ML20063H918
| ML20063H918 | |
| Person / Time | |
|---|---|
| Issue date: | 08/31/1982 |
| From: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| To: | |
| References | |
| NUREG-0485, NUREG-0485-V04-N07, NUREG-485, NUREG-485-V4-N7, NUDOCS 8209020198 | |
| Download: ML20063H918 (96) | |
Text
.
O T C) ss
=!s NUREG-0485 Ei Vol. 4, No. 7 s
July 31,1982
=5 g..
I l SYSTEMATIC EVALUATION PROGRAM STATUS
SUMMARY
REPORT UNITED STATES NUCLEAR REGULATORY COMMISSION am p
q
,,s s
4, 1
i i
Available from NRC/GPO Sales Program Superintendent of Documents Government Printing Office Washington, D. C. 20102 A year's subscription consists of 12 issues for this publicatiort 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
Vol. 4, No. 7 l
July 31,1982 i
l t
1 SYSTEMATIC EVALUATION PROGRAM i
STATUS
SUMMARY
REPORT l
Prepared for: 0FFICE OF NUCLEAR REACTOR REGULATION Prepared By: 0FFICE OF RESOURCE MANAGEMENT I
l UNITED STATES NUCLEAR REGULATORY COMMISSION 5-
=^^R bfl 2-fIV
(
L 2 3
,o William T. Russell, Chief Dennis M. Crutchfield, Chief v
Systematic Evaluation Program Brand Operating Reactors Branch 5 f
ar R or Regulation f e of u R
tor Regulation i
i
TABLE OF CONTENTS SECTION I SECTION 11 SECTION lli 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 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 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 3-29 to 3-32 COMPLETION (Graph)
SAN ONOFRE 2-35 to 2-38 LACROSSE 3-33 to 3-36 YANKEE 2-39 to 2-42 INTEGRATED PLANT 1-8 SAFETY ASSESSMENT SCHEDULE SEP TOPIC STATUS BY 1-9 REVIEW DIVISION l
(Summary Table) l SEP TOPIC STATUS BY 1-10 to 1 11 REVIEW DIVISION (Graphs)
SEP TOPIC fUBMITTALS 1-12 thru 1-13 BY LICENSEES (Graphs)
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SYSTEMATIC EVALUATION PROGRAM TOPIC LIST s
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p.2 veactivity Contral SysteaI5 Incladtag f unc' tonal ll1 4 A, Tornado *issiles design and Protect ton # gainst 5tngle Faj]urgs s
s 14 P m ul at ion D ist ri t>.t i n 5
at ng at unt s
e D d tat t a,
- D ct ent ial Mat ar%
>r i banys
.e C%1tance with Codes and 5tandards ('O Cf R
!!i-4 C. Internally Generated Missiles 50.35al r'
a i
e 11 '
9 Severe.eatber P*.cm.ma
(
J-2 Applicable Code Cases e
L ens tte weteortin ce t measa e,=+t s P eov e.
V-3 Overpressurtaatton Protection r
C.
t weri c T r a n
,7-ant D i f f as ' un L Nr ec-W-4 Piptng and Safe Cnd Integrity terut ics f or Acciet Anal,. '
W site Peceimity Missiles (locluding Aircraf t)
V-5 eesctor Coolant Pressure Soundary (RCFB)
Avat tatility et ct e arolo gi u l L at e in the
{l1-%
A. E f f ect s of P tg e H re4e no 5t ructures. Systems test age. Detection a
Let ru t R oo"'
and Cors onents I nstoe t ontainwnt V-6 pe4ctor vessel Integrity
! !- 3 6'ydrolog1C Descript te"
- 8. P ipe Breat Outside Lontainwnt V-7 Wesctor Coolant Punsi Overspeed
!!I-t seis4ic Design Considerations e
i
. # tcc ng v er-
.I and Protect ion kcawire.
V-8 Steam Generator ( ) Integrity l
eeats ll:-I A. Inservice laspect ion, including Prestressed V-9 Reactor Core Isolation Cooltag System (Best) uvability of Og erating e tant to tse Concrete (*mteinwnts with L tther Grouted
. t r> ses s y Mos e s f louding Condi t 'u'*
or ungrouted f endoes V-10 A. RHR Heat C achanger tube Failures
[
w t y-re tated.e. e W.,o t y !.,!!imate neat t
- u. Desir Codes. Desir Criteria. Load
- 8. RHR Reltablitty i ' '* WWI Coseinet sons, and keector Cavity vest e
- Criteri, V-Il A. Reyutrewnts for Isolation of t'19h and Low 1:-4
'op
,.q sc% )nry Pressure Systems L. Delaeination of Prestressed Concrete Con-iect 4.n e n ovi'Ae t a i n+ nt 5 t risct u res
- 8. RPR Interlock Requirewnts e n
- '1 C ill-n 4
c'.e Facts Monitoring and Lore Barrel
. s: g iul, n o..ite.
a f*iies of s
v e 4t io i Monitoring
.<r H. Cent rol Ecd Drive Mechanism tr* egrity W1-1 Organic Mater.8 als aid Pest Accident
( hemi st rj t eradiat ion Dawi9r. tae of Sensitired II-2
, A. Pressure-Suppression Type BWR Containments
+
5 tat riess 5 teel and e at tgue Res tstaru.e C. I nt 4r i t,
- 8. Subcocstartment Analy5ts
- U. Core ';wwnrts and f uel integrity F.
',et t iena nt of t w e-J..t ' ens eM L'ird C. Ice Condenser Containent e.g n e,
Ill-9,
Norport I nt egrit y D. Mass and Energy Release f or Possible P tpe lil ir,
- a. T herse l-Overload Prot ect von f or Potors r f Break Inside Conta6nent
! ! !- l mi+. it on 3 '
4*.res, s.* <r t s ed Mot or-nperated Walves ew i i en
.r*. !
- 1it s )
- 8. P w s e i r.rieel I nt egr it y VI-3 Containinent Pressure and Heat Removal
.1 4 a m 7, wt. s i r.
Capaglitty i
.4#f.
es
,f di on.
er tr.e1 on st ruce e es
' m' 6 rso and l'i'-(t r se V a l ve*.
W i-4 Lont inent isolation System e
e
'!!'1 vt r,t. eat I nt e grit y VI-5 Contestible Gas Control L Sirctura l and.* me on&g. enc es i e..,
l s ben. e, of tas ty 6*Iet 4 5 c,v,o
<t Vid Containwnt Leak festing i,
l are ct 54f et y I'clated
?!-Ic
- *.t ronwnt al Qualif icat t ne. a s i r ' 6 o f...
,f
,. + r,1r 4 r o e%
a l
u,u.ii, nt i
M DP si pO l n' Wl1
.1 449ta r
,.P{ rr,1 '. t r,c.
14f - 1
. L;: erst le with l t s Ihan AII loold Ir ervice l
tures 1-2
SYSTEMATIC EVALUATION PROGRAM TOPIC LIST TOF IC a T f fi t toclt f fift1 TOPIC f ititt VI 7. A
- 1. [CC5 De-e valuat ion t o Account f<
reased ygg g Instruments f er Manttoring R adiation and Process IV-5 Loss of Normal Feed.ater Flow Wessel Head f em erdiu" varta01es During Accidents XV-6 f eednater System Pipe Breaks Inside and Outside
- 2. Upper Plenue Inject i"n V !!-t f requency Decay Coctalnpent (PWit)
- 3. E CC5 Actuat son Syst**
!!!-?
Acceptability of 5 ming IM Design on SW-4 gy.7 Peactor Coolant ".g Rotor 5etture and P l a nt s Reactor Coolant Pug Shaf t dreat
- 4. Core Spray %:a 'e i e f ect t erness vill-1
- 4. Pct ential Equipment f ailures Associated u tth IV-8 Control Rod Mtsoreration (5ystem Malfunction f rom l e ec t ion t o # cu rcu la t ion a Degraded Grto Volta 9e or Operator Error)
V L I.B i V 5=it rhover r
"Me ( Autowt ic L LS dealignav-nt )
Vll!-2 Onsite [uergemy Pmer Systems - Diesel IV 9 5tartup or an Inauttve loop or RectrCulation v i-7.(
t CC5 Single I a Nn-e t eri on and N equire-benerat or Loop at an incorrect TetTerature, and f low ments f or L oo inq M - er t o Valves Controller Malfunct ton Causing an increase in e I nt erloo s on Vit!-3 A. Stat ion Battery Capacity f est Require =nts B A Core f ic= R at e i nc id i ng I ndet en w -
IV-10 Chemical ant
- Volume Control System Malfunction
- 8. t)C Power System 84 Voltage Ponitoring and that Results in a Decrease tn the Boron Concen-
- 1. Appendi s K - E lect rical Instruwntation Annu nc t at ion tration in the Reactor Coolant (Pift) and I.cntrol (11C) Re-reviews vill-4 Electrical Penetrations of Reactcr Contatnnent IV-f 1 Inadvertent Loading and Operabton of a Fuel
- 2. Fat lure Mode Analysis - ICC5 Assenely tn an Isoroper Posttton 11-1 f uel Storaye L The i f f ect of twu tw Isolation valve IV-12 Spectews of Rod Eject tui Accidents (PA)
Clowre Durtng a t or A on i tu Perf ornume 11-2 Overhead Handitng $ystems - Cranes 4 ; 1.0 L ong term Coot tog - e'assive f ai bres (e.g.,
IV-13 Spactrum of Rod Drop Accidents (BA)
I loodi ng of ReJundant Lo@onent s) 13-3 station Servtce and Cocitng Water Systems IV-14 Inadvertent Operation of ECCS and Chemical v !- 1.I ICCS Sum Design and Test for Rectrculation 11-4 Boron Addition System and volu e Cortrol 5ystem Malfunction that n
m de i f f ect e veness o
lacreases eactor Coolant Inventory 1-5 ent i bt m S et enes W.
7.F Accueulator Isolat tri Valves Pmer and Control IV-15 Inadvertent Opening of a Pd Pressurizer Safety-S y stem Des i gn 11-in F ire Protection Rettef Valve or a BWil Safety / Relief Valve e
e Vb8 (Detrol Room HJt;1tobt Int y I
Au s t li ary f eede at et System IV-16 RadiologtCal Consequences of f ailure of Small V I-9 Fein Steam L ine isolat ton Seal System - liwu 11-1 Appendin !
Lines Carrying Primary Coolant Outside Contatn-ment V 1 10 A. Testing of Reactor T rip Syste:s and ( nqineered ag.y padiological (l f f luent and Process ) M > nit oring gy.ly 5 team Generator Saf et y F eatures including Response II*
S v st ems Tube Fat ture (P.R) festing gl[g-1 Conduct of Operat *nns IV-18 Eadiological Consequences of Main Steam B. Shared (ogineered saf et y f eatures On-site Line Fatlure Gutside Centatnment (BA)
E mr rgency e'n=er, and Service Systems f or 33392 ggfegaards/InthW e edt hcurity Multiple Unit f acilities IV-Ig Lo s-of-Coolant Accidents A*sulting f rom A W-1 Decrease in f ee4saf er f e@eratu e. Increase in Spectrum of Postulated Piping Breaks Within r
vil-1 A. Isolation of Reactor Prote(t ton System f rom F eedeater l low, i ncre#5.e in Steam F inn and the Reactor Coolant Pressury Boundary Non-$df rty Systems. Including Qualifications i nadvert ent Dpr e e ng of a $ team t anerator kellef of I solat ion Deutces
,4f ety val ve XV-20 Radiologica1 Consequences of Fue10amaging or Accidents (Instde and Outside Contatnnent)
B. irto Uncertainty and Setpoint Analysis heview X V-i ec t rum of Steam 5.vstem Piping iallures Inside of uperating Data base gpyy 5 ent Fuel Cask Drop Accidents
,nd Outside of Cont ainn nt (r.w)
V!!-7 i nvincered Saf ety f eatures (157 ) System Control t v-3 a oss of E nternal Lead, Turbine f rip. L oss of IV-22 nticipate Transients without Scram tuot and Desi9n Condenser Vacuum, Clo are of Matn 5 team Isole*
IV-23 Multiple Tube Failures in Steam Generators t ton v alve (Bell), and St ese Pressure Re941ator Vll )
System Required 'or Laie Shutdown f ailure (Closed)
XV-24 Loss of All A C Parer "9'*C#
V11-4 t t tects of f ailure in %n-$af ety Related j
IVI Technical Specifications ysten. on Selected I no ncered Saf e? y 6 eatures XVII Operational QA Program
- Topic deleted from SEP progcam due to duplication by Three Mile island iTMH NRC Action Plan Unresolved Safety issue or ottier SEP Topic per May 7,1981 letter from G. Lainas to all SEP Lecensees.
1-3
I I
6 DESIGN BASIS EVENT REVIEWS I
t THIS SECTION DEFINES DESIGN BASIS EVENT (DBE) REVIEWS FOR THE ELEVEN SEP FACILITIES l
i i
N-
=- ' 3 !! L:5' p.c m 'c J5?
g,a s No og mpg t gs?
i f raas iert Grogs Ac c iare.t..ead T.reas *ect_ Grouns i.er M 9?d m 'a h T!'LE I
1 TQ
,J 1
Groos I ht Cecrease ta f ev&.a t er t emcera t ore s tat 3 m
o-1 t,e urease te vees. ster trperatore LB6 h-1 lacrease ta feco.atc-fio.
(n
..-3A o r roloaic cescr'ptioe o
NL as t im rease ic *emater f l on.
so 1
!ac rease ta s tea *. fio.
! ; - 3. 8 F loodicq pc teettet and pectection t
b-1 Increase ta ster flo.
h9 Start.a cf iasc t s.e loop aad flo.
renwirerects (capettlity c' operatias n-laadwerteet opeeveg o' stea-contro!!er ma'4 action claat to cope.ith cestee bests floodiae gere*ator reI tef /saf et y v a l ve Ib 3 Inad.erteat closure of main stes-c oad i t
- on )
h-s 5 :e r t.
of inac tive loc:
t sela tica va lve
-3.c sa'etr related mater supply (ultimate a.1:
So ter r.al'.ac tion cass tag heat stan )
Gr.of_jj n-5 Loss of enternal i t.a c
.*f ad-J ins a c' enteraet Icad 3.-3 J
Tu t tae trip t[ *.r,
4 l-4. A
'ec tanic prowtace r
r s.- 1
.< oiae t ru n-3 Loss of conderser es:sr
~
- 148 Fromies ty of capatie tectonic structu es r
t v-3 5 ss of coadcaser v ac.u-h-3 Steam cresure reg.14 tor f a41u ir rear plant e
ui stea* c esssre replater f ailu e sv-t Loss of feed.ater f l o.
! ! - 4 r.
- tstortcal seismicit, withia 200 en s r
e U-t
.os s o' f ees ater f l o.
of cleat b -t F ee s.s t er syste c tpe erest Gr_oq m e -li ha3iciosual Consecuent es c' a stacility cf stooes siaia 5ter Ltae Faure 4.ts'de a
r n.-
Ster line t reak tes ue cortaiarget L oa t a t nre rt
.:sstr Givu':ok I:1 a
'creada rustles
. u, u.
I.'
5
- er I t B re a k ow!s tdc (orta)aritat at (El'E';Ch~ - -
[ j -a [
?grtta, eiMiles GrosLD ha Loss c' AC po.ee to statioe 111-4 c leteenally generatea miss tes
.' i ha teu ce A: gome-to s tatio*
a.= 41 t ari es 111-4.0 Site proni tty etssiles (including a.. i l t a t es aircre t) e Gro(y u-7 toss of foeces coolset f i o.
.c
- i toss cf forces ccalert flo.
h7 Priracy er retor seizsre
- t !.;
ced aad toraado load'N i,. m 8e.
PP'*ary pri retor se1Fu e tv 7 Primary pw*C saaf t breaa r
n7 Prmary psc snaft creas Gec(yj ne vacoetrolled rod auertly.itNfee a1
< H.,
6-
,,acoe cclies rce assc41y. i t a-at pc.er dra.41 at po.ec p.-i inc ce t rellea ro$ assertij.itwara. e' b-Lacaatrolled rod asserely.ita-lo. pc.er start-up cra a1 lo. po.er s t art-up u6 Cort-ol rod risoreration p.-t Cor t r ' rod enoperattoe n 13 Spectre of rod orce acciderts hec tre of roc efection a:c tderts a
ur : sL_.
s.1-5pectre of loss of coolart accteerts Gro ; v!!:
u -:'
Rad'ological Comeo.eates cf Foet y c.,.m 3*'
Radiologtcal Consessences of Fuel Camag+ag Accideats (inside and Campes Acc taents ( tas tse sac outs ide conteteer* t ou ts ' de c oc ta t are r t )
Grog _j a h i Ira:*ertert opea>*; cf 2 0 sa'ety a
b-laadwerteat opeatag of Na eelief wal.e e.,
cress urizer relief value iro q_a n-1;
.:.ectent operat ice e' [LC5 r: 18 s o-N laad.erteat operattoe of ECCS or CvC1 r.alNaction that causes ac Gro 4_. 8_I n-11 Irac<erteet loading and operation cf increage in coClar-ipwcef or y a f uel aMe"%Iy ia en ta@ceper DCt i t i o8i ufg a.1 Not a&sltca:ie to P.h Grtn.p Ijj RKt appIMaD e to Bds I
., 3:j
..i Stea- >c.ator 'se, F a i t o e
.c r
1-4
STATUS DEFINITIONS G - Generic 4a-Draft SE Received From Review Branch These topics are being evaluated as part of on-going NRC generic review effort. The ongoing This status is used for internal NRC tracking of generic review and the SEP topic review will be topic review progress. The status indicates that closely integrated to improve the effectiveness a draf t topic safety evaluation is under mange-and efficiency of these efforts and to minimize ment review.
any impact on licensees. The status and conclu-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 S AR is under review and a Final N RC 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.
l Unresolved Safety Issue or another SEP Topic per the May 7,1981 letter from G. Lainas to all SEP licensees.
5 - Draf t SE Sent to Utility 0 - Topic Not Started A draft topic safety evaluation has been formally j
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 fReview Branch 6 - SE Response Received This status is used for internal NRC tracking by N R C of topic review progress. The status indicates that all information necessary to perform a The draft SE has been reviewed and licensee topic evaluation is not available and that ques-comments if any have been formally transmitted tions have been developed and sent to the SEP to the N RC.
branch.
7 - Topic Complete 2 - Questions Sent to Utility 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 j
have been formally transmitted to the licensee that the NRC draft safety evaluation (i.e. status 5) s as a request for additional information.
is correct, or (2) the licensees comments on the NRC draf t safety evaluation (i.e. status 6) have been re-3 - Question Response viewed and if appropriate incorporated into the final safety' evaluation, or (3) the licensee has not Received by NRC responded in the time requested, thus concurring The licensee has formally responded to the informa-that the draft safety evaluation is correct.
tion request issued by NRC regarding the topic.
1-5
SEP TOPIC STATUS
SUMMARY
REPORT w
\\
\\
NUMBER OF QUESTIONS QUESTION DRAFT SE SAR SE N
TOPICS TOPIC RECEIVED QUESTIONS
RESPONSE
RECEIVED RECEIVED DRAFT SE
RESPONSE
TOPIC
\\
GENERIC DELETED NOT FRGM SENT TO RECEIVED FROM FROM SENT TO RECEIVED COMPLETE
\\
(G)
(X)
STARTED REVIEW UTILITY BY NRC REVIEW LICENSEE UTILITY BY NRC (7)
PLANT NAME
\\
(0)
BRANCH (2)
(3)
ERANCH (4b)
(5)
(6)
\\
(1)
(4a)
\\
PALISADES 0
47 0
0 0
0 0
0 0
0 90 GINNA 0
45 0
0 0
0 0
0 0
0 92 OYSTER CREEK 0
54 0
0 0
0 0
0 23 1
59 DRESDEN 2 0
49 0
0 0
0 0
0 8
7 73 MILLSTONE 1 0
51 0
0 0
0 1
0 to 6
69 NADDAM NECK 0
47 1
0 0
3 7
6 9
2 62 YANKEE 3
48 1
0 0
5 4
9 5
3 59 LACROSSE 2
54 2
0 1
1 13 20 8
2 34 BIG ROCK POINT 2
52 1
0 1
9 4
8 10 4
46 SAN ONOFRE 3
48 2
0 1
6 2
11 8
5 51 DRESDEN 1 TOTALS THIS MONTH 10 495 7
0 3
24 31 54 81 30 635 TOTALS LAST MONTH 12 495 to 0
4 25 33 68 80 28 615 m NOTE: Totals do not include Dresden 1,
see page 2-6.
Also included i s May 7, 1981 deletion letter to all SEP licenseos, see footnote page 1-3, 1-6
SYSTEh/i ATIC EVALU ATION PROGRAM I
GOAL PH ASE lil/
Progress Toward Complet. ion
-1/ Not including Dresden 1
^CTUAL l
100 %
100 N
/
/ 7-31-82 '
,/
90 92'x.
/
88%
[
85%
1 m "th 3% ""
83%
80 75%
79%
70%
76%
70 67 72%
- 61'X p/
l
/
.Note: Prior to November 30,1981 the
$ 60 60 %
weighted percent did not include
- 81 U
j #"
generic topics in the progress c
toward completion.
Lu se
/
54%
o 50 f
e
/
/
50 %
47%
I
/
44%
9 p
y 40
,/
42%
/
40 %
/
36%
30
- J 4
30% I estimated)
The plant topic overall completion status (percent complete) is calculated Status Weighting Factor based upon the number of topic reviews to be performed (not including X
Not included deleted topics) and a weighted average of current topic review status.
G,0 0%
20 The calculation is performed using the following formula:
4a.4b 80 %
Percent Complete = Sum of Topics in Status x Weighting Factor of Status 5,6 90 %
7 100 %
10 Sum of Topics 0
10 11 12 1
2 3
4 5
6 6
7 8
9 10 11 12 1
2 3
4 5
6 7
8 9
FY-81 FY-82 17
YHTEGRATED PLANT SAFETY ASSESSMENT REPORV (IPSAR) SCHEDULE TOPIC ALL TOPIC ISSUE IPSAR IPSAR PLANT HAME TECHNICAL FOR ACRS TO EDO AND COMPLETE REVIEWS REVIEW COMMISSIGH
+
TO DL 1/
1 PALISADES 100 02/26/82C 04/01/82C 08/30/82 l
GINHA 100 02/24/82C 05/27/82C 08/30/82 V
j OYSTER CREEK 97 05/31/82 09/30/82 11/30/82 DRESDEN 2 98 06/30/82 10/29/82 12/30/82 MILLSTONE 1 98 06/30/82 11/30/82 01/31/83 N
YANKEE 88 08/30/82 01/31/83 03/31/83 LACROSSE
-84 09/30/82 01/31/83 03/31/83 HADDAM HECK' 93 08/31/82 02/28/83 04/29/83 BIG ROCK POINT 84 09/30/82 04/29/83 06/30/83 SAN ONOFRE 85 12/30/82 g/
04/29/83 06/30/83 1/ Schedule for each topic for each plant is specified.
OVERALL COMPLETION : 93%
2/ All topics except Seismic and High Energy Line Breaks are to be completed by 09/30/82.
1-8 i
SEP TOPIC STATUS by REVIEW DIVISION
SUMMARY
TABLE PLANT PALISADES GINNA OYSTER DRESDEN MILLSTONE HADDAM YANKEE LACROSSE BIG SAN TOTAL CREEK 2
1 NECK ROCK ONOFRE POINT (IAPM) J/
Michaels Wang Fell Cwalina Persinko Brown Boyle Michaels Scholl McKenna NO. OF TOPICS 137 137 137 137 137 137 137 137 137 137 1370 DELETED Z/
47 45 54 49 51 47 48 54 52 48 495 APPLICABLE 90 92 83 88 86 90 89 83.
85 89 875-57./
39
/
35
/
36
/
37
/
34
/
35
/
32
/
32
/
34
/
371 /
DL
/
/
/
/
/
/
/
/
/
/
/
/ 57
/ 30
/ 35
/ 36
/ 37
/ 38
/ 38
/ 35
/ 38
/ 40
/ 393 TECHNICAL
/
/
/
/
/
/
/
/
/
/
/
17
/
20
/
19
/
22
/
20
/
14
/
13
/
9
/
7
/
8
/
149 /
REVIEW DOE
/
/
/
/
' /
/
/
/
/
/
/
/ 17
/ 20
/ 19
/ 22
/
20-
/ 20
/ 20
/ 20
/ 17
/ 17
/ 192 ASSIGNMENT 1/
/
/
/
/
/
/
/
/
/
/
/
16
/
33
/
29
/
30
/
29
/
32
/
23
/
16
/
25
/
24
/
257 /
DSI
/
/
/
/
/
/
/
/
/
/
/
/ 16
/ 33
/ 29
/ 30
/ 29
/ 32
/ 31
/ 28
/ 30
/ 32
/ 290
/
1
/
/
/
/
/
/
/
/
/
90
/
92
/
83
/
88
/
86
/
COMPLETE
/
/
/
/
/
80
/
71
/
57
/
64
/
66
/
777 /
/
/
/
/
/
/
/ 90
/ 92
/ 83
/ 88
/ 86
/ 90
/ 89
/ 83
/ 85
/ 89
/ 875
/
/
/
/
/
/
/
/
/
/
/
TARGET DATE -
ALL TOPICS JAN 82 JAN 82 MAY 82 JUN 82 JUN 82 AUG 82 AUG 82 SEP 82 SEP 82 DEC 82 TECHNICAL REVIEWS TO DL 1/ Division of Licensing Integrated Assessment Project Manager
'Z/
Deleted as not applicable,.or duplicated by USI, TMI Action Plan, or another topic, i
3/ These schedules and assignments are consistent with NRR FY 1982-1984 Operating Plan.
I/_/
No. Completed / No. Assigned 1-9 STATUS AS OF JULY 31, 1982
PROGRESS OF TOPIC REVIEWS TOPICS DIVISION OF LICENSING 450 TARGET 400 350 ACTUAL 25e 2ss 150 108 -
5e 1
I I
I I
I I
I I
I I
I g
SEP OCT NOV DEC JAN FEB MAR APR MAY JUN JUL AUG SEP OCT/DEC 1
6 8
5 3
PER MONTH m 4
7 9
11 7
5 8
7 13 6
TE 337 348 361 371 377 385 398 393 N
298 385 314 325 332 337 345 352 365 371 8
7 PROGRESS OF TOPIC REVIEWS 0
TOPICS DIVISION OF ENGINEERING g
TARGET 298 175 s
ACTUAL 125 108 75 Se 25 1
I I
I I
l-1 I
l-1 I
I SEP OCT NOV DEC JAN FEB MAR APR MAY JUN JUL AUG SEP OCT/DEC TE 8
13 13 23 12 8
5 22 g
m B
8 3
6 7
8 1
5 38 9
T 9
189 122 145 157 165 170 192 TM m 72 72 75 81 88 96 97 182 148 149
PROGRESS OF TOPIC REVIEWS TOPICS OlVISION OF SYSTEE INTEGRATION
~~
TARGET 300 ACTUAL 250
/
200 150 100 50 1
I I
I I
I I
I I
I I
I g
SEP OCT NOV DEC JAN FEB MAR APR MAY JUN JUL AUG SEP OCT/DEC
~
~
~
~
~
PER MONTH ETta 14 27 28 13 17 13 13 27 25 6
TARCET 197 223 253 275 283 286 288 290 VE N 88 115 143 156 173 186 199 226 251 257
^
T PROGRESS OF TOPIC REVIEWS 0
TOPICS TOTAL PROJECT TARGET 900
- - 800
~~
ACTUAL 7sg 600 500 400 300 200 100 1
I I
I I
I I
I I
I I
I O
SEP OCT NOV DEC JAN FEB MAR APR MAY JUN JUL AUG SEP OCT/DEC TARGET 37 50 56 55 26 19 12 27 gg ETta 18 34 40 30 31 26 22 39 76 21 TARCET 630 680 736 791 817 836 858 875 Ella 458 492 532 562 593 619 641 680 756 777
LICENSEE TOPIC SUBMITTALS SlJBMllTALS DIVISION OF LICENSING 4g TARGET 35
_/
3B
/
ACTlJAL p
25
/
2e 15 la 5
1 I
I I
I I
I I
I I
g JUN JUL AUG SEP OCT NOV DEC JAN FEB MAR APR MAY JtN JUL/DEC TARCET 2
4 1
3 8
3 PG M Atita 0
3 1
1 4
6 1
0 5
2 2
3 9
~
~
~
~
~
~
CUMULATIVE ACRE B
3 4
5 9
15 16 16 21 23 25 28 28 9
7 LICENSEE TOPIC SUBMITTALS O
TOPICS DIVISION OF ENGINEERING TARGET 7g 00
/
ACTUAL 58 48 l
3e 2e 18 1
I I
I I
I I
I I
I I
g JUN JUL AUG SEP OCT NOV DEC JAN FEB MAR APR MAY JtN JIL/DEC TARGET 3
2 1
1 1
1 j
Acita 1
8 1
5 7
15 5
1 13 8
3 2
8 TARGET 56 59 61 62 63 64 65 actin 1
9 18 15 22 37 42 43 56 56 59 61 61 i
i LICENSEE TOPIC SUBMITTALS StBMITIALS DIVISIONOFSYSTEMSINTEGRATION 128 II8 TARGET 188 ACTUAL 80 f
78 68 50 48 38 28
'l -- --
1 I
I I
I I
I I
I I
I JUN JUL AUG SEP OCT NOV DEC JAN FEB MAR APR MAY JIN Jll/DEC imT 8
3 6
3 1
8 g
m i
18 3
31 3
2 7
12 7
6 6
3 8
Tmi 76 84 87 93 96 97 97 N
1 11 14 45 48 58 57 69 76 82 88 91 91 8
7 LICENSEE TOPIC SUBMITTALS 0
TOPICS TOTAL PROJECT TARGET 200 175 ACTUAL 158 125 l
180 i
75 50 l
25 1
I I
I I
I I
I I
I I
g JtN J11 AUG SEP OCT NOV DEC JAN FEB MAR APR MAY JUN Jll/DEC 13 9
8 7
2 4
Tmi PB M m
2 21 5
37 14 23 13 13 25 8
11 8
8 l
imi 154 167 17S 184 191 193 197 m
2 23 28 65 79 182 115 128 153 161 172 180 188
_e.
a l
l Z
O
>0W 00 1
1
BIG ROCK P0 INT FACILITY: BIG ROCK POINT 1 TOPIC NO.
REVIEW STATUS REMARKS DIV/BR LICENSEE: CONSUMERS PCWER 11-1 A.
DL/SEPB 7
CPCo to NRC 09/02/80 REGION / LOCATION: 4 MILES HORTH EAST OF CHARLEVOI, MICH.
II-1 B.
DL/SEPB 7
CPCo to NRC 09/02/80 DOCKET 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
HRC to CPCo 08/03/81 OL NUMBER: DPR-6 II-2 B.
X NRC to CPCo 05/07/81 N.S.S.S.
GE.
II-2 C.
DSI/AEB 7
HRC TO CPC0 06/23/82 A/E FIRM: BECH.
II-2 D.
X HRC to CPCo 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL II-3 A.
DE/HGEB 3
CPC0 TO NRC 05/13/82 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD II-3 B.
DE/HGEB 3
CPCO TO NRC 05/13/82 OPERATING REACTORS PROJECT MANAGER:
R.
EMCH II-3 B.
1.
DE/HGEB 3
CPCO TO NRC 05/13/82 SCHOLL k iN INTEGRATED ASSESSMENT PROJECT MANAGER:
R.
II-3 C.
DE/HGEB 3
CPC0 TO HRC 05/13/82 w
II-4 DE/GSB 7.
HRC to CPCo 06/08/81 KEY FOR STATUS CODES II-4 A.
DE/GSB 7
HRC to CPCo 06/08/81 G - CENERIC 4a-DRAFT SE RECEIVED II-4 B.
DE/GSB 3
CPCO TO NRC 10/10/80 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
NRC TO CPCO 07/06/82 STARTED 5 - DRAFT SE SENT II-4 E.
X HRC to CPCo 11/16/79 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.
DE/HGEB 7
NRC TO CPCO 07/20/82 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC III-1 DL/SETB 5(SYS)
HRC TO CPCO 04/16/8?
TO UTILITY DL/SEPB 7CELEC) Part of VII-3 08/19/81 7 - TOPIC COMPLETE 3 - GUESTION RESPONSE III-2 DL/SEPB 3
CPCo to NRC 07/09/81 RECEIVED BY NRC (2-2)
BIG ROCK POINT TOPIC NO.
PEVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR III-5 A.
DE/SEB 3
CPCo to NRC 08/09/80 111-10 B.
X HRC 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/ACEB 4b CPCo to NRC 12/21/81 III-11 X
NRC to CPCO 05/07/81 III-4 A.
DSI/ASB 4B CPCO TO NRC 06/16/82 III-12 X
NRC to CPCo 05/07/81 III-4 B.
DE/NTEB 4B CPCO TO NRC 06/09/82 IV-1 A.
DL/SEPB 7
NRC to CPCo 10/08/81 III-4 C.
DSI/ASB 4B CPC0 TO HRC 06/03/82 IV-2 DSI/ICSB 7
CPCo to NRC 12/22/81 III-4 D.
DE/SAB 4A 07/12/82 IV-3 X
NRC to CPCo 05/04/81 III-5 A.
DL/SEPB 0
V-1 X
NRC to CPCo 11/27/81 III-5 B.
DL/SEPB 4B CPCO TO NRC 05/21/82 V-2 X
NRC to CPCo 11/16/79 III-6 DL/SEPB 2
NRC to CPCo 01/19/82 V-3 X
NRC to CPCo 05/07/81 III-7 A.
X HRC to CPCo 05/07/81 V-4 DE/MTEB 3
CPC0 TO NRC 05/28/82 III-7 B.
DL/SEPB 3
CPCo to NRC 07/09/81 V-5 DL/SEPB 5
NRC TO CPC0 03/19/82 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 7
NRC TO CPC0 03/17/82 V-7 X
NRC to CPCo 11/16/79 III-8 A.
DS' 5
HRC TO CPCO 03/02/82 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 11/16/79
,III-8 C.
DL/SEPB 7
NRC TO CPCO 06/23/82 V-10 A.
DL/SEPB 7
NRC to CPCo 10/09/79 III-8 D.
X NRC to CPCo 05/07/81 V-10 B.
DL/SEPB 6
CPCO TO HRC 03/30/82 III-9 X
NRC to CPCo 05/07/81 V-11 A.
DL/SEPS 6(Elec) CPCo to NRC 11/12/81 III-10 A.
DL/SEPB 7
NRC TO CPC0 03/30/82 V-11 B.
DL/SEPB 6(SYS)
CPCO TO NRC 03/30/82 7(Elec) NRC to CPCo 08/19/81 (2-3)
BIG ROCK POINT TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.
DL/SEPB 7
NRC to CPCo 10/09/79 VI-7 D.
DL/SEPB 7
NRC to CPCo 08/17/78 V-13 X
NRC to CPCo 05/07/81 VI-7 E.
X HRC to CPCo 05/07/81 VI-1 DE/CEB 4B CPC0 TO NRC 03/16/82 VI-7 F.
X NRC to CPCo 11/16/79 VI-2 A.
X HRC to CPCo 05/07/81 VI-8 X
HRC to CPCo 05/07/81 VI-2 B.
X NRC to CPCo 05/07/81 VI-9 X
HRC to CPCo 11/16/79 VI-2 C.
X HRC to CPCo 11/16/79 VI-1L A.
DL/SEPB 5
HRC TO CPCO 06/22/82 VI-2 D.
DSI/CSB 5
NRC TO CPCO 06/10/82 VI-10 B.
X NRC to CPCo 11/16/79 VI-3 DSI/CSB 5
NRC TO CPCO 06/10/82 VII-1 A.
DL/SEPB 5
NRC TO CPC0 03/05/82 VI-4 DSI/CSB 6(SYS)
CPC0 TO NRC 07/20/82 VII-1 B.
DL/SEPB 7
NRC to CPCo 08/17/78 DL/SEPB 7(Elec) NRC to CPCo 11/24/81 VII-2 DL/SEPB. 7 NRC to CPCo 02/01/82 VI-5 X
NRC to CPCo 05/07/81 VII-3 DL/SEPB 6(SYS)
CPCO TO NRC 03/30/82 VI-6 DSI/CSB G
NRC to CPCo 05/07/81 DL/SEPB 7(Elec) NRC to CPCo 08/19/81 VI-7 A.
1.
X NRC to CPCo 11/16/79 VII-4 X
HRC to CPCo 05/07/81 VI-7 A.
2.
X NRC to CPCo 05/07/81 VII-5 X
NRC to CPCo 05/07/81 VI-7 A.
3.
DL/SEPB 6
CPCO TO NRC 06/04/82 VII-6 DL/SEPB 7
HRC to CPCo 09/21/81 VI-7 A.
4.
DSI/RSB 7
NRC to CPCo 04/10/79 VII-7 X
NRC to CPCo 11/16/79 VI-7 B.
DSI/RSB 7(Elec) CPCo to HRC 05/20/82 VIII-1 A.
DSI/PSB 7
NRC TO CPCO 07/08/82 7(SYS)) CPCo to NRC 05/20/82 VIII-2 DL/SEPB 7
HRC TO CPCO 06/22/82 VI-7 C.
DL/SEPB 7
HRC to CPCo 08/05/81 VIII-3 A.
DL/SEPB 7
CPCo to NRC 04/22/81 VI-7 C.
1.
DL/SEPB 7
HRC to CPCo 02/22/82 VIII-3 B.
DL/SEPB 7
NRC to CPCo 02/22/82 VI-7 C.
2.
DL/SEPB 7
NRC to CPCo 08/05/81 VIII-4 DL/SEPB 5
HRC TO CPCO 07/01/80 VI-7 C.
3.
X NRC to CPCo 11/16/79 (2-4)
BIG ROCK POINT TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 7
NRC TO CPC0 06/02/82 XV-10 X
NRC to CPCo 11/16/79 IX-2 X
NRC to CPCo 05/07/81 XV-11 DSI/CPB 7
NRC to CPCo 12/02/81 IX-3 DL/SEPB 7
NRC TO CPC0 07/20/82 XV-12 X
NRC to CPCo 11/16/79 IX-4 X
NRC to CPCo 11/16/79 XV-13 DSI/CPB 7(Sys)
NRC to CPCo 12/02/81 DSI/AEB 7(DOSES) NRC to CPCo 01/12/82 IX-5 DL/SEPB 4B CPCO TO HRC 06/11/82 XV-14 DSI/RSB 7
NRC to CPCo 08/18/81 IX-6 DE G
NRC to CPCo 05/07/81 XV-15 DSI/RSB 7
NRC to CPCo 08/18/81 X
X NRC to CPCo 05/07/81 XV-16 DSI/AEB 7
NRC to CPCo 12/28/81 XI-1 X
HRC to CPCo 12/04/81 XV-17 X
NRC to CPCo 18/16/19 XI-2 X
HRC to CPCo 12/04/81 X V-18 DSI/AEB 6
CPC0 TO NRC 07/19/82 XIII-1 X
HRC to CPCo 05/07/81 XV-19 DSI/RSB 7(Sys)
HRC to CPCo 08/18/81 XIII-2 DL/SSPB 7
NRC to CPCo 03/11/81 DSI/AEB Gb(Doses)CPCo to NRC 06/02/82 XV-1 DSI/RSB 7
NRC TO CPCO 06/25/82 XV-20 DSI/AEB 7
NRC to CPCo 01/12/82 XV-2 X
NRC to CPCo 11/16/79 XV-21 X
NRC to CPCo 05/07/81 XV-3 DSI/RSB 7
NRC to CPCo 06/18/82 XV-22 X
NRC to CPCo 05/07/81 XV-4 DSI/RSB 7
NRC to CPCo 10/16/81 XV-23 X
NRC to CPCo 05/07/81 XV-5' DSI/RSB 7
NRC to CPCo 02/08/82 XV-24 X
NRC to CPCo 05/07/81 XV-6 X
NRC to CPCo 11/16/79 XVI X
NRC to CPCo 11/05/80 XV-7 DSI/RSB 7
NRC TO CPC0 03/11/82 XVII DL 7
NRC to CPco 08/17/78 XV-8 DSI/CPB 7
NRC to CPCo 12/31/81 XV-9 DSI/R$B 7
NRC TO CPCO 04/07/82 (2-5)
DRESDEN1 FACILITY: DRESDEN 1 LICENSEE: COMMONWEALTH EDISON REGICN/ LOCATION: 9 MILES EAST OF MORRIS, ILL.
DOCKET NO.
05000010 POWER CAPACITY: 700(THERMAL) 200(ELECTRICAL)
GE.
A/E FIRM: BECH.
SYSTEMATIC EVALUATION PROCRAM BRANCH CHIEF: W.
RUSSELL OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD OPERATING REACTORS PROJECT MANAGER: P. O'CONNOR By lettor 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, 1931 lotter on SEP redirectien the licen-soo stated that the Dresden 1 SEP review is not being actively pursued, i.e.
defered.
(2-6) 3
DRESDEN 2 FACILITY: DRESDEN 2 TOPIC NO.
REVIEW STATUS REMARKS DIV/BR LICENSEE: COMM0HWEALTH EDISDN II-1 A.
DE/SAB 7
NRC to Ceco 10/06/81 REGION / LOCATION: 9 MILES EAST OF MORRIS, ILL.
11-1 B.
DE/SAB
't NRC to CECO 10/06/81 DOCKET NO.: 05000237 II-1 C.
DE/SAB 7
HRC TO CECO 06/30/82 POWER CAPACITY: 2527(THERMAL) 0794(ELECTRICAL)
II-2 A.
DSI/AEB 7
HRC to CECO 04/24/81 OL NUMBER: DPR-19 II-2 B.
X NRC to CECO 05/07/81 H.S.S.S.*
GE.
II-2 C.
DSI/AEB 7
NRC to CPCo 08/26/81 A/E FIRM: StL.
II-2 D.
X NRC to Ceco 05/07/61 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W.
RUSSELL II-3 A.
DE/HGEB 5
NRC TO CECO 06/21/82 OPERATING REACTORS BRANCH CHIEF:
D.
CRUTCHFIELD II-3 B.
DE/HGEB 5
NRC TO CECO 06/21/82 CPERATING REACTORS PROJECT MANAGER: P. O'CONNOR II-3 B.
1.
DE/HGEB 5
NRC TO CECO 06/21/82 INTEGRATED ASSESSMENT PROJECT MANAGER: G. CWALIH ITM" II-3 C.
DE/HGEB 5
NRC TO CECO 06/21/82' KEY FOR STATUS CODES II-4 DE/GSB 7
HRC 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 7
HRC to CECO 07/09/81 Ab-SAR RECEIVED FROM 0 - TOPIC HOT LICENSEE II-4 C.
DE/GSB 7
HRC to CECO 06/08/81 STARTED 5 - DRAFT SE SENT II-4 D.
DE/HGEB 7
NRC TO CECO 06/30/82 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 E.
DE/HGEB 5
NRC to CECO 02/09/82 6 - SE RESPONSE RECEIVED 2 - QUESTIDHS SENT BY HRC II-4 F.
DE/HGEB 7
HRC TO CECO 06/30/82 TO UTILITY 7 - TOPIC COMPLETE III-1 DL/SEPB 6(SYS)
CECO TO NRC 07/16/82 3 - QUESTION RESPONSE DL/SEPB 7(Elec) Part of VII-3 07/07/81 RECEIVED BY HRC III-2 DL/SEPB 7
NRC TO CECO 06/18/82 (2-7)
DRESDEN 2
TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR 111-3 A.
DE/SEB 7
NRC 10 CECO 06/04/82 III-10 B.
X NRC to CECO 11/16/79 III-3 B.
X NRC to CECO 11/16/79 III-10 C.
DL/SEPB 7
NRC to. Ceco 05/22/79 III-3 C.
DE/HGEB 7
.NRC TO CECO 06/30/82 III-11 X
NRC to Ceco 05/07/81 III-4 A.
DSI/ASB 7
NRC TO CECO 06/28/82 III-12 X
NRC to Ceco 05/07/81 III-4 B.
DE/MTEB
-5 NRC TO CECO 05/26/82 IV-1 A.
DL/SEPB 7
NRC to Ceco 10/26/81 III-4 C.
DSI/ASB 7
NRC TO CECO 06/28/82 IV-2 DSI/ICSB 7
CECO to NRC 12/04/81 III-4 D.
DE/SAB 7
NRC to CECO 02/22/82 IV-3 DE/MTEB 7
NRC to CECO 01/22/82 III-5 A.
DL/SEPB 5
HRC TO CECO 06/29/82 V-1 X
NRC to Ceco 11/27/81 III-5 B.
DL/SEPB 6
Ceco to NRC 07/16/82 V-2 X
NRC to CECO 11/16/79 III-6 DL/SEPB 7
NRC TO CECO 06/30/82 V-3
.X NRC te Ceco 11/16/79 III-7 A.
X NRC to CECO 11/16/79 V-4 DE/MTEB 7
NRC TO CEC 0 06/29/82 III-7 B.
DL/SEPB 5
NRC TO CECO 05/20/82 V-5 DL/SEPB 7
NRC TO CECO 06/23/82 III-7 C.
X NRC to CECO 11/16/79 V-6 DL/SEPB 7
NRC to CECO 03/05/80 III-7 D.
DE/SEB 7
NRC TO CECO 04/13/82 V-7 X
NRC to Ceco 11/16/79 l
III-8 A.
DSI-7 NRC to CECO 02/26/82 V-8 X
NRC to Ceco 11/16/79 III-8 B.
X NRC to CECO 09/11/80 V-9 X
NRC to Ceco 11/16/79 III-8 C.
DL/SEPB 7
NRC TO CECO 06/29/82 V-10 A.
DL/SEPB 7
NRC to Ceco 11/08/79 III-8 D.
X.
NRC to Ceco 05/07/81 V-10 B.
DL/SEPB 7
NRC to Ceco 04/24/81 III-9 X
NRC to Ceco 05/07/81 V-11 A.
DL/SEFB 7
HRC to Ceco 07/10/81 III-10 A.
DL/SEPB 7
NRC to Ceco 06/26/81 V-11 B.
DL/SEPB
-7(Sys)
NRC to Ceco 04/24/81 DL/SEPB 7(Elec) NRC to CECO 07/10/81 l
l l
(2-8)
DRESDEN 2 TCPIC HO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.
DL/SEPB 7
NRC to CECO 04/16/81 VI-7 D.
DL/SEPB 7
NRC to CECO 08/17/78 V-13 X
NRC to CECO 05/07/81 VI-7 E.
X NRC to Ceco 05/07/81 VI-1 DE/CEB 7
NRC TO CECO 06/30/82 VI-7 F.
X NRC to CECO 11/16/79 VI-2 A.
X NRC to Ceco 05/07/81 VI-8 X
HRC to CECO 05/07/81 VI-2 B.
X NRC to Ceco 05/07/81 VI-9 X
HRC to Ceco 11/16/79 VI-2 C.
X HRC to CECO 11/16/79 VI-10 A.
DL/SEPB 7
NRC to Ceco 07/03/81 VI-2 D.
DSI/CSB 6
CECO TO NRC 04/06/82 VI-10 B.
DL/SEPB 7(Sys)
CECO TO NRC 11/03/81 DL/SEPB 7(Elec) NRC TO CECO 04/22/82 VI-3 DSI/CSB 6
CECO TO HRC 04/06/82 VII-1 A.
DL/SEPB 7
NRC to Ceco 08/05/81 VI-4 DSI/CSB 6($YS)
CECO TO NRC 05/21/82 DL/SEPB 7(ELEC) NRC TO CECO 06/23/82 VII-I 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 11/03/81 VI-6 DSI/CSB 7
NRC TO CECO 06/25/82 VII-3 DL/SEPB 7(Sys)
NRC to Ceco 04/24/81 DL/SEPB 7(Elec) NRC to Ceco 07/07/81 VI-7 A.
1.
X NRC to Ceco 11/16/79 VII-4 X
NRC to Ceco 05/07/81 VI-7 A. 2.
X NRC to CECO 11/16/79 VII-5 X
NRC to Ceco 05/07/81 VI-7 A. 3.
DL/SEPB 7
CECO to NRC 11/03/81 VII-6 DL/SEPB 7
NRC to Ceco 08/26/81 VI-7 A. 4.
DSI/RSB 7
NRC to Ceco 02/22/82 VII-7 X
NRC to Ceco 11/16/79 VI-7 B.
X HRC to CECO 11/16/79 VIII-1 A.
DSI/PSB 7
NRC TO CECO 06/15/82 VI-7 C.
DL/SEPB 7
NRC to CECO 03/13/81 VIII-2 DL/SEPB 7
NRC to Ceco 06/26/81 VI-7 C.
1 DSI/PSB 7
NRC TO CECO 02/05/82 VIII-3 A.
DL/SEPB 7
NRC to CECO 07/07/81 VI-7 C. 2.
DL/SEPB 7
NRC to CECO 03/13/81 VIII-3 B.
DL/SEPB 7
NRC to Ceco 06/26/81 VI-7 C. 3.
X NRC to Ceco 11/16/79 VIII-4 DL/SEPB 7
NRC to CECO 11/30/81 (2-9)
DRESDEN 2 TOPIC NO.
REVIEW STATUS REMARKS TOPIC HO.
REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 7
NRC TO CECO 05/05/82 XV-10 X
NRC to Ceco 11/16/79 IX-2 X
NRC to Ceco 05/07/81 XV-11 DSI/CPB 7
NRC to Ceco 02/08/82 IX-3 DL/SEPB 7
CECO to NRC 11/03/81 XV-12 X
NRC to CECO 11/16/79 IX-4 X
NRC to CECO 11/16/79 XV-13 DSI/CPB 7(Sys)
NRC to Ceco 02/08/82 DSI/AEB 7(Doses) HRC to CECO 12/28/81 IX-5 DL/SEPB 6
CECO TO HRC 07/12/82 XV-14 DSI/RSB 7
NRC to CECO 12/15/81 IX-6 DE/CEB 7
NRC TO CECO 06/23/82 XV-15 DSI/RSB 7
NRC to CECO 01/04/82 X
X NRC to CECO 11/16/79 XV-16 DSI/AEB 7
Ceco to NRC 10/20/81 XI-1 X
HRC to Ceco 12/04/81 XV-17 X
HRC to CECO 11/16/79 XI-2 X
NRC to CECO 12/04/81 XV-18 DSI/AEB 6
CECO TO NRC 05/21/82 XIII-1 X
NRC to Ceco 05/07/81 XIII-2 DL/SSPB 7
NRC to CECO 04/14/82 XV-19 DSI/RSB 7(Sys)
HRC to Ceco 12/07/81 DSI/AEB 7(DOSES) CECO to NRC 01/05/82 XV-1 DSI/RSB 7
NRC to CECO 12/29/81 XV-20 DSI/AEB 7
NRC to Ceco 11/20/81 XV-2 X
NRC to CECO 11/16/79 XV-21 X
NRC to Ceco 05/07/81 XV-3 DSI/RSB 7
NRC to Ceco 12/07/81 XV-22 X
NRC to CECO 05/07/81 XV-4 DSI/RSB 7
HRC to CECO 12/07/81 XV-23 X
NRC to Ceco 11/16/79 XV-5 DSI/RSB 7
HRC to Ceco 12/15/81 XV-24 X
NRC to CECO 05/07/81 XV-6 X
NRC to Ceco 11/16/79 XVI X
NRC to Ceco 11/05/80 XV-7 DSI/RSB 7
NRC to Ceco 01/04/82 XVII DL 7
HRC to Ceco 11/20/79 XV-8 RSI/CPB 7
NRC to Ceco 02/08/82 XV-9 DSI/RSB 7
NRC to CECO 12/15/81 (2-10)
GINNA FACILITY: GINNA TOPIC N3.
REVIEW STATUS REMARKS DIV/BR LICENSEE: ROCHESTER GAS & ELECTRIC 11-1 A.
DE/SAB 7
NRC to RGE 07/17/81 REGION /LOCATIDH: 15 MILES NORTH EAST OF RGGHESTER, 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/AEB 7
NRC to RGE 1/03/81 OL NUMBER: DPR-18 II-2 B.
X NR 05/07/81 N.S.S.S.: WEST.
II-2 C.
DSI/AEB 7
NR oR E
/24/81 A/E FIRM: GIL.
II-2 D.
R RGE 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL II-3
/HGEB NRC TO RGE 05/27/82 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD II GB 7
NRC TO RGE 05/27/82 OPERATING REACTCRS PROJECT MANAGER: J.
LYONS DE/HGEB 7
NRC TO RGE 05/27/82 INTEGRATED ASSESSMENT PROJECT MANAGER: A. {0 b 1-
' II-3 C.
GB 7
NRC TO RGE 05/27/82 1
JL "
I -4 DE B
7 NRC to RGE 07/09/81 KEY FOR ST_AT4T~dOD A
'NjRCtoRGE
~~
Tj' g,
-4 A
}
E/ GS3 7
06/08/81 G - GEN O FT SE RECEIVED I
DE/GSB b RC to RGE 07/09/81 FROMREVIEWBftN(Hj NRCtoRGE 06/08/81 4b-SAR RECEIVEDj l
II-4 C. $
Dd G X - DL E b.'
r RO
, DE EB 7
NRC to RGE 02/19/82 0 - TO OT LICENSEE STARTED 5 - DRAFT SE SENT X
NRC to RGE 11/16/79 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.
DE/HGEB 7
NRC to RGE 02/19/82 2 - QUESTIONS SENT B
f III-1 DL/SEPB 7(Sys)
NRC to RGE 12/17/81 TO UTILITY i
DL/SEPB 7(Elec) NRC to RGE 04/02/81 7 - TOP E
3 - QUESTION RESPONSE III-2 DL/SEPB 7
HRC TO RGE 04/21/82 RECEIVED BY NRC W - DATA OR NEXT MONTH (NOVEMBER)
(2-11)
GINNA TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS i
DIV/BR DIV/BR 111-3 A.
DE/ S EB 7
NRC TO RGE 03/03/82 111-10 8.
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 l
III-3 C.
DE/NGEB 7
NRC TO RGE 05/27/82
.III-11 X
NRC to RGE 05/07/81 III-4 A.
DSI/AEB 7
NRC TO RGE 04/16/82 III-12 X
NRC to.RGE 05/07/81 III-4 B.
DE/MTEB 7
NRC to RGE 02/19/82 IV-1 A.
DL/SEPB 7
NRC to RGE 05/29/79 i
III-4 C.
DSI/ASB 7
NRC to RGE 02/17/82 IV-2 DSI/ICSB 7
NRC to RGE 05/26/81 III-4 D.
DE/SAB 7
NRC to RGE 07/21/81 IV-3 X
NRC to RGE 05/07/81 j
III-5 A.
DL/SEPB 7
NRC to RGE 02/22/82 V-1 X
NRC to RGE-11/27/81 III-5 B.
DL/SEPB 7
NRC to RGE 09/04/81 V-2 X
NRC to RGE 11/16/79 III-6 DL/SEPB 7
.NRC to RGE 02/17/82 V-3 X
HRC to RGE 05/07/81 III-7 A.
DL/SEPB 7
NRC TO RGE 04/16/82 V-4 X
NRC to RGE 05/07/81 III-7 B.
DL/SEPB 7
NRC TO RGE 04/21/82 V-5 DL/SEPD 7
NRC to RGE 02/08/82 III-7 C.
DE/SEB 7
RGE to NRC 07/07/81 V-6 DL/SEPB 7
NRC to RGE 03/05/80 III-7 D.
DE/SEB 7
NRC to RGE 05/08/80 V-7 DSI/ASB 7
NRC to RGE 02/17/82 III-8 A.
DSI 7
NRC to RGE 02/17/82 V-8 X
NRC to RGE 05/07/81 III-8 B.
X NRC to RGE 02 12 51 V-9 X
NRC to RGE 11/16/79 III-8 C.
DL/SEPB 7
RGE to NRC 12/07/79 V-10 A.
DL/SEPB 7
NRC to RGE 02/02/79 III-8 D.
X NRC to RGE 05/07/81 V-10 B.
DL/SEPB 7
RGE to NRC 09/29/81 III-9 X
NRC to RGE 05/07/81 V-11 A.
DL/SEPB 7
NRC to RGE 11/05/81 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/$EPB 7(Elec) HRC to RGE 04/24/81 i
t.
a 9
4 4
1 l
(2-12)
~
(ilfilhllt l
TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.
X NRC to RGE 11/16/79 VI-7 D.
DL/SEPB 7
NRC to RGE 08/17/78 V-13 X
NRC to RGE 05/07/81 VI-7 E.
X HRC to RGE 05/07/81 VI-1 DE/CEB 7
NRC to RGE 02/19/82 VI-7 F.
DL/SEPB 7
NRC to RGE 06/24/81 VI-2 A.
X NRC to RGE 05/07/81 VI-8 X
NRC to RGE 05/07/81 VI-2 B.
X NRC to RGE 05/07/81 VI-9 X
NRC to RGE 11/16/79 VI-2 C.
X NRC to RCE 11/16/79 VI-10 A.
DL/SEPB 7
NRC to RGE 11/27/81 VI-2 D.
DSI/CSB 7
NRC-TO RGE 04/12/82 VI-10 B.
X NRC to RGE 11/16/79 A
VI-3 DSI/CSB 7
HRC TO RGE 04/12/82 VII-1 A.
DL/SEPB 7
NRC to RGE 07/30/81 VI-4 DSI/CSB 7(SYS)
NRC TO RGE 04/12/82 VII-1 5.
DL/SEPB 7
" NRC to RGE 08/17/78 DL/SEPB 7(ELEC) -NRC TD RGE 03/19/82 VII-2 DL/SEPB 7
- NRC to RGE 12/28/81 VI-5 X
NRC to RGE 05/07/81 VII-3 DL/SEPB 7(Sys)
NRC to RGE 09/29/81 VI-6 DSI/CSB 7
NRC to RGE 05/06/81 DL/SEPB 7(Elec) NRC to RGE 03/25/82 t
VI-7 A.
1.
DL/SEPB 7
NRC to RGE 02/20/81 VII-4 X
NRC to RGE 05/07/81 VI-7 A. 2.
DL/SEPB 7
NRC to RGE 08/17/73 VII-5 X
NRC to RGE 05/07/81 VI-7 A. 3.
DL/SEPB 7
NRC to RGE 11/27/81 VII-6 DL/SEPB 7
NRC to RGE 06/24/81 VI-7,A. 4.
X NRC.to RGE 05/07/81 VII-7 X
NRC to RGE 11/16/79 VI-7 B.
DSI/R$B 7(SYS)
NRC TO RGE 03/09/82 VIII-1 A.
DSI/PSB 7
HRC to RGE
'03/26/81 DL/SEB 7(Elec) HRC to RGE 09/18/81 VIII-2 DL/SEPB 7
NRC to RGE 06/24/81 VI-7 C.
DL/SEPB 7
HRC to RGE 02/20/81 VIII-3 A.
DL/SEPB 7
NRC to RGE 07/31/81 VI-7 C.
1.
DL/SEPB 7
NRC to RGE 11/27/81 VIII-5 B.
DL/SEPB 7
NRC to RGE 06/09/81 VI-7 C. 2.
DL/SEPB 7
NRC to RGE 02/20/81 VIII-4 DL/SEPB 7
RGE to NRC 10/08/81 VI-7 C.'3.
X
.NRC to RGE 11/16/79 (2-13)
. -. _ _ -. -., ~.. -. - _.
f GINNA TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 7
NRC to RGE 11/24/81 XV-10 DSI/RSB 7
NRC to RGE 09/04/81 IX-2 X
NRC to RGE 05/07/81 XV-11 X
NRC to RGE 10/01/80 IX-3 DL/SE*B 7
NRC to RGE 11/03/81 XV-12 DSI/CPB 7(Sys)
NRC to RGE 09/04/81 DSI/AEB 7(DOSES) HRC TO RGE 03/03/82 IX-4 DSI/RSB 7
NRC to RGE 08/26/81 XV-13 X
NRC to RGE 11/16/79 IX-5 DL/SEPB 7
RGE to NRC 03/29/82 XV-14 DSI/R$B 7
NRC to RGE 09/04/81 IX-6 7
NRC TO RGE 05/07/82 XV-15 DSI/RSB 7
NRC to RGE 09/04/81
'X X
NRC to RGE.
05/07/81 XV-16 DSI/AEB 7
NRC TO RGE 03/03/82 l
XI-1 X
NRC to RGE 12/04/81 XV-17 DSI/RSB 7(Sys)
NRC to RGE 09/04/81 XI-2 X
NRC to RGE 12/04/81 DSI/AEB 7(DOSES) HRC TO RGE 03/03/82 XIII-1 X
HRC to RGE 05/07/81 XV-18 X
HRC to RGE 03/11/80 XIII-2 DL/SEPB 7
NRC to RGE 03/26/81 XV-19 DSI/RSB 7(Sys)
HRC to RGE 10/02/81 DSI/AEB 7(DOSES) - RGE TO NRC 03/09/82 XV-1 DSI/RSB 7
NRC to RGE 09/04/81 j
XV-20 DSI/AEB 7
NRC TO RGE 03/03/82 f
XV-2 DSI/RSB 7(Sys)
NRC to RGE 09/04/81 DSI/AEB 7(DOSES) HRC TO RGE 03/03/82 XV-21 X
NRC to RGE 05/07/81 XV-3 DSI/RSB 7
HRC to RGE 09/04/81 XV-22 X
NRC to RGE 05/07/81 XV-4 DSI/RSB 7
NRC to RGE 09/04/81 XV-23 X
NRC to RGE 05/07/81 XV-5 DSI/RSB 7
NRC to RGE 09/04/81 XV-24 X
NRC to RGE 05/07/81 i
XV-6 DSI/RSB 7
.NRC to RGE 09/04/88 XVI X
HRC 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 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 s
HADDAM NECK a
FACILITY: HADDAM NECK TCPIC NO.
REVIEW STATUS REMARKS DIV/BR LICENSEE: CONNECTICUT YANKEE ATOMIC POWER 11-1 A.
DE/SA8 7
NRC 10 CY.*PC0 04/22/82 REGION / LOCATION: 13 MILES EAST OF MERIDEN, CT.
II-1 B.
DE/SAB' 7
NRC TO CYAPCO 04/22/82 DOCKET NO: 05000213 II-1 C.
DE/SAB 7
HRC TO CfAPCO- 06/28/82 POWER CAPACITY: 1825(THERMAL) 0575(ELECTRICAL)
II-2 A.
DSI/AEB 7
CYAPCo to NRC 01/22/81 OL NUMBER: DPR-61 4
H.S.S.S.
WEST.
II-2 C.
DSI/AEB 7
NRC TO CYAPCO 04/26/82 A/E FIRM: S&W II-2 D.
X NRC to CYAPCo 05/07/81 SYSTEMATIC EVALUATION PROGRAM' BRANCH C_HIEF: W. RUSSELL IJ-3 A.
DE/HUEB Gb CYAPCo to NRC 12/14/81 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD II-3 B.
DE/H GEB 4b CYAPCo to HRC 12/14/81 OPERATING REACTORS PROJECT MANAGER: C.
TROPF
~II-3 B.
1.
DE/HGEB 4b CYAPCo to NRC 12/14/8P BRDWN'I] [
INTEGRATED ASSESSMENT PROJECT MANAGER: S.
II-3 C.
DE/HGEB 4b CYAPCo to NRC 12/14/81
~r' II-4 DE/OsB 7
NRC to CYAPCo 06/04/82 4
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 7
HRC TO CYAPCO 06/04/82 3
FROM 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 7
NRC TO CYAPCO 07/13/82 STARTED i
5 - DRAFT SE SENT II-4 E.
X NRC to CYAPCo 04/16/79 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.
DE/HGEB 7
HRC TO CYAPCO 07/06/82 6 - SE RESPONSE RECEIVED 2 - QUESTI0HS SENT BY NRC III-1 DL/SEPB 4A(SYS) 07/22/82 TO UTILITY
~
DL/SEPB 7(Elec) Part of VII-3 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 4b CYAPCo to NRC 12/14/81 RECEIVED BY HRC C.
W
/
.w (2-13)
HADDAM NECK TOPIC NO.
kdVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/LR DIV/ER III-3 A.
D E/ S E B 4b CYAPCo to NRC 08/31/31 111-10 B.
DL/SEPB 7
NRC 10 CYAPCO 03/36/82 III-3 B.
DE/HGEB 0
III-10 C.
X NRC to CYAPCo 04/16/79 III-3 C.
DE/HGEB 7
NRC TO CYt.PCO 06/28/82 III-11 X
NRC to CYAPCo 05/07/81 III-4 A.
DSI/ASB 4a 12/28/81 III-12 X
NRC to CYAPCo 05/07/81 III-4 B.
DE/MTEB 7
NRC TO CYAPCO 07/13/82 IV-1 A.
DL/SEPB 7
CYAPCo to NRC 06/25/79 III-4 C.
DSI/ASB 5
NRC TO CYAPCO 05/10/82 IV-2 DSI/ICSB 7
NRC to CYAPCo 02/22/82 III-4 D.
DE/SAB 7
NRC TO CYAPCO 04/22/82 IV-3 X
NRC to CYAPCo 05/07/81 III-5 A.
DL/SEPB 3
CYAPCo to NRC 02/07/80 V-1 X
NRC to CYAPCo 11/27/81 III-5 B.
DL/SEPB 7
NRC TO CYAPCO 05/10/82 V-2 X
NRC to CYAPCo 04/16/79 III-6 DL/SEPB 3
CYAPCo to NRC 06/11/R1 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 05/07/80 III-7 B.
DL/SEPS 3
CYAPCo to NRC 09/07/79 V-5 DL/SEPB 7
NRC to CYAPCo 02/22/82 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 7
NRC to CYAPCo 10/16/81 V-7 DSI/ASB 7
NRC TO CYAPCO 06/21/82 III-8 A.
DSI 7
NRC TO CYAPCO 06/2'/82 V-8 X
NRC to CYAPCo 05/07/81 III-8 B.
X HRC to CYAPCo 10/01/80 V-9 X'
S2C to CYAPCo 11/16/79 III-8 C.
DL/SEPB 7
NRC to CYAPCo 01/29/82 V-10 A.'
DL/SEPB 7
NRC to.CYAPCo 01/13/A1 III-8 D.
X NRC to CYAPCo 05/07/81 V-10 B.
DL/hd*B 7
NRC to CYAPCo - 12/28/81 III-9 X
NRC to CYAPCo 05/07/81 V-11 A.
DL/SEPB 7
NRC to CYAPCo 11/03/81 III-10 A.
DL/SEPB 7
CYAPCo to NRC 09/21/81 V-11 B.
DL/SEPB 7(Sys)
HRC to CYAPCo 12/28/81 DL/SEPB 7(Elec) NRC TO CYAPCO C3/03/82 m
(2-16)
HADDAM NECK J
~
TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.
X NRC to CYAPCo 11/16/79 VI-7 D.
DL/SEPB 7
NRC to CYAFCo 08/87/78 V-13 X
NRC to CYAPCo 05/07/81 VI-7 E.
X MRC to CYAPCo 05/07/81 VI-1 DE/CEB 7
HRC TO CYAPCO 07/15/82 VI-7 F.
X N'y to CYAPCo 04/16/79 VI-2 A.
X NRC to CYAPCo 05/07/81 VI-8 X
NRC to CYAPCe 05/07/81 VI-2 B.
X NRC to CYAPCo 05/07/81 VI-9 X
NRC to CYAPCo 11/16/79 VI-2 C.
X NRC to CYAPCo 04/16/79 VI-10 A.
DL/SEPB 5
HPC TO CYAPCO 07/22/82 VI-2 D.
DSI/CSB 5
HRC 70 CYAPCO 07f15/82 VI-10 B.
X NRC to CYAPCo 04/16/79 VI-3 DSI/CSB 5
NRC TO CYAPCO 07/15/82 VII-1 A.
DL/SEP3 5
NRC TO CYAPCO 03/05/82 VI-4 DSI/CSB 5(SYS)
HRC TO CYAPCO 04/26/82 VII-1 B.
DL/SEPB 7
NRC to CYAPCo 08/17/78 DL/SEPB 7(Elec) NRC to CYAPCo 09/21/81 VII-2 DL/SEPB 5
NRC TO CYAPCO 03/05/82 VI-5 X
NRC to CYAPCo 05/07/81 VII-3 DL/SEPB 7(Sys)
NRC to CYAPCo 12/28/81 VI-6 DSI/CSB 7
HRC TO CYAPCO 05/07/82 DL/SEPB 7(Elec) NRC to CYAPCo 08/25/81 VI-7 A.
1.
DL/SEP B 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 (o CYAPCo 05/07/81 VI-7 A.
3.
DL/SEPB 5
NRC to CYAPCo 02/11/82 VII-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 6(SYS)
CYAPCO TO NRC 07/01/82 VIII-1 A.
DSI/PSB 7
NRC TO CYAPCO 07/22/82 DL/SEPB 7(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 03/13/81 s e VIII-5 A.
DL/SEPB 7
CYAPCo to NRC 02/16/19 VI-7 C.
1.
DL/SEPB 7
CYPACO to NRC 01/11/82 VIII-3 B.
DL/SEPB 7
NRC to CYAPCo 08/28/81 VI-7 C. 2.
DL/SEPZ 7
NRC to CYAPCo 03/13/81 VIII-4 DL/SEPb 7
NRC TO CYAPCO 05/17/82 VI-7 C. 3.
DL/SEPB 7
CYAPCo to NRC 02/12/82 (2-17)
HADDAM NECK TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 7
NRC TO CYAPC0 03/01/82 XV-10 DSI/RSB 7
hRC 10 CYAPCD 04/12/s2 IX-2 X
NRC to CYAPCo 05/07/81 XV-11 X
NRC to CYAPCo 10/01/80 IX-3 DL/SEPB 7
NRC TO CYAPCO 05/07/82 XV-12 DSI/CPB 7(SYS)
NRC TO CYAPCO 03/23/82 DSI/RSB 7(DOSES) NRC TO CYAPCO 06/29/82 IX-4 DSI/RSB 7
NRC TO CYAPC0 04/26/82 XV-13 X
NRC to CYAPCo 11/16/79 IX-5 DL/SEPB 4A 05/26/82 XV-14 DSI/RSB 7
NRC TO CYAPCO 04/26/82 IX-6 DE 7
DSI TO DL 05/19/82 XV-15 DSI/RSB 7
NRC TO CYAPCO 04/16/82 X
X NRC to CYAPCo 05/07/81 XV-16 DSI/AEB 6
CYAPCo to NRC 09/28/81 XI-1 X
NRC to CYAPCo 12/04/81 XV-17 DSI/RSB 4A(SYS) 06/21/82 XI-2 X
NRC to CYAPCo 12/04/81 DSI/AEB 4A(DOSES) 06/28/82 XIII-1 X
NRC to CYAPCo 05/07/81 XV-18 X
NRC to CYAPCo 10/01/80 XIII-2 DL/SSPB 7
NRC TO CYAPCO 06/10/82 XY-19 DSI/RSB 7(Sys)
NRC to CYAPCo 12/02/81 DSI/AEB 4A(DOSES) 06/30/92 XV-1 DSI/RSB 7
NRC TO CYAPCO 06/18/82 XV-20 DL/SEPB 7
NRC to CYAPCo 06/09/81 XV-2 DSI/RSB 7 (SYS) NRC TO CYAPCO 05/20/82 DSI/AEB 5(DOSES) 07/15/82 XV-21 X
NRC to CYAPCo 05/07/81 XV-3 DSI/RSB 7
NRC TO CYAPCO 03/17/82 XV-22 X
HRC to CYAPCo 05/07/81 XV-4 DSI/RSB 7
NRC to CYAPCo 12/17/81 XV-23 X
NRC to CYAPCo 05/07/81 XV-5 DSI/RSB 7
HRC TO CYAPCO 04/16/32 XV-24 X
NRC to CYAPCo 05/07/81 XV-6 DSI/RSB 7
NRC TO CYAPCO 05/20/82 XVI X
NRC to CYAPCo 11/05/80 XV-7 DSI/RSS 7
NRC TO CYAPCO 05/25/82 XVII DL 7
NRC to CYAPCo 08/17/78 XV-8 DSI/CP3 7
NRC TO CYAPCO 03/25/82 XV-9 DSI/RSB 7
NRC TO CYAPCO 04/26/82 (2-18)
LACROSSE FACILITY: LACROSSE TOPIC NO.
REVIEW STATUS REMARKS LICENSEE: DAIRYAND POWER Il-1 A.
DE/SAB 4b DPC to NRC 06/23/81 REGION /LCCATION: 19 MILES SOUTH OF LACROSSE, WISC.
II-1 B.
DE/SAB 4A 07/29/82 DOCKET NO.-
05000409 II-1 C.
DE/SAS Ab DPC to NRC 07/15/81 PCWER CAPACITY: 0165(THERMAL) 0050(ELECTRICAL)
II-2 A.
DSI/AEB 7
NRC to DPC 12/15/80 OL NUMBER: DPR-45 5
5,
II-2 B.
X NRC to DPC 05/07/81 II-2 C.
DSI/AEB 4B DPC TO HRC 01/05/82
, pp II-2 D.
X NRC to DPC 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W.
RUSSELL II-3 A.
DE/HGEB 4b DPC to NRC 06/16/81 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD II-3 B.
DE/HGEB 4B DPC TO NRC 05/12/82 OPERATING REACTORS PROJECT MANAGER: D. DUDLEY II-5 B.
1.
DE/HGEB
- B DPC TO NRC 05/12/82 INTEGRATED ASSESSMENT PROJECT MANAGER: T.MICHAELSjfhyf II-3 C.
DE/HGEB Gb DPC to NRC 06/26/81 II-4 DE/GSB 7
NRC to DPC 07/20/82 KEY FOR STATUS CODES II-4 A.
DE/GSB 7
NRC to DPC 06/05/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.
DE/GSB 7
NRC TO DPC 07/20/82 FROM REVIEW BRANCH X - DELETED II-4 C.
DE/GSB 7
NRC to DPC 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.
DE/HGEB 4A 07/27/82 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.
DE/HGEB 7
NRC to DPC 07/29/82 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC III-1 DL/SEPB 6(SYS)
DPC TO NRC 07/02/82 TO UTILITY DL/SEPB 5(ELEC) HRC TO DPC 03/09/82 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 4b DPC to NRC 03/05/82 RECEIVED BY HRC (2-19)
LACROSSE TOPIC NO.
F. EV I EW STATUS 7: r" ? " r "
TDPIC NO.
PEVIEW STATUS REMARKS CIV/LR DIV/BR III-3 A.
DE/SEB 4B LPC 10 NRC 05/12/82 111-10 B.
X NRC to DPC 10/29/79 III-3 B.
X NRC to DPC 03/10/81 III-10 C.
X NRC to DPC 10/29/79 III-3 C.
DE/HGEB 4B DFC TO NRC 01/29/82 III-11 X
NRC to CPC 05/07/81 III-4 A.
PSI /ASB 0
III-12 X
NRC to DPC 05/07/81 III-4 B.
DE/MTEB 4B DPC TO NRC 03/05/82 IV-1 A.
DL/SEPB 7
NRC to DPC 04/19/79 III-4 C.
DSI/ASB 7
NRC TO DSC 07/19/82 IV-2 DSI/ICSB 7
HRC TO DPC 03/25/82 III-4 D.
DE/SAB 4A 07/29/82 IV-3 X
HRC to DPC 05/07/81 III-5 A.
DL/SEPB 4B DPC 10 HRC 02/24/82 V-1 X
NRC to DPC 11/27/81 III-5 B.
DL/SEPB 4A 07/26/82 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 05/97/81 III-7 A.
X NRC to DPC 05/07/51 V-4 X
HRC to DPC 05/07/81 III-7 B.
DL/SEPB 4A 07/23/32 V-5 DL/SLPB 7
NRC TO DPC 07/19/82 III-7 C.
X NRC to DPC 10/29/79-V-6 DL/SEPB 7
NRC to DPC 03/05/80 III-7 D.
DE/SEB 7
NRC TO DPC 04/13/82 V-7 X
NRC to DPC 05/07/81 III-8 A.
DSI 5
hRC TO DPC 02/22/32 V-8 X
NRC to DPC 05/07/81 III-8 B.
X NRC to DPC 09/26/80 V-9 X
NRC to DPC 10/29/79 III-8 C.
DL/SEPB 7
DPC to NRC 03/03/81 V-10 A.
DL/SEPB 7
NRC to DPC 01/07/80 III-S D.
X NRC to CPC 05/07/81 V-10 B.
DL/SEPB 5
NRC to DPC 12/22/80 III-9 X
NRC to CPC 05/07/81 V-11 A.
DL/SEPB 7
NRC to DPC 02/22/82 111-10 A.
DL/SEPB 7
HRC to DPC 09/22/81 V-11 B.
DL/SEPB 5(Sys)
NRC to DPC 12/22/80 DL/SEPB 7(ELEC) NRC TO CPC 03/04/82 (2-20)
LACROSSE TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/ER V-12 A.
DL/SEPB 7
NRC 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 4B DPC to NRC 02/19/82 VI-7 F.
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 6
DPC TO NRC 06/14/82 VI-2 D.
DSI/CSB 5
NRC TO DPC 07/13/82 VI-10 B.
X NRC to DPC 10/29/79 VI-3 DSI/CSB 5
NRC TO DPC 07/13/82 VII-1 A.
DL/SEPB 5
NRC TO DPC 03/09/82 VI-4 DSI/CSB 4A(SYS) 06/30/82 VII-1 B.
DL/SEPB 7
NRC to DPC 08/17/78 DL/SEPB 7(Elec) NRC to DPC 01/05/82 VII-2 DL/SEPB 5
NRC TO DPC 03/11/82 VI-5 X
NRC to DPC 05/07/81 VII-3 DL/SEPS 5(Sys)
NRC to DPC 12/22/83 VI-6 DSI/CSB G
NRC to DPC 05/07/81 DL/SEPB 5(ELEC) NRC TO DPC 03/09/82 VI-7 A.
1.
X NRC to CPC 10/29/79 VII-4 X
NRC to DrC 05/07/81 VI-7 A.
2.
X NRC to DPC 05/07/81 VII-5 X
NRC to DPC 05/07/81 VI-7 A.
3.
DL/SEPB 5
NRC to DPC 02/17/82 VII-6 DL/SEPB 7
NRC to DPC 09/2'1/81 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
NRC to DPC 05/07/81 VI-7 C.
DL/SEPB 7
NRC to CPC 03/13/81 VIII-2 DL/SEPB 7
NRC to CPC 12/18/81 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/SEPS 7
NRC to CPC 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)
1 LACROSSE i
TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/ER DIV/BR IX-1 DSI/ASB 4B DPC 10 NRC 02/26/82 XV-10 X
HRC to DPC 10/29/79 IX-2 X
NRC to DPC 05/07/81 XV-11 DSI/CPB 7
NRC TO DPC 04/05/82 l
I IX-3 DL/SEPB 7
NRC TO DPC 07/20/82 XV-12 X
NRC to DPC 10/29/79 i
L IX-4 X
NRC to DPC 10/29/79 XV-13 DSI/CPB 7(DOSES) NRC TO DPC 07/20/82 DSI/AEB 7(SYS)
NRC TO DPC 04/05/82 i
l IX-5 DL/SEPB 4A 07/23/82 i
XV-14 DSI/RSB 4A 07/16/82 T
IX-6 DSI/ASB 2
HRC TO DPC 05/10/82 XV-15 DSI/RSB 7
NRC to DPC 09/21/81 i
X X
NRC to DPC 05/07/81 XV-16 DSI/AEB 4B DPC TO NRC 03/09/82 L
XI-1 X
NRC to DPC 12/04/81 l
XV-17 X
NRC to DPC 10/29/79 i
XI-2 X
NRC to DPC-12/04/81 l
XV-18 DSI/AEB 4A 06/23/82 XIII-1 X
NRC to DPC 05/07/81 XV-19 DSI/AEB 4B(DOSES)DPC TO NRC 05/28/82 XIII-2 DL/SSPB 7
NRC to DPC 03/11/81 DSI/RSB 4A(SYS) 07/15/82 I
XV-1 DSI/RSB 48 DPC TO NRC 03/05/82 XV-20 DSI/AEB 48 DPC TO NRC 03/12/82
{
XV-2 X
NRC to DPC 10/29/79 XV-21 X
HRC to DPC 05/07/81
[
XV-3 DSI/RSB 7
NRC to DPC 11/13/81 XV-22 X
NRC to DPC 05/07/81 i
l XV-4 DSI/RSB 7
NRC to DPC 11/03/81 XV-23 X
NRC to DPC 05/07/81 l
XV-5 DSI/RSB 48 DPC TO NRC 03/05/82 XV-24 X
NRC to DPC 05/07/81 l
XV-6 X
NRC to DPC 10/29/79 XVI X
NRC to DPC 11/05/80 XV-7 DSI/RSB 4A 07/19/82 XVII DL 7
NRC to DPC 08/17/78 1
XV-8 DSI/CPB 7
NRC TO DPC 04/05/82 l
XV-9 DSI/RSB 4b DPC to NRC
.08/25/81 i
i i
i
)
I (2-22) 1 i
m.
MILLSTONE 1 FACILITY: MILLSTONE 1 TOPIC NO.
REVIEW STATUS REMARKS DIV/BR LICENSEE: NORTHEAST NUCLEAR ENERGY 11-1 A.
DE/SAB 7
hRC to hu 07/31/81 -
REGION / LOCATION: 5 MILES SOUTH WEST OF NEW LONDON, CONN.
II-1 B.
DE/SAB 7
HRC tc NU 11/27/81 DOCKET NO.
0 5 0 0 0 2'+ 5 II-1 C.
DE/SAB 7
NRC te NU 11/27/81 POWER CAPACITY: 2011(THERMAL) 0660(ELECTRICAL)
II-2 A.
DSI/AEB 7
NRC te NU 03/30/81 OL NUMBER: DPR-21 II-2 B.
X NRC to NU 05/07/81 N.S.S.S.
GE.
II-2 C.
DSI/AEB 7
NRC to NU 12/23/81 A/E FIRM: EBASCO II-2 D.
X NRC to NU 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W.
RUSSELL II-3 A.
DE/HGEB 7
HRC TO NU 06/30/82 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFTELD
, ~~)
II-3 B.
DE/HGEB 7
NRC TO NU 06/30/82
. -( ' $\\ '
GPERATING REACTORS PROJECT MANAGEP.: J.
SHEA II-3 B.
1 DE/HGEB 7
NRC TO NU 06/30/32 INTEGRATED ASSESSMENT PROJECT MANAGER: D.PERSIKYO II-3 C.
DE/HGEB 7
NRC TO NU 06/30/82 II-4 DE/GSB 7
NRC to NU 06/08/81 KEY FOR STATUS CODES II-4 A.
DE/GSB 7
hRC to NU 06/08/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.
DE/GSB 1
NRC TO NU 05/11/82 FROM REVIEW BRANCH X - DELETED II-4 C.
DE/GSB 7
NRC to NU 06/08/81 4b-SAR RECEIVED FROM 0 - TOPIC NOT LICENSEE II-4 D.
DE/HGEB 7
NRC TO NU 06/30/82 STARTED 5 - DRAFT SE SENT II-4 E.
X NRC to NU 11/16/79 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.
DE/HGEB 5
NRC TO NU 06/15/82 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC III-1 DL/SEPB 5(Elec) NRC TO NU 02/01/82 TO UTILITY DL/SEPB 5(SYS)
NRC TO NU 05/05/82 7 - TCPIC COMPLETE 3 - CUESTION RESPONSE III-2 DL/SEPB 5
NRC TO NU 05/10/82 RECEIVED BY NRC (2-23)
MILLSTONE 1 TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR III-3 A.
DE/SEB 5
NRC to NU 05/11/81 III-10 B.
X NRC to NU 11/16/79 III-3 B.
X NRC to NU 12/26/80 III-10 C.
DL/SEPB 7
HU to NRC 08/29/79 III-3 C.
DE/HGEB 7
NRC TO NU 06/23/82 III-11 X
NRC to NU 05/07/81 III-4 A.
DSI/AS3 7
NRC TO NU 05/25/82 III-12 X
NRC to NU 05/07/81 III-4 B.
DE/MTEB 7
NRC TO NU 06/29/82 IV-1 A.
DL/SEPB 7
NU to NRC 02/12/79 III-4 C.
DSI/ASB 7
NRC TO NU 06/09/82 IV-2 DSI/ICSB 5
HRC TO NU 06/03/82 III-4 D.
DE/SAB 7
HRC to NU 11/27/81 IV-3 DL 7
NRC to NU 02/22/82 III-5 A.
DL/SEPB 7
NRC TO NU 06/24/82 V-1 X
NRC to NU 11/27/81 III-5 B.
DL/SEPB 6
NU TO NRC 06/28/82 V-2 X
NRC to NU 11/16/79 III-6 DL/SEPB 7
HRC TO NU 06/30/82 V-3 X
NRC to NU 05/07/81 III-7 A.
X NRC to NU 05/07/81 V-4 X
HRC to NU 05/07/81 III-1 B.
DL/SEPB 5
NRC TO NU 05/20/82 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 7
HRC TO NU 03/03/82 Y-8 X
NRC to NU 05/07/81 III-8 B.
X NRC to NU 09/26/80 V-9 X
NRC to NU 11/16/79 III-8 C.
DL/SEPB 7
NRC TO HU 06/24/82 V-10 A.
DL/SEPB 7
NU to bRC 03/05/79 III-8 D.
X NRC to NU 05/07/81 V-10 B.
DL/SEPB 7
NU to >RC 07/22/81 III-9 X
NRC to NU 05/07/81 V-11 A.
DL/SEPB 7
NRC to NU 07/08/81 III-10 A.
DL/SEPB 7
NRC to NU 04/07/82 V-11 B.
DL/SEPB 7(Sys)
NU to hRC 07/22/81 DL/SEPB 5(Elec) NRC to NU 02/01/92 (2-24)
MILLSTONE 1 TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.
DL/SEPE 7
NRC to NU 12/17/19 VI-7 D.
DL/SEPB 7
NRC to NU C6/17/78 V-13 X
NRC to NU 05/07/81 VI-7 E.
X NRC to NU 05/07/81 VI-1 DE/CEB 7
NRC to NU 02/26/82 VI-7 F.
X NRC to NU 11/16/79 VI-2 A.
X HRC 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 HRC to NU 11/16/79 VI-10 A.
DL/SEPB 7
NRC to NU 10/08/81 VI-2 D.
DSI/CSB 5
NRC TO NU 06/03/82 VI-10 B.
DL/SEPB 7
HU to NRC 08/05/81 VI-3 DSI/CSB 5
NRC TO NU 06/03/82 VII-1 A.
DL/SEPB 7
NRC to NU 07/23/81 VI-4 DSI/CSB 6(SYS)
NU TO HRC 04/14/82 DL/SEPB 7(ELEC) NRC TO NU 06/24/82 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
NU TO NRC 06/25/82 VI-6 DSI/CSB 4A 06/01/82 VII-3 DL/SEPB 7(Sys)
NU to NRC 07/22/81 DL/SEPB 5(Elec) HRC to NU 02/01/52 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.
f.
DSI/CPB 7
NRC TO NU 03/11/82 VII-7 X
NRC to NU 11/16/79 VI-7 B.
X HRC to NU 11/16/79 VIII-1 A.
DSI/PSB 7
NRC TO NU 06/30/82 VI-7 C.
DL/SEPB 7
HRC to NU 03/29/81 VIII-2 DL/SEPB 7
NRC to NU 09/30/81 VI-7 C.
1 DL/SEPB 7
NU to NRC 11/02/81 VIII-3 A.
DL/SEPB 7
NRC to NU 08/26/81 VI-7 C. 2.
CL/SEPB 7
NRC to NU 03/29/81 VIII-3 B.
DL/SEPB 7
NRC to NU 07/23/81 VI-7 C. 3.
X NRC to NU 11/16/79 VIII-4 DL/SEPB 7
NRC to NU 07/07/81 (2-25)
.m
__ _=.
J i
. MILLSTONE 1 TOPIC N3.
REVIEW STATUS REf1 ARKS TOPIC HO.
REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 7
NRC 10 NU 03/09/82 -
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/SEPB 7
NRC TO NU 07/16/32 XV-12 X
NRC to NU 11/16/79 IX-4 X
HRC to NU 11/16/79 XV-13 DSI/CPB 7(Sys)
NU to NRC 09/09/81 p
DSI/AEB 7(Doses) NRC to NU 11/03/81 IX-5 DL/SEPB 6
NU TO NRC 07/29/82 XV-14 DSI/RSB 7
NRC to NU 09/18/81 IX-6 DE 7
NRC TO NU C6/15/82 i
i XV-15 DSI 'RSB 7
HRC to NU 10/28/81 X
X NRC to NU 05/07/81 XV-16 DSI/AEB 6
NU to NRC 01/13/82 XI-1 X
NRC to NU 12/04/81 i
XV-17 X
NRC to NU 11/16/79 XI-2 j
X NRC to NU 12/04/81 XV-18 DSI/AEB 6
NU to NRC 01/13/82 XIII-1 X
NRC to NU 05/07/81 XV-19 DSI/RSB 7(Sys)
HRC to NU 08/26/81 XIII-2 DL/SSPB 7
NRC TO NU 06/09/82 DSI/AEB 6(Doses) NU to NRC 01/13/82 XV-1 DSI/RSB 7
NRC to'NU 12/31/81 XV-20 DSI/AEE 7
NRC to NU 11/03/81 XV-2 X
NRC to NU 11/16/79 XV-21 X
NRC 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 7
NRC to NU 01/07/82 XV-24 X
NRC to NU 05/07/81 XV-6 X
HRC to NU 11/16/79 XVI X
NRC to NU 11/15/80 XV-7 DSI/RSB 7
NRC to NU 12/04/81 XVII DL 7
NRC to NU 08/17/78 XV-8 DSI/CPB 7
HRC to NU 08/26/81 XV-9 DSI/RSB 7
NRC to NU 01/12/82
.I i
(2-26) i I
h
0YSTER CREEK FACILITY: OYSTER CREEK 1 TOPIC NO.
REVIEW STATUS REMARKS DIV/BR LICENSEE: JERSEY CENTRAL POWER 8 LIGHT 11-1 A.
DE/SAB 7
NRC to JCPL 02/04/82 REGION / LOCATION: 9 MILES SOUTH OF TOMS RIVER, NJ.
II-1 B.
DE/SAB 7
NRC to JCPL 02/04/82 DOCKET NO.
05000219 II-t C.
DE/SAB 7
NRC to JCPL 02/04/82 POWER CAPACITY: 1930(THERMAL) 0650(ELECTRICAL)
II-2 A.
DSI/AEB 7
HRC to JCPL 11/16/81 OL NUMBER: DPR-16 II-2 B.
X NRC to JCPL 05/07/81 II-2 C.
DSI/AEB 7
NRC TO JCPL 03/16/82 II-2 D.
X NRC to JCPL 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL II-3 A.
DE/HGEB 5
HRC TO JCPL 06/03/82 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD II-3 B.
DE/HGEB 5
NRC TO JCPL 06/03/82 GPERATING REACTORS PROJECT MANAGER:
J. LOMBARDO r
II-3 B.
1.
DE/HGEB 5
HRC TO JCPL 06/03/82 INTEGRATED ASSESSMENT PROJECT MANAGER: R.
FELL 6.,e II-3 C.
DE/HGEB 5
NRC TO JCPL 06/03/82 II-4 DE/GSB 7
NRC to JCPL 08/03/31' KEY FOR STATUS CODES II-4 A.
DE/GSB 7
NRC to JCPL 06/08/81 G - GENERIC Ga-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 7
NRC TO JCPL 06/28/82 STARTED 5 - DRAFT SE SENT II-4 E.
X NRC to JCPL 11/16/79 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.
DE/HGEB 7
NRC TO JCPL 06/15/82 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC Ill-1 DL/SEPB 5(SYS)
HRC TO JCPL 04/12/82 TO UTILITY DL/SEPB 7(Elec) NRC to JCPL 07/09/81 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 7
NRC TO JCPL 06/15/82 RECEIVED BY NRC (2-27)
0YSTER CREEK TOPIC NO.
REVIEW STATUS REMARKS TOPIC HO.
REVIEW STATUS REMARKS DIV/ER DIV/BR III-3 A.
DE/SEB 5
HRC 10 JCPL 05/14/82 III-10 B.
X HRC to JCPL 11/16/79
~
III-3 B.
X NRC to JCPL 12/26/80 III-10 C.
X NRC to JCPL 11/16/79 III-3 C.
DE/NGEB 5
NRC TO JCPL 06/24/82 III-11 X
NRC to JCPL 05/07/81 III-4 A.
DSI/ASB 5
NRC TO JCPL 06/21/82 III-12 X
NRC to JCPL 05/07/81 III-4 B.
DE/MTEB 7
NRC TO JCPL 06/28/82 IV-1 A.
DL/SEPB 7
NRC to JCPL 05/30/79 III-4 C.
DSI/ASB 7
NRC TO JCPL 06/15/82 IV-2 DSI/ICSB 5
HRC TO JCPL 06/18/82 III-4 D.
DE/ SAD 7
NRC TO JCPL 06/21/82 IV-3 X
NRC to JCPL 05/07/81 III-5 A.
DL/SEPB 7
NRC TO JCPL 06/29/82 V-1 X
NRC to JCPL 11/27/81 III-5 B.
DL/SEPB 7
NRC TO JCPL 06/22/82 V-2
'X NRC to JCPL 11/16/79 III-6 DL/SEPB 7
NRC TO JCPL 05/12/82 V-3 X
NRC to JCPL 05/07/81 III-7 A.
X NRC to JCPL 05/07/81 V-4 X
HRC to JCPL 05/07/81 III-7 B.
DL/SEPB 5
NRC TO JCPL 04/30/82 V-5 DL/SEPB 7
NRC to JCPL 02/22/82 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 7
NRC TO JCPL 03/08/82 V-7 X
NRC to JCPL 05/07/81 III-8 A.
DSI/CPB 5
NRC TO JCPL 02/29/82 V-8 X
NRC to JCPL 05/07/81 III-8 B.
X NRC to JCPL 09/26/80 V-9 X
NRC to JCPL 11/16/79 III-8 C.
DL/SEPB 7
NRC to JCPL 10/30/80 V-10 A.
DL/SEPB 7
JCPL to NRC 05/15/79 III-8 D.
X HRC to JCPL 05/07/81 V-10 B.
DL/SEPb 7
HRC to JCPL 09/25/80 III-9 X
NRC to JCPL 05/07/81 V-11 A.
DL/SEPB 7
NRC to JCPL 07/08/81 III-10 A.
DL/SEPB 7
NRC to JCPL 06/29/81 V-11 B.
DL/SEPB 7(Sys)
M., to JCPL 09/25/80 DL/SEPB 7(EIcc) NRC to JCPL 07/09/81 (2-28)
0YSTER CREEK TOPIC HD.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.
DL/SEPB 7
NRC 10 JCPL 03/16/81 VI-7 D.
DL/SEPB 7
NRC to JCPL C8/17/78 V-13 X
HRC to JCPL 05/07/81 VI-7 E.
X NRC to JCPL 05/07/81 VI-1 DE/CEB 5
HRC TO JCPL 06/29/82 VI-7 F.
X NRC to JCPL 11/16/79 VI-2 A.
X NRC to JCPL 05/07/81 VI-8 X
NRC to JCPL 05/07/81 VI-2 B.
X HRC to JCPL 05/07/81 VI-9 X
HRC to JCPL 11/16/79 VI-2 C.
X HRC to JCPL 11/16/79 VI-10 A.
DL/SEPB 7
NRC to JCPL 08/18/81 VI-2 D.
DSI/CSB 7
NRC TO JCPL 94/30/82 VI-10 B.
X NRC to JCPL 11/16/79 VI-3 DSI/CSB 7
NRC TO JCPL 04/30/82 VII-1 A.
DL/SEPB 7
NRC to JCPL 07/30/81 VI-4 DSI/CSB 7($YS)
HRC TO JCPL 06/15/82 VII-1 B.
DL/SEPB 5
NRC to JCPL 12/28/81 DL/SEPB 7(Elec) HRC to JCPL 08/05/81 VII-2 DL/SEPS 6
JCPL to NRC 03/17/81 VI-5 X
HRC to JCPL 05/07/81 VII-3 DL/SEPB 7(Sys)
HRC to JCPL 09/25/80 VI-6 DSI/CSB 5
NRC TO JCPL 03/04/82 DL/SEPB 7(Elec) HRC to JCPL 07/09/81 VI-7 A.
1.
X NRC to JCPL 11/16/79 VII-4 X
NRC to JCPL 05/07/81 VI-7 A. 2.
X HRC to JCPL 05/07/81 VII-5 X
NRC to JCPL 05/07/81 VI-7 A. 3.
DL/SEPB 7
NRC to JCAL 07/30/81 VII-6 DL/SEPB 7
NRC to JCPL 08/29/81 VI-7 A.
4.
DSI/RSB 5
NRC TO JCPL 06/28/82 VII-7 X
NRC to JCPL 11/16/79 VI-7 B.
X NRC to JCPL 11/16/79 VIII-1 A.
DSI/PSB 7
NRC to JCPL 03/03/82 VI-7 C.
DL/SEPB 7
HRC to JCPL 03/13/81 VIII-2 DL/SEPB 7
NRC to JCPL 06/29/81 VI-7 C.
1.
DL/SEPB 7
HRC 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
HRC to JCPL 06/29/81 VI-7 C. 3.
X HRC to JCPL 11/16/79 VIII-4 DL/SEPB 5
HRC to JCPL 03/26/81 (2-29)
0YSTER CREEK TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 7
HRC TO JCPL 06/01/82 XV-10 X
NRC to JCPL 11/16/79 IX-2 X
NRC to JCPL 05/07/81 XV-11 DSI/CPB 7
HRC TO JCPL 05/17/82 IX-3 DSI/ASB 7
NRC to JCPL 11/13/81 XV-12 X
NRC to JCPL 11/16/79 IX-4 X
HRC to JCPL 05/07/81 XV-13 DSI/AEB 5(DOSES) NRC TO JCPL 05/28/82 DSI/CPB 7CSYS)
NRC to JCPL 05/17/82 IX-5 DL/SEPB 5
NRC TO JCPL 06/28/82 XV-14 DSI/RSB 7
NRC to JCPL 07/16/81 IX-6 DE 7
NRC TO JCPL 06/15/82 XV-15 DSI/RSB 7
NRC to JCPL 12/04/81 X
X NRC to JCPL 05/07/81 XV-16 DSI/AEB 5
NRC TO JCPL 06/29/82 XI-1 X
NRC to JCPL 12/04/81 XV-17 X
NRC to JCPL 11/16/79 XI-2 X
NRC to JCPL 12/04/81 XV-18 DSI/AEB 5
NRC TO JCPL 05/28/82 XIII-1 X
HRC to JCPL 05/07/81 XV-19 DSI/AEB 5(DOSES) NRC TO JCPL 06/29/82 XIII-2 DL/SSPB 7
NRC to JCPL 09/25/80 DSI/RSB 7(Sys)
HRC to JCPL 09/04/81 XV-1 DSI/RSB 7
HRC to JCPL 12/07/81 XV-20 DSI/AEB 5
HRC TO JCPL 05/12/82 XV-2 X
NRC to JCPL 11/16/79 XV-21 X
NRC to JCPL 05/07/81 XV-3 DSI/RSB 7
NRC to JCPL 07/16/81 XV-22 X
NRC to JCPL 05/07/81 XV-4 DSI/RSB 7
NRC to JCPL 07/16/81 XV-23 X
NRC to JCPL 05/07/81 XV-5 DSI/RSB 7
NRC to JCPL 12/07/81 XV-24 X
NRC to JCPL 05/07/81 XV-6 X
NRC to JCPL 11/16/79 XVI X
NRC to JCPL 11/05/80 XV-7 DSI/RSB 7
NRC to JCPL 12/04/81 XVII DL 7
NRC to JCPL 08/17/78 XV-8 DSI/CPB 7
NRC TO JCPL 05/17/82 XV-9 DSI/RSB 7
NRC to JCPL 01/07/82 (2-30)
PAllSADES FACILITY: PALISADES TOPIC NO.
REVIEW STATUS REMARKS DIV/BR LICENSEE: CONSUMERS POWER II-1 A.
DL/SEPB 7
CPCo to NRC 12/28/79 REGION / LOCATION: 5 MILES SOUTH OF SOUTH HAVEN, MI.
II-1 B.
DL/SEPB 7
CPCo ts NRC 12/28/79 DOCKET NO: 05000255 II-1 C.
DL/SEPB 7
CPCo to NRC 05/13/81 POWER CAPACITY: 2530CTHERMAL) 0805(ELECTRICAL)
II-2 A.
DSI/AEB 7
NRC to CPCo 6/30/81 OL NUMBER: DPR-20 II-2 B.
X ND o
C 05/07/81 H.S.S.S.-
C-E II-2 C.
DSI/AEB N'
t C
04/23/81 A/E FIRM: BECH.
II-2 D.
o CPCo 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL II-C/H EB NRC to CPCo 02/19/82 OPERATING REACTORS BRANCH CHIEF:
D. CRUTCHFIELD I
GEB 7
NRC to CPCo 02/19/82 OPERATING REACTORS PROJECT MANAGER:
T. WAMBACH I
. 1 DE/HGEB 7
NRC to CPCo 02/19/82 INTEGRATED ASSESSMENT PROJECT MANAGER:
T.
II-3 C.
/
B 7
NRC to CPCo 02/19/82 KEY FOR STAT M O T [
J I-4 DE/GSB 7
RC to CPCo 06/08/81 p
B.
DE dPCo to NRC 07/22/81 G-GH DRAFT SE RECEIVED ]
FRCM REVIEW 'pmCH L
j X - D LE l
II-4 D
B NRC to CPCo 06/08/81 l
CPCo to NRC 06/01/81 STARTED
~
5 - DRAFT SE SENT 1.- QUESTIONS RECEIVED TO UTILITY X
NRC to CPCo 11/16/79 FROM REVIEW BRANCH II-4 F.
DE/HGEB 7
CPCo to NRC 06/01/81 2 - QUESTIONS SENT 4
III-1 DL/SEPB 7(Elec) HRC to CPCo 11/12/80 TO UTILITY i
DL/SEPB 7(Sys)
HRC to CPCo 02/08/82 7 - TOFEC PLETE 3 - CUESTION RESPONSE
\\
RECEIVED BY NRC (2-31)
PALISADES TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR III-2 DL/SEPB 7
NRC to CPCo 02/08/82 111-10 B.
DL/SEPB 7
NRC to CPCo 02/02/82 III-3 A.
DE/SEB 7
NRC to CSCo 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
NRC to CPCo 05/07/81 III-3 C.
DE/HGEB 7
NRC to CPCo 02/22/82 III-12 X
NRC to CPCo 05/07/81 III-4 A.
DSI/AEB 7
NRC to CPCo 02/02/82 IV-1 A.
DL/SEPB 7
CPCo to NRC 02/08/79 III-4 B.
DE/MTEB 7
MRC to CPCo 02/08/82 IV-2 DSI/ICSB 7
NRC to CPCo 02/08/82 III-4 C.
DSI/ASB 7
NRC to CPCo 09/21/81 IV-3 X
NRC to CPCo 05/07/81 III-4 D.
DE/SAB 7
CPCo to M2C 03/03/31 V-1 X
NRC to CPCo 11/27/81 III-5 A.
DL/SEPB 7
NRC to CPCo 02/08/82 V-2 X
NRC to CPCo 11/16/79 III-5 B.
DL/SEPD 7
NRC to CPCo 02/19/82 V-3 X
NRC to CPCo 05/07/81 III-6 DL/SEPB 7
CPCo to fiRC 12/16/81 V-4 X
NRC to CPCo 05/07/81 III-7 s.
DL/SEPB 7
NRC to CPCo 02/10/82 V-5 DL/SEPB 7
NRC to CPCo 02/04/82 III-7 B.
DL/SEPB 7
NRC to C?Co 02/12/82 V-6 DL/SEPB 7
NRC to CPCo 03/05/80 III-7 C.
DE/SEB NRC to CPCo 10/19/81 V-7 DSI/ASB 7
NRC to CPCo 11/16/81 III-7 D.
DE/SEB 7
CPCo to NRC 08/17/81 V-8 X
NRC to CPCo 05/07/81 III-8 A.
DSI 7
NRC to CPCo 11/18/81 V-9 X
NRC to CPCo 11/16/79 III-8 B.
X NRC to CPCo 10/01/80 V-10 A.
DL/SEPB 7
NRC to CPCo 09/26/81 III-8 C.
DL/MTEB 7
CPCo to NRC 12/28/79 V-10 B.
DL/SEPB 7
CPCo to NRC 12/23/81 III-8 D.
X NRC to CPCo 05/07/81 V-11 4.
DL/SEPB 7
HRC to CPCo 11/09/81 III-9 X
HRC to CPCo 05/07/81 V-11 B.
DL/SEPB 7(Sys)
HRC to CPCo 12/23/81 DL/SEPB 7(Elec) NRC to CPCo 12/24/81 III-10 A.
DL/SEPB 7
NRC to CPCo 05/19/81 (2-32)
PALISADES TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.
X NRC to CPCo 11/16/79 VI-7 D.
DL/SEPB 7
NRC to CPCo 08/17/78 V-13 X
NRC to CPCo 05/07/81 VI-7 E.
X HRC to CPCo 05/07/81 VI-1 DE/CEB 7
NRC to CPCo 08/03/81 VI-7 F.
DL/SEPB 7
NRC to CPCo 10/29/81 VI-2 A.
X NRC to CPCo 05/07/81 VI-8 X
NRC to CPCo 05/07/81 VI-2 B.
X NRC to CPCo 05/07/81 VI-9 X
NRC to CPCo 11/16/79 VI-2 C.
X HRC to CPCo 11/16/79 VI-10 A.
DL/SEPB 7
NRC to CPCo 10/16/81 VI-2 D.
DSI/CSB 7
HRC to CPCo 11/16/81 VI-10 B.
X.
NRC to CPCo 11/16/79 VI-3 DSI/CSB 7
HRC to CPCo 11/16/81 VII-1 A.
DL/SEPB 7
NRC to CPCo 08/28/81 VI-4 DL/SEPB 7(Elec) CPCo to NRC 08/18/81 VII-1 B.
DL/SEP8 7
NRC to CPCo 08/17/78 DCI/CSB 7(Sys)
HRC to CPCo 02/C8/82 VII-2 DL/SEPB 7
NRC to CPCo 05/19/81 VI-5 X
NRC to CPCo 05/07/81 VII-3 DL/SEPB 7(Sys)
CPCo to NRC 12/23/81 VI-6 DSI/CSB 7
NRC to CPCo 12/11/81 DL/SEPB 7(Elec) CPCo to NRC 12/31/81 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
KRC to CPCo 05/07/81 VI-7 A.
3.
DL/SEPB 7
NRC to CPCo 12/18/81 VII-6 DL/SEPB 7
NRC to CPCo 05/19/81 VI-7 A.
4.
X NRC to CPCo 05/07/81 VII-7 X
HRC to CPCo 11/16/79 VI-7 B.
DL/SEPB 7(Elec) NRC to CPCo 05/19/81 VIII-1 A.
DSI/PSB 7
HRC to CPCo 12/22/81 DSI/RSB 7(Sys)
NRC to CPCs 06/30/81 VIII-2 DL/SEPB 7
NRC to CPCo 10/29/81 VI-7 C.
DL/SEPB 7
NRC to CPCo 02/20/81 VIII-3 A.
DL/SEPB 7
NRC to CPCo 05/22/81 VI-7 C.
1.
DL/SEPB 7
HRC to CPCo 10/14/81 VIII-3 B.
DL/SEPB 7
NRC to CPCo 08/05/81 VI-7 C. 2.
DL/SEPB 7
NRC to CPCs 02/20/81 VIII-4 DL/SEPB 7
NRC to CPCo 07/31/81 VI-7 C.
3.
X CPCo to N?.C 12/12/79 (2-33)
PALISADES TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 7
NRC to CPCo 02/08/82 XV-10 DL/SEPB 7
NRC to CPCo 11/03/81 IX-2 X
NRC to CPCo 05/07/81 XV-11 X
NRC to CPCo 10/01/80 IX-3 DL/SEPB 7
hRC to CPCo 02/22/82 XV-12 DL/SEPB 7(Doses) NRC to CPCo 12/04/81 IX-4 DSI/RSB 7
NRC to CPCo 02/08/82 XV-13 X
NRC to CPCo 11/16/79 IX-5 DL/SEPB 7
NRC to CPCo 02/11/82 XV-14 DL/SEPB 7
NRC to CPCo 11/03/81 IX-6 DE 7
NRC TO CPC0 04/07/82 XV-15 DL/SEPB 7
NRC to CPCo 11/03/81 X
X NRC to CPCo 05/07/81 XV-16 DL/SEP8 7
NRC to CPCo 11/03/81 XI-1 X
HRC to CPCo 12/04/81 XV-17 DL/SEPB 7(Doses) NRC to CPCo-11/03/81 XI-2 X
NRC to CPCo 12/04/81 DL/SEPB 7(Sys)
HRC to CPCo 11/05/81 XIII-1 X
NRC to CPCo 05/07/81 XV-18 X
NRC to CPCo 10/01/80 XIII-2 DL/SSPB 7
NRC to CPCo 10/01/80 XV-19 DL/SEPB 7(Doses) NRC to CPCo 11/03/81 DL/SEPB 7(Sys)
NRC to CPCo 11/03/81 XV-1 DL/SEPB 7
NRC to CPCo 11/03/81 XV-20 DL/SEPB 7
NRC to CPCo 11/03/81 XV-2 DL/SEPB 7(Doses) HRC to CPCo 11/03/81 DL/SEP3 7(Sys)
NRC to CPCo 11/03/81 XV-21 X
NRC to CPCo 05/07/81 XV-3 DL/SEPB 7
NRC to CPCo 11/03/81 XV-22 X
NRC to CPCo 05/07/81 XV-4 DL/SEPB 7
NRC to CPCo 11/03/81 XV-23 X
NRC to CPCo 05/07/81 XV-5 DL/SEPB 7
HRC to CPCo 11/03/81 XV-24 X
NRC to CPCo 05/07/81 XV-6 DL/SEPB 7
NRC to CPCo 11/03/81 XVI X
NRC to CPCo 11/05/80 XV-7 DL/SEPB 7
NRC to CPCo 11/03/81 XVII DL 7
NRC to CPlo 08/17/78 XV-8 DL/SEPB 7
HRC to CPCo 11/03/81 XV-9 DL/SEPB 7
NRC to CPCo 11/03/81 (2-34)
SAN ON0FRE FACILITY: SAN ONOFRE 1 TOPIC HO.
REVIEW STATUS REMARKS DIV/BR LICENSEE: SOUTHERN CALIFORNIA EDI*a" II-I 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 4b SCE to NRC 11/12/81 POWER CAPACITY: 1347(THERMAL) 0430(ELECTRICAL)
II-2 A.
DSI/AEB 7
NRC to SCE 04/27/81 OL HUMBER: DPR-13 N
05/07/81 H.S.S.S.: WEST.
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
3CE TO NRC 03/15/82 OPERATING REACTORS BRANCH CHIEF: D.
CRUTCHFIELD II-3 B.
DE/HGEB 3
SCE TO NRC 04/12/82 OPERATING REACTORS PROJECT MANAGER: W. PAULSON II-5 B.
1.
DE/HGEB 3
SCE TO NRC 04/12/82 INTEGRATED ASSESSMENT PROJECT MANAGER: E. MCKENNA k lo JA II-3 C.
DE/HGEB 2
HRC to SCE 01/07/82 II-4 DE/GSB 5
NRC to SCE 03/15/81 KEY FOR STATUS CODES II-4 A.
DE/GSB 5
NRC TO SCE 04/05/82 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
NRC TO SCE 04/05/82 4b-SAR RECEIVED FROM 0 - TOPIC NOT LICENSEE II-4 D.
DE/HGEB 4b SCE to NRC 11/02/81 STARTED 5 - DRAFT SE SENT II-4 E.
X HRC to SCE 11/16/79 1'- QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.
DE/HGEB 4b SCE to NRC 11/02/81 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC III-1 DL/SEPB 5(SYS)
HRC TO SCE 06/25/82 TO UTILITY DL/SEPB 7(Elec) Part of VII-3 11/18/31 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 CL/SEPB 4B SCE TO NRC 05/04/82 RECEIVED BY NRC (2-35) 1
SAN ON0FRE TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/bR III-3 A.
DE/SEB 3
SCE to NRC 09/08/80 III-10 B.
D'./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 7
NRC to SCE 11/27/81 III-11 X
NRC to SCE 05/07/81 III-4 A.
DSI/ASB 4B SCE TO NRC 05/04/82 III-12 X
NRC to SCE 05/07/81 III-4 B.
DE/MTEB 5
NRC TO SCE 06/24/82 IV-1 A.
DL/SEPB 7
NRC to SCE 11/13/79 III-4 C.
DSI/ASB 4B SCE TO NRC 04/29/82 IV-2 DSI/ICSB 4B SCE TO NRC 04/30/82 III-4 D.
DE/SAB 4b SCE to NRC 10/23/81 IV-3 X
HRC to SCE 05/07/81 III-5 A.
DL/SEPB 0
V-1 X
NRC to SCE 11/27/81 III-5 B.
DL/SEPB 0
v-2 X
NRC to SCE 11/16/79 III-6 DL/SEPB 3
SCE to NRC 12/08/81 V-3 X
NRC to SCE 05/07/81 III-7 A.
X HRC to SCE 05/07/81 V-4 X
NRC to SCE 05/07/81 III-7 B.
DL/SEPB 3
SCE to NRC 11/20/81 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 7
NRC TO SCE 04/23/82 V-7 DSI/ASB 7
NRC to SCE 12/04/81 III-8 A.
DSI 7
NRC to SCE 12/21/81 V-8 X
HRC to SCE 05/07/81 III-8 B.
X NRC to SCE 10/01/80 V-9 X
NRC to SCE 11/16/79 III-8 C.
DL/SEPB 7
HRC to SCE 01/29/80 V-10 A.
DL/SEPB 7
NRC to SCE 01/07/81 III-8 D.
X NRC to SCE 05/07/81 V-10 B.
DL/SEPB 6
SCE TO NRC 04/26/82 III-9 X
NRC to SCE 05/07/81 V-11 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 6(SYS)
SCE TO NRC 04/26/82 DL/SEPB 7(Elec) HRC to SCE 02/04/82 (2-36)
SAN ON0FRE TOPIC HO.
REVIEW STATUS REMARKS TOPIC HO.
REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.
X HRC to SCE 11/16/79 VI-7 D.
DL/SEPB 7
HRC to SCE 08/17/78 V-13 X
NRC to SCE 05/07/81 VI-7 E.
X NRC to SCE 05/07/81 VI-1 7
HRC TO SCE 07/13/82 VI-7 F.
X HRC to SCE 11/16/79 VI-2 A.
X HRC 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
NRC to SCE 11/16/79 VI-2 C.
X NRC to SCE 11/16/79 VI-10 A.
DL/SEPB 7
NRC to SCE 08/28/81 VI-2 D.
DSI/CSB 7
NRC TO SCE 05/27/82 VI-10 B.
DL/SEPB 7
NRC to SCE 11/15/79
'VI-3 DSI/CSB 7
NRC TO SCE 05/27/82 VII-1 A.
DL/SEPB 7
NRC to SCE 09/09/81 VI-4 DSI/CSB 5(SYS)
NRC TO SCE 03/03/82 DL/SEPB 7(Elec) HRC to SCE 09/03/81 VII-1 B.
DL/SEPB 7
HRC to SCE 08/17/78 VI-5 X
NRC to SCE 25/07/81 VII-2 DL/SEPB 7
NRC to SCE 11/17/31 VI-6 DSI/CSB G
NRC to SCE 05/07/81 VII-3 DL/SEPB 6(SYS)
SCE TO NRC 04/26/82 DL/SEPB 7(Elec) HRC to SCE 06/04/82 VI-7 A.
1 DL/SEPB 7
HRC to SCE 02/20/81 VII-4 X
HRC 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 7
NRC to SCE 11/18/81 VII-6 DL/SEPB 7
HRC to SCE 08/28/81 VI-7 A. 4.
X HRC to SCE 05/07/81 VII-7 X
NRC to SCE 11/16/79 VI-7 B.
DSI/RSB 6(SYS)
SCE TO NRC 01/26/82 DL/SEPB 7(Elec) HRC to SCE 09/04/81 VIII-1 A.
DSI/RSB G
HRC to SCE 05/07/81 VI-7 C.
DL/SEPB 7
NRC to SCE 06/01/81 VIII-2 DL/SEPB 7
HRC to SCE 07/31/81 VI-7 C.
1.
DL/SEPB 7
HRC to SCE 08/03/81 VIII-3 A.
DL/SEPB 7
NRC to SCE 1'/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 HRC to SCE 11/16/79 VIII-4 DL/SEPB 6
SCE TO HRC 05/26/82 (2-37)
SAN ON0FRE TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 4B SCE TO NRC 04/29/82 XV-10 DSI/RSB 7
NRC to SCE 05/07/81 XV-11 X
NRC to SCE 10/01/80 IX-3 DL/SEPB 4b SCE to NRC 11/02/81 XV-12 DSI/RSB 7(Sys)
NRC to SCE 04/05/82 DL/SEPB 7(Doses) HRC to SCE 01/29/80 IX-4 DSI/RSB 7
NRC to SCE 07/16/81 XV-13 X
NRC to SCE 11/16/79 IX-5 DL/SEPB 4A 07/02/82 XV-14 DSI/RSB 7
NRC to SCE 05/07/81 XV-15 DSI/RSB 7
HRC TO SCE 04/20/82 X
X NRC to SCE 05/07/81 XV-16 DSI/AEB 7
NRC to SCE 04/05/82 XI-1 X
NRC to SCE 12/04/81 XV-17 DSI/RSB 7(Sys)
SCE TO NRC 03/12/82 XI-2 X
NRC to SCE 12/04/81 DSI/AEB 7(Doses) HRC to SCE 01/29/80 XIII-1 X
HRC to SCE 05/07/81 XV-18 X
NRC to SCE 10/01/80 XIII-2 DL/SSPB 7
NRC to SCE 01/22/81 XV-19 DSI/RSB 7(Sys)
SCE TO NRC 03/12/82 DL/SEPB 7(Doses) HRC to SCE 01/29/80 XV-1 DSI/RSB 6
SCE TO HRC 03/12/82 XV-20 DL/SEPB 7
NRC to SCE 03/28/80 XV-2 DSI/RSB 6(Sys)
SCE to NRC 03/12/82 DL/SEPB 7(Doses) HRC to SCE 01/29/80 XV-21 X
NRC to SCE 55/07/81 XV-3 DSI/RSB 7
NRC TO SCE 03/12/82 XV-22 X
NRC to SCE 05/07/81 XV-4 DSI/RSB 7
NRC to SCE 04/05/82 XV-23 X
NRC to SCE 05/07/81 XV-5 DSI/RSB 7
NRC to SCE 02/01/82 XV-24 X
NRC to SCE 05/07/81 XV-6 DSI/RSB 7
NRC TO SCE 03/03/82 AVI X
NRC to SCE 11/05/80 XV-7 DSI/RSB 4b SCE to NRC 07/01/81 XVII DL 7
NRC to SCE 11/20/79 XV-8 DSI/CPB 7
SCE TO 14RC 03/12/82 XV-9 DSI/RSB 7
NRC to SCE 02/24/82 (2-38)
YANKEE FACILITY: YANKEE NUCLEAR POWER STATION TOPIC NO.
REVIEW STATUS REMARKS LICENSEE: YANKEE ATOMIC ELECTRIC I
II-1 A.
DE/SAB 7
NRC 10 YAEC 07/13/82 REGION / LOCATION: 25 MILES NORTH EAST OF PITTSFIELD, MASS.
II-1 B.
DE/SAB 7
HRC TO YAEC 07/13/82 DOCKET NO.
05000029 II-1 C.
DE/SAB 7
NRC TO YAEC 07/13/82 POWER CAPACITY: 600(THERMAL) 165(ELECTRICAL)
II-2 A.
DSI/AEB 7
NRC tc YAEC 08/03/81 OL NUMBER: DPR-3 II-2 B.
X NRC to YAEC 05/07/81 H.S.S.S.. WEST.
II-2 C.
DSI/AEB 7
NRC to YAEC 09/04/81 A/E FIRM: S&W II-2 D.
X NRC 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 II-3 B.
DE/HGEB 6
YAEC to NRC 03/16/81 OPERATING REACTORS PROJECT MANAGER: R. CARUSO II-3 B.
1 DE/HGEB 5
NRC to YAEC 02/09/81 M.BOYLElg INTEGRATED ASSESSMENT PROJECT MANAGER:
II-3 C.
DE/HGEB 3
Mtg Summary 11/27/81 II-4 D E/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 7
NRC TO YAEC 07/15/82 FROM REVIEW BRANCH X - DELETED II-4 C.
DE/GSB 7
NRC to YAEC 06/08/81 l
4b-SAR RECEIVED FROM O - TOPIC NOT LICENSEE
.II-4 D.
DE/HGEB 4B YAEC TO HRC 02/26/82 l
STARTED 5 - DRAFT SE SENT II-4 E.
DE/HGEB 3
Mtg Summary 12/17/81 1 - QUESTIONS RECEIVED TO UTILITY
.l FROM REVIEW BRANCH II-4 F.
DE/HGEB 4b YAEC to NRC 08/31/81 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY HRC III-1 DL/SEPB 5(Elec) HRC to YAEC 02/02/82 TO UTILITY DL/SEPB SCSYS)
HRC TO YAEC 06/18/82 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 4B YAEC TO HRC 03/18/82 4
RECEIVED BY NRC l
i (2-39)
YANKEE TOPIC NO.
REVIEW STATUS REMARKS TCPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR III-3 4.
DE/SEB 4B YAEC 10 NRC 03/18/82 III-10 B.
X NRC to YAEC 11/16/79 III-3 B.
X HRC to YAEC 12/26/80 III-10 C.
X NRC t'o YAEC 11/16/79 III-3 C.
DE/HGEB 4b YAEC to NRC 01/04/82 III-11 X
NRC to YAEC 05/07/81 III-4 A.
DSI/ASB 4A 06/30/82 III-12 X
NRC to YAEC 05/07/81 l
III-4 B.
DE/MTEB 7
NRC to YAEC 02/08/82 IV-1 A.
DL/SEPB 7
NRC to YAEC 04/18/79 III-4 C.
DSI/ASB 4B YAEC TO HRC 03/18/82 IV-2 DSI/ICSB 7
NRC to YAEC 12/23/81 III-4 D.
DE/SAB 7
NRC TO YAEC 07/13/82 IV-3 X
NRC to YAEC 05/07/81 III-5 A.
DL/SEPB 4A 07/26/82 V-1 X
NRC to YAEC 11/27/81 III-5 B.
DL/SEPB 7
NRC TO YAEC 06/29/82 V-2 X
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 7
NRC TO YAEC 07/13/82 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 7
NRC TO YAEC 03/18/82*
V-7 X
NRC to YAEC 12/14/81 III-8 A.
DSI 7
HRC to YAEC 12/29/81 V-8 X
NRC to YAEC 05/07/81 III-8 B.
X NRC to YAEC 10/01/80 V-9 X
NRC to YAEC 11/16/79 III-8 C.
DL/SEPB 7
HRC to YAEC 06/23/82 V-10 A.
DL/SEPB 7
NRC to YAEC 11/05/79 III-8 D.
X HRC to YAEC 05/07/81 V-10 B.
DL/SEPB 7
NRC to YAEC 02/01/82 III-9 X
HRC to YAEC 05/07/81 V-11 A.
DL/SEPB 7
NRC to YAEC 07/21/82 III-10 A.
DL/SEPB 7
NRC to YAEC 09/22/81 V-11 B.
DL/SEPB 7(Sys)
HRC to YAEC 02/01/82 DL/SEPB 7(Elec) NRC to YAEC 07/21/82 (2-40)
YANKEE i
i TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.
X HRC 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-1 DE/CEB 4B YAEC TO NRC 06/14/82 VI-7 F.
DL/SEPB 7
HRC 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
HRC to YAEC 11/16/79 VI-2 C.
X NRC to YAEC 11/16/79 VI-10 A.
DL/SEPB 7
NRC to YAEC 06/10/82
(
VI-2 D.
DSI/CSB 5
NRC TO YAEC 06/10/82 VI-10 B.
X NRC to YAEC 11/16/79 VI-3 DSI/CSB 5
HRC TO YAEC 06/10/82 VII-1 A.
DL/SEPB 7
NRC to YAEC 02/22/82 VI-4 DSI/CSB 3(Sys)
YAEC to NRC 01/29/82 VII-1 B.
DL/SEPB 7
NRC to YAEC 08/17/78 DL/SEPB 7(Elec) HRC to YAEC 03/05/82 VII-2 DL/SEPB 7
NRC to YAEC 02/01/82 VI-5 X
NRC to YAEC 05/07/81 VII-3 DL/SEPB 7(Sys)
NRC to YAEC 02/01/82 VI-6 DSI/CSB G
NRC to YAEC 05/07/81 DL/SEPB 5(Elec) NRC to YAEC 02/02/82 VI-7 A.
1.
DL/SEPB 7
HRC to YAEC 02/20/81 VII-4 X
NRC to YAEC 05/07/81 VI-7 A. 2.
X NRC to YAEC 05/07/81 VII-5 X
NRC to YAEC 05/07/81 VI-7 A. 3.
DL/SEPB 7
NRC to YAEC 02/08/82 VII-6 DL/SEPB 7
HRC to YAEC 08/28/81 VI-7'A. 4.
X NRC to YAEC 05/07/81 VII-7 X
NRC to YAEC 11/16/79 VI-7 B.
DSI/RSB 7(Elec) HRC to YAEC 06/04/81 VIII-1 A.
DSI/PSB G
NRC to YAEC 05/07/81 7(SYS)
NRC TO YAEC 07/13/82 VI-7 C.
DL/SEPB 7
NRC to YAEC 03/13/81 VIII-2 DL/SEPB 7
HRC to YAEC 09/03/81 1
VI-7 C. 1 DL/SEPB 7
NRC to YAEC 09/14/81 VIII-3 A.
DL/SEPB 7
NRC to YAEC 11/07/79 j
VI-7 C. 2.
DL/SEPB 7
NRC to YAEC 03/13/81 VIII-3 B.
DL/SEPB 7
NRC to YAEC 08/27/81 i
VI-7 C. 3.
DL/SEPB 7
NRC to YAEC 07/24/80 VIII-4 DL/SEPB 6
YAEC TO NRC 10/15/81 1
i (2-41)
YANKEE TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR I
IX-1 DSI/ASB 4b YAEC to NRC 11/18/81 XV-10 DSI/RSB 7
NRC TO YAEC 04/26/82 IX-2 X
NRC to YAEC 05/07/81 XV-11 X
NRC ts YAEC 10/01/80 I
IX-3 DL/SEPB 7
NRC TO YAEC 06/11/82 XV-12 DSI/CPB 7CSYS)
HRC TO YAEC 04/16/82 l
DSI/AEB 7(Doses) HRC to YAEC 12/29/81 IX-4 DSI/RSB 7
NRC TO YAEC 06/15/82 XV-13 X
NRC to YAEC 11/16/79 IX-5 DL/SEPB 7
NRC TO YAEC 06/14/82 XV-14 DSI/RSS 7
NRC TO YAEC 07/14/82 IX-6 DE G
HRC to YAEC 05/07/81 XV-15 DSI/RSE 7
NRC TO YAEC 05/10/82 X
X NRC to YAEC 05/07/81 XV-16 DSI/AEB 4A 07/28/82 XI-1 X
NRC to YAEC 12/04/81 XV-17 DSI/R$8 4A(SYS) 67/06/82 XI-2 X
NRC to YAEC 12/04/81 DSI/AEB 7(DOSES) HRC TO YAEC 03/30/82 i
XIII-1 X
NRC to YAEC 05/07/81 XV-18 X
NRC to YAEC 10/01/80 XIII-2 DL/SSPB 7
NRC to YAEC 03/11/81 XV-19 DSI/RSB 7(SYS)
HRC TO YAEC 07/13/82 DSI/AEB 4b(Doses)YAEC to NRC 01/04/82 XV-1 DSI/RSB 7
NRC TO YAEC 07/21/82
+
XV-20 DL/SEPB 7
NRC to YAEC 09/06/81 XV-2 DSI/RSB 7($YS)
HRC TO YAEC 07/13/82 DSI/AEB 0(Doses)
XV-21 X
NRC to YAEC 05/07/81 XV-3 DSI/R$8 7
NRC to YAEC 01/25/82 XV-22 X
HRC to YAEC 05/07/81 XV-4 DSI/RSB 7
NRC TO YAEC 07/21/82 XV-23 X
NRC to YAEC 05/07/81 XV-5 DSI/RSB 7
HRC to YAEC 02/10/82 XV-24 X
MRC to YAEC 05/07/81 XV-6 DSI/RSB 7
NRC TO YAEC 07/13/82 XVI X
NRC to YAEC 11/05/80 XV-7 DSI/RSB 7
NRC TO YAEC 06/29/82 XVII DL 7
NRC to YAEC 11/20/79 XV-8 DSI/CPB 7
NRC TO YAEC 03/05/82 XV-9 DSI/RSB 7
NRC TO YAEC 06/25/82 1
(2-42)
I 1
i i
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1.
r i
[
O H
G,3 a.mJ (l/)
1 l
PALISADES p.L PALISADES D.11 SAR 1/
SER 2/
SAR J/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE 111-1 Classification of EUEE 12/15/81C 111-8.A Loose Parts Monitoring and NONE 11/05/81C (SYS)
Structures Components and Core Barrel Vibration Systems (Seismic and Monitoring (NRR B-60, C-12)
Quality)
IV-2 Reactivity Control Systems 07/31/81R 10/16/81C III-5.A Effects of Pipe Break on 08/13/81R 12/04/81C Including Functional Design Structures, Systems and and Protection Against Components Inside Single Failures Containment V-7 Reactor Coolant P NONE 11/16/81C III-5.B Pipe Br eak Outside 08/25/81R 12/23/81C Overspeed (NP 5-Containment VI-6 C
i m n Lea Test ng NONE 08/05/89C III-7.A Inservice Inspection, NONE 08/25/81C (MF 4
Including Prestressed k
Concrete Containments with V
.A t tia quipment E
12/22/81C Either Grouted or Ungrouted
'\\
F ros Associated wi
,}
Tendons i
" Deoraded Grio t o 5
(MP B-23)
}
III-7.B Design Codes, Design NQ
/ 16 1C Criteria. Load G
IX-1 S
NONE 12/31/81C Combinations, and Reactor i Cavity Design rit]ia
")
IX-4{("'k lA on System 10/09/81R 11/18/81C E"
ror kg,/FireProtection(MPB-41) k 1
1 L
mL IX-6 NONE 03/05/82C
- ~
SEi XI-1 Appendix I(MP A-02)
NONE DELETED j,
TOPIC NO. TITLE S
HEI hL k
k J
XI-2 Radiological (Effluent NONE DELETED
-r III-3.C Inservice Inspecti of \\
\\'/ 21$ 1 RJ-0 2/12/ 82 C and Process) Monitoring Water Control ruct res 4A Systems (NRR B-67)
~
III-4.B T
ne Miss Ic MP B NONE 12/02/81C J/ SAR : Licensee Safety Analysis Report-Scheduled or Actual III-7.D
.i t a i renj,S uctural NONE 08/17/81C (Actual (status 4b) when date is followed by R) t gri ;y sests 2/ SER : Staff Safety Evaluation Report -Scheduled or Actual V-1
'ompliance with Codas and NONE DELETED (Actual (status 4a, 5, 7) when date is followed by C)
Standards (10 CFR 50.55a)
(MP A-01.A-14)
J/ Desiginated nu.aber of days from receipt of licensee SAR (Note: if Licensee SAR is received then date is from roccipt of additional information requested)
(3-2)
LICENSEE TOPIC SUBMITTALS PALISADES TOPICS 4g TARGET 35 ACTUAL 30 25 20 ALL SUBMITTALS RECEIVED 15.
'10 5
'/
~~
[I I
l l
l l
l l
l l
l g
JUN JUL AUG SEP OCT NOV DEC JAN FEB MAR APR MAY JUN JUL/DEC TARGET 1 '2 3
PER MONTH ACTUAL 1
2 0
1 1
1 TARGET 1
3 6
CUMULATIVE i
l ACTUAL 1
3 3
4 5
6 G-3)
GINNA EL GINNA p_S_[
SAR 1/
SER 2/
SAR 1/
SER g/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE III-l Classification of Struct-NONE 12/29/81C III-4.C Internally Generated 01/11/82R 02/02/82C (SYS) ures Componcnts and Systems Missiles (Seismic and Quality)
III-8.A Loose Parts Monitoring and NOME 11/ 0 3/81C III-2 Wind and Tornado Loadings NONE 09/23/81C Core Barrel Vibration Monitoring (NRR B-60,C-12)
III-7.A Inservice Inspection, NONE 12/23/81C Including Prestressed V-7 Reactor Coolant Pump NONE 11/05/81C Concreto Containments with Overspeed(NRR 8-68)
Either Grouted or Ungrounded Tendons VI-2.0 Mass and Ener 1
o for NONE 09/25/81C Possibl B eak 4 side III-7.B Design Codos, Desi gn NONE 12/31/81C Ce m
Criteria, Load
\\
Co-binations, and Reactor VI on nme assure and HJ 09/25/81C Cavity Design Criteria a
em Capabillt j
VI-7.C.1 Appendix K - Electrical NONE 11/
4 VI "ESF Switchover om NON 12/18/81C (SY Injection oci c at' j
Instrumentation and Control (EIC) Re-reviews T
Mode (
t o-ti CS j("'k IX-S Ventilation Systems F
1/
IC 1
ht NONE 11/24/81C 90 d'
IX-1 A
1 L 1 Hi
~
IX-6 Fire Protection (MP B-41)
NONE 02/24/82C TOPIC NO. TITLE SCH D ~1/~ q
[
I-1 Appendix I(MP A-02)
NONE DELETED SAR t
11-1.8 Population Distributto 4/ 5 TR 0 342)/8 TE XI-2 Radiological (Effluent NDHE DELETED and Process) Monitoring II-1.C Potential Haza i or 15 R
07/01/81C Systems (NRR B-67)
Changog,4n ter ial H ~ Js Due XV-9 Startup or an Inactive Loop NONE 10/16/81C r s or tat or Recirculation Loop at an idstit t ion,4
- dustrial, Incorrect Temperature, and nb Mi l tary Facilities Flow Controller Malfunction Causing an Increase in BWR II-4.D tability of Slopes 06/30/81R 02/01/82C Core Flow Rate II-4.F Setticment of Foundations 06/30/81R 01/29/82C XV-19 Loss of-Coolant Accidents NONE 09/29/81C o,d Buried Equipment (DOSES)
Resulting from Spectrum of (SYS)
Postulated Piping Breaks 10/02/81C III-3.C Aaservice Inspection of 10/12/81R 02/09/82C Within the Reactor Coolant Water Cantrol Structures Pressure Boundary III-4.B Turbine Missiles (MP B-46)
NONE 12/02/81C J/ SAR Licensee Safety Analysis Report-Scheduled or Actual (actual (status Ab) when date is follwed by R)
III-4.D Site Proximity Missiles 04/16/81R 07/21/81C (Inc)uding Aircraft) 2/ SER : Staff Safety Evaluation Report -Scheduled or Actual (Actual (status 4a, S, 7) when date is followed by C)
VI-1 Organic Materials and 11/06/81R 02/18/82C Post Accident Chemistry J/ Desiqinated number of days from receipt of licensee SAR (Note:
if Licensee SAR is received than date is from receipt of additional information requested)
(3-4)
LICENSEE TOPIC SUBMITTALS GINNA TOPICS 4g TARGET 35 ACTUAL 30 25 20 ALL SUBMITTALS RECEIVED 15 t
la 5
~~
l lT l
l l
l l
l g
JUN JUL AUG SEP OCT NOV DEC JAN FEB MAR APR MAY JUN JUL/DEC T E ET 0
0 2
0 0
1 PER MONTH ACT E O
O O
1 1
1 TEET 0
0 2
2 2
3 CUMULATIVE ACT R 0
0 0
1 2
3 G-5)
DRESDER 2 D1 DRESDEN 2 DE (Cont.)
SAR 1/
SER Z/
SAR 1/
SER Z/
TOPIC HO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE 111-1 Classification of H0HE 05/03/82C 11-3.8 Flooding Potential and NOME 0 6 /11/82C (SYS)
Structures, Components and Protection Requirements Systems (Seismic and Quality)
II-3.B.1 Capability of Operating NONE 06/11/82C Plant to Cope with Design III-2 Wind and Tornado Loadings 06/04/82R 06/21/82C Basis Flooding Conditions l
III-5.A Effects of Pipe Break on 06/04/82R 06/28/82C II-3.C Safety-related Water NDHE 06/11/82C Structures, Systems and Supply (Ultimate Heat Sink Components Inside (UHS))
Containment II-4.D Stabil S o es 12/08/81R 07/02/82C III-7.B Design Codes. Design NOHE 05/17/82C Criteria, Load II-4.E Da nt 12/08/
01/22/82C Combinations, and Reactor Cavity Design Criteria I
et lem f Foundati 06/30/82C T
uried Equipment j
VI-4 Containment Isolation H0HE 11 C
1 s-(ELEC)
System i
II A
Effects o-a rL 1 (12
/ 1R 05/24/82C on S cti VII-1.A Isolation of Reactor
+4%
0 0 81C Protection System from
(
III-3r W(
e ns v
tion of 02/16/82R 06/30/82C ate t
Structures Hon-Safety System j
Including Qu ific tions of 9
III-4 T
ine Misslies H0HE 05/18/82C Isolation av es VII-6 Frequency a
NONE
/
III-4.D Site Proximity Missiles 12/08/81R 02/05/82C (Including Aircraft)
IX-5 Ventilatio,n Systems l
'(
(NO E
/
l ar 1
t
..JL 3r
'L III-7.D Containment Structural 04/27/81R 03/30/82C
-e Integrity Tests
(,s} ""
$AR 1/
SER 2/
V-1 Compilance with Codes NONE DELETED TOPIC H L
SCHEDULE SCHEDULE and Standards (10 CFR l
t
\\
50.55a)(MP A-01,A-14)
II-1.A uslon irrea Authority 06/01/81R 09/16/81C Control V-4 Piping and Safe End NONE 06/25/82C Integrity II-1.B Population Distribution 04/27/81R 09/16/81C VI-1 Organic Materials and 05/21/82k 07/02/82C II-1.C Potential Hazards or 12/08/81R 06/30/82C Post Accident Chemistry Changes in Potential Hazards Due to Transportation, 211 Institutional Industrial, SAR 1/
SER 2/
and Military Facilities TOPIC HO. TITLE SCHEDULE SCHEDULE II-3.A Hydrologic Description NONE 0 6/11/82C 11-2.C Atmospheric Transport and 03/20/81R 08/26/81C Diffusion Characteristics for Accident Analysis III-4.A Tornado Missiles 12/08/81R 06/21/82C (3-6)
~ _ _ _ _
DRESDEN 2 211 (cont.)
211 (Cont.)
SAR 1/
SER g/
SAR J/
SER 2/
TOPIC HO. TITLE SCHEDULE SCHEDULE TOPIC HO. TITLE SCHEDULE SCHEDULE 11I-4.C Internally Generated 05/11/82 R 06/22/82C XV-3 Loss of External Load, 10/15/81R 11/17/81C Missiles Turbine Trip, Loss of Condenser Vacuum, Closure III-8.A Loose Parts Monitoring NONE 02/09/82C of Main Steam Isolation and Core Barrel Vibration Valve (BWR), and Steam Monitoring (NRR B-60,C-12)
Pressure Regulator Failure (Closed)
IV-2 Reactivity Control Systems NONE 09/28/81C Including Functional Design XV-4 Loss of Non-Emergency A-C 10/15/81R 11/17/81C and Protection Against Power to the Station Single Failures Auxillaries VI-2.0 Mass and Energy Release for NONE 12/02/81C XV-5 Loss of Normal Feedwater 10/15/81R 12/04/81C Possible Pipe Break Inside Flow Containment XV-7 Reactor Coolant Pump Rotor 10/15/81R 12/18/81C VI-3 Containment Pressure and NONE 12/02/81C Seizure and Reactor Coolant H.*at Removal Capability Pump Shaft Break VI-4 Containment Isolation NONE 10/02/81C XV-8 Control Rod Misoperation 10/15/81R 01/27/82C (SYS)
System (System Malfunction or Operator Error)
VI-6 Containment Leak Testing NCHE 12/30/81C (MP A-04)
XV-9 Startup or an Inactive Loop 10/15/81R 12/07/81C or Recirculation Loop at an VI-7.A.4 Core Spray Hozzle NONE 02/09/82C Incorrect Temperature, and Effectiveness (NRR A-16)
Flow Controller Malfunction Causing an Increase in BWR VIII-1.A Potential Equipment NONE 03/31/82C Core Flow Rate Failures Associated with a Degraded Grid Voltage XV-11 Inadvertent Loading and 10/15/81R 01/25/82C (MP B-23)
Operation of a Fuel Assembly in an Improper IX-1 Fuel Storage 02/02/82R 03/26/82C Position IX-6 Fire Protection (MP B-41)
N0HE 06/23/82C XV-13 Spectrum of Rod Drop 10/15/81R 01/25/a2C (SYS)
Accidents (BWR)
XI-1 Appendix I(MP A-02)
N0HE DELETED (DOSES) 10/15/81R 12/14/81C XI-2 Radiological (Effluent and NONE
. DELETED XV-14 Inadvertent Operation of 10/15/81R 12/08/81C Process) Monitoring Systems ECCS and Chemical and (NRR B-67)
Volume Control System Malfunction that Increases XV-1 Increase in Feedwater 10/15/81R 12/14/81C Reactor Coolant Inventory Temperature, Increase in i
Feedwater Flow, Increase XV-15 Inadvertent Opening of a 10/15/81R 12/22/81C in Steam Flow and PWR Pressurizer Safety-Inadvertent Opening of a Relief Valve or a BWR Steam Generator Relief or Safety / Relief Valve Safety Valve 1
(3-7)
~
l-r 1)lRti!!!IDilillit R11 (Cont.)
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE XV-18 Radiological Consequences 10/15/51R 12/23/81C of Main Steam Line Failure Outside Containment (BWR)
XV-19 Loss-of-Coolant Accidents 10/15/41R 11/17/81C (SYS)
Resulting from Spectrum of 1
(DOSES)
Postulated Piping Breaks 10/15/d1R 12/15/81C i
Within the Reactor Coolant i
Pressure Boundary XV-20 Radiological Consequences 04/27/81R 11/04/81C of Fuel Damaging Accidents (Inside and Outside Containment 4
t l/ SAR = Licensee Safety Analysis Report-Scheduled or Actual (actual (status 4b) when date is followed b/ R) t i
2/ SER : Staff Safety Evaluation Report -Scheduled or Actual (Actcal (status 4a, 5, 7) when date is followed by C) 1/ Desiginated number of days from receipt of Ilcensee SAR (Notet if Licensee SAR is received then date is from receipt-of additional information requested) i a
I I
i I
(3-8)
L LICENSEE TOPIC SUBMITTALS DRESDEN 2 TOPICS 40 TARGET 35 ACTUAL 30 i
25
, -f
_ f_
20 ALL SUB TTALS RECEIVED 15 10 5
~~
l l
l l
i i
l l
l l
l g
JUN JUL AUG SEP OCT NOV DEC JAN FEB MAR APR MAY JUN JUL/DEC TARGET 0
3 2
0 0
1 2
PER MONTH.
i ACTUAL 0
0 0
14 0
7 0
1 1
0 2
1 22 22 23 25 25 25 26 TARGET CUMULATIVE ACTUAL 0
0 0
14 14-21 21 22 23 23 25 26
{
G-9)
A
0YSTER CREEK RL OYSTER CREEK Ef (Cont.)
SAR 1/
SER 2/
SAR 1/
SER Z/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE III-1 Classification of NONE 01/29/82C 111-4.8 Turbine Missiles 12/07/81R 06/27/82C (SYS)
Structures, Components and Systems III-4.D Site Proximity Missiles 03/31/82N 06/21/82C III-2 Wind and Tornado Loadings 03/31/82N 06/08/82C III-7.D Containment Structural 11/04/81R 02/25/82C Integrity Tests III-7.B Design Codes, Design NONE 04/30/82C Criteria, Load Combinations V-1 Compliance with Codes NONE DELETED and Reactor Cavity Design and Structures (MP A-01, A-14 )
VII-6 Frequency Decay NONE 08/29/81C VI-1 Organic Mat s
d Post 07/30/82H 06/29/82C d
emi try IX-5 Ventilation System 02/28/82N 05/21/82C AgrMh VI-7.A-4 Core Spray Nozzle NONE 06/28/82C 1
t"\\
1 1 "E'
1 Effectiveness (MP D-12)
E11 g
j 7
-r 'T 11 T PI Ne. TITLE HE SCHEDULE 21 D
d i
1/
S 2/ 1 II-2.C Atmo hei sp et afd ' 11/ 04/81R 02/24/82C 9
TOPIC NO. TITLE
/*i ULE H
LE-fu i
acte ~
ics g--(l L
fo lA alysis II-1.A Exclusion Are A ority 30$1R' 01/18/82C J
and Cont ol
)
"'k III
.A sa Missles 03/31/82N 05/27/82C II-1.B Populati a Di tr n
11/30/81R 18 '
III-4.C Internally Generated 05/19/82R 05/28/82C j
Missiles 01/ l8 2C b
II-1.C Potential zards Due to 1
0 8 Transportation, Indus tal III-8.A Loose Parts and Core NONE 02/09/82C and Military Faci ie Barrel Monitoring (NRR B-60,C-12)
II-3.A Hydrolpgi c Des ript on 04/82R 06/28/82C IV-2 Reactivity Control Systems 02/28/82H 05/24/82C II-3.B o 1
,g l' n
and 03/04/82R 06/28/82C rot t i oj L R utrements VI-2.D Mass and Energy Release for NONE 11/20/81C Possible Pipe Break Inside II-3.B-1 ability to Lope with 03/04/82R 06/28/82C Containmant Design Basis Flood VI-3 Containment Pressure and NONE 11/20/81C II-3.C Safety Related Water Supply 03/04/82R 06/28/82C
, Heat Removal Capability (Ultimate Heat Sink)
VI-4 Containment Isolation NGHE 10/22/81C II-4.D Stability of Slopes 12/15/diR 06/14/82C System II-4.F Settlement of Foundation 11/04/81R 06/03/82C VI-6 Containment Leak Testing NONE 06/04/81C and Buried Equipment (MP A-04)
III-3.A Effects of High Water 03/04/82R 05/05/82C VIII-1.A Fotential Equipment NONE 10/16/81C Level on Structures Failures Associated with a Degraded Grid Voltage III-3.C Inservice Inspection of 11/12/81R 06/03/82C (MP B-23)
Water Control Structure (3-10)
0YSTER CREEK 211 (Cont.)
211 (Cont.)
SAR 1/
SER 2/
SAR 1/
SER 2/
TOPIC NO. TITLE SCHtDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCNEDULE IX-1 Fuel Storage 03/04/82R 05/18/82C XV-15 Inadvertent Opening of BWR 05/07/81R 11/19/81C Safety / Relief Valve IX-6 Fire Protection (MP B-41)
NONE 05/18/82C XV-16 Radiological Consequences 11/04/81R 04/01/82C of Failure of Small Lines XI-1 Appendix I(MP A-02)
NONE DELETED Carrying Primary Coolant Outside Containment XI-2 Radiological (Effluent and NONE DELETED Proccss Monitoring Systems)
XV-18 Radiological Consequences 05/07/81R 07/01/81C (NRR B-67)
Main Steam Line Failure XV-1 Decrease in Feedwater 05/07/81R 12/07/81C Outside Containment Temperature, Increase in Feedwater Flow, Increase in XV-19 Loss of Coolant Accideats 05/07/81R 09/04/81C Steam Flow, Inadvertent (SYS)
Resulting From Spectrum Opening of Stcam Generator, Breaks Within Reactor Relief or Safety Valve (DOSES)
Coolant Pressure Boundary 02/28/82N 06/03/82C XV-3 Loss of External Load.
05/07/81R 07/16/81C XV-20 Radiological Consequences 02/26/82N 04/19/82C Turbine Trip, Loss of of Fuel Danaging Accidents Condenser Vacuum, Closure (In & Out of Containment) of Main Steam Isolation Valve (BWR), Steam Pressure Regulatory Failqfe (closed)
J/ SAR : Licensee Safety Analysis Report-Scheduled or Actual (actual (status 4b) when date is followed by R)
XV-4 Loss of Non-Emergency A-C 05/07/81R 07/16/81C Power to the Station 2/ SER = Staff Safety Evaluation Report -Scheduled or Actual Auxillaries (Actual (status 4a, 5, 7) when date is followed by C)
XV-5 Loss of Normal Feedwater 05/07/81R 11/30/81C J/ Desiginated number of days from receipt of licensee SAR Flow (Note 2 if Licensee SAR is received then date is from receipt of additional information requested)
XV-7 Reactor Coolant Pump Rotor 08/25/81R 12/07/81C Sei:ure and Reactor Coolant NOTE:
N-No submittal received, therefore Safety Evaluation Pump Shaft Break preformed without.
XV-9 Startup or an Inactive Loop 05/07/81R 12/30/81C or Rectreulation Loop at Incorrect Temperature and Flow Controller Malfunction Causing an Increase in BWR Core Flow Rate XV-13 Spectrum of Rod Drop HONE 04/09/81C (sys)
Accident 05/07/81R 07/01/81C (doses)
XV-14 Inadvertent Operation of 05/07/81R 07/16/81C ECCS that Increases Reactor Coolant Inventory (3-11)
LICENSEE TOPIC SUBMITTALS OYSTER CREEK TOPICS 4g TARGET 35 ACTUAL 30 25 p
/
20 COMPLETE f
/
/
15 10 5
~~
l l
I l
l l
l l
l l
l g
JUN JUL AUG SEP OCT NOV DEC JAN FEB MAR APR MAY JUN JUL/DEC TARET 5
3 0
0 0
1 PER MONTH ACTUAL 0
0 0
-0 8
2 0
0 6
0 0
1 TARET 16 21 24 24 24 24 25 CUMULATIVE ACTUAL 0
0 0
1 8
10 10 10 16 16 16 17 (3-12) i
MILLSTONE 1 Di MILLSTONE 1 QE (Cont.)
SAR 1/
SER 2/
SAR 1/
SER 2/
TOPIC HO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE III-1 Classification of NONE 03/19/82C II-3.A Hydrologic Description 06/25/81R 06/25/82C (SYS)
Structures, Components and Systems (Seismic and II-3.B Flooding Potential 8 06/26/81R 46/25/82C Quality)
Protection Requirements III-2 Wind and Tornado Loadings NONE 04/30/82C II-3.B.1 Capability of Operating 06/25/81R 06/25/82C Plant to Cope with Design III-5.A Effects of Pipe Break on 04/13/82R 06/08/82C Basis Flooding Conditions Structures, Systems and Components Inside II-3.C Safety Related Wa 04/28/81R 06/25/82C Containment Supply (UHS)
III-5.B Pipe Break Outside 12/04/81R 02/09/82C II-4.B P
Ca able NONE 12/30/81C Containment T
ct es k
P1 Vi y
III-7.B Design Codes, Design NONE 05/20/82C d
Criteria, Load Combinations
"\\
II ity of Slopes 8 1/
R J05/26/82C and Reactor Cavity Design 1
1 II Settlement d tion j4
/(
w, 06/03/82C R
V-11.5 RHR Interlock Requirements NON
/2c
'C and B ed n
(ELEC) d i
III-3pe-(
pction of 08/31/81R 05/24/82C s
v terl atructures VII-3 Systems Required Safe
- ft/22/82C l
CELEC)
Shutdown III-4.
T ine Missiles 08/31/81R 06/27/82C VII-6 Frequency ca NONE 0
/
j III-4.D Site Prximity Missiles 04/29/81R 10/29/81C Station S e and Cooling 11 1
4
/3 f (Including Aircraft)
IX-3 Water Sys,nr tems L
k.
IV-3 BWR Jet Pumps Operating NONE 02/22/82C IX-5 Ventilation Sy ems 19 1 R' 04/28/82C Indications XIII-2 S
IIds du ri 1
~NONE 06/02/82C V-1 Comp) lance with Codes and H0HE DELETED
'(MP 10 Standards (10 CFR 50.55a) u 1
(MP A-dl,A-14)
E5 t 1
~
RE JL '
VI-1 Organic Materials and Post 09/30/81R 01/28/82C SAR 1/
SER 2/
Accident Chemistry TOPIC HO. TITLE SCHEDULE SCHEDULE Il-1.A Exclusion Area Authority &
04/17/81R 07/31/81C Q11 Control SAR 1/
SER 2/
TOPIC NO. TITLE SCHFDU[E SCHEDULE II-1.B Population Distribution 05/19/81R 10/29/81C Il-2.C Atmospheric Transport and 05/19/81R 08/10/81C II-1.C Potential Hazards or 04/29/81R 10/29/81C Diffusion Characteristics Changes in Potential for Accident Analysis Hazards Due to Transporta-tion, Institutional, and III-4.A Tornado Missiles 08/31/81R 05/05/82C Military Facilities (3-13)
MILLSTONE 1 gil (Cont.)
Dil (Cont.)
SAR 1/
SER 2/
SAR 1/
SER 2/
TOPIC NO. TITLE SCHtDULE SCH6DULE TOPIC HO. TITLE SCHEDULE SCHEDULE III-4.C Internally Generated 04/13/82R 05/25/82C XV-3 Loss of External Load.
06/30/81R 09/18/81C Missiles Turbine Trip, Loss of Condenser Vacuum, Closure III-8.A Loose Parts Monitoring and NONE 02/09/82C of Main Steam Isolation Core Barrel Vibration Valve (BWR), and Steam Monitoring (NRR B-60,C-12)
Pressure Regulator Failure (Closed)
IV-2 Reactivity Control Systems 10/28/81R 05/20/820 Including Functional Design XV-4 Loss of Non-Emergency A-C 06/30/81R 09/18/81C and Protection Against Pcwer to the Station Single Failures Auxiliarics VI-2.D Mass and Energy Release for H0HE 05/10/82C XV-5 Loss of Normal Feedwater 06/30/81R 12/23/81C Possible Pipe Break Inside Flow Containment XV-7 Reactor Coolant Pump 06/30/81R 11/18/81C VI-3 Containment Pressure and H0HE 05/10/82C Rotor Seizure and Reactor Heat Removal Capability Coolant Pump Shaft Break VI-4 Containment Isolation NOHE 11/16/81C XV-8 Control Rod Misoperation 06/30/81R 08/26/(1C (SYS)
System (System Malfunction or Operator Error)
VI-6 Leak Testing (MP A-04)
NONE 06/01/82C XV-9 Startup or an Inactive Loop 06/30/81R 12/30/81C VI-7.A.4 Core Spray Hozzle NOME 02/09/82C or Recirculation loop at an Effectiveness (HRR A-16)
Incorrect Temperature, and Flow Contrcller Malfunction VIII-1.A Potential Equipment NDHE 06/02/82C Causing an Increase in BWR Failures Associated With a Core Flow Rate Degraded Grid Voltage XV-11 Inadvertent Loading and 06/30/81R 10/14/81C IX-1 Fuel Storage 08/31/81R 02/19/82C Operation of a Fuel Assembly in an Improper IX-6 Fire Protection (MP B-41)
NONE 05/17/82C Position XI-1 Appendix I(MP A-02)
HONE DELETED XV-13 Spectrum of Rod Drop 06/30/81R 09/09/81C (SYS)
Accidents (BWR)
XI-2 Radiological (Effluent &
NONE DELETED (DOSES) 06/30/81R 0 9/21/81C Process) Monitoring Systems (NRR B-67)
XV-14 Inadvertent Operation of 06/30/81R 09/18/81C ECCS and Chemical and XV-1 Decrease in Feedwater 06/30/81R 12/15/81C Volume Control System Temperature, Increase in Malfunction that Increases
~~
Feedwater Flow. Increase in Reactor Coolant Inventory Steam Flow and Inadvertent Opening of a Steam Gener-XV-15 Inadvertent Opening of a 06/30/81R 10/28/81C ator Relief or safety Valve PWR Pressurizer Safety Relief Valve or a BWR Safety Relief Valve (3-14)
MILLSIONE 1 pil (Cont.)
SAR 1/
SER 2/
TOPIC HO. TITLE SCHEDULE SCHEDULE XV-16 Radiological Consequences 06/30/81R 09/21/81C of Failure of Small Lines Carrying Primary Coolant Outside Containment XV-18 Radiological Consoquences 06/30/81R 09/21/8tC of Main Steam Line Failure Outside Containment (BWR)
XV-19 Loss of Coolant Accidents 06/30/81R 08/26/81C (SYS)
Resulting from Spectrum of (DOSES)
Postulated Piping Breaks 06/3C/81R 09/21/81C Within the Reactor Coolant Pressure Boundary XV-20 Radiological Consequences 06/30/81R 09/21/81C of Fuel Damaging Accidents (Inside and Outside Containment)
J/ SAR : Licensee Safety Analysis Report-Scheduled or Actual (actual (status 4b) when date is followed by R)
Z/ SER : Staff Safety Evaluation Report -Scheduled or Actual.
(Actual (status 4a, S, 7) when date is followed by C) 3/ Desiginated number of days from receipt of licensee SAR (Note:
if Licensee SAR is received then date is from receipt of additional information requested)
(3-15)
LICENSEE TOPIC SUBMITTALS MILLSTONE 1 TOPICS 40 TARGET 35 ACTUAL 30 25 20 ALL SUBMITTALS RECEIVED 15 10
~
s
~~
l I
I i
l l
l l
l l
l g
JUN JUL AUG SEP OCT NOV DEC JAN FEB MAR APR MAY JUN JUL/DEC
~
PER MONTH ACTUAL 0
5 0
2 2
1 0
0 0
2 TARGET 10 10 12 ACTUAL 0
5 5
7 9
10 10 10 10 12 (3-16)
SAN ON0FRE R1 SAN ONOFRE SAR l/
SER 2/
SAR J/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC HO. TITLE SCHEDULE SCHEDULE IX-3 Station Service and Cooling 11/ 02 / 81 R 06/30/82 111-1 Classification of NONE 06/23/82C Water Systems Structures, Components and Systems (Seismic and IX-5 Ventilation Systems 12/16/81 R 07/02/82C Quality)
III-2 Wind and Tornado Loadings 05/04/82R 08/30/82 RE SAR 1/
SER 2/
III-5.A Effects of Pipe Break on 12/01/82 12/30/82 TOPIC NO. TITLE SCHEDULE SCHEDULE Structures, Systems and Components Inside II-1.C Potential Hazarcs-ar 11/12/81R 08/06/82 Containment Changes in Potential Hazards Due to III-5.B Pipe Break Outside 12/01/82 12/10/82 Transpor+ation, Containment Institutional Industrial, and Military Facilities III-6 Seismic Design HONE 08/30/82 Considerations II-3.A Hydrologic Description H0HE 11/30/82 III-7.B Design Codes, Design NDHE 08/31/82 II-3.B Flooding Potential &
N0HE 11/30/82 Criteria, Load Protection Requirements Combinations, and Reactor Cavity Design Critoria II-3.B 1.
Capability of Operating NONE 11/30/82 Plant to Cope with Design V-11.B RHR Interlock Requirements H0HE 02/04/82C Basis Flooding Conditions (ELEC)
II-3.C Safety Related Water NONE 11/30/82 VI-7.A.3 ECCS Actuation System N0HE 11/18/81C Supply (UHS)
VI-7.B ESF Switchover from N0HE 09/04/81C II-4.D Stability of Slopes 11/02/81R 10/31/82 (ELEC)
Injection to Recirculation Mode (Automatic ECCS II-4.F Settlement of Foundations 11/02/81R 10/31/82 Realignment) and Buried Equipment VI-10.A Testing of Reactor Trip NDHE 08/28/81C III-3.A Effects of High Water Level 05/30/82 09/30/82 System and Engineered on Structures Safety Features Including Response Time Testing III-4.B Turbine Missiles (MP B-46)
N0HE 06/24/82C VII-1.A Isolation of Reactor H0HE 09/09/81C III-4.D Site Proximity Missiles 10/23/81R 09/30/82 Protection Systems, (Including Aircraft)
Including Qualifications of Isolation Devices III-7.D Containment Structural 06/09/81R 04/14/82C Integrity Tests VII-2 Engineered Safety Features NONE 11/18/81C (ESF) System Control Logic V-1 Compliance with Codes and NONE DELETED and Design Standards (10 CFR 50.55a)
(MP A-01)
VII-2 Systems Required for Safe N0HE 11/18/81C (ELEC)
Shutdown VI-1 Orqanic Materials and Post 01/28/82C 06/18/82C Accident Chemistry VII-6 Frequency Decay NONE 08/28/81C (3-17)
SAN ON0FRE M
Dil (Cont.)
SAR J/
SER 2/
SAR J/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE 111-4.A Tornado Missiles 05/04/82R 06/15/82 XV-2 Spectrum of Steam System 07/01/81R 10/27/81C Piping Failures Inside and III-4.C Internally Generated 04/29/82R 06/15/82 Outside of Containment (PWR)
Missiles XV-3 Loss of External Load.
07/01/81R 08/26/81C III-8.A Loose Parts Monitoring and NONE 12/07/81C Turbine Trip, Loss of Con-Core Barrel Vibration densor Vaccum, Closure of Monitorinq(NRR B-60,C-12)
Main Steam Isolation Valve (BWR), and Steam Pressure IV-2 Reactivity Control Systems 04/30/82R 06/15/82 Regulator Failure (Closed)
Including Functional Design and Protection Against XV-4 Loss of Hon-Emergency A-C 08/18/81R 12/12/81C Single Failures Power to the Station Auxiliaries V-7 Reactor Coolant Pump NONE 11/05/81C Overspeed(NRR B-68)
XV-5 Loss of Hormal Feedwater 07/01/81R 01/25/82C Flow VI-2.D Mass and Energy Release for NOHE 12/04/81C Possible Pipe Break Inside XV-6 Feedwater System Pipe 07/01/81R 02/19/82C Containment Breaks Inside and Outside Containment (PWR)
VI-3 Containment Pressure and HONE 12/04/81C Heat Removal Capability XV-7 Reactor Coolant Pump Rotor 07/01/81R 05/01/82 seizure and Reactor Coolant VI-4 Containment Isolation NONE 01/29/82C Pump Shaft Break (SYS)
System XV-8 Control Rod Misoperation 07/01/81R 11/19/81C VI-6 Containment Leak Testing NDHE 03/31/82 (System Malfunction or (MP A-04)
Operator Error)
VIII-1.A Potential Equipment Failure NDHE 05/01/82 XV-10 Chemical and Volume Control 07/01/81R 03/28/82C Associated with a Degraded System Malfunction that Grid Voltage (MP B-23)
Results in a Decrease in the Boron Concentration in IX-1 Fuel Storage 04/29/82R 06/15/82 the Reactor Coolant (PWR)
IX-6 Fire Protection (MP B-41)
NDHE 10/31/82 XV-12 Spectrum of Rod Ejection 07/01/81R 11/19/81C Accidents (PWR)
XI-1 Appendix I NONE DELETED XV-14 Inadvertent Operation of 07/01/81R 02/11/82C XI-2 Radiological (Effluent and NONE DELETED ECCS and Chemical and Process) Monitoring Systems Volume Control System (HRR B-67)
Malfunction that Increases Reactor Coolant Inventory XV-1 Decrease in Feedwater 07/01/81R 10/27/81C Temperature, Increase in Feedwater Flow, Increase XV-15 Inadvertent Opening of a 07/01/81R 03/31/82C in Steam Flow and PWR Pressurizer Safety-Inadvsrtent Opening of a Relief Valve of a BWR Steam Generator Relief Safety / Relief Valve or Safety Valve (3-18)
1 SAN ONOFRE 1
j
-p.)1 (Cont.)
SAR l/
SFR 2/
TOPIC HO. TITLE
. SCHEDULE SCHEDULE 1
V.V-16 Radiological Consequences 08/04/81R 11/18/81C 1
of Failure of Small Lines Carrying Primary Coolant Outside Containment t
XV-17 System Generator Tube NGNE 12/07/81C (SYS)
Failure (PWR) 4 3
XV-19 Loss-of-Coolant Accidents 07/01/81R 08/26/81C Resulting From Spectrum of Postulated Piping Breaks Within the Reactor Coolant Pressure Boundary 1/ SAR: Licensee Safety Analysis Report-Scheduled or Actual l
(Actual.(status 4b) when date is followod by R) 2/ SER = Staff Safety Evaluation Report -Scheduled or Actual (Actual (status 4a, 5, 7) when date is followed by C) 1/ Desiginated number of days from receipt of licensee SAR (Note: if Licenses SAR is received then date is from receipt of additional information requested) i.
t I
l 1
(3-19)
LICENSEE TOPIC SUBMITTALS SAN ONOFRE TOPICS 40 TARGET 35 --
ACTUAL 30 25 20 15
/,/
10 p
j l/l I
i i
l l
l l
l l
l g_
JUN JUL AUG SEP GCT NOV DEC JAN FEB MAR APR MAY JUN JUL/DEC TARGET 1
0 3
3 0
2 ACTUAL 0
2 0
1 4
1 1
0 0
2 3
0 0
TARGET 8
9 9
12 15 15 17 ACTUAL 0
2 2
3 7
8 9
9 9
11 14 14 14 G-20)
BIG ROCK POINT pk BIG ROCK POINT El (Cont.)
SAR 1/
SER 2/
SAR 1/
SER 2/
TOPIC H0. TITLE SCHEDULE SCHEDULE TOPIC H0. TITLE SCHEDULE SCHEDULE Ill-1 Classification of Struct-NONE 04/16/82C IX-3 Station Service and 12/10/81R 06/30/82C (SYS) ures, Components and Sys-Cooling Water Systems tems (Seismic and Quality)
III-2 Wind and Tornado Loading 02/01/82 08/30/82 III-5.A Effects of Pipe Break on 05/01/82 09/30/82 El Structures, Systems and SAR J/
SER 2/
Components Inside TOPIC HO. TITLE SCHEDULE SCHEDULE Containment II-3.A Hydrologic Description N0HE 09/10/82 III-5.B Pipe Break Outside 05/21/82R 09/10/82 Containment II-3.B Flooding Potential and NDHE 09/10/82 Protection Requirement-III-6 Seismic Design NONE 09/30/82 Considerations II-3.B.1 Capability of Operating HONE 09/10/82 Plans to Cope with Designs III-7.B Design Codes. Design HONE 05/30/82 Basis Floeding Conditions Criterion, Load Combinations and Reactor II-3.C Safety-Related Water Supply HONE 09/10/82 Cavity Design Criterion (Ultimate Heat Sink UHS))
VI-7.A.3 ECCS Actuation System NONE 01/29/82C II-4.8 Proximity of Capable NOME 09/30/82 Tectonic Structures in VI-7.C ECCS Single Failure Cri-NONE 08/05/81C Plant Vicinity terion and Requirements for Locking Out Power to Valves II-4.D Stability of Slopes 10/05/81R 06/25/82C Including Independence of Interlocks oa ECCS Valve II-4.F Settlement of Foundations 10/19/81R 07/07/82C and Buried Equipment VI-7.C.2 Failure Mode Analysis ECCS NDHE 08/05/81C III-3.A Effects of High Water 03/15/82 09/30/82 VI-10.A Testing of Reactor Trip 03/29/82R 06/22/82C Level on Structures System and Engineered Safety Features, Including III-3.C Inservice Inspection of 12/21/81R 09/01/82 Response Time Testing Water control Structures VII-1.A Isolation of Reactor NONE 02/16/82C III-4.B Turbine Missiles 06/09/82R 09/30/82 Protection System From Hon-Safety Systems, Including III-4.D Site Proximity Missiles 12/14/81R 07/12/82C Qualification of Isolation (Including Aircraft)
Devices III-7.D Containment Structural 12/29/81R 03/03/82C VII-2 Engineered Safety Features HONE 12/31/81C Integrity Tests (ESF) System Control Logic and Design V-1 Compliance with Codes and NONE DELETED Standards 110 CFR 50.S5a)
VII-6 Frequency Decay HONE 09/21/81C (MP A-01, A-14 )
V-4 Piping and Safe End Integ.,
NDHE 08/31/82 VI-1 Organic Materials and Post 03/16/82R 09/30/82 Accident Chemsitry (3-21)
BIG ROCK POINT pil pil (Cont.)
SAR 1/
SER g/
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC HO. TITLE SCHEDULE SCHEDULE II-2.C Atmospheric Transport and 04/06/82R 06/04/82C XV-1 Decrease in Feedwater 07/15/81R 02/18/82C Diffusion Characteristics Temperature Increase in for Accident Analysis Feedwater Flow, Increase in Steam Flow and III-4.A Tornado Missiles 03/16/82R 05/01/82 Inadvertent Opening of a Steam Generator Relief III-4.C Internally Generated 05/01/82 06/15/82 or Safety Valve Missiles XV-3 Loss of Exte.nal Load.
07/15/81R 10/16/81C III-8.A Loose Parts Monitoring and NCHE 02/09/82C Turbine Trip, Loss of Core Vibration Monitoring Condenser Vacuum, Closure (HRR B-60,C-12) of Main Steam Isolation Valve (BWR), and Steam IV-2 Reactivity Control System HONE 12/07/81C Pressure Regulator Failure Including Functional Design (Closed) and Protection Against Single Failures XV-4 Loss of Hon-Emergency A-C 07/15/81R 10/16/81C Power to Uso Station VI-2.D Mass and Energy Release for NONE 05/24/82C Auxiliaries Postulated Pipe Breaks Inside Containment XV-5 Loss of Normal Feedwater 07/15/81R 01/26/82C Flow VI-3 Containment Pressures and NOME 05/24/82C Heat Removal Capability XV-7 Reactor Coolant Pumps 07/15/81R 02/25/82C Rotor Seizure and Reactor VI-4 Containment Isolation Sys.
H0HE 03/24/82C Coolant Pump Shaft Break VI-6 Containment Leak Testing HONE 04/30/82 XV-8 Control Rod Misoperation 09/23/81R 12/21/81C (MP A-04)
(System Malfunction or Operator Error)
VI-7.B ESF Switchover from H0HE 04/22/82C Injection to Recirculation XV-9 Startup of an Inactive Loop 07/15/81R 03/24/82C Mode (Automatic EECS or Recirculation Loop at an Realignment)
Incorrect Temperature and Flow Controller Malfunction VIII-1.A Potential Equipment H0HE 07/08/82C Causing an Increase in BWR Failures Associated with Core Flow Rate Degraded Grid XV-11 Inadvertent Loading and 09/28/81R 11/20/81C IX-1 Fuel Storage H0HE 05/13/82C Operation of a Fuel Assembly in an Improper IX-6 Fire Protection (MP B-41)
H0HE 09/30/82 Position (BWR)
XI-1 Appendix I(MP A-02)
NOHE DELETED XV-13 Spectrum of Rod Drop SYS 07/01/81R 11/20/81C Accidents DOSES 07/01/81R 10/23/81C XI-2 Radiological (Effluent HONE DELETED and Process) Monitoring Systems (HRR B-67)
XV-14 Inadvertent Operation of 06/26/81R 08/18/81C ECCS and Chemical and Volume Control System Malfunction that Increases Reactor Coolant Inventory (3-22)
BIG ROCK POINT R11 (Cont.)
SAR 1/
SER R/
TOPIC NO. TITLE SCHEDULE SCHEDULE XV-15 Inadvertent Opening of a 3 6 / 2 6,'81 R 0 8 /18/ 81 C PWR Pressurizer Safety Relief Valve or a BWR Safety / Relief Valvo XV-16 Radiological Consequences 07/01/81R 12/14/81C of Failure of Small Lines Carrying Primary Coolant Outside Containment XV-18 Radiological Consequences 07/01/81R 04/02/82C of Main Steam Line Failure Outside Containment XV-19 Loss of Coolant Accidents 06/29/81R 08/18/81C (SYS)
Resulting From Spectrum of Postulated Piping Breaks (DOSES) within the Reactor Coolant 06/02/82R 07/01/82 Pressure Boundary XV-20 Radiological Consequences 07/03/81R 10/23/81C of Fuel Damaging Accidents (Inside and Outside Containment) 1/ SAR = Licensee Safety Analysis Report-Scheduled or Actual (Actual (Status 4b) when date is followed by R) 2/ SER = Staff Safety Evaluation Report -Scheduled or Actual (Actual (status 4a, 5, 7) when date is followed by C) 1/ Desiginated number of days from receipt of licensee SAR (Note:
if Licensee SAR is received then date is from receipt of additional information requested)
(3-23)
1 LICENSEE TOPIC SUBMITTALS BIG ROCK POINT TOPICS 40 TARGET 35 ACTUAL 30 25 20 15
/
f 10 f
5
~~
i l
l l
i l
i I
l l
g JUN JUL AUG SEP OCT NOV DEC JAN FEB MAR APR MAY JUN JUL/DEC 1
1 2
3 2
TARGET
~-
PER MONTH ACTUAL 0
0 2
2 0
3 1
0 2
1 2
3 0
TARGET 11 12 13 15 18 20 CUMULATIVE ACTUAL 0
2-2 3
7 8
9 9
9 11 13 16 16 2
G-24)
HADDAM NECK Ek HADDAM NECK EL (Cont.)
SAR J/
SER 2/
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC HO. TITLE SCHEDULE SCHEDULE III-1 Classification of NONE 07/22/82C IX-5 Ventilation Systems 12/14/81R 05/26/82C (SYS)
Structures, Components and Systems (Seismic and XIII-2 Safeguards / Industrial H0HE 06,10/82C Quality)
Security (MP A-10)
III-2 Wind and Tornado Loadings 12/14/81R 07/30/82 El III-5 A.
Effects of Pipe Break 03/12/82 08/31/82 SAR 1/
SER 2/
on Structures, Systems TOPIC HO. TITLE SCHEDULE SCHEDULE and Componets Inside Containment II-1.A Exclusion Area Authority 04/27/81R 03/29/82C B. Pipe Break Outside 10/02/81R 04/08/82C II-1.B Population Distribution 08/31/81R 03/29/82C Containment II-1.C Potential Hazards or 06/30/81R 03/29/82C III-6 Seismic Design H0HE 09/30/82 Changes in Potential Considerations Hazards Due to Transportation, III-7.B Design Codes, Design N0HE 07/30/82 Institutional Industrial, Criteria, Load and Military Facilities Combinations, and Reactor Cavity Design Criteria II-3.A Hydrologic Description 12/14/81R 08/31/82 VI-7.A.3 ECCS Actuation System NONE 01/29/82C II-3.B Flooding Potential and 12/14/81R 08/31/82 Protection Requirements VI-7.C.3 The Effect on PWR Loop N0HE 12/14/81C Isolation Valve Closure II-3.B.1 Capability of Operating 12/14/81R 08/31/82 During a LOCA on ECCS Plant to Cope with Design Performance Basis Flooding Conditions VI-10.A Testing of Reactor Trip NDHE 03/05/82C II-3.C Safety-related Water Supply 12/14/81R 10/01/82 System and Engineered (Ultimate Heat Sink (UHS))
Safety Features Including Response Time Testing II-4.B Proximity of Capable HDHE 05/18/82C Tectonic Structures in VII-1.A Isolation of Reactor NONE 02/16/82C Plant Vicinity Protection System from Hon-Safety Systems, Including II-4.D Stability of Slopes 08/31/81R 06/21/82C Qualifications of Isolation Devices II-4.F Settlement of Foundations 12/18/81R 05/18/82C VII-?
Engineered Safety Features NOHE 02/16/82C and Buried Equipment (ESF) System Control Logic and Design III-3.A Effects of High Water 08/31/81R 06/01/82 Level on Structures VII-6 Frequency Decay H0HE 08/28/81C III-3.B Structural and Other H0HE 08/31/82 VIII-4 Electrical Penetrations N0HE 12/23/81C Consequences (e.g. Flooding of Reactor Containment of Safety-Related Equipment in Basements) of Failure of IX-3 Station Service and Cooling 12/14/81R 04/30/82C Underdrain Systems
. Water Systems (3-25)
HADDAM NECK R1 (cont.)
Hil (Cont.)
SAR l/
SER 2/
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE Ill-3.C Inservice Inspections of 02/12/82R 06/03/82C VI-6 Containment Leak Testing HOME 05/07/82C Water Control Structures (MP A-04)
III-4.B Turbine Missiles (MP B-46)
H0HE 07/13/82C VI.7.B ESF Switchover from HONE 04/01/82C (SYS)
Injection to Recirculation III-4.D Site Proximity Missiles
' 06/25/81R 03/29/82C Mode (Automatic ECCS (Including Aircraft)
Realignment)
III-7.D Consainment Structural 04/27/81R 10/08/81C VIII-1.A Potential Equipment HOME 06/29/82C Integrity Tests Failures Associated with a Degraded Grid Voltage V-1 Compliance with Codes and H0HE DELETED (MP B-23)
Standards (10 CFR 50.55a)
(MP A-01,A-14)
IX-1 Fuel Storage 08/31/81R 12/30/81C VI-1 Organic Materials and Post 02/09/82R 06/04/82C IX-4 Baron Addition Systems 10/02/81R 03/31/82C Accident Chemistry IX-6 Fire Protection (MP B-41)
NONE 05/19/82C 251 XI-1 Appendix I(MP A-02)
HONE DELETED SAR 1/
SER 2/
TOPIC HO. TITLE SCHEDULE SCHEDULE XI-2 Radiological (Effluent HDHE DELETED and Process) Monitoring Ill-4.A Tornado Missiles 08 / 31/ 81 R 12/28/81C Systems (HRR B-67)
III-4.C Internaly Generating 02/12/82R 04/22/82C XV-1 Decrease in Feedwater 09/30/81R 06/01/82C Missiles Temperatures. Increase in Feedwater Flow, Increase in III-8.A Loose Parts Monitoring and NDHE 02/09/82C Steam Flow and Inadvertent Core Barrel Vibration Opening of a Steam Genera-Monitoring (HRR B-60.C-12) tor Relief or Safety Valve IV-2 Reactivity Control Systems 06/30/81R 12/23/81C XV-2 Spectrum of Steam System 09/30/81R 05/04/82C Including Functional Design Piping Failures Inside and and Protection Against Outside of Containment (SYS)
Single Failures (PWR)
(DOSES) 09/30/81R 06/28/82C V-7 Reactor Coolant Pump HONE 11/05/81C Overspeed(NRR B-68)
XV-3 Loss of External Load.
09/30/81R 03/09/82C Turbine Trip, Loss of VI-2.D Mass and Energy Release for HONE 06/21/82C Condenser vacuum, Closure Possible Pipe Break Inside of Main Steam Isolation Containment Valve (BWR), and Steam
~~
Pressure Regulator Failure VI-3 Containment Pressure and NDHE 06/21/82C (Closed)
Heat Removal Capability XV-4 Loss of Non-Emergency A-C 09/30/81R 12/17/81C VI-4 Containment Isolation NONE 04/06/82C Power to the Station System Auxiliaries XV-5 Loss of Normal Feedwater 09/30/81R 04/06/82C Flow (3-26)
HADDAM NECK R11 (Cont.)
Ell (Cont.)
SAR 1/
SER 2/
SAR 1/
SER Z/
TOPIC HO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE XV-6 Feedwater System Pipe 09/30/81R 04/28/82C XV-19 Loss-of-Coolant Accidents 09/30/81R 11/10 / 81 C Breaks Inside and Outside Resulting from Spectrum of Containment (PWR)
Postulated Piping Breaks Within the Reactor Coolant XV-7 Reactor Coolant Pump Rotor 09/30/81R 05/12/82C Pressure Boundary (SYS)
Seizure and Reactor Coolant (DOSES) 09/30/81R 06/30/82C Pump Shaft Break XV-8 Control Rod Misoperation 09/30/81R 03/18/82C J/ SAR = Licensee Safety Analysis Report-Scheduled or Actual (System Malfunction or (Actual (Status 4b) when date is followed by R)
Operator Error) 2/ SER = Staff Safety Evaluation Report -Scheduled or Actual XV-9 Startup or an Inactive 09/30/81R 03/31/82C (Actual (status 4a, 5, 7) when date is followed by Cl Loop or Recirculation Loop at an Incorrect 1/ Desiginated nuinber of days from receipt of licermae SAR Temperature, and Flow (Note: if Licensee SAR is received then date is from Controller Malfunction receipt of additional information requested)
Causing an Increase in BWR Core Flow Rate XV-10 Chemical and Volume Control OS/30/81R 03/29/82C System Malfunction that Results in a Decrease in in Baron Concentration in the Reactor Coolant (PWR)
XV-12 Spectrum of Rod Ejection 09/30/81R 03/15/82C Accidonts (PWR)
(SYS)
(DOSES) 09/30/81R 05/06/82C XV-14 Inadvertent Operation of 09/30/81R 04/01/82C ECCS and Chemical and Volume Control System Malfunction that Increases Reactor Coolant Inventory XV-15 Inadvertent Opening of a 09/30/81R 04/06/82C PWR Pressurizer Safety-Relief Valve or a BWR Safety / Relief Valve XV-16 Radiological Consequences HONE 09/28/81C of Failure of Small Lines carrying Primary Coolant Outside Containment XV-17 Steam Generator (SYS) 04/07/82R 06/21/82C Tube Failure (PWR) (DOSES) 04/07/82R 06/28/82C i
i I
(3-27)
LICENSEE TOPIC SUBMITTALS HADDAM NECK TOPICS 4g TARGET 35 ACTUAL 30
/
25 20
/
l 15
/
10 -
/
l/
l I
l l
I l
i I
i g
JUN JUL AUG SEP GCT NOV DEC JAN FEB MAR APR MAY JUN JUL/DEC TARGET 1
1 PER MONTH ACTUAL 0
6 0
16 0
8 0
2 0
1 0
0 0
TARGET 32 33 34 CUMULATIVE ACTUAL 0
6 6
22 22 30 30 32 32 33 33 33 33 G-28)
L
(
YANKEE RL YANKEE NUCLEAR PCWER STATION EL (Cont.)
SAR 1/
SER 2/
TOPIC HO. TITLE SCHEDULE SCHEDULE TOPIC HO. TITLE SCHEDULE SCHEDULE III-1 Classification of Struct-NONE 06/18/82C IX-5 Ventilation Systems 11/18/81R 04/28/82C ures, Components and Sys-tems (Seismic and Quality) 21 SAR 1/
SER 2/
l III-2 Wind and Tornado Loadings 03/18/82R 07/30/82 TOPIC NO. TITLE SCHEDULE SCHEDULE III-5.A Effects of Pipe Break on 03/18/82R 07/26/82C Structures, Systems and II-1.A Exclusion Area Authority 03/18/82R 06/15/82C and Control Components Inside Containment II-1.B Population Distribution 05/01/81R 06/15/82C III-5.B Pipe Break Outside 01/21/82R 05/06/82C II-1.C Potential Hazards or 04/09/81R 06/15/82C Containment Changes in Potential III-6 Seismic Design NONE 08/31/82 Hazards Due to Transportation, Considerations Institutional Industrial, III-7.B Design Codes, Design NONE 06/30/82 and Military Facilities l
l Criteria, Load Combinations, and Reactor II-3.C Safety-related Water HOME 08/31/82 Supply (Ultimate Heat Sink Cavity Design Criteria (UHS)
V-11.P RHR Interlock Requirements NONE Of/22/82C II-4.B Proximity of Capable N0HE 06/16/82C (ELEC)
Tectonic Structures in VI-7.A.3 ECCS Actuation System 06/30/81R 01/29/82C Plant Vicinity (B-46)
VI-10.A Testing of Reactor Trip 06/30/81R 01/22/82C II-4.D Stabil.ty of Slopes 02/26/82R 08/31/82 System and Engineered II-4.E Dam Inteo-ity H0HE 08/31/82 Safety Features Including Safety Features Including II-4.F Settlement of Foundations 08/31/81R 08/31/82 Response Time Testing and Buried Equipment VII-1.A Isoaltion of Reactor HONE 10/05/81C Protection System from III-3.A Effects of High Water 03/18/82R 08/31/82 Level on Structures Non-Safety Systems, Including Qualifications III-3.C Inservice Inspection of 01/04/82R 08/31/82 of Isolation Devices Wacer Control Structures VII-2 Engineered Safety Features H0HE 10/19/81C III-4.B Turbine Missiles (MP B-46)
HONE 02/08/82C (ESF) System Control Logic and Design III-4.D Site proximity missiles 06/30/81R 06/15/82C VII-5 System Required for Safe H0HE 01/22/82C (Including Aircraft)
IIi-7.D Containment Structural 11/18/81R 03/01/82C (ELEC)
Shutdown VII-6 Frequency Decay NONE 08/28/81C Integrity Tests V-1 Compliance with Codes N0HE DELETED IX-3 Station Service and Cooling 09/17/81R 05/30/82C and Standards (10 CFR 50.55a)(MP A-01,A-14)
Water Systems (3-29)
I t-4 YANKEE 21 (Cont.)
R11 (Cont.)
J SAR 1/
SER 2/
SAR 1/
SER Z/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC HO. TITLE SCHEDULE SCHEDULE VI-1 Organic Materials and 06/14/82R R+14 IX-1 Fuel Storage ll/18/81R 05/01/82 Post Accident chemistry IX-4 Boron Addition System 08/31/81R 05/14/82C All IX-6 Fire Protection (MP B-41)
NONE 08/31/82 i
SAR 1/
SER 2/
TOPIC N0 TITLE SCHEDULE SCHEDULE XI-1 Appendix I(MP A-02)
NONE DELETED.
II-2.C Atmospheric Transport and 06/30/81R 09/04/81C XI-2 Radiological (Effluent NONE DELETED i
Diffusion Characteristics and Process) Monitoring for Accident Analysis Systems (NRR B-67)
III-4.A Tornado Missiles 0 3/18/82P.
06/30/82C XV-1 Decrease in Feedwater 02/01/82R 06/22/82C
~
Temperature, Increase in III-4.C Internally Generated 03/18/82R 05/15/82 Feedwater Flow, Increase Missiles in Steam Flow and Inadvertent Opening of a III-8.A Loose Parts Monitoring NOME 12/07/81C Steam Generator Relief and Core Barrel Vibration or Safety Valve Monitoring (NRR 8-60 C-12)
XV-2 Spectrum of
- team System 06/30/81R 06/21/82C l
IV-2 Reactivity Control Systems 09/17/81R 12/23/81C (SYS)
Piping Failures Inside Including Functional Design (DOSES) and Outside of Containment No date 05/15/82 i
and Protection Against (PWR) i Single Failures l
XV-3 Loss of External Load, 06/30/81R 01/09/82C i
V-7 Reactor Coolant Pump NOME DELETED Turbine Trip, Loss of Overspeed(NRR B-68)
Condenser Vacuum, Closure i
j of Main Steam Isolation VI-2.D Mass and Energy Release NOME 05/10/82C Valve (BWR), and Steam for Possible Pipe Break Pressure Regulator Failure Inside Containment (Closed)
VI-3 Containment Pressure and NOME 05/10/82C XV-4 Loss of Non-Emergency A-C 01/04/82R 06/30/82C l
Naat Removal Capability Power to the Station l
VI-4 Containment Isolation NDME 04/01/82 l
(SYS)
System XV-5 Loss of Normal Feedwater 06/30/81R 01/29/82C Flow VI-6 Containment Leak Testing NONE 06/01/82 (MP A-04)
XV-6 Feedwater System Pipe 02/01/82R 06/30/82C Breaks inside and Outside i
VI-7.5 ESF.Switchover from NONE 06/29/82C Containment (PWR) i
($YS)
Injection'to Recirculation Mode (Automatic ECCS XV-7 Reactor Coolant Pump Rotor 06/30/81R 05/20/82C Realignment)
Seizure and Reactor Coolant Pump Shaft Break VIII-1.A Potential Equipment NONE 08/01/82 Failures Associated with XV-8 Control Rod Misoperation 01/04/82R 02/26/82C a Degraded Grid Voltage (System Malfunction or (MP B-23)
Oper,ator Error)
(3-30)
- \\
4 YANKEE 251 (Cont.)
SAR 1/
SER 2/
TOPIC HO. TITLE SCHEDULE SCHEDULE XV-9 Startup or an Inactive 06/30/81R 06/13/82C Loop or Recirculation Loop at an Incorrect Temperature, anu Flow Controller Malfunction Causing an Increase in BWR Core Flow Rate XV-10 Chemical and Volume Control 06/30/81R 03/02/82C System Malfunction that Results in a Decrease in the Boron Concentration in the Reactor Coolant (PWR)
XV-12 Spectrum of Rod Ejection 06/30/81R 03/29/82C (SYS)
Accidents (PWR)
(DOSES) 08/30/81R 12/18/81C XV-14 Inadvertent Operation of 06/30/81R 06/30/82C i
ECCS and Chemical and Volume Control System Malfunction that Increases Reactor Coolant Inventory XV-15 Inadvertent Opening of a 06/30/81R 04/28/82C PWR Pressurizer Safety-Related Valve or a BWR Savety/ Relief Valve XV-16 Radiological Consequences 02/01/82R 07/28/82C of Failure of Small Lines Carrying Primary Coolant Outside Containment XV-17 Steam Generator Tube H0HE 07/06/82C (SYS)
Failure (PWR)
(DOSES) 02/01/82R 03/19/82C l
XV-19 Loss or-Coolant Accidents 11/18/81R 06/24/82C l
(SYS)
Resulting from Spectrum of l
(DOSES)
Postulated Piping Breaks 01/04/82R 04/15/82 Within the Reactor Coolant Pressure Boundary 1/ SAR = Licensee Safety Analysis Report-Scheduled or Actual (Actual (Status 4b) when date is followed by R)
Z/ SER = Staff Safety Evaluation Report -Scheduled or Actual (Actual (status 4a, 5, 7) when date is followed by C)
~C 1/ Desiginated number of days from receipt of licensee SAR (Hote:
if Licensee SAR is received then date is from receipt of additional information requested)
(3-31)
LICENSEE TOPIC SUBMITTALS YANKEE TOPICS 4g TARGET 35 ACTUAL 30 25
/
20 ALLSUBMITTALfRECE ED 15 10 5
I I
I I
I I
I I
I I
I 0
JUN JUL AUG SEP OCT NOV DEC JAN FEB MAR APR MAY JUN JUL/DEC TARGET 5
PER MONTH ACTUAL 0
2 2
0 4
0 5
5 6
0 0
1 TARGET 20 25 CUMULATIVE ACTUAL 0
2 4
4 8
8 13 18 24 24 24 25 G-32)
[\\
LACROSSE EL LACROSSE l R1 SAR 1/
SER 2/
SAR 1/
SER 2/
TOPIC HO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE 111-1 Classification of NONE 06/07/82C II-1.A EXCLUSION AREA AUTHORITYy 06/22/81R 07/31/82 (SYS)
Structures, Components and and Control Systems (Seismic and Quality)
II-1.B Population Distribution 06/16/81R 07/29/82C III-2 Wind and Tornado Loadings 08/06/81R 08/30/82 II-1.C Potential Hazards or 07/15/81R 07/31/82 Changes in Potential III-5.A Effects of Pipe Break on 02/24/82R 08/06/82 Harards Due to l
I Structures, Systems and Transportation, Components Inside Institutional Industrial, Containment and Military Facilities III-5.8 Pipe Break Outside 06/29/81R 07/26/82C II-3.A Hydrolic Description 06/16/81R 49/30/82 Containment II-3.8 Flooding Potential and D5/12/82R 09/30/82 III-6 Seismic Design H0HE 09/15/82 Protection Requirements Considerations II-3.B.1 Capability of Operating 05/12/82R 09/30/82 III-7.B Design Codes, Design NONE 07/23/82C Plant to Cope with Design Criteria, Load Basis Flooding Conditions Combinations, and Reactor Cavity Design Criteria II-3.C Safety-related Water Supply 06/26/81R 09/30/82 (Ultimate Heat Sink (UHS))
V-11.B RHR Interlock Requirements H0HE 03/04/82C (ELEC)
II-4.8 Proximity of Capable NONE 07/13/82C Tectonic Structures in VI-7.A.3 ECCS Actuation System H0HE 01/29/82C Plant Vicinity VI-10.A Testing of Reactor Trip 06/25/81R 02/16/82C II-4.D Stability of Slopes NDHE 08/01/82 System and Engineered Safety Features Including II-4.E Dam Integrity NONE 07/27/82C Response Time Testing II-4.F Settlement of Foundations 03/09/82R 07/20/82C VII-1.A Isolation of Reactor H0HE 03/09/82C and Buried Equipment Protection System from l
Hon-Safety Systems, III-3.A Effects of High Water Level 05/12/82R 09/30/82 Including Qualifications of on Structures Isolation Devices III-3.C Inservice Inspection of 01/29/82R 09/30/82 VII-2 Engineered Safety Features H0HE 03/11/82C Water Control Structures l
(ESF) System Control Logic and Design III-4.B Turbine Missiles 03/05/82R 09/30/82 l
VII-3 Systems Required for Safe NONE 03/09/82C III-4.D Site Proximity Missiles 09/15/81R 07/29/82C (ELEC)
Shutdown (Including Aircrafts)
VII-6 Frequency Decay NOME 09/21/81C III-7.D Containment Structural 06/29/81R 03/30/82C Integrity Tests IX-3 Station Service and Cooling 03/05/82R 06/30/82C Water Systems V-1 Compliance with Codes and NOME DELETED Standards (to CFR 50.55a)
IX-5 Ventilation Systems 03/09/82R 07/23/82C (MP A-01.A-14)
(3-33)
LACROSSE 21 (Cont.)
R11 (Cont.)
SAR 1/
SER g/
SAR 1/
SER g/
TOPIC HO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE VI-1 Organic Materials and Post 02/19/82R 09/30/82 XI-2 Radiological (Effluent and NONE DELETED Accident Chemistry Process) Monitoring Systems (NRR B-67) 211 XV-1 Decrease in Feedwater 03/05/82R 07/15/82 SAR 1/
SER 2/
Temperature, Increase in TOPIC NO. TITLE SCHEDULE SCHEDULE Feedwater Flow, Increase in Steam Generator Relief II-2.C Atmospheric Transport and 01/05/82R 07/15/82 or Safety Valve Diffusion Characteristics for Accident Analysis XV-3 Loss of External Load, 06/26/81R 11/03/81C Turbine Trip, Loss of Con-III-4.A Tornado Missiles 04/02/82 05/30/82 denser Vacuum, Closure of Main Steam Isolation Valve III-4.C Internally Generated 03/05/82R 06/29/82C (BWR), and Stam pressure Missiles Regulator Failure (Closed)
III-8.A Loose Parts Monitoring and NONE 02/09/82C
, 06/26/81R 10/21/81C Core Barrel Vibration XV-4 Loss of Non-Emergency A-C Monitoring (NRR B-60,C-12)
Power to the Station Auxillaries IV-2 Reactivity Control Systems NONE 12/10/81C Including Functional Design XV-5 Loss of Normal Feedwater 03/05/82R 07/15/82 and Protection Against Flow Single Failures XV-7 Reactor Coolant Pump Rotor 03/11/82R 07/19/82C VI-2.D Mass and Energy Release for NONE 05/28/82C Seizure and Reactor Coolant Possible Pipe Break Inside Pump Shaft Break Containments XV-8 Control Rod Misoperation 02/26/82R 03/25/82C VI-3 containment Pressure and NONE 05/28/82C (System Malfunction or Heat Removal Capability Operation Error)
VI-4 Containment Isolation NONE 06/30/82C XV-9 Startup or an Inactive Loop 08/25/81R 06/01/82 (SYS)
System or Recirculation Loop at an Incorrect Temperature, and VI-6 Containment Leak Testing NONE 03/31/82 Flow Controller Malfunction (MP A-04)
Causing an Increase in BWR Core Flow Rate VIII-1.A PDTENTIAL EQUIPMENT NONE 02/28/82 Failures Associated with a XV-11 Inadvertment Loading and 02/26/82R 03/26/82C Degraded Grid Voltage Operation of a Fuel (MP B-23)
Assembly in an Improper Position IX-1 Fuel Storage 02/26/82R 05/01/82 XV-13 Spectrum of Rod Drop 02/26/82R 03/25/82C IX-6 Fire Protection (MP B-41)
NONE 09/30/82 (SYS)
Accidents (BWR)
(DOSES) 02/26/82R 06/30/82C XI-1 Appendix I(MP A-02)
NONE DELETED (3-34)
O
LACROSSE Ri1 (Cont.)
SAR 1/
SER Z/
TOPIC NO. TITLE SCHEDULE SCHEDULE XV-14 Inadvertent Operation of 08/25/81R 07/16/82C ECCS and Chemical and Volume Control System Malfunction that Increases Reactor Coolant Inventory XV-15 Inadvertent Opening of a 06/30/81R 09/21/81C PWR Pressuring Safety-Relief Valve or a BWR Safety / Relief Valve XV-16 Radiological Consequences 03/09/82R 05/01/82 of Failure of Small Lines Carrying Primary Coolant Outside Containment XV-18 Radiological Consequences 05/28/82R 06/23/82C of Main Steam Line Failure Outside Containment (BWR)
XV-19 Loss of-Coolant Accidents 05/28/82R 07/15/82C (SYS)
Resulting from Spectrum of (DOSES)
Postulated Piping Breaks 05/28/82R 05/01/82 Within the Reactor Coolant Pressure Boundary XV-20 Radiological Consequences 03/12/82R 05/01/82 of Fuel Damaging Accidents (Inside and Outside Containment) 1/ SAR = Licensee Safety Analysis Report-Scheduled or Actual (Actual (Status 4b) when date is followed by R)
Z/ SER = Staff Safety Evaluation Report -Scheduled or Actual (Actual (status 4a, 5, 7) when date is followed by C) 1/ Desiginated number of days from receipt of licensee SAR (Note if Licensee SAR is received then date is from receipt of additional information requested)
(3-35)
LICENSEE TOPIC SUBMITTALS LACROSSE TOPICS 40 TARGET 35 ACTUAL 30 25
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20 15 10
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JUN JUL AUG SEP OCT NOV DEC JAN FEB MAR APR MAY JUN JUL/DEC TARGET 5
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3 1
0 0
0 0
5 10 2
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0 20 25 27 28-29 TARGET CUMULATIVE ACTUAL 1
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C POMM M U.S. NUCLEAR REGULATORY COMMISSION NUREG-0485 Vol. 4, No. 7 BIBLIOGRAPHIC DATA SHEET L TITLE ANo SUBTITLE LAdd volume No.,if apprenan)
- 2. (Leave b/mkl Systematic Evaluation Pr 3 ram Status Summary Report
- 3. RECIPIENT S ACCESSION NO.
- 7. AUTHOR (S)
- 5. DATE REPORT COMPLE TED M ON TH lvEAR August 1982
- 9. PERFORMING ORGANIZATION NAME AND MAILING ADDRESS (/nclude I,p Code /
DATE REPORT ISSUED MOurs lvEma Office of Resource Management August 1982 Office of Nuclear Reactor Regulation
- 6. (tes e bien */
U.S. Nuclear Regulatory Commission Washington, D.C.
20555
- 8. (Leave blank) 12, SPONSORING ORGANIZATION N AME AND MAILING ADDRESS (include 2,p Codel p
Office of Resource Management Offic.e of Nuclear Reactor Regulation ii. CONTR ACT NO.
U.S. Nuclear Regulatory Commission Washington, D.C.
20555
- 13. TYPE OF REPORT PE RIOD COVE RE D (Inclusive dares)
July 1 - 31, 1982
- 15. SUPPLEMENTARY NOTES
- 14. (Leave O/mkl
- 16. ABSTR ACT 000 words'or less!
The Systematic Evaluation Program is intended to examine many safety-related aspects of 11 of the older light water reactors. This document provides the existing status of the review process including individual topic and overall completion status.
- 17. KE Y WORDS AND DOCUMENT AN ALYSl$
17a DESCRIPTORS I
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17b. IDENTIFIE RS/OPEN-ENDE D TE RMS 21 NO OF PAGES 19 SE CURITY Cf ASS (Th,s reporr/
- 18. AVAILABILITY ST ATEMENT Unclassi ied Unlimited
- 22. PRsCE g '
Sjih,spagel 20 c C NRC FOR%4 339 47 77)
UNITED STATES riast class unit NUCLEAR REGULATORY COMMISSION
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