ML20053E754
| ML20053E754 | |
| Person / Time | |
|---|---|
| Issue date: | 05/31/1982 |
| From: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| To: | |
| References | |
| NUREG-0485, NUREG-0485-V04-N04, NUREG-485, NUREG-485-V4-N4, NUDOCS 8206100013 | |
| Download: ML20053E754 (97) | |
Text
. _. _
' sen 5;!
' "jj Vol. 4, No. 4 l
April 30,1982 a
i E i SYSTEMATIC EVALUATION PROGRAM i
j l
STATUS
SUMMARY
REPORT l
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UNITED STATES NUCLEAR REGULATORY COMMISSION
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1 Available from i
i NRC/GPO Sales Prograrn a
Superintendent of Documents Government Printing Office Washington, D. C. 20402 A year's subscription consists of 12 issues for this publication.
Single copies of this publication l 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 1
5 A - - - -
NUREG-0485 Vol. 4, No. 4 April 30,1982 SYSTEMATIC EVALUATION PROGRAM STATUS
SUMMARY
REPORT l
Prepared for: 0FFICE OF NUCLEAR REACTOR REGULATION Prepared By: 0FFICE OF RESOURCE MANAGEMENT l
i UNITED STATES NUCLEAR REGULATORY COMMISSION i
pm aucuq
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p William T. Russell, Chief Dennis M. Crutchfield, Chief Systematic Evaluation Program Branch Operating Reactors Branch 5 ufearR f
f u ear Reactor Regulation Off e f tor Regulation J
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1 Projected dates for. topic completion have been revised to reflect latest licensee commitments and new review division schedules as provided by February 22, 1982 memorandum from R. Mattson to D. Eisenhut and March 25, 1982 memorandum from R. Vollmer to D. Eisenhut.
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l TABLE OF CONTENTS i
SECTION I SECTION 11 SECT!0N 111 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 i
DESIGN BASIS EVENT 14 DRESDEN 2 2-7 to 2-10 DRESDEN 2 13 6 to 3-9 l
GROUP DESCRIPTION GINNA 2-11 to 2-14 OYSTER CREEK
.310 to 3-17 DEFINITIONS OF STATUS 1-5 HADDAM NECK 2-15 to 2-18 MILLSTONE 1 3-13 :t,.3-16 l
LACROSSE 2-19 to 2-22 SAN ONOFRE' 3-17 to 3-20 SEP TOPIC
SUMMARY
1-6 MILLSTONE 1 2-23 to 2-2G '
BIG ROCK POINT 3-21 to 3-24 j
STATUS REPORT OYSTER CREEK 2-27 to 2-30 HADDAM NECK 3-25 to 3-28 PALISADES 2-31 to 2-34 i
PROGRESS TOWARD 17 YANKEC 3-29 to 3-32 i
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 l
SAFETY ASSESSMENT SCHEDULE SEP TOPIC STATUS BY 1-9 REVIEW DIVISION I
(Summary Table)
SEP TOPIC STATUS BY 1-10 to 1-11 REVIEW DIVISION (Graphs) i SEP TOPIC SUBMITTALS 1-12 thru 1-13 BY LICENSEES (Graphs) i i
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SYSTEMATIC EVALUATION PROGRAM TOPIC LIST I
i topic #
Ylftt IOPIC 8 IlIL I.
YoG M e f ili t li-2 areactivity Control Systesa locluding f uncttonal 1:-)
A. I sc ivuon area Authority and ( et rol 1[g*4 A. Torna 10 Mis si les Design and Protection Against Stagle f ailures it. P os.ui et ion D ist r't= t i on 38-3 Bd Jet Puss,s operettag Indications
. Pot ential hazards or than jrs in Petential
- 8. Turt. ne misstles v.)
Compliance with Codes and Standards (10 Cra parach Ne t a f ranwortat ica, l ast it ut iona l 50.55a )
I ndu s t r ' e l. and Milit a y t ac ilit ies
((g-4 C. Interr.aily Generat ed #issiles 1-2 App 11 cable Code Cases f
11-?
5evere weather Phenoie na V-3 Overpressurtsation Protection
- 8. Ursite m t eorological *easu ewnts Progras e
r 8*4 Piping and saf e End Integrity C. Atmowheric t ransport an1 Dif f usion Charac-teristics f or Accident Analysis D. 5tte Prosimity misstleg ([ncluding Aircraf t)
V.S seactor Coolant Pressure soundary (aCPs)
"D.
Avatlabtitty of Meteorological Data in the Ill.S A. Ef f ects of P tpe Breat on Structums. Systees teat age. Detection Control Woom and Cotonents inside Containent g
!! 3
. HydrologtC Description
- 3. Pipe Breat Outside Coctainment W4 Steam Generator (SG) Integetty S. F looding Potent 141 and Protect 60n Require-V-g Reactor Core Isolation Cooling $ystem (Od) ill-?
A. Inserence Inspection, including Prestressed 1
Capaut tity of Operating Plant to Cove Concrete Contain=nts with L ither Grouted nita Design Basis f looding ConditiuM or Ungrouted Tendons
- 8. RMR Reliabtitty
{
C. Saf ety-related Water Supply (Ultimate Heat
- 6. Design Codes. Cesign Criteria. Load i s ra (t;M51)
Comeinations. and Reactor Cavity Deste gy g
g Pnssum Systems 11 4
.c o l o gy and 5elseology I
C. Delamination of Prestressed Concrete Con-0*
I I"I' 9" ' "**I I P. Tectonic Province tainre nt 5tructures 1
V-12 A. Water Purity of Soiltag Water Reactor 1
P. Prostetty of Capable Tectonic 5trustures
- 12. Contain=nt Structural Integrity Tests Primary Coolant l
in Pl nt vicinity 111-6 A. Leose Parts Monitoring and Core Barrel V-13 Water Masser C. mter nal 5eismuit y sit e *
- M Miles o' vibrat ton Monitoring l
Plant VI-l Organtc Matertals and Post Acctdent B. Control Rod Drive mechantsa Integrity Chemistry I
5t ab-lity of S lui es C. Irradiation Damage. Use of Senstttred
{
VI-2
, A. Pressure-$vppression Type Bd Containments 4
Stainless Steel and Iattgue a es t st anc e i
- 5. Subcoavartment Analysts t. Dam Inteur sty
, D. Core suponets anit f uel Integrity C. Ice Condenser Containment F. Sett leent of Ioundat cons and Buried 111-9 Support Integrity L qu ip e.e t D. Mass and Energy Release f or Possible Pipe 111-10 A. Thera I-Overload Protect son f or Motors of B reak lasede Containner t a
111-1
( losif not son of 5t rutturn. Cw4 onents sad Motor-operated v.1ves s, tem Deismic and %elity)
- 8. Puae f lywheel Int egrity VI-3 Contatanent Pressure and Heat Reseval Capabt i t ty Ill-/
.ind aad f ornado t uadings C. wrveillance Requircents o-Ed Rectrcula-t vor Pu ts and Dischar9e valves 11-4 Cont.insent Isolation System n
111-3 A. I f f c(ts of H et m t er Level va 5tructures 111-11' C og onent I nt e grit y VI-5 Coseustible Gas Control 14 Structural and other Consequen(es (e.g.
Ul4 Contatement Leak Testing 5 looding of Saf ety-6*lat ed 19u i.e nt in a
!!!-Il invironwatal yualtf icatinn of Saf ety Related c
llee at s) of f ailuee of de.orrerae n 5,oc%
I quipment i. Inservice lewection of Wat er Cont rol 5truc.
IV-1
- 4. Operation with Le's Then All Loops In-Service tures M
SYSTEMATIC EVALUATION PROGRAM TOPIC LIST l
I 70Plc #
TIYtf 2Lg TrPIC a flui
'* IC 8 V I. 7. A I.1CC5 Be-evelvet son t o Account for I Mrea sed Vgg.g Instruments f or metter$ng Radiatton and Process IV.5 Loss of Normal f eeenater Flom Vessel head f est erat u e V artstles During Actioents r
IWW W MW inject son y t t4 Frequency Decay ContainW M
- 2. Upper Plenus
- 3. E CC5 Act uet ton System
- t i l-I Acceptability of $ sing Bo Cesign on 94-4 IV.?
Reactor Coolant Pwg Rotor 5eigure and Plants Reactor Coolant Pug Shaf t 8eese
- 4. Core Spray hoJyle [ t f ectiveness V!ll=1 A. Potent tal t quipnent f ailern Associated with gy.8 Control Rod Mtsoperation (Systee Malfunction V I-1.5 E 5F Switchceer f rom injection to Recirculat ton a Degraded Grid Voltage or Operator E rfor)
Mode ( Automet tc L Cf.5 6ea lignme nt)
VIII.2 Onstte t errgency Power system - Diesel av.g 5tartup ce an inacttee Loop or Rectrculation V I-1.C i CC5 5 t agl e f a i b re C r i t eri on a nd s qu t re-Generat or toop at an incorrect Testerature, and flos e
ment s f or t oca ing out hwer to V*tves Controller palfunction Causing an Increase to including Inoependen(e of lcterlock s on Vlli-3 A. $t at ion ttery CardCity Test Requirements B A Core f low Rate IV-Deetcal and Volume Control Systes malfunctten
- 8. DC Paner System So Voltage monitcrtng and that Results in a Occrease in tne Soron Concen-
- 1. Appendi a s - [ tect rical Instru1ernt at ion Annu nciat ion tratton in the Reactor Coolant (Pd) l and Cuatrol (t!C) Re-reuteus VIII.4 (lectrical Penetrations of Reactor Contauvent IV-ll inadvertent Loading and Operetton of a Fuel i
- 2. Failure Mode Analysis - ICC5 Assenety in an !sproper Position i
11-1 f uel Storage
- 3. Tne lif ect of I'd t one Isolat tun Valve a v.12 5pectrum of Rod Ejection Accidents (Pd)
Closure During a Lot A on itC5 l'erf ormeace 11-2 Overhead Mandiing Systesis - Cranes V I. 7.D Long Term Cool t ag - Pantee I allures (e.g..
s v.13 Spectn,e of Rod Drop Accidents ($d!
Ilooding of Pc1undant Logonents) 13-3 Statt an Service and Cooling Water Systems X V-14 Inadvertent Operetton of ECCS and Ches1 Cal V I - 7.1 iCCS sus Design and Test f or Recirculat ton II.4 Boron Addition System and Volume Control Systee malfunction that 11 5 Ventilat non System V !- 1.f Accunnalator Isolat son Valves Power and Control IV-15 Inadvertent Opening of a Pd Pressertaer 5afety-
System Design
IX4 fire Protection Rettef Valve or a Bd Safety /Reitef Valve V1 8 Control Room Habitability 1
Aunillary f ee&ater System IV.16 Radiological Consequences of Failure of Small Lines Carrying Pr<eiery Coolant Outs 6de Contats-VI g Main 5 team t one Isolet son Seal System - Bd Ild D#' I "e nt VI-lu A. Testing of Reactor T rip System and E ngineered 13-2 Radiological (t f fluent and Process) Monitoring g y.j y 5 team Generatoe Saf ety f eatures Including Response T iaa' s y st em Tube f attere (par)
T es t ing At t i-1 (nnduct of Operat ians IV-18 Radiological Consequences of main Steam B. Shared ingineered Safety f eatures. On-site Line f at ture Outside Contatament (02)
[mergency Power. and Service system f or 3ll[.2 Saf etards/inMt rial Security Multiple Unit i act let tes IV-19 Loss-of-Coolant Accidents Resulting f rom IV-1 Decrease in f ee<ssat er legerature, lacrease in Spectrue of Postulated Piptag Breams Within Vll.)
A. (solation of Reactor Protection System f rom p ee<smat er 7 Inu, lacrease in 5tese Flow and the Reactor Coolant Pressure Soundary fion.54f ety Systems. Including Qualif uat tons inadvert ent s>pening of a $ team Generator Weltef of Isolation Devues or Saf ety Valve IV.20 Radiological Consequences of feel Damaging Accidents (Inside and Outside Contatament)
- 8. Trip Uncertainty and Setpoint Analysts Review u v.2
- oectrum of Steae System Piping I ativ es Insta' r
IV41 5 pent f uel task Drop Accidents of Operating Data Base end Outside of Coctainnent (Pd)
Vll-2 I nqineered Saf ety f eatures (155 ) System Control sv.3 ton of E sternal Load. Turtune la np. L ou uf L ogic and Design Condenser vacuum C lowre of Main 5tese isota-IV-23 Multiple Tube Failures in Steae Generators t son valve (BA). and Steae Pressure Reapalator VII-1
',y st em R equ ired f or Saf e Shut diaen s ailu e (Closed)
,,,7,e toss of All A-C Power r
f# 3 '**""*"d*"9"Y"-CP"""'5'***
IV!
Techattal Specificattoas vit.4 itoccts of f ailure in non-Saf ety Relate mtem on Selected t nyincered saf et y Ie.
s IVll Operattonal QA Program
- Topic deleted from SEP program due to duplication by Three Mile island (TMil NRC Action Plan, Unresolved Safety issue or other SEP Topic per May 7,1981 letter from G. Lasnas to a 1-3
DESIGN BAS S EVENT REV EWS s
THIS SECTION DEF!NES DESIGN BASIS EVENT (DBE) REVIEWS FOR THE ELEVEN SEP FACILITIES s=_e,4. o e paE TCe:C LI5?
O > ? L5j;_Lj51 fee MEyj:.!5?
v i, w r e f er.veet Groun Ac 'deat. ed t ransP_t_6eown M f 0'11 IEhl ML M M DM A,
,5 TIT E-Grow I sd 1 Decrease in f eed ater temperatu e rim L
r 6ew I s -l Decrease in feed ater t arperature 19=L Iu-1 lacrease in feedwater fl o.
tm Il-s A nyaMoqic aescription (Phi IW 1 Im rease in feesater flw Iv-1 lacrease in stese flaw 11 - }. 3 f toediag actenttel and prote(tion regareren s (capab11 tty of operattag 86-1 Imrease in stear f l om tv-9 Start o cf inactive loop and flo=
s so-1 Inesserteet os,ecing of steam coatroller self.nction plant to cope with cesign basis flooding gee.erator relief safety salve so-3 Inadvertent closure of main stese condi t ion )
/
Red Start uc o* inactive tocc isolatton valve I -) c saf ety related mater sussi, bitteste t i - 10 Syster ralf.actioe caastni; heat sinn )
Gro4~! !
s.- 3 Loss of enternal loss
^-
33 3 fo cine trip I s-3 Loss of condensee vac uir
!!-a
- Tectonic provtme Tu bine trio 5t t s'.C Gran J.
A d-3 Less c' esternal Iced r
r 11 4.3 Presietty of capattle tectonic structures re-3 sv-3 Loss of conense, vacuwe so-3 Steam press.te regulator f ailu e near plant r
pressu e regulator f at hre tv-5 Loss of fees.ater flom 11 -4.t.
Histornal setse1 city attata 200 miles 3 *- 3 S test r
I 84 5 Loss of feed.ater f l o=
of plant i
a s-t f ees.ater syster pipe breat f ro4._!!j a s-18 liasiological Consecuemes of a 14. -
5tabiltty of slopes Maie 5 tear Line Failure Outside Gr % lm tv-2 Ster line creak inside cortairment Contaiwnt it;55LE CistGA7:04 111 Tornado sissiles Tu tine Mssiles IW-2 5 tear lire ticean o.tsice corteur,ent ao P6qQ'[C?lOle~'
[ j l.a E r
Ie o_wf_JJ Na Loss c' AC power to station
~~ - - ~
((] a.(
leternally generated missiles r
a % JJ 36a toss of AC power to stat +on easiliertes 111 4.0 Site pecateits missiles (tacluding
,r sus t 11 eries atecraf t) i Ggul) a d-7 Loss of forced coolant flow wq
- I;-2 ahnd and torna41o loading t
Wro,; _ v a s-7 toss of forced coolant flo.
Ib 7 Prieary pumc rotor se1ra e r
R.-7 Prmary pec rotor set ru e sy-7 primary pu p seaf t breat m
r n7 Primary pump sna*t breat o
j Growl hi 36-8 Osoatrolled rod assertly witecca.at
- f. p u 4 3.- E Lacontrolled rod asserely atta-at power drawal at po,cr 8 e-f UfKCrtrolled FLd assently withdrama" no-8 Uncontrolled rod assarely wita.
Iow power start-up dramal 1> power start-up IW 6 Control rod e'soperation Ee-8 Coe t r w ' rod sisoppretter I V-13
$pectr# of rod drG9 acC14erts E -l A 5pectrJ" of /od ejec tict ' ac C idents
]
r ro.p 311 se-1, 5pestre of loss of coolant accideets Gregg a b-19 Spec tre of loss of coolant arctoceth EF. "f_.bI1I 0
69 ijj !!
s u-D Radiological Conteoueaces of Fuel s.- 2e nadiciogicai Conse.ences o, r ei camaging acetdets (inside and u
j Laragtng Accidents ( tnside s'id outside contriare**)
outside Con ta t time r d i
Grootr
- s. 12 inas.ertert operw, of s.in sa'ety -
4'Wi.!E I 3; Inadvertent opentag of PM relief valve pressoriarr.eltef velve
[ircu;_s s v-M l rad.ertent operation of ECC5 i
4r Q wj _E.
E g. } 4 jegdyertent operation of ECCS or I
CWC5 malfunction that causes an GecyLI) 3n 11
- 1. advertent Icadtag and operatton of increase in coolant inventory a f uel assently in an tapesper l
90161t on Gec 4_ sj hot aprinacle to Pwes Gruup 3j !.
hot appItcable to BmRs i
i ce m;j s.-i' stes-seerstor
- ee f asie e r
r 3
l 4
1-4 4
G - Gensric 4a-Draf t SE Received From Revisa Brench 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 tne SEP topic review will be topic review progress. The status indicates that closely integrated to improve the ef fectiveness a draft 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 ne incorporated in the final safety assessment for each plant.
4b - SAR Received from Licensee Licensee has submitted a Safety Analysis Report X - Deleted (S AR) 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 t.nd a Final N RC safety to the design of a specific plant or at being evaluation (status 7) is being prepared. Draf t SE duplicated by the N RC TMI Action Plan, will not be issued for topics with licensee SA R submittal.
Unresolved Safety Issue or another SEP Topic per the May 7,1981 letter from G. Lainas to all SEP licensees.
5 - Draft SE Sent to Utility 0 - Topic Not Started A draft topic safety evaluation has been formally transmitted to the licensee for their review and This status indicates that the review of the topic certification of the accuracy of the described has not started.
f acility. Licensees may comment upon NRC conclusions or propose alternatives to NRC posi-tions.
1 - Questions Received From Review Branch 6 - SE Response Received This status is used for internal NRC tracking by NRC of topic review progress. The status indicates that all information necessary to perform a The draft SE has been reviewed and licensee topic evaluation is not available and that ques-comments if any have been formally transmitted tions have been developed and sent to the SEP to the N RC.
branch.
2 - Questions Sent to Utility The N RC topic evaluation has been completed and a final safety evaluation issued. A topic is completed The questions developed in the previous status in several ways: (1) The licensee has responded have been formally transmitted to the licensee that the N RC draf t safety evaluation (i.e. status 5) as a request for additional information.
is correct, or (2) the licensees comments on the NRC draf t safety evaluation (i.e. status 6) have been re-3 - Question Response viewed and if appropriate incorporated into the Received by NRC final safety evaluation, or (3) the licens7 has not responded in the time requested, thus concurring The licensee has formally responded to the informa.
that the draft safety evaluation is correct.
tion request issued by N RC regardmg the topic.
1-5
I
+
SEP TOPIC STATUS
SUMMARY
REPORT m N
\\
NUMBER OF QUESTIONS QUESTION DRAFT SE SAR SE N
TOPICS TOPIC RECEIVED QUESTIONS
RESPONSE
RECEIVED RECEIVED DRAFT SE
RESPONSE
TOPIC 1
\\
GENERIC DELETED H3T FROM SENT TO RECEIVED FRCM FRCM SENT TO RECEIVED COMPLETE N
(G)
(X)
STARTED REVIEW UTILITY BY NRC REVIEW LICENSEE UTILITY BY NRC (7) l PLANT NAME
\\
(0)
BRANCH (2)
(3)
BRANCH (4b)
(5)
(6)
N (1)
(4a)
N 1
PALISADES 0
47 0
0 0
0 0
0 1
0 89 i
GINHA 0
45 0
0 0
0 1
0 1
0 90 DRESDEN 2 3
49 1
0 2
7 1
7 5
5 57 OYSTER CREEK 2
54 5
0 4
0 2
11 10 5
44 MILLSTONE 1 4
51 0
0 0
3 5
11 6
5 52 i
SAN ONOFRE 4
48 2
0 1
10 0
10 8
6 48 5
BIG ROCK POINT 3
52 7
0 6
6 3
9 6
5 40 f
I HADDAM NECK 5
47 2
0 1
6 10 18 5
1 42
[
l l
YANKEE 3
48 5
0 0
8 1
24 4
3 41 LACROSSE 3
54 to 0
1 6
0 24 9
0 30 i
DRESDEN 1 TOTALS THIS MONTH 27 495 32 0
15 46 23 114 55 30 533 l
TOTALS LAST MONTH 27 497 41 1
13 50 28 122 61 28 502 i
M NOTE: Totals do not include Dresden 1,
see page 2-6.
Also included is May 7, 1981 deletion letter to all SEP licensees, see footnote page 1-3.
I
'1-6.
/
SYSTEMATIC EVALUATION PROGRAM GOAL PHASEIIF Progress Toward Complet. ion
-1/ Not including Dresden 1 ACTUAt.
100 %
100 9
/
/ 7-31-82
/
,/
90
- /
/*
,e 85%
80 1 m nth 3% /
83%
75 %
79%
70%
76%
70 67 72%
- 61%
p/
H
/
eNote: Prior to November 30,1981 the 60 60 %
weighted percent did not include
' 81 u
/
generic topics in the progress E
p toward completion.
j uJ 54%
50 f /
e 50 %
/
/
47%
I 9
f 44%
/
42%
y 40 j
/
40 %
/
36%
30
- J 30% festimated)
The plant topic overall completion status (percent complete) is calculated Status Weighting Factor
~
based upon the number of topic reviews to be performed (not including X
Not included deleted topics) and a weighted average of current topic review status.
20 The calculation is performed using the following formula:
G,0 0%
4a,4b 80 %
Percent Complete = Sum of Topics in Status x Weighting Factor of Status 5,6 90 %
7 100 %
10 sum of Topics 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 1-7
INTEGRATED PLANT SAFETY ASSESSMENT REPORT (IPSAR) SCHEDULE To Be Provided In The Future (1-8)
~ ~
SEP 70PIC SVAVUS by QEVIEW DIVISION j
SU.*. MARY TABLE PLANT PALISADES GINNA DRESDEN OYSTER MILLSTONE SAN BIG HADDAM YANKEE LACROSSE TOTAL 2
CREEK 1
ONOFRE ROCK NECK POINT (IAPM) 1/
Michaels Wang Cwalina Fell Persinko McKenna Scholl Brown Boyle Michaels NO. OF TOPICS 137 137 137 137 137 137 137 137 137 137 1370 DELETED g/
47 45 49 54 51 48 52 47 43 54 495 APPLICABLE 90 92 88 83 86 89 85 90 89 83 875 57
/
39
/
33
/
32
/
34
/
7
/
30
/
30
/
31
/
27
/
345 /
~
1 DL
/
/
/
/
/
_ __/
/
/
/
/
/
/ 57
/ 39
/ 37
/ 35
/ 37
/ %D
/ 39
/ 38
/ 33
/ 35
/ 395 i
TECHNICAL
/
/
/
/
/
/
/
/
/
/
/
17
/
20
/
10
/
8
/
12
/
6
/
4
/
8
/
8
/
4
/
97
/
REVIEW DOE
/
/
/
/
/
/
/
/
/
/
/
I
/ 17
/ 20
/ 21
/ 19
/ 20
/ 17
/ 16
/ 20
/ 20
/ 20
/ 190 i
ASSIGNMENT 1/
/
/
/
/
/
/
/
/
/
/
/
16
/
33
/
25
/
21
/
22
/
24
/
20
/
20
/
10
/
a
/
199 /
DSI
/
/
/
/
/
/
/
/
/
/
/
J
/ 16
/ 33
/ 30
/ 29
/ 29
/ 32
/ 30
/ 32
/ 31
/ 28
/ 290 i
/
/
/
/
/
/
/
/
/
/
/
90
/
92
/
68
/
61
/
68
/
62
/
54
/
58
/
49
/
39
/
641 /
l COMPLETE
/
/
/
/
/
/
/
/
/
/
/
/ 90
/ 92
/ 88
/ 83
/ 86
/ 89
/ 85
/ 93
/ 89 83
/ 875
/
/
/
/
/
/
/
/
/
/
/
TARGET DATE -
ALL TOPICS JAN 82 JAN 82 OCT 82 MAY 82 JUN 82 DEC 82 JUL 82 OCT 82 AUG 82 NOV 82 TECHNICAL. REVIEWS j
TO DL l/ Division of Licensing Integrated Assessment Project Manager Z/ Deleted as not applicable, or duplicated by USI, TMI Action Plan, or another topic.
4 J/ These schedules and assignments are consistent with HRR FY 1982-1984 Operating Plan.
_/
- No. Completed / No. Assigned
/
1-9 STATUS AS OF APRIL 30, 1982 i
i
PROGRESS OF TOPlc REVIEWS TOPICS DIVISION OF LICENSING g
TARGET 400 350 s
ACTUAL g
l 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 I
T
'5 11 13 10 6
8 5
5 PER MONTH ETE 4
7 9
11 7
5 8
I I
337 348 361 371 377 385 390 395 CUMULATIVE Ein 298 305 314 325 332 337 345 g
T PROGRESS OF TOPIC REVIEWS O
DIVISION OF ENGINEERING TOPICS 225
- _. 200 __
j TARGET 175 ACTUAL 150
/
125 100
~
75 50 25 l
l l
l l
l l
l l
l l
l g
SEP OCT NOV DEC JAN FEB MAR APR MAY JUN JUL AUG SEP OCI/DEC 8
13 13 23 12 8
5 20 T
PER MONTH ETE 8
0 3
6 7
8 i
T 96 109 122 145 157 165 170 190 N ATIVE.IETE 72 72 75 81 88 96 97 l
PROGRESS OF TOPlc REVIEWS TOPICS DIVISION OF SYSTEMS INTEGRATION TARGET 300 ACTUAL 250 - --
/
200 -
150 -
100 50
~
l I
I I
I I
I I
I I
I I
g SEP OCT NOV DEC JAN FE8 MAR APR MAY JUN JUL AUG SEP OCT/DEC
~
~
~
~
~
PER MONTH m 14 27 28 13 17 13 13 TNT 197 223 253 275 283 286 288 290 N
88 115 143 156 173 186 199
^
7 PROGRESS OF TOPIC REVIEWS O
i TOPICS TOTAL PROJECT 1000 l TARGET 900 ggg p
~~
ACTUAL 7gg 600 500 400 l
300 200 100 1
I I
I I
I I
I I
I I
I g
SEP OCT NOV DEC JAN CEB MAR APR MAY JUN JUL AUG SEP OCT/DEC Tmi 37 50 56 55 26 19 12 27 PER MONTH m
18 34 40 30 31 26 22 CUMULATIVE
~
630 680 736 791 817 836 858 875
~
~
~
m 458 492 532 562 593 619 641 i
LICENSEE TOPIC SUBMITTALS SUBNITTALS DIVISION OF LICENSING TARGET 35
_/
/
30 ACTUAL p
25
/
f 15 10 5
1 I
I I
I I
I I
I I
g JUN JUL AUG SEP OCT NOV DEC JAN FEB MAR APR MAY JUN JUL/DEC
~
~
~
~
~
~
~
PER NONTH m 0
3 1
1 4
6 1
8 5
2 2
32 5
CUNULATIVE N 8
3 4
5 9
15 16 16 21 23 T
LICENSEE TOPIC SUBMITTALS O
DIVISION OF ENGINEERING TOPICS 80 TARGET 78
~~~
60 ACTUAL 50 40 3e 20 IB 1
I I
I I
I I
I I
I I
g JUN JUL AUG SEP OCT NOV DEC JM1 FEB MAR APR MAY JUN JUL/DEC 3
2 1
1 i
i e
gg g,g N 1
8 1
5 7
15 5
1 13 0
61 62 63 64 E
CUNLLATIVE m 1
9 18 15 22 37 42 43 56 56
LICENSEE TOPIC SUBMITTALS SUBNITTALS DIVISIONOFSYSTEMSINTEGRATION 128 IIB TARGET IM ACTUAL
/
78 60 50 40 30 20 I'
kI I
I I
I I
I I
I I
I g
JUN JUL AUG SEP OCT NOV DEC JAN FEB NAR APR NAY JUN JUL/DEC T
PER MONTH 8
3 6
3 1
8 ETR 1
IB 3
31 3
2 7
12 7
6 CUMULATIVE 6
84 W
93 97 97 N
1 11 14 45 48 58 57 69 76 82 g
7 LICENSEE TOPIC SUBMITTALS 0
TOPICS TOTAL PROJECT 225 TARGET 2M 175 ACTUAL 150 i
125 IN 75 5e 25 1
I I
I I
I I
I I
I I
g JUN JUL AUG SEP OCT NOV DEC JAN FEB HAR APR NAY JUN JUL/DEC T
PER MONTH 13 9
8 7
2 4
ETR 2
21 5
37 14 23 13 13 25 8
T ET NTIVE 154 167 176 184 191 193 197 ETR 2
23 28 65 79 182 115 128 153 161
a__-
e w
.__mA m-----,,
m.
m
=i-
.m m--
1
\\i i
l l
l
'l i
l 1
I i
i 1
1 I
Z l
O 4
i u.I
&)
1 4
i I
i l
i 3
1 j
i I
_, _ ~. - - - - _ _
BIG ROCK P0 NT FACIllTY: BIG ROCK POINT 1 TOPIC NO.
nEVIEW STATUS REMARKS DIV/BR LICENSEE: CONSUMERS POWER Il-1 A.
DL/SEPB 7
LPCo to NRC 09/02/30 REGION /L0 RATION: 4 MILES NORTH 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 PCWER CAPACITY: 0240(THERMAL) 067(ELECTRICAL)
II-2 A.
DSI/AEB 7
NRC 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 4B CPC0 TO NRC 04/06/82 A/E FIRM: BECH.
II-2 D.
X NRC to CPCo 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W.
RUSSELL II-3 A.
DE/HGEB 2
NRC to CPCo 01/11/82 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD II-3 B.
DE/HGEB 2
HRC to CPCo 01/11/82 OPERATING REACTORS PROJECT MANAGER: R.
EMCH II-3 B.
1 DE/HGEB 2
NRC to CPCo 01/11/82 INTEGRATED ASSESSMENT PROJECT MANAGER:
R.
SCHOLL / j II-3 C.
DE/HGE3 2
NRC to CPCo 01/11/82 II-4 DE/GSB 7
NRC to CP(o 06/08/81 KEY FOR STATUS CODES II-4 A.
DE/GS3 7
NRC to CPCo 06/08/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.
DE/GSB 3
CPCo to NRC 10/10/30 FRCM REVIE!J BRANCH X - DELETED II-4 C.
DE/GSB 7
NRC to CPCo 06/08/31 4b-SAR RECEIVED FRO 1 0 - TOPIC NOT LICEt4SEE II-4 D.
DE/HGEB 4b CPCo to NRC 10/05/81 STAP.TED 5 - DRAFT SE SENT II-4 E.
X NRC to CPCo 11/16/79 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.
DE/HGEB 4b CPCo to NRC 10/19/31 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC III-1 DL/SEPB 5(SYS)
NRC TO CPCO 04/16/82 TO UTILITY DL/SEPB 7(ELEC) Part of VII-3 08/19/81 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEP3 3
CPCo to NRC 07/09/31 RECEIVED BY HKC (2-2)
BIG ROCK POINT TOPIC NO.
REVIEW STATUS R EMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR III-3 A.
DE/SEB 3
CPCo to NRC 08/09/80 111-10 B.
X NRC to CPCo 48/16/79 III-3 B.
X NRC to CPCo 12/26/80 III-10 C.
X NRC to CPCo 11/16/79 III-3 C.
DE/AGEB 4b CPCo to NRC 12/21/81 III-1' X
NRC to CPf0 05/07/81 III-4 A.
DSI/ASB 4B CPCO TO NRC 03/16/82 III-12 X
NRC to CPCo 05/07/81 III-4 B.
DE/MTEB 0
IV-1 A.
DL/SEPB 7
HRC to CPCo 10/08/81 III-4 C.
DSI/ASB 0
IV-2 DSI/ICSB 7
CPCo to NRC 12/22/81 III-4 D.
DE/SAB Ab CPCo to NRC 12/14/81 IV-3 X
NRC to CPCo 05/04/81 III-5 A.
DL/SEPS 0
V-1 X
NRC to CPCo 11/27/81 III-5 B.
DL/SEPB 0
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 NRC to CPCo 05/07/81 V-4 DL/SEPB 2
NRC TO CPC0 04/26/82 III-7 B.
DL/SEPB 3
CPCo to NRC 07/09/81 V-5 DL/SEPB 5
NRC TO CPCO 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.
DSI 5
NRC TO CPCO 03/02/82 V-8 X
MRC to CPCo C5/07/81
'III-8 B.
X NRC to CPCo 09/26/80 V-9 X
NRC to CPCo 11/16/79 III-8 C.
DL/SEPB 6
CPCo to NRC 12/29/81 V-10 A.
DL/SEPB 7
HRC to CPCo 10/09/79 III-8 D.
X NRC to CPCo 05/07/81 V-10 B.
DL/SEPB 6
CPC0 TO NRC 03/30/82 III-9 X
NRC +o CPCo 05/07/81 V-11 A.
DL/SEPB 6(Elec) CPCo to NRC 11/12/81 III-10 A.
DL/SEPB 7
NRC TO CPCO 03/30/82 V-11 B.
DL/SEPB 6(SYS)
CPC0 TO NRC 03/30/82 7(Elec) NRC to CPCo 08/19/81 (2-3)
BIG ROCK POINT TCPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REF. ARKS DIV/BR DIV/BR V-12 A.
DL/SE/a 7
hkC to CPCo 10/09/79 VI-7 D.
DL/SEPB 7
hRC to CPCo 08/17/78 V-13 X
NRC to CPCo 0 5/0 7/.t t V I -7 E.
X NRC to CPCo 05/07/81 Vi-1 DE/CEB 4B CPCO TO NRC 03/16/82 VI-7 F.
X NRC tIo CPCo 11/16/79 VI-2 A.
X NRC to CPCo 05/07/81 VI-8 X
NRC to CPCo 05/07/81 VI-2 3.
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 0
VI-2 D.
DSI/CSB 3
CPCo to NRC 04/02/80 VI-10 B.
X NRC to CPCo 11/16/79 VI-3 DSI/CSB 3
CPCo to NRC 04/02/80 VII-1 A.
DL/SEPB 5
NRC TO CPCO 03/05/82 VI-4 DS!/CSB 4A(SYS) 03/24/32 VII-1 B.
DL/SEPB 7
NRC to CPCo 08/17/78 DL/SEPB 7(Elce) NRC to CPCo 11/24/81 VII-2 Di/SEPB 7
HRC to CPCo 02/01/82 VI-5 X
NRC tu CPCo 05/07/81 VII-3 DL/SEPB 6(SYS)
CPCO TO NRC 03/30/82 VI-5 DSI/CS3 G
NRC to CPCo 05/07/81 DL/SEPB 7(Elec) NRC to CPCo 03/19/81 VI-7 A.
1.
X NRC to CPCo 11/16/79 VII-4 X
NRC to CPCo 05/07/81 VI-7 A.
2.
X NRC to CPCo 05/07/81 VII-5 X
NRC to CPCo 05/07/81 VI-7 A.
3.
DL/SEPB 5
NRC to CPCo 02/22/82 VII-6 DL/SEPB 7
NRC to CPCo 09/21/81 VI-7 A.
4 DSI/RS3 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 NRC 10/21/81 VIII-1 A.
DSI/PSB G
HRC to CPCo 05/07/81 4 A', SYS )
04/22/82 VIII-2 DL/SEPB 6
CPCO TO NRC 04/21/82 VI-7 C.
DL/SEPB 7
NRC to CFCo 08/GS/81 VIII-3 A.
DL/SEPB 7
CPCo to NRC 04/22/81 VI-7 C.
1.
DL/SEPB 7
NRC to CPCo 02/22/82 VIII-3 B.
DL/SEPB 7
NRC to CPCo 02/22/82 VI-7 C. 2.
DL/SEP3 7
NRC to CPCo 08/05/81 VIII-4 DL/SEPB 5
NRC 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 0
XV-10 X
NRC to CPCo 11/16/79 IX-2 X
HRC to CPCo 05/07/81 XV-11 DSI/CPB 7
NRC to CPCo 12/02/81 IX-3 DL/SEPB Gb CPCo to NRC 12/10/81 XV-12 A
NRC to CPCo 11/16/79 IX-4 X
HRC to CPCo 11/16/79 XV-13 DSI/CPB 7(Sys)
HRC to CPCo 12/02/81 DSI/AEB 7(DOSES) NRC to CPCo 01/12/82 IX-5 DL/SEPB 0
XV-14 DSI/RSB 7
NRC to CPCo 08/18/81 IX-6 DE G
NRC to CPCo 05/07/81 XV-15 DSI/RS3 7
NRC to CFCo 08/1S/81 X
X HRC 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
HRC to CPCo 11/16/79 XI-2 X
NRC to CPCo 12/04/81 XV-18 DSI/AES 4A 04/02/82 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 07/01/81 XV-1 DSI/RSS 7
NRC TO CPC0 03/04/82 XV-20 DSI/AEB 7
NRC to CPCo 01/12/82 XV-2 X
NRC to CPCo 11/16/79 XV-21 X
NPC to CPCo 05/07/81 XV-3 DSI/RSB 7
HRC to CPCo 10/16/81 XV-22 X
NRC to CPCo 05/07/81 XV-4 DSI/RSB 7
HRC to CPCo 10/16/81 XV-23 X
NRC to CPCo 05/07/81 XV-5 DSI/RSB 7
HRC to CPCo 02/08/82 XV-24 X
NRC to CPCo 05/07/81 XV-6 X
HRC to CPCo 11/16/79 XVI X
NRC to CPCo 11/05/80 XV-7 DSI/RSB 7
HRC TO CPCO 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/RSB 7
NRC TO CPC0 04/07/62 (2-5)
DRESDEN1 FACILITY: DRESDEN 1 LICENSEE: COMMONWEALTH EDISDN REGIDH/LOCATIGH: 9 MILES EAST OF MORRIS, ILL.
DOCAET NO.
05000010 F2WER CAPACITY: 700(THERMAL) 200(ELECTRICAL)
GE.
A/E FIRM: BECH.
SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD OPERATING REACTORS PROJECT MANAGER: P. O'CONHOR By letter dated December'31, 1980 Commonwealth Edison indi-cated that Dresden 1 was undergoing an extensive modifica-tion and was not scheduled for restart until June, 1986.
Also, by latter dated April 4, 1981, in response to the NRC's January 14, 1981 letter on SEP redirection the lican-see stated that the Dresden 1 SEP review is not being actively pursued, i.e.
defered.
(2-6)
DRESDEN 2 FACILITY: DRESDEN 2 TCPIC NO.
REVIEW STATUS REMARKS DIV/BR LICENSEE: COMMONWEALTH EDISDN II-t A.
DE/SAB
?
NRC to Ceco 10/06/81 REGION /LOCAT10H: 9 MILES EAST OF MORRIS, ILL.
11-1 B.
DE/SAB 7
NRC to Ceco 10/06/31 DOCKET NO.: 05000237 II-1 C.
DE/SAB 4b Ceco to NRC 12/08/81 POWER CAPACITY: 2527(THERMAL) 0794(ELECTRICAL)
II-2 A.
DSI/AEB 7
NRC to Ceco 04/24/81 OL NUMBER: DPR-19 II-2 5.
X NRC to Ceco 05/C7/51 H.S.S.S.: GE.
II-2 C.
DSI/AEB 7
NRC to CPCo 08/26/81 A/E FIRM: S&L.
II-2 D.
X NRC to Ceco 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL II-3 A.
DE/HGEB 3
CECO to NRC 01/04/82 OPERATING REACTORS BRANCH CHIEF:
D. CRUTCHFIELD II-3 8.
DE/HGEB 3
CECO to NRC 01/04/82 OPERATING REACTORS PROJECT MANAGER: P. O'CONNOR j
II-3 B.
1.
DE/HCEB 3
CECO to NRC 01/04/82 vif~
\\
INTEGRATED ASSESSMENT PROJECT MANAGER: G. CWALINA #I m II-3 C.
DE/HGEB 3
Ceco to NRC 01/04/82 KEY FOR STATUS CODES II-4 DE/CSB 7
NRC to CECO 07/09/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 A.
DE/GSB 7
NRC to Ceco 06/08/81 FROM REVIEW BRANCH X - DELETED II-4 B.
DE/GSB 7
NRC to Ceco 07/09/81 4b-SAR RECEIVED FROM 0 - TOPIC NOT LICENSEE II-4 C.
DE/GSB 7
NRC to CECO 06/08/81 STARTED 5 - DRAFT SE SENT II-4 D.
DE/HGEB 4b Ceco to NRC 12/08/81 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 - QUESTIONS SENT BY NRC II-4 F.
DE/HGEB 4b Ceco to NRC 12/08/81 TO UTILITf 7 - TOPIC COMPLETE III-1 DL/SEPB 5(SYt)
HRC TO CECO 03/09/87 3 - QUESTION RESPONSE DL/SEPB 7(Eles) Part of VII-3 07/07/81 RECEIVED BY NRC III-2 DL/SEPB 4B CECO TO NRC 02/22/82 (2-7)
DRESDEN 2
TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/LR DIV/3R III-5 A.
D E/ S E o 4b CECO to hRC 12/08/81 111-10 B.
X NRC to CLCo 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 48 CECO TO NRC 02/16/32 III-11 X
NRC to Ceco 05/07/81 III-4 A.
DSI/ASB 4B CECO TO NRC 12/08/81 III-12 X
NRC to Ceco 05/07/81 III-4 B.
DE/MTEB 3
CECO TO NRC 02/24/82 IV-1 A.
DL/SEPB 7
NRC to Ceco 10/26/81 III-4 C.
DSI/ASB 0
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 2
NRC to CECO 01/04/80 V-1 X
NRC to Ceco 11/27/81 III-5 B.
DL/SEPB 6
Ceco to NRC 03/21/80 V-2 X
NRC to CECO 11/16/79 III-6 DL/SEPB 6
CECO to NRC 03/13/81 V-3 X
NRC to Ceco 05/07/81 III-7 A.
X HRC to CECO 05/07/81 V-4 DL/SEPB 2
NRC TO CECO 04/26/82 III-7 B.
DL/SEPB 3
Ceco to NRC 09/28/79 V-5 DL/SEPB 5
NRC TO CECO 02/24/82 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 05/07/81 III-8 A.
DSI 7
NRC to CECO 02/26/82 V-8 X
HRC to Ceco 05/07/81 III-8 B.
X HRC to CECO 09/11/80 V-9 X
NRC to Ceco 11/16/79 III-8 C.
DL/SEPB 6
CECO to NRC 03/10/80 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/SEPB 7
NRC 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 (2-8)
DRESDEN 2 TOPIC NO.
REVIEW STATUS REMARKS TCPIC NO.
R EVI E'4 STATUS REMARKS DIV/BR DIV/BR V-12 A.
DL/SEPB 7
NRC to CtCo 04/16/81 VI-7 D.
DL/SEPB 7
NRC to CECO OS/17 / 7 8 V-13 X
HRC to Ceco 05/07/81 VI-7 E.
X NRC to Ceco 05/07/81 VI-1 DE/CEB 3
CECO to NRC 07/27/79 VI-7 F.
X NRC to CECO 11/16/79 VI-2 A.
X NRC to CECO 05/07/81 VI-8 X
NRC to CECO 05/07/81 VI-2 B.
X NRC to CECO 05/07/81 VI-9 X
NRC to Ceco 11/16/79 VI-2 C.
X NRC to Ceco 11/16/79 VI-10 A.
DL/SEPB 7
NRC to Ceco 07/03/31 VI-2 D.
DSI/CSB 6
CECO TO NRC 04/06/t2 VI-10 B.
DL/SEPB 7(Sys)
CECO TO NRC 11/03/81 DL/SEPB 7(Elec) hRC TO CECO 04/22/82 VI-3 DSI/CSB 6
CECO TO NRC 04/06/82 VII-1 A.
DL/SEPB 7
NRC tc Ceco 06/05/81 VI-4 DSI/CSB 5(Sys)
NRC to Ceco t <18/81 DL/SEPS 6(ELEC) CECO TO NRC 04/05/82 VII-1 B.
DL/SEPB 7
NRC to CECO 05/17/78 VI-5 X
HRC to Ceco 05/07/81 VII-2 DL/SEPB 7
Ceco to NRC 11/03/81 VI-6 DSI/CSB G
NRC to CECO 05/07/81 VII-3 DL/SEPB 7(Sys)
NRC to Ceco 04/24/81 DL/SEPB 7(Elec) NRC to Ceco 07/07/31 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 HRC to CECO 05/07/81 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
HRC to Ceco 05/26/81 VI-7 A.
4.
DSI/RSB 7
HRC to CECO 02/22/82 VII-7 X
NRC to Ceco 11/16/79 VI-7 B.
X NRC to CECO 11/16/79 VIII-1 A.
DSI/PSB G
NRC to Ceco 05/07/81 VI-7 C.
DL/SEPB 7
NRC to CECO 03/13/81 VIII-2 DL/SEPB 7
NRC to Ceco 06/06/81 VI-7 C.
1 DSI/PSB 7
NRC TO CECO 02/05/82 VIII-3 A.
DL/SEPB 7
HRC 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 HRC 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 NO.
REVIEW STATUS R EMARKS DIV/BR DIV/SR IX-1 DSI/ASB 4A 03/26/82 XV-10 X
hRC to CECO 11/16/79 IX-2 X
HRC to CECO 05/07/81 XV-11 DSI/CPB 7
HRC to Ceco 02/08/82 l
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 5
HRC TO CECD 04/12/82 XV-14 DSI/R$5 7
NRC to CECO 12/15/81 IX-6 DE/CEB G
NRC to CECO 05/07/81 XV-15 DSI/RSB 7
NRC to Ceco 01/04/82 X
X NRC to Ceco 05/07/81 XV-16 DSI/AEB 7
CECO to NRC 10/20/81 XI-1 X
NRC to Ceco 12/04/81 XV-17 X
NRC to Ceco 11/16/79 XI-2 X
NRC to Ceco 12/04/81 XV-18 DSI/AEB 7
NRC to Ceco 02/05/82 XIII-1 X
NRC to Ceco 05/07/81 4
XIII-2 DL/SSPB 7
NRC to CECO 03/11/81 XV 39 DSI/RSB 7(Sys)
NRC to Ceco 12/07/81 DSI/AEB 7(DOSES) CECO to NRC 01/05/82 XV-1 DSI/R$B 7
NRC to Ceco 12/29/81 XV-20 DSI/AEB 7
NRC to Ceco 11/20/81 i
XV-2 X
NRC to CECO 11/16/79 XV-21 X
NRC to Ceco 05/07/81 XV-3 DSI/RSB 7
HRC to Ceco 12/07/81 XV-22 X
HRC to Ceco 05/07/81 XV-4 DSI/R$B 7
NRC to Ceco 12/07/81 XV-23 X
NRC to Ceco 05/07/81 XV-5 DSI/RSS 7
NRC to Ceco 12/15/81 XV-6 X
NRC to Ceco 11/16/19 XVI X
NRC to Ceco 11/05/80 XV-7 DSI/R$B 7
NRC to CECO 01/04/82 XVII DL 7
NRC to Ceco 11/20/79 XV-8 RSI/CPB 7
NRC to Ceco 02/08/82 XV-9 DSI/RSB 7
HRC to Ceco 12/15/81
+
l (2-10)
GINNA I
FACILITY: GINNA TOPIC NO.
REVIEW STATUS REM *RKS DIV/BR LICENSEE: ROCHESTER GAS & ELECTRIC 11-1 A.
DE/SAS 7
hRC to RGE 07/17/81 REGION / LOCATION: 15 MILES NORTH EAST OF ROCHESTER, NY.
II-1 B.
DE/SAB 7
NRC to RGE 07/21/81 DOCKET NO.-
05000244 II-1 C.
DE/SAB 7
NRC to RGE 09/29/81 POWER CAPACITY: 1520(THERMAL) 0490(ELECTRICAL)
II-2 A.
DSI/AEB 7
NRC to RGE 11/03/81 OL NUMBER: DPR-18 N.S.S.S..
WEST.
t 05/07/81 A/E FIRM: GIL.
II-2 D.
X NRC to RGE 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W.
RUSSELL II-3 A.
DE/HGEB 7
HRC TO RGE 04/26/82 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD II-3 B.
DE/HGEB 7
HRC TO RGE 04/26/82 OPERATING REACTORS PROJECT MANAGER: J.
LYONS II-3 B.
1 DE/HGEB 7
NRC TO RGE 04/26/82 INTEGRATED ASSESSMENT PROJECT MANAGER:
A.
WANG II-3 C.
DE/HGEB 7
HRC TO RGE 04/26/82 II-4 DE/GSB 7
NRC to RGE 07/09/81 KEY FOR STATUS CODES II-4 A.
DE/GSB 7
HRC to RGE 06/08/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.
DE/GSB 7
HRC to RGE 07/09/81 FROM REVIEW BRANCH X - DELETED II-4 C.
DE/GSB 7
NRC to RGE 06/08/81 4b-SAR RECEIVED FROM 9 - TOPIC HOT LICENSEE II-4 D.
DE/AGEB 7
NRC to RGE 02/19/82 STARTED 5 - DRAFT SE SENT II-4 E.
X NRC to RGE 11/16/79 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANGH II-4 F.
DE/HGEB 7
NRC to RGE 02/19/82 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC III-1 DL/SEPB 7(Sys)
NRC to RGE 12/17/81 TO UTILITY DL/SFAB 7(Elec) NRC to RGE 04/02/81 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 7
NRC TO RGE 04/21/82 RECEIVED BY NRC d - DATA FOR NEXT MONTH (NOVEMBER)
(2-11)
GINNA TOPIC NO.
REVIEN STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR 111-3 A.
DE/SEB 7
NRC 10 RGE 03/05/82 111-10 B.
DLeSLPB 7
hRC to RGE 06/22/81 III-3 B.
X HRC to RGE 12/31/80 III-10 C.
X NRC to RGE 11/16/79 III-3 C.
DE/NGEB 5
NRC to RGE 02/22/82 III-11 X
HRC 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 III-4 C.
DSI/ASB 7
HRC to RGE 02/17/82 IV-2 DSI/ICSB 7
NRC to RGE 05/26/81 III-4 D.
DE/SAB 7
NRC to RGE 07/21/81 IV-3 X
NRC to RGE 05/07/81 III-5 A.
DL/SEPB 7
NRC to RGE 02/22/82 V-1 X
NRC to RGE 11/27/81 III-5 B.
DL/SEP3 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
NRC to RGE 05/07/81 III-7 A.
DL/SEPB 7
NRC 10 RGE 04/a5/82 V-4 X
NRC to RGE 05/07/81 III-7 B.
DL/SEP3 7
NRC TO RGE 04/21/82 V-5 DL/SEPB 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
HRC to RGE 05/08/80 V-7 DSI/ASB 7
HRC 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 HRC 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 HRC to RGE 05/07/81 V-10 B.
DL/SEPB 7
RGE to NRC 09/29/81 III-9 X
NRC to RGE 05/07/81 V-11 A.
DL/SEPB 7
NRC to RGE 11/07/81 III-10 A.
DL/SEPB 7
NRC to RGE 08/03/81 V-11 B.
DL/SEPB 7(Sys)
RGE to NRC 09/29/81 DL/SEPB 7(Elec) HRC to RGE 04/24/81 (2-12)
GINNA TOPIC NO.
REVIEW STATUS R Ef1 ARKS TOPIC NO.
R EVIELI 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 NRC to RGE 05/07/81 VI-1 DE/CEB 7
HRC to RGE 02/19/82 VI-7 F.
DL/SEPB 7
HRC to RGE 06/24/81 VI-2 A.
X NRC to RGE 05/07/81 VI-8 X
NRC to RGE 05/07/81 i
VI-2 B.
X NRC ts RGE 05/07/81 VI-9 X
NRC to RGE 11/16/79 i
VI-2 C.
X NRC to RGE 11/16/79 VI-10 A.
DL/SEPB 7
NRC to RGE 11/27/81 1
VI-2 D.
DSI/CSB 7
NRC TO RGE 04/12/82 VI-10 B.
X NRC to RGE 11/16/79 VI-3 DSI/CSB 7
NRC TO RGE 04/12/82 VII-1 A.
DL/SEPB 7
NRC to RGE 07/30/81 j
VI-4 DSI/CSB 7(SYS)
NRC TO RGE 04/12/82 VII-1 B.
DL/SEPB 7
NRC to RGE 08/17/78 DL/SEPB 7(ELEC) NRC TO RGE 03/19/82 t
4 VII-2 DL/SEPB 7
NRC to RGE 12/28/81 VI-5 X
NRC to RGE 05/07/81 1
VII-3 DL/SEPB 7(Sys)
NRC to RGE 09/29/81 j
VI-6 DSI/CSB 7
NRC to RGE 05/06/81 DL/SEPB 7(Elec) NRC to RGE 03/25/82
[
VI-7 A.
1 DL/SEPB 7
NRC to RGE 02/20/81 VII-4 X
hRC to RGE 05/07/81 i
i VI-7 A. 2.
DL/SEPB 7
NRC to RGE 08/17/78 VII-5 X
NRC to RGE 05/07/81 VI-7 A. 3.
DL/SEPB 7
NRC to RGE 11/27/81 VII-6 DL/SEPB 7
NRC to RGE 06/24/81 VI-7 A. 4.
X HRC to RGE 05/07/81 VII-7 X
NRC to RGE 11/16/79 VI-7 8*
DSI/RSB 7(SYS)
NRC TO RGE 03/09/82 VIII-1 A.
DSI/PSB 7
NRC to RGE 03/26/81 i
DL/SEB 7(Elec) NRC to RGE 09/18/81 VIII-2 DL/SEPB 7
NRC to RGE 06/24/81 j
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-3 8.
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 HRC to RGE 11/16/79 r
i i
i I
(2-13) i t
t
GINNA TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR IX-t DSI/ASB 7
NRC to RGE 11/24/84 XV-10 DSI/RSS 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/SEPB 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 i
IX-4 DSI/R$8 7
NRC to RGE 08/26/81 XV-13 X
NRC to RGE 11/16/79 IX-5 DL/SEPB 7
RGE to NRC 03/29/82 XV-14 DSI/RSB 7
NRC to RGE 09/04/81 IX-6 4a 02/24/82 XV-15 DSI/RSB 7
NRC to RGE 09/04/81 X
X NRC to RGE 05/07/81 XV-16 DSI/AEB 7
NRC TO RGE 03/03/82 XI-1 X
NRC to RGE 12/04/81 XV-17 DSI/RSR 7(Sys)
NRC to RGE 09/04/81 XI-2 X
NRC to RGE 12/04/81 DSI/AEB 7(DOSES) NEC TO RGE 03/03/82 XIII-1 X
NRC to RGE 05/07/81 XV-18 X
NRC to RGE 03/11/80 XIII-2 DL/SEP8 7
NRC to RGE 03/26/81 XV-19 DSI/RSB 7(Gys)
HRC to RGE 10/02/81 DSI/AEB 7(DOSES) RGE TO NRC 03/09/82 XV-1 DSI/R$B 7
NRC to RGE 09/04/81 XV-20 DSI/AEB 7
NRC TO RGE 03/03/82 XV-2 DSI/RSB 7(Sys)
NRC to RGE 09/04/81 DSI/AEB 7(DOSES) NRC TO RGE 03/03/82 XV-21 X
NRC to RGE 05/07/81 l
XV-3 DSI/RSB 7
NRC to RGE 09/04/81 XV-22 X
NRC to RGE 05/07/81 XV-4 DSI/RSB 7
NRC to RGE 09/04/81 XV-23 X
NRC to RGE 05/07/81 XV-5 DSI/RSB 7
NRC to RGE 09/04/81 XV-24 X
NRC to RGE 05/07/81 XV-6 DSI/R$B 7
NRC to RGE 09/04/81 XVI X
HRC to RGE 11/05/80 XV-7 DSI/RSB 7
NRC to RGE 09/04/81 XVII DL 7
MRC to RGE 08/17/78 XV-8 DSI/CPB 7
HRC to RGE 09/04/81 XV-9 DSI/RSB 7
RGE to NRC 10/16/81 (2-14)
HADDAM NECK FACILITY: HADDAM NECK TCPIC NO.
REVIEW STATUS REMARKS DIV/BR LICENSEE: CONNECTICUT YANKEE ATOMIC POWER REGION / LOCATION: 13 MILES EAST OF MERIDEN. CT.
~
~
DOCKET NO: 05000213 II-1 C.
DE/SAB 4A 03/29/82 POWER CAPACITY: 1825(THERMAL) 0575(ELECTRICAL)
II-2 A.
DSI/AEB 7
CYAPCo to NRC 01/22/81 OL NUMBER: DPR-61 II-2 B.
X NRC to CYAPCo 05/07/81 H.S.S.S.: WEST.
II-2 C.
DSI/AEB 7
NRC TO CYAPCO 04/26/82 A/E FIRMS S&W II-2 D.
X HRC to CYAPCo 05/07/81 SYSTEMATIC EVALUATICN PROGRAM BRANCH CHIEF: W. RUSSELL II-3 A.
DE/HGEB 4b CYAPCo to NRC 12/14/81 OPERATING REACTORS BRANCH CHIEF:
D. CRUTCHFIELD II-3 B.
DE/HGEB 4b CYAPCo to NRC 12/14/81 OPERATING REACTOR $ PRJJECT MANAGER: C. TROFF
./
II-3 B.
1 DE/HGEB
- b CYAPCo to NRC 12/14/81 INTEGRATED ASSESSMENT PROJECT M'ANAGER: S. EROWN II-3 C.
DE/HGEB 4b CYAPCo to NRC 12/14/81 II-4 DE/GSB 7
NRC to CYAPCo 06/08/81 KEY FOR' STATUS CODES II-4 A.
DE/GSB 7
NRC to CYAPCo 06/08/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.
DE/GSB 3
NUREG/CR1582 08/04/80 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 4b CYAPCo to NRC 08/31/81 STARTED 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 4b CYAPCo to NRC 12/18/31 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC III-1 DL/SEPB 2(Sys)
HRC to CYAPCo 11/20/81 TO UTILITY DL/SEPB 7(Elec) Part of VII-5 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 4b CYAPCo to NRC 12/14/81 RECEIVED BY NRC (2-15)
~
l HADDAM NECK TOPIC NO.
REVIEW STATUS REMARKS TOPIC HO.
REVIEW STATUS REMARKS DIV/BR DIV/ER l
111-3 A.
DE/SEB 4b CYAPCo to NRC 08/31/81 111-10 B.
DL/SEPB 7
NRC.TO CYAPCO 03/36/82 l
III-3 B.
DE/HGEB 0
III-10 C.
X NRC to CYAPCo 04/16/79 III-3 C.
DE/HGEB 4b CYAPCo to NRC 08/31/81 III-11 X
NRC to CYAPCo 05/07/81 III-4 A.
DSI/ASB 4a 12/28/81 III-12 X
HRC to CYAPCo 05/07/81 TII-4 B.
DE/MTEB G
NRC to CYAPCo 05/07/81 IV-1 A.
DL/SEPB 7
CYAPCo to NRC 06/25/79 III-4 C.
DSI/ASB 4b CYAPCo to NRC 02/12/82 IV-2 DSI/ICSB 7
NRC to CYAPCo 02/22/82 III-4 D.
DE/fr 4A 03/29/82 IV-3 X
NRC to CYAPCo 05/07/81' III-5 A.
DL/SEPr 3
CYAPCo to NRC 02/07/80 V-1 X
'NRC to CYAPCo 11/27/81 III-5 B.
DL/SF"?
5?
V-2 X
!;RC to CYAPCo 04/16/79 III-6 DL/$6:
CYAPCo to NRC 06/11/81 V-3 X
NRC to CYAPCo 05/07/81 III-7 A.
X HRC to.CYAPCo 05/07/81 V-4 X
NRC to CYAPCo 05/07/81 l
III-7 B.
DL/SEPB 3
CYAPCo to NRC 09/07/79 V-5 DL/SEPB 7
NRC to CYAPCo 02/22/82 i
III-7 C.
X HRC to CYAPCo 04/16/79 V-6 DL/SEPB 7
NRC.to CYAPCo 03/05/60 III-7 D.
DE/SEB 7
NRC to CYAPCo 10/16/81 V-7 DSI/ASB
'4a 11/05/81 III-8 A.
DSI 4a 02/09/82 V-8
'X NRC to CYAPCo 05/07/81
]
III-8 1.
X NRC to CYAPCo 10/01/80 V-9 NRC to CYAPCo 11/16/79 III-l C.
DL/SEPB 7
NRC to CYAPCo 01/29/82 V-10 A.
DL/SEPB 7
NRC to CYAPCo 01/13/81 III-8 D.
X NRC to CYAPCo 05/07/81 V-10 B.
DL/SEPB 7
NRC to CYAPCo 12/28/81 III-9 X
NRC to CYAPCo 05/07/81 V-11 A.
DL/SEPB 7
HRC to CYAPCo 11/03/81 1
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 03/03/82
}
1 i
a i
i 1
(2-16) j
~
HADDAM NECK 1
TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS l
l DIV/BR DIV/ER V-12 A.
X NRC to CYAPCo 11/16/79 VI-7 D.
DL/SEPS 7
hRC to CYAFCo 03/17/78 I
V-13 X
NRC to CYAPCo 05/07/81 VI-7 E.
X NRC to CYAPCo 05/07/81 VI-1 DE/CEB Gb CYAPCO to NRC 02/09/82 i
VI-7 F.
X NRC to CYAPCo 04/16/79 I
VI-2 A.
X HRC to CYAPCo 05/07/81 VI-8 X
NRC to CYAPCo 05/07/81 VI-2 B.
X NRC to CYAPCo 05/07/81 VI-9 X
NRC to CYAPCo 11/16/79 VI-2 C.
X NRC to CYAPCo 04/16/79 VI-10 A.
DL/SEPB 0
VI-2 D.
DSI/CSB 3
CYAPCo to NRC 04/27/81 VI-10 B.
X NRC to CYAPCo 04/16/79 VI-3 DSI/CSB 3
CYAPCo to NRC 04/27/81 VII-1 A.
DL/SEPB 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 i
VI-5 X
NRC to CYAPCo 05/07/81 VII-3 DL/SEPB 7(Sys)
HRC to CYAPCo 12/28/81 VI-6 DSI/CSB G
NRC to CYAPCo 05/07/81 DL/SEPB 7(Elec) HRC to CYAPCo 08/28eSt VI-7 A.
1 DL/SEPB 7
NRC to CYAPCo 02/20/81 VII-4 X
NRC to CTAPCo 05/07/81 VI-7 A.
2.
X NRC to CYAPCo 05/07/81 VII-5 X
NRC to CYAPCo 05/07/81 VI-7 A.
3.
DL/SEPB 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 j
VI-7 B.
DSI/RSB 7(SYS)
HRC TO CYAPCO 04/14/82 VIII-1 A.
DSI/PSB G
NRC to CYAPCo 05/07/81 l
DL/SEPB 7(Elec) NRC to CYAPCo 05/21/81 1
VIII-2 DL/SEPB 7
NRC to CYAPCo 08/28/81 VI-7 C.
DL/SEPB 7
HRC to CYAPCo 03/13/81 VIII-3 A.
DL/SEPB 7
CYAPCo to NRC 02/16/79 VI-7 C.
1 DL/SEPB 7
CYPACO to NRC 01/11/82 VIII-3 B.
DL/SEPB 7
NRC to CYAPCo 08/28/81 VI-7 C. 2.
DL/SEPB 7
NRC to CYAPCo 03/13/81 VIII-4 DL/SEPB 5
NRC to CYAPCo 12/23/81 VI-7 C. 3.
DL/SEPB 7
CYAPCo to NRC 02/12/82 (2-17)
HADDAM NECK TOPIC NO.
REVIEM STATUS REMARKS TOPIC NO.
REVIEW STATUS REMAdKS DIV/BR DIV/BR IX-1 DSI/ASB 7
NRC 10 CYAPCC 03/01/82 XV-10 DSI/RSB 7
hRC 10 CYAPC0 04/12/82 i
IX-2 X
HRC to CYAPCo 05/07/81 XV-11 X
NRC to CYAPCo 10/01/80 IX-3 DL/SEPB 4A 04/30/82 XV-12 DSI/CPB 7(SYS)
HRC TO CYAPC0 03/23/82 DSI/RSB 4bCDoses)CYAPCo to NRC 09/30/81 IX-4 DSI/RSS 7
NRC TO CYAPCO 04/26/32 XV-13 X
NRC to CYAPCo 11/16/79 IX-5 DL/SEPB 4b CYAPCo to NRC 12/14/81 XV-14 DSI/RSB 7
NRC TO CYAPCO 04/26/82 IX-6 DE G
NRC to CYAPCo 05/07/81 XV-15 DSI/R$B 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 J
XI-1 X
NRC to CYAPCo 12/04/81 X'.'- 17 DSI/RSB 4BCSYS) CYAPCO TO NRC 04/07/82 l
XI-2 X
HRC to CYAPCo 12/ A/81 DSI/AEB 4B(DOSES)CYAPCO TO NRC 04/07/82 l
XIII-1 X
NRC to CYAPCo 05/07/81 XV-18 X
NRC to CYAPCo 10/01/80 XIII-2 DL/SSPB G
NRC to CYAPCo 05/07/81 XV-19 DSI/RSB 7(Sys)
HRC to CYAPCo 12/02/81 DSI/AEB 4b(Doses)CYAPCo to NRC 09/30/81 XV-1 DSI/RSB 4b CYAPCo to NRC 09/30/81 XV-20 DL/SEPB 7
NRC to CYAPCo 06/09/81 XV-2 DSI/RSB 4b(Sys) CYAPCo to NRC 09/30/81 DSI/AEB Ab(Doses)CYAPCo to NRC 09/30/81 XV-21 X
NRC to CYAPCo 05/07/81 XV-3 DSI/RSB 7
NRC TO CYAPCO 03/17/82 XV-22 X
NRC to CYAPCo 05/07/81 XV-4 DSI/RSB 7
NRC to CYAPCo 12/17/81 XV-23 X
NRC to CYAPCo 05/07/81 XV-5 DSI/RSB 7
NRC TO CYAPC0 04/16/82 XV-24 X
NRC to CYAPCo 05/07/81 XV-6 DSI/RSB 4A 04/28/82 XVI X
NRC to CYAPCo 11/05/80 XV-7 DSI/RSB 4b CYAPCo to NRC 03/01/82 XVII DL 7
NRC to CYAPCo 08/17/78 XV-8 DSI/CPB 7
NRC TO CYAPCO 03/25/82 XV-9 DSI/RSB 7
NRC TO CYAPCO 04/26/82 (2-18)
LACROSSE FACILITY: LACROSSE TOPIC NO.
REVIEW STATUS REMARKS LICENSEE: DAIRLAND POWER 11 '
A.
DE/SAB
- b DPC to NRC 06/23/31 REGION /LOCATIGN: 19 MILES SOUTH OF LACROSSE, WISC.
II-1 B.
DE/SAB 4b DPC to NRC 06/16/81 DOCKET NO.: 05000409 II-1 C.
DE/SAB Gb DPC to NRC 07/15/81 POWER CAPACITY: 0165(THERMAL) 0050(ELECTRTCAL)
II-2 A.
DSI/AEB 7
NRC to DPC 12/15/80 OL NUMBERt DPR-45 N.S.S.S.: AC.
II-2 C.
DSI/AEB 0
, p 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/HGES 2
NRC to DPC 07/10/81 OPERATING REACTORS PROJECT MANAGER: D.
DUDLEY II-3 b.
1.
DE/HGEB 0
HERRING,I.)[
INTEGRATED ASSESSMENT PROJECT MANAGER: K.
II-3 C.
DE/HGEB 4b DPC to NRC 06/26/81 II 4 DE/GSB 7
HRC to DPC 06/08/81 KEY FOR STATUS CODES II-4 A.
DE/GSB 7
NRC to DPC 06/08/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.
DE/GSB 3
DPC to NRC 07/11/79 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 D
1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.
DE/HGEB 4B DPC TO NRC 03/09/82 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC III-1 DL/SEPB 3(Sys)
DPC to NRC 08/06/81 TO UTILITY DL/SEPB 5(ELEC) NRC TO DPC 03/09/82 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 4b DPC to NRC 03/05/82 RECEIVED BY t!RC I
(2-19)
LACROSSE TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR 111-3 A.
DE/SEB 43 DPC TO NRC 03/09/82 111-10 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 DPC TO NRC 01/29/82 III-11 X
NRC to DPC 05/07/81 III-4 A.
DSI/ASB C
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 4B DPC TO NRC 03/05/82 IV-2 DSI/ICSB 7
NRC TO DPC 03/25/82 III-4 D.
DE/SAB Gb DPC to NRC 09/15/81 IV-3 X
NRC to DPC 05/07/81 III-5 A.
DL/SEPB 4B DPC TO NRC 02/24/82 V-1 X
NRC to DPC 11/27/81 III-5 B.
DL/SEPB 4b DPC to NRC 06/29/81 V-2 X
NRC to DPC 10/29/79 III-6 DL/SEPB 3
DPC to NRC 06/12/81 V-3 X
NRC to DPC 05/07/81 III-7 A.
X NRC to DPC 05/07/81 V-4 X
NRC to DPC 05/07/81 III-7 B.
DL/SEPB D
V-5 DL/SEPB 5
NRC TO DPC 03/17/82 III-7 C.
X HRC 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
HRC to DPC 05/07/81 III-8 A.
DSI 5
NRC TO DPC 02/22/82 V-8 X
HRC 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-8 D.
X NRC to DPC 05/)7/81 V-10 B.
DL/SEPB 5
NRC to DPC 12/22/80 III-9 X
NRC to DPC 05/07/81 V-11 A.
DL/SEPB 7
NRC to DPC 02/22/82 III-10 A.
DL/SEPB 7
NRC to DPC 09/22/81 V-11 B.
DL/SEPB 5(Sys)
HRC to DPC 12/22/80 DL/SEPB 7(ELEC) NRC TO DPC 03/04/82 (2-20)
LACROSSE TOPIC NO.
REVIEW STATUS
. REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.
DL/SEPB 7
NRC to DPC 04/30/79 VI-7 D.
DL/SEPB 7
NRC to DPC 08/17/78 j
V-13 X
NRC to DPC 05/07/81 VI-7 E.
X NRC to DPC 05/07/81 i
VI-1 DE/CES 4B DPC to NRC 02/19/82 VI-7 F.
X NRC to DPC 10/29/79 i
VI-2 A.
X NRC to DPC 05/07/81 VI-8 X
NRC to DPC 05/07/81 1
1 VI-2 B.
X NRC to DPC 05/07/81 VI-9 X
NRC to DPC 10/29/79 n
VI-2 C.
X NRC to DPC 10/29/79 VI-10 A.
DL/SEPB
'5 NRC TO DPC 04/14/82 VI-2 D.
DSI/CSB 3
DPC to NRC 04/26/79 VI-10 B.
X NRC to DPC 10/29/79 VI-3 DSI/CSB 3
DPC to NRC 04/26/79 VII-1 A.
DL/SEPB 5
NRC TO DPC 03/09/82 I'
VI-4 DSI/CSB 3(Sys)
DPC to NRC 08/17/81 VII-1 B.
DL/SEPB 7
NRC to CPC 08/17/78
[
DL/SEPB 7(Elec) NRC to DPC 01/05/82 VII-2 DL/SEPB 5
NRC TO DPC 03/11/82 I
VI-5 X
NRC to DPC 05/07/81 i
VII-3 DL/SEPB 5(Sys)
NRC to DPC
- 2/22/80 i
VI-6 DSI/CSB G
NRC to DPC 05/07/81 DL/SEPD 5(ELEC) NRC TO DPC 03/09/82 i
VI-7 A.
1 X
NRC to DPC 10/29/79 VII-4 X
NRC to CPC 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
N.1C to DPC 09/21/81 VI-7 A. 4 X
NRC to DPC 05/07/81 VII-7 X
NRC to DPC 10/29/79 VI-7 B X
NRC to DPC 10/29/79 VIII-1 A.
DSI/PSB G
NRC to DPC 05/07/81 VI-7 C.
DL/SEPB 7
NRC to DPC 03/13/81 VIII-2 DL/SEPB 7-NRC to DPC 12/18/81
?
l VI-7 C.
1.
DL/SEPB 7
NRC to DPC 09/21/81 VIII-3 A.
DL/SEPB 7
HRC to DPC 06/05/79 VI-7 C. 2.
DL/SEPB 7
.NRC to DPC 03/13/81 VIII-3 B.
DL/SEPB 7
NRC to DPC 08/28/81 VI-7 C. 3.
X NRC to DPC 10/29/79 VIII-4 DL/SEPB 7
NRC to DPC 09/09/81 1
l 4
(2-21)
}
4
LACROSSE TCPIC HO.
REVIEW STATUS REMARKS TOPIC N3.
REVIEW STATUS REMARKS J
DIV/CR DIV/BR i
IX-1 CSI/ASB 0
XV-10 X
NRC 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 IX-3 DL/SEPB 4B DPC TO NRC 03/05/82 XV-12 X
NRC to DPC 10/29/79 IX-4 X
NRC to DPC 10/29/79 XV-13 DSI/CPB 0(Doses)
DSI/AEB 7(SYS)
NRC TO DPC 04/05/82 IX-5 DL/SEPB 4B DPC TO NRC 03/15/82 XV-14 DSI/RSB 4b DPC to NRC 08/25/81 IX-6 DE G
NRC to DPC 05/07/81 XV-15 DSI/R$B 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 XI-1 X
NRC to DPC 12/04/81 XV-17 X
NRC to DPC 10/29/79 XI-2 X
NRC to DPC 12/04/81 XV-18 DSI/AEB 0
XIII-1 X
NRC to DPC 05/07/81 XV-19 DSI/AEB 0(Doses)
XIII-2 DL/SSPB 7
NRC to DPC 03/11/81 DSI/RSB 0(Sys)
XV-1 DSI/RSB 4B DPC TO NRC 03/05/82 XV-20 DSI/AEB 4B DPC TO NRC 03/12/82 XV-2 X
NRC to DPC 10/29/79 XV-21 X
NRC 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
XV-4 DSI/RSB 7
NRC to DPC 11/03/81 XV-23 X
NRC to DPC 05/07/81 XV-5 DSI/RSB 4B DPC TO NRC 03/05/82 XV-24 X
HRC to DPC 05/07/81 a
XV-6 X
NRC to DPC 10/29/79 XVI X
NRC to DPC 11/05/80 1
XV-7 DSI/RSB 4B DPC TO NRC 03/11/82 XVII DL 7
NRC to DPC 08/17/78 XV-8 DSI/CPB 7
NRC TO DPC 04/05/82 1
XV-9 DSI/RSD Ab DPC to NRC 08/25/81 1
i (2-22) i
MILLSTONE 1 FACILITY: MILLSTONE 1 TOPIC NO.
REVIEW STATUS REMARKS DIV/3R LICENSEE: NORTHEAST NUCLEAR ENERGY 11-1 A.
DE/SAB 7
NRC to NU 07/31/88 REGION / LOCATION: 5 MILES SOUTH WEST OF NEW LONDON, CCNN.
II-1 B.
DE/SAB 7
HRC to NU 11/27/81 DOCKET NO.
C5000245 II-1 C.
DE/SAB 7
NRC to NU 11/27/81 POWER CAPACITY: 2011(THERMAL) 0660(ELECTRICAL)
CL NUMBER: DPR-21 N.S.S.S.: GE.
~
II-2 C.
DSI/AEB 7
NRC to NU 12/23/81 II-2 D.
X NRC to NU 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL II-3 A.
DE/HGEB 4b NU to NRC 06/25/81 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD II-3 B.
DE/HGEB 4b NU to NRC 06/26/81 OPERATING REACTORS PROJECT MANAGER: J. SHEA II-3 B.
1 DE/HGEB 4b NU to NRC C5/25/81 INTEGRATED ASSESSMENT PROJECT MANAGER: D. PERSINKO \\ ){
II-3 C.
DE/HCEB 4b NU to NRC 04/28/81 II-4 DE/GSB 7
NRC to NU C6/08/81 KEY FOR STATUS CODES II-4 A.
DE/GSB 7
NRC to NU C4/C8/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.
DE/GSB 5
NRC to NU 01/07/82 FROM REVIEW BRANCH X - DELETED II-4 C.
DE/GSB NRC to NU 06/08/81 4b-SAR RECEIVED FROM 0 - TOPIC NOT LICENSEE II-4 D.
DE/HGEB 4b NU to NRC 08/31/81 STARTED 5 - DRAFT SE SENT II-4 E.
X HRC to NU 11/16/79 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.
DE/HGEB 4b NU to NRC 04/28/81 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY HRC III-1 DL/SEPB 5(Elec) HRC TO NU 02/01/82 TO UTILITY DL/SEPB 4a(Sys) 01/29/82 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 4A 04/30/82 RECEIVED BY NRC (2-23)
I.
MILLSTONE 1 1
TOPIC NO.
REVIEW STATUS REMARKS TCPIC NO.
REVIEW STATUS REMARKS j
DIV/3R DIV/BR j
III-j A.
DE/SES 5
hRC to hu 05/11/81 111-13 B.
X NRC to hu 11/16/79 III-3 B.
X NRC to NU 12/26/80 III-10 C.
DL/SEPB 7
NU to'NRC 08/29/79 III-3 C.
DE/NGEB Gb NU to NRC 08/31/81 III-11 X
NRC to NU 05/07/81 III-4 A.
DSI/ASB 4A 05/05/32 III-12 X
NRC to NU 05/07/81 4
III-4 B.
DE/MTEB 4b HU to NRC 08/31/81 IV-1 4 DL/SEPB 7
NU to NRC 02/12/79 III-4 C.
DSI/ASB 4B 04/13/82 IV-2 DSI/ICSB 4b NU to NRC 10/28/81 j
III-4 D.
DE/SAB 7
NRC to NU 11/z7/81 IV-3 DL 7
NRC to NU 02/22/82 III-5 A.
DL/SEPB 4B NU TO NRC 04/13/82 V-1 X
NRC to NU 11/27/81 4
III-5 B.
DL/SEPB 5
NRC TO NU 03/31/82 V-2 X
NRC to NU 11/16/79 j
III-6 DL/SEPB 5
HRC to NU 05/28/81 V-3 X
NRC
- o NU 05/07/81 III-7 A.
X NRC to NU 05/07/"1 V-4 X
NRC to NU 05/07/81 4
l III-7 B.
DL/SEP3 3
NU to NRC 08/29/79 V-5 DL/SEPB 7
NRC to NU 08/28/81 III-7 C.
X NRC to NU 11/16/79 V-6 DL/SEPB 7
NRC to NU 03/05/80 III-7 D.
DE/SEB 7
NU to NRC 02/17/81 V-7 X
HRC to NU 05/07/81 III-8 A.
DSI 7
NRC TO NU 03/03/82 V-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 j
III-8 C.
DL/SEPB 6
NU to NRC 01/31/80 V-10 A.
DL/SEPB 7
NU to NRC 03/05/79
{
III-8 D.
X HRC to NU 05/07/81 V-10 B.
DL/SEPB 7
NU to NRC 07/22/81
}
III-9 X
NRC to NU 05/07/81 V-11 A.
DL/SEPB 7
NRC to NU 07/08/81 1
4 III-10 A.
DL/SEPB 7
NRC to NU 04/07/82 V-11 B.
DL/SEPB 7(Sys)
NU to NRC 07/22/81
}
DL/SEPB 5(Elec) NRC.to NU 02/01/82 I
I i
b (2-24)^
i MILLSTONE 1 i
i TOPIC N0.
REVIEW STATUS REMARKS TCPIC N0.
REVIEW STATUS REMARKS j
DIV/BR DIV/BR V-12 A.
DL/SEPB 7
NRC to hu 12/17/79 VI-7 D.
DL/SFPR 7
NkC to 30 08/17/78 i
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 j
VI-2 A.
X HRC to NU 05/07/81 VI-8 X
NRC to NU 05/07/81
[
j VI-2 B, X
NRC to NU 05/07/81 VI-9 X
NRC to NU 11/16/79 VI-2 C.
X NRC to NU 11/16/79 VI-10 A.
DL/SEPB 7
NRC to NU 10/08/81 VI-2 D.
DSI/CSB 3
NU 54 NRC 06/09/81 VI-10 B.
DL/SEPB 7
NU to NRC 08/05/81 I
VI-3 DSI/CSB 3
NU to NRC 06/09/81 VII-1 A.
DL/SEPB 7
NRC to NU 07/23/81 VI-4 DSI/CSB 6(SYS)
NU TO NRC 04/14/82 DL/SEPB 7(ELEC) HRC TO NU 04/07/82 VII-1 B.
DL/SEPB 7
NRC to NU 08/17/78 2
i VI-5 X
NRC to NU 05/07/81 VII-2 DL/SEPB 7
HU TO NRC 04/05/82 VI-6 DSI/CSB G
NRC to NU 05/07/81 VII-3 DL/SEPB 7(Sys)
NU to NRC 07/22/81 DL/SEPB 5(Elec) HRC to NU 02/01/82
)
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 HL' 10/27/81 VII-6 DL/SEPB 7
NRC to NU 08/26/81
}
VI-7 A. 4 DSI/CPB 7
NRC TO NU 03/11/82 i
VII-7 X
HRC to NU 11/16/79 j
VI-7 B.
X NRC to NU 11/16/79 4
VIII-1 A.
DSI/PS5 G
NRC to NU 05/07/81 VI-7 C.
DL/SEPB 7
NRC to NU 03/29/81 VIII-2 DL/SEPB 7
NRC to NU 09/30/81 VI-7 C.
1.
DL/SEPB 7
NU to NRC 11/02/81 VIII-3 A.
DL/SEPB 7
NRC to NU 08/26/914.
VI-7 C. 2.
DL/SEPB 7
NRC to NU 03/29/81 M
j
.VIII-3 B.
DL/SEPB 7
NRC to NU 07/23/81 i
t VI-7 C. 3.
X HRC to NU 11/16/79 VIII-4 DL/SEPB 7
NRC to NU 07/07/81
)
i i
(2-25) i
m MILLSTONE 1 TCPIC NO.
REVIEW STATUS REMARKS TOPIC N3.
REVIEW STATUS REMARKS DIV/BR OIV/BR IX-1 DSI/ASB 7
hRC TO 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 4A 04/30/82 XV-12 X
NRC to NU 11/16/79 IX-4 X
NRC to NU 11/16/79 XV-13 DSI/CPB 7(Sys)
NU to NRC 09/09/81 DSI/AEB 7(Doses) NRC to NU 11/03/81 IX-5 DL/SEPS 4A 04/28/82 se XV-14 DSI/RSB 7
HRC to NU 09/18/81' IX-6 DE G
NRC to NU 05/07/81 XV-15 DSI/RSB 7
NRC 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 XV-17 X
NRC to NU 11/16/79 XI-2 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/RSS 7(Sys)
NRC to NU 08/26/81 XIII-2 DL/SSPB G
NRC to NU 05/07/81 DSI/AEB 6(Doses) NU to NRC 01/13/82 XV-1 DSI/R$5 7
HRC to NU 12/31/81 XV-20 DSI/AEB 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 CSI/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
NRC to NU 11/16/79 XVI X
NRC to NU 11/15/80 XV-7 DSI/RSB 7
hRC to NU 12/04/81 XVII DL 7
NRC to NU 08/17/78 XV-8 DSI/CPB 7
NRC to NU 08/26/81 XV-9 DSI/RSB 7
NRC to NU 01/12/82 (2-26)
0YSTER CREEK FACILITY: OYSTER CREEK 1 TOPIC NO.
REVIEW STATUS REMARKS DIV/BR LICENSEE: JERSEY CENTRAL POWER 4 LIGHT II-t A.
DE/SAB 7
NRC to JCPL 02/04/82 REGICN/ LOCATION: 9 MILES SOUTH OF TOMS RIVER, NJ.
II-1 B.
DE/SAB 7
NRC to JCPL 02/04/82 DOCAET NO.
05000219 II-1 C.
DE/SAB 7
NRC to JCPL 02/04/82 POWER CAPACITY: 1930(THERMAL) 0650(ELECTRICAL)
II-2 A.
DSI/AEB 7
NRC to JCPL 11/16/81 OL NUMBEO DPR-16 II-2 B.
X NRC to JCPL 05/07/81 N.S.S.S.
GE.
II-2 C.
DSI/AEB 7
NRC TO JCPL 03/16/82 A/E FIRM B&R II-2 D.
X NRC to JCPL 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W.
RUSSELL II-3 A.
DE/HGEB 4B JCPL TO NRC 03/04/82 CPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD II-3 B.
DE/HGEB 4B JCPL TO NRC 03/04/82 OPERATING PcACTORS PROJECT MANAGER:
J. LOMBARDO II-3 B.
1 DE/HGEB 4B JCPL TO NRC 03/04/8?
k FELL)),Q INTEGRATED ASSESSMENT PROJECT MANAGER: R.
II-3 C.
DE/HGEB 4B JCPL TO NRC 03/04/82 II-4 DE/GSB 7
NRC to JCPL 08/03/S1 KEY FOR STATUS CODES II-4 A.
DE/GSB 7
NRC to JCPL 06/08/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.
DE/GSB 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 Ab JCPL to NRC 12/15/81 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 4b JCPL to NRC 11/04/81 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC III-1 DL/SEPB SCSYS)
NRC TO JCPL 04/12/82 TO UTILITY DL/SEPS 7(Elec) HRC to JCPL 07/09/81 7 - TOPIC COMPLETE 3 - GUESTION RESPONSE III-2 DL/SEPB 2
NRC TO JCPL 11/18/81 RECEIVED BY hRC 1
(2-27)
0YSTER CREEK TOPIC NO.
REVIEW STATUS REMARKS TCPIC NO.
REVIEW STATUS REMARKS DIV'PR DIV/BR III-3 A.
DE/5EB 4B JCPL TO NRC 03/04/82 III-10 B.
X NRC 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/HGEB 4b JCPL to NRC 11/04/81 III-11 X
NRC to JCPL 05/07/81 III-4 A.
DSI/ASB 0
III-12 X
NRC to JCPL 05/P7/81 III-4 B.
DE/MTEB Gb JCPL to NRC 12/07/81 IV-1 A.
DL/SEPB 7
NRC to JCPL 05/30/79 III-4 C.
DSI/ASB 2
NRC to JCPL 01/19/81 IV-2 DSI/ICSB 2
NRC to JCPL 12/15/80 III-4 D.
DE/SAB 0
IV-3 X
NRC to JCPL 05/07/81 III-5 A.
DL/SEPB 6
JCPL to NRC 11/12/81 V-1 X
NRC to JCPL 11/27/81 III-5 B.
DL/SEPB 6
JCPL to NRC 10/06/81 V-2 X
NRC to JCPL 11/16/79 III-6 DL/SEPB 6
JCPL to NRC 06/15/81 V-3 X
NRC to JCPL 05/07/81 III-7 A.
X NRC to JCPL 05/07/81 V-4 X
NRC to JCPL 05/07/81 III-7 B.
DL/SEPB 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 NRC to JCPL 05/07/81 V-10 B.
DL/SEPB 7
NRC to JCPL 09/25/80 III-9 X
NRC to JCPL 05/07/81 V-11 A.
DL/CEPB 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)
NRC to JCPL 09/25/80 DL/SEPB 7(Elec) NRC to JCPL 07/09/81 (2-28)
OYSTER CREEK TOPIC HO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.
DL/SEPB 5
JCPL to NRC 03/16/81 VI-7 D.
DL/SEPS 7
hRC to JCPL 08/17/78 V-13 X
NRC to JCPL 05/07/81 VI-7 E.
X NRC to JCPL 05/07/81 VI-1 DE/CEB 2
NRC to JCPL 06/06/79 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 NRC to JCPL 05/07/81 VI-9 X
HRC to JCPL 11/16/79 VI-2 C.
X NRC to JCPL 11/16/79 VI-13 A.
DL/SEPB 7
NRC to JCPL 08/18/81 VI-2 D.
DSI/CSB 7
NRC TO JCPL 04/30/82 VI-10 B.
X HRC 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 6(SYS)
JCPL TO NRC 03/10/82 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/SEPB 6
JCPL te NRC 08/17/81 VI-5 X
NRC to JCPL 05/07/81 VII-3 DL/SEPB 7(Sys)
NRC to JCPL 09/25/80 VI-6 DSI/ CSS 5
NRC TO JCPL 03/04/82 DL/SEPB 7(Elec) NRC to JCPL 07/09/81 VI-7 A.
1.
X HRC to JCPL 11/16/79 VII-4 X
NRC to JCPL 05/07/81 VI-7 A. 2.
X NRC to JCPL 05/07/81 VII-5 X
NRC to JCPL 05/07/81 VI-7 A.
3.
DL/SEPB 7
NRC to JCPL 07/30/81 VII-6 DL/SEPB 7
HRC to JCPL 08/29/81 VI-7 A. 4.
DSI/RSB G
NRC to JCPL 05/07/81 VII-7 X
NRC to JCPL 11/16/79 VI-7 B.
X HRC to JCPL 11/16/79 VIII-1 A.
DSI/PSB 7
NRC to JCPL 03/03/82 VI-7 C.
DL/SEPB 7
NRC to JCPL 03/13/81 VIII-2 DL/SEPB 7
NRC to JCPL 06/29/81 VI-7 C.
1 DL/SEPB 7
NRC to JCPL 06/29/81 VIII-3 A.
DL/SEPB 7
NRC to JCPL 06/29/81 VI-7.C. 2.
DL/SEPB 7
NRC to JCPL 03/13/81 VIII-3 B.
DL/SEPB 7
HRC to JCPL 06/29/81 VI-7 C. 3.
X NRC to JCPL 11/16/79 VIII-4 DL/SEPB 5
NRC to JCPL 03/26/81 (2-29)
0YSTER CREEK TOPIC NO.
REVIEW STATUS REMARKS TCPIC N0.
REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 4B JCPL TO NRC 03/22/82M XV-10 X
NRC to JCPL 11/16/79 IX-2 X
NRC to JCPL 05/07/81 XV-11 DSI/CPB 5
NRC to JCPL 04/09/81 IX-3 DSI/ASB 7
NRC to JCPL 11/13/81 XV-12 X
NRC to JCPL 11/16/79 IX-4 X
NRC to JCPL 05/07/81 XV-13 DSI/AEB 4a(Doses) 07/01/81 DSI/CPB 5fSys)
NRC to JCPL 04/09/81 XV-14 DSI/RSB 7
NRC to JCPL 07/16/81 IX-6 DE G
NRC to JCPL 05/07/81 XV-15 DSI/RSB 7
NRC to JCPL 12/04/81 X
X NRC to JCPL 05/07/81 XV-16 DSI/AEB 4b JCPL to NRC 11/04/81 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 4a 07/01/81 XIII-1 X
NRC to JCPL 05/07/81 XV-19 DSI/AEB 0(Doses)
XIII-2 DL/SSPB 7
NRC to JCPL 09/25/80 DSI/RSB 7(Sys)
NRC to JCPL 09/04/81 XV-1 DSI/RSB 7
HRC to JCPL 12/07/81 XV-20 DSI/AEB 0
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/R$B 7
NRC to JCPL 12/04/81 XVII DL 7
NRC to JCPL 08/17/78 XV-8 DSI/CPB 5
NRC to JCPL 03/31/81 XV-9 DSI/RSB 7
NRC to JCPL 01/07/82 (2-30)
PALISADES FACILITY: PALISADES TOPIC NO.
REVIEW STATUS REMARKS DIV/BR LICENSEE: CONSUMERS POWER 11-1 A.
DL/SEPB 7
CPCo to NRC 12/28/79 REGION /LOCATIGd: 5 MILES SOUTH OF SOUTH HAVEN, MI.
II-1 B.
DL/SEPB 7
CPCo to NRC 12/28/79 DOCKET NO: 05000255 II-1 C.
DL/SEPB 7
CPCo to NRC 05/13/81 PG'4ER CAPACITY: 2530(THERMAL) 0805(ELECTRICAL)
II-2 A.
DSI/AEB 7
NRC to CPCo 06/30/81 OL NUMBER: DPR-20 II-2 B.
X NRC to CPCo 05/07/81 H.S.S.S.: C-E II-2 C.
DSI/AEB 7
NRC to CPCo 04/23/81 A/E FIRMS BECH.
II-2 D.
X NRC to CPCo 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL II-3 A.
DE/HGEB 7
NRC to CPCo 02/19/82 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD II-3 B.
DE/HGEB 7
NRC to CPCo 02/19/82 OPERATING REACTORS PROJECT MANAGER: T. WAMBACH II-3 B.
1.
DE/HGEB 7
NRC to CPCo 02/19/82 INTEGRATED ASSESSMENT PROJECT MANAGER: T. MICHAELS ;(;n II-3 C.
DE/HGEB 7
NRC to CPCo 02/19/82 II-4 DE/GSB 7
CPCo to NRC 07/22/81 KEY FOR STATUS CODES II-4 A.
DE/GSB 7
NRC to CPCo 06/08/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.
DE/GSB 7
CPCo to NRC 07/22/81 FROM REVIEW BRANCH X - DELETED II-5 C.
DE/GSB 7
NRO to CPCo 06/08/81 4b-SAR RECEIVED FROM 0 - TOPIC HOT LICENSEE II-4 D.
DE/HGEB 7
CPCo to NRC 06/01/81 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
CPCo to NRC 06/01/81 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY HRC III-1 DL/SEPB 7(Elec) NRC to CPCo 11/12/80 TO UTILITY DL/SEPB 7(Sys)
NRC to CPCo 02/08/82 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE RECEIVED BY NRC (2-31)
PALISADES l
TOPIC NO.
REVIEW STATUS MEMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR III-2 DL/SEP8 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 CPCo 08/26/81 III-10 C.
X NRC to CPCo 11/16/79 III-3 B.
X NRC to CPCo 12/26/80 III-11 X
NRC to CPCo 05/07/81 1
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
NRC to CPCo 02/08/82 IV-2 DSI/ICSB 7
HRC to CPCo 02/08/82 III-4 C.
DSI/ASB 7
NRC to CPCo 09/21/81 IV-3 X
NRC to CPCo 05/07/81 III-4 D.
DE/SAB 7
CPCo to NRC 08/03/81 V-1 X
NRC to CPCo 11/27/81 III-5 A.
DL/SEPB 7
HRC to CPCo 02/08/82 V-2 X
NRC to CPCo 11/16/79 III-5 B.
DL/SEPB 7
NRC to CPCo 02/19/82 V-3 X
NRC to CPCo 05/07/81 1
4 III-6 DL/SEPB 7
CPCo to NRC 12/16/81 V-4 X
NRC to CPCo 05/07/81 III-7 A.
DL/SEPB 7
HRC to w.'Co 02/10/82 V-5 DL/SEPB 7
HRC to CPCo 02/04/82 III-7 B.
DL/SEPB 7
NRC to CPCo 02/12/82 V-6 DL/SEPB 7
NRC to CPCo 03/05/80 III-7 C.
DE/SEB 7
NRC to CPCo 10/19/81 V-7 DSI/ASB 7
NRC to CPCo 11/16/81 III-7 D.
DE/SEB 7
CPCo to NRC 08/17/81 V-8 X
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 4
III-8 D.
X NRC to CPCo 05/07/81 V-11 A.
DL/SEPB 7
NRC to CPCo 11/09/81 III-9 X
NRC to CPCo 05/07/81 V-11 B.
DL/SEPB 7(Sys)
NRC 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 i
l l
i
't j
(2-32) l
PAUSADES TDPIC NO.
REVIEW STATUS REMARKS TCPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.
X hRC to-CPCo 11/16/79 VI-7 D.
DL/SEPB
?
NRC to CPCo 08/17/78 1
V-13 X
NRC to CPCo 05/07/81 VI-7 E.
X NRC to CPCo 05/07/81 I
j VI-1 DE/CEB 7
NRC to CPCo 08/03/81 VI-7 F.
DL/SEPB 7
NRC to CPCo 10/29/81 i
- VI-2 A.
X NRC to CPCo 05/07/81 VI-8 X
NRC to CPCo 05/07/81 VI-2 8.
X NRC to CPCo 05/07/81 VI-9 X
NRC to CPCo 11/16/79 j
VI-2 C.
X NRC to CPCo 11/16/79 VI-10 A.
DL/SEPB 7
NRC to CPCo 10/16/81 VI-2 D.
DSI/CSB 7
NRC 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/SEPB 7
NRC to CPCo 08/17/78 DCI/CSB 7(Sys)
NRC to CPCo 02/08/82 VII-2 DL/SEPB 7
NRC to CPCo 05/19/81 VI-5 X
NRC to CPCo 05/07/81 4
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
NRC to CPCo 05/07/81 VI-7 A. 3.
DL/SEP3 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
NRC to CPCo 11/16/79 VI-7 8.
DL/SEPB 7(Elec) HRC to CPCo 05/19/81 VIII-t A.
DSI/PSB 7
NRC to CPCo 12/22/81 DSI/RSB 7(Sys)
HRC to CPCo 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 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 CPCo 02/20/81 1
VI-7 C. 3.
X CPCo to NRC 12/12/79 I
a 1
I (2-33) i
1 PALISADES TOPIC NO.
REVIEW STATUS REMARKS TOPIC HO.
REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 7
hRC to CPCo 02/08/82 XV-10 DL/SEPB 7
NRC to CPCo 11/03/81 IX-2 X
HRC to CPCo 05/07/81 XV-11 X
NRC to CPCo 10/01/80 IX-3 DL/SEPB 7
NRC to CPCo 02/22/82 XV-12 DL/SEPB 7(Doses) NRC to CPCo 12/04/81 DL/SEPB 7(Sys)
HRC to CPCo 11/03/81 IX-4 DSI/R$B 7
HRC to CPCo 02/08/82 IX-5 DL/SEPB 7
HRC to CPCo 02/11/82 XV-14 DL/SEPB 7
HRC to CPCo 11/03/81 IX-6 DE 5
HRC TO CPC0 04/07/82 XV-15 DL/SEPB 7
HRC to CPCo 11/03/81 X
X NRC to CPCo 05/07/81 XV-16 DL/SEPB 7
HRC to CPCo 11/03/81 XI-1 X
NRC to CPCo 12/04/81 XV-17 DL/SEPB 7(Doses) HRQ to CPCo 11/03/81 XI-2 X
NRC to CPCo 12/04/81 DL/SEPB 7(Sys)
NRC to CPCo 11/03/81 XIII-1 X
HRC to CPCo 05/07/81 XV-18 X
NRC to CPCo 10/01/80 XIII-2 DL/SSPB 7
HRC to CPCo 10/01/80 XV-19 DL/SEPB 7(Doses) NRC to CPCo 11/03/81 Ot/SEPB 7(Sys)
HRC to CPCo 11/03/81 XV-1 DL/SEPB 7
NRC to CPCo 11/03/81 e
i XV-20 DL/SEPB 7
HRC to CPCo 11/03/81 XV-2 DL/SEPB 7(Doses) HRC to CPCo 11/03/81 DL/SEPB 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
HRC 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
NRC to CPCo 11/03/81 XV-24 X
NRC to CPCo 05/07/81 XV-6 DL/SEPB 7
HRC to CPCo 11/03/81 XVI X
NRC to CPCo 11/05/80 XV-7 DL/SEPB 7
NRC to CPCo 11/03/81 XVII DL 7
NRC,to CPCo 08/17/78 XV-8 DL/SEPB 7
NRC to CPCo 11/03/81 XV-9 DL/SEPB 7
HRC to CPCo 11/03/81 a
1 (2-34)
SAN ON0FRE FACILITY: SAN ONOFRE 1 TOPIC HO.
REVIEW STATUS REMARKS DIV/BR LICENSEE: SOUTHERN CALIFORNIA EDISON II-1 A.
DL/SEPB 7
NRC to SCE 11/07/79 REGION / LOCATION: 5 MILES SOUTH OF SAN CLEMENTE, CA.
II-l B.
OL/SEPB 7
NRC 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 NUMBER: DPR-13 II-2 B.
X NRC to SCE 05/07/81 H.S.S.S.: WEST.
II-2 C.
DSI/AEB 7
NRC to SCE 11/18/81 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
SCE 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-3 B.
1.
DE/HGEB 3
SCE TO NRC 04/12/82 INTEGRATED ASSESSMENT PROJECT MANAGER: E.MCKENHA[Jr.
II-3 C.
DE/HGEB 2
NRC to SCE 01/07/82 II-4 DE/GSB 5
HRC to SCE 03/15/81 KEY FOR STATUS CODES II-4 A.
DE/GSB 5
NUREG-0712 12/80 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.
DE/GSB 5
HUREG-0712 12/80 FROM REVIEW BRANCH X - DELETED II-4 C.
DE/GSB 5
NUREG-0712 12/80 Ab-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 NRC 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 3(Sys)
SCE to NRC 04/19/82 TO UTILITY DL/SEPB 7(Elec) Part of VII-3 11/18/81 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 3
SCE to NRC 11/20/81 RECEIVED BY NRC l
I (2-35)
. ~
.-~
SAN ONOFRE I
TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR III-3 A.
DE/SES 3
SCE to ttRC 09/05/80 III-10 8.
DL/SEPB 7
NRC to SCE 11/08/79 III-3 B.
X NRC to SCE 11/16/79 III-10 C.
X NRC to SCE 11/16/79
)
III-3 C.
DE/HGEB 7
NRC to SCE 11/21/81 III-11 X
NRC to SCE 35/07/81 III-4 A.
DSI/ASB 3
SCE to NRC 08/14/79 III-12 X
NRC to SCE 05/07/81 III-4 B.
DE/MTEB G
NRC to SCE 05/07/81 I V - 't 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 Ab SCE to NRC 12/23/81 IV-3 X
NRC to SCE 05/07/81 III-5 A.
DL/SEPB 0
V-1 X
NRC to SCE 11/27/81 III-5 B.
DL/SEPB 0
v-2 X
. 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 NRC to SCE 05/37/81 V-4 X
HRC to SCE 05/07/81 I
III-7 B.
DL/SEPB 3
SCE to NRC 11/20/81 V-5 DL/SEPB 5
NRC to SCE 06/03/81 1
'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/SFS
~7 NRC TO SCE 04/23/82 V-7 DSI/ASB 7
NRC to SCE 12/04/81 III-C. A.
DSI 7
NRC-to SCE 12/21/81 V-8 X
NRC to SCE 05/07/81 III-8 D.
X HRC to SCE 10/01/80 V-9 X
HRC to SCE 11/16/79
'III-8 C.
DL/SEPB 7
NRC to SCE 01/29/80 V-10 A.
DL/SEPB 7
NRC to SCE 01/07/81 III-8 D.
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 1
I
)
i (2-36)
I6
SAN ON0FRE TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.
X NRC to SCE 11/16/79 VI-7 D.
DL/SLPB 7
hkC to SCE 08/17/78 V-13 X
HRC to SCE 05/07/81 VI-7 E.
X NRC to SCE 05/07/81 VI-1 4b SCE to NRC 01/28/82 VI-7 F.
X NRC to SCE 11/16/79 VI-2 A.
X NRC to SCE 05/07/81 VI-8 X
HRC to SCE 05/07/81 VI-2 B.
X HRC to SCE 05/07/81 VI-9 X
NRC to SCE 11/16/79 VI-2 C.
X NRC to SCE 11/16/79 VI-10 A.
DL/SEPB 7
NRC to SCE 08/23/81 VI-2 D.
DSI/CSB 5
NRC to SCE 01/12/82 VI-10 B.
DL/SEPB 7
NRC to SCE 11/15/79 VI-3 DSI/CSB 5
NRC to SCE 01/12/82 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 09/03/88 VII-1 S.
DL/SEPB 7
NRC to SCE 08/17/78 VI-5 X
HRC to SCE 05/07/81 VII-2 DL/SEPB 7
NRC to SCE 11/17/81 VI-6 DSI/CSB G
NRC to SCE 05/07/81 VII-3 DL/SEPB 6(SYS)
SCE TO HRC 04/26/82 DL/SEPB 7(Elec) NRC to SCE 11/18/81 VI-7 A.
1.
DL/SEPB 7
FRC to SCE 02/20/81 VII-4 X
NRC to SCE 05/07/81 VI-7 A. 2.
X HRC to SCE 05/07/81 VII-5 X
NRC to SCE 05/07/81 VI-7 A.
3.
DL/SEPB 7
NRC to SCE 11/18/81 VII-6 DL/SEPB 7
NRC to SCE 08/28/81 VI-7 A. 4.
X HRC to SCE 05/07/81 VII-7 X
HRC to SCE 11/16/79 VI-7.B.
DSI/RSB 6(SYS)
SCE TO HRC 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
NRC to SCE 08/03/81 VIII-3 A.
DL/SEPB 7
NRC to SCE 11/07/79 VI-7 C. 2.
DL/SEPB 7
HRC to SCE 06/01/81 VIII-3 B.
DL/SEPB 7
NRC to SCE 07/24/81 VI-7 C.
3.
X NRC to SCE 11/16/79 VIII-4 DL/SEPB 7
HRC to SCE 12/31/81 (2-37)
i SAN ON0FRE TCPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS R EMAR KS DIV/LR DIV/BR IX-1 DSI/ASB 3
SCE to NRC 10/05/79 XV-10 DSI/RSB 7
hRC TO SCE 04/20/82 IX-2 X
HRC to SCE 05/07/81 XV-11 X
HRC to SCE 10/01/80 IX-3 DL/SEPB 4b SCE to NRC 11/02/81 XV-12 DSI/RSB 7(Sys)
HRC to SCE 04/05/82 DL/SEPB 7(Doses) HRC to SCE 01/29/80 IX-4 DSI/RSB 7
NRC to SCE 07/16/81 XV-13 X
NRC to SCE 11/16/79 IX-5 DL/SEPB 4b SCE to NRC 12/16/81 XV-14 DSI/RSB 7
HRC 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
HRC 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) NRC to SCE 01/29/80 XIII-1 X
NRC to SCE 05/07/81 XV-18 X
NRC to SCE 10/01/80 XIII-2 DL/SSPB 7
NRC to SCE 01/22/81 XV-19 DSI/RSB 7(Sys)
SCE TO NRC 03/12/82 DL/SEPB 7(Doses) HRC to SCE 01/29/80 l
XV-1 DSI/RSB 6
SCE TO NRC 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) NRC to SCE 01/29/80 XV-21 X
NRC to SCE 05/07/B1 XV-3 DSI/RSB 6
SCE TO HRC 03/12/82 XV-22 X
HRC to SCE 05/07/81 XV-4 DSI/RSB 7
HRC to SCE 04/05/82 XV-23 X
HRC to SCE 05/07/81 XV-5 CSI/RSB 7
NRC to SCE 02/01/82 XV-24 X
HRC to SCE 05/07/81 XV-6 DSI/RSB 7
NRC TO SCE 03/03/82 XVI X
HRC to SCE 11/05/80 XV-7 DSI/R$B 4b SCE to NRC 07/01/81 XVII DL 7
HRC to SCE 11/20/79 XV-8 DSI/CPB 7
SCE TO NRC 03/12/82 XV-9 DSI/RSB 7
HRC to SCE 02/24/82 (2-38)
YANKEE FACILITY: YANKEE NUCLEAR POWER STATION TOPIC NO.
REVIEW STATUS REMARKS DIV/BR LICENSEE: YANKEE ATOMIC ELECTRIC II-1 A.
DE/SAB 48 YAEC 10 NRC 03/18/82 REGION / LOCATION: 25 MILES NORTH EAST OF PITTSFIELD, MASS.
II-1 B.
DE/SAB Gb YAEC to NRC 05/31/81 DOCKET NO.: 05000029 II-1 C.
DE/SAB 4b YEAC to NRC 04/09/81 POWER CAPACITY: 600(THERMAL) 165(ELECTRICAL)
II-2 A.
DSI/AEB 7
HRC to YAEC 08/03/81 OL NUMBER: DPR-3
?I-2 B.
X HRC to YAEC 05/07/81 N.S.S.S.
WEST.
1 C.
DSI/AEB 7
NRC to YAEC 09/04/81 A/E FIRMS $1W II ~ 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. CARUS 0 II-3 B.
1.
DE/HGEB 5
NRC to YAEC 02/09/81 INTEGRATED ASSESSMENT PROJECT MANAGER: M. BOYLE,tr II-3 C.
DE/HGEB 3
Mtg Summary 11/27/81 II-4 DE/GSB 7
NRC to YAEC 06/08/81 KEY FOR STATUS CODES II-4 A.
DE/GSB 7
HRC to YAEC 06/08/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.
DE/GSB 3
YAEC to NRC 06/26/81 FROM REVIEW BRANCH X - DELETED II-4 C.
DE/GSB 7
NRC to YAEC 06/08/81 4b-SAR RECEIVED FROM D - TOPIC HOT LICENSEE II-4 D.
DE/HGEB 4B YAEC TO NRC 02/26/82 STARTED 5 - DRAFT SE SENT II-4 E.
DE/HGEB 3
Mtg Summary 12/17/81 1 - QUESTIONS RECEIVED TO UTILITY 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 3(Sys)
YAEC to NRC 04/02/82 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 4B YAEC TO NRC 03/18/82 RECEIVED BY HRC (2-39)
YANKEE TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/3R III-3 A.
DE/SEB
- B YAEC 10 NRC 03/15/82 III-10 B.
X NRC to YAEC 11/16/79 III-3 B.
X NRC to YAEC 12/26/30 III-10 C.
X HRC to YAEC 11/16/79 III-3 C.
DE/NGEB 4b YAEC to NRC 01/04/82 III-11 X
NRC to YAEC 05/07/81 III-4 A.
DSI/ASB 4B YAEC TO NRC 03/18/82 III-12 X
NRC to YAEC 05/07/81 III-4 B.
DE/MTEB 7
NRC to YAEC 02/08/82 IV-1 A.
DL/SEPB 7
hRC to YAEC 04/18/79 III-4 C.
DSI/ASB 4B YAEC TO NRC 03/18/82 IV-2 DSI/ICSS 7
NRC to YAEC 12/23/81 III-4 D.
DE/SAB 4b YAEC to NRC 06/30/81 IV-3 X
HRC to YAEC 05/07/81 III-5 A.
DL/SEPB 4B YAEC TO NRC 03/18/82 V-1 X
NRC to YAEC 11/27/81 III-5 B.
DL/SEPB Ab YAEC to NRC 01/21/82 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 5
NRC to YAEC 03/11/82 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
NRC to YAEC 12/29/81 V-8 X
NRC to YAEC 05/07/81 III-8 B.
~ X NRC to YAEC 10/01/80 V-?
X NRC to YAEC 11/16/79 III-8 C.
DL/SEPB
.7 NRC to YAEC 11/15/79 V-10 A.
DL/SEPB 7
NRC to YAEC 11/05/79.
III-8 D.
X NRC to YAEC 05/07/81 V-10 B.
DL/SEPB 7
NRC to YAEC 02/01/82 III-9 X
NRC to YAEC 05/07/81 V-11 A.
DL/SEPB 7
NRC to YAEC 02/01/82 III-10 A.
DL/SEPB 7
HRC te YAEC 09/22/81 V-11 B.
P./SEPS 7(Sys)
NRC to YAEC 02/01/82
'dL /S EP B 7(Elec) NRC to YAEC 02/01/82 (2-40)
YANKEE TOPIC HO.
REVIEW STATUS R EMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR CIV/BR V-12 A.
X NRC to YAEO 11/16/79 VI-7 D.
DL/SEPS 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 V.I - 1 DE/CEB 3
YEAC to NRC 06/26/79 VI-7 F.
DL/SEPB 7
NRC to YAEC 08/28/81 VI-2 A.
X NRC to YAEC 05/07/81 VI-8 X
NRC to YAEC 05/37/81 VI-2 B.
X HRC to YAEC 05/07/81 VI-9 X
NRC to YAEC 11/16/79 VI-2 C.
X HRC to YAEC 11/16/79 VI-10 A.
DL/SEPB 7
NRC to YAEC 02/01/82 VI-2 D.
DSI/CSB 0
VI-10 B.
X NRC to YAEC 11/16/79 VI-3 DSI/CSB 0
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 "4FC 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
NRC 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
NPC to YAEC 08/28/81 VI-7 A. 4.
X HRC to YAEC 05/07/81 VII-7 X
NRC to YAEC 11/16/79 VI-7 B."
DSI/RSB 7(Elec) NRC to YAEC 06/04/81 VIII-1 A.
DSI/PSB G
HRC to YAEC 05/07/81 0(Sys) 4 VI-7 C.
DL/SEPB 7
NRC to YAEC 03/13/81 VIII-2 DL/SEPB 7
NRC to YAEC 09/03/81 VI-7 C.
1.
DL/SEPB 7
-NRC to YAEC 09/14/81 VIII-3 A.
DL/SEPB 7
NRC to YAEC 11/07/79 VI-7 C. 2.
DL/SEPB 7
NRC to YAEC 03/13/81 VIII-3 B.
DL/SEPB 7
NRC to YAEC 08/28/81 VI-7 C. 3.
DL/SEPB 7
NRC to YAEC 07/24/80 VIII-4 DL/SEPB 6
YAEC TO NRC 10/15/81 (2-41)
YANKEE TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 4b YAEC to NRC 11/1d/81 XV-10 DSI/RSB 7
NRC TO YAEC 04/26/82 IX-2 X
NRC to YAEC 05/07/81 XV-11 X
HRC to YAEC 10/01/80 IX-3 DL/SEPB Gb YAEC to NRC 09/17/b1 XV-12 DSI/CPB 7($YS)
NRC TO YAEC 04/16/82 DSI/AEB 7(Doses) HRC to YAEC 12/29/81 IX-4 DSI/RSB 4b YAEC to NRC 08/31/81 l
XV-13 X
HRC to YAEC 11/16/79 IX-5 DL/SEPB 4A 04/28/82 XV-14 DSI/RSB 4b YAEC to NRC 06/30/81 IX-6 DE G
NRC to.YAEC 05/07/81 XV-15 DSI/RSB 4A 04/28/82 X
X HRC to YAEC 05/07/81 XV-16 DSI/AES 4b YAEC to NRC 02/01/82 XI-1 X
HRC to YAEC 12/04/81 XV-17 DSI/RSB 0(Sys)
XI-2 X
NRC to YAEC 12/04/81 DSI/AEB 5(DOSES) NRC TO YAEC 03/30/82 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 4b(SYS) YAEC to NRC 11/18/81 DSI/AEB
'b(Doses)YAEC to NRC 01/04/82 XV-1 DSI/P.SB 4b YAEC to NRC 02/01/82 XV-20 DL/SFPB 7
NRC to YAEC 09/06/81 XV-2 DSI/RSB Gb(Sys) YAEC to NRC 06/30/81 DSI/AEB 0(Doses)
XV-21 X
NRC to YAEC 05/07/81 XV-3 DSI/RSS 7
NRC to YAEC 01/25/82 XV-22 X
NRC to YAEC 05/07/81 XV-4 DSI/RSB 4b YAEC to NRC 01/04/82 XV-23 X
NRC to YAEC 05/07/81 XV-5 DSI/R$B 7
HRC to YAEC 02/10/82 XV-24 X
NRC to YAEC 05/07/81 XV-6 DSI/RSB Gb YAEC to NRC 02/01/82 XVI X
NRC to YAEC 11/05/80 XV-7 DSI/RSB 4b YAEC to NRC 06/30/81 XVII DL 7
NRC to YAEC 11/20/79 l
XV-8 DSI/CP8 7
NRC TO YAEC 03/05/82 l
XV-9 DSI/RSB 4b YAEC to NRC 06/30/81 L
l l
l 1
(2-42)
c O
h-t)
LaJ M
}
9
.s PALISADES DL PALISADES Eli SAR l/
SER 2/
SAR 1/
SER 2/
TOPIC NO.' TITLE SCHEDULE SCHEDULE TOPIC HQ. TITLE SCHEDULE SCHEDULE 111-1 Classification of NONE 12/15/81C III-8.A Loose Parts Monitoring and NONE tt/03/8tc (SYS)
Structures Components and Core Barrel Vibration i
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 *oolant Pump NONE 11/16/8tc III-5.B Pipo Break Outside 08/25/81R 12/23/81C Overspet (NRR B-63)
Containment VI-6 Containne.. Leak Testing NONE 08/05/8tc III-7.A Inservice Ir. spec t i on.
NONE 08/25/81C (MP A-04)
Including Prestressed Concrete Containments with VIII-1.A Potential Equipment NONE 12/22/81C Either Grouted or Ungrouted Failures Associated with a Tendons Degraded Grid Voltage (MP B-23) i III-7.B Design Codes, Design NONE 11/16/81C Criteria, Load IX-1 Fuel Storage NONE 12/31/81C Combinations, and Reactor Cavity Design Criteria IX-4 Boron Addition System 10/09/81R 11/18/81C IX-6 Fire Protection (MP B-41)
NONE 03/05/82C El SAR 1/
SER 2/
XI-l Appendix I(MP A-02)
NONE DELETED TOPIC NO. TITLE SCHEDULE-SCHEDULE XI-2 Radiological (Effluent NONE DELETED III-3.C Inservice Inspection of 12/21/81R -02/12/82C and Process) Monitoring Water Control Structures Systems (NRR B-67) 4 III-4.B Turbine Missiles (MP B-46)
NONE 12/02/81C t/ SAR Licensee Safety Analysis Report-Scheduled or Ac.ual III-7.D Containment Structural NONE 08/17/81C (Actual (status 4b) when date is followed by R)
Integrity Tests 2/ SER : Staff Safety Evaluation Report -Scheduled or Actual V-l Compliance with Codes and NONE DELETED (Actual (status 4a. 5, 7 ) when date is followed by C)
Standards (10 CFR 50.55a)
(MP A-01 A-14) 1/ Desiginated number of days fron receipt of Ilconsee SAR (Notes if Licensee SAR is reconved then date is from receipt of additional information requested) 4 4
(3-2)
LICENSEE SUBMITTALS PALISADES SLIBi!TTALS 43 TARGET 35 ACTUAL 25 23 15 I'
ALL SUBMITTALS RECEIVED
/
n e
e i
e i
e g
M Jll ALE SEP OCT NOV DEC JAN FE')
MAR APR MAY JtN JLL/DEC MONTHS Target 1
2 3
0 0
0 0
0 0
0 0
0 0
PER MONTH MW 1
2 0
1 1
1 Target 1
3 6
6 6
6 6
6 6
6 6
6 6
CUMULATIVE MW 1
3 3
4 5
6 (3-3)
GINNA p1 G1hNA M
SAR 1/
SER 2/
SAR J/
SER 2/
TOPIC HO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE III-l Classification of Struct-NDHE 12/29/81C III-4.C Internally Generated 01/11/82R 02/02/82C (SYS) uros Components and Systems Missiles (Seismic and Quality)
III-8.A Loose Parts Monitoring and NONE 11/03/81C III-2 Wind and Tornado Loadings NDHE 09/23/81C Core Barrel Vibration Monitoring (NRR B-60,C-12)
III-7.A Inservice Inspection, HONE 12/28/81C Including Prestressed V-7 Reactor Coolant Pump NONE 11/05/81C Concreto Containments with Overspeed(NRR B-68) t Either Grouted or Ungrounded Tendons VI-2.D Mass and Energy Release for NOME 09/25/81C t
Possible Pipe Break Insida III-7.B Design Corks, Design NDHE 12/31/81C Containment Criteria, Lead Corbinations, and Reactor VI-3 Containment Pressure and NONE 09/25/81C Cavit, Design Criteria Heat Removal Capability VI-7.C.1 Appendix K - Electrical NOME 11/18/81C VI-7.B ESF Switchover from NONE 12/18/81C Instrumentation and Control (SYS)
Injection to Recirculation i
(EIC) Re reviews Mode (Automatic ECCS Realignment)
IX-5 Ventilation Systems lNONE 11/02/81C I
IX-1 Fuel Storage NONE 11/24/81C 1
21 IX-6 Fire Protection (MP B-41)
NONE 02/24/82C SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE XI-l Appendix ICMP A-02)
NDHE DELETED 11-1.B Pcpulation Distribution 04/15/81R 07/21/81C XI-2 Radiological (Effluent NONE DELETED and Process) Monitoring II-1.C Potential Hazards or 04/15/81R 07/01/81C Systems (HRR B-67)
Changes in Potential Hazards Due to XV-9 Startup or an Inactive Loop NONE 10/16/81C Transportation, or Recirculation Loop at an Institutional Industrial, Incorrect Temperature, and and Military Facilities Flow Controller Malfunction Causing an Increase in BWR II-4.D Stability of Slopes 06/30/81R 02/01/82C Core Flow Rate II-4.F Settlement of Founc'ations 06/30/81R 01/29/82C XV-19 Loss-of-Coolant Accidents NONE 09/29/81C and Buried Equipment (DOSES)
Resulting from Spectrum of (SYS)
Postulated Piping Breaks 10/02/81C III-5.C Inservice Inspection of 10/12/81R 02/09/82C Within the Reactor Coolant Water Control Structures Pressure Boundary III-4.B Turbine Missiles (MP B-46)
NOME 12/02/81C J/ SAR : Licensee Safety Analysis Report-Scheduled or Actual (actual (status 4b) when cate is follwed by R)
III-*.D Site Proximity Missiles 04/16/81R 07/21/81C (Including Aircraft) 2/ SER = Staff Safety Evaluation Report -Scheduled or Actual (Actual (status 4a, 5, 7 ) when date is followed by C) 1 VI-1 Organic Materials and 11/06/81R 02/18/82C Post Accident Chemistry 2/ Desiginated number of days from receipt of licensee SAR (Note
- if Licensee SAR is received then date is from receipt of additional information requested)
(3-4)
C ED
/
L tJ 0
3 la J
t 0
3 YA 41 0
3 R
PA 0
3 R
A I
S I
L 0
3 D
A E
B T
V FE T
l E
I C
0 3
M E
B R
NA UA S
J S
)
H i
L T
3 5
Se 0
I l
A D
3 I
C T
(
I E
I f,
T CE E
M S
B 1
1 3
3 N
U E
S IC Z
I C
L L
I A
0 1
2 2
L TCO 0
1 2
1 PES
/
2 0
2 0
G o
UA 0
0 0
0 l
S J
L l
A TT I
a 0
0 0
0 t
t i
S ls J
8 5
5 9
5 S
5 4
3 2
2 1
I l
t W
t a
e e
g u
g r
t r
M a
c a
T A
T EV T
L H
I E
A G
U T
T R
T N
A A
C T
A O
L M
UM R
U E
C P
il1
l i
DRESDEN 2 21 DRESDEN 2 21 (Cont.)
11 SAR 1/
SER 2/
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC HO. TITLE SCHEDULE SCHEDULE 111-1 Classification of NONE 03/03/82C I1-3.B Flooding Potential and NONE 06/10/82 I
(SYS)
Structures. Components and Protection Requirements Systems (Seismic and Quality)
II-3.B.1 Capability of Operating NONE 96/10/82 Plant to Cope with Dasign III-2 Wind and Tornado Loadings 02/22/82R 06/30/82 Basis Flooding Conditions j
III-5.A Effects of Pipe Break on 09/30/82 10/21/82 II-3.C Safety-related Water NONE 06/10/82 Structures, Systems and Supply (Ultimate Heat Sink 4
Components Inside (UHS)).
Containment II-4.D Stability of Slopes 12/08/81R 04/30/82 III-7.B Design Codes, Design NONE 06/15/82 Criteria, Load II-4.E Dam Integrity 12/08/81R 01/22/82C Combinations, and Reactor Cavity Design Criteria II-4.F Settlement of Foundations 12/08/81R 04/30/82 1
and Buried Equipment
{
VI-4 Containment Isolation NONE 12/15/81C (ELEC)
System III-3.A Effects of High Mator Level 12/08/81R 04/15/82 g
1 on Structures 1
VII-1.A Isolation of Reactor NONE 08/05/81C Protection System from III-3.C Inservice Inspection of 02/16/82R 07/01/82 Non-Safety Systems, Water Control Structures 1
i Including Qualifications of Isolation Devices III-4.8 Turbine Missiles NONE 04/15/82 d
VII-6 Frequency Decay NONE 08/26/81C III-4.D Site Proximity Missiles 12/08/81R 02/05/82C 1
(Including Aircraft) 4 IX-5 Ventilation Systems NONE 01/20/82C III-7.D Containment Structural 04/27/81R 03/30/82C Integrity Tests El SAR 1/
SER 2/
V-1 Compliance with Codes NONE DELETED I
SCHEDULE SCHEDULE and Standards (10 CFR TOPIC NO. TITLE 50.55a)(MP A-01,A-14)
II-1.A Exclusion Area Authority 06/01/81R 10/06/81C and Control VI-1 Organic Materials and 04/15/82 05/30/82 i
Post Accident Chemistry l
l II.1.B Population Distribution 04/27/81R 10/06/81C l
i II-1.C Potential Hazards or 12/08/81R 05/31/82 All t
Changes in Potential SAR 1/
SER 2/
Hazards Due to TOPIC NO. TITLE SCHEDULE SCHEDULE Transportation, Institutional Industrial, II-2.C Atmospheric Transport and 03/20/81R 08/26/81C i
and Military Facilities Diffusion Characteristics for Accident Analysis 4
II-3.A Hydrologic Description NONE 06/10/82 1
III-4.A Tornado Missiles 12/08/81R 04/30/82 l
(3-6) i 1
DRESDEN 2 211 (Cont.)
211 (Cont.)
SAR 1/
SER 2/
SAR 1/
SER R/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE III-4.C Internally Generated 04/15/82 06/15/82 XV-3 Loss of External Load, 10/15/81R 11/17/81C Missiles Turbine Trip, Loss of Condenser Vacuum, Closure III-8.A Looso 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 10/19/81C Including Functional Design XV-4 Loss of Non-Emergency A-C 10/15/81R 11/17/81C and Protection Against Power to the Station Single Failures Auxiliaries VI-2.D Mass and Energy Release for NONE 12/02/81C XV-5 Less 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 Heat Removal Capability Pump Shaft Break VI-4 Containment Isolation NONE 10/02/81C XV-8 Control Rod Misoperation 10/15/81R 01/27/82C (SYS)
System (System Malfunction or Operator Error)
VI-6 Containment _ Leak Testing NONE 05/01/82 (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 Nozzle 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 05/01/82 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)
NONE 06/30/82 XV-13 Spectrum of Rod Drop 10/15/81R 01/25/82C (SYS)
Accidents (BWR)
XI-1 Appendix I(MP A-02)
NONE DELETED (DOSES) 10/15/81R 12/14/81C XI-2 Radiological (Effluent and NONE DELETED XV-14 Inadvertent Operation of 10/15/81R 12/08/81C Process) Monitoring Systems ECCS and Chemical and (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 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 (3-7)
DRESDEN 2 211 (Cont.)
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE XV-18 Radiological Consequences 10/15/81R 12/23/81C of Main Steam Line Failure Outside Centainment (BWR)
XV-19 Loss of-Coolant Accidents 10/15/81R 11/17/81C (SYS)
Resulting from Spectrum of (DOSES)
Postulated Piping Breaks 10/15/81R 12/15/81C Within the Reactor Coolant Pressure Boundary XV-20 Radiological Consequences 04/27/81R 11/20/81C 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 (Notes if Licensee SAR is received then date is from receipt of additional information requested)
(3-8)
(
L
.... =..
LICENSEE SUBMITTALS
[RESEN 2 SLEMITTALS 48 TARGET 35 ACTUAL 25 --
28 15 18 5
/
i t
i i
e i
g M
R ALE SEP OCT lof IEC JAN FEB MAR APR MAY Jt91 m /DEC MONTHS Tarpt 0
0 0
2 0
0 1
PER MONTH Actual o
o o
14 0
7 0
1 1
0 Tarpt 22 23 25 25 25 27 26~
CUMULATIVE l
Actual 0
0 0
14 14 21 21 22 23 23 l
l (3-9) i
0YSTER CREEK RL OYSTER CREEK 21 (Cont.)
SAR 1/
SER 2/
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE-SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEOULE 111-1 Classification of NONE 01/29/82C 111-4.8 Turoine Missiles 12/07/81R 05/31/32
($YS)
Structures, Components and Systems III-4.D Site Proximity Missiles 03/31/82 04/30/82 III-2 Wind and Tornado Loading 03/31/82 05/31/82 III-7.D Containment Structural 11/04/81R c2/25/82C Integrity Tests III-7.B Design Codos. 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 Materials and Post 07/30/82 08/31/82 IX-5 Ventilation System 02/28/82 05/30/82 Accident Chemistry VI-7.A-4 Core Spray Nozzle NONE 05/31/82 Effectiveness (MP D-12)
Lil SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE
~El SAR 1/
SFR 2/
11-2.C Atmospheric Transport and 11/04/StR 02/24/82C TOPIC NO. TITLE SCHEDULE SCHEDULE Diffusion Characteristics for Accident Analysis II-1.A Exclusion Arca Authority 11/30/81R 01/18/82C and Control III-4.A Tornado Missles 03/31/82 05/15/82 II-1.B Population Distribution 11/30/81R 01/18/82C III-4.C Internally Generated 02/28/82 04/15/82 Missiles II-1.C Potential Hazards Due to 11/30/81R 01/18/82C Transportation, Industrial.
III-8.A Loose Parts and Core NDNE 02/09/82C Barrel Monitoring and Military Facilities (NRR B-60.C-12)
II-3.A Hydrologic Description 03/04/82R 07/05/82 IV-2 Reactivity Control Systems 02/28/82 04/15/82 II-3.B Flooding Potential and 03/04/82R 07/05/82 VI-2.D Mass and Energy Release for NONE 11/20/81C Protection Requirements Possible Pipe Break Inside II-3.B-1 Capability to Cope with 03/04/82R 07/05/82 Containment Design Basis Flood VI-3 Containment Pressure and NONE 11/20/81C II-3.C Safety Related Water Supply 03/04/82R 07/05/82 Heat Removal Capability (Ultimate Heat Sink)
VI-4 Containment Isolation NONE 10/22/81C II-4.D Stability of Slopes 12/15/81R 06/01/82 System II-4.F Settlement of Foundation 11/04/81R 06/01/82 VI-6 Containment Leak Testing NONE 06/04/81C (MP A-04) and Buried Equipment III-3.A Effects of High Water 03/04/82R 04/15/82 VIII-1.A Potential Equipment NONE 10/16/81C Failures Associated wi th Level on Structures a Dograded Grid Voltage III-3.C Inservice Inspection of 11/12/81R 06/01/82 (MP B-23)
Water Control Structure (3-10)
0YSTER CREEK 211 (Cont.)
211 (Cont.)
SAR 1/
SER 2/
SAR 1/
SER 2/
TOPIC HO. TITLE SCHEDULE SCHEDULE TOPIC HO. TITLE SCHECULE SCHEDULE IX-1 Fuci Storage 03/C4/82R u4/15/82 XV-15 Inadvertent Opening of BHR 05/07/81R 11/19/81C Safety / Relief Valve IX-6 Fire Protection (MP B-41)
NONE 05/31/82 XV-16 Radiological Consequences 11/0 4/81R 03/15/82 of Failure of Small Lines XI-1 Appendix I(MP A-02)
NONE DELETED Carrying Primary Coolant Outside Containment XI-2 Radiological (Effluent and NDHE DELETED Procwss Monitoring Systems)
XV-18 Radiological Consequences 05/07/81R 07/01/81C (NRR B-67)
Main Stoan Line Failure XV-1 Docrease in Feedwater 05/07/81R 12/07/81C Outside Containment Temperature, Increase in Feedwater Flow, Increase in XV-19 Loss of Coolant Accidents 05/07/81R 09/04/81C Steam Flow, Inadvertent (SYS)
Resulting Fron Spectrum Opening of Steam Generator, Breaks Within Reactor Reaiof or Safety Valvo (DOSES)
Ccolant Pressure Boundary 02/28/82 04/30/82 XV-3 Loss of External Load, 05/07/81R 07/16/81C XV-20 Radiological Consequences 02/28/82 04/30/82 Turbine Trip, Loss of of Fuel Damaging Accidents Condenser Vacuum, Closure (In 8 Out of Containment) of Main Steam Isolation Valve (SWR), Steam Pressure Regulatory Failure (closed)
J/ SAR = Licensee Safety Analysis Report-Scheduled or Actual (actual (status 4b) when date is followed by R)
XV-4 Loss of Hon-Emerqcncy A-C 05/07/81R 07/16/81C Power to the Station 2/ SER : Staff Safety Evaluation Report -Scheduled or Actual Auxiliaries (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: 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 Seizure and Reactor Coolant Pump Shaft Break XV-9 Startup or an Inactivo Loop 05/07/81R 12/30/81C or Recirculation Loop at Incorrect Temporature and Flow Controller Malfunction Causing an Increase in EWR Core Flow Rate XV-13 Spectrum of Rod Drop NDHE 04/09/81C (sys)
Accident 05/07/81R 0 7/ 01/81C (doses)
XV-14 Inadvertent Operation of 05/07/81R 0 7/16 /81C ECCS that Increases Reactor Coolant Inventory (3-11)
LICENSEE SUBMITTALS orsia o m Sim ITTALS 48 TARGET 35 --
5--
25 --
/
/
/
29 --
/
/
/
15 --
18 --
5--
i i
i e
i i
e i
i g
Jim Jtt AUG SEP OCT NOV DEC JAN FEB MAR APR MAY Jim Jtt/DEC MONTHS Target 5
3 0
0 0
1 PER MONTH I
Actual 0
0 0
0 8
2 0
0 6
0 Target 12 16 21 24 24 24 24 25 CUMULATIVE Actual 0
0 0
1 8
10 10 10 16 16 (3-12)
m
= _ _ _-
MILLSTONE 1 El r11LLSTONE 1 1
RE (Cont.)
TOPIC NO. TITLE SC E U E SC DU E TOPIC NO. TITLE SC E U E SC E U E III-1 Classification of h0NE 01/ 2 9/82C II-3.A Hydrologic Description 06/25/81R 06/25/82
($YS)
Structures, Components and Systems (Solsmic and II-3.B Flooding Potential 8 06/26/81R 06/25/82 i
Quality)
Protection Roquirements III-2 Wind and lornado Loadings NONE 04/30/82C II-3.B.1 Capability of Operating 06/25/81R 06/25/82 Plant to Cope with Design III-5.A Effects of Pipe Break on 04/13/82R 05/10/82 Basis Flooding Condit;ons Structures, Systems and Components Inside II-3.C Safety Related Water 04/28/81R 06/25/82 Containment t
Supply (UHS)
III-5.B Pipe Break Outside 12/04/81R 02/09/82C II-4.B Proximity of Capablo NONE 12/30/81C Containment Tectonic Structures in Plant Vicinity III-7.B Design Codos, Dosion NONE 05/30/82 Critoria, Load Combinations II-4.D Stability of Slopes 08/31/81R 06/01/82 and Reactor Cavity Design II-4.F Settlement of Foundations 04/28/81R 06/01/82 V-11.B RHR Intorlock Requirements NONE 01/22/82C and Buried Equipment (ELEC)
III-3.C Inservice Inspection of 08/31/81R 06/01/82 VII-3 Systems Required for Safe NONE 01/22/82C Water Control Structures (ELEC)
Shutdown III-4.B Turbine Missiles 08/31/81R 05/31/82 VII-6 Frequency Decay NONE 08/26/81C III-4.D Site Prximity Missiles 04/29/81R 10/29/81C i
IX-3 Station Service and Cooling 11/24/11R 04/30/82C (Including Aircraft)
Water Syster.s i
IV-3 BWR Jet Pumps Operating NONE 02/22/82C i
l IX-5 Ventilation Systems 11/19/81R 04/28/82C Indications 4
XIII-2 Safoquards Industrial NONE 06/30/82 V-1 Compliance with Codos and NONE DELETED Security (MP A-10)
Standards (10 CFR 50.55a)
(MP A-01,A-14)
Eg VI-1 Organic Materials and Post 09/30/81R 01/28/82C SAR 1/
SER 2/
Accident Chemistry i
TOPIC NO. TITLE SCHEDULE SCHEDULE I
II-1.A Exclusion Arca Authority 1 04/17/81R 0 7 / 31/81 C Ri1 Control SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE II-1.B Population Distribution 05/19/81R 10/29/81C l
II-2.C Atmospheric Transport and 05/19/81R 09/29/81C II-1.C Potential Hazards or 04/29/81R 10/29/81C i
Changes in Potential Diffusion Characteristics Hazards Due to Transporta-for Accident Analysis tion, Institutional, and III-4.A Tornado Missiles 08/31/81R 05/05/82C 1
Military Facilities l
i (3-13) l
l MILLSTONE 1 R11 (Cont.)
211 (Cont.)
SAR J/
SER 2/
SAR J/
SER 2/
TOPIC N0. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE III-4.C Internally Generated 04/13/82R 05/14/82 XV-3 Loss of External Load, 06/30/dlR 3 9/18 / 81 C Missiles Turbine Trip. Loss of Condenser Vacuum. Closure III-8 A Loose Parts Monitoring and NDHE 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 03/31/82 Including Functional Design XV-4 Loss of Non-Emergency A-C 06/30/81R 09/18/81C and Protection Against Power to the Station Single Failures Auxiliaries VI-2.D Mass and Energy Release for NONE 04/01/82 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' d
VI-3 Containment Pressure and NONE 04/01/82 Rotor Seizure and Reactor Heat Removal Capability Coolant Pump Shaft Break VI-4 Containment Isolation NONE 11/16/81C XV-8 Control Rod Misoperation 06/30/81R 08/26/81C (SYS)
System (System Malfunction or Operator Error)
VI-6 Leak Testing (MP A-04)
NONE 05/31/82 XV-9 Startup or an Inactive Loop 06/30/81R 12/30/81C 4
VI-7.A.4 Core Spray Nozzle NONE 02/09/82C or Recirculation Loop at an Effectiveness (NRR A-16)
Incorrect Temperature, and Flow Controller Malfunction VIII-1.A Potential Equipment NONE 06/01/82 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 06/30/82 Position XI-1 Appendix I(MP A-02)
NONE 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 09/21/81C Process) Monitoring Systems (HRR B-67)
XV-14 Inadvertent Operation of 06/30/81R 09/18/81C ECCS and Chemical and XV-1 Decrease in Feodwater 06/30/81R 12/15/81C Volume Control System Temperature, Increase in Malfunction that Increases Fcodwater 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 Pressuri or Safety Relief Valve or a BWR Safety Relief Valve J
(3-14)
MILLSTONE 1 Dil (Cont.)
SAR t/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE XV-16 Radiological Consequences 06/30/81R 09/21/81C of Failure of Small Lines Carrying Primary Coolant Outsiae Containment XV-18 Radiological Consequences 06/30/81R 09/21/81C of Main Steam Line Failure Outside Containment (BWR)
XV-19 Loss of Coolant Accidents 06/30/81R 08/26/81C (SYS)
Resulting from Spectrum of (DOSES)
Postulated Piping Breaks 06/30/81R 0 9/21/81C Within the Reactor Coolant Pressure Boundary XV-20 Radiological Consequences 06/30/81R 09/21/81C of Fuel Damaging Accidents (Inside and Outside Containment) l/ SAR : Licensee Saf ety 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 Ga, 5, 7) when date is followed by C)
J/ Desiginated number of days from receipt of licensee SAR (Note: if Licensoe SAR is received then date is from receipt of additional information requested)
(3-15)
C ED
/
t tJ 2
0 1
M J
t 0
2 1
YAM 2
0 1
R PA 2
2 0
2 1
1 R
AM S
2 0
L 2
0 1
1 A
D E
B T
T EF T
TI 0
0 1
t 0
o I
M M
B 1
N B
U J
S
)
A E
S U G H
6 T
0 0
1 ST S
I 0
1 1
S C
OI (3
L I
C L
P EI E
M O
I E
T S
1 0
L 1
N L
N E
A M
C I
2 9
L T
CO 2
7 P
ES 5
0 E
IA 5
5 l
S l
L J
ATT 0
0 I
NE i
p LS t
J 3
5 8
5 8
5 la 4
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8 l
2 2
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a p
u p
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t r
t a
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SAN ON0FRE 21 SAN OtiOFRE l
SAR 1/
SER 2/
SAR 1/
SER Z/
TOPIC NO. TITLE I SCHEDULE SCHECULE TCPIC NO. TITLE SCHEDULE SCHEDULE IX-3 Station Service and Cooling 11/02/81R 06/3C/82 111-1 Classification of NONE 05/07/82 Water Systems Structuras. Components and Systems (Seismic and IX-5 Ventilation Systems 12/16/81R 06/30/82 Quality)
III-2 Wind and Tornado Loadings 05/01/82 08/30/82 p1 SAR t/
SER 2/
III-5.A Effects of Pipe Break on 12/01/82 01/15/83 TOPIC NO. TITLE SCHEDULE SCHEDULE Structures. Systems and Cceponents Insido 11-1.C Potential Hazards or 11/12/ 81 R 05/31/82 Containment Changes in Potential Hazards Due to III-5.B Pipe Break Outside 12/01/82 12/16/82 Transportation.
Containment Institutional Industrial, and Military Facilities III-6 Seismic Design NONE 08/30/82 Considerations II-3.A Nydrologic Description NONE 12/05/82 III-7.B Design Codos. Design NOSE 08/31/82 II-3.B Flooding Potential 8 NONE 12/05/82 Criteria, Load Protection Requirements Combinations, and Reactor Cavity Design Criteria II-3.B 1 Capability of Operating NONE 12/05/82 Plant to Cope with Dosion V-11.B RHR Interlock Requiremonts NONE 02/04/82C Basis Flooding Conditions (ELEC)
II-3.C Safety Related Water NONE 12/05/82 VI-7.A.3 ECCS Actuation System NONE 11/18/81C Supply (UHS)
VI-7.B ESF Switchover from NONE 09/04/81C II-4.D Stability of Slopes 11/02/81R 11/01/82 (ELEC)
Injection to Recirculation Nodo (Automatic ECCS II-4 F Settlement of Foundations 11/02/81R 11/01/82 Realignment) and Buried Equipment VI-10.A Testing of Reactor Trip NONE 08/28/81C III-3.A Effects of High Water Level 05/30/82 09/30/82 System and Engineered on Structures Safety Fea+ures Including Response Timo Testing III-4.B Turbine Missiles (MP B-46)
NONE 04/30/82 VII-1.A Isolation of Reactor NONE 09/09/81C III-4.D Site Proximity Missiles 10/23/81R 06/30/82 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-3 Systons Required for Safe NONE 11/18/81C (ELEC)
Shutdown VI-1 Organic Materials and Post 01/28/82C 05/30/82 Accident Chemistry VII-6 Frequency Decay NONE 08/28/81C (3-17)
SAN ON0FRE E
M (Cont.)
SAR l/
SER 2/
SAR 1/
$[R ;/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE Ill-4.A Tornado Missiles 05/01/82 06/15/82 XV-2 Spectrum of Steam System 07/01/81R 1C/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 NDHE 12/07/81C Turbino Trip, Loss of Con-Core Barrel Vibration densor Vaccum, Closure of Monitoring (NRR B-60,C-12)
Main Steam Isolation Valve (EWR), and Steam Pressure IV-2 Reactivity Control Systems 04/30/82R 06/15/82 Roqulator Failure (Closed)
Including Functional Design and Protection Against XV-4 Loss of Non-Emergency A-C 08/18/81R 12/12/81C Singlo Failures Power to the Station Auxillaries V-7 Reactor Coolant Pump NONE 11/05/81C Overspeed(HRR B-68)
XV-5 Loss of Normal Feedwater 07/01/81R 01/25/82C Flow VI-2.D Mass and Energy Releaso for NONE 12/04/81C Possible Pipe Break Inside XV-6 Feedwater System P'pe 0 7/ 01/31R 02/19/82C Containment Breaks Inside and Outside Containment (PWR)
VI-3 Containment Pressure and NONE 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 NONE 03/31/82 (System Malfunction or (MP A-04)
Operator Error)
VIII-1.A Potential Equipment Failure NONE 05/01/82 XV-10 Chemical and Volume Control 07/01/81R 03/28/82C Associated with a Degraded System Malfunction that Grid Voltage (MP B-23)
Results in a Decrease in the Boron Concentration in IX-1 Fuel Storage 04/30/82 06/15/82 the Reactor Coolant (PWR)
IX-6 Fire Protection (MP B-41)
NONE 10/31/82 XV-12 Spoetrum 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 (NRR B-67)
Malfunction that Increases Reactor Coolant Inventory XV-1 Decrease in Feedwater 07/01/81R 10/27/81C Temperature, Increase in Feedwater Flow, Increase XV-15 Inadvertent Opening of a 07/01/81R 0 3/31/82C in Steam Flow and PWR Pressurizer Safety-Inadvertent Opening of a Relief Valve of a BWR Steam Generator Relief Safety / Relief Valve or Safety Valve (3-13)
SAN ON0FRE D.11 (Cont.)
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE XV-16 Radiological Conscquences 08/04/81R ll/18/8tC of Failure of Small Linos Carrying Primary Coolant Outside Containment XV-17 Sy= tem Generator Tube NONE 12/07/81C (SYS)
Failu*e (PWR)
XV-19 Loss-of-Coolant Accidents 07/01/81R 08/26/81C Resulting From Spectrum of Postulated Piping Breaks Within the Reactor Coolant Pressuro Boundary J/ SAR: Licensee Safety Analysis Report-Scheduled or Actual (Actual (status 46) when date is followed by R) 2/ SER : Staff Safety Evaluation Report -Scheduled or Actual (Actual (status Aa, S, 7) when date is followed by C) 1/ Desiginated number of days from receipt of licenseo SAR (Notes if Licensee S AR is received then date is from receipt of additional information requested)
(3-19) m
C ED
/
t t
/
J 2
7 1
ip J
l 0
5 g
Y 1
/
5 3
1 R
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1 3
2 1
1
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0 9
9 A
B T
FE T
9 9
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0 M
N BE J
S
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0 N
T 9
9 2
S(
I D
1 M
3 N
(
A C
8 8
N f
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C l
7 I
4 L
TC O
3 1
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0 2
G UA 2
2 S
t L
t A
J TT I
0 0
I DE J
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t 5
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8 5
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BIG ROCK POINT HL BIG RCCK POINT CL (Cont.)
SAR 1/
SER 2/
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE Ill-1 Classification of Struct-NONE 04/16/82C IX-3 Station Service and 12/10/81R 05/30/82 (SYS) ures, Components and Sys-Cooling Water Systems tems (Scismte and Quality)
IX-5 Ventilation Systems 05/15/82 08/30/82 III-2 Wind and Tornado Loading 02/01/82 08/30/82 III-5.A Effects of Pipe Break on 05/01/82 09/21/82 21 Structures, Systems and SAR 1/
SER 2/
Cen.ponents Insi de TOPIC HO. TITLE SCHEDULE SCHEDULE Containment III-5.B Pipe Break Outside 04/01/82 08/20/82 Containment II-3.5 Flooding Potential and NONE 08/10/82 Protection Requirements III-6 Seismic Design NDHE 09/30/82 Considerations II-3.B.1 Capability of Operating NONE 08/10/82 Plans to Cope with Designs III-7.B Design Codes, Design NCHE 05/30/82 Basis Flooding Conditions Criterion, Load Combinations and Reactor II-3.C Safety-Related Water Supply NONE 08/10/82 Cavity Design Critorion (Ultimate Heat Sink UHS))
VI-7.A.3 ECCS Actuation System NDHE 01/29/82C II-4.B Proximity of Capable NDNE 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 06/01/82 Including Independence of Interlocks on ECCS Valve II-4.F Settlement of Foundations 10/19/81R 06/01/82 and Buried Equipment VI-7.C.2 Failure Mode Analysis ECCS NONE 08/05/81C III-3.A Effects of High Water 03/15/82 09/30/82 VI-10.A Testing of Roactor Trip 12/23/31 05/30/82 Level on Structures System and Engineered Safety Features, Including III-3.C Inservice Inspection of 12/21/81R 09/01/82 Response Tina Testing Water Control Structures VII-1.A Isolation of Reactor PONE 02/16/82C III-4.B Turbine Missiles 06/30/82 07/31/82 Protection System From Hon-Safety Systems, Including III-4.D Site Proximity Missiles 12/14/81R 05/15/82 Qualification of Isolation (Including Aircraft)
Devices III-7.D Containment Structural 12/29/81R Cs/03/82C VII-2 Engineered Safety Features NONE 12/31/81C Integrity Tests (ESF) System Control Logic and Design V-1 Compliance with Codes and NONE DELETED Standards 310 CFR 50.55a)
VII-6 Frequency Decay NONE 09/21/81C (MP A-01,A-14)
VI-1 Organic Materials and Post 03/16/82R 05/15/82 Accident Chemsitry Accident Chemsitr/
(3-21)
{
BIG ROCK POINT LH pH (Cont. )
SAR 1/
SER 2/
SAR 1/
SER 2/
TCPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHECULE 11-2.C Atmospheric Transport and 04/06/82R, 06/15/82 XV-1 Decrease in Feeowater Q T~ 15/ 51 R. C2/13/32C
/
Diffusion Characteristics Temperature Increase in for Accident Analysis Feedwater Flow. Increase in Stoam Flow and III-4.A Tornado Missiles 03/16/32R 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 External Load.
07/15/81R 10/16/81C III-8.A Loose Parts Monitoring and N0HE 02/09/82C Turbine Trip, Loss of Core Vibration Monitoring Condenser vacuum, closure (NRR B-60,C-12) of Main Steam Isolation Valve (EWR), and Steam IV-2 Reactivity Control Systen NONE 12/07/81C Pressure Regulator Failure Including Functional Desten (Closed) and Prctection Against Single Failures XV-4 Loss of Non-Emergency A-C 07/t5/81R 10/16/81C Power to Use Station VI-2.D Mass and Energy Release for NONE 03/31/82 Auxiliaries Postulated Pipe Breaks Inside Containment XV-5 Loss of Normal Feedwater 07/15/81R 01/26/82C Flow VI-3 Containment Pressures and HONE 03/31/82 Heat Removal Capability XV-7 Reactor Coolant Pumps 07/15/81R 02/25/82C Rotor Sei:ure and Reactor VI-4 Containment Isolation Sys.
N0HE 03/24/82C Coolant Pump Shaft Ereak VI-6 Containment Leak Testing NCHE 04/30/82 XV-3 Control Rod Misoporation 09/23/81R 12/21/81C (MP A-04)
(System Malfunction or Oparator Error)
VI-7.B ESF Switchover from NONE 04/22/52C Injection to Recirculation XV-9 Startup of an Inactive Loop 07/15/81R 03/24/82C Mode (Autematic EECS or Recirculation Loop at an Realignment)
Incorrect Temperature and Flow Controller Malfunction VIII-1.A Potential Equipment HONE 07/01/82 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 NDHE 07/31/82 Operation of a Fuel Assembly in an Improper IX-6 Fire Protection (MP B-41)
NONE 09/30/82 Position (BWR)
XI-1 Appendix I(MP A-02)
N0HE DELETED XV-13 Spectrum of Rod Drcp SYS 07/01/81R 11/20/81C Accidents DOSES 07/01/31R 10/23/81C XI-2 Radiological (Effluent NONE DELETED and Process) Monitoring Systems (NRR B-67)
XV-14 Inadvertent Operation of 06/26/81R 08/t3/81C ECCS and Chemical and Volume Control System Malfunction that Increases Reactor Coolant Inventory (3-22)
BIG ROCK POINT Hil (Cont.)
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE XV-15 Inadvertent OpeEino of a 06/26/81R 08/18/81C PMR Pressurizer Safety Relief Valve or a BWR Safety / Relief Valve XV-16 Radiological Consequences 07/01/81R 12/14/81C of railure of Imall 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 0 8/18/81C (SYS)
Resulting From Spectrum of Postulated Piping Breaks (DOSES) within the Reactor Coolant No date 07/01/82' Pressure Boundary XV-20 Radiological Consequences 07/03/81R 10/23/81C of Fuel Damaging Accidents (Insido and Outside Containment) 1/ SAR = Licenseo 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 Ga, 5, 7 ) when date is followed by C)
J/ Dar qinated number of days from receipt of licensee SAR 2
(Notes if Licensee SAR is received then date is from receipt of additional information requested)
(3-23)
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0 2
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HADDAM NECK EL HADDAM NECK EL (Cont.)
SAR 1/
SER 2/
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE 111-1 Classification of NONE 06/18/82 IX-5 Ventilation Systems 12/14/81R 05/15/82 (SYS)
Structures, Components and Systems (Seismic and XIII-2 Safeguards / Industrial NONE 06/30/82 Quality)
Securi+y (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 07/30/82 SAR 1/
SER 2/
on Structures, Systems TOPIC NO. TITLE SCHEDULE SCHEDULE and Componets Inside Containment Il-1.A Exclusion Area Authority 04/27/81R 03/29/82C B. Pipe Break Outside 10/02/81R 04/08/82C II-1.B Population Distribution 08/31/81R 03/29/82C Containment II-1.C Potential Ha:ards or 06/30/81R 03/29/82C III-6 Seismic Desic.
NONE 09/30/82 Changos in Potential Considerations Hazards Due to Transportation, III-7.B Design Codes, Design NONE 07/30/82 Institutional Industrial, Criteria, Load and Military Facilities Combinations, and Reactor Cavity Design Criteria II-3.A Hydrologic Description 12/14/81R 10/01/82 VI-7.A.3 ECCS Actuation System NONE 01/29/82C II-3.5 Flooding Potential and 12/14/81R 10/01/82 Protection Requirements VI-7.C 3 The Effect on PWR Loop NONE 12/14/81C Iselation Valve Closure II-3.B.1 Capability of Operating 12/14/81R 10/01/82 During a LOCA on ECCS Plant to Copa with Design Performance Basis Flooding Conditions VI-10.A Testing of Reactor Trip NONE 04/30/82 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 NONE 04/30/82 Tectonic Structures i, VII-1.A Isolation of Reactor NONE 02/16/82C Plant Vicinity Protection System from Non-Safety Systems, Including II-4.D Stabil!'v of Slopes 08/31/81R 07/01/82 Qualifications of Isolation Devices II-4.F Settlement of Foundations 12/18/81R 05/15/82 VII-2 Engineered Safety Features NONE 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 NONE 08/28/81C III-3.B Structural and Other NDHE 10/01/82 VIII-4 Electrical Penetrations NONE 12/23/81C Conscouences (e.g. Flooding af Reactor Containment of Safety-Related Equipment in Basements) of Failure of IX-3 Station Service and Cooling 12/14/81R 04/30/82R Underdrain Systems Water Systems (3-25)
HADDAM NECK Ri (cont.)
Ell (Cont.)
SAR J/
SER 2/
SAR 1/
SER Z/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE III-3.C Inservice Inspections of 02/12/82R 07/01/82 VI-6 Containment Leak Testing N0hE 03/31/82 Water Control Structures (MP A-04)
III-4.B Turbine Missiles (MP B-46)
NONE 04/30/82 VI.7.B ESF Switchover from NONE 04/01/82 (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 Containmont Structural 04/27/81R 10/16/81C VIII-1.A Potential Equipment NONE 10/01/82 Integrity Tests Failures Associated with a Decraded Grid Voltage V-1 Ccmplianco with Cudos and NONE 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 05/30/82 IX-4 Doron Addition Systems 10/02/81R 03/31/82C Accident Chemistry IX-6 Fire Protection (MP B-41)
NONE 08/31/82 til XI-1 Appendix I(MP A-02)
NONE DELETED SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE XI-2 Radiological (Effluent NCHE DELETED and Process) Mrnitoring III-4.A Tornaco fle ssiles 08/51/81R 12/26/81C Systems (NRR B-07)
III-4.C Internaly Generating 02/12/82R 03/15/82 XV-1 Decrease in Feedwater 09/30/81R 04/15/82 Missiles Temperatures, Increase in Feedwater Flow, Increase in III-8.A Loose Parts Monitoring and NDHE 02/09/82C Stoam Flow and Inadvertent Core Barrel Vibration Opening of a Steam Genera-Monitoring (NRR B-60 C-12) tor Reliof or Safety Valve I N* - 2 Reactivity Control Systems 06/30/81R 12/23/81C XV-2 Spectrum cf Steam System 09/30/81R 04/15/82 Including Functional Dasign Piping Failures Inside and and Protcetion Against Outside of Containment (SYS)
Single Failures (PWR)
(D05ES) 09/30/81R 05/01/82 V-7 Reactor Coolant Pump NONE 11/05/81C Overspood(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 Rolcase for NCHE 05/01/82 Condenser vacuum, closure Possible Pipo Dreak Inside of Main Steam Isolation Containment Valve (BWR), and Steam Pressure Regulator Failure VI-3 Containment Pressure and NDHE 05/01/82 (Closed)
Heat Removal Capability XV-4 Loss of Non-Emcrooney A-C 09/30/81R 12/17/81C VI-4 Containment Isolation NCHE 04/06/82C Power to the Station System Auxiliarios XV-5 Loss of Normal Feedwater 09/30/81R 04/06/82C Flow (3-26)
HADDAM NECK pil (Cont.)
2.51 (Cont.)
SAR 1/
SER 2/
SAR 1/
SER 2/
TOPIC HO. TITLE SCHEDULE SCHEDULE TOPIC HC.
T.' T L E SCHEDULE SCHEDULE XV-6 Feedwater System Pipe 03/30/81R 04/28/82C XV-19 Loss of-Coolant Accidents 09/30/41R' 11/10 / 81 C Breaks Inside and Outside Resulting from Spcctrum cf Containment (PWR)
Postulated Piping Breaks Uithin the Reactor Coolant XV-7 Reactor Coolant Pump Rotor 09/30/81R 04/15/82 Pressure Boundary (SYS)
Seizure and Reactor Coolant (DOSES) 09/30/81R C5/01/82 Pura 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 folicwed by R)
Operator Error)
Z/ SER : Staff Safety Evaluation Report -Scheduled or Actual XV-9 Startup or an Inactive 09/30/81R 03/31/82C (Actual (status Ga. 5, 7) when datt is followed by C)
Loop or Recirculation Loop at an Incorrect 1/ Desiginated number of days from recoint of licensee SAR Temperature, and Flow (Note: if Licensco SAR is roccived 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 09/30/81R 03/29/82C System Malfunction that Results in a Decrease in in Soren Concontration in the Reactor Coolant (PWR)
XV-12 Spectrum of Rod Ejection 09/30/81R 03/15/82C Accidents (PWR)
(SYS)
(DOSES) 09/30/81R 05/01/82 XV-14.
Inadvertent Operation of 09/30/81R 0 4/ 01/82 C ECCS and Chemical and volumo Control System Malfunction that Increases Reactor Coolant Inventory XV-15 Inadvertent Opening of a 09/30/81R 04/06/82C PWR Pressuri cr Safety-Relief Valve or a BWR Safety / Relief Valve XV-16 Radiological Consequences NONE 09/28/81C of Failure of Small Lines Carrying Primary Coolant Outside Containment XV-17 Steam Generator (SYS) 04/07/82R 05/01/82 Tube Failure (PWR) (DOSES) 04/07/82R 05/01/82 1
1 (3-27)
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YANKEE RL YANKEE huCLEAR POWER STATION EL (Cont.)
SAR 1/
SER g/
SAR 1/
SER Z/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE 111-1 Classification of Struct-NONE 05/14/82 IX-5 Ventilation Sysrems 11/18 / 81 R f4/28/82C ures. Components and Sys-tems (Seismic and Quality)
~ '-
Rf I
SAR 1/
SER E/ j III-2 Wind and Tornado Loadings 03/18/P2R 07/30/82 SCHECULE SCHECULE TCPIC NO. TITLE
~
III-5.A Effects of Pipe Break on 03/18/42R 06/08/82 03/18/82R 06/30/82 Structures Systems and 11-1.A Exclusion Area Authority Components Inside and Control Contairment II-1.P Populatien Distribution 05/01/81R 06/30/82 III-5.B Pipe Break Cutside 01/21/82R 06/29/82 i
Containment II-1.C Potential Hazards or 04/09/81R 06/30/82 Ch ngos in Fotentic22 a
/
III-6 Sei smic Design NOME 08/31/82
/
Mazards Due to Considerations Transportation, Institutional Industrial.
III-7.B Design Codes. Design NONE 06/30/82 and Military Facilitias Criteria. Load C om b i n. t i o n s, and Reactor II-3.C Safety-related Water NONE 09/05/82 Cavity Design Criteria Supply (Ultimate Heat Sink V-11.8 RHR Interlock Requirements NONE 01/22/82C (ELEC)
II-4.B Proximity of Capable NONE 05/31/82 Tectonic Structures in VI-7.A.3 ECCS Actuation System 06/30/81R 01/29/82C Plant Vicinity (B-46)
J VI-10.A' Testing of Reactor Trip 06/30/81R 01/22/82C II-4.D Stability of Slopes 02/26/32R 10/01/82 1
/
System and Engineered Safoty Features Including II-4.E Dan Irteority NONE 10/01/82 i
Safety Features Including Response Time Testing II-4.F Settlement of Foundations 08/31/81R 10/01/82 and Buried Equipment 1
VII-1.A Isoaltion of Reactor NONE 10/05/81C
- III-3.A Effects of High Water 03/18/82R 05/30/82 I
Protection System from r
Non-Saget/ Systems,
, el '
Level on Structures Including Qualifications 8
of Isolation Devices III-3.C Inservice inspection of
,01/04/t2R ~10/01/82 Water Control Structures VII-2 Engineered Safety Features NONE 10)19/81C (ESF) System Control Logic III-4.5 Turbine Missiles (MP B-46)'
NONE 42/08/824 I
and Design III-4.D Site proximity missiles-06/30/81R 06/30/82 VII-3 System Required for Safe NONE 01/22/82C (Including Aircraft)
(ELEC)
Shutdown III-7.D Containment Structural 11/18/81R 03/01/82C
'VII-6 Frequency Decay NONE 08/28/81C Integrity Tests V-1 Compliance with Codes NONE DELETED IX-3 Station Service and Cooling 09/17/81R 04/15/82 and Standards (10 CFR Water Systems 50.55a)(MP A-01,A-14)
(3-29)
w YANKEE i
DE (Cor.t. )
Ell (Cont.)
SAR 1/
SER 2/
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE VI-l Organic Materials and 02/15/82-04/30/82 IX-1 Fu11 Storage 11/18/81R 05/01/82 Post Accident chemistry IX-4 Doron Addition System' 08/31/81R 05/15/82 231 IX-6 Fire Protection (MP B-41)
N0HE 08/31/82 SAR J/
SER 2/
TOPIC NO. TITLE SCHECULE SCHEDULE XI-1 Appendix I(MP A-02)
NONE DELETED i
II-2.C Atmospheric Transport and 06/30/81R 09/04/81C XI-2 Radiological (Effluent NONE DELETED Diffusion Characteristics and Process) Monitoring for Accicent Analysis Systems (NRR B-67)
III-4.A Tornado Missiles 0 3/18/82R 05/15/82 XV-1 Decrease in Feodwater 02/01/82R 06/30/82 Temperature, Increase in III-4.C Internally Generated 03/18/82R 05/15/82 Feodwater Flow, Increase 4
j Missiles in SteamsFlew and Inadvertent Opening of a III-8 A Loose Parts Monitoring NONE 12/07/81C Steam Generator Relief and Core Barrol Vibration or Safoty Valvo Monitoring (NRR B-60,C-12) 1 XV-2 Spectrum of Steam System 06/30/81R 05/15/82 IV-2 Reactivity Control Systems 09/17/81R 12/23/81C (SYS)
Piping Failuros Inside Including Functional Design (DOSES) and Outside of Containment No date 05/15/82 and Protection Against (PWR)
Single Failures XV-3 Loss of External Load, 06/30/81R 01/09/82C V-7 Reactor Coolant Pump NONE DELETED Turbino Trip, Loss of l
Condenser Vacuum, Closure i
of (1ain Steam Isolation j
VI-2.D Mass and Energy Release NONE 04/01/82 Valve (BWR), and Steam for Possible Pipe Bre 4 Pressure Roqulator Failure 4
Insida Containment (Closed) i VI-3 Containment Pressure and NONE 04/01/82 XV-4 Loss of Non-Emergency A-C 01/04/82R 06/01/82 Heat Renoval Capcbility Power to the Station Auxiliarios j
?
VI-4 Centainment Isolation NONE 04/01/82 (SYS)
System XV-5 Loss of Normal Feedwater 06/30/81R 01/29/82C 6
Flow VI-6 Containment Leak Testing NONE 06/01/82 l
(MP.A-04)
XV-6 Feedwater System Pipe 02/01/82R 06/15/82 Breaks Insido and Outside i
VI-7.5 ESF Switchover from NONE 06/15/82 Containment (PWR) 1 (SYS)
Injection to Recirculation Modo (Automatic ECCS XV-7 Roactor Coolant Pump Rotor 06/30/81R 04/30/82 Realignment)
Soizuro and Reactor Coolant 4
Pump Shaft Break l
VIII-1.A Potential Equipment NONE 08/01/82' Failures Associated with XV-8 Control Rod Misoperation 01/04/82R 02/26/82C a Dograded Grid Voltaqo (System Malfunction or (MP B-23)
Operator Error) 1 (3-30)
YANKEE Eh1 (Cont.)
SAR l/
SER 7/
TOPIC NO. TITLE SCHEDULE SCHEDULE XV-9 Startup or an Inactive 06/30/81R 06/15/82 Loop or Recirculation Loop at an Incorrect Temperature, and Flow Controller Malfunction Causing an Increase in BWR Core Flow Rate XV-10 Chemical and Volume Control 06/30/81R 03/02/82C System Malfunction that Results in a Docrease in the Boron Concentration in the Reactor Coolant CPWR)
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 06/30/82 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 Pressuri mer Saf ety-Related Valve or a BWR Savety/ Relief Valve XV-16 Radiological Consequences 02/01/82R 03/15/82 of Failure of Small Lines Carrying Primary Coolant Outside Containment XV-17 Steam Generstor Tube NONE 06/30/82 (SYS)
Failure (PWR)
(DOSES) 02/01/82R 03/19/82C XV-19 Loss-of-Coolant Accidents 11/18/81R 06/30/82 (SYS)
Resulting from Spectrum of (DOSES)
Postulated Piping Breaks 01/04/82R 04/15/82 Within the Reactor Coolant Pressure Boundary J/ SAR : Licensco Safety Analysis Report-Scheduled or Actual (Actual (Status 4b) when date is followed by R)
Z/ SER = S+aff 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)
(3-31)
C ED
/
L LJ 5
0 2
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2 a
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LACROSSE RL LACROSSE EX SAR 1/
SER 2/
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCliEDULE III-I Classification of NONE 05/01/82 II-1.A Execlusion Area Authority 06/22/81R 07/31/82 (SYS)
Structures, Components and ana Control Systems (Seismic and Quality)
II-1.8 Population Distribution 06/16/81R 07/31/C2 III-2 Wind ar.d Tornado Loadings 08/06/81R 08/30/82 II-1.C Potential Hazards or 07/15/31R 07/31/82 Changes in Potential III-5.A Effects of Pipe Break on 02/24/82R 11/23/82 Harards Due to Structures, Systems and Transportation.
Components Inside Institutional Industrial, Containment and Military Facilities III-5.8 Pipe Break Outside 06/29/81R 11/23/82 II-3.A Hydrolic Description 06/16/81R 11/15/82 Containment II-3.B Flooding Potential and 02/28/82 11/15/82 III-6 Seismic Design NONE 09/15/82 Protection Requirements Considerations II-3.B.1 Capability of Operatina 02/08/82 11/15/82 III-7.5 Design Codes. Design NONE 07/31/82 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 11/15/82 (Ultimato Heat Link (UHS))
V-11.8 RHR Interlock Requirements NONE 03/04/82C (ELEC)
II-4.B Proximity of Capable NONE 06/30/82 Tectonic Structures in VI-7.A.3 ECCS Actuation System NONE 01/29/82C Plant Vicinity VI-10.A Testing of Reactor Trip 06/25/81R 02/16/82C II-4.D Stability of Slopes NONE 08/01/82 System and Enqinonrad Safety Features Including II-4.E Dam Integrity NONE 08/01/82 Response Time Testing II-4.F Settlement of Foundations 03/09/82R 08/01/82 VII-1.A Isolation of Reactor NONE 03/09/82C and Buried Equipment Protection System from Non-Safety Systems.
III-3.A Effects of High Water Level 03/09/82R 04/30/82 Including Qualifications of on Structures Isolation Devices III-3.C Inservice Inspection of Ot/29/82R 10/01/82 VII-2 Engineered Safety Features NONE 03/11/82C Water Control Structures (ESF) System Control Logic and Design III-4.B Turbine Missiles 03/05/82R 05/31/82 VII-3 Systems Required for Safe NONE 03/09/82C III-4.D Site Proximity Missiles 09/15/81R 07/31/82 (ELEC)
Shutdown (Including Aircraf ts)
VII-6 Frequency Decay NONE 09/21/81C III-7.D Containment Strsctural 06/29/81R 03/30/82C Intocrity Tests IX-3 Station Service and Cooling 03/05/82R 05/30/82 Water Systems V-1 Compliance with Codes and NONE DELETED Standards (10 CFR 50.55a)
IX-5 Ventilation Systems 03/09/82R 07/15/82 (MP A-01,A-14)
(3-33)
LACROSSE El (Cont.)
Dil (Cont.)
SAR 1/
SER 2/
SAR 1/
SER 2/
TCPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE VI-1 Organic Materials and Post 02/19/82R 04/30/82 XI-2 Radiological (Effluent and N3NE DELETED Accidant Chemistry Process) Monitoring Systems (HRR B-67)
E11 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 05/15/82 07/15/82 or Safety Valve Dif fusion Characteristics f or Accident Analysis XV-3 Loss of External load.
06/26/81R 11/13/81C Turbine Trip, Loss of Con-III-4.A Tornar o Missiles 04/02/82 05/30/82 denser vacuum, Closure of i
Main Steam Isolation Valve III-4.C Internally Generated 03/05/82R 04/30/82 (EWR), and Stam pressure Missiles Regulator Failure (Closed)
III-8.A Loose Parts Montroring and NONE 02/09/82C Core Barrel Vibration XV-4 Loss of Non-Emergency A-C 06/26/81R 10/21/81C j
Nonitoring(NRR B-60 C-12)
Power to the Station Auxiliaries IV-2 Reactivity Control Systems NCHE 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 0 3/11/82R 07/15/82 VI-2.D Mass and Energy Release for NONE 05/15/82 Seizure and Reactor Coolant Possible Pipe Break Inside Puma Shaft Break Containments XV-8 Control Rod Misoperation 02/26/82R 03/25/82C VI-3 Containment Pressure and NONE 05/15/82 (System Malfunction or Heat Removal Capability Operation Error)
VI-4 Containment Isolation NONE 06/01/82 XV-9 Startup or an Inactive Loop 08/25/81R 06/01/82 or Recirculation Loop at an (SYS)
System 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 A. Potential Equipment NDHE 02/26/22 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 02/28/82 05/01/82 XV-13 Spectrum of Rod Drop 02/26/82R 03/25/82C l
IX-6 Fire Protection (MP B-41)
NONE 09/30/82 (SYS)
Accidents (BWR)
(DOSES) 02/26/82R 05/01/82 XI-1 Appendix I(MP A-02)
NONE' DELETED J
(3-34)
LACROSSE Ell (Cont.)
SAR 1/
SER 2/
TOPIC ND. TITLE SCHEDULE SCHEDULE XV-14 Inadvertent 0poration of 08/25/81R 06/01/62 ECCS and Chemical and Volume Control System Malfunction that Increases Reactor Coolant Inventory XV-15 Inadvertent Opening of a 06/30/81R 0 9/21/81C PWR Pressuring Safety-Relief Valve or a BWR Safety / Relief Valve XV-16 Radiological' Consequences 03/09/82R 05/01/82 of Failure of Small Lines Carrying Primary Coolant Outside Containment XV-18 Radiological Consequences 02/28/82 05/01/82 of Main Steam Line Failure Outside Containment (BWR)
XV-19 Loss-of-Coolant Accidents 02/28/82 07/15/82 (SYS)
Resulting from Spectrum of (DOSES)
Postulated Piping Breaks 02/28/82 05/01/82 Within the Reactor Coolant Pressure Boundary XV-20 Radiological Consequences 03/12/82R G5/01/82 of Fun! Damaging Accidonts (Inside and Outside Containment)
J/ 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
( Ac,tual ( status 4a, 5, 7) when date is followed by C) 1/ Desiginated number of days from receipt of licenseo SAR (Notet if Licensee SAR is received then date is from receipt of additional information requested)
(3-35)
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U.S. 90UCLEAR REGULATORY Chlh000SION (7 771 BIBLIOGRAPHIC DATA SHEET NUREG-0485 Vol. 4 No. 4
- 3. TITLE AN D SUSTITLE (Add vedume Na. if aprenearl
- 2. (Leere 6/m*/
- 3. RECIPIENT'S ACCES$10N NO.
Sptematic Evaluation Program Status Sunnary Report
- 7. AUTHORISI
- 5. DATE REPORT COMPLETED
- T" May 1982
- 9. PE RFORMING ORGANIZATION NAME AND MAILING ADDRESS (inctucir 2,p Codel DATE REPORT ISSUED Office of Resource Management May 1982 Office of Nuclear Reactor Regulation e g,,,,,,,,. ;
U.S. Nuclear Regulatory Commission Washington, D.C.
20555 a st,a, u-*/
- 12. SPONSORING ORGANIZATION NAME AND MAILING ADDRESS (factuele 2 odel p
Office of Resource Management i: CONTRACT NO.
Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Connission Washington 0.C.
20555
- 13. TYPE OF REPORT PE RIOD COVE RED (Inclusive derrst April 1-30, 1982
- 15. SUPPLEMINTARY NOTES 14 (Leere W e */
- 16. A'*.STR ACT 000 words'or less)
The Systematic Evaluation Program is intended to examine many safety-related aspects of eleven of the older light water reactors. This document provides the existing status of the review process including individual topic and overall completion status.
- 17. KE Y WORDS AND DOCUMENT AN ALYSis 17a DESCRIPTORS 17b IDENTIFIE RS'OPEN-EN DE D TE RMS 18 AV AILA8 LITY ST ATEMENT 19 SE CURITY CLASS (7n,s recorrt 21 NO OF P AGES Unc1assifind Unlimited 2Ynclassi fied ECURITY CLASS IThes pege) 22 PRICE S
NCCFORM 335 (7 77)
- U.S. GOVERNMENT PRINTING OFFICE: 1982 361-302/530
UNITED STATES l
I NUCLEAA RECULATORY COMMissitN W.SHINGTON, D. C. 20996
.. MuhEAR masuwomy OFFICI AL aOSINESS FENALTY FOR PRIVATE USE.3300 L
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