ML20049H823
| ML20049H823 | |
| Person / Time | |
|---|---|
| Issue date: | 02/28/1982 |
| From: | NRC OFFICE OF MANAGEMENT AND PROGRAM ANALYSIS (MPA) |
| To: | |
| References | |
| NUREG-0485, NUREG-0485-V04-N01, NUREG-485, NUREG-485-V4-N1, NUDOCS 8203040140 | |
| Download: ML20049H823 (92) | |
Text
.
NUREG-0485 Vol. 4, No.1 January 31,1982 e
SYSTEMATIC EVALUATION PROGRAM STATUS
SUMMARY
REPORT UNITED STATES NUCLEAR REGULATORY COMMISSION p ** "'*%,,
s f
1 8203040140 820228 okB5R PDR
I 1
I l
l Available from NRC/GPO Sales Program i
Sin >erintendent of Documents Government Printing O f fice Washington, D. C. 20402 A year's subscription consists of 12 issues for this publication.
Single copies of this publication are available from National Technical Information Service, Springfield, VA 22161 Microfiche of single copies are available from NRC/GPO Sales Program Washington, D. C. 20555
NUREG-0485 Vol. 4, No.1 1
January 31,1982 l
l SYSTEMATIC EVALUATION PROGRAM STATUS
SUMMARY
REPORT l
Prepared for: 0FFICE OF NUCLEAR REACTOR REGULATION Prepared By: OFFICE OF MANAGEMENT AND PROGRAM ANALYSIS UNITED STATES NUCLEAR REGULATORY COMMISSION
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Y William T. Russell, Chief Dennis M. Crutchfield, Chief Systematic Evaluation Program Branch Operating Reactors Branch 5 0f f u Reactor Regulation Ofe f u ear R tor Regulation
TABLE OF CONTENTS SECTION I SECTION 11 SECTION 111 1-2 to 1-3 BIG ROCK POINT 2-2 to 2-5 PALISADES 3 2 to 3-3 SEP TOPIC LIST DRESDEN 1 2-6 GINNA 3-4 to 3-6 DESIGN BASIS EVENT 14 DRESDEN 2 2-7 to 2-10 DRESDEN 2 3-7 to 3-10 GROUP DESCRIPTION GINNA 2-11 to 2-14 OYSTER CREEK 3-11 to 3-13 DEFINITIONS OF STATUS 1-5 HADDAM NECK 2-15 to 2-18 MILLSTONE 1 314 to 3-17 LACROSSE 2-19 to 2-22 SAN ONOFRE 3-18 to 3-21 SEP TOPIC
SUMMARY
1-6 MILLSTONE 1 2-23 to 2-26 BIG ROCK POINT 3-22 to 3-25 STATUS REPORT OYSTER CREEK 2-27 to 2-30 HADDAM NECK 3 26 to 3-29 PALISADES 2-31 to 2-34 PROGRESS TOWARD 17 YANKEE ROWE 3 30 to 3-33 COMPLETION (Graph)
SAN ONOFRE 2-35 to 2-38 LACROSSE 3-34 to 3-37 IN TEGRATED PLANT l-8 SAFETY ASSESSMENT SCHEDULE SEP TOPIC STATUS BY 1-9 REVIEW DIVISION (Summary Table)
SEP TOPlc STATUS BY 1-10 to 1-11 REVIEW DIVISION (Graphs)
SEP TOPIC SUBMITTALS 1-12 thru 1-13 BY LICENSEES (Graphs)
l mumme Z
O AO Lu M
SYSTEMATIC EVALUATION PROGRAM TORIC LIST Ytetc #
Y1 Tt t topic p grg toptc #
fg IV-2 teactivity Control Systeas Inchetag f unctional
!!.I A. E sclusion Area Avtsortty and (natrol gig.4 A T Or*** M ' SS
- i" vests:t and Protection Agatest 5tagle Failwres B. Population Distributton
,1v 3
$=st Jet Pises Operating Indications f. potential Haaards or C*ianges in Potential
- 'D'"*"""I" W-1 Cons:llance with Codes aad Staadards (10 Cft Naaerk Dae to f ransportation. I nst it ut ional 50.55a )
inestrial, and Military f act ittees ggg,4 c, g,g,,,, g y, g,,,,,g,o,,5 g i g,,
1 T-2 Applicable Code Cases 11-2 A. Severe seather Phenomena V. 3 0=erpress rtsation Protect ton
- 8. Onsite Meteorolog1 cal Measurements Program 8*4 Ptatng and Saf e End Integrity C. Atmospheric t ransport and Dif f aston Charac-teristics f or ACc6 dent Analysts g, $,te Premioity Missiles (locteding Atrcraf t)
V-5 Reactor Coolant Pressure Soundary (BCF8) leakap. Detection on Structu es. Systens
- D.
AvailabtInty of Meteorological Data en the ggg-5 A. Ef fects of Pipe Bream r
Control Room and Cons c7nts Inster Conttiment V-6 acettoe Vessel Integrity
!!.3 A. Hydrologic Description
- 8. P ope Bresi Outside Containment g
W-8*
Steae Generator (5G) !=tegrtty I'
- 8. flooding Poteat tal and Protect ton teowire.
seats V-9 Gesctor Core Isoletten Cooling System (Busi)
))Id A. Inservice lhpection. Including Prestressed 1.
Capabiltty of Operating Plant to Cope Concrete Containaents with titner Grouted V.10 A. awa heat E nchanger Tube f ativres with Desty Basis f fooding Conditicas or yngrouted Tendons
- 8. An9 peliebtitty C. Saf ety-re'ated water Supply (ult tsete Heat
- 8. Destr Codes. Destr Criterta. Load
$ive (UMS))
Coneinattens. and Reactor Cavity cesty V-11 A. #egstrements for Isolation of Mtp ene Los Criterte Pressure Systees ll-4 f.cology and setser, log C. Delaminatton of Prestressed Concrete Con-
- 8. RHR Interloct Sequirements A. Tectonic Province tatnaent Structores V-12 te P tt of Sotling Water teactor
- 8. Premietty of Capable Tectontc Structures D. Contattv:ent Structural lategrity Tests in Plant vicinity 111 8 A. L oose Parts Monttoring and Core Barrel V.13 hater Maawr C. Historical Setselcity within /00 Miles of itbration Monttor eng Pla nt V I-l Organic Materials and Post Accident
- 8. Control Rod Drtve Mechantse Integrity C heet s t ry
- u. Stability of Slopes C. Irradiation Daeage. Use of Senstt taed VI.2 A. Pressure-5uppression Type BelR Containments Stainless Steel and f atspe Resistance
- 8. Subcompartment Analysts E. Das Inte9rtty
,3. Core Supports and f uel Integrity C. Ice Condenser Containment F. Settlement of f oundations and 8v ied r
til-g.
Support Integrity E qu ip.ent D. Mass and Laery Release f or Possible P1pe 111-10 A. Theraial-Overload Protect ton f or Motors of B reak Inside Containment
!!!.1 Classification of $t:vctures. Coas onents and Motor-oper ted valves Setens (keismic and Quality)
- 8. Pug f lywheel lategrity Vl.3 Contatament Pressere and Heat Resonal Capability 111-2 Wind and f ornado loadings t@ Purts and Discharge Valves VI.4 Cont.tnaent isolation Systee
!!!-3 A. if f ect s of H $ heter level on $tructureg
!!!-11*
C ogonent Ir.tegrity V I.5 Contivsti%1e Gas Control
- 8. Structural and Other Conseguen(es (e.g.
V14 Containment Leak Testing I looding of Saf ety-helated I quipment en e
111-12 tavtronerstal tjueltf station cf Saf ety Belated 84wo at s) of f ailure of underdrain Syst e.a t ou tpment C. Inservice lespection of Water Control Struc.
IV-1 A. Operet ton with le.s f nan All Loccs in-Service tures 1-2
SYSTEMATIC EVALUATION PROGRAM TOPIC LIST TCPIC a flit t NP!C $
Tl Tt[
TOPIC i M
V I-7. A
- 1. (CC5 Pe-evaluat ton t o Account f or increased v g g.g Instruments f or monitoring Radiat ton and Process IV-5 Loss cf 16ernal Fee *ater Flam Vessel Head legerature Vertedles During Acctdents IV-6 Feed ater System Pipe Greats Inside and Outstar
- 2. Upper Plenue Injection Vll-6 f requency Decay C ont a t ament (Pd )
- 3. f CC$ Actuetton System Vll-I Acceptability of Setag Bus Des 191 on $d-4 IV-7 Reactor Coolant Pug Rotor Settu e and r
Plant s peactor Coolant Puse Shaf t Oreat
- 4. Core Spray hoaale f f fectheness V! t t-1 A. Potent tal toutpment F atlures Assoctated = ttR If-8 Control tod ptsoperetton (5ystee Malfunction VI F.B E5F Switchover f rom Injection to Rectrtulat ton a Degraded (" arid Volta 9e or Operator Error) mode (Automette LCC5 Realignent)
VIII-2 Onstte toergency power Systees - Diesel IV-g Startup or an inacttee Lony or Rectrculation V I 7.C (CC5 56agle Fat tore Criterion and Require-Geaerator Loap at an t acerrect f eet erature, aad F lom u lfunctica Causing an inctease in eents f or Loca ing Out Power to Valves C ont rolle r a
including ladependence of Interlocks on Vii t-3 A Station Battery Capacity f est Requirements
$d Core F low Sate I V-10 Cheetcal and Volume Control System malfunction
- 8. DC Power System Bus Voltage Monitortag and that tesults in a Decrease ta the Saran Concem-
- 1. Appendi s c - Electrical Instrumentation Ann 6 mct at ion tration in the Reactor Coolant (Pe) and Control (EIC) Re-reviews V111-4 Electrical Penetrations of Reactor Contatasent n V -I l Inadvertent Loadtag and Operation of a f uel
- 2. Fallure Mode Analys ts - ICC5 Assently in am lepruper osition 5tm
- 3. The Ef f ect of Pd Loop Isolation valve XV-12 Spectrue of Rod Ejection Acttdents (PW)
Closure During a LOC A on ECC5 Performance 11-2 Overhead Mandling Systems - Cranes V I-7.0 Long Term Cooling - Passive F ailures (e.g.
tv.13 Spectrue of Rod Drop Acciaents (84)
Floodtog of Redundant Components)
II-3 Station Service and Cooling water Systems IV-14 Inadvertent Operetton of ECC5 and Cheetcal V I-1.E ECCS Svan Design and Test f or Rectrculation 11-4 Boron Addttton System and Volume Control Systes malfunction that I "C"* * " ' "'#
8""I"' "
13 5 ventilation Systees V !- 7.F c a 1 Isolation Valves Power and Control IV-15 Inadvertent Opent ne of a Pidt Press.rtaer Safety.
11-6 Fire Protect @
Rettef Valve or a 8d Safety /nelief valve VI-8 Control Room Habitability I
Austitary Feed.ater Systes g
g y
Lines Carrytag Primary Coolant Outside Contato-VI g Main 5 team Line Isolation Seal System - 8e XI-1 Appendts I ment VI-10 A. Testing of Reactor Trip System and Engineered a g.2 Radiological (tf fluent and Process) Monttos'ing IV-ly Steam Generator Saf ety Features including Response it**
Systems Tuoe f atIsre (Pd) f est ing 3111-1 Conduct of Operations 14-16 Radiological Consequences of mata 5 team
- 8. Shared Engineered Safety Features. On-s ste Line Fatlure Outster Contataneet (8d) terrgency Power and Servtce Systess for E111-2 5af etards/In&strial securtty Multiple Unit Factittles IV-19 Loss-of-Cociant Acctdents Resulting f ree IV.I Decrease 6n Feco.ater legeratu e. Increase in Spectrue of Postulated Piptog Breaks htthis r
Vit-l A. Isolatton of Reactor Protectton System f roe
,,,o,ater F in, tacrease in 5tese Flow and the Reactor Coolant Pressure Soundary Non-Saf ety Systems. InClud+ng Qualifications inadvertent Opening of a steam Generator Reitef of Isolation Devices or Saf ety Valve IV 20 Radtologtcal Consequences of f uel Damaging Accidents (Instde and Outside Contatament)
B. Trip Uncertainty and Setpotnt Analysts Review IV.2 5p,ctrue of Steam System Piping Fatleres lostde IV-21 spent Fuel Cask Drop Accidents of Operettag Data Base and Outside of Contatanent (Pow)
Engineered Safety Featu es (I5F) System Control IV.3 Loss of E sternal Load. Turbine Trip. Loss of "I D*
Vll-2 r
Logic and Design condenser Vacuum. Closure of Main Steam isola-IV-23 nuittple Tube Fat teres in 5tese Generators tion Valve (ed), and Steam Pressure se,1stor VII-3 Systess Required f or Safe Shutdown Failure (Closed)
IV-24 Loss of All A-C Power V i t-4 E f fects of Fatlure in hon-Saf ety Related
-Ener9ency A-C Power to the Station Iul Techatcal 5pectf tcations systeas on Selected E ngineered Saf ety Features Iv!!
Operational QA Progras
- Topic deleted from SEP proaram dte to duplication by Three Mile Island (TMI) NFIC Action Plan. Unresolved Safety issue or other SEP Topic per May 7.1981 letter from G. Lainas to all SEP t ecen 1-3
DESIGN BASIS EVENT REVIEWS THIS SECTION DEFINES DESIGN BASIS EVENT (DBE) REVIEWS FOR THE ELEVEN SEP FACILITIES N; :6! 'Of!C List s.a Det Tast: List s.e 4 %e pat WIC ttP, 8 poert a c Traas' eat Geoups Acc+oert aad Treasieet Groon l
l 7,,IT l t.st Ty!C TITLE DE! T08!C I a Det. =*E yM Gro.5 I sv-1 Decrease ta leed=eter taccerat re F Loct.s Gro4 1 so-1 Decrease in 'eee. ster t empeesta e (s=L s v-1 Iacrease sa feemater flow am--
u-3 a
- yerelogic eescriptica r
LNal_
sv-i sacrease 1. feemater f1w sv-1 tacrease ta stee fia.
itas riedmg peteattal aae pretect+a.
s u-1 Increase in steen flo.
so-g start-a of teac ttee loop and flow reg.t re eats (capatili ty c' operet tag so-1 Inadverteet opentag of steam coatroller mal'e ction staet to cope eita oestga tests floodtag a
generator reisef safety valve a t-3
!aaeserte*t closure of mata steen coaar t toal a s-9 Start-wo of taactive loop tsolat'on valve
)-3 C 54*ety related =ater swooly 1.1timate t
hea t s t a6 )
a d-13 Syster malf. action ca-stag Gr_oug s e-3 Loss of enternet Ic.ad su-3 T rotae trt, s d-3 Loss of conceaser vacus 11-4 a Tectonic proviace Te tSee trip si t splc Gros !j a s-3 Loss o* esteraal load s v-3 r
It-a.s Proniet ty of capante tectonic stewctu es e
sv 3 Loss of condenser vaci.e Id-3 5 team preswre reg.1stor faits e near plant e
au-3 Steae pressure regulator f a t ).re as-5 Loss of feea.atee flow II-a.C mstorical setssictty.6 tate M0 sites of plaat s o-5 Loss of feea ater flow u s -6 fees. ster syster p+pe trese Grow !!!
n o-18 aadiologtcal Coasesveaces of a 11 4 :
Stant11ty of stooes arain 5 team Line f ativ*e outside Grw !!!
s s-2 ster line creas instae coetaterwat Coata t ascat w;sstt GtuuTIch 111-4 a Tornado missiles o tHae misstles 58-2 Ster 1tre breas outside coetainrent so MO*tct:an III-4 8 T
r 5, tere 411y generated missilet group Jv s d-4 Loss o* AC power to station
- { l]-4 c te prostetty eisstles (tacivding G_ r_o =2_.! v In-4 Loss of AC powee to statton apiliaries g i t.4,3 a tecraf t) sai11 aries Group V s #- 7 Loss cf forted Coolaat flo*
g
!!]-2 eiad aad tornado loadtag Peseary pu s rotor sef sw e e
r
@ron V uv 7 Less of forced coolant flow sv-7 Primary pw e saaf t break se-7 prtma*y pep rotor setsure sv4 r
Primary pu p shaf t break uacontrot ted rod asserely witaccanal a b- ?
m Group _vl I V-8 Gro ; 41 s v-8 uncontrolled rod asserely. th-at po-ee dramal at power sV 6 Unco
- trolled rod asserely witN!ramat sv-8 uncoatrolled roe asserely with-los po er start-up dra al low power start-up sv-8 Coatrol rod stsoperettoa sv B Coatrol rod otsoperation sv-1)
$pectre of rod drop acct $erts sv.12
$pec.tr# of rod ejec tion acC tdents Grog ~VII sv-1g Spectre of loss of coolant accidents froup 1H s h 19
$pectra of loss of coolaat accidents Group VIII Grova v!!!
Iv-23 Radiological Coasequences of reel Iv-20 Radiologtcal Coasequences of F e1 Daaestag Acctaents (tastee and outstds coatriaceat)
Damagtag Acctdeats (tastde and outside containneat) trup_lu su-H
!aadvertent coeatag of Pwa ad H Inadverteat opening of 3.a safety /
Group in rettef valve pressertser re'ief valve kroup s f-t a Inadvertent operattoa of ECC$
GroujL s 58-14
!aadvertent operattoa of (CCS Or CvC1 malfwattloa that caeses sa Gro_d sv 11 laadnertent loading avut operattoa of a f I asicaely la sa taproper 4 ;ase ta cootaat saveatory G, r,oAM hot applicable to Pld's Grq ~III not appitcaele to sees Gr2 ; s11 sb17
$ter Generator Tube f ailu e r
14
~
l l
l STATUS DEFINITIONS l
G - Generic 4a-Draf t SE Received From Review Branch These topics are being evaluated as part of on-going N R C generic review effort. The ongoing This status is used for internal NRC tracking of generic review and the SEP topic review will be topic review progress. The status indicates that closely integrated to improve the effectiveness a draf t topic safety evaluation is under mange-and efficiency of these efforts and to menemste ment review.
I any impact on !icensees. The status and conclu-sions of generic SEP topics will be incorporated in the final safety assessment for each plant.
4b - SAR Received from Licensee Licensee has submitted a Safety Analysis Report X - Deleted (S AR) in accordance with SEP redirection. (See Eisenhut letter to SE P owners of January 14,1981)
These topics have been verified as not applicable The S AR is under review and a Final NRC safety to the design of a specific plant or ar being evaluation (status 7) is being prepared. Draf t SE duplicated by the N RC TMI Action Plan, will not be issued for topics with licensee SA R submittal.
Unresolved Safety issue or another SEP Topic per the May 7,1981 letter f rom 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 aid 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 N RC posi-tions.
1 - Questions Received From Review Branch 6 - SE Response Received This status is used for interaal NRC tracking by NRC of topic review progress. The status indicates that all information necessary to perform a The dratt SE has been reviewed and licensee topic evaluation is not available and that ques-comments if eny have been formally transmitted tions have been developed and sent to the SEP to the N RC.
branch.
7 - Topic Complete 2 - Questions Sent to Utility The NRC topic evaluation has been completed and a final safety evaluation issued. A topic is completed The questions developed in the previous status in severai ways: (1 ) The licensee has responded have been formally transmitted to the licensee that thw NRC draf t safety evaluation (i.e. status 5) as a request ;or additional information.
is correct, or (2) the licensees comments on the NRC draf t safety evaluation (i.e. status 6) have been re-3 - Questic,n Response viewed and if appropriate incorporated into the Received by N RC final safety evaluation, or (3) the licensee has not responded in the time requested, thus concurring The licensee has formally responded to the informa-that the draf t safety evaluation is correct.
tion request issued by NRC regarding the topic.
15
SEP TOPIC STATUS
SUMMARY
REPORT *
' \\
\\
NUM3ER OF QUESTIONS QUESTION DRAFT SE SAR SE N
TOPICS TOPIC RECEIVED QUESTIONS
RESPONSE
RECEIVED RECEIVED DRAFT SE
RESPONSE
TOPIC
\\
GENERIC DEL ETED NOT FROM SENT TO RECEIVED FRCM FROM SENT TO RECEIVED COMPLETE
\\
(G)
(X)
STARTED REVIEW UTILITY BY NRC REVIEW LICENSEE UTILITY BY NRC (7)
PLANT NAME
\\
(0)
BRANCH (2)
(3)
BRANCH C4b)
(5)
(6)
\\
(1)
(4a)
\\
PALISADES 1
47 0
0 0
1 0
0 6
12 70 GINNA 1
45 0
0 0
1 0
4 12 14 60 DRESDEN 2 4
50 2
0 1
to 7
7 4
5 47 OYSTER CRE2K 4
54 2
0 13 2
6 7
8 6
35 MILLSTONE 1 7
51 0
0 0
7 3
14 4
5 46 SAN ONOFRE 4
48 1
1 5
7 3
13 15 1
39 BIG ROCK POINT 4
53 to 0
6 to 2
11 1
4 36 HADDAM NECK 7
47 6
0 1
9 1
31 2
5 27 YANKEE ROWE 4
48 9
0 4
11 4
21 2
5 29 LACROSSE 4
54 20 0
9 8
3 11 3
0 25 DRESDEN 1 TOTALS THIS MONTH 40 497 51 1
39 65 29 120 57 57 414 TOTALS LAST MONTH 43 497 50 5
24 79 20 136 61 53 402 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.
1-6
SYSTEIVIATIC EVALUATION PROGRAM GOAL PHASEIIF
-1/ Not including Dresden 1 Progress Toward Complet. ion ACTUAL 100 %
100
^
p 7
-82
/
,/
90 f
,o
/
1 m nth 3% /
80 gL 75%
p 76%
70%
g 70 67 72%
- 61 %
/
p H
/
.Note: Prior to November 30,1981 the Z
60 60 %
weighted percent did not include b
' 81
/
generic topics in the progress g
j y
/
toward completion.
a 50
,, /
54%
l y
,/
47%
I
' f l
O 44%
s u'
40 42%
S p/
40%
l
,- /
ses 30
- J 30% (estimated)
The plant topic overall completion status (percent complete) is calculated Status Weighting Factor
~
based upon the number of topic reviews to be performed (not including X
Not included deleted topics) and a weighted average of current topic review status.
G.0 0%
20 The calculation is performed using the following formula:
1,2,3 35%
l 4a.4b 80 %
Percent Complete = Sum of Topics in Status x Weighting Factor of Status 5,6 90%
7 100%
10 Sum of Topics O
rn 10 11 12 1
2 3
4 6
7 8
9 10 11 12 1
2 3
4 5
6 7
8 9
FY-81 FY-82 1-7
M Naw ZU M
nW aC M
CL m
w bdO Q.
W E
'OGG H
TL Z
ar-3 W
> 4J E
O3
^
m 6A E
M CL 8
w G
m G.C CD &
att oc
>=
HH Hw LA.
MC W
H k
a CL Qw H
ew
&E e-o l
l
l SEP YOPIC STATUS by REVIEW DIVISION
SUMMARY
TABLE PLANT PALISADES GINNA DRESDEN OYSTER MILLSTONE SAN BIG HADDAM YANKEE LACROSSE TOTAL 2
CREEK I
ONOFRE ROCK NECK ROWE POINT (IAPM) l/
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 50 54 51 48 53 47 48 54 497 I
APPLICABLE 90 92 87 83 86 89 84 90 89 83 873 57
/
39
/
32
/
31
/
29
/
31
/
28
/
26
/
29
/
23
/
325 /
DL
/
/
/
/
/
/
/
/
/
/
/
/ 57
/ 39
/ 36
/ 35
/ 37
/ 40
/ 38
/ 38
/ 38
/ 35
/ 393 TECHNICAL
/
/
/
/
/
/
/
/
/
/
/
16
/
17
/
8
/
7
/
11
/
6
/
3
/
4
/
6
/
3
/
81
/
REVIEW DOE
/
/
/
/
/
/
/
/
/
/
/
/ 18
/ 21
/ 22
/- 20
/ 21
/ 18
/ 17
/ 21
/ 21
/ 21
/ 200 ASSIGNMENT 1/
/
/
/
/
/
/
/
/
/
/
/
l 15
/
31
/
22
/
19
/
18
/
20
/
12
/
8
/
6
/
5
/
156 /
\\
DSI
/
/
/
/
/
/
/
/
/
/
/
/ 15
/ 32
/ 29
/ 28
/ 28
/ 31
/ 29
/ 31
/ 30
/ 27
/ 280 l
l
/
/
/
/
/
/
/
/
/
/
/
88
/
87
/
62
/
57
/
58
/
57
/
43
/
38
/
48
/
31
/
562 /
COMPLETE
/
/
/
/
/
/
/
/
/
/
/
/ 90
/ 92
/ 87
/ 83
/ 86
/ 89
/ 84
/ 90
/ 89
/ 83
/ 873
/
/
/
/
/
/
/
/
/
/
/
TARGET DATE -
ALL TOPICS JAN 82 JAN 82 OCT 82 MAY 82 JUN 82 DEC 82 JUL 82 OCT 82 AUG 82 NOV 82 IECHNICAL REVIEWS TO DL 1/ Division of Licensing Integrated Assessment Project Manager 2/ Deleted as not applicable, or duplicated by USI, TMI Action Plan, or another topic.
A/ These schedules and assignments are consistent with NRR FY 1982-1984 Operating Plan.
- No. Completed / No. Assigned I/
l
_/ l t-9 STATUS AS OF JANUARY 31, 1982
PROGRESS OF TOPIC REVIEUS DIY!!!DN 7 LICDGIC TT!CS 438 l
TM
~~
W ""~
,,9 l
ACTUAL y~
- gg ISS --
IN --
g_
8 M
JJ.
AT.
SEP OCT EV E
JAN FEB IWI APR stay M Jul/Dec IOdTH Target 10 14 20 17 7
3 4
3 66 E R MMTH 1
10 3
4 7
g ig Actual y,,,
309 323 343 360 367 170 374 377 393 CUMULATIVE 281 291 294 298 305 314 325 Actual PROGRESS OF TOPIC REVIEWS 3
DIVIS!38 F EEllEERIE TFICS 250 TARET 2N --
m e#,#
/,a 158 - ~
j
/
/
/
,/
1N - ~
3 i
g M
JAN FD lear art itAY ADI Jul/Dec IOffH l
Tarpt 2
2 40 36 21 6
2 7
11 i
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0 2
0 0
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Actual y,,,
75 77 117 153 174 180 182 189 200 Actual 70 70 72 72 72 75 81
PROGRESS OF TOPIC REVIEWS O!VISI@ W SYSTEMS INTEGRATI(h TCPICS YA TMtGli 3gg _
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10 14 27 28 13 Yarpt 131 166 201 231 246 261 264 274 280 CUMut ATIVE Actuas 61 64 74 88 115 143 155 PROGRESS OF TOPIC REVIEWS 5
TOTAL noJECT TIFICS LM TAfET
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LICENSEE TOPIC SUBMITTALS CIVI$10M OF LICDS!IC EamelTTALS TAmCET 3-y------=*~~~
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Jim JLL AUG SEP OCT MDV DEC JAN FEB MAR AMI st4Y Jtm Jtt IENTHE T rpt 1
SS 26 20 27 a
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33 se 124 144 171 175 133 137 137 137 igg
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I Z
O O
Lu G0
BIG ROCK POINT FACILITY: BIG ROCK POINT 1 TOPIC NO.
REVIEW STATUS REMARKS DIV/BR LICENSEE: CONSUMERS POWER 11-1 A.
DL/SEPB 7
CPCo to hRC 09/02/80 REGION /LCCATION: 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 POWER CAPACITY: 0240(THERMAL) 067(ELECTRICAL)
II-2 A.
DSI/AEB 7
NR* to CPCo 08/03/81 OL NUMBER: DPR-6 II-2 B.
X NRC to CPCo 05/07/81 II-2 C.
DSI/AEB 0
II-2 D.
X NRC to CPCo 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL II-3 A.
DE/HGEB 2
NRC to CPCo 01/11/82 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD II-3 B.
DE/HGEB 2
NRC to CPCo 01/11/82 OPERATING REACTORS PROJECT MANAGER: R. EMCd II-3 B.
1.
DE/HGEB 2
NRC to CPCo 01/11/82 INTEGRATED ASSESSMENT PROJECT MANAGER: P SCHOLLy.j II-3 C.
DE/HGEB 2
NRC to CPCo 01/11/82 II-4 DE/GSB 7
NRC to CPCo 06/08/81 KEY FOR STATUS CODES II-4 A.
DE/GSB 7
NRC to CPCo 06/08/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.
DE/GSB 3
FROM REVIEW BRANCH II-4 C.
DE/GSB 7
NRC to CPCo 06/08/81 X - DELETED Ab-SAR RECEIVED FROM 0 - TOPIC NOT LICENSEE II-4 D.
DE/HGEB Gb CPCo to NRC 10/05/81 STARTED 5 - DRAFT SE SENT II-4 E.
X NRC to CPCo 11/16/79 1 - QUESTIONS RECEIVED TO UTILITY II-4 F.
DE/HGEB 4b CPCo to NRC 10/19/81 FROM REVIEW BRANCH 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC III-1 DL/SEPB 3(Sys)
CPCo to NRC 12/29/81 DL/SEPB 7(ELEC) HRC to CPCo 08/19/81 TO UTILITY 7 - TOPIC COMPLETE III-2 DL/SEPB 3
CPCo to NRC 07/09/81 3 - QUESTION RESPONSE RECEIVED BY NRC (2-2)
BIG ROCK POINT TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR III-3 A.
DE/SEB 3
CPCo to SRC 08/09/80 111-10 B.
X hRC to CPCo 11/16/79 III-3 B.
X NRC to CPCo 12/26/80 III-10 C.
X NRC to CPCo 11/16/79 III-3 C.
DE/AGEB 4b CPCo to NRC 12/21/81 III-11 X
NRC to CPC0 c5/07/81 III-4 A.
DSI/ASB 0
III-12 X
NRC to CPCo 05/07/81 III-4 B.
D E/ MT EB 0
IV-1 A.
DL/SEPB 7
NRC to CPCo 10/08/81 III-4 C.
DSI/ASB 0
IV-2 DSI/ICSB 6
CPCo to NRC 12/22/81 III-4 D.
DE/SAB 4b CPCo to NRC 12/14/81 IV-3 X
NRC to CPCo 05/04/81 III-5 A.
DL/SEPB 3
V-1 DE/MTEL X
NRC to CPCo 11/27/81 III-5 B.
DL/SEPB 2
NRC to CPCo 01/04/80 V-2 X
NRC to CPCo 11/16/79 III-6 DL/SEPB 2
NRC to CPCo 01/19/82 V-3 X
NRC to CPCo 05/07/81 III-7 A.
X HRC to CPCo 05/07/81 V-4 X
NRC to CPCo 05/07/81 III-7 B.
DL/SEPB 3
CPCo to NRC 07/09/81 V-5 DL/SEPB 7
NRC to CPCo 09/30/81 III-7 C.
X NRC to CPCo 11/16/79 V-6 DL/SEPB 7
NRC to CPCo 03/05/80 III-7 D.
DE/SEB 4b CPCo to NRC 12/29/81 V-7 X
NRC to CPCo 11/16/79 III-8 A.
DSI G
NRC to CPCo 05/07/81 V-8 X
NRC to CPCo 05/07/81 III-8 B.
X NRC to CPCo 09/26/80 V-9 X
NRC to CPCo 11/16/79 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 7
NRC to CPCo 05/13/81 III-9 X
NRC to CPCo 05/07/81 V-11 A.
DL/SEPB 6(Elec) CPCo to NRC 11/11/81 III.-10 A.
DL/SEPB 7
NRC to CPCo 08/03/81 V-11 B.
DL/SEPB 7(Sys)
HRC to CPCo 05/13/81 7(Elec) NRC to CPCo 08/i9/81 i
1 1
(2-3) l l
BIG ROCK POINT TOPIC HO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.
DL/SEPS 7
NRC to CPCo 10/09/79 VI-7 D.
DL/SEPB 7
NRC to CPCo 08/17/78 V-13 X
NRC to CPCo 05/07/81 VI-7 E.
X NRC to CPCo 05/07/81 VI-1 DE/CEB 3
CPCo to NRC 07/12/79 VI-7 F.
X HRC to CPCo 11/16/79 VI-2 A.
X HRC to PCo 05/07/81 VI-8 X
NRC to CPCo 05/07/81 VI-2 B.
X NRC to CPCo 05/07/81 VI-3 X
HRC to CPCo 11/16/79 VI-2 C.
X NRC to CPCo 11/16/79 VI-10 A.
DL/SEPB 0
VI-2 D.
DSI/CSB 3
CPCo to HRC 04/02/80 VI-10 B.
X HRC to CPCo 11/16/79 VI-3 DSI/CSB 3
CPCo to NRC 04/02/80 VII-1 A.
DL/SEPB 0
VI-4 DSI/CSB 0(Sys)
VII-1 B.
DL/SEPB 7
NRC to CPCo 08/17/78 DL/SEPB 7(Elec) HRC to CPCo 11/24/81 VII-2 DL/SEPB 5
NRC to CPCo 12/31/81 VI-5 X
HRC to CPCo 05/07/81 VII-3 DL/SEPB 7(Sys)
NRC to CPCo 05/13/81 VI-6 D3I/CSB G
NRC to CPCo 01/07/81 DL/SEPB 7(Elec) HRC to CPCo 08/19/81 VI-7 A.
1.
X NRC to CPCo 11/.o/79 VII-4 X
NRC to CPCo 05/07/81 VI-7 A. 2.
X HRC to CPCo 05/07/81 VII-5 X
NRC to CPCo 05/07/81 VI-7 A.
3 DL/SEPB 4a VII-6 DL/SEPB 7
NRC to CPCo 09/21/81 VI-7 A. 4.
DSI/RSB 7
HRC to CPCo 04/10/79 VII-7 X
HRC to CPCo 11/16/79 VI-7 B.
DSI/RSB 7(Elec) CPCo to NRC 10/21/81 VIII-1 A.
DSI/PSB G
NRC to CPCo 05/07/81 0(sys)
VIII-2 DL/SEPB 7
NRC to CPCo 08/28/81 VI-7 C.
DL/SEPB 7
NRC to CPCo 08/05/81 VIII-3 A.
DL/SEPB 7
CPCo to NRC 04/22/81 VI-7 C.
1 DL/SEPB 7
NRC to CPCo 08/05/81 VIII-3 B.
DL/SEPB 6
CPCo to NRC 01/07/82 VI-7 C. 2.
DL/SEPB 7
NRC to CPCo 08/05/81 VIII-4 DL/SEPB 3
CPCo to NRC 11/16/81 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
hRC 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 4b CPCo to NRC 12/10/81 XV-12 X
HRC to CPCo 11/16/79 IX-4 X
NRC to CPCo
!!/16/79 XV-13 DSI/CPB 7(Sys)
NRC to CPCo 12/02/81 DSI/AEB 7a(Doses)HRC 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
HRC to CPCo 05/07/81 XV-15 DSI/RSB 7
HRC to CPCo 08/18/81 X
X HRC to CPCo 05/07/81 XV-16 DSI/AEB 7
HRC to CPCo 12/28/81 XI-1 DSI/ETSB X
NRC to CPCo 12/04/81 XV-17 X
NRC to CPCo 11/16/79 XI-2 DSI/ETSB X
NRC to CPCo 12/04/81 XV-18 DSI/AEB 4b HRC to CPCo 07/01/81 XIII-1 X
HRC to CPCo 05/07/81 XV-19 DSI/RSB 7(Sys)
NRC to CPCo 08/18/81 XIII-2 DL/SSPB 7
NRC to CPCo 03/11/81 DSI/AEB 4b(Doses)CPCo to NRC 07/01/81 XV-1 DSI/RSB 4b CPCo to NRC 07/15/81 XV-20 DSI/AEB NRC to CPCo 01/12/82 XV-2 X
HRC to CPCo 11/16/79 XV-21 X
HRC to CPCo 05/07/81 XV-3 DSI/RSB 7
NRC 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
HRC to CPCo 05/07/81 XV-5 DSI/RSB 4a NRC to CPCo 01/26/82 XV-24 X
HRC to CPCo 05/07/81 XV-6 X
NRC to CPCo 11/16/79 XVI X
NRC to CPCo 11/05/80 XV-7 DSI/RSB Gb CPCo to NRC 07/15/81 XVII DL 7
NRC to CPco 08/17/78 XV-8 DSI/CPB 7
NRC to CPCo 12/31/81 XV-9 DSI/RSB Gb CPCo to NRC 07/15/81 (2-5)
~
DRESDEN1 FACILITY: DRESDEN 1 LICENSEE: COMMONWEALTH EDISON REGION / LOCATION: 9 MILES EAST OF MORRIS, I ll_.
DOCKET NO.
0S000010 POWER 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'CONNOR By lettor dated December 31, 1980 Commonwealth Edison indi-cated that Dresden 1 was undergoing an extensive modifica-tion and was not scheduled for restart until June, 1986.
Also, by 1citor dated April 4, 1981, in response to the NRC's January 14, 1931 Intter on SEP redirection the licen-see stated that the Dresden 1 SEP review is not being actively pursued, i.e.
defered.
(2-6)
DRESDEN 2 FACILITY: DRESDEN 2 TOPIC NO.
REVIEW STATUS REMARKS DIV/BR LICENSEE: COMMONWEALTH EDISON II-1 A.
DE/SAS 7
f.RC to CECO 10/06/81 REGIDH/ LOCATION: 9 MILES EAST OF MORRIS, ILL.
II-1 B.
DE/SAB 7
NRC to CECO 10/06/81 DOCKET NO.
05000237 II-1 C.
DE/SAB 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 B.
X NRC to CECO 05/07/81 N.S.S.S.6 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 B.
DE/HGEB 3
CECO to NRC 01/04/82 OPERATING REACTORS PROJECT MANAGER:
P. C'CONNOR II-3 B.
1.
DE/HGEB 3
CECO to NRC 01/04/82 INTEGRATED ASSESSMENT PROJECT MANAGER: G. CWALINA II-3 C.
DE/HGEB 3
CECO to NRC 01/04/82 KEY FOR STATUS CODES II-4 DE/GSB 7
NRC to Ceco 07/09/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 A.
DE/GSB 7
NRC to Ceco 06/08/81 FROM REVIEW BRANCH X - DELETED II-4 B.
DE/GSB 5
NRC to CECO 07/09/81 4b-SAR RECEIVED FROM 0 - TOPIC NOT LICENSEE II-4 C.
DE/GSB 7
NRC to CECO 06/03/81 STARTED 5 - DRAFT SE SENT II-4 D.
DE/HGEB Gb CECO to NRC 12/08/81 1 - QUESTIONS RECEIVED TO UTILITY FRGM REVIEW BRANCH II-4 E.
DE/HGEB Ga 6 - SE RESPONSE RECEIVED 2 - CUESTIONS SENT BY NRC II-4 F.
DE/HGEB 4b Ceco to NRC 12/08/81 TO UTILITY 7 - TCPIC COMPLETE III-1 DL/SEPC 3(sys)
NRC to CECO 06/26/81 3 - QUESTION RESPONSE DL/SEPB 7(Elec) Part of VII-5 07/07/81 RECEIVED BY HRC III-2 DL/SEPB 3
(2-7)
DRESDEN 2
TOPIC HO.
REVIEW STATUS REMARKS TOPIC HD.
REVIEW STATUS REMARKS DIV/BR DIV/BR III-3 A.
D E/ S EB Ab CECO to NRC 12/08/81 111-10 B.
X NRC to CECO 11/16/79 III-3 B.
X NRC to Ceco 11/16/79 III-10 C.
DL/SEPB 7
HRC to Ceco 05/22/79 III-3 C.
DE/HGEB C
III-11 X
NRC to Ceco 05/07/81 III-4 A.
DSI/ASB 4b CECO to NRC 12/08/81 III-12 X
HRC to Ceco 05/07/81 III-4 B.
DE/MTEB 3
Site Visit 06/01/81 IV-1 A.
DL/SEPB 7
HRC 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 4b CECO to NRC 12/08/81 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 1
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 NRC to Ceco 05/07/81 V-4 X
NRC to CECO 05/07/81 III-7 B.
DL/SEPB 3
CECO to NRC 09/28/79 V-5 DL/SEPB 6
Ceco to NRC 09/02/80 III-7 C.
X NRC to CECO 11/16/79 V-6 DL/SEPB 7
HRC to Ceco 03/05/80 III-7 D.
DE/SEB.
Ab CECO to NRC 04/27/81 V-7 X
NRC to Ceco 05/07/81 III-8 A.
DSI
'G NRC to CECO 05/07/81 V-8 X
NRC to Ceco 05/07/81 III-8 B.
X NRC to Ceco 09/11/80 V-9 N.
NRC to Ceco 11/16/79 III-8 C.
DL/SEPB 6
Ceco to NRC 03/10/80 V-10 A.
DL/SEPB 7
HRC 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) HRC to Ceco 07/10/81 (2-8)
-n.
DRESDEN 2 TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.
DL/SEPB 7
NRC to CECO 04/16/81 VI-7 D.
DL/SEPB 7
hRC to Ceco 08/17/78 l
V-13 X
NRC to Ceco 05/07/81 VI-7 E.
X NRC to Ceco C5/07/81 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 07/03/81 VI-2 D.
DSI/CSB 5
NRC to CECO 12/28/81 VI-10 B.
DL/SEPB 7(Sys)
NRC to Ceco 06/20/81 i
DL/SEPB 7(Elec) CECO to NRC 11/03/81 VI-3 DSI/CSB 5
NRC to Ceco 12/28/81 VII-1 A.
DL/SEPB 7
NRC to Ceco 12/24/81 VI-4 DSI/CSB 5(Sys)
NRC to Ceco 12/18/81 DL/SEPB 5(Elec) NRC to Ceco 12/15/81 VII-1 B.
DL/SEPB 7
NRC to Ceco 08/17/78 VI-5 X
NRC to CECO 05/07/81 VII-2 DL/SEPB 7
CECO to NRC 11/03/81 VI-6 DSI/CSB 4a VII-3 DL/SEPB 7(Sys)
NRC to Ceco 04/24/81 DL/SEPB 7(Elec) NRC to CECO 07/07/81 VI-7 A.
1.
X NRC to CECO 11/16/79 VII-4 X
NRC to CECO 05/07/81 VI-7 A. 2.
X NRC to CECO 05/07/81 VII-5 X
NRC to CECO 05/07/81
.VI-7 A. 3.
DL/SEis 7
CECO to NRC 11/03/81 VII-6 DL/SEPB 7
NRC to Ceco 08/26/81 VI-7 A. 4.
DSI/RSB G
NRC to Ceco 05/07/81 VII-7 X
NRC to Ceco 11/16/79 VI-7 B.
X NRC to Ceco 11/16/79 VIII-1 A.
DSI/RSB G
NRC to CECO 05/07/81 VI-7 C.
DL/SEPB 7
NRC to CECO 03/13/81 VIII-2 DL/SEPB 7
NRC to CECO 06/26/81 VI-7 C.
1.
DSI/PSB 6
CECO to NRC 06/12/81 VIII-3 A.
DL/SEPB 7
NRC to Ceco 07/07/81 VIw7 C. 2.
DL/SEPB 7
NRC to Ceco 03/13/81 VI-7'C. 3.
X NRC to CECO 11/16/79 VIII-4 DL/SEPB 7
NRC to Ceco 11/30/81 (2-9)
DRESDEN 2 TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 3
Ceco to NRC 06/02/80 XV-10 X
NRC to CECO 11/16/79 IX-2 X
NRC to CECO 05/07/81 XV-11 DSI/CPB 4a 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 4a(Sys)
DSI/AED 7(Doses) HRC to CECO 12/28/81 IX-5 DL/SEPB 4a XV-14 DSI/RSB 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/'.6/79 XI-2 X
NRC to CECO 12/04/81 XV-18 DSI/AEB 4a XIII-1 X
NRC to Ceco 05/07/81 XIII-2 DL/SSPB 7
NRC to CECO 03/11/81 XV-19 DSI/RSB 7(Sys)
NRC to Ceco 12/07/81 DSI/AEB 7b(DOSES) CECO to NRC 01/05/82 XV-1 DSI/RSB 7
NRC to CECO 12/29/81 XV-20 DSI/AEB 7
NRC to Ceco 11/20/86 XV-2 X
NRC to CECO 11/16/79 XV-21 X
NRC to Ceco 05/07/81 XV-3 DSI/RSB 7
NRC to CECO 12/04/81 XV-22 X
NRC to Ceco 05/07/81 XV-4 DSI/RSB 7
NRC to Ceco 12/04/81 XV-23 X
NRC to Ceco 05/07/81 XV-5 DSI/RSB 7
NRC to CECO 12/15/81 XV-24 X
NRC to Ceco 05/07/81 XV-6 X
NRC to CECO 11/16/79 XVI X
NRC to Ceco 11/05/80 XV-7 DSI/RSB 7
NRC to CECO 01/04/82 XVII DL 7
NRC to CECO 11/20/79 XV-8 RSI/CPB 4a XV-9 DSI/RSB 7
NRC to CECO 12/15/81 (2-10)
G NNA FACILITY: GINNA TOPIC NO.
REVIEW STATUS REMARKS DIV/BR LICENSEE ROCHESTER GAS 1 ELECTRIC II-1 A.
DE/SAB 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 0s/29/81 POWER CAPACITY: 1520(THERMAL) 0490(FLECTRICAL)
II-2 A.
DSI/AEB 7
NRC to RGE 11/03/81 OL NUMBER: DPR-18 II-2 B.
X NRC to RGE 05/07/81 H.S.S.S.
WEST.
II-2 C.
DSI/AEB 7
NRC to RGE 09/24/81 A/E FIRMS GIL.
II-2 D.
X NRC to RGE 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL II-3 A.
DE/HGEB 6
RGE to NRC 08/18/81 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD II-3 B.
DE/HGEB 6
RGE to NRC 08/18/81 II-3 B.
1.
DE/HGEB 6
RGE to NRC 08/18/81 OPERATING REACTORS PROJECT MANAGER: j. Iyons INTEGRATED ASSESSMENT PROJECT MANAGER:
A. WANG ABW 02/02/82 II-3 C.
DE/HGEB 7
RGE to NRC 04/10/81 II-4 DE/GSB 7
NRC to RGE 07/09/81 KEY FOR STATUS CODES II-4 A.
DE/GSB 7
NRC to RGE 06/08/81 G - GENERIC 4a-DRAFT SE RECEIVE 0 II-4 B.
DE/GSB 7
HRC to RGE 07/09/81 FROM REVIEW BRANCH X - DELETED II-4 C.
DE/GSB 7
HRC to RGE 06/05/81 4b-SAR RECEIVED FROM 0 - TOPIC NOT LICFNSEE II-4 D.
DE/AGEB Gb RGE to NRC 06/30/81 STARTED 5 - DRAFT SE SENT II-4 E.
X NRC to RGE 11/16/79 1 - QUESTIDMS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.
DE/HGEB 45 RGE to NRC 06/30/81 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY HRC III-1 DL/SEPB SCSys)
NRC to RGE 12/30/81 TO UTILITY DL/SEPB 7(EIoc) NRC to RGE 04/02/81 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 5
NRC to RGE 12/29/81 RECEIVED BY HRC
- - DATA FOR NEXT.90 NTH (NOVEMBER)
(2-11)
GINNA TGPIC NO.
REVIEW STATUS REMARKS TGPIC HO.
REVIEW STATUS REMARKS DIV/BR DIV/BR III-3 A.
DE/SEB 6
RGE to NRC 08/18/81 III-10 B.
DL/S. e 7
NRC to RGE 06/22/81 III-3 B.
X NRC to RGE
$2/31/80 III-10 C.
X NRC to RGE 11/16/79 III-3 C.
DE/HGEB 4b RGE to NRC 10/12/81 III-11 X
NRC to RGE 05/07/81 III-4 A.
DSI/AEB 5
NRC to RGE 09/28/81 III-12 X
NRC to RGE 05/07/81 III-4 B.
DE/MTEB 5
NRC to RGE 12/18/81 IV-1 A.
DL/SEPB J
NRC to RGE CS/29/79 III-4 C.
DSI/ASB Gb RGE to NRC 12/30/81 IV-2 DSI/ICSB 7
HRC to RGE 05/26/81 III-4 D.
DE/SAB 7
NRC to RGE 07/21/81 IV-3 X
NRC to RGE 05/07/81 III-5 A.
DL/SEPB 6
RGE to NRC 10/01/81 V-1 X
NRC to RGE 11/27/81 III-5 B.
DL/SEPB 7
NRC to RGE 09/04/81 V-2 X
NRC to RGE 11/16/79 III-6 DL/SEPB 6
RGE to NRC 02/06/81 V-3 X
NRC to RGE 05/07/81 III-7 A.
DL/SEPB 5
NRC to RGE 12/29/81 V-4 X
HRC to RGE 05/07/81 III-7 B.
DL/SEPB 5
NRC to RGE 12/30/81 V-5 DL/SEPB 6
RGE to NRC 10/12/81 III-7 C.
DE/SEB 7
RGE to NRC 07/07/81 V-6 DL/SEPB 7
NRC to RGE 03/05/80 III-7 D.
DE/SEB 7
NRC to RGE 05/08/80 V-7 DSI/ASB 5
NRC to RGE 11/27/81 III-8 A.
DSI 5
NRC to RGE 12/28/81 V-8 X
NRC to RGE 05/07/81 III-8 B.
X NRC to RGE 10/01/80 V-9 X
NRC to RGE 11/16/79 III-8 C.
DL/SEPB 7
RGE to NRC 12/07/79 V-10 A.
DL/SEPB 7
NRC to RGE 02/02/79 III-8 D.
X NRC to RGE 05/07/81 V-10 B.
DL/SEPB 7
RGE to NRC 09/29/81 III-9 X
NRC to RGE 05/07/81 V-11 A.
DL/SEPB 7
NRC to RGE 07/22/81 III-10 A.
DL/SEPB 7
NRC to RGE 08/03/81 V-11 B.
DL/SEPB 7(Sys)
RGE to NRC 09/29/81 3L/SEPB 7(Elec) NRC to RGE 04/24/81 (2-12)
GINNA TCPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.
X NRC to RGE 11/16/79 VI-7 D.
DL/SEPB 7
NRC to RGE 08/17/78 V-13 X
NRC to RGE 05/07/81 VI-7 E.
X NRC to RGE 05/07/81 VI-1 DE/CEB 3
RGE to NRC 11/06/81 VI-7 F.
DL/SEPB 7
NRC to RGE 06/24/81 VI-2 A.
X NRC to RGE 05/07/81 VI-8 X
NRC to RGE 05/07/81 VI-2 B.
X NRC to RGE 05/07/81 VI-9 X
NRC to RGE 11/16/79 VI-2 C.
X NRC to RGE 11/16/79 VI-10 A.
DL/SEPB 7
NRC to RGE 11/27/81 VI-2 D.
DSI/CSB 5
NRC to RGE 11/03/81 VI-10 B.
X NRC to RGE 11/16/79 VI-3 DSI/CSB 5
NRC to RGE 11/03/81 VII-1 A.
DL/SEPB 7
NRC to RGE 07/30/81 VI-4 DSI/CSB 6(sys)
RGE to NRC 12/30/81 VII-1 B.
DL/SEPB 7
NRC to RGE 08/17/78 DL/SEPB 6(Elec) RGE to NRC 03/02/81 VII-2 DL/SEPB 7
HRC to RGE 12/28/81 VI-5 X
NRC to RGE 05/07/81 VII-3 DL/SEPB 7(sys)
HRC to RGE 09/29/81 VI-6 DSI/CSB 7
NRC to RGE 05/06/81 DL/SEPB 7(Elec) NRC to RGE 06/24/81 VI-7 A.
1.
DL/SEPB 7
HRC to RGE 02/20/81 VII-4 X
NRC to RGE 05/07/81
'o RGE 08/17/78 VII-5 X
NRC to RGE 05/07/81 VI-7 A.
2.
DL/SEPB 7
NRC c
VI-7 A.
3.
DL/SEPB 7
NRC to RGE 11/27/81 VII-6 DL/SEPB 7
NRC to RGE 06/24/81 VI-7 A. 4.
X NRC to RGE 05/07/81 VII-7 X
HRC to RGE 11/16/79 VI-7 B.
DSI/RSB 5(Sys)
RGE to NRC 12/31/81 VIII-1 A.
DSI/PSB 7
NRC to RGE 03/26/81 DL/SEB 7(Elec) HRC to RGE 09/18/81 VIII-2 DL/SEPB 7
NRC to RGE 06/24/81 VI-7 C.
DL/SEPB 7
NRC 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 B.
DL/SEPB 7
NRC to RGE 06/09/81 VI-7 C. 2.
DL/SEPB 7
NRC to RGE 02/20/81 VIII-4 DL/SEPB 7
RGE to NRC 10/08/81 VI-7 C.
3.
X NRC to RGE 11/16/79 (2-13)
-=
=
GINNA TOPIC NO.
REVIEM STATUS REMARKS TOPIC NO.
REVIEW STATUS R EMARKS DIV/BR DIV/BR IX-1 DSI/ASB 7
NRC to RGE 11/24/81 XV-10 DSI/RSB 7
NRC to RGE 09/04/81 IX-2 X
NRC to RGE 05/07/81 XV-11 X
NRC to RGE 10/01/80 IX-3 DL/SEPB 7
HRC to RGE 11/03/81 XV-12 DSI/CPB 7(Sys)
NRC to RGE 09/04/81 DSI/AEB 6(Doses) RGE to NRC 11/04/81 IX-4 DSI/RSB 7
NRC to RGE 08/26/81 XV-13 X
NRC to RGE 11/16/79 IX-5 DL/SEPB 5
HRC to RGE 12/31/81 XV-14 DSI/RSB 7
NRC to RGE 09/04/81 IX-6 G
NRC to RGE 05/07/81 XV-15 DSI/RSB 7
NRC to RGE 09/04/81 X
X NRC to RGE 05/07/81 XV-16 DSI/AEB 6
RGE to NRC 09/24/80 XI-1 X
NRC to RGE 12/04/81 XV-17 DSI/RSB 7(Sys)
NRC to RGE 09/04/81
'XI-2.
X NRC to RGE 12/04/81 DSI/AEB 6(Doses) RGE to NRC 11/04/81 XIII-1 X
NRC to RGE 05/07/81 XV-IS X
NRC to RGE 03/11/80 XIII-2 DL/SEPB 7
NRC to RGE 03/26/81 XV-19 DSI/RSB 7(Sys)
HRC to RGE 10/02/81 DSI/AEB 6(Doses) RGE to NRC 10/29/81 XV-1 DSI/RSB 7
NRC to RGE 09/04/81 XV-20 DSI/AEB 6
RGE to NRC 11/04/81 XV-2 DSI/RSB 7(Sys)
HRC to RGE 09/04/81 DSI/AEB 6(Doses) RGE to NRC 11/04/81 XV-21 X
NRC to RGE 05/07/81 XV-3 DSI/RSB
-7 NRC to RGE 09/04/81 XV-22 X
NRC to RGE 05/07/81 XV-4 DSI/RSB 7
NRC to RGE 09/04/81 XV-23 X
NRC to RGE 05/07/81 XV-5 DSI/RSB 7
NRC to RGE 09/04/81 XV-24 X
NKC o RGE 05/07/81 XV-6 DSI/RSB 7
NRC to RGE 09/04/81 XVI X
NRC to RGE 11/05/80 XV-7 DSI/RSB 7
NRC to RGE 09/04/81 XVII DL 7
NRC to RGE 08/17/78 XV-8 DSI/CPB 7
NRC to RGE 09/04/81 XV-9 DSI/RSB 7
RGE to NRC 10/16/81 (2-14)
l HADDAM NECK 1
I FACILITY: HADDAM NECK TOPIC NO.
REVIEW STATUS REMARKS l
DIV/BR LICENSEE: CONNECTICUT YANKEE ATOMIC POWER II-1 A.
DE/SAB 4b CYAPCo to NRC 04/27/81 REGION / LOCATION: 13 MILES EAST OF MERIDEN, CT.
II-1 B.
DE/SAB 4b CYAPCo to NRC 08/31/31 DOCKET NG: 05000213 II-1 C.
DE/SAB Gb CYAFCo to NRC 06/30/81 POWER CAPACITY: 1825(THERMAL) 0575(ELECTRICAL)
II-2 A.
DSI/AEE
)
CYAPCo to NRC 01/22/81 OL NUMBER: DPR-61 II-2 B.
X NRC to CYAPCo 05/07/81 N.S.S.S.4 WEST.
II-2 C.
DSI/AEB 7
CYAPCo to NRC 02/16/79 A/E FIRM: S8W II-2 D.
X NRC to CYAPCo 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL II-3 A.
DE/HGEB 4b CYAPCo to NRC 12/14/81 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIEL3 II-3 B.
DE/HGEB 4b CYAPCo to NRC 12/14/81 OPERATING REACTORS PROJECT MANAGER: C. TROPF II-3 B.
1 DE/HGEB Gb CYAPCo to NRC 12/14/81
, k[1 INTEGRATED ASSESSMENT PROJECT MANAGER: S. BROWN II-3 C.
DE/HGEB Gb 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 Ga-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 03/31/81 STARTED 5 - DRAFT SE SENT II-4 E.
X HRC 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)
NRC to CYAPCo 11/20/81 TO UTILITY DL/SEPB 7(Elec) Part of VII-3 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 4b CYAPCo to NRC 12/14/81 RECEIVED BY NRC (2-15)
HADDAM NECK TOPIC NO.
REVIEW STATUS REMARKS TCPIC MO.
REVIEW STATUS REMARKS DIV/SR DIV/BR III-3 A.
LE/SEB 4b CYAPCo to hRC 08/31/81 111-10 B.
LL/SEPB 6
CYAPCo to NRC 12/09/80 III-3 B.
D E/ H ',E B D
III-10 C.
X NRC to CYAPCo 04/16/79 III-3 C.
DE/NGEB 4b CYAPCo to NRC 08/31/81 III-11 X
NRC to CYAPCo 05/07/81 III-4 A.
DSI/ASB Gb CYAPCo to NRC 08/31/81 III-12 X
NRC to CYA' Co 05/07/81 III-4 B.
DE/MTEB G
HRC to CYAPCo 05/07/81 IV-1 A.
DL/SEPB 7
CYAPCo to NRC 06/25/79 III-4 C.
DSI/ASB 0
IV-2 DSI/ICSB 5
NRC to CYAPCo 12/23/81 III-4 D.
DE/SAB 4b CYAPCo to NRC 06/25/81 IV-3 X
NRC to CYAPCo 05/07/81 III-5 A.
DL/SEPB 3
CYAPCo to NRC 02/07/80 V-1 DE/MTEB X
NRC to CYAPCo 11/27/81 III-5 B.
DL/SEPB 46 CYAPCo to NRC 10/02/81 V-2 X
HRC to OYAPCo 04/16/79 III-6 DL/SEPB 3
CYAPCo to NRC 06/11/81 V-3 X
NRC to CYAPCo 05/07/81 III-7 A.
X NRC to CYAPCo 05/07/81 V-4 X
NRC to CYAPCo 05/07/81 III-7 B.
DL/SEPB 3
CYAPCo to NRC 09/07/79 V-5 DL/SEPB 6
CYAPCo to NRC 08/19/81 III-7 C.
X NRC to CYAPCo 04/16/79 V-6 DL/SEPB 7
NRC to CYAPCo 03/05/80 III-7 D.
DE/SEB 7
NRC to CYAPCo 10/16/81 V-7 DSI/ASB G
NRC to CYAPCo 05/07/81 III-8 A.
DSI
.G NRC to CYAPCo 05/07/81 V-8 X
NRC to CYAPCo 05/07/81 III-8 B.
X HRC to CYAPCo 10/01/80 V-9 X
NRC to CYAPCo 11/16/79 III-8 C.
DL/SEPB 6
CYAPCo to NRC 12/18/79 V-10 A.
DL/SEPB 7
NRC to CYAPCo 01/13/81 III-8 D.
X HRC to CYAPCo 05/07/81 V-10 B.
DL/SEPB 7
CYAPCo to NRC 11/10/81 III-9 X
NRC to CYAPCo 05/07/81 V-11 A.
DL/SEPB 6
CYAPCo to NRC 11/05/81 III-10 A.
DL/SEPB 7
CYAPCo to NRC 09/21/81 V-11 B.
DL/SEPB 7(Sys)
CYAPCo to NRC 11/10/81 DL/SEPB 7(Eluc) Part of VII-3 08/28/81 (2-16)
HADDAM NECK TCPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.
X NRC to CYAPCo 11/16/79 VI-7 D.
DL/SEPB 7
hRC to CYAPCo C8/17/78 V-13 X
NRC to CYAPCo 05/07/81 VI-7 E.
X NRC to CYAPCo 05/07/81 VI-1 DE/CEB 3
CYAPCO to NRC 10/31/79 VI-7 F.
X NRC to CYAPCo 04/16/79 VI-2 A.
X NRC to CYAPCo 05/07/81 VI-8 X
NRC to CYAPCo 05/07/81 VI-2 B.
X NRC to CYAPCo 05/07/81 VI-9 X
NRC to CYAPCo 11/16/79 VI-2 C.
X NRC to CYAPCo 04/16/79 VI-10 A.
DL/SEPB 0
VI-2 D.
DSI/CSB 3
CYAPCo to NRC 04/27/81 VI-10 B.
X NRC to CYAPCo 04/16/79 VI-3 DSI/CSB 3
CYAPCo to NRC 04/27/81 VII-1 A.
DL/SEPB 3
CYAPCo to NRC 08/07/81 VI-4 DSI/CSB 0(Sys)
VII-1 B.
DL/SEPB 7
NRC to CYAPCo 08/17/78 DL/SEPS 7(Elec) NRC to CYAPCo 09/21/81 VII-2 DL/SEPB 3
CYAPCo to NRC 08/07/81 VI-5 X
NRC to CYAPCo 05/07/31 VII-3 DL/SEPB 7(Sys)
HRC to CYAPCo 12/28/81 VI-6 DSI/CSB G
NRC to CYAPCo 05/07/81 DL/SEP3 7(Elec) NRC to CYAPCo 08/28/81 VI-7 A.
1 DL/SEPB 7
NRC to CYAPCo 02/20/81 VII-4 X
NRC to CYAPCo 05/07/81 VI-7 A. 2.
X NRC to CYAPCo 05/07/81 VII-5 X
NRC to CYAPCo 05/07/81 VI-7 A.
3.
DL/SEPB Ga VII-6 DL/SEPB 7
NRC to CYAPCo 08/28/81 VI-7 A.
4.
X NRC to CYAPCo 05/07/81 VII-7 X
NRC to CYAPCo 04/16/79 VI-7 B.
DSI/RSB 0(Sys)
VIII-1 A.
DSI/PSB G
NRC to CYAPCo 05/07/81 DL/SEPB 7(Elec) NRC to CYAPCo 05/21/81 V;II-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
NRC to CYAPCo 12/14/81 (2-17)
HADDAM NECK TCPIC NO.
REVIEW STATUS REMARKS TOPIC HO.
REVIEW STATUS REMARKS DIV/ER DIV/BR IX-1 DSI/ASB 4b CYAPCo to NRC 08/31/81 XV-10 DSI/RSB 4b CYAPCo to NRC 09/30/81 IX-2 X
NRC to CYAPCo 05/07/81 XV-11 X
NRC to CYAPCo 10/01/80 IX-3 DL/SEPB Gb CYAPCo to NRC 12/14/81 XV-12 DSI/CPB ib(Sys) CYAPCo to NRC 09/30/81 DSI/RSL Gb(Doses)CYAPCo to NRC 09/30/81 IX-4 DSI/RSB 4b CYAPCo to NRC 10/02/81 XV-13 X
NRC to CYAPCo 11/16/79 IX-5 DL/SEPB 4b CYAPCo to NRC 12/14/81 XV-14 DSI/RSB 4b CYAPCo to NRC 09/30/81 IX-6 DE G
NRC to CYAPCo 05/07/81 XV-15 DSI/RSB Gb CYAPCo to NRC 09/30/81 X
X NRC to CYAPCo 05/07/81 XV-16 DSI/AEB 6
CYAPCo to NRC 09/28/81 XI-1 DSI/ETSB X
NRC to CYAPCo 12/04/81 XV-17 DSI/RSB 0(Sys)
XI-2 DSI/ETSB X
NRC to CYAPCo 12/04/81 DSI/AEB 0(Doses)
XIII-1 X
NRC to CYAPCo 05/07/81 XV-18 X
NRC to CYAPCo 10/01/80 XIII-2 DL/SSPB G
NRC to CYAPCo 05/07/81 XV-19 DSI/RSB 7(Sys)
NRC to CYAPCo 12/02/81 DSI/AEB Ab(Doses)CYAPCo to NRC 09/30/81 XV-1 DSI/RSB 4b CYAPCo to NRC 09/30/81 XV-20 DL/SEPB 7
NRC to CYAPCo 06/09/81 XV-2 DSI/RSB 4b(Sys) CYAPCo to NRC 09/30/81 DSI/AEB 4b(Doces)CYAPCo to NP^
09/30/81 XV-21 X
NRC to CYAPCo 05/07/81 XV-3 DSI/RSB 4b CYAPCo to NRC 09/50/81 XV-22 X
NRC to CYAPCo 05/07/81 XV-4 DSI/RSD 7
NRC to CYAPCo 12/17/81 XV-23 X
NRC to CYAPCo 05/07/81 XV-5 DSI/RSB 4b CYAPCo to NRC 09/30/81 XV-24 X
NRC to CYAPCo 05/07/81 XV-6 DSI/RSB 4b CYAPCo to NRC 09/30/81 XVI X
NRC to CYAPCo 11/05/80 XV-7 DSI/RSB Gb CYAPCo to NRC 09/30/81 XVII DL 7
NRC to CYAPCo 08/17/78 XV-8 DSI/CPB Gb CYAPCo to NRC 09/30/81 XV-9 DSI/RSB 4b CYAPCo to NRC 09/30/81 (2-18)
LACROSSE FACILITY: LACROSSE TOPIC NO.
REVIEW STATUS REMARKS DIV/BR LICENSEE: DAIRLAND POWER Il-1 A.
DE/SAB 4b DPC to NRC 06/23/81 REGIDH/ LOCATION: 19 MILES SOUTH OF LACROSSE, WISC.
II-1 B.
DE/SAB Gb DPC to NRC 06/16/81 DOCKET NO.: 05000409 II-1 C.
DE/SAB 4b DPC to NRC 07/15/81 POWER CAPACITY: 0165(THERMAL) 0050(ELECTRICAL)
II-2 A.
DSI/AEB 5
NRC to DPC 12/15/80 OL NUMBER: DPR-45 II-2 B.
X NRC to DPC 05/07/81 N.S.S.S.'
AC.
II-2 C.
DSI/AEB 0
A/E FIRM: SSL II-2 D.
X NRC to DPC 05/07/81 SYSTEMATIC EVALUA1 ION PROGRAM BRANCH CHIEF: W. RUSSELL II-3 A.
DE/HGEB 4b DPC to NRC 06/16/81 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD II-3 B.
DE/HGEB 2
NRC to DPC 07/10/81 OPERATING REACTORS PROJECT MANAGER: D. DUDLEY II-3 B.
1.
DE/HGEB D
kh II-3 C.
DE/HGEB Gb DPC to NRC 06/26/81 INTEGRATED ASSESSMENT PROJECT MANAGER: T. MICHAELS II-4 DE/GSB 7
NRC to DPC 06/08/81 KEY FOR STATUS CODES p
G - GENERIC Ga-DRAFT SE RECEIVED II-4 B.
DE/GSB 3
FROM REVIEW BRANCH X - DELETED II-4 C.
DE/GSB 7
HRC to DPC 06/08/81 4b-SAR RECEIVED FROM 0 - TCPIC NOT LICENSEE II-4 D.
DE/HGEB Site Visit 07/10/79 STARTED 5 - DRAFT SE SENT II-4 E.
DE/HGEB 0
1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW SRANCH II-4 F.
DE/HGEE 2
6 - SE RESP 0 HSE RECEIVED 2 - QUESTIONS SENT BY NRC III-1 DL/SEPB 3(Sys)
DPC to NRC 08/06/81 TO UTILITY DL/SEPB C(Elwc) 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB
<b DPC to NRC 08/06/81 RECEIVED BY NRC (2-19) l
LACROSSF TOPIC HO.
REVIEW STATUS REMARKS TDPIC NO.
REVIEW STATUS R EMA RKS DIV/BR DIV/BR III-3 A.
DE/SEB 2
NRC to DPC 08/09/79 III-10 B.
X NRC to DPC 10/29/79 III-3 B.
X NRC to DPC 03/10/81 III-10 C.
X NRC to DPC 10/29/79 III-3 C.
- DE/HGEB 0
III-11 X
NRC to DPC 05/07/81 III-4 A.
DSI/ASB 0
III-12 X
NRC to CPC 05/07/81 III-4 B.
DE/MTEB C
IV-1 A.
DL/SEPB 7
HRC to DPC 04/19/79 III-4 C.
DSI/ASB G
IV-2 DSI/ICSB 5
NRC to DPC 01/25/82 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 2
NRC to DPC 01/04/80 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
HRC to DPC 05/07/81 III-7 B.
DL/SEPB 2
NRC to DPC 08/09/79-V-5 DL/SEPB 4a III-7 C.
X HRC to DPC 10/25/79 V-6 DL/SEPB 7
NRC to DPC 03/05/80 III-7 D.
DE/SEE 4b DPC to NRC 06/29/81 V-7 X
HRC to DPC 05/07/81 III-8 A.
DSI G
NRC to DPC 05/07/81 V-8 X
NRC to DPC 05/07/81 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 HRC to DPC 05/07/81 V-10 B.
DL/SEPB 5
NRC to DPC 12/22/80 III-9 X-MRC to DPC 05/07/81 V-11 A.
DL/SEPB 7
HRC to DPC 12/22/80 III-10 A.
DL/SEPB 7
HRC to DPC 09/22/81 V-11 B.
DL/SEPB 5(Sys)
HRC to DPC 12/22/80 DL/SEPB 0(Elec)
~
e-(2-20) a e "'Y_'m nawm. =.~,. ~. -
LACROSSE TDPIC HO.
REVIEW STATUS REMARKS TOPIC HO.
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 EPC 08/17/78 V-13 X
NRC to DPC 05/07/81 VI-7 E.
Y NRC to DPC 05/07/81 VI-1 2'
1 3
DPC to NRC 08/23/79 VI-7 F.
X NRC to DPC 10/29/79 VI-2 A.
X HRC to DPC 05/07/81 VI-8 X
HRC to DPC 05/07/81 VI-2 B.
X HRC to 05/07/81 VI-9 X
NRC to DPC 10/29/79 VI-2 C.
X NRC to D. C 10/29/79 VI-10 A.
DL/SEPB 4a i
VI-2 D.
DSI/CSB 3
DPC+tagD' 04/26/79 VI-10 B.
X NRC to DPC 10/29/79 VI-3 DSI/CSB 3
DPC to "1 04/26/79 VII-1 A.
DL/SEPB 2
NRC to DPC 10/06/81 4'%
VI-4 DSI/CSB 3(Sys)
DPC to NIC 08/17/81 VII-1 B.
DL/SEPB 7
NRC to DPC 08/17/78 3*
1/05/82 DL/SEPB 7(Elec) HRC to DPC VII-2 DL/SEPB 2
NRC to DPC 10/06/81 VI-5 X
NRC to DPC
/07/81 VII-3 DL/SEPB 5(Sys)
NRC to DPC 12/22/80 VI-6 DSI/CSB G
NRC to DPC OS"47/81 DL/SEPB 3(Elec)
VI-7 A.
1 X
NRC to DPC 10/29f79 VII-4 X
NRC to DPC 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 4a VII-6 DL/SEPB 7
NRC to EPC 09/21/81 VI-7 A.
4.
X HRC to DPC 05/07/81 VII-7 X
NRC to DPC 10/29/79 VI-7 B.
X NRC to DPC 10/29/79 VIII-1 A.
DSI/PSB G
HRC to DPC 05/07/81 VI-7 C.
DL/SEPB 7
NRC to DPC 03/13/81 VIII-2 DL/SEPB 7
NRC to DPC 12/18/81 VI-7 C.
1.
DL/SEPB 7
HRC to DPC 09/21/81 VIII-3 A.
DL/SEPB 7
NRC to DPC 06/05/79 VI-7 C. 2.
DL/SEPB 7
NRC to DPC 03/13/81 VIII-3 B.
DL/SEPB 7
NRC to DPC 08/28/81 VI-7 C.
3.
X HRC to DPC 10/29/79 VIII-4 DL/SEPB 7
NRC to DPC 09/09/81 (2-21)
LACROSSE TDPIC NO.
R EVI ELI STATUS REMARKS TDPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 0
XV-10 X
hKC to DPC 10/29/79 l
IX-2 X
NRC to DPC 05/07/51 XV-11 DSI/CPB 0
IX-3 DL/SEPB 2
XV-12 X
NRC to DPC 10/29/79 IX-4 X
NRC to DPC 10/49/79 XV-13 DSI/CPB OCDoses)
DSI/AEB 0(Sys)
IX-5 DL/SEPB 0
XV-14 DSI/RSB 4b DPC to NRC 08/25/81 IX-6 DE G
NRC to DPC ON/07/81 l
XV-15 DSI/RSB 7
NRC to DPC 09/21/81 i
X X
HRC to DPC 65/07/81 1
XV-16 DSI/AEB 0
XI-1 DSI/ETSB X
NRC to DPC 2/04/81 XV-17 X
NRC to DPC 10/29/79 XI-2 DSI/ETSB 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 0
XV-20 DSI/AEB 0
XV-2 X
NRC to DPC 10/29/79 XV-21 X
NRC to DPC 05/07/81 XV-3 DSI/RSB 7
NRC to DPC 11/13/81 XV-22 X
NRC to DPC 05/07/81 XV-4 DSI/RSB 7
NRC to DPC 11/03/81 XV-23 X
NRC to DPC 05/07/81 XV-5 DSI/RSB 0
XV-24 X
NRC to DPC 05/07/81 XV-6 X
NRC to DPC 10/29/79 XVI X
NRC to DPC 11/05/80 XV-7 DSI/RSB 0
XVII DL 7
NRC to DPC 08/17/78 XV-8 DSI/CPB 0
XV-9 DSI/RSB 4b DPC to NRC 08/25/81 (2-22)
MILLSTONE 1 FACILITY: MILLSTOHE 1 TOPIC HD.
REVIEW STATUS REMARKS DIV/BR LICENSEE: HORTHEAST NUCLEAR ENERGY II-1 A.
DE/SAB 7
hRC to NU 07/31/81 REGION / LOCATION: S MILES SOUTH WEST OF NEW LONDON, CONH.
II-1 B.
DE/SAB 7
HRC to NU 11/27/81 DOCKET NO.+
05000245 II-1 C.
DE/SAB 7
HRC to NU 11/27/81 POWER CAPACITY: 2011(THERMAL) 0660(ELECTRICAL)
II-2 A.
DSI/AEB 7
NRC to NU 03/30/81 OL NUMBER: DPR-21 II-2 B.
X NRC to NU 05/07/81 N.S.S.S.
GE.
II-2 C.
DSI/AEB 7
HRC to NU 09/29/81 A/E FIRM. EBASCO II-2 D.
X NRC to NU 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W.
RUSSELL II-3 A.
DE/HGEB Ab NU to NRC 06/25/81 OPERATING REACTORS BRANCH CHIEF:
D.
CRUTCHFIELD II-3 B.
DE/HGEB 4b HU to NRC 06/26/81 OPERATING REACTORS PROJECT MANAGER: J. SHEA II-3 B.
1.
DE/HGEB Ab NU to HRC 06/25/81 D.PERSIHKO]{}
INTEGPATED ASSESSMENT PROJECT MANAGER:
II-3 C.
DE/HGEB 4b NU to NRC 04/28/81 II-4 DE/GSB 7
NRC to NU 06/08/81 KEY FOR STATUS CODES II-4 A.
DE/GSB 7
NRC to NU 06/08/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.
DE/GSB 5
NRC to NU 01/07/82 FROM REVIEW BRANCH X - DEL ETED II-4 C.
DE/GSB 7
HRC to HU 06/08/81 4b-SAR RECEIVED FROM 0 - TOPIC HOT LICENSEE II-4 D.
DE/HGEB 4b NU to HRC 08/31/81 STARTED 5 - DRAFT SE SEHT II-4 E.
X NRC to NU 11/16/79 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.
DE/HGEB Gb NU to NRC 04/28/81 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY HRC III-1 DL/SEPB 4a(Elec)
TO UTILITY DL/SEPB 3(Sys)
HU to HRC 08/20/81 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 3
NU to NRC 08/29/79 RECEIVED BY NRC (2-23)
MILLSTONE 1 TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR 111-3 A.
DE/SEB 5
NRC to NU 05/11/81 111-10 B.
Y.
NRC to NU 11/16/79 III-3 B.
X NRC to NU 12/26/80 III-10 C.
DL/5EPB 7
NU to NRC 08/29/79 III-3 C.
DE/NGEB 4b HU to NRC 08/31/81 III-11 X
NRC to NU 05/07/81 III-4 A.
DSI/ASB 4b NU to NRC 08/31/81 III-12 X
NRC to NU 05/07/81 III-4 B.
DE/MTEB 4b NU to NRC 08/31/81 IV-1 A.
DL/SEPB 7
NU to NRC 02/12/79 III-4 C.
DSI/ASB 3
HU to NRC 12/05/80 IV-2 DSI/ICSB 4b NU to NRC 10/28/81 III-4 D.
DE/SAB 7
HRC to NU 11/27/81 IV-3 DE/MTEB G
hRC to NU' 05/07/81 III-5 A.
DL/SEPB 3
HU to NRC 11/08/79 V-1 X
NRC to NU 11/27/81 III-5 B.
DL/SEPB 4b HU to NRC 12/04/81 V-2 X
NRC to NU 11/16/79 III-6 L./SEPB 5
NRC to NU 05/28/81 V-3 X
HRC to NU 05/07/81 III-7.A.
X NRC to NU 05/07/81 V-4 X
NRC to NU 05/07/81 III-7 B.
DL/SEPB 3
NU to NRC 0 8/.".9/7 9 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
HU to NRC 02/17/81 V-7 X
HRC to NU 05/07/81 III-8 A.
DSI G
NRC to NU 05/07/81 V-8 X
NRC to NU 05/07/81 III-8 B.
X HRC to NU 09/26/80 V-9 X
NRC to NU 11/16/79 III-8 C.
DL/SEPB 6
HU.to NRC 01/31/80 V-10 A.
DL/SEPB 7
NU to NRC 03/05/79 III-8 D.
X NRC to NU 05/07/81 V *O B.
DL/SEPB 7
NU to NRC 07/22/81 III-9 X
HRC.to NU 05/07/81 V-11 A.
DL/SEPB 7
HRC to NU 07/08/81 III-10 A.
DL/SEPB 7
NRC to NU 06/28/81 V-11 B.
DL/SEPB 7(Sys)
HU to NRC 07/22/81 DL/SEPB Ga(Elec) l (2-24)
c MILLSTONE 1 TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.
DL/SEPB 7
NRC to NU 12/17/79 VI-7 D.
DL/SEPB 7
NRC to NU 08/17/78 V-13 X
NRC to NU 05/07/81 VI-7 E.
X NRC to NU 05/07/81 VI-1 DE/CEB Ga VI-7 F.
X HRC to HU 11/16/79 VI-2 A.
X HRC to NU 05/07/81 VI-8 X
NRC to NU 05/07/81 VI-2 B.
X NRC to HU 05/07/81 VI-9 X
NRC to NU 11/16/79 VI-2 C.
X HRC to HU 11/16/79 VI-10 A.
DL/SEPB 7
NRC to HU 10/08/81 VI-2 D.
DSI/CSB 3
NU to NRC 06/09/81 VI-10 3.
DL/SEPB 7(Sys)
NU to NRC 08/05/81 DL/SEPB 7(Elec)
VI-3 DSI/CSB 3
NU to NRC 06/09/81 VII-1 A.
DL/SEPB 7
HRC to NU 07/23/81 VI-4 DSI/CSB 5(Sys)
NRC to HU 12/09/81 DL/SEPB 5(Elec) NU to NRC 08/12/81 VII-1 B.
DL/SEPB 7
NRC to NU 08/17/78 VI-5 X
NRC to HU 05/07/81 VII-2 DL/SEPB 6
NU to NRC 08/26/81 VI-6 DSI/ CSS G
NRC to NU 05/07/81 VII-3 DL/SEPB 7(Sys)
NU to NRC 07/22/81 DL/SEPB 4a(Elec)
VI-7 A.
1.
X NRC to NU 11/16/79 VII-4 X
HRC to NU 05/07/81 VI-7 A. 2.
X NRC to NU 05/07/81 VII-5 X
NRC to HU 05/07/81 VI-7 A.
3.
DL/SEPB 7
NRC to NU 10/27/81 VII-6 DL/SEPB 7
HRC to HU 08/26/81 VI-7 A. 4.
DSI/RSB G
NRC to NU 05/07/81 VII-7 X
NRC to NU 11/16/79 VI-7 B.
X NRC to NU 11/16/79 VIII-1 A.
DSI/RSB G
HRC to NU 05/07/81 VI-7 C.
DL/SEPB 7
HRC to NU 03/29/81 VIII-2 DL/SEPB 7
NRC to NU 09/30/81 VI-7 C.
1.
DL/SEPB 7
NU to NRC 11/02/81 VIII-3 A.
DL/SEPB 7
HRC to HU 08/26/81 VI-7 C. 2.
DL/SEPB 7
HRC to NU 03/29/81 VIII-3 B.
DL/SEPB 7
HRC to HU 07/23/81 VI-7 C. 3.
X HRC to NU 11/16/79 VIII-4 DL/SEPB 7
HRC to HU 07/07/81 (2-25)
MILLSTONE 1 TOPIC NO.
REVIEW STATUS REMAR(S TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/AS3 4b NU to NRC 08/31/81 XV-10 X
HRC 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 4b NU to NRC 11/24/81 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 l
DSI/AEB-7(Doses) HRC to NU 11/03/81 j
IX-5 DL/SEPB
.Ab NU to NRC 11/19/81 XV-14 DSI/RSB 7
NRC 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
HU to NRC 01/13/82 XIII-1 X
NRC to NU 05/07/81 XV-19 DSI/RSB 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/RSB 7
NRC 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 DSI/RSS 7
NRC to NU 09/18/81 XV-22 X
HRC to NU 05/07/81
.XV-4 DSI/RSB 7
NRC to NU 09/18/81 XV-23 X
HRC 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
NRC to NU 12/04/81 XVII DL 7
HRC to NU 08/17/78
.XV-S DSI/CPB 7
NRC to NU 08/26/81 XV-9 DSI/RSB 7
NRC to NU 11/12/82 d
(2-26)
0YSTER CREEK FACILITY: OYSTER CREEK 1 TOPIC NO.
REVIEW STATUS REMARKS DIV/BR LICENSEE: JERSEY CENTRAL POWER & LIGHT II-1 A.
DE/SAB Ga REGION / LOCATION: 9 MILES SOUTH OF TOMS RIVER. HJ.
II-1 B.
DE/SAB 4a DOCKET NO.' 05000219 II-1 C.
DE/SAB 4a POWER CAPACITY: 1930(THERMAL) 0650(ELECTRICAL)
II-2 A.
DSI/AEB 5
NRC to JCPL 12/17/80 OL NUMBER: DPR-16 II-2 B.
X NRC to JCPL 05/07/81 N.S.S.S.
GE.
II-2 C.
DSI/AEB Gb JCPL to NRC 11/04/81 A/E FIRN: B&R II-2 D.
X HRC to JCPL 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL II-3 A.
DE/HGEB 2
OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD II-3 B.
DE/HGEB 2
OPERATING REACTORS PROJECT MANAGER: J. LOMBARDO II-3 B.
1.
DE/HGEB 2
FELL /h,f INTEGRATED ASSESSMENT PROJECT MANAGER:
R.
II-3 C.
DE/HGEB 2
j II-4 DE/GSB 7
NRC to JCPL 08/03/81 KEY FOR STATUS CODES II-4 A.
DE/GSB 7
HRC 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
KRC to JCPL 06/08/81 4b-SAR RECEIVED FROM 0 - TOPIC NGT LICENSEE II-4 D.
DE/HGEB Gb JCPL to NRC 12/15/81 STARTED 5 - DRAFT SE SENT II-4 E.
X NRC to JCPL 11/16/79 1 - QUESTIUNS 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 3(Sys)
NRC to JCPL 12/07/81 TO UTILITY DL/SEPB 5(Elec) NRC to JCPL 07/09/81 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 2
RECEIVED BY HRC (2-27)
OYSTER CREEK
' TOPIC NO.
REVIEW STATUS R EMARKS TOPIC HO.
REVIEW STATUS REMARKS DIV/3R DIV/BR III-3 A.
DE/SEB-2 111-10 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
HRC to JCPL 05/07/81 III-4 B.
DE/MTEB 4b 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 2
IV-3 X
NRC to JCPL 05/07/81 III-5 A.
DL/SEPB 6
JCPL to NRC 11/12/81 V-1 X
HRC to JCPL 11/24/81 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
HRC to JCPL 05/07/81
-III-7 A.
X HRC to JCPL 05/07/81 V-4 X
NRC to JCPL 05/07/81
-III-7 B.
DL/SEPB Ga V-5 DL/SEPB 6
JCPL to NRC 11/04/81 III-7 C.
X NRC to JCPL 11/16/79 V-6 DL/SEPB 7
NRC to JCPL 03/05/80 III-7 D.
DE/SEB Gb JCPL to NRC 11/04/81-V-7 X
NRC to JCPL 05/07/81 III-8 A.
DSI G
NRC to JCPL 05/07/81 V-8 X
NRC to JCPL 05/07/81 f
III-8 B.
X NRC to JCPL 09/26/80 V-9 X
HRC to JCPL 11/16/79 l
III-8 C.
DL/SEPB 7
NRC to JCPL
'/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
HRC to JCPL 09/25/80 III-9 X
NRC to JCPL 05/07/81 V-11 A.
DL/SEPB 7
NRC to JCPL 07/08/81 III-10 A.
DL/SEPB 7
NRC to JCPL 06/29/81 V-11 B.
DL/SEPB 7(Sys)
NRC to JCPL 09/25/80 DL/SEPB 7(Elec) HRC to JCPL 07/09/81
-(2-28)
OYSTER CREEK TOPIC HO.
REVIEW STATUS REMARKS TDPIC HO.
REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.
DL/SEPS 6
JCPL to NRC 11/04/81 VI-7 D.
DL/SEPB 7
hRC to JCPL 08/17/78 V-13 X
NRC to JCPL 05/07/81 VI-7 E.
X NRC to JCPL 05/07/81 VI-1 DE/CEB 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-10 A.
DL/SEPB 7
HRC to JCPL 08/18/81 VI-2 D.
DSI/CSB 5
NRC to JCPL 12/10/81 VI-10 B.
X HRC to JCPL 11/16/79 VI-3 DSI/CSB 5
NRC to JCPL 12/10/81 VII-1 A.
DL/SEPB 7
HRC to JCPL 07/30/81 VI-4 DSI/CSB 5(Sys)
HRC to JCPL 11/18/81 VII-1 B.
DL/SEPB 5
NRC to JCPL 12/28/81 DL/SEPB 5(Elec) HRC to JCPL 08/05/81 VII-2 DL/SEPB 6
JCPL to NRC 08/17/81 VI-5 X
NRC to JCPL 05/07/81 VII-3 DL/SEPB 7(Sys)
HRC to JCPL 09/25/80 VI-6 DSI/CSB G
NRC to JCPL 05/07/81 DL/SEP3 7(Elec) NRC to JCPL 07/09/81 VI-7 A.
1.
X NRC to JCPL 11/16/70 VII-4 X
HRC to JCPL 05/07/81 VI-7 A. 2.
X NRC to JCPL 05/07/81 Vil-5 X
HRC to JCPL 05/07/81 VI-7 A. 3.
DL/SEPB 7
NRC to JCPL 07/30/81 VII-6 DL/SEPB 7
NRC to JCPL 08/29/81 VI-7 A. 4.
DSI/RSB G
NRC to JCPL 05/07/81 VII-7 X
NRC to JCPL 11/16/79 VI-7 B.
X NRC to JCPL 11/16/79 VIII-1 A.
DSI/PSB 7
NRC to JCPL 10/16/81 VI-7 C.
DL/SEPB 7
NRC to JCPL 03/13/81 VIII-2 DL/SEPB 7
HRC to JCPL 06/29/81 VI-7 C.
1 DL/SEPB 7
NRC to JCPL 06/29/81 VIII-3 A.
DL/SEPB 7
HRC to JCPL 06/29/81 V.I-7 C. 2.
DL/SEPB 7
'NRC to JCPL 03/13/81 VIII-3 B.
DL/SEPB 7
NRC to JCPL 06/29/81 VI-7 C. 3.
X NRC to JCPL 11/16/79 VIII-4 DL/SEPB 2
NRC to JCPL 03/26/81 (2-29)
0YSTER CREEK TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STAT'JS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 3
JCPi to NRC 12/14/79 XV-10 X
NRC to JCPL 11/16/79 IX-2 X
HRC 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)
DSI/CPB 5(Sys)
HRC to JCPL 04/09/81 IX-5 DL/SEPB 0
XV-14 DSI/RSB 7
NRC to JCPL 07/16/81 IX-6 DE G
NRC to JCPL 05/07/81 XV-15 DSI/RSL 7
NRC to JCPL 12/04/81 X
X NRC to JCPL 05/07/81 XV-16 DSI/AEB Gb 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 XIII-1 X
NRC to JCPL 05/07/81 XV-19 DSI/AEB 2(Doses)
XIII-2 DL/SSPB 7
NRC to JCPL 09/25/80 DSI/RSS 7(Sys)
HRC to JCPL 09/04/81 XV-1 DSI/RSB 7
NRC to JCPL 12/07/81 XV-20 DSI/RSB 2
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 05/07/21 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/RSS 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 l
FACILITY: PALISADES TOPIC NO.
R EVI E!J STATUS REMARKS DIV/BR LICENSEE: CONSUMERS POWER 11-1 A.
DL/SEPB 7
CPCo to NRC 12/28/79 REGION /LOCATICH: 5 MILES SOUTH OF SOUTH HAVEN, MI.
II-1 B.
DL/SEPB 7
CPCo to MRC 12/28/79 DOCKET NO: 05000255 II-1 C.
DL/SEPB 7
CPCo to NRC 05/13/81 POWER CAPACITY: 2530(THERMAL) 0805(ELECTRICAL)
II-2 A.
DSI/AEB 7
NRC to CPCo 06/30/81 OL NUMBER: DPR-20 II-2 B.
X hRC to CPCo 05/07/81 N.S.S.S.
C-E II-2 C.
DSI/AEB 7
NRC to CPCo 04/23/81 A/E FIRM: BECH.
II-2 D.
X NRC to CPCo 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL II-3 A.
DE/HGEB 6
CPCo to NRC 08/13/81 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD II-3 B.
DE/HGEB 6
CPCo to NRC 08/13/81 OPERATING PEACTORS PROJECT MANAGER: T. WAMBACH II-3 B.
1 DE/HGEB 6
CPCo to NRC 08/13/81 II-3 C.
DE/HGEB 6
CPCo to NRC 08/13/81 INTEGRATED ASSESSMENT PROJECT MANAGER: T. MICHAELS j pty II-4 DE/GSB 7
CPCo to NRC 07/04/81 KEY F3R STATUS CODES II-4 A.
DE/GSB 7
NRC to CPCo 07/04/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.
DE/GSB 7
CPCo to NRC 07/22/81 FROM REVIEW BRANCH X - DELETED II-4 C.
DE/GSB 7
NRC to CPCo 06/08/81 4b-SAR RECEIVED FROM 0 - TOPIC NOT LICENSEE II-4 D.
DE/HGEB
)
CPCo to NRC 06/01/81 STARTED 5 - DRAFT SE SENT II-4 E.
X NRC to CPCo 11/16/79 1 - QUESTICNS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.
DE/HGEB 7
CPCo to NRC 06/01/81 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC III-1 DL/SEPB 7(Elec) HRC to CPCo 11/12/60 TO UTILITY DL/SEPB 5(Sys)
HRC to CPCo 12/29/81 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE RECEIVED BY NRC (2-31)
~. _ -
PALISADES TOPIC NO.
REVIEW STATUS REMARKS TOPIC ND.
REVIEW STATUS REMARKS DIV/BR DIV/BR III-2 DL/SEPB 6
HRL to CPCo 10/09/81 III-10 B.
DL/SEPB 6
CPCo to NRC 07/02/81 III-3 A.
DE/SEB 7
NRC to CPCo 08/26/81 III-10 C.
X NRC to CPCo 11/16/79 III-3 B.
X NRC to CPCo 12/26/80 III-11 X
NRC to CPCo 05/07/81 III-3 C.
DE/HGEB 4b CPCo to NRC 12/21/81 III-12 X
NRC to CPCo 05/07/81 III-4 A.
DSI/AEB 6
CPCo to NRC 10/09/81 IV-1 A.
DL/SEPB 7
CPCo to NRC 02/08/79 III-4 B.
DE/MTEB 5
NRC to CPCo 12/02/81 IV-2 DSI/ICSB 7
NRC to CPCo 10/16/81 III-4 C.
DSI/ASB 7
NRC to CPCo 09/21/81 IV-3 X
NRC to CPCo 05/07/81 III-4 D.
DE/SAB 7
CPCo to NRC 08/03/81 V-1 X
NRC to CPCo 11/27/81 III-5 A.
DL/SEPB 5
NRC to CPCo 12/04/81 V-2 X
NRC to CPCo 11/16/79 t
III-5 B.
DL/SEPR 5
NRC to CPCo 12/23/81 V-3 X
NRC to CPCo 05/07/81 III-6 DL'SEPB 6
CPCo to NRC 07/13/81 V-4 X
NRC to CPCo 05/07/81 III-7 A.
DL/SEPB 6
CPCo to NRC 11/13/81 V-5 DL/SEPB 6
CPCo to NRC 10/07/81 III-7 B.
DL/SEPB 5
HRC to CPCo 11/16/81 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 III-8 D.
X HRC to CPCo 05/07/81 V-11 A.
DL/SEPB 7
HRC to CPCo 11/09/81 III-9 X
NRC to CPCo 05/07/81 V-11 B.
DL/SEPB 7(Sys)
CPCo to NRC 12/23/81 DL/SEPB 7(Elec) HRC to CPCo 12/24/81 III-10 A.
DL/SEPB 7
NRC to CPCo 05/19/81 (2-32)
PALISADES I
TCPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR I
V-12 A.
X hRC to CPCo 11/16/79 VI-7 D.
DL/SEPB 7
NRC to CPCo 08/17/78 l
l V-13 X
HRC to CPCo 05/07/81 VI-7 E.
X NRC to CPCo 05/07/81 VI-1 DE/CEB 7
NRC to CPCo 08/03/81 VI-7 F.
DL/SEPB 7
NRC to c9Co 06/30/81 VI-2 A.
X NRC to CPCo 05/07/81 VI-8 X
NRC to CPCo 05/07/81 I
VI-2 B.
X HRC to CPCo 05/07/81 VI-9 X
NRC to CPCo 11/16/79 l
VI-2 C.
X NRC to CPF.
11/16/79 VI-10 A.
DL/SEPB 7
NRC to CPCo 06/19/81 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 C8/17/78 DCI/CSB 6(Sys)
CPCo to NRC 08/10/81 VII-2 DL/SEPB 7
NRC to CPCo 05/19/81 VI-5 X
NRC to CPCo 05/07/81 7(Sys)
CPCo to NRC 10/27/81 VII-3 DL/SEPB VI-6 DSI/CSB 7
NRC to CPCo 12/11/81 DL/dEPB 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 l
VI-7 A. 2.
X NRC to CPCo 05/07/81 VII-5 X
HRC to CPCo 05/07/81 i
VI-7 A.
3.
DL/SEPB 7
NRC to CPCo 12/18/81 VII-6 DL/SEPB 7
NRC to CPCo 05/19/81 l
VI-7 A.
4.
X HRC to CPCo 05/07/81 VII-7 X
HRC to CPCo 11/16/79 l
VI-7 B.
DL/SEPB 7(Elec) NRC to CPCo 05/19/81 VIII-1 A.
DSI/PSB 7
HRC to CPCo 12/22/81 DSI/RSB 7(Sys)
HRC to CPCo 06/30/81 i
VIII-2 DL/SEPB 7
HRC to CPCo 06/09/81 1
VI-7 C.
DL/SEPB 7
NRC to CPCo 02/20/81 l
VIII-3 A.
DL/SEPB 7
HRC to CPCo 05/22/81
{
i
(
VI-7 C.
1.
DL/SEPB 7
HRC to CPCo 11/18/80 1
l VIII-5 B.
DL/SEPB 7
HRC to CPCo 08/05/81 VI-7 C. 2.
DL/SEPB 7
NRC to CPCo 02/20/81
{
VIII-4 DL/SEPB 7
HRC to CPCo 07/31/81 VI-7 C.
3.
X CPCo to NRC 12/12/79 (2-33)
. PALISADES TCPIC NO.
REVIEM STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR, DIV/BR j
IX-1 DSI/ASB 5
NRC to CPCo 12/31/81 XV-10 DL/SEPB 7
NRC to CPCo 07/17/81 IX-2 X
NRC to CPCo 05/07/81 XV-11 X
HRC to CPCo 10/01/80 IX-3 DL/SEPB 7
'NRC to CPCo 09/06/81 XV-12 DL/SEPB 7(Doses) NRC to CPCo 01/29/80 4
DL/SEPB 7(Sys)
NRC to CPCo 12/04/81 IX-4 DSI/RSB 7
HRC to CPCo 11/23/81 XV-13 X
NRC to CPCo 11/16/79 IX-5 DL/SEPB 6
CPCo to NRC 11/10/81 i
XV-14 DL/SEPB 7
NRC to CPCo 07/17/81 IX-6 DE G
NRC to CPCo 05/07/81 i
XV-15 DL/SEPB 7
NRC to CPCo 07/17/81 X
X NRC to CPCo 05/07/81 XV-16 DL/SEPB 7
HRC to CPCo 12/31/80 XI-1 X
HRC to CPCo 12/04/81 XV-17 DL/SEPB 7(Doses) HRC to CPCo 01/29/80 XI-2 X
NRC to CPCo 12/04/81 DL/SEPB 7(Sys)
HRC to CPCo 07/17/81 XIII-1 X
!.KC to CPCo 05/07/81 XV-18 X
NRC to CPCo 10/01/80
-XIII-2.
DL/SSPB.
7 NRC to CPCo 10/01/80 XV-19 DL/SEPB 7(Doses) HRC to CPCo 11/21/80 I
DL/SEPB 7(Sys)
NRC to CPCo 07/17/81
-XV-1 DL/SEPB 7
NRC to CPCo 07/17/81 XV-20 DL/SEPB 7
NRC to CPCo 11/21/80 XV-2 DL/SEPB 7(Doses) NRC to CPCo 05/18/81 DL/SEPB 7(Sys)
NRC to CPCo 07/17/81 XV-21 X
NRC to CPCo 05/07/81 XV-3 DL/SEPB 7
HRC to CPCo 07/17/81 XV-22 X
NRC to CPCo 05/07/81 XV-4 DL/SEPB 7
NRC to CPCo 07/17/81 XV-23 X
NRC to CPCo 05/07/81 XV-*
'DL/SEPB 7
NRC to CPCo 07/17/81 XV-24 X
NRC to CPCo 05/07/81 XV-6 DL/SEPB 7
NRC to CPCo 07/17/81 XVI X
NRC to CPCo 11/05/80 XV-7 DL/SEPB 7
NRC to.CPCo 07/17/81 XVII DL 7
NRC to CPCo 08/17/78 XV-8 DL/SEPB 7
NRC to CPCo 07/17/81 XV-9 DL/SEPB 7
.NRC to CPCo 07/17/81 b
(2-34) i
SAN ON0FRE FACILITY: SAN CHOFRE 1 TOPIC HO.
REVIEW STATUS REMARKS DIV/BR LICENSEE: SOUTHERN CALIFORHIA E'
'9N 7
hRC to SCE 11/07/79
.i-1 A.
DL/SEPd REGICH/ LOCATION: 5 MILES SOUTH OF SAN CLEMENTE, CA.
II-1 B.
DL/SEPB 7
HRC to SCE 11/07/79 DOCKET NO.
05000206 II-1 C.
DE/SAB 4b SCE to HRC 11/12/81 PCWER 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 HRC to SCE 05/07/31 N.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 2
HRC to SCE 01/07/82 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD II-3 B.
DE/HGEB 2
HRC to SCE 01/07/82 OPERATING REACTORS PROJECT MANAGER: W.
PAULSON II-3 B.
1.
DE/HGEB 6
SCE to NRC 10/08/31 INTEGRATED ASSESSMENT PROJECT MANAGER:
E. MCKENHA l h: is(
II-3 C.
BE/HGEB 2
NRC to SCE 01/07/82 II-4 DE/GSB 5
NRC to SCE 03/15/81 KEY FOR STATUS CODES II-4 A.
DE/GSB 5
HUREG-0712 12/80 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.
DE/GSB 5
NUREG-0712 12/80 FROM REVIEW BRANCH X - DELEiED II-4 C.
DE/GSB 5
HUREG-0712 12/80 4b-SAR RECEIVED FROM 0 - TOPIC NOT LICENSEE II-4 D.
DE/HGEB 4b SCE to NRC 11/02/81 STARTED 5 - DRAFT SE SENT II-4 E.
X HRC to SCE 11/16/79 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.
DE/HGEB 4b SCE to NRC 11/02/81 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY HRC III-1 DL/SEPB 3(Sys)
SCE to HRC 08/29/79 TO UTILITY DL/SEPB 5(Elec) HRC to SCE 11/18/81 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 3
5CE to NRC 11/20/81 RECEIVED BY NRC (2-35)
SAN ON0FRE TOPIC HO.
REVIEW STATUS REMARKS TOPIC HO.
REVIEW STATUS REMARKS DIV/BP DIV/BR III-3 A.
DE/SEB 3
SCE to NRC 09/08/80 III-10 B.
DL/SEPB 7
NRC to SCE 11/08/79 III-3 B.
X HRC to SCE 11/16/79 III-10 C.
X NRC to SCE 11/16/79 III-3 C.
DE/HGEB 7
NRC to SCE 11/27/81 III-11 X
NRC to SCE 05/07/81 III-4 A.
DSI/ASB 3
SCE to NRC 08/14/79 III-12 X
HRC to SCE 05/07/81 III-4 B.
DE/MTEB G
HRC to SCE 05/07/81 IV-1 A.
DL/SEPB 7
NRC to SCE 11/13/79 III-4 C.
DSI/ASB 0
IV-2 DSI/ICSB 2
HRC to SCE 12/15/80 III-4 D.
DE/SAB 4b SCE to HRC 10/23/81 IV-3 X
HRC to SCE 05/07/81 III-5 A.
DL/SEPB 1
V-1 X
NRC to SCE 11/27/81 III-5 B.
DL/SEPB 2
NRC to SCE 01/04/80 v-2 X
NRC to SCE 11/16/79 III-6 DL/SEPB 3
SCE to HRC 12/08/81 V-3 X
HRC to SCE 05/07/81 III-7 A.
X HRC to SCE 05/07/81 V-4 X
NRC to SCE 05/07/81 III-7 B.
DL/SEPB 3
SCE to HRC 11/20/81 V-5 DL/SEPB 5
HRC to SCE 06/03/81 III-7 C.
X HRC to SCE 11/16/79 V-6 DL/SEPB 7
NRC to SCE 03/05/80 III-7 D.
DE/SEB 4b SCE to NRC 06/09/81 V-7 DSI/ASB 7
HRC to SCE 12/04/81 III-8 A.
DSI
.7 NRC to SCE 12/28/81 V-8 X
HRC to SCE 05/07/81 III-8 B.
X NRC to SCE 10/01/80 V-9 X
NRC to SCE 11/16/79 III-8 C.
DL/SEPB 7
NRC to SCE 01/29/80 V-10 A.
DL/SEPB 7
HRC to SCE 01/07/81 III-8 D.
X HRC to SCE 05/07/81 V-10 B.
DL/SEPB 5
NRC to SCE 06/20/81 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 5(Sys)
HRC to SCE 06/20/81 DL/SEPB 4a(Elec)
(2-36)
SAN ON0FRE TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.
X NRC to SCE 11/16/79 VI-7 D.
DL/SEPB 7
NRC to SCE 08/17/78 V-13 X
NRC to SCE C5/07/81 VI-7 E.
X HRC 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 HRC to SCE 05/07/81 VI-8 X
NRC to SCE 05/07/81 VI-2 B.
X HRC to SCE 05/07/81 VI-9 X
HRC to SCE 11/16/79 VI-2 C.
X HRC to SCE 11/16/79 VI-10 A.
DL/SEPB 5
NRC to SCE 08/28/81 VI-2 D.
DSI/CSB 5
HRC to SCE 01/12/82 VI-10 E,.
DL/SEPB 7(Sys)
NRC to SCE 11/15/79 DL/SEPB 7(Elec) NRC to SCE 11/15/79 VI-3 DSI/CSB 5
HRC to SCE 01/12/82 VII-1 A.
DL/SEPB 5
NRC to SCE 09/09/81 VI-4 DSI/CSB 4a(Sys)
DL/SEPB 7(Elec) HRC to SCE 09/03/81 VII-1 B.
DL/SEPB 7
NRC to SCE 08/17/78 VI-5 X
NRC to SCE 05/07/81 VII-2 DL/SEPB 5
NRC to SCE 11/17/81 VI-6 DSI/CSB G
NRC to SCE 05/07/31 VII-3 DL/SEPB 5(Sys)
HRC to SCE 06/20/81 DL/SEPB 5(Elec) HRC to SCE 11/18/81 VI-7 A.
1 DL/SEPB 7
NRC to SCE 02/20/81 VII-4 X
NRC to SCE 05/07/81 VI-7 A. 2.
X NRC to SCE 05/07/31 VII-5 Y
NRC to SCE 05/07/81 VI-7 A.
3.
DL/SEPB 5
HRC to SCE 11/18/81 VII-6 DL/SEPB 7
NRC to SCE 08/28/81 VI-7 A. 4.
X NRC to SCE 05/07/81 VII-7 X
NRC to SCE 11/16/79 VI-7 B.
DSI/RSB 5(Sys)
HRC to SCE 07/24/81 DL/SEPB 5(Elec) HRC to SCE 09/04/81 VIII-1 A.
DSI/RSB G
NRC to SCE 05/07/81 VI-7 C.
DL/SEPB 7
NRC to SCE 06/01/81 VIII-2 DL/SEPB 7
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
NRC to SCE 06/01/81 VIII-3 B.
DL/SEPB 7
NRC to SCE 07/24/81 VI-7 C.
3.
X HRC to SCE 11/16/79 VIII-4 DL/SEPB 7
NRC to SCE 12/31/81 (2-37)
l I
l
. SAN ONOFRE TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/ER IX-1 DSI/ASB 3
SCE to NRC 10/05/79 XV-10 DSI/RSB 4b SCE to NRC 07/01/81 IX-2' X
NRC to SCE 05/07/81 XV-11 X
NRC to SCE 10/01/80 IX-3 DL/SEPB Gb SCE to NRC 11/02/81 XV-12 DSI/RSB 7(Sys)
HRC to SCE 11/19/81 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 IX-6 DE G
NRC to SCE
.05/07/81 Gb SCE to NRC 07/01/81 XV-15 DSI/RSB 4b SCE to NRC 07/01/81 X
X NRC to SCE 05/07/81 XV-16 DSI/AEB 7
NRC to SCE 11/18/81 XI-t-X NRC to SCE 12/04/81 l
f XV-17 DSI/RSB 7(Sys)
HRC to SCE 12/07/81 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-12 DSI/RSB 7(Sys)
NRC to SCE 08/26/81 CL/SEPB 7(Doses) HRC to SCE 01/29/80
'XV-1 DSI/RSB 7
NRC to SCE 10/27/81 XV-20 DL/SEPB 7
NRC to SCE 03/28/80 XV-2 DSI/RSB 7(Sys)
SCE to NRC 10/27/81 DL/SEPB 7(Doses) HRC to SCE 01/29/80 XV-21 X
NRC to SCE 05/07/81 XV-3 DSI/RSB 7
NRC to SCE 08/26/81 XV-22 X
NRC to SCE 05/07/81 XV-4 DSI/PSB 7
NRC to SCE 12/21/81 XV-23 X
NRC to SCE 05/07/81 XV-5 DSI/RSB Ga XV-24 X
NRC to SCE 05/07/81 XV-6 DSI/RSB 4b SCE to NRC 07/01/81 XVI X
NRC to SCE 11/05/80 XV-7 DSI/RSB 4b SCE to NRC 07/01/81 XVII DL 7
NRC to SCE 11/20/79 XV-8 DSI/CPB 7
NRC to SCE 11/19/81 XV-9 DSI/RSD 5
NRC to SCE
-05/11/81 (2-38)
YANKEE R0WE FACILITY: YAhKEE ROWE 1 TOPIC NO.
REVIEW STATUS REMARKS DIV/BR LICENSEE: YANKEE ATCMIC ELECTRIC II-1 A.
DE/SAB 0
REGION / LOCATION: 25 MILES NORTH EAST OF PITTSFIELD, MASS.
II-1 B.
DE/SAB 4b YAEC to NRC 05/01/81 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
NRC to YAEC 08/03/81 OL NUMBER: DPR-3 1I-2 B.
X NRC to YAEC 05/07/81 N.S.S.S.
WEST.
II-2 C.
DSI/AEB 7
HRC to YAEC 09/04/81 A/E FIRM: S&W II-2 D.
X NRC to YAEC 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL II-3 A.
DE/HGEB 6
YAEC to NRC 03/16/81 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD II-3 B.
DE/HGEB 6
YAEC to NRC 03/16/81 OPERATING REACTORS PROJECT MANAGER:
R. CARUSO II-3 B.
1.
DE/HGEB 5
NRC to YAEC 02/09/81 INTEGRATED ASSESSMENT PROJECT MANAGER: M. BOYLE)9[ h II-3 C.
DE/HGEB 3
Site Visit II-4 DE/GSB 7
HRC to YAEC 06/03/81 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
FROM REVIEW BRANCH X - DELETED II-4 C.
DE/GSB 7
NRC to YAEC 06/08/81 4b-SAR RECEIVED FROM 0 - TOPIC NOT LICENSEE II-4 L.
DE/HGEB 3
Sito Visit STARTED 5 - DRAFT SE SENT II-4 E.
DE/HGEB 3
Site Visit 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.
DE/HGEB 4b YAEC tc NRC 08/31/81 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY HRC III-1 DL/SEPB Ga(Elec)
TO UTILITY DL/SEPB 3(Sys)
YAEC to NRC 01/31/79 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 3
YAEC to NRC 08/21/81 RECEIVED BY NRC (2-39) l
YANKEE R0WE TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
R Eb IEW STATUS REMARKS DIV/BR DIV/BR III-3 A.
DE/SE3 3
YAEC to NRC 09/06/79 III-10 B.
X NRC to YAEC 11/16/79 III-3 B.
X NRC to YAEC 12/26/80 III-10 C.
X NRC to YAEC 11/16/79 III-3 C.
DE/HGEB 4b YAEC to NRC 01/04/82 III-11 X
NRC to YAEC 05/07/81 III-4 A.
DSI/ASB 0
III-12 X
NRC to YAEC 05/07/81 III-4 B.
DE/MTEB G
NRC to YAEC 05/07/81 IV-1 A.
DL/SEPB 7
NRC to YAEC 04/18/79 I ! ! 'i C.
DSI/ASB 0
IV-2 DSI/ICSB 7
NRC to YAEC 12/23/81 III-4 D.
DE/SAB 4b YAEC to NRC 06/30/81 IV-3 X
NRC to YAEC 05/07/81 III-5 A.
DL/SEPB 2
NRC to YAEC 01/04/80 V-1 DE/MTEB X
NRC to YAEC 11/27/81 III-5 B.
DL/SEPB 4b 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-S DL/SEPB 5
NRC to YAEC 01/24/80 III-7 C.
X NRC to YAEC 11/16/79 V-6 DL/SEPB 7
NRC to YAEC 03/05/80 III-7 D.
DE/SEB Gb YAEC to NRC 11/18/81 V-7 DSI/ASB X
NRC to YAEC 12/14/81 III-8 A.
DSI 7
NRC to YAEC 12/07/81 V-8 X
NRC to YAEC 05/07/81 III-8 B.
X NRC to YAEC 10/01/80 V-9 X
NRC to YAEC 11/16/79 III-8 C.
DL/SEPB 7
NRC to YAEC 11/15/79 V-10 A.
DL/SEPB 7
NRC to YAEC 11/05/79 III-8 D.
X NRC to YAEC 05/07/81 V-10 B.
DL/SEPB 6
YAEC to NRC 11/24/81 III-9 X
NRC to YAEC 05/07/81 V-11 A.
DL/SEPB 7
NRC to YAEC 12/08/80 III-10 A.
DL/SEPB 7
NRC to YAEC 09/22/81 V-11 B.
DL/SEPB 6(Sys)
YAEC to NRC 11/24/81 DL/SEPB 4a(Elec)
(2-40)
YANKEE R0WE TCPIC NO.
REVIEW STATUS REMARKS TCPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.
X NRC to YAEC 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 VI-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 HRC to YAEC 05/07/81 VI-8 X
NRC to YAEC 05/07/81 VI-2 B.
X NRC to YAEC 05/07/81 VI-9 X
NRC to YAEC 11/16/79 VI-2 C.
X NRC to YAEC 11/16/79 VI-10 A.
DL/SEPB 4a VI-2 D.
DSI/CSB 2
VI-10 B.
X NRC to YAEC 11/16/79 VI-3 DSI/CSB 2
VII-1 A.
DL/SEPB 6
YAEC to NRC 11/24/81 VI-4 DSI/CSB 2(Sys)
HRC to YAEC 12/07/81 VII-1 B.
DL/SEPB 7
NRC to YAEC 08/17/78 DL/SEPB 7(Elec) HRC to YAEC 10/16/81 VII-2 DL/SEPB 6
YAEC to NRC 11/24/81 VI-5 X
NRC to YAEC 05/07/81 VII-3 DL/SEPB 6(Sys)
YAEC to NRC 11/24/81 VI-6 DSI/CSB G
HRC to YAEC 05/07/81 DL/SEPB 4a(Elec)
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 4a VII-6 DL/SEPB 7
NRC to YAEC 06/28/81 VI-7 A.
4.
X NRC to YAEC 05/07/81 VII-7 X
NRC to YAEC 11/16/79 VI-7 B.
DSI/RSB 7(Elec) HRC to YAEC 06/04/81 VIII-1 A.
DSI/PSB G
NRC to YAEC 05/07/81 0(Sys)
VI-7 C.
DL/SEPB 7
HRC to YAEC 03/13/81 VIII-2 DL/SEDB 7
NRC to YAEC 09/03/81 VI-7 C.
1.
DL/SEPB 7
NRC to YAEC 09/04/81 VIII-3 A.
DL/SEPB 7
NRC to YAEC 11/07/79 VI-7 C. 2.
DL/SEPB 7
NRC to YAEC 03/13/81 VIII-3 B.
DL/SEPB
/
HRC to YAEC 08/28/81 VI-7 C.
3.
DL/SEPB 7
NRC to YAEC 07/24/80 VIII-4 DL/SEPB 3
YAEC to NRC 10/15/81 (2-41) l
l YANKEE R0WE TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSl/ASB 4b YAEC to NRC 11/18/81 XV-10 DSI/RSB 40 YAEC to NRC 06/30/81 IX-2 X
NRC to YAEC 05/07/81 XV-11 X
NRC to YAEC 10/01/80 IX-3 DL/SEPB 4b YAEC to NRC 09/17/81 XV-12 DSI/CPB 4b(Sys) YAEC to NRC 06/30/81 DSI/AEB 4b(Doses)YAEC to NRC 08/31/81 IX-4 DSI/RSB Gb YAEC to NRC 08/31/81 XV-13 X
NRC to YAEC 11/16/79 IX-5 DL/SEPB Gb YAEC to NRC 11/18/81 XV-14 DSI/RSB Gb YAEC to NRC 06/30/81 IX-6 DE G
NRC to YAEC 05/07/81 XV-15 DSI/RSB Gb YAEC to NRC 06/30/81 X
X NRC to YAEC 05/07/81 XV-16 DSI/AEB 0
XI-1 DSI/ETSB X
NRC to YAEC 12/04/81 XV-17 DSI/RSB 0(Sys)
XI-2 DSI/ETSB X
HRC to YAEC 12/04/81 DSI/AEB 0(Doses)
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 4bSys)
YAEC to NRC 11/18/81 DSI/AEB 4b(Doses)YAEC to NRC 01/04/82 XV-1 DSI/RSB 0
XV-20 DL/SEPB 7
NRC to YAEC 09/06/81 XV-2 DSI/RSB 4b(Sys) YAEC to NRC 06/30/81 DSI/AEB 0(Doses)
XV-21 X
NRC to YAEC 05/07/81 XV-3 DSI/RSB 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/RSB 4b YAEC to NRC 06/30/81 XV-24 X
NRC to YAEC 05/07/81 XV-6 DSI/RSB 0
XVI X
NRC to YAEC 11/05/80 XV-7 DSI/RSS 4b YAEC to NRC 06/30/81 XVII DL 7
NRC to YAEC 08/17/78 XV-8 DSI/CPB Gb YAEC to NRC 01/04/82 XV-9 DSI/RSB 4b YAEC to NRC 06/30/81 (2-42)
w_.--
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PALISADES DL PALISADES pil SAR 1/
SFR 2/
SAR 1/
SER 2/
TOPIC HO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE III-1 Classification of NDHE 12/29/81C III-8.A Loose Parts Monitoring and NONE 11/ 0 3/81 C (SYS)
Structures Components and Core Barrel Vibration Systems (Seismic and Monitoring (NRR B-60. C-12)
Quality)
IV-2 Reactivity Control Systems 07/31/81R 10/16/81C III-5.A Effects of Pipe Break on G8/13/81R 12/04/81C Including Functional Design Structures, Systems and and Protection Against Components Inside Single Failures Containment V-7 Reactor Coolant Pump HONE 11/16/81C III-5.B Pipe Break Outside 08/25/81R 12/23/81C Overspeed (HRR B-68)
Containmert VI-6 Containment Leak Testing NONE 08/05/81C III-7.A Inservice Inspection, NONE 08/25/81C (MP A-04)
Including Prestressed Concrete Containments with VIII-1.A Potential Equipment H0HE 12/22/81C Either Grouted or Ungrouted Failures Associated with a Tendons Degraded Grid Voltage (MP B-23)
III-7.B Design Codes, Design HONE 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 XI-1 Appendix I(MP A-02)
SER 2/
XI-2 Radiological (Effluent NONE DELETED TOPIC NO. TITLE SCHEDULE SCHEDULE and Process) Monitoring Systems (HRR B-67)
III-3.C Inservice Inspection of 12/21/81R R+30 1/
Water Control Structures J/ SAR : Licensee Safety Analysis Report-Scheduled or Actual III-4.B Turbine Missiles (MP B-46)-
H0HE 12/02/81C (Actual (status 4b) when date is followed by R)
III-7.D Containment Structural NDHE 08/17/81C 2/ SER : Staff Safety Evaluation Report -Scheduled or Actual Integrity Tests (Actual (status 4a, 5, 7) when date is followed by C)
V-1 Compliance with Codes and HDHE DELETED 1/ Desiginated number of days from receipt of licensee SAR Standards (10 CFR 50.55a)
(Note: if Licensee SAR is received then date is from (MP A-01 A-14) receipt of additional information requested)
IX-6 Fire Protection (MP B-02)
NOHE 01/31/82 (3-2)
LICENSEE SUBMITTALS PALISADES SlABIITTALS 48 TARGET 35 ACTUAL 25 29 15 IS
/
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e e
i i
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g JLN Jll.
ALE SEP TT M
EC JAN FEB NAR APR MAY Jim JLt.
MONTHS Target 1
2 3
0 0
0 0
0 0
0 0
0 0
PER MONTH 1
7 0
1 1
1 0
Actual Target 1
3 6
6 6
6 6
6 6
6 6
6 6
CUMULATIVE MW 1
3 3
4 5
6 6
(3-3)
SER 2/
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE III-1 Classification of Struct-NONE 12/29/81C (SYS) ures Components and Systems IX-6 Fire Protection (MP B-02)
NONE 02/26/82 (Seismic and Quality)
III-2 Wind and Tornado Loadings NONE 09/23/81C Q11 SAR 1/
SEF. 2/
III-7.A Inservice Inspection, NONE 12/28/81c TCPIC NO. TITLE SCHEDULE SCHEDULE Including Prestressed Concrete Containments with III-4.C Internally Generated 01/11/82R R+30 J/
Missiles Containments Grouted or Ungrounded Tendons III-8.A Loose Parts Monitoring and NONE 11/03/31C III-7.B Design Codes, Design NONE 12/31/81C Core Barrel Vibration Monitoring (NRR B-60,C-12)
Criteria, Load Combinations, and Reactor V-7 Reactor Coolant Pump NONE 11/05/81C Cavity Design Criteria Overspeed(!Gn 3-68)
VI-7.C.1 Appendix K - Electrical NONE 11/18/81C Instrumentation and Control VI-2.D Mass and Energy Release for NONE 09/25/81C Possible Pipe Break Inside (EIC) Re-reviews Containment IX-5 Ventilation Systems NONE 11/02/81C VI-3 Containment Pressure and NONE 09/25/81C Heat Removal Capability DE SAR 1/
SER 2/
VI-7.B ESF Switchover from NONE 12/18/81C TOPIC NO. TITLE SCHEDUEE SCHEDULE (SYS)
Injection to Recirculation Mode (Automatic ECCS II-1.B Population Distributian 04/15/81R 07/21/81C Realignment)
II-1.C Potential Hazards or.
04/15/81R 07/01/81C IX-1 Fuel Storage NONE 11/24/81C Changes in Potential Hazards Due to XI-1 Appendix I(MP A-02)
NDHE DEL ET ED Transportation, Institutional Industrial, XI-2 Radiological (Effluent NONE DELETED and Process) Monitoring and Military Facilities Systems (HRR B-67) i II-4.D Stability of Slopes 06/30/81R 01/30/82 XV-9 Startup or an Inactive Loop NONE 10/16/81C II-4.F Settlement of Foundations 06/30/81R 01/29/82C or Recirculation Loop at an and Buried Equipment Incorrect Temperature, and Flow Controller Malfunction i
l III-3.C Inservice Inspection of 10/12/81R O2/11/82 Causing an Increase in BWR l
Water Control Structures Core Flow Rate i
III-4.B Turbine Missiles (MP B-46)
NONE 12/02/81C XV-19 Loss-of-Coolant Accidents NONE 09/29/81C 1
(DOSES)
Resulting from Spectrum of l
i III-4.D Site Proximity Missiles 04/16/81R 07/21/81C (SYS)
Postulated Piping Breaks 10/01/81C Within the Reactor Coolant (Including Aircraft)
Pressure Boundary VI-1 Organic Materials and 11/06/81R 02/05/82 Post Accident Chemistry (3-4)
GINNA l/ SAR : Licensee Safety Analysis Report-Scheduled or Actual (actual (status 4b) when date is follwed by R) 2/ SER : Staff Safety Evaluation Report -Scheduled or Actual (Actual (status 4a.
5, 7) when date is followed by C) 1/ Dvsiqinated number of days from receipt of licensee SAR (Note: if Licensee SAR is received then date is from receipt of additional information requested)
(3-5)
/
f t
t J
3 0
i lk J
0 3
b Y
AM 0
3 R
PA 0
3 R
3 A
B T
FE T
0 3
I M
B NA UA J
SH i
T 3
3
)
S#
D N
0 0
O 4
G N
3
(
E C
E E
y S
1 1
3 3
N E
V C
E I
0 1
2 2
L TCO 1
2 1
0 PES 2
0 2
0 E
LA
.0 0
0 0
l S
J L
l A
II I
0 l
0 0
0 D
i l
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f S
l J
5 8
5 8
5 8
8 5
4 3
B 2
2 1
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DRESDEN 2 DL DRESDEN 2 DE (Cont.)
SAR 1/
SER 2/
SAR 1/
SER 2/
TCPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE III-1 Classification of NONE 12/30/81C II-3.B Flooding Potential and hCNE R+45 (SYS)
Structures, Components and Protection Requirements Systems (Seismic and Qua2ity)
II-3.B.1 Capability of Operating NONE R+45 Plant to Cope with Design III-2 Wind and Tornado Loadings 01/31/82 R+60 J/
Basi s Flooding Conditions III-5.A Effects of Pipe Break on 06/30/82 10/12/82 II-3.C Safety-related Water NONE R+45 Structures, Systems and Supply (Ultimate Heat Sink Components Inside (UHS))
Containment II-4.D Stc5ility of Slopes 12/08/81R R+30 III-7.B Design Codes, Design NDHE 10/30/82 Criteria, Load II-4.E Dam Integrity 12/08/81R D1/22/82C Combinations, and Reactor Cavity Design Criteria II-4.F Settlement of Foundations 12/08/81R R+30 and Buried Equipment VI-4 Containment Isolation NONE 12/15/81C (ELEC)
System III-3.A Effects of High Water Level 12/08/81R 03/31/82 on Structures VII-1.A Isolation of Reactor NDHE 08/05/81C Protecticn System from III-3.C Inservice Inspection of 01/31/82 R+30 Non-Safety Systems, Water Control Structures Including Qualifications of Isolation Devices III-4.B Turbine Missilos NDHE 01/15/82 VII-6 Frequency Decay NONE 08/26/81C III-4.D Site Proximity Missiles 12/08/81R R+30 (Including Aircraft)
IX-5 Ventilation Systems NONE 12/11/81 l
III-7.D Containment Structural 04/27/81R 03/31/82 Integrity Tests DE SAR 1/
SER 2/
V-1 Compliance with Codes NONE DELETED TOPIC NO. TITLE SCHEDULE SCHEDULE and Standards (10 CFR 50.55a)(MP A-01 A-14)
Il-1.A Exclusion Area Authority 06/01/81R 10/06/31C and Control VI-1 Organic Materials and 01/31/82 R+45 Post Accident Chemistry II-1.B Population Distribution 04/27/81R 10/06/81C IX-6 Fire Protection NDHE 02/01/82 II-1.C Potential Hazards or 12/08/81R R+30 Changes in Potential Hazards Due te DH Transportation, SAR 1/
SER 2/
Institutional Industrial, TOPIC NO. TITLE SCHEDULE SCHEDULE and Military Facilities ll-2.C Atmospheric Transport and 03/20/81R 08/26/81C II-3.A Hydrologic Description NONE R+45 Diffusion Characteristics for Accident Analvsis III-4.A Tornado Missiles 12/08/81R R+30 (3-7)
m DRESDEN 2 i Sil (Cont.)
211 (Cont.)
SAR 1/
SER 2/
SAR l/
SER 2/
TOPIC HO. TITLE SCHEDULE SCHEDULE TOPIC HO. TITLE SCHEDULE SCHEDULE 111-4.C Internally Generated 01/31/82 R+30 XV-3 Loss of External Load, 10/15/81R 11/17/81C Missiles Turbine Trip, Loss of Condenser Vacuum. Closure III-8 A Loose Paris !1onitoring NCNE 11/30/81 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 Re'. ease for NONE 12/02/81C XV-5 Loss of Normal Feedwater 10/15/81R 12/04/81C Possible Pipe Break Inside Flow Containment XV-7 Reactor Coolant Pump Rotor 10/15/81R 12/18/81C VI-3 Containma,t 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 Operatar Error)
VI-6 Containment Laak Testing NONE 12/04/81C (MP A-04)
XV-9 Startup or an Inactive Loop 10/15/8tR 12/37/81C or Recirculation Loop at an VI-7.A.4 Core Spray Nozzle NONE 11/30/81 Incorrect Temperature, and 3
Effectiveness (NRR A-16)
Flow Controller Malfunction Causing an Increase in EWR VIII-1.A Potential Equipment NONE 02/26/82 Core Flow Rate Failures Associated with a Dcoraded 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 01/31/82 R+30 Position XI-1 Appendix I(MP A-02)
NONE DELETED XV-13 Spectrum of Rod Drop 10/15/81R 01/25/82C (SYS)
Accidents (BWR)
XI-2 Radiological (Effluent and NONE DELETED (DOSES) 10/15/81R 12/14/81C Process) Monitoring Systems (NRR B-67)
XV-14 Inadvertent Operation of 10/15/81R 12/08/81C ECCS and Chemical and XV-1 Increase in Feedwater 10/15/81R 12/14/81C Volume Control System Temperature. Increase in Malfunction that Increases Feodwatnr Flow, Increase Reactor Coolant Inventory in Steam Flow and Inadvertent Opening of a XV-15 Inadvertent Opening of a 10/15/81R 12/22/81C Steam Generator Rolle* or PWR Pressurizer Safety-Safety Valve Relief Valve or a BWR Safety / Relief Valve i
(3-8) 4
l l
l DRESDEN 2 All (Cont.)
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHECULE XV-18 Radiological Consequences 10/15/81R 12/23e31C of tiain Steam Line Failure Outside Containment 'IBWR)
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 Peassure Boundary XV-20 Radiological Consequences 04/27/81R ti/20/81C of Fuel Damaging Accidents (Inside and Outside Containmsnt i
i 1/ SAR : Licensee Safety Analysis Report-Scheduled or Actual t
(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) 4 i
4 (3-9) l
l Y
N o
4 N
E o
N E
N o
5 m
M
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X CD I
l g
D o
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LLI tu (f)
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N N
Z LLI u
N 3
H o
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g M
3 N
N N
N e
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0YSTER CREEK EL OYSTER CREEK i
Ef (Cont.)
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC HO. TITLE SCHEDULE SCHEDULE III-1 Classification of NONE 01/15/82 III-7.D Containment Structural 11/ 0 4 / 81 R 03/01/82 (SYS)
Structures. Components Integrity Tests and Systems III-2 Wind and Tornado Loading 03/31/82 R+30 V-1 Compliance with Codes NONE DELETED and Structures VII-6 Frequency Decay NONE 08/29/81C (MP A-01.A-14)
VI-1 Orgaaic Materials and Post 07/3C/82 R+45 IX-5 Ventilation System 02/28/82 R+30 1/
Accident Chemistry VI-7.A-4 Core Spray Hozzle NONE 05/31/82 Effectiveness (MP D-12)
IX-6 Fire Protection (MP A-02)
NONE 05/01/82 Ef Ell SAR 1/
SER 2/
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE II-1.A Exclusion Area Authority 11/30/81R 01/18/82 C II2.C Atmospheric Tra sport and 09/30/81R 11/20/81 and Control Diffusion Characteristics for Accident Analysis II-1.B Population Distribution 11/30/81R 01/18/82C III-4.A Tornado Missles 03/31/82 R+30 II-1.C Potential Hazards Due to 11/30/31R 01/18/82C Transportation, Industrial, III-4.C Internally Generated 02/28/82 R+30 and Military Facilities Missiles II-3.A Hydrologic Description 02/18/82 R445 III-8.A Loose Parts and Core NONE 11/30/81 Barrel Monitoring II-3.B Flooding Potential and 02/28/82 R+45 (NRR B-60,C-12)
Protection Requirements II-3.B-1 Capability to Cope with 02/28/82 R+45 Design Basis Flood VI-2.D Mass and Energy Release for NONE 11/20/81C Possible Pipe Break Inside II-3.0 Safety Related Water Supply 02/28/82 R+45 Containment (Ultimate Heat Sink)
VI-3 Containment Pressure and NONE 11/20/81C II-4.D Stability of Slopes 12/15/81R R+30 Heat Removal Capability II-4.F Settlement of Foundation 11/04/81R R+30 VI-4 Containment Isolation NONE 10/22/81C and Buried Equipment System III-3.A Effects of High Water 02/28/82 R+45 VI-6 Containment Leak Testing NONE 06/04/81C Level on Structures (MP A-04)
III-3.C Inservice Inspection of 11/12/81R k+45 VIII-1.A Potential Equipment NONE 10/16/81C Water Control Structure Failures Associated with a Degraded Grid Voltage III-4.B Turbine Missiles 12/07/81R R+30 (MP B-23)
III-4.D Sito Proximity Missiles 03/31/82 r+30 IX-1 Fuel Storage 02/28/82 R+30 (3-11)
0YSTER CREEK 211 (Cont.)
211 (Cont.)
SAR 1/
SER Z/
SAR 1/
SER Z/
TOPIC HD. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHECULt SCHEDULE XI-1 Appendix I(MP A-02)
NONE DELETED XV-16 Radiological Consequences 11/04/61R R+30 of Failure of Small Lines XI-2 Radiological (Effluent and NONE DELETED Carrying Primary Coolant Process Monitoring Systems)
Outside Containment (NRR B-67)
XV-18 Radiological Consequences 05/07/81R 07/ 01/81C XV-1 Decrease in Feedwater 05/07/81R 12/07/81C Temperature, Increase in Main Steam Line Failure Feedwater Flow, Increase in Outside Containment Steam Flow, Inadvertent Opening of Steam Generator, XV-19 Loss of Coolant Accidents 05/07/81R 09/04/81C Relief or Safety Valve (SYS)
Resulting From Spectrum Breaks Withic Rawctor XV-3 Loss of External Load, 05/07/81R 07/16/81C (DOSES)
Coolant Pressure Boundary 02/28/82 R+30 Turbino Trip, Loss of Condenser Vacuum, closure XV-20 Radiological Consequences 02/28/82 R+30 of Main Steam Isolation of Fuci Damaging Accidents Valve (BWR), Steam Pressure (In & Out of Containment)
Regulatory failure (closed)
XV-4 Loss of Non-Energency A-C 05/07/81R 07/16/81C l/ SAR : Licensee Safety Analysis Report-Scheduled or Actual Power to the Station (actual (status 'b) when date is followed by R)
Auxiliaries Z/ SER = Staff Safety Evaluation Report -Scheduled or Actual XV-5 Loss of Normal Feedwater 05/07/81R 11/30/81C (Actual (status Ga, 5, 7) when date is followed by C)
Flow
}/ Desiginated number of days from receipt of licensoo SAR XV-7 Reactor Coolant Pump Rotor 08/25/81R 12/07/81C (Note: if Licensee SAR is received then date is from Scizure and Reactor Coolant receipt of additional information requested)
Pump Shaft Break XV-9 Startup or an Inactive Loop 05/07/81R 12/30/81C or Recirculation Lo.
at Incorrect Temperature and Flow Controller Malfunction Causing an Increase in BWR Core Flow Rate XV-13 Spectrum of Rod Drop NONE 04/09e81C (sys)
Accident 05/07/81R 0 7/ 01/81C (doses)
XV-14 Inadvertent Operation of 05/07/81R 07/16/81C ECCS that Increases Reactor Coolant Inventory XV-15 Inadvertent Opening of BWR 05/07/81R 11/19/81C Safety / Relief Valve (3-12)
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SER 2/
SAR 1/
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TOPIC HO. TITLE SCHEDULE SCHEDULE TCPIC FO. TITLE SCHEDULE SCHEDULE
~~
III-1 Classification of NONE 01/22/82 II-3.A Hydrologic Description 06/25/81R R+45 (SYS)
Structures, Components and Systems (Seismic and II-3.5 Flooding Potential 8 06/26/81R R+45 Quality)
Protection Requirements III-2 Wind and Tornado Loadings NONE 12/30/81 II-3.B.1 Capability of Ope?ating 06/25/81R R+45 Plant to Cope with Design III-5.A Effects of Pipe Break on 01/31/82 02/10/82 Basis Flooding Conditions Structures, Systems and Components Inside II-3.C Safety Related Water 04/28/81R R+45 Containment Supply (UHS)
III-5.B Pipe Dreak Outside 12/04/81R 01/20/32 II-4.B Proximity of Capable NONE 12/30/81C Containment Tectonic Structures in Plant Vicinity III-7.B Design Codes, Design NONE 06/30/82 Criteria, Load Combinations II-4.D Stability of Slopes 08/31/81R 01/30/82 and Reactor Cavity Design II-4.F Settlement of Foundations 04/28/81R 01/30/82 V-11.B RHR Interlock Requirements NONE 01/22/82C and Buried Equipment (ELEC)
III-3.C Inservico Inspection of 08/31/81R R+45 VII-3 Systems Required for Safe NONE 01/22/82C Water Control Structures (ELEC)
Shutdown III-4.B Turbine Missiles 08/31/81R R+30 VII-6 Frequency Decay NONE 08/26/81C III-4.C Site Prximity Missiles 04/29/81R 10/29/81C IX-3 Station Service and Cooling 11/24/81R R+30 1/
(Including Aircraft)
Water Systems l
IV-3 BWR Jet Pumps Operating NONE 06/30/82 IX-5 Ventilation Systems 11/19/81R R+30 Indications XIII-2 Sa feguards Industrial NONE 06/30/82 V-1 Compliance with Codes and NDHE DELETED Security (MP A-10)
Standards (10 CFR 50.55a)
(MP A-01 A-14) gg VI-1 Organic Materials and Post 09/30/81R 01/28/82C SAR 1/
SER 2/
Accident Chemistry TOPIC NO. TITLE SCHEDULE SCHEDULE IX-6 Fire Protection NONE e6/30/82 II-1.A Exclusion Area Authority &
04/17/81R 07/31/81C Control 211 II-1.B Population Distribution 05/19/81R 10/29/81C SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE II-1.C Potential Hazards or 04/29/81R 10/29/81C Changes in Potential II-2.C Atmospheric Transport and 05/19/81R 09/29/81C Hazards Due to Transporta-Diffusion Characteristics tion, Institutional, and for Accident Analysis Military Facilities III-4.A Tornado Missiles 08/31/81R 12/30/81 (3-14)
MILLSTONE 1 Q11 (Cont.)
E11 (Cont.)
l SAR J/
S'EP 2/
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEUULE TOPIC NO. TITLE SCHEDULE SCHEDULE III-4.C Internally Generated 01/31/82 R+30 XV-3 Loss of External Load.
06/30/81R 09/18/81C Missiles Turbine Trip, Loss of Condenser Vacuum, Closure III-8.A Loose Parts Monitoring and N0hh 12/31/81 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 R+30 Includ'ng Functional Design XV-4 Loss of Non-Emergency A-C 06/30/81R 09/18/81C and Protection Against Power to the Station
$1ngle Failures Auxiliaries VI-2.D Mass and Energy Release for NONE 12/01/81 XV-5 Loss of Normal Feedwater 06/30/81R 12/23/81C Possible P1pe Break Inside Flow Containment XV-7 Reactor Coolant Pump 06/30/81R 11/18/81C VI-3 Containment Pressure and HDHE 12/01/81 Rotor Seizure and Reactor Heat Removal Capability Coolant Pump Shaft Break VI-4 Containment Isolation NONE 11/16/81C XV-8 Control Rod Misoperation 06/30/81R 08/26/01C (SYS)
System (System Malfunction or Operator Error) t VI-6 Leak Tosting (MP A-04)
NONE 01/30/82 XV-9 Startup or an Inactive Loop 06/30/81R 12/30/8tC VI-7.A.4 Core Spray Nozzle NONE 12/31/81 or Recirculation Loop at an Effectiveness (NRR A-16)
Incorrect Temperature, and Flow Controller Malfunction VIII-1.A Potential Equipment NONE 03/31/82 Causing an Increase in SWR Failures Associated With a Core Flow Rate Degraded Grid Voltage XV-11 Inadvertent Loading and 06/30/81R 10/14/810 IX-1 Fuel Storage 08/31/81R R+30 Operation of a Fuel Assembly in an Improper XI-1 Appendix I(MP A-02)
NONE DELETED Position i
XI-2 Radiological (Effluent 8 NONE DELETED XV-13 Spectrum of Rod Drop 06/30/81R 09/09/81C i
Process) Monitoring Systems (SYS)
Accidents (BWR)
(NRR B-67)
(DOSES) 06/30/81R 09/21/81C XV-1 Decrease in Feedwater 06/30/81R 12/15/81C XV-14 Inadvertent Operation of 06/30/81R 09/18/81C Temperature, Increase in ECCS and Chemical and Feedwater Flow, Increase in Volume Control Systen Steam Flow and Inadvertent Malfunction that Increases Opening of a Steam Gener-Reactor Coolant Inventory ator Relief or safety Valve XV-15 Inadvertent Opening of a 06/30/81R 10/28/81C PWR Pressurizar Safety Relief Valve or a BWR Safety Relief Valve (3-15)
_.m MILLSTONE 1 211 ( C o r.t. )
l SAR 1/
SER 2/ I TOPIC NO. TITLE
,$CHEDULE SCHEDULE XV-16 Radiological Consequences - 06/30/81R 0 9/21/81C of Failure of Small Lines Carrying Primary Coolant Outside Containment XV-18 Radiological Consequences 06/30/81R 09/21/81C of Main Steam Line Failure Outside Containment (BLR)
XV-19 Loss of Coolant Accidents 06/30/81R 08/26/81C (SYS)
Resulting from Spectrum of (DOSES)
Postulated Piping Breaks 06/30/81R 09/21/81C Within the Reactor Coolant Pressure Boundary XV-20 Radiological Ceasequences 06/30/81R 09/21/81C of Fuel Damaging Accidents (Inside and Outside Containment) 1/ SAR : Licenste Safety Analysis Report-Scheduled or Actual (actual (status 4b) when date is followed by R)
[
Z/ SER : Staff Safety Evaluation Report -Scheduled or Actual (Actual (status 4a, 5, 7 ) when dato is followed by C) 1/ Desiginated number of days from receipt of licensee SAR (Notes if Licenson SAR is received then date is from receipt of additional information requested) l 1
b (3-16) l
l' l-tt J
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TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC HO. TITLE SCHEDULE SCHEDULE IX-3 Station Service and Cooling 11/ 0 2 / 81 R 04/30/82 111-1 Classification of NONE 05/30/82 Water Systens Structures, Components and Systems (Seismic and IX-5 Ventilation Systems 12/16/81R 05/30/82 Quality) l III-2 Wind and Tornado Loadings 05/01/82 R+60 J/
pt SAR 1/
SER 2/
III-5.A Effects of Pipe Break on 11/15/81 03/26/82 TOPIC NO. TITLE S*HEDULE SCHEDULE Structures, Systems and Components Inside II-1.C Pot 9ntial Hazards or 11/12/81R C2/28/82 Containment Changes in Potential Hazards Due to
.II-5.B Pipe Break Outside 10/15/81 03/05/82 Transportation, Institutional Industrial, Containment and Military Facilities III-6 Seismic Design NONE 12/31/82 f
Considerations II-3.A Hydrologic Description NONE 03/30/82 l
l III-7.B Design Codes, Design NONE 09/30/82 II-3.B Flooding Potential &
NONE 03/30/82 I
Criteria, Load Protection Requirements Combinations, and Reactor i
Cavity Design Criteria II-3.C Safety Related Water NONE 03/30/82 l
Supply (UHS) 1 V-11.B RHR Interlock Requirements NONE 02/28/82 II-4.D Stability of Slopes 11/02/81R 03/15/82 (ELEC)
VI-7.A.3 ECCS Actuation System NONE 11/18/81C II-4.F Settlement of Foundations 11/02/81R 03/15/82 and Buried Equipment VI-7.B ESF Switchover from N0HE 09/04/81C (ELEC)
Injection to Recirculation III-3.A Effects of High Water Level 05/30/82 R*30 Mode (Automatic ECCS on Structures Realignment)
III-4.B Turbine MissilesCMP B-46)
NDHE 03/30/82 VI-10.A Testing of Reactor Trip HONE 08/28/81C System and Engineered III-4.D Site Proximity Missiles 10/23/81R 12/31/81 Safety Features Including (Including Aircraft)
Response Time Testing III-7.D Containment Structural 06/09/81R 02/15/82 VII-1.A Isolation of Reactor HONE 09/09/81C Integrity Tests Protection Systems, Including Qualifications V-1 Compliance with Codes and HONE DELETED of Isolation Devices Standards (10 CFR 50.55a)
(MP A-01)
VII-2 Engineered Safety Features H0HE 11/18/81C (ESF) System Control Logic VI-1 Organic Materials and Post 01/28/82C R+45 and Design Accident Chemistry VII-3 Systems Required for Safe NONE 11/18/81C IX-6 Fire Protection (MP B-02)
NONE f0/Of/62 (ELEC)
Shutdown VII-6 Frequency Decay NDHE 08/28/81C (3-18)
SAN ON0FRE Dil Ell (Cont.)
SAR 1/
SER g/
SAP 1/
SER g/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCNEDULE III-4.A Tornado Missiles 05/01/82 R+30 XV-3 Loss of External Load.
0 7/ 01/81 R 08/26/81C Turbine Trip, Loss of Con-III-4.C Internally Generated 04/30/82 R+30 densor Vaccum, Closure of Missiles Main Steam Isolation a l v e (BWR), and Steam Pret?ure III-8.A Loose Parts Monitoring and NONE 12/07/81C Regulator Failure (Closed)
Core Barrel Vib.ation Monitoring (NRR B-60,C-12)
XV-4 Loss of Non-Emergency A-C 09/18/81R 12/1?/81C Power to the Station IV-2 Reactivity Control Systems 04/30/82 R+30 Auxiliaries l
Including Functional Design 5
and Protection Against XV-5 Loss of Normal Feedwater 07/01/81R Of/25/32C Single Failures Flow V-7 Reactor Coolant Pump HONE 11/05/81C XV-6 Feedwater System Pipe 07/01/81R 02/15/82 Overspeed(NRR B-68)
Breaks Inside and Outside Containment (PWR)
VI-2.D Mass and Energy 9elease for NONE 12/04/81C Possible Pipe 8rcak Insi de XV-7 Reacter Coolant Pump Rotor 07/01/81R 01/29/82 Containment Seizure and Reactor Coolant Pump Shaft Break VI-3 Containment Pressure and NONE 11/13/81 Heat Remaval Capability XV-8 Control Rod Misoperation 07/01/81R 11/19/81C (System Malfunction or VI-4 Containment Isoletion NONE 01/29/82C Operator Error)
(SYS)
System XV-10 Chemical and Volume Control 07/01/81R 02/15/82 VI-6 Containment Leak Testing NONE 03/31/82 System Malfunction that (MP A-04)
Results in a Decrease in the Boron Concentration in VIII-1.A Potential Equipment Failure NONE 03/31/82 the Reactor Coolant (PWR)
Associated with a Degraded Grid Voltage (MP B-23)
XV-12 Spectrum of Rod Ejection 07/01/81R 11/19/81G" Accidents (PWR)
IX-1 Fuel Storage 04/30/82 R+30 XV-14 Inadvertent Operation of 07/01/81R 02/19/82 XI-1 Appendix I NONE DELETED ECCS and Chemical and Volume Control System
'XI-2 Radiulogical (Effluent and NONE DELETED Malfunction that Increases Process) Monitoring Systems Reactor Coolant Inventory (NRR B-67)
XV-1 Decrease in Feedwater 07/01/81R 10/27/81C XV-15 Inadvertent Opening of a G7/01/81R 02/15/82 Temperature, Increase in PWR Pressurizer Safety-Feedwater Flow, Increase Relief Valve of a BWR in Steam Flow and Safety / Relief Valve Inadvertent Opening of a Steam Generator Relief XV-16 Radiological Conscauences 08/04/81R 11/18/81C or Safety Valve of Failure of Small Lines Carrying Primary Coolant XV-2 Spectrum of Steam System 07/01/81R 10/27/81C Outside containment Piping Failures Inside and Outside of Containment (PWR)
- I5-19)
SAN ON0FRE ESI (Cont.)
SAR 1/
SER 2/
TOPIC HO. TITLE SCHEDUEE SCHEDULE XV-17 Gystem Generator Tube NONE 12/07/81C (SYS)
Failure (PWR)
XV-19 Loss of-Coolant Accidents C7/01/81R 08/26/81C Resulting From Spectrum of Postulated Piping Breaks Lii t' ai n the Reactor Coolant Pressure Boundary 1/ SAR: Licensee Safety Analysis Report-Scheduled or Actual (Actual (status 4b) when date is followed by R) 1/ SER = Staff Safety Evaluation Report -Scheduled or Actual (Actual (status 4a, S, 7) when date is followed by C)
J/ Desiginated number of days from receipt of licensee SAR (Note:
if Litensee SAR is received then date is from receipt of aduitional information requested) e (3-20)
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BIG ROCK POINT pk BIG ROCK POINT El SAR J/
SER 2/
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITL2 SCHEDULE SCHEDULE 111-1 Classification of Struct-NONE 02/19/82 II-3.A Hydrologic Description NONE.
R+45 (SYS) ures, Components and Sys-tems (Seismic and Quality)
II-3.B Floodin? Potential and NONE R+45 Protectis7 Rcquirements III-2 Wind and Tornado Loading 02/01/82 R+60 II-3.B.1 Capability of Operating NONE R+45 III-5.A Effects of Pipe Break on 12/01/81 0?r.0/82 Plans to Cape with Designs Structures, Systems and Basis Floeding Conditions Components Inside Containment II-3.C SafetV-Related Water Supply NONE R+45 (Ultimate Heat Sink UHS))
III-5.B Pipe Break Lutside 12/15/81 04/16/82 Containment II-4.B Proximity of Capable NONE 01/31/82 Tectonic Structures in III-6 Seismic Design NONE 07/31/82 Plant Vicinity Considerations II-4.D Stability of Slopes 10/05/81R 02/15/82 III-7.B Design Codes, Design NONE 07/31/82 Criterion, Load II-4.F Settlement of Foundations 10/19/81R 02/15/82 Combinations and Reactor and Buried Equipment Cavity Design Criterion III-3.A Effects of Nich Water 03/15/82 R+30 VI-7.A.3 ECCS Actuation System NONE 01/29/82C Level on Structures VI-7.C ECCS Single Failure Cri-NONE 08/05/81C III-3.C Inservice Inspection of 12/21/81R 02/15/82 torion and Requirements for Water Control Structures Locking Out Power to Valves Including Independence III-4.B Turbine Missiles 12/15/81 R+30 j
of Interlocks on ECCS Valve III-4.D Site Proximity Missiles 12/14/81R 03/31/82 j
l VI-7 C.2 Failure Mode Analysis ECCS HONE i 08/05/81C (Including Aircraft)
VI-10.A Testing of Reactor Trip 12/23/81 R+30 III-7.D Containment Structural 12/29/81R 03/31/82 System and Engineered Integrity Tests Safety Features, Including Response Time Testing V-1 Compliance with Codes and NONE DELETED Standards )1o CFR 50.55a)
VII-1.A Isolation of Reactor NONE 01/31/82 (MP A-01,A-14)
Protection System From Hon-Safety Systems. Including VI-1 Organic Materials and Post 10/15/81 R+45 Qualification of Isolation Accident Chemsitry Devices Accident Chomsitry i
i VII-2 Engineered Safety Features NONE 12/31/81C IX-6 Fire Protection (MP B-02)
NONE 01/04/82 (ESF) System Control Logic and Design E.11 VII-6 Frequency Decay NONE 09/21/81C SAR 1/
SER 2/
IX-3 Station Service and 12/10/81R R+30 TOPIC NO. TITLE SCHEDULE SCHEDULE Cooling Water Systems II-2.C Atmospheric Transport and 09/25/81 R+30 IX-5 Ventilation Systems 01/15/82 R+30 Diffusion Character stics for Accident Analysis (3-22)
l BIG ROCK POINT R11 (Cont.)
D11 (Cont.)
SAR 1/
SER Z/
SAR 1/
SER Z/
TOPIC HO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE III-4.A Tornado Missiles 03/15/82 R+30 XV-3 Loss of External Load.
07/15/81R 10/16/81C Turbine Trip, Loss of III-4.C Internally Generated 03/15/82 R+30 Condenser Vacuum, Closure Missiles of Main Steam Isolation Valve (BWR), and Steam III-3.A Loose Parts Monitoring and HDHE 03/31/82 Pressure Regulator Failure Core Vibration Monitoring (Closed)
(NRR B-60,C-12)
XV-4 loss of Non-Emergency A-C 07/15/81R for16/A1C IV-2 Reactivity Control System NONE 12/07/81C Powor to Use Station Ir.cluding Functional Design Auxiliaries and Protection Against Single Failures XV-5 Loss of Normal Feedwater 07/15/81R 01/26/82C Flow VI-2.D Mass and Energy Release for NONE 01/22/82 Postulated Pipe Dreaks XV-7 Reactor Coolant Pumps 07/15/81R 03/15'82 Inside Containment Rotor Seizure and Reactor Coolant Pump Shaft Break VI-3 Containment Pressures and NONE J1/22/82 Heat Removal Capability XV-8 Control Rod Misoperation 09/23/81R 12/31/81C (System Malfunction or VI-4 Containment Isolation Sys.
NDHE 01/22/82 Operator Error)
VI-5 Containment Leak Testing NONE 11/30/81 XV-9 Startup of an Inactive Loop 07/15/81R 03/30/82 (MP A-04) or Recirculation Loop at an Incorrect Temperature and VI-7.B ESF Switchover from NONE 03/01/82 Flow Controller Malfunction Injection to Recirculation Causing an Increase in BWR Mode ( Autom.. si c EECS Core Flow Rate Realignment)
XV-11 Inadvertent Loading and 09/28/81R 11/20/81C VIII-1.A Potential Equipment NONE 01/29/82 Operation of a Fuel Failures Associated with Assembly in an Improper Degraded Grid Position (BWR)
IX-1 Fuel Storage 08/31/81 R+30 XV-13 Spectrum of Rod Drop SYS 07/01/81R 11/20/81C Accidents DOSES 07/01/81R 10/23/81C XI-1 Appendix I(MP A-02)
NONE DELETED XI-2 Radiological (Effluent NONE DELETED XV-14 Inadvertent Operation of 06/26/81R 08/18/81C and Process) Monitoring ECCS and Chemical and Systems (NRR B-67)
Volume Control System Malfunction that Increases XV-1 Decrease in Feedwater 07/15/81R 03/15/82 Reactor Coolant Inventory Temperature Increase in Feedwater Flow, Increase XV-15 Inadvertent Opening of a 06/26/81R 08/18/81C in Steam Flow and PWR Pressurizer Safety Inadvertent Opening of a Relief Valve or a BWR Steam Generacor Relief Safety / Relief Valve or Safety Valve (3-23)
BIG ROCK POINT E11 (Cont.)
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE XV-16 Radiological Consequences 0 7 / 01/ 81R 12/14/81C of Failure of Small Lines Carrying Primary Coolant Outside Containment XV-18 Radiological Consequences 07/01/81R 11/27/81 of Main Steam Line Failure Outside Containment XV-19 Loss of Coolant Accidents 06/29/81R 08/18/81C (SYS)
Resulting From Spectrum of Postulated Piping Breaks (DOSES) within the Reactor Coolant 07/01/81R R+30 Pressure Boundary XV-20 Radiological Consequences 07/03/81R 10/23/81C of Fuel Damaging Accidents (Inside and Outside Containment) 1/ SAR : Licensee Safety Analysis Report-Scheduled or Actual (Actual (Status 4b) when date is followed by R) g/ SER : Staff Safety Evaluation Report -Scheduled or Actual (Actual (status 4a, 5, 7 ) when date is followed by C) 1/ Desiginated number of days from receipt of licensee SAR (Note: if Licensee SAR is received then date is from receipt of additional information requested)
(3-24)
~..
LICENSEE SUBMITTALS BIG ROCK POINI SLBMITTALS 48 7
TN 35 ---
38 --
25 -
28 --
,s 15 --
i 19 --
/
5--
i i
i i
i i
g JUN JLL -
ALE SEP OCT NOV DEC JAN FEB MAR APR MAY JLN Jtt METHS Target 0
0 2
4 4
5 1
1 4
0 0
0 0
PER MONTH Actual 0
0 2
2 0
3 1
Target 0
0 2
6 10 15 16 17 21 21 21 21 21 CUMULATIVE Actual 0
0 2
4 4
7 8
(3 25)
HADDAM NECK Ek HADDAM NECh
~f' EL (Cont.)
SAR 1/
SER Z/
SAR 1/
SER Z/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE 111-1 Classifiestion of NONE 03/19/82 IX-5 Ventilation Systems 12/14/ 81 R 04/15/82 (SYS)
Structures, Components and Systems (Seismic and XIII-2 Safeguards / Industrial NONE 10/30/82 Quality)
Security (MP A-10)
III-2 Wind and Tornado Loadings 12/14/81R R+60 J/
Ef "II-5 A.
Effects of Pipe dreak 01/31/82 06/24/82 SAR 1/
SER Z/
on Structures, Systems TOPIC NO. TITLE SCHEDULE SCHECULE and Componets Inside Containment II-1.A Exclusion Area Authority 04/27/81R 04/30/82 B. Pipe Break Outside 10/02/81R 05/27/82 II-1.B Population Distribution 08/31/81R 04/30/82 Containment II-1.C Potential Hazards or 06/30/81R 04/30/82 III-6 Seismic Design NONE 10/30/82 Changes in Potential Considerations Hazards Due to Transportation.
III-7.B Design Codes, Design NONE 10/30/82 Institutional Industrial, Criteria. Load and Military Facilities Combinations, and Reactor Cavity Design Criteria II-3.A Hydrologic Description 12/14/81R R+45 VI-7.A.3 ECCS Actuation System NONE 01/29/82C II-3.B Flooding Potential and 12/14/81R R+45 Protection Requirements VI-7.C.3 The Effect on PWR Loop NONE 12/14/81C Isolation Valve Closure II-3.B.1 Capability of Operating 12/14/81R R+45 During a LOCA en ECCS Plant to Cope with Design Performance Basis Flooding Conditions VI-10.A Testing of Reactor Trip 01/31/82 R+30 II-3.C Safety related Water Supply 12/14/81R R+45 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 in VII-1.A Isolation of Reactor NONE 01/31/82 Plant Vicinity Protection System fr6m Hon-Safety Systems, Including II-4.D Stability of Slopes 08/31/81R 02/28/82 Qualifications of Isolation Devices II-4.F Settlement ot Foundations 12/18/81R 02/28/82 VII-2 Engineered Safety Features NONE 01/31/82 and Seried Equipment (ESF) System Control Logic and Design III-3.A Effects of High Water 08/31/81R 01/25/a2 Level on Structures VII-6 Frequency Decay NONE 08/28/81C III-3.B Structural and Other NDHE 01/31/82 VIII-4 Electrical Penetrations NONE 12/23/81C Consequences (e.g. Flooding of Reactor Containment of Safety-Related Equipment in Basements) of Failure of IX-3 Station Service and Cooling 12/14/81R 03/15/82 Underdrain Systems Water Systems (3-26)
. _ _ ~
HADDAM NECK 21 (cont.)
Hil (Cont.)
SAR 1/
SER Z/
SAR 1/
SER Z/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE III-3.C Inservice Inspections of 08/ 31/81R 02/28/82 VI-6 Containment Leak Testing NONE 11/30/81 Water Control Structures (MP A-04)
III-4.B Turbine Missiles (MP B-46)
NONE 12/31/81 VI.7.B ESF Switchover from NONE 04/01/82
($YS)
Injection to Recirculatf ore III-4.D Site Proximity Missiles 06/25/81R 04/30/82 Mode (Automatic ECCS (Including Aircraft)
Realignment)
III-7.D Containment Structural 06/27/81R 10/16/81C VIII-1.A Potenti'al Equipment NONE 03/31/82 Integrity Tests Failures Associated with a Degradad Grid Voltage V-1 Compliance with Codes and NONE DELETED (MP B-23)
Standards (10 CFR 50.55a)
(MP A-01,A-14)
IX-1 Fuel Storage 08/31/81R 11/15/81 VI-1 Organic Materials and Post 01/31/82 R+45 IX-4 Baron Addition Systems 10/02/81R 04/01/82 Accident Chemistry XI-1 Appendix ICMP A-02)
NONE DELETED IX-6 Fire Protection (MP B-02)
NONE 07/01/82 XI-2 Radiological (Effluent NONE DELETED and Process) Monitoring 211 Systems (NRR B-67)
SAR 1/
SER 2/
TOPIC !i0. TITLE SCHEDULE SCHEDULE XV-1 Decrease in Feedwater 09/30/81R 04/09/82 Temperatures, Increase in III-4.A Tornado Missiles 08/31/81R 12/28/81C Feedwater Flow. Increase in Steam Flow and Inadvertent III-4.C Internaly Generating 01/31/82 R+30 Opening of a Steam Genera-Misslies tor Relief or Safety Valve III-8.A Loose Parts Monitoring and NONE 04/30/82 XV-2 Spectrum of Steam System 09/30/81R 04/15/82 Core Barrel Vibration Piping Failures Inside and Monitoring (NRR B-60,C-12)
Outside of Containment (SYS)
(PWR)
(DOSES) 09/30/81R R+30 IV-2 Reactivity Control Systems 06/30/81R 12/23/81C Including Functional Design and Protection Against XV-3 Loss of External Load.
09/30/81R 03/17/82 Single Failures Turbine Trip, Loss of Condenser vacuum, Closure V-7 Reactor Coolant Pump NONE 11/05/81C of Main Steam Isolation Oversoeed(NRR B-68)
Valve (BWR), and Steam Pressure Regulator failure VI-2.D Mass and Energy Release for NONE 04/30/82 (Closed)
Po:sible Pipe Dreak Inside Containment XV-4 Loss of Non-Emergency A-C 09/30/81R 12/17/81C Power to the Statian VI-3 Containment Pressure and NONE 04/30/82 Auxillaries Heat Recoval Capability XV-5 Loss of Normal Feedwater 09/30/81R 04/20/82 VI-4 Containment Isolation NONE 01/22/82 Flow System (3-27)
n HADDAM NECK 211 (Cont.)
211 (Cont.)
SAR 1/'
SER 2/
S A R 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE XV-6 Feedwater System Pipe 09/30/81R 04/20/82 XV-19 Loss of-Coolant Accidents 09/30/81R 11/10 / 81 C Breaks Inside and Outside Resulting from Spectrum of Containment (PWR)
Postulated Piping Breaks Within the Reactor Coolant I
XV-7 Reactor Coolant Pump Rotor 09/30/81R 03/15/82 Pressure Boundarv (SYS)
Seizure and Reactor Coolant (DOSES) 09/30/81R R+30 Pump Shaft Break XV-8 Control Rod Misoperation 99/30/81R 03/15/82 1/ SAR Licensee Safety Analysis Report-Schcduled or Actual (System Malfunction or (Actual (Status 4b) when date is followed by R)
Operator Error) 2/ SER = Staff Safety Evaluation Report -Scheduled or Actual XV-9 Startup or an Inactive 09/30/81R 04/01/82 (Actual (status 4a, S,
- 7) when date is followed by C)
Loop or Recirculation Lcop at an Incorrect 1/ Desiginated number of days from receipt of licensee SAR Temperature, and Flow (Note: if Licensee SAR is received then date is from s
Controller Malfunction receipt of additional information requested)
Causing an Increase in BWR Core Flow Rate XV-10 Chemical and Volume Control 09/30/81R 04/01/82 System Malfunction that Results in a Decrease in in Boron Concentration in the Reactor Coolant (PWR)
XV-12 Spectrum of Rod Ejection 09/30/81R 03/15/82 Accidents (PWR)
(SYS)
(DOSES) 09/30/81R R+30 XV-14 Inadvertent Operation of 09/30/81R 04/15/82 ECCS and Chemical and Volume Control System Malfunction that Increases Reactor Coolant Inventory XV-15 Inadvertent Opening of a 09/30/81R 04/16/82 PWR Pressurizer 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) 02/28/87 04/30/82 Tube Failure (PWR) (DOSES) 02/28/E2 R+30 (3-28)
LICENSEE SUBMITTALS HADDAM ECK StBUTTALS g
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7 18 2
0 6
1 0
0 0
0 0
0 PER MONTH Actual 0
6 0
16 0
7 0
Target 0
7 25 27 27 33 34 34 34 34 34 34 34 CUMULATIVE Actual 0
6 6
22 22 29 29 (3-29)
YANKEE R0WE RL YANKEE R0WE DL (Cont.)
SAR 1/
SER Z/
SAR 1/
SER Z/
TOPIC NO. TITLE SCHECULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE III-1 Classification of Struct-NONE 04/16/32 IX-5 Ventilation Systems 11/18/81R R+30 ures, Components and Sys-tems (Seismic and Quality) 21 III-2 Wind and Tornado Loadings 02/15/82 R+60 J/
SAR 1/
SER Z/
TOPIC NO. TITLE SCHEDULE SCHEDULE III-5.A Effects of Pipe Break on 01/22/82 08/10/82
~
06/30/82 Structures, Systems and Il-1.A Exclusion Area Authority 02/15/82 l
Camponents Inside and Control Containment II-1.B Pipulation Distrubution 05/01/81R 06/30/82 III-5.B Pipe Break Outside 01/21/82R 07/16/82 Containment II-1.C Potential Hazards or 04/09/81R 06/30/82 l
Changes in Potential III-6 Seismic Dasign NOME 07/31/82 Hazards Due to Ccnsiderations Transportation, Institutional Industrial, III-7.B Design Codes, Design NONE 08/31/82 and Military Facilities Criteria, Load II-3.C Safety-related Water NONE 02/28/82 Combinations, and Reactor Cavity Design Criteria Supply (Ultimate Heat Sink (UHS)
V-11.B RHR Interlock Requirements NONE 01/22/82C (ELEC)
II-4.B Proximity of Capable NONE 06/30/82 Tectonic Structures in VI-7.A.3 ECCS Actuation System 06/30/81R 01/29/82C Plant Vicinity (B-46)
VI-10.A Testing of Reactor Trip 06/30/81R 01/22/82C II-4.D Stability of Slopes 02/15/82 R+30 System and Engineered Safety Features Including II-4.E Dam Integrity NONE 02/28/82 Safety Features Including Response Time Tetting II-4.F Settlement of Foundations 08/31/81R 02/28/82 and Buried Equipment VII-1.A Isoaltion of Reactor NONE 10/05/81C Protection System from III-3.A Effects of High Water 02/15/82 R+30 Hon-Safety Systems, Level on Structures Including Qualifications of Isolation Devices III-3.C Inservice Inspection of 01/04/82R 02/28/82 Water Control Structures VII-2 Engineered Safety Features NOME 10/19/81C (ESF) System Control Logic III-4.B Turbine Missiles (MP b-46)
NONE 12/31/81 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 Centainment Structural 11/18/81R R+30 VII-6 Frequency Dacay NONE 08/28/81C Integrity Tests l
VIII-4 Electrical Penetrations of NONE 02/28/82 V-1 Compliance with Codes NOME DELETED Reactor Containment and Standards (to CFR 50.55a)(MP A-01,A-14) 09/17/81R 11/30/61 IX-3 Station Service and Cooling Water Systems (3-30)
YANKEE R0WE 21 (Cent.)
~~Dil (Cont.)
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC HO. TITLE SCHEDULE SCHEDULE VI-1 Organic Materials and 02/15/82 R+30 IX-1 Fual Storage 11/18/81R R+30 Post Accident chemistry IX-4 Baron Addition System 08/31/81R 05/07/82 IX-6 Fire Protection (MP B-02)
NONE 01/15/82 XI-1 Appendix I(MP A-02)
NONE DELETED Dil XI-2 Radiological (Effluent NONE DELETED SAR 1/
SER 2/
and Process) Monitoring TOPIC NO. TITLE SCHEDULE SCHEDULE Systems (NRR B-67) 11-2.C Atmospheric Transport and 06/30/81R 09/04/81C XV-1 Decrease in Feedwater 01/31/82 06/30/82 Diffusion Characteristics Temperature. Increase in for Accident Analysis Feedwater Flow, Increase in Steam Flow and III-4.A Tornado Missiles 02/15/82 R+3G Inadvertent Opening of a Steam Generator Relief III-4.C Internally Generated 02/15/82 R+30 or Safety Valve Missiles XV-2 Spectrum of Steam System 06/30/81R 05/21/82 III-8.A Loose Parts Monitoring NDHE 12/07/81C (SYS)
Piping Failures Inside and Core Barrel Vibration (DOSES) and Outside of Containment 09/30/81 R+30 Monitoring (NRR B-60,C-12)
(PWR)
IV-2 Reactivity Control Systems 09/17/81R 12/23/81C XV-3 Loss of External Load.
06/30/81R 01/25/82C Including Functional Design Turbine Trip, Loss of and Protection Against Condenser Vacuum, Closure Single Failures of Main Steam Isolation Valve (BWR), and Steam V-7 Reactor Coolant Pump NONE DELETED Pressure Regulator Failure Overspeed(NRR B-68)
(Closed)
VI-2.D Mass and Energy Release
' NONE 01/22/82 XV-4 Loss of Non-Emergency A-C 01/04/82R 06/01/82 for Possible Pipe Break Power to the Station Inside Containment Auxiliaries VI-3 Containment Pressure and NONE 01/22/82 XV-5 Loss of Normal Feedwater 06/30/81R 01/29/82C Heat Removal Capability Flow VI-4 Containment Isolation NONE 04/01/82 XV-6 Feedwater System Pipe 01/31/82 06/16/82 (SYS)
System Breaks Inside and Outside Containment (PWR)
VI-6 Containment Leak Testing NONE 03/30/82 (MP A-04)
XV-7 Reactor Coolant Pump Rotor 06/30/81R 12/31/81 Soirure and Reactor Coolant VI-7.B ESF Switchover from NONE 06/11/82 Pump Shaft Break (SYS)
Injection to Recirculation Mode (Automatic ECCS XV-8 Control Rod Misoperation 01/04/82R R+30 Realionment)
(Systcm Malfunction or Operator Error)
VIII-1.A Potaatial Equipment NONE 03/31/82 F ilures Associated with a Degraded Grid Voltage (MP B-23)
(3-31)
YANKEE R0WE R11 (Cont.)
SAR 1/
SER 2/
TOPIC HO. 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 t
XV-10 Chemical and Volume Control 06/30/81R 03/01/82 1
System Malfunction that Results in a Decrease in the Boron Concentration in the Reactor Coolant (PWR)
XV-12 Spectrum of Rod Ejection 06/30/8tR R+30 (SYS)
Accidents (PWR)
(DOSES) 08/30/81R 11/15/81 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 04/23/82 PWR Pressurizer Safety-Related Valve or a BWR Savety/ Relief Valve XV-16 Radiological Consequences 01/31/82 R+30 of Failure of Small Lines Carrying Primary Coolant Outside Containment XV-17 Steam Genceator Tube 01/31/82 06/30/82 (SYS)
Failure (PWR)
(DOSES) 01/31/82 R+30 XV-19 Loss of-Coolant Accidents 11/18/81R 06/30/82 (SYS)
Resultirq from Spectrum of (DOSES)
Postulated Piping Breaks 01/04/82R R+30 Within the Reactor Coolant Pressure Boundary 1/ SAR : Licensee Safety Analysis Report-Scheduled or Actual (Actual (Status 40) when date is followed by R)
Z/ SER = Staff Safety Evalvation Report -Scheduled or Actual (Actual (status 4a, 5, 7) when date is followed by C,3 J/ Desiginated number of days from receipt of licensee SAR (Notes if Licenseo SAR is received then date is from receipt of additional information requested)
(3-32)
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TDPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE III-1 Classification of NCNE 05/14/82 11-l.A Execlusion Area Authority 06/22/81R 07/31/82 (SYS)
Structures, Components and and Control Systems (Seismic and Quality)
II-1.B Popu)ation Distribution 06/16/81R 07/31/82 III-2 Wind and Tornado Loadings 08/06/81R 02/28/82 II-1.C Potential Hazards or 07/15/81R 07/31/82 l
Changes in Potential III-5.A Effects of Pipe Break on 11/02/81 39/30/82 Harards Due to l
Structures. Systems and Transportation.
Components Inside Institutional Industrial, Containment and Military Facilities III-5.B Pipe Break Outside 06/29/81R 08/27/82 II-3.A Hydrolic Description 06/16/81R R+45 Cantainment II-3.B Flooding Potential and 09/01/81 R+45 III-6 Seismic Design NONE 11/30/82 Protection Requirements Con si dera'ti ons II-3.B.1 Capability of Operatinq 09/01/81 R+45 i
III-7.B' Design Codes, Design NONE 1*/30/82 Plant to Cope with Design i
Criteria, Load Basis Flooding Conditions Combinations, and Reactor Cavity'Dosign Criteria II-3.C Safety related Water Supply 06/26/81R R+45 (Ultimate Heat Sink (UHS))
8 V-11.3 RHR Interlock Requirements NONE R+30 (ELEC)
II-4.8 Proximity of Capable NONE 07/31/82 Tectonic Structures in VI-7.A.3 ECCS Actuation System NONE 01/29/82C Plant Vicinity VI-11.A Testing of Reactor Trip 06/25/81R 01/22/82C II-4.D Stability of Slopes NONE R+30 System and Engineered Safety Features Including II-4.E Dam Integrity NONE R+30 Response Time Testing II-4.F Settlement of Foundations 12/31/81 02/28/82 VII-1.A Isolation of Reactor NONE 11/30/61 and Buried Equipment Protection System from Hon-Safety Systems 4 III-3.A Effects of High Water Level 12/31/81 R+30 Including Qualifications of on Structurc; Isolation Devices III-3.C Inservice Inspection of 12/31/81 A+45 VII-2 Engineered Safety Features NONE 11/30/81 Water Control Structures (ESF) System Control Logic and Design III-4.B Turbine Missiles 09/01/81 R+30 VII-3 Systems Required for Safe NONE 01/31/82 III-4.D Site Proximity Missiles 09/15/81R 07/31/82 (ELEC)
Shuf.down (Including Aircrafts)
VII-6 Frequency Decay NONE 09/21/81C III-7.D containment Structsral 06/29/81R 62/01/82 IX-3 Station Service and Cool'ng 11/02/81 R+30 i
Water Systems V-1 Compliance with Codes and NDHE DELETED Standards (10 CFR 50.55a)
IX-5 Ventilation Systems 11/02/81 R+30 (MP A-Oi,R-14)
(3-34)
LACROSSE D1 (Cont.)
D11 (Cont.)
SAR 1/
SER 2/
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE VI-1 Organic Materials and Post 12/S6/81 R+30 XI-2 Radiological (Effluent.and NONE DELETED Accident Chemistry Process) Monitoring Systems (NRR B-67)
IX-6
. Fire Protection (MP B-02)
NONE 10/30/82 XV-1 Decrease in Feedwater CS/21/81 07/31/82
. Temperature, Increase in Dil Feedwater Flow, Increase SAR J/
SER 2/
in Steam Generator Relief TOPIC NO. TITLE SCHEDutE SCHEDULE or Safety Valve II-2.C Atmospheric Transport and 10/01/81 R+30 XV-3 Loss of External Load.
06/26/81R 11/13/81C
. Diffusion Charactoristics Turbine Trip, Loss of Con-fer Accident Analysis denser Vacuum, Closure of Main Steam Isolation Valve III-4.A Tornado Missiles 11/02/81 R+30 (BWR), and Stam pressure Regulator Failure (Closed)
III-4.C Internally Generated 11/02/81 R+30 Missiles XV-4 Loss of Non-Emergency A-C 06/26/81R 10/21/81C III-8.A Loose Parts Montroring and NONE 07/30/82 Power to the Station Core Barrel Vibration Auxiliaries Monitoring (NRR B-60,C-12)
XV-5 Loss of Nor201 Feedwater 08/21/81 07/31/82 IV-2 Reactivity Control Systems NONE 12/10/81C Flow Including Functional Design and Protection Against XV-7 Reactor Coclant Pump Rotor 08/21/81 07/31/82 Single Failures Seizure and Reactor Coolant Pump Shaft Break VI-2.D Mass and Energy Release for NONE 01/22/82 6
Possible Pipe Break Inside.
XV-8 Control Rod Misoperation 08/21/81 R+30 Containments.
(System Malfunction or Operation Error)
VI-3 Containment Pressure and NONE 01/22/82 Heat Removal Capability XV-9 Startup or an Inactive Loop 08/25/81R 07/31/82 or Recirculation Loop at an VI-4 Containment Isolation NONE 05/03/82 Incorrect Temperature, and (SYS)
System Flow Controller Malfunction Causing an Increase in BWR VI-6 Containment Leak Testing NONE 11/30/81 Core Flow Rate (MP A-04)
XV-11 Inadvertment Loading and 12/31/81 R+30 VIII-1.A A. Potential Equipment NONE 03/31/82 Operation of a Fuel Failures Associated with a.
Assembly in an Improper Dograded Grid Voltage Position f
(MP B-23)
XV-13 Spectrum of Rod Drop 12/31/81 R+30 IX-1.
Fuel Storage 11/02/81 R+30 (SYS)
Accidents (BWR)
(DOSES) 12/31/81 R+30 XI-1 Appendix I(MP A-02)
NONE DELETED i
(3-35) 1 e
l LACROSSE Dil (Cont.)
SAR 1/
SER 2/
TOPIC HO. TITLE SCHEDULE SCHEDULE XV-14
-Inadvertent Ophyation of 08/25/81R 06/01/82 ECCS and Chemical and Volume Control System Malfunction that Increases Reactor Coolant Inventory XV-15 Inadverte"nt Opening of a 06/30/81R 09/21/81C PWR Pressuring Safety-Relief Valve cr a BWR Safety / Relief Valve XV-16 Radiological Consequences 08/21/81 R+30 of Failure of Small Lines Carrying Primary Coolant Outside Containment XV-18
. Radiological Consequences 11/02/81-R+30 of Main Ste.1m Line Failure-Outside Containment (BWR)
XV-19 Loss of-Coolant Accidents 08/21/81 07/31/82 (SYS)
Resulting from Spectrum of (DOSES)
Postulated Piping Breaks 08/21/81 R+30 Within the Reactor Coolant Pressure Boundary XV-20 Radiological Consequences.
11/02/81 R+30 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) g/ 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 (Nota: if Licensee SAR is received then date is from receipt of additional information requested) d (3-36)
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f,RC eom 335 U S. NUCLE AQ REIUL ATCQY COMMISSION BIBLIOGRAPHIC DATA SHEET NUREG-0485 Vol. 4 No. 1
- 4. 78TLE AND SU8 TITLE (Add Votume No, s/approphare)
- 2. (Leere elevel Systematic Evaluation Program Status Summary Report
- 3. RECIPIENT'S ACCESSION NO.
- 7. AUTHORtSi
- 5. DATE REPORT COMPLETED M ON TM l YEAR February 1982
- 9. PERFoAMING ORGANIZATION N AME AND MAILING ADDRESS IIncluor 2,0 Cocel DATE REPORT ISSUED "oN7" lYEAR Office of Management and Program Analysis Office of Nuclear Reactor Regulation February 1982 U.S. Nuclear Regulatory Comission s (tu e $sn*/
Washington, D.C.
20555 8 (Leave blanki
'2. SPONSO G ORGANIZATION NAME AND M AILING ADDRESS Itactude 2,0 Codel 10 PROJECT T ASK/ WORK UNIT NO Office of Management and Program Analys's Office of Nuclear Reactor Regulation
- 11. CONTR ACT NO.
U.S. Nuclear Regulatory Commission Washington, D.C.
20555
- 13. TYPE OF REPORT PE RICO COVE RE D (Inclus.ve dates 1 January 1 - 31, 1982
- 13. SUPPLEMENTARY NOTES
- 14. / Leave ele 141
- 16. ASSTR 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 4
status of the review process including individual topic and overall completion status.
- 17. KEY WORDS AND DOCUMENT AN ALYSIS 17a DESCRIPTORS l
l 1?b IDENTIFik RS/OPEN-EN DE D TERMS i
- 18. AV AILABILITY ST ATEMENT 19 SE CURITY, C1, ASS (Th<s report) 21 NO OF P AGES Unclassified Unlimited 20 SECURITY CLASS (This page/
22 P836CE Unclassified s
N RC FORM 335 (7 771
- U.S. COVERNMENT FRINTING OFFICE: 1982 361-302/508
-~
l UNITED STATES nucle AR REautAToRY couwissioN r
3 W AS HINGTON, D. C. 20883 POSTAGE ANO Pggs FAeO U.S. NUCLE A R REGULATOR Y OPPICI AL SUSINggg COMusssion PEN ALTY POR PRIVATE USE.$300 L
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