Text

Systematic Evaluation Program Status Summary Report.Data as of October 31,1981.(Buff Book)
	ML20033C444
Person / Time
Issue date:	11/30/1981
From:	; NRC OFFICE OF MANAGEMENT AND PROGRAM ANALYSIS (MPA), Office of Nuclear Reactor Regulation
To:	;
References
	NUREG-0485, NUREG-0485-V03-N12, NUREG-485, NUREG-485-V3-N12, NUDOCS 8112030228
	Download: ML20033C444 (100)
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NUREG-0485 g

Vol. 3, No.12 Sk"novl s 1981 1

%~ i October 31,1981 l

4 g9

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SYSTEMATIC EVALUATION PROGRAM STATUS

SUMMARY

REPORT UNITED STATES NUCLEAR REGULATORY COMMISSION p acoy N:. ]

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Available from

- NRC/GPO Sales Program Superintendent of Documents

. Government Printing Office 3

Washington, D. C. 20402 A year's subscription consists of 12 issues for this publication.

Single copies of this publication are available from National Technical information Service, Springfield, VA 22161 Microfiche of single copies are available from NRC/GPO Sales Program

. Washington, D. C. 20555 s

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1 NUREG-0485 Vol. 3, No.12 October 31,1981 SYSTEMATIC EVALUATION PROGRAM STATUS

SUMMARY

REPORT Prepared for: OFFICE OF NUCLEAR REACTOR REGULATION Prepared By: OFFICE OF MANAGEMENT AND PROGRAM ANALYSIS l

UNITED STATES NUCLEAR REGULATORY COMMISSION p s** coq f.YH t

-fa *T./a. x v'

,, l,.- l r.

tj. W 'N llllAj'g/

k]*%r',o William T. Russell, Chief Dennis M. Crutchfield, Chief M*l"Of [ic"M " "' "' "' "'*"*"

Mffn""f Cce'$7n*'*" "'

Office of Nuclear Reactor Regulation Office of Nuclear Reactor Regulation j

TABLE OF CONTENTS SECTION I SECTION ll SECTION lil l, SEP TOPIC LIST 1-2 to 1-3 BIG ROCK POINT 2-2 to 2-5 PALISADES 3-2 to 3-3 DRESDEN 1 2-6 GINNA 3-4 to 3-5 1 l DESIGN BASIS EVENT 14 DRESDEN 2 2-7 to 2-10 DRESDEN 2 3-6 to 3-9 GROUP DESCRIPTION GINNA 2-11 to 2-14 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 i

LACROSSE 2-19 to 2-22 SAN ONOFRE 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 PALISADES 2 31 to 2-34 PROGRESS TOWARD 17 YANKEE ROWE 3-29 to 3-32 COMPLETION (Graph)

SAN ONOFRE 2-35 to 2-38 LACROSSE 3-33 to 3-36 l

INTEGRATED PLANT l-8 l

SAFETY ASSESSMENT SCHEDULE SEP TOPIC STATUS BY 1-9 REVIEW DIVISION (Summary Table)

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

SEP TOPIC SUBMITTALS 1-12 thru 1-13 BY LICENSEES (Graphs)

a J

4 l.

I i

I 4

4 M

i I

Z i

O i

O W

M t

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SYSTEMATIC EVALUATION PROGRAM TOPIC LIST i

fre ti #

IIYL(

T3p!C e lifLE Top f C #

,T, lit E t

!!.1 A. I sc bsson Area Aetnority and t ont rol g g g-g

4. yoreado *Itsst les W

HadWy MM MW MW hWM Desty and Protection Agalest Stagle f ailures

?. Papv f at on Distrttwt sca

,17-3 but Jet Pumps Operettng Indications i. e teatiat pasares or Chevs na Potential a

g, yW ae "'is des nazar$s Due to Iran %crtation. In t itut toaal e 00 CFR I n64st ri a l, and Milttery f acilitici

!!!-4 C. Internally Generatee Misstles

!!-2 4 Severe oestber Pnear.nena V.2 Appilcable Code Cases e

e B. Unsite "eteorological neasurearets Program V-3 Overpressertration Protectton C. Atmoss eric Transcort and Dif f,ston Charac.

8-NU9 ed W8 N IDNI n

teristics f or Acct 1 rat Aaalys's D. $ste Pres setty ptssiles (includtag Aircraf t)

V.5 Reactor Coolant Pressert Soundary (RCPS)

'O Availability of Meteorological Data to the 333 5 A. Ef f ects of P tpe Breat on 5tristtures. Systees Leak age. Detection Contror toon and Costonents Instae Containment v.6 Reactor vessel lategrtty

!!-3

1. hydeologic Description g, pipe Breat Outside Contatrwent V.?

Reactor Coolant Pune Overspeed I"

5

8. Ilooding Potential and Protection segwire-V-8*

Steam Generator (SG) Integrity meet s

!!!.7 A. Inservice Inspection, lecteding Prestressed I-9 Reactor Core Isolation Coolta; System (shp) 1 Capat:tlity of C;erating Plant to Cope Concrete Containrents with t tther Grouted I-10 A. RHR eat (EChanger Tube Fatleres with bes t@t Basis Ilooding Csiditions or Ungrouted Tendons C. Saf ety-related ester 5 opty (Ulf smete Meat

8. Design Codes. Design Criteria. Load

8. RNR Reliability k"*

(UH5))

Costinations, and keactor Cavity De'tyt Criterta V-Il A. %uWeents M Isolation of Mtyi and Low

!!-4 be otogy and Setsaclogy Pressure Systems -

C. Delacination of Prestressed Concrete Con-3 feCiontC Province tainsa nt Structureg B. SHA Interlock Requirements B. Prosietty of Capable TectentC 5trutu es D. Contatnnent 5tructural Integrity Tests V-12 A. Water Purity of Bot ting Water Reactor r

en Plent Viciasty Primary Coolant 111-8 A. Loose Parts Monitoring and Core Barrel

'*l3 Water Masser i

C. Mntorical Sensicit y..tri- /JG Miles of vibratton Monitoring Plant

8. Control Rod Drive Mechanism Integrity VI-I Organtc Materials and Post Acctdent l

Chemistry L. Stanility of Slopes C. Irradiation Oaatsge, use of Senstttred Stainless Steel and Iatit>e teststance VI.2 A. Pressa-Suppressten Type best Containments L. Das Inte9rtty

' 8. Subcompartment Analysis

, C. Core $vpports sai f sel Irtegrity F. Settleaent of Iow det eens sad Berted C. Ice Condenser Containment a

(g a ip.e et (11 9 5.pport Integrity D. Mass and Energy Release for Possible Ptpe 111 10 A. Thermal-Overload Protection f or pators of Break Inside.onta6ndient r

!!!-l f lessif icat son of 5t rutures. Cus on. at s

- d Motor-operated valves bstens (Wesent and Wality)

8. Peas Flye eel Integrity V I-3 Containment Pressure and Heat temoval n

til-2 bind a*d Tornado L oadtavs Capability 111 3 A. E f fects of wit m eter level on Structures t ion Purps and Discurge Valves VI.4 Conteinment Isolation Systee

!!!-11' Cortonent Integrity VI.5*

Coacustible Gas Control B. Structeral and utner Consequences (e.g.

VI-6 Containment Leak festing E luoding of adf et y-ke t at ed I go speent sa Pawat s) of f a s bre of umJerdrain $yucas 111 12 in ironmental Qualtitcation of Safety Related v

tquipment

r. Inservue l aspect 6oa of m ater C ont rol 5 t rue.

If-l A. Operat too witn L e.s Than All too;>5 in-Service tures 12 I

t

SYSTEMATIC EVALUATION PROGRAM TOPIC LIST TCPIC a 117t f TOPIC #

f.liit.

TOPIC #

TITtt VI-7.P

1. ECC5 s -e valuation to Account f or Increased V11-5 Instrueents f or Monitoring Radiation and Process IV-5 toss of Normal Fee < heater flow e

vessel Head f ess eratu e Wartables During Accidents r

IV-6 Fee

ster System Pipe 8reaks inside and Outside

2. tipper Plenum InjeClion V f!-6 Frequency Decay Contatnpent (PWR)

3. ECC5 Actaation systea V l f-7 Acceptability of swing Bus esign on BWR-4 IV-7 acactor Coolant Puae totor setzure and Plant s Reactor Coolant Puay Shaf t Break

4. Core Spray llozzle i f f ect t veness Vll!-l A. Potent tal tquipment F ailures Associated a tth IV-8 Control Rod Mtsoperation (System MalfunCtton V I-7.5 f 5F 5.itchover f rom Injection to tecirculation a Degraded Grid Voltage or Operator Error)

Mode (Automatic ECC5 Realtonsent)

W!!!-2 Onstte Emergency Paner Systems - Diesel XV-9 5tartup er en Inartive loop or Rectrculation V I-7.C f CCS 5t agne F ailure Criterion and Require-Cenerator toop at an incorrect f ewerature, and Flow ments f or toca ing out Ner to Valves Controller Malfunction Causing an Increase in laciuding independence of Interlock s on Vllt-3 A. Stat ion Battery Capacity Test Requirearnts ga Core Flow Rate I V-10 Chemical and volusu Control system Malfunction B DC Power System Bus Voltage Monitoring and that Results in a Decrease tn the Soron Concen-

1. Appendis s - E lectrical Instrumentation Annu nc t at ion tration in the Reactor Coolant (Pd) and Control (EIC) Re-reviews VI!!-4 tiectrical Penetrat tons of acactor Containment XV-Il Inadvertent Loading and operatton of a Fuel

2. Fat fore Mode Analys 6s - (CCS Assently in an ! groper Position

3. The E f f ect of Pd toop Isolation Valve IV-12 Spectrum of Rod Ejection Accidents (P2)

Clowre During a LOCA on (CCS Perf orpunce 11-2 Overhead Handitng Systems - Cranes adbt II-3

'tation Service and Cooling water 5fstems IV-13 Spectrum of Rod Drop Accidents (BW) ood n o o a X V-14 Inadvertent Operetton of ECC5 and Chemical V !- 7.E (CC5 Sug Design and Test for Rectrculation in-4 soron Addttton System and Volume Control System Malfunction that 8

II-5 Ventilatton Systems V I-7.F Accumblator Isolation valves Power and Control gV-15 inadvertent opening of a Pm Pressortaer Safety-

System Design

11-6 Fire Protection Rettef Valve or a ed Safety /Rettef Valve WI-8 Control Room Habitability A

Avalltary Fee 4sater System IV-16 Radiological Consequences of f ailure of inall VI-g Mats Steam Line isolation seal System - 8.st Al-1 Append 1=,-

Lines Carrying Primary Coolant Outside Contain.

,,ng VI-10 A. Testing of Reactor Trip System and Engineered gg 2 padiological ([f fluent and Process) Mone;oring IV-l y 5 team Generator Saf ety Features including Response Time Systems Tube Failure (PA) resting XI!!-l Conduct of Operations IV-18 Radiological Consequences of Main Steam

8. Shared Engineered Saf ety Features. On-site Line Fatlure Outside Contal#went (5hst)

Esergency Power, and Service Systems f or I!!I.

Saf ewards/ industrial Security Multiple Unit f acilittes XV-19 Loss-of-Coolant Accidents Resulting fram IVJ 9* crease in F eeeeater legerature, increase in Spectrum of Postulated Piptog Breaks Within V II-l A. Isolation of Reactor Protectton System f rom Icedwater F low, increase in Steam Flow and the Reactor Coolant Pressure Soundary Non-Saf ety Systems. Including Quellficet tons inadvertent Opening uf a Ste*= Generator kellef of Isolation Devices or Safety Valve IV-20 Radiological Consequences of Fuel Damaging Acctdents (Inside and Outside Coataiament)

8. Trty Uncertainty and Setpoint Analysts Review IV-2 5pectrum of Steam System Piping Failures lastde of Operating Data Base and Outside of Containaent (Pw) n-2 t Fu ask Dmp AccWnts Vll-2 (agineered Safety Features (L5F) System Control nV-3 Loss of E sternal Load. Turbine Trip. Loss of N'

to9tc and Design Condenser Vacuum. Closure of Mann Steam Isota-gy,y3' Multiple Tube Failures in Steam 0enerators t ton valve (3d). and Steam Pressure ReW ator l

V!l-3 Systenis Required f or Saf e Shutdown f ailure (Closed)

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

-Emergency A-C Pmeer to the Station Vil-4 f f f ects of f ailue, in non-Saf ety Related

[

IVI Technical Spectf tcations systems on selected Engineered Saf ety Iestures IVil Operattonal QA Program

' Topic deleted frorn SEP prograrn due to duplication by Three Mile Island (TMI) NRC Action Plan, Unresolved Safety Issue or other SEP Topic per May 7,1981 letter from G. Lainas to all SEP Lecensees.

1-3

_r,_-_,._ _,,, _ _.,,, _ _ _,,, _.,, _ _.,, _ - _ _ _,

DESIGN BAS S EVENT REVIEWS THIS SECTION DEFINES DESIGN BASIS EVENT (DBE) REVIEWS FOR THE ELEVEN SEP FACILITIES M f *

'810 LI$'

Boa DELTyf] bj$T Bd 4 W8 DP LTOPJC,.M ST, r..,,... ;

T,. 3.,, t r,,sid Ameert a e Treasiert srag Ce! T38 ;'.

TILJ In TCe!r T Pt t

E " $.

Tj'd crea i I.-:

cec ress e i. feed. ter temer. tare um beha I 88 1 Decrease le 8eedma'.ee t erper a tsre (B= 2_

Ie-1 increase in fegoi.afer flow t f..nOS i:-3. A Fydro109 C description 1

8L =L 78-i Increase to feem eter f ? a.

aul Increase sa stee+ fla.

2 ; 2.6 a loodtng poteettel and protection as+

Intresse le 5teer f l om Is-9

$ttrt-4 Cf 164C i tte 10GD 4*d flow req a t terea t 5 (Cepobility Of operating 88-1 ine3eerteat ocer.teg c* stee*

co* trol l er eelf rection plant to cope with dest 9e basis flooding I

1ererttor relief /iafety alve s o-3

n d.erteat closure of metri stea*

c ondit tua)

$ tert.e 0# taa tte 15aldt104 velve

]! ).C lated water 5.pply (ultiedte 88 4 s,,Ir e. :..s t s e. t.100:

$dfety re,m

i. t:

C s,.s neat 3 Tar %j.I Res k 0% of eaternal load be.',, *a 8=5 L OS S C en ter*el Iced 3.-J Tsre tce trte M;W;c l

8e 3 Turd 1a. trt&

Ru]

Lou Cf Comdemier vacup 1l-4. A Tectocic province s

l l -4. 8 Proatet ty of capable tectopic StructJres l

Ab) irg; ef COr de% er te< mr d'-1

$ leer preNre reb et3r f ei IdPr rear pleet s

l I

Id-3

$ t e4* $ceibre regeletCr fetIw e 3 *-$

Loss of feedmater flom j f.4.0 st15torical SetsmiCity witht4 200 miles e

E*1

.,3%

0' fee 3ee ter f l om 6f piert 38 4 Icedmeter Spite

Dipe Dre##

67) s 3

Il s83l07091;d1 C06%eGae"e5 Cf a ll.4

$tettllty of Slopes s

41e SteF Liae F411e e Cutilde r

E. %,. u,,t I s- ?

$ te d*

line greae teilde c Cet41FFI CO85 t a

Rr* 8t w;$$LF G[EkA*]Ch ] ] [ torneio m1bltlet f

IW"2 S teer l'Fe trees Odtllde Cortetareet AN' 4rhi }#

3 s'-I LO51 Of AC D0wer 10 Stal1OM

' ' ^ "s SWICT104"

] ! ! -4. E Turbine missiles

' " ~ '

11l-4 (

Irternally generated 215511e5 l

bis I* -4 L CH C' A0 power to Station aan il t eries

!!!.4.0 5tte premioty etstIIe5 ( t r cluding e.. m r ies aircraf t) e l

r e-7 toss ef forces coole t fis.

n7 Pet eff pe; rotor seirs e vew;j i.a Loss of forcee cooleat f!o.

g,,

111-2 w tad **d tor **do 10*di"'

cw e

Ab7 Pri ery ppa rctor sentare 3..'

Frim ry OCD Shaf t break a

B o-7 PrMery pu s $msft breat e

~

u le8 Uecoetrclied POC a;5ertly withdrewel Grog 0,7 842 Acetr0lle$ rDd 4%ertly mi?*

41 00=er e_.

drtmeI at power I,-

@tcetrCIIe3 etd 415ertly witMdrawai fuE Jr40r trolled red euertl y a tt>-

IQu power Start-up ces=al 13. Power start-u, Is-8 Corteol rod ensoperetton l' - t CDe t r+ ' rod OtsoperstlCe E d= 13

$2*4t er Gf rod drGy SCC 13tnts s

3.-12

$' t!. t r # C# Fod 0;ftt10e acciderts is7kE_,,V,Ij 8e l)

$:#C tr.A* Of 10% 0' Coclan t 4< c ? dee'

~

cr%;~c Gr?.; dE

~

~'

s.

Radtslogical Consecuences of Fuel n-2c assictoccat consewues of roe'

.weg acc tets (taside aed Oe"#9t ej ACC ice *ti l 4651de and out31de CCetriver* '

09ti de Cor:la1Hrvetj i

Grw;, lj a.,13 leedverteet CPemI"9 Cf BdR S a f e ty.'

h* L*g,jj 38-li 164deerte91 CDePS*G Cf Pm E relief v41we pressortar reitef.41.e breaLa 26 14 lr.43,ertent cperettoe cf [CC$

be,J,4f]

Rel4 Ine$eertert Operat1or of ECES or (80$ reifanctice that Cadei en GrP_4 3]

IUll I8ed'*rtert loading and DDerett0D of inc reau in cC.ol.at ie.etery a Net aneels ta en 'mrecaer pot t tion 6f$elfl

%Gt 4;;ItceDle tG PnEl cr%p ~sjj het ancitC. ele to s.%

r,,j M f e t'

$ led

Greers!Or Tsbe Fativre

~~

e 1-4 I

l

+

STATUS DEFINITIONS G - Generic 4a-Draft SE Received From Review Branch These topics are being evaluated as part of on-going N RC generic review effort. The ongoing This status is used for internal NRC tracking of generic review and the SEP topic review will be closely integrated to improve the effectiveness topic review progress. The status indicates that and efficiency of these efforts and to minim e a draft topic safety evaluation is under mange-any impact on licensees. The status and cor ment review.

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 NRC TMl Action Plan, will not be issued for topics with licensee SAR submittal.

Unrtsolved Safety issu-e or another SEP Topic per the May 7,1981 letter from G. Lainas to all SEP licensees.

5 - Draft SE Sent to U tility 0 - 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, facility. 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 drr" SE has been reviewed and licensee tLpic evaluation is not available and that ques-commt

' any have been formally transmitted tions have been developed and sent to the SEP to the N RC.

branch.

e 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 licensee has responded have been formally transmitted to the licensee that the NRC draft safety evaluation (i.e. status 5) as a request for additional information.

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

1-5

r 7

SEP TOPIC STATUS

SUMMARY

REPORT"

\\

N NUM3ER OF ~

QUESTIONS QUESTION DRAFT SE SAR SE

'N TCPICS TOPIC RECEIVED GUESTIONS RESPCNSE RECEIVED RECEIVED DRAFT SE

RESPONSE

-TCPIC

\\'

GEtiERIC DELETED NOT FRCM SENT TC RECEIVED FROM FROM SENT TO RECEIVED COMPLETE N

(G)

(X)

STARTED REVIEW UTILITY BY NRC REVIEW LICENSEE UTILT1/

BY NRC (7)

PLANT NAME N

(0)

ERANCH (2)

(3)

B R A t!CH (4b)

(5)

(6)

\\

(1)

(Ga)

\\

PALISADES to 44 1

0 0

3 1

3 5

11 59 GI':N A 8

42 1

1 0

4 7

4 2

14 54 CRESDEM 2 8

47 9

0 2

12

-0 15 5

6 33 OYSTER CREEK 8

51 8

0 5

3 5

17 7

4 29 MILLSTOME 1 10 48 1

1 3

8 4

20 5

1 36-SAN OND*:tE 9

45 5

2 3

14 3

11 12 4

29 50 12 1

2 16 3

9 3

1 34 BIG ROCK P3 INT hl.DDAM i:ECK to 44 6

0 1

18 2

23 2

9 22 YANKEE RCME 9

44 13 2

7 13 0

16 5

2 26 LACROSSE 7

51 20 1

to 6

3 1'

2 1

22 Dr:ESDEN 1 TCTALS THIS MONTH 25 466 76 8

33 97 25 132 48 53 344 TOTALS LAST MONTH 85 456 10E f

8 35 103 27 1C4 51 55 327 i

r HOTE: Totals do not include Dresden 1,

see page 2-6.

Also incluoed is May 7, 1931 deletion letter to all SEP licensees, saa footnote page 1-3.

1-6

SYSTEMATIC EVALUATION PROGRAM GOAL PHASE lil/

-1/ Not inc uding Dresden 1 Progress Toward Complet. ion ACTUAL 100

/7

-82

./p

'/

90

,s 80

,, d' 75%

1. l3%

y

~

/

1 month 70%

j 70 67 a

61 p/

/

~

$ 60 60 %

' 81 O

j C'

p*

50 p *'

54%

50 %

y j/

47%

I

/

44%

9 p

tu 40

,/

42%

5

/

M%

s

36%

30

- J 30 % iestimated)

~

The plant topic overall completion status (percent complete) is calculated Status 1Bleighting Factor based upon the number of topic reviews to be performed (not including generic or deleted topics) and a weighted average of current topic review G,X Not included 20 status. The calculation is performed using the following formula:

0 0%

1,2,3 35%

4a,4b 80 %

)

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

00 %

10 Sum of Topics 0

10 11 12 1

2 3

4 5

6 7

8 9

10 11 12 1

2 3

4 5

6 7

8 9

FY-81 FY-82 17 l

.c.

INTEGRATED PLANT SAFETY ASSESSMENT SCHEDULE' n

n l~

l TOPIC TARGET DATE DRAFT SER DRAFT SER DRAFT SER ACRS COMMISSION FINAL SER.1:

PLANT NAME ALL TOPICS INTERNAL DIVISION TO ACRS AND' MEETING.

MEETING TOLICENSEE.l' COMPLETE-COMPLETE DISTRIBUTION

. REVIEW LICENSEE-

/

PALISADES-94 Sept.-81 Oct.

81 Nov.

81 Dec.

81 Jan-82 Feb.

82 Mar.

82 GI'NN A -

91

'f Sept. 81

.Nov.

81 Dec.

81 Jan.

82 Feb.

82 Mar.

82 Apr.

82 DRESDEN 2 73' Oct..81 Dec.

81 Jan.

82 Feb.

82

. Mar.

82

.Apr.

82 ~

May 82

-l

'1 i

OYSTER CREEK 76 Nov.

81 Jan.

82 Feb.

Mar.

82 Apr.

82-May-82 June 8 2...

M 82 Apr.

82 May 82 June 82

'luly 82 MILLSTONE 1-82 Dec.

81 Feb.

82

.1

. SAN ONOFRE 74 Feb.

82 Apr.

2 ay 82 June 82 July 82 Aug.

82 Sept.'82 BIG ROCK POINT-66 Mar.

82 Ma 2

June 82

. July 82 Aug.

82' Sept. 82 net.

82 HADDAM HECK

71 Apr.

82 June 82 July 82 Aug.

82 Sept. 82 Oct.

82

.Nov.

82-YANKEE ROWE 63 June 82 July 82 Aug.

82 Sept. 82 Oct.

82 Nov.

82 Dec. '82 LA CROSSE 56 July 82 Aug.

82 Sept. 82 Oct.

82 Nov.

82 Dec.

82 Jan.

83 a Tentative - Need and schedule for ACRS/ Commission review to be determined after completion of lead plant (Palisades) review.

OVERALL COMPLETION : 75%

1-8

l SEP TOPIC STATUS by REVIEW DIVISIDH

SUMMARY

TABLE PLANT' PALISADES GINNA DRESDEN' OYSTER MILLSTONE SAN

. ROCK HECK ROWE BIG HADDAM YANKEE' LACROSSE TOTAL.

2 CREEK 1

ONOFRE POINT (IAPM) 1/

Michaels

. Wang Cwalina Fell Persinko McKenna

-Scholl Brown Wang Michaels N0' 0F TOPICS 137 137 137 137 137 137 137 137'

.137 137-

~ 370 1

DELETED,2/.

44 42 47 51 48 45 50 44 44 51.

-466 APPLICABLE 93 95 90 86 89 92 87 93 93.

86

'904-53

/

35

/

31

/

31

/

7

.27

/

26

/

23

/

25 2

DL

/

. /

/

. /

21

/

299 /

/'

/

/ 57

/ 39

/ 36

/ 34

/ 3 p/ 40

/ 38

/ /. 38

/ 35

' /

392' TECHNICAL:

/

\\

/

16

/

16

/

7

/

4

/

9

/

3-

/

4

/

6

/

3.

/

74- -/

REVIEW DOE

/

/1

/

'/"

/ 19

/ 22

/ 23

/ 2

/ 19

/ 18

/ 22

/ 210 ASSIGNMENT 1/

/

9-

/

27

/

6

/

>' 13

/

9

/

8

/

3

/

1

/

2

/

88

/

DSI

/

/'

/ 17

/ 34

/ 31 f

/3

/ 30

/ 33

/ 31

/ 33

/ 29

/ 302

/

d

/

/'

/

78

/

78

/

44

/ Xf5

/

46

/

45

/

37

/

30

/

32.

/

26

/

461

/

COMPLETE

/

7

/'

/

/ 93

/ 95

/ 90

/ 86

/ 89

/ 92

/ 87

/ 93

/ 95

/ 86

/ 904

/

/'

/

/-

TARGET DATE -

SEP 81 SEP 81 OCT 81 NOV.81 DEC 81 FEB 82 MAR 82 APR 82 JUN 82 JUL 82 ALL TOPICS COMPLETE l/ Division of Licensing Integrated Assessment Project Manager

_ 2/ Deleted as not applicable, or duplicated by USI, TMI Action Plan, or another topic.

_1/

All~ topic review completion dates are before end of FY 1982.

These schedules and assignments are consistent with NRR budget requests.

__/

No. Completed'/ Ho. Assigned

.I/

1-9 STATUS AS OF OCTOBER 31, 1981

[-

[:

4

. PROGRESS'0F TOPIC' REVIEWS J

DIVIS!IDI W UCBSIE TPICS e

TAfEET

~~

8--

m ACTUAL p

/

25 --

3_

15 --

IN --

g i

e i

i e

i g

JUN JIL AUG SEP OCT lef DEC JAN FEB MAR APlt MAY JLal JIL leml PER MONTH

.b3 Target 19 19 17 10 10 6

6 4

3 2

2 1

J Actual 1

to f

g Target 299 318 335 3N 368 374 300 384 387

' 309 391 392 b)

CUMULATIVE Actul 281 291 294 P

S OF TOPIC REVIEWS I (31 W EEIIEst!E TtPICS A

TAfEET

~ ~ ~

g__

- - ~

s

/

15 -~

p

/

is --

/

l

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i i

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i i

g Jtti Jll AUG SEP CCT 90f DEC JAN FEB 11 Aft APR MAY Juf JJ.

IENTH i

Target 28 27 22 19 14 9

6 6

5 3

2 2

1 PER MONTH 2

2 Actual 4

0 I

Target 94 121 143 162 176 195 191 197 202 205 207 209 210 IY 70 70 72 1G4 Ac,y,;

i I

-PROGRESS OF TOPIC REVIEWS i

j DIVISION OF SYSTDG INTEGRATION -

, TOPICS -

358 TARGET

_ 3g3 ---

p

/

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p Y

/

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/

158 -~

/

/' l

/

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AUG SEP OCT

- NOV DEC JAN FEB MAR APR MAY.

Jtal JtL Target 43 42 38 M

24 18 14 14 10 7

4 4

2 F

Actual 11 3

1Q 14) h30 248 262 276 286 293 297

'301 303 Target 93 ~

135 173 CUMULATIVE -

Actual 61 64 74 PNG E OF TOPIC REVIEWS 5

AL PELECT h

ftFICS -

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/

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y

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ALE EP (ET Mlv EEE JAN FEB HAR APR 14AY 2 81 JL l4 Target 90 88 77 64' 48 37 26 26 19 13 8

8 PER MONTH Actual 18 13 16 20 Target 486 574 651 715 783 800 826 852' 871 884 892 900 004 COMULATIVE 412 425 441 461

' Actuat

.7,.

.1:

1 LICENSEE TOPIC.SUBMITTALS DIVISION W LICDSING

. StastTTALS -

i 48 i

TAREET 35 --

y------s, o.

_/

f.

. ACTUAL :

V

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R ALE SEP

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DEC JAN -

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. IOm6 8

5 6

2 1

0 0

.0 1

0 PER MONTH Actual 0

3 1

g 1

21.

26 31 33 34 34 34 34 35 35 CUMULATIVE

. Actual 0

3 4

5 i

N

^E i.

LICENSEE TOPIC SUBMITTALS DIVISION & DCINEERIIC SimsITTALS l

0 19 TARGET

"~'~

~-----.

ACTUAL

. gg

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f

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DEC JAN FEB

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1-

.9 14 11 5-

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5 1

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. PER MONTH Actual 1

8' 1-5 Tarpt 1

10 24 35 40 52 53 58 59 59 59 59 59 CUMULATIVE Actual '

1.

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1

' LICENSEE TOPIC SUBMITTALS DIY!$10N OF SYSTDIS INTEIstATION SEMINALS tm

"~~~~~

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/

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MONTHS Twget 1

14 46 7

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2 3

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10 3

31 Target 1

15 61 68 78 88 91 94 94 94 94

' 94 94 Actual 1

11 14 45 m

3-LICENSEE TOPIC SUBMITTALS TOTu. rR0nct SEMITTALE 2N TARGET f

g*-----

175 --

1M --

a 125 --

[

/

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D JtL '

AUG SE.

. OCT NOV DEC JAN FEB MAR ArR MAY Jtm JLA.

MONTHS PER MONTH 0

'O 1

0 Actual 2

21 5

37 Tweet 2 --

33 98 124 144 171 175 183 187 187 187 188 188 CUMULATIVE Actual '

2 23 28 65

,,4

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..-.- --,,.~.., -.,. - -... _,.,

BIG ROCK POINT FACILITY: BIG ROCK POINT 1 TOPIC NC.

REVIEW STATUS REMARKS DIV/BR LICENSEE: CONSUMERS POWER

___11-1 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 DOCKFT NO.

05000155 II-1 C.

DL/SEPB 7

NRC to CPCo 05/13/81 POWER CAPACITY: 0240(THERMAL) 067(ELECTRICAL)

II-2 A.

DSI/AEB 7

NRC to CPCo 08/03/81

~

II-2 B, X

HRC to CPCo 05/07/81 II-2 C.

DSI/AEB 0

II-2 D.

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

DE/HGEB 3

CPCo to NRC 08/21/81 OPERATING REACTORS BRANCH CHIEF:

D.

CRUTCHFIELD II-3 B.

DE/HGEB 3

CPCo to NRC 08/21/81 OPERATING REACTORS PROJECT MANAGER: W. PAULSON II-3 B.

1.

DE/HGEB 3

Site Visit 07/16/71 INTEGRATED ASSESSMENT PROJECT MANAGER: R.SCHOLL/hkS!II-3 C.

DE/HGEB 3

NRC to CPCo 08/04/80

% II-4 DE/GSB 7

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

DE/GSB 7

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

DE/GSB 3

FROM REVIEW BRANCH X - DELETED II-4 C.

DE/GSB 7

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

DE/HGEB 4b CPCo to NRC 10/05/81 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 4b CPCo to NRC 10/19/81 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC III-1 DL/SEPB 2(Sys)

HRC to CPCo 05/00/80 TO UTILITY DL/SEPB 7(ELEC) NRC to CPCo 08/19/81 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 3

CPCo to NRC 07/09/81 RECEIVED BY NRC (2-2)

BIG ROCK POINT TOPIC NO.

REVIEW STATUS REMARKS TOPIC NO.

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

DE/SEB 3

CPCo to NRC 08/08/80 III-10 B.

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

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

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

DE/AGEB 0

III-11 X

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

DSI/ASB 0

III-12 X

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

DE MTEB 0

IV-1 A.

DL/SEPB 7

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

DSI/ASB 0

IV-2 DSI/ICSB 3

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

DE/SAB 0

IV-3 X

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

CL/SEPB 3

V-1 DE/MTEB G

NRC to CPCo 05/07/81 III-5 B.

DL/SEPB 2

NRC to CPCo 01/04/80 V-2 X

NRC to CPCo 11/16/79 r

l III-6 DL/SEPB 3

CPCo to NRC 07/27/81 V-3 X

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

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

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

DL/SEPB 3

CPCo to NRC 07/09/81 V-5 DL/SEPB

~

NRC to CPCo 09/30/81 III-7 C.

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

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

DE/SEB 3

HRC to CPCo 08/09/79 V-7 X

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

DSI G

HRC to CPCo 05/07/81 V-8 X

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

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

NRC to CPCo 11/16/7?

III-8 C.

DL/SEPB 7

HRC to CPCo 02/05/80 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.

H./SEPB 5

NRC to CPCo 05/13/81 III-9 X

NRC to CPCo 05/07/88 V-11 A.

ul/SEPB 7(Elec) NRC to CPCo 08/14/81 III-10 A.

DL/SEPB 7

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

DL/SEPB 5(Sys)

HRC to CPCo 05/13/81 7(Elec) NRC to CPCo 08/19/81 l

l l

(2-3)

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BIG ROCK POINT TDPIC NO.

R EVI E!!

$TATUS REMARKS TOPIC NO.

REVIEW STATUS REMARP.S DIV/BR DIV/BR IX-1 DSI/ASB C

XV-10 X

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

NRC to CPCo 05/07/81 XV-11 DSI/CPB 4b CPCo to NRC 09/28/81 IX-3 DL/SEPB 2

XV-12 X

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

NRC to CPCo 11/16/79 XV-13 DSI/CPB 4b(Sys) CPCo to NRC 07/01/81 DSI/AEB 4a(Doses)

IX-5 DL/SEPB 0

XV-14 DSI/RSB 7

HRC to CPCo 08/18/81 IX-6 DE 7

NRC to CPCo 02/06/81 1

XV-15 DSI/R$B 7

HRC to CPCo 08/18/81 X

X NRC to CPCo 05/07/81 XV-16 DSI/AEB 4b CPCo to NRC 07/01/81 XI-1 DSI/ETSB G

HRC to CPCo 05/07/81 XV-17 X

NRC to CPCo 11/16/79 XI-2 DSI/ETSB G

NRC to CPCo 05/07/81 XV-18 DSI/RSB 4b NRC to CPCo 07/01/81 XIII-1 X

HRC to CPCo 05/07/81 XV-19 DSI/R$8 7(Sys)

HRC to CPCo 08/18/81 XIII-2 DL/SSPB

)

HRC to CPCo 03/11/81 DSI/AEB 4b(Dosas)CPCo to NRC 07/01/81 XV-1 DSI/RSB Gb CPCo to NRC 07/15/81 XV-20 DSI/AEB 4a CPCo to NRC 07/03/81

~

XV-2 X

NRC to CPCo

?1/16/79 XV-21 X

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

HRC to CPCo 10/16/8 1 XV-22 X

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

HRC to CPCo 10/16/81 XV-23 X

NRC to CPCo 05/07/81 XV-5 DSI/RSB 4b CPCo to NRC 07/15/81 XV-24 X

NRC to CPCo 05/07/81 XV-6 X

NRC to CPCo 11/16/79 XVI X

NPC to CPCo 11/05/80 XV-7 DSI/RSB Ab CPCo to NRC 07/15/81 XVII DL 7

HRC to CPeo 08/17/78 XV-8 DSI/CPB 4b CPCo to NRC 09/23/81 XV-9 DSI/RSB 4b CPCo to NRC 07/15/81 (2-5)

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

DOCKET NO.

05000010 POWER CAPACITY: 700(THERMAL) 200(ELECTRICAL)

OL NUMBER: DPR-2 N.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: r. O'CONNOR f

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 licen-see stated that the Dresden 1 SEP review is not being actively pursued, i.e.

defered.

(2-6)

i DRESDEN 2 FACILITY: DRESDEN 2 TOPIC NO REVIEW STATUS REMARKS DIV/BR LICENSEE: COMMONWEALTH EDISON 11-1 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-I C.

DE/SAB 0

POWER CAPACITY: 2527(THERMAL) 0774(ELECTRICAL)

II-2 A.

DSI/AEB 7

NRC to Ceco 04/24/81 OL NUMBER: DPR-19 II-2 B.

X NRC to CECO 05/07/81

~ ~ ' '

II-2 C.

DSI/AEB 7

NRC to CPCo 08/26/81 II-2 D.

X NRC to Ceco 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W.

RUSSELL II-3 A.

DE/HGEB 3

CECO to NRC 09/11/81 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD II-3 B.

D E/ HGEB 3

CECO to NRC 09/11/81 OPERATING REACTORS PROJECT MANAGER:

P.

O'CONNOR II-3 B.

1.

DE/HGEB 3

CECO to NRC Sito Visit 01/09/79 INTEGRATED ASSEShMENT PROJECT MANAGER: G. CWALINA,j[,(-

II-3 C.

DE/HGEB 3

Ceco to NRC Site Visit 01/09/79 KEY FOR STATUS COD 11 II-4 DE/GSB 7

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

DE/GSB 7

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

DE/GSB 5

NRC to CECO 07eGv/81 Ab-SAR RECEIVED FROM 0 - TOPIC NOT LICENSEE II-4 C.

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

DE/HGEB 0

1 - QUESTIONS RECEIVED TO UTILITY II-4 E.

DE/HGEB 0

FROM REVIEW BRANCH

.6 - SE RESPONSE RECEIVED 2 - QUESTI0HS SENT BY NRC II-4 F.

DE/HGEB 0

TO UTILITY 7 - TOPIC COMPLETE III-1 DL/SEPB 3(sys)

HRC to Ceco 06/26/81 3 - QUESTION RESPONSE DL/SEPB 7(Elec) Part of VII-3 07/07/81 RECEIVED BY NRC III-2 DL/SEPB 3

(2-7)

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o o o R

t t

t A

a e

o o o

o o

M t

C c C C C C C C C c C C C d0 E

/

i R

E E R E R

E R

R E

R R R

R N

S N

C C N C N C H N C N N N S

U T

b A

3 X 0

0 3

0 0

2 6 6

X 3 X 4 G X 6

X X 7

T S

B B

B B B B B B

B B

WR B

E S

B P P P

P B

P P

EB E

G A T

A A E

E E

2 I/

S H

/ M /

S S S

S S

S VV

/

I

/

I

/ / / /

/

I

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EI E

E S E S E L

L L

L E S L

L RD D

D D D D D D D D D

D D D

D N

ED O

A N

A B C A B C D A B A B C D A B C D S

0 C

3 3

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8 8 8 8 9

1 E

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7 s

DRESDEN 2 TOPIC NO.

REVIEW STATUS REMARKS TOPIC NO.

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

DL/SEPB 7

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

DL/SEPB 7

NRC to CECO 08/I7/78 V-13 X

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

X NRC to Ceco P.

37/81 VI-1 DE/CEB 3

CECO to NRC 07/27/79 VI-7 F.

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

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

NRC 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 NRC to Ceco 11/16/79 VI-14 A.

DL/SEPB 7

NRC to Ceco 07/03/81 VI-2 D.

DSI/CSB 3

CECO to NRC 11/20/80 VI-10 B.

DL/SEPB 7(Sys)

NRC to CECO 06/20/81 DL/SEPB 7(Elec) HRC to CECO 07/07/81 VI-3 DSI/CSB 3

CECO to NRC 11/20/80 VII-1 A DL/SEPB 5

NRC to CECO 08/05/81 VI-4 DSI/CSB 4a(Sys)

DL/SEPB 1(EInc)

VII-1 B.

DL/SEPB 7

NRC to Ceco 08/17/78 VI-5 X

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

CECO to NRC 03/18/81 VI-6 DSI/CSB G

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

NRC to Ceco 04/24/81 DL/SEPB 7(Elec) HRC to CECO 07/07/88 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 05/07/81 VII-5 X

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

DL/SEPB 7

CECO to NRC 06/23/81 VII-6 DL/SEPB 7

hRC to CECO 08/26/81 VI-7 A. 4.

DSI/RSB G

NRC to CECO 05/07/81 VII-7 T

NRC to CECO 11/16/79 VI-7 B.

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

DSI/RSB G

NRC to Ceco 05/07/81 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 6

CECO to NRC 06/12/81 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 6

CECO to NRC 06/25/81 (2-9) t

DRESDEN 2

TOPIC NO.

REVIEW STATUS REMARKS TOPIC NG.

REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 3

CECO to NRC 06/02/80 XV-10 X

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

NRC to CECO 05/07/81 XV-11 DSI/CPB 4b CECO to NRC 10/15/81 IX-3 DL/SEPB 5

NRC to Ceco 06/30/81 XV-12 X

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

HRC to CECO 11/16/79 XV-13 DSI/SPB 4b(Sys) CECO to NRC 10/ 15/81 DSI/AEB 4b(Soses) CECO to NRC 10/15/81 IX-5 DL/SEPB 0

XV-14 DSI/RSB 4b CECO to NRC 10/15/81 IX-6 G

NRC to CECO 05/07/81 XV-15 DSI/RSB 4b CECO to HRC 10/15/81 X

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

Ceco to NRC 10/15/81 XI-1 DSI/ETSB G

HRC to Ceco 05/07/81 XV-17 X

NRC to Ceco 11/16/79 XI-2 DSI/ETSB G

NRC to Ceco 05/07/81 XV-18 DSI/RSB CECO to NRC

'0/15/81 XIII-1 X

NRC to CECO 05/07/81 DSI/AEB 4b(Doses) CECO to NRC 10/15/81 XIII-2 DL/SSPB 7

HRC to CECO 03/11/81 XV-11 DSI/RSB 4b(Sys) CECO to NRC 10/15/81 DSI/AEB Ab(DOSES) CECO to NRC 10/15/81 XV-1 DSI/RSB 4b CECO to NRC 10/15/81 XV-20 DSI/AEB 4b CECO to NRC 04/27/81 XV-2 X

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

NRC to Ceco 05/07/81 XV-3 DSI/RSB 4b CECO to NRC 10/15/81 XV-22 X

NRC to CECO 05/07/81 XV-4 DSI/RSB Gb CECO to NRC 10/1$/81 XV-23 X

N9, to CECO 05/07/81 XV-5 DSI/RSB 4b CECO to NRC 10/15/81 XV-24 X

HRC to Ceco 05/07/81 XV-6 X

HRC to CECO 11/16/79 XVI X

NRC to Ceco 11/05/80 XV-7 DSI/RSB 4b CECO to NRC 10/15/81 XVII DL 7

NRC to CECO 08/17/78 XV-8 RSI/CPB 4b CECO to NRC 10/15/81 XV-9 DSI/RSB 4b CECO to NRC 10/15/81

+

e (2-10)

GINNA FACILITY-GINNA TOPIC NO.

REVIEW STATUS REMARKS DIV/BR LICENSEE: ROCHESTER GAS 2 ELECTRIC II-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

NRC to RGE 07/21/81 DOCKET NO.

05000244 II-1 C.

DE/SAB 7

NRC to RGE 09/29/81 POWER CAPACITY: 1520(THERMAL) 0490(ELECTRICAL)

II-2 A.

DSI/AE3 6

REG to NRC 01/19/81 OL NUMBER: DPR-18 II-2 B.

X NRC to RGE 05/07/81 N.S.S.S.: WEST.

II-2 C.

DSI/AEB 7

NRC to RGE 09/24/81 A/E FIRM: GIL.

II-2 D.

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

DE/HGES 6

RGE to NRC 08/18/81 OPERATING REACTORS BRANCH CHIEF:

D. CRUTCHFIELD II-3 B.

DE/HGEB 6

RGE to NRC 08/18/81 DPERATING REACTORS PROJECT MANAGER:

R.

$NAIDER II-3 B.

1 DE/HGEB 6

RGE to NRC 08/18/81 2NTEGRATED ASSCSSMENT PROJECT MANAGER:

A. WANG,g,,

II-3 C.

DE/HGEB 7

RGE to NRC 04/10/81 II-4 DE/GSB 7

NRC to RGE 07/09/81 KEY FOR STATUS COD.E1 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.

DE/GSB 8

NRC to RGE 07/09/81 FROM REVIEW BRANCH X - DELETED II-4 C.

DE/GSB 7

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

DE/AGEB Gb RGE to NRC 06/30/81 STARTED S - DRAFT SE SENT II-4 E.

X

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

DE/HGEB 4b RGE to NRC 06/30/81 6 - SE RESPONSE RECEIVED 3 - QUESTIONS SENT BY NRC III-1 DL/SEPB 3(Sys)

RGE to NRC 08/14/81 TO UTILITY DL/SEPB 6(Elec) RGE to NRC 01/23/81 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 4a RECEIVED BY NRC M - DATA FOR NEXT MONTH (NOVEMBER) b (2-11)

GINNA TOPIC NO.

REVIEW STATUS REMARKS TOPIC NO.

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

DL/SEB 6

RGE to NRC 08/18/81 111-10 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/HGEB Gb RGE to NRC 10/12/81 III-11 X

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

DSI/AEB 5

NRC to RGE 09/28/81 III-12 X

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

DE/MTEB G

NRC to RGE 05/07/81 IV-1 A.

DL/SEPB 7

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

DSI/AS3 0

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 6

RGE to NRC 08/05/81 V-1 DE/MTEB G

NRC to RGE 05/07/81

)

III-5 B.

DL/SEPB 7

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

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

RGE to NRC 02/06/81 V-3 X

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

DL/SEP8 G

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

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

DL/SEPB 3

RGE to NRC 11/14/79 V-5 DL/SEPB 5

NRC to RGE 07/22/81 III-7 C.

DE/SEB 7

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

NRC to RGE 03/05/30 III-7 D.

DE/SEB 7

NR" to RGE 05/08/80 V-7 DSI/ASB G

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

DSI G

HRC to RGE 05/07/81 V-8 X

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

X NRC to RGE 10/01/80 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/SEPE 7

NRC to RGE 07/22/81 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 7CElec) NRC to RGE 04/24/81 (2-12)

8 1

1 1

9 0

9 1

8 1

11 1

1 1

9 1

1 1

7 8 8 8 7

8 7

8 88 8 8 8 7

8 8 3 8 8

/ / / / / / / / / / // / / / / / / / / /

7 7

4 7

6 5

6 0

7 3

94 7

7 4

6 6

4 1

9 8

1 0

2 0

1 1

1 3

1 2 22 0

0 2

1 2 2 3 0

0

/ / / / / / / / / / // / / / / / / / / /

8 5 6

5 1

2 1

7 8

0 96 5

5 6

1 3

6 7

6 0

0 0

1 1

1 0

0 1

00 0

0 0

1 0

0 0

0 1

E E E E E E E E E C EE E E E E E E E E C G G G G G G G G G R GG G G G G G G G G R R R R R R R R R R N RR R R R R R R R R N S

K o o o o o o o o o o oo o o o o o o o o o R

t t

tt t

t t

A M

C C C C C C C C C E CC C C C C C C C C E E

R R R R R R R

R R G RR R R R

R R R R

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H N N N N N N N N R NN N N N N H N N N 3

)

) c se S

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((

A 7

X 7

X X 7

X 7

7 6

77 X X 7

X 7

7 7 7 7

T S

B B

B B B B

BB B

B B B

B B WR P

P P

P PP P

S P P P P

EB E

E E

E E E EE E

P E E E

E I/

S S

S S S S

SS S

/

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L L

L LL L

S L

L L

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D D

D D D DD D

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2 3

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7 7 7 8

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V V V V V

V V V V V V V V V V V V V V V

)

3 1

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9 1

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1 11 1

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8 8 8 7

88 8 8 8 7

8 8 88 8 8 8 7

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// / / / / / / // / / / /

6 7

7 7

6 72 7

6 0

7 5

7 89 0

4 0

6 1

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1 73 5 5 2 8 2 5 89 2

7 2

1 1

0 0

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0 0

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0 00 0

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1 E E E E E EC E E E E E E CE E C E E G G G G G GR G G G G G G RG G R

G G R R R R 2 RN R R P.

R R R NR R N R R S

K o o o o o oo o o o o o o oo o o o o R

t t

t tt t

t t

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M C C C C C CE C C C C C C EC C E C C E

R R

R RG R

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A X X X X X 4

4 56 X 7 7

7 7 X 77 7

3 7

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B B BB B B B B B

B B B WR B

S S SP S P P P SB P P P

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C C CE C E E E RE E E E

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L L

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D D DD D D D D DD D D D A

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IGillipill 4

1 TOPIC NO.

REVIEW-STATUS' REMARKS

. TOPIC NO.

. REVIEW STATUS-REMARKS

-DIV/BR-DIV/5R

~

IX-1 DSI/ASB 3

RGE to NRC 06/09/81 XV-10

.DSI/RS3.

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

NRC to RGE 05/07/81 XV X NRC.'to RGE

'10/01/80

'IX 'DL/SEPB 7*,

NRC to RGE 11/03/81 XV DSI/CPB 7(Sys).. NRC to RGE_

109/04/81 DSI/AEB 5(Dosos) NRC to'RGE

'09/24/81

' IX-4 '

DSI/RSB 7

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

NRC to RGE 11/16/79 IX-5 DL/SEPB Gau 09/04/81' XV-14 DSI/R$B-7

.NRC to RGE IX-6 G

NRC to RGE 05/07/81 XV-15 DSI/RSB-7 NRC to RGE

.09/04/81

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

NRC to RGE 0 9.^24 /8 0.

XI-1' ESI/ETSBD G'

NRC to RGE 05/07/81 DSI/RSB 7(Sys)

NRC to.RGE 09/04/81 XV-17

'XI-2'

'DSI/ETSB G

NRC to RGE 05/07/81 DSI/AEB 5(Doses)'NRC to RGE 09/24/81 XIII-t-X' NRC to RGE 05/07/81 XV-18 X

NRC to RGE 03/11/80 XIII-2 DL/SEPB 7

NRC to RGE 03/26/81 XV-19 DSI/RSB 7(Sys)

NRC'to RGE 10/02/81 DSI/AEB 5(Doses) HRC to RGE 09/29/81r

.XV-1 DSI/RSB 7

HRC to RGE 09/04/81 XV-2c DSI/AEB 5

HRC to RGE 09/29/81~

'XV-2' DSI/RSB 7sSys)

HRC to RGE 09/04/81

.DSI/AEB 5(Doses) NRC to RGE 09/24/81 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 DSI/RSB 7

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

HRC-to RGE 05/07/81

-XV-6 DSI/RSB 7

NRC to RGE 0y/04/81 XVI X

NRC to RGE 11/05/80

'XV-7' DSI/RSB 7

NRC to RGE 09/04/81 XVII DL 7

NRC to RGE 08/17/78 l

XV-8 DSI/CPB 7

NRC to RGE 09/04/81

.XV-9 DSI/RSB 7

RGE to NRC 10/16/81 (2-14) i V

HADDAM NECK FACILITY-HADDAM NECK TOPIC NO.

REVIEW STATUS REMARKS DIV/BR LICENSEE: CONNECTICUT YANKEE ATCMIC POWER 11-1 A.

DE/SAB 4b CYAPCo to hRC 04/27/81 REGION / LOCATION: 13 MILES EAST OF MERIDEN. CT.

II-1 B.

DE/SAB Gb CYAPCo to NRC 08/31/81 00CKET NO: 05000213 II-1 C.

DE/SAB 4b CYAPCo to NRC 06/30/81 POWER CAPACITY 8 1825(THERMAL) 0575(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 H.S.S.S.: WEST.

II-2 C.

DSI/AEB 7

CYAPCo to NRC 02/16/79 A/E FIRM: SIW II-2 D.

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

DE/HGEB 3

CYAPCo to NRC 08/23/81 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD II-3 B.

DE/HGEB 3

CYAPCo to NRC 08/23/81 OPERATING REACTORS PROJECT MANAGER: W. Pf.ULSON II-3 B.

1.

DE/HGEB 3

Site Visit INTEGRATED ASSESSMENT PROJECT MANAGER:

S.

BROWN II-3 C.

DE/HGEB 3

Site Visit II-4 DE/GSB 7

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

DE/GSB 7

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

DE/GSB 3

NUREG/CR1582 08/04/81 FRON REVIEW BRANCH X - DELETED II-4 C.

DE/GSB 7

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

DE/HGEB 4b CYAPCo to NRC 08/31/81 STARTED 5 - DRI.FT 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 4b CYAPCo to NRC 06/22/8i 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC III-1 DL/SEPB 3(Sys)

CYAPCo to NRC 09/28/79 TO UTILITY DL/SEPB 7(Elec) Part of VII-3 7 - TLPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 3

CYAPCo to NRC 09/07/79 RECEIVED BY NRC (2-15)

4 HADDAM NECK TOPIC NO.

REVIEW STATUS REMARKS TOPIC HO.

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

DE/SEB 4b CYAPCo to NRC 08/31/81 III-10 B.

DL/SLPB 6

CYAPCo to NRC 12/09/80 III-3 B.

DE/HGEB 0

III-10 C.

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

DE/HGEB 4b CYAPCo to NRC 08/31/81 III-11 X

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

DSI/ASB 4b CYAPCo to NRC 08/31/31 III-12 X

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

DE/MTEB G

NRC to CYAPCo 05/07/81 IV-1 A.

DL/SIFB 7

CYAPCo to NRC 06/25/79 III-4 C.

DSI/ASB 0

IV-2 DSI/;CSB Gb CYAPCo to NRC 06/30/81 III-4 D.

DE/SAB 4b CYAPCo to NRC 06/25/81 IV-3 X

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

DL/SEPB 3

CYAPCo to NRC 02/07/80 V-1 DE/MTEB G

NRC to CYAPCo 05/07/81 III-5 B.

DL/SEPB 4b CYAPCo to NRC 10/02/81 V-2 X

NRC to CYAPCo 04/16/79 III-6 DL/SEPB 3

CYAPCo to NRC 06/11/81 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 3

CYAPCo to NRC 09/07/79 V-5 DL/SEPB 6

CYAPCo to NRC 08/19/81 III-7 C.

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

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

DE/SEB 5

NRC to'CYAPCo 10/16/8 1 V-7 DSI/ASB

^

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

DSI G

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

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

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

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

DL/SEPB 6

CYAPCo to NRC 12/18/79 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 5

NRC to CYAPCo 09/09/81 III-9 X

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

DL/SEPB 7

NRC to CYAPCo 09/01/81 III-10 A.

DL/SEPB 7

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

DL/SEPB 5(Sys)

NRC to CYAPCo 09/09/81 DL/SEPB 7(EIcc) Part of VII-3 (2-16)

HADDAM NECK TOPIC NO.

REVIEW STATUS R EMARKS T O PIP, NO.

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

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

DL/SEPS 7

NRC to CYAPCo 09/87/78 I

V-13 X

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

X NRC to CYAPCo 05/07/81 VI-1 DE/CEB 3

CYAPCO to NRC 10/31/79 VI-7 F.

X NRC to CfAPCo 04/16/79 VI-2 A.

X NRC to CY.*FCo 05/07/81 VI-8 X

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

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

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

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

DL/SEPB 0

VI-2 D.

DSI/CSB 3

CYAPCo to NRC 04/27/81 VI-10 B.

X NRC to CYAPCo 04/16/79 VI-3 DSI/CSB 3

CYAPCo to NRC 04/27/81 VII-1 A.

DL/SEPB 3

CYAPCo to NRC 08/07/81 VI-4 DSI/CSB 0(Sys)

VII-1 B.

DL/SEPB 7

NRC to CYAPCo C8/17/78 DL/SEPB 7(Elec) NRC to CYAPCo 09/21/81 VII-2 DL/SEPB 3

CYAPCo to NRC 08/07/81 VI-5 X

NRC to CYAPCo 05/07/81 VII-3 DL/SEPB 5(Sys)

NRC to CYAPCo 09/09/81 VI-6 DSI/CSB G

NRC to CYAPCo 0S/07/81 DL/SEPB 7(Elec) NRC tr 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 0

WII-6 DL/SEPB 7

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

4.

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

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

DSI/RSB 0(Sys)

VIII-1 A.

DSI/PSB G

NRC to CYAPCo 05/07/81 DL/SEPB 5(Elec) NRC 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/E1 VIII-3 A.

DL/SEPB 7

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

1.

DL/SEPB 7

NRC to CYPACo 08/28/81 VIII-3 B.

DL/SEPB 7

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

DL/SEPB 7

NRC to CYAPCo 03/13/8i VIII-4 DL/SEPB 2

NRC to CYAPCo 06/20/81 VI-7 C. 3.

DL/SEPB 2

NRC to CYAPCo 06/26/81 (2-17)

HADDAM NECK TOPIC NO.

REVIEW STATUS REMARKS TOPIC HO.

REVIEW STATUS REMARKS DIV/BR DIV/BR IX-l DSI/ASB 4b CYAPCo to NRC 08/31/81 XV-10 DSI/RSB 4b CYAPCo to NRC 09/30/81 IX-2 X

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

NRC to CYAPCo 10/01/80 IX-3 DL/SEPB 2

XV-12 DSI/CPB Ab(Sys) CYAPCo to NRC 09/30/81 DSI/RSB 4b(Doses)CYAPCo to NRC 09/30/81 IX-4 DSI/RSB Gb CYAPCo to NRC 10/02/81 XV-13 X

NRC to CYAPCo 11/16/79 IX-5 DL/SEPB 0

XV-14 DSI/RSB 4b CYAPCo to NRC 09/30/81 IX-6 DE G

NRC to CYAPCo 05/07/81 XV-15 DSI/RSB 4b CYAPCo to NRC 09/30/A1 X

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

CYAPCo to NRC 09/28/81 XI-1 DSI/ETSB G

NRC to CYAPCo 05/07/81 XV-17 DSI/RSB 0(Sys)

XI-2 DSI/ETSB G

NRC to CYAPCo 05/07/81 DSI/AEB 0(Doses)

XIII-1 X

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

NRC to CYAPCo 10/01/80 XIII-2 DL/SSPB G

NRC to CYAfCo 05/07/81 XV-19 DSI/RSB 4b(Sys) CYAPCo to NRC 09/30/81 DSI/AEB 4b(Doses)CYAPCo to NRC 09/30/81 XV-1 DSI/RSB 4b CYAPCo to NRC 09/30/81 XV-20 DL/SEPB 7

NRC to CYAPCo 06/09/81 XV-2 DSI/RSB 4b(Sys) CYAPCo to NRC 09/30/81 DSI/AEB 4b(Dosos)CYAPCo to NRC 09/30/81 XV-21 X

NRC to CYAPCo 05/07/81 XV-3 DSI/RSB 4b CYAPCo to NRC 09/30/81 XV-22 X

NRC to CYAPCo 05/07/81 XV-4 DSI/R$B 4b CYAPCo to NRC 09/30/81 XV-23 X

NRC to CYAPCo 05/07/81 XV-5 DSI/RSB 4b CYAPCo to NRC 09/30/81 XV-24 X

NRC to CYAPCo 05/07/81 XV-6 DSI/RSB 4b CYAPCo to NRC 09/30/81 XVI X

NRC to CYAPCo 11/05/80 XV-7 DSI/RSB 4b CYAPCo to NRC 09/30/81 XVII DL 7

NRC to CYAPCo 18/17/78 XV-8 DSI/CPB

'L CYAPCo to NRC 09/30/81 XV-9 DSI/RSS 4b CYAPCo to NRC 09/30/81 i

(2-18) l f

LACROSSE FACILITY: LACROSSE TOPIC NO.

REVIEW STATUS REMARKS DIV/BR LICENSEE: DAIRLAND POWER II-l A.

DE/SAB 4b DPC to NRC 06/23/81 REGION / LOCATION: 19 MILES SOUTH OF LACROSSE, WISC.

11-1 B.

DE/SAB 4b DPC to NRC 06/16/81 DOCKET NO.

05000409 II-1 C.

DE/SAB Gb DPC to NRC 07/15/81 POWER CAPACITY: Ol65(THERMAL) 0050(ELECTRICAL)

II-2 A.

DSI/AEB 5

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

X NRC to DPC 05/07/81 H.S.S.S.: AC.

II-2 C.

DSI/AEB 0

A/E FIRM: SSL II-2 D.

X NRC to DPC 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL 11-3 A.

DE/HGEB Gb DPC to NRC 06/1S/81 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD II-3 B.

DE/HGEB 2

NRC to DPC 07/10/81 OPERATING REACTORS PROJECT MANAGER:

R. CARUSO II-3 6.

1.

DE/HGEB D

INTEGRATED ASSESSMENT PROJECT MANAGER:

T. MICHAELS f[7q II-3 C.

DE/HGEB 4b DPC to NRC 06/26/81 II-4 DE/GSB 7

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

DE/GSB 7

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

DE/GSB 3

FROM REVIEW BRANCH X - DELETED II-4 C.

DE/GSB 7

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

DE/HGEB 3

Site Visit 07/10/79 STARTED 5 - DRAFT SE SENT II-4 E.

DE/HGEB 0

1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.

DE/HGEB 2

6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY HRC III-1 DL/SEPB 3(Sys)

DPC to NRC 08/06/81 TO UTILITY DL/SEPB 0(Elec) 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 4b DPC to NRC 08/06/81 RECEIVED BY NRC (2-19)

LACROSSE TOPIC NO.

REVIEW STATUS REMARKS TOPIC NO.

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

DE/SEB 2

NRC to CPC 03/09/79 III-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/NGEB 0

III-11 X

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

DSI/ASB 0

III-12 X

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

DE/MTEB 0

IV-1 A.

DL/SEPB 7

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

DSI/ASB 0

IV-2 DSI/ICSB 2

NRC to DPC 12/15/80 III-4 D.

DEeSAB 4b DPC to NRC 09/15/81 IV-3 X

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

DL/SEPB 2

HRC to DPC 01/04/80 V-1 DE/MTEB G

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

DL/SEPB Gb DPC to NRC 06/29/81 V-2 X

NRC to DPC 10/29/79 III-6 DL/SEPB 3

DPC to NRC 06/12/81 V-3 X

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

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

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

DL/SEPB 2

HRC to DPC 08/09/79 V-5 DL/SEPB 6 3 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/ SED 4b DPC to NRC 06/29/81 V-7 X

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

DSI G

NRC to DPC 05/07/81 V-8 X

NRC to DPC 05/07/81 Ill-8 2.

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

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

DL/SEPB 7

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

7 NRC to DPC 01/07/81 III-8 D.

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

DL/SEPB 5

NRC to DPC 12/22/80 III-9 X

NRC to DPC 05/07/81 V-It A.

DL/SEPB 7

NRC to DPC 12/22/80 III-10 A.

DL/SEPB 7

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

DLe5EPB 5(Sys)

NRC to DPC 12/22/80 DL/SEf5 0(Elec)

(2-20)

LACROSSE TOPIC NO.

REVIEW STATUS REMARKS TOPIC NO.

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

DL/SEPB 7

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

DL/SEPB 7

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

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

X NRC to DPC 05/07/81 VI-1 DE/CEB 3

DPC to NRC 08/23/79 VI-7 R.

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

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

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

X NRC 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 2

NRC to DPC 07/21/81 VI-2 D.

DSleCSB 3

DPC to NRC 04/26/79 VI-10 B.

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

DPC to NRC 04/26/79 VII-1 A.

DL/SEPB 2

NRC to DPC 10/06/81 VI-4 DSI/CSB 3(Sys)

DPC to NRC 08/17/81 VII-I B.

DL/SEPB 7

NRC to DPC 08/17/78 DL/SEPB 6(Elec) DPC to NRC 08/26/81 VII-2 DL/SEPB 2

NRC to DPC 10/06/81 VI-5 X

HRC to DPC 05/07/81 VII-3 DL/SEPB 5(Sys)

N1C to DPC 12/22/80 VI-6 DSI/CSB G

NRC to DPC 05/07/81 DL/SEPB 3(Elec)

VI-7 A.

1 X

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

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

2.

X NRC to DPC 0 5.~ 0 7 /81 VII-5 X

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

3.

DL/SEPB 0

VII-6 DL/SEPB 7

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

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

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

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

DSI/PSB G

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

DL/SEPB 7

NRC to DPC 03/13/81 VIII-2 DL/SEPB 6

DPC to NRC 11/20/80 VI-7 C.

1.

DL/SEPB 7

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

DL/SEPB 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

NRC 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 NO.

REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 0

XV-10 X

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

NRC to DPC 05/07/81 XV-11 DSI/CPB 0

IX-3 DL/SEPB 2

XV-12 X

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

NRC to DPC 10/29/79 XV-13 DSI/CPB 0(Doses)

DSI/AEB 0(Sys)

IX-5 DL/SEPB 0

XV-14 DSI/RSB Gb DPC to NRC 08/25/81 IX-6 DE G

NRC to DPC 05/07/81 XV-15 DSI/RSB 7

NRC to DPC 09/21/81 X

X NRC to Dr; 05/07/81 XV-16 DSI/AEB D

XI-1 DSI/ETSB G

NRC to DPC 05/07/81 XV-17 X

NRC to CPC 10/29/79 XI-2 DSI/ETSB G

NRC to DPC 05/07/81 XV-18 DSI/AEB 0

XIII-1 X

NRC to DPC 05/07/81 XV-19 DSI/AEB 0(Doses)

XIII-2 DL/SSPB 7

NRC to DPC 03/11/81 DSI/RSB 0(Sys)

XV-1 DSI/RSB 0

XV-20 DSI/AEB 0

XV-2 X

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

NRC to DPC 05/07/81 XV-3 DSI/RSB 4b DPC to NRC 06/26/81 XV-22 X

NRC to DPC 05/07/81 XV-4 DSI/R$B 4b DPC to NRC 06/26/81 XV-23 X

NRC to DPC 05/07/81 XV-5 DSI/RSB 0

XV-24 X

NRC to DPC 05/07/81 nV-6 X

NRC to DPC 10/29/79 XVI X

NRC to DPC 11/05/80 XV-7 DSI/RSB 0

XVII DL 7

NRC to DPC 08/17/78 XV-8 DSI/CPB 0

XV-9 DSI/RSB 4b DPC to NRC 08/25/81 (2-22)

MILLSTONE 1 FACILITY: MILLSTONE 1 TOPIC NO.

REV:EW STATUS REMARKS DIV/BR LICENSEE: NORTHEAST NUCLEAR ENERGY 11-1 A.

DE/SAB 7

NRC to NU 07/31/81 REGION / LOCATION: 5 MILES SOUIH WEST OF NEW LONDON, CONN.

II-1 B.

DE/SAB 4b NU to NRC 05/19/81 DOCKET NO.*

05000245 II-1 C.

DE/SAB 4b NU to NRC 04/29/81 POWER CAPACITY: 2011(THERMAL) 0660(ELECTRICAL)

II-2 A.

DSI/AEB 7

NRC to NU 03/30/81 OL NUMBER: DPR-21 II-2 B.

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

DSI/AEB 7

NRC to NU 09/29/81 II-2 D.

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

DE/HGEB 4b NU to NRC 06/25/81 OPERATING REACTORS BRANCH CHIEF:

D.

CRUTCHFIELD II-3 B.

DE/HGEB 4b NL' to NRC 06/26/81 OPERATING REACTORS PROJECT MANAGER: J. SHEA II-3 B.

1.

DE/HGEB 4b NU to NRC 06/25/81 PERSINKO]Cl\\

II-3 C.

DE<HGEB 4b NU to NRC 04/28/81 INTEGRATED ASSESSMENT PS0 JECT MANAGER:

D.

II-4 DE/GSB 7

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

DE/GSB 3

NUREG/CR1582 08/00/80 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 4b HU to NRC 08/31/81 STARTED 5 - DRAFT SE SENT II-4 E.

X NRC to NU 11/16/79 1 - QUESTIONS RECEIVED TO UTILITY FR0il REVIEW BRANCH II-4 F.

DE/HGEB 4b NU to NRC 04/28/81 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC III-1 DL/SEPB 2(Elec) HRC to NU 06/09/81 TO UTILITY DL/SEPB 3(Sys)

NU to NRC 08/20/88 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 3

NU to NRC 08/29/79 RECEIVED BY NRC (2-23)

MILLSTONE 1 TOPIC NO.

REVIEW STATUS REMARKS TOPIC NO.

REVIEW STATUS RE"*RKS DIV/BR DIV/BR III-3 A.

DE/SEE 5

NRC to NU 05/11/81 111-10 B.

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

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

DL/SEPB 7

HU to NRC 08/29/79 III-5 C.

DE/HGEB 4b NU to NRC 08/31/81 III-11 X

NRC to NU 05/01/81 III-4 A.

DSI/ASB Gb NU to NRC 08/31/81 III-12 X

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

DE/MTEB 4b NU to NRC 08/31/81 IV-1 A.

DL/SEPB 7

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

DSI/ASB 3

NU to NRC 12/05/80 IV-2 DSI/ICSB 4b NU to NRC 10/28/81 III-4 D.

LE/SAB 4b NU to NRC 04/29/81 IV-3 DE/MTEB G

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

DL/SEPB 3

Nu to NRC 11/08/79 V-1 DE/MTEB G

NRC to NU 05/07/81 III-5 B.

DL/SEPB 1

V-2 X

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

HRC to NU 05/28/81 V-3 X

NRC to NU 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 3

HU to NRC 08/29/79 V-5 DL/SEPB 7

NRC to NU 08/28/81 III-7 C.

X NRC to NU 11/16.*79 V-6 DL/SEPB 7

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

DE/SEB 7

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

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

DSI G

NRC to NU 05/07/81 V-8 X

NRC to NU 05/07/81 III-8 3.

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

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

DL/SEPB 6

NU to NRC 01/31/80 V-10 A.

DL/SEPB 7

NU to NRC 03/05/79 III-8 D.

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

DL/SEPA 7

NU to NRC 07/22/81 III-9 X

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

DL/SEPB NRC to NU 07/08/81 III-10 A.

DL/SEPB 7

NRC to NU 06/28/81 V-11 B.

DL/SEPB 7(Sys)

HU to NRC 07/22/81 DL/SEPB 0(Elec)

(2-24)

MILLSTONE 1 TOPIC-NO.

REVIEW STATUS REMARKS TDPIC NO.

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

DL/SLPB 7

NRC to NU 12/17/79 VI-? 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 PE/CEB 4b NU to NRC 09'30/81 VI-7 F.

X NRC to NU 11/16/79 VI-2 A.

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

NRC to NU 05/07/81 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 NU 11/16/79 VI-10 A.

DL/SEPB 7

NRC to NU 10/08/81 VI-2 D.

ESI/CSB 3

NU to NRC 06/09/81 VI-10 B.

DL/SEPB 7(Sys)

NU to NRC 08/05/81 DL/SEPB 7(Elec)

VI-3 DSI/CSB 3

NU to NRC 06/09/81 VII-1 A.

DL/SEPB 7

NRC to NU 07/23/81 VI-4 DSI/CSB 0(Sys)

DL/SEPS 6(Elec) NU to NRC 08/12/81 VII-1 B.

DL/SEPB 7

NRC to NU 08/17/78 VI-5 X

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

NRC to NU 08/28/81 VI-6 DSI/ CSS G

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

NU to NRC 07/22/81 DL/SEPB 2(Elec) NRC to NU 06/09/81 VI-7 A.

1.

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

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

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

NRC 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/RSB G

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

NRC to NU 11/16/79 VI-7 B.

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

DSI/RSB G

NRC to NU 05/07/81 VI-7 C.

DL/SEPB 7

NRC to NU 03/29/81 VIII-2 DL/SEPB 7

NRC to NU 09/30/81 VI-7 C.

1.

DL/SEPB 7

NRC to NU 09/11/81 VIII-3 A.

DL/SEPB 7

NRC to NU 08/26/81 VI-7 C. 2.

DL/SEPB 7

NRC to NU 03/25/81 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

NRC to NU 07/07/81 (2-25)

MILLSTONE 1 TOPIC NO.

REV'EW STATUS REMARKS TOPIC NO.

REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 4b NU to NRC 08/31/81 XV-10 X

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

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

NRC to NU 10/14/81 IX-3 DL/SLPB 2

XV-12 X

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

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

NU to NRC 09/09/81 DSI/AEB Ga(Doses)

IX-5 DL/SEPB 0

XV-14 DSI/RSB 7

NRC to NU 09/18/81 IX-6 DSI DE NRC to NU 05/07/81 XV-15 DSI/RSB 7

NRC to NU 10/28/81 X

X NRC to NU 05/L1/81 XV-16 DSI/AEB 4a XI-1 DSI/ETSB G

NRC to NU 05/07/81 XV-17 X

NRC to NU 11/16/79 XI-2 DSI/ETSh G

NRC to NU 05/07'81 XV-18 DSI/AEB 4a(Doses)

XIII-1 X

NRC to NU L5/07/81 XV-19 DS!.*RSB 7(Sys)

NRC to NU 08/26/81 XIII-2 DL/SSPB G

NRC to NU 05/07/81 DSI/tEB 4a(Doses)

XV-1 DSI/RSB 4b MU to NRC 06/30/81 XV-20 DSI/AEB Ga XV-2 X

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

HRC to NU 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 NU 05/07/81 XV-5 DSI/RSB 4b NU to NRC 06/30/81 XV-24 X

NRC to NU 05/07/81 XV-6 X

NRC So NU 11/16/79 XVI X

hRC to NU 11/15/80 XV-7 DSI/R$B 4b NU to KRC 06/30/81 XVII DL 7

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

NRC to NU 08."26/81 XV-9 DSI/RSB 4b NU to NRC 06/30/31 (2-26)

p..

0YSTER CREEK FACILITY: OYSTER CREEK 1 TOPIC NO.

REdIEW STATUS REMARKS DIV/BR LICENSEE: JERSEY CENTRAL POWER 8 LIGHT II-1 A.

DE/SAB 4b JCPL to NRC 05/07/81 REGICN/ LOCATION: 9 MILES SOUTH OF TDMS RIVER, NJ.

II-1 B.

DE/SAB 4b JCPL to NRC 05/07/81 DOCKET NO.? 05000219 II-1 C.

DE/SAB 4b JCPL to NRC 05/07/81 PCMER CAPACITY: 1930(THERMA () 0650(ELECTRICAL)

II-2 A.

DSI/AEB 5

NRC to JCPL 12/17/80 OL NUMBER: DPR-16 II-2 B.

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

DSI/AEB 0

II-2 D.

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

DE/HGEB 4b JCPL to NRC 05/07/81 OPERATING REACTORS BRANCH CHIEF:

D.

CRUTCHFIELD II-5 B.

DE/H3EB 4b JCPL to NRC G5/07/81 OPERATING REACTORS PROJECT MANAGER:

J.

LOMBARDO II-3 B.

1.

DE/HGEB 4b JCPL to NRC 05/07/81

/

INTEGRATED ASSESSMENT PROJECT MANAGER: R. FELL #/$7j/

11-3 C.

DE/HGEB 4b JCPL to NRC 05/07/81 II-4 DE/GSB 7

NRC to JCPL 08/03/81 KEY FOR STATUS COD _F,,1 II-4 A.

DE/GSB 7

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

DE/GSB 5

NRC to GPU 08/03/81 FROM REVIEW 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 0

STARTED 5 - DRAFT SE SENT II-4 E.

X NRC to JCPL 11/16/79 1 - QUESTIONS RECEIVED TO UTILITY FR0f1 REVIEW BRANCH II-4 F.

DE/HGEB 0

6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC III-1 DL/SEPB 3(Sys)

NRC to JCPL 02/2t/79 TO UTILITY DL/SEPB 5(Elec) NRC to JCPL 07/09/81 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 4b JCPL to NRC 05/07/81 RECEIVED BY NRC (2-27)

OYSTER CREEK TOPIC NO.

REVIEW STATUS REMARKS TOPIC NO.

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

.DE/SEB Ab JCPL to NRC 05/07/81 III-10 B.

X NRC to JCPL 11/16/19 III-3 B.

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

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

DE/HGEB D

III-11 X

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

DSI/ASB 0

III-12 X

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

DE/MTEB 0

IV-1 A.

DL/SEPB 7

NRC to JCPL 05/30/79 III-4 C.

DSI/ASB 2

NRC to JCPL 01/19/81 IV-2 DSI/ICSB 2

NRC to JCPL 12/15/80 III-4 D.

DE/SAB Gb JCPL to NRC 05/07/81 IV-3 X

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

DL/SEPB 5

NRC to JCPL 06/10/81 V-1 DE/MTEB G

NRC to JCPL 05/07/81 III-5 B.

DL/SEPB 6

JCPL to NRC 10/06/81 V-2 X

NRC to JCPL 11/16/79 III-6 DL/SEPB 6

JCPL to NRC 06/15/81 V-3 X

NRC 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 4a V-5 DL/SEPB 5

NRC to JCPL 03/16/81 III-7 C.

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

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

DE/SEB 3

JCPL to NRC 12/07/79 V-7 X

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

DSI G

HRC to JCPL 05/07/81 V-8 X

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

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

DL/SEPB 7

NRC to JCPL 09/25/80 III-9 X

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

DL/SEPB 7

NRC to JCPI 07/08/81 III-10 A.

DL/SEPB 7

NRC to JCPL 06/29/81 V-11 E.

DL/SEPB 7(Sys)

HRC to JCPL 09/25/8C DL/SEPB 7(Elec) NRC to JCPL 07/09/81 (2-26)

~

7 y

OYSTER CREEK TOPIC NO.

REVIEW STATUS REMARKS TOPIC NO.

REVIEW STATUS REMARKS DIV/BR DIV/BR V

'.2 A.

DL/SEPB 5

NRC to JCPL 03/16/81 VI-7 D.

DL/SEPB 7

NRC 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 2

NRC to JCPL 06/06/79 VI-7 F.

X NRC to JCPL 11/16/79 VI-2 A.

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

NRC 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 2

VI-10 B.

X HRC to JCPL 11/16/79 VI-3 DSI/CS3 2

VII-t A.

DL/SEPB 7

NRC to JCPL 07/30/81 VI-4 DSI/CSB 4a(Sys)

VII-1 B.

DL/SEPB 7

NRC to JCPL 08/17/78 DL/SEPB 5(Elec) NRC to JCPL 08/05/81 VII-2 DL/SEPB 6

JCPL to NRC 08/17/81 VI-5 X

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

NRC to JCPL 09/25/80

'VI-6 DSI/CSB G

NRC to JCPL 05/07/81 DL/SEPB 7(Elec) NRC to JCPL 07/09/81 VI-7 A.

1.

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

HRC to JCPL 05/07/81 VI-7 A. 2.

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

NRC 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 G

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

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

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

DSI/PSB G

NRC to JCPL 05/07/81 VI-7 C.

DL/SEPB 7

NRC to JCPL 03/13/81 VIII-2 DL/SEPB 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

NRC 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 06/29/81 VI-7 C. 3.

X NRC to JCPL 11/16/79 VIII-4 DL/SEPB 2

HRC to JCPL 03/26/80 (2-29)

OYSTER CREEK TOPIC NO.

REVIEW STATUS REMARKS TOPIC NO.

REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 3

JCPL to NRC 12/14/79 XV-10 X

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

NRC to JCPL 05/07/81 XV-11 DSI/CPB 5

NRC to JCPL 04/09/81 IX-3 DSI/ASB 6

JCPL to NRC 10/01/81 XV-12 X

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

HRC to JCPL 05/07/81 XV-13 DSI/AEB 4a(Doses)

DSI/CPB 5(Sys)

NRC to JCPL 04/09/81 IX-5 DL/SEPB 0

XV-14 DSI/R$B 7

NRC to JCPL 07/16/81 IX-6 DE G

NRC to JCPL 05/07/81 XV-15 DSI/RSB 4b JCPL to NRC 05/07/81 X

X NRC to JCPL 05/07/81

~

DSI/ETSB G

NRC to JCPL 05/07/81 XI-1 XV-17 X

NRC to JCPL 11/16/79 XI-2 DSI/ETSB G

NRC to JCPL 05/07/81 XV-18 DSI/AEB 4a XIII-1 X

NRC to JCPL 05/07/81 XV-19 DSI/AEB Gb(Doses)JCPL to NRC 05/07/81 XIII-2 Dl/SSPB 7

NRC to JCPL 09/25/30 DSI/RSB 7(Sys)

NRC to JCPL 09/04/81 XV-1 DSI/RSB Gb JCPL to NRC 05/07/81 XV-20 DSI/RSB 4b JCPL to NRC 05/07/81 XV-2 X

NRC to JCPL

'1/16/79 XV-21 X

NRC to JCPL 05/07/81 XV-3 DSI/R3B 7

NRC to JCPL 07/16/31 XV-22 X

NRC to JCPL 05/07/81 XV-4 DSI/EN 7

NPC to JCPL 07/16/81 XV-23 X

NRC to JCPL 0 5/ tt7/81 XV-5 DSI/RSB 4b JCPL to NRC 05/07/81 XV-24 X

NRC to JCPL 05/07/81 XV-6 X

NRC to'JCPL 11/16/79 XVI X

NRC to JCPL 11/05/80 XV-7 DSI/RSB 4b.

JCPL to NRC 08/25/81 XVII DL 7

NRC to JCPL 08/17/78 XV-8 DSI/CPB 5'

NRC to'JCPL 03/31/81 XV-9 DSI/RSB 4b JCPL to NRC 05/07/81 d

4 (2-30)

~

"PAllSADES I

FACILITY: PALISADES TOPIC NO.

REVIEW STATUS REMARKS DIV/BR LICENSEE: CONSUMERS POWER 11-1 A.

DL/SEPB 7

CPCo to nRC 12/28/79 REGION / LOCATION: 5 MILES SOUTH OF SOUTH HAVEN. MI.

11-1 B.

DL/SEPB 7

CPCo to NRC 12/28/79 DOCKET NO: 05000253 II-1 C.

DL/SEPB 7

CPCo to NRC 05/13/81 POWER CAPACITY: 2530(THERMAL) 0508(ELECTRICAL)

Il-2 A.

DSI/AEB 7

NRC to CPCo 05/30/81 OL NUMBER: DPR-20 II-2 B.

X NRC to CPCo-05/07/81 H.S.S.S.*

C-E II-2 C.

DSI/AEB 7

NRC to CPCo 04/23/81 A/E FIRM: BECH.

II-2 D.

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

DE/HGEB 6

CPCo to NRC 08/13/81 OPERATING REACTORS BRANCH CHIEF:

D. CRUTCHFIELD II-3 B.

DE/HGEB 6

CPCo to NRC 08/13/81 OPERATING REACTORS PROJECT MANAGER:

T. WAMBACH II-3 B.

1 DE/HGEB 6

CPCo to NRC 08/13/81 INTEGRATED ASSESSMENT PROJECT MANAGER: T. MICHAELS II-3 C.

DE/HGEB 6

CPCo to NRC 08/13/81 II-4 DE/GSB 7

CPCo to NRC 07/04/81 KEY FOR STATUS CODES II-4 A.

DE/GSB 7

NRC to CPCo 07/04/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.

DE/GSE 7

CPCo to NRC 07/22/81 FROM REVIEW BRANCH X - DELETED II-4 C.

DE/GSB 7

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

DE/HGEB 7

CPCo to NRC 06/01/81 STARTED S - DPAFT 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

CPCo to NRC 06/01/81 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC III-1 DL/SEPB 7(Elec) HRC to CPCo 11/12/80 TO UTILITY DL/SEPB 3(Sys)

CPCo to NRC 08/17/81 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE RECEIVED BY NRC (2-31)

p L

PAllSADES,

~

LTOPIC NO.'

REVIEW STATUS '

REMARKS

' TOPIC NO.

REVIEW, STATUS

~-REMARKS-DIV/DR-DIV/BR-

.III DL/SEPB

-7 NRC to CPCo 02/27/81 III-10 B.

DL/SEPB 6

CPCo to NRC.

-07/02/81-

III-3.A.

DE/SEB 7

NRC to CPCo 08/26/81

'III-10 C.

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

NRC to-CPCo 12/26/80

-III-11 X

'HRC to.CPCo 05/07/81 III-3 C.

DE/HGEB

-0 III-12

X NRC to CPCo

-05/07/81:

III-4'A.

DSI/AEB 5

NRC to'CPCo 08/28/8'1 IV-1 A.

DL/SEPB 7

.CPCo to NRC~

02/08/79' III-4 B.

'DE/MTEB G

NRC to CPCo 05/07/81

IV-2 DSI/ICSB 5

NRC to CPCo 10/16/81-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 DE/MTEB' G

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

DL/SEPB 4b CPCo to NRC 08/13/81 V-2 X

NRC to CPCo 11/16/79' III-5 B.

DL/SEPB 4b CPCo to NRC 08/25/81 V-3 X

NRC to CPCo 05/07/81 III-6 DL/SEPB 6

CPCo to NRC 07/13/81 V-4 X

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

DL/SEPB G Part NRC to CPCo 05/07/81 V-5 D L /',6 P B 6

CPCo to NRC 10/C7/81~

5 Bal NRC to CPCo 08/25/81 V-6 DL/SEPB 7

NRC to CPCo:

03/05/80 III-7 B.

DL/SEPB-3 CPCo to NRC 12/14/79 V-7 DSI/ASB 3

NRC to CPCo 05/07/81-I I *. -7 ' C.

DE/SEB 6

CPCo to NRC 07/21/81 V-8 X

HRC.to CPCo' 05/07/81-CPCo to NRC 08/17/81 III-7.D.

DE/SEB V-9 X

HRC to CPCo 11/16/79-

.III-8 A.

DSI NRC to CPCo 05/07/81 V-10 A.

DL/SEPB 7

NRC to'CPCo-09/26/81 III-8 B.

X NRC to CPCo 10/01/80 V-10 B.

.DL/SEPB 7

CPCo to NRC 10/27/81 III-8 C.

DL/MTEB 7

CPCo to NRC 12/28/79 V-11 A.

DL/SEPB 6

CPCo to NRC' 07/03/81 III-8'D.

X NRC to CPCo 05/07/81 V-11.B.

DL/SEPB 7(Sys)

CPCo to NRC 10/27/81

' III 'X NRC to CPCo' 05/07/81 DL/SEPB 7(Elec) HRC to CPCo 06/02/81 III-10 A.'

DL/SEPB 7-NRC to CPCo~

05/19/81-(2-32) a

ab.

l PALISADES t

' STATUS REMARKS.

DIV/ER

~ ~

. REMARKS' TOPIC HO.

' REVIEW

'TATUS' S

TOPIC.NO.

-REVIEW.

DIV/LR V-12 A.

X

.NRC to CPCo

.11/16/79-1 VI-7 D.

.DL/SEPB 7

NRC,to CPCo 08/17/78 V-13

-X

-MRC to CPCo 05/07/01 VI-7 E.

X NRC to CPCo 05/07/81

'VI DE/CEB 7

NRC to CPCo 08/03/81 VI-7 F.

DL/SEPB 7.

NRC to CPCo 06/30/81

'VI-2 A.

X NRC to CPCo 05/01/81 VI-8 X-NRC to CPCo' 05/07/81

-VI-2'B.

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

~N'RC to CPCo.

11/16/79 VI-2 C.

X NRC to CPCo 11/16/79 VI-10 4.

DL/SEPB 7

NRC to CPCo 06/19/21 LVI-2 D.

DSI/CSB 6

CPCo to NRC 07/09/81 VI-10 B.

X NRC'to CPCo

-11/16/79-

'V1-3 DSI/CSB 6

CPCo to NRC 07/09/81 VII-1 A.

DL/SEPB 7

NRC to CPCo-08/28/81 VI-4

-DL/SEP8 7(Elec) CPCo to NRC 08/18/81 VII-1 B.

DL/SEPB 7~

.NRC.to CPCo 08/17/78.'

DCI/CSB 6(Sys)

CPCo to NRC 08/10/81

~

.VII-2 DL/SEPB 7

NRC to CPCo 05/19/81

-VI X NRC to CPCo 05/07/81 VII-3 DL/SEPB.

7(Sys)

CPCo to NRC 10/27/81 VI-6 DSI/CSB G

NRC to CPCo 05/07/81

.DL/SEPB.

~7(Elec) CPCo to NRC 09/30/81 VI-7 A.

1 X

NRC 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 CPC-

'05/07/81

.VI-7 A.~3.

DL/SEPB 7

NRC to.CPCo 10/29/S1 VII-6 DL/SEPB 7

NRC to CP;o-05/19/81 4

VI-7 A.

4.

-X

.NRC to CPCo 05/07/81 VII X NRC to CPCo 11/16/79-VI-7 B.

DL/SEPB 7(Elec) HRC to-CPCo 05/19/81 VIII-1 A.

DSI/*SB G

NRC to CPCo-05/07/81 DSI/RSB 7(Sys)-

NRC to CPCo 06/30/81 VIII-2 DL/SEPB 7

NRC to CPCo 06/09/81 VI-7 C.

DL/SEPB 7

NRC to c'fo 02/20/8f VIII-3 A.

DL/SEPB 7

NRC to CPCo 05/22/81

'VI-7 C.11 DL/SEPB 7

NRC to CPCo 11/18/80 VIII-3 B.

DL/SEPB 7

NRC-to CPCo 08/05/81 VI-7 C. 2.

DL/SEPB 7

NRC to CPCo 02/20/81 WIII-4

.DL/SEPB 7.

NRC-to CPCo

-07/31/81 VI-7 C.

3.

X CPCo to NRC 12/12/71 (2-33) e-4

.y a r-1 tU l'JLlLllSJRilDil!!iL

^

REVIEU STATUS.

R EMARKS '-

TOPIC'NO.

, REVIEW STATUS REMARKS

-TOPIC N0;

..DIV/BR

)

DIV/BR-IX-1 DSI/ASB 3

CPCo to NRC 09/29/81 XV - DL/SEPB-7 NRC to CPCo.

07/17/81 IX-2 X.'

.NRC to CPCo 05/07/81 XV-It

X NRC:to!CPCo-10/01/80

' IX-3'

-DL/SEPB 7

NRCLto CPCo 09/06/81' XV-12 DL/SEPB 7(Doses) NRC'to CPCo!

.01/29/80:

- DL/SEPB

-7(Sys).

NRC'to CPCo 07/17/81

'IX-4 DSI/RSB-4b-CPCo to NRC 10/09/81 XV-13 X

HRC to'CPCor 11/16/79'-

-IX-5:

DL/SEPB 5'

NRC to CPCo 08/03/81 XV-14 DL/SEPB 7

.NRC to:CPCo 07/l7/81-IX-6 DE G-NRC to CPCo 05/07/81

'NRC to-CPCo-07/17/81-XV DL/SEPB 7-

^X'

.X

-NRC to CPCo 05/07/81 XV-16

. DL/SEPB.

7' NRC to CPCo 12/31/80 X'!- t DSI/ETSB G

NRC to,CPCo 05/07/81 XV-17 DL/SEPBl 7(Dosos) HRC'to'CPCo 01/29/80' XI-2 DSI/ETSB G

NRC to CPCo 05/07/81 DL/SEPB 7(Sys)

-NRC to CPCo-07/.17/81

'XIII-t X

NRC to CPCo 05/07/81 XV X NRCoto CPCo 10/01/80:

XIII DL/SSPB

.7

.NRC to CPCo 10/01/80 XV-19 DL/SEPB 7(Doses) HRC to CPCo -

'11/21/80; XV-1 DL/SEPB 7

NRC to CPCo 07/17/81 XV-20 DL/SEPB

'7-NRC to CPCo.

11/21/80

-XV-2 DL/SEPB 7(Doses)~NRC.to CPCo 05/18/31 DL/SEPB 7(Sys)

NRC to CPCo 07/17/81 XV-21 X

NRC to CPCo.-

05/07/81~

'iXV-3'

.DL/SEPB 7

NRC to CPCo 07/17/81 XV-22 X

'HRC to CPCo-05/07/31 XV-4 DL/SEF3' 7

NRC to CPCo 07/17/81

.XV-23 X

HRC to CPCo.

05/07/81 XV-5 DL/SEPB-7 NRC to CPCo 07/17/81 XV-24 X

NRC-to CPCo 05/07/81 XV-6 DL/SEPB

'7 NRC to CPCo 07/17/81 XVI X

NRC to CPCo 11/05/80' XV-7 DL/SEPB 7

NRC to CPCo

-07/17/81 XVII

. DL 7.

NRC to CPCo' 08/17/78 1

XV-8 DL/SEPB 7

NRC to'CPCo-07/17/81 XV-9

,DL/SEPB 7

.HRC to CPCo.

07/17/81 1

4 3

d (2-34) l

^

m

SAN ON0FRE FACILITY: SAN ONOFRE 1 TOPIC NO.

REVIEW STATUS REMARKS DIV/BR LICENSEE: SOUTHERN CALIFORNIA EDISON 11-1 A.

DL/SEPB 7

NRC to SCE 11/07/79 REGION / LOCATION: 5 MILES SOUTH OF SAN CLEMENTE, CA.

II-1 B.

DL/SEPB 7

HRC to SCE 11/07/79 DOCKET NO.'

05000206 II-1 C.

DE/SAB 3

SCE to NRC 05/07/79 POWER CAPACITY: 1347(THERMAL) 0430(ELECTRICAL)

II-2 A.

DSI/AEB 7

NRC to SCE 04/27/81 OL NUMBER: DPR-13 II-2 B.

X NRC to SCE 05/07/81 N.S.S.S.'

WEST.

II-2 C.

DSI/AEB 6

SCE to NRC 12/07/79 A/E FIRM: BECH.

II-2 D.

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

DE/HGEB 3

OPERATING REACTORS BRANCH CHIEF:

D. CRUTCHFIELD II-3 B.

DE/HGEB 3

OPERATING REACTORS PROJECT MANAGER: S.

NOWICKI II-3 B.

1 DE/HGEB 6

SCE to NRC 10/08/81

("27L9)\\

II-3 C.

DE/HGEB 4a INTEGRATED ASSESSMENT PROJECT MANAGER: E. MCKENHA II-4 DE/GSB 5

HRC to SCE 03/12/81 KEY FOR ST ATUS CODJ_S 11-4 A.

DE/GSB 5

NUREG-0712 12/80

^

G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.

DE/GSB 5

NUREG-0712 12/80 FROM REVIEW BRANCH X - DELETED II-4 C.

DE/GSB 5

HUREG-0712 12/88 4b-SAR RECEIVED FROM 0 - TOPIC NOT LICENSEE II-4 D.

DE/HGEB D

STARTED 5 - DRAFT SE SENT II-4 E.

X HRC to SCE 11/16/79 t 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.

DE/HGEB 0

6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC III-1 DL/SEPB 3(Sys)

SCE to NRC 08/29/79 TO UTILITY DL/SEFB 0(Elec) 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 3

SCE to NRC 09/08/80 RECEIVED BY NRC (2-35)

SAN ON0FRE TOPIC NO.

REVIEW STATUS REMARKS TOPIC HO.

REVIEW STATUS REMARKS DIV/BR DIV/5R III-3 A.

DE/SEB 3

SCE to NRC 09/08/80 111-10 B.

DL/SEPB 7

NRC 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 6

SCE to NRC 10/23/81 III-11 X

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

DSI/ASB 3

SCE to NRC 03<14/79 III-12 X

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

DE/MTEB G

HRC to SCE 05/07/81 IV-1 A.

DL/SEPB 7

NRC to SCE 11/13/79 III-4 C.

DSI/ASB 0

IV-2 DSI/ICSS 2

NRC to SCE 12/15/80 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 1

V-1 DE/MTEB G

NRC to SCE 05/07/81 III-5 B.

DL/SEPB 2

NRC to SCE 01/04/80 v-2 X

NRC to SCE 11/16/79 III-6 DL/SEPB 3

SCE to NRC 08/11/81 V-3 X

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

X NRC to SCE 35/07/81 V-4 X

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

DL/SEPB 3

SCE to NRC 09/08/80 V-5 DL/SEPB 5

NRC to SCE 06/03/81 III-7 C.

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

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

DE/SEB Gb SCE to NRC 06/09/81 V-7 DSI/ASB G

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

DSI G

NRC to SCE 05/07/81 V-8 X

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

X NRC to SCE 10/0'/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 HRC to SCE 05/07/31 V-10 B.

DL/SEPB 5

NRC to SCE 06/20/81 III-9 X

HRC to SCE 05/03/81 V-st A.

DL/SEPB 7

NRC to SCE 08/03/81 III-10 A.

DL/SEPB 7

SCE to NRC 07/24/81 V-11 B.

DL/SEPB 5(Sys)

NRC to SCE 06/20/81 LL/SEPB 2(Elec) Part of VII-3 (2-36)

+

.w, LSANTONOFRE

. TOPIC NO.

' REVIEW I STATUS REMARKS TOPIC HO.

REVIEW ~ STATUS REMARKS

'DIV/BR DIV/BR V-12 A.

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

DL/SEPB 7

NRC to SCE

.08/17/78-V-13 X

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

X NRC-'to SCE J5/07/81 VI-1 3

SCE to NRC

-08/03/79 VI-7 F.

X' NRC to SCE 11/16/79

'VI-2 A.

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

HRC to SCE' 05/07/81 VI-2 B.

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

HRC~to SCE 11/16/79.

tVI-2 C.

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

DL/SEPB 5

NRC to SCE

-08/28/81 VI-2 D.

DSI/CSB 3

SCE to NRC 06/22/79 VI-10 B.

DL/SEPB 7(Sys)

'NRC-to SCE

-11/15/79 DL/SEPB 7(Elec)

VI-3 DSI/CSB 3

SCE to NRC 06/22/79

' HRC to SCE 11/15/79^

VII-1 A.

DL/SEPB 5

NRC to SCE

'09/09/81 VI-4 DSI/CSB 2(Sys)

-NRC.to SCE 07/27/81 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 3

SCE to NRC 07/28/81 VI-6' DSI/CSB G

NRC to SCE 05/07/81 VII-3 DL/SEPB 5(Sys)

NRC to SCE 06/20/81-DL/SEPB 3(Elec) SCE to NRC 07/28/81

~VI-7 A.

1.

-DL/SEPB 7

NRC.to SCE 02/20/81 VII-4 X

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

2.

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

NRC to SCE 05/07/81'

.VI-7 A.

3.

DL/SEPB 0

VII-6 DL/SEPB 7

NRC to'SCE 08/28/81 VI-7.A. 4.

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

NRC to SCE 11/16/79-VI-7 B.

DSI/R$B

.5(Sys)

NRC to SCE 07/24/81 DL/SEPB 5(Elec) NRC to SCE 09/04/81 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

NRC'to SCE 07/31/81 VI-7 C.

1 DL/SEPB 7

NRC to SCE 08/03/81 VIII-3 A.'

DL/SEPB.

7 NRC to SCE 11/07/79 VI-7 C. 2.

DL/SEPB 7

HRC to SCE 06/01/81 VIII-3 B.

DL/SEPB 7

NRC to SCE

'07/24/81 VI-7 C. 3.

.X NRC to SCE 11/16/79 VIII-4 DL/SEPB 6

SCE to NRC 08/14/81 (2-37)

SAN ON0FRE TOPIC NO.

REVIEW STATUS REMARKS TOPIC N3.

REVIEW STATUS REMARKS DIV/BR DIV/BR IX-t DSI/ASB 3

SCE to NRC 10/05/79 XV-10 DSI/RSB 4b SCE to NRC 07/08/81 IX-2 X

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

HRC to SCE.

10/01/80 IX-3 DL/SEPB 2

XV-12 DSI/RSB Gb(Sys) SCE to NRC 07/01/81 DL/SEPB 7(Doses) NRC to SCE 01/29/80 IX-4 DSI/RSB 7-NRC to SCE 07/16/81 XV-13 X

HRC to SCE 11/16/79 IX-5 DL/SEPB 0

XV-14 DSI/RSB 4b SCE to NRC 07/01/81 IX-6 DE G

NRC to SCE 05/07/81 XV-15 DSI/RSB 4b SCE to NRC 07/01/81 X

X HRC to SCE 05/07/81 XV-16 DSI/AEB 4b SCE to NRC 08/04/81 XI-1 DSI/ETSB G

HRC to SCE 05/07/81 XV-17 DSI/RSB 4b(Sys) SCE to NRC 07/01/81 XI-2 DSI/ETSB G

NRC to SCE 05/07/81 DSI/AEB 7(Doses) NRC to SCE 01/29/80 XIII-t X

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

NRC to SCE 10/01/80 XIII-2 DL/SSPB 7

NRC to SCE 01/22/81 XV-19 DSI/RSB 7(Sys)

NRC to SCE 08/26/81 DL/SEPB 7(Doses) HRC to SCE 01/29/80 XV-1 DSI/RSB 7

NRC to SCE 10/27/81 XV-20 DL/SL?B 7

HRC to SCE 03/28/80 XV-2 DSI/RSB 7(Sys)

SCE to NRC 10/27/81 DL/SEPB 7(Dosos) HRC to SCE 01/29/80 XV-21 X

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

HRC to SCE 08/26/81 XV-22 X

NRC to SCE 05/07/81 XV-4 DSI/RSB Gb SCE to NRC 08/18/81 XV-23 X

NRC to SCE 05/07/81 XV-5 DSI/RSB 4b SCE to NRC 07/01/81 XV-24 X

NRC to SCE 05/07/81 XV-6 DSI/RSB 4b SCE to NRC 07/01/81 X'!I X

NRC to SCE 11/05/80 XV-7 DSI/RSB Gb SCE to NRC 07/01/81 XVII DL 7

NRC to SCE 08/17/78 XV-8 DSI/CPB Ab SCE to NRC 07/01/81 XV-9 DSI/RSB 5

NRC to SCE 05/11/81 (2-38)

YANKEE R0WE FACILITY: YANKEE ROWE 1 TOPIC NO.

REVIEW STATUS REMARKS DIV/BR LICENSEE: YANKEE ATOMIC ELECTRIC 11-1 A.

DE/SAB 0

REGION / LOCATION: 25 MILES NORTH EAST OF PITTSFIELD, MASS.

11-1 B.

DE/SAB 4b YAEC to NRC 05/01/81 DOCKET NO.: 05000029 II-1 C.

DE/SAB Ab YEAC to NRC 04/09/81 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 II-2 C.

DSI/AEB 7

NRC to YAEC 09/04/81 A/E FIRM: S&W II-2 D.

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

DE/HGEB 6

YAEC to NRC 03/16/81 OPERATING REACTORS BRANCH CHIEF:

D. CRUTCHFIELD 11-3 B.

DE/HGEB 6

YAEC to NRC 03/16/81 OPERATING REACTORS PROJECT MANAGER:

R.

CARUSO II-3 B.

1.

DE/HGEB 5

HRC to YAEC 02/09/81 INTEGRATED ASSESSMENT PROJECT MANAGER:

A. WANG g,g.,

II-3 C.

DE/HGEB 3

Site Visi' II-4 DE/GSB 7

NRC to YAEC 06/08/81 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 3

FRGM REVIEW BRANCH X - DELETED II-4 C.

DE/GSB 7

NRC to YAEC 06/08/31 Ab-SAR RECEIVED FROM 0 - TOPIC NOT LICENSEE II-4 D.

DE/HGEB 3

Site Visit STARTED 5 - DRAFT SE SENT II-4 E.

DE/HGEB 3

Sito Visit 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.

DE/HGEB Ab YAEC to NRC 08/31/81 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC III-1 DL/SEPB 0(Elec)

TO UTILITY DL/SEPB 3(Sys)

YAEC to NRC 01/31/79 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 3

YAEC to NRC 08/21/81 RECEIVED BY NRC (2-39)

a YANKEE R0WE TOPIC NO.

REVIEW STATUS REMARKS TOPIC HO.

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

DE/SES 3

YAEC to NRC 09/06/79 III-10 B.

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

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

X HRC to YAEC 11/16/79 III-3 C.

DE/HGEB 0

III-11 X

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

DSI/ASB 0

III-t2 X

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

DE/MTEB G

HRC to YAEC 05/07/81 IV-1 A.

DL/SEPB 7

NRC to YAEC 04/18/79 III-4 C.

DSI/ASB 0

IV-2 DSI/ICSB 4b YAEC to NRC 09/17/81 III-4 D.

DE/SAB 4b YAEC to NRC 06/30/81 IV-3 X

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

DL/SEPB 2

NRC to YAEC 01/04/80 V-1 DE/MTEB G

HRC to YAEC 05/07/81 III-5 B.

DL/SEPB 1

V-2 X

NRC to YAEC 11/16/81 III-6 DL/SEPB 3

YAEC to NRC 06/30/81 V-3 X

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

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

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

DL/SEPB 3

YAEC to NRC 08/21/81 V-5 DL/SEPB 5

HRC to YAEC 01/24/80 III-7 C.

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

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

DE/SEB 3

NRC to YAEC 11/16/79 V-7 DSI/ASB G

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

DSI G

NRC to YAEC 05/07/81 V-8 X

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

X NRC to YAEC 10/01/80 V-9 X

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

DL/SEPB 7

NRC to 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 5

HRC to YAEC 09/06/8' III-9 X

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

DL/SEPB 7

NRC to YAEC 12/08/80 III-10 A.

DL/SEPB 7

NRC to YAEC 09/22/81 V-11 B.

DL/SEPB 5(Sys)

HRC to YAEC 09/06/81 DL/SEPB 0(Elec)

(2-40)

YANKEE R0WE TDPIC 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 to YAEC 05/07/81 VI-t DE/CEB 3

YEAC to NRC 06/26/79 VI-7 F.

DL/SEPB 7

NRC to YAEC 08/28/81 VI-2 A.

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

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

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

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

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

DL/SEPB 3

YAEC to NRC 06/30/81 VI-2 D.

DSI/CSB 2

VI-10 B.

X HRC to YAEC 11/16/79 VI-3 DSI/CSB 2

VII-1 A.

DL/SEPB 5

NRC to YAEC 10/05/81 VI-4 DSI/CSB 0(Sys)

VII-I B.

DL/SEPB 7

NRC to YAEC 08/17/78 DL/SEPB 5(Elec) NRC to YAEC 10/16/81 VII-2 DL/SEPB 5

HRC to YAEC 10/19/81 VI-5 X

NRC to YAEC 05/07/88 VII-3 DL/SEPB 5(Sys)

HRC to YAEC 09/06/81 VI-6 DSI/CSB G

HRC to YAEC 05/07/81 DL/SEPB 0(Elec)

VI-7 A.

1.

DL/SEPB 7

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

HRC to YAEC 05/07/81 VI-7 A. 2.

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

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

DL/SEPB 4b YAEC to NRC 06/30/81 VII-6 DL/SEPB 7

NRC to YAEC 08/28/81 VI-7 A. 4 X

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

NRC to YAE0 11/16/79 VI-7 B.

DSI/RSP 7(EInc) HRC to YAEC 06/04/81 VIII-1 A.

DSI/PSB G

HRC to YAEC-05/07/81 0(Sys)

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 09/04/81 VIII-3 A.

DL/SEPB 7

HRC to YAEC 11/07/79 VI-7 C. 2.

DL/SEPB 7

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

DL/SEPB 7

NRC to YAEC 03/28/81 VI-7 C. 3.

DL/SEPB 7

NRC to YAEC 07/24/80 VIII-4 DL/SEPB 2

NRC to YAEC 06/23/81 (2-41)

YANKEE R0WE TOPIC ND.

REVIEW STATUS REMARKS TOPIC NO.

REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 0

XV-10 DSI/RSB 4b YAEC to NRC 06/30/81 IX-2 X

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

Nhc to YAEC 10/01/80 IX-3 DL/SEPB 4b YAEC to HRC 09/17/81 XV-12 DSI/CPB 4b(Sys) YAEC to NRC 06/30/81 DSI/AEB 4b(Doses)YAEC to NRC 08/31/81 IX-4 DSI/RSB 4b YAEC to HRC 08/31/81 XV-13 X

HRC to YAEC 11/16/79 IX-5 DL/SEPB 0

XV-14 DSI/RSB 4b YAEC to NRC 06/30/81 IX-6 DE G

HRC to YAEC 05/07/81 XV-15 DSI/RSB 4b YAEC to NRC 06/30/81 X

X HRC to YAEC 05/07/81 XV-16 DSI/AEB 0

-XI-1 DSI/ETSB G

NRC to YAEC 05/07/81 XV-17 DSI/RSB 0(Sys)

XI-2 DSI/ETSB G

NRC to YAEC 05/07/81 DSI/AEB O(Dones)

XIII-1 X

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

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

NRC to YAEC 03/11/81 XV-19 DSI/RSB 0(Sys)

DSI/AEB 0(Doses)

XV-t DSI/RSB 0

XV-20 DL/SEPB 7

HRC to YAEC 09/06/81 XV-2 DSI/RSB 4b(Sys) YAEC to NRC 06/30/81 DSI/AEB 0(Dosos)

XV-21 X

HRC to YAEC 05/07/81 XV-3 DSI/RSB Gb YAEC to HRC 06/30/81 XV-22 X

HRC to YAEC 05/07/81 XV-4 DSI/RSB 0

XV-23 X

NRC to YAEC 05/07/81 XV-5 DSI/R$B 4b YAEC to NRC 06/30/ft XV-24 X

NRC to YAEC 05/07/81 XV-6 DSI/RSB 0

XVI X

HRC to YAEC 11/05/80 XV-7 DSI/RSB Gb YAEC to NRC 06/30/81 XVII DL 7

HRC to YAEC 08/17/78 XV-8 DSI/CPB D

XV-9 DSI/RSB 4b YAEC to NRC 06/30/81 (2-42)

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7 RECEIVED ' COMPLETE:

TOPIC NO.' TITLE ~

RECEIVED COMPLETE TOPIC HO. TITLE

=

>111 Classification of.

NDHE 111-8.A Loose Parts Monitoring and. NAME-(SYS)

Structures. Components and

. Core Barrel Vibration-.

s-Systems (Seismic and Monitoring (NRR.B-60, C-12)

. :-y

-Quality)'

IV-2 Reactivity Control Systems -- 07/31/81R : 10/16/8ti

III-5.A' Effects of Pipe Break on 08/13/81R Including Functional. Design

. Structures, Systems and and. Protection Against Components Inside.

Single Failures Containment NOME V-7

. Reactor Coolant Pump

' III-5.B" Pipe Break Ou,,tside 08/25/31R Oversdeed (NRR B-68)

" 1 Containment VI-6 Containment Leak Testing NOME

- III-7.A.. Inservice Inspection, H0HE 08/25/81

'(MP A-04)

~

Including Prestressed Concrete Containments with VIII-1.A Potential Equipment-HONE

-Either Grouted or Ungrouted Failures Associated with a.'

Degraded Grid Voltage Tendons (MP.B-23)

LIII-7.B' ' Design Codes.. Design NONE 09/03/81 Criteria, Load IX-1' Fuel Storage Combinations, and Reactor Cavity Design Criteria IX-4 Boron Addition System 10/09/81R XI-1 Appendix ICMP A-02)

NDHE.

EE SAR 1/

'SER 2/

XI-2 Radiological-(Effluentf NDHE' T I T L E..

RECEIVED COMPLETE and Process) Monitoring TOPIC NO.

Systems (NRR B-67) 111-3.C Inservice Inspection of 09/30/81 Water Control Structures 1/ SAR : Licensee Safety Analysis Report-Scheduled or Actual III-4.8 Turbine Missiles (MP B-46)

NONE 08/28/81 (Actual (status 4b) when date is followed by R)~

III-7.D Containment. Structural NONE

'08/17/81 2/ SER : Staff Safety Evaluation Report (Status 4a,5,6,7)

Integrity Tests V-1 Compliance with Codes and NONE Standards (10 CFR 50.55a)

(MP.A-01,A-14)

IX-6 Fire Protection (MP B-02)

HDHE s

(3-2)-

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TCPIC NO. TITLE RECEIVED COMPLETE TOPIC NO. TITLE RECEIVED COM."LETE III-1 Classification of Struct-NONE IX-6 Fira Protection (MP B-02)

NONE (SYS) cros Compcnents and Systems (Seismic and Quality)

III-2 Wind and Tornado Loadings NONE 09/23/81

~hil SAR 1/

SER 2/

III-7.A Inscrvice Inspection, NONE TOPIC NO. TITLE RECEIVED COMPLETE Including Prestressed III-4.C Internally Generated 11/30/81 Cencrete Containments with Missiles Containments Grouted ur Ungrounded Tendons III-8.A Loose Parts Monitoring and NONE Core Barrel Vibration III-7.B Design Codes. Design NONE Monitoring (HRR B-60,C-12)

Criteria, Load Combinations, and Reactor V-7 Reactor Coolant Pump HONE Cavity Design Criteria Overspeed(NRR B-68)

VI-7.C.1 Appendix K - Electrical NONE VI-2.D Mass and Energy Release for HONE C9/25/81 Instromontation and Control Possible Pipe Break Inside (EIC) Re-reviews Containment IX-5 Ventilation Systems NONE 11/02/81 VI-3 Containment Pressure and NONE 09/25/81 Heat Rcmoval Capability DE SAR 1/

SER 2/

VI-7.B ESF Switchover from NONE TOPIC HO. TITLE RECEIVED COMPLETE (SYS)

Injection to Recirculation Mode (Automatic ECCS 11-1.B Population Distribution 04/15/81R 07/21/81 Realignment)

II-1.C Potential Hazards or 04/15/81R 07/01/81 IX-1 Fuel Storage 11/15/81 Changes in Potential XI-1 Appendix I(MP A-02)

NONE Hazards Due to Transportation, XI-2 Radiological (Effluent NONE Institutional Industrial, and Process) Monitoring and Military Facilities Systcms(NRR B-67)

II-4.D Stability of Slopes 06/30/81R XV-9 Startup or a, Inactive Loop NONE 10/i6/81 or Recirculation Loop at an II-4.F Settlement of roundations 06/30/81R Incorrect Temperature, and and Buried Equipment Flow Controllor Malfunction Causing an Increase in BWR III-3.C Inservice Inspection of 10/12/81R Core Flow Rate Water Control Structures XV-19 Loss-cf-Coolant Accidents HONE 09/29/S1 III-4.B Turbine Missiles (MP B-46)

(DOSES)

Resulting from Spectrum of III-4.D Site Proximity Missiles 04/16/81R 07/21/81 (SYS)

Postulated Piping Breaks 10/02/81 Within the Reactor Coolant (Including Aircraft)

Pressure Boundary VI-1 Organic Materials and 09/30/81 1/ SAR = Licensee Safety Analysis Report-Scheduled or Actual Post Accident Chemistry (actual (status 4b) when date is follwed by R)

Staff Safety Evaluation Report 2/ SER (3-4) e

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. GAR 1/

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SAR-1/

-SFR 1/1 TOPIC NC. TITLE RECEIVED COMPLETE-TOPIC NO. TITLE RECEIVED COMPLEIE III-1 Classification-of NONE I1-3.3 Flooding Potential and NONE-(SYS)

Structures, Components and Protection Requirements:

Systems (Seismic and Quality)

II-3.B.1 Capability of Operating NONE Plant to Cope with Design

-III-2 Wind ano Tornado Loadings 10/30/81 Basis Flooding Conditions -

III-5.A Effects of Pipe Break on 06/30/82.

II-3.C Safety ralated Water.

NONE

~

Structures, Systems and Supply (Ultimate Heat Sink

-Congonents Inside (UNS))

Containment II-4.D Stability of Slopes-07/30/81 III-7.5 Design Codes, Design NONE Criteria, Load-II-4.E Dam Integrity 10/20/81 Combinations, and Reactor Cavity Design Criteria II-4.F Settlement of Foundations 0943)/81 and Buried Equipment VI-4 Containment Isolation NONE (ELEC)

System III-3.A Effects of High Water Level 10/20/81 on Structures VII-1.A Isolation of Reactor NONE 08/05/81 Protection System from III-3.C Inservice Inspection of 10/20/81 Non-Safety Systems, Water Control Structuras Including Qualifications of Isolation Devices III-4.B Turbine Missiles NONE VII-6 Frequency Decay NONE 08/26/81 III-4.D Site Proximity Misslies 10/31/81 (Including Aircraft)

IX-5 Ventilation Systems NONE III-7.D Containment Structural 04/27/81R Integrity Tests 21 SAR J/

SER 2/

V-1 Compliance with Codes NONE TOPIC NO. TITLE RECEIVED COMPLETE and Standards-(10 CFR 50.554)(MP A-01,A-14)

(

II-1.A Exclusion Area Authority 06/01/81R 10.'06/81 and Control VI-1 Organic Materials and 10/31/81' Post Accident Chenistry-II-1.B Population Distribution 04/27/81R

.0/06/81 IX-6 Fire Protection NONE II-1.C Potential Hazards or 10/30/81 Changes in Potential Nazards Due to

,Dil

. Transportation, SAR 1/

SER 2/

Institutional Industrial, TOPIC NO. TITLE RECEIVED COMPLETE' and Military Facilities II-2.C Atmospheric Transport and 03/20/81d 08/26/81 II-3.A Hydrologic Description NONE Diffusion Characteristics for Accident Analysis III-4.A Tornado Missiles 10/31/81 (3-6)

__________/

DRESDEN;2 J211 (Cont.)

.pjl (Cont.)

l SAR 1/

SER 2/

,SAR 1/

SER 2/

l TOPIC HO.' TITLE RECEIVED COMPLETE

' TOPIC NO.' TITLE RECEIVED COMPLETE; III-4.C~~

Missiles Turbine Trip, Luss of Internally Generated 10/31/81 XJ-3 Loss of 2xternal Load,:

10/ 15/81I Condensar' Vacuum,' Closure III-8.A Loose Parts Monitaring NONE of !!ain Stoam Isolation and Core Barrel Vibration Valve (BWR), and Steam...

l Monitoring (NRR B-60 C-12)

Pressure Regulator Failure.

-(Closed)

IV-2 Reactivity Control Systems 10/31/81 10/19/81 l

Including Functional Design XV-4 Loss of Non-Emergency A-C 10/15/81R l

~ and Protection Against Power to the Station-j Single Failures Auxiliaries VI-2.D Mass and Energy Release for NONE XV-5 Loss of Normal:Feedwater 10/15/81R Possible Pipe Break Inside Flow Containment XV-7 Reactor Coolant Pump Rotor 10/15/81R VI-3 Containment Pressure and NONE Seizure and Reactor Coolant Heat Removal Capability Pump Shaft Break l

VI-4 Containment Isolation NONE 10/02/81 XV-8 Control Rod Misoperation 10/15/81R (SYS)

System (System Malfunction or-Operatcr Error)

VI-6 Containment Leak Testing NONE

-(MP A-04)

XV-9 Startup or an Inactive Loop 10/15/81R or Recirculation Loop at an VI-7.A.4 Core Spray Hozzle NONE Incorrect Temperature, and Effectiveness (NRR A-16)

Flow Controller Malfunction Causing an Increase in BWP

-VIII-1.A Potential Equipment NONE Core " low Rate Failures Associated.with a

. Degraded Grid Voltage XV-11 Inadvertent Loading and 10/15/81R (MP B-23)

Operation rf a Fuel Assembly in an Improper IX-1 Fuel Storage 09/15/81 Position XI-1 Appendix I(MP A-02)

NONE XV-15 Spectrum of Rod Drop 10/15/81R (SYS)

' Accidents-(BWR)

XI-2 Radiological (Effluent and NONE (DOSES) 10/15/81R Process) Monitoring Systems (NRR B-67)

XV-14 Inadvertent Operation of 10/15/81R ECCS and Chemical and XV-1 Increase in Feedwater 10/15/81R Volume Control System Temperature, Increase in Malfunction that Increases Feedwater Flow, Increase Reactor Coolant Inventory

in Steam Flow and Inadvertent Opening of a XV-15 Inadvertent Opening of a' 10/15/81R Steam Generator Relief or PWR Pressurizer Safety-Safety Valve Relief Valve or a BWR Safety / Relief Valve (3-7)

c 1

DRESDEN 2 211 (Cont.)

SAR J/

SER 2/

TOPIC HO. TITLE RECEIVED COMPLETE XV-18 Radiological Consequences 10/15/81R of Main Steam Line Failure Cutside Containment (BWR)

XV-19 Loss of-Coolant Accidents 10/15/81R (SYS)

Resulting from Spectrun of (DOSES)

Postulated Piping Braaks 10/15/81R Within the Reactor Coolant Prassure Boundary XV-20 Radiolocical Consequences 04/27/81R of Fuel Danaging Acci' dents (Inside and Outside Containment Licensee Safety Analysis Report-Scheduled or Actual 2/ SAR factual (status 4b) when date is followed by R) g/ SER Staff Safety Evaluation Report (Status 4a,5,6,7)

=

(3-8)

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SAR 1/

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SAR 1/

SER 2/

TOPIC NO. TITLE RECEIVED COMPLETE TOPIC NO. TITLE RECEIVED COMPLETE III-1 Classification of NONE (SYS)

Structures, Components V-1 Compliance with Codes NONE and Systems and Structures (MP A-01.A-14)

III-2 Wind and Tornado Loading 05/07/81R VI-1 Organic Materials and Post 10/30/81 VII-5 Frequency Decay NONE 08/29/81 Accident Chemistry IX-5 Ventilation Systen 12/31/81 IX-6 Fire Protection (MP A-02)

NONE E

M1 SAR 1/

SER 2/

SAR 1/

SER 2/

TOPIC NO. TITLE RECEIVED COMPLETE TOPIC HO. TITLE RECEIVED COMPLETE II-1.A Exclusion Arca Authority 05/07/81R Il2.C Atmospheric Transport and 09/3u/8T and Cnntrol Diffusion Characteristics II-1.3 Population Distribution 05/07/81R III-4.A Tornado Missles 09/30/81 II-1.C Potential Hazards Due to 05/21/81R Transportation, Industrial, III-4.C Internally Generated 02/28/8:

and Military Facilities Missiles II-3.A Hydrologic Description 05/07/81R III-8.A Loose Parts and Core NONC Barrel Monitoring II-3.B Flooding Potential and 05/07/81R (HRR B-60,C-12)

Protection Requirements II-3.B-1 Capability to Cope with 05/07/81R Design Basis Flood VI-2.D Mass and Energy Release for NONE Possible Pipe Break Inside II-3.C Safety Related (Jater Supply 05/07/81R Containment (Ultimate Heat Sink)

VI-3 Containment Pressure and NONE II-4.D Stabliity of Slopes 10/15/81 Heat Removal Capability II-4.F Settlement of Foundation 10/15/81 VI-4 Containment Isolation NONE 10/22/81 and Buried Equipment System III-3.A Effects of High Water 05/07/81R VI-6 Containment Leak Testing NONE Level on Structures (MP A-04)

III-3.C Inservice Inspection of 09/01/81 VI-7.A-4 Core Spray Nozzle NONE Water Control Structure Effectivencss(MP D-12)

III-4.B Turbine Missiles 09/30/81 VIII-1.A Potential Equipment NONE Failures Associated with III-4.D Site Proximity Misslies 05/07/81R a Degraded Grid Voltage (MP E-23)

III-7.D Containment Structural 09/01/81 Integrity Tests IX-1 Fuel Storage 11/15/81 (3-10)

OYSTER CREEK All (Cont.)

211 (Cont.)

SAR 1/

SER R/

SAR 1/

SER 1/

TOPIC NO. TITLE RECEIVED COMPLETE TOPIC NO. TITLE RECEIVED CO.5PLETE XI-1 Appencix I(MP A-02)

NDHE XV-16 Radiclogical Consequences 09/01/81 of Failure of Small Lines XI-2 Radiological (Effluent and NONE Carrying Primary Coolan+

Process Monitoring Systems)

Outsida Containment (NRR S-67)

XV-1 Decrease in Feedwate" 05/07/81R Temperature, Increas a in Main Steam Line Failure Foodwater Flow, Incraase in Outside Containment Steam Flow, Inadvertent Opening of Steam Generator, XV-19 Loss of Coolant Accidents 05/07/81R 09/04/81 Relief or Safety Valve (SYS)

Resulting Frc-Spectrem Breaks Within Reactor XV-3 Loss of External Load.

05/07/81R 10/01/81 (DOSES)

Coolant Pressure Boundary 05/07/81R Turbine Trip, Loss of Condenser Vacuum, Closure XV-20 Radiological Consequences G5/07/81R of Main Steam Isolation of Fuel Damaging Accidents Valve (BWR), Steam Pressure (In 1 Out of Containment)

Regulatory Failura (closed)

XV-4 Loss of Non-Emergency A-C 05/07/81R 07/16/81 1/ SAR = Licensee Safety Analysis Report-Scheduled or Actual Power to the Station (actual (status 4b) when date is followed 'oy R)

Auxillaries 2/ SER : Staff Safety Evaluation Report (Status 4z,5,6,7)

XV-S Loss of Normal Feedwater 05/07/81R Flow XV-7 Reactor Coolant Pump Rotor 08/25/81R Seizure and Reactor Coolant Pump Shaft Break XV-9 Startup or an Inactive Loop 05/07/81R or Recirculation Loop at Incorrect Temperature and Flow Controller Malfunction Causing an Increase in BWR Core flow Rate XV-13 Spectrum of Rod Drop NONE 07/01/81 (sys)

Accident 05/07/81R (doses)

XV-14 Inadvertent Operation of 05/07/81R 07/16/81

~~

ECCS that Increases Reactor Coolant Inventory XV-15 Inadvertent Opening of BWR 05/07/81R Safety / Relief Valve (3-11)

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SAR 1/

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TOPIC NO. TITLE RECEIVED COMPLETE TCPIC NO. TITLE RECEIVED COMPLETE

~

Ill-4.C Internally Generated 09/30/81 XV-3 Loss of External Lead, 06 53/81R 99/18/81 Missiles Turbino Trip, Less of Condanser Vacuum, Closure III-8.A Loose Parts Monitoring and NONE of Main S~ team Isolation Core Barrel Vibration valve (SWR), and Steam Monitoring (NRR B-60,C-12)

Pressure Regulator failura (Closed)

IV-2 Reactivity Control Systems 10/28/81R Including Functional Design XV-4 Loss of Non-Emergency A-C 06/30/81R 99/18/81 and Protection Against Power to the Station Single Failures Auxiliaries VI-2.D Mass and Energy Release for NONE XV-5 Loss of Normal Feedwater 06/30/21R Possible Pipe Break Inside Flow Containment XV-7 Rea= tor Coolant Pump 06/30/81R VI-3 Containment Pressure and NONE Rotor Seizure and Roactor Heat Removal Capability Coolant Pump Shaft Break VI-4 Containment Isolation HONE XV-8 Control Rod Nisoperation 06/30/81R 02/26/81 (SYS)

System (System Malfunction or Operator Error)

VI-6 Leak Testing (MP A-04)

XV-9 Startup or an Inactive Loop 06/30/81R VI-7.A.4 Core Spray Hozzle NONE or Recirculation Loop at an Ef fect ivenese(NRR A-16)

Incorrect Tamparature, and Flow Controller Malfunctirn VIII-1.A Potential Equipment NONE Caesing an Increase in BWR Failures Associated With a Core Flow Rate Dograded Grid Voltage XV-11 Inadvertent Loading and 06/30/81R 10/14/81 IX-1 Fuel Storage 08/31/81R Operation of a Fuci Assembly in an Improper XI-1 Appendix I(MP A-02)

NONE Position XI-2 Radiological (Effluent 2 NONE XV-13 Spectrum of Rod Drop 06/30/81R 09/09/81 Process) Monitoring Systems (SYS)

Accidents (BWP.)

(NRR 3-67)

(DOSES) 06/30/81R 09/21/81 XV-1 Decrease in Feodwater 06/30/81R XV^14 Inadvertant Operation of 06/30/81R 09/18/81 Temperature, Increase in ECCS and Chemical and Feedwater Flow, Increase in Voluma Cortrol S stem

/

Steam Flow and Inadvertent Malfunction that Increases Opening of a Steam Gener-Reactor Coolant Inventory ator P.elief or safety Valve XV-15 Inadvertent Opening of a 06/30/81R 10/28/81 PWR Pressurizer Safety Relief Vcive or a BWR Safety Relief Valve (3-14)

_. ~

.. ~ - -

MILLSTONE 1 211 (Cont.)

SAR 1/

SER 2/

TOPIC HO. TITLE RECEIVED COMPLETE XV-16 Radiological Consequences 06/30/81R 09/21/81 of Failure of Small Lines Carrying Primary Coolant Outside Containment XV-18 Radiological Consegaences 06/30/81R 09/21/81 of Main Steam Line.~3tlure Outside Containment (BWR)

XV-19 Loss of Coolant Accidents 06/30/81R 08/26/81 (SYS)

Resulting from Spectrum of (DOSES)

Postulated Piping Breaks 06/30/81R 09/21/81 Within the Reactor Coolant Pressure Boundary XV-20 Radiological Consequences 06/30/81R 09/21/81 of Fuel Damaging Accidents (Inside and Outside Containment) l/ SAR = Licensee Safety Analysis Report-Scheduled or Actual (actual (status 4b) when date is followed by R)

Z/ SER = Staff Safety Evaluation Report (Status 4a,5,6,7)

(3-15)

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TOPIC NO. TITLE RECEIVED

COMPLET E TOPIC NO. TITLE RECEIVED COMPl.ET E IX-3 Station Service and Cooling 08/31/81

.111-1 Classification of NONE Water Systems c

Structures, Components and-Systems-(Seismic and IX-5 Ventilation Systems 10/30/81 Quality)

III-2 Wind and Torando Loadings 10/15/81

[f SAR 1/

SER Z/ -

-III-5A Effects of Pipe Break o 10/15/81

. TOPIC N9 TITLE RECEIVED COMPLETE.

Structures, Systems and Components Inside-II-1.C Potential Hazards or.

11/15/81 Containment Changes in Potential Hazards Due to III-5.3 Pipe Break Outside 10/15/81 Transportation, Containment Institutional Industrial, and Military Facilities III-6~

Seismic Design NONE Considerations II-4.D Stability ~of Slopes 08/31/81 III-7.B' Design Codes, Design NONE II-4 F Settlement of Foundations 08/31/81 Criteria, Load and Buried Equipment-Combinations, and Reactor Cavity Design Criteria III-3.A Effects of High Water Level 02/28/82 on Structures

'V-11.3 RHR Interlock Requirements NONE (ELEC)

III-4.5 Turbine Missiles (MP B-46)

NOME -

VI-7.A.3 ECCS Actuation System NONE III-4.D Site Proximity Missiles 10/23/81R (Including Aircraft)

VI-7.B ESF Switchover from NONE 09/04/81 (ELEC)

' Injection to-Recirculation III-7.D Containment Structural 06/09/81R Mode (Automatic ECCS Integrity Tests Realignment) l V-1 Compliance with Codes and NONE VI-10 A Testing of Reactor Trip

' HONE 08/28/81 Standards (to CFR 50.55a)

System and Engineered (MP A-01)

Safety Features Including

. Response Timo Testing VI-1 Organic Materials and Post 11/15/81 Accident Chemistry VII-1.A Isolation of Reacter NONE 09/09/81 Protection Systems, IX-6 Fire Protection (MP B-02)

NONE Including Qualifications of Isolation Devices E.11 VII-2 Engineereo Safety Fnatures NONE SAR 1/

SER 2/

(ESF) System Control L ngi c '.-

TOPIC NO. TITLE RECEIVED COMPLETE

.and Design III-4.A Tornado Missiles 10/15/88 VII-3 Systems Required for Safe NONE (ELEC)

Shutdown III-4.C Internally Generated 11/15/81 Missiles VII-6 Frequency Decaf NONE 08/28/81 l

(3-17)

r F

SAN ON0 RE 211 (Cont.)

211 (Cont.)

SAR 1/

SER 2/

SAR J/

SER 2/

TOPIC NO. TITLE RECEIVED COMPLETE TOPIC NO. TITLE RECEIVED COMPLETE I l l-8. k Loose Parts (1onitoring and NONE XV-3 Loss of Extornal Load, 0 7 / 01/8 ) R 08/26/81 Core Barrel Vibration Turbino Trip, Loss of Con-Monitoring (NRR B-60,C-12) densor Vaccum, Closure of Main Steam Isolation Valva IV-2 Enactivity Control Systems 09/30/81 (BWR), cnd Staam Pressure Including Functional Design Rcgulator Failure (Closod) and Protection Against Single Failures XV-4 Loss of Non-Emcrgency A-C 08/18/81R Power to the Station V-7 Reactor Caolant Pump NONE Auxillaries Overspeed(NRR B-68)

X7-5 Loss of Normal Feedwater 37/01/81R VI-2.D Mass and Ene gy Release for NONE Flew Possible Pipe Break Inside Containment XV-6 Feedwater System Pipe 07/01/81R Dreaks Insido and Gutside VI-3 Containment Pressure and NONE Containment (PWR)

Heat Removal Capability XV-7 Resctor Coolant Nump Rot r 07/01/81R VI-4 Containment Isolation NDHE Seizure and Reactor Cool it (SYS)

System Pump Shaft Preak VI-6 Containment Leak Yesting NONE XV-8 Control Rod Misoparation 07/01/81R (f1P A-04)

(System Malfunction or Operator Error)

VIII-1.A Potential Equipment Failure NONE Associated :4ith a Degraded XV-10 Chemical and Volume Control 07/01/81R Grid Voltage (MP B-23)

System Malfunction that Results in a Decrease in IX-1 Fuel Storage 12/15/81 the Boron Concentratien in the Reactor Coolant (PWR)

XI-1 Appendix I HONE XV-52 Spectrum of Rod Ejection 07/01/81R XI-2 Radiological (Effluent and NONE Accidents (PWR)

Process) Monitoring Systems (NRR B-67)

Y,-14 Inadvertent Operation of 07/01/81R ECCS and Chemical and XV-1 Decrease in Feodwater 07/01/81R 10/27/81 Volemo Control System Temperature, Increasu in Mal 4 unction that Increases Feedwater Flow. Increase Roactor Coolant Inventory in Steam Flow and Inadvertent Opening of a XV-15 Inadvertent Opening of a 07/01/81R Stcan Generator Relief PWR Pressurizer Safety-or Safety Valve Relief Valve of a BWR XV-2 Spectrum of Steam System 07/01/81R 10/27/81 Piping Failures Inside and XV-16 Radiological Consequences 08/04/81R Dutside of Containment (PWR) of Failure of Small Lines Carrying Primary Coolant Outsida Centainment (3-18)

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TCPIC NO. TITLE RECEIVED COMPLETE TOPIC NO. TITLE RECEIVED CCMPLETE III-1 Classification of Struct-NONE Il-3.A Nydrologic Description NONE (SYS) ures. Corponents and Sys-tems (Seismic and Quality)

II-3.B Flooding Potential and NONE Protection Requirements III-2 Wind and Tcrnado Loading 02/01/82 II-3.B.1 Capability of Operating NCNE III-5.A Effects cf Pipe Break en 12/01/81 Plans to Cope with Designs Structures, Systems and Basis Flooding Conditions Components Insido Containment II-3.C Safety-Related Water Supply NONE (Ultimate Heat Sink UHS))

III-5.B Pipe Bresk Outsida 12/15/81 II-4.8 Proximity of Capable NONE Containnant Tectonic Structures in III-6 Soismic Design NONE Plant Vicinity Considerations II-4.D Stability of Slopes 10/05/81R III-7.B Dosion Codes, Design NONE Criterion, Load II-4.F Settic. ment o f Foundations 10/19/81R I

Combinations and Reactor and Buried Equipment Cavi ty Dasi gn Criterion III-3.A Effects of High Water 03/15/82 VI-7.A.3 ECCS Actuation System NONE Level on Structures VI-7.C ECCS Single Failure'Cri-NONE 08/05/81 III-3.C Inservice Inspection of 12/01/81 terion and Requirements for tJater Control Structures Locking Out Power to Valves Including Independence III-4.B Turbine Missiles 12/15/81 of Interlocks on ECCS Valve III-4.D Site Proximity Missiles 11/01/81 I

l VI-7.C.2 Failure Mode Analysis ECCS NONE 08/05/81 (Including Aircraft)

VI-10.A Testing of Reactor Trip 12/23/81 III-7.D Contair. ment Structural 09/20/81 System and Engincored Integrity Tests Safety Featuros, Including Response Time Testing V-1 Compliance with Codes and NONE Standards 310 CFR 50.55a)

VII-1.A Isolation of Reactor NONE (MP A-01.A-14)

Protection Systen From Non-Safety Systems, Including VI-1 Organic Materials and Post 10/15/81 Cualification of Isolation Accident Chemsitry Devices IX-6 Fire Protection (MP B-02)

NONE VII-2 Engineered Safety Features NONE (ESF) System Control Logic and Design Dil SAR 1/

SER 2/

VII-6 Frcquency Dncay NONE 09/21/81 TOPIC NO. TITLE RECEIVED COMPLETE IX-3 Station Service and 11/15/81 Cooling Water Systems II-2.C Atmospheric Transport and C 9/25/81 Diffusion Characteristics IX-5 Ventilation Systems 01/15/82 for Accident Analysis (3-21)

BIG ROCK POINT Ril (Cont.)

Ril (Cont.)

SAR 1/

SER 2/

SAR 1/

SER 2/

TOPIC NO. TITLE RECEIVED COMPLE1E TOPIC NO. TITLE RECEIVED CCMPLETE III-4.A Tornado Missiles 03/15/82 XV-3 Loss of External Load.

07/tS/8tR 10/16/81 Turbine Trip. Loss of III-4.C Internally Generated 03/15/82 Condensar Vacuum, closure Missiles of Main Steam Isolation valve (3HR), and Steam III-8.A Loose Parts Monitoring and NONE Pressura Regulator Failure Core Vibration Monitoring (Closed)

(NRR B-63.C-12)

XV-4 Loss of Non-Emergency A-C 07/15/81R 10/16/81 IV-2 Reactivity Control System 10/01/81 Power to Use Station Including Functional Design Auxiliaries and Protection Against Singla Failures XV-5 Loss of Normal Feedwater 07/15/81R Flow VI-2.D Mass and Energy Release for NONE Postulated Pipe Breaks XV-7 Reactor Coolant Purps 07/15/81R Inside Containment Rator Seizure and Raactor Coolant Pump Shaft Break VI-3 Containment Pressures and NONE Heat Removal Capability XV-8 Control Rod Misoperation 09/23/81R (Systcm Malfunction or VI-4 Containment Isolation Sys.

HONE Operator Error) bI-6 Containment Leak Testing NONE XV-9 Skartup of an Inactive Loop 07/15/81R (MP A-04) or Recirculation Loop at an Incorrect Temperature and VI-7.B ESF Switchover from NONE Flow Controller Malfunction Injection to Recirculation Causing an Increase in BWR Mode (Automatic EECS Core Flow Rate Realignment)

XV-11 Inadvertent Loading and 09/28/81R VIII-1.A Potential Equipment NDHE Operation of a Fuel Failures Associated with Assembly in an Improper Position (LWR)

Degraded Grid IX-1 Fual Storage C8/31/81 XV-13 Spectrum of Rod Drop 07/01/81R 10/23/81 Accidants XI-1 Appendix I(MP A-02)

NONE XV-14 Inadvertent Operation of 06/?6/81R 08/18/81 XI-2 Radiological (Effleant NONE ECCS and Choraical and and Frocess) Monitoring Volene Control System Systems (NRR B-67)

Malfunction that Increases Reactor Coolant Inventory XV-1 Decrensa in Feedwater 07/15/81R Temperature Increasa in XV-15 Inadvertent Opening of a 06/26/81R 08/18/81 Foadwater Flow, Increase PWR Prassurizer Safety in Stean Flow and Relief Valve or a BWR Inadvertent Opening of a Safety /2elief Valve Steam Generator Relief or Safety Valve (3-22)

N

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BIG ROCK POINT 211 (Cont.)

SAR 1/

SER 2/

TOPIC NO. TITLE RECEIVED CO.MP L ET E XV-16 Radiological Consequences 07/01/81R of Failure of Small Lines Carrying Primary Coolant Outside Containment XV-18 Radiological Consequences 07/01/81R of Main Steam Line Failure Outside Containment XV-19 Loss of Coolpnt Accidents 06/29/81R 08/18/88 (SYS)

Resulting From Spectrum of Postulated Piping Breaks (DOSES) within the Reactor Coolant 07/01/A1R Pressure Boundary XV-20 Radiological Consequences 07/03/81R 10/23/81 6f Fuel Damaging Accidents (Inside and Cutside Containment) 1/ SAR : Licensee Safety Analysis Report-Scheduled or Actual (Actual (Status 4b) when date is folloued by R)

Z/ SER Staff Safety Evaluation Report (Status 4a,5,6,7)

(3-23)

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TCPIC NO. TITLE RECEIVED COMPLETE TOPIC NO. TITLE RECEIVED COMPLETE III-l Classification of NONE 1X-5 Ventilation Systems 10/30/81 (SYS)

Structures, Compononts and Systems (Soismic and XIII-2 Safoquards/ Industrial NONE Quality)

Security (MP A-10)

III-2 Wind and Tornado Loadings 12/31/81 D1 SAR 1/

SER 2/

III-5 A.

Effects of Pipe Break 09/30/81 on Structures, Systems TOPIC NO. TITLE RECEIVED COMPLETE and Componets Inside Containment II-1.A Exclusion Area Authority 04/47/81R B. Pipe Break Outside 10/02/81R II-1.B Population Distribution 08/31/81R Containment II-1.C Potential Hazards or 06/30/81R III-6 Sei smic Design NONE Changos in Potential Hazards Due to Considerations Transportation, III-7.B Design Codes, Design NONE Institutional Industrial, Criteria, Load and Military Facilities Combinations, and Reactor Cavity Dosign Cri toria II-3.A Hydrologic Description 12/15 eat VI-7.A.3 ECCS Actuation System NONE II-3.B Flooding Potential and 12/15/81 Protection Requiremonts VI-7.C.3 The Effect on PWR Loop NONE Isolation Valve Closure II-3.B.1 Capability of Operating 12/15/81 During a LOCA on ECCS Plant to Cope with Desiga Performance Basis Flooding Conditions VI-10.A Testing of Reactor Trip 08/31/81 II-3.C Safety-related Water Supply 12/15/81 System and Engineered (Ultimate Heat Sink (UHS))

l l

Safety Features Including Responso Time Testing II-4.B Proximity of C:pable NONE Tectonic Structures in VII-1.A Isolation of Reactor NONE Plant Vicinity Protection System from Non-Safety Systems, Including II-4.D Stability of Slopes 08/31/81R I

I Qualifications of Isolation Devices II-4.F Settlement of Foundations 06/22/81R and Buried Equipment VII-2 Engineered Safety Features NONE CESF) System Control Logic III-3.A Effects of fligh Water

. 08/31/81R and Design Level on $4ructures VII-6 Frequency Decay NONE 08/28/81 III-3.B Structural and Other NONE Consequences (e.g. Flooding VIII-4 Electrical Penetrations NONE of Safety-Related Equipment of Roactor Containment in Basements) of Failure of Underdrain Systems IX-3 Station Service and Cooling 10/30/81 Water Systems (3-25)

HADDAM NECK Ef (cont.)

All (Cont.)

SAR 1/

SER 2/

SAR 1/

SER 2/

TOPIC HO. TITLE RECEIVED Cot 1PLETE TOP!C NO. TITLE RECEIVED CCMPLETE III-3.C Inservice Inspections of 08/ 31/81 R VI-6 Containment Leak Testing NGNE Water Control Structures (MP A-04)

III-4.B Turbine Mi ssiles(MP B-46)

NDHE VI.7.B ESF Switchover frca NONE (SYS)

Injectico to Recirculation III-4.D Site Proxinity Missiles 06/25/8tR Mode (Automatic ECCS (Including Aircraft)

R ea li gnm en t )

III-7.D Containnent Structural 04/27/81R 10/16/81 VIII-1.A Potential Equipmont NONE Integrity Tests Failures Asso-iated with a Degraded Grid Voltage l

V-1 Compliance with Codes and NONE (MP B-23) j Standards (to CFR 50.55a) i (MP A-01,A-14)

IX-1 Fuel Stcrage OS/31/81R l

VI-1 Organic Materials and Post 01/31/82 IX-4 Boron Addition Systems 10/02/81R Accident Chemistry XI-1 Appendix I(M? A-02)

NONE IX-6 Fire Protection (MP B-02)

NONE XI-2 Radiological (Effluent NONE and Process) Monitoring Ell Systems (NRR S-67)

SAR 1/

SER 2/

TO.'IC HO. T:TLF RECEIVED COMPLETE XV-1 Decrease in Feodoater C9/30/31R Tenparatures, Increaso in III-4.A Tornado Missiles 08 /31/ 81 R Feedwater Flow, Increase in Steam Flow and Inadvertent III-4.C Internaly Generating 09/30/81 Opening of a Steam Genera-Missiles tor Relief or Safety Valve III-8.A Loose Parts Monitoring and NONE XV-2 Scectrum of Steam System 07/30/81R Core Barrel Vibration Piping Failures Inside and Monitoring (NRR B-60,C-12)

Outside of containm:nt (PWR)

IV-2 Reactivity Control Systems 06/30/81 Including Functional Design XV-3 Loss of External Load, OS/30/81R and Protection Against Turbine Trip, Loss of Single Failures Condencer vacuum, Closure of Main Steam Isolatico V-7 Reactor Coolant Pump HDHE Valve (BWR), and Sicam Overspeed(NRR B-68)

Prossure Regulator Failure (Closed)

VI-2.D Mass and Energy Release for NONE Possible Pipo Break Inside XV-4 Loss of Hen-Emergency A-C 09/30/81R Containment Power to the Station Auxiliaries VI-3 Containment Pressure and NONE nset Removal Capability XV-5 Loss of Normal Feedwater 09/30/81R Flow I

VI-4 Containment Isolation NGNE l

System (3-26)

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211 (Cont.)

SAR l/

SER 2/

SAR J/

SER 2/

TOPIC NO, TITLE RECEIVED COMPLETE TOPIC HD. TITLE RECEIVED COMPLETE XV-6 Feedwater System Pipe 09/30/81R XV-19 Loss-of-Coolant Accidents 09/30/81R Breaks Inside and Outside Resulting from Spectrum of Containment (PWR)

Postulated Piping Breaks Within the Reactor Coolant h

XV-7 Reactor Coolant Pump Rotor 09/30/81R Pressure Boundary Seizure and Reactor Coolant Pump Shaft Break 1/ SAR = Licensee Safety Analysis Report-Scheduled or Actual XV-8 Control Rod Misoperation 09/30/81R (Actual (Status 4b) when date is followed by R)

(System Malfunction or Operator Error) 2/ SER = Staf ff Safety Evaluation Roport (Status 4a,5,6,7)

XV-9 Startup or an Inactive 09/30/81R 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 09/30/81R System Malfunction that Results in a Decrease in in Baron Concentration in the Reactor Coolant (PWR)

XV-12 Spectrum of Rod Ejection 09/30/3fR Accidents (PWR)

XV-14 Inadvertent Operation of 09/30/81R ECCS and Chemical and Volume Control System Malfunction that Increases Reactor Coolant Inventory XV-15 Inadvertent Opening of a 09/30/81R PWR Pressurizer Safety-Rolief Valve or a BWR Safety / Relief Valve XV-16 Radiological Consequences NONE 09/28/88 of Failure of Small Lines Carrying Primary Coolant Outside Containment XV-17 Steam Generator 09/30/81 Tube Failure (PWR)

(3-27)

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SAR 1/

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TOPIC NO. TITLE RECEIVED COMPLETE TOPIC NO. TITLE RECEIVED COMPLETE II-2.C Atmospheric Transport and 06/30/81R 09/04/81 XI-2 Radiological (Effluent NOME Diffusion Characteristics and Process) Monitoring for Accident Analysis Systems (NRR B-67)

III-4.A Tornado Missiles 01/15/82 XV-1 Decrease in Foodwater

12/31/81 Tcmperature, Increase in III-4.C Internally Generated 02/15/82 Feedwater Flow, Increase Missiles in Steam Flcw and Inadvertent Opening of a III-8.A Loose Parts Monitoring NONE Steam Conwrator Relief and Core Barrel Vioration or Safety Valve Monitoring (NRR B-60,C-12)

XV-2 Spectrum of Steam Systen 06/30/81R IV-2 Reactivity Control Systems 09/17/81R (SYS)

Piping Failures Inside Including Functional Design (DOSES) and Outside of Containment 09/30/81 ard Protection Against (PWR)

Single Failures XV-3 Loss of External Load.

06/30/81R V-7 Reactor Coolant Pump NONE Turbine Trip, Loss of Overspeed(HRR B-68)

Condansar Vacuum, Closure o f Plai n Steam Itolation VI-2.D Mass ar.d Energy Release NONE Valve (BUR), and Steam for Possible Pipe Break Pressure Regulator Failure Inside Containment (Closed)

VI-3 Containment Pressure and NONE XV-4 Loss of Non-Emergency A-C 12/31/81 Heat Removal Capability Powar to the Station Auxiliaries VI-4 Containmant Isolation NONE XV-5 Loss of Normal Feadwater 06/30/81R (SYS)

System Flow VI-Containment Leak Testing NONE (MP A-04)

XV-6 Foodwater System Pipo 12/31/81 Breaks Inside and Outsida VI-7.B ESF Switchover from HDHE Containment (PWR)

(SYS)

Injection to Recirculation Mode (Automatic ECCS XV-7 Reactor Coolant Pump Rotor 06/30/81R Realignment)

Seizure and Reactor Coolant VIII-1.A Potential Equipment NONE Failures Associated with XV-8 Control Rod Misoperation 12/31/81 a Degraded Grid Voltage (System Malfunction or (MP B-23)

Operator Error)

IX-1 Fuel Storage 12/31/81 XV-*

Startup or an Inactive 06/30/81R Loop or Rceirculation Loop IX-4 Boron Addition System 08/31/81R at an Incorrect Temporature, and Flow XI-1 Appendix I(MP A-02)

NONE Controller Malfunction Causing an Increase in BWR Core Flow Rate of (3-30)

YANKEE R0WE pil (Cont.)

SAR 1/

SER 2/

TOPIC fiO. TITLE RECEIVED COMPLETE XV-10 Chemical and Volume Control 06/30/81R System Malfunction that Rosults in a Decrease in the Eeron Concentration in the Reactor Coolant (PWR)

XV-12 Spectrum of Rod Ejection 06/30/81R (SYS)

Accidents (PWR)

(DOSES) 08/30/81R XV-16 Inadvertent Operation of 06/30/81R ECCS and Chemical and Volume Control System I1alfunction that Increases Roactor Coolant Inventory XV-15 Inadvertent Opening of a 06/30/81R PWR Pressurizer Safety-Related Valve or a BWR Savety/Rolief Valve XV-16 Radiological Consequences 12/31/81 of Failur. of Small Lines Carrying Primary Coolant Outsids Containment XV-1, Steam Generator Tube 12/31/81 i

(SYS)

Failure (PWR) l (DOSES) 12/31/81 XV-19 Loss-of-Coolant Accidents-09/30/81 (SYS)

Resulting from Spectrum of (DOSES)

Postulated Piping Breaks 09/30/81 Within the Reactor Coolant Pressure Boundary l

1/ SAR = Licanseo Safety Analysis Report-Scheduled or Actual (Actual (Status 4b) when date is followed by R) 2/ SER = Staff Safety Evaluation Report (Status 4a,5,6,7) l l

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. TOPIC NO. TITLE RECEIVED COMPLETE TOPIC NO. TITLE RECEIVED COMPLETE-III-1 Classification of NONE II-1.A Execlusion Area Authority 06/22/81R (SYS)-

Structures, Components and and Control-Systems (Seismic and

' Quality)

II-1.B Population Distribution 06/16/81R III-2

' Wind and Tornado Loadings 08/06/61R II-1.C Potential Hazards or 07/15/81R Chances in Potential

-III-5.A Effcets of Pipe Break on 11/02/81 Harards Due to Structures. Systems and Transportation, Components Inside Institutional Industrial, Containment' and Military Facilities.

III-5.B P!po Break Outside 06/29/81R II-3.A Hydrolic Description.

06/16/81R Containment II-3.B Flooding Potential and 09/01/81' III-6 Solsmic Design-NONE Protection Requirements Ccnsiderations II-3.B.1 Capability of Operating 09/01/81

III-7.B Design Codes, De si gn NONE Plant to Cope with Design Criteria, Load Basis Flooding Conditions-Combinations, Land Reactor Cavity Design Criteria II-3.C Safety-related Water Supply 06/26/81R (Ultimate Neat Sink (UNS))

V-11.B RHR Interlock Requirements NONE (ELEC)

II-4.B Proximity of Capable NONE Tectonic Structures in VI-7.A.3 ECCS Actuation System NONE Plant Vicinity

'l VI-10.A Testing of Reactor Trip 06/25/81R II-4.D Stability of Slopes' NONE l

l System and Engineered Safety Features Including II-4.E Dam Integrity NONE l

Responso Time Testing II-4.F Settlement of Foundations 12/31/81-VII-1.A Isolation'of Reactor NONE and Buried Equipment Protection System from

'l Non-Safety Systems, III-3.A Effects of Nigh Water Level 12/31/81 Including Qualifications of on Structures i

Isolation Devices l

III-3.C Inservice Inspection of 12/31/81 VII-2 Engineered Safety Features NONE Water Control Structures (ESF) System Control Logic and Design III-4.8 Turbino Misslies 09/01/81 VII-3 Systems Required for Safe NONE III-4.D Site Proximity Missiles 09/15/81R (ELEC)

Shutdown (Including Aircrafts)

VII-6 Frequency Decay.

HONE 09/21/81 III-7.D Containment Structural 06/29/81R Integrity Tests IX-3 Station Service and Cooling 11/02/81 Water Systems V-1 Compliance with Codes and-NONE Standards (10 CFR 50.55a)

IX-5 Ventilation Systems 11/02/81 (MP A-01,A-14)

(3-33)

LACROSSE 21 (Cont.)

kil (Cont.)

SAR 1/

SER g/

SAR 1/

SER 2/

TCPIC NO. TITLE RECEIVYD COMPLETE TOPIC NO TITLE RECEIVED CCMPLETE VI-1 Organic riaterials and Post 12/31/31 XI-2 Radiological (Effluent and NONE Accident Chemistry Proccss) Monitoring Syste.as (NRR B-67)

IX-6 Fire Prot <.ction(MP B-02)

NONE XV-1 Decrease in Feadwater 08/21/81 Tamparature. Increase in Q11 Feedwater Flow, Increase SAR 1/

SER g/

In Stcam Generator Relief TOPIC NO. TITLE RECEIVED COMPLETE or Safety Valve II-2.C Atmospheric Transport anc 10/01/81 XV-3 Loss of External Load.

06/26/81R Diffusion Characteristics Turbine Trip, Loss of Con-for Accident Analysi s donsor Vacuum, closure of Main Stea, Isolation Valve III-4.A Tornado Missiles 11/02/81 (BWR), and Stam pressure l

Regulator Failure (Closed)

III-4.C Internally Generated 11/02/81 Missiles XV-4 Loss o f Non-Emergency A-C 06/26/81R III-8.A Loose Parts Montroring and NONE Power to the Station Core Barrel Vibration Auxiliaries Monitoring (NRR B-60,C-12)

XV-5 Loss of Normal Feudwater 08/21/81 IV-2 Reactivity Control Systems 11/02/81 Flow Including Functional Design and Protection Against XV-7 Reactor Coolant Pump Rotor 08/21/81 Single Failures Satzure and Reactor Coolant Pump Snaft Break VI-2.D Mass and Energy Release for NCHE Possible Pipe Break Inside XV-8 Control Rod Misoperation 08/21/81 Containments (System Malfunction or Operation Error)

VI-3 Containment Pressure and NONE Neat Removal Capability XV-9 Startup or an Inactive Loop 08/25/81R or Recirculation loop at an VI-4 Containment Isolation NDHE Incorreet Temperature, and (SYS)

System Floa Controller Malfunction Causing an Increase in BWR VI-6 Containment Leak Testing NONE Core Flcw Rate (MP A-04)

XV-11 Inadvertment Loading and 12/31/81 VIII-1.A A. Potential Equipment NONE Operation of a Fuel Failures Associated with a Assembly in an Improper Degraded Grid Voltage Position (MP B-23)

XV-13 Spectrum of Rod Drop 12/31/81 IX-1 Fuel Storage 11/02/81 (SYS)

Accidents (BWR)

(DOSES)

XI-1 Appendix IfMP A-02)

NONE i

(3-34)

LACROSSE Ril (Cent.)

SAR 1/

SER 2/

TOPIC NO. TITLE RECEIVED C0!1PLETE xv-14 Inadvertent Operation of 08/25/81R ECCS and Chemical and Volume Control System Malfunction that Increases Reactor Coolant Inventory XV-15 Inadvertent Opening of a 06/30/81R 39/2t/81 PWR Pressuring Safety-Relief Valve or a EWR Safety / Relief Valve XV-16 Radiological Consequences 08/21/81 of Failure of Small Lines Carrying Primary Coolant Outside Containment XV-18 Radiological Consequences 11/02/81 of Main Steam Line Failure Outside Containment (DWR)

XV-19 Loss of-Coolant Accidents 08/21/81 (SYS)

Resulting from Spectrum of (DOSES)

Postulated Piping Breaks 08/21/81 Within the Reactor Coolant Pressure Boundary' XV-20 Radiological Consequences 11/02/81 of Fuul Damaging Accidents (Inside and Outside Containment) l/ SAR = Licensee Safety Analysis Report-Scheduled or Actual (Actual (Status 4b) when date is followed by R) g/ SER = Staff Safety Evaluation Report (Status 4a,5,6,7)

(3-35)

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u.s. NUCLEAR REGULATORY COMMISSION BIBLIOGRAPHIC DATA SHEET l

NUREG-0485 Vol. 3 No. 12

4. T TLE AND SU8 TITLE (Add vokme Na,if alspecueneer/

2. (Leave b/ait!

Systematic Evaluation Program Status Summary Report

3. RECLPIENT4 ACCESSION NO.

7. AUTHOR (S)

5. DATE REPORT COMPLETED November 1981

9. PERFORMING ORGANIZATION NAME AND MAILING ADORESS (include 2,p Code /

DATE REPORT ISSUED Office of Management and Program Analysis

="m Ive^R Office of Nuclear Reactor Regulation November 1981 U.S. Nuclear Regulatory Comission

s. (te.<, be.,*>

Washington, D.C.

20555

8. (Leave bleski

12. SPONSORING ORGANIZATION NAME AND MAILING ADDRESS (include lip Codel Office of Management and Program Analysis

10. PROJECT / TASK / WORK UNIT NO.

Office of Nuclear Reactor Regulation it. CONTR ACT NO.

U.S. Nuclear Regulatory Comission Washington, D.C.

20555

13. TYPE OF REPORT PE RIOD COVE RED (inclus,re daars/

October 1 - 31, 1981 j

15. SUPPLEMENTARY NOTES

14. (teave crath/

16. ABSTRACT Q00 words'or less)

The Systematic Evaluation Program is intended to examine many safety related aspects I

of eleven of the older light water reactors. This document provides the existing status of the review process including individual topic and overall completion status.

17. KEY WORDS AND DOCUMENT ANALYSIS 17a DESCRIPTORS 17b. IDENTIFIERS /OPEN-ENDE D TERMS

18. AV AILABILITY STATEMENT 19 CUR TY A

(Thes report /

21. NO. OF PAGES Unlimited 2o. SECURITY CtASS (rn, p i 22.PR:CE Unclassified s

NRC FORM 335 (7 77)

\\

i i

UNITE 3 STATES NUCLEAR REGULATORY COMMisstON I

l WASHINGTON, D. C. 205SS g,,,,,,

OPPICIAL SUSINESS

.5. WCLE AR REMATOR Y FENALTY POR PRIV ATE USE,5300 C " * **' "

L J

)

1/ J ')'> 5 J 6 4 / 1 9 J ANN 5 A A9 A9 69C 9 U.:, NRL ACM d i,(, t) h' t. ', I

(.

N I r< ul Oc SK PUR O l t.

JC 2J555 w A.,H I ho l UN t

.

ML20033C444

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