ML20065D301
| ML20065D301 | |
| Person / Time | |
|---|---|
| Issue date: | 09/30/1982 |
| From: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| To: | |
| References | |
| NUREG-0485, NUREG-0485-V04-N08, NUREG-485, NUREG-485-V4-N8, NUDOCS 8209280337 | |
| Download: ML20065D301 (95) | |
Text
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Vol. 4, No. 8 l
g August 31,1982
- I !E i
lE l SYSTEMATIC EVALUATION PROGRAM i.
l STATUS
SUMMARY
REPORT i
UNITED STATES NUCLEAR REGULATORY COMMISSION l
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l Available from
- NRC/GPO Sales Program i
Superintendent of Documents
' Government Printing Office -
Washington, D. C. 20402 i
A year's subscription consists of 12 issues for this publication.
a Single copies of this publication are available from National Technical information Service, Springfield, VA 22161 '
E Microfiche of single copies are available from NRC/GPO Sales Program s
Washington, D. C. 20555 d
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.I i
NUREG-0485 Vol. 4, No. 8 August 31,1982 SYSTEMATIC EVALUATION PROGRAM STATUS
SUMMARY
REPORT Prepared for: 0FFICE OF NUCLEAR REACTOR REGULATION Prepared By: OFFICE OF RESOURCE MANAGEMENT UNITED STATES NUCLEAR REGULATORY COMP'a" e..n p
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TABLE OF CONTENTS SECTION I SECTION 11 SECTION 111 1
SEP TOPIC LIST 1-2 to 1-3 BIG ROCK POINT 2-2 to 2-5 PALISADES 3-2 to 3-3 DRESDEN 1 2-6 GINNA 3-4 to 3-5 DESIGN BASIS EVENT 14 DRESDEN 2 2-7 to 2-10 DRESDEN 2 3-6 to 3-9 GROUP DESCRIPTION GINNA 2-11 to 2-14 OYSTER CREEK 3-10 to 3-12 DEFINITIONS OF STATUS 1-5 HADDAM NECK 2-15 to 2-18 MILLSTONE 1 3-13 to 3-16 LACROSSE 2-19 to 2-22 SAN ONOFRE 3-17 to 3-20 I
SEP TOPIC
SUMMARY
1-6 MILLSTONE 1 2-23 to 2-26 BIG ROCK POINT 3-21 to 3-24 STATUS REPORT OYSTER CREEK 2-27 to 2-30 HMDDAM NECK 3-25 to 3-28 PALISADES 2-31 to 2-54 PROGRESS TOWARD 17 YANKEE 3-29 to 3-32 l
COMPLETION (Graph)
SAN ONOFRE 2-35 to 2-38 LACROSSE 3-33 to 3-36 INTEGRATED PLANT l-8
)
SAFETY ASSESSMENT SCHEDULE SEP TOPIC STATUS BY 1-9 REVIEW DIVISION (Summary Table)
SEP TOPIC STATUS BY 1-10 to 1-11 REVIEW DIVISION (Graphs)
SEP TOPlc SUBMITTALS 1-12 thru 1-13 l
BY LICENSEES (Graphs) l
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l
SYSTEMATIC EVALUATION PROGRAM TOPIC LIST 4
T9 K e f i tt i TNic p lifit IUPIC #
YlIL E, IV-2 Weactivity Control Systens including f unctional 11 5 A. t ac lup en Area Aut%rity and '.*t rO ggg-4 g y *'*d d0 " ' 5 5 ' I'5 oesten and Protectton Against 5* agte f at tures
- 9. Poru l at ion D istri but ">n
,lV.3 Bd Jet Pugs Operating Indications
. P ot ent i a l H az ards or ( na nge s n e P ot ent i a l
- 8. Turt e ne wissiles V-1 CogItance with Codes and Standards (10 CFR wazaris Le to Tran4 ort et toa. I ns t it u t ional 50.554)
Indust r' el, and Military f acilit ies ggi.4 C. Internally Generated Missiles 11-?
A. Severe seattier Pneaor ena V-2 Applicable Code Cases
- B. Onsite m teorological measure =nts Program V-3 Overpressurtaatton Protection e
C. Ats=2s;:neric Transport and Dif f ston Charac-V-4 Ptatng and Saf e End integrity teristics f or Actirient Analy s's D. Site Prostetty missiles (Including Atrcraf t)
V-5 Reactor Coolant Pressure Soundary (RCF8)
' D.
Availability of Meter,roloqual Data in the g g [.5 A. Ef fects of P tpe Breat on Structures. Systens Leakage. Detection Control Room and Cotonents inside Containment V-6 Reactor Vessel Integrity
! !.1
. Hydrologic Description g, p,pe Sreat outside Contatnpent V-7 Reactor Coolant Punq) O verspeed
{
I t il-6 Seis4ic Design tonsiderations V-8, Steam Generator (SG) Integrtty
- 8. f looding Potential and Protection Req. ire-seat s V-9 Reactor Core Isolation Cooltng System (82)
!!!-7 A. Inservice inspection. Including Prestressed
- i. Ca& ability of Operating Plant to Cope Concrete Containcepts with Lither t. routed I* l u.
A. owe Heat f achanger Tube Fallures A
estn Design 84Us Ilooding Condit to s or Utigrouted lendons n
L. hatety-related unter Supply lultiawte " eat
- 8. Design Codes, Cesign Criteria. Load
- 8. RHR Reliability W* M ll Continations, and Reactor Cavity Destyi N1 A. ReqMaents M 15clation M Hgh and Low Criteria
!!.4
'.cology anc Seisem, logy Pressure Systems C. Delamination of Prestressed Concrete Con-
- . Tect onic Province tainnent Structures
- 8. RHR Interlock Requirements
- 8. P rosiett, of Capable Tectonic ' truttures tJ. Contain-nt 5tructural integrity Tests V.12 A. We er P t of 80tling Water Reactor in Plant Victnity Ill 8 A. L ose Parts Monttoring and Core Barrel v,y3, Water Hampier L. *isst or ual Seiwn it y wit r m M Miles of vibration Monttoring Plant
- 8. Control Rod Dre ve Mechanism integrity V!-1 Organte Materials and Post Accident C hemist ry St abilit y of S tos+s C. Irrettiation Damage. Use of Senstt taed s.
5tainless Steel and F attgJe Reststance II*2 A. Pressure-Suppression Type BWR Containments L. Das Integrity
' 8. Subcogartment Analysis
, O. Core Superts and f uel Integrity F. Settleau nt of Iou dations and Buried C. Ice Condenser Contatnnent n
i E qu u. cot til-9,
bpport Ititerty D. Mass and Energy Release for Posstble Pipe
!!!-10 A, Thersel-Overload Protect 6on f or Motors of Sreak inside Contain=nt III.I t iessif icat ion of st rutores, les <w-ats and Motor-operated Valves 1, *.t ens U.r e sen t avt hality) e t en el Int tgrity VI.3 Containpent Pressure and Heat Resoval
- 8. P ues i
111-2 mmd aed Tornado L aediac Capabil6ty
!!!-3 A. Effects of Higt i.eter t evel tin Structu pg 1 t er Pg"t,s and Discher p Valves V I. 4 (UHtainment isolation Systes r
111 1l'
- o%onent l at egr it y VI.5 Coseustible Gas Control B. St rutural and other Consequences (e.9 VI-6 Containaent Leak Testeng i luoding of Saf et y4 elated 199 :s+ent se Base"a at s) of f ailure of underdrain Syo can
!!l 12 l* st ronent.1 Qualif icat nna of Saf ety Related t goi,wnt
(. leservice Inspect ion of Wat er Cont r91 5t ruc.
IV.I P..~ e s t i e w it h L c's Than All Coops In-Service t u res
___._ an 1-2
SYSTEMATIC EVALUATION PROGRAM TOPIC LIST TCPIC a TITL E TuPIC #
_T I TL__E_
TOPIC #
_T I_Tt t v i-1. A I, ECC5 Re-evaluet ton to Account f' reased y g g.s[
f nstruinents f or Monttortnq Radiation and Process X V-5 Loss of Normal Fee &ater Flow Wessel head lect erature Variables During Accidents
- 2. Upper Plenum inject ma XV-6 Fee &ater System Pipe Breaks inside and Outside Vll-6 Frequency Decay Containment (PWR)
- 3. ECCS Actuation System Vll-?
Acceptabiltty of Swing Bus Design on 8d-4 g y. y peactor Coolant Pug Rotor Setture and Plant 5
- 4. Core $rray norile E f fectiveness Reactor Coolant Pug Shaf t Break
)
Vill-1 A. Potential tquipment f ailures Associated with IV-8 Control Rod Mtsoperation (System Malfunction V; 1.8 f sF switchwer f rom Injection to accerculat von a L,egraded Grid Voltage i* ode (Autorutic [CC5 Realignent) or Operator E rror) v!!I-2 Onstte Emergency Power Systems - Diesel X V-9 Startup or an inactive Loop or Rectreulation W 1-7.0 t CC5 Single Fat N~. -f erson and Wequire-Generator ment s f or t oce *ng o
=*r t o Val ves Loop at an Incorrect Temerature, and Flow i nc ludi ng i ndet en% -
- Interlock s on Vlll-3 A Station Battery Capacity Test Requirements Controller Malfunction Causing an Increase in (CC5 Val es BW Core Flow Rate
- 8. DC Power System Bus Voltage Monitoring and XV-10 Chemical and volume Control System Malfunction I. Appendis t - [lectrical instrumentation f nnu nci at ion that Results in a Decrease in the Boron Concen-and Control (TIC) Re-reviews
- *"'"
- h* * # 8" M Vl!!-4 Electrical Penetrations of Reactor Contatnpent
- 2. Failure Mude Analys ts - (CC5 y
y g,.
Assenely in an Igroper Position
- 3. The E f f ect of Pd t oop 1 solation valve Closure During a LOCA on iCCS Perf ornience X V-12 Spectrum of Rod Ejection Accidents (PW) e IX-2 Overheed Handitng Systems - Cranes 81-1.0 tong Term Cooling - Passive F ailures (e.g.,
F looding of Redundar.t Co@onents)
IX-3 Station Service and Cooling Water Systems XV-13 Spectrum of Rod Drop Accidents (88)
- IV-14 Inadve t Oper t f(
a hem 81 1.f ECC5 Sum Destqn and Test for Rectreviation 11-4 Baron Addition System IX-5 Vent t lat ton Systems increasn Reactw CMant lawnton 1
1.F Accushletor Isolation Valves Power and Control
System Design
II-6 Fire Protection XV-15 Inadvertert Opening of a PW Pressuriser Safety-Rettd Valw w a 82 5det@Hd Valw v:-8 Cor trol Room Habitability I
Austitary Feehater System XV-16 Radiolog1 Cal Consequences of Failure of Small W!-9 Patn 5 team t tne Isolat ton Seal System - Bd 11-1 A pendia I nn a g
man ant S
44 P
ment VI-10 A. Test)ng of Reactor T rip System and E ngineered g g.2 Safety f eatures including Response f ame Rad.iologiCal (Ef fluent and Process) Monitortng XV-ly 5 team Generator 3,s. ems Testt49 fube Fath (PA)
If!!-1 Conduct of Operat uns XV-18 Radiological Consequences of Main Steam b ihared E ngineered Saf ety F eatures. On-s ite Line Fatlure Outside Cortainment (88)
[mergency Pwer, and Service Systems f or Ill!-2 Saf ewards/ indust rtal Security Mult iple Unit Iacilities XV-19 Loss-of-Coclant Accidents Resulting f rom IV-l Decrease in f ee4 ater legerature, lacrease in Spectrum of Postulated Ptptng Breaks Within l eedwater F law, increase in Steam Flow and the Reactor Coolant Pressure 80undary on afe V SFs I nc n9 va at ons of Isolat ton Devices Inadvertent opening of a 5 team Generator actief o, >af ety Valve XV-20 Radiological Consequences d Fuel Damsgtag Accidents (laside and Outside Conta1nment)
B. Trip Uncertainty and Setpo6nt Analysts Review Xb-2 rc t rum of Steam System Diving Failures inside of Operating Data Base
,ad outside of Coctainas.nt (Pw)
X V-21 Spent Fuel Cask Drop Accidents VII-2 E ngineered Safety Features (EST) System Control X V-3 t uss of E xternal Load. Turbine Trip, toss of IV-22 Anticipate Transients Without Scram t oglC and Design Condenser vacuuie Closure of Main Steam Isota-XV-23 Multiple Tube Failures in 5 team Generators vi t-3 Systems Required f or 5af e Shutdown t ton Valve (8d), and 5 team Pressure Regulator g es tor, (Ciog,4) e XV-24 Loss of All A-C Power X V-4 to f
-tmergency A-C Power to the St ation VII-a I f f ect s of F ailure in non-Saf et y Related XVI TechntW SWfWth wstem nn selected inqineered saf ety f eatures XVII Operattonal QA Program l
- Topic deleted feom SEP program due to duplication.by Three Mile Island (TMI) NRC Action Plan, Unresolved Safety issue or other SEP Topic per May 7,1581 letter from G. Lainas to all SEP L_
1-3
i DESIGN BAS S EVENT REVIEWS i.
l THIS SECTION DEFINES DESIGN BASIS EVENT (DBE) REVIEWS FOR THE ELEVEN SEP FACILITIES 1
e f
'l N-81: L i$'
le3 OE E 'Or". M Bm8 % P'# D%]ppjG.,_1j$.,T f
J_r aaj ' ert. Grcq Acc idert and Trarsytet Group t
Ob f '7 R
' %I
.El 731f TITLI it i1%E 1
6r04 1 E h-i Decrease in feedwater targeratu e I g,CS r
j j
' Pe(,
t i. t j ac re ag g in f eco, a ter f i on, t v-l lecrease te steam fl h 1:.34 kvarologic description 1 a 2_
It l increase ia fee'2 mater flow
- C 0
4
-4 so-l Decrease te f e*1=st er terTerat.re 1].3 p f looding potential and pre te(Iton l
I-Int resse Stear 'l om 34-9
$ tart-ce Gf leactSee loo? and flow requirewnts (capability of opera ting to-Ina3.erteet occet eg o' stea-cGrtroller salf a etton pleet to cope with desige b405 f 1004169 n
Inca.e teat closure of matn ster-condition )
f gercrator relie*/ safety vaive as-3 r
I Ff Star!. of tas' tl ee loc:
1%Clat'cn talve s i-3 (
$afety related wate' Swfply (i.Itteate heat sink) 8-Sy s t e" "'al ' N t io" Ca i t ne
]
a tine trip g i s*'..
.1 -a. A Tectonic prow've j
le-m,
- estereal ica!
3*-2 T
r i
fa-
",.i t or t r ;'
- 3. - l Lo% cf C Dndee.S ee secas
![.a S Prostrity of capable tecteatc Structures e
f ailw e peer plant
$1es",prens e reg lator e
I 88
63% o' coade*ser wat e R e-A Lots tf fee % ster flom
!!.4 f.
eentorical seismicity atthin 200 miles f a t ?.re h'
l 1e.
.tes cren u e regeisto r
r cf plant 8-
.On L'
f eeJ=6 3 tee f l o=
e eiadtoi qical Ccase%e9Ces cf a ti -
Statility of SloDei
]
d e -f Feedo t'e' s y g tes" ; 1 ;. g treat Grq s,.
t o
Main $ tear Lire Failu e Owt5 tde r
a a
3*-
ates" lief t ream r> *e c or ta eg ge l (ce ta irwic e t er,g(( 6[y,iseT J(;g { } }..
Tornado etSlile5 Bu'
$
- ee" l ' 'e P re s a hil1 Gr t oet a ' nreet a,% pi,(it[(T ZPi
!!! a :
Turbtae miniles 4.r s,{ j_,
t.4 60 0 t AC Dower to Statica
!!!-a (
IPternally t2eersted pittiles 3
3e a LMs o' AC C wer te S t a t t oa ava t l t arl es
[ l g.a,0
$9te prostetty eigg11eg ( ccluding
]
aircref t) t a.. ' D a' m j
bry a 3.-
Lon of forced coola'it flom i ;,7 tot nd and toreado load **9 4
Lot (f fort e ! (c Maat f M.
1..'
Pe t w eep pwi'tg rctGr 5e'Igre Pr ~- s*y pa g rctcr settu e E.'
Cr1 mary pu' C st'af t brtak r
r se 3
P, t t.ar, pung 19 48t *.>re a6 firo.L b.
a b-e Uncoetrol'ed rod anest!y ottedramal at DC=fr
..e t ec 'It a rod as sert,.
4 er a.a t a t p:,.ee u.-
Uncc-trellec ec3 aucet 1,r withdre a' ve:oe trolled rod due.el y aita.
lo= pe.ee start-up 5
d*aw a l 19. pwer starts It-L Corleol rod einoperation Cce% ' rod e nope ra t ue n-13
$recter of rod deep ate tsents
$;.r te r c' roc efec tion acc'deat
.rowp y as-li 5:n er of leu c' coviaat ecc tdeats l
See;tre of lou of c ool ar t ac c t acr t t
GrN; ' ' 'bl' e..'
Rao:lcreal Comet.,eates c' Fuel j
em i
8.-4 Deo d op ca' C oa.easenc es e* F e' La*a-ing Acc iJeats (195 $+ aad o
l Lar a ;1 a; Amderts (ins tae av ou ts 'ae c ortriere outs : se c.ar.tairre atl s..
- a;.ertert oper ' cf 6w* safety Gry. l 3.-
. aherteat erecia; cf Pn:
rehe f valve 4
remr uer reli,*.al.e
- . +
s.-.
Iraser.et cperatior c' f;3 o*
ts
- E Nu tic.c test c a,ses a, Gec 4 :
a,
'. ac.er tea + load'ng and operation e' a 'wel assent ly *r a* imrroer in rease sa (no'a t Sc.eet er y D05111 Dr l
at :licaD e to PwL3 i
ey 4 ht 4
d
' awy nj _1
%M a;Gl ttat le 'O $md5 Gre a
8
- >"er a tor 'st'e f a t lure 1-4 1
4
G - Gsneric 4a-Draft SE Rsceivsd From Review Branch These topics are being evaluated as part of on-l 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 ef fectiveness a draft topic safety evaluation is under mange-and efficiency of these efforts and to minimize ment review.
any impact on licensees. The status and conclu-sions of generic SEP topics will be incorporated in the final safety. assessment for each plant.
4b - SAR Received from Licensee Licensse has submitted a Safety Analysis Report X - Deleted (SAR)in accordance with SEP redirection. (See Eisenhut letter to SEP owners of January 14,1981)
These topics have been verified as not applicable The SAR is under review and a Final NRC safety to the design of a specific plant or ar being evaluation (status 7)is being prepared. Draf t SE duplicated by the NRC TM1 Action Plan, will not be issued for topics with licensee SAR submittal.
Unresolved Safety issue or another SEP Topic per the May 7,1981 letter from G. Lainas to all SEP licensees.
5 - Draf t SE Sent to Utility 0 - Topic Not Started A draft topic safety evaluation has been formally transmitted to the licensee for their review and This status indicates that the review of the topic certification of the accuracy of the described has not started.
facility. Licensees may comment upon NRC conclusions or propose alternatives to NRC posi-tions.
4 1 - Questioas Received From fReview Branch 6 - SE Response Received This status is used for internal NRC trackin9 by N R C of topic review progress. The status indAares i
that all information necessary to perform a The draft SE has been reviewed and licensee f
topic evaluation is not available and that qucs-comments if any have been formally transmitted tions have been developed and sent to the SEP ta the N RC.
branch.
7 - Topic Completo 2 - Questions Sent to Utility The NRC topic evaluation has been completed and i
a final safety evaluation issued. A topic is completed
+
The questions developed in the nrevious status in several ways: (1 ) The licensee has responded have been formally transmitted 4o the licensee that the N RC draf t safety evaluation (i.e. status 5) as a request for additional information, is correct, or (2) the licensees comments on the NRC draf t safety evaluation (i.e. status 6) have been re.
3 - Question '. ponse 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 NRC' regarding the topic.
1-5
SEP TOPIC STATUS
SUMMARY
REPORT.m N
\\
NUMBER OF QUESTIONS QUESTION DRAFT SE SAR SE
\\
TOPICS TOPIC RECEIVED QUESTIONS
, RESPONSE RECEIVED RECEIVED DRAFT SE
RESPONSE
TOPIC!
A GENERIC DELETED NOT FROM SENT TO RECEIVED FROM FROM SENT TO RECEIVED
-COMPLETE N
(G)
(X)
PLANT HAME N
'-STARTED REVIEW UTILITY BY NRC REVIEW LICENSEE UTILITY BY NRC (7)
(0)
BRANCH (2)
(3)
BRANCH (4b)
(5)
(6)
N (t)
(4a)
N PALISADES 0-47 0
0 0
0 0
0 0
.0 90 GINNA 0
45 0
0 0
0 0
0 0
0-92 OYSTER CREEK 0
54'
-0 0
0 0
0 0
5-8.
78 DRESDEN 2
-0 49 0
0 0
0 0
0 5
7 76 MILLSTONE 1 0
51 0
0 0
0 1
0 6
9 70 HADDAM NECK 0
47 0
0 0
1 to 0
7 4-68 YANKEE 2
48 1
0 0
1 12 1
1 2-69 LACROSSE O
54 0
0 1
1 9
17 4
5 46 BIG ROCK POINT 2
52 1
-0 1
8 6
6 7
5 49 SAN ONOFRE 2
48 2
0 1
6 2
10 8
6 52 DRESDEN 1 TOTALS THIS MONTH 6
495 4
0 3
17 40 39 43 38 690 TOTALS LAST MONTH 10 495 7
0 3
24 31 54 81 30
'635 w NOTE: Totals do not include Dresden 1, see page'2-6. iAlso.' included is May 7, 1981 deletion letter to all SEP licensees -
see footnote page 1-3.
1-6
SYSTEMATIC EVALUATION PROGRAM GOAL P H AS E 11.'7
-1/ Not including Dresdea 1 Progress Toward Complet. ion
^CTUAL 100 %
100 7
-82 s
- ,e #
95%
9%
90 j'
92%
,a 88%
85%
80 1 m nth 3% /
83%
75 %~
79%
70%
76 %
70 67 72%
- 61
/
H
/
eNote: Prior to November 30,1981 the 2 60 60 %
,,e
'3041 weighted perce,nt did not include g
generic topics m the progress gr d
g se toward completion.
o 50 f *
(
54%
y
,/
47%
I
/
44%
2 j
y 40 42%
/
40%
s#'
36%
30
- J 30%lestimated)
The plant topic overall completion status (percent complete) is calculated Status Weighting Factor based upon the number of topic reviews to be performed (not including 20 deleted topics) and a weighted average of current topic review status.
X Not Included The calculation is performed using the following formula:
G,0 0%
4a.4b 80 %
Percent Complete = Sum of Topics in Status x Weighting Factor of Status 5,6 90 %
7 100 %
10 Sum of Topics 1
0 a
10 11 12 1
2 3
4 5
6 6
7 8
9 10 11 12 1
2 3
4 5
6 7
8 9
FY-81 FY-82 17
.=
l INTEGRATED PLANT SAFETY ASSESSMENT REPORT (IPSAR) SCHEDULE TOPIC ALL TOPIC ISSUE IPSAR IPSAR PLANT HAME TECHNICAL FOR ACRS TO EDO AND COMPLETE REVIEWS REVIEW COMMISSIDH TO DL l/
PALISADES 100 02/26/82C 04/01/82C 06/30/82 GINNA 100 02/24/82C 05/27/82C 07/30/82 4
OYSTER CREEK 99 05/31/82 09/30.'82 11/30/82 DRESDEN 2 99 06/30/82 10/29/82 12/30/82 MILLSTONE 1 98 06/30/82 11/30/82 01/31/83 YANKEE' 92 08/30/82 01/31/83 03/31/83 LACROSSE 91 09/30/82 01/31/83 03/31/83..
HADDAM DECK 95 08/31/82 02/28f83 04/29/83 BIG ROCK POINT 85 09/30/82
'04/29/83 0 6'/30.B 3 SAN ONOFRE' 86 12/30/82 1/
04/29/83 06/30/83 1/ Schedule for each topic for each plant is specified.
OVERALL COMPLETION =,95%
2/ All topics except Seismic and High Energy Line Breaks are to be completed by,09/30/82.
,_8 h
4 b
SEP TOPfC STATUS by REVIEW DIVISION
SUMMARY
TABLE PLANT PALISADES GINNA OYSTER DRESDEN MILLSTONE HADDAM YANKEE LACROSSE BIG sad TOTAL CREEK 1
1 NECK ROCK ONOFRE POINT (IAPM) J/
Michaels Wang Fell Cwalina Persinko Brown Boyle Michaels Scholl McKenna NO. OF TOPICS 137 137 137 137 137 137 137 137 ip
?37 1370 DELETED 2/
47 45 54 49 51 47 48 54 52 48 495 APPLICABLE 90 92 83 88 86 90 89 83 85 89 875 57
/
39 ~7 35
/
36
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37
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37
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37
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33
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34
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34
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379 e DL
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/
/
/
/
_f
/
/
/
/ 57
/ 39
/ 35
/ 36
/ 37
/ 38
/ 38
/ 35
/ 38
/ 40
/ 393 TECHNICAL
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20
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19
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22
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20
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20
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20
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11
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8 e
8
/
165 /
REVIEW DOE
/
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/ 17
/ 20
/ 19
/ 22
/ 20
/ 20
/ 20
/ 20
/ 17
/ 17
/ 192 ASSIGNMENT 1/
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s 16
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33
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29
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30
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29
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27
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20
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25
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26
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267 /
DSI
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/
/
/
/ 16
/ 33
/ 29
/ 30
/ 29
/ 32
/ 31
/ 28
/ 30
/ 32
/ 293
/
/
/
/
/
/
/
/
/
/
/
90
/
92
/
83
/
88
/
86
/
89
/
84
/
64
/
67
/
68
/
811 /
COMPLETE
/
/
/
/
/
/
/
/
/
/
/
/ 90
/ 92
/ 83
/ 88
/ 86
/ 90
/ 89
/ 83
/ 85
/ 89
/ 875
/
/
/
/
/
/
/
/
/
/
/
TARGET DATE -
ALL TOPICS JAN 82 JAN 82 MAY 82 JUN 82 JUN 82 AUG 82 AUG 82 SEP 82 SEP'82 DEC 82 TECHNICAL REVIEWS TO DL l/ Division of Licensing Integrated Assessment Project Manager 2/ Deleted as not applicable, or duplicated by USI, TMI Action Plan, or another topic.
1/ These schedules and assignments are consistent with HRR FY 1982-1984 Operating Plan.
__/
s No. Completed / No. Assigned
/
t-9 STATUS AS OF AUGUST 31, 1982
PROGRESS OF TOPIC REVIEWS TOPICS DIVISION OF LICENSING gg TARGET 400 350 ACTUAL 00 250
~~
200 150 1
100 5B 1
I I
I I
I I
I I
I I
I g
SEP OCT NOV DEC JAN FEB MAR APR MAY JUN JUL AUG SEP OCT/DEC TARGET 5
11 13 16 l 6 8
5 3_
PER MONTH ETUAL 4
7 9
11 7
5 8
7 13 6
8 61 371 377 385 390 393 i
CUMULATIVE Em 298 305 314 325 332 337 345 352 365 371 379 8
7 i
PROGRESS OF TOPIC REVIEWS 0
TOPICS DIVISION OF ENGINEERING TARGET 200 175 s
ACTUAL 150 125 100 75 50 25 1
I I
I I
I I
I I
I I
I g
SEP OCT NOV DEC JAN FEB MAR APR MAY JUN JUL AUG SEP OCT/DEC
~
~
~
~
~
PER MONTH
. ETUAL 0
0 3
6 7
8 1
5 38 9
16 TARGET 109 122 145 157 165 170 192 Em 72 72 75 81 88 96 97 102 140 149 165 b
-~s
.-v y#..
r.
,mp
.r vn --
+--w vw-
- --w r
PROGRESS OF TOPIC REVIEWS TOPICS DIVISION OF SYSTEMS INTEGRATION 350 TARGET 300 ACTUAL. 250 - -
/
200
/
150 100 50
~~
l I
I I
I I
I I
I I
I I
e SEP OCT NOV DEC JAN FEB HAR APR MAY JUN JUL AUG SEP OCT/DEC te 24 26 30 22 8
3 2
2 ggg ggg7g Eith.
14 27 28 13 17 13 13 27 25 6
la ClNJLATIVE 86 288 2M_
EM 88 115 143 156 173 186 199 226 251 257 267
^
7 PROGRESS OF TOPIC REVIEWS O
TOPICS TOTALFROJECT I000 TARGET 900
~
__g
~~
ACTUAL 73-500 400
~~
100 1
I I
I I
I I
I I
I I
I g
SEP GCI NOV DEC JAN FEB MAR APR MAY JUN JUL AUG SEP OCT/DEC
~
~
PER MONTH
~
~
~
ETE 18 34 40 30 31 26 22 39 76 21 34 TARGET 630 680 736 791 817 836 858 875 ETE 458 492 532 562 593 619 641 680 756 777 811
LICENSEE TOPIC SUBMITTALS SUBMITTALS DIVISION OF LICENSING g
TARGET 35
__ /
/
30 ACTUAL
~
p 25
,/
20 15 10 5
~~
l I
I I
I I
I I
I I
0 JUN JUL AUG SEP OCT NOV DEC JAN FEB MAR APR MAY JUN JUL/DEC
~
~
~
~
~
~
~
PER MONTH ETE O
3 1
1 4
6 1
0 5
2 2-3 1
~
~
~
~
~
~
CUMULATIVE ACTE 8
3 4
5 9
15 16 16 21 23 25 28 29 9
7 LICENSEE TOPIC SUBMITTALS 0
OlVISION OF ENGINEERING TOPICS 80 TARGET 7g 00 ACTUAL
/
50 40 30 20 10 g
l I
l' I
I I
I I
I I
I JUN JUL AUG SEP OCT NOV DEC JAN FEB MAR APR MAY JUN JUL/DEC
~
~
~
~
~
~
~
PER MONTH ACTE 1
8 1
5 7
15 5
1 13 0
3 2
0
~
~
~
~
~
~
CUMULATIVE ACTE 1
9 10 15 22 37.
42 43 56 56 59 61 61
' LICENSEE TOPIC SUBMITTALS SUBNITTALS DIVISION OF SYSTEMS INTEGRATION I20 II0 TARGET 100
. ACTUAL BB
/
70
~~
60
~~
50
~~
30
~~
20
~~
10 1
I I
I I
I I
I I
I I
I g
JUN JUL AUG SEP OCT NOV DEC JAN FEB MAR APR HAY JUN JUL/DEC TARGET 8
3 6
3 1
0
" " ETm 1
10 3
31 3
2 7
12 7
6 6
4 1
~
~
~
~
~
~
CUMULATIVE ETE 1
11 14 45 48 50 57 69 76 82 88 92 93 S
T LICENSEE TOPIC SUBMITTALS 0
TOPICS TOTALPROJECT 225 TARGET 200
, ___ ~
175
,- '[
ACTUAL 150 125 100 75 50 25 l
i I
I I
I I
I I
I I
g JUN JUL AUG SEP OCT NOV DEC JAN FEB MAR APR HAY JUN Jll/DEC mi D
9 8
7 2
4 ggg,gg7g Enw.
2 21 5
37 14 23 13 13 25 8
11 9
2 i
TARGET 154 167 176 184 191 193 197 ETE 2
23 20 65 79 102 115 128 153 161 172 181 183
l l
l l
f I.
I Z
O
>0 uJ (4
i l
l l
r l
l
\\
t
BIG ROCK POINT FACILITY: BIG ROCK POINT 1 TOPIC HO.
REVIEW STATUS REMARKS DIV/BR LICENSEE CONSUMERS POWER I1-1 A.
DL/SEPB 7
CPCo to NRC 09/02/80 REGION / LOCATION: 4 MILES HORTH EAST OF CHARLEVOI, MICH.
II-1 B.
DL/SEPB 7
CPCo to NRC 09/02/80 DOCKET NO.
05000155 II-1 C.
DL/SEPB 7
NRC to CPCo 05/13/81 POWER CAPACITY: 0240(THERMAL) U67(ELECTRICAL)
II-2 A.
DSI/AEB 7
NRC to CPCo 08/03/81 OL NUMBER: DPR-6 II-2 D.
X NRC to CPCo 05/07/81 H.S.S.S.: GE.
II-2 C.
DSI/AEB 7
NRC TO CPC0 06/23/82 A/E FIRMS BECH.
II-2 D.
X NRC to CPCo 05/07/81 SYSTEMATIC EVALUATIDH PROGRAM BRANCH CHIEF: W. RUSSELL II-3 A.
DE/HGEB 4A 08/08/82 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD II-3 B.
DE/HGEB 4A 08/08/82 OPERATING REACTORS PROJECT MANAGER: R. EMCH
/
II-3 B.
1 DE/HGEB 4A 08/08/82 j
INTEGRATED ASSESSMENT PROJECT MANAGER: R. SCHOL.
II-3 C.
DE/HGEB 4A 08/08/82 II-4 DE/GSB 7
NRC to CPCo 06/08/81 KEY FOR STATUS CODES II-4 A.
DE/GSB 7
NRC to CPCo 06/08/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.
DE/GSB 3
CPC0 TO NRC 10/10/80 FROM REVIEW BRANCH X - DELETED II-4 C.
DE/GSB 7
NRC to CPCo 06/08/81 4b-SAR RECEIVED FROM 0 - TOPIC NOT LICENSEE II-4 D.
DE/HGEB 7
NRC TO CPC0 07/06/82 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 7
NRC TO CPCD 07/20/82 6 - SE RESPONSE RECEIVED 2 - QUESTI0HS SENT BY NRC III-1 DL/SEPB 5(SYS)
NRC TO CPC0 04/16/82 TO UTILITY DL/SEPB 7(ELEC) Part of VII-3 08/19/81 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 4B CPCD TO NRC 08/03/82 RECEIVED BY NRC (2-2)
BIG ROCK POINT TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR III-3 A.
DE/SEB 3
CPC0 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 4A 08/04/82 III-11 X
NRC to CPCO 05/07/81 III-4 A.
DSI/ASB 4B CPCO TO NRC 06/16/82 III-12 X
NRC to CPCo 05/07/81 III-4 B.
DE/MTEB 4B CPC0 TO NRC 06/09/82 IV-1 A.
DL/SEPB 7
NRC to CPCo 10/08/81 III-4 C.
DSI/ASB 45 CPC0 TO NRC 06/03/82 IV-2 DSI/ICSB 7
CPCo to NRC 12/22/81 III-4 D.
DE/SAB 7
NRC TO CPCD 08/12/82 IV-3 X
NRC to CPCo 05/04/81 III-5 A.
DL/SEPB 0
V-1 X
NRC to CPCo 11/27/81 III-5 B.
DL/SEPB 4A 08/30/82 V-2 X
NRC to CPCe 11/16/79 III-6 DL/SEPB 2
NRC to CPCo 01/19/82 V-3 X
NRC to CPCo 05/07/81 III-7 A.
X NRC to CPCo 05/07/81 V-4 DE/MT EB 3
CPC0 TO NRC 05/28/82 III-7 B.
DL/SEPB 3
CPCo to NRC 07/09/81 V-5 DL/SEPB 5
NRC TO CPC0 03/19/82 III-7 C.
X NRC to CPCo 11/16/79 V-6 DL/SEPB 7
NRC to CPCo 03/05/80 III-7 D.
DE/SEB 7
NRC TO CPCO 03/17/82 V-7 X
NRC to CPCo 11/16/79 III-8 A.
DSI 5
NRC TO CPC0 03/02/82 V-8 X
HRC to CPCo 05/07/81 III-8 B.
X NRC to CPCo 09/26/80 V-9 X
NRC to CPCo 11/16/79 III-8 C.
DL/SEPB 7
NRC TO CPCO 06/23/82 V-10 A.
DL/SEPB 7
NRC to CPCo 10/09/79 III-8 D.
X NRC to CPCo 05/07/81 V-10 B.
DL/SEPB 6
CPC0 TO NRC 03/30/82 III-9 X
NRC to CPCo 05/07/81 V-11 A.
DL/SEPB 7(ELEC) NRC TO CPCO 08/12/82 III-10 A.
DL/SEPB 7
HRC TO CPC0 03/30/82 V-11 B.
DL/SEPB 6(SYS)
CPCO TO NRC 03/30/S2 7(Elec) NRC to CPCo 08/12/82 (2-3)
BIG ROCK POINT TOPIC NO.
REVIEW STATUS REMARKS TOPIC FO.
REVIEW STATUS REMARKS DIV/BR DIV/BR h'7-12A.
DL/SEPB 7
NRC to CPCo 10/09/79 VI-7 D.
DL/SEPB 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 4A 08/08/82 VI-7 F.
X HRC to CPCo 11/16/79 VI-2 7.
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
HRC to CPCo 11/16/79 VI-2 C.
X HRC to CPCo 11/16/79 VI-10 A.
DL/SEPB 6
CPC0 TO NRC 08/05/82 VI-2 D.
DSI/CSB 6
CPC0 TO HRC 08/05/82 VI-10 B.
X NRC to CPCo 11/16/79 VI-5 DSI/CSB 6
CPC0 TO HRC 08/05/82 VII-1 A.
DL/SEPB 5
NRC TO CPCO 03/05/82 VI-4 DSI/CSB 6(SYS)
CPC0 TO HRC 07/20/82 VII-1 B.
DL/SEPB 7
NRC to CPCo 08/17/78 DL/SEPB 7(Elec) NRC to CPCo 11/24/81 VII-2 DL/SEPB 7
NRC to CPCo 02/01/82 VI-5 X
NRC to CPCo 05/07/81 VII-3 DL/SEPB 6(SYS)
CPC0 TO HRC 03/30/82 VI-6 DSI/CSB G
HRC to CPCo 05/07/81 DL/SEPB 7(Elec) HRC to CPCo 08/19/81 VI-7 A.
1.
X HRC to CPCo 11/16/79 VII-4 X
NRC to CPCo 35/07/81 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 7
NRC TO CPC0 08/20/82 VII-6 DL/SEPB 7
NRC to CPCo 09/21/81 VI-7 A. 4.
DSI/RSB 7
NRC to CPCo 04/10/79 VII-7 X
NRC to CPCo 11/16/79 VI-7 B.
DSI/RSB 7(Elec) CPCo to NRC 05/20/82 VIII-1 A.
DSI/PSB 7
NRC TO CPC0 07/08/82 7(SYS)) CPCo to NRC CS/20/82 VIII-2 DL/SEPB 7
HRC TO CPC0 08/02/82 VI-7 C.
DL/SEPB 7
HRC to CPCo 08/05/81 VIII-3 A.
DL/SEPS 7
CPCo to NRC 04/22/81 VI-7 C.
1.
DL/SEPB 7
NRC to CPCo 02/22/82 VIII-3 B.
DL/SEPB 7
NRC to CPCo 02/22/82 VI-7 C. 2.
DL/SEPB 7
NRC to CPCo 08/05/81 VIII-4 DL/SEPB 5
HRC TO CPC0 07/01/80 VI-7 C. 3.
X HRC to CPCo 11/16/79 (2-4)
BIG ROCK POINT TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 7
NRC TO CPCO 06/02/82 XV-10 X
HRC to CPCo 11/16/79 IX-2 X
NRC to CPCo 05/07/81 XV-11 DSI/CPB 7
NRC to CPCo 12/02/81 IX-3 DL/SEPS 7
NRC TO CPC0 07/20/82 XV-12 X
NRC to CPCo 11/16/79 IX-4 X
NRC to CPCo 11/16/79 XV-13 DSI/CPB 7(Sys)
HRC to CPCo 12/02/81 DSI/AEB 7(DOSES) NRC to CPCo 01/12/82 IX-5 DL/SEPB 4A 08/13/82 XV-14 DSI/RSB 7
NRC to CPCo 08/18/81 IX-6 DSI/ASB G
NRC to CPCo 05/07/81 XV-15 DSI/RSB 7
NRC to CPCo 08/18/81 X
X NRC to CPCo 05/07/81 XV-16 DSI/AEB 7
NRC to CPCo 12/28/81 XI-1 X
NRC to CPCo 12/04/81 XV-17 X
NRC to CPCo 11/16/79 XI-2 X
NRC to CPCo 12/04/81 XV-18 DSI/AEB 6
CPCO TO NRC 07/19/82 XIII-1 X
NRC to CPCo 05/07/81 XV-19 DSI/RSB 7(Sysl HRC to CPCo 08/18/81 XIII-2 DL/SSPB 7
NRC to CPCo 03/11/81 DSI/AEB 4b(Doses)CPCo to NRC 06/02/82 XV-1 DSI/RSB 7
NRC TO CPCO 06/25/82 XV-20 DSI/AEB 7
HRC to CPCo 01/12/82 XV-2 X
NRC to CPCo 11/16/79 XV-21 X
NRC to CPCo 05/07/81 XV-3 DSI/RSB 7
NRC to CPCo 06/18/82 XV-22 X
HRC to CPCo 05/07/81 XV-4 DSI/RSB 7
NRC to CPCo 10/16/81 XV-23 X
NRC to CPCo 05/07/81 XV-5 DSI/RSB 7
NRC to CPCo 02/08/82 XV-24 X
NRC to CPCo 05/07/81 XV-6 X
NRC to CPCo 11/16/79 XVI X
NRC to CPCo 11/05/80 XV-7 DSI/RSB 7
NRC TO CPC0 03/11/82 XVII DL 7
NRC to CPco 08/17/78 XV-8 DSI/CPB 7
HRC to CPCo 12/31/81 XV-9 DSI/RSB 7
NRC TO CPCO 04/07/82 (2-5)
DRESDEN1 FACILITY: DRESDEN 1 LICENSEE: COMMONWEALTH EDISON REGION /LOCATIDH: 9 MILES EAST OF MORRIS, ILL.
DOCKET NO.
05000010 POWER CAPACITY: 700(THERMAL) 200(ELECTRICAL)
A/E FIRMS BECH.
SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD OPERATING REACTORS PROJECT MANAGER: P. O'CONHOR
-ty letter dated December 31, 1980 Commonwealth Edison indi-cated that Dresden 1 was undergoing en extensive modifica-tion and was not scheduled for restart until June, 1986.
Also, by letter dated April 4,
1981, in response to the NRC's January 14, 1981 letter on SEP redirection the licen-see stated that the Dresden 1 SEP review is not being actively pursued, i.e. defered.
(2-6)
DRESDEN 2 FACILITY: ERESDEN 2 TOPIC NO.
REVIEW STATUS REMARKS DIV/BR LICENSEE: COMMONWEALTH EDISDN II-1 A.
DE/SAB 7
NRC to CECO 10/06/81 REGION /LOCATIGHz 9 MILES EAST OF MORRIS, ILL.
II-1 8.
DE/SAB 7
NRC to Ceco 10/06/81 DOCKET NO.: 05000237 II-1 C.
DE/SAB 7
NRC TO CECO 06/30/82 POWER CAPACITY: 2527(THERMAL) 0794(ELECTRICAL)
II-2 A.
DSI/AEB 7
NRC to CECO 04/24/81 OL NUMBER: DPR-19
/07/81 N.S.S.S.: GE.
II-2 C.
DSI/AEB 7
NRC to CPCo 08/26/81 A/E FIRMS S8L.
II-2 D.
X NRC to Ceco 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL II-3 A.
DE/HGEB 5
NRC TO CECO 06/21/82 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD II-3 B.
DE/HGEB 5
NRC TO CECO 06/21/82 OPERATING REACTORS PROJECT MANAGER: P. O'CONNOR II-3 B.
1 DE/HGEB 5
NRC TO CECO 06/21/82 INTEGRATED ASSESSMENT PROJECT MANAGER: G. CWALINA II-3 C.
DE/HGEB 5
NRC TO CECO 06/21/82 KEY FOR STATUS CODES II-4 DE/GSB 7
NRC to Ceco 07/09/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 A.
DE/GSB 7
NRC to Ceco 06/08/81 FROM REVIEW BRANCH X - DELETED II-4 B.
DE/GSB 7
HRC to Ceco 07/09/81 4b-SAR RECEIVED FROM 0 - TOPIC NOT LICENSEE II-4 C.
DE/GSB 7
NRC to Ceco 06/08/81 STARTED II-4 D.
DE/HGEB 7
NRC TO CECO 06/30/82 5 - DRAFT SE SENT 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 E.
DE/HGEB 5
NRC to Ceco 02/09/82 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT bY NRC II-4 F.
DE/HGEB 7
NRC TO CECO 06/30/82 TO UTILITY 7 - TOPIC COMPLETE III-1 DL/SEPB 6($YS)
CECO TO HRC 07/16/82 3 - QUESTION RESPONSE DL/SEPB 7(Elec) Part of VII-3 07/07/81 RECEIVED BY NRC III-2 DL/SEPB 7
NRC TO CECO 06/18/82 (2-7)
DRESDEN 2
TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR III-3 A.
DE/SEB 7
NRC TO CECO 06/04/82 III-10 B.
X NRC to CECO 11/16/79 III-3 5.
X NRC to Ceco 11/16/79 III-13 C.
DL/SEPB 7
HRC to Ceco 05/22/79 III-3 C.
DE/NGEB 7
NRC TO CECO 06/3C/82 III-It X
HRC to Ceco 05/07/81 III-4 A.
DSI/ASB 7
NRC TO CECO 06/28/82 IIl-12 X
NRC to Ceco 05/07/81 III-4 8.
DE/MTEB 6
CECO TO NRC 08/30/82 IV-1 A.
DL/SEPB 7
HRC to CECO 10/26/88 III-4 C.
DSI/ASB 7
NRC TO CECO 06/28/82 IV-2 DSI/ICSB 7
CECO to NRC 12/04/81 III-4 D.
DE/SAB 7
NRC to Ceco 02/22/82 IV-3 DE/MTEB 7
HRC to Ceco 01/22/82 III-5 A.
DL/SEPB 6
CECO TO NRC 08/23/82 V-1 X
NRC to Ceco 11/27/81 III-5 B.
DL/SEPB 7
NRC TO CECO 08/20/82 V-2 X
HRC to Ceco 11/16/19 III-6 DL/SEPB 7
NRC TO CECO 06/30/82 V-3 X
NRC to Ceco 11/16/79 III-7 A.
X NRC to Ceco 11/16/79 V-4 DE/MTEB 7
NRC TO CECO 06/29/82 III-7 B.
DL/SEPB 6
CECO TO NRC 08/02/82 V-5 DL/SEPB 7
NRC TO CECO 06/23/82 III-7 C.
X HRC to Ceco 11/16/79 V-6 DL/SEPB 7
NRC to Ceco 03/05/80 III-7 D.
DE/SEB 7
NRC TO CECO J4/13/82 V-7 X
NRC to Ceco 11/16/79 III-8 A.
DSI 7
NRC to Ceco 02/26/82 V-8 X
NRC to Ceco 11/16/79 III-8 B.
X HRC to CECO 09/11/80 V-9 X
NRC to OECo 11/16/79 III-8 C.
DL/SEPB 7
HRC TO CECO 06/29/82 V-10 A.
DL/SEPB 7
NRC to Ceco 11/08/79 III-8 D.
X NRC to Ceco 05/07/81 V-10 B.
DL/SEPB 7
NRC to CECO 04/24/81 III-9 X
NRC to Ceco 05/07/81 V-st A.
DL/SEPB 7
HRC to Ceco 07/10/81 III-10 A.
DL/SEPB 7
HRC 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 I-TOPIC HO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.
DL/SEPS 7
HRC to CECO 04/16/81 WI-7 D.
DL/SEPB 7
NRC to, Ceco-08/17/78 V-13 X
NRC to Ceco 05/07/81 VI-7 E.
X-MRC to Ceco 05/07/81 VI-1 DE/CEB 7
NRC TO CECO 06/30/82 VI-7 F.
X MRC to Ceco 11/16/79 VI-2 A.
X NRC to Ceco 05/07/81 VI-8 X
MRC to Ceco 85/07/41 VI-2 B.
X NRC to Ceco 05/07/81 VI-9 X
MRC to Ceco.
11/16/79-VI-2 C.
X NRC to Ceco 11/16/79 VI-10 A.
DL/SEPB 7
NRC to Ceco 07/03/81
[
i VI-2 D.
DSI/CSB 7
NRC TO CECO 08/19/82 VI-10 B.
DL/SEPS 7(Sys)
CECO TG NRC 11/03/81 DL/SEPB 7(Elec) HRC TO CECO 04/22/82.
VI-3 DSI/CSB 7
HRC TO CECO 08/19/82 VII-1 A.
DL/SEPR 7
HRC to CECO 04/05/81 i
VI-4 DSI/CSB 6(SYS)
CECO TO HRC 05/21/82 DL/SEPR 7(ELEC) NRC TO CECO 06/23/82 VII-1 B.
DL/SEPB 7
MRC to Ceco 08/17/78-VI-5 X
NRC to Ceco 05/07/81 VII-2 DL/SEPS 7
Ceco to NRC 11/03/81 VI-6 DSI/CSB 7
NRC TO CECO 06/25/82 VII-3 DL/SEPB 7(Sys)
HRC to Ceco 04/24/81 DL/SEPS 7(Elec) HRC to Ceco 07/07/81 VI-7 A.
1 X
MRC to CECO 11/16/79 VII-4 X
MRC to Ceco 05/07/41 VI-7 A. 2.
X NRC to CECO 11/16/79 VII-5 X
NRC to Ceco 05/07/41 VI-7 A. 3.
DL/SEPB 7
Ceco to NRC 11/03/81 VI-7 A. 4.
DSI/RSB 7
NRC to Ceco 02/22/82 VII-7 X
NRC to Ceco 11/16/79' VI-7 B.
X NRC to Ceco 11/16/79 i
VIII-1 A.
DSI/PSB 7
NRC TO CECO 86/15/82 VI-7 C.
DL/SEPB 7
MRC to Ceco 03/13/81 VIII-2 DL/SEPB 7
NRC to Ceco 06/26/81 VI-7 C.
1 DSI/PSB 7
MRC TO CECO 02/05/82 VIII-3 A.
DL/SEPB 7
NRC to Ceco 07/07/81 j
VI-7 C.,2.
DL/SEPB 7
NRC to Ceco 03/13/81 VIII-5 3.
DL/SEPR 7
HRC to Ceco 06/26/41 VI-7 C. 3.
X HRC to Ceco 11/16/79 VIII-4 DL/SEPB 7
NRC to CECO 11/30/81 t
s t
i j
(2-9)
S
l DRESDEN 2 TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS R Et1 ARKS DIV/BR DIV/BR IX-l DSI/ASB 7
NRC TO CECO 05/05/82 XV-10 X
NRC to CECO 11/16/79 IX-2 X
NRC to Ceco 05/07/81 XV-11 DSI/CPB 7
HRC to Ceco 02/08/82 IX-3 DL/SEPB 7
CECO to NRC 11/03/81 XV-12 X
NRC to Ceco 11/16/79 IX-4 X
NRC to CECO 11/16/79 XV-13 DSI/CPB 7(Sys)
HRC to Ceco 02/08/82 DSI/AEB 7(Doses) HRC to Ceco 12/28/81 IX-5 DL/SEPB 6
CECD TO HRC 07/12/82 XV-14 DSI/RSB 7
NRC to CECO 12/15/81 IX-6 DE/CEB 7
NRC TO CECO 06/23/82 XV-15 DSI/R$8 7
NRC to Ceco 01/04/82 X
X HRC to CECO 11/16/79 XV-16 DSI/AEB 7
CECO to NRC 10/20/81 XI-1 X
NRC to Ceco 12/04/81 XV-17 X
NRC to Ceco 11/16/79 XI-2 X
NRC to Ceco 12/04/81 XV-18 DSI/AEB 6
CECO TO HRC 05/21/82 XIII-1 X
HRC to Ceco 05/07/81 XIII-2 DL/SSPB
.7 NRC to Ceco 04/14/82 XV-19 DSI/R$B 7(Sys)
HRC to Ceco 12/07/81 DSI/AEB 7(DOSES) CECO to NRC 01/05/82 XV-1 DSI/RSB 7
HRC to Ceco 12/29/81 XV-20 DSI/AEB 7
NRC to Ceco 11/20/81
.XV-2 X
HRC to Ceco 11/16/79 XV-21 X
NRC to Ceco 05/07/81 XV-3 DSI/RSB 7
NRC to Ceco 12/07/81 XV-22 X
hRC to CECO 05/07/81 XV-4 DSI/RSB 7
NRC to CECO 12/07/81 XV-23 X
NRC to Ceco 11/16/79 XV-5 DSI/RSB 7
NRC to Ceco 12/15/81 XV-24 X
NRC to Ceco 03/07/81 XV-6 X
HRC to Ceco 11/16/79 XVI X
NPC to Ceco 11/05/80 XV-7 DSI/RSB 7
HRC to Ceco 01/04/82 XVII DL 7
NRC to CECO 11/20/79 XV-8 RSI/CPB 7
NRC to Ceco 02/08/82 XV-9 DSI/RSB 7
NRC to CECO 12/15/81 (2-10) i
GINNA I
FACILITY: GINNA 8
TOPIC NO.
REVIEW STATUS REMARKS DIV/BR LICENSEE: ROCHESTER GAS 1 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.
DF/SAB 7
NRC to RGE 07/21/81 DOCKET NO.
05000244 II-1 C.
DE/SAB 7
NRC to RGE 09/29/81 PO:JER CAPACITY: 1520(THERMAL) 0490(ELECTRICAL)
II-2 A.
DSI/AEB 7
NRC to RGE 1/03/81 OL NUMBER: DPR-18 II-2 B.
X NR 05/07/81 H.S.S.S.4 WEST.
II-2 C.
DST /AEB 7
ORE
/24/81 A/E FIRM: GIL.
II-2 D.
RGE 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL II-3
" /HGEB NRC TO RGE 05/27/82 OPERATING REACTORS ERANCH CHIEF: D. CRUTCHFIELD II r
B 7
NRC TO RGE 05/27/82 OPERATING REACTCRS PROJECT MANAGER: J. LYONS DE/HGEB 7
NRC TO RGE 05/27/82 INTEGRATED ASSESSMENT PROJECT MANAGER: A. pC b 1
' II-3 C.
GB 7
HRC TO RGE 05/27/82
\\
\\
V I -4 DE
'B 7
NRC to RCE 07/09/81 KEY FOR STAT d 10.
Tj'
,,4 A-hgRCtoRGE
-4 A E/GSB 7
06/08/81 G - GENr 'C
%a CDFT SE RECEIVED I
DE/GSB
> RC to RGE 07/09/81 FROM REVIEW B % Hl j
4b-SAR RECEIVED l l
II-4 C.
D G RRC to RGE 06/08/81 X - DL ET i
ld y/
R O.
NRC to RGE 02/19/82 STARTED l
5 - DRAFT SE SENT 1 - QUESTIONS RECEIVED TO UTILITY X
NRC to RGE 11/16/79 FROM REVIEW BRANCH II-4 F.
DE/HGEB 7
HRC t0 RGE 02/19/82 2 - QUESTIONS SENT B
f III-1 DL/SEPB 7(Sys)
HRC to RGE 12/17/81 TO UTILITY I
DL/SEPB 7(Elec) HRC to RGE 04/02/81 7 - TOP L E 3 - QUESTION RESPONSE III-2 DL/SEPB 7
NRC TO RGE 04/21/82 RECEIVED BY NRC u - DATA OR NEXT MONTH (NOVEMBER)
(2-11)
GINNA TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS RtMARKS DIV/BR DIV/BR III-5 A.
DE/SEB 7
NRC TO RGE 03/03/82 III-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 7
NRC TO RGE 05/27/82 III-11 X
NRC to RGE 05/07/81 III-4 A.
-DSI/AEB 7
hRC TO RGE 04/16/82 III-12 X
NRC to RGE 05/07/81 III-4 B.
DE/MTEB 7
HRC to RGE 02/19/82 IV-1 A.
DL/SEPB 7
NRC to RGE 05/29/79 III-4 C.
DSI/ASB 7
NRC to RGE 02/17/82 IV-2 DSI/ICSB 7
HRC to RGE 05/26/81 III-4 D.
DE/SAB 7
HRC to RGE 07/21/81 IV-3 X
NRC to RGE 05/07/81 III-5 A.
DL/SEPB 7
NRC to RGE 02/22/82 V-1 X
NRC to RGE 11/27/81 III-5 B.
DL/SEPB 7
NRC to RGE 09/04/81 V-2 X
NRC to RGE 11/16/79 III-6 DL/SEPB 7
HRC to RGE 02/17/82 V-3 X
NRC to RGE 05/07/81 III-7 A.
DL/SEPB 7
NRC TO RGE 04/16/82 V-4 X
NRC to RGE 05/07/81 III-7 B.
DL/SEPB 7
HRC TC RGE 04/21/82 V-5 DL/SEPB 7
HRC to RGE 02/08/82 III-7 C.
- DE/SEB 7
RGE to NRC 07/07/81 V-6 DL/SEPB 7
NRC to RGE 03/05/80 HRC 'o RGE 05/08/80 V-7 DSI/ASB 7
HRC to RGE 02/17/82 III-7 D.
DE/SEB 7
t III-8 A.
DSI 7
NRC to RGE 02/17/82 V-8 X
HRC to RGE 05/07/81 III-8 B.
X NRC to RGE 02 12 51 V-9 X
NRC to RGE 11/16/79 III-8 C.
DL/SEPB 7
RGE to NRC 12/07/79 V-10 A.
DL/SEPB 7
NRC to RGE 02/02/79 III-8 D.
X NRC to RGE 05/07/81 V-10 8.
DL/SEPB 7
RGE to NRC 09/29/81 III-9 X
NRC to RGE 05/07/81 V-11 A.
DL/SEPB 7
NRC to RGE 11/07/81 III-10 A.
DL/SEPB 7
NRC to RGE 08/03/81 V-11 B.
DL/SEPB 7(Sys)
RGE to NRC 09/29/81 DL/SEPB 7(Elec)' NRC to RGE-04/24/31 (2-12)
_m.
GINNA
~~
TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS-DIV/BR DIV/BR V-12 A.
X NRC to RGE 11/16/79 VI-7 D.
DL/SEPB 7
NRC to RGE 08/17/78 V-13 X
NRC to RGL' b;/07/81 VI-7 E.
X NRC to RGE 05/07/81 VI-1 DE/CEB 7
NRC to RGE 02/19/82 VI-7 F.
DL/SEPB 7
HRC to RGE 06/24/81 VI-2 A.
X NRC to RGE 05/07/81 VI-8 X
NRC to RGE 05/07/81 VI-2 B.
X HRC to RGE 05/07/81 VI-9 X
NRC to RGE 11/16/79 VI-2 C.
X NRC to RCE 11/16/79 VI-10 A.
DL/SEPB 7
NRC to RGE 11/27/81 VI-2 D.
DSI/CSB 7
HRC TO RGE 04/12/82 VI-10 8.
X NRC to RGE 11/16/79 VI-3 DSI/CSB 7
NRC TO RGE 04/12/82 VII-1 A.
DL/SEPB 7
NRC to RGE 07/30/81 VI-4 DSI/CSB 7(SYS)
NRC TO RGE 04/12/82 VII-1 B.
DL/SEPB 7
NRC to RGE 08/17/78 DL/SEPB 7(ELEC) NRC TO RGE 03/19/82 VII-2 DL/SEPB 7
NRC to RGE 12/28/81 VI-5 X
HRC to RGE 05/07/81 VII-3 DL/SEPB 7(Sys)
HRC to RGE 09/29/81 VI-6 DSI/CSB 7
NRC to RGE 05/06/81 DL/SEPB 7(Elec) HRC to RGE 03/25/82 VI-7 A.
1 DL/SEPB 7
HRC to RGE 02/20/81 VII-4 X
NRC to RGE 05/07/81 VI-7 A. 2.
DL/SEPB 7
NRC to RGE 08/17/78 VII-5 X
NRC to RGE 05/07/81 VI-7 A.
3.
DL/SEPB 7
NRC to RGE 11/27/81 VII-6 DL/SEPB 7
NRC to RGE 06/24/8' VI-7 A.
4.
X NRC to RGE 05/07/81 VII-7 X
NRC to RGE 11/16/79 VI-7 B.
DSI/RSD 7(SYS)
HRC TO KGE 03/09/82 VIII-1 A.
DSI/PSB 7
NRC to RGE 03/26/81 DL/SES 7(Elec) NRC to R3E 09/18/81 VIII-2 DL/SEPB 7
HRC to RGE 06/24/81 VI-7 C.
DL/SEPB 7
NRC to RGC 02/20/81 VIII-3 A.
DL/SEPB 7
NRC to RGE 07/31/81 VI-7 C.
1 DL/SEP5 7
NRC to RGE 11/27/81 VIII-3 B.
DL/SEPB 7
NRC to RGE 06/09/81 VI-7 C. 2.
DL/SEPB 7
NRC to RGE 02/20/81 VIII-4 DL/SEPB 7
RGE to NRC 10/08/81 VI-7 C.
3.
X NRC to RGE 11/16/79 i
(2-13) 1
GINNA TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/A5B 7
NRC to RGE 11/24/81 XV-10 DSI/RSB 7
NRC to RGE 09/04/81 IX-2 X
NRC to RGE 05/07/81 XV-11 X
NRC to RGE 10/01/80 IX-3 DL/SEPB 7
NRC to RGE 11/03/81 XV-12 DSI/CPB 7(Sys)
NRC to RGE 09/04/81 DSI/AEB 7(DOSES) NRC TO RGE 03/03/82 IX-4 DSI/RSB 7
NRC to RGE 08/26/81 XV-13 X
NRC to RGE 11/16/79 IX-5 DL/SEPB 7
RGE to NRC 03/29/82 XV-14 DSI/RSB 7
NRC to RGE 09/04/81 IX-6 7
NRC TO RGE 05/07/82 XV-15 DSI/RSB 7
NRC to RGE 09/04/81 X
X NRC to RGE 05/07/81 XV-16 DSI/AEB 7
NRC TO RGE 03/03/82 XI-1 X
NRC to RGE 12/04/81 XV-17 DSI/RSB 7(Sys)
HRC to RGE 09/04/81 XI-2 X
NRC to RGE 12/04/81 DSI/AEB 7(DOSES) HRC TO RGE 03/03/82 XIII-1 X
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/RSS 7(Sys)
HRC to RGE 10/02/81 DSI/AEB 7(DOSES) RGE TO NRC 03/09/82 XV-1 DSI/RSB 7
NRC to RGE 09/04/81 XV-20 DSI/AE3 7
HRC TO RGE 03/03/82 XV-2 DSI/RSB 7(Sys)
NRC to RGE 09/04/81 DSI/AEB 7(DOSES) HRC TO RGE 03/C3/82 XV-21 X
NRC to RGE 05/07/81 XV-3 DSI/RSB 7
NRC to RGE 09/04/81 XV-22 X
NRC to RCE 05/07/81 XV-4 DSI/RSE 7
NRC to RGE 09/04/81 XV-23 X
NRC to RGE 05/07/81 XV-5 DSI/RSB 7
HRC 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/RSS 7
NRC to RGE 09/04/81 XVII DL 7
NRC to RGE 08/17/78 XV-8 DSI/CPB 7
NRC to RGE 09/04/81 XV-9 DSI/RSB 7
RGE to NRC 10/16/81 (2-14)
HADDAM NECK FACILITY: NADDAM NECK TOPIC NO.
REVIEW STATUS R EMARKS DIV/BR LICENSEE: CONNECTICUT YANKEE ATOMIC POWER 11-1 A.
DE/SAB 7
HRC TO CYAPCO 04/22/82 REGION / LOCATION: 13 MILES EAST OF MERIDEN, CT.
II-1 B.
DE/SAB 7
NRC TO CYAPC0 04/22/82 DOCKET NO: 05000213 II-1 C.
DE/SAB 7
NRC TO CYAPCD 06/28/82 POWER CAPACITY: 1825(THERMAL) 0575(ELECTRICAL)
II-2 A.
DSI/AEB 7
CYAPCo to NRC 01/22/81 OL NUMBER: DPR-61 II-2 B.
X NRC to CYAPCo 05/07/81 N.S.S.S.: WEST.
II-2 C.
DSI/AEB 7
NRC TO CYAPCO 04/26/82 II-2 D.
X NRC to CYAPCo 05/07/81 l
SYSTEMATIC EVALUATIDH PROGRAM BRANCH CHIEF: W. RUSSELL II-3 A.
DE/HGEB 4A 08/30/82 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD II-3 B.
DE/HGEB 4A 08/30/82 f
OPERATING REACTORS PROJECT MANAGER: C. TROPF II-3 B.
1 DE/HGEB 4A 08/30/82 INTEGRATED ASSESSMENT PRGJECT MANAGER: S. BROWN
'f>
II-3 C.
DE/HGEB 4A 08/30/82 l
II-4 DE/ GSB 7
NRC to CYAPCo 06/04/82
{
KEY FOR STATUS CODES t
II-4 A.
DE/GSB 7
HRC to CYAPCo 06/08/81 l
G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.
DE/GSB 7
HRC TO CYAPCO 06/04/82 FROM REVIEW BRANCH II-4 C.
DE/CSB 7
NRC to CYAPCo 06/08/81 I
X - DELETED 4b-SAR RECEIVED FROM 0 - TOPIC NOT LICENSEE II-4 D.
DE/HGEB 7
NRC 70 CYAPCO 07/13/82 STARTED 5 - DRAFT SE SENT II-4 E.
X NRC to CYAPCo 04/16/79 1 - QUESTIONS RECEIVED TO UTILITY II-4 F.
DE/HGEB 7
NRC TO CYAPCO 07/06/82 FROM REVIEW BRANCH 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC III-1 DL/SEPB 5(SYS)
HRC TO CYAPCO 08/12/82 DL/SEPB 7(Elec) Part of VII-3 TO UTILITY 7 - TOPIC COMPLETE III-2 DL/SEPB 4A 08/11/82 3 - QUESTION RESPONSE RECEIVED BY NRC (2-15)
HADDAM NECK TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS R EMA RKS DIV/BR DIV/BR III-3 A.
DE/SEB 7
NRC TO CYAPCO 08/26/82 III-10 B.
DL/SEPB 7
HRC 10 CYAPCO 03/36/82 III-3 B.
DE/NGEB 4A 08/30/82 III-10 C.
X NRC to CYAPCo 04/16/79 III-3 C.
DE/HGEB 7
NRC TO CYAPCO 06/28/82 III-11 X
NRC to CYAPCo 05/07/81 III-4 A.
DSI/ASB 7
HRC TO CYAPCO 08/02/82 III-12 X
NRC to CYAPCo 05/07/81 III-4 B.
DE/MTEB 7
HRC TO CYAPCO 07/13/82 IV-1 A.
DL/SEPB 7
CYAPCo to NRC 06/25/79 III-4 C.
DSI/ASB 5
NRC TO CYAPCO 05/10/82 IV-2 DSI/ICSB 7
NRC to CYAPCo 02/22/82 III-4 D.
DE/SAB 7
NRC TO CYAPCO 04/22/82 IV-3 X
NRC to CYAPCo G5/07/81 III-5 A.
DL/SEPB 4A 08/27/82 V-1 X
NRC to CYAPCo 11/27/81 1II-5 B.
DL/SEPB 7
NRC TO CYAPC0 05/10/82 V-2 X
NRC to CYAPCo 04/16/79 III-6 DL/SEPB 3
CYAPCo to NRC 06/11/81 V-3 X
NRC to CYAPCo 05/07/81 III-7 A.
X NRC to CYAPCo 05/07/81 V-4 X
NRC to CYAPCo 05/07/31 III-7 B.
DL/SEPB 5
NRC TO CYAPCO 08/27/82 V-5 DL/SEPB 7
NRC to CYAPCo 02/22/82 III-7 C.
X HRC to CYAPCo 04/16/79 V-6 DL/SEPB 7
NRC to CYAPCo 03/05/80 III-7 D.
DE/SEB 7
NRC to CYAPCo 10/16/81 V-7 DSI/ASB 7
NRC TO CYAPCO 06/21/82 III-8 A.
DSI 7
NRC TO CYAPCC 06/21/82 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-5 C.
DL/SEPB 7
NRC to CYAPCo 01/29/82 V-10 A.
DL/SEPB 7
NRC to CYAPCo 01/13/81 III-8 D.
X NRC to CYAPCo 05/07/81 V-10 B.
DL/SEPB 7
NRC to CYAPCo 12/28/81 III-9 X
hRC to CYAPCo 05/07/.1 V-11 A.
DL/SEPB 7
NRC to CYAPCo 11/03/81 III-10 A.
DL/SEPB 7
CYAPCo to NRC 09/21/81 V-11 B.
DL/SEPB 7(Sys)
HRC to CYAPCo 12/28/81 DL/SEPB 7(Elec) NRC TO CYAPCO 03/03/82 (2-16)
HADDAM NECK TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.
X NRC to CYAPCo 11/16/79 VI-7 D.
DL/SEPB 7
NRC to CYAPCo 08/17/78 V-13 X
NRC to CYAPCo 05/07/81 VI-7 E.
X NRC to CYAPCo 05/07/81 VI-1 DE/CEB 7
HRC TO CYAPCO 07/15/82 VI-7 F.
X NRC to CYAPCo 04/16/79 VI-2 A.
X NRC to CYAPCo 05/07/81 VI-8 X
HRC to CYAPCo 05/07/81 VI-2 B.
X NRC to CYAPCo 05/07/81 VI-9 X
NRC to CYAPCo 11/16/79 VI-2 C.
X HRC to CYAPCo 04/16/79 VI-10 A.
DL/SEPB 5
NRC TO CYAPCO 07/22/82 VI-2 D.
DSI/CSB 6
CYAPCO TO NRC 08/04/82 VI-10 B.
X NRC to CYAPCo 04/16/79 VI-3 DSI/CSB 6
CYAPCD TO NRC 08/04/82 VII-t A.
DL/SEPB 6
CYAPC0 TO NRC 08/11/82 VI-4 DSI/CSB 6(SYS)
CYAPCO TO NRC 08/18/82 VII-1 B.
DL/SEPB 7
NRC to CYAPCo 08/17/78 DL/SEPB 7(Elec) HRC to CYAPCo 09/21/81 VII-2 DL/SEPB 5
HRC TO CYAPCO 03/05/82 VI-5 X
NRC to CYAPCo 05/07/81 VII-3 DL/SEPB 7(Sys)
HRC to CYAPCo 12/28/81 VI-6 DSI/CSB 7
NRC TO CYAPCO 05/07/82 DL/SEPB 7(Elec) NRC to CYAPCo 08/28/81 VI-7 A.
1.
DL/SEPB 7
HRC to CYAPCo 02/20/81 VII-4 X
NRC to CYAPCo 05/07/51 VI-7 A. 2.
X NRC to CYAPCo 05/07/81 VII-5 X
NRC to CYAPCo 05/07/81 VI-7 A. 3.
DL/SEPB 5
t:RC to CYAPCo 02/11/82 VII-6 DL/SEPB 7
NRC to CYAPCo 08/28/81 VI-7 A. 4.
X HRC to CYAPCo 05/07/81 VII-7 X
NRC to CYAPCo 04/16/79 VI-7 B.
DSI/RSB 7(SYS)
HRC TO CYAPCO 08/12/82 VIII-1 A.
DSI/PSB 7
NRC TO CYAPC0 07/22/82 DL/SEPB 7(Elec) HRC to CYAPCo 05/21/81 VIII-2 DL/SEPB 7
NRC to CYAPCo 08/28/81 VI-7 C.
DL/SEPB 7
NRC to CYAPCo 03/13/81 VIII-3 A.
DL/SEPB 7
CYAPCo to NRC 02/16/79 VI-7 C.
1.
DL/SEPB 7
CYPACO to NRC 01/11/82 VIII-3 B.
DL/SEPB 7
NRC to CYAPCo 08/28/81 VI-7 C. 2.
DL/SEPB 7
NRC to CYAPCo 03/13/81 VIII-4 DL/SEPB 7
NRC TO CYAPCD 05/17/82 VI-7 C.
3.
DL/SEPB 7
CYAPCo to NRC 02/12/82 (2-17)
HADDAM NECK TOPIC NO.
REVIEW STATUS REMARKS TOPIC HO.
REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 7
NRC TO CYAPCO 03/01/82 XV-10 DSI/RSB 7
NRC to CYAPCo 05/07/81 XV-11 X
NRC to CYAPCo 10/01/80 IX-3 DL/SEPB 7
KRC TO CYAPCD 06/07/82 XV-12 DSI/CPB 7(SYS)
NRC TO C)APCO 03/23/82 DSI/RSB 7(DOSES) HRC TO CYAPCO 06/29/82 IX-4 DSI/R$B 7
NRC TO CYAPCO 04/26/81 XV-13 X
NRC to CYAPCo 11/16/79 IX-5 DL/SEPB 7
HRC TO CYAPCO 08/27/82 XV-14 DSI/RSB 7
HRC TO CYAPCO 04/26/82 IX-6 DE 7
DSI TO DL 05/19/82 XV-15 DSI/RSB 7
NRC TO CYAPC0 04/16/82 X
X NRC to CYAPCo 05/07/81 XV-16 DSI/AEB 6
CYAPCo to NRC OV/28/81 XI-1 X
NRC to CYAPCo 12/04/81 XV-17 DSI/RSB 7(SYS)
HRC TO CYAPCO 08/1?/82 XI-2 X
NRC to OYAPCo 12/04/81 DSI/AEB 7(DOSES) HRC TO CYAPCO 08/19/82 XIII-1 X
HRC to CYAPCo 05/07/81 XV-18 X
NRC to CYAPCo 10/01/80 XIII-2 DL/SSPB 7
HRC TO CYAPCO 06/10/82 XV-19 DSI/RSB 7(Sys)
HRC to CYAPCo 12/02/81 DSI/AEB 7(DOSES) NRC TO CYAPCO 08/27/82 XV-1 DSI/RSB 7
HRC TO CYAPCO 06/18/82 XV-20 DL/SEPB 7
NRC to CYAPCo 06/09/81 XV-2 DSI/RSB 7 (SYS) NRC TO CYAPCO 05/20/82 DSI/AEB 5(DOSES) HRC TO CYAPCO 07/15/82 XV-21 X
NRC to CYAPCo 05/07/81 XV-3 DSI/RSB 7
NRC TO CYAPCO 03/17/82 XV-22 X
HRC to CYAPCo 05/07/81 XV-4 DSI/RSB 7
HRC to CYAPCo 12/17/81 XV-23 X
hRC to CYAPCo 05/07/81 XV-5 DSI/RSB 7
HRC TO CYAPCO 04/16/82 XV-24 X
NRC to CYAPCo 05/07/81
.XV-6 DSI/RSB 7
NRC TO CYAPCO 05/20/82 XVI X
HRC to CYAPCo 11/05/80 XV-7 DSI/R$B 7
HRC TO CYAPCO 05/25/82 XVII DL 7
NRC to CYAPCo 08/17/78 XV-8 DSI/CPB 7
HRC TO CYAPCO 03/25/82 XV-9 DSI/RSB 7
HRC TO CYAPCO 04/26/82 (2-18)
LACROSSE FACILIIY: LACROSSE TOPIC NO.
R EVI EW STATUS R EMA RKS DIV/BR LICENSEE DAIRYAND POWER 11-1 A.
DE/SAS 4b DPC to NRC 06/23/81 REGIDM/ LOCATION: 19 MILES SOUTH OF LACROSSE, WISC.
II-1 B.
DE/SAB 4A 07/29/82 DOCKET NO.'
05000409 II-1 C.
DE/SAB 7
NRC TO DPC 08/30/82 POWER CAPACITY: 0165(THERMAL) 0050(ELECTRICAL)
II-2 A.
DSI/AEB 7
NRC to DPC 12/15/80 OL NUMBER: DPP.-45 II-2 8.
X HRC to DPC 05/07/81 N.S.S.S.: AC.
II-2 C.
DSI/AEB 4B DPC TO NRC 01/05/82 A/E FIRM: S&L II-2 D.
X NRC to DPC 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W.
RUSSELL II-3 A.
DE/HGEB 4b DPC to NRC 06/16/81 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD II-3 B.
DE/HGEB 4B DPC TO NRC 05/12/82 OPERATING REACTORS PROJECT MANAGER: D. DUDLEY II-3 B.
1.
DE/HGEB 4B DPC TO NRC 05/12/82 INTEGRATED ASSESSMENT PROJECT MANAGER: T. MICHAELS f '; }.
II-3 C.
DE/HGEB 4b DPC to NRC 05/26/81 II-4 DE/GSB 7
NRC to DPC 07/20/82 Kff 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 7
NRC TD DPC 07/20/82 FROM REVIEW BRANCH X - DELETED II-4 C.
DE/GSB 7
NRC to DPC 06/08/81 ib-SnR RECEIVED FROM 0 - TOPIC NOT LICENSEE II-4 D.
DE/HGES 5
NR0 TO DPC 08/27/82 STARTED 5 - DRAFT SE SENT II-4 E.
DE/HGEB 7
HRC TO DPC 08/16/82 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.
DE/HGEB 7
NRC TO DPC 07/29/82 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY HRC III-1 DL/SEPB 6(SYS)
DPC TO HRC 08/26/82 TO UTILITY DL/SEPB 6(ELEC) DPC TO NRC 08/26/82 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 4b DPC to NRC 03/05/82 RECEIVED BY HRC (2-19)
LACROSSE TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR III-3 A.
DE/SEB 48 DPC TO NRC 05/12/82 III-10 B.
X NRC to DPC 10/29/79 III-3 B.
X HRC to DPC 03/10/81 III-10 C.
X HRC to DPC 10/29/79 III-3 C.
DE/HGEB 4B DPC TO NRC 01/29/82 III-11 X
NRC to DPC 05/07/81 III-4 A.
DSI/ASB 48 DPC TO NRC 08/16/82 III-12 X
NRC to DPC 05/07/81 III-4 B.
DE/MTEB 4B DPC TO HRC 03/05/82 IV-1 A.
DL/SEPB 7
NRC to DPC 04/19/79 III-4 C.
DSI/ASB 7
NRC TO DPC 07/19/82 IV-2 DSI/ICSB 7
HRC TO DPC 03/25/82 III-4 D.
DE/SAB 7
NRC TO DPC 08/23/82 IV-3 X
HRC to DPC 05/07/81 III-5 A.
DL/SEPB 4A 08/06/82 V-1 X
NRC to DPC 11/27/81 III-5 B.
DL/SEPB 7
NRC TO DPC 08/12/82 V-2 X
NRC to DPC 10/29/79 III-6 DL/SEPB 3
DPC to NRC 06/12/81 V-3 X
NRC to DPC 05/07/81 III-7 A.
X NRC to DPC 05/07/81 V-4 X
NRC to DPC 05/07/81 III-7 B.
DL/SEPB 4A 07/23/82 V-5 DL/SEPB 7
HRC TO DPC 07/19/82 III-7 C.
X NRC to DPC 10/29/79 V-6 DL/SEPB 7
NRC to DPC 03/05/80 III-7 D.
DE/SEB 7
NRC TO DPC 04/13/82 V-7 X
NRC to DPC 05/07/81 III-8 A.
DSI 5
HRC TO DPC 02/22/82 V-8 X
HRC to DPC 05/07/81 III-8 B.
X NRC to DPC 09/26/80 V-9 X
NRC to DPC 10/29/79 III-8 C.
DL/SEPB 7
DPC to NRC 03/03/81 V-10 A.
DL/SEPB 7
NRC to DPC 01/07/80 III-8 D.
X NRC to DPC 05/07/81 V-10 B.
DL/SEPB 6
DPC TO NRC 08/26/82 III-9 X
NRC to DPC 05/07/81 V-11 A.
DL/SEPB 7
HRC to DPC 02/22/82 III-10 A.
DL/SEPB 7
HRC to DPC 09/22/81 V-11 B.
DL/SEPB 6(SYS)
DPC TO NRC 08/26/82 DL/SEPB 7(ELEC) HRC TO DPC 03/04/82 (2-20)
LACROSSE TDPIC NO.
REVIEW STATUS R EMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.
DL/SEPB 7
HRC to DPC 04/30/79 VI-7 D.
DL/SEPB 7
NRC to DPC 08/17/78 V-13 X
NRC to DPC C5/07/81 VI-7 E.
X NRC to DPC 05/07/81 VI-l DE/C EB 45 DPC to NRC 02/19/82 VI-/ F.
X NRC to DPC 10/29/79 VI-2 A.
X HRC to DPC 05/07/81 VI-8 X
NRC to DPC 05/07/81 VI-2 B.
X NRC to DPC 05/07/81 VI-9 X
NRC to DPC 10/29/79 VI-2 C.
X HRC to DPC 10/29/79 VI-10 A.
DL/SEPB 6
DPC TO NRC 06/14/82 VI-2 D.
DSI/CSB 7
NRC TO DPC 03/27/82 VI-10 B.
X NRC to DPC 10/29/79 VI-3 DSI/CSB 7
NRC TO DPC 08/27/82 VII-1 A.
DL/SEPB 5
NRC TO DPC 03/09/82 VI-4 DSI/CSB 5(SYS)
HRC TO DPC 08/27/82 VII-1 B.
DL/SEPS 7
NRC to DPC 08/17/78 DL/SEPB 7(Elec) NRC to DPC 01/05/82 VII-2 DL/SEPB 5
NRC TO DPC 03/11/82 VI-5 X
NRC to DPC 05/07/81 VII-3 DL/SEPB 6(SYS)
DPC TO NRC 08/26/82 VI-6 DSI/CSB 7
HRC TO DPC 08/24/82 DL/SEPB 6(ELEC) DPC TO HRC 08/26/82 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
HRC to DPC 05/07/81 VI-7 A. 3.
DL/SEPB 5
NRC to DPC 02/17/82 VII-6 DL/SEPB 7
NRC to DPC 09/21/81 VI-7 A. 4.
X NRC to DPC 05/07/81 MII-7 X
NRC to DPC 10/29/79 VI-7 B.
X NRC to DPC 10/29/79 VIII-1 A.
DSI/PSB 4A 06/25/82 VI-7 C.
DL/SEPB 7
NRC to DPC 03/13/81 VIII-2 DL/SEPB 7
NRC to DPC 12/18/81 VI-7 C.
1 DL/SEPB 7
HRC to DPC 09/21/81 VIII-3 A.
DL/SEPB 7
NRC to DPC 06/05/79 VI-7 C. 2.
DL/SEPB 7
HRC to DPC 03/13/81 VIII-3 B.
DL/SEPB 7
HRC to DPC' 08/28/s1 VI-7 C. 3.
X NRC to DPC 10/29/79 VIII-4 DL/SEPB 7
NRC to DPC 09/09/81 (2-21)
LACROSSE TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO, REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 48 DPC 10 NRC 02/26/82 XV-10 X
HRC to DPC 10/29/79 IX-2 X
NRC to DPC 05/07/81 XV-11 DSI/CPB 7
NRC TO DPC 04/05.'82 IX-3 DL/SEPR 7
NRC TO DPC 07/20/82 XV-12 X
NRC to DPC 10/29/79 IX-4 X
N2C to DPC 10/29/79 XV-13 DSI/CPB 7(DOSES) HRC TO DPC 07/20/82 DSI/AEB 7(SYS)
HRC TO DPC 04/05/82 IX-5 DL/SEPB 4A 08/13/82 XV-14 DSI/RSB 7
NRC TO DPC 08/06/82' IX-6 DSI/ASB 2
NRC TO DPC 05/10/82 XV-15 DSI/R$5 7
X NRC to DPC 05/07/81 XV-16 DSI/AEB 48 DPC TO NRC 03/09/82 XI-1 X
NRC to DPC 12/04/81 XV-17 X
NRC to DPC 10/29/79 XI-2 X
NRC to DPC 12/04/81 XV-18 CSI/AEB 7
NRC TO DPC 08/06/82 XIII-1 X
NRC to DPC 05/07/81 XV-19 DST /AEB 4B(DOSES)DPC TO NRC 05/28/82
+
XIII-2 DL/SSPB 7
NRC to DPC 03/11/81' DSI/RSB 7(SYS)
HRC TO DPC 08/06/82 XV-1 DSI/RSB 4A 08/23/82 XV-20 DSI/AEB 48 DPC TO NRC 03/12/82 XV-2 X
NRC to DPC 10/29/79 XV-21 X
NRC to DPC 05/07/81 XV-3 DSI/RSB 7
NRC to DPC 11/13/81 XV-22 X
WRC to DPC 05/07/81 XV-4 DSI/R$8 7
NRC to DPC 11/03/81 XV-23 X
NRC to DPC 05/07/81 XV-5 DSI/R$B 7
NRC TO DPC 08/24/82 XV-24 X
NRC to DPC 05/07/81 XV-6 X
f4RC to DPC 10/29/79 XVI X
NRC to DPC 11/05/80 XV-7 DSI/RSB 7
NRC TO DPC 08/06/82 XVII DL 7
NRC to DPC 08/17/78 XV-8 DSI/CPB 7
NRC TO DPC 04/05/82 XV-9 DSI/R$B 4b DPC to NRC 08/25/81 (2-22)
MILLSTONE 1 FACILITY: MILLSTONE 1 TOPIC NO.
REVIEW STATUS REMARKS DIV/BR LICENSEE: NORTHEAST NUCLEAR ENERGY 11-1 A.
DE/SAB 7
NRC to NU 07/31/81 REGION /LOCATIDH: 5 MILES SOUTH WEST OF NEW LONDON, CONN.
II-1 B.
DE/SAB 7
HRC to NU 11/27/81 DOCKET NO.*
2:000245 II-1 C.
DE/SAB 7
NRC to NU 08/04/82 POWER CAPACITY: 2011CTHERMAL) 0660(ELECTRICAL)
~
II-2 8.
X HRC to NU 05/07/81 N.S.S.S.
GE.
II-2 C.
DSI/AEB 7
NRC to NU 12/23/81 A/E FIRM: EBASCO II-2 D.
X NRC to NU 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL II-3 A.
DE/HGEB 7
NRC TO HU 06/30/82 OPLkATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD II-3 B.
DE/HGEB 7
NRC TO NU 06/30/62 OPERATING REACTORS PRCJECT MANA6t2 J. SHEA II-3 B.
1.
DE/HGEB 7
NRC TO NU 06/30/82
~
PERSINKg h II-3 C.
DE/HGEB 7
HRC TO NU 06/30/82 INThGRATED ASSESSMENT PROJECT MANAGER: D.
.II-4 DE/GSB 7
HRC to NU 06/08/81 JLELLDR ST ATUS CODES.
~V 06/08/81 II-4 A.
DE/GSB 7
HRC to NU G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.
DE/GSB 7
NRC TO NU 05/11/82 FROM REVIEW BRANCH
~
II-4 C.
DE/CSB 7
NRC to NU 06/08/61 X - DELETED _
Ab-SAR RECEIVED FROM 0 - TOPIC NOT LICENSEE II-4 D.
DE/HGEB 7
NRC TO NU 06/30/82 STARTED S
DRAFT SE SENT~
II-4 E.
X NRC to NU 11/16/79 1 - QUESTIONS RECEIVED-TO UTILITY FROM REVIEW BRANCH II-4 F.
DE/HGEB 5
NRC TO NU 06/15/82 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT, BY NRC III-1 DL/SEPB 5(Elec) NRC TO NU 02/01/82 7G UTILITY DL/SEPB 5(SYS)
NRC TO NU 05/05/82 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 5
NRC TO NU 05/10/82 RECEIVED BY NRC (2-23)
MILLSTONE 1 TOPIC NO.
REdiEW STATUS REMARKS TOPIC HO.
REVIEW STATUS REMARKS DIV/BR DIV/BR III-5 A.
DE/SEB 5
NRC to NU 05/11/81 111-10 8.
X NRC to NU 11/15/79 III-3 B.
X HRC to NU 12/26/83 III-10 C.
DL/SEPB 7
NU to NRC 08/29/79 s
III-3 C.
DE/HGEB 7
HRC TO NU 06/23/82 III-11 X
NRC to NU 05/07/81 III-4 A.
DSI/ASB 7
NRC TO NU 05/25/82 III-12 X
NRC to NU 05/07/81
}II-4B.
DE/MTEB 7
NRC TO HU 06/29/82 IV-1 A.
DL/SEPB 7
HU to NRC
'02/12/79 III-4 C.
D3I/ASB 7
HRC TO MU 06/09/82 IV-2 DSI/ICSB 6
NU TO HRC 08/02/82 III-4 D.
~ - DE/S AB 7
84tC to NU 11/27/81 IV-3 DL 7
NRC to NU 02/22/82 III-5 A.
DL/SEPB 7
NRC TO NU 06/24/42 V-1 X
NRC to NU 11/27/81 III-5 B.
DL/SEPB 6
HU TO HRC 06/28/82 V-2 X
NRC to NU 11/16/79 III-6 DL/SEPB 7
NRC TO NU 06/30/82 V-3 X
NRC to NU 05/07/81 III-7 A.
X NRC to NU 05/07/88 V-4 X
HRC to NU 05/07/81 III-7 B.
DL/SEPB 7
HRC TO NU 08/11/82 V-5 DL/SEPB 7
NRC to NU 08/28/81 III-7 C.
X NRC to NU 11/16/79 V-6 DL/SEPB 7
HRC to NU 03/05/80 III-7 D.
DE/SEB 7
HU to NRC 02/17/81 V-7 X
HRC to NU 05/07/81 III-8 A.
DSI 7
HRC TO NU 03/03/82 V-8 X
HRC to NU 05/07/81 III-8 B.
X HRC to NU 09/26/80 V-9 X
NRC to NU 11/16/79 III-8 C.
DL/SEPB 7
HRC TO MU 06/24/82 V-10 A.
DL/SEPB 7
HU to NRC 03/05/79 III-8 D.
X HRC to NU 05/07/81 V-10 B.
DL/SEPB 7
NU to NRC 07/22/81 III-9 X
NRC to NU 05/07/81 V-11 A.
DL/SEPB 7
HRC to NU 07/08/81 III-10 A.
DL/SEPB 7
HRC to NU 04/07/82 V-11 B.
DL/SEPB 7(Sys)
NU to NRC 07/22/81 DL/SEPB 5(Elec) HRC to NU 02/01/82 (2-24)
~~
MILLSTONE 1 TOPIC NO.
REVIEW ~ STATUS
' REMARKS, TOPIC N3.
REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.
DL/SEPS 7
NRC to NU 12/17/79 WI-7 D.
DL/SEPS 7
NRC to NU 98/17/7&
V-13L X
HRC to NU'
.05/07/81 VI-7 E.
X HRC to NU 05/07/81' VI-1 DE/CEB 7
NRC to MU 02/26/82' VI-7 F.
X NRC to MU 11/16/79 VI-2 A.
X NRC to NU 05/07/81 VI-8 X
HRC to MU 05/07/81 j
VI-2 B.
X HRC to NU 05/07/81 VI-9.
X NRC to NU 11/16/79 VI-2 C.
X NRC to MU 11/16/79 VI-10 A.
DL/SEPB 7
NRC to NU 10/08/81 t
VI-2 D.
DSI/CSB 6
NU TO MRC 08/26/82 VI-10 B.
DL/SEPB 7
NU to NRC 08/05/81 l.
l VI-3
.DSI/CSB 6
HU TO NRC 08/26/82 i
VII-1 A.
DL/SEPB 7
NRC to NU 07/23/81 VI-4 DSI/CSB 6(SYS)
HU TO HRC 04/14/82 DL/SEPB 7(ELEC) HRC TO MU 06/24/82 VII-1 B.
DL/SEPB 7
NRC to NU 08/17/78' VI-5 X
HRC to NU 05/07/81 VII-2 DL/SEPB 7
NU TO MRC 06/25/82~
VI-6 DSI/CSB 4A 06/01/82 VII-3 DL/SEPB 7(Sys)
NU to NRC 07/22/81 DL/SEPB 5(Elec) HRC to NU 02/01/82 VI-7 A.
1.
X NRC to NU 11/16/79 4
VII-4 X
NRC to NU.
05/07/81 VI-7 A. 2.
X HRC to NU 05/07/81 VII-5 X
NRC to NU 05/07/81 VI-7 A. 3.
DL/SEPB 7
HRC to NU 10/27/81 i
VI-7 A. 4.
DSI/CPB 7
NRC TO HU 03/11/82 i
VII-7 X
NRC to NU 11/16/79 i
VI-7 B.
X NRC to MU 11/16/79 VI-7 C.
DL/SEPB 7
HRC to NU 03/29/81 VIII-2 DL/SEPB 7
NRC to NU 09/30/81 VI-7 C.
1 DL/SEPB 7
NU to MRC 11/02/81 VIII-3 A.
DL/SEPB 7
NRC to NU 08/26/81 VI-7 C. 2.
DL/SEPB 7
NRC to NU 03/29/81 VIII-3 B.
DL/SEPB 7
NRC to NU 07/23/81 d
VI-7 C. 3.
X HRC to NU 11/16/79 l
VIII-4 DL/SEPB 7
NRC to MU 07/07/81 1
i i
l (2-25) m w.
MILLSTONE 1 TOPIC NO.
REVIEW STATUS REMARKS TOPIC HO.
REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 7
NRC 10 NU 03/09/82 XV-10 X
NRC to NU 11/16/79 IX-2 X
HRC to NU 05/07/81 XV-11 DSI/CPB 7
NRC to NU 10/14/81 IX-3 DL/SEPB 7
NRC TO NU 07/16/82 XV-12 X
HRC to NU 11/16/79 IX-4 X
NRC to NU 11/16/79 XV-13 DSI/CPB 7(Sys)
NU to NRC 09/09/81 DSI/AEB 7(Doses) NRC to NU 11/03/81 IX-5 DL/SEPB 6
NU TO HRC 07/29/82 XV-14 DSI/RSB 7
NRC to NU 09/18/81 IX-6 DE 7
NRC TO NU 06/15/82 XV-15 DSI/RSB 7
HRC to NU 10/28/81 X
X NRC to NU 05/07/81 XV-16 DSI/AEB 6
NU to NRC 01/13/82 XI-1 X
NRC to NU 12/94/81 XV-17 X
NRC to NU 11/16/79 XI-2 X
HRC to NU 12/04/81 XV-18 DSI/AEB 6
HU to NRC 01/13/82 XIII-1 X
HRC to NU 05/07/81 XV-19 DSI/RSB 7(Sys)
NRC to NU 08/26/81 XIII-2 DL/SSPB T
NRC TO NU 06/09/82 DSI/AEB 6(Doses) NU to NRC 01/13/82 XV-1 DSI/RSB 7
NRC to NU 12/31/81 XV-20 DSI/AEB 7
NRC to NU 11/03/81 XV-2 X
HRC to NU 11/16/79 XV-21 X
NRC to NU 05/07/81 XV-3 DSI/RSB 7
NRC to NU 09/t8/81 XV-22 X
NRC to NU 05/07/81 XV-4 DSI/RSB 7
NRC to NU 09/18/81 XV-23 X
NRC to NU 05/07/81 XV-5 DSI/RSB 7
HRC to NU 01/07/82 XV-24 X
NRC to NU 05/07/81 XV-6 X
HRC to NU 11/16/79 XVI X
NRC to NU 11/15/80 XV-7 DSI/RSB 7
NRC to NU 12/04/81 XVII DL 7
HRC to NU 08/17/78 XV-8 DSI/CPB 7
NRC to NU 08/26/81 XV-9 DSI/RSB 7
NRC to NU 01/12/32 (2-26) l l
l
0YSTER CREEK FACILITY: OYSTER CREEK 1 TOPIC HO.
REVIEW STATUS REMARKS DIV/BR LICENSEE: JERSEY CEHTRAL POWER 8 LIGHT 11-1 A.
D E/ S AB 7
HRC to JCPL 02/04/82 REGION / LOCATION: 9 MILES SOUTH OF TOMS RIVER, NJ.
II-1 B.
DE/SAB 7
HRC to JCPL 02/04/82 DOCKET NO.
05000219 II-1 C.
DE/SAB 7
HRC to JCPL 02/04/82 PCWER CAPACITY: 1930(THERMAL) 0650(ELECTRICAL)
II-2 A.
DSI/AEB 7
NRC to JCPL 11/16/81 OL NUMBER: DPR-16 II-2 B.
X NRC to JCPL 05/07/81
~
II-2 C.
DSI/AEB 7
HRC TO JCPL 03/16/82 II-2 D.
X HRC to JCPL 05/07/81 SYSTEMATIC EVALUATIDH PROGRAM BRANCH CHIEF: W.
RUSSELL II-3 A.
DE/HGEB 7
HRC TO JCPL 08/27/82 OPERATING REACTORS BRANCH CHIEF:
D. CRUTCHFIELD II-3 B.
DE/HGEB 7
HRC TO JCPL 08/27/82 OPERATING REACTORS PROJECT MANAGER: J. LOMBARDO II-3 B.
1.
DE/HGEB 7
HRC TO JCPL 08/27/82 FELLJhevd II-3 C.
DE/HGEB 7
HRC TO JCPL 08/27/82 INTEGRATED ASSESSMENT PROJECT MANAGER: R.
II-4 DE/GSB 7
HRC to JCPL 08/03/81 KEY FOR STATUS CODES II-4 A.
DE/GSB 7
HRC to JCPL 06/08/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.
DE/GSB 7
HRC to JCPL 08/03/81 FROM REVIEW BRANCH X - DELETED II-4 C.
DE/GSB 7
NRC to JCPL 06/08/81 4b-SAR RECEIVED FROM 0 - TOPIC NOT LICENSEE II-4 D.
DE/HGEB 7
HRC TO JCPL 06/28/82 STARTED 5 - DRAFT SE SENT II-4 E.
X HRC to JCPL 11/16/79 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.
DE/HGEB 7
HRC TO JCPL 06/15/82 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC III-1 Ds./SEPB 7(SYS)
HRC TO JCPL 08/30/82 DL/SEPB 7(Elec) HRC to JCPL 07/09/81 TO UTILITY 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 7
HRC TO JCPL 06/15/82 RECEIVED BY HRC (2-27)
OYSTER CREEK TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR III-5 A.
DE/SEB 7
NRC TO JCPL 05/14/82 III-10 B.
X NRC to JCPL 11/16/19 III-3 B.
X NRC to JCPL 12/26/80 III-10 C.
X NRC to JCPL 11/16/79 III-3 C.
DE/HGEB 7
NRC TO JCPL 08/27/82 III-11 X
NRC to JCPL 05/07/81 III-4 A.
DSI/ASB 7
NRC TO JCPL 08/27/82 III-12 X
NRC to JCPL 05/07/81 III-4 B.
DE/MTEB 7
NRC TO JCPL 06/28/82 IV-1 A.
DL/SEPB 7
NRC to JCPL 05/30/79 III-4 C.
DSI/ASB 7
NRC TO JCPL 06/15/82 IV-2 DSI/ICSB 7
NRC TO JCPL 06/18/82 III-4 D.
DE/SAB 7
NRC TO JCPL 06/21/82 IV-3 X
NRC to JCPL 05/07/81 III-5 A.
DL/SEPB 7
HRC TO JCPL 06/29/82 V-1 X
NRC to JCPL 11/27/81 III-5 B.
DL/SEPB 7
NRC TO JCPL 06/22/82 V-2 X
NRC to JCPL 11/16/79 III-6 DL/SEPB 7
NRC TO JCPL 05/12/82 V-3 X
NRC to JCPL 05/07/81 III-7 A.
X HRC to JCPL 05/07/S1 V-4 X
NRC to JCPL 05/07/81 III-7 B.
DL/SEPB 7
NRC TC JCPL 08/27/82 V-5 DL/SEPB 7
NRC to JCPL 02/22/82 III-7 C.
X NRC to JCPL 11/16/79 V-6 DL/SEPB 7
NRC to JCPL 03/05/80 III-7 D.
DE/SEB 7
NRC TO JCPL 03/08/82 V-7 X
NRC to JCPL 05/07/81 III-8 A.
DSI/CPB 7
NRC TO JCPL 02/29/82 V-8 X
HRC to JCPL 05/07/81 III-8 8.
X NRC to JCPL 09/26/80 V-9 X
NRC to JCPL 11/16/79 III-8 C.
DL/SEPB 7
NRC to JCPL 10/30/80 V-10 A.
DL/SEPB 7
JCPL to NRC 05/15/79 III-8 D.
X NRC to JCPL 05/07/81 V-10 B.
DL/SEPB 7
NRC to JCPL 09/25/80 III-9 X
NRC to JCPL 05/07/81 V-11 A.
DL/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)
HRC to JCPL 09/25/80 DL/SEPB 7(Elec) HRC to JCPL 07/09/81 (2-28)
OYSTER CREEK TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.
DL/SEPB 7
NRC TO JCPL 03/16/81 VI-7 D.
DL/SEPn 7
NRC to JCPL 08/17/78 V-13 X
NRC to JCPL 05/07/81 VI-7 E.
X HRC to JCPL 05/07/81 VI-1 DE/CEB 7
HRC TO JCPL 06/29/82 VI-7 F.
X NRC to JCPL 11/16/79 X
NRC to JCPL 05/07/81 VI-8 X
HRC to JCPL 05/07/81 X
NRC to JCPL 05/07/81 VI-9 X
NRC to JCPL 11/16/79 X
HRC to JCPL 11/16/79 VI-10 A.
DL/SEPB 7
NRC to JCPL 08/18/81
.SB 7
HRC TO JCPL 04/30/82 VI-10 B.
X NRC to JCPL 11/16/79
/1-3 DSI/CSB 7
NRC TO JCPL 04/30/82 VII-1 A.
DL/SEPB 7
NRC to JCPL 07/30/81 VI-4 DSI/CSB 7(SYS)
HRC TO JCPL 06/15/82 VII-1 B.
DL/SEPB 7
NRC to JCPL 12/28/81 DL/SEPB 7(Elec) HRC to JCPL 08/05/81 VII-2 DL/SEPB 7
HRC TO JCPL 06/29/81 VI-5 X
NRC to JCPL 05/07/81 VII-3 DL/SEPB 7(Sys)
HRC to JCPL 09/25/80 VI-6 DSI/CSB 7
HRC TO JCPL 03/04/82 DL/SEPB 7(Elec) NRC to JCPL 07/09/81 VI-7 A.
1.
X MRC to JCPL 11/16/79 VII-4 X
HRC to JCPL 05/07/81 VI-7 A. 2.
X NRC to JCPL 05/07/81 VII-5 X
NRC to JCPL 05/07/81 VI-7 A.
3.
DL/SEPB 7
HRC to JCPL 07/30/81 VII-6 DL/3EPB 7
HRC to JCPL 08/29/81 VI-7 A. 4.
DSI/RSB 7
NRC TO JCPL 08/27/82 VII-7 X
HRC to JCPL 11/16/79 VI-7 B.
X NRC to JCPL 11/16/79 VIII-1 A.
DSI/PSB 7
NRC to JCPL 03/03/82 VI-7 C.
DL/SEPB 7
HRC to JCPL 03/13/81 VIII-2 DL/SEPB 7
NRC to JCPL 06/29/81 VI-7 C.
1.
DL/SEPB 7
NRC to JCPL 06/29/81 VIII-3 A.
DL/SEPB 7
NRC to JCPL 06/29/81 VI-7 C. 2.
DL/SEPB 7
NRC to JCPL 03/13/81 VIII-3 B.
DL/SEPB 7
NRC to JCPL 06/29/81 VI-7 C. 3.
X NRC to JCPL 11/16/79 VIII-4 DL/SEPB 7
NRC TO JCPL 08/26/81 (2-29)
0YSTER CREEK TOPIC HO.
REVIEW STATUS REMARKS TOPIC H0.
REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 7
HRC 10 JCPL 06/01/82 XV-10 X
NRC to JCPL 11/16/79 IX-2 X
HRC to JCPL 05/07/81 XV-11 DSI/CPB 7
HRC TO JCPL 05/17/82 IX-3 DSI/ASB 7
HRC to JCPL 11/13/81 XV-12 X
NRC to JCPL 11/16/79 1X-4 X
NRC to JCPL 05/07/81 XV-13 DSI/AEB 5(DOSES) HRC TO JCPL 05/28/82 DSI/CPB 7(SYS)
HRC to JCPL 05/17/82 IX-5 DL/SEPB 7
NRC TO JCPL 06/28/82 XV-14 DSI/RSB 7
NRC to JCPL 07/16/81 IX-6 DE 7
HRC TO JCPL 06/15/82 XV-15 DSI/R$B 7
HRC to JCPL 12/04/81 X
X HRC to JCPL 05/07/81 XV-16 DSI/AEB 5
HRC TO JCPL 06/29/82 XI-1 X
HRC to JCPL 12/04/81 XV-17 X
HRC to JCPL 11/16/79 XI-2 X
HRC to JCPL 12/04/81 XV-18 DSI/AEB 5
HRC TO JCPL 05/28/82 XIII-1 X
HRC to JCPL 05/07/81 XV-19 DSI/AEB 5(DOSES) HRC TO JCPL 06/29/82 XIII-2 DL/SSPB 7*
NRC to JCPL 09/25/80 DSI/RSB 7(Sys)
HRC to JCPL 09/04/81 XV-1 DSI/RSB 7
HRC to JCPL 12/07/81 XV-20 DSI/AEB 5
HRC TO JCPL 05/12/82 XV-2 X
HRC to JCPL 11/16/79 XV-21 X
HRC to JCPL 05/07/81 XV-3 DSI/RSB 7
NRC to JCPL 07/16/81 XV-22 X
NRC to JCPL 05/07/81 XV-4 DSI/RSB 7
HRC to JCPL 07/16/81 XV-23 X
HRC to JCPL 05/0//81 XV-5 DSI/RSB 7
HRC to JCPL 12/07/81 XV-24 X
NRC to JCPL 05/07/81 XV-6 X
HRC to JCPL 11/16/79 XVI X
HRC to JCPL 11/05/80 XV-7 DSI/RSB 7
NRC to JCPL 12/04/81 XVII DL 7
HRC to JCPL 08/17/78 XV-8 DSI/CPB 7
HRC TO JCPL 05/17/82 XV-9 DSI/RSB 7
HRC to JCPL 01/07/82 (2-30)
PALISADES FACILITY: PALISADES TOPIC NO.
REVIEW STATUS REMARKS DIV/BR LICENSEE: CONSUMERS POWER II-1 A.
DL/SEPB 1
CPCo to NRC 12/28/79 REGION / LOCATION: 5 MILES SOUTH OF SOUTH HAVEN, MI.
II-1 B.
DL/SEPB 7
CPCo to NRC 12/28/79 DOCKET NO: 05000255 II-1 C.
DL/SEPB 7
CPCo to NRC 05/13/81 POWER CAPACITY: 2530(THERMAL) 0805(ELECTRICAL)
II-2 A.
DSI/AEB 7
NRC to CPCo 6/30/81 OL NUMBER: DPR-20 II-2 B.
X hgM 05/07/81 N.S.S.S.
C-E II-2 C.
DSI/AEB Hi t
4/23/81 II-2 D.
CPCo 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL II
/H EB NRC to CPCo 02/19/82 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD I
GEB 7
HRC to CPCo 02/19/82 OPERATING REACTORS PROJECT MANAGER: T. WAMBACH I
1 DE/HGEB 7
NRC to CPCo 02/19/82 INTEGRATED ASSESSMENT PROJECT MANAGER:
T.
II-3 C.
B 7
NRC to CPCo 02/19/82 1
V I-4 D
7 CPCo to NRC 07/22/81 KEY FOR STAT M O J-T[
)
I-4 DE/GSB 7
RC to CPCo 06/08/81 IPCo to NRC 07/22/81 G-GH-I DRAFT SE RECEIV D B.
DE I
FROM REVIEW CH l
II-4 D
B NRC to CPCo 06/08/81 L-s X - D LE E l
0-T OT E E I-DE EB 7
CPCo to NRC 06/01/81 5 - DRAFT SE SENT
,I -
X NRC to CPCo 11/16/79 1 - QUEST ONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.
DE/HGEB 7
CPCo to NRC 06/01/81 2 - CUESTIONS SENT III-1 DL/SEPB 7(Elec) HRC to CPCo 11/12/80 TO UTILITY DL/SEPB 7(Sys)
HRC to CPCo 02/08/82 7 - TOFEC LETE 3 - QUESTION RESPONSE
\\
RECEIVED BY HRC (2-31)
PALISADES TOPIC NO.
REVIEW STATUS REMARKS TOPIC HO.
REVIEW STATUS REMARKS DIV/BR DIV/BP III-2 DL/SEPB 7
HRC to CPCo-02/08/82 III-10 B.
DL/SEPB 7
NRC to CPCo 02/02/82 III-3 A.
DE/SEB 7
NRC to CPCo 08/26/81 III-10 C.
X HRC to CPCo 11/16/79 III-3 B.
X HRC to CPCo 12/26/80 III-11 X
NRC to CPCo 05/07/81 III-3 C.
DE/HGEB 7
NRC to CPCo 02/22/82 III-12 X
HRC to CPCo 05/07/81 III-4 A.
DSI/AEB 7
NRC to CPCo 02/02/82 IV-1 A.
DL/SEPB 7
CPCo to NRC 02/08/79 III-4 B.
DE/MTEB 7
NRC to CPCo 02/08/82 IV-2 DSI/ICSB 7
NRC to CPCo 02/08/82 III-4 C.
DSI/ASB 7
NRC to CPCo 09/21/81 IV-3 X
NRC to CPCo 05/07/81 III-4 D.
DE/SAB 7
CPCo to NRC 08/03/81 V-1 X
NRC to CPCo 11/27/81 III-5 A.
DL/SEPB 7
NRC to CPCo 02/08/82 V-2 X
NRC to CPCo 11/16/79 III-5 B.
Dt./SEPB 7
NRC to CPCo 02/19/82 V-3 X
HRC to CPCo 05/07/81 III-6 DL/SEPB 7
CPCo to NRC 12/16/81 V-4 X
NRC to CPCo 05/07/81 III-7 A.
DL/SEPB 7
HRC to CPCo 02/10/82 V-5 DL/SEPB 7
NRC to CPCo 02/04/82 III-7 B.
DL/SEPB 7
NRC to CPCo 02/12/82 V-6 DL/SEPB 7
NRC to CPCo 03/05/80 III-7 C.
DE/SEB 7
NRC to CPCo 10/19/81 V-7 DSI/ASB 7
NRC to CPCo 11/16/81 III-7 D.
DE/SEB 7
CPCo to NRC 08/17/81 V-8 X
NRC to CPCo 05/07/81 III-8 A.
DSI 7
NRC to CPCo 11/18/81 V-9 X
HRC to CPCo 11/16/79 III-8 B.
X NRC to CPCo 10/01/80 V-10 A.
DL/SEPB 7
NRC to CPCo 09/26/81 III-8 C.
DL/MTEB 7
CPCo to NRC 12/28/79 V-10 B.
DL/SEPB 7
CPCo to NRC 12/23/81 III-8 D.
X NRC to CPCo 05/07/81 V-11 A.
DL/SEPB 7
HRC to CPCo 11/09/81 III-9 X
HRC to CPCo 05/07/81 V-11 B.
DL/SEPB 7(Sys)
HRC to CPCo 12/23/81 DL/SEPB 7(Elec) HRC to CPCo 12/24/81 III-10 A.
DL/SEPB 7
NRC to CPCo 05/19/81 (2-32)
PALISADES TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.
X NRC to CPCo 11/16/79 VI-7 D.
DL/SEPB 7
NRC to CPCo 08/17/78 V-13 X
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 10/29/81 VI-2 A.
X NRC to CPCo 05/07/81 VI-8 X
NRC to CPCo 05/07/81 VI-2 B.
X NRC to CPCo 05/07/81 VI-9 X
NRC to CPCo 11/16/79 VI-2 C.
X NRC to ChCo 11/16/79 VI-10 A.
DL/SEPB 7
NRC to CPCo 10/16/81 VI-2 D.
DSI/CSB 7
NRC to CPCo 11/16/81 VI-10 B.
X NRC to CPCo 11/16/79 VI-3 DSI/CSB 7
HRC to CPCo 11/16/81 VII-1 A.
DL/SEPB 7
NRC to CPCo 08/28/81 VI-4 DL/SEPB 7(Elec) CPCo to NRC 08/18/81 VII-1 B.
DL/SEPB 7
NRC to CPCo 08/17/78 DCI/CSB 7(Sys)
NRC to CPCo 02/08/82 VII-2 DL/SEPB 7
NRC to CPCo 05/19/81 VI-5 X
NRC to CPCo 05/07/81 VII-5 DL/SEPB 7(Sys)
CPCo to NRC 12/23/81 VI-6 DSI/CSB 7
NRC to CPCo 12/11/81 DL/SEPB 7(Elec) CPCo to NRC 12/31/81 VI-7 A.
1.
X NRC to CPCo 11/16/79 VII-4 X
NRC to CPCa 05/07/81 VI-7 A. 2.
X NRC to CPCo 05/07/81 VII-5 X
NRC to CFCo 05/07/81 VI-7 A.
3.
DL/SEPB 7
NRC to CPCo 12/18/81 VII-6 DL/SEPB 7
NRC to Cpcc 05/19/81 VI-7 A.
4.
X NRC to CPCo 05/07/81 VII-7 X
NRC to CPGo 11/16/79 VI-7 3.
DL/SEPB 7(Elec) HRC to CPCo 05/19/81 VIII-1 A.
DSI/PSB 7
HRC to CPCo 12/22/81 DSI/RSB 7(Sys)
HRC to CPCs 06/30/81 VIII-2 DL/SEPB 7
NRC to CPCo 10/29/81 VI-7 C.
DL/SEPB 7
NRC to CPCo 02/20/81 VIII-3 A.
DL/SEPB 7
NRC to CPCo 05/22/81 VI-7 C.
1.
DL/SEPB 7
NRC to CPCo 10/14/81 VIII-3 B.
DL/SEPB 7
NRC to CPCo 08/05/81 VI-7 C. 2.
DL/SEPB 7
NRC to CPCo 02/20/81 VIII-4 DL/SEPB 7
NRC to CPCo 07/31/81 VI-7 C.
3.
X CPCo to NRC 12/12/79 (2-33)
PAUSADES TOPIC NO.
REVIEW STATUS REMARKS TCPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 7
NRC to CPCo 02/08/82 XV-10 DL/SEPB 7
NRC to CPCo 11/03/81.
IX-2 X
NRC to CPCo 05/07/81 XV-11 X
NRC to CPCo 10/01/80 IX-3 DL/SEPB 7
HRC to CPCo 02/22/82 XV-12 DL/SEPB 7(Doses) HRC to CPCo 12/04/81 DL/SEPB 7(Sys)
HRC to CPCo 11/03/81 IX-4 DSI/RSB 7
NRC to CPCo 02/08/82 XV-13 X
NRC to CPCo 11/16/79 IX-5 DL/SEPB 7
NRC to CPCo 02/11/82 XV-14 DL/SEPB 7'
NRC to CPCo 11/03/81 IX-6 DE 7
NRC TO CPC0 04/07/82 XV-15 DL/SEPB 7
NRC to CPCo 11/05/81 X
X NRC to CPCo 05/07/81 XV-16 DL/SEPB 7
NRC to CPCo 11/03/81-XI-1 X
NRC to CPCo 12/04/81 XV-17 DL/SEPB 7(Doses) NRC to CPCo 11/03/81 XI-2 X
NRC to CPCo 12/04/81 DL/SEPB 7(Syr)
NRC to CPCo 11/03/81 XIII-1 X
HRC to rico 05/07/81 XV-18 X
NRC to CPCo 10/01/80 XIII-2 DL/SSPB 7
HRC to CPCo 10/01/80 XV-19 DL/SEPB 7(Doses) HRC to CPCo 11/03/81 DL/SEPB 7(Sys)
HRC to CPCo 11/03/81 XV-1 DL/SEPB 7
NRC to CPCo 11/03/81 XV-20 DL/SEPB 7
NRC to CPCo 11/03/81 XV-2 DL/SEPB 7(Doses) NRC to CPCo 11/03/81 DL/SEPB 7(Sys)
HRC to CPCo 11/03/81 XV-21 X
'NRC to CPCo 05/07/81 XV-3 DL/SEPB 7
HRC to CPCo 11/03/81 XV X NRC to CPCo 05/07/81 XV-4 DL/SEPB 7
NRC to CPCo 11/03/81 XV-23 X
HRC to CPCo 05/07/81 XV-5 DL/SEPB 7
NRC to CPCo 11/03/81 XV-24 X
NRC to CPCo~
05/07/81 XV-6 DL/SEPB 7
NRC to CPCo 11/03/81 XVI X
NRC to CPCo 11/05/80 XV-7 DL/SEPB 7
NRC to CPCo 11/03/81 XVII DL 7
HRC to CPCo
-08/17/78 XV-8 DL/SEPB 7
.HRC to CPCo 11/03/81 XV-9 DL/SEPB 7
NRC to CPCo 11/03/81 A
(2-34)
SAN ON0FRE FACILITY: SAN OHOFRE 1 TOPIC HO.
REVIEW STATUS REMARKS DIV/BR LICENSEE: SOUTHERH CALIFORHIA EDISON 11-1 A.
DL/SEPB 7
NRC to SCE 11/07/79 REGIDH/ LOCATION: 5 MILES SOUTH OF SAN CLEMENTE, CA.
II-1 B.
DL/LEPB 7
HRC to SCE 11/07/79 DOCKET NO.
05000206 II-1 C.
DC/SAB 4b
- 4CE to NRC 11/12/81 POWER CAPACITY: 1347(THERMAL) 0430(ELECTRICAL)
II-2 A.
DSI/AEB 7
HRC to SCE 04/27/81 OL NUMBER: DPR-13 II-2 B.
X HRC to SCE 05/07/81 H.S.S.S.: WEST.
II-2 C.
DSI/AEB 7
HRC to SCE 11/18/81 A/E FIRM BECH.
II-2 D.
X NRC to SCE 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL II-3 A.
DE/HGEB 3
SCE TO NRC 03/15/82 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD II-3 B.
DE/HGEB 3
SCE TO HRC 04/12/82 OPERATING REACTORS PROJECT MANAGER: W. PAULSON II-3 B.
1.
DE/HGEB 3
SCE TO NRC 04/12/82 INTEGRATED ASSESSMENT PROJECT MANAGER: E. MCKENNA {' 24j)){
II-3 C.
DE/HGEB 2
HRC to SCE 01/07/82 II-4 DE/GSB 5
HRC to SCE 03/15/81 KEY FOR STATUS CODES II-4 A.
DE/GSB 5
HRC TO SCE 04/05/82 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.
DE/GSB 5
HUREG-0712 12/80 FROM REVIEW BRANCH X - DELETED II-4 C.
DE/GSB 5
NRC TO SCE 04/05/82 4b-SAR RECEIVED FROM 0 - TOPIC NOT LICENSEE II-4 D.
DE/HGEB 4b SCE to NRC 11/02/81 STARTED 5 - DRAFT SE SENT II-4 E.
X NRC to SCE 11/16/79 1 - QUESTI0HS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.
DE/HGEB 4b SCE to NRC 11/02/81 6 - SE RESP 0 HSE RECEIVED 2 - QUESTIONS SEHT BY NRC III-1 DL/SEPB 5(SYS)
HRC TO SCE 06/25/82 TO UTILITY DL/SEPB 7(Elec) Part of VII-3 11/18/81 7 - TOPIC COMPLETE 3 - QUESTION RESP 0 HSE III-2 DL/SEPB 4B SCE TO NRC 05/04/82 RECEIVED BY NRC (2-35)
SAN ONOFRE TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS R EMARKS DIV/BR DIV/BR III-5 A.
DE/SEB 3
SCE to NRC 09/08/80 III-10 B.
DL/SEPB 7
NRC to SCE 11/08/79 III-3 5.
X NRC to SCE 11/16/79 III-10.C.
X NRC to SCE 11/16/79 III-3 C.
DE/HGEB 7
NRC to SCE 11/27/81 III-11 X
NRC to SCE 05/07/81 III-4 A.
DSI/ASB 4B SCE TO NRC 05/04/82 III-12 X
NRC to SCE 05/07/81 III-4 B.
DE/NTEB 5
NRC TO SCE 06/24/82 IV-1 A.
DL/SEPB 7
NRC to SCE 11/13/79 III-4 C.
DSI/ASB 4B SCE TO HRC 04/29/82 IV-2 DSI/ICSB 4A 08/25/82 III-4 D.
DE/SAB 4b SCE to NRC 10/23/81 IV-3 X
NRC to SCE 05/07/81 III-5 A.
DL/SEPB 0
V-1 X
NRC to SCE 11/27/81 III-5 B.
DL/SEPB 0
v-2 X
NRC to SCE 11/16/79 III-6 DL/SEPB 3
SCE to NRC 12/08/81 V-3 X
NRC to SCE 05/07/81 III-7 A.
X NRC to SCE 05/07/81 V-4 X
NRC to SCE 05/07/81 III-7 B.
DL/SEPB 3
SCE to NRC 11/20/81 V-5 DL/SEPB 5
NRC to SCE 06/03/81 III-7 C.
X NRC to SCE 11/16/79 V-6 DL/SEPB 7
NRC to SCE 03/05/80 III-7 D.
DE/SEB 7
NRC TO SCE 04/23/82 V-7 DSI/ASB 7
NRC to SCE 12/04/81 III-8 A.
DSI 7
NRC to SCE 12/21/81 V-8 X
NRC to SCE 05/07/81 III-8 B.
X HRC 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
NRC to SCE 01/07/81 LII-8 D.
X NRC to SCE 05/07/81 V-10 B.
DL/SEPB 6
SCE TO NRC 04/26/82 III-9 X
HRC to SCE 05/07/81 V-11 A.
DL/SEPB 7
NRC to SCE 08/03/81 III-10 A.
DL/SEPB 7
SCE to NRC 07/24/81 V-11 B.
DL/SEPB 6(SYS)
SCE TO NRC 04/26/82 DL/SEPB 7(Elec) HRC to SCE 02/04/82 (2-36)
SAN ON0FRE TOPIC NO.
REVIEW STATUS REMARKS TOPIC NG.
REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.
X NRC to SCE 11/16/79 VI-7 D.
DL/SEPB 7
HRC to SCE 08/17/78 V-13 X
HRC to SCE 05/07/81 VI-7 E.
X NRC to SCE 05/07/81 VI-1 7
NRC TO SCE 07/13/82 VI-7 F.
X HRC to SCE 11/16/79 VI-2 A.
X HRC to SCE 05/07/81 VI-8 X
HRC to SCE 05/07/81 VI-2 B.
X 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 7
NRC to SCE 08/28/81 VI-2 D.
DSI/CSB 7
HRC TO SCE 05/27/82 VI-10 B.
DL/SEPB 7
HRC to SCE 11/15/79 VI-3 DSI/CSB 7
NRC TO SCE 05/27/82 VII-1 A.
DL/SEPB 7
HRC to SCE 07/09/81 VI-4 DSI/CSB 5(SYS)
HRC TO SCE 03/03/82 DL/SEPB 7(Elec) HRC to SCE 09/03/81 VII-1 B.
DL/SEPB 7
HRC to SCE 08/17/78 VI-5 X
NRC to SCE 35/07/81 VII-2 DL/SEPB 7
NRC to SCE 11/17/81 VI-6 DSI/CSB 7
HRC TO SCE 08/12/82 VII-3 DL/SEPB 6(SYS)
SCE TO HRC 04/26/82 DL/SEPB 7(Elec) HRC to SCE 06/04/82 VI-7 A.
1.
DL/SEPB 7
NRC to SCE O2/20/81 VII-4 X
HRC to SCE 05/07/81 VI-7 A. 2.
X HRC to SCE 05/07/81 VII-5 X
HRC to SCE 05/07/81 VI-7 A.
3.
DL/SEPB 7
NRC to SCE 11/18/81 VII-6 DL/SEPB 7
HRC to SCE 08/28/81 VI-7 A. 4.
X HRC to SCE 05/07/81 VII-7 X
NRC to SCE 11/16/79 VI-7 B.
DSI/RSB 6(SYS)
SCE TO HRC 01/26/82 DL/SEPB 7(Elec) HRC to SCE 09/04/81 VIII-1 A.
DSI/RSB G
HRC to SCE 05/07/81 VI-7 C.
DL/SEPB 7
HRC to SCE 06/01/81 VIII-2 DL/SEPB 7
HRC to SCE 07/31/81 VI-7 C.
1 DL/SEPB 7
HRC to SCE 08/03/81 VIII-3 A.
DL/SEPB 7
HRC to SCE 11/07/79 VI-7 C. 2.
DL/SEPB 7
NRC to SCE 06/01/81 VIII-3 B.
DL/SEPB 7
HRC to SCE 07/24/81 VI-7 C. 3.
X NRC to SCE 11/16/79 VIII-4 DL/SEPB 6
SCE TO HRC 05/26/82 (2-37)
SAN ONOFRE TOPIC NO.
REVIEW STATUS REMARKS TOPIC HO.
REVIEW STATUS RENARKS DIV/BR DIV/BR IX-1 DSI/ASB 48 SCE TO FRC 04/29/82 XV-10 DSI/RSS 7
NRC TO SCE 04/20/82 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 04/05/82 DL/SEPB 7(Doses) HRC to SCE 01/29/80 IX-4 DSI/RSB 7
HRC to SCE 08/24/82 XV-13 X
HRC to SCE 11/16/79 IX-5 DL/SEPB 4A 07/02/82 XV-14 DSI/RSB 7
NRC to SCE 05/07/81 XV-15 DSI/RSB 7
HRC TO SCE 04/20/82 X
X NRC to SCE 05/07/81 XV-16 DSI/AEB 7
NRC to SCE 04/05/82 XI-1 X
NRC to SCE 12/04/81 XV-17 DSI/RSB 7(Sys)
SCE TO NRC 03/12/82 XI-2 X
HRC to SCE 12/04/81 DSI/AEB 7(Doses) NRC to SCE 01/29/80 XIII-1 X
HRC to SCE 05/07/81 XV-18 X
NRC to SCE 10/01/80 XIII-2 DL/SSPB 7
NRC to SCE 01/22/81 XV-19 DSI/RSB 7(Sys)
SCE TO HRC 03/12/82 DL/SEPB 7(Doses) HRC to SCE 01/29/80 XV-1 DSI/RSB 7
NRC TO SCE 07/22/82 XV-20 DL/SEPB 7
NRC to SCE 03/28/80 XV-2 DSI/RSB 6(Sys)
SCE to NRC 03/12/82 DL/SEPB 7(Doses) HRC to SCE 01/29/80 XV-21 X
NRC to SCE 05/07/81 XV-3 DSI/RSB 7
NRC TO SCE 03/12/82 XV-22 X
HRC to SCE 05/07/81 XV-4 DSI/RSB 7
HRC to SCE 04/05/82 XV-23 X
NRC to SCE 05/07/81 XV-5 DSI/RSB 7
NRC to SCE 02/01/82 XV-24 X
HRC to SCE 05/07/81 XV-6 DSI/RSB 7
HRC TO SCE 03/03/82 XVI X
HRC to SCE 11/05/80 XV-7 DSI/RSB 4b SCE to NRC 07/01/81 XVII DL 7
NRC to SCE 11/20/79 XV-8 DSI/CPB 7
SCE TO HRC 03/12/82 XV-9 DSI/RSB 7
HRC to SCE 02/24/82 (2-38)
YANKEE FACILITY: YANKEE NUCLEAR POWER STATIDH TOPIC HO.
REVIEW STATUS REMARKS DIV/BR LICENSEE: YANKEE ATOMIC ELECTRIC II-1 A.
DE/SAB 7
NRC TO YAEC 07/t3/82 REGIDH/ LOCATION: 25 MILES HORTH EAST OF PITTSFIELD, MASS.
II-1 B.
DE/SAB 7
NRC TO YAEC 07/13/82 DOCKET NO.
05000029 II-1 C.
DE/SAB 7
HRC TO YAEC 07/13/82 POWER CAPACITY: 600(THERMAL) 165(ELECTRICAL)
II-2 A.
DSI/AEB 7
NRC to YAEC 08/03/81 OL NUMBER: DPR-3 II-2 B.
X HRC to YAEC 05/07/81 H.S.S.S.: WEST.
II-2 C.
D5I/AEB 7
HRC to YAEC 09/04/81 A/E FIRM: S&W II-2 D.
X HRC to YAEC 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL II-3 A.
DE/HGEB 6
YAEC to NRC 03/16/81 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD II-3 B.
DE/HGEB 6
YAEC to NRC 03/16/81 OPERATING REACTORS PROJECT MANAGER:
R. CARUS 0 II-3 B.
1.
DE/HGEB 5
HRC to YAEC 02/09/81 INTEGRATED ASSESSMENT PROJECT MANAGER M. BOYLE jr II-3 C.
DE/HGEB 4A 08/27/82 II-4 DE/GSD 7
HRC to YAEC 07/15/82 KEY FOR STATUS CODES G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.
DE/GSB 7
HRC TO YAEC 07/15/82 FROM REVIEW BRANCH X - DELETED II-4 C.
DE/GSB 7
HRC to YAEC 06/08/81 4b-SAR RECEIVED FROM 0 - TOPIC NOT LICENSEE II-4 D.
DE/HGEB 4A 08/26/82 STARTED 5 - DRAFT SE SENT II-4 E.
DE/HGEB 4A 08/31/82 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.
DE/HGEB 4A 08/31/82 6 - SE RESPONSE RECFIVED 2 - QUESTIONS SENT BY NRC III-1 DL/SEPB 7(Elec) HRC to YAEC 02/02/82 DL/SEPB 7(SYS)
HRC TO YAEC 06/18/82 TO UTILITY 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 7
NRC TO YAEC 08/31/82 RECEIVED BY HRC (2-39)
YANKEE TOPIC HO.
REVIEW STATUS REMARKS TOPIC H0.
REVIEW STATUS REMARKS DIV/BR DIV/BR III-3 A.
DE/SEB 4A 08/27/82 III-10 8.
X NRC to YAEC 11/16/79 III-3 B.
X HRC to YAEC 12/26/80 III-10 C.
X NRC to YAEC 11/16/79 III-3 C.
D E/HCEB 4A 08/26/82 III-11 X
HRC to YAEC 05/07/81 III-4 A.
DSI/ASB 7
HRC TO YAEC 08/31/82 III-12 X
NRC to YAEC 05/07/81 III-4 B.
DE/MTEB 7
HRC to YAEC 02/08/82 IV-1 A.
DL/SEPB 7
HRC to YAEC 04/18/79 III-4 C.
DSI/ASB 4B YAEC TO HRC 03/18/82 IV-2 DSI/ICSB 7
HRC to YAEC 12/23/81 III-4 D.
DE/SAB 7
NRC TO YAEC 07/13/82 IV-3 X
HRC to YAEC 05/07/81 III-5 A.
DL/SEPB 7
HRC TO YAEC 08/20/82 V-1 X
HRC to YAEC 11/27/81 III-5 B.
DL/SEPB 7
HRC TO YAEC 06/29/82 V-2 X
HRC to YAEC 11/16/81 III-6 DL/SEPB 3
YAEC to HRC 06/30/81 V-3 X
HRC to YAEC 05/07/81 III-7 A.
X HRC to YAEC 05/07/81 V-4 X
HRC to YAEC 05/07/81 III-7 B.
DL/SEPB 3
YAEC to NRC 08/21/81 V-5 DL/SEPB 7
HRC TO YAEC 07/13/82 III-7 C.
X HRC to YAEC 11/16/79 V-6 DL/SEPB 7
HRC to YAEC 03/05/80 III-7 D.
DE/SEB 7
HRC TO YAEC 03/18/82 V-7 X
HRC to YAEC 12/14/81 III-8 A.
DSI 7
HRC to YAEC 12/29/81 V-8 X
HRC to YAEC 05/07/81 III-8 B.
X HRC to YAEC 10/01/80 V-9 X
HRC to YAEC 11/16/79 III-8 C.
DL/SEPB 7
HRC to YAEC 11/15/79 V-10 A.
DL/SEPB 7
HRC to YAEC 11/05/79 III-8 D.
X HRC to YAEC 05/07/81 V-10 8.
DL/SEPB 7
HRC to YAEC 02/01/82 III-9 X
HRC to YAEC 05/07/81 V-11 A.
DL/SEPB 7
HRC to YAEC 07/27/82 III-10 A.
DL/SEPB 7
HRC to YAEC 09/22/81 V-11 B.
DL/SEPB 7(Sys)
HRC to YAEC 02/01/82 DL/SEPB 7(Elec) NRC to YAEC 07/27/82 (2-40)
YANKEE TOPIC NO.
REVIEW STATUS REMARKS TOPIC HO.
REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.
X NRC to YAEC 11/16/79 VI-7 D.
DL/SEPB 7
NRC to YAEC 08/17/78 V-13 X
HRC to YAEC 05/07/81 VI-7 E.
X NRC to YAEC 05/07/81 VI-1 DE/CEB 4A Oles */42 VI-7 F.
DL/SEPB 7
NRC to YAEC 08/28/81 VI-2 A.
X HRC to YAEC 05/07/81 VI-8 X
NRC to YAEC 05/07/81 VI-2 B.
X HRC to YAEC 05/07/81 VI-9 X
HRC to YAEC 11/16/79 VI-2 C.
X HRC to YAEC 11/16/79 VI-10 A.
DL/SEPB 7
HRC to YAEC 06/10/82 a
VI-2 D.
DSI/CSB 7
HRC TO YAEC 08/20/82 VI-10 B.
X HRC to YAEC 11/16/79 VI-3 DSI/CSB 7
HRC TO YAEC 08/20/82 VII-1 A.
DL/SEPB 7
HRC to YAEC 02/22/82 f
VI-4 DSI/CSB 3(Sys)
YAEC to NRC 01/29/82 VII-1 8.
- DL/SEPS 7
HRC to YAEC 08/17/78 DL/SEPB 7(Flec) HRC to YAEC 03/05/82 l
VII-2 DL/SEPB 7
HRC to YAEC 02/01/82 VI-5 X
HRC to YAEC 05/07/81 VII-3 DL/SEPB 7(Sys)
HRC to YAEC 02/01/82 VI-6 DSI/CSB G
NRC to YAEC 05/07/81 DL/SEPS 7(Elec) HRC to YAEC 02/02/82 VI-7 A.
1.
DL/SEPB 7
NRC to YAEC 02/20/81 VII-4 X
NRC to YAEC 05/07/81 VI-7 A. 2.
X NRC to YAEC 05/07/81 VII-5 X
HRC to YAEC 05/07/81 VI-7 A. 3.
DL/SEPB 7
HRC to YAEC 02/08/82 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 8.
DSI/RSB 7(Elec) HRC to YAEC 06/04/81 VIII-1 A.
DSI/PSB 4A 08/31/82 7(SYS)
HRC TO YAEC 07/13/82 VI-7 C.
DL/SEPB 7
NRC to YAEC 03/13/81 VIII-2 DL/SEPB 7
NRC to YAEC 09/03/81 VI-7 C.
1 DL/SEPB 7
NRC to YAEC 09/14/81 VIII-3 A.
DL/SEPB 7
HRC to YAEC 11/07/79 VI-7 C.
2.
DL/SEPB 7
NRC to YAEC 03/13/81 VIII-3 B.
DL/SEPB 7
NRC to YAEC 08/28/81 VI-7 C. 3.
DL/SEPB 7
NRC to YAEC 07/24/80 VIII-4 DL/SEPB 7
HRC TO YAEC 08/13/82 i
.i (2-41)
_=
YANKEE TOPIC HO.
R EVI EW STATUS REMARKS TOPIC HO.
REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 4A 08/31/82 XV-10 DSI/R$8 7
NRC TO YAEC 04/26/82 IX-2 X
HRC to YAEC 05/07/81 XV-11 X
HRC to YAEC 10/01/80 IX-3 DL/SEPB 7
NRC TO YAEC 06/11/82 XV-12 DSI/CPB 7(SYS)
HRC TO YAEC 04/16/82 DSI/AEB 7(Doses) HRC to YAEC 12/29/81 IX-4 DSI/R$8 7
NRC TO YAEC 06/15/82 XV-13 X
HRC to YAEC 11/16/79 IX-5 DL/SEPB 7
NRC TO YAEC 06/14/82 IX-6 DE G
HRC to YAEC 05/07/81 XV-15 DSI/ ASB 7
HRC TO YAEC 05/10/82 X
X NRC to YAEC 05/07/81 XV-16 DSI/AEB 7
HRC TO YAEC 08/31/82 XI-1 X
HRC to YAEC 12/04/81 XV-17 DSI/R$8 7(SYS)
HRC TO YAEC 08/31/82 XI-2 X
HRC to YAEC 12/04/81 DSI/AEB 7(DOSES) HRC TO YAEC 03/30/82 XIII-1 X
NRC to YAEC 05/07/81 XV-18 X
HRC to YAEC 10/01/80 XIII-2 DL/SSPB 7
NRC to YAEC 08/31/82 XV-19 DSI/RSB 7($YS)
HRC TO YAEC 07/13/82 DSI/AEB 4A(Doses) 08/23/82 XV-1 DSI/RSB 7
NRC TO YAEC 07/19/82 I
XV-20 DL/SEPB 7
HRC to YAEC 09/06/81 XV-2 DSI/RSB 7(SYS)
HRC TO YAEC 07/13/82 DSI/AEB O(Doses)
XV-21 X
HRC to YAEC 05/07/81 XV-3 DSI/RSB 7
HRC to YAEC 01/25/82 XV-22 X
HRC to YAEC 05/07/81 XV-4 DSI/RSB 7
HRC TO YAEC 07/21/82 XV-23 X
NRC to YAEC 05/07/81 XV-5 DSI/RSB 7
HRC to YAEC 02/10/82 XV-24 X
HRC to YAEC 05/07/81 XV-6 DSI/RSB 7
NRC TO YAEC 07/13/82 XVI X
NRC to YAEC 11/05/80 XV-7 DSI/RSB 7
NRC TO YAEC 06/29/82 XVII DL 7
NRC to YAEC 11/20/79 XV-8 DSI/CPB 7
HRC TO YAEC 03/05/82 XV-9 DSI/RSB 7
NRC TO YAEC 06/25/82 (2-42)
2_
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PALISADES D_L PALISADES DS_L SAR 1/
SER 2/
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE III-1 Classification of N0hE 12/15/81C III-8.A Loose Parts Monitoring and NONE 11/03/81C (SYS)
Structures Ccmponents and Core Barrel Vibration Systems (Seismic and Monitoring (NRR B-60, C-12)
Quality)
IV-2 Reactivity Control Systems 07/31/81R 10/16/81C III-5.A Effects of Pipe Break on 08/13/81R 12/04/81C Including Functional Design Structures, Systems and and Protection Against Compononts Inside Single Failures Containment V-7 Reactor Coolant P NONE 11/16/81C III-5.B Pipe Break Outside 08/2r/81R 12/23/81C Overspeed (N Containment VI-6 C
m n Lea Test NONE 08/05/81C III-7.A Inservice Inspection, NONE 08/25/81C (M
4 Including Prestressed k
Concrete Containments with V
.A la quipment 12/22/81C Either Grouted or Ungrouted
'I res Associato i
,)
Tendons
(
d" Degraded Grid t e (MP B-23)
}
III-7.B Design Codes, Design HQ
/1 1C Criteria, Load M
IX-1 NONE 12/11/81C
")
IX-4l(~'k Combinations, and Reactor 1 d'
Cavity Design rit1 ia ro A n System 10/09/81R 11/18/81C
/
k 1
1 i et IX-6
%./ Fire Protection (MP B-41)
NONE 03/05/82C j,
S XI-l Appendix I(MP,A-02)
NONE DELETED TOPIC NO. TITLE S
HEI hL L
L J
XI-2 Radiological (Effluent NONE DELETED III-3.C Inservice Inspecti of
/21S IR,kO2/12/82C and Process) Monitoring Water Control. ruct res A
Systems (NRR B-67)
III-4.B T
n e'Mit s le MP B NONE 12/02/81C 1/ SAR : Licensee Safety Analysis Report-Scheduled or Actual III-7.D ntai nenj,5 uctural NONE 08/17/81C
( Actual (status 4b) when date is followed by R) t gri :y aests 2/ SER : Staff Safety Evaluation Report -Scheduled or Actual V-1 ompliance with Codes and NONE DELETED (Actual (status 4a, 5, 7) when date is followed by C)
Standards (10 CFR 50.55a)
(MP A-01,A-14) 1/ Desiginated number of days from receipt of licensee SAR (Note: if Licensee SAR is received then date is from receipt of additional information requested) l
{
(3-2)
LICENSEE TOPIC SUBMITTALS PALISADES TOPICS 0
TARGET 35 ACTUAL 30 25 20 ALL SUBMITTALS RECEIVED 15 l
10 5
'/
~~
[I I
I I
I i
l l
I I
l g
JUN JUL AUG SEP OCT NOV DEC JAN FEB MAR APR MAY JUN JUL/DEC TARGET 1
2 3
PER MONTH ACTUAL 1
2 0
1
.1 1
l TARGET 1
3 6
CUMULATIVE ACTUAL 1
3 3
4 5
6 G-3)
GINNA D1 GINNA M,1 SAR 1/
SER 2/
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE III-I Classification of Struct-NONE 12/29/81C lll-4.C Internally Generated 01/11/82R 02/02/82C (SYS) ures Components and Systems Missiles (Seismic and Quality)
III-8.A Loose Parts Monitoring and NONE 11/03/81C III-2 Wind and Tornado Loadings NONE 09/23/81C Core Barrel Vibration Monitoring (NRR B-60,C-12)
III-7.A Inservice Inspection, NONE 12/28/81C Including Prestressed V-7 Reactor Coolant Pump NONE 11/05/81C Concrete Contair.ments with Overspeed(NRR B-68)
Either Grouted or Ungrounded Tendons VI-2.D Mass and Enor 1
e for NONE 09/25/81C Possibt B eak
. side III-7.B Design Codes, Design NONE 12/31/8tC Ce mrf%m Criteria, Load Combinations, and Reactor VI on nme t essure and N
09/25/81C Cavity Design Criteria a
em a Capability VI
- "ESF Switchover om NON 12/18/81C VI-7.C.1 Appendix K - Electrical NONE 11/
g (S
Injection oci e at j
Instrumentation and Control (EIC) Re-reviews Mode (
to ti CS
{("'k IX-5 Ventilation Systems 1/
IC l
kt NONE 11/24/81C Mf d'
IX-1
- K
\\
L 2 El IX-6 Fire Protection (MP B-41)
NONE 02/24/82C SAR 1/
SCpq%{${q HE LI
'I-1 Appendix I(MP A-02)
NONE DELETED TOPIC NO. TITLE 11-1.B Population Distributio
/15 1R OA(2)/8TE XI-2 Radiological (Effluent NDHE DELETED and Process) Monitoring II-1.C Potential Haza s or 5
R 07/01/81C Systems (NRR B-67)
Changeg,in te tal H - Js Due XV-9 Startup or an Inactive Loop NOME 10/16/81C r s or tat or Recirculation Loop at an stit i ion d
- dustrial, Incorrect Temperature, and g
il tary Facilities Flow Controller Malfunction Causing an Increase in BWR II-4.D tability of Slopes 06/30/81R 02/01/82C Core Flow Rate II-4.F Settlement of Foundations 06/30/81R 01/29/82C XV-19 Loss-of-Coolant Accidents NONE 09/29/81C and Buried Equipmer.t (DOSES)
Resulting from Spectrum of (SYS)
Postulated Piping Breaks 10/02/81C III-3.C Inservice Inspection of 10/12/81R 02/09/82C Within the Reactor Coolant Water Control Structures Pressure Boundary Licensoe Safety Analysis Report-Scheduled or Actual III-4.B Turbine Missiles (MP B-46)
NONE 12/02/81C 2/ SA$ =(actual (status 4b) when date is follwed by R)
III-4.D Site Proximity Missiles 04/16/81R 07/21/81C (Including Aircraft) 2/ SER : Staff Saftty Evaluation Report -Scheduled or Actual (Actual (status 4a, 5, 7 ) when date is followed by C)
VI-1 Organic Materials and 11/06/81R 02/18/82C Post Accident Chemistry J/ Desiginated number of days from receipt of licensee SAR (Note if Licensoe SAR is received then date is from receipt of additional information requested)
(3-4)
LICENSEE TOPIC SUBMITTALS GINNA TOPICS 4g TARGET 35 ACTUAL 30 25 20 ALL SUBMITTALS RECEIVED 15 10 5
~~
l lT l
l l
l l
l g
JUN JUL AUG SEP OCT NOV DEC JAN FEB MAR APR MAY JUN JUL/DEC TARGET 0
0 2
0 0
1 PER MONTH ACTUAL 0
0 0
1 1
1 TARGET 0
0 2
2 2
3 CUMULATIVE ACTUAL 0
0 0
1 2
3 G-5)
DRESDEN 2 EL DRESDEN 2 21 (Cont.)
SAR 1/
SER 2/
SAR 1/
SER 1/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC HO. TITLE SCHEDULE SCHEDULE 111-1 Classification of NONE 03/03/82C II-3.B Flooding Potential and HONE 0 6 /11/ 82 C (SYS)
Structures, Components and Protection Requirements Systems (Seismic and Quality)
II-3.B.1 Capability of Operating NONE 0 6/11/82C Plant to Cope with Design III-2 Wind and Tornado Loadings 06/04/82R 06/21/82C Basis Flooding Conditions 1
III-5.A Effects of Pipe Break on 06/04/82R 06/28/82C II-3.C Safety-related Water N0HE 06/11/82C Structures, Systems and Supply (Ultimate Heat Sink Components Inside (UHS))
Containment S o(pes II-4.D Stabil' f
12/08/81R 07/02/82C III-7.B Design Coces, Design NONE 05/17/82C Criteria, load II-4.E Da nt 12/08/8 01/22/82C Combinations, and Reactor Cavity Design Criteria I
-4.
et leme of Foundation 06/30/82C T
uried Equipment j
VI-4 Containment Isolation NDHE 11/'
M i
s-(ELEC)
System L
II
.A Ef fects o-a
.r L 1 (12
/ 1R-05/24/82C on S cti e
(*$$
III-3ge%( l VII-1.A Isolation of Reactor 0 0 81C Protection System from
.ns v
tion of 02/16/82R 06/30/82C ato l Hon-Safety System s"
Structures j
Including Qu ofic tions of III-4kg,/TurbineMissiles HONE 05/18/82C Isolation ev es 9
VII-6 Frcquency as NONE
/ 1 III-4.D Site Proximity Missiles 12/08/81R 02/05/82C j,
(Including Aircraft)
IX-5 Ventilation Systems l
'I
\\E NO
/o er 1
__\\
..JA 3-
'L III-7 D Containment Structural 04/27/81R 03/30/82C
-e Integrity Tests DE
\\
1 U
SAR 1/
SER 2/
V-1 Compliance with Codes NONE DELETED TOPIC H W SCHEDJLE SCHEDULE and Stanoards (10 CFR 1 1 50.55a)(MP A-01,A-14)
Il-1.A t
usTon"frea Authority 06/01/81R_ _ _
09/16/81C 1
' Control V-4 Piping and Safe End N0HE 06/25/82C Integrity II-1.B Population Distribution 04/27/31R 09/16/81C VI-1 Organic Materials and 05/21/82R 07/02/82C II-1.C Potential Hazards or 12/08/81R 06/30/82C Post /ccident C5amistry Changos in Potential Hazards Due to Transportation, Dji.L l
Institutional Industrial, I
SAR 1/
SER g/
and Military Facilities TOPIC HO. TITLE SCHEDULE SCHEDULE II-3.A Hydrologic Description H0HE 0 6/11/82C II-2.C Atmospheric Transport and 03/20/81R 08/26/81C Diffusion Characteristics for Accident Analysi s III-4.A Tornado Missiles 12/08/81R 06/21/82C (3-6)
~~ -
DRESDEN 2 211 (Cont.)
RL1 (Cont.)
SAR 1/
SER 2/
SAR 1/
SER 2/
TOPIC NO. TITtE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE
.GCHEDULE 111-4.C Internally Gonerated 05/17/E2R 06/22/82C XV-3 Loss of External Load,
~~~
10/15/81R 11/17/81C Missiles Turbine Trip, Loss of Condenser Vacuum, Closure III-8.A Looso Parts Monitoring NONE 02/09/82C of Main Steam Isolation and Core Barrel Vibration Valve (BWR), and Steam Monitoring (HRR B-50,C-12) l Pressure Regulator Failure (Closed)
IV-2 Reactivity Control Systems 'NONE 09/28/81C Including Functional Design XV-4 Loss of Non-Emergency A-C 10/15/81R 11/17/81C and Protection Against Power to the Station Single Failures Auxiliaries VI-2.D Mass and Energy Release for N0HE 12/02/81C XV-5 Loss of Hormal Feodwater 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 HONE 12/02/81C Seizure and Reactor Coolant Heat Removal Capability Pump Shaft Break VI-4 Containment Isolation NDHE 10/02/81C XV-8 Control Rod Misoperation 10/15/81R 01/27/82CI (SYS)
System (System Malfunction or Operator Error)
VI-6 Contali. ment Leak Testing NONE 12/30/81C (MP A-04)
XV-9 Startup or an Inactive Loop 10/15/81R 12/07/81C or Recirculation Loop at an VI-7.A.4 Core Spray Hozzle N0HE 02/09/82C Incorrect Temperature, and EffectivenessCNRR A-16)
Flow Controller Malfunction Causing an Increase in PWR VIII-1.A Potential Equipment NONE 03/31/82C Core Flow Rate i
Failures Associated with a Degraded Grid Voltage XV-11 Inadvertent Loading and 10/15/81R 01/25/82C (MP B-23)
Operation of a Fuel l
Assembly in La Improper IX-1 Fuel Storage 02/02/82R 03/26/82C Position I
10/15/81R 01/25/82C IX-6 Fire Protection (MP B-41)
NONE-06/23/82C XV-13 Spectrum of Rod Drop (SYS)
Accidents (BWR) 4 XI-1 Appendix I(MP A-02)
NDHE DELETED (DOSES) 10/15/81R 12/14/81C XI-3 Radiological (Effluent and HONE DELETED XV-14 Inadvertent Operation of~
10/15/81R 12/08/81C 4
l Process) Monitoring Systems ECCS and Chemical and (NRR 3467)
Volume Control System 4
Malfunction that Increases 10/15/CsR 12/14/81C Reactor Coolant Inventory XV t Increabe in Feedwater 4
Temperature, Increase in 4
Feedwater Flow, Increase XV-15 Inadvertent Opening of a 10/15/81R 12/22/81C j
in Steam Flow and PWR Pressurizer Safety-Inadvertent Opening of a Relief Valve or-a BWR Safety / Relief Valve' Steam Generator Relief or, 6
l Safety Valve 4
(3-7)'
_. ort e
.7 l
s.___
b DRESD.EN 2
~
H R2.,L 4 Con t. -)
SAR l/
SER Z/
TOPIC NO. TITLE SCNEDULE SCHEDULE l
XV-18
- Radiological Consegoences 10/15/ SIR 12/23/81C of Main Steam tine Failure Cutside Contain eni (BWR)
XV-19 Loss of-Coolant Accidents 10/15/d1R 11/17/81C (SYS)
Resulting from Spectrum of (DOSES)/ Postulated Piping Breaks 10/15/61d 12/15/81C Within the Reactor Coolant Pressure Boundary l
XV-20 Radiological Conseq'vences 04/27/81R 11/04/81C of Fuel Damaging Accidents-4 (Inside and Outside Containment I
1/ SAR
- Licensee Safety Analysis Report-Scheduled or Actual I
(actual (status 46) when date is followed b/ R)
+ -
2/ SER = Staff Safety Evaluation Report -Scheduled or Actual j-(Actual (status 4a, 5, 7) When date i s f ollowed by C) 4 J/ Desiginated number of days from receipt of licensee SAR (Note if Licensee 'SAR is received then date i s from j.
receipt of additional information requested).
j
.t a
4
/
I.
4 1
i
-(3-8) i
LICENSEE TOPIC SUBMITTALS DRESDEN 2 TOPICS 4g TARGET 35 ACTUAL 30 25
, -g-s m
20 ALL SUB TALS RECEIVED 15
~
/
10
-.+
5
,l.
J'] -
~
l l
_ _ ;[.
l -T'~l l
l
-l l.
l a
JUN 'JUL Aid SEPEOCT NOV DEC' JAN FEB-MAR APR 'MAYJUN JUL/DEC,' _
~
,-~
phy
~ ~ _
2 0
0 1
0 0~
ACTUAL 0
0 0
14 0
7 0
1
'[1 0
2 1
t PER MONTH I
~
22 22 23 25 25
- 25 26 TARGET CUMULATIVE ACTUAL 0
0
.0 14 14 21 21 22 23 23 25'
.26_
(3-9)
\\
OYSTER CREEK IRL OYSTER CREEK D1 (Cent.)
i SAR 1/
SER 2/
SAR 1/
SER 2/
l TOPIC NO. TITLE SCHEDULE SCHEDULE' TOPIC NO. TITLE SCHEDULE SCHEDULE III-1 Classification of NONE 01/29/82C 111-4.6 Turbine Missiles 12/ 0 7/81R 06/27/82C (SYS)
Structures, Components and Systems III-4.D Site Proximity Missiles 03/31/82N 06/21/82C III-2 Wind and Tornado Loadings 03/31/82N 06/08/82C III-7.D Containment Structural 11/ 04/81 R C2/25/82C III-7.5 Deslan Codes, Design NONE 04/30/82C Criteria, Load Combinations V-1 Compliance with Codes NONE DELETED and Reactor Cavity Design and Structures (MP A-01.A-14)
VII-6 Frequency Decay NONE 08/29/81C VI-1 Organic Mat s
d Post 07/30/82N 06/29/82C IX-5 Ventilatf or System 02/28/82H 05/21/82C
$ rM(el emi try VI-7.A-4 Core Spray Nozzle NONE 06/28/82C s-~& _
\\
1"T 1 3 "f'"li Effectiveness (MP D-12) m g
j 7
\\
,r "h SA
- d?]' SCHEDULE
/
SER 2/
-r"'T E
T PI Mt. TITLE HF d'
Rg d
1 1/
S 2/
II-2.C Atm hel sp ajs ' 11/ 04/ 81R 02/24/82C y
TOPIC NO. TITLE "i
ULE H
LE "
fu
'on acte ics d
o A
d alysis II-1.A Exclusion Are A ority 1 363L1R" 01/18/82C i
k gp!a o Missles 03/31/82N 05/27/82C and Cont ol
)
""W(
III
.A E
II-1.B Populati ).
Di tr n
11/30/81R 18 TII-4.
Internally Generated 05/19/82R 05/28/82C Missiles II-1.C PotentigL, zards Due to 1
038 01/ l8 2C L
Transportation, Indus tal III-8.A Loose Parts and Core NONE 02/09/82C and Military Faci le Barrel Monitoring (NRR B-60,C-12)
II-3.A Hydro 1pgie De ript on 04/82R 06/28/82C IV-2 Reactivity Control Systems 02/28/82N 05/24/82C II-3.B o i
,g i n
and 03/04/82R 06/28/82C rot tio L R uirements VI-2.D Mass and Energy Release for NONE 11/20/81C Possible Pipe Break Inside II-3.B-1 ability to Cope with 03/04/82R 06/28/82C Containment Design Basis Flood VI-3 Containment Pressure and NONE 11/20/81C II-3.C Safety Related Water Supply 03/04/82R 06/28/S2C Heat Removal Capability (Ultimate Heat $1nk)
VI-4 Containment Isolation NONE 10/22/81C II-4.D Stability of Slopes 12/15/a:R 06/14/82C System II-4.F Gettlement of Foundation 11/04/81R 06/03/82C
- VI-6 Containment Leak Testing NONE 06/04/81C and Buried Equipment (MP A-04)
III-3.A Effects Tf High Water 03/04/82R 05/05/82C VIII-1.A Potential Equipment NDHE 10/16/81C Level on Structures Failures Associated with a Degraded Grid Voltage III-3.C Inservice Inspection of 11/12/81R 06/03/82C (MP B-23)
Water Control Structure (3-10)
0YSTER CREEK 211 (Cont.)
~~~~~
211 (Cont.)
53.3 l/
SER g/
SAR 1/
SER 2/
TOPIC NO. TITLE SCHtDJLE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE 1X-1 Fuel Storage 03/04/82R 05/18/82C XV-15 Inadvertent Opening of BWR 05/07/81R 11/19/81C Safety / Relief Valve IX-6 Fire Protection (MP B-41)
NOME 05/18/82C XV-16 Radiological Consequences 11/04/81R 04/01/82C of Failure of Small Lines XI-1 Appendix I(MP A-02)
HDHE DELETED Carrying Primary Coolant Outside Containment XI-2 Radiolooical (Effluent end NONE DELETED Process Monitoring Systems)
XV-18 Radiological Consequences 05/07/81R 07/01/81C (NRR B-67)
Main Steam Line Failure XV-1 Decrease in Feedwater 05/07/81R 12/07/81C Outside Containment Temperature. Increase in Feeduator Flow, Increase in XV-19 Loss of Coolant Accidents 05/07/81R 09/04/81C Stcam Flow, Inadvertent
($YS)
Resulting From Spectrum Opening of Stoem Generator, Breaks Within Reactor i
Relief or Safety Valve (DOSES)
Coolant Pressure Boundary 02/28/82N 06/03/82C l
XV-3 Loss of External Load.
05/07/81R 07/16/81C XV-20 Radiological Consequences 02/26/82N 04/19/82C Turbino Trip, Loss of of Fuel Damaging Accidents Condenser vacuum, Closure (In 8 Out of Containmet.t) of Main Steam Isolation Valve (BWR), Steam Pressure Regulatory Failure (closed) 1/ SAR = Licensee Safety Analysis Report-Scheduled or Actual (actual (status Ab) when date is followed by R)
XV-4 Loss of Non-Emergency A-C 05/07/81R 07/16/81C Power to the Station 2/ SER = Staff Safety Evaluation Report -Scheduled or Actual Auxillaries (Actual (status 4a, 5, 7) when date is followed by C)
XV-5 Loss of Normal Feedwater 05/07/81R 11/30/81C J/ Desiginated number of days from receipt of licensee SAR Flow (Note: if Licensee SAR is received then date is from receipt of additional information requested)
XV-7 Reactor Coolant Pump Rotor 08/25/81R 12/07/81C Seizure and Reactor Coolant NOTE:
h-No submittal received, therefore Safety Evaluation Pump Shaft Break preformed without.
XV-9 Startup or an Inactive Loop 05/07/81R 12/30/81C or Recirculation Loop at Incorrect Temperature and Flow Controller Malfunction Causing an Increase in BWR Core Flow Rate XV-13 Spectrum of Rod Drop NONE 04/09/81C (sys)
Accident 05/07/81R 07/01/81C (doses)
XV-14 Inadvertent Operation of 05/07/81R 07/16/81C ECCS that Increases Reactor Coolant Inventory (3-11)
LICENSEE TOPIC SUBMITTALS OYSTER CREEK TOPICS 4g TARGET 35 ACTUAL 30 i
25 20 COMPLETE f p
~
ig 5
I I
I I
I I
I I
I I
I 0
JUN JUL AUG SEP OCT NOV DEC JAN FEB MAR APR. MAY JUN JUL/DEC TARGET 5
3 0
0 0
1 PER MONTH ACTUAL 0
0 0
0 8
2 0
0 6
0 0
1 TARGET 16 21 24 24 24 24 25 CUMULATIVE ACTUAL 0
0 0
1 8
10 10 10 16 16 16 17 G-12) i i
MILLSTONE 1 EL MILLSichE 1 EL (Cont.)
SAR 1/
SER g/
SAR 1/
SER g/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE 111-1 Classification of NONE 03/19/82C II-3.A Hydrologic Description 06/25/81R 06/25/82C
($YS)
Structures, Components and Systems (Seismic and II-3.B Flooding Potential 8 06/26/81R 06/25/82C Quality)
Protection Pequirements III-2 Wind and Tornado Loadings NONE 04/30/82C II-3.B.1 Capability of Operating 06/25/81R 06/25/82C Plant to Cope with Design III-5.A Effects of Pipe Break en 04/13/82R 06/08/82C Basis Flooding Conditions Structures, Systems and Components Inside II-3.C Safety Ralated Wa 04/28/81R 06/25/82C Containment Supply (UHS)
III-5.B Pipe Break Outside 12/04/81R 02/09/82C II-4.B P
Ca able NDHE 12/30/81C Containment T
r et es k
Pla Vi y
III-7.B Design Codes, Design NONE 05/20/82C Criteria, Load Combinations
"\\
II ity of Slopes 58 1/
105/26 /82C and Reactor Cavity Design 1
/
4 II Settlement d tion j4/ / 8' L,
06/03/82C R
V-11.B RHR Interlock Raquirements NONF
/2t
'C and B iac n
(ELEC) d III-3ge-(
s vi tion of 08/31/81R 05/24/82C i
VII-3 Systems Require,d Safe t
- ft/22/82C ter Cn tructures (ELEC)
Shutdown
~
III-4.
T ine Missiles 08/31/81R 06/07/82C VII-6 Frequency ca, NONE
,0
/
J III-4.D Site Prximity Missiles 04/29/81R 10/29/81C IX-3 Station Spr e and Cooling 11 -
1.
a
/3 C
(Including Aircraft)
Water Systems LL IV-3 BWR Jet Pumps Operating NONE 02/22/82C IX-5 Ventilation Sy ems 19 1 R' 04/28/82C Indications XIII-2 ds du ri 1
' HONE 06/02/82C V-1 Compliance with Codes and NONE DELETED u
(MP 10 Standards (10 CFR 50.55a) 1 (MP A-01,A-14)
~
T\\ t 1
Eg jg,8 VI-1 Organic Materials and Post 09/30/81R 01/28/82C SAR l/
SER g/
Accident Chemistry TOPIC NO. TITLE SCHEDULE SCHEDULE Il-1.A Exclusion Area Authority &
04/17/81R 0 7/ 31/81C E11 Control SAR 1/
SER g/
TOPIC NO. TITLE SCHEDULE SCHEDULE II-1.B Population Distribution 05/19/81R 10/29/81C Il-2.C Atmospheric Transport and 0 5/19/81 R 08/10/88C II-1.C Potential Hazards or 04/29/81R 10/29/81C Diffusion Characteristics Changes in Potential for Accident Analysis Hazards Due to Transporta-tion, Institutional, and III-4.A Tornado Missiles 08/31/E1R 05/05/82C Military Facilities (3-13)
MILLSTONE 1 Q11 (Cont.)
Rhl (Cont.)
SAR 1/
SER-Z/
SAR 1/
SER Z/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE III-4.C Internally Generated 04/13/82R 05/25/82C XV-3 Loss of External Load, 06/30/81R 09/18/81C Missiles Turbine Trip, Loss of Condenser Vacuum, Closure III-8.A.
Loose Parts Monitoring and NONE 02/09/82C of Main Steam Isolation Core Barrel Vibration Valve (BWR), and Steam Monitoring (NRR B-60,C-12)
Pressure Regulator Failure (Closed)
IV-2 Reactivity Control Systems 10/28/81R 05/20/82C Including Functional Design XV-4 Loss of Non-Emergency A-C 06/30/81R 09/18/81C and Protection Against Power to the Station Single Failures Auxiliaries VI-2.D Mass and Energy Release for NONE 05/10/82C XV-5 Loss of Normal Feedwater 06/30/81R 12/23/81C Possible. Pipe Break Inside Flow Containment XV-7 Reactor Coolant Pump 06/30/81R tt/18/81C VI-3 Containment Pressure and NONE 05/10/82C Rotor Seizure and Reactor Heat Removal Capability Coolant Pump Shaft Break VI-4 Containment Isolation NDHE 11/16/81C XV-8 Control Rod Misoperation.
06/30/81R 08/26/81C
($YS)
System (System Malfunction or Operator Error)
VI-6 Leak Testing (MP A-04)
NONE 06/01/82C XV-9 Startup or an Inactive Loop 06/30/81R 12/30/81C VI-7.A.4 Core Spray Nozzle NONE 02/09/82C or Recirculation Loop at an Effectiveness (HRR A-16)
Incorrect Temperature, and Flow Controller Malfunction VIII-1.A Potential Equipment NONE 06/02/82C Causing an Increase in BWR Failures Associated With a Core Flow Rate Degraded Grid Voltage 1{
XV-ft Inadvertent Loading and 06/30/81R 10/14/81C IX-1 Fuel Storage 08/31/81R 02/19/82C Operation of a Fuel
)
Assembly in an Improper l
IX-6 Fire Protection (MP B-41) t:0NE 05/17/82C Position XI-t Appendix I(MP A-02)
NONE DELETED XV-13 Spectrum of Rod Drop 06/30/81R 09/09/81C (SYS)
Accidents (BWR)
XI-2 Radiological (Effluent &
'NONE DELETED (DOSES) 06/30/81R 09/21/81C Process) Monitoring Systems (NRR 5-67)
XV-14 Inadvertent Operation of 06/30/81R 09/18/8tC ECCS and Chemical and XV-1 Decrease in Feedwater.
06/30/61R 12/15/8tC Volume Control System Temperature, Increase ln Malfunction that Increases
~
Feedwater Flow, Increase in Reactor Coolant Inventory Steam Ficw and Inadvertent Opening of a Steam Gener-XV-15 Inadvertent Opuning of a 06/30/81R 10/28/81C ator Relief or safety Valve PWR Pressurizar Safety
~~~
~
Relief Valve or a BWR Safety Relief Valve l
l (3-14) l l
w
"~
MILLSTONE 1 211 (Cont.)
~~
SAR 1/
SER Z/
TOPIC NO. TITLE SCHEDn2 SCHEDULE X V-16 Radiological Consequences 06/33/3'5 09/21/81C 1
of Failure of Small Lines Carrying Primary Coolant Outside Containment XV-18 Radiological Consequences 06/30/81R 0 9/21/81C 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 06/30/8tR 07/21/81C of Fuel Damaging Accidents (Inside and Cutside Containment) 1/ SAR : Licensee Safety Analysis Report-Scheduled or Actual (actual (status 4b) when date is followed by R)
Z/ SER = Staff Safety Evaluation Report -Scheduled or Actual (Actual (status 4a, 5, 7) when date is followed by C) 1/ Desiginated number of days from receipt of licensee SAR (Note:
if Licensee SAR is received then date is from receipt of additional information requested)
(3-15)
_ - = _
LICENSEE TOPIC SUBMITTALS.
MILLSTONE 1 TOPICS 4g TARGET 35 i
ACTUAL 30 1
25 20 ALL SUBMITTALS RECEIVED 4
15 i
10
'/
^
~~
l i
i l
l I
I
-l l
I l-g JUN JUL AUG SEP OCT NOV DEC JAN FEB MAR APR MAY JUN JUL/DEC TARGET 0
2 Actual 0
5 0
2
~2 1
0-0 0
2
~
~
~
~
CUMULATIVE ACTUAL 0
5 5
7 9
10 10 10 10 12 G-16) i
SAN ON0FRE fl SAN ONOFRE SAR t/
SER 2/
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE TCPIC NO. TITLE SCHEDULE SCHEDULE IX-3 Station Service and Cooling 11/02/81R 06/30/82 111-1 Classification of NONE 06/23/82C Water Systems Structures, Components and Systems (Seismic and IX-5 Ventilation Systems 12/16/81R 07/02/82C Quality)
III-2 Wino and Tornado Loadings 05/04/a20 08/30,'2 21 SAR 1/
SER 2/
III-5.A Lffects of Pipe Break on 12/01/82 12/36'82 TOPIC NO. TITLE SCHEDULE SCHEDULE Structures, Systems and Components Inside II-1.C Potential HazarJs or 11/12 / 81 R 08/06/82 Containment Changes in Potential Hazards Due to III-5.B Pipe Break Outside 12/01/82 12/10e82 Transportation.
Containennt Institutional Industrial, and Military Facilities III-6 Seismic Design NONE 08/30/82 Considerations II-3.A Hydrologic Description NONE 11/30/82 III-7.B Design Codos, Design NONE 08/31/82 II-3.B Flooding Potential &
NONE 11/30/82 Criteria, Load Protection Requirements Combinations, and Reactor Cavity Design Criteria II-3.B 1 Capability of Operating NONE 11/30/82 Plant to Cope with Design V-11.B RHR Interlock Requirements NDHE 02/04/82C Basis Flooding Conditions (ELEC)
II-3.C Safety Related Water NONE 11/30/82 VI-7.A.3 ECCS Actuation System NONE 11/18/81C Supply (UHS)
VI-7.B ESF Switchover from NDHE 09/04/81C II-4.D Stability of Slopes 11/02/81R 10/31/82 (ELEC)
Injection to Recirculation t1odo (Automatic ECCS II-4.F Settlement of Foundations 11/02/81R 10/31/82 Realignment) and Buried Equipment VI-10.4 Testing of Reactor Trip NONE 08/28/81C III-3.A Effects of High Water Level 05/30/82 09/30/82 System and Engineered on Structures Safety Features Including Response Tine Testinq III-4.R Turbino Missiles (MP B-46)
NONE 06/24/82C VII-1.A Isolation of Reactor NONE 09/09/81C III-4.D Site Proximity Missiles 10/23/81R 09/30/82 Protection Systems.
(Including Aircraft)
Includino Qualifications of Isolation Devices III-7.D Containment Structural 06/09/81R 04/14/82C Integrity Tests VII-2 Engineered Safety Features NONE 11/18/81C (EST) System Control Logic V-1 Compliance with Codes and NONE DELETED and Design Standards (10 CFR 50.55a)
(MP A-01)
VII-3 Systems Required for Safe NONE 11/18/81C (ELEC)
Shutdown VI-1 Organic Materials and Post 01/28/82C 06/18/82C Accident Chemistry VII-6 Frequency Docay NONE 08/28/81C (3-17)
SAN ON0FRE M
M (Cont.)
SAR 1/
SER g/
SAR _1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE III-4.A Tornado Missiles 05/04/82R 06/15/82 XV-2 Spectrum of Steam System 07/01/81R 10/27/81C Piping Failures Inside and III-4 C Internally Generated 04/29/82R 06/15/82 Outside of Containment (PWR)
Missiles XV-3 Loss of External Load.
07/01/81R 08/26/81C III-8.A Loose Parts Monitoring and NONE 12/07/81C Turbino Trip, Loss of Con-Core Barrel Vibration densor Vaccum, Closure of Monitorinq(NRR B-60 C-12)
Main Steam Isolation Valve (EWR), and Steam Pressure IV-2 Reactivity Control Systems 04/30/82R 08/25/82C Regulator Failure (Closed)
Including Functional Design and Protection Against XV-4 Loss of Non-Emerg rncy A-C 08/18/81R 12/12/81C Single Failures Power to the Station Auxiliaries V-7 Reactor Coolant Pump HONE 11/ 05/31C Overspeed(NRR B-68)
XV-5 Loss of Normal Feodwater 07/01/81R 01/25/82C Flow VI-2.D Mass and Energy Release for NONE 12/04/81C Possible Pipe Break Inside XV-6 Feedwater System Pipe 07/01/81R 02/19/82C Containment Breaks Inside and Outside Containment (PWR)
VI-3 Containment Pressure and NONE 12/04/81C Heat Removal Capability XV-7 Reactor Coolant Pump Rotor 0 7 / 01/81 R 05/01/82 Seizure and Reactor Coolant VI-4 Containment Isolation NONE 01/29/82C Pump Shaft Break (SYS)
System XV-8 Control Rod Misoperation 07/01/81R 11/19/81C VI-6 Containment Leak Testing NONE 08/03/82C (System Malfunction or (MP A-04)
Operator Error)
VIII-1.A Potential Equipment Failure NONE 05/0i/82 XV-10 Chemical and Volume Control 07/01/81R 03/28/82C Associated with a Degraded System Malfunction that Grid Voltage (MP B-23)
Results in a Docrease in the Boron Concentration in IX-1 Fuel Storage 04/29/82R 06/15/82 the Reactor Coolant (PWR)
IX-6 Fire Protection (MP B-41)
NONE 10/31/82 XV-12 Spectrum of Rod Ejection 07/01/81R 11/19/81C Accidents (PWR)
XI-1 Appendix I NONE DELETED XV-14 Inadvertent Coeration of 07/01/81R 02/11/82C XI-2 Radiological (Effluent and NONE DELETED ECCS and Chemical and Process) Monitoring Systems Voluma Control System thRR B-67)
Malfunction that Increases Reactor Coolant Inventory XV-1 Decrease in Feedwater 07/nt/81R 10/27/81C Temperature, Increase in i*cdwater Flow, Increase XV-15 Inadvertent Opening of a 0 7/ 01/81R 03/31/82C in Steam Flow and PWR Pressuricor Safety-Inadv'rtent Opening of a Relief Valve of a EWR Steam Canerator Relief Safety / Relief. Valve or Safety Valve (3-18)
SAN ON0FRE 211 (Cont.)
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE XV-16 Radiological Consequences 08/04/81R 11/18/81C of Failure of Small Lines Carrying Primary Coolant Outside Containment XV-17 System Generator Tube NONE 12/07/81C (SYS)
Failure (PUR)
XV-19 Loss-of-Coolant Accidents 0 7/01/81R 08/26/81C Resulting From Spectrum of Postulated Piping Breaks Within the Reactor Coolant Pressure Boundary J/ SAR: Licensee Safety Analysis Report-Scheduled or Actual (Actual (status 4b) when date is followed by R)
Z/ SER : Staff Safety Evaluation Report -Scheduled or Actual (Actual (status 4a. 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)
(3-19) 9
LICENSEE TOPIC SUBMITTALS SAN ONOFRE TOPICS 4g TARGET 35 ACTUAL 30 25 1
20 15 10 5
0 b/I I
I I
I I
I' I
I JUN JUL AUG SEP OCT - NOV DEC JAN FEB MAR APR MAY JUN JUL/DEC
~
PER MONTH -
ACTUAL 0
2 0
1 4
1 1
0 0
2 3
0 0
~
~
~
CUMULATIVE ACTUAL 0
2 2
3 7
8 9-9 9
11--
14 14 14 G-28)
~
BIG ROCK POINT DL 51G ROCK POINT QL (Cont.)
SAR 1/
SER 2/
SAR t/
SER 2/
TOPIC HO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE III-t Classification of Struct-NONE 04/16/82C IX-3 Station Service and 12/10/81R 06/30/82C (SYS) ures, Components and Sys-Cooling Water Systems tems (Seismic and Quality)
IX-5 Ventilation Systems 06/tt/82R 08/13/82C III-2 Wind and Tornado Loading 08/03/82R 08/30/82 III-5.A Effects of Pipe' Break on 05/01/82 09/30/82 EL Structures. Systems and SAR 1/
SER 2/
Components Inside TOPIC NO. TITLE SCHEDULE SCHEDULE Containment 11-3.A Hydrologic Description NONE 09/10/82 III-5.B Pipe Break Outside 05/21/82R 08/30/82C Containment II-3.B Flooding Potential and NCHE 09/10/82 Protection Requirements III-6 Seismic Design NONE 09/30/82 Considerations II-3.B.1 Capability of Operating NONE 09/10/82 Plans to Cope with Designs III-7.B Design Codes, Design NONE 05/30/82 Basis Flooding Conditions Criterion, Load Combinations and Reactor II-3.C Safety-Related Water Supply NONE 09/10/82 Cavity Design Criterion (Ultimate Heat Sink UHS))
VI-7.A.3 ECCS Actuation System NONE 01/29/82C II-4.B Proximity of Capable NONE 09/30/82 Tectonic Structures in VI-7.C ECCS Single Failure Cri-NONE 08/05/81C Plant Vicinity terion and Requirements for Locking Out Power to Valves II-4.D Stability of Slopes 10/05/81R 06/25/82C Including Independence of Interlocks on ECCS Valve II-4.F Settlement of Foundations 10/19/81R 07/07/82C and Burind Equipment VI-7.C.2 Failure Mode Analysis ECCS NONE 08/05/8tC III-3.A Effects of High Water 03/15/82 09/30/82 VI-10.A Testing of Reactor Trip 03/29/82R 06/22/82C Level on Structures System and Engineered Safety Features, Including III-3.C Inservice Inspection of 12/21/81R 08/04/82C Response Time Testing Water Control Structures VII-1.A Isolation of Reactor NONE 02/16/82C III-4.B Turbine Missiles 06/09/82R 09/30/82 Protection System From Hon-Safety Systems, Including III-4.D Site Proximity Missiles 12/14/81R 07/12/82C Qualification of Isolation (Including Aircraft)
Devices III-7.D Containment Structurel 12/29/81R 03/03/82C VII-2 Engineered Safety Features NONE 12/31/81C Integrity Tests (ESF) System Control Logic and Design V-1 Compilance with Codeu and NONE DELETED Standards 110 CFR 50.55a)
VII-6 Frequency Decay NONE 09/21/81C (MP A-01.A-14)
V-4 Piping and Safe End Integ.
HONE 08/31/82 VI-1 Organic Materials and Post 03/16/82R 09/30/82 Accident Chemsitry (3-28)
BIG ROCK POINT M
SER 2/
SAR 1/
SER 2/
Dil (Cont.)
SAR 1/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE I II-2.C Atmospheric Transport and 04/06/82R 06/04/82C XV-1 Decrease in Feodwater 07/15/81R 02/18/82C Diffusion Characteristics Temperature Increase in for Accident Analysis Feedwater Flow, Increase in Stean Flow and III-4.A Tornado Missiles 03/16/82R 05/01/82 Inadvertent Opening of a Steam Generator Relief III-4.C Internally Generated 06/03/82R 06/15/82 or Safety Valve Missiles XV-3 Loss of External Load.
07/15/81R 10/16/81C III-8.A Looso Parts Monitoring and NONE 02/09/82C Turbine Trip, Loss of Core Vibration Monitoring Condenser Vacuum. Closure (NRR B-60.C-12) of Main Steam Isolation Valve (BWR), and Steam IV-2 Reactivity Control System NONE 12/07/81C Pressure Regulator Failure Including Functional Design (Closed) and Protection Against Single Failures XV-4 Loss of Non-Emergency A-C 07/15/81R 10/16/81C Power to Use Station VI-2.D Mass and Fnergy Release for NONE 05/24/82C Auxiliaries Pestulated Pipe Breaks Inside Containment XV-5 Loss of Normal Feedwater 07/15/81R 01/26/82C Flow VI-3 Containment Pressures and h3NE 05/24/82C Heat Removal Capability XV-7 Reactor Ceolant Pumos 07/15/81R 02/25/82C Rotor Sei:ure.,nd Reactor VI-4 Containment Isolation Sys.
NONE 03/24/82C Coolant Pump Shaft Break VI-6 Containment Leak Testing NONE 04/30/82 XV-8 Control Rod Misoperation 09/23/81R 12/21/81C (MP A-04)
(System Malfunction or Operatur Error)
VI-7.B ESF Switchever from NONE 04/22/82C Injection to Recirculation XV-9 Startup of an Inactive Loop 07/15/81R 03/24/82C Mode (Automatic EECS or Recirculation Loop at an Realignment)
Incorrect Temperature and Flow Controller Malfunction VIII-1.A Potential Equipment NONE 07/08/82C Caesing an Increase in BWR Failures Associated with Core Flow Rate D,egraded Grid XV-11 Inadvertent Loading and 09/28/81R 11/20/81C IX-1 Fuel Storage NONE 05/13/82C Operation of a Fuel Assembly in an Improper IX-6 Fire Protection (MP B-41)
NONE 09/30/82 Position (BWR)
XI-1 Appendix I(MP A-02)
NONE DELETED XV-13 Spectrum of Rnd Drop SYS 07/01/81R 11/20/81C Accidents DOSES 07/01/81R 10/23/81C XI-2 Radiological (Effluent NONE DELETED and Process) Monitoring Systems (NRR B-67)
XV-14 Inadvertent Operation of 06/26/81R 08/18/81C l
ECCS and Chemical and Volume Control System Malfunction that Increases Reactor Coolant Inventory (3-22)
BIG ROCK POINT Dil (Cont.)
SAR 1/
SER 2/
TCPIC NO. TITLE SCHEDULE SCHECULE XV-15 Inadvertent Opening of a 06/26/81R 08/18/8 t C PWR. Pressurizer Safety Relief Valve or a BWR Safety / Relief Valve XV-16 Radiological Consequences 0 7/ 01/81R 12/14/81C of Failure of Small Lines Carrying Primary Coolant i
Outside Containment XV-18 Radiological Consequences 07/01/81R 04/02/82C l
of Main Steam Line Failure Outside Containment XV-19 Loss of Coolant Accidents 06/29/81R 08/18/81C (SYS)
Resulting From Spectrum of Postulated Piping Breaks (DOSES) within the Reactor Coolant 06/02/82R 07/01/82 Pressure Boundary XV-20 Radiological Consequences 07/03/81R 10/23/81C of Fuel Damaging Accidents (Inside and Outside Containment) 1/ SAR : Licensee Safety Analysis Report-Scheduled or Actual (Actual (Status 4b) when date is followed by R) 2/ SER : Staff Safety Evaluation Report -Scheduled or Actual (Actual (status 4a. 5, 7) when date is followed by C)
J/ Desiginated number of days from receipt of licensee SAR (Note if Licensee SAR is received then date is from receipt of additional information requested) l (3-23)
LICENSEE TOPIC SUBMITTALS BIG ROCK POINT TOPICS 4g TARGET 35 ACTUAL 30 25 20 15 10 5
I b
I I
I I
I I
I I
I 0
JUN JUL AUG SEP OCT NOV DEC JAN FEB MAR APR MAY JUN JUL/DEC TARGET 1
1 2
3 2
PER MONTH ACTUAL 0
0 2
2 0
3 1
0-2 1
2 4
1 TARGET 11' 12 13 15 18 20 CUMULATIVE ACTUAL 0
2 2
3 7
8 9-9 9
11 13 17 18 G-24)
HADDAM NECK EL HADDAM NECK 21 (Cont.)
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDU' TOPIC NO. TITLE SCHEDULE SCHEDULE 111-1 Classification of N0hE 07/22/82C IX-5 Ventilation Systems 12/14/81R 05/26/82C (SYS)
Structures. Components and Systems (Seismic and XIII-2 Safeguards / Industrial NONE 06/10/82C Quality)
Security (MP A-10)
III-2 Wind and Tornado Loadings 12/14/81R 08/11/82C
~~~
21 III-5 A.
Effects of Pipe Break 03/12/82 08/27/82C SAR 1/
SER 2/
on Structures. Systems TOPIC HO. TITLE SCHEDULE SCHEDULE and Componets Inside Containment II-1.A Exclusion Area Authority 04/27/81R 03/29/82C B. Pipe Break Outside 10/02/81R 04/08/82C II-1.B Population Distribution 08/31/81R 03/29/82C Containment II-1.C Potential Hazards er 06/30/81R 03/29/82C III-6 Seismic Design H0HZ 09/30/82 Changes in P7tential Considerations Hazards Due to Transportation.
III-7.B Design Codes. Design NONE 08/20/82C Institutional Industrial.
Critoria. Load and Military Facilities Combinations, and Reactor Cavity Design Criteria II-3.A Hydrologic Description 12/14/81R 08/30/82C VI-7.A.3 ECCS Actuation System NONE 01/29/82C II-3.B Flooding Potential and 12/14/81R 08/30/82C Protection Requirements.
VI-7.C.3 The Effect on PWR Loop H0HE 12/14/81C Isolation Valve Closure II-3.B.1 Capability of Operating 12/14/81R 08/30/82C During a LOCA on ECCS Plant to Cope with Design Performance Basis Flooding Conditions VI-10.A Testing of Reactor Trip NONE 03/05/82C II-3.C Safety related Water Supply 12/14/81R 08/30/82C System and Engineered (Ultimate Heat Sink (UHS))
Safety Features Including Response Time Testing II-4.B Proximity of Capable N0HE 05/18/82C Tectonic Structures in VII-1.A Isolation of Reactor NONE 02/16/82C Plant Vicinity Protection System from Non-Safety Systems. Including II-4.D Stability of Slopes 08/31/81R 06/21/82C Qualifications of Isolation Devices II-4.F Settlement of Foundations 12/18/i1R 05/18/82C VII-2 Engineered Safety Features NONE 02/16/82C and Buried Equipment (ESF) System Control Logic and Design III-3.A Effects of High Water 08/31/81R 08/26/82C Level on Structures VII-6 Frequency Decay H0HE 08/28/81C III-3.B Structural and Dther NONE 08/30/82C VIII-4 Electrical Penetrations NONE 12/23/81C Consequences (e.g. Flooding of Reactor Containment of Safety-Related Equipment in Basements) of Failure of IX-3 Station Service and Cooling 12/14e81R 04/30/82C Underdrain Systems Water Systems (3-25)
HADDAM NECK El (cont.)
H E11 (Cont.)
SAR 1/
SER 2/
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC HO. TITLE SCHEDULE SCNEDULE III-3.C Inservice Inspections of 02/12/82R 06/03/82C VI-6 Containment Leak Testing NONE 05/07/82C Water Control Structures (MP A-04)
III-4.B Turbine Missiles (MP B-46)
NONE 07/13/82C VI.7.B ESF Switchover from NONE 04/01/82C (SYS)
Injection to Recirculation III-4.D Site Proximity Missiles 06/25/81R 03/29/82C Mode (Automatic ECCS (Including Aircraft)
Realignment)
III-7.D Containment Structural 04/27/61R 10/08/81C VIII-1.A Potential Equipment NONE 06/29/82C Integrity Tests Failures Associated with a Degraded Grid Voltage V-1 Compliance with Codes and NONE DELETED (MP B-23)
Standards (10 CFR 50.55a)
(MP A-01 A-14)
IX-1 Fuel Storage 08/31/81R 12/30/81C VI-1 Organic Materials and Post 02/09/82R 06/04/82C IX-4 Boron Addition Systems 10/02/81R 03/31/82C Accident Chemistry IX-6 Fire Protection (MP B-41)
NONE 05/19/82C Ell XI-1 Appendix I(MP A-02)
NONE DELETED SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE XI-2 Radiological (Effluent NONE DELETED and Process) Nonitoring III-4.A Tornado Missiles 08/31/81R 12/28/81C Systems (NRR B-67)
III-4.C Internaly Generating 02/12/82R 04/22/82C XV-1 Decrease in Feedwater 09/30/81R 06/01/82C Missiles Temperatures, Increase in Feedwater Flow, Increase in III-8.A Loose Parts Monitoring and NONE 02/09/82C Steam Flow and Inadvertent Core Barrel Vibration Opening of a Steam Genera-Monitoring (HRR B-60 C-12) tor Relief or Safety Valve IV-2 Reactivity Control Systems 06/30/81R 12/23/81C XV-2 Spectrum of Steam System 09/30/81R 05/04/82C Including Functional Design Piping Failures Inside and and Protection Against Outside of Containment (SYS)
Single Failures (PWR)
(DOSES) 09/30/81R 06/28/82C V-7 Reactor Coolant Pump NONE 11/ 05/81C Overspee (NRR B-68)
XV-3 Loss of External Lead.
09/30/81R 03/09/82C Turbine Trip, Loss of VI-2.D Mass and Energy Release for NONE 06/21/82C Condenser vacuum, closure Possible Pipe Break Inside of Main Steam Isolation Containme,t Valve (BWR), and Steam Pressure Regulator Failure VI-3 Containment Pressure and NONE 06/21/82C (Closed)
Heat Removal Capability XV-4 Loss of Non-Emergency A-C 09/30/81R 12/17/81C VI-4 Contsinment Isolation NONE 04/06/82C Power to the Station System Auxiliaries XV-5 Loss of Normal Feedwater 09/30/81R 04/06/82C Flow (3-26)
HADDAM NECK l R11 (Cont.)
211 (Cont.)
SAR 1/
SER 2/
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE Resulting from Spectrum of {09/30/81R Loss-of-Coolant Accidents 11/10 / 81 C XV-6 Feodwater System Pipe 09/30/81R 04/28/82C XV-19 Breaks Insido and Outside Containment (PWR)
Postulated Piping Breaks Within the Reactor Coolant XV-7 Poactor Coolant Pump Rotor 09/30/81R 05/12/82C Pressure Boundary (SYS)
Seizure and Reactor Coolant (DOSES) 09/30/81R 06/30/82C Pump Shaft Break XV-8 Control Rod Nisoperation 09/30/81R 03/18/82C J/ SAR : Licensee Safoty Analysis Report-Scheduled or Actual (System Malfunction or (Actual (Status 4b) when date is followod by R)
Operator Error) 2/ SER = Staff Safety Evaluation Report -Scheduled or Actual XV-9 Startup or a r.
.. active 09/30/81R 03/31/82C (Actual (status 4a, 5, 7) when date is followed by C)
Loop or Rocircul.ition loop at an Incorrect 1/ Desiginated number of days from receipt of licensee SAR Temperature, ar.d Flow (Note:
if Licensee SAR is received then date is from Controller Malfunction recoipt of additional information requested)
Causing an Increase in BWR Core Flow Rate XV-10 Chemical and Volume Control 09/30/81R 03/29/82C System Malfunction that Results in a Decreate in in Eoren Concentration in the Reactor Coolant (PWR)
XV-12 Spectrum of Rod Ejection 09/30/81R 03/15/82C Accidents (PWR)
(SYS)
(DOSES) 09/30/81R 05/06/82C XV-14 Inadvertent Operation of 09/30/81R 04/01/82C ECCS and Chemical and Volumo control System Malfunction that Increases Reactor Coolant Inventory XV-15 Inadvertent Opening cf a 09/30/81R M/06/82C PWR Pressurizor Safety-Relief Valve or a BWR Safety / Relief Valve XV-16 Radiological Conscouences NONE 09/28/81C of Failure of Small Lines Carryino Primary Coolant Outsido Containment XV-17 Steam Generator (SYS) 04/07/82R 06/21/82C lube Failure (PW9) (DOSES) 04/07/82R 06/28/82C I
I (3-27)
LICENSEE TOPIC SUBMITTALS HADDAM NECK TOPICS 4g TARGET 35
/
ACTUAL 30 25 20 15
/
/
/
10
[
f V
l I
l I
l i
l i
i g
JUN JUL AUG SEP GCT NOV DEC JAN FEB MAR APR MAY JUN JUL/DEC TARGE' 1
1 PER MONTH ACTUAL a
6 0
16 0
8 0
2 0
1 0
0 0
TARGET 32 33 34 CUMULATIVE ACIuAL 0
6 6
22 22 30 30 32 32 33 33 33 33 G-28)
YANKEE El YANKEE NUCLEAR POWER STATION RL (Cont.)
SAR 1/
SER 2/
SAR 1/
SER 2/
TOPIC HO. TITLE SCHEDULE SCHEDULE TCPIC NO. TITLE SCHEDULE SCHEDULE III-1 Classification of Struct-NONE 06/88/82C IX-S Ventilation Systems 11/18/81R 04/28/82C ures, Components and Sys-tems (Seismic and Quality)
RE SER 2/
III-2 Wind and Tornado Londings 03/18/82R 08/31/82C SAR 1/
. SCHEDULE TOPIC NO. TITLE SCHEDULE III-5.A Effects of Pipe treak on 03/18/82R 07/26/82C Structures, Systems and ll-l.A Exclusion Area Authority 03/18/ 82R 06/15/82Cl Components Inside and Control Containment II-1.B Population Distribution 05/01/81R 06/15/82C III-5.B Pipe Break Outside 01/21/82R 05/06/82C Containment II-1.C Potential Hazards or 04/09/81R 06/15/82C Chanaos in Potential III-6 Seismic Design NONE 08/31/82 tiarards Due to Considerations Transportation.
Institutional Industrial.
III-7.B Design Codos. Design NONE 08/30/82 and Military Facilities Criteria. Load Combinations, and Reactor II-3.C Safety related Water NONE 08/27/82C Cavity Design Criteria Supply (Ultimate Heat Sink (UHS)
V-11.8 RNR Interlock Requirements NOME 01/22/82C (ELEC)
II-4.B Proximity of Capable HONE 06/16/82C Tectonic Structures in VI.-7.A.3 ECCS Actuation System 06/30/81R 01/29/82C Plant Vicinity (D-46)
VI-10.A Testing of Reactor Trip 06/30/81R 01/22/82C II-4.D Stability of Slopes 02/26/82R 08/26/82C System and Engineered Safety Features Including II-4.E Dam Ir.tegri ty NONE 08/31/82C Safety Features Including Response Time Testing II-4.F Settlement of Foundations 08/31/81R 08/31/82C and Buried Equipment VII-1.A Isaaltion of Reactor NONE 10/05/81C Protection System from III-3.A Effects of High Water 03/18/82R 08/27/82C Non-Safety Systems, level on Structures Including Qualifications of Isolation Devices III-3.C Inservice Inspection of 01/04/82R 08/26/82C Water Control Structures VII-2 Engineered Safety Features NONE 10/19/81C (ESF) System Control Logic III-4.B Turbine Missiles (MP B-46)
NONE 02/08/82C and Design III-4.D Site proximity missiles 06/30/81R 06/15/82C VII-3 System Required for Safe NONE 01/22/82C (Including Aircraft)
(ELEC)
Shutdown III-7.D Containment Structural 11/18/81R 03/01/82C VII-6 Frequency Decay NDHE 08/28/81C Integrity Tests V-1 Compliance with Codes NONE DELETED IX-3 Station Service and Cooling 09/17/81R 05/30/82C and Standards (10 CFR Water Systems 50.55a)(MP A-01.A-14)
(3-29)
YANKEE E1 (Cont.)
~$11 (Cont.)
SAR 1/
SER R/
SAR t/
SER Z/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE VI-I Organic Materials and 06/14/82R 08/31/82C IX-1 Fual Storage il/18/8tR 08/31/82C Post Accident chemistry l
gil IX-6 Fire Protection (MP B-41)
NONE 08/31/82 SAR t/
SER 2/
TOPIC HO. TITLE SCHEDULE SCHEDULE XI-t Appendix I(MP A-02)
NONE DELETED 11-2.C Atmospheric Transport and 06/30/81R 09/04/81C XI-2 Radiological (Effluent NONE DELETED Diffusion Characteristics and Process) Monitoring for Accident Analysis Systems (NRR B-57)
III-4.A Tornado Missiles 03/18/82R 06/30/82C XV-1 Decrease in Feedwater 02/01/82R 06/22/82C Temperature. Increase in III-4.C Internally Generated 03/18/82R 05/95/82 Feedwater Flow, Increase Missiles in Steam Flow and Inadvertent Opening of a III-8.A Loose Parts Monitoring NONE 12/07/8tc Steam Generator Relief i
and Core Barrel Vibration or Safety Valve Monitoring (NRR B-60,C-12)
XV-2 Spectrum of Steam System 06/30/81R 06/21/82C IV-2 Reactivity Control Systems 09/17/81R 12/23/8tC (SYS)
Piping Failures Inside
~
Including Functional Design (DOSES) and Outside of Containment No date 05/15/82 and Protecticn Against (PWR)
Single Failures XV-3 Loss of External Load.
06/30/81R Ot/09/82C V-7 Reactor Coolant Pump HONE DELETED Turbine Trip, Loss of Overspeed(NRR B-68)
Condenser Vacuum. Closure of Main Steam Isolation VI-2.D Mass and Energy Release NONE 05/10/82C Valve (BWR), and Steam for Possible Pipe Break Pressure Regulator Failure 4
Inside Containmont (Closed)
VI-3 Containment Pressure and NONE 05/10/82C XV-4 Loss of Non-Emergency A-C Ot/04/82R 06/30/82C Heat Removal Capability Power to the Station Auxiliaries VI-4 Containment Isolation NONE C8/30/82C (SYS)
System XV-5 Loss of Normal Feedwater 06/30/81R 01/29/82C Flow VI-6 Containment Leak Testing NDHE 06/01/82 (MP A-04)
XV-6 Feedwater System Pipe 02/01/82R 06/30/82C Breaks Inside and Outside VI-7.3 ESF Switchover from NONE 06/29/82C Containment (PWR)
(SYS)
Injection to Recirculation Mode (Automatic ECCS XV-7 Reactor Coolant Pump Rotor 06/30/81R 85/20/82C Realignment)
Seizure and Reactor Coolant Pump Shaft Break VIII-1.A Potential Equipment NDHE 08/31/82C Failures Associated with XV-8 Control Rod Misoperation 01/04/82R 02/26/82C a Deoraded Grid Voltage (System Malfunction or (MP B-23)
Operator Error)
(3-30)
YANKEE 211 (Cont.)
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE XV-9 Startup er an Inactive 06/30/SSR 06/13/82C Loop or Recirculation loop at an Incorrect Temperature, and Flew Controller Malfunction Causing an Increase in BWR Core F l o.4 Rate XV-10 Chemical and Volume Control 06/30/81R 03/02/82C System Malfunction that Results in a Decrease in the Boron Concentration in the Reactor Coolant (PWR)
XV-12 Spectrum of Rod Ejection 06/30/81R L3/29/82C (SYS)
Accidents (PWR)
(DOSES) 08/30/81R 12/18/ 81C XV-14 Inadvertent Operation of 06/30/81R 06/30/82C I
ECCS and Chemical and l
Volume Control System Malfunction that Increases l
Reactor Coolant Inventory l
XV-15 Inadvertent Opening of a 06/30/81R 04/28/82C PWR Pressurizer Safety-Related Valve or a BWR t
l Savety/ Relief Valve l
XV-16 Radiological Consequences 02/01/82R 07/28/82C of Failure of Small Lines Carrying Primary Coolant i
Outside Containment XV-17 Steam Generator Tube NDHE 07/06/82C (SYS)
Failure (PWR)
(DOSES) 02/01/82R 03/19/82C XV-19 Loss-of-Coolant Accidents 11/18 /81 R 06/24/82C
($YS)
Resulting from Spectrum of (DOSES:
Postulated Piping Breaks 01/04/82R 08/23/82C Within the Reactor Coolant Pressure Boundary 1/ SAR : Licensee Safety Analysi s Report-Scheduled or Actual (Actual (Status 4b) when date is followed by R) 2/ SER : Staff Safety Evaluation Report -Scheduled or Actual (Actual (status 4a, 5,
- 7) when date is followed by C) 1/ Desiginated number of days from receipt of licensee SAR (Nota:
if Licensoe SAR is received then date as from receipt of additional information requested)
(3-31)
LICENSEE TOPIC SUBMITTALS YANKEE TOPICS 40 TARGET 35 ACTUAL 30 25
/
/
20 ALLSUBMITTAlfRECE ED 15 10 5
~~
l i
I l
l l
1 I
I l
0 JUN JUL AUG SEP OCT NOV DEC JAN FEB MAR APR MAY JUN JUL/DEC BRGET 5
PER MONTH AtitW.
0 2
2 0
4 0
5 5
6 0
0 1
TARGET 20 25 CUMULATIVE ACTim.
0 2
4 4
8 8
13
' 18 24 24 24 25 G-32)
LACROSSE El LACROSSE RE
-SAR J/
SER 2/
SAR 1/
SER 2/
TOPIC HO. TITLE SCHEDULE SCHEDULE TOPIC HO. TITLE.
SCHEDULE SCHEDULE III-t Classification of NONE 06/01/82C II-1.A EXCLUSION AREA AUIHORIIYy 06/22/81R 07/31/82 (SYS)
Structurus, Components and and Control Systems (Seismic and Quality).
II-1.B Population Distribution 06/16/81R 07/29/82C III-2 Wind and Tornado Loadings 08/06/81R 08/30/82 II-1.C Potential Hazards or 07/15/81R 08/04/82C changes in Potential III-5.A Effects of Pipe Break on 02/24/82R 08/06/82C Harards Due to Structures. Systems and Transportation.
Components Inside Institutional Industrial.
Containment and Military Facilities III-5.B Pipe Break Outside 06/29/81R 07/26/82C II-3.A Hydrolic Description 06/16/81R 09/30/82.
Containment II-3.B-Flooding Potential and 05/12/82F 09/30/82 III-6 Scismic Design NONE 09/15/82 Protection Requirements Considerations II-3.B.1 Capability of Operating 05/12/82R 09/30/82 III-7.B Dosion Codos, Design NONE 07/23/82C Plant to Cope with Design Criteria, Lead Basi s Flooding Conditions -
Combinations, and Reactor Cavity Design criteria II-3.C Safety-related Water Supply 06/26/81R 09/30/82 (Ultimate Heat Sink (UHS))
V-11.B RHR Interlock Requirements HONE 03/04/82C (ELEC)
II-4.B Proximity of Capable NONE 07/13/82C Tectonic Structures in VI-7.A.3 ECCS Actuation System NONE 01/29/82C Plant Vicinity VI-10.A Testing of Reactor Trip 06/25/81R 02/16/82C II-4.D Stability of Slopes HONE 08/16/82C System and Engineered l
Safety Features Including II-4.E Dam Integrity NONE 07/27/82C l
Response Time Testing II-4.F Settlement of Foundations -
03/G9/82R 07/20/82C VII-1.A Isolation of Reactor NONE 03/09/82C and Buried Equipment Protection System from Hon-Safety Systems, III-3.A Effects of High Water Level 05/12/82R 09/30/82 Including Qualifications of on Structures Isolation Devices III-3.C Inservice Inspection of 01/29/82R 09/30/82 VII-2 Engineered Safety Features NONE 03/11/82C Water Control Structures (ESF) System Control Logic and Design III-4.B Turbine Missiles-03/05/82R 09/30/82 VII-3 Systems Required for Safe NONE 03/09/82C III-4.D Site Proximity Missiles 09/15/81R 07/29/82C (ELEC)
Shutdown (Including Aircrafts)
VII-6 Frequency Decay NONE 09/21/81C III-7.D Containment Structural 06/29/81R 03/30/82C Integrity Tests IX-3 Station Service and Coolinq 04/05/82R 06/30/82C Water Systems V-1 Compliance with Codes and NOME DELETED Standards (10 CFR 50.55a)
IX-5 Ventilation Systems 03/09/82R 07/23/82C (MP A-01.A-14)
(3-33) l I
1
LA. CROSSE El (Cont.)
D11 (Cont.)
SAR 1/
SER 2/
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE VI-1 Organic Materints and Post 02/19/82R 09/30/82 XI-2 Radiological (Effluent and NOME DELETED Accident Chemistry Process) Nonitoring Systems (NRR B-67)
E11 XV-1 Decrease in Feedwater 03/05/82R 08/23/82C SAR 1/
SER 2/
Temperature. Increase in TOPIC NO. TITLE SCHEDULE SCHEDULE Feedwater Flow. Increase in Steam Generator Relief II-2.C Atmospheric Iransport and 'OS/05/82R 0 ~ /15/82 or Safety Valve
/
Di f fusion Characteri stics for Accident Analysis XV-3 Loss of External Load.
06/26/81R 11/03/81C Turbine Trip, Loss of Con-III-4.A Tornaoo Missiles 08/16/82R 05/30/82 denser Vacuum, Closure o+
Main Steam Isolation Valve III-4.C Internally Generated 03/05/82R 06/29/82C (BWR), and Stam pressure Mi ssi les Regulator Failure (Closed)
III-8.A Loose Parts MonlToring and NONE 02/09/82C Core Barrel Vibration XV-4 Loss of Non-Emergency A-C 06/26/81R 10/21/81C Monitoring (NRR B-60,C-12)
Power to the Station Auxiliaries IV-2 Reactivity Control Systems NONE 12/10/81C Including Functional Design XV-5 Loss of Normal Feedwater 03/05/82R 08/12/82C and Protection Against Flow Single Failures XV-7 Reactor Coolant Pump Rotor 03/11/82R 07/19/82C VI-2.D Mass and Energy Release for NONE 05/28/82C Seizure and Reactor Coolant Possible Pipe Break Inside Pump Shaft Break Containments XV-8 Control Rod Misoperation 02/26/82R 03/25/82C VI-3 containment Pressure and NONE 05/28/82C (System Malfunction or Heat Removal Capability Operation Error)
VI-4 Containment Isolation NONE 06/30/82C X'l-9 Startup or an Inactive Loop 08/25/81R 06/01/82 (SYS)
System or Recirculation Loop at an In:orrect Temperature, and VI-6 Containment Leak Testing NONE 08/24/82C Flow Controller Malfunction (MP A-04)
Causing an Increase in BWR Core Flow Rate >
VIII-1.A POTENTIAL EQUIPMENT HONE 06/25/82C Failurns Associated with a XV-11 Inadvertment Loading and 02/25/82R 03/26/82C Degraded Grid Voltage Operation of a Fuel (MP B-23)
Assembly in an Improper Position IX-1 Fuel Storage 02/26/82R 05/01/82 XV-13 Spectrum of Red Drop 02/26/82R 03/25/82C IX-6 Fire Protection (MP B-41)
NDHE 09/30/82 (SYS)
Accidents (BWR)
(DOSES) 02/26/82R 06/30/82C I
XI-1 Appendix I(MP A-02)
NONE DELETED (3-34)
i lafkCllt()!i!il!
L All (Cont.)
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE XV-14 Inadvertent Operation of 08/25/81R 07/16/82C ECCS and Chemical and i
Volume Control System 1
Malfunction that Increases Reactor Coolant Inventory XV-15
' Inadvertent Opening of a 06/30/81R 09/21/81C PWR Pressuring Safety-Relief Valve or a BWR Safety / Relief Valve XV-16 Radiological Consequences 03/09/82R 05/01/82 of Failure of Small Lines Carrying Primary Coolant Outside Containment XV-18 Radiological Consequences 05/28/82R 06/23/82C of Main Steam Line Failure Outside Containment (BWR)
XV-19 Loss of-Coolant Accidents 05/28/82R 07/15/82C (SYS)
Resulting from Spectrum of (DOSES)
Postulated Piping Breaks 05/28/82R 05/01/82 Within the Reactor Coolant Pressure Boundary XV-20 Radiological Consequences 03/12/82R 05/01/82 of Fuel Damaging Accidents (Inside and Outside Containment) i l
1/ SAR : Licensee Safety Analysis Report-Scheduled or Actual (Actual (Stains 4b) when date is followed by R)
Z/ SER : Steff 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 (Nate
.if Licensea SAR is received then date is from receipt'of additional information reouested)
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N C mmu 335 u s, tucLE AR mEGUL ATORY C OMMISSION NUREG-0485 Vol. 4 No. 8 BIBLIOGRAPHIC DATA SHEET i TITLE AND SUBTITLE (Avd Vodume Na,if apprepneof
- 2. (Leeve dim &f Systematic Evaluation Program Status Surmiary Report 3 nac,p, guy.S ACCESSION NO.
- 7. AUTHOR (S)
- 5. DATE REPORT COMPLETED M ON TH l YE AR September 1982
- 9. PERFORMING ORGANIZATION N AME AND MAILING ADDRESS (/nclude Isa Code /
DATE REPORT ISSUED uOurs lvEAR Office of Resource Management September 1982 Office of Nuclear Reactor Regulation s (te,ve u.a * >
U.S. Nuclear Regulatory Commission l
Washington, D.C.
20S55
- 8. (Leave blank)
- 12. SPONSORING ORGANIZATION NAME AND MAILING ADDRESS 6nclude Isp Codel
- 10. PROJECT! TASK / WORK UNIT NO.
Office of Resource Management Office of Nuclear Reactor Regulation
- 11. CONTR ACT NO.
U.S. Nuclear Regulatory Commission
!!ashington, D.C.
20555
- 13. TYPE OF REPORT PE RIOD COVE RE D //eclustre darrs)
August 1-31, 1982
- 14. (Leave e-ma*J
- 15. SUPPLEMENTARY NOTES
- 16. ABSTR ACT 000 words'or less)
The Systematic Evaluation Program is intended to examine many safety-related aspects of 11 of the older light water reactors. This document provides the existing status of the review process including individual topic and overall completion status.
- 19. SE CURITY CL ASS (This reporff
- 21. N O OF P A GE S
- 18. AVAILABILITY STA'EMENT Unclassified Unlimited 22 PRICE Enc"Mggsgra,s o,gri 2
NEC F OKV 335 47 77)
UNITED STATES sissT4L Ass mL NUCLEAR REGULATORY COMMISSION
'0"' $ ','g" * '
WASHINGTON, D.C. 20%5
- An 0 C-etsuit n 111 0FFICIAL BUSINESS PENALTY FOR PRIVATE USE. 4300 l
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