ML20031G526
| ML20031G526 | |
| Person / Time | |
|---|---|
| Issue date: | 10/31/1981 |
| From: | NRC OFFICE OF MANAGEMENT AND PROGRAM ANALYSIS (MPA), Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| NUREG-0485, NUREG-0485-V03-N11, NUREG-485, NUREG-485-V3-N11, NUDOCS 8110230080 | |
| Download: ML20031G526 (96) | |
Text
__
'HE Vol. 3, No.11
%d September 30,1981 as g 9-SYSTEMATIC EVALUATION PROGRAM j'g[lTh STATUS
SUMMARY
REPORT D
i GCT22 igggh p
- E0f!@== f
%d UNITED STATES NUCLEAR REGULATORY COMMISSION pa arcoy Nbff
s s
i Available from NHC/GPO Sales Program Superintendent of Documents i
Government Printing Office Washington, D. C. 20402 A year's subscription consists of 12 issues for this publication.
Single copies of this publication are available from National Technical
- Information Service, Springfield..VA 22161 Microfiche of single copies are available from NRC/GPO Sales Program
. Washington, D. C. 20555
__=.
NUREG-0485 Vol. 3, No.11 September 30,1981 1
SYSTEMATIC EVALUATION PROGRAM STATUS
SUMMARY
REPORT Prepared for: 0FFICE OF hUCLEAR REACTOR REGULATION Prepared By: OFFICE OF MANAGEMENT AND PR0fiRAM ANALYSIS 1
UNITED STATES NUCLEAR REGULATORY COMMISSION pa aro o
[.
1 (c ~.., __.. %
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t/ II
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%, ' we p William T. Russell, Chief Dennis M. Crutchfield, Chief
(
Systematic Evaluation Program Branch Operating Reactors Branch 5 u fe r Reactor Regulation 0 f ce f Off ce f u ear Reactor Regulation
TABLE OF CONTENTS SECTION I SECTION li SECTION lli SEP TOPIC LIST 12 to 1-3 BIG ROCK POINT 2-2 to 2-5 PALISADES 3-2 to 3-3 DRESDEN 1 2-6 GINNA 3-4 to 3-5 DESIGN BASIS EVENT 14 DRESDEN 2 2-7 to 2-10 DRESDEN 2 3-6 to 3-9 GROUP DESCRIPTION GINNA 2-11 to 2-14 OYSTER CREEK 3-10 to 3-12 DEFINITIONS OF STATUS 1-5 HADDAM NECK 2-15 to 2-18 MILLSTONE 1 3-13 to 3-16 LACROSSE 2-19 to 2-22 SAN ONOFRE 3-17 to 3-20 SEP TOPIC
SUMMARY
1-6 MILLSTONE 1 2-23 to 2-26 STATUS REPORT BIG ROCK POINT 3-21 to 3-24 OYSTER CREEK 2-27 to 2-30 HADDAM NECK 3-25 to 3-28 PALISADES 2-31 to 2-34 PROGRESS TOWARD 1-7 YANKEE ROWE 3-29 to 3-32 COMPLETION (Graph)
SAN ONOFRE 2-35 to 2-38 LACROSSE 3-35 to 3-36 INTEGRATED PLANT 1-8 YANKEL ROWE 2-39 to M2 SAFETY ASSESSMENT SCHEDULE i
SEP TOPIC STATUS BY 1-9 REVIEW DIVISION (Summary Table)
SEP TOPIC STATilS BY 1-10 to 1-11 REVIEW DIVISION (Graphs)
(
SEP TOPIC S? JBMITTALS d-12 thru 1-13 g
BY LICENSEES (Graphs)
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T j
l Z
O O
Lu M
I l
I a
SYSTEMATIC EVALUATION PROGRAM TOPIC LIST
-C.
ly-2 l'eactivity Control Systemn including f unctional
[J.1 A. L ac lu'. son Area A ut horit y and ( ret ros
!!!.4 A. Tornado utggtles Uesign and Protection Against itngle Failures ti. Porulet iovi Distribut son
,163 B* Jet Pur+5 Operet tng ladications
. Pot eet t af H4zards or t hanars in Potent t al B. Turtu ne Missiles Hater =ts Ne to f ramport at ton. int stut ional
- v. !
Cogitance with Codes aad Standards (10 (fil 50.W )
I ntiu s t r i a l, and Milit ary f acilit ies
!!. 4 C. Internally bencreted Missiles ll.?
A. Severe scather P9te* airna f.2 Applicade (ode Cageg
- B. Onsite Meteorological m awenu nts Proar &*
V-3 Overpressurtretton Protectton e
C. Atsauspheric t ranspert and Dif f usion Charac.
W.4 P1ptag and Saf e E nd Integrity teristics f or Acc htent Analy.is
- p. gtte Frostetty Missiles (including Aircraf t)
V-5 Reactor Coolant Pressure Boundary (RCPS)
- D.
Availability of Me teorologst. Data tn the
!!!.S A. L i f ec t s of P ip e B reak on St ructures. Systm LMW*MM*
Control Room and C oat onent s l es ide C ont ai rwernt
!!.3
. Hydrologic Deursption
- 9. Ptpe Bred Outside Contatnrent B. f looding Fotential and Protection Require-Wam 6ennatw N InWtty V.g acactor Core Isoletton (ooling System (E A) 111 1 A. Inservice Inspection. Including Prestressed 1.
Capability of Operat 'ng Plant to Cope Concrete Containents with L tt her Grouted V.10 A. RMR Heat ( schenger Tube f at tures with Des t:;n Bas t s f looding Conditions or Ungrouted Ien1ons C. Saf et y.related Water Sur, *r (Ultimate Heat B. Des tyn Codes. Ces tgn Criterna. Load B. RMA Reltabiltty 5 t f*
(UNS) )
Contanations. end Nedctor Cavity L'esign V.II A. RequtreNits f or Isolation of High and Cow 11 4 t.cology and $elssiGlogy PNs'uN SystN C. Delamination of Prestressed Cencrete Con-A. Tectonic Province tag nee et Str ctures
- 8. RM IntnM %uwwnts u
- 11. Pronia.ty o* Capable Tectonic 5t ruttures D. Containrent $tructural Integrity Tests V.12 A. hMer Pucity of Botitag Water Reactor in Plant WIC enity Primary Coolant
!!!-d A. t oose Parts Monitoring and Core Barrel I"
U8 MNF C. Historical $eigen(it y w if P e n /dll Miles i3f Vibret ton Monitoriq Plant B. Control pod Drt ve Merhanism Integrity VI-I Organic Materiale and Pcrit Accident C hemist ry
- u. Stabilit y of s l@M C. t eradiat ion Damage. Use of Sens ttised Stainless Steel and i at1que #*stst ance VI-2 A. Pressure-Wppression Type Best Contat aents L. Dam Integrity
- 8. Sukostartment Analysis
,0. Com surcarts an s l uel lat earity I. Sett lewnt of f oundat ions and Bur ted C. ice Condenser Containent
( q 2 i p., n t 111-9,
Support l at e9r it y D. Mass and Energy Release for Pos.ible P tpe 111-10
- 4. Thernial.0verinad Prnt ect ion f or Mot ors of B reat Inude Containeet Ill.)
t insif ecat ion of St ewt ures. Coot on. nt s and Mot or-6rerated Val ves i
systems { w nmic and Quality)
- 8. Pu x s ly.ncel Int egrit y VI-3 Contatnent Pressure and Heat Reseval 111-/
mind and f ornado L oadings Capability Ill.3 A. E f f ect s of Higb ester level on St ructu es t e ne Purt's and U tuharge Valves V I.4 Containent Isolation $ystes r
. !l-11 C ot onent I nt egrit y VI-5 Contivstible Gas Control B. Structural and other Consequences (e.g.
gl.6 Contetnaent Led Testing t lundenq of saf et y-6, tat eo i quicaert sa B ew+nt s ) of f ailure of ueener train svo ers 111 12 t evironwnt al Qualif ication cf Saf ety Related L Q a tpwat
(, Imeretcp i mpect ton of wat er C ont rol 5t ruc.
IV.1
- s. Werat ton m'tn t e's Than All loops In-service tures mas sed 1-2
SYSTEMATIC EVALUATION PROGRAM TOPIC LIST Yppt[ a Tg 70910 f fif ti TOPIC #
fiftt V !- 7. A
- 1. ECCS Re-evaluation tr Accourt f or 1mreased g g g.g gest rument s f or Monitoring R at ation and Proceu IV-5 Lou of Itormal f ee< heater f low Wessel Head tect erature varianies During Accidents
- 2. Upper Plenum Inject um IV-6 f eceater System Pipe Greeks laside and Outside Vgg.6 f requency ocay Cont etnwnt (PwR)
- 3. ECCS Actuation syste=
vil-1 Accertability of swing Be Design on 9#-4 Plant s IV-7 Peactor Conlant Pug Rotor letlure and
- 4. Core Spray 8sortle E f f ectivenen peactor Coolant Puam Shaf t Bresh vill
- A. Pc,t ent tal L avipm=nt F at iures Anoctated witti v i-1.8
[5F $mitchover f rom inject ton to Retirculat ton a Delraded Grid Vo tar IV-8 Control Rod utsoperac ton (5ystem Malfunction Mode (Autonutic 1005 Realt gownt) or Operator [rror)
V l t !-2 Onsit e t mergency P=*r System - Diesel v i-1.C f CC5 $ n.gle f r* lure C riterton and Require.
Genera t or IV-9 5tartup or an inact tee Loop or Rectrculation meets f or t mt ing out P=er t o Valves t oap at an incorrect Tegerature, and f low including Independeme of l at erlot-t s on Vill-3 A. Stat son Battery Capacity fest Requirewnts tortro11er Malfunction Caustag an lacrease in ICC5 Valves 9 toe, p you mag,
- 1. Appendia K - f lect rical lastrumentat 4n B. DC Power System Bn Voltage Monitoring and IV-10 Chettcal and Voluay Control System m lf unction a
A nnunc t at 4on and Control (LIC) Re-revie=5 that Results to a Decrease in the Baron Concen-tration in the Reactor Coolant (Patt) vill *
[tectrical Penetrat tons of Reactor Cont ainment
- 2. Iall.ere Mode Analys ts - ECts IV-11 Inadvertent Leading and Operation of a f uel 11-1 f uel Storage Asseefafy in an Igroper Position
- 3. The E f f ect of Pud loop Isolat non 'alve flosure During a L uf A on i L05 Perf ormance IV-12 5pectrwa of Rod Eject 'un Accidents (PW) 11 2 Overhead HandInng Systems - Craneg V I-7.D L ong Term Coo 16ng - Pantve f allu e6 (e.q.
r ilooding of Re&ndant toTonents)
II-3 Station Servt(e and Coolleg Water Systems IV-13 Spectrum of Ro/ ' -g Accidents (BA)
V I-7.E ICCS Suw Destqn and Test for Recirculation 11-4 Boron Addit ton Systr, IV-14 Inadvertent Operatton of ICC5 and CheatCal Mode lf fett e veness and Volume Control System Malfunction that II-5 Ventilation Systems Increases Reactor Coolant Inventory
- 1 ?.i Actuanalator isolat lon Valves Power and Control System Deste i n - t>
f t re Pretect tog IV-15 InaJvertent Opentag of a Pd Pressortier Safety.
Reltef Valve of a 8Jt 5dfety/ Relief Valve VI 8 Coetrol Rooe Habitabilit y I
Aust itary f ee bter Sy stem I V-16 Raatological Consequences of f ailure of Small VI-9 Main 5 team L ine Isolat om Seal System - 9dt Il-1 Appendia I L t es Carry tag Prtmary Coolant Outside Contain-ment VI-10 A. Testing of Reactor f rtp System and Engin ered e
Saf ety F eatures includtag Reiponse fine Il-2 Rad ological (t ' ment and f'rm en ) i*onit or t eg IV-17
- ** W rator resting S ys t em Tube f a61ure (par)
Illi-l tmn%ct of Oper a e nns
- 8. Shared Engineered Saf ety t eatures. On-site IV-?8 Radiological Consequences of stair: Steam
[wrgency Power. and 5erette Syst?ms f or gggg.2 saf e.pards/ indust rial security Line iailure Outside Contataarnt (BA)
Multiple Unit iactietles I f-l IV.19 Loss-of-Coolant Acctdents ResuItIng f rGa Vil-1 A. Isotation of Reactor Prot ect ion System fro
- Decrease in ieedseter ieteratu e. Intresse in 5pectrum os Postulated Piping Breaks Withle r
le n-Safety Systems. Including Quellf Mattons F ecomet er i Inu. Imrease in Steam F lam and o
of Isolation Devices i nadvertent Ope ing of a 5 team Generat or kel ef the Reactor Coolant Pressure Boundary n
or 5afety Valve IV-20 B. Trip Uncertainty and setpoint Anal sts Review Rad 101ogical Consequences of fuel Damaging of Operating Dat. Base
<a,ectrum of 5 team System Pipiny Iailures !ss ede Accidents (Instde and Outside Contalwat)
I V-2 and Outside of Containne nt (Pow)
IV-2 5pc t f uel Cask Drop Accidents V ! !-2 Ingineered Safe'.y Featu es (l57 ) hstem Control r
IV-3 Logic and DestP loss of t aternal Load. Turbine Trip. Loss of "I
Condenser Vacuum. C lowre of Main Steam isola.
Vil-3 Systems Required for Saf e Shutdown t ton Valve (Buu). and 5 team Pressure Eceplator IV-23 Mult tpie Tube f at tures in $ team Generators f ailure (Closed)
IV-24 Lou of All A+C Pusee Vll-4 E f f ects of f ailure in hon-Safety Related iou
-lmergemy A-C Power to the Stat ton Systems on Selected ingsneered Saf et y f eatures g
,yg IVil Operational QA Program atopic deleted from SEP program due to duplication by Three Mele Island (TMI) NRC Action Plan, Unresolved Safety issue or other SEP Topic per May 7,1981 letter from G. Lainas to all SEP Lecenvas.
1-3
DESIGN BASIS EVENT REVIEWS THIS SECTION DEFINES DESIGN BASIS EVENT (DBE) REVIEWS FOR THE ELEWN SEP FACILITIES Mf _ W { '. L i*>
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f r.no power gtert-w d e em a l l as ponie' 5 tert c no-h Caetra' rM e i soperat ion B e-B Coe;t s' rod encperettoc re - 13
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a, 1-4
STATUS DEFINITIONS G - Generic 4a-Draf t SE Received From Review Branch These topics are being evaluated as part of on-going N RC generic review effort. The ongoing This status is used for 9ternal NRC tracking of generic review and the SEP topic review will be topic review progress. ine status indicates that closely integrated to improve the effectiveness a draf t topic safety evaiuation is under mange-and efficiency of these efforts and to minimize ment review.
any impact on licensees. The status and conclu-sions of generic SEP topics will be incorporated in the final safety assessment for each plant.
4b - SAR Received from Licensee Licensee has submitted a Safety Analysis Report X - Deleted (S AR)in accordance with SEP redirection. (See Eisenhut letter to SEP owners of January 14,1981)
These topics have been verified as not applicable The S AR is under review and a Final N RC safety to the design of a specific plant or ar being evaluation (status 7) is being prepared. Draf t SE duplicated by the N RC TMI 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.
f acility. Licensees may comment upon N RC conclusions or propose alternatives to N RC posi-tions.
1 - Questions Received From Review Branch 6 - SE Resm..se Received This status is used for internal NRC tracking by NRC of topic review progress. The status indicates that all information necessary to perform a The draf t SE has been reviewed and licensee topic evaluation is not available and that ques-comments if any have been formally transmitted tions have been developed and sent to the SEP to the N RC.
branch.
7 - Topic Complete 2 - Questions Sent to Utility The NRC topic evaluation has been completed and a final safety evaluation issued. A topic is completed The questions developed in the previous status in several ways: (1) The licensee has responded have been formally transmitted to the licensee that the NRC draf t safety evaluation (i.e. status 5) as a request for additional information.
is correct, or (2) the licensees comments on the N RC draf t safety evaluation (i.e. status 6) have been re-3 - Question Response viewed and if appropriate incorporated into the Received by N RC final safety evaluation, or (3) the licensee has not responded in the time requested, thus concurring The licensee has formally responded to the informa-that the draf t safety evaluation is correct.
tion request issued by N RC regarding the topic.
1-5
SEP TOPIC STATUS
SUMMARY
REPORT
- m
\\
NUMBER OF (JESTIONS QUESTION DRAFT SE SAR SE
\\
TOPICS TOPIC bECEIVED QUESTIONS
RESPONSE
RECEIVED RECEIVED DRAFT SE RESPCHSE TOPIC
\\
GENERIC DELETED NOT TROM SENT TO RECEIVr0 FROM FROM SENT TO RECEIVED C0r,P L ET E N
(G)
(X)
STARTED REVIEW UTILITY BY NRC REVIEW LICENSEE UTILITY L't NRC (7)
PLANT NAME
\\
(0)
BRANCH (2)
(3)
BRANCH (4b)
(5)
(6)
N (1)
(4a)
N PALISADES to 44 1
0 1
1 3
2 5
'4 56 GINNA 8
42 2
1 0
5 6
3 3
15 52 DRESDEN 2 8
47 22 0
2 13 2
2 5
6 30 OYSTER CREEK 8
51 8
0 6
3 4
17 8
3 29 MILLSTONE 1 10 48 1
1 4
9 4
20 5
3 32 SAN ONOFRE 9
45 6
2 2
16 2
11 14 2
27 BIG ROCK POINT 6
50 12 1
5 16 1
10 4
1 31 HADDAM NECK 10 44 21 0
1 19 2
8 2
8 22 YANKEE ROWE 9
44 13 2
6 15 0
17 3
2 26 LACROSSE 7
51 22 1
8 6
3 14 2
1 22 DRESDEN 1 TOTALS THIS MONTH 85 466 108 8
35 103 27 104 51 55 327 TOTALS LAST MONTH 87 466 til j
10 48 95 22 115 48 61 307 I
w NOTE: Totals do not include Dresdan 1,
see page 2-6.
Also included is May f.
1981 deletion letter to all SEP licensees, sue footnote page 1-3.
1-6
~
SYSTEMATIC EVALUATION PROGRAM coat PH ASE lil/
- " " "" d ' "'
Progress Toward Completion
^c
^'
100 %
100
- 7 1-82 s'
90
/
/
80 p
,,#l3%
/
1 month 70%
71%,
&,V' 70 s
61 %
/
H
/
$ 60 60 %
O
' ' 30-81 f
w
,a*
o 50 p'/
54%
s 50 %
/
47%
I 2
f 44%
W 40
- , e' 42%
,/
40 %
/
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 generic or deleted topics) and a weighted average of current topic review G,X Not included 20 status. The calculation is performed using the following formula:
0 0%
1,2,3 35%
4a,4b 80 %
Percent Complete = Sum of Topics in Sta tus x Weighting Factor of Status 5,6 90%
I 100 %
10 sum of Topics 0
9 10 11 12 1
2 3
4 5
6 7
8 9
10 11 12 1
2 3
4 5
L 7
8 9
FY-81 FY-82 17
INTEGRATED PLANT SAFETY ASSESSMENT SCNEDULE n
n TOPIC TARGET DATE DRAFT SER DRAFT SER DRAFT SER ACRS COMMISSION FINAL SER PLANT HAME ALL TOPICS INTLXNAL DIVISION TO ACRS AND MEETING MEETING TO LICENSEE COMPLETE COMPLETE DISTRIBUTION REVIEW LICENSEE PALISADES 94 Sept. 81 Oct.
81 Nov.
81 Dec.
81 Jan 82 Feb.
82 Mar.
82 GINNA 89 Sept. 81 Nov.
88 Dec.
81 Jan.
82 Feb.
82 Mar.
82 Apr.
82 DRESDEN 2 59 Oct.
81 Dec.
81 Jan.
82 Feb.
82 Mar.
82 Apr.
82 May 82 OYSTER CREEK 75 Nov.
81 Jan.
82 Feb.
8 Mar.
82 Apr.
82 May 82 June 82 MILLSTONE 1 80 Dec.
81 Feb.
82 82 Apr.
82 May 82 June 82 July 82 SAN ONOFRE' 72 Feb.
82 Apr.
8 May 82 June 82 July 82 Aug.
82 Sept. 82 BIG ROCK POINT 64.
Mar.
82 M
82 June 82 July 82 Aug.
82 Sept. 82 Oct.
82 HADDAM NECK 55 Apr.
82 June 82 July 82 Aug.
82 Sept. 82 Oct.
82 Nov.
82 YANKEE ROWE 62 June 82 July 82 Aug.
82 Sept. 82 Oct.
82 Nov.
82 Dec.
82 LA CROSSE 55 July 82 Aug.
82 Sept. 82 Oct.
82 Nov.
82 Dec.
82 Jan.
83
- Tentative - Need and schedule for ACRS/ Commission review to be determined aftwr completion of lead plant (Palisades) review.
OVERALL COMPLETION c 71%
1-8
+
SEP TOPIC STATUS by REVIEW DIVISION
SUMMARY
TABLE PLANT PALISADES GINNA DRESDEN OYSTER MILLSTONE SAN BIG HADDAM YANKEE LACROSSE TOTAL 2
CREEK 1
OMOFRE ROCK NECK ROWE POINT i
(IAPM) J/
Michaels Wang Cwalina Fell Persinko McKenna Scholl Brown Wang Michaels NO. OF TOPICS 137 137 137 137 137 137 137 137 137 137 1370 DELETED g/
46 42 47 31 48 45 50 44 44 51 466 APPLICABLE 93 95 90 86 89 92 87 93 93 86 904 i
A 52
/
33
/
31
/
31
/
27
/(' \\ 27
/
26
/
23
?
23
/
21
/
294 /
DL
/
/
/
/
A%
\\
/
/
/
/
/
/
/ 57
/ 39
/ 36
/ 34
/
/ )40
/ 38
/ 38
/ 38
/ 35
/ 392 TECHNICAL
/
/
/
/
/
_/
/
/
/
/
/
15
/
16
/
7
/
4
/
6 N REVIEW DOE
/
/
/
/
/7, 9
/
3
/
3
/
6
/
3
/
72
/
/
_/
/
/
/
/
/
19
/ 22
/ 23
/ 21 g/
2
/
19
/ 18
/ 22
/ 22
/ 22
/ 210 ASSIGNMENT }/
/
/
/
/
//
/
/
/
/
/
/
9
/
27
/
/
Y N '8
/
7
/
4
/
3
/
1
/
2
/
74
/
w DSI
/
/
/
/h
/
/
/
/
/
/
/
/ 17
/ 34
/ 31 31
/ / 30
/ 33
/ 31
/ 33
/ 33
/ 29
/7dT
/
/
/
/
/
/
/
/
/
/
/
76
/
76
/
42
/
4)/ /
41
/
43
/
33
/
29
/
30
/
26
/
440
/
COMPLETE
/
/
/
/
/
/
/
/
/
/
/
/ 93
/ 95
/ 90
/ 86
/ 89
/ 92
/ 87
/ 93
/ 95
/ 86
/ 904
/
/
/
/
/
/
/
/
/
/
/
TARGET DATE -
SEP 81 SEP 81 OCT 81 NOV 81 DEC 81 FEB 82 MAR 82 APR 82 JUN 82 JUL 82 ALL TOPICS COMPLETE l/ Division of Licensing Integrated Assessment Project Manager g/ Deleted as not applicable, or duplicated by USI, TMI Action Plan, or ar.sther topic.
}/ All topic review completion dates are before end of FY 1982.
These schedules and assignments are consistent with HRR budget requests.
l __/l
- No. Completed / No. Assigned 1/
I 1-9 STATUS AS OF SEPTEMBER 30,1981
PROGRESS OF TOPIC REVIEWS DIVISD D LICD6!E 17tCS 450 TMET
~
4N __
1
~ ~ ~
35 -
AC"uAL p
/
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//
2'iB --
m 150 --
IN --
g i
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i i
g D
R AX.
SEP OCT EV EC JAN FEB MAR APR MY D
R
)
1k]13j Tarpt 19 19 g to 10 6
6 4
3 2
2 1
PER MONTH I
\\
Actual 1
10 3
g\\
)
Tarpt 299 318 335 3
- 358, 368 374 380 384 387 389 391 392 CUMULATIVE Actual 281 291 294 PRd[
J F TOPIC REVIEWS DIVI EEIEI3t!C T: PICS 258
^z tMut I
M~~
(
/
158 -~
p
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1N ~~
l
/
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- 4_
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B D
R ME SEP OCT ICV EC JAN FEB MAR APR MY D
R IOfTH Tarpt 28 27 22 19 14 9
6 6
5 3
2 2
1 PER MONTH Actual 4
0 2
Tarpt 94 121 143 162 176 185 191 197 2G2 205 207 209 210 Actual 70 70 72
/
PROGRESS OF TOPIC REVIEUS O! VISION W SYSTEMS INTEGRAf!ON TIFICS 35*
s TARGET 3N -~
~
-=
s
/
ACTUAL 25s ----
y
/
/
2ss --
p 4
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15s --
/
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ses --
/
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V S8 _
y Jtm R
AUG SEP DCT NOV KC JAN FEB MAR APR MAY JtM JUL MONTH d,h4 18 l 14 14 to 7
4 4
2 Target
_43 42 38 PER MONTH Actual 11 3
10 Tar 9et 93 135 173 20d 2%P 247 261 275 285 292 296 300 302 CUMULATIVE Actual 61 64 74 1
PROG S
TOPIC REVIEWS 5
TFI3 15 1
1ANET aus --
i
- ~ ~
g__
/
m p
sus --
y sus ['
/
-'/
el m--
25 ---
IM -~
Jim JLL AUG SP OCT BOf IEC JAN FD llAR APR llAY Jlm R
j Target 90 88 77 64 43 37 26 26 19 13 8
8 4
PER MONTH Actual 16 13 15 Target 486 574 651 715 763 800 826 852 871 884 892 900 904 CUMULATIVE Actual 417 425 440
LICENSEE TOPIC SUBMITTALS D!v!S10N OF LICDSING Sas!TTALS 48 TARGET
~~
y-----_s"
/
- ~
/
Acnn.
/
f m--
/
15 --
/
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h ALC SEP OCT NOV DEC JAN FEB MNt APR MAY Jim R
DENTHS PER MONTil 8
5 8
5 5
2 1
0 0
0 1
0
> < neal 0
3 1
1 33 34 34 34 34 35 35 CUMULATIVE Actuat 0
3 4
N h
LICENSEE TOPIC SUBMITTALS DIVIS!!M OF DCIEDING REDl!TTALS 70 TMIGET se --
7-ACTUAL
~
/
as --
7
/
m--
/
/
~
/
18 --
S Jim R
AUG SEP OCT MDV DEC JAN FEB MMt APR MAY AM R
MONTHS Tarpt 1
9 14 11 5
12 1
1 0
u O
O PER MONTH Actual 1
8 1
Target 1
10 24 35 40 52 53 58 59 59 59 59 59 CUMULATIVE Actuai 1
9 10
LICENSEE TOPIC SUBMITTALS DIVIS!0N E SYSTD6 INTEGtAf!CN SLBMITTALS 188 TAEET
~~~~~~
p
,/
/
/
es --
(
/
y 48 -~
/
23 -~
/
AN JtL ALG SEP OCT NOV DEC JAN FEB MAR APR MAf JtM J11 M(NTHS Target 1
14 46 8
10 10 1
2 3
0 0
0 0
p Actual 1
10 3
Target 1
15 61 69 79 89 92 95 95 95 95 95 95 CUMULATIVE Actual 1
11 14 m;
LICENSEE TOPIC SUBMITTALS m AL m atCT SB+!TTALS 200 TAEET g
175 --
f#
$ 50 --
f gg
/
[
125 ~ -
?
/
188 --
T, --
/
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/
/
Jim Jtt AUG
$[P OCT NOV OEC JAN FEB MAR APR MAY JLN JUL NowTHS PER MONTH 8
4 0
0 1
0 Actual 2
21 5
Target 2
33 98 125 145 172 176 184 188 188 188 189 189 Actual 2
23 28
-mm a.-._
a J.a
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_m.sa__m-m.
h_.C- _. ___.
m.
m
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i I
Z 1
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uJ 00 l
BIG ROCK POINT FACILITY: BIG ROCK POINT 1 TOPIC NO.
REVIEW STATUS REMARKS DIV/BR LICENSEE: CONSUMERS POWER II-1 A.
DL/SEPB 7
CPCo to NRC 09/02/80 REGION / LOCATION: 4 MILES NORTH EAST OF CHARLEVOIS, MICH.
II-1 B.
DL/SEPB 7
CPCo to NRC 09/02/80 DOCKET NO.4 05000155 II-1 C.
DL/SEPB 7
NRC to CPCo 05/13/81 POWER CAPACITY: 0240(THERMAL) 067(ELECTRICAL)
II-2 A.
DSI/AEB 7
NRC to CPCo 08/03/81 II-2 B.
X NRC to CPCo 05/07/81 II-2 C.
DSI/AEB 0
II-2 J.
X NRC to CPCo 05/07/81 SYSTEMATIC EVAlbATION PROGRAM BRANCH CHIEF: W. RUSSELL II-3 A.
DE/HGEB 3
NRC to DPCo 08/21/81 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD II-3 B.
DE/HGEB 3
HRC to CPCo 08/21/81 OPERATING REACTORS PROJECT MANAGER: W.
PAULSON II-3 B.
1.
DE/HGEB 3
Sito Visit 07/16/79 INTEGRATED ASSESSMENT PROJECT MANAGER:
R.
SCHOLL II-3 C.
DE/HGEB 3
NRC to CPCo 08/04/80 II-4 DE/GSB 7
NRC to CPCo 06/08/81 KEY FOR STATUS CODES II-4 A.
DE/GSB 7
HRC to CPCo 06/08/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.
DE/GSB 3
FROM REVIEW BRANCH X - DELETED II-4 C.
DE/GSB 7
NRC to CPCo 06/08/31 4b-SAR RECEIVED FROM 0 - TOPIC NOT LICENSEE II-4 D.
DE/HGEB 2
Site Visit 07/19/79 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 2
Site Visit 07/19/79 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC III-1 DL/SEPB 2(Sys)
NRC to CPCo DL/SEPB 7(ELEC) HRC to CPCo 08/19/81 TO UTILITY 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 3
CPCo to NRC 07/09r81 RECEIVED BY NRC (2-2) e
n
-~
BIG ROCK POINT TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR III-3 A.
DE/SEB 3
CPCo to NRC 08/08/80 III-10 D.
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 0
III-11 X
NRC to CPCO 05/07/81 III-4 A.
DSI/ASB 0
III-12 X
NRC to CPCo 05/07/81 III-4 B.
DE/MTEB 0
IV-1 A.
DL/SEPB 7
NRC to CPCo 10/09/79 III-4 C.
DSI/ASB 0
IV-2 DSI/ICSB 3
NRC to CPCo 05/07/81 III-4 D.
DE/SAB 0
IV-3 X
NRC to CPCo 05/07/81 III-5 A.
DL/SEPB 3
V-1 DE/MTEB G
NRC to CPCo 05/07/81 III-5 B.
DL/SEPB 2
NRC to CPCo 01/04/80 V-2 X
NRC to CPCo 11/16/79 III-6 DL/SEPB 3
CPCo to NRC 07/27/81 V-3 X
NRC to CPCo 05/07/81 III-7 A.
X NRC to CPCo 05/07/81 V-4 X
NRC to CPCo 05/07/81 III-7 B.
DL/SEPB 3
CPCo to NRC 07/09/81 V-5 DL/SEPB 5
NRC to CPCo 03/10/81 III-7 C.
X NRC to CPCo 11/16/79 V-6 DL/SEPB 7
HRC to CPCo 03/05/80 III-7 D.
DE/SEB 3
HRC to CPCo 08/09/79 V-7 X
NRC to CPCo 05/07/81 III-8 A.
DSI 3
NRC to CPCo 05/07/81 V-8 X
NRC to CPCo 05/07/81 III-8 B.
X NRC to CPuo 09/26/80 V-9 X
NRC to CPCo 11/16/79 III-8 C.
DL/SEPB 7
NRC to CPCo 02/05/80 V-10 A.
DL/SEPB 7
NRC to CPCo 10/09/79 III-8 D.
X NRC to CPCo 05/07/81 V-10 B.
DL/SEPB 5
NRC to CPCo 05/13/81 III-9 X
NRC to CPCo 05/07/81 V-11 A.
DL/SEPB 7(Elec) HRC to CPCo 08/14/81 III-10 A.
DL/SEPB 7
NRC to CPCo 08/03/81 V-11 B.
DL/SEPB 5(Sys)
HRC to CPCo 05/13/81 7 ( El ec. )
HRC to CPCo 08/09/81 (2-3)
BIG ROCK POINT TOPIC NO.
REVIEW ST ATflS REMARKS TOPIC HO.
REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.
DL/SEPB 7
HRC to CPCo 10/09/79 VI-7 D.
DL/SEPB 7
HRC to CPCo 08/17/78 V-13 X
NRC to CPCo 05/07/81 VI-7 E.
X HRC to CPCo 05/07/81 VI-1 DE/CEB 3
CPCo to NRC 07/12/79 VI-7 F.
X HRC to CPCo 11/16/79 VI-2 A.
X NRC to CPCo 05/07/81 VI-8 X
NRC to CPCo 05/07/81 VI-2 B.
X HRC to CPCo 05/07/81 VI-9 X
NRC to CPCo 11/16/79 VI-2 C.
X HRC to CPCo 11/16/79 VI-10 A.
DL/SEPB 0
VI-2 D.
DSI/CSB 3
CPCo to NRC 04/02/80 VI-10 B.
X NRC to CPCo 11/16/79 VI-3 DSI/CSB 3
CPCo to NRC 04/02/80 VII-1 A.
DL/SEPB 0
VI-4 DSI/CSB 0(Sys)
VII-1 B.
DL/SEPB 7
HRC to CPCo 08/17/78 DL/SEPB 3 ( *.l ec )
CPCo to NRC 12/02/80 VII-2 DL/SEPB 0
VI-5 X
NRC to CPCo 05/07/81 VII-3 DL/SEPB 5(Sys)
HRC to CPCo 05/13/81 VI-6 DSI/CSB G
HRC to CPCo 05/07/81 DL/SEPB 7(Elec) NRC to CPCo 08/19/81 VI-7 A.
1.
X NRC to CPCo 11/16/79 VII-4 X
NRC to CPCo 05/07/81 VI-7 A. 2.
X NRC to CPCo 05/07/81 VII-5 X
NRC to CPCo 05/07/81 VI-7 A.
3 DL/SEPB 0
VII-6 DL/SEPB 7
HRC to CPCs 09/21/81 VI-7 A. 4.
DSI/RSB 7
NRC to CPCo 04/10/79 VII-7 X
HRC to CPCo 11/16/79 VI-7 B.
DSI/RSB 7(Elec) HRC to CPCo 06/04/81 VIII-1 A.
DSI/PSB G
NRC to CPCo 05/07/81 0(sys)
VIII-2 DL/SEPB 7
NRC to CPCo 08/28/81 VI-7 C.
DL/SEPB 7
NRC to CPCo 08/05/81 VIII-3 A.
DL/SEPB 7
CPCo to NRC 04/22/81 VI-7 C.
1.
DL/SEPB 7
HRC to CPCo 08/05/81 VIII-5 B.
DL/SEPB 7
NRC to CPCo 08/18/81 VI-7 C. 2.
DL/SEPB 7
NRC to CPCo 08/05/81 VIII-4 DL/SEPB 2
NRC to CPCO 03/31/81 VI-7 C. 3.
X NRC to CPCo 11/16/79 (2-4)
BIG ROCK POINT TOPIC NO.
REVIEW STATUS REMARKS TOPIC HO.
REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 0
XV-10 X
HRC to CPCo 11/16/79 IX-2 X
NRC to CPCo 05/07/81 XV-11 DSI/CPB 4b CPCo to NRC 09/28/81 IX-3 DL/SEPB 2
XV-12 X
NRC to CPCo 11/16/79 IX-4 X
HRC to CPCo 11/16/79 XV-13 DSI/CPB 4b(Sys) CPCo to NRC 07/01/81 DSI/AEB 4b(Doses)CPCo to NRC 07/Ot/81 IX-5 DL/SEPB 0
XV-14 DSI/RSB 7
HRC to CPCo 08/18/81 IX-6 DE 7
NRC to CPCo 02/06/81 XV-15 DSI/RSB 7
NRC to CPCo 08/18/81 X
X NRC to CPCo 05/07/81 XV-16 DSI/AEB Gb CPCo to NRC 07/01/81 XI-1 DSI/ETSB C
NRC to CPCo 05/07/81 XV-17 X
NRC to CPCo 11/16/79 XI-2 DSI/ETSB G
NRC to CPCo 05/07/81 XV-18 DSI/RSB 4b(Sys) NRC to CPCo 07/01/81 XIII-1 X
HRC to CPCo 05/07/81 DSI/AEB 0(Doses)
XIII-2 DL/SSPB 7
NRC to CPCo 03/11/81 XV-19 DSI/RSB 7(Sys)
HRC to CPCo 08/18/81 DSI/AEB 4b(Doses)CPCo to NRC 07/01/81 XV-1 DSI/RSB 4b CPCo to NRC 07/15/81 XV-20 DSI/AEB 4b CPCo to NRC 07/03/81 XV-2 X
NRC to CPCo 11/16/79 XV-21 X
NRC to CPCo 05/07/81 XV-3 DSI/RSB 4b CPCo to NRC 07/15/81 XV-22 X
NRC to CPCo 15/07/81 XV-4 DSI/RSB 4b CPCo to NRC 07/15/81 XV-23 X
NRC to CPCo 05/07/8 XV-S DSI/RSB 4b CPCo to NRC 07/15/81 XV-24 X
HRC to CPCo 05/07/81 XV-6 X
NRC to CPCo 11/16/79 XVI X
NRC to CPCo 11/05/80 XV-7 DSI/RSB 4b CPCo to NRC 07/15/81 XVII DL 7
HRC to CPco 08/17/78 XV-8 DSI/CPB 4b CPCo to NRC 09/23/81 XV-9 DSI/RSB 4b CPCo to NRC 07/15/81 (2-5)
DRESDEN1 FACILITY: DRESDEN 1 LICENSEE: COMM0HWEALTH EDISON REGIDH/ LOCATION: 9 MILES EAST OF MORRIS, ILL.
DOCKET NO.
05000010 POWER CAPACITY: 700(THERMAL) 200(ELECTRICAL)
GE.
A/E FIRM: BECH.
SYSTEMATIC EVALUATION PROGR Ali BR ANCH CHIEF: W.
RUSSELL OPERATING REACTORS BRANCH C".IEF: D. CRUTCHFIELD DPERATING REACTCRS PROJCcT MANAGER: P. O'CONNOR By letter dated December 31, 1980 Commonwealth Edison indi-cated that Dresden 1 was undergoing an extensive modifica-tion and was not scheduled for restart until June, 1986.
Also, by 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) s
DRESDEN 2 FACILITY: DRESDEN 2 TOPIC NO.
REVIEW STATUS REMARKS DIV/BR LICENSEE: COMMONWEALTH EDISON Il-1 A.
DE/SAB 4a R EG I 0 he '. 0 C A T IO N : 9 MILES EAST OF MORRIS, ILL.
II-1 B.
DE/SAB Ga DOCKET N0.2 05000237 II-1 C.
DE/SAB 0
POWER CAPACITY: 2527(THERMAL) 0794(ELECTRICAL)
II-2 A.
DSI/AEB 7
NRC to CECO 04/24/81 OL NUMBER: DPR-19 II-2 B.
X NRC to Ceco 05/07/81 N.S.S.S.*
GE.
II-2 C.
DSI/AEB 7
NRC to CPCo 08/26/81 A/E FIRM: SAL.
II-0 D.
X NRC to Ceco 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W.
RUSSELL II-3 A.
DE/HGEB 3
Ceco to NRC 09/11/81 OPERATING REACTORS BRANCH CHIEF: D.
CRUTCHFIELD II-3 B.
DE/HGEB 3
CECO to NRC 09/11/81 OPERATING REACTORS PROJECT MANAGER: P.
O'CONNOR II-3 B.
1.
DE/HGEB 3
CECO to NRC Site Visit 01/09/79 INTEGRATED ASSESSMENT PROJECT MANAGER: G. CWALINA II-3 C.
DE/HGEB 3
CECO to NRC Site Visit 01/09/79 KEY FOR STATUS CODES II-4 DE/GSB 7
NRC to Ceco 07/09/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 A.
DE/GSB 7
NRC to Ceco 06/08/81 FRCM REVIEW BRANCH X - DELETED II-4 B.
DE/GSB NRC to Ceco 07/09/81 4b-SAR RECEIVED FROM 0 - TOPIC NOT LICENSEE II-4 C.
DE/GSB 7
HRC to CECO 06/08/81 STARTED 5 - DRAFT SE SENT II-4 D.
DE/HGEB 0
1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 E.
DE/HGEB 0
6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC II-4 F.
DE/HGEB 0
TO UTILITY 7 - TOPIC COMPLETE III-1 DL/SEPB 3(sys)
NRC to CECO 06/26/81 3 - QUESTION RESPONSE DL/SEPB 7(Elec) Part of VII-3 07/07/81 RECEIVED BY NRC III-2 DL/SEPB 3
(2-7)
DRESDEN 2 TOPIC NO.
REVIEW STATUS RE;1 ARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR III-3 A.
DE/SEB 3
Ceco to NRC 09/28/79 111-10 B.
X NRC to CECO 11/16/79 III-3 B.
X HRC to Ceco 11/16/79 III-10 C.
DL/SEPB 7
NRC to CECO 05/22/79 III-3 C.
DE/HGEB 0
III-11 X
HRC to Ceco 05/07/81 III-4 A.
DSI/ASB 0
III-12 X
NRC to Ceco 05/07/81 III-4 B.
DE/MTEB 3
Site Visit 06/01/81 IV-1 A.
DL/SEPB 7
NRC to Ceco 11/13/79 III-4 C.
DSI/ASB 0
IV-2 DSI/ICSB 3
CECO to NRC 06/08/81 III-4 D.
DE/SAB 0
IV-3 DE/MTEB 7
NRC to Ceco 01/01/80 III-5 A.
DL/SEPB 2
NRC to Ceco 01/04/80 V-1 DE/MTEB G
NRC to CECO 05/07/81 III-5 B.
DL/SEPB 6
Ceco to NRC 03/21/80 V-2 X
NRC to Ceco 11/16/79 III-6 DL/SEPB 6
CECO to NRC 03/13/81 V-3 X
NRC to CECO 05/07/81 III-7 A.
X NRC to CECO 05/07/81 V-4 X
HRC to Ceco 05/07/81 III-7 B.
DL/SEPB 3
CECO to NRC 09/28/79 V-5 DL/SEPB 6
Ceco to NRC 09/02/80 III-7 C.
X NRC to Ceco 11/16/79 V-6 DL/SEPB 7
NRC to CECO 03/05/80 III-7 D.
DE/SEB 4b Ceco to NRC 04/27/81 V-7 NRC to CECO 05/07/81 III-8 A.
DSI G
NRC to Ceco 05/07/81 V-8 X
NRC to CECO 05/07/81 III-8 B.
X NRC to CECO 09/11/80 V-9 X
NRC to CECO 11/16/79 III-8 C.
DL/SEPB 6
Ceco to NRC 03/10/80 0-10 A.
DL/SEPB 7
HRC to CECO 11/08/79 III-8 D.
X NRC to Ceco 05/07/81 V-10 B.
DL/SEPB 7
NRC to Ceco 04/24/81 III-9 X
HRC to Ceco 05/07/81 V-11 A.
DL/SEPB 7
NRC to Ceco 07/10/81 III-10 A.
DL/SEPB 7
NRC to Ceco 06/26/81 V-11 B.
DL/SEPB 7(Sys)
HRC to Ceco 04/24/81 DL/SEPB 7(Elec) NRC to CECO 07/10/81 (2-8)
DRESDEN 2 TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.
DL/SEPB 7
NRC to CECO 04/16/81 VI-7 D.
DL/SEPB 7
NRC to Ceco 08/17/78 V-13 X
NRC to Ceco 05/07/81 VI-7 E.
X NRC to Ceco 05/07/81 VI-1 DE/CEB 3
CECO to NRC 07/27/79 VI-7 F.
X NRC to CECO 11/16/79 VI-2 A.
X NRC to CECO 05/07/81 VI-8 X
NRC to Ceco 05/07/81 VI-2 B.
X NRC to Ceco 05/07/81 VI-9 X
NRC to Ceco 11/16/79 VI-2 C.
X NRC to Ceco 11/16/79 VI-10 A.
DL/SEPB 7
NRC to Ceco 07/03/81 VI-2 D.
DSI/CSB 3
CECO to NRC 11/20/80 VI-10 S.
DL/SEPB 7(Sys)
HRC to Ceco 06/20/81 DL/SEPB 7(Elae) HRC to CECO 07/07/81 VI-3 DSI/ css 3
CECO to NRC 11/20/80 VII-1 A.
DL/SEPB 5
NRC to Ceco Of/05/81 VI-4 DSI/CSB 3(Sys)
CECO +c NRC 06/17/81 DL/SEPL 1(Elec)
VII-1 B.
DL/SEPB 7
HRC to Ceco 08/17/78 VI-5 X
NRC to Ceco 05/07/81 VII-2 DL/SEPB 7
Ceco to NRC 03/18/81 VI-6 DSI/CSB G
NRC to Ceco 05/07/81 VII-5 DL/SEPB 7(Sys)
NRC to CECO 04/24/81 DL/SEPB 7(Elec) NRC to Ceco 07/07/81 VI-7 A.
1.
X NRC to Ceco 11/16/79 VII-4 X
NRC to CECO 05/07/81 VI-7 A.
2.
X NRC to CECO 05/07/81 VII-5 X
NRC to CECO 05/07/81 VI-7 A.
3.
DL/SEPB 7
Ceco to.m' 06/23/81 VII-6 DL/SEPB 7
NRC to Ceco 08/26/81 VI-7 A.
4.
DSI/RSB G
NRC to CECO 05/07/81 VII-7 X
NRC to Ceco 11/16/79 VI-7 B.
X HRC to Ceco 11/16/79 VIII-1 A.
DSI/RSB G
NRC to Ceco 05/07/81 VI-7 C.
DL/SEP8 7
NRC to CECO 03/13/81 VIII-2 DL/SEPB 7
NRC to CECO 06/26/81 VI-7 C.
1.
DSI/PSB 6
CECO to NRC 06/12/81 VII?-3 A.
DL/SEPB 7
NRC to Ceco 07/07/81 VI-7 C. 2.
DL/SEPB 7
NRC to Ceco 03/13/81 VIII-3 B.
DL/SEPB 7
NRC to CECO 06/26/81 VI-7 C.
3.
X NRC to Ceco 11/16/79 VIII-4 DL/SEPB 6
CECO to NRC 06/25/81 (2-9)
DRESDEN 2
TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 3
CECO to NRC 06/02/80 XV-10 X
NRC to Ceco 11/16/79 IX-2 X
NRC to CECO 05/07/81 XV-11 DSI/CPB 0
IX-3 DL/SEPB 5
NRC to Ceco 06/30/81 XV-12 X
NRC to Ceco 11/16/79 IX-4 X
HRC to CECO 11/16/79 XV-13 DSI/SPB 0(Sys)
DSI/AEB 0(Doses)
IX-5 DL/SEPB 0
XV-14 DSI/RSB C
IX-6 G
HRC to CECO 05/07/81 XV-15 DSI/RSB 0
X X
HRC to CECO 05/07/81 XV-16 DSI/AEB 5
NRC to Ceco 06/30/81 XI-1 DSI/ETSB G
NRC to Ceco 05/07/81 XV-17 X
NRC to CECO 11/16/79 XI-2 DSI/ETSB G
HRC to Ceco 05/07/81 XV-18 DSI/RSB 0(Sys)
XIII-1 X
HRC to CECO 05/07/81 DSI/AEB 0(Doses)
XIII-2 DL/SSPB 7
NRC to Ceco 03/11/81 XV-19 DSI/RSB 0(Sys)
DSI/AEB 0(doses)
XV-1 DSI/RSB 0
XV-20 DSI/AEB Gb CECO to NRC 04/27/81 XV-2 X
HRC to CECO 11/16/79 XV-21 X
NRC to Ceco 05/07/81 XV-3 DSI/RSB 0
XV-22 X
HRC to Ceco d5/07/81 XV-4 DSI/RSB 0
XV-23 X
NRC to Ceco 05/07/81 XV-5 DSI/RSB 0
XV-24 X
HRC to Ceco 05/07/81 XV-6 X
NRC to Ceco 11/16/79 XVI X
NRC to Ceco 11/05/30 XV-7 DSI/RSB 0
XVII DL 7
NRC to CECO 08/17/78 XV-8 RSI/CPB 0
XV-9 DSI/RSB D
(2-10)
~
~
GINNA FACILITY: GINNA TOPIC HO.
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 HORTH EAST OF ROCHESTER, NY.
II-1 B.
DE/SAS 7
HRC to RGE 07/21/81 DOCKET NO.: 05000244 II-1 C.
DE/SAB 7
NRC to RGE 09/29/81 POWER CAPACITY: 1520(THERMAL) 0490(ELECTRICAL)
II-2 A.
DSI/AEB 6
REG to NRC 01/19/8; OL NUMBER: DPR-18 II-2 B.
X HRC to RGE 05/07/81 N.S.S.S.
WEST.
II-2 C.
DSI/AEB 6
RGE to NRC 06/30/81 A/E FIRM: GIL.
II-2 D.
X NRC to RGE 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF:
W.
RUSSELL II-3 A.
DE/HGEB 6
RGE to NRC 08/18/81 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD II-3 B.
DE/HGEB 6
RGE to NRC G8/18/81 OPERATING REACTORS PROJECT MANAGER: R. SNAIDER II-3 B.
1 DE/HGEB 6
RGE to NRC 08/18/81 INTEGRATED ASSESSMENT PROJECT MANAGER: A.
WANG II-3 C.
DE/HGEB 7
HRC to RGE 04/10/81 II-4 DE/GSB 7
HRC to RGE 07/09/81 KEY FOR STATUS CODES II-4 A.
DE/GSB 7
HRC to RGE 06/08/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.
DE/GSB 8
HRC to RGE 07/09/81 FROM REVIEW BRANCH X - DELETED II-4 C.
DE/GSB 7
NRC to RGE 06/08/81 4b-SAR RECEIVED FROM 0 - TOPIC NOT LICENSEE II-4 D.
DE/AGEB 4b RGE to NRC 06/30/81 STARTED 5 - DRAFT SE SENT II-4 E.
X NRC to RGE 11/16/79 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.
DE/HGEB 4b RGE to NRC 06/30/81 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY HRC III-1 DL/SEPB 3(Sys)
RGE to NRC 08/14/81 TO UTILITY DL/SEPB 6(Elec) RGE to NRC 01/23/81 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 3
SITE VISIT 07/23/81 RECEIVED BY HRC (2-11)
GINNA TOPIC NO.
REVIEW STATUS REMARKS TCPIC HO.
REVIEW STATUS REMARKS DIV/BR DIV/BR III-3 A.
DE/SEB 6
RGE to NRC 08/18/81 111-10 B.
DL/SEPB 7
NRC to RGE 06/22/81 III-3 B.
X HRC to RGE 12/31/80 III-10 C.
X NRC to RGE 11/16/79 III-3 C.
DE/HGEB 0
III-11 X
NRC to RGE 05/07/81 III-4 A.
DSI/AEB 5
NRC to RGE 09/28/81 III-12 X
HRC to RGE 05/07/81 III-4 B.
DE/MTEB G
NRC to RGE 05/07/81 IV-1 A.
DL/SEPB 7
NRC tc RGE 05/29/79 III-4 C.
DSI/ASB 0
IV-2 DSI/ICSB 7
NRC to RGE 05/26/81 III-4 D.
DE/SAB 7
NRC to RGE 07/21/81 iV-3 X
NRC to RGE 05/07/81 III-5 A.
DL/SEPB 6
RGE to NRC 08/05/81 V-1 DE/MTEB G
NRC to RGE 05/07/81 III-5 B.
DL/SEPB 7
NRC to RGE 09/04/81 V-2 X
NRC to RGE 11/16/79 III-6 DL/SEPB 6
RGE to NRC 02/06/G1 V-3 X
NRC to RGE 05/07/81 III-7 A.
DL/SEPB G
NRC to RGE 05/07/81 V-4 X
NRC to RGE 05/07/81 III-7 B.
DL/SEPB 3
RGE to NRC 11/14/79 V-5 DL/SEPB 5
HRC to RGE 07/22/81 III-7 C.
DE/SEB 7
RGE to NRC 07/07/81 V-6 DL/SEPB 7
NRC to RGE 03/05/80 III-7 D.
DE/SEB 7
NRC to RGE C5/08/80 V-7 DSI/ASB G
NRC to RGE 15/07/81 III-8 A.
DSI G
HRC to RGE 05'07/81 V-8 X
NRC to RGE 05/37/81 III-8 B.
X NRC to RGE 10/01/80 V-9 X
NRC to RGE 11/16/79 III-8 C.
DL/SEPB 7
RGE to NRC 12/d7/79 V-10 A.
DL/SEPB 7
NRC to RGE 02/02/79 III-8 D.
X NRC to RGE C5/07/81 V-10 B.
DL/SEPB 7
RGE to NRC 09/29/81 III-9 X
NRC to RCE 05/07/81 V-11 A.
DL/SEPB 7
NRC to RGE 07/22/81 III-10 A.
DL/SEPB 7
NRC to RGE 08/03/81 V-11 B.
DL/SEPB 7(Sys)
RGE to t.R C 09/29/81 DL/SEPB 7(Elec) NRC to RGE 04/24/81 (2-12) m
_ _. ~. -.. _ _
GINNA l
TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS t
DIV/BR DIV/BR V-12 A.
X NRC to RGE 11/16/79 VI-7 D.
DL/SEPB 7
NRC to RGE 08/17/78 V-13 X
NRC to RGE 05/07/81 VI-7 E.
X NRC to RGE 05/07/81 VI-1 DE/CEB 1
VI-7 F.
DL/SEPB 7
NRC to RGE 06/24/81 VI-2 A.
X NRC to RGE 05/07/81 VI-8 X
NRC to RGE 05/07/81 I
VI-2 B.
X NRC to RGE 05/07/81 VI-9 X
NRC to RGE 11/16/79 VI-2 C.
X NRC to RGE 11/16/79 VI *:- A.
DL/SEPB 7
NRC to RGE 12/15/80 VI-2 D.
DSI/CSB 4a VI-10 B.
X NRC to RGE 11/16/79 VI-3 DSI/CSB 4a VII-1 A.
DL/SEPB 7
NRC to RGE 07/30/81 VI-4 DSI/CSB 5(sys)
HRC to RGE 07/27/81 VII-1 B.
DL/SEP4 7
NRC to RGE 08/17/78 l
DL/SEPB 7(Elec) NRC to RGE 01/12/81 VII-2 DL/SEPB 7
NRC to RGE 06/12/81 VI-5 X
NRC to RGE 05/07/81 VII-N DL/SEPB 7(sys)
NRC to RGE 09/29/81 VI-6 DSI/CSB 7
NRC to RGE 05/06/81 DL/SEPB 7(Elec) NRC to RGE 06/24/81 i
VI-7 A.
1.
DL/SEPB 7
NRC to.9GE 02/20/81 VII-4 X
NRC to RGE 05/07/81 i
VI-7 A. 2.
DL/SEPB 7
NRC to RGE 08/17/78 VII-5 X
NRC to RGE 05/07/81 VI-7 A. 3.
DL/SEPB 7
NRC to RGE 12/15/80 VII-6 DL/SEPB 7
NRC to RGE 06/24/81 VI-7 A. 4.
X HRC to RGE 05/07/81 VII.7 X
NRC to RGE 11/16/79 VI-7 B.
DSI/RSB 7(Sys)
RGE to NRC 08/18/81 VIII-1 A.
DSI/PSB 7
NRC to RGE 03/26/81 t
i DL/SEB 7(Elec) NRC to RGE 09/18/81 I
VIII-2 DL/SEPB 7
NRC to RGE 06/24/81 6
.VI-7 C.
DL/SEPB 7
NRC to RGE 02/20/81 I
VIII-3 A.
DL/SEPB 7
NRC to RGE 07/31/81 i
j VI-7 C.
1 DL/SEPB 3
RGE to NRC 07/14/81 VIII-3 B.
DL/SEPB 7
NRC to RGE 06/09/81 I
VI-7 C. 2.
DL/SEPB 7
NRC to RGE 02/20/81 i
VIII-4 DL/SEPB 6
RGE to NRC 07/14/81 I
VI-7 C. 3.
X NRC to RGE 11/16/79 l
[
i i
i J
i I
f i
t
)
(2-13)
A.
~. _ _ _ _ _
GINNA TCPIC NO.
REVIEW STATUS REMARKS TOPIC HO.
REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 3
RGE to NRC 06/09/81 XV-10 DSI/RS8 7
NRC to RGE 09/04/81 IX-2 X
NRC to RGE 05/07/81 XV-11 X
HRC to RGE 10/01/80 IX-3 DL/SEPB 6
RGE to NRC 03/21/81 XV-12 DSI/CPB 7(Sys)
HRC to RGE 09/04/81 DSI/AES 5(Doses!'NRC to RGE 09/04/81 IX-4 DSI/RSB 7
NRC to RCE 08/26/81 XV 13 X
NRC to RGE 11/16/79 IX-5 DL/SEPB 3
RGE to NRC 09/17/81 XV-14 DSI/RSB 7
NRC to RGE 09/04/81 IX-6 G
NRC to RGE 05/07/81 XV-15 DSI/RSB 7
HRC to RGE 09/04/81 X
X NRC to RGE 05/07/81 XV-16 DSI/AEB 5
NRC to RGE 09/24/80 XI-1 DSI/ETtB G
NRC to RGE 05/07/81 XV-17 DSI/R$B 7(Sys)
HRC to RGE 09/04/81 XI-2 DSI/ETSB G
FRL to RGE 05/07/81 DSI/AEB 5(Doses) HRC to RGE 09/24/81 XIII-1 X
NRC to RGE 05/07/81 XV-18 X
NRC to RGE 03/11/80 XIII-2 DL/SEPB 7
HRC to RGE 03/26/81 XV-19 DSI/RSB 6(Sys)
RGE to NRC 09/15/
DSI/AEB 5(Doses) HRC to RGE 09/24/. 8 XV-t DSI/RSB 7
NRC to RGE 09/J4/81 XV-20 DSI/AEB 5
NRC to RGE 09/24/81 XV-2 DSI/RSB 7(Sys)
HRC to RGE 09/04/81 DSI/AEB 5(Doses) HRC to RGE 09/24/81 XV-21 X
NRC to RGE 05/07/81 XV-3 DSI/RSB 7
H R 1' to RGE 09/04/81 XV-22 X
NRC to RGE 05/07/81 XV-4 0;I/RSB 7
HRC to RGE 09/04/81 XV-23 X
NRC to RGE 05/07/81 XV-5 DSI/RSB 7
NRC to RGE 09/04/81 XV-24 X
NRC to RGE 05/07/81 XV-6 DSI/RSB 7
HRC to RGE 09/04/81 XVI X
NRC to RGE 11/05/80 XV-7 DSI/RSB 7
NRC to RGE 09/04/81 XVII DL 7
NRC to RGE 08/17/78 XV-8 DSI/CPB 7
NRC to RGE 09/04/81 XV-9 DSI/RSB 5
NRC to RGE 08/26/81 (2-14)
HADDAM NECK FACILITY: HADDAM HECK TOPIC NO.
REVIEW STATUS RIMARK3 DIV/BR LICENSEE: CONNECTICUT YANKEE ATOMIC POWER 11-1 A.
DE/SAB 4b CYAPCo to NRC 04/27/81 REGION / LOCATION: 13 MILES EAST OF MERIDEN, CT.
II-1 B.
DE/ SAD 4b CYAPCo to NRC 08/31/81 DO(KET NO: 05000213 II-1 C.
DE/SAB 4b CYAPCo to NRC 06/30/81 POWER CAPACITY: 1825(THERMAL) 0575(ELECTRICAL)
II-2 A.
DSI/AEB 7
CYAPCo to NRC 01/22/81 OL NUMBER: DPR-61 II-2 B.
X NRC to CYAPCo 05/07/81 N.S.S.S.: WEST.
II-2 C.
DSI/AEB 7
CYAPCo to NRC 02/16/79 A/E FIRM: S&W II-2 D.
X NRC to CYAPCo 05/07/81 SYSTEMATIC EVALUATION rROL'AM BRANCH CHIEF: W.
RUSSELL II-3 A.
DE/HGEB 3
CYAPCo to NRC 08/23/81 OPERATING REACTORS BRANCH CHI?F:
D.
CRUTCHFIELD II-3 B.
DE/HGEB 3
CY /.P C o to NRC 08/23/81 OPERATING REACTORS PROJECT MANA1ER: W. PAULSON II-3 B.
1.
DE/HGEB 3
Site Visit INTEGRATED ASSESSMENT PROJECT MANAGER:
S.
BROWN II-3 C.
DE/HGEB 3
Site Visit II-4 DE/GSB 7
NRC to CYAPCo 06/08/81 KEY FOR STATUS CODES II-4 A.
DE/GSB 7
NRC to CYAPCo 06/08/81 G - GENERIC Ga-DRAFT SE RECEIVED II-4 B.
DE/GSB 3
NUREG/CR1582 08/04'81 FROM REVIEW BRANCH X - DELETED II-4 C.
DE/GSB 7
NRC to CYAPCo 06/08/81 4b-SAR RECEIVED FROM 0 - TOPIC NOT LICENSEE II-4 D.
DE/HGE8 4b CYAPro to NRC 08/31/81 STARTED 5 - DRAFT SE SENT II-4 E.
X NRC to CYAPCo 04/16/79 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.
DE/HGEB 4b CYAPCo to NRC 06/22/81 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC III-1 DL/SEPB 3(Sys)
CYAPCo to NRC 09/28/79 TO UTILITY DL/SEPB 7(Elec) Part of VII-3 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 3
CYAPCo to NRC 09/07/79 RECEIVED BY NRC (2-15)
HADDAM NECK TOPIC NO.
REVIEW STATUS REMARKS TOPIC HO.
REVIEW STATUS REMARKS DIV/BR DIV/BR III-3 A.
DE/SEB 4b CYAPCs to NRC 08/31/81 111-13 B.
DL/SEPB 6
CYAPCo to NRC 12/09/80 III-3 B.
DE/HGEP 0
III-10 C.
X NRC to CYAPCo 04/16/79 III-3 C.
DE/HGEB 4b CYAPCo to NRC 08/31/81 III-11 X
NRC to CYAPCo 05/07/81 III-4 A.
DSI/ASB 4b CYAPCo to NRC 08/31/81 III-12 X
NRC to CYAPCo 05/07/81 III-4 B.
DE/MTEB G
NRC to CYAPCo 05/07/81 IV-1 A.
DL/SEPB 7
CYAPCo to NRC 06/25/79 III-4 C.
DSI/ASB 0
IV-2 DSI/ICSB Gb CYAPCo to NRC 06/30/81 III-4 D.
DE/SAB 4b CYAPCo to NRC 06/25/81 IV-3 X
NRC to CYAPCo 05/07/81 III-5 A.
DL/SEPB 3
CYAPCo to NRC 02/07/80 V-1 DE/MTEB G
NRC to CYAPCo 05/07/81 III-5 B.
DL/SEPB 3
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
HRC to CYAPCo 05/07/81 III-7 B.
DL/SEPB 3
CYAPCo to NRC 09/07/79 V-5 DL/SEPB 6
CYAPCo to NRC 08/19/81 III-7 C.
X NRC to CYAPCo 04/16/79 V-6 DL/SEPB 7
NRC to CYAPCo 03/0!'80 III-?
D.
DE/ srb 4b CYAPCo to NRC 04/27/81 V-7 DSI/ASB C
NRC to CYAPCc 05/07/81 III-8 A.
DSI G
NRC to CYAPCo 05/07/81 V-8 X
HRC 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-d C.
DL/SEPB 6
CYAPCo to NRC 1?/18/79 V-10 A.
DL/SEPB 7
NRC to CYAPCo 01/13/81 III-8 D.
X NRC to CYAPCo 05/07/81 V-10 B.
DL/SEPB 5
N?C to CYAPCo 09/09/81 III-9 X
NRC to CYAPCo 05/07/81 V-11 A.
DL/SEPB 7
NRC to CYAPCo 09/01/81 III-10 A.
DL/SEPB 7
CYAPCo to NRC 09/21/81 V-11 B.
DL/S'PB 5(Sys)
NRC to CYAPCo 09/*
DL/SEPB 7(EInc) Part of VII-3 (2-16)
HADDAM NECK TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR f-12 A.
X NRC to CYAPCo 11/16/19 ~
VI-7 D.
DL/SEPB 7
NRC to CfAPCo 09/17/78
-13 X
NRC to CYAPCo 05/07/81 VI-7 E.
X NRC to CYAPCo 05/07/81 VI-1 DE/CEB 3
CYAPCO to NRC 10/31/79 VI-7 F.
X NRC to CYAPCo 04/16/79 VI-2 A.
X NRC to CYAPCo 05/07/81 VI-8 X
NRC to CYAPCo 05/07/81 VI-2 B.
X NRC to CYAPCo 05/07/81 VI-9 X
NRC to CYAPCo 11/16/79 VI-2 C.
X NRC to CYAPCo 04/16/79 VI-10 A.
DL/SEPB 0
VI-2 D.
DSI/CSB 3
CYAPCo to NRC 04/27/81 VI-10 B.
X NRC to CYAPCo 04/16/79 VI-3 DSI/CSB 3
CYAPCo to NRC 04/?7/81 VII-1 A.
DL/SEPB 3
CYAPCo to NRC 08/07/81 VI-4 DSI/CSB 0(Sys)
VII-1 B.
DL/SEPB 7
NRC to CYAPCo 08/17/78 DL/SEPB 7(Elec) HRC to CYAPCo 09/21/81 VII-2 DL/SEP3 3
CYAPCo to NRC 08/07/81 VI-5 X
NRC to CYAPCo 05/07/81 VII-3 DL/SEPB 5(Sys)
HRC to CYAPCo 09/09/81 VI-6 DSI/CSB G
NRC to C /APCo 05/07/81 DL/SEPB 7(Elec) HRC to CYAPCo 08/28/81 VI-7 A.
1 DL/SEPB 7
HRC to CYAPCo 02/20/81 VII-4 X
HRC to CYAPCo 05/07/81 VI-7 A.
2.
X NRC to CYAPCo 05/07/81 VII-5 X
NRC to CYAPCo 05/07/81 VI-7 A.
3.
DL/SEPB 0
VII-6 DL/SEPB 7
NRC to CYAPCo 08/28/81 VI-7 A.
4.
X NRC to CYAPCo 05/07/81 VII-7 X
NRC to CYAPCo 04/16/79 VI-7 B.
DSI/RSB 0(Sys)
VIII-1 A.
DSI/PSB G
NRC to CYAPCo 05/07/81 DL/SEPB 5(Elec) NRC to CYAPCo 05/21/81 VIII-2 DL/SEPB 7
NRC to CYAPCo 08/28/81 VI-7 C.
DL/SEPB 7
NRC to CYAPCo 03/13/81 VIII-3 A.
DL/SEPB 7
CYAPCo to NRC 02/16/79 VI-7 C.
1 DL/SEPB 7
NRC to CYPACo 08/28/81 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 2
NRC to CYAPCo 06/20/81 VI-7 C.
3.
DL/SEPB 2
NRC to CYAPCo 06/26/81 (2-17)
HADDAM NECK TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 4b CYAPCo to NRC 08/31/81 XV-10 DSI/RSB 0
IX-2 X
NRC to CYAPCo 05/07/81 XV-11 Y
NRC to CYAPCo 10/01/80 IX-3 DL/SEPB 2
XV-12 DSI/CPB O(Sys)
DSI/RSB 0(Doses)
IX-4 DSI/RSB 0
XV-13 X
NRC to CYAPCo 11/16/79 IX-5 DL/SEPB 0
XV-t4 DSI/RSB 0
IX-6 DE G
fC to CYAPCo 05/07/81 XV-15 DSI/R$B 0
X X
NRC to CYAPCo 05/07/81 XV-16 DSI/AEB 5
NRC to CYAPCO 07/10/81 XI-1 DSI/ETSB G
NkC to CYAPCo 05/07/81 XV-17 DSI/RSB 0(Sys)
XI-2 DSI/ETSB C
NRC to CYAPCo 05/07/81 DSI/AEB 0(Doses)
XIII-1 X
HRC to CYAPCo 05/07/81 XV-18 X
HRC to CYAPCo 10/01/80 XIII-2 DL/SSPB G
NRC to CYAPCo 05/07/81 XV-19 DSI/RSB 0(Sys)
DSI/AEB 0(Doses)
XV-1 DSI/RSB 0
XV-20 DL/SEPB 7
NRC to CYAPCo 06/09/81 XV-2 DSI/RSB 0(Sys)
DSI/AEB 0(Doses)
XV-21 X
NRC to CYAPCo 05/07/81 XV-3 DSI/RSB 0
XV-22 X
NRC to CYAPCo 05/07/81 XV-4 DSI/RSB C
XV-23 X
NRC to CYAPCo 05/07/81 XV-5 DSI/ r.3B 0
XV-24 X
NRC
+.o CYAPCo 05/07/81 XV-6 DSI/RSB 0
XVI X
NRC to CYAPCo 11/05/80 XV-7 DSI/RSB 0
XVII DL 7
NRC to CYAPCo 08/17/78 XV-8 DSI/CPB 0
XV-9 DSI/RSB 0
(2-18)
LACROSSE FACILITY: LACROSSE TOPIC NO.
REVIEW STATUS REMARKS DIV/BR LICENSEE: DAIRLAND POWER 11-1 A.
DE/SAB 4b DPC to NRC 06/23/81 REGION / LOCATION: 19 MILES SOUTH OF LACROSSE, WISC.
II-1 B.
DE/SAB 4b DPC to NRC 06/16/81 DOCKET NO.
05000409 II-1 C.
DE/SAB 4b DPC to NRC 07/15/81 POWER CAPACITY: 0165(THERMAL) 0050(ELECTRICAL)
II-2 A.
DSI/AEB 5
NRC to DPC 12/15/80 OL NUMBER: DPR-45 II-2 B.
X HRC to DPC 05/07/81 N.S.S.S.
AC.
II-2 C.
DSI/AEB 0
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 2
NRC to DPC 07/10/81 OPERATING REACTORS PROJECT MANAGER:
R.
CARUSO II-3 B.
1 DE/HGEB 0
l INTEGRATED ASSESSMENT PROJECT MANAGER:
T. MICHAELS II-3 C.
DE/HGEB 4b DPC to NRC 06/26/81 II-4 DE/GSB 7
HRC to DPC 06/08/81 KEY FOR STATUS CODES II-4 A.
DE/GSB 7
NRC to DPC 06/08/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.
DE/GSB 3
FROM REVIEW BRANCH X - DELETED II-4 C.
DE/GSB 7
NRC to DPC 06/08/81 4b-SAR RECEIVED FROM 0 - TOPIC HOT LICENSEE II-4 D.
DE/HGEB 3
Site Visit 07/10/79 STARTED 5 - DRAFT SE SENT II-4 E.
DE/HGEB 0
1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.
DE/HGE3 2
6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY HRC III-1 DL/SEPB 3(Sys)
DPC to NRC 08/06/81 TO UTILITY DL/SEPB 0(Elec) 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 4b DPC to NRC 08/06/81 RECEIVED BY NRC (2-19)
. ~.
I.ACROSSE TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR III-3 A.
DE/SEB 2
HRC to DPC 08/09/79 III-10 B.
X NRC to DPC 10/29/79 III-3 B.
X NRC to DPC 03/10/81 III-10 C.
X NRC to DPC 10/29/79 III-3 C.
DE/ HGEB 0
III-11 X
NRC to DPC 05/07/81 III-4 A.
DSI/ASB 0
III-12 X
NRC to DPC 05/07/81 III-4 B.
DE/MTEB 0
IV-1 4.
DL/SEPB 7
HRC to DPC 04/19/79 III-4 C.
DSI/ASB 0
IV-2 DSI/ICSB 2
NRC to DPC 12/15/80 III-4 D.
DE/SAB 4b DPC to NRC 09/15/81 IV-3 X
NRC to DPC 05/07/81 III-5 A.
DL/SEPB 2
NRC to DPC 01/04/80 V-1 DE/MTEB G
NRC to DPC 05/07/81 i
i III-5 B.
DL/SEPB 4b DPC to NRC 06/29/81 V-2 X
NRC to DPC 10/29/79 III-6 DL/SEPB 3
DPC to NRC 06/12/81 V-3 X
NRC to DPC 05/07/81 III-7 A.
X NRC to DPC 05/07/81 V-4 X
NRC to DPC 05/07/81 III-7 B.
DL/SEPB 2
NRC to DPC 08/09/79 V-5 DL/SEPB 4a III-7 C.
X HRC to DPC 10/29/79 V-6 DL/SEPB 7
NRC to DPC 03/05/80 III-7 D.
DE/SEB 4b DPC to NRC 06/29/81 V-7 X
NRC to DPC 05/07/81 III-8 A.
DSI G
HRC to DPC 05/07/81 V-8 X
NRC to DPC 05/07/81 III-8 B.
X NRC to DPC 09/26/80 V-9 X
NRC to DPC 10/29/79 DL/SEPB III-8 C.
DL/SEPB 7
DPC to NRC 03/03/81 V-10 A.
7 NRC to DPC 01/07/81 III-8 D.
X NRC to DPC 05/07/81 V-10 B.
DL/SEPB 5
NRC to DPC 12/22/80 III-9 X
NRC to DPC 05/07/81 V-11 A.
DL/SEPB 7
HRC to DPC 12/22/80 III-10 A.
DL/SEPB 7
NRC to DPC 09/22/81 V-11 B.
DL/SEPB 5(Sys)
NRC to DPC 12/22/80 DL/SEPB 0(Elec) i i
l f
i (2-20) l
{
-m....
b i
i i
LACROSSE TOPIC HO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.
DL/SEPB 7
NRC to DPC 04/30/79 VI-7 D.
DL/SEPB 7
NRC to DPC 08/17/78 V-13 X
HRC to DPC 05/07/81 VI-7 E.
X NRC to DPC 05/07/81 VI-1 DE/CEB 3
DPC to NRC 08/23/79 VI-7 F.'
X HRC to DPC 10/29/79 VI-2 A.
X NRC to DPC 05/07/81 VI-8 X
HRC to DPC 05/07/81 L
VI-2 B.
X HRC to DPC 05/07/81 VI-9 X
NRC to DPC 10/29/79 VI-2 C.
X
'NRC to DPC 10/29/79 VI-10 A.
DL/SEPB-2 NRC to DPC 07/21/81 VI-2 D.
DSI/CSB 3
DPC to NRC 04/26/79 VI-10 B.
X NRC to DPC 10/29/79 VI-3 DSI/CSB 3
DPC to NRC 04/26/79 VII-1 A.
DL/SEPB 0
VI-4 DSI/CSB 3(Sys)
DPC to NRC 08/17/81 VII-1 B.
DL/SEPB 7
NRC to DPC 08/17/78 DL/SEPB 6(Elec) DPC to NRC 08/26/81 VII-2 DL/SEPB 0
VI-5 X
NRC to DPC 05/07/81 VII-3 DL/SEPB 5(Sys)
NRC to DPC 12/22/80 VI-6 DSI/CSB G
HRC to DPC 05/07/81 DL/SEPB 3(Elec!
VI-7 A.
1 X
HRC to DPC 10/29/79 VII-4 X
HRC 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 t
VI-7 A.
3.
DL/SEPB 0
VII-6 DL/SEPB 7
NRC to DPC 09/21/81 VI-7 A. 4.
X NRC to DPC 05/07/81 VII-7 X
NRC to DPC 10/29/79 VI-7 B.
X NRC to DPC 10/29/79 VIII-1 A.
DSI/PSB G
HRC to DPC 05/07/81 i
VI-7 C.
DL/SEPB 7
NRC to DPC 03/13/81 VIII-2 DL/SEPB 6
DPC to NRC 11/20/80 VI-7 c.
1.
DL/SEPB 7
HRC to DPC 09/21/81 VIII-3 A.
DL/SEPB 7
HRC to DPC 06/05/79 VI-7 C.
2.
DL/SEPB 7
NRC to DPC 03/13/81 VIII-3 B.
DL/SEPB 7
NRC to DPC 08/28/81 l
'VI-7 C.
3.
X NRC to DPC 10/29/79 VIII-4 DL/SEPB 7
NRC to DPC 09/09/81 i
t f
I I
(2-21)
LACROSSE TOPIC HO.
REVIEW STATUS REMARKS TOPIC HO.
REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 0
XV-10 X
HRC to DPC 10/29/19 IX-2 X
HRC to DPC 05/07/81 XV-11 DSI/CPB 0
IX-3 DL/SEPB 2
XV-12 X
HRC to DPC 10/29/79 IX-4 X
NRC to DPC 10/29/79 XV-13 DSI/CPB 0(Doses)
DSI/AEB 0(Sys)
IX-5 DL/SEPB 0
XV-14 DSI/RSB Gb DPC to NRC 08/25/81 IX-6 DE G
NRC to DPC 05/07/81 XV-15 DSI/RSB 7
NRC to DPC 09/21/81 X
X NRC to DPC 05/07/81 XV-16 DSI/AEB 0
XI-1 DSI/ETSB G
HRC to DPC 05/07/81 XV-17 X
HRC to DPC 10/29/79 XI-2 DSI/ETSB G
HRC to DPC 05/07/81 XV-18 DSI/AEB 0(Doses)
XIII-1 X
NRC to DPC 05/07/81 DSI/RSB 0(Sys)
XIII-2 DL/SSPB 7
HRC to DPC 03/11/81 XV-19 DSI/AEB 0(Doses)
DSI/RSB 0(Sys)
XV-1 DSI/RSB 0
XV-20 DSI/AEB 0
XV-2 X
HRC to DPC 10/29/79 XV-21 X
HRC to DPC 05/07/81 XV-3 DSI/RSB Gb DPC to NRC 06/26/81 XV-22 X
NRC to DPC 05/07/81 XV-4 DSI/RSB 4b DPC to NRC 06/26/81 XV-23 X
HRC to DPC 05/07/81 XV-5 DSI/RSB 0
XV-24 X
NRC to DPC 05/07/81 XV-6 X
NRC to DPC 10/29/79 XVI X
HRC to DPC 11/05/80 XV-7 DSI/RSB 0
XVII DL 7
NRC to DPC 08/\\7/78
'V - 8 DSI/CPB 0
XV-9 DSI/RSB 4b DPC to NRC 08/25/81 i
(2-22)
MILLSTONE 1 TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR III-3 A.
DE/SEB 5
HRC to NU 05/11/81 III-10 B.
X HRC to NU 11/16/79 III-3 B.
X NRC to NU 12/26/80 III-10 C.
DL/SEPB 7
NU to NRC 08/29/79 III-3 C.
DE/HGEB 4b NU to NRC 08/31/81 III-11 X
NRC to NU 05/07/81 III-4 A.
DSI/ASB 4b NU to NRC 08/31/81 III-12 X
NRC to NU 05/07/81 III-4 B.
DE/MTEB 4b NU to NRC 08/31/81 IV-1 A.
DL/SEPB 7
HU to NRC 02/12/79 III-4 C.
DSI/ASB 3
NU to NRC 12/05/80 IV-2 L "il/I CS B 2
NRC to NU 12/15/80 III-4 D.
DE/SAB 4b NU to NRC 04/29/81 IV-3 DE/MTEB G
HRC to NU 05/07/81 III-5 A.
DL/SEPB 3
NU to NRC 11/08/79 V-1 DE/MTEB G
NRC to NU 05/07/81 III-5 B.
DL/SEPB 1
V-2 X
HRC to NU 11/16/79 III-6 DL/SEPB 5
HRC to NU 05/28/81 V-3 X
NRC to NU 05/07/81 III-7 A.
X HRC to NU 05/07/81 V-4 X
NRC to HL 05/07/81 III-7 B.
DL/SEPB 3
NU to NRC 08/29/79 V-5 DL/SEPB 7
HRC to NU 08/28/81 III-7 C.
X NRC to NU 11/16/79 V-6 DL/SEPB 7
NRC to NU 03/05/80 III-7 D.
DE/SEB 7
NU to NRC 02/17/81 V-7 X
NPC to NU 05/07/81 III-8 A.
DSI G
NRC to NU 05/07/81 V-8 X
NRC to NU 05/07/81 III-8 B.
X NRC to NU 09/26/80 V-9 X
NRC to NU 11/16/79 III-8 C.
DL/SEPB 6
NU to NRC 01/31/80 V-10 A.
DL/SEPB 7
NU to NRC 03/05/79 III-8 D.
X NRC 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 5
HRC to NU 07/08/81 III-10 A.
DL/SEPB 7
HRC to NU 06/28/81 V-11 B.
DL/SEPB 7(Sys)
HU to NRC 07/22/81 DL/SEPB 0(EIcc)
(2-24)
MILLSTONE 1 FACILITY: MILLSTONE 1 TOPIC NO.
REVIEW STATUS REMARKS DIV/BR LICENSEE: NORTHEAST NUCLEAR ENERGY 11-1 A.
DE/SAB 7
HRC to NU 07/31/81 REGION / LOCATION: 5 MILES SOUTH WEST OF NEW LONDON, CONN.
II-1 B.
DE/SAB 4b NU to NRC 05/19/81 DOCKET HO.
05000245 II-1 C.
DE/SAB 4b NU to NRC 04/29/81 POWER CAPACITY: 2011(THERMAL) 0660(ELECTRICAL)
II-2 A.
DSI/AEB 7
NRC to NU 03/30/81 OL NUMBER: LPR-21 II-2 B.
X NRC to NU 05/07/81 N.S.S.S.
GE.
II-2 C.
DSI/AEB 7
NRC to NU 09/29/81 A/E FIRM: EBASCO II-2 D.
X NRC to NU 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W.
RUSSE'l II-3 A.
DE/HGEB 4b HU to HRC 06/25/81 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD II-3 B.
DE/HGEB 4b NU to NRC 06/26/81 OPERATIHG REACTORS PROJECT MANAGER:
J.
SHEA II-3 B.
1 DE/HGEB 4b NU to NRC 06/25/81 INTEGRATED ASSESSMENT PROJECT MAHAGER:
A.
PERSINKO II-3 C.
DE/HGEB 4b HU to NRC 04/28/81 II-4 DE/GSB 7
NRC to NU 06/08/81 KEY FOR STATUS C'2E1 II-4 A.
DE/GSB 7
HRC to HU 06/08/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.
DE/GSB 3
HUREG/CR1582 08/00/81 FROM REVIEW BRANCH X - DELETED II-4 C.
DE/GSB 7
NRC to NU 06/08/81 4b-SAR RECEIVED FROM 0 - TOPIC HOT LICENSEE II-4 D.
DE/HGEB 4b NU to NRC 08/31/81 STARTED 5 - DRAFT SE SENT II-4 E.
X "RC to NU 11/16/79 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.
DE/HGEB Gb Nu to NRC 04/28/81 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC III-1 DL/SEPB 2(Elec) NRC to NU 06/09/81 TO UTILITY DL/SEPB 3(Syr)
NU to NRC 08/20/81 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 3
HU to NRC 08/29/79 RECEIVED BY HRC (2-23)
MILLSTONE 1 TOPIC HO.
REVIEW STATUS REMARKS TOPIC HO.
REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 4b HU to NRC 08/31/81 Xc-10 X
HRC to NU 11/16/79 IX-2 X
HRC to NU 05/07/81 eV-11 DSI/CPB 4b NU to HRC 06/30/81 IX-3 DL/SEPB 2
XV-12 X
NRC to NU 11/16/79 IX-4 X
HRC to NU 11/16/79 XV-13 DSI/CPB 7(Sys)
NU to NRC 09/09/81 DSI/AEB 4a(Doses)
IX-5 DL/SEPB 0
XV-14 DSI/RSB 7
HRC to HU 09/18/81 IX-6 DSI DE HRC to NU 05/07/81 XV-15 DSI/RSB 4b NU to NRC 06/30/81 X
X HRC to NU 05/07/81 XV-16 DSI/AEB 4a XI-1 DSI/ETSB G
HRC to NU 05/07/81 XV-17 X
NRC to NU 11/16/79 XI-2 DSI/ETSB G
HRC to NU 05/07/81 XV-18 DSI/RSB 4b(Sys) HU to HRC 06/30/81 XIII-1 X
HRC to NU 05/07/81 DSI/AEB Ga(Doses)
XIII-2 DL/SSPB G
NRC to NU 05/07/81 XV-19 DSI/RSB 7(Sys)
NRC to NU 08/26/81 DSI/AEB 4a(Doses)
XV-1 DSI/RSB 4b HU to NRC 06/30/81 XV-20 DSI/AEB 4a XV-2 X
HRC to NU 11/16/79 XV.1 X
HRC to NU 05/617/81 XV-3 DSI/RSB 7
NRC to NU 09/18/81 XV-26 X
HRC to HU 05/07/81 XV-4 DSI/RSB 7
HRC to NU 09/18/81 XV-23 X
HRC to NU 05/07/81 XV-5 DSI/RSB 4b NU to NRC 06/30/81 XV-24 X
NRC to NU 05/07/81 XV-6 X
NRC to NU 11/16/79 XVI X
HRC to NU 11/15/80 XV-7 DSI/RSB 4b HU to HRC 06/30/81 XVII DL 7
HRC to NU 08/17/78 XV-8 DSI/CPB 7
NRC to HU 08/26/81 XV-9 DSI/RSB 4b ftU to HRC 06/30/81 (2-26)
--.n..-.
_.~
... -. ~...
1 MILLSTONE 1 1
TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STA:US REMARKS DIV/BR DIV/BR V-12 A.
DL/SEPB 7
NRC to NU 12/17/79 VI-7 D.
DL/SEPB 7
hRC to NU 08/17/78 I
V-13 X
NRC to NU 05/07/81 VI-7 E.
X NRC to NU 05/07/81 VI-1 DE/CEB 3
WJ to NRC 10/10/80 VI-7 F.
X' NRC to NU 11/16/79 VI-2 A.
X NRC to NU 05/07/81 VI-8 X
HRC to HU 05/37/81 V7-2 B.
X HRC to NU 05/07/81 VI-9 X
NRC to HU 11/16/79 "I ' C.
X NRC to NU 11/16/79 VI-10 A.
DL/SEPB 6
NU to hRC 08/04/81 VI-2 D.
DSI/C B 3
NU to NRC 06/09/81 VI-10 B.
DL/SEPB 7(Sys)
NU to NRC 08/05/81 DL/SEPB 7(Elec)
VI-3 CSI/CSB 3
HU to NRC 06/09/81 VII-1 A.
DL/SEPB 7
HRC to NU 07/23/81 1
VI-4 DSI/CSB 0(Sys)
DL/SEPB 6(Elec) NU to NRC 08/12/81 VII-1 B.
DL/SEPB 7
NRC to NU 08/17/78 I
VI-5 X
NRC to NU 05/07/81 VII-2 DL/SEPB 7
NRC to NU 08/28/81 VI-6 DSI/CSB G
NRC to NU 05/07/81 VII-3 DL/SEPB 7(Sys)
NU to NRC 07/22/81 I
VI-7 A.
1.
X NRC to NU 11/16/79 VII-4 X
NRC to HU 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 6
NU to NRC 08/25/81 6
VII-6 DL/SEPB 7
NRC to NU 08 '26/81 VI-7 A.
4.
DSI/RSB G
NRC to NU 05/07/81
'i VII-7 X
NRC to NU 11/s,/79 VI-7 B.
X NRC
+A NU 11/16/79 VIII-1 A.
DSI/RSB G
NRC to NU 05/07/81 VI-7 C.
DL/SEPB 7
NRC to NU 03/29/81 VIII-2 DL/SEPB 7
NRC to NU 02/13/81 VI-7 C.
1.
DL/SEPB 7
HRC to NU 09/11/81 VIII-3 A.
DL/SEPB 7
HRC to NU 08/26/81 VI-7 C. 2.
DL/SEPB 7
NRC to NU 03/29/81 i
VIII-3 B.
DL/SEPB 7
HRC to NU 07/23/81 VI-7 C.
3.
X NRC to NU 11/16/79 VIII-4 DL/SEPB 7
NRC to NU 07/07/81 I
h a
l (2-25) m.
0YSTER CREEK FACILITY: OYSTER CREEK 1 TOPIC HO.
REVIEW STATUS REMARKS DIV/BR LICENSEE: JERSEY CENTRAL POWER 4 LIGHT 11-1 A.
DE/SAB 4b JCPL to NRC 05/07/81 REGION / LOCATION: 9 MILES SOUTH OF TOMS RIVE 2, NJ.
II-1 B.
DE/SAB 4b JCPL to HRC 05/07/81 DOCKET NO.
05000219 11-1 C.
DE/SAB 4b JCPL to NRC 05/07/81 POWER CAPACITY: 1930(THERMAL) 0650(ELECTRICAL)
II-2 A.
DSI/AEB 5
NRC tc JCPL 12/17/80 OL NUMBER: DPR-16 II-2 B.
X HRC to JCPL 05/07/81 N.S.S.S.
GE.
II-2 C.
DSI/AEB 0
A/E FIRM: B8R II-2 D.
X HRC to JCPL 05/07/81 SYSTEMATIC EVALUATION PROGRAM. uncH CHIEF: W.
RUSSELL II-3 A.
DE/HGEB 4b JCPL to NRC 05/07/81 OPERATING REACTORS BRANCH CHIEF:
D. CRUTCHFIELD II-3 B.
DE/HGEB 4b JCPL to HRC 05/07/81 OPERATING REACTORS PROJECT MANAGER:
J.
LOMBARDJ II-3 B.
1 DE/HGEB 4b JCPL to NRC 05/07/81 INTEGRATED ASSESSMENT PROJECT MANAGER:
R.
FELL II-3 C.
DE/HGEB 4b JCPL to HRC 05/07/81 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 0 - GENERIC 4a-DRAFT SE RECEIVED II-4 B.
DE/GSB 5
HRC to JCPL 08/03/81 FROM REVIEW BRANCH X - DELETED II-4 C.
DE/GSB 7
NRC to JOPL 06/08/81 4b-SAR RECEIVED FROM 0 - TOPIC HOT I.ICENSEE II-4 D.
DE/HGEB 0
STARTED 5 - DRAFT SE SENT II-4 E.
X NRC to JCPL 11/16/79 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.
DE/HGEB 0
6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC III-1 DL/SEPB 3(Sys)
HRC to JCPL 07/09/81 TO UTILITY DL/SEPB 5(Elec) HRC to JCPL 07/09/81 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 4b JCPL to NRC 05/07/81 RECEIVED BY HRC (2-27)
{
0YSTER CREEK TOPIC NO.
REVIEW STATUS REMARKS TOPIC HO.
REVIEW STATUS REMARKS DIV/BR DIV/BR III-3 A.
OE/SEB 4b JCPL to NRC 05/07/81 III-10 8.
X HRC to JCPL 11/16/79 III-3 B.
X NRC to JCPL 12/26/80 III-10 C.
X NRC to JCPL 11/16/79 III-3 C.
DE/HGEB 0
III-11 X
HRC to JCPL 05/07/81 III-4 A.
DSI/ASB 0
III-12 X
NRC to JCPL 05/07/81 III-4 B.
DE/M T EB 0
IV-1 A.
DL/SEPB 7
NRC to JCPL 05/30/79 III-4 C.
DSI/ASB 2
NRC to JCPL 01/19/81 IV-2 DSI/ICSB 2
dRC to JCPL 12/15/80 III-4 D.
DE/SAB 4b JCPL to NRC 05/07/81 IV-3 X
NRC to JCPL 05/07/81 III-5 A.
DL/SEPB 5
NRC to JCPL 06/10/81 V-1 DE/MTEB C
NRC to JCPL 05/07/81 III-5 B.
DL/SEPB 6
JCPL to NRC 10/06/80 V-2 X
NRC to JCPL 11/16/79 III-6 DL/SEPB 6
JCPL to NRC 06/15/81 V-3 X
NRC to JCPL 05/07/81 III-7 A.
X NRC to JCPL 05/07/81 V-4 X
NRC to JCPL 05/07/81 III-7 B.
DL/SEPB 4a V-5 DL/SEPB 5
NRC to JCPL 03/16/81 III-7 C.
X NRC to JCPL 11/16/79 V-6 DL/SEPB 7
NRC to JCPL 03/05/80 III-7 D.
DE/SEB 3
JCPL to NRC 12/07/79 V-7 X
NRC to JCPL 05/07/81 III-8 A.
DSI G
HRC to JCPL 05/07/81 V-8 X
NRC to JCPL 05/07/81 III-8 B.
X NRC to JCPL 09/26/80 V-9 X
NRC to JCPL 11/16/79 III-8 C.
DL/SEPB 7
NRC to JCPL 10/30/80 V-10 A.
DL/SEPB 7
JCPL to NRC 05/15/79 III-S 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) NRC 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 5
NRC to JCPL 03/16/81 VI-7 D.
DL/SEPB 7
NRC to JCPL 08/17/78 V-13 X
NRC to JCPL 05/07/81 VI-7 E.
X NRC to JCPL 05/07/81
)
VI-1 DE/Cto 2
NRC to JCPL 06/06/79 VI-7 F.
X NRC to JCPL 11/16/79 VI-2 A.
X NRC to JCPL 05/07/81 VI-8 X
HRC to JCPL 05/07/81 VI-2 B.
X NRC to JCPL 05/07/P*
VI-9 X
HRC to JCPL 11/16/79 VI-2 C.
X NRC to JCPL 11/16/79 VI-10 A.
DL/SEPB 7
NRC to JCPL 08/18/81 VI-2 D.
DSI/CSB 2
VI-10 B.
X NRC to JCPL 11/16/79 VI-3 DSI/CSB 2
VII-1 A.
DL/SEPB 7
NRC to JCPL 07/30/81 VI-4 DSI/CSB 2(Sys)
HRC to JCPL 04/17/81 VII-1 8.
DL/SEPB 7
NRC to JCPL 08/17/78 DL/SEPB 5(Elec) HRC to JCPL 08/05/81 VII-2 DL/SEPB 6
JCPL to NRC 08/17/81 VI X NRC to JCPL 05/07/81 VII-3 DL/ SEPP 7(Sys)
HRC to JCPL 09/25/80 VI-6 DSI/CSB G
NRC to JCPL 05/07/81 DL/SEPB 7(Elec) HRC to JCPL 07/09/81 VI-7 A.
1.
X NRC to JCPL 11/16/79 VII-4 X
NRC to JCPL-05/07/81 VI-7 A.
2.
X NRC to JCPL 05/07/81 VII-5 X
NRC to JCPL 05/07/81 VI-7 A.
3.
DL/SEPB 7
NRC to JCPL 07/30/81 VII-6 DL/SEPB 7
NRC to JCPL 08/29/81 VI-7 A. 4.
DSI/RSB G
NRC to JCPL 05/07/81 VII-7 X
NRC to JCPL 11/16/79 VI-7 B.
X NRC to JCPL 11/16/79 VIII-1 A.
DSI/PSB G
NRC to JCPL 05/07/81 8
VI-7 C.
DL/SEPB 7
HRC to JCPL 03/13/81 VIII-2 DL/SEPB 7
NRC to JCPL 06/29/81 VI-7 C.
1.
DL/SEPB 7
HRC to JCPL 06/29/81 VIII-3 A.
DL/SEPB 7
NRC to JCPL 06/29/81 VI-7 C. 2.
DL/SEPB 7
NRC to JCPL 03/13/81 VIII-3 B.
DL/SEPB 7
NRC to JCPL 06/29/81 VI-7 C.
3.
X NRC to JCPL 11/16/79 VIII-4 DL/SEPB 2
NRC to JCPL 03/26/80 l
i 4
.i (2-29)
0YSTER CREEK TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 3
JCPL to NRC 12/14/79 XV-10 if NRC to JCPL 11/16/79 IX-2 X
NRC to JCPL 05/07/81 XV-11 DSI/CPB 5
NRC to JCPL 04/09/81 IX-3 DSI/ASB 5
NRC to JCPL 06.'12/81 XV-12 X
NRC to JCPL 11/16/79 IX-4 X
NRC to JCPL 05/07/81 XV-13 DS I/ A E f.
4a(Doses)
DSI/CPb 5(Sys)
HR: to JCFL 04/09/81 IX-5 DL/SEPB 0
XV-14 DSI/RSB 7
HRC to JCPL 07/16/81 IX-6 DE G
NPC to JCPL 05/07/81 XV-15 Dit/RSB Gb JCPL to NRC 05/07/81 X
X NRC to JCPL 05/07/81 XV-16 DSI/AEB 0
XI-1 DSI/ETSB G
HRC to JCPL 05/07/81 XV-17 X
NRC to JCPL 11/16/79 XI-2 DSI/ETSS G
NRC to JCPL 05/07/81 XV-18 DSI/ AFB 4a(Doses)
XIII-1 X
HRC to JCPL 05/07/81 DSI/RSS 4b(Sys) JCPL to NRC 05/07/81 XIII-2 DL/SSPB 7
NRC to JCPL 09/25/80 XV-19 DSI/AEB 4b(Doses)JCPL to NRC 05/07/81 DSI/RSB 7(Sys)
NRC to JCPL 09/04/81 XV-1 DSI/RSB 4b JCPL to NRC 05/07/81 XV-20 DSI/RSB 4b JCPL to NRC 05/07/81 XV-2 X
NRC to JCPL 11/16/79 XV-21 X
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
NRC to JCPL 07/16/81 XV-23 X
NRC to JCPL 05/07/81 XV-5 DSI/RSB 4b JCPL to NRC 05/07/81 XV-24 X
NRC to JCPL 05/07/81 XV-6 X
NRC to JCPL 11/16/79 XVI X
HRC to JCPL 11/05/80 XV-7 DSI/RSB 4b JCPL to NRC 08/25/81 XVII DL 7
NRC to JCPL 08/17/78 XV-8 DSI/CPB 5
NRC to JCPL 03/31/81 XV-9 DSI/RSB Gb JCPL to NRC 05/07/81
'30) l
PALISADES I
FACILITY: PALISADES TOPIC HO.
REVIEW STATUS REMARKS DIV/BR LIC2NSEE: CONSUMERS POWER 11-1 A.
DL/SEPB 7
CPCo to NRC 12/28/79 REGION / LOCATION: 5 MILES SOUTH OF SOUTH HAVEN, MI.
II-1 B.
DL/SEPB 7
CPCo to NRC 12/28/79 DOCKET NO: 05000255 II-1 C.
DL/SEPB 7
CPCo to NRC 05/13/81 POWER CAPACITY: 2530(THERMAL) 0508(ELECTRICAL)
II-2 A.
DSI/AEB 7
NRC to CPCo 06/30/81 OL NUMBER: DPR-20 II-2 B.
X HRC to CPCo 05/07/81 N.S.S.S.: C-E II-2 C.
DSI/AEB 7
HRC to CPCo 04/23/81 A/E FIRM: BECH.
II-2 D.
X NRC to CPCo 05/07/81 SYSTEMATIC E'JALUATION PROGRAM BR ANCH CHIEF: W. RUSSELL II-3 A.
DE/HGEB 6
CPCo to NRC 08/13/81 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD II-3 B.
DE/HGEB 6
CPCo to NRC 08/13/81 OPERATING REACTORS PROJECT MANAGER:
T. WAMBACH II-3 B.
1 DE/HGEB 6
CPCo to NRC 08/13/81 INTEGRATED ASSESSMENT PROJECT MANAGER:
T. MICHAELS II-3 C.
DE/HGEB 6
CPCo to NRC 08/13/81 II-4 DE/GSB 7
CPCo to NRC 07/04/81 KEY FOR STAT 95 CODES II-4 A.
DE/GSD 7
NRC to CPCo 07/04/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.
DE/GSB 7
CPCo to NRC 07/22/81 FROM REVIEW BRANCH X - DELETED II-4 C.
DE/GSB 7
HRC to CPCo 06/08/81 4b-SAR RECEIVED FROM 0 - TOPIC NOT LICENSEE II-4 D.
DE/HGEB 7
CPCo to NRC 06/01/81 STARTED 5 - DRAFT SE SENT II-4 E.
X NRC to CPCo 11/16/79 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.
DE/HGEB 7
CPCo to NRC 06/01/81 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC III-1 DL/SEPB 7(Elec) NRC to CPCo 11/12/80 TO UTILITY DL/SEPB 3(Sys)
CPCo to NRC 08/17/81 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE RECEIVED BY HRC (2 31)
m.. _. _ _ _. _ _
PALISADES TOPIC NO.
REVIEW. STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR III-2 DL/SEPB 7
NRC to CPCo 02/27/81 111-10 B.
LL/SEPB 6
CPCo to NRC 07/02/81 III-3 A.
DE/SEB 7
NRC to CPCo 08/26/81 III-10 C.
X NRC to CPCo 11/16/79 III-3 B.
X NRC to CPCo 12/26/80 III-11 X
NRC ta CPCo 05/07/81 III-3 C.
DE/HGEB 0
III-12 X
NRC to CPCo 05/07/81 III-4 A.
DSI/AEB
-5 NRC to CPCo 08/28/81 IV-1 A.
DL/SEPB 7
CPCo to NRC 02/08/79
)
III-4 B.
DE/MTEB G
NRC to CPCo 05/07/81 IV-2 DSI/ICSB 4a CPCo to NRC 07/21/81 III-4 C.
DSI/ASB 7
HRC to CPCo 09/21/81 IV-3 X
NRC to CPCo 05/07/81 f
III-4 D.
DE/SAB 7
CPCo to NRC 08/03/81 V-1 D E/MT EB G
NRC to CPCo 05/07/81 III-5 A.
DL/SEPB 4b CPCo to NRC 08/13/81 V-2 X
HRC to CPCo 11/16/79 j
III-5 B.
DL/SEPB.
4b CPCo to NRC 08/25/81 V-3 X
NRC to CPCo 05/07/81 III-6 DL/SEPB 6
CPCo to NRC 07/13/81 V-4 X
NRC to CPCo 05/07/81 III-7 A.
DL/SEPB G Part NRC to CPCo 05/07/81 V-5 DL/SEPB 5
HRC to CPCo 07/16/81 5 Bal NRC to CPCo 08/25/81 V-6 DL/SEPB 7
HRC to CPCo 03/05/80 III-7 B.
DL/SEPB 4a V-7 DSI/ASB G
NRC to CPCo 05/07/81 l
J III-7 C.
DE/SEB 6
CPCo to NRC 07/21/81 V-8 X
NRC to CPCo 05/07/81 4
III-7 D.
DE/SEB 7
CPCo to NRC 08/17/81 V-9 X
NRC to CPCo
!1/16/79 3
III-8 A.
DSI G
HRC to CPCo 05/07/81 V-10 A.
DL/SEPB 7
NRC to CPCo 09/26/81 III-8 B.
X NRC to CPCo 10/01/80 V-10 B.
DL/SEPB 6
CPCo to NRC 07/22/81
)
III-8 C.
DL/MTEB 7
CPCo to NRC 12/28/79 V-11 A.
DL/SEPB 6
CPCo to NRC 07/03/81 a
i III-8 D.
X NRC to CPCo 05/07/81 V-11 B.
DL/SEPB 6(Sys)
CPCo to NRC -
07/22/81 III-9 X
NRC to CPCo 05/07/81 DL/SEPB 7(Elec) NRC to CPCo 06/02/81 III-10 A.
DL/SEPB 7
HRC to CPCo 05/19/81 4
i i'
(2-32) 9
8 1
1 1
9 1
9 1
8 1
11 1
1 1
9 1
1 1
1 1
7 8 8 8 7
8 7 8 7
8 88 8 8 8 7
8 8 8 8 8
/ / / / / / / / / / // / / / / / / / / /
7 7
0 7
6 9
6 8
7 9
27 7
7 9
6 7
9 2
5 1
1 0
3 0
1 1
1 2
1 1
21 0
0 1
1 0
0 2
0 3
/ / / / / / / / / / // / / / / / / / / /
8 5 6
5 1
6 1
8 8 5 78 5
5 5 1
5 6
5 8 7
0 0
0 0
1 0
1 0
0 0
00 0
0 0
1 0
0 0
0 0
o o o o o o o o o o CC o o o o o o o o o C C C C C C C C C C RR C C C C C C C C C P P P P P P P P P P NN P P P P P P P P P C C C C C C C C C C C C C C C C C C C S
oo K
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t t
t t
t t
t t
t t
t t
t t
t t
t t
t A
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C C C C C C C C C C CC C C C C C C C C C E
R R R R
R R R R R R PP R R
R R R
R R R
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N H H N N H N H N N CC N N N N N N N H N
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A 7
X 7
X X 7
X 7 7 7
66 X X 7 X G 7 7 7 7 T
S B
B B
B B B BB B
B B B B B WR P
P P
P P P PP P
S P P
P P
EB E
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EE E
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S S
S S S S SS S
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L L
L L
L LL L
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L L
L RD D
D D
D D D DD D
D D D D D O
A A B H
A B A B D E F 1
2 3 3 4 C
0 0
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2 3 4
5 6 7 I
7 7
7 8
9 1
1 I
I I
I I
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V V V V V V V V V V V V V V V V V V V V
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3 3
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9 1
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1 9
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9 7
8 8 8 8 7
8 8 88 8 8 7
8 8 8 88 8 8 8 7
/ / / / / / / / // / / / / / / // / / / /
6 7
3 7 7 6
9 9
80 7
7 6
7 2 7
90 0
8 0
2 1
0 0
0 0
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0 11 0
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/ / / / / / / / // / / / / / / // / / / /
1 5
8 5 5 1
7 7
88 5 5 1
5 7
5 56 2
1 2 2 1
0 0
0 0
1 0
0 00 0
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0 00 0
1 0
1 o o o o o o C C CC o o o o C o oo o o o C C C C C C C R
R RR C C C C R
C CC C C C R
P P P P P P
N H HN P P P P N P PP P P P N C C C C C C C C C C C CC C C C S
o o oo o
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o o o o o o t
t tt o o o o t
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t t
t t
t t
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C C C C C C C C CC C C C C C C CC C C C C
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((
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A X X 7 X X X 6
6 76 X G X X 6 X 77 7 7 7 X
T S
B B BB B
S S PS S
P PS P P P
EB E
C C EC C
E ER E E E I/
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/ / S/
/
S S/
S S S S
VV
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I I
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/
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/ / /
EI E
S S LC S
L LS L
L L
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D D DD D
2 3 1
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A A B C D A A A A B C C C C C
L I
2 3
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6 7
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T V V V V V V V V V V V V V V V V V V V V P
f
- i fl l
ilt
PALISADES TOPIC NO.
REVIEW STATUS REMARKS TOPIC HO.
REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 2
NRC to CPCo 01/29/81 XV-10 DL/SEPB 7
NRC to CPCo 07/17/81 IX-2 X
NRC to CPCo 05/07/81 XV-11 X
NRC to CPCo 10/01/80 IX-3 DL/SEPB 7
NRC to CPCo 09/06/81 XV-12 DL/SEPB 7(Doses) HRC to CPCo 01/29/80 DL/SEPB 7(Sys)
HRC to CPCo C7/17/81 IX-4 DSI/RSB 2
NRC to CPCo 12/26/80 XV-13 X
HRC to CPCo 11/16/79 IX-5 DL/3EPB 5
NRC to CPCo 08/03/81 XV-14 DL/SEPB 7
NRC to CPCo 07/17/81 IX-6 DE G
NRC to CPCo 05/07/81 XV-15 DL/SEPB 7
NRC to CPCo 07/17/81 X
X NRC to CPCo 05/07/81 XV-16 DL/SEPB 7
NRC to CPCo 12/31/80 XI-9 DSI/ETSB G
NRC to CPCo 05/07/81 XV-17 DL/SEPB 7(Doses) HRC to CPCo 01/29/80 XI-2 DSI/ETSB G
HRC to CPCo 05/07/81 DL/SEPB 7(Sys)
NRC to CPCo 07/17/81 XIII-1 X
NRC to CPCo 05/07/81 XV-18 X
NRC to CPCo 10/01/80 XIII-2 DL/SSPB 7
NRC tc CPCo 10/01/80 XV-19 DL/SEPB 7(Doses) NRC to CPCo 11/21/80 DL/SEPB 7(Sys)
NRC to CPCo 07/17/81 XV -1 DL/SEPB 7
NRC to CPCo 07/17/81 XV-20 DL/SEPB 7
NRC to CPCo 11/21/80 XV-2 DL/SEPB 7(Doses) HRC to CPCo 05/18/81 DL/SEPB 7(Sys)
HRC to CPCo 07/17/81 XV-21 X
HRC to CPCo 05/07/81 XV-3 DL/SEPB 7
NRC to CPCo 07/17/81 XV-22 X
NRC to CPCo 05/07/81 XV-4 DL/SEPB 7
NRC to CPCo 07/17/81 XV-23 X
NRC to CPCo 05/07/81 XV-5 DL/SEPB 7
NRC to CPCo 07/17/81 XV-24 X
NRC to CPCo 05/07/81 XV-6 DL/SEPB 7
NRC to CPCo 07/17/81 XVI X
HRC to CPCo 11/05/80 XV-7 DL/SEPB 7
NRC to CPCo 07/17/81 XVII DL 7
NRC to CPCo 08/17/78 XV-8 DL/SEPB 7
HRC to CPCo 07/17/81 XV-9 DL/SEPB 7
HRC to CPCo 07/17/81 (2-34) l l
l
\\
SAN ON0FRE FACILITY: SAH ONOFRE 1 TOPIC NO.
REVIEW STATUS REMARKS DIV/BR LICENSEE: SOUTHERN CALIFORHIA EDISON II-1 A.
DL/SEPB 7
NRC to SCE 11/07/79 P.EGI O H / L O C A T I O N : 5 MILES SOUTH OF SAN CLEMENTE, CA.
II-1 B.
DL/SEPB 7
NRC to SCE 11/07/79 DOCKET NO.
05000206 II-1 C.
DE/SAB 3
SCE to NRC 05/07/79 POWER CAPACITY: 1347(THERMAL) 0430(ELECTRICAL)
II-2 A.
DSI/AEB 7
NRC to SCE 04/27/81 OL NUMBER: DPR-13 II-2 B.
X NRC to SCE 05/07/81 N.S.S.S.: WEST.
II-2 C.
DSI/AEB 6
SCE to NRC 12/07/79 A/E FIRM: BECH.
II-2 D.
X HRC to SCE 05/07/81 SYSTEMATIC EVALUATIbH PRf. GRAM BRANCH CHIEF: W.
RUSSELL II-3 A.
DE/HGEB 3
OPERATING REACTORS BRAFCH CHIEF:
D. CRUTCHFIELD II-3 E.
DE/HGEB 3
OPERATING REACTORS PROJECT MANAGER: S. NOWICKI II-3 B.
1.
DE/HGEB 5
NRC to SCE 06/12/81 INTEGRATED ASSESSMENT PROJECT MANAGER:
E. MCKENNA II-3 C.
DE/HGEB 4a II-4 DE/GSB 5
HRC to SCE 03/12/81 KEY FOR STATUS CODES II-4 A.
DE/GSB 5
NUREG-0712 12/80 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.
DE/GSB 5
HUREG-0712 12/80 FROM REVIEW BRANCH X - DELETED II-4 C.
DE/GSB 5
HUREG-0712 12/80 4b-SAR RECEIVED FROM S - TOPIC HGT LICENSEE II-4 D.
DE/HGEB 0
STARTED 5 - DRAFT SE SENT II-4 E.
X NRC to SCE 11/16/79 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.
DE/HGEB 0
6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY HRC III-1 DL/SEPB 3(Sys)
SCE to NRC 08/29/79 TO UTILITY DL/SEPB 0(Elec) 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 3
SCE to NRC 09/08/80 RECEIVED BY NRC k
(2-35)
__m
_ _ ~ _. _.
SAN ONOFRE TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR III-3 A.
DE/SEB 3
SCE to NRC 09/08/80 111-10 B.
DL/SEP6 7
NRC to SCE 11/08/79 III-3 B.
X HRC to SCE 11/16/79 III-10 C.
X HRC to SCE-11/16/79 III-3 C.
DE/HGEB 5
NRC to SCE 07/17/81 III-11 X
NRC to SCE 05/07/81
[
III-4 A.
DSI/ASB 3
SCE to NRC 08/14/79 III-12 X
NRC to SCE 05/07/81 III-4 B.
DE/MTEB G
NRC to SCE 05/07/81 IV-1 A.
DL/SEPB 7
NXC to SCE 11/13/79 III-4 C.
DSI/ASB 0
IV-2 DSI/ICSB 2
NRC to SCE 12/15/80 i
III-4 D.
DE/SAB 0
IV-3 X
HRC to SCE 05/07/81 III-5 A.
DL/SEPB 1
V-1 DE/MTEB G
NRC to SCE 05/07/81 III-5 B.
DL/SEPB 2
NRC to SCE 01/04/80 v-2 X
NRC to SCE 11/16/79 III-6 DL/SEPB 3
SCE to NRC 08/11/81 V-3 X
NRC to SCE 05/07/81 III-7 A.
NRC to SCE 05/07/81 V-4 X
NRC to SCE 05/07/81 i
III-7 B.
DL/SEPB 3
SCE to NRC 09/08/80 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 4b SCE to NRC 06/09/81 V-7 DSI/ASB G
NRC to SCE 05/07/81 III-8 A.
DSI G
NRC to SCE 05/07/81 V-8 X
NRC to SCE 05/07/81 III-8 B.
X NRC to SCE 10/01/80 V-9 X
HRC to SCE 11/16/79 III-8 C.
DL/SEPB NRC to SCE 01/29/80 V-10 A.
DL/SEPB 7
NRC to SCE 01/07/81 i
4 III-8 D.
X HRC to SCE 05/07/81 V-10 B.
DL/SEPB 5
NRC to SCE 06/20/81 III-9 X
NRC to SCE 05/07/81 V-11 A.
DL/SEPB 7
NRC to SCE 08/03/81 III-10 A.
DL/SEPB 7
SCE to NRC 07/24/81 V-11 B.
DL/SEPB 5(Sys)
HRC to SCE 06/20/81 DL/SEPB 2(Elec) Part of VII-3 f
r l
(2-36)
SAN ON0FRE TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.
X NRC to SCE 11/16/79 VI-7 D.
DL/SEPB 7
NRC to SCE 08/17/78 V-13 X
NRC to SCE 05/07/81 VI-7 E.
X NRC to SCE 05/07/81 VI-1 3
SCE to NRC 08/03/79 VI-7 F.
X NRC to SCE 11/16/79 VI-2 A.
X NRC to SCE 05/07/81 VI-8 X
NRC to SCE 05/07/81 VI-2 B.
X NRC to SCE 05/07/81 VI-9 X
NRC to SCE 11/16/79 VI-2 C.
X NRC to SCE 11/16/79 VI-10 A.
DL/SEPB 5
NRC to SCE 08/23/81 VI-2 D.
DSI/CSB 3
SCE to NRC 06/22/79 VI-10 B.
DL/SEPB 7(Sys)
NRC to SCE 11/15/79 DL/SEPB 7(Elec) HRC to SCE 11/15/79 VI-3 DSI/CSB 3
SCE to NRC 06/22/79 VII-1 A.
DL/SEPB 5
NRC to SCE 09/09/81 VI-4 DSI/CSB 2(Sys)
HRC to SCE 07/27/81 DL/SEPB 7(Elec) NRC to SCE 09/03/81 VII-1 B.
DL/SEPB 7
NRC to SCE 08/17/78 VI-5 X
NRC to SCE 05/07/81 VII-2 DL/SEPB 3
SCE to NRC 07/28/81 VI-5 DSI/CSB G
HRC to SCE 05/07/81 VII-3 DL/SEPB 5(Sys)
NRC to SCE 06/20/81 DL/SEPB 3(Elec) SCE to NRC 07/28/81 VI-7 A.
1 DL/SEPB 7
NRC to SCE 02/20/81 VII-4 X
NRC to SCE 05/07/81 VI-7 A. 2.
X NRC to SCE 05/07/81 VII-5 X
NRC to SCE 05/07/81 VI-7 A.
3.
DL/SEPB 0
VII-6 DL/SEPB 7
NRC to SCE 08/28/81 VI-7 A. 4.
X NRC to SCE 05/07/81 VII-7 X
HRC to SCE 11/16/79 VI-7 B.
DSI/RSB 5(Sys)
HRC to SCE 07/24/81 DL/SEPB 5(Elec) HRC to SCE 09/04/81 VIII-1 A.
DSI/RSB G
NRC to SCE 05/07/81 VI-7 C.
DL/SEPB 7
NRC to SCE 06/01/81 VIII-2 DL/SEPB 7
NRC to SCE 07/31/81 VI-7 C.
1 DL/SEPB 7
NRC to SCE 08/03/81 VIII-3 A.
DL/SEPB 7
NRC to SCE 11/07/79 VI-7 C.
2.
DL/SEPB 7
NRC to SCE 06/01/81 VIII-3 B.
DL/SEPR 7
NRC to SCE 07/24/81 VI-7 C.
3.
X NRC to SCE 11/16/79 VIII-4 bl/SEPB 6
SCE to NRC 08/14/81 (2-37)
.__m SAN ONOFRE TOPIC NO.
REVIEW STATUS REMARKS TOPIC HO.
REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 3
SCE to NRC 10/05/79 XV-10 DSI/RSB 4b SCE to NRC 07/01/81 IX-2 X
HRC to SCE 05/07/81 XV-11 X
NRC to SCB 10/01/80 IX-3 DL/SEPB 2
XV-12 DSI/RSB 4b(Sys) SCE to NRC 07/01/81 DL/SEPB 7(Doses) NRC to SCE 01/29/80 IX-4 DSI/RSB 7
NRC to SCE 07/16/81 XV-13 X
NRC to SCE 11/16/79 IX-5 DL/SEPB 0
XV-14 DSI/RSB 4b SCE to NRC 07/01/81 IX-6 DE G
NRC to SCE 05/07/81 XV-15 DSI/R$8 4b SCE to NRC 07/01/81 X
X HRC to SCE 05/07/81 XV-16 DSI/AEB 4b SCE to NRC 08/04/81 XI-1 DSI/ETSB G
NRC to SCE 05/07/81 XV-17 DSI/RSB 4b(Sys) SCE to NRC 07/01/81 XI-2 DSI/ETSB G
NRC to SCE 05/07/81 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
HRC to SCE 01/22/81 XV-19 DSI/RSB 7(Sys)
HRC to SCE 08/26/81 DL/SEPB 7(Doses) HRC to SCE 01/29/80 XV-1 DSI/RSB 4b SCE to HRC 07/01/81 XV-20 DL/SEPB 7
NRC to SCE 03/28/80 XV-2 DSI/RSB 4b(Sys) SCE to NRC 07/01/81 DL/SEPB 7(Doses) HRC to SCE 01/29/80 XV-21 X
NRC to SCE 05/07/81 XV-3 DSI/RSB 7
HRC to SCE 08/26/81 XV-22 X
NRC to SCE 05/07/81 XV-4 DSI/RSB 4b SCE to NRC 08/18/81 XV-23 X
HRC to SCE 05/07/81 XV-5 DSI/RSS 4b SCE to NRC 07/01/81 XV-24 X
NRC to SCE 05/07/81 XV-6 DSI/RSB 4b SCE to NRC 07/01/81 XVI X
HRC to SCE 11/05/80 XV-7 DSI/RSB 4b SCE to HRC 07/01/8?
XVII DL 7
NRC to SCE 08/17/78 XV-8 DSI/CPB 4b SCE to NRC 07/01/81 XV-9 DSI/RSB 5
HRC to SCE 05/11/81 (2-38) i
YANKEE R0WE FACILITY: YANKEE ROWE 1 TOPIC NO.
REVIEW STATUS REMARKS DIV/BR LICENSEE: YANKEE ATOMIC ELECTRIC 11-1 A.
DE/SAB 0
REGIDH/ LOCATION: 25 MILES HORTH EAST OF PITTSFIELD, NASS.
II-1 B.
DE/SAB 4b YAEC to NRC 05/01/81 DOCKET HO.+
05000029 II-1 C.
DE/SAB Gb YEAC to NRC 04/09/31 POWER CAPACITY: 600(THERMAL) 165(ELECTRICAL)
II-2 A.
DSI/AEB 7
HRC to YAEC 08/03/81 OL NUMBER: DPR-3 II-2 B.
X NRC to YAEC 05/07/81 N.S.S.S.: WEST.
II-2 C.
DSI/AEB 7
HRC to YAEC 09/04/81 A/E FIRM: S8W II-2 D.
X NRC to YAEC 05/07/81 SYSTEMATIC EVALUATIDH 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 MANAGERf R.
CARUSO II-3 B.
1 DE/HGEB 5
HRC to YAEC 02/09/81 INTEGRATED ASSESSMENT PROJECT MANAGER:
A.
WANG II-3 C.
DE/HGEB 3
Site Visit II-4 DE/G3d 7
hPC to YAEC 06/08/81 KEY FOR STATUS CODES II-4 A.
DE/GSB 7
NRC to YAEC 06/; /*1 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.
DE/GSB 3
FROM REVIEW BRANCH X - DELETED II-4 C.
DE/GSB 7
HRC to YAEC 06/08/81 4b-SAR RECEIVED FROM 0 - TOPIC HOT LICENSEE II-4 D.
DE/HGEB 3
Site Visit STARTED 5 - DRAFT SE SEHT II-4 E.
DE/HGEB 3
Site Visit 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.
DE/HGEB 4b YAEC to NRC 08/31/81 6 - SE RESPONSE RECEIVED 2 - QUESTI0HS SENT BY HRC III-1 DL/SEPB 0(Elec)
TO UTILITY DL/SEPB 3(Sys)
YAEC to HRC 01/31/79 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 3
YAEC to NRC 08/21/81 RECEIVED BY NRC (2-39)
YANKEE R0WE TOPIC HO.
REVIEW STATUS REMARKS TOPIC HO.
REVIEW STATUS REMARKS DIV/BR DIV/BR III-3 A.
DE/SEB 3
YAEC to NRC 09/06/79 111-10 8.
X NRC to YAEC 11/16/79 III-3 B.
X NRC to YAEC 12/26/80 III-10 C.
X NRC to YAEC 11/16/79 III-3 C.
DE/HGEB 0
III-11 X
HRC to YAEC 05/07/81 III-4 A.
DSI/ASB 0
III-12 X
NRC to YAEC 05/07/81 III-4 B.
DE/NTEB G
HRC to YAEC 05/07/81 IV-1 A.
DL/SEPB 7
NRC to YAEC 04/18/79 III-4 C.
DSI/ASB 0
IV-2 DSI/ICSB 4b YAEC to NRC 09/17/81 III-4 D.
DE/SAB 4b YAEC to HRC 06/30/81 IV-3 X
HRC to YAEC 05/07/81 III-5 A.
DL/SEPB 2
NRC to YAEC 01/04/80 V-1 DE/MT EB G
NRC to YAEC 05/07/81 III-5 B.
DL/SEPB 1
V-2 X
NRC to YAEC 11/16/81 III-6 DL/SEPB 3
YAEC to NRC 06/30/81 V-3 X
NRC to YAEC 05/07/81 III-7 A.
X HRC to YAEC 05/07/81 V-4 X
HRC to YAEC 05/07/81 III-7 B.
DL/SEPB 3
YAEC to HRC 08/21/81 V-5 DL/SEPB 5
NRC to YAEC 01/24/80 III-7 C.
X HRC to YAEC 11/16/79 V-6 DL/SEPB 7
NRC to YAEC 03/05/80 III-7 D.
DE/SEB 3
HRC to YAEC 11/16/79 V-7 DSI/ASB G
HRC to YAEC 05/07/81
'o YAEC 05/07/81 V-8 X
HRC to YAEC 05/07/81 III-8 A.
DSX G
III-8 B.
X L
YAEC 10/01/80 V-9 X
HRC to YAEC 11/16/79 III-8 C.
DL/SEPB 7
HRL so 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 B.
DL/SEPB 5
NRC to YAEC 09/06/81 III-9 X
HRC to YAEC 05/07/81 V-11 A.
DL/SEPB 7
NRC to YAEC 12/08/80 III-10 A.
DL/SEPB 7
NRC to YAEC 09/22/81 V-11 B.
DL/SEPB 5(Sys)
HRC to YAEC 09/06/81 DL/SEPB 0(Elec)
(2-40)
YANKEE R0WE TOPIC HO.
RE"IEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.
X NRC to YAEC 11/16/79 VI-7 D.
DL/SEPB 7
NRC to YAEC 08/17/78 V-13 X
HRC to YAEC 05/07/81 VI-7 E.
X HRC to YAEC 05/07/81 VI-1 DE/CEB 3
YEAC to HRC 06/26/79 VI-7 F.
DL/SEPB 7
HRC 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
NRC to YAEC 11/16/79 VI-2 C.
X NRC to YAEC 11/16/79 VI-10 A.
DL/SEPS 3b YAEC to NRC 06/30/81 VI-2 D.
DSI/CSB 2
VI-10 B.
X NRC to YAEC 11/16/79 VI-3 DSI/CSB 2
VII-1 A.
DL/SEPB 3
YAEC to HRC 08/07/81 VI-4 DSI/CSB 0(Sys)
VII-1 B.
DL/SEPB 7
NRC to YAEC 08/17/78 DL/SEPB 7(Elec) NRC to YAEC 12/08/80 VII-2 DL/SEPB 3
YAEC to NRC 08/07/81 VI-5 X
HRC to YAEC 05/07/81 VII-3 DL/SEPB 5(Sys)
HRC to YAEC 09/06/81 VI-6 DSI/CSB G
HRC to YAEC 05/07/81 DL/SEPB 0(Elec)
VI-7 A.
1.
DL/SEPB 7
HRC to YAEC 02/20/81 VII-4 X
NRC to YAEC 05/07/81 VI-7 A. 2.
X HRC to YAEC 05/07/81 VII-5 X
NRC to YAEC 05/07/81 VI-7 A.
3.
DL/SEPB 4b YAEC to HRC 06/30/81 VII-6 DL/SEPB 7
HRC to YAEC 08/28/81 VI-7 A.
4.
X NRC to YAEC 05/07/81 VII-7 X
NRC to YAEC 11/16/79 VI-7 B.
DSI/RSB 7(Elec) HRC to YAEC 06/04/81 VIII-1 A.
DSI/PSB G
NRC to YAEC 05/07/81 0(Sys)
VI-7 C.
DL/SEPB 7
NRC to YAEC 03/13/81 VIII-2 DL/SEPB 7
NRC to YAEC 09/03/81 VI-7 C.
1 DL/SEPB 7
HRC to YAEC 09/04/81 VIII 3 A.
DL/SEPB 7
HRC to YAEC 11/07/79 VI-7 C.
2.
DL/SEPB 7
NRC to YAEC 03/13/31 VIII-3 B.
DL/SEPB 7
HRC to YAEC 08/28/81 VI-7 C.
3.
DL/SEPB 7
NRC to YAEC 07/24e80 VIII-4 DL/SEPB 2
NRC to YAEC 06/23/81 (2-41)
YANKEE R0WE TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 0
XV-10 DSI/RSB 4b YAEC to NRC 06/30/81 IX-2 X
NRC to YAEC 05/07/81 XV-11 X
HRC to YAEC 10/U 0 80 IX-3 DL/SEPB 4b YAEC to NRC 09/17/81 XV-12 DSI/CPB
<b(F/s)
YAEC to NRC
' 06/30/81 DSI/AEB 4b(Doses)YAEC to NRC 08/31/81 IX-4 DSI/RSB 4b YAEC to NRC 08/31/81 XV-13 X
NRC to YAEC' 11/16/79 IX-5 DL/SEPB 0
XV-14 DSI/RSB 4b YAEC to NRC 06/30/81 IX-6 DE G
NRC to YAEC 05/07/81 XV-15 s DSI/RSB 4b YAEC to NRC 06/30/81 X
X NRC to YAEC 05/07/81 XV-16 DSI/AEB 0
XI-1 DSI/ETSB G
NRC to YAEC 05/07/81 XV-17 DSI/RSB 0(Sys)
XI-2 DSI/ETSB G
NRC to YAEC 05/07/81 DSI/AEB 0(Doses)
[ NRC to YAEC 10/01/80 XIII-1 X
NRC to YAEC 05/07/81 XV-18 X
XIII-2 DL/SSPB 7
NRC to YAEC 03/11/81 XV-11 DSI/RSS 0(Sys)
DSI/AE8 0(Doses)
XV-1 DSI/RSB 0
XV-20 DL/SEPB 7
NRC to YAEC 09/06/81 XV-2 DSI/RSB 4b(Sys) YAEC is NRC 06/30/81 DSI/AEB 0(Doses)
XV-21 X
HRC to YAEC 05/07/81 XV-3 DSI/RSB Gb YAEC +o NRC 06/30/81 XV-22 X
NRC to YAEC 05/07/81 XV-4 DSI/RSB 0
XV-23 X
NRC to YAEC 05/07/81 XV-5 DSI/RSB 4b YAEC to NRC 06/30/81 XV-24 X
NRC to YAEC 05/07/81 XV-6 DSI/RSB 0
XVI X
NRC to YAEC 11/05/80 XV-7 DSI/RSB 4b YAEC to NRC 06/30/81 XVII DL 7
NRC to YAEC 08/17/78 XV-8 DSI/CPB 0
XV-9 DSI/RSP 4L YAEC to NRC 06/30/81 (2-42)
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SAR 1/
SER 7/
SAR 1/
SER 2/
TOPIC NO. TITLE RECEIVED COMPLETE TOPIC NO. TITLE RECEIVED COMPLETE III-1 Classificatien of NONE III-8.A Loose Parts Monitoring and NONE (SYS)
Structures Components and Core Barrel Vibration Systems (Scismic and l
"snitoring (NRR B-60, C-12)
Quality) i IV-2 Reactivity Control Systems 07/31/81R 09/04/81 III-5.A Ef fect s of Pipe Dreak on 08/13/81R Including Functional Design Structuros, Systems and and Protection Against Components Insido Single Failures Containment V-7 Reactor Coolant Pumo NONE III-S.B Pipe Break Outside 08/25/81R Overspeed (NRR B-68)
Containment V-Containment Leak Tes+.ing NONI III-7.A Inservice Inspection, NONE (MP A-04)
Including Prestressed Concrete Containments with VIII-1.A Potential Equipment NONE Either Grouted or Ungrouted Failures Associated with a Tendons Degraded Grid Voltage (MP B-23)
III-7.B Desion C) des, Design NDNE 07/15/81 Criteria, Load IX-1 Fuel Storago 09/03/81 Combinations, and Reactor Cavity Design Criteria IX-4 Boron Addition System 1/30/81 Et XI-1 Appendix ICMP A-02)
NONE 5AR J/
SER R/
XI-2 Radirlogical (Effluent NONE TOPIC NO. TITLE RECEIVED COMPLETE and Process) Monitoring Systems (NRR B-67)
III-3.C Inservice Inspection of 09/30/81 Water Control Structures l/ SAR : Licensee Safety Analysis Report-Scheduled or Actual III-4.B Turbine Missiles (MP B-46)
NONE (Actual (status 4b) when date is followed by RJ III-7.D Core Supports and Fuel NONE 07/30/81 2/ SER : Staff Safety Evaluation Report (Status 4a,5,6,7)
(MP A-01.A-14)
V-1 Compliance with Codes and NONE Standards (10 CFR 50.55a)
IX-6 Fire Protection (MP B-02)
NONE (3-2) l
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SAR 1/
SER 2/
TOPIC NO. TITLE RECEIVED COMPLITE TOPIC NO. TITLE RECEIVED COMPLETE III-1 Classification of Struct-t:0 N E (SYS) uros Components and Systems IX-6 F.re Protection (MP B-02)
NONE (Scismic and Quality)
III-2 Wi nd and To rna<i.' Loadings NONE pli SAR J/
SER 2/
III-7.A Inservice Inspection, HONE TCPIC NO. TITLE RECEIVED COMPLETE Including Prestressed Concrete Containments with Ill-4.C Internally Generated 11/30/8' Containments Grouted or Missiles Ungrounded Tendons III-8.A Loose Parts Monitoring and NONE III-7 B Design Codes, Design NONE Core Barrel Vibration Criteria, load Monitorinq(NRR P o0.C-12)
Combinations, and Reactor Cavity Design Critoria V-7 Reactor Coolant Pump NONE Overspeed(NRR B-68)
VI-7.C.1 Appendix K - Electrical NONE Instrumentation and Control VI-2.D M,ss and Encroy Release for NONE 09/25/81 (EIC) Re reviews Possible Pipe Break Inside Containment IX-5 Ventilation Systems NONE VI-3 Containment Pressure and NDHE 09/25/81 Heat Removal Capability Eli SAR 1/
SER 2/
VI-7.B ESF Switchover from NONE TOPIC NO. TITLE RECEIVED COMPLETE (SYS)
Injection to Recirculation Modo (Automatic ECCS 11-1.B Population Distribution 04/15/81R 07/21/81 Realignment)
II-1.C Potential Hazards or 04/1S/81R 07/01/81 IX-1 Fuel Storage 11/15/81 Channes in Potential Hazards Due to XI-1 Appendix I(MP A-02)
NONE Transportation, Institutional Industrial.
XI-2 Radiological (Effluent NCHE and Military Facilities and Process) Monitoring Systems (NRR B-t7)
II-4.D Stability of Slopes 06/30/81R XV-9 Startur or an Inactive Loop NONE 08/26/81 II-4.F Sottlement of Foundations 06/30/81R or Recirculation Loop at an and Buried Equipment Incorrect Temperature, and Flow Controller Malfunction III-3.C Inservico Inspection of 09/30/81 Causing an Increase in EWR Water Control Structures Core Flow Rate III-4.B Turbine Missiles (MP B-46)
XV-19 Loss-of-Coolant Accidents NONE 06/26/81 (DOSES)
Resulting from Spectrum of III-4.D Site Proximity Missiles 04/16/81R 07/21/81 (SYS)
Postulated Piping Breaks 07/27/81 (Including Aircraft)
Within the Reactor Coolant Pressure Boundary VI-1 Organic Materials and 09/30/81
__, Safety Analysis Report-Scheduled or Actual __,
Post Accident Chemistry 1/ SAR : Licensee (actual (status 4b) when date is follwed b/ R)
Z/ SER : Staff Safety Evaluation Report (3-4)
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SAR 1/
SER 2/
SAR 1/
SER 2/
TOPIC HO. TITLE RECEIVED COMPLETE TCPIC NO. TITLE RECEIVED COMPLETE 111-1 Classification of ISONE II-3.B Flooding Potential and NCNE (SYS)
Structures, Components and Protection Requirements i
Systems (Scirmic and Quality)
II-3.B.1 Capability of Operating NONE Plant to Copo with Design III-2 Wind and Tornada loadings 10/30/81 Basis Flooding Conditions III-S.A Effects of Pipe Break on 06/30/82 II-3.C Safety-related Water NONE Structures. Systems and Supply (Ultimate Heat Sink Comconents Insido (UHS))
Containment II-4.D Stability of Slopes Os/3C/81 III-7.B Design Codos. Desiqa NONE l
Criteria. Load l
II-4.E Dam Integrity 10/20/81 Combinations, and Reactor Cavity Design Critoria II-4.F Settlement of Foundations 09/30/81 and Buried Equipment VI-4 Containment Isolation NONE (ELEC)
System III-3.A Ef fects of liiqh Water Level 10/20/81 on Structures VII-1.A Isolation of Reactor NONE 08/05/81 Protection System from III-3.C Inservico Intpection of 10/20/81 Non-Safety Systems.
Water Control Structuros Including Qualifications of Isolation Devices III-4.B Turbino Missiles NONE VII-6 Frequency Decay NONE 08/26/81 III-4.D Sito Proximity Missiles 10/31/81 (Including Aircraft)
IX-5 Ventilation Systems NONE III-7.D Containment Structural 04/27/81 Integrity Tests LLh SAR t/
SER 2/
V-1 Compliance with Codes NONE TOPIC NO. TITLE RECEIVED COMPLETE and Standards (10 CFR 50.55a)(MP A-01.A-14)
Il-1.A Exclusion Area Authority O b / 01/ 81 R 09/06/s1 and Control VI-1 Organic Materials and 10/31/81 Post Accident Chemistry II-1.B Population Distribution 04/27/81R 09/06/81 IX-6 Fire Protection NONE II-1.C Potential Hazards or 10/30/81 r.hanges in Potential Hazards Due to Eil Tranroortation.
SAR 1/
SER 2/
Inststutional Industrial.
TOPIC NO. TITLE RECEIVLD COMPLETE and Military Facilitics 11-2.C Atmospb-;*ic Iran: port and 03/20/31R C8/26/81 II-3.A Hydroloqic Description NONE Diffusion Characteristics for Accident Analysis III-4.A Tornado Missiles 10/31/81 (3-6)
DRESDEN 2 H11 (Cont.)
DS1 (Cont.)
StR 1/
SER 2/
SAR 1/
SER 2/
TOPIC HO. TITLE RECEIVED COMPLElE TCPIC NO. TITLE RECEIVED COMPLETE lil-4.C Internally Generated 10/31/81 XV-3 Loss of External Load.
09/30/81 Missiles Turbino Trip, Loss of Condenser Vacuum, Closure III-8.A Loose Parts Monitoring NCHE of Main Steam Isolation and Coro Barrol Vibration Valvo (BWR), and Steen Monitoring (NRR B-60,C-12)
Pressure Regulator Failuro (Closed)
IV-2 Reactivity Control Systems 10/31/81 Including Functional Design XV-4 Loss of Non-Emergency A-C 09/30/81 and Protection Against Powcr to the Station Single Failures Auxiliaries VI-2.D Mass and Enerqv Rolcase for NONE XV-5 Loss of Normal Feedwater 09/30/81 Possible Pipo Break Insido flow Containment XV-7 Reactor Coolant Pump Rotor 09/30/81 VI-3 Containment Pressure and NONE Soicuro and Reactor Coolant Noat Removal Capability Pump Shaft Break VI-4 Containment Isolation NONE XV-8 Control Rod Misoperation 09/30/81 (SYS)
System (System Malfunction or Operator Error)
VI-6 Containment Leak Testinq NONE (MP A-04)
XV-9 Startup or an Inactive Loop 09/30/81 or Rocirculation loop at an VI-7.A.4 Core Spray Norric NONE Incorrect lerperature, and Effectiveness (NRR A-16)
Flow Controller Malfunction Causing an Increase in EWR VIII-1.A Potential Equirnent NONE Core Flow Rato Failuros Associated with a Dooraded Grid Voltaqo XV-11
- 1. advertent Loading and 09/30/81 (MP B-23)
Or; ration of a Fuel Assembly in an Improper IX-1 Fuel Storaqo "09/15/81 Position XI-1 Appendix I(MP A-02)
NONE XV-13 Socctrum of Rod Drop 09/30/81 (SYS)
Accidents (BWR)
XI-2 tadiological (Effluent and NONE (DOSES) 09/30/81
'rocess) Monitoring Systems (1RR B-67)
XV-14 Inadvertent Operation of 09/30/81 ECCS and Chemical and XV-1 Increase in Foodwater 09/30/81 Volumo Control System Temperature. Increase in Malfunction that Increases Focdaster flow. Increaso Reactor Coolant Inventory in Steam Flow and Inadvertent Opening of a XV-15 Inadvertent Opening of a 09/30/81 Steam Generator Relief or PWR Pressuricor Satoty-Safety Valve Relief Valvo or a BWR Safety /Rolief Valve (3-7)
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TOPIC NO. TITLE RECEIVED COMPLEIE TOPIC NO. TITLE RECEIVED COMPLETE 111-1 Classification of NONE (SYS)
Structures. Components V-1 Compliance with Codes NONE and Systems and Structures (MP A-01.A-14)
III-2 Wind and Tornado Loading 05/07/81R VI-1 Organic Matorials and Post 10/30/81 VII-6 Frequency Deccy NONE 08/29/81 Accident Chemistry IX-5 Ventilation System 12/32/31 IX-6 Fire Protection (MP A-02)
NONE El Ell SAR J/
SER 2/
SAR 1/
SER 2/
TOPIC NO. TITLE RECEIVED COMPLETE TOPIC NO. TITLE RECEIVED COMPLEIE Il-1.A Exclusion Area Authority 05/07/81R Il2.C Atmospheric Transport and 09/30/81 and Control Diffusion Characteristics II-1.B Population Distribution 05/07/81R III-4.A Tornado Misslos 09/30/81 II-1.C Potential Hazards Due to 05/21/81R Transnortation, Industrial.
III-4.C Internally Generated 02/28/82 and Military Facilitics Missiles II-3.A Hydrologic Description 05/07/81R III-8.A Loose Parts and Core NCHE Barrel Monitoring II-3.B Fiooding Potential anc 05/07/81R (NRR B-60.C-12)
Protection Requirements IV-2 Reactivity Control Systems NONE II-3.B-1 Capability to Cope with 05/07/81R Design Basis Flood VI-2.D Mass and Encroy Release for NONE Possible Pipe Break Inside II-3.C Safety Related Water Supply 05/07/81R Containmont (Ultimate Heat Sink)
VI-3 Containment Pressure and NDHE II-4.D Stability of Slopos 10/15/81 Heat Rcmoval Capability II-4.F Settlement of Foundation 10/15/81 VI-4 Containment Isolation NONE and Buried Equipment System III-3.A Effects of High Water 05/07/81R VI-6 Centainment Leak Testing NONE Level on Structures (PP A-0 4 )
III-3.C Inservice Inspection of 09/01/81 VI-7.A-4 Core Spray Nor le NONC Water Control Structure Effectiveness (MP D-17)
III-4.B Turbine Missiles 09/30/81 VIII-1.A Potential Equipment NONE Failures Associated with III-4.D Site Proximity Missiles 05/07/81R a Degraded Grid Voltage (MP B-23)
III-7.D Containment Structural 09/01/81 Integrity Tests IX-1 Fuel Storage 11/15/81 (3-10)
1 0YSTER CREEK D11 (Cont.)
psi (Cont.)
SAR 1/
SER R/
SAR _1/
SER 2/
TOPIC NO. TITLE RECEIVED COMPLETE TOPIC NO. TITLE RECEIVED COMPLETE X1-1 Appendix 1(NP A-02)
NONE XV-16 Radiological Consequences 09/01/81 of Failuro of Small Lines XI-2 Radiological (Effluent and NONE Carrying Primary Coolant Process Monitoring Systems)
Outsi de Containment (NRR B-67)
XV-18 Radiological Consequences 05/07/81R 07/01/81 XV-1 Decrease in Feedwater 05/07/81R Temperature, Increase in Main Steam Line Failure Feedwater Flow, Increase in Outside Containment Steam Flow, Inadvertent Opening cf Steam Generator, XV-19 Loss of Coolant Accidents 05/07/81R 07/13/81 Rolief or Safety Valve (SYS)
Resulting From Spectrum Break s Wi thin Reactor XV-3 Loss of External Load.
05/07/81R 07/16/81 (DOSES)
Coolant Pressure Boundary 05/07/81R Turbino Trip, Loss of Condenser Vacuum, Closuro XV-20 Radioleqical Consequences 05/07/81R of Main Steam Isolation of Fuel 9amaging Accidents Valve ( BtJR ), Steam Pressure (In 8 Out of Containmont)
Regulatory Failure (closed)
XV-4 Loss of Non-Emergency A-C 05/07/81R 07/16/81 1/ SAR = Licensee Safety Analysis Report-Scheduled or Actual Power to the Station (actual (status 4b) uhen dato is followed by R) l Auxiliaries 2/ SER = Staff Safety Evaluation Report (Status Aa,5,6,7)
XV-5 Loss of Normal Feedwater 05/07/81R Flow I
XV-7 Reactor Coolant Pump Rotor 08/25/81R Soizuro and Reactor Coolant Pump Shaft Break XV-9 Startup or an Inactivo Loop 05/07/81R or Recirculation Loop at l
Incorrect Temperature and flow Centroller Malfunction Causing an Increase in DWR Core Flow Rato l
XV-13 Spectrum of Rod Drop HONE 07/01/81 l
(sys)
Accident 05/07/81R (doses)
XV-14 Inadvertent Operation of 05/07/81R 07/16/81 ECCS that Increases Reactor Coolant Inventory XV-15 Inadvertent Opening of EWR 05/07/8tR Safety / Relief Valvo I
(3-11)
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TOPIC HO. TITLE RECEIVED COMPLETE TOPIC NO. TITLE RECEIVED COMPLETE
(
i l
111-1 Classification of NONE Il-3.A Hydrologic Description 06/25/81R (SYS)
Structures. Components and Systems (Seismic and II-3.B Flooding Potential 1 06/26/81R Quality)
Protection Requirements t
III-2 Wind and Tornado Loadings NDHE II-3.B.1 Capability of Operating 06/25/81R Plant to Cope with Design III-5.A Effec'.s of Pipe Break on 09/30/81 Basis Flooding Conditions Structures. Systems and Components Inside II-3.C Safety Related Water 04/28/81R Containment Supply (UHS)
TII-5.B Pipe Break Outside 08/31/81 II-4.3 Proximity of Capable NDHE Containment Tectonic Structures in Plant Vicinity III-7.B Design Codes, Design NONE Criteria, Load Combinations II-4.D Stability of Slopes 08/31/81R and Reactor Cavity Design II-4 F Settlement of Foundations 04/28/81R V-11.B RHR Interlock Requirements NONE and Buried Equipment (ELEC)
III-3.C Inservice Inspection of 08/31/81R VII-3 Systems Required for Safe NONE Water control Structures (ELEC)
Shutdown III-4.B Turbine Missiles 08/31/81R VII-6 Frequency Decay NONE 08/26/81 III-4.D Site Prximity Missiles 04/29/81R IX-3 Station Service and Cooling 09/30/81 (Including Aircraft) 4 Water Systems IV-3 BWR Jet Pumps Operating NONE IX-5 Ventilation Systems 09/30/81 Indications i
XIII-2 Safeguards Industrial NONE V-1 Compliance with Codes and NONE Security (MP A-10)
Standards (10 CFR 50.55a)
(MP A-01.A-14)
VI-1 Organic Materials and Post 10/30/81 pg SAR 1/
SER 2/
Accident Chemistry TC"IC NO. TITLE RECEIVED COMPLETE IX-6 Fire Protection NONE 11-1.A Exclusion Area Authority &
04/17/81R 07/31/81 Control Dkl II-1.B Population Distribution 05/19/81R SAR 1/
SER 2/
TOPIC NO. TITLE RECEIVED COMPLETE 4
II-1.C Potential Ha:ards or 04/29/81R Changes in Potential II-2.C Atmospheric Transport and 05/19/81R 09/29/81 Hazards Due to Transporta-Diffusion Characteristics tion, Institutional, and for Accident Analysis Military Facilities III-4.A Tornado Missiles 08/31/81R j
(3-13)
MILLSTONE 1 Eft 1 ( Co n t. )
i Rh1 (Cont.)
SAR J/
SER 2/
TOPIC NO. TITLE ne;FIV!D COMPi f.T E TOPIC NO. TITLE RECEIVIO COMPLEYE 111-4.C Internally Gctorated 09/30/81 XV-3 Loss of External Load.
06/30/8 fat Missiles Turbino Trip, Loss of Condonsor Vacuum, Closure III-8.A Looso Parts Monitoring and NDHE of Main Steam Isolation Coro Barrel Vibration Valvo (BWR), and Steam Monitoring (NRR B-60,C 12; Prossuro Roqulator Failure (Closod)
IV-2 Reactivity Control Systems 09/30/81 T--luding Functional Desion XV-4 Loss of Non-Emorgency A-C 06/30/81R wod Protection Aqainst Power to the Station Single Failures Auxiliarios VI-2.D Nass and Enerqy Release for NONE XV-S Loss of Normal Feedwater 06/30/81R Possiblo Pipo 3reak Insido Flow Containment I
XV-7 Reactor Coolant Pump
'06/30/81R VI-3 Containment Prossero and NONE Rotor Soizure and Reactor Hoat Removal Capability Coolant Pump Shaft Break VI-4 Containment Isolation NONE XV-8 Control Rod Misoperation 06/30/81R 08/26/81 (SYS)
System (Systen Malfunction or Operator Error)
VI-6 Leak Testing (MP A-04)
XV-9 Startup or an Inactivo Loop 06/30/81R VI-7.A.4 Coro Spray Norrlo NONE or Recirculation loop at an Effectiveness (NRR A-16)
Incorrect Temperature, and Flow Controllor Malfunction VIII-1.A Potential Equipment NONE Lausing an Increase in BWR Failures Associated With a Core Flow Rato Dograded Grid Voltaqo XV-11 Inadvortont Loading and 06/30/81R IX-1 Fuol Storaqo 08/31/31R Operation of a Fuel Assembly in an Improper XI-1 Appendix I(MP A-02)
NONE Position XI-2 Radioloqical (Effluent i NONE XV-13 Spectrum of Rod Drop 06/30/81R 08/18/81 Process) Monitoring Systems (SYS)
Accidents (BWR)
(NRR B-67)
(DOSES) 06/30/81R Cs/;'/81 XV-1 Decrease in Feodwater 06/30/81R XV-14 Inadvertent Operation of 06/30/81R Temperature, Increaso in ECCS ar.d Chemical and Feodwater Flow, Increase in Volume Control System Steam Flow and Inadvertent Malfunction that Increases Opening of a Steam Goncr-Reactor Coolant Inventory ator Rnlief or safety Valve XV-1S Inadvertent Opening of a 06/30/81R PWR Pressurizer Safety Relief Valve or a BWR Safety Relief Valvo (3-14)
MILLSTONE 1 211 (Cont.)
SAR 1/
SER 2/
TOPIO NO. TITLE RECEIVED COMPLETE XV-16 Radiological Conscoucnces 06/30/81R 09/21/81 of Failure of Small Lines Carrying Primary Coolant Outside Containment XV-18 Radiological Consequences 06/30/81R (SYS) of Main Sicam Line Failure (DOSES)
Outside Containment (EWR) 09/21/81 XV-19 Loss of Coolant AcciJents 06/33/81R 08/26/81 (SYS)
Resulting from Spectrum of (DOSES)
Postulated Pipinq Breaks 06/30/81R 09/21/81 Within the Reactor Cool nt Pressure Boundary l
XV-20 Radiological Consequences 06/30/81R 09/21/81 of Fuel Damaging Accidents (Inside and Outside Containment)
J/ SAR Licensco Safety Analysis Report-Scheduled or Actual (c tual (status 4b) when dato is followed by R) 2/ SER : Sta*-
Safety Evaluation Report (Status Ga,5,6,7)
(3-15)
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TOPIC NO. TITLE RECEIVED COMPLETE TOPIC HO. TITLE RECEIVED COMPLETE IX-3 Station Service and Cooling 08/31/81 111-1 Classification of NONE Water Systems Structures. Components and i
Systems (Seismic and IX-5 Ventilation Systems 10/30/81 Quality)
III-2 Wind and Torando Loadings 10/15/81 El SAR 1/
SER 2/
III-5A Effects of Pipe Break on 10/15/81 TOPIC NO. TITLE RECEIVED COMPLETE Structures, Systems and Components Inside 11-1.C Potential Ha:ards or 11/15/81 Containment Changes in Potential Hazards Due to III-5.B Pipe Break Outsido 10/1S/81 Transportation, Containment Institutional Industrial, and Military Facilities
'III-6 Seismic Design NONE Considerations II-4.D Stability of Slopes 08/31/81 III-7.B Design Codes, Design NONE II-4.F Settlement of Foundations 08/31/81 Criteria, Load and Buried Equipment Combinations, and Reactor Cavity Design Criteria III-3.A Effects of High Water Level 02/28/82 on Structures V-11.B RHR Interlock Requirements NONE (ELEC)
III-4.B Turbine Missiles (MP B-46)
NONE VI-7.A.3 ECCS Actuation System NONE III-4.D Site Proximity Missiles 08/31/81 (Including Aircraft) i VI-7.B ESF Switchover from NONE 09/04/81 (ELEC)
Injection to Rerirculation III-7.D Containment Structural 06/09/81R Mode (Automatic F.CCS Integrity Tests Realignment)
V-1 Compliance with Codes and NOME VI-10.A Testing of Reactor Trip NONE 08/28/81 Standards (10 CFR 50.55a)
System and Engineered (MP A-01)
Safety Features Including Response Time Testing VI-1 Organic Materials and Post 11/15/81 Accident Chemistry VII-1.A Isolation of Roactor NONE 09/09/81 Protection Systems.
IX-6 Fire Protection (MP B-02)
NONE Including Qualifications of Isolation Devices Ell VII-2 Engineered Safety Features NONE SAR 1/
SER 2/
(ESF) System Control Logic TOPIC HO. TITLE RECEIVED COMPLETE and Design III-4.A Tornado Missiles 10/15/81 VII-3 Systens Required for Safe NONE (ELEC)
Shutdown III-4.C Internally Generated 11/15/81 Missiles VII-6 Frequency Decay NONE 08/28/81 (3-17)
SAN ON0FRE Dil (Cont.)
Eid (Cont.)
SAR 1/
SER 2/
SAR 1/
SER R/
TOPIC NO. TITLE RECEIVED COMPLETE TOPIC NO. TITLE RECEIVLD COMPLETE III-8.A Looso Parts Monitoring and NONE XV-3
'oss of External Load, 07/Ol/81R 08/26/81 Coro Barrel Vibration Turbine Trip, Loss of Con-Monitorinq(NRR B-60,C-12) densor Vaccum, Closure of Main Stosm Isolation Valvo IV-2 Reactivity Cortrol Systems 09/30/81 (BWR), and Steam Pressure Including Functional Design Roqulator Failure (Closed) and Protcetion Against Single Failures XV-4 Loss of Non-Emergency A-C 08/18/81R Power to the Station V-7 Reactor Coolant Pump NONE Auxiliaries Overspood(NRR B-68)
XV-S Loss of Normal Feodwater 07/01/81R VI-2.D Mass --d Energy Release for NONE Flow Poss to Pipe Break Inside Cont.inment XV-6 Feedwater System Pipe 07/01/81R Breaks Insido and Outside VI-3 Containment Pressure and NONE Containment (PWR)
Heat Renoval Capability XV-7 Reactor Coolant Pump Rotor 07/01/81R VI-4 Containment Isolation NONE Scirure and Reactor Coolant (SYS)
Systen Pump Shaft Break VI-6 Containment Leak Testing NONE XV-8 Control Rod Misoperation 07/01/81R (MP A-04)
(System Malfunction or Operator Error)
VIII-1.A Potential Equipment Failuro NONE Associated with a Degraded XV-10 Chemical and Volume Control 0 7/ 01/81R Grid Voltage (MP B-23)
System Malfunction that Results in a Decrease in IX-1 Fuol Storago 12/15/81 the Boron Concentration in the Roactor Coolant (PWR)
XI-1 Appendix I NONE l
XV-12 Spectrum of Rod Ejection 0 7/ 01/81R XI-2 Radiological (Effluent and NONE Accidents (PWR)
Process) Monitoring Systems (NRR B-67)
XV-14 Inadvertent Operation of 07/01/81R ECCS and Chemical and XV-1 Decrease in Foodwater 07/01/81R Voluma Control System Temperature, Increase in Malfunction that Increasos Feedwater Flow, Increaso Reactor Coolant Inventory in Steam Flow and Inadvertent Openinq of a XV-15 Inadvertent Oponing of a 07/01/81R Steam Generator Relief PWR Pressuricor Safety-or Safety Valve Relief Valvo of a BWR Safety /Rolief Valvo XV-2 Spectrum of Steam System 07/01/81R Piping Failures Inside and XV-16 Radiological Consequences 08/04/81R Outsido of Containment (PWR) of Failure of Small Lines Carrying Primary Coolant Outside Containment (3-18)
SAN ON0FRE 251 (Cont.)
SAP. 1/
SER R/
TOPIO NO. TITLE RECEIVED COMPLETE XV-17 System Generator Tube NONE (SYS)
Failure (PWR)
XV-19 Loss of-Coolant Accidents 07/01/81R 08/26/81 Resulting From Spectrum of Postulated Piping Breaks liithin the Reactor Coolant Pressuro Doundary 1/ SAR: Licensee Safety Analysis Report-Scheduled or Actual (Actual (status 4b) when dato is followed by R) g/ SER: Staff Safety Evaluation Report (Status 4a,5,6,7)
(3-19)
1l,1
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SER 2/
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SER 2/
TOPIC NO. TITLE RECEIVED COMPLETE TOPIC ND. TITLE RECEIVED CCMPLETE 111-1 Classification of Struct-NONE II-3.A Hydrologic Description NONE (SYS) to es, Components and Sys-seas (Soismic and Quality)
II-3.B riooding Potential and NONE Protection Requirements III-2 Wind and Tornado Loading 02/01/82 II-3.B.1 Capability of Operatina NONE III-5.A Effects of Pipo Break on 12/01/31 Plans to Cope with Designs Structures. Systems and Basis Flooding Conditions Components Inside Containment II-3.C Safety-Related Water Supply-NONE (Ultimate Heat Sink UNS))
III-5.B Pipe Break Outside 12/15/31 Containment II-4.B Proximity of Capable NONE Tectonic Structures in III-6 Seismic Design NDHE Plant Vicinity Considerations II-4.D Stability of Slopes 11/01/81 III-7.B Design Codos. Design NONE Criterion, Load II-4.F Settic ent of Foundations 11/01/81 Combinations and Reactor and Duried Equipment Cavity Design Criterion III-3.A fffects of Nich Water 03/15/81 VI-7.A.3 ECCS Actuation Systen NONE Level on Structures VI-7.C ECCS Single Failure Cri-NONE 08/05/81 III-3.C Inservice Inspection of 12/01/81 terion and Requirements for Water Control Structures Lockinq Out Power to Valvos Including Independence III-4.B Turbine Missiles 12/15/81 of Interlocks on ECCS Valve III-4.D Site Proximity Missiles 11/01/81 VI-7.C.2 Fa81ure Modo Analysis ECCS NDHE 08/05/81 (Including Aircraft)
VI-10.A Testing of Reactor Trip 12/23/81 III-7.D Containment Structural 09/20/81 System and Engineered Integrity Tests Safety Features. Including Response Time Testing V-1 Ccmpliance with Codes and HDHE Standards 310 CFR 50.55a)
VII-1.A Isolation of Reactor NONE (MP A-01, A-14 )
Protection System From Non-Safety Systems. Including VI-1 Organic Materials and Post 10/15/81 Qualification of Isolation Accident Chemsitry Devices IX-6 Fire ProtectionfMP B-02)
NONE VII-2 Engineerod Safety Features NONE (ESF) System Control Logic and Design pil SAR 1/
SER ?/
VII-6 Frequency Decay NONE 09/21/81 TOPIC NO. TITLE RECEIVED COMPLEIE IX-3 Station Service and 11/15/81 Cooling Water Systems II-2.C Atmospheric Iransport and 09/25/81 Diffusion Characteristics IX-5 Ventilation Systems 01/15/82 for Accident Analysis I
I (3-2')
BIG ROCK POINT E11 (Cont.)
Dil (Cont.) '~
SAR 1/
SER 2/
SAR 1/
SER 2/
TOPIC NO. TITLE RECEIVED COMPLETE TOPIC NO. TITLE RECEIVED COMPLETE III-4.A Tornado Missiles 03/15/82 XV-3 Loss of External Loa:f, 07/15/81R Turbine Trip, Loss of III-4.C Internally Generated 03/15/82 Condenser Vacuum, Closure Missiles of Main Steam Isolation Valve (BWR), and Steam III-8.A Loose Parts Monitoring and NONE Pressure Roqulator Failure Gw.e Vibration Monitoring (Closed)
(NRR B-60.C-12)
XV-4 Loss af Non-Emergency A-C 07/15/81R IV-2 Reactivity Control System 10/01/81 Power to Use Station Including Functional Design Auxiliarios and Protection Against Single Failures XV-5 Loss of Normal Feedwater 07/15/81R Flow VI-2.D Mass and Energy Rolcase for NDHE Postulated Pipe Breaks XV-7 Reactor Coolant Pumps 07/15/81R Inside Containment Rotor Seizure and Reactor Coolant Pump Shaft Break VI-3 Containnent Pressures and NONE Heat Removal Capability XV-8 Control Rod Misoporation 09/23/81R (System Malfunction or VI-4 Containment Isolation Sys.
NDHE Operator Error)
VI-6 Containment Leak Testing NDHE XV-9 Startup of an Inactive Loop 07/15/81R (MP A-04) or Recirculation Loop at an Incorrect Temperature and VI-7.B ESF Switchover from NONE Flow Controller Malfunction Injection to Recirculation Causing an Increase in BWR Mode (Automatic EECS Core Flow Rate Realignment)
XV-11 Inadvertent Loading and 09/28/81R VIII-1.A Potential Equipment NONE Operation of a Fuel Failures Associated with Assembly in an Improper Degraded Grid Position (BWR)
IX-1 Fuel Storago 08/31/81 XV-13 Spectrum of Rod Drop 07/01/81R Accidents XI-1 ippendix ICMP A-02)
NONE XV-14 Inadvertent Operation of 06/26,otR 08/18/81 XI-2 Radiological (Effluent NONE ECCS and Chemical and and Process) Monitoring Volume Contr el System Systems (NRR B-67)
Malfunction that Increases Reactor Coolant Inventory XV-1 Decrease in Foodwater 07/15/81R Temperature Increase in XV-15 Inadvertent Opening of a 06/26/81R 08/18/81 Foodwater Flow, increase PWR Pressurizer Safety in Steam Flow and Relief Valve or a BWR Inadvertent Opening of a Safety / Relief Valve Steam Generator Relief or Safety Valve (3-22)
/
N BIG ROCK POINT E11 (Cont.)
SAR 1/
SER R/
TOPIC NO. TITLE RECEIVED COMPLETE XV-16 Radiological Consequences 0 7 / 01/ 81 R
~"~
of failure of Small Lines Carrying Primary Coolant Outside Containment XV-18 Radiological Consequences 07/01/81R of Main Steam Line Failure Outside Containment XV-19 Loss of Coolant Accidents 06/29/81R 08/18/81 (SYS)
Resulting From Spectrum of Postulated Piping Breaks (DOSES) within the Reactor Coolant 07/01/81R Pressure Boundary XV-20 Radiological Consequences 07/03/81R of Fuel Damaging Accidents (Inside and Outside Containment) 1/ SAR = Licenseo Safety Analysis Report-Scheduled or Actual (Actual (Status 4b) when date is followed by R) 2/ SER : Staff Safety Evaluation Report (Status 4a,5,6,7)
(3-23)
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i SAR 1/
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TOPIC NO. TITLE RECEIVCD COMPLETE TOPIC NO. TITLE RECEIVED COMPLETE 111-1 Classification of NONE 1x-5 Ventilation Systems 10/30/81 (SYS)
Structures. Components and Systems (Seismic and XIII-2 Safeguards / Industrial NONE Quality)
Security (MP A-10)
III-2 Wind and Tornado Loadings 12/31/81 III-5 A.
Effects of Pipe Break 09/30/81 SAR J/
SER 2/
on Structures. Systems TOPIC NO. TITLE REC 21VED COMPLETE and Componets Inside Containment II-1.A Exclusion Area Authority 04/27/81R B. Pipo Break Outside 08/3t'81 II-1.B Population Distribution 08/ 31/81R Containment II-1.C Potential Hazards or 06/30/81R III-6 Seism:- Design NONE Changes in Potential Considerations Hazards Due to Transportation.
III-7.B Design Codes. Design NONE Institutional Industrial.
Criteria. Load and Military Facilities Combinations, and Reactor Cavity Design Criteria II-3.A Hydrologic Description 12/15/81 VI-7.A.3 ECCS Actuation System NONE II-3.B Floooing Potential and 12/15/81 Protection Requirements VI-7.C.3 The Effect on PWR Loop NONE Isolation Valve Closure II-3.B.1 Capability of Operating 12/15/81 During a LOCA on ECCS Plant to Cope with Design Pe 'ormance Basis Flooding Conditions
.I-10.A Testing of Reactor Trip 08/31/81 II-3.C Safety-related Water Supply 12/15/81 System and Engineered (Ultimate Heat Sink (UHS))
Safety Features Including Response Timo Testing II-4.B Proximity of Capable NONE Tectonic Structures in VII-1.A Isolation of Reactor NONE Plant Vicinity Protection System from Non-Safety Systems. Including II-4.D Stability of Slopes 08/31/81R Qualifications of Isolation Devices II-4.F Settlement of Foundations 06/22/81R and Boried Equipment VII-2 Engineered Safety Features NONE (ESF) System Control Logic III-3.A Effects of High Water 08/31/81R and Design Level on Structures VII-6 Frequency Decay NONE 08/28/81 III-3.B Structural and Other NONE Consequences (e.g. Flooding VIII-4 Electrical Penatrations NONE of Safety-Related Equipment of Reactor Contain9ent in Basements) of Failure of Underdrain Systems IX-3 Station Service and Cooling 10/33/81 Water Systems (3-25)
HADDAM NECK Di (cont.)
E11 (Cont.)
SAR 1/
SER 2/
TOPIC NO. TITLE RECEIVED CCMPLETE TOPIC NO. TITLE RECEIVED COMPLETE lil-3.C Inservice Inspections of 08/51/81R VI-6 Containment Leak Testing NONE Water Control Structures (MP A-04)
III-4.B Turbine Missiles (MP B-46)
NONE VI.7.B ESF Switchover from NONE (SYS)
Injection to Recirculation III-4.D Site Proximity Missiles 06/25/81R hude (Automatic ECCS (Including Aircraft)
Realignment)
III-7.D Containment Structural 04/27/81R VIII-1.A Potential Equipment NONE Integrity Tests Failures Associated with a Degraded Grid Voltage V-1 Compliance with Codes and NONE (MP B-23)
Standards (10 CFR 50.55a)
(MP A-01.A-14)
IX-1 Fuel Storage 08/31/81R VI-1 Organic Materials and Post 01/31/82 IX-4 Boron Addition Systems 09/30/81 Accident Chemistry XI-1 Appendix I(MP A-02)
NONE IX-6 Fire Protection (MP B-02)
NONE XI-2 Radiological (Effluent NONE and Process) Monitoring Systems (NRR B-67)
I 2S1 SAR 1/
SER ?/
TOPIC NO. TITLE RECEIVED COMPLETE XV-1 Decrease in Feedwater 09/30/81 Temperatures, Increase in lil-4.A Tornado Missiles 08/31/81R Feedwater Flow. Increase in Steam Flow and Inadvertent III-4.C Internaly Generating 09/30/81 Opening of a Steam Genera-tor Relief or Safety Valve Missiles EII-8.A Loose Parts Monitoring and NONE XV-2 Spectrum of Steam System 09/30/81 Core Barrel Vibration Piping Failures Inside and Outside of Containment Monitoring (NRR B-60,C-12)
(PWR)
IV-2 Reactivity Control Systems 06/30/81 Including Functional Design XV-3 Loss of External load, 09/30/81 and Protection Against Turbine Trip, Loss of Condenser vacuum, Closure Single Failures of Main Steam Isolation V-7 Reactor Coolant Pump NONE Valve (BWR), and Steam Overspeed(NRR B-68)
Pressure Regulator Failure (Closed)
VI-2.D Miss and Energy Release for NONE Possible Pipe Break Inside XV-4 Loss of Non-Emergency A-C 09/30/81 Power to the Station Containment Auxiliaries VI-3 Containment Pressure and NONE Heat Removal Capability XV-S Loss of Normal Feedwater 09/30/81 Floo VI-4 Containment Isolation NONE System (3-26) 1
HADDAM NECK E11 (Cont.)
]
D11 (Cont.)
SAR 1/
SER 2/ I TOPIC NO. TITLE RECEIVED COMPLETE '
TOPIC NO. TITLE RECEIVED COMPLETE SAR 1/
SER 7/
XV-6 feedwater System Pipe 09/30/81 XV-19 Loss of-Coolant Accidents 09/30/81 Breaks Insido and Outside Containment (PWR)
Resulting from Spectrum of Postulated Piping Breaks Within the Reactor Coolant XV-7 Roactor Coolant Pump Rotor 09/30/81 Pressure Boundary Soizure and Reactor Coolant Pump Shaft Break 1/ SAR : Licensee Safety Analysis Report-Scheduled or Actual XV-8 Control Rod fiisoperation 09/30/81 (Actual (Status 4b) when date is followed by R)
(System Malfunction or Operator Error)
Z/ SER : Stafff Safety Evaluation Report (Status 4a.5.6.7)
XV-9 Startup or an Inactive 09/30/81 Loop or Rocircul: tion Loop at an Incorrect Temperature. and Flow Controller Malfunction Causing an Increase in BWR Core Flow Rato XV-10 Chemical and Volumo Control 09/30/81 System Malfunction that Results in a Decrease in in Boron Concentration in the Reactor Coolant (PWR)
XV-12 Spectrum of Rod Ejection 09/30/81 Accidents (PWR)
XV-14 Inadvertent Operation of 09/30/81 ECCS and Chemical and Volume Control System Mal funct i o n that Increases Reactor Coolant Inventory XV-15 Inadvertent Opening of a 09/30/81 PWR Pressuricor Safety-Relief Valve or a BWR Safety /Rolief Valve XV-16 Radiological Consequences NONE 07/10/81 of Failure of Small Lines Carrying Primary Coolant Outside Containment XV-17 Steam Generator 09/30/81 Tubo Failure (PWR)
(3-27)
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TOPIC HO. TITLE RECEIVED COMPLETE TOPIC NO. TITLE RECEIVED COMPLETE 111-1 Classification of Struct-NONE ures, Components and Sys-II-1.A Exclusion Area Authority NONE tems (Seismic and Quality) and Control III-2 Wind and Tornado Loadings 01/15/82 II-1.B Pipulation Distrubution 05/01/81R III-5.A Effects of Pipe Break on 10/30/81 II-1.C Potential Hazards or 04/09/81R Structures, Systems and Changes in Potential Components Inside Hazards Due to Containment Transportation, Institutional Industrial, III-5.B Pipe Break Outside 10/30/81 Containment and Military Facilities II-3.C Safety-related Water NONE III-6 Seismic Design NONE supply (Ultimate Heat Sink Considerations (UNS)
Ia B
Design Codes, Design NONE II-4.B Proximity of Capable NDNE Criteria, load Tectonic Structures in Combinations, and Reactor Plant Vi;inity (B-46) ravity Design Criteria o-
..L
'HR Interlock Requirements NONE CFLEC)
II-4.E Dam Integrity NONE VI-7.A.3 ECCS Actuation System 06/30/81R II-4.F Settlement of Foundations 08/31/81R and Buried Equipment VI-10.A Testing of Reactor Trip 06/30/81R System and Engineered III-3.A Effects of High Water 02/15/82 Safety Features Including Level on Structures Response Time festing III-3.C Inservice Inspection of 12/31/81 VII-1.A Isoaltion of Reactor NONE Water Control Structures Protection System from Hon-Safety Systems, III-4.B Turbine Missiles (MP b-46) g Including Qualifications of Isolation Devic.cs III-4.D Site prvximity missiles Ot/30/81R VII-2 Engineered Safety Features 1 NOME (ESF) System Control Logic III-7.D Containment Structural D2/15/82 and Design Integrity Tests VII-3 System Required for Safe NONE V-1 Compliance with Codes NONE (LLEC)
Shutdown and Standards (10 CFR 50.55a)(MP A-01,A-14)
VII-6 Frequenc/ Decay NONE 08/28/81 VI-1 Organic Materials and 02/15/82 VIII-4 Electrical Penetrations of NONE Post Accident chemistry Reactor Containment IX-5 Ventilation Systems DUE IX-3 Station Service and Cooling 09/17/81R Water Systems IX-6 Fire Protection (MP D-02)
NONE (3-29)
YANKEE R0WE M
E (Cont.)
SAR 1/
SER ?/
SAR 1/
SER 2/
TOPIC NO. TITLE RECEIVED COMPLETE TOPIC HO. TITLE RECEIVED COMPLETE.
t II"2.C Atmospheric Transport and 06/30/81R XI-2 Radiological (Effluent
~
Diffusion Characteristics and Process) Monitoring for Accident Analysis Systems (NRR B-67)
III-4.A Tornado Mi ssilos 01/1S/82 XV-1 Decrease in Feodwater 12/ft/81 Temperaturo. Increase in III-4.C Internally Generated 02/1S/82 Feedwater Flou, Increase Missiles in Stoam Flow and Inadvertent Opening of a III-8.A Looso Parts Monitoring NONE Steam Generator Relief and Core Barral Vibration or Safety Valve Monitoring (NRR B-60,C-12)
XV-2 Spectrum of Steam System 06/30/81R IV-2 Reactivity Control Systems 09/17/81R (SYS)
Piping Failures Inside Including Functional Design (DOSES) and Outsido of Containment 09/30/81 and Protection Against (PWR)
Single Failures XV-3 Loss of External Load.
06/30/81R V-7 Reactor Coolant Pump NONE Turbino Trip, Loss of Overspeed(HRR B-68)
Condenser Vacuum, Closure of Main Steam Isolation VI-2.D Mass and Energy Releaso NONE Valve (BWR), and Steam for Possible Pipe Break Pressure Roquiator Failure Inside Containment (Closed)
VI-3 Contain-ent Pressure and NONE XV-4 Loss of Non-Emergency A-C 12/31/81 Power to the Station Heat Rcmoval Capability Auxiliaries VI-4 Containment Isolation NONE XV-5 Loss of Normal Feodwater 06/30/81R (SYS)
System Flow VI-6 Containment Leak Testing NONE (MP A-04)
XV-6 Feedwater System Pipe 12/31/81 Breaks Inside and Outside VI-7.B ESF Switchover from NONE Containment (PWR)
(SYS)
Injection to Recirculation Mode (Automatic ECCS XV-7 Reactor Coolant Pump Rotor 06/30/81R Seizure and Reactor Coolant Realignment)
Pump Shaft Break VIII-1.A Potential Equipment NONE Failures Associated with XV-8 Control Rod r1isoperation 12/31/81 a Degraded Grid Voltaqo (System Malfunction or (MP B-23)
Operator Error)
IX-1 Fuel Storaao 12/31/81 XV-9 Startup or an Inactive 06/30/81R Loop or Rocirculation Loop IX-4 Boron Addition System 08/3' at an Incorrect Temperature, and Flow XI-1 Appendix I(MP A-02)
NONE Controller Malfunction Causing an Increase in BWR Core Flow Rate (3-30)
YANKEE R0WE E11 (Cont.)
SAR 1/
SER 2/
TOPIC NO. TITLE RECElVED COMP L EY E XV-10 Chemical and Volume Control 06/30/81R System Malfunction that Results in a Decrease in the Boren Concentration in the Reactor Coolant (PWR)
XV-12 Spectrum of Rod Ejection 06/30/81R (SYS)
Accidents (PWR)
(DOSES) 09/30/81R XV-14 Inadvertent Operation of 06/30/81R ECCS and Chemical and Volume Control System Malfunction that Increases Reactor Coolant Inventory XV-15 Inadvertent Opening of a 06/30/81R PWR Pressuricer Safety-Related Valve or a BWR Savoty/ Relief Valve XV-16 Radiological Consequences 12/31/81 of Failure of Small Lines Carrying Primary Coolant Outside Containment XV-17 Steam Generator Tube 12/31/81 (SYS)
Failure (PWk)
(DOSES) 12/31/81 XV-19 Loss-of-Coolant Accidents 09/30/01 (SYS)
Resulting from Spectrum of (DOSES)
Postulated Piping Breaks 09/30/81 Within the Reactor Coolant Pressure Boundary J/ SAR : Licensee Safety Analysis Report-Sci.
uled or Actual (Actual (Status 4b) when date is followed by R) 2/ SER : Staff Safety Evaluation Report (Status 4a 5,6,7)
(3-31)
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LACROSSE 21 LACROSSE SER 2/
SAR 1/
SER 2/
21 SAR 1/
TOPIC NO. TITLE RECEIVED COMPLETE TOPIC HO. TITLE RECEIVED COMPLETE 111-1 Classification of NONE Il-1.A Execlusion Area Authority 44)22/81R (SYS)
Structures, Components and and Control Systems (Seismic and Quality)
II-1.B Population Distribution 06/16/81R III-2 Wind and Tornado Loadings 08/06/81R II-1.C Potential Hazards or 07/15/81R Changes in Potential III-5.A Effects of Pipe Break on 11/02/81 Harards Due to Structures, Systems and Transportation, Components Insido Institutional Industrial, Containment and Military Facilities III-5.B Pipe Break Outside 06/29/81R II-3.A Hydrolic Description 06/16/81R Containment II-3.B Flooding Potential and 09/01/81 III-6
. Seismic Design NONE Protection Requirements Considerations II-3.B.1 Capability of Operating 09/01/81 III-7.B' Design Codes, Design NONE Plant to Cope with Design Criteria, Load 8 asis Flooding Conditions Combinations, and Reactor Cavity Design Criteria II-3.C Sataty-related Water Supply 06/26/81R r
V-'
.B RHR Interlock Requirements NONE (EL6C)
II-4.B Proximity of Capable NONE Tectonic Structures in VI-7.A.3 ECCS Actuation System NONE Plant Vicinity VI-10.A Testing of Reactor Trip L O6/ G/31R II-4.D Stability of Slopes NONE System and Engineered Safety Features Including II-4.E Dam Integrity NONE Response Time Testing II-4.F Settlement of Foundations 12/31/81 VII-1.A Isolation of Rocctor NONE and Buried Equipment Protection System from Non-Safety Systems, III-3.A Effectr of High Water Level 12/31/81 Including Qualifications of on Structures Isolation Devices III-3.C Inservice Inspection of 12/31/81 VII-2 Engineered Safety Features. HONE Water Control Structures (ESF) System Control Logic and. Design III-4.B Turbine Missiles 09/01/81 VII-3 Systems Required for Safe NDHE III-4.D Site Proximity Missiles 09/15/81R (ELEC)
Shutdown (Including Aircrafts)
VII-6
' Frequency Decay NONE 09/21/81 III-7.D Containment Structural 06/29/81R IX-3 Station Service and Cooling 11/02/81 Water Systems V-1
. Compliance with Codes and NONE Standards (10 CFR 50.55a)
IX-5 Ventilation Systems 11/02/81 (MP A-01,A-14)
(3-33)
LACROSSE 21 (Cont.)
~h11 (Cont.)
SAR 1/
SER 2/
SAR 1/
SER 7/
TOPIC NO. TITLE RECEIVED COMPLETE TOPIC NO. TITLE RECEIVED COMPLETE VI-1 Organic Materials and Post 12/31/81 XI-2 Radiological (Effluent and NONE Accident Chemistry Process) Monitoring Systems (NRR B-67)
IX-6 Fire Protection (MP B-02)
NONE XV-1 Decrease in Foodwater 08/21/81 Temperature, Increase in D11 Feodwater Flow, Increase SAR 1/
SER ?/
in Steam Generator Relief TOPIC NO. TITLE RECEIVED COMPLETE or Safety Valve II-2.C Atmospheric Transport and 10/01/81 XV-3 Loss of External Lcad.
06/26/81R Diffusion Characteristics Turbine Trip, Loss of Con-for Accident Analysis densor Vacuum, Closure of Main Steam Isolation Valve III-4.A Tornado Missiles 11/02/81 (BWR), and Stam pressuro Requlator Failure (Closod)
III-4.C Internally Generated 11/02/81 Missilos XV-4 Loss of Non-Emergency A-C 06/26/81R III-8.A Looso Parts Moniroring and NONE Power to the Station Coro Barrel Vibration Auxiliaries Monitoring (NRR B-60,C-12)
XV-5 Loss of Normal Feodwater 08/21/81 IV-2 Reactivity Control Systems 11/02/81 Flcw Including Functional Design and Protection Against XV-7 Reactor Coolant Pump Rotor 08/21/81 Single Failures Seizure and Reactor Coolant Pump Shaft Break VI-2.D Mass and Energy Release for NONE Possible Pipe Break Insido XV-8 Control Rod Misoperation 08/21/81 Containments (System Malfunction or Operation Error)
VI-3 Containment Pressure and NONE Heat Rcmoval Capability XV-9 Startup or an Inactivo Loop 08/25/81R or Recirculation Loop at an VI-4 Containment Isolation NONE Incorrect Temperaturo, and (SYS)
System Flow Controller Malfunction Causing an Increase in BWR VI-6 Containment Leak Testing NONE Core Flow Rate (MP A-04)
XV-11 Inadvertment loading and 12/31/81 VIII-1.A A.
Potential Equipment NONE Operation of a Fuel failures Associated with a Assembly in an Improper Dograded Grid Voltaqo Position (MP B-23)
XV-13 Spectrum of Rod Drop 12/31/81 IX-1 Fuol Storaqo 11/02/81 (SYS)
Accidents (DWR)
(DOSES)
XI-1 Appendix I(MP A-02)
NONE (3-34)
LACROSSE DS1 (Cont.)
SAR 1/
SER 2/
TOPIC NO. TITLE RECEIVED COMPLETE XV-14 Inadvertent Operation of 08/25/81R ECCS and Chemical and Volume Control System Malfunction that Increases Reactor Coolant Inventory XV-15 Inadvertent Opening of a 06/30/81R 09/21/81 PWR Pressuring Safety-Relief Valve or a EWR Safety /Rolief Valvo XV-16 Radiological Consequences 08/21/81 of Failure of Small Lines Carrying Primary Coolant Outsido Containment XV-1F Radiological Consequences 11/02/81 of Main Steam Line Failure Outsido Containment (BWR)
XV-19 Loss-of-Coolant Accidents 08/21/81 (SYS)
Resulting from Spectrum of (DOSES)
Postulated Piping Breaks 08/21/81 Within the Reactor Coolant Pressure Boundary XV-20 Radiological Conscouences 11/02/81 of Fuel Damaging Accidents (Insido 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 (Status 4a,5.6,7)
(3-35)
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u.s. NuCLEAn neoutArony commission NUREG-0485 Vol. 3 No.11 B19LIOGRAPHIC DATA SHEET 4 TITLE AND SUsTITLE LAdd vokme No.,iteprorrane)
- 2. (Leave bimari l
- 3. RECfPfENT'S ACCESSf CW NO.
Systematic Evaluation Program Status Summary Report
- 7. AUTHOR (S)
- 5. DATE REPORT COMPLETED M ON TH l YEAR October 1981
- 9. PERFORMING ORGANIZATION NAME AND MAlltNG ADDRESS (include tra Coel DATE REPORT ISSL ED MONTH l YEAR Office of Management and Program Analysis October 1981 Office of Nuclear Reactor Regulation s
(t,,,,,si U.S. Nuclear Regulatory Commission Washington, D.C.
20555
- s. (te=, u-ai
- 12. SPONSORING ORGANIZATION N AME AND M AILING ADDhESS (include lea Cooel 10 PROJECT / TASK / WORK UNIT NO Office of Management and Program Analysis M. CONTRACT NO.
Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555
- 13. TYPE OF REPORT PE RIOD COV E RE D (inclus,ve carest October 1-31, 1981 14 (Leave ar*/
- 15. SUPPLEMENTARY NOTES
- 16. ALSTR ACT 000 words or lessl The Systematic Evaluation Program is intended to examine many safety related aspects of eleven of the older light water reactors. This document provides the existing status of the review process including individual topic and overall completion status.
l l
i I
- 17. KE Y WORDS AND DOCUMENT AN ALYSIS 17a DESCRIPTORS l
4 17e IDENTIFIE RS'OPEN EN DE D TE RMS 19 SECURITY CLASS (This reporr/
21 NO OF P AGES
- 18. AV AILA8:LITY STATEMENT Unciassifind Unlim ted 2a. SECURITY f L ASS (This pegr) 22 PRICE s
unclass111ed
.S NRC FORu 335 17 77t
i UNITED STATES MUCLEQQ QEGULATORY COMMICSION I
l W ASP *NGTON, O. C. 20555 POSTA1E AND PEES PAID OFFICI AL BUSINESS U.E NU ;LE AR REGULATORY PEN ALTY F3M PRIVATE USE,3300 CC"'"O" L
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