35 ACTUAL 30 25 20 ALL SUBMITTALS RECEIVED 15 10 5

'/

~~

[l i

I l

l l

l g

JUN JUL AUG SEP OCT NOV DEC JAN FEB MAR APR MAY JUN JUL/DEC i

TARGET 1

2 3

PER MONTH ACTlW.

1 2

0 1

1 1

TARGET 1

3 6

CUMULATIVE ACTUAL 1

3 3

4 5

6 i

G-3)

GINNA R GINNA 25,1 SAR 1/

SER 2/

SAR 1/

SER 2/

TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCNEDULE III-1 Classification of Struct-NONE 12/29/81C III-4.C Internally Generated 01/11/ 82 R 02/02/82C (SYS) ures Components and Systems Missiles (Seismic and Quality)

III-8.A Loose Parts Monitoring and NONE 11/03/81C III-2 Wind and Tornado Loadings NONE 09/23/81C Core Barrel Vibration Monitorinq(NRR B-60,C-12)

III-7.A Inservice Inspection, NONE 12/23/81C Including Prestressed V-7 Reactor Coolant Pump NONE 11/05/81C Concrete Containments with Cverspeed(NRR B-68)

Either Grouted or Ungrounded Tendons VI-2.D Mass and Ener 1

e for NONE 09/25/81C Possibt B eak side III-7.B Design Codes, Design NONE 12/31/8tC Co m

Criteria, Load Combinations, and Reactor VI on nme essure and N

09/25/81C Cavity Design Criteria a

em Capability VI-7.C.1 Appendix K - Electrical NONE 11/

4 VI s"ESF Switchover om NON 12/18/81C Instrumentation and Control (S

Injection eci e at j

(EIC) Re-reviews Mode (

oi ti wCS IX-5 Ventilation Systems 1/

IC rk

~1 1

L J ~

IX-1 l 1 It NONE 11/24/81C 90 d'

a 21 IX-6 Fire Protection (MP B-41)

NONE 02/24/82C SAR 1/

SCpq%{q q

L I-1 Appendix I(MP A-02)

NONE DELETED TOPIC NO. TITLE 11-1.8 Population Distributio

/15 IR O M(Z)/8 TU XI-2 Radiological (Effluent NONE DELETED and Process) Monitoring II-1.C Potential Haza s or 5

R 07/01/81C Systems (NRR B-67)

Change 44n te ial H

s Due XV-9 Startup or an Inactive Loop NONE 10/16/81C s or tat or Recirculation Loop at an tit i l og gJ dustrial.

Incorrect Temperature, and il tary Facilities Flow Controller Malfunction Causing an Increase in BWR II-4.D ability of Slopes 06/30/81R 02/01/82C Core Flow Rate II-4.F Settlement of " andations 06/30/81R 01/29/82C XV-19 Loss-of-Coolant Accidents NDHE 09/29/81C and Buried Equipment (DOSES)

Resulting from Spectrum of (SYS)

Postulated Piping Breaks 10/02/81C III-3.C Inservice Inspection of 10/12/81R 02/09/82C Within the Reactor Coolant Water Control Structures Pressure Boundary III-4.B Turbine Missiles (MP B-46)

NONE 12/02/81C le SAR = Licenson Safety Analysis Report-Scheduled or Actual (actual (status 4b) when date is follwed by R)

III-4.D Site Proximity Missiles 04/16/81R 07/21/81C (Including Aircraft)

Z/ SER = Staff Safety Evaluation Report -Scheduled or Actual (Actual (status 4a, 5, 7) when date is followed by C)

VI-1 Organic Materials and 11/06/81R 02/18/82C Post Accident Chemistry J/ Desiginated number of days from receipt of licensee SAR (Note:

if Licensee SAR is received then date is-from receipt of additional information requested)

(3-4)

LICENSEE TOPIC SUBMITTALS GINNA TOPICS 4g TARGET 35 ACTUAL 30 25 20 ALL SUBMITTALS RECEIVED 15 10 5

~~

l lT l

l l

l g

JUN JUL AUG SEP OCT NOV DEC JAN FEB MAR APR MAY JUN JUL/DEC 1

TARGET 0

0 2

0 0

1 PER MONTH ACTUAL 0

0 0

1 1

1 TARGET 0

0 2

2 2

3 CUMULATIVE ACTUAL 0

0 0

1 2

3

- G-5)

DRESDEN 2 D1 DRESDEN 2 D1 (Cont.)

SAR 1/

SER 2/

SAR J/

SER 2/

TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE 111-1 Classification of NONE 03/03/82C 11-3.B Flooding Potential and NONE 0 6 /11/ 82 C (SYS)

Structures, Components and Protection Requirements Systems (Seismic and quality)

II-3.B.1 Capability of Operating NONE 06/11/82C Plant to Cope with Design III-2 Wind and Torrado Loadings 06/04/82R 06/21/82C Basis Flooding Conditions i

III-5.A Effects of Pipe Break on 06/04/82R 06/28/82C TT 3.C Safety-related Water NONE 06/11/82C Structures, Systems and Supply (Ultimate Heat Sink Components Inside (UHS))

Containment II-4.D Stabil S opes 12/08/81R 07/02/82C III-7.B Design Codes, Design NONE 05/17/82C Criteria, Load II-4.E Da nt 12/08/

01/22/82C Conbinations, and Reactor Cavity Design Criteria I

-4.

et leme f Foundati 06/30/82C VI-4 Containment Isolation NONE 11 M "iT uried Equipmen j

(ELEC)

System L

II

.A Effects o' a rL 1 (12

/ 1R 05/24/82C on St ti e

(+My VII-1.A Isolation of Reactor 0 0 81C Protection System from III-3geW(

ns v tion of 02/16/82R 06/30/82C Hon-Safety System t

t Structures Including Cu ific tions of Isolation ev es 9

III-4 T

ine Missiles NONE 05/18/82C VII-6 Frequency ca NONE

/ 1 III-4.D Site Proximity Missiles 12/08/81R 02/05/82C (Including Aircraft)

IX-5 Ventilat; ion Systems LNO. E

/-

'(

\\

u mr 1

\\

JL 3-III-7.D Containment Structural 04/27/81R 03/30/82C

-e Integrity Tests

~

(,s SAR 1/

SER 2/

V-1 Compliance with Codes NONE DELETED TOPIC N 4 L SCHEDJLE SCHEDULE and Standards (10 CFR t

\\

Il-1.A Q usTon'Frea Authority 06/01/81R___

09/16/81C._

50.55a)(MP A-01 A-14)

J Control V-4 Piping and Safe End NONE 06/25/82C In tegri ty II-1.B Population Distribution 04/27/J1R 09/16/81C VI-1 Organic Materials and 05/21/82R 07/02/82C II-1.C Potential Hazards or-12/08/at.t 06/30/82C Post Accident Chemistry Changes in Potential Hazards Due to Transportation, Dil Institutional Industrial, SAR 1/

SER 2/

and Military Facilities TOPIC HO. TITLE SCHEDULE SCHEDULE II-3.A Hydrologic Description NONE 06/11/82C II-2.C Atmospheric Transport and 03/20/81R 68/26/81C Diffusion Characteri stics for Accident Analysis III-4.A Tornado Missiles 12/08/81R 06/21/82C.

(3-6)

DRESDEN 2 E11 (Cont.)

211 (Cont.)

i SAR 1/

SER Z/

SAR 1/

SER 7/

TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE Ill-4.C Internally Generated 05/17/82R 06/22/82C XV-3 Loss of External Load.

10/15/81R 1 1/17 / 81 C Missiles Turbine Trip, Loss of Condenser Vacuum. Closure III-8.A Looso Parts Monitoring NONE 02/09/82C of Main Steam Isolation and Core Barre.1 Vibration Valve (BWR), and Steam Monitoring (HRR B-60,C-12)

Pressure Regulator Failure (Closed)

IV-2 Reactivity Control Systems NONE 09/28/81C Including Functional Design XV-4 Loss of Non-Emergency A-C 10/15/81R 11/17/81C and Protection Against Power to the Station Single Failures Auxiliaries VI-2.D Mass and Energy Release for NONE 12/02/81C XV-5 Loss of Normal Feedwater 10/15/81R 12/04/81C Possible Pipe Break Inside Flow Containment XV-7 Reactor Coolant Pump Rotor 10/15/81R 12/18/81C VI-3 Containment Pressure and NONE 12/02/81C Seizure and Reactor Coolant Neat Removal Capability Pump Shaft Break VI-4 Containment Isolation NONE 10/02/81C XV-8 Control Rod Misoperation 10/15/81R 01/27/82C (SYS)

System (System Malfunction or Operator Error)

VI-6 Containment Leak Testing NONE 12/30/81C (MP A-04)

XY-9 Startup or an Inactive Loop 10/15/81R 12/07/81C or Recirculation Loop at an VI-7 A.4 Core Spray Nozzle NONE 02/09/82C Incorrect Temperature, and Effectiveness (HRR A-16)

Flow Controller Malfunction Causing an Increase in BWR VIII-1.A Potential Equipment NONE 03/31/82C Core Flow Rate Failures Associated with a Degraded Grid Voltage XV-11 Inadvertent Loading and 10/15/8tR 01/25/82C (MP B-23)

Operation of a Fuel Assembly in an Improper IX-1 Fuel Storage 02/02/82R 03/26/82C Position IX-6 Fire Protection (MP B-41)

NONE 06/23/82C XV-13 Spectrcm of Rod Drop 10/15/81R 01/25/82C (SYS)

Accidents (BWR)

XI-1 Appendix I(MP A-02)

NONE DELETED (DOSES) 10/15/81R 12/14/81C XI-2 Radiological (Effluent and NONE DELETED XV-14 Inadvertent Operation of 10/15/81R 12/08/81C Process) Monitoring Systems ECCS and Chemical and (HRR B-67)

Volume Control System Malfunction that Increases XV-1 Increase in Feedwater 10/15/81R 12/14/81C Reactor Coolant Inventory Temperature, Increase in Feedwater Flow, Increase XV-15 Inadvertent Opening of a 10/15/81R 12/22/8tC in Steam Flow and PWR Pressurizer Safety-Inadvertent Opening of a Relief Valve or a BWR Steam Generator Relief or Safety / Relief Valve Sofety Valve (3-7)

DRESDEN 2

' E11 (Cent.)

S*R 1/

SER Z/

T0*IC NO. TITLE S C H E U.?. E SCHEDULE xv-18 Radio 1cqtcal Consequences 10/157514 12/23/81C of Main Sto m Line Failure Out-ide Centain,cnt ( B'R )

XV-19 Los of-Coolant Accidents 10/19/51,1 11/17/81C (SYS)

Fesulting from Spectrum of I

(DOSES)

Postulated Piping Breaks 10/15/s14 12/15/81C Within the Reactor Coolant Pressure Boundary XV-20 Radiological Consequences O w / 2 / / a ;.<. 11/04/81C of Fuel Dceaqing Accidents (Inside and Outsice Containment Licensee Safety Analysis Report-Scheduled or Actual l/ SAR (actual (:tatus 46) when date is folic.wd af R)

Z/ SER = Staff Safety Evaluation Report -Sch0CJIed or Actual (Actual (status 4a, 5, 7 ) when date is fallow 2d by C) 1/ Desiginated number of days from receipt of lic2nsee SAR (Note:

if Licensee SAR is received then dati i s f rom receipt of additional information requested)

(3-8)

LICENSEE TOPIC SUBMITTALS DRESDEN 2 TDPICS 4g TARGET 35 1

ACTUAL 30 l

25

, -g-20 ALL SUB TALS RECEIVED 15 10, 5

I I

I l

0 JUN JUL AUG SEP OCT NOV DEC JAN FEB MAR APR MAY JUN JUL/DEC TARGET 0

0 2

0 0

1 j

ACTUAL 0

0 0

14 0

7 0

1 1

0 2

1 TARGET 22 22 23 25 25 25 26 CUMULATIVE ACTUAL 0

0 0

14 14 21 21 22 23 23 25 26 G-9)

OYSTER CREEK RL OYSTER CREEK pf (Cont.)

SAR 1/

SER 2/

SAR 1/

SER Z/

TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE Ill-1 Classification of NONE 01/29/82C 111-4.8 Turbine Missiles 12/07/81R 06/27/82C (SYS)

Structures, Components and Systems III-4.D Site Proximity Missiles 03/31/82N 06/21/82C III-2 Wind and Tornado loadings 03/31/82N 06/08/82C III-7.D Containment Structural 11/04/81R 02/25/82C Integrity Tests III-7.B Design Codes, Design NONE 04/30/82C Criteria, Load Combinations V-1 Compliance with Codes NONE DELETED and Reactor Cavity Design and Structures (MP A-01,A-14)

VII-6 Frequency Decay NONE 08/29/81C VI-1 Organic Mat ' s Post 07/30/82N 06/29/82C

&gei gel IX-5 Ventilation System 02/28/82N 05/21/82C emi try j

VI-7.A-4 Core Spray Nozzle NONE 06/28/82C s--a

\\

1- \\

t 1

.-1 1

Effectiveness (MP D-12)

J pli

\\ g*

'.k{

,\\

\\

7

%* ITLE SA N6. T T

HE

-1/1 SER 2/

-r""T 11 T PI E" SCHEDULE p1 i

T7 TT1 i

A-

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S 2/ l Il-2.C Atmo he rp6sp rt jd 11/04/81R 02/24/82C y

TOPIC NO. TITLE

/*i ULE H

LE"

(**( {

Mf u 'o acte ics L

fon A

'y

, alysi s II-1.A Exclusion Are A ority 1T{30351W" 01/18/8 2 C J

kgp!

'd P

and Cont ol

)

"'k III

.A iado'Missles 0 3/31/82N 05/27/82C II-1.B Populati o Di tr n

11/30/81R

'18 III-4.C Internally Generated 05/19/82R 05/28/82C Missiles II-1.C Potentigt zards Due to 1

08 01/ l8 2C L

Transportation, Indus tal III-8.A Loose Parts and Core NONE 02/09/82C and Military Faci ' ie Barrel Monitoring (NRR B-60,C-12)

II-3.A HydroJpgii De ript on 04/82R 06/28/82C 1

IV-2 Reactivity Control Systems 02/28/82N 05/24/82C

'II-3.B o i ng n d and 03/04/82R 06/28/82C rot tio L R unrements VI-2.D Mass and Energy Release for NONE 11/20/8tc

~

Possible Pipe Break Inside II-3.B-1 ability to Cope with 03/04/32R 06/28/82C Containment Design Basis Flood VI-3 Containment Pressure and NONE 11/20/81C II-3.C Safety Related Water Supply 03/04/82R 06/28/82C Heat Removal Capability (Ultimate Heat Sink)

VI-4 Containment Isolation HDHE 10/22/81C II-4.D Stability of Slopes 12/15/d Ut 06/14/82C System II-4.F Settlement of Foundation 11/04/d1R 06/03/82C VI-6 Containment Leak Testing NONE 06/04/81C and Buried Equipment (MP A-04)

III-3.A Effects of High Water 03/04/62R 05/05/82C VIII-1.A Potential Equipment NONE 10/16/81C Level on Structures Failures Associated with a Degraded Grid Voltage III-3.C Inservice Inspection of 11/12/81R 06/03/82C (MP B-23)

Water Control Structure (3-10)

l l

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l H11 (Cont.)

~

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S ?..t y

SER 2/

SAR 1/

SER g/

TOPIC NO. TITLE SCHiOJLE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE l

IX-1 Fuel Storage 03/04/52T 05/18/82C XV-15 Inadvertent Opening of BWR 05/07/81R 11/19/8tC Safety /Relie4 Valve l

IX-6 Fire Protection (MP B-41)

NONE 05/18/82C XV-16 Radiological Consequences 11/04/81R 04/01/82C of Failure of Small Lines XI-1 Appendix ICMP A-02)

NONE DELETED Carrying Primary Coolant j

Outside Containment XI-2 Radiological (Effluent and NONF DELETED Process Monitoring Systems)

XV-18 Radiological Consequences 05/07/81R 07/01/81C (NRR B-67)

Main Steam Line Failura XV-1 Decrease in Feedwater 05/07/81R 12/07/81C Outside Containment Temperature. Inct. ease in Fceduator Flou, Increase in XV-19 Loss of Coolant Accidents 05/07/81R 09/04/81C Steam Ficw, Inadvertent (SYS)

Resulting From Spectrum Opening of Steam Gene-ator, Breaks Within Reactor Relief or Safety Valve (DOSES)

Coolant Pressure Boundary 02/28/82N 06/03/82C XV-3 Loss of External Load.

05/07/81R 07/16/81C XV-20 Radiological Consequences 02/26/82N 04/19/82C Turbino Trip, Loss of of Fuel Danaging Accidents Condenser Vacuum, Closure (In & Out of Containment) o f fla i n Steam Isolation i

Valve (BWR), Steam Pressure l

Roqulatory Failure (closed) l/ SAR : Licensee Safety Analysis Report-Scheduled or Actual I

(actual (status 4b) when date is followed by R)

XV-4 Loss of Non-Emergency A-C 05/07/81R 0 7/16/81C Power to the Station 2/ SER : Staff Safety Evaluation Report -Scheduled or Actual Auxiliaries (Actual (status Aa, 5, 7) when date is followed by C)

XV-5 Loss of Normal Feedwater 05/07/81R 11/30/81C 1/ Desiginated number of days from receipt of licensee SAR Flow (Note: if Licensee SAR is received then date is from receipt of additional information requested)

XV-7 Reactor Coolant Pump Rotor 08/25/81R 12/07/81C Seizuec and Reactor Coolant NOTE:

h-No submittal received, therefore Safety Evaluation Pump Shaft Break preformed without.

XV-9 Startup or an Inactive Loop 05/07/81R 12/30/81C or Recirculation Loop at Incorrect Temperate e and Flow Controller Malfunction Causing an Increase in BWR Core Flow Rate XV-13 Spectrum of Rod Drop NONE 04/09/81C (sys)

Accident 05/07/81R 07/01/81C (doses)

XV-14 Inadvertent Operation of 05/07/81R 07/16/81C ECCS that Increases Reactor Coolant Inventory (3-11)

l LICENSEE TOPIC SUBMITTALS OYSTER CREEK TOPICS 4g TARGET 35 ACTUAL 30 25

/

20 COMPLETE f 10 5

~~

l I

i l

l I

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JUN JUL AUG SEP OCT NOV DEC JAN FEB MAR APR MAY JUN JUL/DEC TARGET 5

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1 PER MONTH ACTUAL 0

0 0

0 8

2 0

0 6

0 0

1 TARGET 16 21 24 24 24 24 25 CUMULATIVE ACTUAL 0

0 0

1 8

la 10 10 16 16 16 17 G-12)

MILLSTONE 1 EL MILLSTONE 1 21 (Cont.)

SAR 1/

SER 1/

SAR 1/

SER Z/

TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE III-1 Classification of NONE 03/19/82C II-3.A Hydrologic Description 06/25/81R 06/25/82C

($YS)

Structures, Components and l

Systems (Seismic and II-3.B Flooding Potential &

06/26/81R 06/25/82C Quality)

Protection Requirements III-2 Wind and Tornado Loadings N0HE 04/30/82C II-3.B.1 Capability of Operating 06/25/81R 06/25/82C Plant to Cope with Design III-5.A Effects of Pipe Break on 04/13/82R 06/08/82C Basis Flooding Conditions Structures, Systems and Components Inside II-3.C Safety Related Wa 04/28/81R 06/25/82C Containment Supply (UHS)

III-5.B Pipe Break Outside 12/04/81R 02/09/82C II-4.5 P

Ca able NDHE 12/30/81C Containment T

r et es k

Pla Vi y

III-7.B Design Codes, Design NDHE 05/20/82C Criteria, Load Combinations "1

I ity of Slopes 8 1/8 105/26/82C and Reactor Cavity Design 1

/ 8" L-06/03/82C n

II Settlement o d tion j 4/,

R V-11.B RHR Interlock Requirements NONr 2c C

and B lec Eq i n

~

(ELEC) d s

vi p tion of 08/31/81R 05/24/82C i

III-3ge*(

VII-3 Systems Required Safe sft/22/82C ter Cn tructures (ELEC)

Shutdown III-4.

T ine Missiles 08/31/81R 06/27/82C

~

O

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VII-6 Frequency ca NOHE

' i III-4.D Site Prximity Missiles 04/29/81R 10/29/81C IX-3 Station Spr a and Cooling 11 1s 4

/3( f8C (Including Aircraft)

Water Sys: ems LL IV-3 BWR Jet Pumps Operating NONE 02/22/82C IX-5 Ventilation Sy ems 19 1R' 04/28/82C Indications XIII-2 5

a5Ids du ri 1

'NONE 06/02/82C V-1 Compliance with Codes and N0HE DELETED t"(MF 10 Standards (10 CFR 50.55a) 1 (MP A-01,A-14)

T*i 1

~

VI-1 Organic Materials and Post 09/30/81R 01/28/82C ag JL,3 SAR 1/

SER 2/

Accident Chemistry TOPIC NO. TITLE SCHEDULE SCHEDULE II-1.A Exclusion Area Authority & 34/17/81R 0 7/ 31/81C Eli Control SAR 1/

SER g/

TOPIC HO. TITLE SCHEDULE SCHEDULE II-1.B Population Distribution 05/19/81R 10/29/81C II-2.C Atmospheric Transport and 05/19/81R 08/10/81C II-1.C Potential Hazards or 04/29/81R 10/29/81C Diffusion Characteristics Changes in Potential for Accident Analysis Hazards Due to Transporta-tion, Institutional, and III-4.A Tornado Missiles 08/31/81R 05/05/82C Military Facilities (3-13)

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SER 2/

TOPIC NO. TITLE SCHEDstc SCHEDULE XV-16 Radiological Consequences 06/3]/11R 09/21/81C of Failure of Small Lines Carrying Primary Coolant Outside Containment XV-18 Radiological Consequences 06/33/31R 09/21/81C of Main Steam Line Failure Outside Containment (BWR)

XV-19 Loss of Coolant Accidents 06/30/81R 08/26/81C (SYS)

Resulting from Spectrum of (DOSES)

Postulated Piping Breaks 06/30/81R 0 9/21/81C Within the Reactor Coolant Pressure Boundary XV-20 Radiological Consequences 06/30/81R 09/21/81C of Fuel Damaging Accidents (Inside and Cutside Containment) 1/ SAR : Licensee Safety Analysis Report-Scheduled or Actual (actual (status 4b) when date is followed by R)

Z/ SER : Staff Safety Evaluation Report -Sche-Juled or Actual (Actual (status 4a, S.

7) when dale is followed by C)

J/ Desiginated number of days from receipt of licensee SAR (Note:

if Licensee SAR is received then date is from receipt of additional information requested)

(3-15)

LICENSEE TOPIC SUBMITTALS MILLSTONE 1 TOPICS zg TARGET 35 ACTUAL 30 25 20 ALL SUBMITTALS RECEIVED 15

~~

'/

ig 5

~~

l i

l I

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5 0

2 2

1 0

0 0

2 TARGET 10 10 12 CUMULATIVE ACTUAL 0

5 5

7 9

10 10 10 10 12 G-16) i

fijLri ()LriCil:lRtli I

p1 SAN UHorRE AR 1/

SER 2/

l SAR 1/

SER 2/

TOPIC NO. TITLE SCcEDULE SCHEDULE l

TOPIC NO. TITLE S CilEDUL E SCHEDULE IX-3 Station Service and Cooling it/02/8tR 09/30/82C 111-1 Classification of NONE 06/23/82C Water Systems Structures. Components and Systems (59ismic and IX-S Ventilation Systems 12/16/81R 07/02/82C Quality) l l

III-2 Wind and Tornado Loadings 05/04/82R 09/03/82C p_(

l SAR 1/

SER 2/

l III-5.A Effects of Pipe Break on 12/01/82 12/30/82 TOPIC NO. TITLE SCHEDULE SCHEDULE

)

Structures. Systems and i

Components Inside Il-1.C Potential Hazards or 11/12/8IR 08/06/82 Containment Changes in Potential Nazards Due to III-5.B Pipe Break Outside 12/01/82 12/10/82 Transportation.

Containment Institutional Industrial, and Military Facilities III-6 Seismic Design NONE 08/30/82 considerations II-3.A Nydrologic Description NDHE 11/30/82 III-7.B Design Codes. Design NONE 09/21/82C II-3.B Flooding Potential 8 NONE 11/30/82 Criteria. Load Protection Requirements Combinations, and Reactor Cavity Design Criteria II-3.5 1 Capability of Operating NONE 11/30/82 Fiant to Cope with Design V-11.8 RilR Interlock Requirements NONE 02/04/82C Basis Flooding Conditions (ELEC)

II-3.C Safety Related Water NONE 11/30/82 VI-7.A.3 ECCS Actuation System NONE 11/18/81C Supply (UHS)

VI-7.B ESF Switchover from NONE 09/04/8tC II-4.D Stability of Slopes 11/02/81R 10/28/82C (ELEC)

Injection to Recirculation Mode (Automatic ECCS II-4.F Settlement of Foundations 11/02/81R 10/31/82 Realignment) and Buried Equipment VI-10.A Testing of Reactor Trip NONE 08/28/81C III-3.A Effects of High Water Level 05/30/82 09/30/82 System and Engineered on Structures Safety Features Including Response Timo Testing III-4.8 Turbine Missiles (MP B-46)

NONE 06/24/82C VII-1.A Isolation of Reactor NDHE 09/09/8tC III-4.D Site Proximity Missiles 10/23/81R 09/30/82 Protection Systems.

(Including Aircraft)

Including Qualifications of Isolation Devices III-7.D Containment Structural 06/09/81R 04/14/82C Integrity Tests VII-2 Engineered Safety Features NONE 11/18/8tC (ESF) System Control Logic V-1 Compliance with Codes and NONE DELETED and Design Standards (10 CFR 50.55a)

(MP A-01)

VII-3 Systems Required for Safe NONE 11/18/81C (ELEC)

Shutdown VI-1 Organic Materials and Post Of/28/82C 06/18/82C Accident Chemistry VII-6 Frequency Decay NONE 08/28/81C (3-17)

1 i

SAN ON0FRE ASI R u (Cont.)

SAR 1/

SER 2/

SAR 1/

SER 2/

TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCttEDUL E SCHEDULE 1

Tornado 'easiles 05/04/82R 09/30/82C XV-2 Scectrum of Steam System 01/Ol/81R 10/21/8tC H

III-4.A Piping failures Inside and III-4.C Internally Generated 04/29/82R 09/30/82C Outside of Containment (ruR)

Missiles XV-3 Loss of External Load.

07/01/81R C8/26/81C III-8.A Loose Parts Monitoring and H0HE 12/07/8tC Turbine Trip, Loss of Con-Core Barrel Vibration d'nsor Vaccum, Closure of i

Monitoring (NRR B-60,C-12)

Main Steim Isolation Valve (BUR), and Steam Pressure IV-2 Reactivity Control Systems 04/30/82R 08/25/82C Roquiator Failure (Closed)

Including Functional Design and Protection Against XV-4 Loss of Non-Erergency A-C 08/18/81R 12/12/81C Single failures Powcc to the Station Auxiliaries V-7 Reactor Coolant Pump HONE tt/05/81C Overspeed(NRR B-68)

XV-S Loss of Normal Feedwater 07/08/8IR Ot/25/82C Flow VI-2.D Mass and Eneroy Release for NONE 12/04/81C Possible Pipe Break Inside XV-6 Feedwater System Pipe 07/01/81R 02/19/82C Containment Breaks Inside and Outside Containment (PUR)

VI-3 Containment Pressure and NONE 12/04/81C Heat Removal Capability XV-7 Reactor Coolant Pump Rotor 07/08/8tR 09/29/82C Scirure and Reactor Coolant VI-4 Containment Isolation H0HE Ot/29/82C Pump Shaft Break (SYS)

System XV-8 Control Rod Misoperation 07/01/81R 11/19/8tC VI-6 Containment Leak Testing NDHE 08/03/82C (System Malfunction or (MP A-04)

Operator Error)

VIII-1.A Potential Equipment Failure NONE 05/01/82 XV-10 Chemical and Volume Control 07/01/81R 03/28/82C Associated with a Degraded System Malfunction that Grid Voltage (MP B-23)

Results in a Decreasa the Boron Concentration in IX-1 Fuel Storage 04/29/82R 09/29/82C the Reactor Coolant (FUR)

IX-6 Fire Protection (MP B-41)

H0HE 10/31/82 XV-12 Spectrum of Rod Ejection 07/01/81R 11/19/81C Accidents (PUR)

XI-1 Appendix I HONE DELETED XV-14 Inadvertent Operation of 07/01/8tR 02/11/82C XI-2 Radiological (Effluent and NONE DELETED ECCS and Chemical and Process) Monitoring Systems Volume Control Systen (NRR B-67)

Malfunction that Increases Reactor Coolant Inventory XV-1 Decrease in Feedwater 07/01/81R 10/27/81C Temperature. Increase in Feedwater Flow. Increase XV-15 Inadvertent Opening of a 07/01/81R 03/31/82C in Steam Flow and FUR Pressurizer Safety-Inadvertent Openino of a Relief Valve of a BMR Steam Generator Relief Safety / Relief Valve or Safety Valve (3-18)

SAN ONOFRE

~E5I (Crnt.)

l SAR 1/

SER ?/

I"rIC N7. TITLE SCilE D Ji E SCliE DUL E XV-t6 Radiological Consa v'coces 08/C4/61R 11/18/8tC of Failuro of 5 ull Lincs Carryinq r r i ci.ir y Coolant Cutsico Cont.winment XV-17 Syrtam Generator Tube NOME 12/07/81C (SYS)

Failorn (PWR)

XV-19 Loss-of-Coolant Accidents 07/01/81R 05/26/81C Resulting from Spectrum of Postulated Pipino Dreaks Within the Reictor Coolant Frencuro Boundar y 1/ SAR: Licansco Sainty Analysis Rep 7rt-Scheduled or Actual (Actual (status 4b) uhen dato is follourd by R) 2/ SER : Staff Safety Evaluation Rcrort -Schaduled or Actual (Actual (.tatus Ga, 5,

7) oben date is follourd by C)

J/ Dosiqinated nuetcr of days trom receipt of licensen SAR (Note:

if Licenteo SAR is rcccived then date is from rcccipt of acfdi t i onal information requested)

(3-19) i

LICENSEE TOPIC SUBMITTALS SAN ONOFRE zg ___ TOPICS TARGET 35 ACTUAL 30 25 20 15 10 5

LA I

I I

I 0

JUN JUL AUG SEP OCT NOV DEC JAN FEB MAR APR MAY JUN JUL/DEC TARGET 1

0 3

3 0

2 PER MONTH ACTUAL 0

2 0

1 4

1 1

0 0

2 3

0 0

TARGET 8

9 9

12 15 15 17 CUMULATIVE ACTUAL 0

2 2

3 7

8 9

9 9

11 14 14 14 G-20)

BIG ROCK POINT RL BIG ROCK P0lNT pi (Cont.)

l SAR 1/

SFR 7/

SAR _1/

SER 7/

TOPIC HO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHFDULE 111-1 Classification of Struct-NONE 0 4 /16 / 82 C IX-3 Station Service and 12/10/81R 06/30/82C (SYS) ures, Components and Sys-Cooling Water Systems tems (Seismic and Quality)

IX-5 Ventilation Systems 06/tt/82R ' 08/13/82C III-2 Wind and Tornado Loading 08/03/82R 09/21/82C III-5.A EFFECTS OF PIPE BREAK ON 09/30/82R 10/27/82C RR Structures, Systems and SAR 1/

SER 7/

Components Inside TOPIC NO. TITLE SCHEDULE SCHEDULE Containment 11-3.A Hydrologic Description N o t4E 09/08/S2C III-5.8 Pipe Break Outside 05/21/82R 08/30/82C Containment II-3.B Flooding Potential and NONE 09/08/82C Protection Requirements III-6 Seismic Design NONE 09/30/82C Considerations II-3.B.1 Capability of Operating NONE 09/08/82C Plans to Cope with Designs III-7.B Design Codes, Design NONE 09/13/82C Basis Flooding Conditions Criterion, Load Combinations and Reactor II-3.C Safety-Relatcd Water Sucoly NONE 09/08/82C Cavity Design Criterion (Ultimate Heat Sink UHS))

VI-7.A.3 ECCS Actuation System NONE Ot/29/82C II-4.B Proximity of Capable NONE 09/13/82C Tectonic Structures in VI-7.C ECCS Single Failure Cri-NONE 08/05/81C Plant Vicinity terion and Requirements for Locking Out Power to Valves II-4.D Stability of Slopes 10/05/81R 06/25/82C Including Independence of Interlocks on ECCS Valve II-4.F Settlement of Foundations 10/19/81R 07/07/82C and Buried Equipment VI-7.C.2 Failure Mode Analysis ECCS NDHE 08/05/81C III-3.A Effects of High Water 03/15/82 09/30/82 VI-10.A Testing of Reactor Trip 03/29/82R 06/22/82C Level on Structures System and Engineered Safety Features. Including III-3 C Inservice Inspection of 12/21/81R 08/04/82C Response Time Testing Water Control Structures VII-1.A Isolation of Reactor NONE 02/16/82C III-4.4 Turbine Missiles 06/05/822 09/30/82 Protection System From Hon-Safety Systems, Including III '*.ts Site Proximity Missiles 12/14/812 07/12/82C Qualification of Isolation (Including Aircraft)

Devices III-7.D Containment Structural 12/29/81R 03/03/82C VII-2 Engineered Safety Features NONE 12/31/81C Integrity Tests

'(ESF) System Control Lonic and Design V-1 Compliance with Codes and NONE DELETED Standards 310 CFR 50.55a)

VII-6 Frequency Decay NONE 39/21/8tC (T1P A-01,A-14)

V-4 Piping and Safe End Inteq.

HONE 08/31/82 VI-t Organic Materials and Post 03/16/82R 08/04/82C Accident Chomsitry 1

(3-21)

BIG ROCK P0 INT D51 p_S1 (Cont.)

SAR 1/

SER 7/

SAR 1/

SER 7/

TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULF SCHEDULE Il-2.C Atmospheric Transport and 105/06/82R 06/04/82E XV-1 Decrease in Feedwater 07/15/81R 02/18/82C Diffussen Charactoristics Tc perature Increase in for Accident Analysis Ferdwater Flou, Increase in Steam Flow and III-4.A Tornado Missiles 0 3/16 /82 R 09/28/82C Inadvertent Opcning of a Steam Genrrator Relief III-4.C Internally Gnnorated 06/03/82F 09/24/82C or Safety Valve fli ss i l n s XV-3 Loss of External Load.

0 7/15/81R 10/15/81C III-5.A Loosa Parts Monitoring and NOME 02/09/82C Turbine Trip, Loss of Core Vibration Monitoring Condensor Vacuum, Closure

( f tCR B-60.C-12) of Main Steam Isolation Valve (BUR), and Steam IV-2 Reactivity Control System NONE 12/07/81C Pressure Regulator Failure Including Functional Design (Closed) and Protection Acainst Single railures XV-4 Loss of Non-Emergency A-C 07/15/81R 10/16/S8C Power to Use Station VI-2.D Mass and Energy Releasa for NDNE 05/24/82C Auxiliaries Postulated Pipe Breaks Inside Containment XV-5 Loss of Normal Feedwater 07/15/81R 01/26/32C Flow VI-3 Containment Pressures and NONE 05/24/82C Hnat Removal Capability XV-7 Reactor Coolant Pumps 07/15/81R 02/25/82C Rotor Seizure and Reactor VI-4 Containment Isolation Sys.

NONE 03/24/82C Coolant Pump Shaft Break VI-6 Containment Leak Testing NONE 04/30/82 XV-8 Control Rod Misereration 09/23/81R 12/21/81C (MP A-04)

(System Malfunction or Operator Error)

VI-7.B ESF Switchover from NONE 04/22/82C Inicction to Recirculation XV-9 Startup of an Inactive Loop 37/15/61R 03/24/82C Moda (Automatic EECS or Recirculation Loop at an Rnalignment)

Incorrect Trepcrature and Flow Controllee Malfunction VIII-1.A Potential Equipment NONE 07/08/82C Causina an Increase in BWR failurcs Associated with Co.e Flow Rate Dcqradod Grid XV-11 Inadvertent Loadina and 09/28/81R 11/20/81C IX-1 Fuel Storaqn NONE 05/13/82C Operation of a Fuel Assembly in an Improper IX-6 Fire Protection (MP B-41)

NONE 09/30/82 Position (EWR)

XI-1 Appendix I(MP A-02)

NONE DELETED XV-13 Spectrum of Rod Drop SYS 07/01/81R 11/20/81C Accidents DOSES 07/01/81R 10/23/81C XI-2 Radiological (Effluent NONE DELETED and Process) Monitoring Systems (NRR B-67)

XV-14 Inadvertant Operation of 06/26/81R 08/18/81C ECCS and Chemical and Volume Control System Malfunction that Increases Reactor Coolant Inventory (3-22)

r BIG ROCK POINT

.D31 (Cont.)

SAR 1/

SER 2/

TOPIC HO. TITLE SCHEDULE S Cite DU L E XV-15 Inadvertent Opening of a 06/26/81R 0 8 /18 /81 C l

PWR Pressurizer Safety Relief Valve or a BWR Safety / Relief Valve XV-16 Radiological Conscouences 07/01/81R 12/14/81C of Failure of Small Lines Carrying Primary Coolant Outsida Containment XV-18 Radiological Consequences 0 7/ 01/81R 04/02/82C of Main Steam Line railure Outside Containment XV-19 Less of Coolant Accidents 06/29/81R 08/18/81C (SYS)

Resulting From Spectrum of Postulated Piping Breaks (DOSES) within the Reactor Coolant 06/02/82R.

09/28/82C Pressure Boundary XV-20 Radiological Consequences 07/03/81R 10/23/81C of Fuel Damaging Accidents (Inside and Outside Containment) l/ SAR Licensee Safety Analysis Report-Scheduled or Actual (Actual (Status 4b) wivn date is followed by R)

R/ SER : Staff Safety Evaluation Report -Scheduled or Actual (Actual (status 4a, 5,

7) when date is folloucd by C) 1/ Desiqinated number of days from receipt of licensee SAR (Note:

i f Licensee SAR is received then dite is fron rneciot of additional information requested)

LICENSEE TOPIC SUBMITTALS BIG ROCK POINT TOPICS 40 TARGET 35 ACTUAL 30 25 20 15 10, 5

~~

l l

I i

i l

l I

I i

l g

JUN JUL AUG SEP OCT NOV DEC JAN FEB MAR APR MAY JUN JUL/DEC TARGET 1

1 2

3 2

PER MONTH ACTUAL 0

0 2

2 0

3 1

0 2

1 2

4 2

TARGET 11 12 13 15 18 20 CUMULATIVE ACTUAL 0

2 2

3 7

8 9

9 9

11 13 17 19 G-24)

HADDAM NECK D( HADDAM NECK pl (Cont.)

l SAR 1/

SER 2/

SAR 1/

SER 2/

TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC HO. TITLE SCHEDULE SCHEDULE III-1 Classification of NONE 07/22/82C IX-5 Ventilation Systems 12/14/81R 05/26/82C (SYS)

Structures. Components and Systems (Seismic and XIII-2 Safeguards / Industrial NONE 06/10/82C Quality)

Security (MP A-10)

III-2 Wind and Tornado Loadings 12/14/81R 08/11/82C DE III-5 A.

Effects of Pipe Break 09/17/82R 09/28/82C SAR 1/

SER 2/

on Structures. Systems TOPIC NO. TITLE SCHEDULE SCHEDULE and Componets Insido Containment Il-1.A Exclusion Area Authority 04/27/81R 03/29/82C B. Pipe Break Outside 10/02/81R 04/08/82C II-1.5 Population Distribution 08/31/81R 03/29/82C l

Containment II-1.C Potential Hazards or 06/30/81R 03/29/82C III-6 Seismic Design NONE 09/30/82C Changes in Potential Considerations Hazards Due to Transportation.

III-7.B Design Codes. Design i NONE 08/20/82C Institutional Industrial.

Criteria. Load and Military Facilities Combinations, and Reactor Cavity Dosign Criteria II-3.A Hydrologic Description 12/14/81R 08/30/82C VI-7.A.3 ECCS Actuation System NONE 01/29/82C II-3.B Flooding Potential and 12/14/81R 08/30/82C Protection Requirements VI-7.C.3 The Effect on PWR Loop NONE 12/14/81C Isolation Valve Closurn II-3.B.1 Capability of Operating 12/14/81R 08/30/82C During a LOCA on ECCS Plant to Cope with Design Performance Basis Flooding Conditions VI-10.A Testing of Reactor Trip NONE 03/05/82C II-3.C Safety-Pelated Water Supply 12/14/81R 08/30/82C System and Engineered (Ultimate Heat Sink (UHS))

Safety Features Including Response Time Testing II-4.B Proximity of Capable NONE 05/18/82C Tectonic Structures in VII-1.A Isolation of Reactor NONE 02/16/82C Plant Vicinity Protection System from Hon-Safety Systems, Including II-4.D Stability of Slopes 08/31/81R 06/21/82C Qualifications of Isolation Devices II-4.F Settlement of Foundations 12/18/81R 05/18/82C VII-2 Engineered Safety Features NONE 02/16/82C and Buried Equipment (ESF) System Control Logic and Design III-3.A Effects of Hiq5 Water 08/31/81R 08/26/82C Level on Structures VII-6 Frequency Decay NDHE 08/28/81C III-3.B Structural and Other NONE 08/30/82C VIII-4 Electrical Penetrations NONE 12/23/81C Consequences (e.g. Flooding of Reactor Containment of Safety-Related Equipment in Basements) of Failure of IX-3 Station Service and Cooling 12/14/81R 04/30/82C Underdrain Systems Water Systems (5-25)

HADDAM NECK QX (cont.)

DSL (Cont.)

SAR 1/

SER 2/

SAR.t./

SER 2/

TOPIC NO. TITLE SCIIE DUL E SCHEDULE TOPIC NO. TITLE SCHEDULE SCitLDUL E III-3.C Inservice Inspections of 02/12/82R 06/03/82C VI-6 Containment Leak icsting i:UN E 05e07/82C Water Control Structures (MP A-04)

III-4.8 Turbine Missiles (MP B-46)

NONE 07/13/82C VI.7.B ESF Switchover from NONE 04/01/80C (SYS)

Injection to Recirculation III-4.D Site Proximity Missiles 06/25/81R 03/29/82C Mode (Automatic ECCS (Including Aircraft)

Rnalignment)

III-7.D Containment Structural 04/27/81R 10/08/81C VIII-1.A Potential Equicment NONE 06/29/82C Intaqrity Tests failures Associated with a Degraded Grid Voltage V-1 Compliance with Codes and NONE DELETED (MP B-23)

Standards (10 CFR 50.55a)

( MP A- 01. A-14 )

IX-1 Fuel Storage 08/31/8tR 12/30/81C VI-1 Organic Materials and Post 02/09/82R 06/04/82C IX-4 Boron Addition Systems 10/ 02/ 81R 03/31/82C Accident Chemistry IX-6 Fire Protection (MP B-41)

NONE 05/19/82C Q1[

XI-t Appendix ICMP A-02)

NONE DELETED SAR 1/

SER 7/

TOPIC tiO. TITLE SCilEDULE SCilEDUL E XI-2 Radiological (Effluent NONE DELETED and Process) Monitoring III-4.A Tornado Missiles 08/5t/81R._

12/28/81C Systens(MRR B-67)

III-4.C Internaly Generating 02/12/82R 04/22/82C XV-1 Decrease in feedwater 09/30/81R 06/01/82C l

Missiles Temperatures. Increase in Fecdwater Flow. Increase in i

III-8.A L?ose Parts Monitoring and NONE 02/09/82C Steam Flow and Inadvertent l

Core Barrel Vibration Opening of a Steam Genera-l Monitorinq(NRR B-60.C-12) ter Relief or Safety Valve l

IV-2 Reactivity Control Systems 06/30/81R 12/23/81C XV-2 Spectrum of Steam System 09/30/81R OS/04/82C Including Functional Design Piping failures Inside and and Protection Against Outside of Containment (SYS)

Single Failures (PWR)

(DOSES) 09/30/81R 06/28/82C V-7 Reactor Coolant Pump NONE 11/05/81C Overspeed(NRR B-68)

XV-3 Loss of External Load.

09/30/81R 03/09/82C Turbine Trip. Loss of VI-2.D Mass and Energy Relesse for NDHE 0 6/21/82C Condensor vacuum. Closure Possible Pipe Break Inside of Main Steam Isolation Containment Valve (BIIR), and Steam Pressure Requlator failure VI-3 Containment Pressure and NONE 06/21/82C (Closed)

Heat Removal Capability XV-4 Loss of Non-Emergency A-C 09/30/81R 12/17/81C VI-4 Containment Isolation NONE 04/06/82C Power to the Station System Auxiliaries XV-5 Loss of Normal Feedwater 09/30/81R 04/06/82C Flow (3-26)

HADDAM NECK D S I. (Cont.)

ES1 (Cont.)

SAR.1/

SER 7/

SAR 1/

SER R/

TOPIC NO. TITLE SCilEDUL E SCilEDU L E TOPIC HO. TITLE SCHEDULE S CllEDUL E XV-6 fonduater System Pipe 09/30/8tR O's/28/82C XV-19 Loss of-Coolant Accidents.

09/30/88R 11/10/81C l

Breaks Inside and Outside Resulting frem Spectrum of Containnrnt (PWR)

Postulated Piping Dreaks Within the Reactor Coolant XV-7 Raactor Coolant Pump Rotor 09/30/81R 05/f2/82C Pressure Boundary (SYS)

Seizure and Reactor Coolant (DOSES) 09/30/81R 06/30/82C Pump Shaft Break XV-8 Control Rod Misoperation 09/30/81R 03/18/82C 1/ SAR : Licensee Safety Analysis Report-Scheduled or Actual (Sy>tc,fialfunction or (Actual (Status 4b) when dato is folloued by R)

Operator Error) 2/ SER Staff Safety Evaluation Report -Scheduled or Actual XV

')

Startup or an Inactive 09/30/81R 03/31/82C (Actual (status 4a. S. 7) uhen date is followed by C)

Locp nr Recirculation Loop at an Incorrect 1/ Desiginated number of days from receipt of licensee SAR Temperature. and Flow (Note:

if Licensee SAR is received then date is from Controller Malfunction roccipt of additional information requested)

Causino an Increano in BWR Corn flow Rato XV-10 Chemical and Volumn Control 09/30/81R 03/29/82C System flal function that Rosults in a Decrease in in Boron Concentration in the Reactor Coolant (PWR)

XV-12 Spectrum of Rod Eicction 09/30/81R 03/15/82C Accidonts (PLM)

(SYS)

(DOSES) 09/30/81R 05/06/82C XV-li Inadvertnnt Operation of 09/30/81R 04/01/82C ECCS and Che,ical and Volume Control System fialfunction that Increases Reactor Coolant Inventory XV-15 Inadvertent Opening of a 09/30/81R 04/06/82C PWR Pressurizer Safety-Rnlief Valve or a BilR Safety /Rolief Valvn XV-16 Radiological Conscournces NONE 09/28/8tC of Failure of Small Lines Carryino Primary Coolant Outsid1 Containment XV-17 Stram Generator (SYS) 04/07/82R 06/21/82C Tube Failure (PWR) (DOSES) 04/07/82R 06/28/8?C I

l (3-27)

LICENSEE TOPIC SUBMITTALS HADDAM NECK TOPICS 40 TARGET 35

's f

ACTUAL 30 25 20 ALL SUBMITTALS RECEIVED 15 10 5

~~

V l

l l

g JUN JUL AUG SEP OCT NOV DEC JAN FEB MAR APR MAY JUN JUL/DEC TARGET 1

1 PER MONTH ACTUAL 0

6 0

16 0

8 0

2 0

1 0

0 1

TARGET 32 33 34 CUMULATIVE ACTUAL 0

6 6

22 22 30 30 32 32 33 33 33 34 G-28)

YANKEE El (Cont.)

RL YANKEE NUCLEAR POWER STATION SAR 1/

SER F/

SAR 1/

SER 7/

TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE Ill-1 Classification of Struct-NONE 06/18/82C IX-5 Ventilation Systems 11/18/81R 04/28/82C ures. Components and Sys-tems (Seismit and Quality)

+

El III-2 Wind and Tornado Loadings 0 3/18/82R 08/31/82C SAR 1/

SER 2/

TOPIC NO. TITLE SCHEDULE SCHEDULE III-5.A Effects of Pipo hreak on 0 3/18 /82R 07/26/82C

_33/18/82R 06/15/82C Structures. Systems and II-1.A Exclusion Area Authorit/

Components Insida and Control Containment II-1.B Population Distribution 05/?l/81R 06/15/82C III-5.8 Pipe Break Outside 01/21/82R, 05/06/82C Containment II-1.C Potential Hazards or 0%/09/81R 06/15/82C Changos in Potential III-6 Seismic Design ~ '

NONE 09/30/d2C Hazards Due to Consideratione Transportation.

Institutional Industrial.

III-7.8 Design Codes. Design NONE 08/30/82 and Military Facilities Criteria. Load Combinations, and Reactor II-3.C Safety-related IJater NONE 08/27/82C Cavity Design Criteria Supply (Ultimate Heat Sink (UHS)

V-11.8 RHR Interlock Requirements NONE 01/22/82C (ELEC)

II-4.B Proximity of Capable NDHE 06/16/82C Tectonic Structures in VI-7.A.3 ECCS Actuation System 06/30/81R 01/29/82C Plant Vicinity (B-46)

VI-10.A Testing of Reagtor Trip 06/30/81R

.91/22/82C II-4.D Stability of Slopes 02/26/82R 08/26/82C System and Engineered Safety Features Including II-C.E Dam Integri+y NONE 08/31/82C

~

Safety Features: Including l

Response Time Testing

, J I-4.F Set t lemen'ts o f',founda t i on s 08/31/81R 08/31/82C and Buried Equipment VII-1.A Isoaltion of Reactor NONE^

10/05/81C Effects of High Water 03/18/82R 08/27/82C III-3.A Protection System from i

Hon-Safety Systems.

Level on Structures Including Qualifications of Isolation Devices III-).C Inservice Inspection of 01/04/82R 08/26/82C Water Control Structures

+

VII-2 Engineered Safety Features NONE 10/19/81C (ESF) System Control Logic III-4.5 Turbine Missiles (MP B-46)

NDHE 02/08/82C and Design VII-3 System Required for Safe NONE Of/22/82C

~'

Site proximity missiles 06/30/81R 06r:5/82C III-4.D (Including Aircraft)

(ELFC)

Shutdown III-7.D Containment Structural 11/18/81R 03/01/82C VII-6 Frequency Decay NONE 08/28/81C Integrity Tests V-1 Compliance with Codes NONE DELETED IX-3 Station Service and Cooling 09/17/81R 05/30/82C and Standards (10 CFR 50.55a)(MP A-01.A-14) yater Systems s

(3-29)

YANKEE PR (Cont.)

R11 (Cont.)

SAR 1/

SER 2/

SAR 1/

SER Z/

TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCNEDULE vi-1 Organic Materials and 06/14/82R 08/31/82C IX-1 Fuel Storage II/18/81R 08/31/82C Post Accident chemistry IX-4 Baron Addition System 08/31/81R 05/14/82C p,Si IX-6 Fire Protection (MP B-41)

NONE 08/31/82 SAR J/

SER 7/

TOPlc NO. TITLE SCHEDULE SCHEDULE XI-t Appendix I(MP A-02)

NDNE DELETED ll-2.C Atmospheric Iransport and 06/30/81R 09/04/81C XI-2 Radiological (Effluent NOME DELETED Diffusion Characteristics and Process) Monitoring for Accident Analysis Systems (NRR B-67)

III+4.A Tornado Missiles 03/18/82R 06/30/82C XV-t Decrease in Feedwater 02/01/82R 06/22/82C Temperature. Increase in III-4.C Internally Generated 03/18/82R 09/10/82C Feodwater Flow, Increase Missiles in Steam Flow and Inadvertent Opening of a III-8.A Loose Parts Monitoring NONE 12/07/8tC Steam Generator Relief and Core Barr el Vibration or Safety Valve Monitorinq(NRR B-60,C-12)

'i XV-2 Spectrum of Steam System 06/30/81R 06/21/82C IV-2 Reactivity Control Systems 09/17/81R 12/23/81C (SYS)

Piping Failures Inside including Functional Design (DOSES) and Outside of Containment No date 09/01/82C and Protection Against (PWR)

Single Failures XV-3 Loss of External Load, O'6 / 30/81R 01/09/82C V-7 Reactor Coolant Pump NONE DELETED Turbine Trip, Loss of Overspeed(NRR B-63)

Condenser Vacuum, Closure of Main Steam Isolation VI-2.D Mass and Energy Release NONE 05/10/82C Valve (BWR), and Steam for Possible Pipe Break Pressurb Regulator Failure Inside Containment (Closed)

VI-3 Containment Pressure and NONE 05/10/82C XV-4 Loss of Non-Emergency A-C 01/04/82R 06/30/82C Neat Removal Capability Power to the Station Auxiliaries VI-4 Containment Isolation NONE 08/30/82C (SYS)

System XV-5 Loss of Normal Feedwater 06/30/81R 01/29/82C Flow VI-6 Containment Leak Testing NONE 09/02/82C (MP A-04)

XV-6 Feedwater System Pipe 02/01/82R 06/30/82C Breaks Inside and Outside VI-7.8 ESF Switchover from NONE 06/29/82C Containment (PWR)

(SYS)

Injection to Recirculation Mode (Automatic ECCS XV-7 Reactor Coolant Pump Rotor 06/30/81R 05/20/82C Realignment)

Seizure and Reactor Coolant Pump Shaft Break VIII-l.A Potential Equipment NONE 08/31/82C Failures Associated with XV-8 Control Rod Misoperation Of/04/82R 02/26/82C a Dcqraded Grid Voltage (System Malfunction or (MP B-23)

Operator Error)

(3-30)

YANKEE Ell (Cont.)

SAR 1/

SER 2/

TOPIC NO. TITLE SCHEDULE SCHEDULE XV-9 Startup or an Inactive 06/30/81R 0 6 /13/ 82C Loop or Recirculation loop at an Incorrect Temperature, and Flow Controller Malfunction Causing an Increase in BWR Core Flow Rate XV-10 Chemical and Volume Control 06/30/81R 03/02/82C System Malfunction that Results in a Decrease in the Boron Concentration in the Reactor' Coolant !FMR)

XV-12 Spectrum of Rod Election 06/30/81R 03/29/82C (SYS)

Accidents (PWR)

(DOSES) 08/30/81R 12/18/81C XV-14 Inadvertent Operation of 06/30/81R 06/30/82C ECCS and Chemical and Volume Control System Malfuncticn that Increases i

Reactor Coolant Inventory XV-15 Inadvertent Opening of a 06/30/81R 04/28/82C PWR Pressurizer Safety-Related Valve or a BNR Savety/ Relief Valve XV-16 Radiological Consequences 02/01/82R 07/28/82C of Failure of Small Lines Carrying Primary Coolant Outside Containment XV-17 Stean Generator Tube HONE 07/06/82C (SYS)

Failure (rWR)

(DOSES) 02/01/82R 03/19/82C XV-19 Loss of-Coolant Accidents 11/18/81R 06/24/82C (SYS)

Resulting from Spectrum of (DOSES)

Postulated Piping Breaks 01/ 0 4/82R 08/23/82C Within the Reactor Conlant Pressure Boundary l/ SAR - Licensee Safety Analysis Report-Scheduled or Actual (Actual (Status Ab) when date is followed by R) 2/ SER = Staff Safety Evaluation Report -Scheduled or Actual (Actual (status 4a, 5, 7 ) when date is followed by C) 1/ Desiginated number of days from receipt of lice'see SAR n

(Notes if Licensee SAR is received then date i s f rom receipt of additional information requested)

(3-31) 1

LICENSEE TOPIC SUBMITTALS YANKEE TOPICS 4g TARGET 35 ACTUAL 30 4

25

/

20 ALLSUBMITTALfRECE ED 15 10 5

~~

l l

l l-l l

l l

l g

JUN JUL AUG SEP OCT NOV DEC JAN FEB MAR APR MAY JUN JUL/DEC TARGET

-5 PER MONTH ACTUAL 0

2 2

0 4

0 5

5 6

0 0

1 TARGET 20 25 i

CUMULATIVE ACTUAL 0

2 4

4 8

8 13 18 24 24 24 25 G-32)

LACROSSE RL LACROSSE DE SAR 1/

SER 7/

SAR 1/

SER 2/

TOPIC HD. TITLE SCHEDULE SCHEDULE TOPIC HD. TITLE SCHEDULE SCHEDULE 111-1 Classification of NONE 06/07/82C ll-1.A EXCLUSIDH AREA AUIHORITYy 06/22/81R 10/29/82C (SYS)

Structures. Components and and Control Systems (Seismic and Quality)

II-1.B Population Distribution 06/16/81R 07/29/82C III-2 Wind and Tornado Loadings 08/06/81R 08/16/82C II-1.C Potential Hazards or 07/15/81R G8/04/82C Changes in Potential III-5.A Effects of Pipe Break on 02/24/82R 08/06/82C Harards Due to Structures, Systems and Transportation, Components Inside Institutional Industrial, Containment and Military Facilities III-5.B Pipe Break Outside 06/29/81R 07/26/82C II-3.A Hydrolic Description 06/16/81R 09/30/82C Containment II-3.B Flooding Potential and 05/12/82R 09/30/82C III-6 Seismic Design NONE 09/50/82C Protection Requirements Considerations II-3.B.1 Capability of Operating 05/12/82R 09/30/82C r

III-7.B Design Codes. Design NONE 07/23/82C Plant to Cope with Design Criteria, Load Basis Flooding Conditions Combinations, and Reactor Cavity Design Criteria II-3.C Safety-related Water Supply 06/26/81R 09/30/82C 1

(Ultimate Heat Sink (UHS))

V-11.B RHR Interlock Requirements NONE 03/04/82C (ELEC)

II-4.B Proximity of Capable NONE 07/13/82C Tectonic Structures in VI-7.A.3 ECCS Actuation System HONE 01/29/82C Plant Vicinity VI-10.A Testing of Reactor Trip 06/25/81R 02/16/82C II-4.D Stability of Slopes H0HE 08/16/82C System and Engineered Safety Features Including II-4.E Dam Integrity H0HE 07/27/82C Response Timn Testing II-4.F Settlement of Foundations 03/09/82R 07/20/82C VII-1.A Isolation of Reactor NONE 03/09/82C and Buried Equipment Protection System from Non-Safety Systems, III-3.A Ef fects of High Water Level 05/12/22R 09/30/82 Including Qualifications of on Structures Isolation Devices III-3.C Inservice Inspection of 01/29/82R 09/10/82C VII-2 Engineered Safety Features NOHE 03/11/82C Water Control Structures (ESF) System Control Logic and Design III-4.B Turbine Missiles 03/05/82R 10/19/82C VII-3 Systems Required for Safe HOME 03/09/82C III-4.D Site Proximity Missiles 09/15/81R 07/29/82C (ELEC)

Shutdown (Including Aircrafts)

VII-6 Frequency Decay NOHE 0 9/21/81C III-7.D Containment Structural 06/29/81R 03/30/82C IX-3 Station Service and Coolino 03/05/82R 06/30/82C Water Systems V-1 Compliance with Codes and NONE DELETED Standards (10 CFR 50.55a)

IX-5 Ventilation Systems 03/09/82R 07/23/82C (MP A-01 A-14)

(3-33)

LACROSSE Eg (Cont.)

R11 (Cont.)

SAR 1/

SER 7/

SAR 1/

SER R/

TCPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE V1-1 Organic Materials and Post 02/19/82R 09/13/82C XI-2 Radiological (Effluent and NONE DELE 1ED Accident Chemistry Process) Monitoring Systems (NRR B-67)

D31 XV-1 Decrease in Feedwater 03/05/82R 08/23/82C SAR 1/

SER g/

Temperature, Increase in TOPIC HO. TITLE SCHEDULE SCHEDULE Fendwater Flow. Increase in Steam Generator Relief Il-2.C Atmospheric Transport and Ot/05/82R 09/28/82C or Safety Valve Diffusion Characteristics for Accident Analysis XV-3 Loss of External Load.

06/26/81R 11/03/81C Turbine Trip, Loss of Con-III-4.A Tornado Missiles 08/16/82R 09/23/82C densor Vacuum, Closure of Main Stenn Isolation Valve III-4.C Internally Generated 03/05/82R 06/29/82C (BUR), and Stam pressure Missiles Regulator Failure (Closed)

III-8.A Loose Parts Monitoring and NONE 02/09/82C Core Barrel Vibration XV-4 Loss of Non-Emergency A-C 06/26/81R 10/21/81C Monitoring (NRR B-60 C-12)

Power to the Station Auxiliaries IV-2 Reactivity Control Systems NONE 12/10/81C Including Functional Design XV-5 Loss of Normal Feedwater 03/05/82R 08/12/82C and Protection Against Flow Single Failures XV-7 Reactor Coolant Pump Rotor 03/11/82R 07/19/82C VI-2.D Mass and Energy Release for NONE 05/23/82C Seizure and Reactor Coolant Possible Pipe Break Inside Pump Shaft Break 4

Containments i

XV-8 Control Rod Misoperation 02/26/82R 03/25/82C VI-3 Containment Pressure and NONE 05/28/82C (System Malfunction or Heat Removal Capability Operation Error)

VI-4 Containment Isolation NONE 05/30/82C XV-9 Startup or an Inactive Loop 08/25/81R 10/01/82C (SYS)

System or Recirculation Loop at an Incorrect Temperature, and VI-6 Containment Leak Testing NONE 08/24/82C Flow Controller Malfunction (MP A-04)

Causing an Increase in BW9 Core Flow Rate VIII-1.A POTENTIAL EQUIPMENT NONE 06/25/82C Failures Associated with a XV-11 Inadvertment Loading and 02/26/82R 03/26/82C Dcqraded Grid Voltage Operation of a Fuel (MP B-23)

Assembly in an Improper Position IX-1 Fuel Storage 02/26/82R 09/23/82C XV-13 Spectrum of Rod Drop 02/26/82R 03/25/82C IX-6 Fire Protection (MP B-41)

NDHE 09/30/82 (SYS)

Accidents (BWR)

(DOSES) 02/26/82R 06/30/82C XI-1 Appendix I(MP A-02)

NONE DELETED (3-34)

l LACROSSE

~E31 (Cont.)

SAR 1/

SER 7/

TOPIC NO. TITLE SCllEDUL E SCIIEDULE XV-14 Inadvertent Operation of 08/25/81R 07/16/82C ECCS and Chemical and Volume Control System Malfunction that Increases Reactor Coolant Inventory XV-15 Inadvertent Opening of a 06/30/81R 0 9/21/81C PWR Pressuring Safety-Relief Valve or a BWR Safety / Relief Valve i

XV-16 Radiological Consequences 03/09/82R 09/28/82C of Failure of Small Lines Carrying Primary Coolant Outside Containment XV-18 Radiological Consequences 05/28/82R 06/23/82C l

of Main Steam Line railure i

Outsi(o Containment (BWR) l XV-19 Loss of-Coolant Accidents 05/28/82R 07/15/82C (SYS)

Resulting from Spretrum of i

(DOSES)

Postulated Piping Breaks 05/28/82R 09/28/82C

'l Within the Reactor Coolant Pressure Boundary 4

XV-20 Radiological Consequences 03/12/82R 09/28/82C l of Fuel Damaging Accidents (Inside and Outside Containment) t/ SAR : Licensee Safety Analysis Report-Scheduled or Actual (Actual (Status ib) when date is folloued by R) 2/ SER : Staff Safety Evaluation Report -Scheduled or Actual (Actual (status 4a, 5, 7 ) when date is followed by C) 1/ Desiginated number of days from receipt of licensee SAR q-(Note if Licensee SAR is received then date is from i

receipt of additional information requested) i 1

i (3-35)

LICENSEE TOPIC SUBMITTALS LACROSSE TOPICS 4g TARGET 35 ACTUAL 30 25

/

20 ALLSUBMITTALfRECEIVE 15 10

~~

l l

I l

l l

l 1

l l

0 JUN JUL AUG SEP OCT NOV DEC JAN FEB MAR APR NAY JUN JUL/DEC Tm 5

2 1

1 PER MONTH ACTUAL 1

3 1

0 0

5 10 2

5 1

1 TARGET 20 25 27 28 29 CUMULATIVE ACTUAL 1

4 5

5 5

10 20 22 27 28 29 G-36) -

U.S. NUCLEAR REOULATORY COMMISSION

(?778 NUREG-0485 Vol. 4 No.10 81Bl.lOGRAPHic DATA SHEET 1 TITLE AND SUBTITLE (Add Vokme No.,if eprerissel

2. (Leave b/m A/

Systematic Evaluation Program Status Summary Report

3. RECIPIENT'S ACCESSION NO.

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5. DATE REPORT COMPLETED M ON TH l YEAR November 1982

9. PERFORMING ORGANIZATION N AME AND MAILING ADDRESS (Inc/vcir Inp Codel DATE REPORT ISSUED uOura l YEAR Office of Resource Management November 1982 Office of Nuclear Reactor Regulation

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U.S. Nuclear Regulatory Commission Washington, D.C.

20555 8 (Leave blonhl

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October 1-31, 1982

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16. ABSTR ACT 000 words'or less)

The Systematic Evaluation Program is intended to examine many safety-related aspects of 11 of the older light water reactors. This document provides the existing status of the review process including individual topic and overall completion status.

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