ML20010H175
| ML20010H175 | |
| Person / Time | |
|---|---|
| Issue date: | 09/30/1981 |
| From: | NRC OFFICE OF MANAGEMENT AND PROGRAM ANALYSIS (MPA), Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| NUREG-0485, NUREG-0485-V03-N09, NUREG-485, NUREG-485-V3-N9, NUDOCS 8109240030 | |
| Download: ML20010H175 (82) | |
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- j Vol. 3, No. 9 "8
July 31,1981 e
.l SYSTEMATIC EVALUATION PROGRAM STATUS
SUMMARY
REPORT k,
(.EP 18138F 2
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45 tO UNITED STATES NUCLEAR REGULATORY COMMISSION p na,u E
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Available from TJ RC/GPO Sales Program l
l Superiritendent of Documents Government Printing Of fice Washington, D. C. 20402 A year's subscription co isists of 12 issues for this pubhcation.
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Assessment Schedule (page 1-8) has changed in order to eflect more per-
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tinent information. Three new pages (1-9,1-10,1-11) have beer. added which are surmiary pages of Section III. This new section (III)
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SEP Book is a breakout by review division of the outsta.' ding topics as of June 30, 1931. Also Section II now reflects the review division and branch of a topic as well as its status and remarks.
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NUREG-0485 Vol. 3, No. 9 July 31,1981 SYSTEMATIC EVALUATION PROGRAM STATUS
SUMMARY
REPORT UNITED STATES NUCLEAR REGULATORY COMMISSION
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f*2 $f William T. Russell, Chief Dennis M Crutchfield, Chief
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Systematic Evaluation Program Branch Operating Reactors Branch 5 O f ce f uclear Reactor Regulatio.,
O f e of ear Reactor Regulatien i
TABLE OF GONTENTS d
SECTION I SECTION ll SECTION lll SEP TOPIC LIST 1-2 to 1-3 BIG ROCK POINT 2-2 to 2-5 PALISADES 3-2 DRESDEN 1 2-6 GINNA 3-3 DESIGN BASIS EVENT 14 DRESDEN 2 2-7 to 2-10 DRESDEN 2 3-4 to 3-6 GROUP DESCRIPTION GINNA 2-11 to 2-14 OYS1 ER CREEK 3-7 to 3-8 DEFINITIONS OF STATUS 15 HADDAM NECK 2-15 to 2-18 MILLSTONE 1 3' 9 to 3-11 LACROSSE 219 to 2 22 SAN ONOFRE 3-12 to 3-14 SEP TOP,:C
SUMMARY
16 MILLSTONE 1 2 23 to 2-26 STATUS REPORT BIG rlOCK POINT 3-15 to 3-17 OYSTER CREEK 2 27 to 2-30 HADDAM NECK 3-18 to 3-20 PROGRdSS TOWARD 17
. - 1 to 2-34 YANKEE ROWE 3-21 to 3-23 COMPLETION (Graph)
SAN ONOFRE 2 35 to 2 38 LACROSSE 3-24 to 3 26 INTEGRATED PLANT l'8 SAFETY ASSESSMENT SCH EDULE SEP TOPIC STATUS BY 1-9 REVIEW DIVISION (Summary Table)
SEP TOPIC STATUS BY 1-10 to 1-11 REVIEW DIVISION (Graphs) i
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- 3. [ 15 ar+.4?3.i st'ee lil-I actrit #5t lity of s e '"i F - *, 8PM EA4 Ig F Peactor Coolant Fust Rotor Sellere and Piaris 8 Ctre eay 4W F ' e f ' ' n t l er 'w s 1 sesCtor Coolant Puer Seief t Breen ett; t
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t t ne I a :Ture Outs tde Contstaaret (Saal)
- e t em f or F i l l- /
Sa'e a. orh / l"4.# P e t a l securit y
=a t i e et t o:i ities IV-19 toss-of-Coolant Accidents Resulting f rue a v-rev rene iafee*4ter T enerat ure, t ar rene in 50eCt rue of Postulated Piping Breaa n Wittiin vi: *
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IV-20 Raatolog1 Cat Consequences of Fuet Damaging tt. tri
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~ect ro of stene spie. r n ia, sat ures inside ACCtden's (Inside and outside Contataseat) e av n ere 7 9 :st a F r.e eaJ Nt u je of C ont e i n+ at Pe) 15-21 Spent Fuel Cao Drop Accidents v i g -,
i e v ace <,3 '..+ et y f e e t re (tu 1 Syu ea Cortro a g.1
> v e. cJ Less e ms of (.t ernal t o 4, f urt ine f ree, t on of XM Ant ktpate han11ents Othout Suas
( m aenser s. % e, Ci m re of w.i i Ste = t sota-
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t ion v a l ee 4Fea), and M ese Fr uure Rep lator Multiple Tube f ailures in steae Generators
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- Topic deleted from SEP program due to duphcation by Three Mile Island (TMI) NRC Action Plan, Ur. resolved Safety issue or other SEP Topic per May 7,1981 tetter from G. Lainas to all SEP Lecensees.
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STATUS DEFINITIONS G - Generic 4a-Draf t SE Received From Review Branch l
These top;cs are being evaluated as part of on-going NRC generic review effort. The ongoing This status is used for internal NRC tracking of generic review and the SE P topic review will be topic review progress. The states indicates that closely integrated to improve the effectiveness a draf t topic safety evaluation is under mange-and ef ficiency of these efforts and to minimae ment review.
any impact on licensees. The status and conclu.
I sions of generic SE P topics will be i.tcorporated in the final safety assessment f or each plant.
4b - SAR Received from Licensee Licensee has submitted a Safety Analysis Report X - Deleted (S A R) in accordance with SEP redirection. (See Eisenhut letter to SEP owners of January 14,1981)
These topics have been verified as not apphcable The S AR is under review and a Final N R C 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 T M I Action Plan, will not be issued for topics with licensee SAR submittal.
Unresolved Safety issue or another SEP Topic per the f.iay 7 '981 letter from G. Lainas to all SEP licensees.
5 - Draf t SE Sent to Utility 0 - Topic Not Started A draf t topic safety evaluation has been formally transmitted to the licensee for their review and l
This status indicates that the review of the topic certification of the accuracy of the d? scribed has not started.
f acility. Licensees may comment upon N RC conclusions or propose alternatives to N RC posi-tions.
1 - Questions Received From R e vie w Branch 6 - SE Response Received This status is used for internal NRC tracking by NRC of topic review progress. The status indicates that all inf ormation necessary to perform a
[
The draf t SE has been reviewed and licensee topic evaluation is not available ar'd that ques-C' comments if any have been formally transmitted tsons have been developed and sent to the SEP to the N RC.
branch.
7 - Topic Complete 2 - Ciuestions Sent to U tilit y The N RC topic evaluation has been completed and a final safety evaluation issued. A topic is completed The questions developed in the previous status in several ways: (1 ) The licensee has responded have been formally transmitted to the licensee that the N RC draf t safety evaluation (i.e. status 5) as a request for additional information.
is correct, or (2) the licensees comments on the NRC draf t saf ety evaluation (i.e. status 6) have been re-viewed and if appropriate incorporated into the 3 - Question Response final safety evaluation, or (3) the licensee has not Received by N RC responded in the time requested, thus concurring that the draft safety evaluation is correct.
The licensee has formally responded to the informa-tion request issued by N RC regarding the topic.
1-5
SEP TOPIC STATUS
SUMMARY
REPORT '
I M
M 8
i NUMBER OF TOPICS DRAFT SE QUE STIONS GENERIC DELETED TOPIC NOT R E CE IVE D QUESTIONS QUESTION RECEtVED SA R SE l
IG)
IX)
STARTED FROM SENT TO R ESPONSE FROM HECEIVED DRAFT SE
RESPONSE
TOPIC RECEIVED REVIEW FROM SENT TO R ECE IVE D COMPLE TE BY NRC BRANCH LICE NSE E UTILIT Y BY NRC (Il l
PLANT NAME 2
BRAN,CH 13#
14.>
(46) is)
(si l
PALISADES 10 44 1
1 4
0 3
0 11 13 50 l
GINNA 8
42 2
3 1
5 9
3 15 10 39 DRESDEN 2 9
47 22 0
5 11 1
5 4
4 29 OYSTER CREEK 9
51 9
0 6
3 4
16 9
2 28 1
i MILLSTONE 1 11 48 5
1 4
10 1
24 7
2 24 SAN ONOFRE 10 45 7
2 9
11 4
to 14 1
24 BIG ROCK POINT 7
50 16 1
8 12 1
12 3
3 24 0
6 3
6 20 l
HADDAM NECK 11 44 26 0
9 12 YANKEE ROWE 10 44 14 2
11 13 0
13 4
3 23 LACROSSE 8
51 27 1
11 5
3 7
3 1
20 DRESDEN 1 TOTALS This Month 93 466 129 11 68 82 26 96 73 45 281 TOTALS Last Month 94 465 171 14 62 93 27 68 75 57 244 N
' Note: Totals do not include Dresden 1. see page 2 6. Also mcluded is May 7,1981 deletion letter to all SEP facensees, see footnote page 1-3.
SYSTEMATIC EVALUATIOl\\' PROGRAM GOAL P H A S E lil/
Progress Toward Ccmplet. ion
-1/ Not including Dresden 1
^c
^'
100 %
100 I
i f 7 I
p 7-31-82 p
,/
90 y
,s f
/
80
/
p 'l1%
/
s
/
1 month 70 67L p
L
/
61 */
f
/
2 60 60 %
130-81 y
,o
- '/
50 54%
50 %
I
/
47%
0 p
44%
42%
y 40
/
40%
/
36%
30
- 4 30% (estimated)
The plant topic overall completion status (percent complete)is calculated Status Weighting Factor
~
based upon the number of topic reviews to be performed (not including 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 SO%
Percent Complete = Sum of Topics in Status x Weighting Factor of Status 5,6 90%
10 Sum of Topics O
i 10 11 12 1
2 3
4 5
6 7
8 9
10 11 1
1 2
3 4
5 6
7 8
9 FY-81 FY-82 17
p.rEca s T ED pt :s r sa rF TY aWpM%T SMf;y(F I
1 l
1 i
i i
i i
TO?IC TARGET D2TE ! 2 RAFT 5-u,. r i SEA
!; AFT SER l ACRS I CC M*:ISSION I FINtl SER I Plini NAME ALL TOPIC 5 i INTEFNAL l
MEETINO l
f*EETINC i TO LICLhtEE I
t CGNPLETE C C:*.? L E T E I DISTRIIUTION!
Fc/IE4 l
LICENSEE I
I I
I I
i l
I 4
u i
6 i
i i
e i
t f
i I
i i
i I
I i
i i
l i
i
[
i l P Al f 31~,ES i
91 j
Sect. 81 j
cct.
81 Nov.
81 Dec.
81 l
Jan 82 i
Feb.
82 Mar.
80 t
i i
l
(
I I
1
(
i I
i i
i I
I l
i l GINNA 85 l
Sept. 81 1
Nov.
81 1
Coc.
81 i
Jan.
82 l
Feb.
82 M2r.
52 Apr.
82 i
i I
i i
i 1
i l
I i
i I
i i
l I
( L3E50EN 2 55 i
Oct.
01 i
Cec.
81 l
Jan.
32 l
Feb.
82 l
Mar.
22 l
- 1. o r. 32 l May F2 l
i I
I i
i i
I I
I I
i l
1 i
I l
I i
l L
Gr5TLR C2EEK i
74 bev.
21 Jan.
82 Feb Mar.
82 1
Apr.
82 i May 82
- Ju ic 8?
l I
I l
\\-
l l
1 l
1 i
i
! MILL 5TCHE t 74
- e
- .
81 i
Feb.
8'
- ar 82 l
Apr.
82 May 82 June 82 July 80 i
l l
i
- Q i
(
I I
I i
i i
~
t I
i l
i e
S A *4 ONCFFE 6) l Feb.
82
)
- pr 4 Ma/
22 June 82 July 82 i
Avq.
8' (opt. 82 u
i I
I i
i y
l 1
l 6
1 i
t I
I I BIG RCC< POINT j
59 i
Mar.
82
' May - 82 1
June 82 July 52 l
Aug.
8:
1 Sept. 82 i
Oct.
82 l
1 1
1 i
1 i
i i
i i
l i
I 1
I i
i i
i 1
i l
HALDAM PC (
i 49 i
Aor.
- ' 2 Junu f,2 i July 82 1
Avo.
82 i
Seat. 82 i
Oct.
82 i ric a. 8; i
i f
I i
1 I
I I
I I
(
l i
I I
I i
i fANKEE R O.J E l
59 i
Juno 'i July 82 l
A u e:. 82 l
Sept. 8?
Oct.
82 i
Nov.
82 l
tev c. 32 I
1 l
l i
l I
i i
i I
LA C 3SSE i
55 July 32 Aug.
82 l
Scat. 82 Oct.
8 Nov.
32 Occ.
82 Jan.
83 1
i l
i i
i i
i t
i I
i i
l
- Tentative - incd and,chadtle (cr ACE 5/Cemmission review to be dwinrninced.after completion of lead plant (?ali saa n) revica.
I 1-8 l
l
SEP TCPIC STATUS by REVIEW DIVISICN
SUMMARY
TABLE I
i PLANT l PALISADES GINNA DRESDEN CYSTER MILLSTCHE SAN BIG HADDAM YANKEE LACROSSE TOTAL l
2 CREEK 1
ONOFRE RCCK NECK RCWE POINT (I A Pft) 1/
Michaels Wang Cwalina Fell Persinko McKenna Scholl Michaels Wang Cwalina NO. CF TCPICS 137 137 137 137 137 137 137 137 137 137 1370 DELETED 2/
4%
42 47 51 48 45 50 44 44 51 466 AFPLICABLE 93 95 90 86 89 92 87 93 93 86 904 j'%
52
/
33
/
29
/
30
/
l 24
/
23
/
22
/
22
/
20
/
281 /
26 (/g A
DL
/
/
/
/
/r
/
/
/
/
/
/
/ 57
/ 39
/ 36
/ 34
- 0
/ 38
/ 38
/ 33
/ 35
/ 392 TECHNICAL
/
/
'/
/
/
/
/
/
/
/
/
15
/
16
/
5
/
4
/1
/
9
/
3
/
3
/
6
/
3
/
70
/
REVIEW DOE
/
/
/
/
/
/
/
/
/
/
/
/
19
/ 22
/ 23
/ '
2
/ 19
/ 18
/ 22
/ 22
/ 22
/ 210 ASSIGNMEHT 1/
/
/
/
/
/
/
/
/
/
/
8
/
25
/
4
/
N '
1
/
6 e
3
/
3
/
1
/
1
/
61
/
d/
/
/
/
/
/
/
/
/
D5I
/
/
/
/ 17
/ 34
/ 31 q
1
/ 30
/ $3
/ 31
/ 33
/ 33
/ 29
/ 302
/
/
/
h
/
/
/
/
/
/
/
3r43 75
/
74
/
38
/
/
33
/
39
/
29
/
22
/
29
/
24
/
412
/
CCMPLETE
/
/
/
/
/
/
/
/
/
/
/
/ 93
/ 95
/ 90
/ 86
/ 89
/ 92
/ 87
/ 95
/ 95
/ 86
/ 904
/
/
/
/
/
/
/
/
/
/
/
TALGET DATE -
ALL TOPICS COMPLETE l/ Division of Licensing Intefrated Assessment Project Manager 2/ Deleted as not applicable, or duplicated by USI, Tt1I Action Plan, or another tops.
J/ All topic review completion dates are before end of FY 1982.
These schedules and assignments are consistant with HRR budget requests.
I __/
- No. Completed / Ho. Assigned
\\/
1-9 STATUS AS OF JULY 31, 1981
PROGRESS OF TOPIC REVIEWS DIv18tel W Litastes flP!G W
TM e-_
g-f
$M p
3 89 - ~
p t
I, G
au --
19 - ~
15 -~
g..
i e
a i
e i
g M
R Als SEP 001 IOf E
JAN FG law APR My a
R seITH 1kjk3, h 10 10 4
6 4
3 2
2 1
Tarpt 19 19 PER MONTH I
\\
Actual I
sf\\
3
\\ j w
Twyt 299 318 335 3W
- 358, 368
_374 300 384 387 3e9 391 392 Actual 281 l
U"U'# '
,, y PROGR.,ES.S pF TOPIC REVIEWS 01V15 DE!IEDIM; TF!ts
)
a.
(
TAnlET
~ ~~~ ~
~
e*
s
/
89 -~
l
/
to --
/
/
~Z--.
9 k
8 E
j g
g g
M R
AIL EF OCT tof E
JAN FIR eWt APR WY m
R tomt Target 28 27 22 19 14 9
6 6
5 3
2 2
1 PER MONTH Actuoi 4
Tarpt 94 121 143 162 176 1B5 191 197 202 205 207 299 210 CUMULATIVE 70 Actung 1 10
mm.
PROGRESS OF TOPIC REVIEWS O! VISION W SYSTEMS INTEGRAf!ON f(FICS 358 IAfKKI 300 ~ ~
" ~
p W
s ACIDAL g
2M --
E N
/
l 200-
/
/
ise --
/
/
,a --
/
.. /
V w..
An a
i a
a i
g JLM Jti AUG i
MN DEC JAN FEB MAR APR MAY Jt#4 JtL g
v#
M(NTH f i Y;Y4 18 14 14 10 7
4 4
?
Twget 43 42 38 Actual 11 f)
Target h
h-261 275 285 292 296 300 302 CUMULATIVE
~93 135 173 205 x
Actual 61 Y
/
A PROGRES y TOPIC REVIEWS TOTAL FMIKCT ftFICS 15 TAMT
~~
se --
~ ~ ~
m--
/
s
/
pg --.
Y as-y su ~ - l 4 --
an-3..
g--
15 --
g 1
JAss FG IIM N4 isAY Jtal R
j issme f arget 90 88 77 64 48 37 26 26 19 13 8
8 4
PER MONTH Actust gg 78'984 486 674 651 715 763 800 816 852 871 884 892 900 904 COMUL ATIVE Actual 413 1 11
--.---a-_a aa_m m.
A._
_m
- ----m.
J
- a-.a s-_
---aau---.a--
A h---
1 I
e i
i, i
l i
i 1
i e
l f
i I
i.
Z l
O
{
l O
l u.i 4
4 l
1 l
i i
b a
i
}
i i
I i
. _ ~. _ _.
BIG ROCK POINT I
I FACILITY: 3IS RCCK P3 INT 1 l
TCPIC N3.
REVIEW STATUS REMARKS l
DIV/BR LICENSEE: CCNLUMERS PCaER 1
11-1 A.
DL/SEPS 7
CPLc to h4C J9/C2>50 RT0!CN/LCCATICN: ' MILES NORTH EAST CF CHARLEVOIS. T4CH.
I II-t B.
DL/SEPE 7
CPCo to hRC 09/02/80 f
DO KET NO.
05:00!55 Il-1 C.
OL/SEPB 7
NPC to CPCo 05/13/31 PCAER CAFACITY: 0240(THERMAL) t67CELECTRICAL)
II-2 A.
OSI/AEB 6
CPCo to NRC 03/09/81 6
CL SLM3ER: CpR-6 8
II-2 B.
X SRC to CPCo 05/07/31 N.S.S.S.
GE.
II-2 C.
DSI/AE3 0
3/E FIRM: B2CH.
l l
11-2 D.
X NRC to CFCo 35/07/81 l
SY STE.MATIC EV AL'J AT ION PROGRAM BRANCH CHIEF:
W.
RUSSELL II-3 A.
DE/hGE3 2
NRC o LPCo 37/10/31 CPERATINS REACTCRS 2PANCH CHIEF:
D.
CRUTCHFIELD II-3 B.
DE/HGEB 2
NRC to CPCc 07/10/L1 i
CPERATING REACTCRS PDCJECT MANAGER:
W.
PAULSCN l
!I-3 B.
1.
C E/ tiG E B 3
S i to 'li si t 07/16/79 I
INTEGRATED ASSESSMENT PR3 JECT MAN *CER:
R.
SCHCLL i i 11-3 C.
DE/HGEB 3
NRC to CFCo 08/04/33 I i l
II-4 DE/GSB 7
NRC to CPCo 06/08/81 I
<Y r 9 5 t Ait;Ugfji i
II
'e A.
DE/GS3 7
bRC to CPCo 06/08/E1 G - GENERIC Ga- 0PAFT SE RECEIVED II-4 B.
DE/GSB 2
?PCN REttIEW ERAhCH X-DELETED 11-4 C.
DE/GS3 7
SRC to C?Co 06/08/31 4b-SAR RECEIVEC FROM 0 - !CPIC NCT LICENSEE II-4 D.
DE/HGEB 2
Site Visit 07/19/79 ST.RTED 5 - DRAFT SF SENT II-4 E.
X NRC to CPCo 11/16/79 l
l 1 - CLE TION % RECEIVED TO UTILITY t
i F7 C:1 retie 2 ERANCH II-4 F.
DE/HGEB 2
l l
6 - SE RESPCNSE FECEIVED 1
2-QUESTiG"5 SFNT 2Y NnC III-1 DL/SEPB 2(Sys)
NRC to CPCc I
TO UTILI!Y EL/SEPB 7(ELEC) NRC to CPCo 10/29/30 1
7 - TCPIC CCNPLETE i
- - OLESTICN RESPCNSF I
III-2 LL/SEPB 3
CPCo to NRC 07/09/81 l
l FECE!VED EY NRC l
I i
l (2-2)
BIG ROCK POINT TCPIC NO.
FEVIEW STATUS REMARKS TCPIC 50.
REVIEW STATUS REMAR(S DI'//ER DIV/BR l
III-2 A.
Lt/ 5 ES 3
CPCo to HRC 03/08/d0 1
-~III-10 8.
X hRC to C t' C o 11/16 / / )
e l
l III-3 B.
X NRC to CPCo 12/26/80 III-10 C.
X NRC to CFCo 11/16/79 8
III-3 C.
D E/ t.C E B C
l III-11 X
%RC to CPCO 05/07/51 I
III-4 A.
DSI/AS3 0
III-12 X
NRC to CPCo 05/67/81 III-4 P.
DE/MTEC 0
IV-1 A.
DL/SEFB 7
No,C to CPCo 10/09/79 III-4 C.
DSI/ASB 3
IV-2 DSI/ICSB 3
CPCo to NRC 05/04/81
!!I-4 D.
DE/SA3 0
IV-3 X
NRC to CPCo 05/07/81
!II-5 A.
CL/SEPB 3
V-1 DE/MTEB G
NRC to CPCo 05/;7/81 I
III-5 3.
DL/SEPB 2
NPC to CPCo 01/04/80 l
J-2 X
NRC to CPCo 11/16/79 III-6 DL/SEPB CPCo to NDC 07/09/81 V-3 X
NRC to CPCo 05/07/58 III-7 A.
X NRC to CPCo 05/07/81 V-4 X
NRC to CPCo 05/07/81 III-7 B.
DL/SE?B 3
CPCo to NRC 07/C9/31 V-5 DL/SEPB 5
SRC to CPCo 03/10/81 III-7 C.
X NRC to CPCo 11/16/79 V-6 DL/SEPB 7
NRC to CPCo 03/05/80 III-7 C.
DE/SEB 3
NRC to CPCo 08/09/79 V-7 X
NRC to CPCo 05/07/81 III-8 A.
DSI G
NRC to CPCo 05/.7/81 V-8 X
hRC to CPCo 05/07/81 III-8 B.
X NRC to CPCo 09/26/30 V-9 X
NRC to CPCo 11/16/79 III-? C.
DL/SEPB 7
NRC t<
CPCo 02/05/80 V-10 A.
DL/%EPB 7
NRC to CPCo 10/09/79 III-3 C.
X HRC to CPCo 05/07/81 V-10 B.
D L,' S LP 3 5(Sys)
NRC to CPCo 05/13/81 III-9 X
HRC to CPCo 05/07/81 V-11 A.
DL/SEPB 6(Elec) CPCo to NRC 39/24/30 III-10 A.
DL/SEPB 7
hRC to CPCo 08/03/81 V-11 B.
DL/SEPB SCSys) hRC to CPCo 05/13/81 1
(2-3)
I i'
il1l ll!
'l 8
1 9
1 9
9 t
1 C 1
1 1
7 1
C 1
3 c
7 7
5 7
7 i
3S 4
8 3
7 3
8 0
E a
/ / / / /
/
39 7
7 7
6 7
4 2
4 4
/ / / / / / / / / / /
7 7
6 7
6 1
1 12 C
0 C
1 C
2 2
2 2
6 7
6 0
1 0
1
/ / / / /
/
/
/ /
e
/ / / / /
L'
/ /
3 5
1 5
1 1
6 50 5
5 5
1 S
9 9
9 0
3 1
3 1
1 0
01 3
0 3
1 C
0 C
0 0
o o o o o
o c
oo a
o e o o C
C C
C C
C C
C C
C C
CC C
C C
C C
R R
R R
F T
F P
P P
T PP P
P P
P P
N S
N h
C C
C C
C C
C CC C
C C
C C
S o o o o K
3-o o o o o
o oo o o o o o t
t t
t R
t t
t t
t t
t tt t
t t
t t
A o
o c
o M
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
R7 R
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N N
H m
S N
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C C
C C
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( (
A 7
X X X X 3
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7 7
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2 BB B
B B
B B
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P PF f
3 F
P f
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P F
E E
E I'
S S
S S
S SS S
/
S S
S S
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/
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/ / / //
/
I
/ / / /
EI i
L L
L L
LL L
S L
L L
L RC O
S O
C D CD D
D D D D D
D A
A B
N A
B A
3 D E F
1 3
3 4
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3 1
1 2
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5 6
7 I
7 7
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9 1
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1 9
1 9
1 0
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8 7
8 S
7 8
3 8
8 8
7 8
7 3
3 7
/ / / / / / / /
/ / / / /
/ /
/
/
9 7
2 7
7 6
2 2
2 7
7 6
7 0
4 4
6 J
0 1
C 1
0 0
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0 2
1
/ / / / / / / /
/ / / / /
/ /
/
0 5
7 S
5 1
4 4
2 5
5 1
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6 9
1/
0 0
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c C
C R
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t o o o o o
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t t
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o o a
M C
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C h
)
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yl T
L SE I
(T A
7 X
3 X X X 3
3 32 X G X X
C 7
0 7
0 X
N T
S I
0 3
S S
E3 S
B B
3 3
Wk P
3 S
S SP 3
P S
P P
P P
E2 i
E C
C CE S
E R
E E
E I/
S C
/ /
/S C
S
/
S S
S VJ
/
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I I/
/
/
I I
/ / /
EI L
E S
3 SL E
L S
3 L
L L
FD D
D D
0 DC C
D D D D D D
K CO 1
2 3
4 1
2 3
3 R
S A
t, S
C D A
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C C
C C
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2 3
1 2 2 2
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6 7
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7 7
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1 1
C I
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V V
V L
V V
V V
V V
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I Il 1
,lI s
BIG ROCK P0 INT I
I I
! TOPIC S0.
EEVIE'A STATUS REMARKS
! TCPIC N3.
P EV I E.4 SitTLS ret 11RKS 1
i CIV/ER l
DIV/BR t
Ix-1 01J/ ASS a
x/-13 x
NRC to CPCo 11/16//T"-
]
IX-2 X
NRC to CPCo 05/07/81 XV-11 DSI/ CPS 0
1 l
IX-3 DL/SEPB 2
XV-12 X
SRC to CPCo 11/15/79 IX-4 X
NRC to CPCo 11/t5/79 XV-13 DSI/CPB 4ttsys) CPCc to bT C 37/01/81 DSI/AE3 4b(Danes)CPCa te f,E C 07/01/31 l
IY-5 DL/SEPS 0
l XV-14 DSI/RS2 46 CPCo to Si0 06/26/31 1 IX-6 CSI 7
0 2 / 0 4. / 81 P C o 11/16/79 l
XV-15 DSI/RSS 4'a CPCo to SRC CL/26/11 X
X NrC to CFCo 05/07/01 XV-16 DSI/AEC Ab CPCo to NFC C 7/ 01/ 31 l
XI-1 "SI/ETSB G
NIC te CPto C5/G7/S1 1
XV-17 X
NRC to CPCo 11/16/71 XI-2 D3!/ETS3 G
NRC te CPCo 05/07/31 XV-18 DSI/R5B 4bfSys) cpi o to hRC 07/Ot/$1 I
XIII-t X
r4 R C to PCo 05/07/81 DSI/ALS OCD:nns; i
l i
l XIII-2 DL/SSPB 7
NRC to CPCo J 3/11/ 81 1
XV-19 DSI/PS3 4b(Sys) CPCo to hRC 06/29/31 DSI/AE3 A b!I'o t at i c f C 3 to SRC 07/31/21 XV-1 DSI/RSB 46 CPCo +o hPC 07/15/81 i
XV-20 DSI/AED Ab CPCo to NRC 07/02r31 XV-?
X NRC to CPCo 11/16/79 XV-21 X
hRC to CPCc 05/07/31 XV-3 DSI/RSB 4b CPCo to NRC 07/15/31 XV-22 X
NRC to CPCo 05/07/31 XV-4 DOI /RS3 46 CPCa to NRC 07/15/31 XV-23 X
SRC to CPCo 05/37/*.1 XV-5 DSI/RSL Ab CPCo to NRC 07/15/81 1
XV-04 X
NRC to CPCo 03/07/81 XV-6 X
hRC to CPCo 11/16/79 i
XVI X
NRC to CPCo Y : / " 5 /.8. 3 1
XV-7 DSI/RS3 4b C"Co te NRC 37/15/81
, XVII DL 7
i:F C to Crea 07/17/7.5 l
XV-8 CS!/CFB 0
l 1
XV-9 D5I/RSB wa CPCo to NRC 07/15/31 l
}
_l (2-5)
DRESDEN 1 FACILITY: ORESDEN 1 LICENSEE: C C M?,O M W E A L T H EDISDN R E GI CrulC C A T IO N : 9 MILES CAST OF MORRIS, ILL.
DCCKE' NO.
05000010 PCWER CAPACITY: 700(THERMAL) 200(ELECTRICAL)
CL NUM3ER: DPR-2 N.S S.5.
GE.
A/E FIR:1: EECH.
SYSTEMATIC EV A'.U ATION PROGR AM E R ANCH CHIEF:
W.
RUSSELL OPERATING REAl' ORS LRANCH CHIEF:
D.
CRUTCHFIELD OPERATING REACT.,,25 PROJECT MANAGER: P.
O'CONNCR Dy letter dated December 31, 1930 Commonw alth Edison indi-3 cated that Droeden 1 was undaracino an extensive rnodifica-tion and was not scheduled for restart until June, 1936.
Also, by letter dated April 4,
1981, in response to the NRC's January 14, 1931 1citor on SEP redirection t hr$ licen-see stated that the Dresden 1 SEP review is not being actively pursued, i.e.
defered.
l (2-6) s
DRESDEN 2 1
j FACILITY: ORE 3:5N 2 IOPIC hD.
REVIEW STATUS REMARKS LICENSEE: COMN0hWEALTH EDIGCN I
11-1 A.
$T7' IIB
- t CiCo to hRC C6/C1/81~~!
l REGILT /LCCATICH: 9 MILES EAST OF FORi!L. ILL.
l t
I 1I-1 3.
DE/5Ab 4b CECc to hRC 04/27/J1 i
DOCKET hD,.
05000237 1
i II-1 C.
DE/SA3 0
i PCWER C/PACITY: 2527(TFERMAL) 0794(ELECTRICAL)
II-2 A.
D51/AE3 7
SRC to CECO 04/24/01 i
OL NUMBER: D/R-19
{
II-2 3.
X NRC to CECO 05/07/31 ?
r!.S.S.S.
GE.
i I
II-2 C.
DEI /AE3 Ab CECO to NRC 03/20/21 A/E FIF.M: Sgt.
l l
II-2 D.
X Ni.C to CECO 05/07/31 i
SYSTEMATIC EVALUATION ?ROGRAM BRANCH CHIEF:
W.
RUSSELL II-3 A.
DE/HGEB 2
tJ C to CECr 07/10/81 1
CP; RATING REACTDRS ERANCH CHIEF:
D.
CRUTCHFIELD II-5 3.
DL/VSEB 2
SRC to CECO 07/10/31 GPERATING REACT 0F.5 PROJECT MANAGER:
P.
O'CONNOS II-3 8.
1.
Di/ HSE 3 3
CECA to Nic Sit. Visit 01/09/79 INTEGRATES ASSESSMENT PRO.'ECT MANAGER:
G.
CWALINA II 3 C.
DE/F0E0 3
CECO to hKC Sito Visit 01/ C 9/ 7 9
((Y FOR STATU3 CODE)
II-4 DE/GSB 7
hRC to Ceco 06/08/31 0 - GENERIC Ga-CRAFT SE RECEIVED II-4 A.
DE/GSL 7
NRC to CECO 06/08/31 FRCi1 REVIEW BRANCH X - DELETED II-4 E.
DE/GSB 7
NRC to CECO 07/09/51 6h-5 /, R RECEIVED FRCM 3 - TC?IC NOT LICEh5EE II-4 C.
DE/05B 7
NRC to CFCo 06/03/31 STARTEP 5 - DRAFT SE SENT I
II-4 D.
LE/ HOE 3 0
1 - GUESTI0h5 RECEIVED T3 UTILITY l
FRGM FEVIEW 3 RANCH I
II-4 E.
DE/HGEB 0
6 - SE RESPCNSE RECEIVE 3 1
2 - CUESTICHS SENT Br FRC l
II-4 F.
DE/HGLL 0
TO 'JTILIT(
i I
7 - TOPIC COM?LETE I
III-1 DL/SEPL 3(sys)
NPC to CECO 06/2b/81 3 - QUESTION RESPONSE DL/CEPB 5(Elec) Part of VII-3 RECEIVED Ei hRC III-2 DL/3EPB 3
i (2-7) l
DRESDEN 2 TCPIC 50.
PEVIEW STATUS REF. ARKS TCPIC NO.
REVIEW STATUS REMARKS DIV/ER LIV /BR III-!s DL/5E2 3
Ceco to NRC C9/28/79 l 1 GI-to B.
X NEC to CECO 11/16/79 i i III-3 B.
X bRC to CECO 11/16/79 I
III-10 C.
DL/SEPB 7
NRC to CECO 05/02/79 III-3 C.
DE/PGEs 0
III-11 X
NRC to Ceco 05/07/8f III-4 A.
DSI/ASB 0
111-12 X
NRC to Ceco 05/07/81 III ',
B.
DE/MTEB 3
Site visit 06/01/81 IV-1 A.
DL/SEPB 7
NRC to CECc 11/13/19 III-4 C.
DSI/AS3 J
IV-2 DSI/ICSB 3
CECc to NRC 06/08/81 III-4 D.
DE/SAE C
IV-3 DE/MTEB 7
NRC to Ceco 01/01/80 t
!II-5 DL/SEP3 2
NRC to CECO 01/04/80 V-1 DE/MTEB G
SRC to Ceco 35/07/81 [
III-5 B.
DL/SEPB 6
Ceco o NRC 03/21/80 V-2 X
HRC to CECO tt/16/79 III-6 DL/SEPB 6
CECO to bRC 03/13/81 V-3 X
NRC to CECO C5/0//8f III-7 A.
X NRC to CECO 05/07/51 V-4 X
NRC to CECO 05/07/81 III-7 B.
DL/SEPB 3
CECO to NRC 09/28/79 V-5 DL/SEPB 6
Ceco to NRC 09/02/80 III-7 C.
X NRC to Ceco 11/16/79 V-6 DL/SEPB 7
SRC to Ceco 03/05/80 III-7 D.
DE/SE3 Ab Ceco to NRC 04/27/81 V-7 X
NRC to CECO 05/07/81 III-8 A.
DSI G
NRC to CECO 05/C7/81 V-8 X
NRC to CECc 05/07/81 III-8 B.
X NRC to CECO 01/11/50 V-9 X
NRC to Ceco ff/16/79 I
III-8 C.
DL/SEFB 6
CECO to NPC 03/10/80 V-10 A.
DL/SEPB 7
NRC to CECO 31/C8/79 III-8 D.
X NRC to CECO 05/07/81 V-10 B.
DL/SEPB 7
NRC to Ceco 04/24/81 II'-)
X NRC te CECO 05/07/81 V-11 A.
D L / S t'F 3 7
Ceco to tiR C 09/30/80 III-13 A.
DL/SEPB 7
NRC to Ceco 06/26/81 V-11 B.
DL/SEPB 7(Sys)
HRC to Ceco 04/24/81 1
DL/SEPB 7(Elec) HRC to CECO 07.'10/81 (2-8) k
.-~
+
DRESDEN 2
~
l TCPIC ND.
REVIEW 57ATUS R EM A R KS TO?IC S0.
REVIEW C T /. ( U S REMARAS i
DIV/LR DIk/BR l
i V-12 A.
DL/SEPS 7
HRC to CECO 04/16/81 WI-/ D.
LL/SEFB 7
NRC to CECO 08/ i7/ 71 V-13 X
NRC to CECO 05/07/81 VI-7 E.
X SRC to CECO 05/07/81 VI-1 DE/CEB 3
CECO to NRC 07/27/79 VI-7 F.
X NRC to Ceco 11/16/71 VI-2 A.
X NRC to Ceco 05/37/81 VI-8 X
NRC to CCCo 05/07/31 I
VI-2 B.
X NRC to CECc 05/07/81 i
VI-9 X
hRC to CECO 11/16/79 VI-2 C.
X NRC to Ceco 11/16/79 VI-10 A.
DL/SEPB 7
NRC to Ceco 07/030/81 VI-2 D.
CLI/CSB 3
Ceco to NFC 11/20/80 VI-10 B.
DL/SEPB 7(Sys)
NRC to Ceco 06/20/81 DL/SEP3 7(Elec) NRC to Ceco 01/30/81 VI-3 DSI/CSB 3
CECO to ERC 11/20/80 JII-1 A.
DL/SEPB 2
NRC to CECO 10/22/80 V!-4 DS!/CSB 3(Sys)
CECO to NRC 06/17/81 DL/SEPB 1(Elec)
VII-f B.
DL/SEPB 7
NRC to CECc 38/17/78 VI-5 X
NRC
- 8. o CECO 05/07/81 VII-2 DL/SEPB 7
CECO to NRC 03/08/81 VI-6 DSI/CSE G
NAC to Ceco 05/07/81 VII-3 DL/SEPB 7(Sys)
NRC to CECO 04/24/81 DL/SEPB 7(Eloc) NRC to CECO 07/37/81 VI-7 A.
1.
X NRC to CECO 11/16/79 VII-4 X
hRC to CECc 05/07/88 VI-7 A.
2.
X NRC to Ceco 05/07/81 VII-5 X
NRC to CECc C5/01/81 VI-7 A.
3.
DL/SEPB 7
Ceco to NRC 06/23/81 VII-6 DL/SEPB G
HRC tc CECO 05/07/81 VI-7 4
DSI/RS3 C
NRC to CECO 05/07/81 VII-7 X
NRC to CECO 11/16/79 VI-7 B.
X NRC to CECO 11/16/79 VIII-1 A.
DSI/RSB G
NRC to CECO 05/07/81 VI-7 C.
DL/SEPB 7
NRC to Ceco 03/13/81 VIII-2 DL/SEP3 7
NRC to CECO 06/26/81 l
VI-7 C.
1.
DSI/PSS S
NRC to Ceco 03/11/81 VIII-3 A.
DL/SEPB 7
NRC to CECO 11/08/79 VI-7 C.
?
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 MRC to CECO 11/16/79 VIII-4 DL/SEPB 5
NRC to Ceco 06/12/83 (2-9)
DRESDEN 2
I TCPIC bD.
REVIEW STATUS P Eli A R (.S TOPIC ND.
REVIEW STATUS RE." ARKS DIV/BR DIV/BR IX-t DSI/ASE 3
CtCo to NRC 06/02/83 XV-tc X
NRC to CECO 11/16/19 IX-2 X
NRC to CECO 05/07/81 XV-11 DSI/CPB C
IX-3 DL/SEP3 5
HRC to CECO 06/30/81 XV-12 X
NRC to Ceco 11/16/79 IX-4 X
NRC to CECO 11/16/79 XV-13 DSI/SPB 3(Sys)
DSI/AE3 O(Doses)
IX-5 DL/SEPB C
XV-14 DSI/RSB C
IX-6 DSI G
NRC to Ceco 05/07/81 X v'- 15 DSI/RSS 0
X X
NRC to CECO 05/07/81 1
XV-16 CSI/AEB 5
NRC to CECO XI-t DSI/ETS3 G
NPC t-Ceco 05/07/81 l
1 XV-17 X
NRC to CCCc 11/16/79 XI-2 DSI/ETSB G
NPC to CECO 05/07/81 1
XV-18 DSI/RSS OCSys; XIII-1 X
r4 R C to Ceco 05/07/81 DSI/AE3 O(Dates)
XIII-2 OL/SSPB 7
HRC to Ceco 03/11/31 XV-17 DSI/RSB 0(Sys)
DSI/AEB 0(dosos)
XV-1 DSI/RSB 0
XV-20 DSI/AEB 4b CECO to hRC 34/27/8.
XV-2 X
NRC to Ceco 11/16/79 XV-21 X
NRC to Ceco 05/07/81 XV-3 DSI/RS3 0
XV-22 X
NRC to CECO 05/07/81 XV-4 DSI/RSS 0
XV-23 X
NRC to Ceco 05/07/81 XV-5 DSI/RSS 0
XV-24 X
NRC to CECO 05/07/81 XV-6 X
NRC to CECc 11/16/79 XVI X
NRC to CECO 11/05/80 XV-7 DSI/RSS 0
XVII DL 7
NRC to CECO 08/1//78 XV-8 RSI/CP3 0
XV-9 DSI/RS3 0
i (2-10) n
~
-a
1 GINNA e
. FACILITY: GINNA TCPIC NO.
REVIEW STATUS REMARKS DIV/ER LICENSEE: ROCHESTER GAS 4 ELECTRIC 11-1 A.
DE/SAS
/
NRC to RGE 07/17/31 R EGI O N.' L C C A T I C H : 15 MI'ES NORTH EAST CF ROCHESTER, II-1 B.
DE/SAS 7
NRC to RGE 07/21/81 DOCrif NO.
05000244 II-1 C.
DE/SAB 4b RGE to NRC 34/1S/81 F.MER CAP ACITY: 1520(THERMAL) 0490(ELECTRICAL)
II-2 A.
DSI/AEB 6
REG to NRC 01/19/81 OL NUP.3ER: DPR-18 II-2 B.
X NRC to RGE 35/07/81 N.S.S.S.
WEST.
l 11-2 C.
DSI/AEB 6
RGE to NRC 05/22/81 A/E FIRM: GIL.
II-2 D.
X NRC to RGE 05/07/81 SYSTEMATIC EVALUATION PROCRAM BRANCH CHIEF:
W.
RUSSELL II-3 A.
DE/HGEB 7
NRC to RGE J4/10/81 1
OPERATIhG REACTCRS BRANCH CHIEF:
D.
CRUTCHFIELD I
II-3 3.
DE/HGES 7
HRC to RGE 04/10/81 l
OPERATING REACTCRS PROJECT MANAGER:
R.
SNAIDER II-3 B.
1 DE/HGEB 5
NRC to RGE 04/10/81 INTEGRATED AS3ESSMENT PROJECT MANAGER: A.
WANG II-3 C.
DE/HGEB 7
NRC to RGE 04/10/81 II-4 DE/GSB 7
NRC to RGE 06/08/81 (FY FDD STATUS CODFS II-4 A.
DE/GSB 7
NRC to RGE 06/05/31 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.
DE/GSB 7
NRC to RGE 07/09/81 FRCM REVIEW BRANCH X - CELETED II-4 C.
DE/G3B 7
NRC to RGE 06/08/81 4b-SAR RECEIVED FROM 0 - TCPIC NOT LICENSEE II-4 D.
DE/ AGE 3 Ab RGE to NRC 06/30/81 STARTED 5 - GRAFT SE SENT II-4 E.
X NRC to RGE 1 t/16 / 7 9 1 - QUESTIONS RECEIVED TO UTILITY FRGM REVIEW hRANCH II-4 F.
DE/HGEB Gb RGE to NRC 06/30/81 6 - SE RESPCNSE RECEIVED 2 - GUESTICNS SENT BY NRC III-I DL/SEPB 2(Sys)
NRC to RGE 01/13/81 TO UTILITY DL/SEPB 6(Ele:) PGE to HRC 01/23/51 7-TO??C COMPLETE 3 - CUESTION RESPONSE III-2 DL/SEPB 3
RECEIVED SY NRC (2-11)
iI l
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TCPIC N3.
FEVIEW STATUS REMARKS TOPIC NG.
REVIEW STATUS REMARKS DIV/BR DIV/SR v-12 A.
n; C to RGE 1 1/16 / 7 'd VI-7 D.
DLeS PE 7
NRC to AGE 08/11/18 -
V-13 X
sp; to RGE 05/07/81 i
VI-7 E.
X LRC to ROE 05/07/81 i
VI-l DE/CEB 1
VI-7 F.
DL/StPF 7
hRC to RGE 06/24/11 VI-2 A.
X NRC to RGE 05/07/81 7
VI-8 X
HRC to RGE 05/07/81 VI-2 3.
X NRC to RGE 05/07/81 VI-9 X
NRC to ROE 11/16/79 VI-2 C.
X NRC to RGE 11/16/79 VI-10 A.
DL/SEPB 7
NRC to RCE 12/15/80 VI-2 T..
DSI/CSB 3
VI-10 B.
X NRC te RGE 11/16/79 VI-3 DSI/CS3 3
VII-1 A.
DL/SEPB 7
NRC to RGE 07/30/81 VI-4 DSI/ CSS Sa(sys) NRC to RGE 07/27/81 VII-1 B.
DL/SEP3 7
NRC to RGE 08/17/78 DL/SEPB 7(Elec) NRC to RGE 31/12/81 VII-2 DL/SEPB 7
NRC to RGE 06/12/81 VI-5 X
NRC to RCE 05/07/81 VII-3 DL/SEPB 6(sys)
SRC to RGE 06/23/81 VI-6 DSI/CSB 7
NRC to RGE 05/06/81 DL/SEF3 7(Elec) NRC to RGE 06/24/81 VI-7 A.
l.
DL/SEP3 7
NRC to RGE 02/20/81 VII-4 X
SRC to RGE 05/07/81 l
VI-7 A.
2.
DL/SEPB 7
tiRC to RGE 03/17/78 VII-5 X
NRC to RGE 05/07/81 1
VI-7 A.
3.
CL/SEPB 7
NRC to RGE 12/15/80 VII-6 DL/SEPB 7
hRC to RGE 06/24/81 l
VI-7 A.
4.
X SRC to RGE C5/07/81 VII-7 X
KRC to RGE 11/16/15 VI-7 B.
DSI/RSS 2(Sys)
HRC to RGE 02/27/81 VIII-1 A.
DSI/PSB 7
NRC to RGE 03/26/81 DL/SEB 0(Elec)
VIII-2 DL/SEPS 7
NRC to RGE 06/24/81 VI-7 C.
DL/ScPB 7
NRC to RGE 02/23/81 VIII-3 A.
DL/SEPB 7
NRC to RGE 07/31/81 VI-7 C.
1 DL/SEPE 2
NRC to RGE 04/24/81 VIII-3 B.
DL/SEPB 7
NRC to RGE 06/09/81 VI-7 C.
2.
DL/SEPB 7
NRC to RGE 02/20/81 VIII-4 DL/SEPB 6
RGE to MRC 05/01/81 i
VI-7 C.
3.
X SRC to RGE 11/16/79 I
(2-13)
GINNA i
it 7 "_ ' I " NO.
92/IEW STATUS R EP. A R K S l
TOPIC N3, REVIEW STATUS REMARKS DIV/BR i
- IV/Ed I
I4-1 LSI/ ASS 1
RGE to hkC C6/09/31 XV-13 DSI/RSB 5
NRC to RGE C6/29/81
'e-2 X
NRC to RGE 35/07/81 XV-11 X
NRC to RGE 10/01/80 i
I
-2 CL/SEPB 5
hRC to RGE 06/23/81 XV-12 DSI/ CPL 5(Sys)
HRC to RCE 06/29/81 DSI/AES 4acDCsos)
IX~
OSI/RSB 5
NRC te RCE 07/27/8i XV-13 X
NRC to RGE 11/16/79 I / ',
DL/SEPB 1
I/-
05I G
NPC ta RGE 05/07/31 XV-15 DSI/RS3 5
hRC to RGE 05/29/81 i
Y X
NPC to RGE 05/07/81 XV-16 DSI/AEB 4a RGE to NRC 06/18/80 i
1 XI-1 DSI/ETSB G
NRC to RCE 05/07/81 XV-17 DSI/RSB 5(5ys)
HRC to RGE 06/29/81 XI-:
CSI/ETSB G
FRC to RGE 05/07/81 DSI/AE3 4a(Dases)
!!I-1 X
NRC to RGE 05/07/31 X V-18 X
SRC to RGE 33/11/80 i
XI'i-DL/SEP3 7
NRC to RGE 03/26/81 XV-19 DSI/RSB 5(Sys) t' R C to RGE 07/27/81 DSI/AdB 4;(Desos) i
/V-1 D5I/RSB 5
HRC to RGE 06/29/81 XV-20 DSI/AEB 4a
"! - 2 LSI/RSB 5(Sys)
HRC to RGE 06/29/E1 XV-21 X
NRC to RGE 05/07/81 Dil/AEB 4a(Dosas)
I l
Xf' DSI/RSB 5
NRC to RGE 06/29/81 XV-22 X
NRC to RGE 05/07/81 l
X '/ - 4 D3I/RSB 5
HRC to RGE 05/29/81 XV-23 X
HRC to RGE 05/07/81 1'
XV-24 X
HRC to RGE 05/07/81 XV-5 33I/REE 5
HRC to RGE 06/29/81 i > V - *,
D3I/RSB 5
NRC to RGE 06/29/31 XVI X
NRC to RGE 11/05/80 l
l X/-7 D5I/RSB 5
HRC to RGE 06/29/81 XVII DL 7
NRC to RGE C3/17/78 i
xu '
D;I/CFB 5
NRC to RGE 06/29/81 XV
's DSI/RSB Ga (2-14) w -- _ -
A
. -~
HADDAM NECK 1
1 ~~
l l FACILITY: HACDAM FEC<
l TOPIC NO.
REVIEW STATUS REMARKS I
i DIV/BR t LICE'4SEE: CCSNECTICUT YANKEE ATGNIC PCWER I
II-1 A.
DL/bAB 45 CfAPCo te NkC 04/27/41 l REGICN/LCCATICN: 13 MILES EAST CF MERIDEN, CT.
l i
i II-1 B.
DE/SAB 0
DCCKET h3: 050C0213 II-1 C DE/SAB Gb CYAPCo to NRC 06/13/81 PCWER CAPACITY: 1825(THERMAL) 0575(ELECTRICAL) 1 II-2 A.
DSI/AEB 7
CYAPCo to NRC G1/22/81 1 OL NU"BER: DPR-61 II-2 B.
X hRC to CYAPCo 05/07/81 N.S.S.S.
WEST.
[
II-2 C.
DSI/AEB 7
CYAPCo to NRC 02/16/,9 l
A/E FIRM S&W II-2 D.
X NRC to CYAPCo 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF:
W.
RUSSELL II-3 A.
DE/HGEB 2
HRC to CYAPCo 07/10/81 OPERATINO REACTORS BRANCH CHIEF:
D.
CRUTCHFIELD II-3 B.
DE/HGEB 2
NRC to CYAPCo 07/10/81 OPERATING REACTORS PROJECT MANAGER:
W.
PAULSON II-3 B.
1 DE/HGEB 3
Sito Visit INTEGRATED ASSESSMENT PROJECT MANAGER:
T.
MICHAELS II-3 C.
DEiHGEB 3
Sito visit II-4 DE/CS3 7
bRC to CYAPCo 06/08/81 KEY FC2 STATUS CCpH II-4 A.
DE/GSB 7
NRC to CYAPCo 06/0Ae81 l
G - GENERIC 4a-CRAFT SE RECEIVED II-4 B.
DE/GSB 2
FCCM REVIEW BRANCH X-DELETE 7 II-4 C.
DE/GSB 7
NRC to CYAPCo 06/08/81 4b-SAR RFCEIVED FRCM O - TODIC NOT LICEN5EE II-4 D.
DE/HGEB 0
STARIED 5 - DRAFT SE SENT II-4 E.
X NRC to CYAPCo 04/16/79 1 - C'JESTICHS RECEIVED TO UTILITY FRG1 REVIEW BRANCH II-4 F.
OE/HGEB 4b CYAPCo to NRC P./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 7tEluc) Part of VII-3 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 3
CYAFCo to NRC 09/07/79 RECEIVED BY NRC (2-15)
HADDAM NECK l
1 YCPIC NO.
REVIEM STATUS RE"AFAS TOPIC hD.
PEVIEW STATUS REMAMS l
DIV/5R DIV/EP III-3 A.
D E.' 5 L 3 3
CrAFCo to hRC 09/07/79 111-10 B.
DL/SLPb 6
CYAPCo to hKC 12/i9/$0 l
l III-10 C.
X HRC to CYAPCo 04/16/79 III-3 B.
DF/HGE3 0
I l
III-18 X
NRC to CYAPCo c5/07/31 III-3 C.
DE/HGE3 0
l I l l III-12 X
NRC to CYAFCo 05/07/$1 II!-4 A.
DSI/A5:
0 I
III-4 B.
"E/MTES G
NRC to CYAPCo 05/07/31 i
IV-1 A.
Li/SEPB 7
CTAPCo to NRC D 6,'2 5/ 7 9 l
l IV-2 DSI/IC5B sb CYAPCo to NRC 06/30/31 III,
C.
DSI/A53 0
1 III '
D.
DZ/SAB 4b CYAPCo 'o NRC C6/25/31 1
IV-3 X
HEC to CYAFCo 25/07/81 i
III-5 A.
DL,
'B 3
CYAPCo te NRC 02/07/30 i
V-1 DE/MTEB G
NRC to CYAPCo 35/07/81 1
i V-2 X
nxC to CYAPCo 04/16/79 II!-5 E.
DL/5FP3 3
I III-6 LL/S[PS 2
NRC to CYAPCo 04/08/31 1
V-3 X
fM to CYAFCo 05/07/51 I
III-7 A.
X bRC to CYAPCo 05/07/31
"-4 X
NRC tc CYAPCo 05/07/81 III-7 3 DL/3EPB 3
CYAPCo to NRC 39/07/79 V-5 DL/SEPE 5
NRC to CYtP:o 06/30/81 2
III-7 C.
X
%; to CYAPCo 04/ 6/79 V-6 DL/SEP3 7
NRC to CYAPCo 03/05/80 f
III 7 D.
DE/SEE 4b CYAPCc to NRC 04/27/S1 V-7 DSI/ASB G
hRC to C Y.*J C o 05/07/a1 III-3 A.
DSI G
NRC to CYAPC3 05/07/81 V-8 X
NRL to CYAPCo 05/07/81 III-3 B.
X NRC to CYAPCo 10/01/30 V-9 X
NRC to CYtFCo 11/16/79 III-3 C.
DL/SEPB 6
CYAPCo to NRC 12/18/79 V-10 A.
DL/SEPB 7
NRC to CY#PCo 31/13/31 l
III-3 D.
X NRC to CYAPCo 05/07/21 V-i" B.
DL/SEPS 6
CYAPCo to NRC 09/23/77 NRC to CYAPCo J5/07/31 V-11 A.
CL/SEP3 7
CYAPCo to NRC 09/04/8" III-9 l
l III- 0 A.
DL/SEPB 7
CYAPCo to bRC 07/04/3 l
V-11 B.
DL/SEFB 6(Sv2)
CYAPCO to tRC C7/28/79 '
i l
DL/SEPB 7CElec) Part of VII-3 l
l (2-16)
_ _ - - - _ - - - - - __=--
HADDAM NECK I
TCPIC ND.
REVIEA STATUS REMARKS I
TCPIC NO.
REVIEW STATUS REMARKS O!V/LR I
CIV/52 I
i V-12 A.
X NmC to CYAPCo 04/16/19 i
VI-J D.
O!./ S lP S 7
hRC to CYAFCu 03/17/78---
l t
V-13 X
NPC to CYAPCo 05/07/81 i VI-7 E.
X NRC to C(APCo 05/07/81
[
l VI-1 CE/CLB 3
CYtPCO to NRC 10/31/79 VI-7 F.
X NRC to CYAPCo 04/16/79 i
VI-2 X
NRC to CYAPCo 05/07/81 VI-8 X
NRC to CYAPCo 05/07/81 VI-2 3.
X NRC to CYAPCo 05/07/81 VI-3 X
HRC to CYAFCo 11/16/79 i
VI-2 C.
X NRC to CYAPCo 04/16/79 VI-10 A.
DL/SEPB C
I i
VI-2 SI/ CSS 3
CYAPCo to NRC 04/27/31 VI-10 B.
X NRC to CYAPCo 04/16/79 VI-I DSI/ CSS 3
CYAPCo to NRC 04/27/81 VII-1 A.
DL/SEPB 2
NPC to CYAPCo 06/12/31 VI-4 DSI/CSB CCSys)
VII-1 B.
OL/SEPB 7
HEC to CYAPCo 08/17/78 ul/iEP3 7(EI(c) CYAFCo to NRC 12/03/80 i
i VII-2 CL/SEPB 2
hRC to CYAFCo 05/12/81 VI-5 X
bRC to CYAPCo 0 5 / 0 7 /t.1 VII-3 DL/SEPB 6(Sys) hRC te CYAlCo 09/28/79 VI-6 DSI/CSB G
hRC to CYAPCo 05/07/81 DL/SEP3 7(Elec) CYAPCo to NRC 01/22/81
[
i l
VI-7 A.
1.
DL/CEPB 7
NRC to CYAPCo 02/20/81 l
VII-4 X
HRC to CYAPCo 05/07/81 f
V!-7 A.
2.
X hRC to CYAPCo 05/07/81 VII-5 X
NRC to CYAPCo 05/07/81 7I-7 A.
3.
OL/SFPB 0
VII-6 DL/SEP3 G
NRC to CYADCo 05/07/81 VI-7 A.
4.
X NRC to CYAPCo 05/07/81 VII-7 X
NRC to CYAPCo 04/16/79 VI-7 B.
CSI/RS3 5(Sys)
HRC to CYAPCo 05/21/81 VIII-1 A.
DSI/PS3 G
NRC to CYAPCo 05/07/31 DL/SEF3 0(Eicc)
VIII-2 CL/SEP3 6
CYAPCo to NRC 10/03/80 V!-7 C.
DL/SEPB 7
NRC to CYAf00 03/13/81 VIII-3 A.
CL/5EP3 7
CYAPCo to NRC 02/16/79 VI-7 C.
1.
DL/SEPS 7
CvAPCo to NRC 09/04/00 VIII-3 3.
DL/SLP3 7
CYAPCo to NRC 01/22/81 l
VI-7 C.
2.
DL/SEPB 7
NRC to CYAPCo 03/13/81 1
VIII-4 DL/SEPB 2
NRC to CYAPCo 06/20/81
]
VI-7 C.
3.
DL/SEP3 3
i I
(2-17)
HADDAM NECK l
l l
l 1 l
TOPIC FD.
REVIEW STATUS REMARKS l l TOPIC NO.
REVIEW STATUS REMARKS DIV/3R i l LIV /BR l
l Ix-1 C5!/aS3 0
xv-10 Lil/ksB C
IX-2 X
NRC to CYAPCo 05/07/8" XV-11 X
HRC to CYAPCo 10/01/80 I
i IX-3 DL/SEP3 2
i XV-12 DSI/CPB 0(Sys)
I DSI/RSS 0(Doses)
IX-4 D S I / r.5 3 0
XV-13 X
NRC to CYAPCo 11/16/79 IX-5 D L ' ', t F B C
i XV-14 DSI/RSE O
IX-6 DSI C
NRC to CYAPCo 05/07/31 l l
XV-15 DSI/RS3 0
X X
ND.C to CYAPCo 05/07/81 XV-16 DSI/AEB 5
NRC to CYAPCO 07/10/81 XI-1 CSI/ETSB G
NRC to CYAPCo 05/07/81 l
XV-17 DSI/RSE 0(Sys)
XI-2 DSI/EISS G
NRC to CYAPCo 05/07/81 DSI/AE3 JCDoses)
XIII-1 X
NRC to CYAPCo 05/07/81 XV-18 X
NRC to CYAPCo 10/01/80 XIII-2 CL/SSPB G
NRC to CYAPCo 05<07/81 XV-19 OSI/RSS O(Sys) l DSI/AEB C(Dcsos)
XV '
n;I/RSB 0
l XV-20 CL/SEfB 7
NRC to CYAPCc 06/09/81 X i-2 DiI/RS3 0(Sys)
DS /AEB 0(Dosas?
XV-21 X
NRC to CYAFCo 05/07/81 XV-3 DSI/RS3 0
l XV-22 X
NRC to CYAPCs 05/07/81 XV-4 DSI/RS3 0
XV-23 X
NRC to CYAPr, 05/07/81 XV-5 D3I/RSB 0
XV-24 X
NRC to CYAPCo 05/07/81 XV '
DSI/RSB 0
XVI X
NRC to CYAPCo 11/05/80
- J-7 DSI/RSB 0
1 XVII DL 7
NRC to CYAPCo OE/17/78 l
XV-8 DSI/CPB 0
XV-9 DSI/RSB 0
(2-18)
.________..._-n
,l 1
LACROSSE FACILITY: LACROSSE TOPIC NO.
REVIEW STATUS REMARKS DIV/3R LICENSEE: DAIRLAND PCWER 11-1 A.
DE/ SAL Ab OPC to NRC 36/23/84 PEGICN/ LOCATION: 19 MILES SCUTH OF LACRCSSE, WISC.
II-1 B.
DE/SAS 4b DPC to NRC 06/16/81 DOCKET NO.
05000409 y
II-1 C.
DE/SAB 0
POWER CAPACITY: Ot6S(THERMAL) 0050(ELECTRICAL) l II-2 A.
DSI/AEB 5
NRC to D?C 12/1S/80 l CL NUM3EP: DPR-45 i
I II-2 B.
X hRC to DPC 05/07/81 N.S.S.S.
AC.
II-2 C.
DSI/AEB 3
A/E FIRM: S&L I
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 06/10/81 OPERATING REACTORS ERANCH CHIEF:
D.
CRUTCHFIELD II-3 B.
DE/MGEB 2
NRC to DPC 07/1C/31 CPERATING REACTCRS PROJECT MANAGER:
R.
CARUSO II-3 B.
1.
DE/HGEB 0
INTEGRATED ASSESSMENT PROJECT MANAGER:
G.
CWALINA II-3 C.
DE/HGEB 0
II-4 DE/GSE 7
NRC to DPC 06/08/81 vEY FOR STATUS CODES II-4 A.
DE/GSB 7
NRC to DPC 0(/08/81 i
G - GENERIC 4a-CRAFT SE RECEIVED lI-4 B.
DE/GSB 3
FRGM REVIEW ERANCH X - DEL, D
II-4 C.
DE/GSB NRC to DPC 36/08/81 4b-SAR RECEIVED FROM 0 - TOPIC NOT LICENSEE II-4 D.
DE/HGEB 3
Sito Visit 07/10/79 STARTED 5 - DRAFT SE SENT II-4 E.
DE/HGEB 0
i 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW ERANCH II-4 F.
DE/HGEB 5
6 - SE RESPONSE RECEIVED 2 - CUESTIONS SENT BY bRC Ill-1 DL/SEPB 2(Sys)
NRC to DPC 07/07/81 TO UTILITY DL/5LPB 3(Elec) 7 - TOPIC COMPLETE i
3 - QUESTION RESPONSE l
III-2 DL/SEPB 2
HRC to CPC 08/09/79 RECEIVED BY HRC 1
(2-19)
LACROSSE 1
i i IOPIC h3.
REVIE'A STATUS REPAR>5 TCPIC NO.
REVIE'd STATUS RENARKS DIV/ER 1
D I'. / E R l
l_
III-3 A.
LE/SLb 2
SEC to OPC 03/09/19 I
III-1; S.
I
! l i
III-3 E.
III-10 C.
X NRC to OPC 10/29/79 I
I III-3 C.
CE/dGEB 3
1 III-11 X
!II-4 A.
031/At3 1 i
!II-12 X
hRC to OPC 05/07/81 1
III-4 3.
LE/91E3 0
IV-1 A.
OL/SEPB 7
NRC to LPC 04/19/79 I
l i !!I '
SI/ALS 3
IV-2 DSI/ICSS 2
NRC to OPC 12/13/20 l
i l
i III-4 C.
CE/SAS 0
i !
IV-3 X
NRC to CPC C5/07/81 l
i i III-5 A.
CL/SEaB 2
b?C to CPC 01/04/80 l I V-1 D E/P.T E 3 C
HRC to LPC C5/07/31 1 l
!!I-3 B.
Oi/5EP3 2
SRC to D?C 01/04/80 i
V-2 X
NRC to DPC 1C/29/7)
)
l l
l III-6 CL/SEPE 2
SRC to 2PC 04/24/81 1
V-3 X
4RC to CPC 05/07/11 l
i i
i III-7 A.
X N ;. C to CPC Of/07/31 i
V-4 X
NRC to LPC C5/07/81 i
l 1
i III-7 :.
Di/SEr*
7 FRC tc EFC 35/09/79 i
V-5 DL/SEP3 4a I
III-7 C.
X NRC to CPC 10/29/79
)
V-6 JL/SEPB 7
NRC to DPC 03/05/8C 1
i I
III-7 C.
DE/SE3
&c OPC to NRC C6/29/81 I l V-7 X
NRC to CPC 05/37/01
! I l
III-5 A.
D31 G
NRC to DPC 05/07/81 l I V-8 X
NRC to OPC 05/07/51 i I
!!I-B 0.
X SRC to CFC 09/26/30 l l V-1 X
NRC to DPC 10/23/79 l
l DL/SFFB l
l III-8 C.
OL/SEPB 7
DPC to NRC 03/03/81 1
V-10 A.
7 NRC to LPC 01/C7/81 l
l 1
III-8 D.
X NRC to OPC C5/C7/81 l
V-10 B.
DL/SEPB 5
hRC to CPC 12/22/80 !
i III-9 X
t4 R C to OPC 05/07/31 V-11 A.
CL/SEPE 7
NRC to DFC 12/22/3G f
1 III-10 A.
DL/5EPC 7
V-11 B.
CL/SEPB 5(Sys)
HRC to DPC 12/22/30 i
l DL/SEPB 0(Elec)
}
j (2-Oe) s
LACROSSE I I t
7DPIC ND.
REJIEW STA7US REMARKS i l TOPIC NC.
REVIEW STATUS REMARKS DIV/SR DIV/BR I
4-12 A.
DL/3EFB
/
NiC to DFC 04/30/79 VI-7 D.
DL/SEPS 7
NRC to DPC C8/1//73____
I V-13 X
NFC to DPC 05/07/81 VI-7 E.
X NRC to DPC 05/07/81 VI-1 DE/CEo 3
X hRC to DPC 10/29/79 VI-2 A.
X NRC to DPC 05/07/81 VI-S X
NRC to DPC 05/07/S1 VI-2 B.
X NT;C to DPC 05/07/81 VI-9 X
NRC to DPC 10/29/79 VI-2 C.
X hRC to DPC 10/29/79 VI-10 A.
DL/SEPB 2
NRC to D~C 07/21/31 VI-2 D.
DSI/CSB 3
DPC to NRC
.4/26/79 VI-10 B.
X NRC to DPC 1C/29/79 VI-3 DSI/CSB 3
DPC to hkC 04/26/79 VII-1 A.
DL/SEFB 0
VI-4 DSI/CSB 2(Sys) hCC to DPC 05/26/81 VII-1 B.
DL/SEPB 7
NRC to D?C 08/17/78 DL/SEPB 7(Elec) NRC to CPC 07/02/81 VII-2 DL/SEPB 0
VI-5 X
NRC to DPC 05/07/81 I
VII-3 DL/SEP3 5(Sys)
NRC 6o Drc 12/22/80 VI-6 DS!/CS3 G
NRC to DPC 05/07/81 OL/SEPB 3(Elec)
VI-7 A.
1 X
HRC to DPC 1C/29/79 VII-4 X
NRC to DPC 05/07/81 1
VI-7 t.
2.
X NRC to DPC 05/07/8 VII-5 X
NRC to DPC 05/07/81 VI.
4.
3.
DL/SEPB 0
VII-6 DL/SEPB G
NRC te DPC 05/07/81 VI-7 A.
4.
X NRC to DPC 05/07/81 i
VII-7 X
HRC to DPC 10/29/79 I
I VI-7 B.
X NRC to DPC 10/29/79 l
VIII-1 A.
DSI/PSB G
NRC to DPC 05/07/81 I
VI-7 C.
DL/SEPB 7
NRC to DPC 03/13/E1 i
VIII-2 DL/SEPB 6
DPC to NRC 11/20/80 VI-7 C.
1.
DL/SEPB 7
NRC to DPC 07/10/80 VIII-3 A.
DL/SEPB 7
NRC to DPC 36/05/79
/I-7 C.
2.
DL/SEP3 7
NPC tc DPC
-03/13/81 VIII-3 B.
DL/SEPB 7
NRC to DPC 07/10/30 VI-7 C.
3.
X NRC to DPC 10/29/79 VIII-4 DL/SEPB 7
NRC to DPC 03/30/81 (2-21)
LACROSSE l
J
! l T3?!C ND.
REVIE4 STATLS REMARv5 l ! TCPIC hG.
REVIfW STATUS REMARKS i
1 l
DIV/LR DI%/LR I
I/-1 D'2 I / A 5 B 3
l XV-10 X
NWC to DFC 10/29/1#
l IX-2 X
X/-11 DSI/CPB 0
XV-12 X
NRC to DPC 10/29/79 IX-3 DL/SE?B 2
I IX-4 X
Nr.C to LPC 10/29/79 l
XV-13 DSI/CPB 0(Cases)
DSI/AEB OiSys)
IX-5 DL/SEP3 0
1 XV-14 DSI/FSB 0
IX-6 DSI G
NRC to DPC 05/07/8I XV-15 DSI/ESB 4b DPC to nRC C6/30/31 l
l X
X HRC to DPC 05/07/81 1
XV-16 DSI/AEB C
j XI-1 D5I/ETSC G
bkC to DPC 05/07/81 XV-17 X
NRC to DFC 10/29/79 i
}
XI -2 DSI/ETSB G
NF C to DPC 05/07/81 i
j XV-13 DSI/AEB 0(Dosts)
XIII-1 X
h r. C to DPC 05/0./81 l
DSI/RSB OCSys)
I XIII-2 DL/SSPL 7
NRC to LPC 0 3 ' 11/ $ 1 XV-19 DSI/AEB 0(Dosos)
D S I/ F.S B C(S/s) l i
l l
XV-1 DSI/RSB 0
XV-20 DSI/AEB 0
i 1
XV-2 X
NRC to DPC 10/29/79 l
i XV-21 X
NRC to DPC 05/07/81 XV-3 DSI/ES3 Ab DPC to NRC 06/26/81 l
XV-?2 X
hRC to DPC 05/07/81 XV-4 DSI/RSB 4b DPC to NRC 06/26/81 l
XV-23 X
bRC to DPC 05/J7/81 XV-5 DSI/RSB C
XV-24 X
NRC to DPC 05/07/81 XV-6 X
HRC to DPC 10/09/79 l
XVI X
NRC to PC
'1/05/80 l
XV-7 D S I / P.S B G
XVII DL 7
hRC to CPC C S /17 / 78 XV-3 DSI/CPB C
X"-9 DSI/RSS 0
(2-22) i
~
~
w
r
~
~
-~
- ' ~
M LLSTONE1 l l l
l FACILITY: MILLSTCNE 1 l l TOPIC NO.
REVIEW STATUS REMARKS l I DIV/BR LICENSEE: NCRTHEAST NUCLEAR ENERGY l
l 11-1 A.
LE/SAB 7
NRC to NU G7/31/81 i
REGION /LOCAT!;H: 5 MILES SOUTH WEST OF NEW LONDON, CONN.
l 1
II-1 S.
DE/SAS 46 NU to NRC C5/19/81 DOCKET N3.
05000245 i
l II-1 C.
DE/ SAP
'b NU to NRC 04/27/81 I
PCWER CAPACITY: 20t1 THERMAL) C 6 6 0 ( EL E C T R I C A 1. )
CL NUMBER: DPR-21 II-2 S.
X HRC to NU 35/C7/81 N.S.S.S.
OE.
I
!I-2 C.
DSI/AEB.
Ab NU to NRC 05/19/81 i
i A/E FIRM: EEASCO II-2 D.
X NRC to NU 03/07/81 SYSTEMATIC EVALUATICN FROGRAM BRANCH CHIEF:
W.
RUSSELL II-3 A.
D E/ H 3 E3 46 NU to NRC 06/25/81 OPERATING REACTCRS BRANCH CHIEF:
D.
CRUTCHFIELD II-3 3.
DE/HGEB 4b NU to NRC 06/06/81 GPERATING REACTORS PROJECT MANAGER:
J.
SHEA II-3 B.
1.
DE/HGEB Gb NU to NRC 06/25/81 1
INTECRATED ASS ;SMENT PROJECT MANAGER:
A.
PERSINKO II-3 C.
DE/HGES 46 NU to NRC 04/28/81 1
i II-4 DE/CSB 7
NRC to NU 06/C8/S1 ifY rcP STATUS PCDFS I
I II-4 A.
DE/GSB 7
NRC to hu 06/C8/81 C - GENERIC 4a-LRAFJ SE RECEIVED II-4 B.
DL'/GSB 3
FRCM REVIEW BRANCH X - DELETED II-4 C.
DE.GSB 7
NRC to NU 06/05/81 4b-SAR RECEIVED FROM 0 - TCPIC NOT LICENSEE l
II-4 D.
DE/HGEB 0
STARIEL 5-DRAFT SE SENT II-4 L X
NRC to NU 11/16/79 1 - QUESTIONS RECEIVED TO UTILITY FRO:1 R E /I EW E R ANCH II-4 F.
DE/HGEB 4b NU to NRC C4/28/81 6 - SE RESPONSE RECEIVED 2 - CUESTICMS SENT BY hRC III-t DL/SEPB 2(Elec) NRC to Hti 06/09/81 l
TO UTILI17 DL/SEPB 2(bys)
NRC to NU 35/22/81 l l
7 - TCPIC CCMPLETE 3 - QUESTION RESPONSE III-2 CL/SEPB 3
NU to NRC 08/27/79 l RECEIVED BY NRC
]
1 l
I i
(2-23)
MILLSTONE 1 TOPIC NO.
PEVIEW
$7ATUS REMARKS TODIC ha.
REtIEW STATUS REMARKS DIV/ER DIV/BR III-3 A.
LE/SEb 5
PRC to NU 05/11/81 III-10 E X
hkC to hu 11/16/19 f
III-3 3.
X nRC to NU 12/26/80 III-10 C.
DL/SEPB 7
NU to NRC 08/29/79 X
hRC to NU 05/07/81 l
III-15
\\
III-! C.
DE/HGEB 0
X NRC to hu 05/07/81 III-4 A.
DSI/ASB 3
HU to HEC 12/05/80 III-12 IV-1 A.
DL/SEPB 7
NU to hRC 02/10/79 III-4 B.
DE/MTEB 0
II'-4 C.
DSI/ASB 3
SU to NRC 12/05/80 IV-2 DSI/ICSP 2
NRC to NU 12/15/80 III-4 D.
DE/SAB 46 HU t NRC 04/29/81 IV-3 DE/MTEB G
NRC to NU 05/07/31 III-5 A.
DL/SEPB 3
NU to NRC f1/08/79 V-1 DE/MTEB G
hRC to NU 05/07/81 X
NRC to NU 11/16/79 V-2 III-5 3.
DL/SEF3 1
X NRC to NU 05/07/81 l
III-6 DL/SEPE 5
NRC to NU 05/28/8t V-3 X
HRC to hu 05/07/81 III-7 a X
NRC to NU 05/07/81 V-4 III-7 B.
CL/SEPB 3
NU to NRC 08/29/79 V-5 DL/SEPB 5
NRC to NU 06/03/81 III-7 C.
X HRC to NU t 1/16 / 7 9 V-6 DL/5EPB 7
NRC to NU 03/05/30 III-7 D.
DE/SE3 7
NU to NRC 02/17/81 V-7 X
NRC to NU 05/37/81 III-8 A.
DSI G
hRC to NU 05/07/81 V-8 X
HRC to NU 05/07/81 l
X HRC to NU 11/16/79 III-8 B.
X NRC to NU 09/I6/80 V-9 III-8 C.
DL/SEPB 6
NU to NRC 01/31/80 V-10 A.
DL/SEPL 7
NU to NRC 03/05/79 III-8 D.
X HRC to NU 05/07/81 V-10 B.
DL/SEPB 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.
3L/SEP8 7
NRC to NU 06/04/81 V-11 B.
DL/SEP3 7(Sys) hU to NRC 07/22/31 DL/SEPB 0(Elec)
(2-24) s
MILLSTONE 1 I TCPIC NL.
?EVIEW STATUS REMARKS l TCPIC N3.
REVIEW STATUS REMARKS DIV/LR l
DIV/3R V - 1 '. A.
CL/ Serb 7
b<r to ha 12/ 17/7's VI-7 D.
DL/ set 3 7
NRC to bu G 8 /11/18 i
- -13 X
NRC to NU 05/07/81 VI-7 E.
X NRC to NU 05/07/31 l
VI-1 DE/CEB 3
NU to NEC 10/10/80 VI-7 F.
X NRC to NU
'1/16/79 I
VI-2 A.
X NRC to hu 05/07/81 VI-8 X
SRC to NU 05/07/81 i
VI-2 B.
X HRC to NU 05/07/81 VI-9 X
NRC to NU 11/16/79 VI-2 C.
X NRC to NU 11/16/79 VI-1C A.
DL/SEPB 5
NRC to NU 06/C5/81 VI-10 B.
DL/SEPB 7(Sys)
NRC to NU 06/23/81 l
l VI-2 D.
CSI/ CSS 3
NU to NRC 06/09/81 CL/SEPB 7(Elec) i VI-3 OSI/CSB 3
bU to NRC 06/09/81 i
VI!-1 A.
CL/SEPB 7
NRC to NU 07/23/81 VI-4 DSI/CSB 0(Sys; CL/SEPL 5(Elac) NRC to NU 06/23/81 VII-1 B.
DL/SEPB 7
NRC to NU 08/17/78 VI-5 X
NRC to NU 05/07/81 VII-2 DL/SEPB 5
hRC to NU 06/30/81 VI-6 DSI/CSB G
NPC to NU 05/07/81 VII-3 DL/SEPB 7(Sys) hJ ts NRC 07/22/31
)
DL/SEFB 2(Elec) SRC to NU 06/09/81 l
VI-7 A.
1.
X NRC to NU 11/16/79 VII-4 X
NRC to NU 05/C7/31 VI-7 A.
2.
X NRC to NU 05/07/81 VII-5 X
NRC to NU 05/07/21 VI-7 A.
3.
DL/SEPB 5
NRC to NU 06/30/81 VII-6 DL/SEPB G
NRC t3 NU 05/C7/61 VI-7 A.
4.
DSI/RSB G
NRC to NU 05/C7/81 VII-7 X
NRC to NU 11/16/79 VI-7 B.
X NRC to NU 11/16/79 VIII-1 A.
DSI/RSB G
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 SU 02/13/31 V)-7 C.
1 DL/SEPD 6
HU to NRC 04/16/01 VIII-3 A.
DL/SEPB 7
NRC to NU 04/18/79 VI-7 C.
2.
D'_ / S E P B 7
HRC so NU 03/29/81 VIII-3 B.
DL/SEPB 7RC to NU 07/23/81 VI-7 C.
3.
X NRC to NU 11/16/79 VIII-4 DL/SEFB 7
NU to NRC 01/29/81 1
l (2-25)
m-m - --
e MILLSTONE 1 l
TCPIC NO.
REVIEW 3TA!US REMAFKS TCPIC NO.
REVIFW STATUS REMARKS DIV/LR DIV/ER IX-1 D51/A35 C
XV-1J X
6AC to 60 11/16/79 I
IX-2 X
NRC to NU 05/07/81 l
XV-11 DSI/CeB 4b NU to hRC C6/33/31 I
IX-3 DL/SEP3 2
l XV-12 X
NRC to NU 11/16/79 1
IX-4 X
tiR C to NU 11/16/79 i
XV-13 D5I/CPB 4b(Sys) Nu to NRC 06/30/31 l
DSI/AE3 4b(Dosos)NU to SRC C6/30/31 IX-5 DL/SEPB C
l l l XV-14 DS!/RL3 4b SU to NRC C6/3J/31 IX-6 DSI G
NRC to 50 05/07/81 l
l XV-15 DSI/RSB 4b NU to NRC 36/33 81 X
X HRC to hL C5/07/81 1
XV-16 05I/AE3 46 Nu to hRC XI-1 Dil/ETSB G
HRC to NU 05/07/81 06/30/31 l
XV-17 X
t:R C to SU 11/16/79 XI-2 D5I/ETSB C
hRC to NU 05/07/31 l
l XV-13 DSI/RSB Gb(Sys) Nu to NRC 06/30/31 XIII-1 X
NRC to NU C3/07/E1 i
DSI/A23 4b(Dosas)bu to NRC 06/30/31 i
l 1
XIII-2 DL/SSPB G
NRC to f.U 05/07/81 XV-19 D S I 'C. 3 B Gb(Sys) bd to NRC 06/30/81 1
DSI.
IB sb(Deses)hu to N3C 06/30/81 l
XV-t USI/RS3 4b NU to NRC C6/30/51 l
l l XV-20 DSI EL 4b NU to hRC 06/30/51 1
XV-2 X
NRC to NU 11/16/79 i
XV-21 X
NRC to NJ 05/07/81 XV-3 0: I / F. 5 3 4b NU to NiC 06/30/81 XV-22 X
NRC to NU 35/07/P1 XV-4 DSI/F3B 4b NU to haC 06/30/81 XV-23 X
NEC to NU 05/G7/81 XV-5 D3I/RSS 4b NU to NRC 06/30/81 1
XV-24 X
NRC to tHI 05/07/31 XV-6 X
NRC to HU 11/10/79 i
l XJI X
NRC tn NU 1t/05/30 X '! - 7 05I/RS3 4b NU to NRC 06/30/81 XJII DL 7
hRC to NU 08/17/73 XV-8 DSI/CP3 Ab NU to NRC 06/30/81 i
XV-9 DSI/RSB 4h NJ to NRC 06/30/81 (2-26)
0YSTER CREEK g
FACILITY: OYSTER CREEK 1 i
TOPIC NC.
REVIEW STATUS R E' ARKS t
DIV/ER LICENSEE: JERSEY CENTRAL POWER E LIGHT 11-1 A.
DE/SAB 4b JCPL to SRC 05/01/31 REGION /L7 CATION: 9 MILES SCUTH OF TCMS RIVER, NJ.
11-1 B.
DE/SAB Gb JCPL to NRC 05/07/81 DOC <ET NC.
C5000219 II-1 C.
DE/ stb 4b JCPL to NRC 05/07/81 PCWER CAFACITY' 1930(THERMA.) 0650(ELECTRICAL)
}
II-2 A.
DSI/AEB 5
NRC to JCPL 12/17/80
[
II -2 B.
X NRC to JCPL 05/07/81 N.S.S.S.
GE.
II-2 C.
OSI/AEB 0
A/E FIF^1: 32R e
II-2 D.
X NRC to JCPL 05/J7/81 l l
SYSTEMATIC EVALUATICH PROGRAM BRANCH CHIEF: W.
RUSSELL II-3 A.
DE/HGES 46 JCPL to NRC 05/07/8I i
1 CPERATING REACTORS 3RANCP CHIEF:
D.
CRUTCHFIELD II-3 B.
DE/HCEB sb JCPL to NRC 05/07/81 OPERATING rsEACTORa PROJECT MANAGEP:
J.
LCMBARDO II-3 B.
1 DE/HGEB 4b JCPL to NRC 05/C7/81 INTEORATED ASSESS-MENT PROJECT r.ANAGER:
R.
FELL II-3 C.
DE/HGED 4b JCPL to NRC 05/07/81 i
II-4 DE/GSB 7
NRC to JCPL 06/08/81 KfY FOR ". T A Til5 COD]
II-4 A.
DE/GSB 7
hRC to JCPL 36/08/81 G-GENERIC 4a-DRAFT SE RECEIVED I!-4 B.
DE/CSB 3
FROM REVIEW ERANCH X - DELETED II-4 C.
DE/GS3 7
NRC to JCPL 06/08/81 4b-SAR RECEIVED FRGM 0 - TOPIC HDT LICENSEE II-4 D.
DE/HGEa 0
STA1TED 5 - DRAFT SE SENT II-4 E.
X NRC to JCPL 11/16/79 1 - QUESTI?HS RECEIVED TO UTILITY FROM DEVIEW BRANCH II-4 F.
DE/HGEB 0
6 - SE RESPONSE RECEIVED 2-QUESTICNS SEbT -
BY HRC III-1 DL/ SEPP 3(Sys) hRC to JCPL 07/09/81 TO UTILITY DL/SEP3 Sa(Elec) 7 - TCPIC COMPLETE 3 - CUESTION RESFCNSE III-2 DL/SEPB Gb JCPL to hRC 05/07/81 RECEIVED BY HRC (2-27)
0YSTER CREEK l
l TCPIC h0.
F.EVIEW STATUS D E;1; u S
} IC?IC N3.
REVITW S*ATUS FEMAEAS I
DIV/BR I
CIV/BR l
i 111-3 A.
LE/ DEL 4b JCPL to NRC 05/07e81 fl!-10 B.
X SRC to JLPL 11/16/[
l i
III-3 3.
X NRC to JCPL 12/2J/80 III-10 C.
X NRC to aCFL 11/16/79 l
III-3 C.
DE/FGE3 0
l III-11 X
N P.C to JCPL 05/C7/81 I
III-4 A.
DSI/tSE G
l III-12 X
NRC to JCFL 05/37/81 1
I III-4 B.
D E/ r1T E B C
l IV-1 A.
DL/SEPB 7
hRC to JCPL 05/30/79 III-4 C.
CSI/ASB 2
NRC to JCPL 01/19/81 IV-2 DSI/ICSB 2
NRC to JCPL 12/15/80 i
i III-4 D.
DE/SAB 4b JCPL to NRC 05/07/81 IV-3 X
NRC to JCPL 05/07/81
)
l l
I I
l III-5 A.
DL/SEAB 5
hRC to JCPL 06/10/81 V-1 DE/F1I E3 G
NRC to JCPL 05/07/81 l
III-5 3.
CL/SEP3 6
JCPL to NRC 10/06/30 V-2 X
HRC to JCFL 11/16/79 i
i III-6 DL/SEF3 6
JCPL to NRC 06/15/81 V-3 X
hPC to sCPL 05/07/81 i
l i
l III-7 A.
X NRC to JCFL 05/07/81 V-4 X
NRC to JCPL 05/07/81 1
III-7 S.
DL/SEPB 4a V-5 DL/SEPB 5
NRC to JCPL 03/16/81 III-7 C.
X NRC to JCPL 11/16/79 l l V-6 DL/SEPB 7
SRC to JCPL 03/05/80 I
i III-7 D.
DE/SEB 3
JCPL to NRC 12/07/79 V-7 X
NRC to JC?L C5/07/81 III-8 A.
DSI G
NRC to JCPL C5/07/81 I
t-C X
NRC to JCPL 05/07/81 III-E L.
X NPC to JCPL 09/26/80 V-9 X
NRC to JCPL 11/16/79 i
III-8 C.
DL/SEP2 7
NFC tc JCPL 10/30/80 V-10 A.
DL/SEPS 7
JCPL to NRC 05/15/79 !
l III-8 D.
X ERC to JCPL 05/07/81 V-10 B.
DL/SEPD 7
NRC to JCPL 09/25/80 i
III-9 X
NRC to JCPL 05/07/81 V-11 A.
DL/SEPB 7
hRC to JCPL 12/15/80 III-10 A.
DL/SEPB 7
hPC to JCPL 06/29/81 V-11 d.
DL/SEPB 7(Sv2)
N 't C to JCPL 09/25/80 DL/SEPB 7a(Elec) NRC to JCPL 07/09/11 (2-28) m
0YSTER CREEK l
TCPIC h0.
REVIEM STATUS R EP. A R K S l
TOPIC ND.
REVIEW STATUS REMARKS DIV/ER I
DIV/SR V-12 A.
CL/5EPS S
NGC to JCFL 03/16/81 VI-7 D.
DL/3EPS 7
N r:0 to JCPL 08/17/78~~
V-13 X
NRC to JCPL 05/07/81 VI-7 E.
X NRC to JCPL 05/07/81 VI-1 DE/CEB 2
NRC to JCPL 06/06/79 VI-7 F.
X NRC to sCPL 11/16/79 VI-2 A.
X NRC to JCPL 05/07/81 VI-8 X
SRC to sJPL 05/07/88 VI-2 E.
X NRC to JCPt 05/07/81 VI-9 X
NRC to JCPL 11/16/79 VI-2 C.
X NRC to JCPL 11/16/79 VI-10 A.
DL/SEPB 5
NRC to JCPL 06/30/81 VI-2 D.
DSI/CSB 2
VI-10 B.
X NRC to JCPL 11/16/79 VI-3 D3I/ CSS 2
VII-l A.
DL/SEPB 5
NRC to JCPL 06/17/81 VI-4 DSI/CSE 2(Sys)
NEC to JCPL 04/17/81 VII-1 B.
DL/SEP3 7
NRC to JCPL 08/17/78 DL/SEP3 3(Elec) JCPL to NRC 04/09/81 VII-2 DL/SEPB 7
NRC to JCPL 06/29/81 VI-5 X
NRC to JCPL 05/07/81 VII-3 DL/SEPS
/(Sys)
NRC to JCPL 09/25/80 VI-6 DSI/CSB G
NRC to JCPL 05/07/81 DL/SEPB 7(Elec) NRC to JCPL 07/09/81 i
VI-7 A.
1.
X NRC to JCPL 11/16/79 VII-4 X
hRC to JCPL 05/07/81 VI-7 A.
2.
X NRC to JCPL 05/07/81 VII-5 X
NRC to JCPL 05/07/81 VI-7 A.
3.
DL/SEPE 7
NRC to JCPL 07/30/81 VII-6 DL/SEPB G
NRC to JCPL 05/07/81 VI-7 A.
4.
CSI/RSB G
NRC to JCPL 05/07/8t VII-7 X
NRC to JCPL ti/16/79 VI-7 3.
X NRC to JCFL 11/16/79 VIII-1 A.
D5I/PSB G
NRC to JCPL C5/07/81 VI-7 C.
DL/SEPB 7
NRC to JCPL 03/13/81 VIII-2 DL/SEPD 7
NRC to JCPL 06/29/81 VI-7 C.
t.
DL/SEPB 7
NRC to JCPL 06/29/E1 VIII-3 A.
CL/SEPB 7
hRC to JCPL 06/19/81 VI-7 C.
2.
DL/SEPB 7
f;R C to JCPL 03/13/31 VIII-3 B.
DL/SEPB 7
hRC to JCPL 06/29/81 l
VI-7 C.
3.
X NRC to JCPL 11/16/79 i
VIII-4 DL/SEPB 7
NRC to JCPL 12/15/80 i
__I I
(2-29)
0YSTER CREEK I
TCPIC h3.
REVIEW STATUS REMARKS i
TOPIC No.
REVIEW STATUS REMARKS DIV/SR l
DIV/BR l
,P1 SSI/ASB 3
J;PL to NRC 12/ 14/79 i
XV-10 X
bkC to JCPL 11/16/.'9 1
IX-2 X
NRC to aCPL 05/07/51 XV-11 DSI/CP5 5
NRC to JCPL 04/09/81 IX-3 DSI/ASB 5
NRC te JCPL 06/12/81 g
XV-12 X
HRC to JCPL 11/16/79 IX-4 X
NRC to JCTL 11/16/79 XV-13 DSI/AEB 4a(Doses)
DSI/CPE 5(Sys) hRC to JCPL 04/09/81 IX-5 DI/SEPB 3
XV-14 SSI/RSB 7
NRC to JCPL 37/16/81 IX-6 3SI G
NRC to JCPL C5/07/81 XV-15 DSI/RSS 4b JCPL to NRC CS/07/81 X
X NRC to JCPL C5/07/81 XV-16 DSI/AE3 0
XI-1 DSI/ETSB G
N.1 C to JCPL C5/07/J1 XV-17 X
hRC to JLPL 11/16/79 XI-2 DSI/ETSB G
hFC to JCPL 05/07/81 i
XV-18 DSI/AE3 4a(Doses)
XIII-1 X
NRC to JCPL C5/07/31 DSI/RSB
<b(Sys)
JCPL to NRC 05/07/81 XIII-2 DL/SSPB 7
NRC to JCPL C9/25/80 XV-19 DSI/AE3 Ab(Doses)JCPL to NRC C5/C7/81 DSI/RSB Gb( Sy s)
JCPL to NRC 05/C7/31 XV-1 LSI/RSB 4b JCPL to NPC c5/07/81 XV-20 DSI/R$3 Ab JCPL to NRC 05/C7/81 XV-2 X
NRC to JCPL 11/16/79 XV-21 X
NRC to JCPL G5/07/81 XV-3 DSI/RS3 7
HRC to JCPL 07/16/81 XV-22 X
NRC to JCPL 05/07/81 XV-4 DSI/RS3 7
NRC to JCFL 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 JCP'.
05/07/81 XV-6 x
hRC to JCPt 11/16/79 l XVI X
NRC to JCPL 11/05/80 1 XV-7 DSI/RSB C
l l
l XVII DL 7
NRC to JCPL 08/17/78 I XV-8 DSI/CPB 5
NRC to JCPL 03/31/81 l
l XV-9 DSI/RSD 4b JCPL to NRC 05/07/81 (2-30) n
PAL SADES I
FACILITY: PALISADES TCPIC NO.
REVIEW STATUS REMAR(5 DIV/;R LICENSEE: CONSUMERS 'CAER II-1 A.
DL/SLc5 7
CPCo to hkC 12/28/79 REGICN/LOCATICN: 5 MILES SOUTH OF SOUTH HAVEN, MI.
II-1 B.
DL/SEP3 7
CPCo to NRC 12/28/79 LOC (ET ND: 05003:55 l
II-1 C.
CL/SEPO 7
CPCo to NRC 05/t3/81 PCLER CAPACITY: 2530(THERMAL) 0508(ELECTRICAL)
II-2 A.
CSI/AEB 7
NRC to CPCo 06/30/81 OL NUMOER: DPR-20 II-2 3.
X NRC to JPCo O Se. 7, P 1 N.S.S.S.
C-E i
II-2 C.
OSI/AEB 7
rRC to CPCo 04/23/81 l A/E FIRM: aECH.
]
II-2 D.
X FRC to CPCo 05/07/81 SYSTEMATIC EVALUATION PRCORAM 3RAhCH CHIEF:
W.
RUSSELL II-3 A.
DE/HGEB 5
NRC to CFCo 03/23/81 OPERATING REACTCRS BRANCH CHIEF:
D.
CRUTCHFIELD II-3 B.
DE/HGES 5
HRC to CPCo C3/2J/81 GPERATING REACTORS PROJECT MANAGER
- T.
WAMBACH II-3 B.
1.
DE/HGEB 5
HRC to CFCo 03/20/81 I:4TEGRATED ASSESSMENT PROJECT MAN AGER:
T.
MICHAELS
!I-3 C.
CE/HGEB 5
NRC ta CPCo 03/20/81 II-4 DE/GSB 7
NRC to CPCo 06/08/81 ff,J__F_0 R TTATUS CODES l
II-4 A.
DE/GSB 7
hRC to CPCo C6/08/81 i
G - GENERIC 4a-CRAFT SE RECEIVED II-4 B.
DE/GSB 7
CPCo to NRC 07/22/81 l
FROM REVIEW 3EANCH X-DELETED IA-4 C.
DE/GSB 7
NRC to CPCo 06/08/81 4b-SAR RECEIVED FRCM i
0 - TOPIC HOT LICENSED II-4 D.
DE/hGEB 7
CPCo to HRC 06/01/31 STARTED 5 - DRAFT SE SEHT l
II-4 E.
X NRC to CPCo 11/16/79 1 - QUESTICHS RECEIVED TO U'ILITY FRCt1 REVIEW BR ANCH II-4 F.
DE/HGEB 7
CPCo to hRC 06/01/81 6 - SE RESPONSE RECEIVED 2 - Q'ESTIONS SENT BY NRL III-1 DL/SEFB 7(Elec) NRC to CPCo 11/12/80 J
TO LTILITY DL/SEPB 2(Sys)
NRC to CPCo 12/15/30 7 - TOPIC CGMFLETE 3 - QUESTION RESPONSE RECLIVED BY NRC i
(2-31)
PAUSADES I
I I
TCPIC NO.
FEVIEW STATUS REMARKS l
TCPIC ND.
REVIEW STATUS REMARKS I
LIV /BR I
DIV/SR l
III-2 DL/5EPB SRC to CPCc 32/27/81 III-10 b.
CL/SEPB 6
hWC to CPCo 05/15/31 III-5 A.
DE/SEE 5
HRC to CPCo O f. /17 / 81 III-10 C.
X NRC to CPCo 11/16/79 III-3 B.
X NRC to CPCo 12/26/80 III-11 X
NRC to CPCo 35/07/8t III-3 C.
CreHSEL 0
III-12 X
NRC to CPCo 35/07/81 III-4 A.
CSI/AEB 5
NRC to CFCa G3/04/81 IV-1 A.
DL/SEPS 7
CPCo to NRC 02/C8/79 III-4 B.
DE/MTE3 G
NRC to CPCo 05/07/81 IV-2 DSI/ICSB 2
III-4 C.
CSI'ASE 5
NRC to CPCo 07/20/31 I/-3 X
NRC to CPCo 05/07/81 III-4 D.
DE/SAB 6
CFCo to NRC 07/02/81 V-1 DE/MTEB G
NC to CPCo 05/07/81 III-5 A.
DL/SEP3 2
NRC to CPCo 01/11/79 V-2 X
HRC to CPCo 11/16/79 III-5 B.
DL/SEPB 1
V-3 X
NRC to CFCo 05/07/81 III-6 DL/SEPB 6
CPCo to NRC 03/27/81 V-4 X
HRC to CPCo 05/07/81 III-7 A.
DL/SEPB G
NRC to CFCo 05/07/81 V-5 DL/SEPB 5
NRC to CPCo 03/10/81 1
III-7 B.
DL/SEPB Ga V-6 DL/SEPB 7
NRC to CPCo 03/05/30 III-7 C.
DE/SEB 6
CPCo to NRC 07/21/81 V-7 DSI/ASB G
NRC to CPCo 05/07/81 III-7 D.
DE/SE3 42 V-8 X
NRC to CPCo 05/07/81 i
III-8 A.
DSI G
NRC to CPCo C5/07/81 V-9 X
hRC to CPCo 11/16/79 l
III-8 3.
X NRC to CPCc 10/01/30 V-10 A.
DL/SEPB 7
NRC to CPCo 04/21/79 III-8 C.
DLsMTE3 7
CPCo to NRC 2/28/79 V-10 B.
DL/SEPB 6
CPCo to NRC 07/22/31
!II-8 D.
X NRC to CPCo 05/07/81 V-11 A.
DL/SEPB 6
CPCo to NRC 07/03/81 1
III-9 X
NRC to CPCo 05/07/81 V-11 B.
DL/SEPB 6(Sys)
CFCo to NRC 07/22/81 DL/SEPB 7(LIec) NRC to CPr, 06/02/81 III-13 A.
DL/SEFB 7
HRC to CPCo 35/19/81 (2-32) s
PAllSADES I
i TCPIC NO.
REV:E.J STATJS REM 72KS 1 TCPIC NO.
REVIEW STAIUS REMARKS DIV/BR DIV/ER 4
1 V-12 A.
X SkC tc CPCo 11/16/73 VI-7 D.
DL/5tF3 7
NRC to CPCo 05/17/78 l
I l
V-13 X
NRC to CPCo 05/07/81 VI-7 E.
X NRC to CPCo 35/07/81 i
VI-1 DE/CEB 7
hRC to CPCo C8/03/81 VI-7 F.
DL/02PB 7
SRC to CPCo 05/09/81 VI-2 A.
X NRC to CPCo 05/07/81 VI-8 X
NRC to CPCo 05/07/81 VI-2 5.
X NRC to CPCo C5/07/81 VI
- X NRC to CPCo 11/16/79 VI-2 C.
X N E ', to CPCo 11/16/79 VI-10 A.
DL/SEPB 7
NRC to CPCo 06/19/81 L I
VI-2 D.
DSI/ CSS 6
CPCo to NRC 07/09/81 VI-10 B.
X NRC to CPCo 11/16/79 l
VI-3 DSI/CSB 6
CPCc to NRC 07/09/81 VII-1 A.
DL/SEPB 6
CPCo to NRC C6/29/81 VI-4 DL/SEPB 5(Elec) NRC to CPCc 05/06/81 VII-1 B.
DL/SEP3 7
NRC to CPCo 03/17/78 OCI/ CSS 5(Sys)
NRC to CPCo 06/09/81 VII-2 DL/SEPB 7
NEC to CPCo 05/19/88 VI-5 X
NRC to CPCo 05/07/81 VII-3 DL/SEPB 6(Sys)
CPCo to NRC 07/22/81 1 VI-6 DSI/ CSS G
NRC to CPCo 05/07/81 DL/SEPC 3(Elec) HRC to CPCo 01/24/31 VI-7 A.
1.
X hRC to CPCo 11/16/79 VII-4 X
NRC to CPCo 05/07/81 VI-7 A.
2.
X N P. C to CPCo 05/0//81 VII-5 X
NRC to CPCo 05/07/81 I
VI-7 A.
3.
DL/SEPB 6
CPCo to NRC 07/22/81 l
VII-6 DL/SEPB 7
NRC to CPCo 05/14/81 VI-7 A.
4.
X SRC to CPCo 05/07/81 VII-7 X
NRC to CPCo 11/16/79 VI-7 B.
DL/SEPB 7(Elec) NRC to CPCo 05/19/81 VIII-1 A.
DSI/P5B G
NRC to CPCo 05/07/81 DSI/RSB 7(Sus)
HRC to CPCo 06/30/81 VIII-2 DL/$EPB 7
NRC to CPCo 02/27/81 VI-7 C.
DL/SEPB 7
NRC to CPCo 02/20/81 VI!I-3 A.
DL/SEPL 7
HRC to CPCo 01/28/81 VI-7 C.
1.
DL/SEPB 7
NRC to CPCo 11/18/80 VIII-3 B.
DL/SEP3 6
HRC to CPCo 07/14/81 VI-7 C.
2.
DL/SEPE 7
hRC to CPCo C.?/20/81 i
VIII-4 DL/SE?B 7
HRC to CPCo C 7 / 31/ 81 l
VI-7 C.
3 X
CPCo to NRC 12/12/79 '
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i FACILITY: SAN CNJFRE 1 TCPIC NO.
REVIEW STATUG REMARKS DI V/ ?, R LICENSEE: SOUTHERN CALIFORNIA EDISCH II-1 A.
DL/SEPB 7
NRC to SCE
)!/C7/19 REGIC4/LCCITION: 5 MILES SCUTH CF SAN CLEMENTE. CA.
l l
II-1 B.
DL/SEPB 7
NRC to SCE 11/07/79 DOCKE! N3.
05CCC205 II-1 C.
DE/SAB 3
SCE to NRC 15/07/79 I
PCWER CAPACITY: 1347CTHERMAL) C430(ELECTFICAL)
OL NUMBER: DFR-13 l
l II-2 B.
x NRC to SCE 05/07/81 I
N.S.S.S.
MEST.
l II-2 C.
DSI/AE3 6
S C r, t o NaC 12/07/79 l
A/E FIPM: BE0d.
II-2 D.
X NRC to SCE 05/07/81 l
SYSTE*UTIC EVALUATION PROGRAM BRANCH CHIEF:
W.
PUSSELL I
II-3 A.
DE/HGED 43 l
l OPERATIFG REACTORS BRANCH CHIEF:
D.
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DE/HGEB 4a g
1 OPEPATI?G PEACTORS PROJECT MANACER:
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1 DE/HGEB 5
NRC to SCE 06/12/81 INTEGRATED ASSESSMEhT PRCJECT MANAGER:
E.
MCKENNA II-3 C.
DE/HOCB 4a II-4 DE/GSB 5
NRC to SCE 03/12/81 i
KFY Fr? ST ATUS CCD j II-4 A.
DE/GSB 5
NJREG-0712 12/80 G-GENE".IC 4a-DRAFT SE RECEIVED II-4 B.
DE/G3B 5
NUREG-0712 12/80 FROM FEVIER BRtNCH X - 0:LETED II-4 C.
DE/GSB 5
huREG-07'2 12/83 4b-SAR RECEIVED FROM 0 - TOPIC NOT LICENSEE II-4 D.
LE/HGEB 0
(
S T f f, T E D l
5 - CRAFT SE SENT i
II-4 E.
X NRC to SCE 11/16/79 1 - CUESTICNS PECEIVED TO UTILITY FRC'1 REVI EW BRANCH 11-4 F.
DE/HOEB C
{
2-CUESTIONS SENT SY NRC III-1 CL/SEPB 3(Sys)
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3 - QUESTICH RESPONSE i
III-2 DL/SEP3 3
SCE to NRC 09/08/80 i F E EI V E ra BY NRC l
l l
t l
l l
l (2-35)
I
SAN ON0FRE l
I
~l I-RE.AE/S I l TCPIC NO.
REVIEW STATUS REMARKS T3FIC NO.
PEJ7EW STATU; DIV/3R I
DIV/CR III-!
A.
LL/iEB 5
SCE to bRC G9/G8/80 III-10 B.
DL/SEPB 7
NxC to SCt 11eGS/79 i
III-3 E.
X HDC to SCE 11/ts/79 III-13 C.
X NRC to SCE 11/16/79 l
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DE/HCE3 5
NRC to SCE 07/17/81 1
III-11 X
NRC to SCE d5/07/81 I
III-4 A.
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SCE to hRC 08/14/79 I III-12 X
NRC to SCE 05/07/81 I
I I
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NE.C to SCE 05/07/81 IV-1 A.
DL/SEPB 7
NRC to SCE 07/19/79 l
III-4 C.
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i IV-2 DSI/ICSB 2
NRC to SCE 12/15/80 III-4 D.
DE/SAB C
IV-3 X
NRC to SCE 05/07/81 III-5 A.
DL/SEPB 1
V-1 CEeMTEB C
NRC to SCE 05/07/81 l
III-> 3.
DL/SEPB 2
htC to SCE 01/04/83 1
v-2 X
NRC to SCE 11/16/79 l
III-6 DL/SE'B 2
NRC to SCE C4/04/d1 l
V-3 X
NRC to SCE 05/07/58 l
.II-7 A.
X NRC tc SCE C5/07/81 V-4 X
HRC to SCE 05/07/81 l
I l
III-7 B.
DL/SEPB 3
SCE to NRC 09/08e80 V-5 DL/SEPB 5
NRC to SCE 06/03/81
(
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X NRC to SCE 11/16/79 V-6 OL/SEPB 7
NRC to SCE 03/C5/8C l
l III-7 D.
DE/SFI 46 SCE to h4C 06/09/81 l
V-7 DSI/AS3 G
NRC to SCE 05/07/81 l
I
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III-8 A.
DSI G
NRC to SCE 05/C7/83 i
V-8 X
NRC to SCE 05/07/81 III-8 3.
X NRC to SCE 10/01/80 V-9 X
HRC to SCE 11/16/79 l
l III-8 C.
DL/SEPB 7
HRC to SCE 01/29/80 V-10 A.
DL/SEPB 7
HRC to SCE 01/07/81 l
III-8 D.
X NFC to SCE 05/07/81 l
V-10 B.
CL/SEPB 5
NRC to SCE 06/20/81 I
l I III-9 X
NRC to SCE 05/37/81 l l V
.I A.
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NRC to SCE 08/03/81 l
l III-10 A.
DL/SEPB 7
SCE to NRC 07/24/81 V-11 B.
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NRC to SCE C6/20/81 DL/SEPB 2(Elec) Part of VII-3 l
I (2-36)
'T SAN ON0FRE I
I I TCPIC NG.
DEV!EW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS I
SIV/BR DIV/ER l
l V-12 A.
X HEC tc SCL 11/16/79 VI-/ D.
OL/SEPB 7
hkC to SCL 68/17//E V-13 X
NPC to SCE 05/07/81 VI-7 E.
X hRC to SCE 05/07/81
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VI-1 CE to NRC 08/03/79 VI-7 6.
X NRC d.o SCF 11/16/79 l
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X t.R C to SCE 05/07/81 VI-8 X
HRC to SCE 05/07/81 VI-2 B.
X NPC to SCE 05/07/81 VI-9 X
NRC to SCE 11/16/79 VI-2 C.
X HRC to SCE 11/16/79 VI-10 A.
D L.'S E P L 2
NRC to SCE 03/16/81 VI-2 C.
CSI/ CSS 2
VI-10 B.
DL/SEPB 7(Sys)
NRC to SCE 11/15/79 i
LL/SEPB 7(Elec) NRC to SCE 11/15/79 i
VI-3 DSI/CS2 2
i VII-!
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DL/SEPC 2
FRC to SCE G5/07/81 l
VI-4 CSI/CS3 2(Sys)
NRC to SCE 07/27/81 DL/SEPB 7(Elec) l VII-1 3.
DL/SEPB 7
hRC to SCE 08/17/78 l I VI-5 X
NRC to SCE 05/07/81 l l VII-2 DL/SEPB 2
hRC to SCE 33/ts/81 VI-6 DSI/CSB C
HRC to SCE 05/07/81
' l 1
VII-3 DL/SEPB 5(Sys)
NRC to SCE C6/20/81 DL/SEP3 2(Elec) HRC to SCE 03/16/81 V
-7 A.
t.
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NFC to SCE 02/20/81 l
i VII-4 X
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X NRC to SCE 05/07/81
~
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VII-6 DL/SEPB G
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X NRC tc SCE 05/07/81 i
VII-7 X
NRC to SCE 11/16/79 VI-7 B.
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l DL/SEPB 2(Elec) NRC to SCE 03/04/81 VIII-1 A.
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VI-7 C.
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NRC to SCE 07/31/81 l
l Vl-7 C.
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NRC to SCE C7/24/81 VI-7 C.
3.
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NRC to SCE 03/02/31 (2-37)
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YANKEE R0WE I
i FACILITY: YANKEE RCWE 1 TOPIC NO.
REVIEW STATUS REMARKS DIV/BR LICENSEE: YAhr.EE ATOMIC ELECTRIC I
l R E GI C h/ L O C #.T I O N : 25 MILES NORTH EAST OF PITTSFIELD. MASS.
DOCKET NO.
05000029 II-1 C.
DE/SAB Gb YEAC to NRC 04/09/81 POWER CA?ACITY: 600(THEF*.AL) 16 5( EL EC T RIC AL )
II-2 A.
DSI/AES 7
NRC to YEAC 03/03/81 OL HUM 3ER: DPR-3 II-2 B.
X NRC to YAEC 05/07/81 N.S.S.S.
WE37.
II-2 C.
DSI/AE3 4b YAEC to NRC 06/30/81 A/E FIRM: SIN II-2 D.
X NRC to YAEC 05/07/81 l
SYSTEMATIC EVALUATICN PROGRAM BRANCH CHIEF: W.
RUSSELL II-3 A.
DE/HGEB
(
YEAC to V J 03/16/81 i i
OPERATING REACTORS ERANCH CHIEF:
D.
CRUTCHFIELD II-3 B.
DE/HGEB 6
YEAC to.*_
03/16/81 OPERATING REACTODS PROJECT MANAGER:
R.
CARUSO II-3 B.
1 DE/HGEB S
NaC to YAEC 02/09/S1 INTEGRATED ASSESSMENT PROJECT MANAGER:
A. WANG II-3 C.
DE/HGEB 3
Sito Visit II-4 DE/GSB 7
hRC to YAEC 06/03/81 KEY FOR STATUS CODES II-4 A.
DE/GSB 7
NRC to YAEC 06/08/81 G-GENERIC 4a-DRAFT SE RECEIVED II-4 B.
DE'GLB 3
FRCM REVIEW BRANCH X - DELETED II-4 C.
DE/GSB 7
NRC to YAEC 06/08/81 4b-SAR RECEIVED FRC 1 0 - TOPIC NOT LICENSEE II-4 D.
DE/NCEB 3
Site Visit STARIED 5 - LRAFT SE SENT II-4 E.
DE/HGEB 3
Sito Visit
[ 1 - OUESTICNS RECEIVED TO UTILITY l
FRO,1 REVIEW BRANCH II-4 F.
DE/HGED 3
Sito Visit 6 - SE RESPCNSE RECEIVED 2-
?dESTICNS SENT BY NRC III-1 DL/SEPB 0(Elec) 10 UTILITY DL/SEPD 3(Sys)
YEAC to NRC 01/31/79 7 - TOPIC COMPLETE 3 - QUESTION RESPCNSE III-2 DL/SEPB 3
YEAv to NRC 09/06/79 RECEIVED BY NRC (2-39)
YANKEE R0WE l
1 1
TCPIC hD.
JEVIEW STATUS REMARKS l
TCPIC NC.
REVIEW STATUS REMARKS i
DIV/3E I
DIV/3R l
l l
III-3 A.
LE/ stb 3
YLAC to NEC 09/06/79 iia-10 B.
X NRC to YAEC 11/16/79 l
l 1
III-3 3.
X NFC to YAEC 12/26/80 III-10 C.
X NRC to YAEC 11/16/79 I I I
III-3 C.
DE/HGES 0
1 !
III-11 X
NRC to YAEC 05/37/*1 1
II!-4 A.
DSI/4SB 0
t III-:2 X
NRC to YAEC C5/0)
III-4 B.
SE/MTEB C
FPC to YAEC 05/07/81 1
IV-1 A.
DL/SEPB 7
NRC to YAEC 04/18//9 1
III-4 C.
LSI/ASL 0
IV-2 DSI/ICSB 2
NRC to YAEC 12/15/30 8
l III-4 D.
DE/SAB 4b YAEC to hRC 06/30/81 IV-3 X
NRC to YAEC 05/07/81 !
I I
III-5 A.
DL/SEPB 2
NRC to YAEC 01/C4/80 V-1 DE/MTES G
NRC to YAEC C5/07/81 III-5 B.
GL/SEPB 1
V-2 X
NRC to YAEC 11/16/79 III-6 C'./ S E P B 2
hRC to YAEC 04/24/81 V-3 X
NRC to YAEC 05/07/81 l
III-7 A.
X NRC to YAEC 05/07/81 V-4 X
hRC to YaEC 05/07/81 1
I III-7 L.
DL/SEP3 3
YEAC to NRC 09/06/79 V-5 LL/0EP3 5
hRC to YAEC 01e24/30 III-7 C.
X NPC to YAEC 11/16/79 V-6 DL/SEFB 7
NRC to YAfC 03/05/80 III-7 D.
DE/SEB 3
NRC to YAEC 11/16/79 V-7 DSI//SB G
hRC to YtEC 05/07/S1 I
III-8 A.
DSI G
SPC to YAEC 05/G7/81 1
V-8 X
NRC to YAEC 05/07/41 I
III-t L.
X NRC to YAEC 10/01/80 I
V-9 X
HRC to Y4EC 11/f6/79 I
III-8 C, 3L/SEPB 7
NRC to Yt. c c 11/15/79 i
V-10 A.
CL/SEPB 7
NRC to YAEC 1 /05/79 i i III-8 D.
X NRC to YAEC 05/07/81 l l V-10 L.
CL/SEPB 6
YEAC to NRC O'/13/79 I
III-9 X
HRC to YAEC 05/07/81 l
V-11 A.
CL/SEPB 7
NRC to YAEC 12/08/80 l
i III-10 A.
DL/SEPB 7
NRC to YAEC 12/08/80 l
V-11 B.
DL/SEPB 6(Sys)
YEaC to NRC O'./13/79 l
l DL/SEPS C(Eltc) l I
1 (2-40)
YANKEE R0WE I
I l
! TOPIC h3.
REVIEW STATUS REMARKS TOPIC NC.
REVIEW STATUS REMARKS DIV/2R DIV/BR l
v-12 %
/
SRC to YAEC 11/16/79 l
vl-7 D.
DL/5EPS
/
le R C to YAEC 06/17/78 i
V-13 X
NRC to YAEC 35/07/81 I
VI-7 E.
X NRC to YAEC 05/C7/81 VI-1 DE/CEB 3
YEAC to NRC 36/26/79 VI-7 F.
DL/SEPB 7
NRL to YA[C 12/08/83 VI-2 A.
X NPC to YAEC 05/C7/81 VI-8 X
MRC to YAEC 05/07/81 VI-2 B.
X NRC to YAEC 05/07/81 VI-9 X
NRC to YAEC 11/16/79 l
VI-2 C.
X NRC to YAEC
'1/16/79 i
VI-10 A.
DL/SEPB 4b YAEC to NRC 36/30/81 VI-2 D.
DSI/CSB 2
VI-10 B.
X NRC to YAEC 11/16/79 i
VI-3 DSI/CSI.
2 VII-1 A.
DL/SEPB 2
NRC to YAEC 04/23/81 1
VI-4 CSI/ CSS 0(Sys)
VII-1 B.
DL/SEPB 7
NRC to YAEC 08/17/78 at/SEPS 7(Elec) NEC '. o YAEC 12/08/80 l
VII-2 DL/SEPB 2
NRC to YAEC 04/03/81 VI-5 X
NRC to YAEC 05/07/81 i
l VII-3 DL/SEPB 6(Sys)
.EAC to NRC 04/13/79 VI-6 DSI/CSB G
hRC to YAEC 05/07/81 l
DL/SEPB 0(Elec)
VI-7 A.
1 DL/SEPB 7
- .RC to YAEC 02/20/81 VII-4 X
NRC to YAEC 05/07/81 VI-7 A.
2.
X NRC to YAEC 05/07/81 VII-5 X
NRC to YAEC 05/07/11 VI-7 A.
3.
DL/SEFB 4b YAEC to NiC 06/30/81 VII-6 DL/SEPB G
NRC to YAEC 05/07/81 VI-7 A.
4.
X NRC to YAEC 05/07/8' VII-7 X
hRC to YAEC 11/16/79 VI-7 B.
D5I/RSB 5
NRC to YAEC 06/04/81 VIII-1 A.
6SI/PSB G
NRC to YAEC 05/07/81 I
VI-7 C.
DL/SEPB 7
NRC to YAEC 03/13/81 1
VIII-2 DL/SEPB 7
NRC to YAEC G6/12/81 1
VI-7 C.
1 UL/SEPB 7
NRC to YAEC 12/08/30 VIII-3 A.
DL/SEPB 7
NRC to YAEC 11/07/79 VI-7 C.
2.
DL/SEP3 7
NRC to YAEC 03/13/31 1
VIII-3 B.
DL/SEPB 5
NRC to YAEC 12/15/80 I
VI-7 C.
3.
OL/SEPB 7
NRC tc YAEC 07/24/80 i
VIII-4 DL / C Er'B 2
NRC to YaEC 06/23/81 I
(2-41)
YANKEE R0WE 1
TCPIC ND.
REVIEW STATUS PEMARKS TOPIC NO.
REVIEW STATUS REMARKS IIV/BR CIV/ER
-~ I /. - 1 ESI/Asd 0
AV-1J DSI/RSb
- o YAEC to bRC 06/30/81 IX-2 X
hRC to YAEC 05/07/81 i
XV-11 X
NRC to YAEC 10/01/SG I
IX-!
DL/SEPB 2
XV-12 DSI/CPB 4b(Sys) YAEC to SRC 06/30/81 DSI/AEB 0(Doses) 1X 3
CSI/RSB 0
XV-13 X
NRC to YAEC 11/16/79 i
IX-5 DL/5EPB 0
l XV-14 DSI/RSB 4b YAEC to NRC 06/30/81 l
IX-6 DSI G
NRC to YAEC 05/^7/E1 XV-15 DSI/RSB 46 YAEC to NRC 06/30/81 l
X X
N f:C to YAEC 05/07/81 i
XV-16 DSI/AEB 0
X!-1 DSI/ETSB G
NRC to YAEC 05/^'/81 XV-17 DSI/RSB 0(5/s) i XI-2 OSI/ETS3 G
NRC to YAEC 05 rie :
DSI/AEB 3CDoses) l
/III-1 X
NRC to YAEC 0 5e c t/81 XV-18 X
NRC to YAEC 10/01/80 XIII-2 DL/SSPB 7
NRC to YAEC 03/11/81 XV-19 DSI/RSB 0(Sys)
DSI/AEB 0(Dosas) l 1
'-1 DSI/PSB C
l XV-20 DL/SEPB 7
hRC to YAEC 03/07/80 l
l XV-2 DSI/RSB 4b(Sys) YAEC to NRC 06/30/81 l
DSI/AEB 0(Doses)
XV-21 X
NRC to YAEC 05/07/81 X"-3 P3?/FSB 4b YAEC to NRC 06/30/81 XV-22 X
NRC to YAEC 05/07/81 1
<V-4 DS'/ES3 0
XV-23 X
NRC tn YAEC 05/07/81 1
1 XV-S DSI/PSB 4b YAEC to NRC 06/30/81 XV-24 X
NRC to YAEC 05/07/81 I
XV-6 D}I/PSB 0
XVI X
NRC to YAEC 11/05/80 1
XV-7 LSi/RSB 4b YAEC to NRC 06/30/8$
XVII DL 7
NRC to YAEC 08/17/78 i
XV-S DSI/CPB 0
l XJ-9 D31/RSB 4b YAEC to NkC 06/30/81 1
1 I
l (2-42)
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4
PALISADES I E.L i
l E.11 SAR 1/
SER ?/
5AR 1/
SER 2/
TCPIC NO. T I T 8. E RECEIVED COMPLETE TCPIC NO. TITLE RECEIVED COMPLETE l
111-1 Classificatten of NONE i
III-8.A Loose Parts Monitoring and NCNE l.
(SYS).
Structures Co ponents and Core Barrel Vibration Systces (Suismic and Monitoring (NRR B-60. C-12)
Quality) i IV-2 Reactivity Control Syss,.s
' 7/31/31 l
III-5.A Effccts of Pipe Break on OUE Including Functional Cesign Structures. Systems and ind Protection Against C=mponents Inside Single Failures Containment V-7 Reactor Coolant Pump NOME III-5.B Pipe Break Cutside DUE Overspeed (NRR L-68)
Containment VI-6 Containment Leak Testing.
NONE III-7.A Inservice Inspection.
NONE Including Prestressed VIII-1.A Potential Eauipment NONE Cencrete Containments with Failures Associated with a Either Grouted or Ungrouted Degraded Grid Voltage Tendons IX-1 Fuel Storage DUE III-7.B Design Codes. Design NGNE 07/15/81 Criteria. Load IX-4 Baron Addition System CUE Cc-binations, and Reactor Cavi ty Oesign Criteria XI-1 Appendix I(MP A-02)
NONE XI-2 Radiological (Effluent NONE El and Precess) Monitoring i
SAR 1/
SER g/
Systens(NRR B-67) l TCPIC NO. TITLE RECEIVED CCMPLETE i
III-3.C Inservice Inspe=tien of
'DUE 1/ SAR : Licensee Safety Analysis Report (Status eb)
Water Control Structures 2/ SER : Staff Safety Evaluaticn Report (Status 4a.S.6.7)
III-4.B Turbine Missiles (MP B-46)
NONE III-7.D Core Supports and Fuci NONE 07/30/81 (MP A-01.A-14)
V-1 Covoliance with Codes and NONE Standards (10 CFR 50.55a)
IX-6 Fire Protectien(MP B-C2)
NONE I
l I
(3-2)
+
M e
i GINNA EL i I El SAR 1/
SER 2/
TCPIC NO. TITLE.
RECEIVED CCMPLETE 4
TOPIC NO. TITLE RECEIVED COMPLETE 4
III-l Classification of Struct-NJ9E (SYS) ures Components and Systems IX-6 Fire Protection (MP.B-C2)
NONE-(Seismic and Quality)
III-2 Wind and Tornado loadings NONE Eli SAR 1/
SER 2/
III-7.A Inservice Inspection, NONE TOPIC NO. TITLF RECEIVED COMPLETE' Including Prestressed l.
Concrete Containments witn 111-4.C, Internally Generated DUE Containments Grouted or Missiles Ungrounded Tendons III-8.A Loose Parts Monitoring and NONE III-7.5 Design Codes, Design NONE Core Barrel Vibration Criteria, Load
. Monitoring (NRR B-60,C-12)
Conbinations, and Reactor Cavity Design Criteria V-7 Reactor Coolant Pump NONE Dverspeed(NRR B-68)
VI-7.C.1 Appendix K - Electrical NONE
,i Instrumentation and control VI-2.D Mass and Energy Release for NONE (EIC) Re reviews Possible Pipe Break Inside i
Containment j
IX-5 Ventilation Systems NONE
~
VI-3 Containment Pressure and NONE Heat Rcmoval Capability El SAR 1/
SER 2/
VI-7.B ESF Switchover fron NONE TOPIC NO. TITLE RECEIVED COMPLETE (SYS)
Injection to Recirculation Mode (Autematic ECCS 11-1.B Populat:en Distribution 04/15/81 07/21/81 Realignment)
II-1.C Potential Hazards or 04/15/31 07/01/81 IX-1 Fuel Storage DUE Changes in Potential Ha:ards Due to XI-1 Appendix I(MP A-02)
NONE l'
Transportation, Institutional Industrial, XI-2 Radiological (Effluent NONE and Military Facilities and Process) Monitoring Systems (NRR B-67)
II-4.D Stability of Slopes 06/30/81 r/-9 Startup or an Inactive Loop NONE 07/01/31 II-4.F Settlement of Foundations 36/30/81 or Recirculation Loop at an and Buried Equipment Incorrect Temperature, and Flow Controller Malfunction III-3.C Inservice Inspoction of DUE Causing an Increase in BWR Water Control Structures Core Flow Rate III-4 B Turbine Mi ssiles(MP B-46 )
XV-19 Loss of-Coolant Accidents NONE 06/26/81 (DOSES)
Resulting from Spectrum of III-4.D Sits Proximity Missiles 04/16/81 07/21/31 (SYS)
Postulated Piping Breaks 07/27/81 (Including Aircraft)
Within the Reactor Coolant Pressure Boundary VI-1 Organic Materials and DUE t
Post Accident Chemistry J/ SAR :
Licensee Safety Analysis Report (Status 4b) 2/ SER = Staff Safety Evaluation Report (Status 4a,5,6,7) 1 (3-5) s
DRESDEN 2 gi 21 (Cont.)
SAR 1/
SER 2/
SAR l' SER I' TOPIC No. TITLE RECEIVED CCMPLETE YOPIC NO. TITLE RECEIVED CCMPLETE III-l Classification of NONE 11-3.3 Flooding Potential and NONE (SYS)
Structures, Components and Protection Requirements Systems (Seismic and Quality)
II-3.B.1 Capability of Operating NONE Plant to Cope with Design I
III-2 Wind and Tornado Loadings EUE Basis Flooding Conditions III-5.A Effects of Pipe Break on DUE II-3.C Safety related Water NONE Structures. Systems and Supply (Ultimate Heat Sink Corponents Inside (UNS))
Containment DUE II-4.D Stability of Slopes III-7.3 Design Codes, Design NONE Criteria, Load II-4.E Dam Integrity DUE Combinations, and Reactor Cavity Design Criteria II-4.F Settlement of Foundations DUE and Buried Equipment VI-4 Containment Isolation
'NONE III-3.A Ef fects or Mlah Water Level DUE (ELEC)
System on Structures VII-1.A Isolation of Reactor NONE Protection System from III-3.C Inservica Inspection of DUE Non-Safety Systems.
Water Control Structures Including Qualifications of Icelation Devices III-4.B Turbine Missiles NONE VII-6 Frequency Decay NONE III-4.D Site Proximity Missiles DUE (Including Aircraft)
IX-5 Ventilation Systems NONE III-7.D Cens,inment Structural 04/27/81 insc;rity Tests El SAR 1/
SER 2/
V-1 Crmpliance with Codes NONE i
TOPIC NO. TITLE RECEIVED COMPL ET E and Standards (to CFR 50.55a)(NP A-01,A-14)
Il-1.A Exclusion Area Authority 06/01/81 and Control VI-1 Organic Materials and DUE Post Accident Chemistry II-1,-
Population Distribution 04/27/81 II-1.C Potential Hazards or DUE Changos in Potential Hazards Due to D.S.1 Transportation.
SAR 1/
SER t/
Institutional Industrial, TOPIC NO. TITLE RECEIVED COMPLETE and Military Facilities II-2.C Atmospheric Transport and 03/20/81 07/30/81 II-3.A Hydrologic Description NONE Diffusion Characteristics I
for Accident Analysis i
III-4.A Tornado Missiles DUE (3-4)
. ~~
_~
... _ - ~
. ~.
DRESDEN 2 E11 (Cont.)
Eil (Cont.)
I SAR 1/
SER 2/
SAR 1/
SER 2/
TOPIC HO. TITLE RECEIVED CVdPLETE TOPIC NO. TITLE RECEIVED COMPLETE
~
lll-4.C Internally Generated DUE XV-3 Loss of External Load, DUE
~
Missiles Turbine Trip. Loss of i
Condenser Vacuum, Closure III-8.A Loose Parts Monitoring NONE of Main Stean Isolation and Core Barrel Vibration Valve ( B LIR ), and Steam Monitoring (NRR B-60 C-12) i Pressure Regulator Failure (Closed)
IV-2 Reactivity Control Systems NONE Including Functional Design XV-4 Loss of Non-Eme rgency A-C DUE and Protection Against Pcwer to the Station Single Failures Auxiliaries VI-2.D Mass and Enercy Release for NONE XV-5 Loss of Normal Feedwater DUE Possible Pipe Break Inside Flow Containment XV-7 Reactor Coolant Pump Rotor (DUE VI-3 Containment Pressure and NONE Seizure and Reactor Coolant Heat Removal Capability Pump Shaft Break VI-4 Containment Isolation NONE XV-S Control Rod Misoperation DUE (SYS)
System (Systen Malfunction or Operator Error)
VI-6 Containment Leak Testing NONE (MP A-04)
XV-9 Startup or an Inactive Loop DUE or Recirculation loop at an VI-7.A.4 Core Spray Nozzle NDHE Incorrect Temperature, and Effectiveness (NRR A-16)
Flow Controller Malfunction Causing an Increase in BWR VIII-1.A Potential Equipment NONE Core Flow Rate Failures Associated with a Degraded Grid Voltage XV-11 Inadvertent Loading and DUE (MP B-23)
Operation of a Fuel Assembly in an Improper IX-1 Fuel Storage DUE Position XI-1 Appendix I(MP A-02)
NONE (V-13 Spectrum of Rod Drop DUE (SYS)
Accidents (Et'R)
XI-2 Radiological (Effluent and NONE (DOSES)
DUE Process) Monitoring Systems (NRR B-67)
XV-14
.nadvertent Operatic 1 of DUE ECCS and Chemical and XV-1 Increase in Feedwater DUE Volume Control System Temperature, Increase in Malfunction that Increases Feedwater Flow, Increase i
Reactor Coolant Inventory in Steam Flow and Inadvertent Opening of a XV-15 Inadvertent Opening of a DUE Steam Generator Relief or PWR Pressuri:er Safety-Safety Valve Relief Valve or a BWR Safety / Relief Valve (3-5) t
.m l
CRESDEN 2 Dil (Conte )
SAR J/
SER 2/
TOPIC H3. TITLE RECEIVED COMPLETE XV-18 Raciclogical Conscauences DUE I
of Main Steam Line Failure l
Outside Centainment
( B' R )
J XV-1)
Loss-of-Coolant Accidents DUE (SYC).
Resulting fro,Spectru, of (DOSES)
Postulated Piping Breaks 1
Within the Reactor Coolant I l
Pressure Boundary
(
't XV-20 Radiological Consequences 104/27/81 of Fuel Danacing Accidents I (Inside and Outside Centain,ent 4
1/ SvR : Licensee Safety Analysis Report (Status Ab) 2/ SER = Staff Safety Evaluation Report (Status 4a.5.6.7) u t
t 1
I i
i l
i t
a 1
(3-6)
- ~.. -.. _ - -, -.
=
OYSTFR roEEK EL El (Cont.)
I i
SAR 1/
SER 7/
SAR 1/
SER 2/
TOPIC NO. TITLE RECEIVED COMPLETE TOPIC NO TITLE RECEIVED COMPLETE III E' Classification of (SYSJ Structures, Components V-1 Conoliance with Codes and Systems
.and Struc&uret (MP A-01.A-14)
III-2 Wind and Tornado Loading 05/07/81 VI-1 D ganic Materials and Post DUE VII-6 Frequency Decay
[
Accident Chemistny IX-5 Ventilation System DUE IX-6 Fire Protection (MP A-02)
I El 211
. 3ER 2/ I SAR 1/
SE; 2/
SAR 1/
TOPIC NO. TITLE RECEIVED COMP ETE TOPIC NO. TITLE RECEIVED COMPLETE,
II-1.A Exclusion Area Authority 05/07/8 II2.C Atmospheric Transport and DUE and Control Diffusion Chara:teristics for Accident Analysis II-1.B Population Distribution 05/07/81 III-4.A Torr.do Missles DUE II-1.C Potential Ha:crds Due to 05/21/81 Transportation, In6 strial, III
- ,.C Internally Generated' DUE and Military Facilities Missies II-3.A Hydrologic Description 05/07/81 III-8.A Loose Parts and Core Barrel Monitori:17 1
II-3.B Flooding Potential and 05/07/81 (NRR B-60,C-12)
Protection Requirements IV-2 Reactivity Control Systems 11-3.8-apability to Cope with 35/07/81 Design Basis Flood VI-2.D Mass and Energy Release for Possible Pipe Break Inside II-3.C Safety Related Water Supply 05/07/81 Containnent (Ultimate Heat Sink)
VI-3 Cnntainment Pressure and II-4.D Stability of Slopes DME Heat Removal Capability II-4.F Settlement of Foundation DUE VI-4 Containment Isolation Systen and Buried Equipment i
I III-3.A Effects of High Water 05/07/81 VI-6 Containment Leak Testing Level on Structures (MP A-04)
III-3.C Inservice Inspect'sn of DUE VI-7.A-4 Core Spray No le Water Control Structure Effectiveness (MP D-12)
III-4.B Turbine Milliles DUE VIII-1.A Potential Equipment Failures Associated with III-4.D Site Proximity Missle 05/07/81 a Degraded Grid Voltage (MP B-23)
III-7.D Containment Structural DUE Integrity Tests IX-1 Fuel Storage DUE i
(3-7) i l
l l
l l
CYSTER CREER 211 (Cont.)
Ell (Cont.)
S A R 1/
SER Z/
SAR J/
SER 2/
TOPIC NO. TITLE RECEIVED COMPLETE TCPIC NO. TITLE RECEIVED COMPLETE XI-I Appendix I(MP A-02)
XV-13 Radiological Consequences 05/07/81 07/08/81 Main Steam Line failure i
XI-2 Padiological (Effluent and Outside Containment' Process Monitoring Systems)
(NRR B-67)
XV-19 Loss of Coolant Accidents 05/07/81 07/13/81 (SYS)
Resulting From Spectrum XV-1 Decrease in Feedwater 05/07/81 Breaks Within Reactor Te perature, Increase in (DOSES)
Coolant Pressure Boundary 05/07/81 Feedwater Flou. Increase in Steam Flow, I na d v er t en *c XV-20 Radiological Consequences 05/07/81 Opening of Steam Generator, of Fuel Damaging Accidents Relief or Safety Valve (In % Out of Containment)
XV-3 Loss of Externa' Load.
05/07/81 (T/16/81 Turbine Trip,
'.o s s o f 1/ SAR : Licensee Safety Analysis Report (Status Ab)
Staff Safety Evaluation Report (Status 4a,5,6,7)
Condenser vacuum, Closure 2/ SER of Main Steam Isolation Valve-(EWR). Steam Pressure Regulatory Failure (closed)
XV-4 Loss of Non-Emergency A-C 05/07/81 07/t6/81 Pouer to the Station Auxiliaries XV-5 Loss of Normal Feedwater lCS/07/81 Flow XV-7 Reactor Coolant Pump Rotor DUE Soi:ure and Reactor Coolant Purp Shaft BreBk XV-9 Startup or an Inactive Loop 05/07/81 or Recirculation Loop at Incorrect Temperature and Flow Controller Malfunction i
Causing an Increase in BWR Core Flow Rato XV-13 Spectrum of Rod Drop NONE 07/01/81 Accident XV-14 Inadvertent Operation of 05/07/81 07/16/81 DOSES ECCS that Increases Reactor Coolant Inventory XV-15 Inadvertent Opening of BWR 05/07/81 Safety / Relief Valve XV-16 Radiological Consequences LUE of Failure of Small sines Carrying Primary Coolant Outside Containment (3-8)
MILLSTONE 1 I El I R1 (Cont.)
SAR 1/
SER 2/
SAR 1/
SER 2/-
TOPIC NO. TITLE RECEIVED COMPLETE TOPIC NO. TITLE-RECEIVED COMPLETE 1
III-1 Classification of NONE II-3.A Hydrologic Description 06/25/81
($YS)
Structures, Components and Systems (Seismic and II-3.8 Flooding Potential 8 06/26/81 Quality)
Protection Requirements III-2 Wind and Tornado Loadings NONE II-3.B.1 Capability of Operating 06/25/81 Plant to Cope with Design III-5.A Effects of Pipe Break on DUE Basis Flooding Conditions Structures. Systems and Coeponents Inside II-3.C Safety Related Water 04/28/81 Containment Supply (UHS)
III-5.B Pipe Break Outside DUE II-4.B Proximity of Capable NONE 4
Containment Tectonic Structures in Plant Vicinity III-7.B Design Codes. Design NONE II-4.D Stability of Slopes DUE Criteria, Load Combinations and Reactor Cavity Design II-4.F Settlement of Foundations 04/28/81 V-11.5 RHR Interlock Requirements NONE and Buried Equipment (ELEC)
III-3.C Inservice Inspection of
,DUE VII-3 S/ stems Required for Safe NONE Water Control Structures (ELEC)
Shutdown III-4.B Turbine Missiles DUE VII-6 Frequency Decay H2NE III-4.D Site Frximity Missiles 04/29/81 IX-3 Station Service and Cooling DUE (Including Aircraft) i Water Systems IV-3 BWR Jet Pumps Operating NONE IX-5 Ventilation Systems DUE Indications XIII-2 Safequerds Industrial NONE V-1 Compliance with Codes and NONE Security (MP A-10)
Standards (10 CFR 50.55a) i (MP A-01.A-14) p1 VI-1 Organic Materials ac.d Pest DUE SAR 1/
SER 2/
Accident Chemistry TOPIC NO. TITLE RECEIVED COMPLETE IX-6 Fire Protection NONE 11-1. A Exclusion Area Authority a 04/17/81 07/31/81 Control D.1L II-1.B Population Distribution 05/19/81 SAR 1/
SER 2/
TOPIC NO. TITLE RECEIVED COMPLETE IP ?.C Potential Ha:ards or 04/29/81 05/19/81 Changos in Potential II-2.C Atmospheric Transport ano Hazards Due to Transporta-Diffusion Characteristics tion, Institutional, and for Accident Analysis i
Military Facilities III-4.A Tnrnado Missiles DUE (3-9)
-.- ~. -. _.. _ _ _..
MILLSTONE 1 l Hil (Cont.)
l Ell (Cont.)
SAR J/
SER 2/ l.
SAR J/
SER 2/-
TCPIC NO. TITLE RECEIVED COMPLETE TCPIC NO. TITLE RECEIVED COMPLEIE 1
III-4.C Internally Generated DUE XV-3 Loss of External Lead, 06/30/81 Missiles Turbine Trip, Loss of.
l I
Cendenser Vacuum. Closure l-1 III-8.A Loose Parts Menitoring and NONE of Main Steam Isolatien Core Barrel Vibration i
Valve (BWR), and Steam Meni+.oring(NRR B-60,C-12) l l
Pressure Regulator Failure I
(Closed)
IV-2 Deactivity Control Syste,s IDUE f
XV-4 Loss of Non-Emergency A-C 06/30/81 Including Fun tional Design and Protection Against Powcr +o the Station Single Failurcs Auxiliaries VI-2.D Mass and Energy Release for NONE XV-5 Loss of Normal Feedwater 06/30/81 Flcw Possible Pipe Break
- Inside, Containment l
XV-7 Reactor Coolant Pu-p 06/30/81 VI-3 Contairment Pressure and NONE Rotor Sei:ure and Reactor Heat Re-oval Capability Coolant Pung Shaft Break VI-4 Contain ont Isolation NONE XV-8 Control Rod Misoperation 06/30/81 (System Malfunction or (SYS)
System Operator Error)
VI-6 Leak Testirq (MP A-04)
XV-9 Startuo or an Inactive Loop 06/30/81 VI-7.A.4 Core Spray No::le NONE
.or Recirculation Lcop at an Effectiveness (NRP A-16)
Incorrect Te perature, and Flcw Centroller Malfunction VIII-1.A Potential Equipment NONE Causing an 1, crease in EWR
.ailures Associated With a Core Flow Rate Oaqraded Grid Voltage XV-11 Inadvertent Loading and 06/30/81 IX-1 Fuel Storage DUE Operation of a Fuel Assembly in an Improper i
XI-I Appendix I(MP A-02)
NONE Position XI-2 Radiological (Effluent 3 NONE XV-13 Spectrum of Rod Drop 06/30/81 Process) Monitoring Systems (SYS)
Accidents (BWR)
(NRR B-67)
(C0SES) 06/30/81
=
5 XV-1 Decrease in Feedwater 06/30/81 XV-14 Inadvertent Operation of 06/30/81 Temperature. Increase in ECCS and Chemical and Fcodw0ter Flow, Increase in Volume Control System i
Stcae Flow and Inadvertent Malfunction that Increases Ocening of a Steam Gener-Reactor Coolant Inventory ator Relief or safety Valve XV-15 Inadvertent Opening of a 06/30/81 i
PWR Pressurizer Safety I
Relief Valve or a EWR l
Safety Relief Valvo l
t
- 0) 6 i
i
, a MILL 5 TONE *
^
i SAR 1/
SER Z/
TCPIC NO. TITLE RECEIVED CGMPLETE 1'
XV-16 Radiological Conseauences 06/30/81 of Failure of Small Lines Carrying Primary Cnolant Outside Containment XV-18 Radiological Consequences 06/30/81 of Main Steam Line Failure Outside Containment (BWR)
XV-19 Loss of Coolant Accidents 06/30/81 (SYS)
Resulting frcm Spectrum of (DOSES)
Postulated Piping Breaks 06/30/81 Within the Reactor Coolant Pressure Boundary XV-20 Radiological Consequences.
06/30/81 of Fuel Damaging Accidents (Inside and Outside Centainment) 1/ SAR = Licensee Safety Analysis Report (Status 4b) 2/ SER : Staff Safety Evaluation Report (Status 4a,5,6,7)
I (3-11) l m
--m
SAN,0NOFRE EL SAR J/
SER R/
SAR 1/
SER 2/
TOPIC NO. TITLE RECEIVED COMPLETE TOPIC No. TITLE RECEIVED. COMPLETE IX-3 Station Service and cooling DUE I
III-1 Classification of Water mystems Structures, Components and Systems (Seismic and IX-5 Ventilation Systems DUE Quality)
III-2 Wind and Tarando Loadings DUE 21 SAR 1/
SER 2/
III-5A Effects of Pipe Break on DUE TOPIC NO. TITLE RECEIVED COMPLE1E Structures, Systems and Corpenents Inside II-1.C Potential Hazaros or DUE Containment Changes in Potential Hazards Due to III-5.5 Pipe Break Cutside DUE Transportation, Containment Institutional Industrial, and Military Facilities III-6 Seismic Design NONE Considerations II-4.D Stability of Slopes DUE III-7.B Design Codes, Design NONE II-4.F, Settlement of Foundations DUE Criteria. Load and Buried Equipment Combinations, and Reactor Cavity Design Criteria III-3.A Effects of High Water Level DUE on Structures i
V-11.B RHR Interlock Requirements NONE (ELEC)
III-4.B Turbine Missiles (MP B-46)
DUE 3
VI-7.A.3 EECS Actuation System NONE III-4.D Site Proximity Missiles DUE (Including Aircraft)
VI-7.B ESF Switchover from NONE 4
(ELEC)
Injection to Recirculation III-7.D Containment Structural 06/09/81 Mode (Automatic ECCS Integrity Tests Realignment)
V-1 Compliance with Codes and NONE VI-10.A Testing of Reactor Trip NONE Standards (10 CFR 50.55a)
System and Engineered (MP A-01) i Safety Features including Response Time Testing VI-1 Organic Materials and Post
. DU E Accident Chemistry I.
VII-1.A Isolation of Reactor NONE Protection Systems, IX-6 Fire Protection (MP B-02)
NONE Incl. ding Cualifications of isolation Devices Dkk VII-2 Engineered Safety Features NONE SAR 1/
SER 2/
(ESF) System Control Logic TOPIC NO. TITLE RECEIVED COMPLETE and Design III-4.A Tornado Missiles DUE VII-3 Systems Required for Safe NONE
^
(ELEC) dhutdown III-4.C Internally Generated DUE i
Missiles VII-6 Frequency Decay NONE l
(3-12) i e
SAN ONOFRE E11 (Cont.)
211 (Cont.)
SAR 1/
SER g/
SAR t/
SER 2/
TOPIC NO. TITLE RECEIVED COMPLETE TOPIC NO. TITLE RECEIVED COMPLETE Ill-8.A Loose Parts Monitcring and NONE XV-3 Loss of External Load.
07/01/81 Core Barrel Vibration Turbine Trip. Loss of Con-Monitoring (NRR 3-60.C-12) densor vaccum. Closure of Main Steam Isolation Valve IV-2 Reactivity Control Systems NONE (BWR). and Steam Pressure Including Functional Design Regulator Failure (Closed) and Protection Against Single Failures XV-4 Loss of Non-Emergency A-C DUE Power to the Station V-7 Reactor Coolant Putp HONE Auxiliaries l
Overr eed(NRR B-68)
XV-S Loss of Normal Feedwater 07/01/81 VI-2.D Mass and Energy Release for NONE Flow Possible Pipe Break Inside Centainment XV-6 Feedwater System Pipe 07/01/81 Breaks Inside and Outside VI-3 Containment Pressure and NONE Containment (PWR) f Heat Removal Capability XV-7 Reactor Coolant Pump Rotor 07/01/81 VI-4 Contains at Isolation NONE Seizure and Reactor Coolant (SYS)
System Pump Shaft Break VI-6 Containment Leak Testing NONE XV-8 Control Rod Misoperation 07/01/81 (MP 3.- 0 4 )
(System Malfunction or Operator Errer, VIII-1.A Potential Equipment Failure NONE Associated with a Degraded XV-10 Chemical and Volume control 07/01/81 Grid Voltage (MP B-23)
System Malfunction that Results in a Decrease in IX-1 Fuel Storage DUE the Boron Concentration in the Reactor Coolant (PWR)
XI-t Appendix I NONE XV-12 Spectrum of Rod Ejection 07/01/81 XI-2 Radiological (Effluent and NONE Accidents (PWR)
Process) Monitoring Systems (NRR B-67)
XV-14 Inadvertent Operation of 07/01/81 ECCS and Chemical and XV-1 Decrease in Feedwater 07/01/81 Volume Control System Temperature. Increase in Malfunction that Increases
- Feedwater Flow, Increase Reactor Coolant Inventory in Steam Flou and Ir. advertent Opening of a XV-15 Inadvertent Opening of a 07/01/81 Cteam Generator Relief PWR Pressurimer Safety-or Safety Valve Relief Valve of a BWR Safety / Relief Valve XV-2 Spectrum of Steam System 07/01/81 Piping Failuris Inside and XV-16 Radiological Consequences DUE Outside of Containment (PWR) of Failure of Small Lines l
Carrying Primary Coolant Outside Containment (3-13)
?m.,
's;,N SAN ONOFRE 211 (Cont.)
SAR 1/
SER 2/
TCPIC NO. TITLE RECEIVED C0ft?LETE I
XV-17 System Generator Tube DUE (SYS)
Failure (PWR)
XV-19 Less of-Coolant Accidents 07/01/81 07/23/81 Resulting From Spectrum of Postulated Piping 3rea'a s Within the Reactor Coolant l
Pressure Soundary 1/ SAR: Licensee Safety Analysis Report (Status 4b) 2/ SER: Staff Safety Evaluation Report (Status 4a,S,6,7) l I
l A
1 (3-14)
I
m BIG ROCK POINT IE I
E H
SAR t/
SER 2/
SAR J/
SER 2/
TCPIC NO. TITLE RECEIVED CCMPLETE TOPIC NO. TITLE RECEIVED COMPLETE 111-1 Classification of Struct-h0 net /80 01/30/80 Il-3.A l'.. ologic Description N0hE
~'
(SYS) uros, Components and Sys-
' ems (Seismic and Quality)
II-3.B Flcoding Potential and NONE III-2 Wind and Tornado Loading DUE II-3.B.t Capability of Coerating NONE i
III-5.A Effects of Pipe Break on DUE 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 UHS))
III-S.B Pipe Brc.n Outside DUE Containnent II-4.B Proxinity a+' Capable NONE Tectonic Sh,ctueos in III-6 Soismic Design NONE Plant Vic8ai$y Considerations II-4.D Stability of Slopes DUE III-7.B Ecsion Codes, Design NONE riterion, Lead II-4.F Settlement of Foundations DUE Combinations and Reactor and Buried Equipment Cavity Design Criterion III-3.A Effects of High Water DUE VI-7.A.3 ECCS Actuation System NONE Level on Structures I
VI-7.C ECCS Single Failure Cri-NONE III-3.C Inservice Inspecticn of DUE terion and Requirements for Water Control Structures Locking Out Power to Valves Including Independence III-4.B Tu-bine Missiles DUE of Interlocks on ECCS Valve III-4.D Site Proximity Missiles DUE VI-7.C.2 Failure Mode Analysis ECCS NONE (Including Aircraft)
VI-10.A Testing of Reactor Trip DUE III-7.D Containment Structural DUE Systen and Engineered Integrity Tests Safety Features, including Response Tine Testir.g V-1 Compliance with Codes and NOME Standards 310 CFR 50.55a)
VII-1.A Isolation of Reactor NONE (MP A-01.A-14)
Prctection Systen From Hon-Safety Systems, Includinc VI-t Organic Materials and Post DUE Qualification of Isolation Accident Chemsitry D2 vices IX-6 Fire Protection (MP B-02)
NONE VII-2 Encina red Safety Featur(s NONE (ESF) system Control Logic and Design
_Dil
. SAR 1/
SEP 2/
VII-6 Frequency Decay TOPIC NO. TITLE RECEIVED COM*LETE IX-3 Station Service and D'JE t
Cooling Mater Systems II-2.C Atmospheric Transport and DUE Diffusion Characteristics IX-S Ventilation Systems DUE for Accident Analysis t
(3-15) i
BIG POCK POINT I All (Cont.)
l Lil (Cor t. )
l l
SAR 1/
SEE ;/
4 TOPIC t.0.
TITLE RECEIVED CCMPLETE TCPIC N3. TITLE I RECEIVED COMPLETE l
~~
111-6.4 Tornacs Miss ies DUE XV-5 Loss of External Load.
07/tS/88 Turbine Trip, Loss of I
i III-4.C Internally Generated DUE Condanser vacuum. Closure i I
I Missiles of Main Steam Isolation I
i Valve (EWR), and Steam III-8.A Loose Parts Mar.itor nq and Pressure Regulator Failure Core vibration Monitoring (Closed)
(NRR B-63.C-12) 1 i
l XV-4 Loss of Non-E=ergency A-C 07/15/81 IV-2 Feactivity Control Syste' DUE I
Pcwer te use Station i
Including Functional Design i
Auxiliaries i
l and Prctaction Against Single F..iures XV-5 Loss of Noemal Feedwater 07/15/81 Flow VI-2.D Mars and Energy Release for NONE Postulated Pice Breaks XV-7 Reactor Coolant Pueos 07/15/88 Inside Containment Rotor Sei:ure and Reactor Coolant Pump Shaft 7.reak VI-3 Centaintent Pressures and NCNE Heat Re-oval Capability XV-S Control Rod Misoperation C9E (System Malfunction or VI-4 Containment Isolation Sys.
NONE Cperator Error)
VI-6 Containment Leak Testing NCNE I
XV-9 Startup of an Inactive Loop 07/15/81 (MP A-34) or Recirculation Loop at an Incorrect Te perature and VI-7.B ESF Switeho/cr frcn NCNE I
Flow Controller Malfunction Injection to Recirculation I
Causing an Increase in BWR Moda (Aute atic EECS I
Core Flow Rate l
I Realignment)
XV-11 Inadvertent Lcading and DUE VIII-1.A Potential Equip-ent NONE Cceration of a Fuel Failures Associated with Asse=bly
.n an Improper Degraced Grid Position (BWR) i IX-1 Fuel Storage DUE XV-13 Spectrum of Rod Drop 07/01/81 Accidents l
XI-1 Appendix I(PP A-C2)
NCNE l
XV-14 Inadvertent Operation of
$6/26/81 07/10/81 l
XI-2 Radiological (Effluent NONE l
ECCS and Chemical and and Process) Monitoring Volume Control System l
Systems (NRR B-67)
Malfunction that Increases Reactor Coolant Inventory XV-1 Decrease in Fecdwater 07/15/81 Te-perature Increase in XV-15 Inadvertent Opening of a 06/26/81 C8/03/88 Fecewater Flow. Increase PWR Pressurizer Safety in Steam Flow and Relief Valve er a BWR l
Inadverte:it Opening of a Safety / Relief Valve l
I Steam Generator Relief l
or Safety Valve (3-16)
~_
~
QIG ROCK POINT
'l 211 (Cont.)
SAR 1/
SER 2/
TCPIC NO. TITLE RECEIVED COMPLETE XV-16 Radiological Consee.uences 07/01/81 of Failure of Small Lines Carrying Primary Coolant Outside Containment XV-18 Radiological Consequences 07/01/81 of Main Steam Line Failur e Outside Cor'ainment t
XV-19 Loss of Coolant Accidents 06/29/61 07/20/11 (SYS)
Resulting From Spectrum of Postulated Piping Breaks (DOSES) within the Reactor Coolant 07/01/A1 P essure Boundary XV-20 Radiological Consequences 07/03/81 of Fuel Damaging Accicants (Inside and Outside Containment) 1/ SAR = Licensee Safety Analysis Report (Status 4b) 2/ SER : Staff Safety Evaluation Report (Status 4a,S,6,7)
(3-17)
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S A R 1/
SER g/
SAR t/
SER 2/
TOPIC NO. TITLE RECEIVED COMPLETE TOPIC NO. 'i l ', '
RECEIVED COMPLETE III-3.C Inservice Inspections of DUE 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/F1 Mode (Automatic ECCS (Including Aircraft)
Realignment)
III-7.D Containment Structural 04/27/81 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 DUE VI-1 Organic Materials and Post DUE IX-4 Boron Addition Systems DUi 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 D11 Systems (NRR B-67)
SAR 1/
SER 2/
TOPIC NO. TITLE RECEIVED COMPLETE XV-1 Decrease in Feedwater DUE Temperatures, Increase in III-4.A Tornado Missiles
___DUE Feedwater Flow, Increase in Steam Flew and Inadvertent III-4.C Internaly Generating DUE Opening of a Steam Geneca-Missiles tor Relief or Safety Valve III-8.A Loose Parts Monitoring and NONF XV-2 Spectrum of Stear System DUE Core Barrel Vibration Piping Failures Inside and Mooitoring(NRR B-60,C-12)
Outside of Containment (PWR)
IV-2 Reactivity Control Systems 06/30/81 Including Functional Design XV-3 Loss of External Load, DUE and Protection Against Turbine Trip, Loss of Single Failures Condenser vacuum, Closure of Main Steam Isolation V-7 Reactor Coolant Pump NONE Valve (BWR), and Steam OverspeedCNRR B-68)
Pressure Regulator Failure (Closed)
VI-2.D Mass and Energy Release for NONE Possible Pipe Break Inside XV-4 Loss of Non-Emergency A-C DUE Containment Power to the Station Auxiliaries VI-3 Containment Pressure and NONE Heat Removal Capability XV-5 Loss of Normal Fcedwater DUE Flow VI-4 Containment Isolation NONE Systen (3-19)
HAUDAM NECK l 211 (Cent.)
211 (Cont.)
I SAR 1/
SER 2/
SAR 1/
SER R/
TCPIC N3. TITLE RECEIVED CCMPLETE TOPIC NO. TITLE RECElVED COMPLETE 1
xv-6 Fecebater System Pope DUE XV-19 Loss-of-Coolant Accidents DUE Breaks Inside and Outside Resulting fran Spectrum of Containment tPWR)
Postulated Piping Breaks Within the Reactor Coolant XV-7 Reactor Coolant Pump Rotor DUE Pressure Boundary Saizure and Reactor Coolant Pump Shaft Break XV-8 Control Red Misoperation DUE (Systcm Malfunction or 2/ SER Stafff Safety Evaluation Report (Status 4a,5,6.7)
Operator Errer)
XV-9 St'. tup cr an Inactive DUE Loop or Recirculation Loop at an Incorrect Torperature, and Flow Controller Malfunction Causinc an Increase in EWR Core Flow Rate XV-10 Chemical and Volume Control DUE Systs* Malfunction that Results in a Dect case in in Boron Concentration in the Reactor Coolant (PUR)
XV-12 Spectru, of Rod Ejection DUE Accidents (PWR)
XV-14 Inadvertent Operation of DUE ECCS and Chemical and Volume Contrel System Malfunction that Increases Reactor Coolant Inventory XV-15 Inadvertent Opening of a DUE PU? Pressurizer Safety-Relief Valve or a 3WR Srfsty/ Relief Valve XV-16 Radiological Consequences NONE 07/10/81 of Failure of Small Lines Carrying Primary Coolant Cutside Containment XV-17 Steam Generator DUE Tube Failure (PWR)
(3-20)
4 YANXEE ROXE Di EE i
l SER R/
StR J/l SER R/
SAR 1/
TCPIC NO. TITLE RECEIVED COMPLETE TOPIC HO. TITLE KCCE!fLD CGarLETE 111-1 Clacsificateen of Struct-50hE IX-5 Ventilation Systems D'J h cres, Ccepenents and Sys-toms (Scismic and Quality)
II-1.A Exclusion Area Aud ority NOME and Control III-2 Mind and Tornado Loadings DUE II-1.B Pipulation Distrubutien
- 05/01,31 III-5.A Effects of Pipe Brcak on DUE Structures, Systems and II-1.C Potential Harirds or 04/07/81 Ccroononts Inside Changes in Pettntial Containment Hazards Duo is Transportati n.
III-5.B Fipe Croak Cuisida DUE Institutional Industriil, Contairxant and flilitary Facilities III-6 Soismic Design NONE II-3.C' Safety-related Waior NONE Confiderations Supply (Ultieate Heat Sink
+
(UHS)
III-7.B Design Codas. Design NONE Criteria, Load II-4.B Proximity of Canable HONE Combinations, and Reactor Tectenic Struct;res in Cavity Design Criteria Plant Vicinity V-11.B PHR Interlock Requirements NDHE II-4.D Stability of Slopes NGMC (ELEC)
II-4.E Dam Intscrity
? HONE VI-7.A.3 ECCS Actuation System 06/30/81 II-4.F Sotticment of Fcandaticnu DUE VI-10.A Testing of Reactor Trip C6/30/81 and Buriod Equip:ror.t System and Engine 2 rod Safcty reatures Including III-3.A Ef fects of Fiqh Water DUE Response Tine Testing Level on Structures VII-1.A Isaaltion of Rcactor HONE III-3.C Inscrvice Inspection of EUE Protection System fecm Water Cenical Strrctures Non-Safety Systems, Including Qualifications III-4.D Turbine Misailou (MP b-46) of Isolation Devices III-4.D Sito perwimity r.issiles 05/30<31 VII-2 Engineered Safety Features NONE (Including Aircraft) 1 (ESF' Systen Conteel Logic and Cchign III-7.D Containment Stra: Lural DUE Intacrity Testo VII-3 Systcu Required for Safe NONE (ELEC)
Shutdowa V-1 Compliance with Ccdes NONE and 58.andards (13 CFR VII-6 Frcquency Decay NONE 30.35a)(MP A-Ot,A-14)
VIII-4 Electrical Penetrations of NCHE VI-1 Grqanic flaterials and EVE Reactor Contsinment Post Accident chemistry IX-3 Station Sorvice and Cooling DDE IX-6 Firo Prchactioa(MP 3-C2)
NONE Water Systems (3-21)
YANKEE RCWE f 211 l
R11 (Cont.)
SAR J/
SER 2/
SAR 1/
SER 2/
TOPIC NO. TITLE l RECEIVED COMPLETE TOPIC NO. TITLE RECEIVED COMPLETE Il-2.C At o5pheric Transport and C6/50/81 X1-2 Radiological (Effluent Diffusion Characteristics and Process) Monitoring for Accident Analysis Systems (HRR B-67)
III-4.A Tornado Missiles DUE XV-1 Decrease in Feefwater DUE Temperature, Increase in III-4.C Internally Generated DUE Feedwater Flow, Increase Missiles in Steam Flew and Inadvertent Opening of a III-8.A Looso Parts Monitoring NONE Stean Generator Relief and Core Barrel Vibration or Safety Valve Mcnitoring(NRR B-60,C-12)
XV-2 Secetrum of Steam System 06/30/81 IV-2 Reactivity Control Systems DOE (SYS)
Piping Failures Inside Including Functional Design (DOSES) and Outside of Centainment DUE and Protection Against (PWR)
Single Failures XV-3 Loss of External Load, 06/30/81 V-7 Reactor Coolant Pump NONE Turbine Trip, Loss of Overspeed(NRR B-68)
Condenser Vacuun, Closure of Main Steam Isolation VI-2.D Mass and Energy Releaso NONE valve (BNR), and Steam for Possible Pipe Break Pressure Regulator Failure Inside Con *at.-ent (Closed)
VI-3 Centain ent *. essure and NCN; XV-4 Loss o f Non-Emergency A-C DUE Hoat Remova! (apability Power to the Station Auxiliaries VI-4 Containment 15alation NONE (SYS)
Systen XV-5 Loss of Normal Feodwater 06/30/81 Flow VI-6 Containtent Leak Testing NONE (MP A-04)
XV-6 Feodwater System Pipe DUE Breaks Inside and Outside VI-7.B ESF Switchover from NONE Containment (PWR)
($YS)
In jection to Recirculation Mode (Automatic ECCS XV-7 Reactor Coolant Pump Rotor 06/30/81 Realignnent)
Seizure and Reactor Coolant Pump Shaft Break VIII-1.A Potontial Equipment NONE Failures Associated with XV-8 Control Rod Misoperation DUE a Dcqraded Grid Voltage (Systen Malfunction or (MP B-23)
Operator Error)
IX-1 Fuel Storage DUE XV-9 Startup or an Inactivo 06/30/81 Loop or Recirculation Loop IX-4 Baron Addition System DUE at an Incorrect Temperature, and Flow XI-1 Appendix I(MP A-02)
NONE Controller Malfunction Causing an Increase in BWR Core Flow Rate (3-22)
~ -
YANKEE ROWE' Q11 (Cont.)
SAR 1/-
SER 2/
TOPIC NO. TITLE RECEIVED COMPLETE XV-10 Chemical and volume Control 06/30/81 System Malfuncticn that Results in a Decrease in the Boron Concentration in the Reactor Coolant (PWR)
XV-12 Spockrum of Rod Ejection 06/30/81 (SYS)
Accic?ents (PWR)
(DOSES)
DUE XV-14 Inadvertent Operation of C6/30/31 ECCS and Chemical and Volume Control System Mr. function that Increases Rc.ctor Coolant Inventory XV-15 Inadvertent Opening of a 06/30/81 PUR Pressurizer Safety-Related Valve or a BWR Savety/ Relief Valve XV-16 Radiological Conscquences DUE of Failure of S-all Lines Carrying Primary coolant Outside Containment XV-17 Steam Generator Tube DUE (SYS)
Failure (PWR)
(DOSES)
DUE XV-19 Loss-of-Coolant Accidents DUE (SYS)
Resulting from Spectrum of (DOSES)
Postulated Piping Breaks DUE Within the Reactor Coolant Pressure Boundary Licensee Safety Analysis Report (Status Ab) 1/ SAR :
1/ SER : Staff Safety Evaluation Report (Status 4a,5,6,7)
(3-23)
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TOPIC HO. TITLE RECEIVED COMPLETE TOPIC NO. TITLE RECEIVED COM?LETE VI-1 Organic Materials and Post DUE XI-2 Radiological (Effluent and NONE Accident Chemistry Precess) Monitoring Systems (NRR B-67)
IX-6 Fire Protection (MP B-02)
NONE XV-1 Decrease in Feedwater DUE Temperature, Increase in 211 Feedwater Flow, Increase SAR 1/
SER 2/
in Steam Ocnerator Relief TOPIC NO. TITLE RECEIVED COMPLETE or Safety Valve II-2.C At espheric Transport and DUE XV-3 Loss of External Load.
06/26/81 Diffusien Characteristics Turbine Trip, Loss of Con-fer Accident Analysis denser Vacuun. Closure of Main Steam Isolation valve III-4.A Tornado Missiles DUE (BWR). and Stam pressure Regulator Failure (Closed)
III-4.C Internally Generated DUE Missiles XV-4 Loss of Non-Emergtocy A-C 06/25/81 III-8.A Loese Parts Moniroring and NONE Power to the Station Core Barrel Vibration Auxiliaries Monitoring (NRR B-60,C-12)
XV-S Loss of Normal Feedwater DUE IV-2 Reactivity Control Systems DUE Flow Including Functional Design and Protection Against XV-7 Reactor Coolant Pump Rotor DUE Single Failures Seizure and Reactor Coolant Pump Shaft Break VI-2.D Mass and Energy kelease for NONE Possible Pipe Break Inside XV-8 Control Rod Misoperation DUE Containments (System Malfunction or Operation Error)
VI-5 Containment Pressure and NONE Heat Removal Capability XV-9 Startup or an Inactive Loop DUE or Recirculation Loop at an VI-4 Containment Isolation NONE Incorrect Temperature, and (SYS)
System Flow Controller Malfunction Causing an Increase in BWR VI-6 Containment Leak Testing Core Flow Rate (MP A-04)
XV-11 Inadvertment loading and D02 VIII-1.A A.
Potential Equipment NONE Operation of a Fuel Failures Associated with a Assembly in an Improper Degraded Grid Voltage Position (MP B-23)
XV-13 Spectrum of Rod Drop DUE IX-1 Fuel Storage DUE
($YS)
Accidents (BWR)
(DOSES)
Accidents (BWR)
XI-1 Appendix I(MP A-02)
NONE (3-25)
LACROSSE E11 (Cont.)
SAR 1/
SER 2/
TOPIC NO. TITLE RECEIVED COMPLETE XV-14 Inadvertent Operation of DUE ECCS and Chemical and Volumo Control System Malfunction that Increases Reactor Coolant Inventory XV-15 Inadvertent Opening of a 06/30/81 PWR Pressuring Safety-Relief Valve or a EWR Safety / Relief Valve XV-16 Raolological Consequences DUE of Failure of Small Lines Carrying Primary Coolant Outside Containment
.XV-18 Radiological Consequences DUE of Main Steam Line Failure Outside Containment (BWR)
XV-19 Loss-of-Coolant Accidents DUE (SYS)
Resulting from Spectrum of (DOSES)
Postulated Piping Breaks DUE Within the Reactor Coolant Pressure Boundary XV-20 Radiological Consequences DUE of Fuel Damaging Accidents (Insida and Outsido Containment) l/ StR : Licensee Safety Analysis Report (Status 4b)
Z/ SER : Staff Safety Evaluation Report (Status 4a,5,6,7) i (3-26)
gf,** 336 u.s. NuctsAa naoutAToav conomisSION Bl:LIOGRAPHIC DATA SHEET NUREG-0485 Vol. 3 No.
9 JaTLE AND SU8 TITLE LAdd Volume No.. nf eprenarr)
- 2. (Leave bimk)
Syste"iatic Evaluation Program Status Summary Report 3 RECIPIENT S ACCESSION NO.
CUTHoR ISI
- 5. D ATE REPORT COMPLE TED MONTH l YEAR August 1981 pE RFoRMING ORGANIZATION N AME AND M AILING ADDRESS Itactuor lip Codel DATE REPORT ISSUED MONTH l YE AR l Office of i4anagement and Program Analysis September 1981 l Office of Nuclear Reactor Regulation e
ft,,,, y,,.i U.S. Nuclear Regulatory Commission Washington, D.C.
20555 s (te e wea*>
. SPONSORING ORGANIZ ATION N AME AND M AILING ADDRESS (Include lea Codel 10 PROJE CT!T ASKiWORK UNIT NO Of fice of Man 6gement and Program Analysis
! Office of Nuclear Reactor Regulation M. CONTR ACT No l U.S. Nuclear Regulatory Commission Washington, D.C.
20555 TYPE OF REPORT PE AIOD COVE RE D (Inclusewe deres/
g Julv 1, 1981 tbru July 31, 1981
'. SU7PLE ME NT ARY NOTE S 14 (t c,< e os an * >
. ADSTR ACT 000 words'or rossi
! The Systematic Evaluation Program is intended to examine many 509ty related aspects
! of eleven of the older light water reactors.
This document provides the existing l status'of the review process including individual topic and overall completion status.
l t
1
. KE T WORDS AND DOCUME NT AN ALYSIS 1 74 DE SC RIPTOF S l
'O IDE NTIF 4E RS OPEN-iNDE D TE RYS
. AV AIL ABILITY ST ATE MENT 19 SE CURITY CLASS fTn,s reporo 21 NO OF PAGES Unclassified Unlimited 2a 3E CURITY CL ASS (Ters osW 22 PAICE Unclassified S
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