ML20040E557
| ML20040E557 | |
| Person / Time | |
|---|---|
| Issue date: | 12/31/1981 |
| From: | NRC OFFICE OF MANAGEMENT AND PROGRAM ANALYSIS (MPA) |
| To: | |
| References | |
| NUREG-0485, NUREG-0485-V03-N14, NUREG-485, NUREG-485-V3-N14, NUDOCS 8202050086 | |
| Download: ML20040E557 (96) | |
Text
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=is NUREG-0485 si Vol. 3, No.14 December 31,1981 gs I
SYSTEMATIC EVALUATION PROGRAM (g.
^2 STATUS
SUMMARY
REPORT
- $g#M ya e n
%7g;rjf UNITED STATES NUCLEAR REGULATORY COMMISSION 3
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Available from NRC/GPO Sales Program Superintemient of Documents
- Govarnment Printing Office 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 4r m
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NUREG-0485 Vol. 3, No.14 December 31,1981 i
SYSTEMATIC EVALUATION PROGRAM STATUS
SUMMARY
REPORT Prepared for: OFFICE OF NUCLEAR REACTOR REGULATION Prepared By: OFFICE OF MANAGEMENT AND PROGRAM ANALYSIS UNITED STATES NUCLEAR REGULATORY COMMISSION T
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tor Regulation
TABLE OF CONTENTS SECTION I SECTION 11 SECTION 111 i
SEP TOPIC LIST 1-2 to 1-3 BIG ROCK POINT 2-2 to 2-5 PALISADES 3-2 to 3-3 DRESDEN 1 2-6 GINNA 3-4 to 3-6 DESIGN BASIS EVENT 1-4 DRESDEN 2 2-7 to 2-10 DRESDEN 2 3-7 to 3-10 GROUP DESCRIPTION GINNA 2-11 to 2-14 OYSTER CREEK 311 to 313 i
DEFINITIONS OF STATUS 1-5 HADDAM NECK 2-15 to 2-18 MILLSTONE 1 3-14 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 PROGRESS TOWARD 17 YANKEE ROWE 3-30 to 3-33 PALISADES 2-31 to 2-34 COMPLETION (Graph)
SAN ONOFRE 2-35 to 2-38 LACROSSE 3-34 to 3-37 INTEGRATED PLANT l'8 SAFETY ASSESSMENT SCHEDULE SEP TOPIC STATUb BY 1-9 REVIEW DIVISION (Summary Table)
SEP TOPIC STATUS BY 1-10 to 1-11 REVIEW DIVISION (Graphs)
SEP topic SUBMITTALS 1-12 thru 113
\\,
BY LICENSEES (Graphs)
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i SYSTEMATIC EVALUATION PROGRAM TORIC LIST
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- {
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TWIC #
f i f t t'
- s
!w.2 Westtivity Contrul Systea6 Including f p.-tional
!!.I A. [stluston Ases Anthority eM Control Ill a A. Tornado t e ss t les Design and Protection Against 5tp3 e f at ti,res e
1 O Popstation D istrtbut tee
.!V-3 BmR Jet Punos Operating Indications
(. P ot ent ia l M aa seos or C hangrs i n P ct ant i a l g*,'"
"','I'5 y-i Cono1lance with Codes and Standards (10 CIR Mazards Owe to tranwortat 6oa. I ns t it ut iona l Industrial. and MtInary I act fit ses 111 4 C. 'inNen)Hy Generate.s Misst tes 50.55a )
!!-?
A. Severe weatha Phenwena I-2 Appiltet'le Code Cases
- 8. Onstte Metecrological Measurearnts Program V.3 Overt *ressurtaatton Protection C, 8W%hern Iransport and Dif f aston Charac-7 Piptsg as* Saf e End levegrats
^
W4 3
teristics f or A 4toent Apalysis D. Site ProatsitiMisults (Includirg '4 t rcraf t)
V-5 pactor Coclant Presburg Soundary (RCPS)
A. Ef fec'.s of P tpe Bred on $t rurt*vres. 5.ystc.
tescage. Detection
' D.
ant laht ? tty of pe'eorotoqual Data in the ggpe2 Contral Room and Cogone it s l as t se Cortalwnt V-6 peo Vessel Integrity
~
II 3 A. Hydrologic Description
- g. pipe great Outstde Containne at V-7 fesctor CWM Pump Overspeed B. f f ooding Potent tal and Protect son Require.
V-8*
5 team Generator (5G) Integrity i
ment s V-9 Reactor Coee flotation Cooling System (Coat) 111 7 A. Intervice ' mpectior.' including Prestressed,
I.
Capantltty of Operating Plant to Cope Concrete Coe.tatocents with Etther Grouted V.14 A. RHR Heat E schenger fuhe Fatlures w9th Design Bests Ilooding Condit tons or Ungrouted f endons C. Saf ety related Water Supply (Ultina'e Heat
- 8. Design Codes, Design Criteria. Load
CombtNt tons. and fleactor Cavity Design V-11 A. Requirements for Isolation of High and Low Crit ei ta
!!.4 Wology annt Setsmology Pressure Systems C. Cels.atnat ton of Prestressed Concrete Con-A. Tectouc Provtae tatace nt 5tructures V-12 A. Water Purity of Sotilng Water Reactor P, Prostet ty of Capable f ectonic 5tructures D. Contatnnent 5tructural Integrity fests in Plant Vict ntty Primsry Coolant 111 8 A. toose Parts Monitortng and Core Barrel 01)e Water Hammu C. Historital $etsmicity withre /U0 Males of fibration Monttoring Plant B. Control Rod Drive Mechantsm Integrity VI.)
Organic Materials and Post Accident t hemistry D. Stability of Slus C. Irradiation Damage. Use of Sensttired Stataless Steel and Iattwe tieststance V I-2 A. P ressure-Suppresuon Type 6.st Containments
[. Dam integrity
- $. Subcogartment Analysts
, D. Core Supports and F uel lategrtty I. Settleent of f cundet tons and Suried C. Ice Condenser Contalnment Ill-9,
Support Integrity L quipme nt D. Mass and Energy Release f or Post Ible Pipe ll1-10 A. Therms t-Overload Prot ect tan f or Motors of Break Inside Containent fli-1 Classit uation of 5tructures. Cuwonents and Motor-operat ed Valves Systeens (',etsmic and gue16ty )
1 B. Pump Flywheel Integrity VI.3 Containarnt Pressure and 'teet Reseval J
111-2 Wind aad f ornado Loadings Capability III.3 A. [f f ects of Mitt Water Level on Structures tion Pugs and Discharge Valves V [.4 Contelnpent Isolation System
!!!-11' Cogonent integrity VI-5*
Coatiustible Gas Control l
B. Structural and other Consequentes (e.g.
l V I-6 Contetnaent Leak festing f ioeding of Saf etydeleted I quipment in e
Basearnts) of f eelvre of Umscrdrain Systens Il l* 12 L evt ronnevital Qualtf tcation of Saf ety Pelated i ou tpment C. Inservice Inspection of Wat er Cont rol 5truc.
IV-l A. Operatica with less Than All Loops In-service tures i
1 2'
l SYSTEMATIC EVALUATION PROGRAM TOPIC LIST TOPIC 3 T13(,
TUP!C f fift!
Tapgc,
ign[
V I 1. A
- 1. cCC5 Re-evaluat ion t o Aucunt f or increased y g g.g Instruments f or Monitoring P adiation and Process IV-5 Loss of Normal Freewater flow Vessel head leqerat u '
Variables During Accidents l
IV-6 Feertsater System Ptpe Breaks lastde and Oestside r
Containment (PWR)
- 2. Upper P lence in ject '"n Vll-6 Frequency Decay L [CC5 Actuat ton Lystem V!l-?
Acceptability of Swing ilus Desi9n on BW#-4 IV-1 9eattor Coolant Pug Rotor Se12ure and Plants Reactor Coolant Pug Shaf t Break
- 4. Core Stray hoirle I f f ectiveness Vill-1 A. Potential Equipment f ailures Associated with IV-8 Control Rod Mtsoperation (System Malfunction VI-I.B E 5F Sw it chove r f rom i n)+ c t ion t o Recirculat ion a Degraded Grid Volta Je or Operator Error) wMe ( Autonet ic [ CL5 Wrali gnent) n s tte E mergency Pruer Systm - Diesel IV-9 Startup or an inactive toop or pecirculation Will-2 n
Generat or Loop at an Incorrect Tegerature, and Flow V I - 7.C f.CC5 Single F at lure C r it erion and Require.
Controller Malfunction Causing an Increase in meat s f or l ock ing Out PNer t o Valves i nc ludi ng i ndependenc e of I nt erloce s on V il l-3 A. Station Battery Capacity Test Requirements y d Core F lc= Rate IV-10 Cheetcal and volume Control System Malfunction
- 8. DC Power System Bus Voltage Monitoring and that Results in a Decrease in the Boron Concen-Mnu nCi at hn tration in the Reactor Coolant (Pd)
- 1. Appendia I - ( lectrical InstrustPnt at ion and Co<it rol (llc) Re-reviews V ill-4
[lectrical Penetrations of Reactor Contatnnent IV41 IW pt LWW W UpmW of a Fwl
- 2. f at ture Mode Analysis - ICC5 Assemely in an Isoroper Posttion II-I F uel 5torage
- 3. T he I f f ec t of Fue t oop isolat ion Valve IV-12 Spectrum of Rod Ejection Accidents (Pist)
Clowre During a t w A on (CCS Perf ormance II-2 Overhead Handling Systems - Cr.nes VI-7 D Long Term Cooling - Pan t ve f ailures (e.g*
- IV-13 5pectrum of Rod Drop Accidents (88)
F looding of Redundant Corronents) 13-3 Station Service and Cooling Water Systems IV-14 Inadvertent Operation of ECC5 and ChestCal II-4 Boron Addition System gg g
g V I-7.f ICC5 Su=p Des t gn and Test f or Rectrculation Mode t f f ect iveness Increases Reactor Coolant inventory ent ila on tem Accu ulator isolation Velves P(=cr and Control IV-15 Inadverteitt Opening of a Phst Pressurtrer Safety.
V I-i.f n
11-6 f tre Protectio's Reitef valve or a BA Safety /Reitef Valve
System Design
I Aust 11ery f eetsvater System IV-16 RadiologtCal Coesquences of Failure of Small Vl-8 Coctrol Room Habitability Lines carrying Prtmary Coolant Outside Contato.
VI-9 Main Steam Line isolat son Seal System - Bw 11-1 Appendis I ment v !- 10
- 1. Testing of Peactor Trip System and E nviceered gl.2 Padiological (tf fluent and Pro < ess) monit oring gy.ly Steam Generator Saf ety f eatures including Response Inne-sy st em Tube Failure (Pd) j festIng 3111-1 C onduct of Operations IV-18 Radiological Consequences of Main Steam B. 5 hared [ ngineered Saf ety F eatures. On-5.te Line Fatlure Outside Containment (SWR)
Larrgency Prmer, and Scroice Systems f or Illl-2 Saf e.pards/ Industrial Security ultiple Unit f acilities IV-19 Loss-of-Coolant Accidents Resulting f rom m
IV-l Decrease in f eerksater ; erg erature, increase in Spectrum of Postulated Piping Breaks letthin Vil-1 A. Isolation of Reactor Pr.e(t ton System f rom t eerheater f Inw, increase in 5 team F low and the Reactor Coolant Pressure Suundary Non-5af ety Systems, including Quallt ications I na dvert ent Opening of a 5 team benerator Relief of isolat ion Devices or Sa f et y V al ve IV*20 Radiological Consequences of Fuel Dawging Accidents (Instde and Outside Containment)
- 8. Trip Uncertainty and Setpoint Analysts Review IV-2
%ectrum of Steae System Pipiny I allures inside "I
of Operating Data Base and Outside of Cont ainwnt (P=W) vil-2
[ngineered Safety Feat res (15F) System Control gy 3 t ogg og (,ternal load Turbine Trip, loss of lo DC and Design Condenser Vacuum. Closure of Main Steae 15014-gy.73 Multiple Tube f ailures in Steam Generators t ion Valve (ftwa j, and St eam Pressure Repletor Vll-3 Systems Required f or int e Shutdow's f ailure (Closed) gy 74' Loss of All A-C Power IV1 Technical Spectf tcations l
I ~
8 vli-4 I f f ect s of F ailure in Non-5af et y Relat ed W stems on Selected i nge nrered Saf et y f eatures l
IVil Operational QA Program f
G. Lainas to all SEP Lwcensees.
- Topic deleted from SEP program due to duplication by Three Mile island (TMI) NRC Action Plan, Unresolved Safety issue or other SEP Topic per May 7,1981 fetter rom 1-3 l
DESIGN BASIS EVENT REVIEWS I
THIS SECTION DEFINES DESIGN BASIS EVENT (DBE) REVIEWS FOR THE ELEVEN SEP FACILITIES l
Bea D6E TOPIC L157 Boo 4 P%e DPQOP]CJ15T a.e ae t a e Trees teet Growfs Accident aad Treasteet Grown D6E TCPic-flTL E De_t _70s IC T!TLt-Grows !
IV 1 Decrease in feed =ater temperature flom Gec4 I s e-1 Decrease ta feedmater t anpera to re
{BaL.
I V-1 Increase in feeonater flow s t rgE II-3 A Hydrologic description
('w L av-l Increase in fee & ster flow E U-1 Imrease in steen f!>
11 - 3. B Flooding potential and protection 8 t-1 increase in steer flow ad-9 Start-up of inac tive loop and flom requirements (capabiltty of operating 34-1 Inadvertert opening of steam controller malfu ction plant to cope ette des 6gn bests flooding n
gere ator relief / safety waive au-3 InaJvertent Closure of main stes' condition) as-9 Start c of inac tive loos isolet'on valve
! !.1. C Safety related matee supply (vitimate Id 13 Syster ealf.nction causing Nat sint)
Groud!
g r-3 toss of esternal load l
Grg J I so-3 Loss of enternal load s..3 Tu bine trip SE ISp;C av 3 Loss of condeeser vacus I I-4. A Tectontc province r
rv 3 1,rg ene t rip 11-4.8 Pro 1mity of ceaable tectonic structures An 3 Loss of coedenser vacuum Eb-3 Steam pressu e regulator f at1w e near plant r
r tv 3 Steam presse e regulator f a ilure 3W-5 Loss of feedwater flom 11 -4 C Historical selsatCity within 200 miles r
I W-5 Lou of feedmater flow of plant 3 h -6 feedwater system pipe bresh Gr.owLJJJ X t-18 Radiological Consequences of a 11-4 0 5tatt11ty of slopes Main Steam Line f a11w e Outside r
Gr % JJI Ie ?
S teer line treak ins tde cortalvert Conta t anent pl%Lt GLERATIOh 11!-4 e Tornado missiles I v-2 Stear line t' rest outside contatrewnt A33 pecttCTION- - ' ' ~ Ill-a e Tu bine missiles r
Grydy Ed 4 Loss of AC peser to station
~ ' ' '
))l-4 (
internally generated missiles
.rowp_1 W Id-4 Loss of AC poner to s tat toe aus 111 art es
[ t [ -4.D site prontaity s 'ssiles (including w
awa ll'ac t es aircraf t )
q l l g -2 W6nd and tornado loadin9 GroutV a d-7 Loss of forced coolant flow Gro-L W BW 7 loss of forced coolart flo.
In - 7 Prwary pu s rotor seizure m
Iv 7 Peirery purc rotor setrare r e-7 Primary purip shaf t breat so-7 Prwary pump snaf t brea6 Groug_yi s v.8 uncontrolled rod assertly atthdrawal GfM_0 se-8 cmortrolled rod asserely.it*-
at power dvs.a1 at power In-E Unccetrolled rod asse=tly withdrawal 36-8 uacontrolled rod assembly mits-low po.ec start-up drenal law po=ce start-up R e-8 Control rod sisoperation su-8 Coatrol rod sisoperation I W - 13 Spectre of rod drop accidents E.-17 Spec tre of rod ejec tion accideets GrpyL WJ:
a v-li Spectr m of loss'of coolaat acctacris u
Group v!!!
Gro*p V !!-
s v-?9 Radtological Consecuences cf Fuel s v 2C Radiological Consewemes of f uel Damaging Accidents (f aside and Damaging Accidents (inside and outsise toetrinment) outside containsnert)
Group _IJ n o-15 Inadvertent ocentag of Swa s af ety /
Wi 33 3 *- 1; Inadvertent opentag of M relief valve presse iter ret tef valve r
Gros u a u-14 Inadvertent operation of ECCS Growd Iv 14 leadvertent operatton of ECCS or CvC5 malfumtion that causes an Growgl s v-11 Inadvertent loading and operation of
- mrease in coolant inventory a f uel anesely in an improper Grpsg El hut aesitcable to P>as GrSop 3 j hot applicatie to 8=Rs GrnJ!j s o l' 5 tea" Geaerator 'obe f ailure
~~
1-4
STATUS DEFINITIONS G - Generic 4a-Draf t SE Received From Review Branch These topics are being evaluated as part of on-going NRC generic review effort. The ongoing This status is used for internal NRC tracking of generic review and the SEP topic review will be topic review progress. The status indicates that closely integrated to improve the effectiveness a draft topic safety evaluation is under mange.
and efficiency of these efforts and to mi:.imize ment review.
any impact on licensees. The status and conclu-sions of generic SEP topics will be incorporated in the final safety assessment for each plant.
4b - SAR Reaived from Limnsee Licensee has submitted a Safety Analysis Report X - Deleted (SAR)in accordance with SEP redirection. (See Eisenhut letter to SEP owners of January 14,1981)
These topics have been verified as not applicable The SAR is under review and a Final NRC safety to the design of a specific plant or ar being evaluation (status 7) is being prepared. Draf t SE i
duplicated by the N RC TMI Action Plan, will not be issued for topics with licensee SA R submittal.
I Unresolved Safety issue or another SEP Topic per the May 7,1981 letter from G. Lainas to all SEP licensees.
5 - Draf t SE Sent to Utility j
0 - Topic Not Started A draft topic safety evaluation has been formally transmitted to the licensee for their review and This status indicates that the review of the topic certification of the accuracy of the described has not started.
facility. Licensees may comment upon NRC conclusions or propose alternatives to NRC posi.
tion s.
1 - Questions Received From Review Branch 6 - SE Response Received This status is used for internal NRC tracking by NRC of topic review progress. The status indicates j
that all information necessary to perform a The draft SE has been reviewed And licensee topic evaluation is not available and that ques-comments if any have been for@h transmitted l
tions have been developed and sent to the SEP to the NRC.
branch.
7 - Topic Complete 2 - Questions Sent to Utility The NRC topic evaluation has been completed and a final safety evaluation issued. A topic is completed The questions developed in the previous status in several ways: (1) The licensee has responded have been formally transmitted to the licensee that the NRC draft safety evaluation (i.e. status 5) as a request for additional information.
is correct, or (2) the licensees comments on the NRC draf t safety evaluation (i.e. status 6) have been re-3 - Question Response viewed and if appropriate incorporated into the Received by NRC final safety evaluation, or (3) the licensee has not responded in the time requested, thus concurring The licensee has formally responded to the informa, that the draft safety evaluation is correct.
tion request issued by N RC regarding the topic.
15
SEP TOPlc STATUS
SUMMARY
REPORT *
{
\\
\\
NUMBER OF QUESTIONS QUESTION DRAFT SE SAR SE I
N TOPICS TOPIC RECEIVED QUESTIONS
RESPONSE
RECEIVED RECEIVED DRAFT SE RESPONSF TOPIC
\\
GENERIC DELETED NOT FROM SENT TO RECEI'ED FROM FROM SENT TO RECEIVED COMPLETE
\\
(G)
(X)
STARTED REVIEW UTILITY BY NRC REVIEW LICENSEE UTILITY BY NRC (7)
PLANT NAME N
(0)
BRANCH (2)
(3)
BRANCH (4b)
(5)
(6)
N (1)
(4a)
\\
PALISADES 2
47 0
0 0
1 1
1 8
11 66 GINNA 1
45 0
0 0
2 2
5 8
16 58 DRESDEN 2 5
50 3
0 1
9 1
to 7
5 46 OYSTER CREEK 5
54 2
0 5
2 5
20 5
6 33 MILLSTONE 1 7
51 0
0 0
7 3
15 7
1 46 SAN ONOFRE 4
48 1
2 2
11 2
13 14 1
39 BIG ROCK POIrrt 4
53 9
0 1
17 2
11 3
2 35 HADDAM NECK 7
47 5
0 0
11 1
31 3
6 26 YANKEE ROWE 4
48 10 2
6 13 1
0 18 3
5 28 LACROSSE 4
54 20 1
9 6
3 12 3
0 25 DRESDEN 1 TOTALS THIS MONTH 43 497 50 5
24 79 20 136 61 53 402 TOTALS LAST MONTH 51 496 65 6
30 92 25 138 45 59 363 w NOTE: Totals do not include Drosdon 1,
sco pago 2-6.
Also included is May 7, 1981 deletion letter to all SEP licensees.
l l
see footnote pago 1-3.
l 1-6 l
SYSTEMATIC EVALUATION PROGRAM GOAL PHASE li'/
-1/ Not including Dresden 1 Progress Toward Complet. ion ac7un 100 %
100 7 31-82
/p 90
- p
,s f
/,,
1 m nth 3
/
l 80 75 %
70%
76%
70 67 72%
61'Y
'/
F-
/
.Note: Prior to November 30,1981 the 2
60 c0%
weighted percent did not include b
' 81 genene topics in the progress (r
p p
toward completion.
uJ o
50 j'/
54%
So*
s I
47%
9
,' f 44%
/,
42%
u' 40 5
j/*
40 %
/
36%
30 30% lestimatedf The plant topic overall completion status (percent complete) is calculated Status Weighting Factor
~
based upon the number of topic reviews to b*J performed (not including X
Not included deleted topics) and a weighted average of current topic review status.
G-20 The calculation is performed using the following formula:
2a 4a,4b 80 %
Percent Complete = Sum of Topics in Status x Weighting Factor of Status 5.6 90 %
7 100 %
10 S,um of Topics g
0 10 11 12 1
2 3
4 5
6 7
8 9
10 11 12 1
2 3
4 5
6 7
8 9
4 FY-81 FY-82 1-7
.i
INTEGRATED PLANT SAFETY ASSESSMENT REPORT (IPSAR) SCHEDULE To Be Provided In The Future (1-8)
SEP TOPIC STATUS by REVIEW DIVISION
SUMMARY
TABLE PLANT PALISADES GINNA DRESDEN OYSTER MILLSTONE SAN BIG HADDAM YANKEE LACROSSE TOTAL 2
CREEK 1
ONOFRE ROCK HECK ROWE POINT (IArM) J/
Michaels Wang Cwalina Fell Persinko McKenna Scholl Brown Boyle Michaels NG. OF TOPICS 137 137 137 137 137 137 137 137 137 137 1370 DELETED 2/
47 45 50 54 51 48 53 47 48 54 497 APPLICABLE 90 92 87 83 86 89 84 90 89 83 873 57
/
39
/
31
/
31
/
27
/
31
/
27
/
25
/
25
/
21
/
314 /
DL
/
/
/
/
/
/
/
/
/
/
/
/ 57
/ 39
/ 36
/ 35
/ 37
/ 40
/ 38
/ 38
/ 38
/ 35
/ 393 TECHNICAL
/
/
/
/
/
/
/
/
/
/
/
16
/
16
/
7
/
4
/
10
/
6
/
3
/
4
/
6
/
3
/
75
/
REVIEW DOE
/
/
/
/
/
/
/
/'
/
/
/
l
/ 18
/ 21
/ 22
/ 20
/ 21
/ 18
/ 17
/ 21
/ 21
/ 21
/ 200 l
ASSIGNMENT 1/
/
/
/
/
/
/
/
/
/
/
/
15
/
31
/
18
/
19
/
18
/
16
/
11
/
6
/
4
/
5
/
143 /
DSI
/
/
/
/
/
/
/
/
/
/
/
i
/ 15
/ 32
/ 29
/ 28
/ 28
/ 31
/ 29
/ 31
/ 30
/ 27
/ 280 l
/
/
/
/
/
/
/
/
/
/
/
88
/
86
/
56
/
54
/
55
/
53
/
41
/
35
/
35
/
29
/
532
/
COMPLETE
/
/
/
/
/
/
/
/
/
/
/
/ 90
/ 92
/ 87
/ 83
/ 86
/ 89
/ 84
/ 90
/ 89
/ 83
/ 873
/
/
/
/
/
/
/
/
/
/
/
TARGET DATE -
l ALL TCPICS JAN 82 JAN 82 OCT 82 MAY 82 JUN 82 DEC 82 JUL 82 OCT 82 AUG 82 NOV 82 TECHNICAL 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.
2/ These schedules and assignments are consistent with NRR FY 1982-1984 Operating Plan.
I/_/
= No. Completed / Ho. Assigned 1-9 STATUS AS OF DECEMBER 31, 1981
PROGRESS OF TOPIC REVIEWS CIVISI317 LICDEIM; TIFICS S
TAfET e
,,,,a
= * * * * *
- m--
- # p # ****
ACTUAL
- 2 ms --
9 <8 g
2 2, __
15 --
1E --
i i
i g
M JLA.
AUG SEP OCT BOf IEC JM FG W
APR MY M Jut /Dec leffH Tarpt 10 14 20 17 7
3 l 4 3
16 R MONTH 1
10 3
4 7
g Actual Tarpt 309 323 343 360 367 370 374 377 393 CUMULATIVE 281 291 294 298 305 314 PROGRESS OF TOPIC REVIEWS DIVIS!38 7 DCIIEDIIC T: Pits 258 TMET
~ ~ ~
3
- #.m* #,
/,
- =*
==
ACTUAL 15 --
7
/
f
/
1E --
,/
= = "
g M
JLL AUG SEP OCT IOf DEE JM FG W
APR IIAY M
Jut /Dec lorIM Tarpt 2
2 40 36 21 6
2 7
11 PER MONTH 4
0 2
0 0
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75 77 117 153 174 180 182 189 200 CUMULATIVE 70 70 72 72 72 75 Actual
PROGRESS OF TOPIC REVIEWS DIVISION & SYSTDIS INTEGRATI3d TOPICS 358 TutGET ass --
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AUG SEP OCT MN KC JAN FEB MAR APR MAY JLN Jul/Dec Target 28 35 35 30 15 15 3
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PER MONTH Actual 11 3
10 14 27 28 Target 131 166
,201 1231 246 261 264 1274 280 CUMULATIVE Actual 61 64 74 88 115 143 PROGRESS OF TOPIC REVIEWS 5
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'J3 PER MONTH Actual 16 13 16 20 34 40 Target 515 566 661 I744 787 811 820
'840 473 CUMULATIVE Actual 482 425 441 458 492 532
LICENSEE TOPIC SUBMITTALS O!Y! Sites y Lla3stes Sal!TTALS 48 TAAEET 35 --
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52 53 58 59 59 59 59 59 CUMULATIVE Actual 1
9 10 15 22 37
LICENSEE TOPlc SUBMITTALS O!VIS10M & SYSTDS INTE13 TAT 10M SBIITTALS 15 TAMET p
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10 3
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15 61 68 78 88 91 94 94 94 94 94 94 Actual 1
11 14 45 48 50
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LICENSEE TOPIC SUBMITTALS TCTu. mxCT EMIITTALS M
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31 85 28 20 27 4
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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 NRC 09/02/80 REGION / LOCATION: 4 MILES NORTH EAST OF CHARLEVOI, MICH.
II-1 B.
DL/SEPB 7
CPCo to NRC 09/02/80 DOCKET NO.
05000155 II-I C.
DL/SEPB 7
NRC to CPCo 05/13/81 POWER CAPACITY: 0240(THERMAL) 067(ELECTRICAL)
II-2 A.
DSI/AEB 7
HRC to CPCo 08/03/81 OL NUMBER: DPR-6 II-2 B.
X HRC to CPCo 05/07/81 H.S.S.S.
GE.
II-2 C.
DSI/AEB 3
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 3
CPCo to NRC 08/21/81 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD II-3 B.
DE/HGEB 3
CPCo to NRC 08/21/81 OPERATING REACTORS PROJECT MANAGER: R.
EMCH II-3 B.
1.
DE/HGEB 3
Site Visit 07/16/79 INTEGRATED ASSESSMENT PROJECT MANAGER: R. SCHOLL/dg/
.II-3 C.
DE/HGEB 3
Site Visit 07/16/79 II-4 DE/GSB 7
NRC to CPCo 06/08/81 KEY FOR STATUS CODES II-4 A.
DE/GSB 7
NRC to CPCo 06/08/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.
DE/GSB 3
FROM REVIEW BRANCH X - DELETED II-4 C.
DE/GSB 7
NRC to CPCo 06/08/81 4b-SAR RECEIVED FROM 0 - TOPIC NOT LICENSEE II-4 D.
DE/HGEB 4b CPCo to NRC 10/05/81 STARTED 5 - DRAFT SE SENT II-4 E.
X NRC to CPCo 11/16/79 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.
DE/HGEB 4b CPCo to NRC 10/19/81 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC III-1 DL/SEPB 2(Sys)
HRC to CPCo 05/00/80 TO UTILITY DL/SEPB 7(ELEC) HRC to CPCo 08/19/81 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 3
CPCo to NRC 07/09/81 RECEIVED BY NRC (2-2)
BIG ROCK POINT TOPIC HO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STAIUS ret 1 ARKS DIV/BR DIV/BR III-3 A.
DE/SEB 3
CPCo to NRC 08/09/80 111-10 B.
X NRC to CPCo 11/16/79 III-3 B.
X NRC to CPCo 12/26/80 III-10 C.
X NRC to CPCo 11/16/79 III-3 C.
DE/AGEB Ab CPCo to NRC 12/21/81 III-11 X
NRC to CPCO 05/07/81 III-4 A.
DSI/ASB 0
III-12 X
HRC to CPCo 05/07/81 III-4 B.
DE/MTC3 0
IV-1 A.
DL/SEPB 7
HRC 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
HRC to CPCo 05/04/81 III-5 A.
DL/SEPB 3
V-1 DE/MTEB X
HRC 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 3
CPCo to HRC 07/27/81 V-3 X
HRC to CPCo 05/07/81 III-7 A.
X NRC to CPCo 05/07/81 V-4 X
HRC to CPCo 05/07/81 III-7 B.
DL/SEPB 3
CPCo to HRC 07/09/81 V-5 DL/SEPB 7
HRC to CPCo 09/30/81 III-7 C.
X HRC to CPCo 11/16/79 V-6 DL/SEPB 7
HRC to CPCo 03/05/80 III-7 D.
DE/SEB 3
CPCo to NRC 08/09/79 V-7 X
NRC tc CPCo 11/16/79 III-8 A.
DSI G
HRC 'o 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
HRC to CPCo 11/16/79 III-8 C.
DL/SEPB 7
NRC to CPCo 02/05/80 V-10 A.
DL/SEPB 7
NRC to CPCo 10/09/79 III-8 D.
X HRC to CPCo 05/07/81 V-10 B.
DL/SEPB 7
NRC to CPCo 05/13/88 III-9 X
H2C to CPCo 05/07/81 V-11 A.
DL/SEPB 6(Elec) CPCo to HPC 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) HRC to CPCo 08/19/81 (2-3)
BIG ROCK POINT TOPIC HD.
REVIEW STATUS REMARKS TDPIC HO.
REVIEW STATUS REMARKS DIV/BR DIV/DR v-12 A.
DL/SEPB 7
NRC to CPCo 10/09/79 VI-7 D.
CL/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 NRC to CPCo 05/07/81 VI-8 X
HRC to CPCo 05/07/81 VI-2 B.
X HRC to CPCo 05/07/81 VI-9 X
HRC to CPCo 11/16/79 VI-2 C.
X HRC to CPCo 11/16/79 VI-10 A.
DL/SEPB 0
VI-2 D.
DSI/CSB 3
CPCo to NRC 04/02/80 VI-10 B.
X HRC to CPCo 11/16/79 VI-5 DSI/CSB 3
CPCo to NRC 04/02/80 VII-l A.
DL/SEPB 0
VI-4 DSI/CSB 0(Sys)
VII-1 B.
DL/SCPB 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
NRC to CPCo 05/07/81 VII-3 DL/SEPB 7(Sys)
HRC to CPCo 05/13/81 VI-6 DSI/CSB G
NRC to CPCo 05/07/81 DL/SEPB 7(Elec) NRC to CPCo 08/19/81 VI-7 A.
1.
X NRC to CPCo 11/16/79 VII-4 X
HRC to CPCo 05/07/81 VI-7 A.
2.
X NRC to CPCo 05/07/81 VII-5 X
HRC to CPCo 05/07/81 VI-7 A.
3 DL/SEPB 0
VII-6 DL/SEPB 7
NRC to CPCo 09/21/81
{
VI-7 A.
4.
CSI/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
HRC to CPCo 05/07/81 0(sys)
VIII-2 DL/SEPB 7
NRC to CPCo 08/28/81 VI-7 C.
DL/SEPB 7
HRC to CPCo 08/05/81 VIII-3 A.
DL/SEPB 7
CPCo to HRC 04/22/81 VI-7 C.
1.
DL/SEPB 7
HRC to CPCo 08/05/31 VIII-3 B.
DL/SEPD 7
HRC to CPCo 08/18/81 VI-7 C.
2.
DL/SEPB 7
HRC to CPCo 08/05/81 VIII-4 DL/SEPB 3
CPCo to NRC 11/16/81 VI-7 C.
3.
X HRC to CPCo 11/16/79 (2-4)
BIG ROCK POINT TOPIC NO.
REVIEW STATUS REMARKS TOPIC HO.
REVIEW STATUS REMARKS DIV/BR DIV/3R IX-1 DSI/ASB 0
XV-10 X
NRC to CI'Co 11/ 16/1 I IX-2 X
HRC to CPCo 05/07/81 XV-11 DSI/CPB 7
HRC to CPCo 1?/02/81 IX-3 DL/SEPB Gb CPCo to HRC 12/10/81 XV-12 X
tlRC to CFCo 11/16/79 IX-4 X
HRC to CPCo 11/16/79 XV-13 DSI/CPB 7(Sys) f4RC to CPCo 12/02/31 DsI/AEB 4a(Dosos)
IX-5 DL/SEPB 0
XV-14 DSI/RSB 7
HRC to CPCo G8/18/81 IX-6 DE G
HRC to CPCo 05/07/81 XV-15 DSI/RSB 7
NRC to CPCo 08/18/81 X
X tiRC to CPCo 05/07/81 XV-16 DSI/AEB 7
r4RC to CPCo 12/23/01 XI-1 DSI/ETSB X
HRC to CPCo 12/04/81 XV-17 X
HRC to CPCo 11/16/79 XI-2 DSI/ETSB X
NRC to CPCo 12/04/81 XV-18 DSI/AEB 4b HRC to CPCo 07/01/31 XIII-1 X
HRC to CPCo 05/07/81 XV-19 DSI/RS3 7(Sys)
HRC to CPCo 08/IS/81 XIII-2 DL/SSPB 7
HRC to CPCo 03/11/81 DSI/AEB 4b(Dosos)CPCo to tiRC 07/01/31 XV-1 DSI/RSB 4b CPCo to NRC 07/15/81 XV-20 DSI/AEB 4a CPCo to br,C 07/03/81 XV-2 X
NRC to CPCo 11/16/79 XV-21 X
t4RC to CPCo 05/07/81 XV-3 DSI/RSB 7
HRC to CPCo 10/16/81 XV-22 X
HRC 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 4b CPCo to HRC 07/15/81 XV-24 X
HRC to CPCo 05/07/81 XV-6 X
HRC to CPCo 11/16/79 XVI X
HRC to CPCo 11/05/00 XV-7 DSI/RSB 4b CPCo to tiRC 07/15/81 XVII DL 7
NRC to CPco 08/l7/78 XV-8 DSI/CPB 7
HRC to CPCo 12/31/81 XV-9 DSI/RSB Gb CPCo to HRC 07/15/81 (2-5)
DRESDEN1 FACILITY: DRESDEN 1 LICENSEE: COMM0HWEALTH EDISDN REGIDH/ LOCATION: 9 MILES EAST OF MORRIS, ILL.
DOCKET HO.
05000010 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'CONHOR By letter dated December 31, 1980 Commonwealth Edison indi-cated that Dresden 1 was underqcing an extensive modifica-tion and was not scheduled for restart until June, 1986.
Also, by letter dated April 4, 1981, in response to the NRC's January 14, 1981 letter on SEP redirection the licen-I 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: COMM0HWEALTH EDISON 11-1 A.
DE/SAB 7
hRC to CECO 10/06/31 REGION / LOCATION: 9 MILES EAST OF MORRIS. ILL.
II-1 B.
DE/SAB 7
HRC to Ceco 10/06/8?
DOCKET NO.*
05000237 II-1 C.
DE/SAB Gb CECO to HRC 12/08/81 POWER CAPACITY: 2527(THERMAL) 0794(ELECTRICAL)
II-2 A.
DSI/AEB 7
HRC to Ceco 04/24/81 OL NUMBER: DPR-19 II-2 B.
X HRC to Ceco 05/07/81 H.S.S.S.6 GE.
II-2 C.
DSI/AEB 7
HRC to CPCo 03/26/81 A/E FIRM: S&L.
II-2 D.
X HRC to Ceco 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W.
RUSSELL II-3 A.
DE/HGEB 3
Ceco to NRC 09/11/81 OPERATING REACTORS BRANCH CHIEF: D.
CRUTCHFIELD II-3 B.
DE/HGEB 3
CECO to NRC 09/11/81 OPERATING REACTORS PROJECT MANAGER: P.
O'CONHOR II-3 B.
1 DE/HGEB 3
CECO to NRC Site Visit 01/09/79
(
INTEGRATED ASSESSMENT PROJECT MANAGER: G. CWALINA II-3 C.
DE/HGEB 3
CFCo to HRC Site Visit 01/09/79 KEY FOR STATUS CODES II-4 DE/GSB 7
NRC to Ceco 07/09/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 A.
DE/GSB 7
HRC to Ceco 06/08/81 FROM REVIEW BRANCH X - DELETED II-4 B.
DE/GSB 5
HRC to Ceco 07/09/81 4b-SAR RECEIVED FROM 0 - TOPIC NOT LICENSEE II-4 C.
DE/GSB 7
HRC to Ceco 06/08/81 STARTED 5 - DRAFT SE SENT II-4 D.
DE/HGEB 4b CECO to NRC 12/03/81 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 E.
DE/HGEB 4b CECO to NRC 12/08/81 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC II-4 F.
DE/HGEB Gb CECO to NRC 12/08/81 TO UTILITY 7 - TOPIC COMPLETE III-1 DL/SEPB 3(sys)
NRC to Ceco 06/26/81 3 - QUESTION RESPONSE DL/SEPB 7(Elec) Part of VII-3 07/07/81 RECEIVED BY NRC III-2 DL/SEPB 3
(2-7)
DRESDEN 2
TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/CR DIV/BR III-3 A.
DE/SEB Gb 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
NRC to Ceco 05/22/79 III-3 C.
DE/HGEB 0
III-11 X
NRC to Ceco 05/07/81 III-4 A.
DSI/ASB 4b CECO to NRC 12/08/81 III-12 X
NRC to Ceco 05/07/81 III-4 B.
DE/MTEB 3
Site Visit 06/01/81 IV-1 A.
DL/SEPB 7
NRC to CECO 10/26/81 III-4 C.
DSI/ASB C
IV-2 DSI/ICSB 7
CECO to NRC 12/04/81 III-4 D.
DE/SAB Gb CECO to NRC 12/08/81 IV-3 DE/MTEB 7
HRC to CECO 01/01/80 III-5 A.
DL/SEPB 2
NRC to Ceco 01/04/80 V-1 DE/MTEB X
NRC to Ceco 11/27/81 III-5 B.
DL/SEPB 6
CECO to NRC 03/21/80 V-2 X
NRC to Ceco 11/16/79 III-6 DL/SEPB 6
CECO to NRC 03/13/81 V-3 X
NRC to Ceco 05/07/81 III-7 A.
X NRC to CECO 05/07/81 V-4 X
HRC 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
NRC 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 X
NRC to CECO 11/16/79 III-8 C.
DL/SEPB 6
CECO to NRC 03/10/80 V-10 A.
DL/SEPB 7
NRC to Ceco 11/08/79 III-8 D.
X HRC to Ceco 05/07/81 V-10 B.
DL/SEPB 7
NRC to CCCo 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)
HRC to CECO 04/24/81 DL/SEPB 7(Elec) HRC to CECO 07/10/81 (2-8)
DRESDEN 2 TDPIC HO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS R Ell A R KS DIV/BR DIV/BR V-12 A.
DL/SEPB 7
NRC to CECO 04/16/81 VI-7 D.
DL/SEPB
/
HRC to CECO 08/11//8 V-13 X
HRC to Ceco 05/07/81 VI-7 E.
X HRC to CECO 05/07/81 VI-1 DE/CEB 3
Ceco to HRC 07/27/79 VI-7 F.
X NRC to CECO 11/16/79 VI-2 A.
X HRC to Ceco 05/07/81 VI-8 X
NRC to Ceco 05/07/81 VI-2 B.
X HRC to Ceco 05/07/81 VI-9 X
HRC to CECO 11/16/79 VI-2 C.
X NRC to Ceco 11/16/79 VI-10 A.
DL/SEPB 7
HRC to CECO 07/03/31 VI-2 D.
DSI/CSB 5
HRC to CECO 12/30/81 VI-10 B.
DL/SEPB 7(Sys)
HRC to CECO 06/20/81 DL/SEPB 7(Elec) Ceco to NRC 11/03/81 VI-5 DSI/CSB 5
HRC to CECO 12/28/81 VII-1 A.
DL/SEPB 7
HRC to Ceco 12/24/S1 VI-4 DSI/CSB 5(Sys)
HRC to CECO 12/18/81 DL/SEPB 5(Elec) HRC to CECO 12/15/81 VII-1 B.
DL/SEPB 7
NRC to CECO 08/17/78 VI-5 X
HRC to CECO 05/07/81 VII-2 DL/SEPB 7
Ceco to NRC 11/03/31
(
VI-6 DSI/CSB G
HRC to Ceco 05/07/81 VII-3 DL/SEPB 7(Sys)
HRC to Ceco 04/24/C1 DL/SEPB 7(Elec) HRC 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
HRC to CECO 05/07/81 VI-7 A.
3.
DL/SEPB 7
Ceco to NRC 11/03/81 VII-6 DL/SEPB 7
HRC to Ceco OC/26/81 VI-7 A.
4.
DSI/RSB G
NRC to Ceco 05/07/81 VII-7 X
HRC 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
HRC to Ceco 03/13/81 VIII-2 DL/SEPB 7
HRC to Ceco 06/26/81 VI-7 C.
1 DSI/PSB 6
Ceco to NRC 06/12/31 VIII-3 A.
DL/SEPB 7
HRC to CECO 07/07/31 VI-7 C. 2.
DL/SEPB 7
HRC to CECO 03/13/31 VIII-3 B.
DL/SEPB 7
HRC to C8'Co 06/26/81 VI-7 C.
3.
X HRC to CECO 11/16/79 VIII-4 DL/SEPB 7
HRC to CECO 11/30/81 (2-9)
DRESDEN 2 TOPIC NO.
REVIEW STATUS REMARKS TCPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 3
CECO to NRC 06/02/80 XV-10 X
t4RC to Ceco 11/16/19 IX-2 X
NRC to Ceco 05/07/81 XV-11 DSI/CPB Gb CECO to NRC 10/15/81 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 4b(Sys) Ceco to NRC 10/15/81 DSI/AED 7(Doses) NRC to CECO 12/28/81 IX-5 DL/SEPB 0
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 DSI/ETSB X
NRC to Ceco 12/04/81 XV-17 X
HRC to Ceco 11/16/79 XI-2 DSI/ETSB X
NRC to Ceco 12/04/81 XIII-1 X
HRC to CECO 05/07/81
' DSI/AEB 4a XV-18 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 4b(DOSES) CECO to NRC 10/15/81 XV-1 DSI/RSB 7
NRC to CECO 12/29/81 XV-20 DSI/AEB 7
NRC to CECO 11/20/81 XV-2 X
NRC to Ceco 11/16/79 XV-21 X
NRC to Ceco 05/07/81 XV-3 DSI/RSB 7
NRC to CECO 12/04/81 XV-22 X
NRC to Ceco 05/07/81 I
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 01/04/81 XVII DL 7
NRC to CECO 11/20/79 XV-8 RSI/CPB 4b CECO to NRC 10/15/41 XV-9 DSI/RSB 7
NRC to CECO 12/19/81 (2-10)
_ _ _ _ _ ________ _ _____ __._______ _ ____ ____ _ _ ~ _ _.
G NNA FACILITY: GINNA TOPIC HO.
REVIEW STATUS REMARKS DIV/BR LICENSEE: ROCHESTER GAS 8 ELECTRIC 11-1 A.
DE/SAB 7
NRC to RGE 07/17/81 REGION / LOCATION: 15 MILES NORTH EAST OF ROCHESTER, NY.
II-1 B.
DE/SAB 7
NRC to #GE 07/21/81 DOCKET NO.: 05000244 II-1 C.
DE/SAB 7
HRC to RGE 09/29/81 POWER CAPACITY: 1520(THERMAL) 0490(ELECTRICAL)
II-2 A.
DSI/AEB 6
REG to NRC 01/19/81 OL NUMBER: DPR-18 II-2 B.
X HRC to RGE 05/07/81 H.S.S.S.: WEST.
4 4
II-2 C.
DSI/AEB 7
HRC to RGE 09/24/81 A/E FIRM: GIL.
II-2 D.
X NRC to RGE 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL II-3 A.
DE/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 OPERATING REACTORS PROJECT MANAGER: J. Iyons II-3 B.
1 DE/HGEB 6
RGE to NRC 08/18/81 i
INTEGRATED ASSESSMENT PROJECT MANAGER: A. WANG 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 4
II-4 A.
DE/GSB 7
NRC to RGE 06/08/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.
DE/GSB 7
NRC to RGE 07/09/81 FROM REVIEW BRANCH j
4b-SAR RECEIVED FROM 0 - TOPIC HOT LICENSEE 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 - QUESTIONS RECEIVED TO UTILITY 1
FROM REVIEW BRANCH II-4 F.
DE/HGEB 4b RGE to NRC 06/30/81 i
6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC III-1 DL/SEPB 5(Sys)
NRC to RGE 12/30/81 TO UTILITY DL/SEPB 6(Elec) RGE to NRC 01/23/81 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 5
HRC to RGE 12/29/81 RECEIVED BY NRC M - DATA FOR NEX* MONTH j
(NOVEMBER) f 4
(2-11) 4
GINNA TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR III-5 A.
DE/SEB 6
RGE to NPC 08/18/81 111-10 B.
DL/SEPB 7
NRC to RGE 06/22/81 III-3 B.
X NRC to RGE 12/31/80 III-10 C.
X NRC to RGE 11/16/79 III-3 C.
DE/HGEB 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.
D E/!1T EB 5
NRC to RGE 12/18/81 IV-1 A.
DL/SEPB 7
NRC to RGE 05/29/79 III-4 C.
DSI/ASB 4b 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 C5/07/81 III-5 A.
DL/SEPB 6
RGE to NRC 10/01/81 V-1 DE/MTEB 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
NRC to RGE 05/07/81 III-7 B.
DL/SEPB 5
NRC to RGE 12-23-81 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
HRC to RGE 05/08/80 V-7 DSI/ASB 7
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 DL/SEPB 7(Elec) HRC to RGE 04/24/81 4
(2-12)
GINNA TOPIC NO.
REVIEW STATUS REMARKS TOPIC HO.
REVIEW STATUS R Ef1 ARKS DIV/BR DIV/BR
-V-12 A.
X HRC to RGE 11/16/79 VI-7 D.
DL/SEPS 7
f4RC to RGE 08/17/78-V 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/SEPD 7
HRC to RGE 06/24/81 VI-2 A.
X HRC 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 HRC to RGE 11/16/79 VI-3 DSI/CSB 5
NRC to RGE 11/03/81 VII-1 A.
DL/SEPB 7
flRC to RGE 07/30/81 VI-4 DSI/CSB 5(sys)
NRC to RGE 07/27/81 VII-1 B.
DL/SEPB 7
NRC to RGE 08/17/78 DL/SEPB 6(Elec) RGE to NRC 0?,'02/81 VII-2 DL/SEPB 7
NRC to RGE 12/24/01 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(Ele =)
HRC to RCE 06/24/01 VI-7 A.
1 DL/S*PB 7
HRC to RGE 02/20/81 VII-4 X
NRC to RCE 05/07/81 VI-7 A. 2.
DL/SEPB 7
NRC to RGE 08/17/78 VII-5 X
NRC to RGE 05/07/81
-VI-7 A. 3.
DL/SEPB 7
HRC to RGE 11/27/81 VII-6 DL/SEPB 7
NRC to RGE 06/24/81 VI-7 A. 4 X
NRC to RGE 05/07/81 VII-7 X
NRC to RGE 11/16/79 VI-7 B.
DSI/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) NRC 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 02e20/81 VIII-3 A.
DL/SEPB 7
HRC to RCE 07/31/81 VI-7 C.
1 DL/SEPB 7
NRC to RGE 11/27/81 VIII-3 B.
DL/SEPB 7
HRC to RGE 06/09/81 VI-7 C. 2.
DL/SEPB 7
HRC 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)
__m_
.m__
___.. _. ~
i i
GINNA i
TGPIC NO.
REVIEW STATUS REl1 ARKS TOPIC ND.
REVIEW STATUS REf1 ARKS DIV/DR DIV/BR IX-1 DSI/ASB 7
NRC to RGE 11/24/81 XV-80 DSI/RSB 7
NRC to RGE 09/04/81 IX-2 X
NRC to RGE 05/07/31 XV-11 X
NRC to RGE 10/01/80 IX-3 DL/SEPB 7
NRC to RGE 11/03/81 XV-12 DSI/CPB 7(Sys)
NRC to RGE 09/04/81 DSI/AEB 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
NRC 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 DSI/ETSB X
NRC to RGE 12/04/81 XV-17 DSI/RSB 7(Sys)
HRC to RGE 09/04/81 XI-2 DSI/ETSB 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-18 X
NRC to RGE 03/11/80 XIII-2 DL/SEPB 7
NRC to RGE 03/26/81 XV-19 DSI/RSB 7(Sys)
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)
NRC to RGE 09/04/81 DSI/AEB 6(Doses) RGE to NRC 11/04/81 XV-21 X
NRC to RGE 05/07/81 l
XV-3 DSI/RSB 7
NRC to RGE 09/04/81 XV-22 X
NRC to RGE 05/07/81 XV-4 DSI/RSB 7
NRC to RGE 09/04/81 XV-23 X
NRC to RGE 05/07/81 i
i XV-5 DSI/RSB 7
NRC to RGE 09/04/81 XV-24 X
NRC to RGE 05/07/81
]
XV-6 DSI/RSB 7
NRC to RGE 09/04/81 XVI X
NRC to RGE 11/05/80 XV-7 DSI/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 l
(2-14)
I
3 HADDAM NECK FACILITY: HADDAM HECK TOPIC HO.
REVIEW STATUS REMARr.S DIV/BR
, LICENSEE: CONNECTICUT YAHKEE ATOMIC POWER II-1 A.
DE/SAB 4b CrAPto to NRL c4/2//81 REGIn"/ LOCATION: 13 MILES EAST OF MERIDEH, CT.
II-1 B.
DE/SAB Gb CYAPCo to NRC 08/31/81 DOCKET NO: 05000213 II-1 C.
DL/SAB 4b CYAPCo to NRC 06/30/81 POWER CAPACITY: 1825(THERMAL) 0575(ELECTRICAL)
II-2 A.
DSI/AEB 7
CYAPCo to NRC 01/22/81 OL HUMBER: DPR-61 II-2 B.
X HRC to CYAPCo 05/07/81 H.S.S.S.
WEST.
II-2 C.
DSI/AEB 7
CYAPCo to NRC 02/16/79 A/E FIRM: SIW II-2 D.
X HRC to CYAPCo 05/07/51 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL II-3 A.
DE/HGEB 4b CYAPCo to NRC 12/14/81 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD II-3 B.
DE/HGEB 4b CYAPCo to NRC 12/14/8 1 OPERATING REACTORS PROJECT MANAGER: C.
TROPF II-3 B.
1.
DE/HGEB 4b CYAPCo to NRC 12/14/81 INTEGRATED ASSESSMENT PROJECT MANAGER: 5. BROWN II-3 C.
DE/HGEB 4b CYAPCo to NRC 12/14/81 II-4 DE/GSB 7
NRC to CYAPCo 06/08/81 KEY FOR STATUS CODES II-4 A.
DE/GSB 7
HRC to CYAPCo 06/08/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.
DE/GSB 3
HUREG/CR1582 08/04/80 FROM REVIEW BRANCH X - DELETED II-4 C.
DE/GSB 7
HRC to CYAPCo 06/03/81 4b-SAR RECEIVED FROM 0 - TOPIC NOT LICENSEE I7-4 D.
DE/HGEB 4b CYAPCo to NRC 08/51/81 STARTED 5 - DRAFT SE SENT II-4 E.
X HRC to CYAPCo 04/t6/79 I - QUESTI0HS RECEIVED
'TO UTILITY FROM REVIEW BRANCH II-4 F.
DE/HGEB 4b CYAPCo to NRC 12/18/81 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC III-1 DL/SEPB 2(Sys)
HRC to CYAPCo 11/20/81 TO UTILITY DL/SEPB 7(Elec) Part of VII-3 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB Ab CYAPCo to NRC 12/14/81 RECEIVED BY NRC (2-15)
l
~
J HADDAML NECK
' {(
s TGPIC NO.
REVIEW STATUS REMARKS TOPIC fl0.
REVIEW STATUS R Et1A RKS
]
DIV/BR
~
DIV/BP.
III-3 DE/SEB 4b CYAPC: to NkC 08/31/81
~III-10 B.
DL/SEPB 6
CYAPCo to NRC 12/09/80 NI 3 B.
DE/HGEB D
III-10 C.
X HRC to CYAPCo 04/16/79
{
s l
III-3 C.
DE/HGEB Gb CAAr'Co to NRC s08/31/81 II!-11 X
(WC to CYAPCo 05/07/8$
III-4 A.
05I/ASB~
4b CYt.PCo to NRC 08/31/81 III-12 X
NRC to CYA?Co 05/07/81 III-4 B.
DE MTEB
.G NRL to CYAPCo 05/07/81 IV-1 A.
DL/SEPB 7
CYAPCo to NRC 06/e5/79 l
III.4 C.
DSI/ A SB -
,4 IV-2 DSI/ICSB 7
HRC to CYAPCc 12/31/31 III-4 C.
DE/SAB
'b CYAPCo to NRC 06/25/81 IV-3 X
HRC to CYAPCS 35/07/81 III-5 A.
DL/SEPB 3
CYAPCo to NRC 02/07/80 V-1 D E/MT EB X
NRC to CYAFCo 11/27/61
)
t t
III-5 B.
DL/SEPB Gb CYAPCo to NRC 10/02/81 V-2 X
NRC to CYAPCo 01/16/79 X
NRC to CYAPCo 05/07/81 III-6 DL/SEPB 3
CYAPCo to NRC 06/11/81 V-3 III-7 A.
X HRC to CYAPCo 05/07/81 V-4 X
HRC to CYAPCo 05/07/81 III-7 B.
DL/SEPB 3
CYAPCo to NRC 09/07/79 V-5 DL/SEPB C
CYAPCo to NRC 08/1'3/61 III-7 C.
X NCC to CYAPCo 04/16/79 V-6 DL/SEFB 7
HRC to CYAPCo 03/05/80 III-7 D.
DE/SEB 7
NRC to CYA?Co 50/16/81 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 NRC to CYAPCo 05/07/81 V-10 B.
DL/SEPB 7
CYAPCo to NRC 11/10/88 III-9 X
HRC 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(Elec) Part of VII-3 08/23/81 (2-16) 4
s
~
e HADDAM NECK 4.-
s TOPIC NO.
REVIEW STATUS REMARKS TO?IC NO.
REVIEW STATUS FEFAN S l
DIV/BK DIV/BR I-h V-12 A.
X tiRC to CTAPCo 11/16/79 VI-7 D.
DL/5EPC 7
NRCxto
(. v a i r-P.. ?///C s
1 V-13 X
NRC to CYAPCo 05/07/81 VI-7 E.
X',
NRC to CrAFCr, 05/07/81 VI-1 DE/CEB 3
CYAPCO to NRC 10/31/79 VI-7 F.
X NRC to C) APCo' - 04/16/79 VI-2 A.
X NRC to CYAPCo 05/07/81 VI-8 X
NRC to CrAPCo C5/01/'.1 i
VI-2 E.
X NRC to CYAPCo 05/07/81 VI-9 X
NRC to C P Co 11/16/79 VI-2 C.
X NRC to CYAPCo 04/16/79 VI-10 A.
CL/SEPB 0
VI-2 D.
DSI/CSB 3
CYAPCo to NRC 04/27/81 VI-10 B.
X NPC to CYAFCc 04/16f79 VI-3 DSI/CSB 3
CYAPCo to NRC 04/27/81 VII-1 A.
DL/SEPB 3
CYAPCo t o t;F C 08/67/31 VI-4 DSI/CSB 0(Sys)
VII-1 B.
DL/SEPB 7
tiRC t o CYAPCo DC/17/78 DL/SEPB 7(Elec) NRC to CYAPCo 09/21/81 VII-2 DL/SEPB 3
CYAPCo to NEC 08/07/81 VI-5 X
NRC to CYAPCo 05/07/81 VII-3 DL/SEPB 7(Sys)
HRC to CfAPCo 11/ ; Q /81 VI-6 DSI/CSB G
NRC to CYAPCo 05/07/81 DL/SEPB 7(Elec) LRC to CYtJCo 0*/28/C1 VI-7 A.
1.
DL/SEPB 7
NRC to CYAPCo 02/20/81 VII-4 X
NRC to CYArco 05/07/31 VI-7 A.
2.
X NRC to CYAPCo 05/07/81 VII-5 X
14 R C to CYAPCo 05/07/81 VI-7 A. 3.
DL/SEPB 0
VII-6 DL/SEP3 7
NRC to CYAFCo 03/28/81 VI-7 A.
4.
X NRC to CYAPCo 05/07/81 VII-7 X
IIRC to CYAPCa 04/16/77 VI-7 B.
DSI/RSB CCSys)
VIII-1 A.
DSI/PSB G
NRC to CYAPCo 05/07/81 DL/SEPB 7(Elec) NRC to CYAPCo 05/21/81 VIII-2 DL/SEPB 7
14RC to CYAPCo 08/28/$1 VI-7 C.
DL/SEPB 7
HRC to CYAPCo 03/13/81 VIII-3 A.
DL/SEPS 7
CYAPCo to NEC 02/16/79 VI-7 C.
1.
DL/SEPB 6
CYPACO to NRC 12/02/81 VIII-3 B.
DL/SEPB 7
NRC to CYAPCo 03/23/31 VI-7 C. 2.
DL/SEPB 7
NRC to CYAPCo 03/13/81 VIII-4 DL/SEPB 5
NRC to CYAPCo 12/23/81 l
VI-7 C. 3.
DL/SEPB 5
NRC to CYAPCo 12/14/81 l
(2-17)
HADDAM NECK TOPIC h0.
REVIEW STATUS REMARKS TCPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 4b CfAPCo to hRC 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 D6/SEPB Gb CYAPCo to NRC 12/14/81 XV-12 DSI/CPB 4b(Sys) CYAPCo to NRC 09/30/81 DSI/RSB Eb(Doses)CYAPCo to NRC 01/30/81 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 hRC 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/AED 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/AES 4b(Dosos)CYAPCo to NRC 09/30/81
'V - 1 DSI/RSB 4b CYAPCo to NRC 09/30/81 4
XV-20 DL/SEPB 7
HRC te, CYAPCo 06/09/81 1-2 DSI/RSB Gb(Sys) CYAPCo to NRC 09/30/81 DSI/AEB Gb(Doses)CYAPCo to NRC 09/30/81 XV-21 X
NRC to CYAPCo 05/07/81 XV-3 DSI/RSB Gb CYAPCo to NRC 09/30/81 XV-22 X
NRC to CYAPCo 0S/07/81 XV-4 DSI/RSB 7
NRC to CYAPCo 12/17/81 XV-23 X
NRC to CYAPCo 05/07/81 XV-5 DSI/RSB Gb CYAPCo to NRC 09/30/81 XV-24 X
NRC to CYAPCo 05/07/81 XV-6 DSI/RSB Gb CYAPCo to NRC 09/30/81 XVI X
N<C 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 Gb CYAPCo to NRC 09/30/81 (2-18)
LACROSSE FACILITY: LACROSSE TOPIC NO.
REVIEW STATUS R Ef1 A RKS DIV/BR LICENSEE: DAIRLAND PCWER II-l A.
DE/SAB Ab DPC to hRC 06/23/88 REGION / LOCATION: 19 MILES SOUTH OF LACROSSE. WISC.
II-1 B.
DE/SAB Gb DPC to t!RC 06/16/81 DOCKET NO.
05000409 II-1 C.
DE/SAB Gb 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: 58L II-2 D.
X NRC to LPC 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W.
RUSSELL II-3 A.
DE/HGEB 4b DPC to NRC 06/16/81 CPERATING 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 0
MICHt.ELShh2 c/-
II-3 C.
DE/HGEB 4b DPC to NRC 06/26/81 INTEGRATED ASSESSMENT PROJECT MANAGER: T.
j II-4 DE/GSB 7
NRC to DPC 06/08/81 KEf FOR STATUS CODES II-4 A.
DE/GSB 7
NRC to DPC 06/08/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.
DE/GSB 3
FROM REVIEW BRANCH X - DELETED II-4 C.
DE/GSB 7
NRC to DPC 06/08/81 Ab-SAR RECEIVED FROM O - TOPIC NOT LICENSEE II-4 D.
DE/HGEB 3
Site Visit 07/10/79 STARTED 5 - DRAFT SE SENT II-4 E.
DE/HGEB 0
1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.
DE/HGEB 2
6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC III-1 DL/SEPB 3(Sys)
DPC to NRC 08/06/81 TO UTILITY DL/SEPB 0(Elec) 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 D L / S E.'B 4b DPC to NRC 08/06/81 RECEIVED BY NRC (2-19)
LACROSSE TOPIC ND.
REVIEW STATUS REMARKS TCPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR 111-3 A.
DE/SEB 2
NhC to OPC 08/09/79 III-10 D.
X NRC to DPC 10/29/79 III-3 B.
X NRC to DPC 03/10/81 III-10 C.
X NRC to DPC 10/29/79 III-3 C.
DE/NGEB 0
III-11 X
NRC to DPC 05/07/81 III-4 A.
DSI/ASB 0
III-12 X
NRC to DPC 05/07/81 III-4 B.
DE/MTEB 0
IV-1 A.
DL/SEPB 7
14RC to DPC 04/19/79 III-4 C.
DSI/ASB 0
IV-2 DSI/ICSB 5
NRC to DPC 12/28/81 III-4 D.
DE/SAB Ab 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 DFC 11/27/81 III-5 B.
DL/SEPB 4b DPC to NRC 06/29/81 V-2 X
NRC to DPC 10/29/79 III-6 DL/SEPB 3
DPC to NRC 06/12/81 V-3 X
NRC to DPC 05/07/81 III-7 A.
X NRC to DPC 05/07/81 V-4 X
NRC to DPC 05/07/81 III-7 B.
DL/SEPB 2
NRC to DPC 08.09/79 V-5 DL/SEPS 4a III-7 C.
X NRC to DPC 10/29/79 V-6 DL/SEPB 7
NRC to DPC 03/0.**80 III-7 D.
DE/SEB 4b DPC to NRC 06/29/81 V-7 X
HRC to DPC 05/0) 81 III-8 A.
DSI G
NRC to DPC 05/07/81 V-8 X
NRC to DPC 05/07/81 III-8 3.
X NRC to DPC 09/26/80 V-9 X
NRC to DPC 10/29/79 III-8 C.
DL/SEPC 7
DPC to NRC 03/03/81 V-10 A.
DL/SEPB
/
NRC to DPC 01/07/80 III-8 D.
X NRC to DPC 05/07/81 V-10 B.
DL/SEPB 5
NRC to DPC 12/22/80 III-9 X
NRC to DPC 05/07/81 V-11 A.
DL/SEPB 7
NRC to DPC 12/22/80 ;
III-10 A.
DL/SEPB 7
NRC to DPC 09/22/81 V-11 B.
DL/SEPB 5(Sys)
NRC to DPC 12/22/80 DL/SEPB 0(Elec)
(2-20)
LACROSSE TDPIC NO.
REVIEW STATUS REMARKS TCPIC NO.
REVIEW STATUS REMt.RKS DIV/3R DIV/BR V-12 A.
DL/SEPB 7
hRC t D PC 04/30/79 VI-7 D.
DL/SEPD 7
bRC to DPC 0 8/11/ / C V-13 X
NRC to DPC 05/07/81 VI-7 E.
X NRC to DPC 05/07/81 VI-1 DE/CEB 3
DPC to NRC 08/23/79 VI-7 F.
X NRC to DPC 10/21/79 VI-2 A.
X NRC to DPC 05/07/81 VI-8 X
NRC to DPC 05/07/81 VI-2 B.
X NRC to DPC 05/07/81 VI-?
X NRC to DPC 10/29/79 VI-2 C.
X NRC to DPC 10/29/79 VI-10 A.
DL/SEPB 2
NRC to DPC 07/21/81 VI-2 D.
DSI/CSB 3
DPC to NRC 04/26/79 VI-10 E.
X NRC to DPC 10/29/79 VI-3 DSI/CSB 3
DPC to NRC 04/26/79 VII-1 A.
DL/SEPB 2
NRC to DPC 10/96/81 VI-4 DSI/CSB 3(Sys)
DPC to NRC 08/17/81 VII-1 B.
DL/SEPB 7
NRC to DPC 08/17/78 DL/SEPB 6(Elec) DPC to NRC 08/26/81 VII-2 DL/SEPB 2
NPC to DPC 19/06/81 VI-5 X
NRC to DPC 05/07/81 VII-3 DL/SEPB 5(Sys)
NRC to DPC 12/22/80 VI-6 DSI/CSB G
NRC to DPC 05/07/81 DL/SEPB 3(Elec)
VI-7 A.
1.
X NRC to DPC 10/29/79 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 0
VII-6 DL/SEPB 7
HRC to DPC 09/21/81 VI-7 A.
4.
X NRC to DPC 05/07/81 VII-7 X
NRC to DPC 10/29/79 VI-7 B.
X NRC to DPC 10/29/79 VIII-1 A.
DSI/PSB G
NRC to DPC 05/07/81 VI-7 C.
DL/SEPB 7
NRC to DPC 03/13/88 VIII-2 DL/SEPB 7
HRC to DPC 12/18/81 VI-7 C.
1.
DL/SEPB 7
NRC to DPC 09/21/81 VIII-3 A.
DL/SEPC 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 C8/28/81 VI-7 C. 3.
X NRC to DPC 10/29/79 VIII-4 DL/SEPB 7
NRC to DPC 09/09/81 (2-21)
LACROSSE TOPIC HO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB u
XV-10 X
NRC to DPC 10/29/79 IX-2 X
NRC to DPC 05/07/81 XV-11 DSI/CPB C
IX-3 DL/SEPB 2
XV-12 X
NRC to DPC 10/29/79 IX-4 X
NRC to DPC 10/29/79 XV-13 DSI/CPB 0(Doses)
DSI/AEB 0(Sys)
IX-5 DL/SEPB 0
XV-14 DSI/RSB 4b DPC to NRC 08/25/81 IX-6 DE G
NRC to DPC 05/07/81 XV-15 DSI/RSB 7
NRC to DPC 09/21/81 X
X NRC to DPC 05/07/81 XV-16 DSI/AEB 0
XI-1 DSI/ETSB X
HRC to DPC 12/04/81 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
HRC to DPC 11/13/81 XV-22 X
HRC 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 D
XV-24 X
NRC to DPC 05/07/81 XV-6 X
HRC to DPC 10/29/79 XVI X
HRC 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 08/25/31 (2-22)
MILLSTONE 1 FACILITY: MILLSTONE 1 TOPIC NO.
REVIEW STATUS REMARKS DIV/BR LICENSEE: NORTHEAST NUCLEAR ENERGY 11-1 A.
DE/5AB 7
NRC to NU 07/31/81 REGION / LOCATION: 5 MILES SOUTH WEST OF NEW LONDON. CONN.
II-1 B.
DE/SAB 7
NRC 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)
Il-2 A.
DSI/AEB 7
NRC to NU 03/30/81 OL NUMBER: DPR-21 II-2 B.
X HRC to NU 05/07/81 H.S.S.S.
GE.
II-2 C.
DSI/AEB 7
NRC to NU 09/29/81 A/E FIRM EBASCO II-2 D.
X HRC to NU 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL I;-3 A.
DE/HGEB 4b Nu to NRC 06/25/81 OPERATING REACTORS BRANCH CHIEF:
D.
CRUTCHFIELD II-3 B.
DE/HGEB Gb NU to NRC 06/26/81 GPERATING REACTORS PROJECT MANAGER:
J.
SHEA
/1 II-3 B.
1 DE/HGEB 4b HU to NRC 06/25/81 INTEGRATED ASSESSMENT PROJECT MANAGER: D. PERSINKO II-3 C.
DE/HGEB 4b NU to NRC 04/28/81 II-4 DE/GSB 7
HRC 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 4a NUREG/CR1532 12/30/81 FROM REVIEW BRANCH X - DELETED II-4 C.
DE/GSB 7
NRC to NU 06/08/81 4b-SAR RECEIVED FROM 0 - TOPIC NOT LICENSEE II-4 D.
DE/HGEB 4b NU to NRC 08/31/81 STARTED 5 - DRAFT SE SENT II-4 E.
X NRC to NU 11/16/79 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.
DE/HGEB 4b NU to NRC 04/28/81 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY HRC III-1 DL/SEPB 3(Elec) NU to NRC 09/21/81 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 3
HU to NRC 08/29/79 RECEIVED BY NRC (2-23)
MILLSTONE 1 TOPIC NO.
REVIEW STATUS REMARKS TOPIC f40.
REVIEW STATUS REMARKS DIV/DR DIV/ER III-3 A.
DE/SEB 5
NkC to tiu 05/11/81 111-10 B.
X NRC to NU ll/16/19 III-5 B.
X NRC to NU 12/26/80 III-10 C.
DL/SEPB 7
NU to NRC 08/29/79 III-3 C.
DE/NGED 4b NU to NRC 08/31/81 III-11 X
NRC to NU 05/07/81 III-4 A.
DSI/ASB 4b HU to NRC 08/31/81 III-12 X
NRC to NU 05/07/81 III-4 B.
DE/MTEB 4b NU to NPC 08/31/81 IV-1 A.
DL/SEPB 7
NU to NRC 02/12/79 III-4 C.
DSI/ASB 3
NU to NRC 12/05/80 IV-2 DSI/ICSB Ab NU to NRC 10/28/81 III-4 D.
DE/SAB 7
NRC to NU 11/27/81 IV-3 DE/MTEB G
NRC to NU 05/07/81 III-5 A.
DL/SEPB 3
NU to NRC 11/08/79 V-1 X
NRC to NU 11/27/81 III-5 B.
DL/SEPB 4b NU to NRC 12/04/81 V-2 X
HRC to NU 11/16/79 III-6 DL/SEPB 5
NRC to NU 05/28/81 V-3 X
NRC to NU 05/07/81 III-7 A.
X NRC to NU 05/07/81 V-4 X
NRC to NU 05/07/81 III-7 B.
DL/SEPB 3
HU to NRC 08/29/79 V-5 DL/SEPB 7
HRC to NU 08/28/81 III-7 C.
X NRC to NU 11/16/79 V-6 DL/SEPB 7
NRC to NU 03/05/80 III-7 D.
DE/SEB 7
NU to NRC 02/17/81 V-7 X
NRC to NU 05/07/81 III-8 A.
DSI G
HRC to NU 05/07/81 V-8 X
NRC to NU 05/07/81 III-5 B.
X HRC to NU 09/26/80 V-9 X
NRC to NU 11/16/79 III-8 C.
DL/SEPS 6
NU to NRC 01/31/80 V-10 A.
DL/SEPB 7
NU to NRC 03/05/79 III-8 D.
X NRC to NU 05/07/81 V-10 B.
DL/SEPB 7
NU to NRC 07/22/81 III-9 X
tlP.C to NU 05/07/81 V-11 A.
DL/SEPB 7
NRC to NU 07/08/81 III-10 A.
DL/SEPB 7
NRC to NU 06/28/81 V-11 B.
DL/SEPB 7(Sys)
NU to NRC 07/22/81 DL/SEPB 3(EInc) NU to NRC 09/21/81 (2-24)
MILLSTONE 1 TOPIC HO.
REVIEW STATUS REMARKS TCPIC NO.
REVIEW STATUS REMARKS DIV/ER DIV/ER V-12 A.
DL/SEPB 7
NRC to flu 12/17/79 VI-7 D.
UL/SEFB 7
tlR C to t,U 00/1//78 V-13 X
NRC to NU 05/07/81 VI-7 E.
X NRC to t;U 05/07/81 VI-1 DE/CEB 4b NU to NRC 09/30/81 VI-7 F.
X NRC to NU 11/16/79 VI-2 A.
X NRC to NU 05/07/81 VI-8 X
tlRC to NU 05/07/81 i VI-2 B.
X NRC to NU 05/07/81 VI-9 X
NRC to NU 11/16/79 VI-2 C.
X NRC to NU 11/16/79 VI-10 A.
DL/SEPB 7
NRC to NU 10/05/01 VI-2 D.
DSI/CSB 3
HU to NRC 06/09/81 VI-10 *.
DL/SEPB 7(Sys)
NU to NRC 03/05/81 DL/SEPB 7(EIcc)
VI-3 DSI/CSB 3
NU to NRC 06/09/81 VII-1 A.
DL/SEPB 7
tiP.C to NU 07/23/81 VI-4 DSI/CSB 5(Sys)
HRC to NU 12/09/81 DL/SEPB 6(Elec) NU to NRC 08/12/81 VII-1 B.
DL/SEPB 7
H"C to NU 08/17/78 VI-5 X
NRC to 110 05/07/81 VII-2 DL/SEPD 6
tiu to tiR C 03/26/01 VI-6 DSI/CSB G
HRC to NU 05/07/81 VII-3 DL/SEPB 7(Sys)
NU to fiRC 07/22/81 DL/SEPD 3(Elec) NU 4 o 14RC 09/21/81 VI-7 A.
1 X
NRC to NU 11/16/79 VII-4 X
NRC to fiU O '>/ 0 7 /01 VI-7 A.
2.
X flRC to NU 05/07/81 VII-5 X
tlR C to NU 05/C7/01 VI-7 A.
3.
DL/SEPB 7
NRC to NU 60/27/81 VII-6 DL/SEPB 7
NEC to NU 03/26/81 VI-7 A.
4.
DSI/RSB G
HRC to NU 05/07/81 VII-7 X
t:RC to flu 11/16/79 VI-7 B.
X HRC to NU 11/16/79 l
VIII-1 A.
DSI/RSB G
NRC to fiU 05/07/31 VI-7 C.
DL/SEPB 7
HRC to NU 03/29/81 VIII-2 DL/SEPB 7
NRC to NU 09/3c/81 VI-7 C.
1 DL/SEPB 7
HU to NRC 11/02/81 VIII-3 A.
DL/SEPB 7
NRC to NU 05/?6/31 VI-7 C.
2.
DL/SEPD 7
NRC to NU 03/29/81 VIII-3 B.
DL/SEPD 7
t'R C to NU 07/23/81 VI-7 C. 3.
X NRC to NU 11/16/79 VIII-4 DL/SEPB 7
NCC to NU 07/07/81 (2-25)
i MILLSTONE 1 TOPIC HO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/ER DIV/BR
[
IX-1 DSI/ASB 4b NU to NRC 08/31/81 XV-10 X
NRC to NU 11/16/19 IX-2 X
HRC to NU 05/07/81 XV-11 DSI/CPB 7
NRC to NU 10/14/81 t
IX-3 DL/SEPB 4b NU to NRC 11/24/81 XV-12 X
NRC to NU 11/16/79
[
i IX-4 X
NRC to NU 11/16/79 XV-13 DSI/CPB 7(Sys)
NU to NRC 09/09/81 DSI/AEB 7(Doses) HRC to NU 11/03/81 i
IX-5 DL/SEPB 4b NU to NRC 11/19/81
(
2 XV-14 DSI/RSB 7
NRC to NU 09/18/81 l
IX-6 DE G
NRC to NU 05/07/81 XV-15 DSI/RSB 7
NRC to NU 10/7.8/81 I
X X
NRC to NU 05/07/81 4
XV-16 DSI/AEB 5
NRC to NU 11/'J 3/81 XI-1 DSI/ETSB X
NRC to NU 12/04/81 XV-17 X
NRC to NU 11/16/79 4
XI-2 DSI/ETSB X
NRC to NU 12/04/81 XV-18 DSI/AEB S
NRC to NU 11/03/81 XIII-1 X
NRC to NU 05/07/81 XV-19 DSI/RSB 7(Sys)
HRC to NU 08/26/81 XIII-2 DL/SSPB G
NRC to NU 05/07/81 DSI/AEB 5(Doses) NRC to NU 11/03/81 XV-1 DSI/R$5 7
NRC to NU 12/31/81 XV-20 DSI/AEB 7
NRC to NU 11/03/81 XV-2 X
NPC to NU 11/16/79 XV-21 X
NRC to NU 05/07/81 XV-3 DSI/RSB 7
HRC to NU 09/18/81 XV-22 X
NRC to NU 05/07/81 i
XV-4 DSI/RSB 7
NRC to NU 09/18/81 XV-23 X
NRC to NU 05/07/81 i
XV-5 DSI/RSB 4a 12/23/81 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 j
XV-7 DSI/RSB 7
NRC te NU 12/04/81 XVII DL 7
NRC to NU 08/17/78 XV-8 DSI/CPB 7
HRC to NU 08/26/81 XV-9 DSI/RSB Ga 12/30/81 2
i (2-26)
0YSTER CREEK.
FACILITY: OYSTER CREEK 1 TOPIC NO.
REVIEW STATUS REl1 ARKS DIV/BR LICENSEE: JERSEY CEMTRAL POWER 4 LIGHT II-1 A.
DE/SAB 4b JCPL to NRC ll/30/8I~~
I T"JION/ LOCATION: 9 MILES SOUTH OF TOMS RIVER, NJ.
II-I B.
DE/SAB 4b JCPL to N'C 11/30/81 DOCKET t:C. : 05000219 II-1 C.
DE/SAB Gb JCPL to NRC 11/30/81 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 H.S.S.S.
GE.
II-2 C.
DSI/AEB Gb JCPL to NRC 11/04/81 A/E FTRM: B4R II-2 D.
X NRC to JCPL 05/07/81 SYSTEMATTC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL II-3 A.
DE/HGEB 4b JCPL to NRC 05/07/81 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD II-3 B.
DE/HGEB 4b JCPL to NRC 05/07/81 Di'ERATING REACTORS PROJECT MANAGER:
J.
LOMBARDO II-3 B.
1 DE/HGEB Gb JCPL to NRC 05/07/81 INTEGRATED ASSESSMENT PROJECT MANAGER: R F E L' #
II-3 C.
DE/HGEB 4b JCPL to NRC 05/07/81 II-4 DE/GSB 7
NRC to JCFL 03/03/81 KEY FOR STATUS CODES II-4 A.
DE/GSB 7
NRC to JCPL 06/08/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.
DE/GSB 5
NRC to CPU 08/03/81 FROM REVIEW BRANCH X - DELETED II-4 C.
DE/GSB 7
NRC to JCPL 06/C8/81 4b-SAR RECEIVED FROM 0 - TOPIC NOT LICENSEE II-4 D.
DE/HGEB 4b JCPL to NRC 12/15/81 STARTED 5 - DRAFT SE SENT II-4 E.
X NRC to JCPL 11/16/79 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.
DE/HGEB 4b JCPL to NRC 11/04/81 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY HRC III-1 DL/SEPB 3(Sys)
NRC to JCPL 02/21/79 TO UTILITY DL/SEPB 5(Elec) NRC to JCPL 07/09/81 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 4b JCPL to NRC 05/07/81 RECEIVED BY NRC (2-27)
0YSTER CREEK TCPIC NO.
REVIEW STATUS REMARKS TCPIC NO.
REVIEW STATUS REMARKS DIV/ER DIV/BR III-5 A.
DE/SLB 4b JCPL to NRC 05/07/81 111-10 B.
X 14RC to JCPL 11/16/79 III-3 B.
X NRC to JCPL 12/26/80 III-10 C.
X 11RC to JCPL 11/16/79 III-3 C.
DE/HGEB 4b JCPL to NRC 11/04/81 III-11 X
NRC to JCPL 05/07/81 III-4 A.
DSI/ASB 0
III-12 X
NRC to JCPL 05/07/81 III-4 B.
DC/MTEB Gb JCPL to NRC 12/07/81 IV-1 A.
DL/SEPB 7
NRC to JCPL 05/30/79 III-4 C.
DSI/ASB 2
HRC to JCPL 01/19/81 IV-2 DSI/ICSB 2
NRC to JCPL 12/15/80 III-4 D.
DE/SAB 4b JCPL to NRC 05/07/81 IV-3 X
NRC to JCPL 05/07/81 III-5 A.
DL/SEPB 5
NRC to JCPL 06/10/81 V-1 DE/t1T EB X
HRC to JCPL 11/24/81 III-5 B.
CL/SEPB 6
JCPL to NRC 10/06/81 V-2 X
NRC to JCPL 11/16/79 III-6 DL/SEPB 6
JCPL to tiRC 06/15/81 V-3 X
NRC to JCPL 05/07/81 III-7 A.
X NRC to JCPL 05/07/81 V-4 X
NRC to JCPL 05/07/81 III-7 B.
DL/SEPB 4a V-5 DL/SEPB 6
JCPL to NRC 11/04/81 III-7 C.
X NRC to JCPL 11/16/79 V-6 DL/SEPB 7
ilRC to JCPL 03/05/80 III-7 D.
DE/SEB 4b JCPL to NRC 11/04/81 V-7 X
HRC to JCPL 05/07/81 III-8 A.
DSI G
HRC to JCPL 05/07/81 V-8 X
tiRC to JCPL 05/07/81 III-8 B.
X NRC to JCPL 09/26/80 V-9 X
NRC to JCPL 11/16/79 III-8 C.
DL/SEPB 7
NRC to JCPL 10/30/80 V-10 A.
DL/SEPB 7
JCPL to t1RC 05/15/79 III-8 D.
X HRC to JCPL 05/07/81 V-10 B.
DL/SEPB 7
tiRC to JCPL 09/25/30 III-9 X
NRC ta 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(EIce) NRC to JCPL 07/09/81 (2-28)
OYSTER CREEK TOPIC ND.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARY,5 DIV/BR DIV/ER V-12 A.
DL/SEPB 6
JCPL to NRC i1/04/81 VI-7 D.
DL/SEPB 7
HRC to J Cl' L u t,/1/ / 74 V-13 X
NRC to JCal 05/07/81 VI-7 E.
X NRC to JCPL 0 5 / 0 7 /P,1 VI-1 DE/CEB 2
NR0 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
NRC to JCPL 11/16/79 VI-2 C.
X NRC to JCPL 11/16/79 VI-10 A.
DL/SEPB 7
NRC to JCPL 08/18/81 VI-2 D.
DSI/CSB 2
VI-10 B.
X NRC to JCPL 11/16/79 VI-3 DSI/CSB 2
VII-1 A.
DL/SEPB 7
NRC to JCPL 07/30/St VI-4 DSI/CSB Ga(Sys)
VII-1 B.
DL/SEPB 7
NPC to JCPL 03/17/78 DL/SEPB 5(Elec) NRC to JCPL 08/05/81 VII-2 DL/SEPB 6
JCPL to NRC 08/t7/81 VI-5 X
NRC to JCPL 05/07/81 VII-3 DL/SEPB 7(Sys)
NRC to JCPL 09/25/80 VI-6 DSI/CSB G
NRC to JCPL 05/07/81 DL/SEPB 7(Elec) hRC to JCPL 07/09/',1 VI-7 A.
1.
X NRC to JCPL 11/16/79 VII-4 X
NRC to JCPL 05/07/81 VI-7 A.
T X
NRC to JCPL 05/07/81 VII-5 X
NRC to JCPL 05/07/81 VI-7 A. 3.
DL/SEPB 7
NRC to JCFL 07/30/81 VII-6 DL/SEPD 7
NRC to JCPL 03/29/81 VI-7 A.
4.
DSI/RSB G
NRC to JCPL 05/07/81 VII-7 X
HRC to JCPL 11/t6/79 VI-7 B.
X NRC to JCPL 11/16/79 VIII-1 A.
DSI/PSB G
NRC to JCPL 05/07/31 VI-7 C.
DL/SEPB 7
NRC to JCPL 03/13/81 VIII-2 DL/SEPB 7
NRC to JCPL 06/29/81 VI-7 C.
1 DL/SEPB 7
NRC to JCPL 06/29/81 VIII-3 A.
DL/SEPB 7
NRC to JCPL 06/09/81 VI-7 C. 2.
DL/SEPB 7
NRC to JCPL 03/13/81 VIII-3 B.
DL/SEPB 7
NRC to JCPL 06/29/81 VI-7 C.
3.
X NRC to JCPL 11/16/79 VIII-4 DL/SEPB 2
HRC to JCPL 03/26/81 (2-29)
0YSTER CREEK TOPIC NO.
REVIEW STATUS REMARKS TCPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 3
JCPL to NRC 12/14/79 XV-10 X
NRC to JCPL 11/16/79 IX-2 X
NRC to JCPL 05/G7/81 XV-11 DSI/CPB 5
NRC to JCPL 04/09/81 IX-3 DSI/ASB 6
JCPL to NRC 10/01/81 XV-12 X
NRC to JCPL 11/16/79 IX-4 X
NRC to JCPL 05/07/81 XV-13 DSI/AEB 4b(Doses)JCPL to NRC 11/04/81 DSI/CPB 5(Sys)
NRC to JCPL 04/09/81 IX-5 DL/SEPB 0
XV-14 DSI/R$8 7
NRC to JCPL 07/16/81 IX-6 DE G
NRC to JCPL 05/07/81 XV-15 DSI/RSB 7
NRC to JCPL 12/04/81 X
X HRC to JCPL 05/07/81 XV-16 DSI/AEB Gb JCPL to NRC 11/04/81 XI-1 DSI/ETSB X
NRC to JCPL 12/04/81 XV-17 X
NRC to JCPL 11/16/79 XI-2 DSI/ETSB X
NRC to JCPL 12/04/81 XV-18 DSI/AEB 4a XIII-I X
NRC to JCPL 05/07/81 XV-19 DSI/AEB Ab(Doses)JCPL to NRC 11/04/81 XIII-2 DL/SSPB 7
NRC to JCPL 09/25/80 DSI/RSB 7(Sys)
NRC to JCPL 09/04/81 XV-1 DSI/RSB 7
NRC to JCPL 12/07/81 XV-20 DSI/RSB 4b JCPL to NRC 05/07/81 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
HRC to JCPL 05/07/81 XV-4 DSI/RSB 7
HRC 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
HRC to JCPL 05/07/81 XV-6 X
NRC to JCPL 11/16/79 XVI X
NRC to JCPL 11/05/80 XV-7 DSI/RSB 7
NRC to JCPL 12/04/81 XVII DL 7
NRC to JCPL 08/17/78 XV-8 DSI/CPB 5
NRC to JCPL 03/31/81
~
XV-9 DSI/RSB 4b JCPL to NRC 11/04/81 (2-30)
PALISADES FACILITY: PhtISADES TOPIC NO.
REVIEW STATUS REMARKS DIV/DR LICENSEE: CONSUMERS POWER II-1 A.
DL/SEPB 7
CPCo to NRC 12/28/19 REGION / LOCATION: 5 MILES SOUTH OF SOUTH HAVEN MI.
II-I B.
DL/SEPB 7
CPCo to NRC 12/28/79 DOCKET NO: 35000255 II-1 C.
DL/SEPB 7
CPCo to NRC 05/13/81 POWER CAPACITY: 2530(THERMAL) 08 0 5 ( E L ECTF.IC A L )
II-2 A.
DSI/AEB 7
NRC to CPCo 06/30/81 DL NUMBER: DPR-20 II-2 B.
X NRC to CPCo 05/07/81 H.S.S.S.
C-E II-2 C.
DSI/AEB 7
NRC to CPCo 04/23/81 A/E FIRM: EECH.
II-2 D.
X NRC to CPCo 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W.
RUSSELL 11-3 A.
DE/HGEB 6
CPCo to NRC 08/13/31 OPERATING REACTORS BRANCH CHIEF:
D. CRUTCHFIELD II-3 B.
DE/HGEB 6
CPCo to NRC 08/13/81 OPERATING REACTOR! PROJECT MANAGER:
T. WAMBACH II-3 B.
1.
DE/HGEB 6
CPCo to NRC 08/13/41 T.MICHAELSh(f INTEGRATED ASSESSMENT PROJECT MANAGER:
r II-3 C.
DE/HGEB 6
CPCo to NRC 08/13/31 g
II-4 DE/GSB 7
CPCo to NRC 07/04/81 KEY FOR STATUS CODES II-4 A.
DE/GSB 7
NRC to CPCo 07/04/81 G
GENERIC 4a-DRAFT SE PECEIVED II-4 B.
DE/GSB 7
CPCo to NRC 07/22/83 FROM REVIEW BRANCH X - DELETED II-4 C.
DE/GSB 7
Ntc to CPCo 06/08/81 Ab-SAR RECEIVED FROM 0 - TOPIC N3T LICENSEE II-4 D.
DE/HGEB 7
CPCo to NRC 06/05/81 STARTED 5 - DRAFT SE SENT II-4 E.
X NRC to CPCo 11/16/79 1 - QUESTICHS 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) NRC to CPCo 11/12/83 TO UTILITY DL/SEPB 5(Sys)
HRC to CPCo 12/27/81 7 - TOPIC COMPLETE 3 - QUESTIOP4 RESPONSE RECEIVED BY NRC (2-31)
l 4
PAllSADES i
TOPIC NO.
REVIEW STATUS REMARKS
' TOPIC HO.
REVIEW STATUS REMARKS DIV/BR DIV/BR III-2 DL/SEPB 7
NRC to CPCo 02/27/81 111-10 B.
DL/SEPB 6
CPCo to NRC 07/02/81 l
III-3 A.
DE/SEB 7
NRC to CPCo 08/26/81 III-10 C.
X HRC to CPCo 11/16/79 III-3.B.
X NRC to CPCo 12/26/80 III-11 X
NRC to CPCo 05/07/81 j
l III-3 C.
DE/NCEB 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 1
III-4 B.
DE/MTEB 5
NRC to CPCo 12/02/81 IV-2 DSI/ICSB 5
NRC to CPCo 10/16/81 I
III-4 C.
DSI/ASB 7
NRC to CPCo 09/21/81 IV-3 X
NRC to CPCo 05/07/81 J
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 4
III-5 B.
DL/SEPB 5
NRC to CPCo 12/23/81 V-3 X
HRC to CPCo 05/07/81 j
III-6 DL/SEPB 6
CPCo to NRC 07/13/81 V-4 X
HRC 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 I
III-7 B.
DL/SEPB 5
HRC to CPCo 11/16/81 V-6 DL/SEPB 7
NRC to CPCo 03/05/80 i
III-7 C.
DE/SEB 7
NRC to CPCo 10/19/81 V-7 DSI/ASB 7
HRC 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 l
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 l
III-8 C.
DL/MTEB 7
CPCo to NRC 12/28/79 V-10 B.
DL/SEPB 7
CPCo to NRC 12/23/81 III-8 D.
X NRC to CPCo 05/07/81 V-11 A.
DL/SEPB 7
NRC to CPCo 11/09/81 III-9 X
HRC to CPCo 05/07/81 V-11 B.
DL/SEPB 7(Sys)
CPCo to NRC 12/23/81
. NRC to CPCo 12/24/81 DL/SEPB 7(Elec)
III-10 A.
DL/SEPB 7
NRC to CPCo 05/19/81 i
l i
4
}
(2-32) a i
l
PAUSADES TOPIC HO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.
X NRC to CPCo 11/16/79 VI-7 D.
DL/5EPB 7
NRC to CPCo 08/17/78 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 CPCo 06/30/81 VI-2 A.
X NRC to CPCo 05/07/81 VI-8 X
NRC to CPCo 05/07/81 VI-2 B.
X NRC to CPCo 05/07/81 VI-9 X
NRC to CPCo 11/16/79 VI-2 C.
X NRC to CPCo 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
HRC to CPCo 08/17/78 DCI/CSB 6(Sys)
CPCo to NRC 08/10/81 VII-2 DL/SEPB 7
HRC to CPCo 05/19/81 VI-5 X
NRC to CPCo 05/07/81 VII-3 DL/SEPB 7(Sys)
CPCo to NRC 10/27/81 VI-6 DSI/CSB 5
HRC to CPCo 12/11/81 DL/SEPB 7(Elec) CPCo to NRC 12/31/81 VI-7 A.
1 X
NRC to CPCo 11/16/79 VII-4 X
NRC to CPCo 05/07/81 VI-7 A. 2.
X NRC to CPCo 05/07/81 VII-5 X
NRC to CPCo 05/07/81 VI-7 A. 3.
DL/SEPB 7
NRC to CPCo 12/18/81 VII-6 DL/SEPB 7
NRC to CPCo 05/19/81 VI-7 A.
4.
X NRC to CPCo 05/07/81 VII-7 X
HRC to CPCo 11/16/79 VI-7 B.
DL/SEPB 7(Elec) HRC to CPCo 05/19/81 VIII-1 A.
DSI/PSB 7
NRC to CPCo 12/22/81 DSI/RSB 7(Sys)
HRC to CPCo 06/30/81 VIII-2 DL/SEPB 7
NRC to CPCo 06/09/81 VI-7 C.
DL/SEPB 7
NRC to CPCo 02/20/81 VIII-3 A.
DL/SEPB 7
NRC to CPCo 05/22/81 VI-7 C.
1 DL/SEPB 7
NRC to CPCo 11/18/80 VIII-3 B.
DL/SEPB 7
NRC to CPCo 08/05/81 VI-7 C. 2.
DL/SEPB 7
HRC.to CPCo 02/20/81 VIII-4 DL/SEPO 7
HRC to CPCo 07/31/81 VI-7 C.
3.
X CPCo to NRC 12/12/79 (2-33)
PALISADES TOPIC NO.
REVIEW STATUS REMARKS TOPIC ND.
REVIEW STATUS REMARKS DIV/BR DIV/BR 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
NRC 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 DL/SEPB 5(Sys)
HRC to CFCo 12/04/81 IX-4 DSI/RSB 5
NRC 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 XV-14 DL/SEPB 7
NRC to CPCo 07s17/81 IX-6 DE G
NRC to CPCo 05/G7/81 XV-15 DL/SEPB 7
NRC to CPCo 07/17/81 X
X NRC to CPCo 05/07/81 XV-16 DL/SEPB 7
NRC to CPCo 12/31/30 XI-1 DSI/ETSS X
NRC to CPCo 12/04/81 XV-17 DL/SEP3 7(Dosos) NRC to CPCo 01/29/80 XI-2 DSI/ETSB X
NRC to CPCo 12/04/81 DL/SEPB 7(Sys)
NRC to CPCo 07/17/31 XIII-1 X
NRC to CPCo 05/07/81 XV-18 X
HRC to CPCo 10/01/80 XIII-2 DL/SSPB 7
NRC to CPCo 10/01/80 XV-19 DL/SEPB 7(Doses) NRC to CPCo 11/21/80 DL/SEPB 7(Sys)
HRC to CPCo 07/17/61 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) HRC to CPCo 05/18/81 DL/SEPB 7(Sys)
HRC to CPCo 07/17/81 XV-21 X
NRC to CPCo 05/07/81 XV-3 DL/SEPB 7
NRC to CPCo 07/17/81 XV-22 X
NRC to CPCo 05/07/81 XV-4 DL/SEPB 7
HRC to CPCo 07/17/81 XV-23 X
NRC to CPCo 05/07/81 XV-5 DL/SEPB 7
NRC to CPCo 07/17/81 XV-24 X
NRC to CPCo 05/07/81 XV-6 DL/SEPB 7
NRC to CPCo 07/17/81 XVI X
NRC to CPCo 11/05/80 XV-7 DL/SEPB 7
NRC to CPCo 07/17/81 XVII DL 7
NRC to CPCo 08/17/78 XV-8 DL/SEPB 7
NRC to CPCo 07/17/81 XV-9 DL/SEPB 7
HRC to CPCo 07/17/81 (2-34)
SAN ON0FRE FACILITY: SAN ONOFRE 1 TOPIC NO.
REVIEW STATUS REMARKS DIV/BR LICENSEE: SOUTHERN CALIFORNIA EDISON II-l A.
DL/SEPB 7
HRC to SCE 11/01/19 REGIDH/LOCATIDH: 5 MILES SOUTH OF SAH CLEMENTE, CA.
11-1 B.
DL/SEPB 7
NRC to SCE 11/07/79 DOCKET NO.
05000206 II-1 C.
DE/SAB 4b SCE to NRC 11/12/81 POWER CAPACITY: 1347(THERMAL) 0430(ELECTRICAL)
II-2 A.
DSI/AEB 7
NRC to SCE 04/27/81 OL NUMBER: DPR-13 II-2 B.
X NRC to SCE 05/07/81 H.S.S.S.'
WEST.
II-2 C.
DSI/AEB 7
NRC to SCE 11/18/81 A/E FIRM: BECH.
II-2 D.
X NRC to SCE 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL II-3 A.
DE/HGEB 3
SCE to NRC 11/17/81 OPERATING REACTORS BRANCH CHIEF:
D. CRUTCHFIELD II-3 B.
DE/HGEB 3
SCE to hRC 11/17/81 OPERATING REACTORS PROJECT MANAGER: W. PAULSON II-3 B.
1.
DE/HGEB 6
SCE to NRC 10/08/81 INTEGRATED ASSESSMENT PROJECT MANAGER: E.MCKENHAf)qy II-3 C.
DE/HGEB 4a II-4 DE/GSD S
hRC to SCE 03/15/81 KEY FOR STATUS CODES II.
A.
DE/GSB 5
NUREG-0712 12/80 G - GENERIC 4a-DRAFT SE RECEIVED II '
B.
DE/GSB 5
NUREG-0712 12/80 FROM REVIEW BRANCH X - DELETED II-4 C.
DE/GSB 5
NUREG-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 NRC 08/29/79 DL/SEPB 0(Elec)
TO UTILITY 7 - TOPIC COMPLETE 3 - QUESTI0H RESPONSE III-2 DL/SEPB 3
SCE to NRC 11/20/81 RECEIVED BY NRC (2-35)
SAN ON0FRE TOPIC HO.
REVIEW STATUS REMARKS TG?IC ND.
REVIEW STATUS REMARKS DIV/DR DIV/BR III-3 A.
DE/SEB 3
SCE to NRC 09/08/80 111-10 B.
DL/SEPD 7
HRC to SCE 11/08/79 III-3 B.
X HRC to SCE 11/16/79 III-10 C.
X HRC to SCE 11/16/79 III-3 C.
DE/HGEB 7
HRC to SCE 11/27/81 III-11 X
HRC 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.
D E/t1T E B 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
NRC to SCE 12/15/80 J
III-4 D.
DE/SAB 4b SCE to NRC 10/23/81 IV-3 X
HRC to SCE 05/07/81 III-5 A.
DL/SEPB 1
V-1 DE/MTEB X
HRC to SCE 11/27/81 III-5 B.
DL/SEPB 2
HRC to SCE 01/04/80 v-2 X
NRC to SCE 11/16/79 III-6 DL/SEPB 3
SCE to NRC 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
HRC to SCE 05/07/81 III-7 B.
DL/SEPB 3
SCE to HRC 11/20/81 V-5 DL/SEPB HRC to SCE 06/03/81 III-7 C.
X HRC to SCE 11/16/79 V-6 DL/SEPB 7
HRC to SCE 03/05/80 III-7 D.
DE/SEB 4b SCE to NRC 06/09/81 V-7 DSI/ASB 7
NRC to SCE 12/04/81 III-8 A.
DSI 7
HRC 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
HRC 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 3(Elec) Part of VII-3 (2-36)
SAN ON0FRE TOPIC HD.
REVIEW STATUS REMARKS TOPIC HD.
REVIEW STATUS REMARKS DIV/BR DIV/LR
' V-12 A.
X NRC to SCE 11/16/79 VI-7 D.
DL/SEPB 7
NRC to SLE 08/17/78 V-13 X
NRC to SCE 05/07/81 VI-7 E.
X NRC to SCE 05/07/81 VI-1 3
SCE to NRC 08/03/79 VI-7 F.
X NRC to SCE 11/16/79 VI-2 A.
X NRC to SCE 05/07/81 VI-8 X
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 08/28/8t VI-2 D.
DSI/CSB 3
SCE to NRC 06/22/79 VI-10 B.
DL/SEPB 7(Sys)
HRC to SCE 11/15/79 DL/SEPB 7(EIcc) HRC to SCE 11/15/79 VI-5 DSI/CSB 3
SCE to NRC 06/22/79 VII-1 A.
DL/SEPB 5
NRC to SCE 09/09/81 VI-4 DSI/CSB 3(Sys)
SCE to HRC 11/18/81 DL/SEPB 7(Elec) HRC to SCE 09/03/81 VII-1 B.
9L/SEPB 7
HRC to SCE 08/17/78 VI-5 X
HRC to SCE 05/07/81 VII-2 DL/SEPB 5
NRC to SCE 11/17/81 VI-6 DSI/CSB G
HRC to SCE 05/07/81 VII-3 DL/SEPB 5(Sys)
NRC to SCE 06/20/81 DL/SLPD 5(Elec) NRC to SCE 11/18/81 VI-7 A.
1.
DL/SEPB 7
NRC to SCE 02/20/81 VII-4 X
HRC to SCE 05/07/81 VI-7 A.
2.
X NRC to SCE 05/07/81 VII-5 X
NRC to SCE 05/07/81 VI-7 A.
3.
DL/SEPB 5
NRC to SCE 11/18/81 VII-6 DL/SEPB 7
NRC to SCE 08/28/31 VI-7 A. 4.
X NRC to SCE 05/07/81 VII-7 X
HRC to SCE 11/16/79 VI-7 B.
DSI/RSB 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
NRC to SCE 07/31/81 VI-7 C.
1.
DL/SEPB 7
NRC to SCE 08/05/81 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 11/16/70 VIII-4 DL/SEPS 7
HRC to SCE 12/31/81 (2-37)
SAN ON0FRE I
TOPIC NO.
REVIEW STATUS REMARKS TCPIC NO.
REVIEN STATUS RE!1 ARKS l
DIV/BR DIV/CR IX-1 DSI/ASB 3
SCE to NRC 10/05/79 XV-10 DSI/RSB 4b SCE. to NRL 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 4b SCE to NRC 11/02/81 XV-12 DSI/RSB 7(Sys)
NRC to SCE 11/19/81 DL/SEPB 7(Doses) f4RC to SCC 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 4b SCE to NRC 07/01/31 IX-6 DE G
NRC to SCE 05/07/81 XV-15 DSI/RSB 4b SCE to NRC 07/01/31 X
X NRC to SCE 05/07/81 XV-16 DSI/AEB 7
HRC to SCE 11/18/81 XI-1 DSI/ETSB X
NRC to SCE 12/04/81 XV-17 DSI/RSB 7(Sys)
HRC to SCE 12/07/81 XI-2 DSI/ETSB X
NRC to SCE 12/04/81 DSI/AEB 7tDoses) NRC to SCE 01/29/80 XIII-1 X
NRC to SCE 05/07/81 XV-18 X
fiRC to SCE 10/01/80 XIII-2 DL/SSPB 7
HRC to SCE 01/2'/81 XV-19 DSI/RSB 7(Sys)
HRC to SCE 08/26/81 DL/SEPB 7(Doses) NRC to SCE 01/29/80 XV-1 DSI/RSB 7
NRC to SCE 10/27/81 XV-20 DL/SEPB 7
NRC to SCE 03/23/*,0 XV-2 DSI/RSB 7(Sys)
SCE to NRC 10/27/81 DL/SEPB 7(Doses) NRC 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 0$/07/81 XV-4 DSI/RSB 7
NRC to SCE 12/21/81 XV-23 X
NRC to SCE 05/07/81 XV-5 DSI/RSB tb SCE to NRC 07/01/81 XV-24 X
NRC to SCE 05/07/81 XV-6 DSI/RSB Gb 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
HRC to SCE 11/20/79 l
XV-8 DSI/CPB 7
NRC to SCE 11/19/81 XV-9 DSI/RSB 5
NRC to SCE 05/11/81 (2-38)
YANKEE R0WE FACILITY: YANKEE ROWE 1 TOPIC NO.
REVIEW STATUS REMARKS DIV/BR LICENSEE: YANKEE ATOMIC ELECTRIC II-1 A.
DE/SAB 0
REGION /LOCATICH: 25 MILES HORTH EAST OF PITTSFIELD, NASS.
II-1 B.
DE/SAB 4b YAC.C 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 GL NUMBER: DPR-3 II-2 B.
X HRC to YAEC 05/07/81 d.S.S.d.: WEST.
II-2 C.
DSI/AEB 7
NRC to YAEC 09/04/81 A/E FIRM: S4W II-2 D.
X NPC to YAEC 05/07/81 SYSTEMATIC EVALUATIDH PROGRAM BRANCH CHIEF: W. RUSSELL II-3 A.
DE/HGEB 6
YAEC to NRC 03/16/81 CPERATING REACTORS BRANCH CHIEF:
D.
CRUTCHFIELD II-3 B.
DE/HGEB 6
YAEC to HRC 03/16/81 OPERATING REACTORS PROJECT MANAGER:
R. CARUSO II-3 B.
1 DE/HGEB 5
NRC to YAEC 02/09/81 INTEGRATED ASSESSt1ENT PROJECT MANAGER: M.
BOYLE II-3 C.
DE/HGEB 3
Site Visit II-4 DE/GSL 7
NRC to YAEC 06/08/81 KEY FOR STATUS CODES II-4 A.
DE/GSB 7
NRC to YAEC 06/08/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.
DE/GSB 3
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 D.
DE/HGEB 3
Site 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 to NRC 08/31/81 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY HRC III-1 DL/SEPB 0(Elec)
TO UTILITY DL/SEPB 3(Sys)
YAEC to NRC 01/31/79 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 3
YAEC to NRC 08/21/81 RECEIVED BY NRC (2-39)
YANKEE R0WE TOPIC NO.
REVIEW STATUS R E!1 AR KS TOPIC NO.
REVIEW STATUS REf1 ARKS DIV/BR DIV/BR 111-3 A.
DE/SE3 3
YAEC to tiR C 09/06/79 111-10 D.
X NRC to YAEC 11/16/19 III-3 B.
X NRC to YAEC 12/26/80 111-10 C.
X NRC to YAEC 11/16/19 III-3 C.
DE/HGEB 0
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/MIEB G
HRC to YAEC 05/07/81 IV-1 A.
DL/SEPB 7
NRC to YAEC 04/18/79 III-4 C.
DSI/ASB 0
IV-2 DSI/ICSB 7
NRC to YAEC 12/23/31 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
HRC to YAEC 01/04/80 V-1 DE/MTEB X
NRC to YAEC 11/27/81 III-5 B.
DL/SEPB 1
V-2 X
NRC to YAEC 11/16/81 III-6 DL/SEPB 3
YAEC to NRC 06/30/81 V-3 X
NRC to YAEC 05/07/81 III-7 A.
X NRC to YAEC 05/07/81 V-4 X
NRC to YAEC 05/07/81 III-7 B.
DL/SEPB 3
YAEC to NRC 08.'21/81 V-5 DL/SEPB 5
NRC to YAEC 01/24/80 III-7 C.
X NRC to YAEC 1 t/16/7 9 V-6 DL/SEPB 7
NRC to YAEC 03/05/30 III-7 D.
DE/SEB 4b 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
HRC 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
HRC 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 0(Elec)
(2-40)
YANKEE R0WE TOPIC ND.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.
X NRC to YAEC 11/16/79 VI-7 D.
DL/SEPB 7
NRC to YAEC 03/17/78 V-13 X
NRC to YAEC 05/37/81 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
HRC to YAEC 05/07/81 V;-2 B.
X NRC to YAEC 05/07/81 VI-9 X
HRC to YAEC 11/16/79 VI-2 C.
X NRC to YAEC 11/16/79 VI-10 A.
DL/SEPB 3
YAEC to NRC 06/30/81 VI-2 D.
DSI/CSB 2
VI-10 B.
X HRC to YAEC 11/16/79 VI-3 DSI/CSB 2
VII-1 A.
DL/SEPB 6
YAEC to NRC 11/24/81 VI-4 DSI/CSB 3(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 hRC 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
NRC to YAEC 05/07/81 DL/SEPB 0(Elec)
VI-7 A.
1.
DL/SEPB 7
NRC to YAEC 02/20/81 VII-4 X
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 4b YAEC to NRC 06/30/81 VII-6 DL/SEPB 7
NRC to YAEC 08/28/81 VI-7 A.
4.
X HRC to YAEC 05/07/81 VII-7 X
NRC to YAEC 11/16/79 VI-7 B.
DSI/RSB 7(Elec) HRC to YAEC 06/04/81 VIII-1 A.
DSI/PSB G
HRC to YAEC 05/07/81 0(Sys)
VI-7 C.
DL/SEPB 7
NRC to YAEC 03/13/81 VIII-2 DL/SEPB 7
NRC to YAEC 09/03/81 VI-7 C.
1 DL/SEPB 7
NRC to YAEC 09/04/81 VIII-3 A.
DL/SEPB 7
HRC to YAEC 11/07/79 VI-7 C. 2.
DL/SEPB 7
HRC to YAEC 03/13/81 VIII-3 B.
DL/SEPB 7
NRC to YAEC 08/28/81 VI-7 C.
3.
DL/SEPB 7
NRC to YAEC 07/24/80 VIII-4 DL/SEPB 2
hRC to YAEC 06/23/81 (2-41)
YANKEE R0WE TDPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 USI/ASB 4b YAEC to NRC 11/18/81 XV-10 DSI/RSB 4b 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 Gb YAEC to NRC 09/17/81 XV-12 DSI/CPB 4b(Sys) YAEC to NRC 06/30/81 DSI/AEB Gb(Dosos)YAEC to NRC 08/31/81 IX-4 DSI/RSB 4b YAEC to NRC 08/31/81 XV-13 X
HRC to YAEC 11/16/79 IX-5 DL/SEPB 4b YAEC to NRC 11/18/b1 XV-14 DSI/R$B 4b YAEC to NRC 06/30/81 IX-6 DE G
NRC to YAEC 05/07/81 XV-15 DSI/RSB 4b YAEC to NRC 06/30/81 X
X NRC to YAEC 05/07/81 XV-16 DSI/AEB 0
XI-1 DSI/ETSB X
NRC to YAEC 10/04/81 XV-17 DSI/RSB 0(Sys)
XI-2 DSI/ETSB X
NRC to YAEC 12/04/81 DSI/AEB 0(Doses)
XIII-1 X
HRC to YAEC 05/07/81 XV-18 X
NRC to YAEC 10/01/80 XIII-2 DL/SSPB 7
NRC to YAEC 03/11/81 XV-19 DSI/RSB 4bSys)
YAEC to NRC 11/18/81 DSI/AEB 0(Doses)
XV-1 DSI/RSB 0
XV-20 DL/SEPB 7
NRC to YAEC 09/06/81 XV-2 DSI/RSS 4b(Sys) YAEC to NRC 06/30/81 DSI/AEB 0(Doses)
XV-21 X
NRC to YAEC 05/07/81 XV-3 DSI/RSB 4b YAEC to SRC 06/30/81 XV-22 X
NRC to YAEC 05/07/81 XV-4 DSI/RSB 0
XV-23 X
NRC to YAEC 05/07/81 XV-5 DSI/RSB Gb YAEC to NRC 06/30/81 XV-24 X
NRC to YAEC 05/07/81 XV-6 DSI/RSB 0
XVI X
NRC to YAEC 11/05/80 XV-7 DSI/RSB 4b YAEC to NRC 06/30/81 XVII DL 7
NRC to YAEC 08/17/78 XV-8 DSI/CPB 0
XV-9 DSI/RSB 4b YAEC to NRC 06/30/81 (2-42)
4 l
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SAR 1/
SER 2/
s e
TOPIC HO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE
'SCHEUILE III-1 Classification of NONE 12/29/81C III-8.A Loose Parts Monitoring and NONC 18/0$/d:C
($YS)
Structures Components and Core Barrel Vibration Systems (Seismic and Monitoring (NRR B-60, C-12)
Quality)
I IV-2 Re ctivity Control Systems 07/31/81R
'10/16/81C III-5.A Effrcts of Pipe Break on 08/13/81R 12/04/81C Including Functional Design Structures, Systems and and Protection Against Components Inside Single Failures Containment V-7 Reactor Coolant Pump HDNE 1,11/16/81C III-5.B. > Pis.a Break Outsida 08/25/81R 12/23/81C Overspeed (NRR B-68)
.\\
containment
-'i.
VI-6 Containment Leak Testing NDHE 08/05/81C j
III-7.A Inservice Inspection, NONE 08/25/81C (MP A-04)
Including Prestressed Concrete Containments with VIII-1.A Potential Equipment HOFE 12/22/81C Either Grouted or Ungrouted Failures Associated with a
_ Tendons Degraded Grid Voltage (MP B-23)
III-7.5 Design Codes. Design NONE 11/16/81C Criteria, Load IX-1 Fuel Storage NONE 12/31/81C Combinations, and Reactor Cavity Design Criteria IX-4 Baron Addition System 10/09/81R 11/18/81C XI-1 Appendix I(MP A-02)
NONE DEL ET EE)
SAR 1/
SER 2/
XI-2 Radiological (Effluent NONE DELETED TOPIC HO. TITLE SCHEDULE SCHEDULE and Process) Monitorinq<
Systems (NRR B-67)
III-3.C Inservice Inspection of 12/21/81R R+30 1/
Water Control Structures 1/ SAR : Licensee Safet/ Analysis Report-Scheduled or Actual III-4.B Turbine Missiles (MP B-46)
NONE 12/02/81C (Actual (status Ab) when date is followed by R)
III-7.D Containment Structural NONE 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) 4
)
V-1 Compliance with Codes and NONE 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)
NONE J 1/31/82 1
i (3-2)
~ ~ n ~ ? '**w-( prv ~~~
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s 4
L IJ 0
6 M
0 6
YAM
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6 7
0 R
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6 R
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6 L
0 A
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6 M
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BE J
S A
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S T
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6 6
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6 4
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S 3
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3 E
2 LA 2
2 3
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SER 2/
SAR 1/
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TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDUEE SCHEDULE III-1 Classification of Struct-NONE 12/29/81C (SYS) ures Components and Systems IX-6 Fire Protection (MP B-02)
NONE 01/0'/81 (Seismic and Quality)
III-2 Wind and Tornado Loadings NOME 09/23/81C Dil i
SAR 1/
SER 2/
III-7.A Inservice Inspection, NONE 12/28/81c TOPIC HO. TITLE SCHEDULE SCHEDULE Including Prestressed Concrete Containmonts with III-4.C Internally Generated 12/30/31R R+30 1/
Containments Grouted or Missiles Ungrounded Tendons III-8.A Loose Parts Monitoring and NONE 11/03/81C III-7.B Design Codes, Design NONE 12/31/81C Core Barrel Vibration Criteria, Load Monitoring (NRR B-60,C-12)
Combinations, and Reactor Cavity Design Criteria V-7 Reactor Coolant Pump HONE 11/05/81C Overspeed(NRR B-68)
VI-7.C.1 Appendix K - Electrical NONE 11/18/81C Instrumentation and Control VI-2.D Mass and Energy Release for NDHE 09/25/81C (EIC) Re reviews Possible Pipe Break Inside Containment IX-5 Ventilation Systems NONE 11/02/81C VI-3 Containment Pressure and NONE 09/25/81C Heat Removal Capability El SAR 1/
SER 2/
VI-7.B ESF Switchover from NONE 12/18/81C TOPIC'NO. TITLE SCHEDULE SCHEDULE (SYS)
Injection to Recirculation Mode (Automatic ECCS 11-1.8 Pcoulation Distribution 04/15/81R 0 7/21/81C 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)
NONE DELETED Transportation, Institutional Indostrial, XI-2 Radiological (Effluent NONE DELETED and Military Facilities and Process) Monitoring Systems (NRR B-67)
II-4.D Stability of Slopes 06/30/81R 01/31/82 XV-9 Startup or an Inactive Loop NONE 10/16/81C II-4.F Settlement of Foundations 06/30/81R 01/31/82 or Recirculation Loop at an and Buried Equipment Incorrect Temperature, and Flow Controller Malfunction III-3.C Inservice Inspection of 10/12/81R 12/23/81 Causing an Increase in BWR Water Control Structures Core Flow Rate III-4.B Turbine Missiles (MP B-46)
NONE 12/02/81C XV-19 Loss-of-Coolant Accidents NONE 09/29/81C (DOSES)
Resulting from Spectrum of III-4.D Site Proximity Missiles 04/16/81R 07/21/81C (SYS)
Postulated Piping Breaks 10/02/81C (Including Aircraft)
Within the Reactor Coolant VI-1 Organic Materials and 11/06/81R 01/30/81 Post Accident Chemistry (3-4) i M
GINNA l/ SAR : Licensee Safety Analysis Report-Scheduled or Actual (actual (status 4b) when date is follwed by R)
Z/ SER : Staff Safety Evaluation Report -Scheduled or Actual (Actual (status 4a, 5, 7 ) when date is followed by C) 1/ Desiqinated number of days from receipt of licensee SAR (Hote:
if Licensee SAR is received then date is from receipt of additional information requested)
(3-5)
l lJ 3
0 M
0 3
YM 0
3 R
PA 0
3 RAN S
0 3
L A
B T
E F
T I
0 3
M N
B J
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3
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4 G
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1 3
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0 1
2 2
L TCO 0
1 2
1 PES 2
0 2
0 o
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0 0
0 1
S 1
LATT I
I 0
B 0
0 0
N S
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5 5
8 5
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2 2
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DRESDEN 2 QL DRESDEN 2 Q1 (Cont.)
SAR 1/
SER 2/
SAR 1/
SER 2/
TOPIC HO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE 111-1 Classification of NONE 12/30/81 11-3.B Flooding Potential and NONE R+45 (SYS)
Structures, Components and Protection Requirements Systems (Seismic and Quality)
II-3.B.1 Capability of Operating NONE R+45 Plant to Cope with Design III-2 Wind and Tornado Loadings 10/30/81 R+60 1/
Basis 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 i
Structures, Systems and Supply (Ultimate Heat Sink Components Inside (UHS))
Containment II-4.D Stability of Slopes 12/08/81R R+30 III-7.B Design Codes, Design NONE 10/30/82 Criteria, Load II-4.E Dam Integrity 12/08/81R R+30 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 NONE 08/05/81C Protection System from III-3.C Inservice Inspection of 10/20/81 R+30 Non-Safety Systems, Water Control Structures Including Qualifications of Isolation Devices III-4.B Turbine Missiles NCNE 01/15/82 VII-6 Frequency Decay NONE 08/26/81C III-4.D Site Proximity Missiles 12/08/81R R+30 (Including Aircraft) 1 IX-5 Ventilation Systems NONE 12/11/81 III-7.D Containment Structural 04/27/81R 03/31/82 Inteerity Tcsts Rh SAR 1/
SER 2/
V-1 Compliance wita Codes NONE DELETED TOPIC NO. TITLE SCHEDULE SCHEDULE and Standaros (10 CFR 4
50.55a)(MP A-bl.A-14)
II-1.A Exclusion Area Authority 0 6/ 01/81 R 10/06/81C and Control VI-1 Organic Materials and 10/31/81 R+45 Post Accident Chemistry II-1.B Population Distribution 04/27/81R 10/06/81C IX-6 Fire Protection NONE 02/01/82 i
II-1.C Potontial Hacards or 12/08/81R R+30 Changos in Potential Hazards Due to Q11 Transportation, SAR 1/
SER 2/
Institutional Industrial, TOPIC NO. TITLE SCHEDULE SCHEDULE and Military Facilities 11-2.C Atmospheric Transport and 03/20/81R 08/26/81C II-3.A Hydrologic Description NONE R+45 Diffusion Characteristics for tecident Analysis III-4.A Tornado Missiles 12/08/81R R+30 a
(3-7)
I)lRll!!llDililtit Dil (Cont.)
Dil (Cont.)
SAR 1/
SER 2/
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC MO. TITLE SCHEDULE SCHEDULE III-4.C Internally Generated 10/31/81 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 Parts Monitoring NONE 11/30/81 of Main Steam Isolation and Core Barrel Vibration Valve (EWR), 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 i
VI-2.D Mass and Energy Release for NONE 12/02/81C XV-5 Loss of Normal Feedwater 10/15/81R 12/04/81C Possible Pipe Break Inside Flow Containment XV-7 Reactor Coolant Pump Rotor 10/15/81R 12/18/81C VI-3 Containment Pressure and NONE 12/02/81C Seizure and Reactor Coolant a
Heat Removal Capability Pump Shaft Break VI-4 Containment Isolation NDHE 10/02/81C XV-8 Control Rod Misoperation 10/15/81R 12/18/81 (SYS)
System (System Malfunction or Operator Error)
VI-6 Containment Leak Testing NDHE 11/30/81 (MP A-04)
XV-9 Startup or an Inactive Loop 10/15/81R 12/07/81C or Recirculation Loop at an VI-7.A.4 Core Spray Nozzle NONE 11/30/81 Incorrect Tcnparature, and Effectiveness (NRR A-16)
Flow Controller Malfunction Cousing an Increase in BWR VIII-1.A Potential Equipment NONE 02/26/82 Coro Flow Rato Failures Associated with a Dcqradod Grid Voltage XV-11 Inadvertent Loading and 10/15/81R 12/18/81 (MP B-23)
Operation of a Fuel Assembly in an Improper 1
IX-1 Fuel Storage 09/15/81 R+30 Position 1
XI-1 Appendix I(MP A-02)
NONE DELETED XV-13 Spectrum of Red Drop 10/15/81R 12/18/81 (SYS)
Accidents (BWR) 1 1
XI-2 Radiological (Effluent and NONE DELETED (DOSES) 10/15/81R 12/14/81C Process) Monitoring Systems (NRR B-67)
XV-14 Inadvortent 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 Feedwater Flow, Increase Reactor Coolant Inventory in Steam Flow and Inadvertent Cpening of a XV-15 Inadvertent Opening of a 10/15/81R 12/22/31C Steam Generator Relief or PWR Pressurizer Safety-Safety Valve Reliof Valve or a BWR Safety / Relief Valve (3-8) 5
4 1)lltl!!ilDililtit j
R11 (Cont.)
SAR 1/
SER 2/
TOPIC HO. TITLE' SCHEDULE SCHEDULE I
XV-18 Radiological Consequences 10/15/81R 12/23/81C of Main Steam Line Failure Outside Containment (BWR)
XV-19 Loss-of-Coolant Accidents 10/15/81R 11/17/81C (SYS)
Resulting from Spectrum of (DOSES)
Postulated Piping Breaks 10/15/81R 12/15/81 Within the Reactor Coolant Pressure Boundary XV-20 Radiological Consequences 04/27/81R 11/20/81C of Fuol Damaging Accidents (Inside and Outside i
Containment 1/ SAR = Licensee Safety Analysis Report-Scheduled or Actual (actual (status 4b) when date is followed by R)
Z/ SER : Staff Safety Evaluation Report -Scheduled or Actual (Actual (status 4a, 5, 7 ) when date is followed.by C)
I 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) i 1
)
4 i
1 F
(3-9) i i
4 r ~
LICENSEE SUBMITTALS IRESDEN 2 SLEMITTALS 48 1
TM i
l 35 B
l f
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2B
[
15
/
/
18
~
/
/
8 JtM Jll AUG SEP OCT NOV DEC JAN FEB NAR APR MAY JIM Jll IO THS Target 0
0 16 9
0 0
0 0
0 0
0 1
0 PER MONTH Actual 0
0 0
14 0
7 Target 0
0 16 25 25 25 25 25 25 25 25 25 25 CUMULATIVE Actual 0
0 0
14 14 21 (3-10)
OYSTER CREEK 21 OYSTER CREEK R1 (Cont.)
SAR 1/
SER 1/
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE III-1 Classification of NONE 01/15/82 III-7.D Containment Structural 09/01/81 03/01/82 (SYS)
Structures, Components Integrity Tests and Systems III-2 Wind and Tornado Loading 05/07/81R 01/31/82 V-Compliance with Codes NDHE DELETED and Structures VII-6 Frequency Decay NONE 08/29/81C (MP A-01,A-14)
VI-1 Organic Materials and Post 10/30/81 R+45 IX-5 Ventilation System 12/31/31 R+30 1/
Accident Chemistry VI-7.A-4 Core Spray Nozzle NOME 05/31/82 Effectiveness (MP D-12)
IX-6 Fire Protection (MP A-02)
NONE 05/01/82 El Eli SAR 1/
SER 1/
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE II-1.A Exclusion Area Authority 11/30/81R 01/31/82 II2.C Atmospheric Transport and 09/30/81R 11/20/81 and Control Diffusion Characteristics for Accident Ar.alysi s II-1.B Population Distribution 11/30/81R 01/31/82 III-4.A Tornado Missles 09/30/81 R430 II-1.C Potential Hazards Due to 11/30/81R 01/31/82 Transportation, Industrial, III-4.C Internally Generated 02/28/82 R+30 and Military Facilities Mi ssiles II-3.A Hydrologic Descrip& ion 05/07/81R R+45 III-8.A Loose Parts and Core NONE 11/30/81 Barrel Monitoring II-3.D Flooding Potential and 05/07/81R R+45 (NRR B-60,C-12)
Protection Requirements IV-2 Reactivity Control Systems NONE R+30 II-3.B-1 Capability to Cope with 05/07/81R R+45 Design Basis Flood VI-2.D Mass and Energy Release for NONE 11/20/81C Possible Pipe Break Inside II-3.C Safety Related Water Supply 05/07/81R R+45 Containment (Ultimate Heat Sink)
VI-3 Containment Pressure and NDHE 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 NOME 10/22/81C and Buried Equipment System III-3.A Effects of High Water 05/07/81R 02/28/82 VI-6 Containment Leak Testing NONE 06/04/81C Level on Structures (MP A-04)
III-3.C Inservice Inspection of 11/12/81R R+45 VIII-1.A Potential Equipment NDHE 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 Site Proximity Missiles 05/07/81R 01/31/82 IX-1 Fuel Storage 11/15/81 R+30 (3-11)
OYSTER CREEK Ril (Cont.)
R11 (Cont.)
SAR 1/
SER g/
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE XI-1 Appendix I(MP A-02)
NONE DELETED XV-16 Radiological Consequences 09/01/81 R+30 of Failure of Small Lines XI-2 Radiological (Effluent and NDHE 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 Spoetrum Breaks Within Reactor XV-3 Loss of External Load.
05/07/81R 07/16/81C (DOSES)
Coolant Pressure Boundary 05/07/81R R+3'.
Turbine Trip, Loss of Condensor Vacuum, closure XV-20 Radiological Consequences 05/07/81R R+3C of Main Steam Isolation of Fuel Damaging Accidents Valve (BWR), Steam Pressure (In 8 Out of Containment)
Regulatory Failure (closed)
XV-4 Loss of Non-Emergency A-C 05/07/81R 07/16/81C J/ SAR : Licensee Safety Analysis Report-Scheduled or Actual Power to the Station (actual (status 4b) when date is followed by R)
Auxillaries 2/ SER : Staff Safety Evaluation Report -Scheduled or Actual XV -3 Loss of Normal Feedwater 05/07/81R 11/30/81C (Actual (status 4a, 5,
- 7) when date is followed by C)
Flow 1/ Desiginated number of days from receipt of licensee SAR XV-7 Reactor Coolant Pump Rotor 08/25/81R 12/07/81C (Note: if Licensee SAR is received then date is from Seizure 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 Loop at Incorrect Temperature and Flow Controller Malfunction Causing an Increase in BWR Core Flow Rate XV-13 Spectrum of Rod Drop H0HE 04/09/81C (sys)
Accident 05/07/81R 07/01/81C (doses)
XV-14 Inadvertent Operation of 05/07/81R 07/16/81C ECCS that Increases Reactor Coolant Inventory XV-15 Inadvertent Opening of BWR 05/07/81R 11/19/81C Safety / Relief Valve (3-12)
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TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE 111-1 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.B 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 Operating 06/25/81R R+45 Plant to Cope with Design III-5.A Effects of Pipe Break on 09/30/81 02/10/82 Basis Flooding Conditions 4
Structures. Systems and Components Inside II-3.C Safety Related Water 04/28/81R R+45 Containment supply (UHS)
III-5.B Pipe Break Outside 12/04/81R 01/20/82 II-4.B Pro *1mity of Capable NONE 12/30/81C Containment 7.ctonic Structures in 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-11.8 RHR Interlock Requirements NONE 11/30/81 and Buried Equipment (ELEC)
III-3.C Inservice Inspection of 08/ 31/81R R+45 i
VII-3 Systems Required for Safe NONE 11/30/81 Water Control Structures (ELEC)
Shutdown 3
VII-6 Frequency Decay NCHE 08/26/81C III-4.D Site Prximity Missilas 04/29/81R 10/29/81C IX-3 Station Service and Cooling 09/30/81 R+30 1/
(Including Aircraft)
Water Systems IV-3 BWR Jet Pumps Operating NONE 06/30/82 IX-5 Ventilation Systems 09/30/81 R+30 Indications XIII-2 Safeguards Industrial NONE 06/30/82 V-1 Compliance with Codes and NONE DELETED Security (MP A-10)
Standards (10 CFR 50.55a)
(MP A-01,A-14)
RE VI-1 Organic Materials and Post 09/30/81R 01/30/82 SAR 1/
SER 2/
Accident Chemistry TOPIC NO. TITLE SCHEDULE SCHEDULE IX-6 Fire Protection NONE 06/30/82 II-1.A Exclusion Area Authority 8 0 4/17/81R 0 7/ 31/81C Control E11 II-1.B Population Distribution 05/19/81R 10/29/81C SAR J/
SER 2/
y TOPIC NO. TITLE SCHEDULE SCHEDULE II-1.C Potential Hazards or 04/29/81R 10/29/81C Changes in Potential Il-2.C Atmospheric Transport and 05/19/81R 09/29/81C Hazards Due to Transporta-Diffusion Charactoristics tion, Institutional, and for Accident Analysis Military Facilities III-4.A Tornado Missiles 08/ 3 './81 R 12/30/81 (3-14) 4
^ = - - -
m MILLSTONE 1 Dil (Cont.)
211 (Cont.)
SAR 1/
SER 2/
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC HO. TITLE SCHEDULE SCHEDULE III-4.0 Internally Generated 09/30/81 R+30 XV-3 Loss of External Load, 06/30/81R 09/18/81C Missilos Turbine Trip, Loss of Condenser Vacuum, Closure III-8.A Loose Parts Monitoring and NONE 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 Including Functional Design XV-4 Loss of Non-Emergency A-C 06/30/81R 09/18/81C and Protection Against Power to the Station Single failuros Auxiliaries VI-2.D Mass ano Tnergy Release for NDHE 12/01/81 XV-5 Loss of Normal Feedwater 06/30/81R 12/23/81C Possible Pipo Break Inside Flow Containment XV-7 Reactor Coolant Pump 06/30/81R 11/18/81C VI-3 Containmont Pressure and NONE 12/01/81 Rotor Seizure and Reactor Heat Romaval Capability Coolant Pump Shaft Break VI-4 Containment Isolation NONE 11/16/81C XV-8 Control Rod Misoperation 06/30/81R 08/26/81C (SYS)
System (System Malfunction or Operator Error)
VI-6 Leak Testing (MP A-04)
NONE 01/30/82 XV-9 Startup or an Inactive Loop 06/30/81R 12/30/81C VI-7.A.4 Coro Spray Hozzle NONE 12/31/81 or Recirculation Loop at an l
Effectivanos:(NRR A-16)
Incorrect Temperature, and Flow Controller Malfunction VIII-1.A Potential Equipment NONE 03/31/82 Causing an Increase in BWR Failures Associated With a Core Flow Rate Degraded Grid Voltaqo XV-11 Inadvertent Leading and 06/30/81R 10/14/81C 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 XI-2 Radiological (Effluent 8 NONE DELETED XV-13 Spectrum of Rod Drop 06/30/81R 09/09/81C Process) Monitoring Systems (SYS)
Accidents (BWR)
(NRR B-67)
(DOSES) 06/30/81R 09/21/81C XV-1 Dacrease in Foodwater 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 System Steam Flow and Inadvertent Malfunction that Increases i
'I 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 Pressurizer Safety Relief Valvo or a BWR Safety Relief Valve (3-15)
~.-
MILLSTONE 1 l
Q11.(Cont.)
SAR 1/
SER 2/
1 TOPIC HO. TITLE SCHEDULE SCHEDULE XV-16 Radiological Consequences 06/30/81R 0 9/21/81C of Failure of Small Lines Carrying Primary Coolant Outside Containment I
XV-18 Radiological Consequences 06/30/81R 09/21/81C of Main Steam Line Failure Outside Containment (BWR)
XV-19 Loss of Coolant Accidents 06/30/81R 08/26/81C (SYS)
Resulting from Spectrum of (DOSES)
Postulated Piping Breaks 06/30/81R 09/21/81C Within-the Reactor Coolant Pressure Boundary XV-20 Radiological Consequences 06/30/81R 0 9/21/81C of Fuel Damaging Accidents (Inside and Outside Containment)
I i
1/ SAR : Licensec ~'fety Analysis Report-Scheduled or Actual
]
(actual (stasus 4b) when date is followed by R) 2/ SER : Staff Safety Evaluation Report -Scheduled or Actual j
(Actual (status Ga, 5, 7) when date is followed by C)
J/ Desiginated number of days from receipt of Ilconsee SAR (Notes if Licensee SAR is received then date is from receipt of additional information requested) i i
i i
i u
l l
(3-16) y w
m w
L LJ 2
0 1
M I
J L
0 2
1 f
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2 1
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1 f
2 1
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0 1
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0 1
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N 1
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5 5
5 5
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SAN ONOFRE EL SAN ONOFRE SAR 1/
SER 2/
SAR l/
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TOPIC HO. TITLE SCNEDUEE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE IX-3 Station Service and Cooling 11/02/81R 01/31/82 111-1 Classification of NONE 01/29/82 Water Systems i
Structures, Components and i
Systems (Seismic and IX-5 Ven+ilation Systems 12/16/81R R+30 Quality) i III-2 Wind and Tornado Loadings 10/15/81 R+60 J/
HE SAR 1/
SER 2/
III-5.A Effects of Pipe Break on 11/15/81 03/26/82 TOPIC NO. TITLE SCHEDULE SCHEDULE i
Structures, Systems and Components Inside Il-1.C Potontial Hazards or 11/12/81R 02/28/82 Containment Changes in Potential Hazards Due to i
i III-5.B Pipe Break Outside 10/15/81 03/05/82 Transportation, j
Containment Institutional Industrial, and Military Facilities III-6 Sei smic Design NONE 12/31/82 Considerations II-3.A Hydrologic Description NONE 02/05/82 III-7.B Design Codos, Dosion NONE 12/31/82 I?-3.B Flooding Potential 8 HONE 02/05/82 Criteria, Load Protec tion Requirements Combinations, and Roactor Cavity Design Criteria II-3.C Safety Related Water NONE 02/05/82 Supply (UHS)
V-11.B RHR Interlock Requirements NONE 11/30/81 (ELEC)
II-4.D Stability of Slopes 11/02/81R 01/31/82-l VI-7 A.3 ECCS Actuation System NONE 11/18/81C II-4.F Sottlement of Foundations 11/02/81R 01/31/82 and Buried Equipment VI-7.B ESF Switchover from NONE 09/04/81C I
(ELEC)
Injection to Rocirculation III-3.A Efiocts of High Water Level 02/28/82 R+30 Modo (Automatic ECCS on Structures Realignment)
III-4.B Turbine Missiles (MP B-46)
NDHE 12/31/81 VI-10.A Testing of Reactor Trip HONE 08/28/81C 3
System and Engineered III-4.D Site Proximity Missiles 10/23/81R 12/31/81 Safety Featuros Including (Including Aircraft)
]
Response Time Testing III-7.D Containment Structural 06/09/81R 02/15/82 l
VII-1.A Inclation of Reactor NONE 09/09/81C Integrity Tests Protection Systems, 1
Including Qualifications V-1 Compliance with Codos and NONE DELETED j
of Isolation Devices Standards (10 CFR 50.55a)
(MP A-01) 4 VII-2 Engineered Safety Features NONE 11/18/81C
+
(ESF) System Control Logic VI-1 Organic Materials and Post 11/15/81 R+45 and Design Accident Chemistry VII-3 Systems Required for Safe NDHE 11/18/81C IX-6 Fire Protection (MP B-02)
NONE 10/01/82 (ELEC)
Shutdown VII-6 Frequency Decay NONE 08/28/81C (3-18)
SAN ON0FRE SAR 1/
SER 2/
~
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE III-4.A Tornado Missiles 10/15/81 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 11/15/81 R+30 densor Vaccum, Closure of Missiles Main Steara Isolation Valve (BWR), and Steam Pressure III-8.A Loose Parts Monitoring and NONE 12/07/81C Roqulator Failure (Closod)
Core Barrel Vibration Monitoring (NRR B-60 C-12)
XV-4 Loss of Non-Emercency A-C 08/18/81R 12/12/81C Power to the Station IV-2 Reactivity Control Systems 09/30/81 R+30 Auxiliarios Including Functional Design and Protection Against XV-5 Loss of Normal Feedwater 07/01/31R 02/15/82 Single Failures Flow V-7 Reactor Coolant Pump NONE 11/05/81C XV-6 Foedwater System Pipe 07/01/81R 02/15/82 Overspeed(NRR B-68)
Breaks Inside and Outside Containment (PWR)
VI-2.D Mass and Energy Rolnase for NONE 11/13/81 Possible Pipo Break Inside XV-7 Reactor Coolant Pump Rotor 07/ 01/81R 01/29/82 Containment Scirure and Reactor Coolant Pump Shaft Break VI-3 Containment Pressure and NONE 11/13/81 Heat Removal Capability XV-8 Control Rod Misoperation 07/01/81R 11/19/81C (System Malfunction or VI-4 Coni iement Isolation NONE 01/05/82 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 Baron Concentration in VIII-1.A Potential Ljuipment 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 11/19/81C Accidents (PWR)
IX-1 Fuel Storage 12/15/81 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 Radiological (Effluent and NONE DELETED Malfunction that Increases Process) Monitoring Systems Roactor Coolant Inventory (NRR B-67)
XV-1 Decrease in Feedwater 07/01/81R 10/27/81C XV-15 Inadvertent Oooning of a 07/ 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 Openino of a Steam Generator Relief XV-16 Radiological Consequences 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 Dutside Containment Piping Failures Inside and Outside of Containment (PWR)
(3-19)
SAN ON0FRE R11 (Cont.)
SAR 1/
SER Z/
TOPIC NO. TITLE SCHEDULE SCHEDULE XV-17 System Generator Tube NONE 12/07/81C
($YS)
Failure (PWR)
XV-19 Loss-of-Coolant Accidents 07/01/81R 08/26/81C Resulting From Spectrum of Postulated Piping Breaks Within the Reactor Coolant Pressure Boundary 1/ SAR: Licensee Safety Analysis Report-Scheduled or Actual (Actual (status 4b) when date is followed by R)
Z/ SER : Staff Safety Evaluation Report -Scheduled or Actual (Actual (status 4a, 5, 7) when date is followed by C) 1/ Desiginated number of days from receipt of licensee SAR (Note: if Licensee SAR is received then date is from receipt of additional information requested)
(3-20)
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BIG ROCK POINT Di BIG ROCK POINT pf SAR 1/
SER 2/
SAR J/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE III-1 Classification of St.act-NONE 02/19/82 II-3.A Hydrologic Description NONE R+45 (SYS) ures, Components and Sys-tems (Seismic and Quality)
II-3.B Flooding Potential and NONE R+45 Protection Requirements 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 05/10/82 Plans to Cope with Designs Structures. Systems and Basis Flooding Conditions Components Inside Containment II-3.C Safety-Related Water Supply NONE R+45 (Ultimate Heat Sink UHS))
III-5.B Pipe Break Outside 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 10/05/31R 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 High Water 03/15/82 R+30 VI-7.A.3 ECCS Actuation System NONE 12/30/81 Level on Structures VI-7.C ECCS Single Failure Cri-NONE 08/05/81C III-3.C Insarvice Inspection of 22/21/81R 02/15/82 terion and Requirements for Water Control Structures Locking Out Power to Valves Including Independence III-4.B Turbine Missiles 12/15/81 R+30 of Interlocks on ECCS Valve III-4.D Site Proximity Missiles 12/14/81R 03/31/82 VI-7.C.2 Failure Mode Analysis ECCS NONE 08/05/81C (Including Aircraft)
VI-10.A Testing of Reactor Trip 12/23/81 R+30 III-7.D Containment Structural 09/20/81 03/31/82 System and Engineered Integrity Tests Safety Features, including Response Time Testing V-1 Compliance with Codos and NONE DELETED Standards 310 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 Chomsitry Devices Accident Chemsitry VII-2 Engineered Safety Features NONE 12/31/81C IX-6 Fire Protection (MP E-02)
NONE 01/04/82 (ESF) System Control Logic and Design D$.1 VII-6 Frequency Decay NONE 09/21/81C SAR 1/
SER Z/
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 Di f fusion Characteri stics for Accident Analysis (3-22)
)
BIG ROCK POINT Dil (Cont.)
I Dil (Cont.)
SAR 1/
SER 2/
SAR 1/
SER 2/
TOPIC NO. 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/*6/81C Turbine Trip, Loss of III-4.C Internally Generated 03/15/82 R+30 Condenser Vacuum, Closure Missilos of Main Steam Isolation Valve (BWR), and Steam III-8.A Loose Parts Monitoring and NONE 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 10/16/81C IV-2 Reactivity Control System NONE 12/07/81C Power to Use Station Including Functional Design Auxiliaries and Protection Against Single Failures XV-5 Loss of Hornal Feedwater 07/15/81R 03/15/82 Flow VI-2.D Mass and Enorgy Release for NONE 01/22/82 Postulated Pipo Breaks 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 01/22/82 Heat Removal Capability XV-8 Control Rod Misoperation 09/23/81R 12/31/81C (System Malfunction or VI-4 Containment Isolation Sys.
HONE 01/22/82 Operator Error)
VI-6 Containment Leak Testing N0HE 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 (Automatic EECS Core Flow R&te 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 0 7/01/81R 11/20/81C Accidonts DOSES 07/01/81R 10/23/81C XI-1 Appendix I(MP A-02)
NDHE DELETED XI-2 Radiological (Effluent NDHE 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 Feedaatar 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 Generator Relief Safety / Relief Valve or Safety Valve (3-23)
BIG ROCK POINT Dil (Cont.)
SAR l/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE XV-16 Radiological Consequences 07/Ol/81R R+30 of Failure of Small Lines Carrying Primary Coolant Outside Containment XV-18 Radiological Consequences 07/01/81R 11/27/81 of Main Stoam Line Failure Outside Containment XV-19 Loss of Coolant Accidents 06/29/81R 08/18/81C (51 5)
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) 2/ SER : Staff Safety Evaluation Report -Scheduled or Actual (Actual (status 4a, 5, 7 ) when date is followed by C)
}/ Desiginated number of days from receipt of licenseo SAR (Notes if Licensee SAR is received than date is from receipt of additional information requested)
(3-24)
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SAR 1/
SER 2/
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE III-1 Classification of NONE 03/19/82 IX-5 Ventilation Systems 12/14/81R R+30 (SYS)
Structures, Ccmponents and Systems (Scismic 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/
I Et III-5 A.
Effects of Pipe Dreak 09/30/81 06/24/82 SAR 1/
SER 2/
on Structures, Systems TOPIC HO. TITLE SCHEDULE SCHEDULE and Componets Insido 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 N0HE 10/30/82 Changes in Potential Considerations Hazards Due to Transportation.
III-7.B Design Codos, 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 Actuacion System HONE 01/31/82 II-3.B Flooding Potential and 12/14/81R R+45 Protection Requirements VI-7.C.3 The Effect on PWR Loop N0HE 12/14/81C Isolation Valve Closure II-3.B.1 Capability of Operating 12/14/81R R+45 During a LOCA on ECCS Plant to Cope with Design Performance Basis Flooding Conditions VI-10.A Testing of Reactor Trip 08/31/81 R+30 II-3.C Safety-related Water Supply 12/14/81R R+45 System and Engineered (Ultimate Heat Sink (UHS))
Safety Features Including Rnsponse Timo Testing II-4.B Proximity of Capable NONE 04/30/82 Tactonic Structures in VII-1.A Isolation of Reactor NONE 01/31/82 Plant Vicinity Protection System from Hon-Safety Systems, Including II-4.D Stability of Slopes 08/31/81R 02/28/82 Qualifications of Isolation Devices II-4.F Settlement of Foundation's 12/18/81R 02/28/82 VII-2 Engineered Safety Features HONE 01/31/82 and Buried Equipment (ESF) System Control Logic and Design III-3.A Effects of High Water 08/31/81R 01/25/82 Level on Structures VII-6 Frcquency Decay H0HE 08/28/81C III-3.B Structural and Other NOHE 01/31/82 VIII-4 Electrical Penetrations HONE 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 R+30 Underdrain Systems Water Systems (3-26)
HADDAM NECK Q1 (cont.)
Q11 (Cont.)
SAR l/
SER 2/
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE III-3.C Inservice Inspections of 08 / 31/81 R 02/28/82 VI-6 Containment Leak Testing NONE 11/30/81 Water Centrol 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 (SYS)
Injection to Recirculation III-4.D Site Prcximity Missiles 06/25/81R 04/30/82 Modo (Automatic ECCS (Including Aircraft)
Realignment)
III-7.D Containment Structural 04/27/81R 10/16/31C VIII-1.A Potential Equipment NONE 03/31/82 Integrity Tests Failures Associated with a Degraded Grid Voltage V-1 Compliance with Codes and NDHE 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 Boron Addition Systems 10/02/81R 04/01/82 Accident Chemistry XI-1 Appendix I(MP A-02)
NONE DELETED IX-6 Fire Protection (MP B-02)
NONE 07/01/82 XI-2 Radiological (Effluent NONE DELETED and Process) Monitoring Q11 Systems (NRR B-67)
'SAR 1/
SER 2/
TOPIC HO. TITLE SCHEDULE SCHEDULE XV-1 Decrease in Feedwater 09/30/81R 04/09/82 Temperatures, Increase in Ill-4.A Tornado Missiles 08 / 31/ 81 R 11/30/81 Feedwater Flow, Increase in Steam Flow and Inadvertent III-4.C Internaly Generating 09/30/t1 R+30 Opening of a Steam Genera-Missiles 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 Singlo Failures Turbine Trip, Loss of Condenser vacuum, Closure V-7 Reactor Coolant Pump NONE 11/05/81C of Main Stocm Isolation Overspeed(NRR B-68)
Valve (BWR), and Steam Pressure Regulator Failure VI-2.D Mass and Energy L_:se for NDHE 01/22/82 (Closed)
Possible Pipe Break Inside Containment XV-4 Loss of Non-Emergency A-C 09/30/81R 12/17/81C Power to the Station VI-3 Containment Pressure and NONE 01/22/82 Auxiliaries Heat Removal 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)
HADDAM NECK REI (Cont.)
011 (cont.)
SAR l/
SER 2/
SAR l/
SER 2/
TOPIC HO. 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 11/10/81C Breaks Inside and Outside Resulting from Spectrum of Containment (PWR)
Postulated Piping Breaks Within the Reactor Coolant XV-7 Reactor Coolant Pump Rotor 09/30/81R 11/15/82 Pressure Boundary (SYS)
Seizure and Reactor Coolsnt (DOSES) 09/30/81R
.R+30 Pump Shaft Break XV-8 Control Rnd Misoperation 09/30/81R 11/15/81 1/ SAR : Licensee Safety Analysis Report-Scheduled or Actual (System Malfunction or (Actual (Status 4b) when date is followed by R)
Operator Error) 2/ SER Staff Safety Evaluation Report -Scheduled or Actual XV-9 Startup or an Inactive 09/30/81R 04/01/82 (Actual (status 4a, 5, 7 ) when date is followed by C)
Loop or Rocirculation Loop at an Incorrect l/ Desiginated number of days from receipt of licensee SAR Temperature, and Flow (Note: if Licensee SAR is received then date is from Controllor Malfunction receipt of additional information requested)
Causing an Increase in BWR Coro FJow Rato XV-10 Chemical and Volume Control 09/30/81R 04/01/82 System Malfunction that Rnsults in a Decrease in in Boron Concentration in the Reactor Coolant ( P1JR )
XV-12 Spectrum of Rod Ejection 09/30/81R 11/15/81 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 Prossurizer Safety-Relief Valvo or a BWR Safoty/Rolief Valve XV-16 Radiological Consecuences NONE 09/28/81C of railure of Small Lines Carrying Primary Coolant Outside Containment XV-17 Stec.n Generator (SYS) 09/30/81 04/30/82 Tube failure (PWR) (DOSES) 09/30/81 R+30 (3-28)
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t TOPIC HO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE y
III-l Classification of Struct-NONE 04/16/82 IX-5 Ventilation Systems 01/30/81 R+30 ures, Components and Sys-tems (Saismic and Quality)
~'
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III-2 Wind and Tornado loadings 01/15i82 R+60 1/
.SAR 1/
SER 2/
'; T s r TOPIC NO. TITLE-
,SCHEDGLE SCHEDULE III-5.A Effects of Pipe Break on 10/30/81 08/10/82 Il-1.A Exclusion Area Authority
' 02/15/82 36/30/82 v s Structures, Systems and Components Inside and Control Containment
/
.d5/01/31R 06/30/82 II-1.3 Pipulati6n Distrubutiod 4
III-5.B Pipe Break Outside 10/30/81 07/16/82
.'; i-Containment II-1.C Potential Ha:ards or 04/09/81R 66/30/fe L
Changes in Potential III-6 Seismic Design NDHE 07/31/82 Hazards Due to-IN Considerations Transportation.
/
Institutional Industrial.
III-7.B Design Codes, Design NDHE 08/31/82 and Military Facilities Criteria, Load Combinations, and Reactor II-3.C Safety-related Water NONE' 02/28/82 Cavity Design Criteria supply (Ultimate Heat Sink (UHS)
V-11.8 RHR Intorlock Requirements H0HE 02/28/82 (ELEC)
II-4.B Proximity of Capable NONE 06/30/82 Tectonic Structur6s in VI-7.A.3 ECCS Actuation System 06/30/81R 02/28/82 Plant Vicinity (B-46)
VI-10.A Testing of Reactor Trip 06/30/81R 02/28/827 II-4.D Stability of Slopes 02/15/82 R+30 System and Engineered-Safety Features Including II-4.E Dam Integrity H0HE 02/28/82 Safety Features Including Response Time Testing II-4.F Settlement of Foundations 08/31/81R 02/28/82 and Buried Equipment VII-1.A Isoaltion of Reactor HDHE 10/05/81C Protection System from III-3.A Effects of High Water 02/15/82 R+30 l
Han-Safety Systems, Level on Structures Including Qualifications of Isolation Devices III-3.C Inservice Inspection of 12/31/81 02/28/82 Water Control Structures VII-2 Engineered Safety Features HOME 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 02/28/82 (Including Aircraft)
(ELEC)
Shutdown III-7.D Containment Structural 02/15/82 R+30 VII-6 Frequency Decay NONE 08/28/81C Integrity Tests VIII-4 Flectrical Penetrations of H0HE 02/28/82 V-1 Compliance with Codos HONE DELETED Reactor Containment and Standards (10 CFR 50.55a)(MP A-01,A-14)
IX-3 Station Service and Cooling 09/17/81R 11/30/81 Water Systems (3-30)
YANKEE R0WE DL (Cont.)
D11 (Cont.)
SAR 1/
SER g/
SAR 1/
SER 1/
TCPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE vi-1 Organic Materials and 02/15/82 R+30 IX-1 Fuel Storage 12/31/81 R+30 Post Accident chemistry IX-4 Boron Addition System 08/31/8tR 05/07/82 IX-6 Fire Protnetion(MP B-02)
NONE 01/15/82 XI-1 Appendix I(MP A-02)
NONE DELETED D}1 XI-2 Radiological (Effluent NDHE DELETED SAR 1/
SER 2/
and Process) Monitoring TOPIC NO. TITLE SCHEDULE SCHEDULE Systems (NRR B-67)
Il-2.C Atmosphersc Transport and 06/30/81R 09/04/81C XV-1 Decrease in Feedwater 12/31/81 06/30/82 Diffusion Characteristics Temperature, Increase in for Accident Analysis Feodsater Flow, Increase in Steam Flow and III-4.A Tornado Missiles 01/15/82 R+30 Inadvertent Opening of a Stoam Generator Relief III-4.C Internally Generated 02/15/82 R+30 or Safety Valve Missilas XV-2 Spectrum of Steam System 06/30/81R 05/21/82 III-8.A Looso Parts Monitoring NONE 12/07/81C (SYS)
Piping Failures Inside and Coro Larrel Vibratior.
(DOSES) and Outside of Containment 09/30/81 R+30 Monitorinq(HRR 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 01/08/82 Including Functior.al 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 H0HE Pressure Regulator Failure Overspnod(NRR B-68)
(Closed)
VI-2.D Mass and Energy Roloaso NGHE 01/22/82 XV-4 Loss of Noa-Emergency A-C 12/31/81 06/01/82 for Possible Pipo Ercak Power to the Station Inside Containment Auxiliaries VI-3 Containment Pressure and NONE 01/22/82 XV-5 Loss of Normal Feodwater 06/30/81R 02/05/82 Hoat Removal Capability Flow VI-4 Containment Isolation NONE 04/01/82 XV-6 Fcedwater System Pipe 12/31/81 06/16/82 (SYS)
System Breaks Inside and Outside Containment (PWR)
VI-6 Containment Leak Testing NONE 03/30/82 (ftP A-04)
XV-7 Reactor Coolant Pump Rotor 06/30/81R 12/31/81 Seizure and Reactor Coolant VI-7.B ESF Switchover from NONE 06/11/82 Pump Shaft Break (SYS)
Injection to Rocirculation Mode (Autenatic ECCS XV-3 Control Rod Misoperation 12/31/81 R+30 Realignment)
(System Malfunction cr Operator Error)
VIII-1.A Potential Equipment NONE 03/31/82 Failurcs Associated with a Dooraded Grid Voltage (MP B-23) i (3-31)
YANKEE R0WE Dil (Cont.)
SAR 1/
SER 2/
TOPIC HD. TITLE SCHEDULE SCHEDULE XV-9 Startup or an Inactive 06/30/81R 06/15/8.I Loop or Recirculation Loop at an Incorrect Temperature, and Flow Controller Malfunction Causing an Increase in BWR Core Flow Rate XV-10 Chemical and Volume Control 06/30/81R 03/01/82 System Malfunction that Results in a Cecrease in the Baron Concentration in the Reactor Coolant (PWR)
XV-12 Spectrum of Rod Ejection 06/30/81R R+30 (SYS)
Accidents (FWR)
(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 BUR Savety/ Relief Valve XV-16 Radiological Consequences 12/31/81 R+30 of Failure of Small Lines Carrying Primary Coolant Outside Containment XV-17 Steam Generator Tube 12/31/81 06/30/82 (SYS)
Failure (PWR)
(DOSES) 12/31/81 R+30 XV-19 Loss-of-Coolant Accidents 09/30/81 06/30/82 (SYS)
Resulting from Spectrum of (DOSES)
Postulated Piping Breaks 09/30/81 R+30 Within the Reactor Coolant Pressur e Boundary 1/ SAR = Licensee Safety Analysis Report-Scheduled or Actual (Actual (Status 4b) when date is followed by R) 2/ SER = Staff Safety Evaluation Report -Scheduled or Actual (Actual (status Aa, 5, 7) when date is followod 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)
(5-32)
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SER 2/
SAR 1/
SER 2/
4 TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC HO. TITLE SCHEDUEE SCHEDULE III-1 Classification of NONE 05/14/82 II-1.A Execlusion Area Authority 06/22/81R 07/31/82 (SYS)
Structures. Components and and Control Systnms (Seismic and Quality)
II-1.B Population Distribution 06/16/81R 07/31/82 III-2 Wind and Tornado Loadings 08/C6/81R 02/28/82 II-1.C Potential Hazards or 07/15/81R 87/31/82 Changes in Potential III-5.A Effects of Pipe Break on 11/02/81 09/30/82 Harards Due to 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 Containment II-3.B Flooding Potential and 09/01/81 R+45 III-6 Seismic Design NONE 11/30/82 Protection Requirements Considerations II-3.B.1 Capability of Operating 09/01/81 R+45 III-7.B Design Codes. Design NONE 11/30/82 Plant to Cope with Design Criteria, Load Basis Flooding Conditions Combinations, and Reactor Cavity Design Criteria II-3.C Safety-related Water Supply 06/26/81R R+45 (Ultimate Heat Sink (UHS))
V-11.B RHR Interlock Requirements NONE R+30 (ELEC)
II-4.B Proximity of Capable NOME 07/31/82 Tectonic Structures in VI-7.A.3 ECCS Actuation System NONE 11/30/81 Plant Vicinity VI-10.A Testing of Reactor Trip 06/25/81R 02/28/82 II-4.D
' Stability of Slopes NONE R+30 System and Engineered Safety Features Including II-4.E Dam Integrity NONE R+30 l
Resoonse Time Testing I
II-4.F Settlement of Foundations 12/31/81 02/28/82 I
VII-1.A Isolation of Reactor NONE 11/30/81 and Buried Equipment Protection System from Hon-Safety Systems.
III-3.A Effects of High Water Level 12/31/81 R+30 Including Qualifications of on Structures Isolation Devices III-3.C Inservice Inspection of 12/31/81 R+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 09/15/81k 07/31/82 (ELEC)
Shutdown (Including Aircrafts)
VII-6 Frequency Decay NONE 09/21/81C III-7.D Containment Structural 06/29/81R O2/01/82 Integrity Tests IX-3 Station Service and Cooling 11/02/81 R+30 Water Systems V-1 Compliance with Codes and NOME DELETED Standards (10 CFR 50.55a)
IX-5 Ventilation Systems 11/02/81 R+30 (MP A-01.A-14)
(3-34) l
LACROSSE 21 (Cont.)
211 (Cont.)
SAR 1/
SER 2/
SAR 1/
SER Z/
TOPIC HO. TITLE SCHEDULE SCHEDULE TOPIC HO. TITLE SCHEDULE SCHEDULE VI-1 Organic Materials and Post 12/31/81 R+30 XI-2 Radiological (Effluent and NCHE DELETED Accident Chemistry Process) Monitoring Systems (NRR B-67)
IX-6 Fire Protection (MP B-02)
N D:4 E 10/30/82 XV-1 Decrease in Fcedwater 03/21/81 07/31/82 Temperature. Increase in Dil Feedwater Flow. Increase SAR 1/
SER 2/
in Stoan Generator Relief TOPIC NO. TITLE SCHEDULE SCHEDULE or Safety Valve 11-2.C Atmospheric Transport and 10/01/81 R+30 XV-3 Loss of External Load.
06/26/81R 11/13/81C Diffusion Characteristics Turbine Trip. Loss of Con-for Accident Analysi s denser Vacuum, Closure of Main Steam isolation Valve III-4.A Tornado f1issiles 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 Moniroring and NONE 07/30/82 Power to the Station Core Barrel Vibration Auxiliaries Monitoring (NRR B-60.C-12)
XV-5 Loss of Normal Feedwater 08/21/81 07/31/82 IV '2 Reactivity Control Systems NONE 12/10/81C Flew Including functional Design and Protcetion Against XV-7 Roactor Coolant Pump Rotor 08/21/81 07/31/82 Single Failures Seizuro and Reactor Coolant Pump Shaft Break VI-2.D Mass and Enoray Release for HDHE 01/22/82 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 HONE 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 H0HE 05/03/81 Incorrect Temperature, and (SYS)
System Flow Controller Malfunction Causing an Increase in EWR VI-6 Containment Leak Testing NDHE 11/30/81 Core Flou Rate (MP A-04)
XV-11 Inadvertment Loading and 12/31/81 R+30 VIII-1.A A.
Polantial Equipment NDHE 03/31/81 Operation of a Fuol Failures Associated with a Assembly in an Improper Degraded Grid Voltage Po si t i on (MP B-23)
XV-13 Spectrum of Rod Drop 12/31/81 R+30 IX-1 Fuel Storage 11/02/81 R430 (SYS)
Accidents (BWR)
(DOSES) 12/31/81 R+30 XI-1 Appendix I(MP A-02)
NONE DELETED (3-35)
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TOPIC NO. TITLE SCHEDULE SCHECULE XV-14 Inadvertent Operation of 08/25/81R 06/01/82 ECCS and Chemical and Volume Control System Malfunction that Increases Reactor Coolant Inventory XV-15 Inadvertent Opening of a 06/30/81R 0 9/21/81C PWR Pressuring Safety-Relief Valve or a BJR Safety / Relief Valve XV-16 Radiological Consequences 08/21/81 R+30 of Failure of Small Lines Carrying Primary Coolant Outside Containment L
XV-18 Radiological Consequonces 11/02/81 R+30 of Main Steam 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 Pressuro Boundary I
XV-20 Radiological Consequences 11/02/81 R+30 of Fuel Damaging Accidents (Inside and Outside Containment)
J/ SAR : Licensee Safety Analysis Report-Scheduled or Actual (Actual (Status 4b) when date is followed by R) 2/ SER : Staff Safety Evaluation Report -Scheduled or Actual (Actual (status 4a. 5, 7) when date is followed by C) 1/ Desiginated numbe~ of days from receipt of Ilcensee SAR (Hotor if Licent e SAR is received then date is from receipt of additional information requested) t (3-36)
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u s. wuCLEAn tsoutATonY commission BIBLIOGRAPHIC DATA SHEET NUREG-0485 Vol. 3 No. 14 4 TITLE AND SUSTITLE (Add vo4w Na,,rapprapneep 2.(tesy,are as Systematic Evaluation Program Status Summary Report 3 RECIPIENT 15 ACCESSION NO.
- 7. AUTHOR 15)
- 5. DATE REPORT COMPLETED M ON TH lvtAm January 1982
- 9. PERFORMING ORGANIZATION N AME AND MAILING ADDRESS (tactuar les Codel DATE REPORT ISSUED Office of Management and Program Analysis wonta lveAn Office of Nuclear Reactor Regulation January 1982 d.S. Nuclear Regulatory Consnission 6- (Le. e u.ans Washington, D.C.
20555
- 8. (Leave Omkl
- 12. SPONSORING ORG ANIZATION NAME AND MAILING ADDRESS (Inctuar I,a Code /
p Office of Management and Program Analysis Office of Nuclear Reactor Regulation
- 11. CONTRACT NO U.S. Nuclear Regulatory Comission Washington, D.C.
20555
- 13. TYPE OF REPORT PE mioD covt ago (lactus,ve dams /
December 1 - 31, 1981
- 15. SUPPLEMENTARY NOTES 14 (Leave we41
- 16. A8STR ACT 200 svoras'or less1 The Systematic Evaluation Program is intended to examine many safety related aspects of eleven of the older light water reactors. This document provides the existing status of the review process including individual topic and overall completion status.
l l
- 17. KE Y WORDS AND DOCUMENT AN ALYSis 17a DESCRIPTORS 17b. IDENTIFIE RSIOPEN ENDE D TERMS 1
- 21. NO OF PAGE S j
Unlimited 20 SECURITY CLASS (Thes papel 22 PRICE Unclassified s
NRC FonM 335 (7-77)
A U.S. GOVERNMENT PRINTING OFFICE: 1982 361-302/503
l UNITED STATES NUCLEA2 CSCULAT3QY COMMitalON I
l WASHIN370N. O. C. 20855 PosTACC an@ rc::s FAno U.S. NUCLE AR REGULATOR Y OPPICIAL SUSINESS couwesslON FEN ALTY FOR PRIVATE USE.8300 L
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