ML20054D285
| ML20054D285 | |
| Person / Time | |
|---|---|
| Issue date: | 04/30/1982 |
| From: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| To: | |
| References | |
| NUREG-0485, NUREG-0485-V04-N03, NUREG-485, NUREG-485-V4-N3, NUDOCS 8204220529 | |
| Download: ML20054D285 (98) | |
Text
_
~.
NUREG-0485 Vol. 4, No. 3 March 31,.1982
~
SYSTEMATIC EVALUATION PROGRAM l
STATUS
SUMMARY
REPORT f
1 UNITED STATES NUCLEAR REGULATORY COMMISSION
- o. nnq
i l
Available from NRC/GPO Sales Program Superintendent of Documents Government Printing Office Washington, D. C. 20402 A year's subscription consists of 12 issues for this publication.
Single copies of this publication are available from National Technical information Service, Springfield, V A 22161 Microfiche of single copies are wailable from NRC/GPO Sales Program Washington, D. C. 20555
NUREG-0485 Vol. 4, No. 3 March 31,1982 i
SYSTEMATIC EVALUATION PROGRAM STATUS
SUMMARY
REPORT Prepared for: 0FFICE OF NUCLEAR REACTOR REGULATION Prepared By: 0FFICE OF MANAGEMENT AND PROGRAM ANALYSIS UNITED STATES MUCLEAR REGULATORY COMMISSION fa atooq 7
i 1,
i
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Il' OL
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/
_ - e Ok 1 $L.
E William T. Russell, Chief Dennis M. Crutchfield, Chief
\\
. *,o Systematic Evaluation Program Branch Operating Reactors Branch 5 u fe Reactor Regulation Off e fNu e Re, actor Regulation ff of
l Projected dates for topic completion have been revised to reflect latest licensee commitments and new review division schedules as provided by February 22, 1982 memorandum from R. Mattson to D. Eisenhut and March 25, 1982 memorandum from R. Vollmer to D. Eisenhut.
l l
l
TABLE OF CONTENTS l
SECTION I SECTION 11 SECTION 111 l
l SEP TOPIC LIST 1-2 to 1-3 BIG ROCK POINT 2-2 to 2-5 PALISADES 3-2 to 3-3 l
DRESDEN 1 2-6 GINNA 3 4 to 3 5 DESIGN BASIS EVENT 14 DRESDEN 2 2 7 to 2-10 DRESDEN 2 3-6 to 3-9 GROUP DESCRIPTION GINNA 2-11 to 2-14 OYSTER CREEK 3-10 to 3-12 DEFINITIONS OF STATUS 1-5 HADDAM NECK 215 to 2-18 MILLSTONE 1 313 to 3-16 LACROSSE 2-19 to 2-22 SAN ONOFRE 3-17 to 3-20 SEP TOPIC
SUMMARY
1-6 MILLSTONE 1 2-23 to 2 26 BIG ROCK POINT 3-21 to 3-24 STATUS REPORT OYSTER CREEK 2-27 to 2-39 HADDAM NECK 3 25 to 3-28 PALISADES 2-31 to 2-34 PROGRESS TOWARD 17 YANKEE 3 29 to 3-32 COMPLETION (Graph)
SAN ONOFRE 2-35 to 2-38 LACROSSE 3-33 to 3-36 INTEGRATED PLANT lO SAFETY ASSESSMENT SCHEDULE SEP TOPIC STATUS BY 1-9 REVIEW DIVISION l
(Summary Table) l SEP TOPIC STATUS BY 1-10 to 1-11 I
REVIEW DIVISION l
(Graphs)
SEP TOPIC SUBMITTALS 1-12 thru 1-13 BY LICENSEES (Graphs)
Z O
O W
V)
)
1 I
l h
r
SYSTEMATIC EVALUATION PROGRAM TOPIC LIST
'~
wo int rs,
w je.2 6eactiesty Conteel System incIvetag Fie ctional a
t'.1 A. I ac toine Area A A *'n tf aad, i
631 4 r, r e,,,,.y> o g g l ei Legtp and Protection A statt Single f alle ts r
9 54.)et Pe r s Cperet tag Indications
- . t y s l at e na D i s t r i ta.t i m
,14 3 a
Co,q liance with Codes and Standards (10 Cf t c e cat iai mas eros se. maa an i e i'.t ratta' g, g,,t i n, ei n s t t,%
v.1 a
' u *a l gygg ess ert. J.e t o I r ang ort at W.
6au.
r i n in t r ' e i. aad "i t 't ary s a<. + 1 s t '"
111 4 C. I rt eraa l ty r.caer ate 1
- us t les J2 Appitcable Code Cases i f.)
R. \\evere orather Pne w e+a v.)
Overprenurt z et ton Prot ect ion a t e<) rot ot t e t =cauret nt s Pre,,,e M. uns it e c
V.4 Piping and Saf e lad letegrity C. atar>se er s t Iraan vt and Dit ta v La irac -
n t er ut ics f or A u l tr'.t Analysi g, g, g, p yg,,,, t y m i g s s teg ([ncluding Aircraf t)
V.5 Renctor Coolant Pressere Soundary (RCPS)
L eak age, Oet ett lon n St r* acto es. System et e.r rilogi( 41 at e ra he g g l.$
A. { f f ec t s of P ipe Brede r
o A,ailane lity cf w
and (og oments 1 es 'de Contat wat eb 8eactor t ene) lat egrity Lont rc ? E o'*
vdroto r t Destr yt n oe S. P ipe Breat Outstic tretatore ett W.7 hesct or C oolaat PwT O verspeed
! !,1 a
- 5. f Iw !* *g f ot e*t t al a"d P rot M t sm k e% i re -
W.9 Weactor Com 150 latten Cooling Systesi @)
aseat s 111 1 A. Inservu e Inve(t ton. including P restrene4 (n a,,s i tt y of Overat taq P lert L G t.w e Concrete Contaime nts with lither Grouted Nat (spanW Tutie f ailums
.st e pes t e En is ! loodi ng L undi t 'u'".
or ungrouted f eMons
- 8. RHG Reltabiltty a et y-re lat ed eat er WW1r (dt immte Prat
- s. Des t y Codes, Design Criterna tc.ed s
r, Cort'inat tons, and Heattor Ca vity Cestr W.Il
- 4. Requirements f or Isolet ton of f*19h and Low r m))
I
'. i ra u
Criterta Pressure System l
l
!!.a
.ci. l og aru
'.c i ssio lo gy
- t. Delaminat. ton o' Prest ressed Concrete Lon.
B. RPR I nt erlod Requi reernt s
(
t ect :.r.i c P ro v i n(*
t annes et St ructu es r
4 12 A. eater Purity of Bolling aater #eactor 4
P ros'*1 t, of Cacable T ect on i c
',t r6.tt ares o,
Lontaincent 5tructeral Intey tty f e%ts Prietary Coolant in r iant V uinit y ill.s A. & - 0%e Parts Monitoring and Core Carrel U 13, hatn Hawr
. w i o ur n a l $c i s... < i t,.ett-u neles d w i t> rat i on %n t t or i e9 P I 4..r V l.1 Organic Mai,ert els and Pnt Accidret it. Cont rol R od Ort ve Pe(hant se lategr tty t hesi s t ry st eriil e y or s im -s L. Irradi at im 0avia,Jr, be of Sens tt ired Vt.2 A. Pressure-Suppreuton Type Billt Contatnaents M aic ten steel and I at tgue l'es t st ante
' 6. Suttoms artment Analysts
- t. Lam i ct e,a s t y
,i. Core hert s aN f vel l at ege t t y C. Ice Condenser Cont ainnuent
- b. ' et t f eromt of I v441.ons a.!
ueird n
lil i#
utport i nt egr it y twiet D. Mass and Energy itelease f or Poultile Ptpe 111 16
- 4. Therms).0,erined Frat ect ion f or Mot ors of B reak i nsi de C ont ainismant C# *C'OI'd v 5 "i
!!}-1 is % f i c 4 t 64.*i of
.s t rvt t.ste %, 4. ms sw + nt % a mi i 6-*Iri i i 1 s1881 c 48"1. 4$ %I))
- 9. Peg e ly.* eel I nt ey t t y 11 3 Contat runrnt Pressure and Heat Reasies) e Capability li' e %f ari t rne h> L adifNs
\\ ItEe
'I # PN\\ O 4 U'\\E O * 'IP v 0 i '#S v i' 4 COt0i0"E*t lI' Et$00 I
! l.
- a. l 9 (re t s L.f M i qf wdrr ( e we I o*l $t W(I6efP5 e
1!!.It o g t errit i et e ir11y Vl.5 Cost >wst tDle Gas Cont rol e
A s t ru t ural en.1 Lt her. unmreene es (e.9 Vh*6 Contstownt Leak f esting II #fici n &g Qi s af r' p b e lal fil I qu ipret t
g II
l e vir onme*t al dualif ic at i v Of saf ety RelJted s
e~et g ) o f 3 4 e he of, e.tv r11r a t es s,
- en g s
i ga1g, ment psre vis e I nn er t i
,t w 4t e.t t unt ro l ", t ru.
[ v.1 L. 0; crat ion eith L t" s T han A ll l oops I n-ServlCe t9e 1-2
SYSTEMATIC EVALUATION PROGRAM TOPIC LIST TWCf fMt
%#IC 8 Y lill lC #
tI tt VI-7.A
- 1. ( CES a e-e va lu at i on to A(cond f or IMreased ggg.g IMtruments f cr mmtoring Radiation and PNest g g.g (ogs of hoestal f ee&ater f 1N t
vessel Mea.1 f e*s erat ue variables Oscing Acciorats g
ggg 2 t;pper Plenue in)*ct =
y i t-e f redency Decay C ont ai ment ( P=R )
- 3. (CCS Act.at ion 5 6t e*
Vil 1 Accett abilit y of 5= tag h*, re,i gn on t'#-4 Ev F 5eactor Coolant Pu e Rotor setze e sad s
r P lants Reactor Coolaat Puap 5'ta't Irvak
- 4. Core Sp*ay in str ie i t f ect i vees W:ll-1 A Potent t et tqwtprirnt F ai bres AsociateJ wits' EW.S Cont rol Rod # tsoperation (Systee Malfu ction n
V I 1.4 15f SwitcMuer f rom in:ert ion to Reti rculet it.
a Legra1ed Gria voltar or Operator (rror) mode ( A ut oma t ic L CC 5 h eal t gaae+t )
s111-2 Destte l eergency Prwer System - D iesel a v.9 5tartup ce as inactive Log or Rect rculat toa f CC5 Sinste F ai u re C riterioe and Require.
Generat or L 000 at an incorrect legerature, and F low V l-1.0 8
Contro11er Malfu ction Cassing an Imrease te eents f or t eo ing Out P =er t o V al ves n
i nc ludiaq Incepenoenre nf i nv erixs s on bi13-3
- s. 5t at ion Battery Cap acity test Rewecents fid Core i 1o. R at e tv-10 Chemical and Volume Control System malfunction
- 8. DC F =cr System Ba volt age Montt ort og and that Rewits in a Decrease in the Doron Comen-
- 1. Appendi s
- f lect rical Intrwt ation Annunci at ion tratico 's the Reactor Coolant (Pd) and Control (11C) Ne-reetees Vill-4 t iectrtcal Penetratices of beactor Cont aivent M1 inhM LMM de M a FM 2 Failure *iode Analysis - EG5 A s ge.e ty,e an lagroper Position 3, The ( f f ect of FmR loop llolat ion Valve 3y-12
$pectrue of Rod ( ject ton AcCtdents (Pd)
Clowre Dortag a LOi A on im Ferf ornwnce 11-2 Overhead HandItag Systems - Cranes w i-7.3 Long Teen C ool tag - Fass ive F at lores (*.&.
IV-13 Spectrue of Rod Drop Accidents (B A) f looding of Re%ndant terronents) 13-3 Station Service and Cooltng water Systems IV.14 Inadvertent Operat ton of tCC5 and Cheetcal V I-7.E
[ CCS b@ Oes t rys a nd T es t f or R ec t rcu l at ion 11-4 Boron Addition Systee y
11-5 Vent flat von System Increases Reactor Coolant Inventory V I-1.F
$,gg,, g,gg, isolation valves Power and Cont rol Accano lat or IV-15 Inadvertent Opentng of a Pd Pressertaer $afety-t s.t>
f ire Protect ton Relief Walve or a Bd $afety/1teltef Valve V !- 8 C;ntrol Roog Habitabilit y I'
Aus11tary Fee ssater Systee IV-16 RadiologtCal Consequences of FaIIWre of 58aII VI-9 Main $tese Line isolat son Seal System - Bd II-I APP'ad I Lines Carrytog Prtenary Coolant Outside Contato-aient I
(
VI-10 A. Testing cf Reactor f rtp Systea and (n9trecred 11-2 em ological (if fivent and Proc ess) ausgering gy.ly Stese Generats'e l
Saf et y Featu es inc lecing Respune fire 5 n t ees Tube I ailure (PmR) r testing a
IllI.I t onduct of Operat ions IV-18 Radiological Consequences of Mata $ team
- 5. Shared E ngi neered Saf et y I est ures, On-s it e Line f atlure Owtside Contatnment (52)
L ae r gency P ower, and service System f or Illl-7 Saf etszards/In&st rial Security Mwit ip le unit I ac t lit les IV-19 Loss-of-Coolant Accidents Resulting f rom IV-1 Decrease in f ee&st er Icag erature, IMrease in Socctrue of Postulated Peptog Breaks within Vll-1 A. Isolation of Reactor Prote(t ton S ystee f rom S ee&st er I Irme, lacrease in itese !Inw and the Reactor Coolant Pressure Boundary lion-Saf ety Systems, le luding Qualifications 194 vert ent Opening of a $t eam venerator Eclief of Isolation Devices or wif et y Val,e XV-20 Radtological Consequences of Fuel Damaging Accidents (Instde and Outside Containernt)
- 8. Trip Uncertainty and Setpoint Analysts Reutew a f-2 t c.ectrum of Steam $yst em P ep sey f ailures Imide of Operettnq Data Base IV-2 5 pent Fuel Cask Drop Acctdrnts and fist s t de of Cont ainre et (PmW )
vit 2 E ngs prered Saf ety Features (19 ) System Control IV-3 L oss of l at ernal L oad, Turt>tne Trto, loss of IV-22 Anticipate Transtents without scram t olic a nd Des i gn Condenser Vacvue, C losure of Main 5tese isola-gyq)
Multiple Tube f ailures in $ team Generators t ton Valve (BeW), and Steae Preswre Repletor bl!-3 System Required f or 54*e Shut own f ailure (*losed)
,v,24 Lo s of All A-C Pcmer Vll-a i f f ects of f ailyre t vi %9n+5af ety Related y
o th MMW g
IVI Technical 5pectf tcations system ost $ elected ingineered Saf et y Ieatures IVl!
Operational QA Program
' Topic deleted from SEP program due to duplication by Three Mile Island (TMI) NRC Action Plan Unresolved Safety issue or other SEP Topic per May 7,1981 letter from G. Lainas to all SEP Lecensees.
DESIGN BASIS EVENT REVIEWS THIS SECTION DEFINES DESIGN BASIS EVENT (DBE) REVIEWS FOR THE ELEVEN SEP FACILITIES
..a ~e m usr
..m e x. i 5,
~- m m5e
- 8.. ' :ert a c Treasiert Grown Ac c.ioet aad Treas iert Groqs, DE f ?;8 M--
?i.!
T,. _' p 's TITLt-7 Gros,; !
Be-1 Lecreaie ta femater terceratsre F L YC5 GrGas 1 8 *- 1 Decrease ia f eed=#t er terrpera%et
[B*L 3# I lacre85e la f recaster f l om 4 fn
!!-31 kvdrolcgic descr4pttee iP.L n1 laccesse in femat,c fl, ad 1 Increase in s tee = f1=
11-3.5 5 tooesag peteatiet aad pntec tica s e-1
- =c reas, 'a steer f l o=
I49 Start-- a cf trac tive looc a'id fican emieverats hapeta l t t, of ocerat *rq c or t rol ler ma f f sa ct i on plant to cow wita seuga tiesis floodsag s e-1 laadwertent ocessag of stea-c o*d i t t oa )
generater relief /sa'e!, valve It 3
!aad.erteat closure of esta stes*
1 solation valve it-31 is'ety related mater surely (.l t tma te Bed Start ; of tea:tive loo:
%et Dae )
8 t-10 Sy st e* cal f ac tica ca ss i a; GroqJ
- e-3 Loss of enteredt t oa d
' ' ~ ~
R e-3 7.ro 'ae t re p Q J %=,, s
! !-4 1 Tecteetc pmoine 8 es terea l lead Grpib fe-3 L os. G
- I-4 E Prc 5eity o' capaMe te(tor'c strw(ta esr n-3 Loss ce conceaser vac uar r
Ta otae trts R e-3 8
3.-3 Stese premre reg lator f ailw w aese pleet r
38 4 Loss 0 conde*ser e nc ing 1s 3 Stes' ;resse e regelettr f atle e led Loss of f eedwater f i ons
.1 4 C Htstert(al se'snu tty ettMa 200 miles r
r ef plaat "d-5 Lo'.s Gf f eed.a ter f l o=
E e -t Fee 3 eater systesa pir,e treat Grey. h B s-It Ess1ctoqical Co'We2 eates of a
!!-4.
Stat'111 ty ef s icMs meia 5 tear Liee f at t.re his toe (r od ' 3 E d+ 2 Steer lime reeak 1rside cortainrea; Coe t a i w at u ! EL E GI 4t 4AT !0ai Ill-4 e Tornaso ot s:11es At re0't:T :,1h
.lI 4 a T.,re$w et ssiles 36-2 5 teer l'9 treest catsue corta urwat
' ~ " - jgt 4 C f aternally generated otssiles Groady n4 Less c' A; power to stattoa site r,ecitetty esssites (sec teding as 11
- aries
! ! [.4.0 ch.D fv 4 Loss of AC po er to station ain af t)
.s a 4s t i t ar t es 6cpgj s e-7 Loss of foned coolaat f i o=
[! t.2 v ed and tornado load t ag P-iracy co e rotor seizwre GrG iJ
' 8-7 Loss cf forces coolset flo.
sv-?
m so '
P rime rs pump sPaf t break 3k-7 Pe t sa y pumc rotor seizu e r
r s o-7 Prs =4ry pvec s* af t trea6 Groqj F e'- 8 Lac Det r:11ed rod aslently eitheranal at power GrN * '
h-E wec octrc' led rod asserely.ita.
re-t Lmetec11ec rod assertly ettacra-al drawa t at power low poner start we re 9 Wocontrolled rod asserely mit e drawal 13. power start-v; I V-8 Coetrot rod e'60perat toa re-13 Spc< t rJr' cf red orcs accideats s e-B Coef e. ' rod eisoperation 8.
l:
5Lettr# of rod eJec tion accideat s Grcwp.y l E v-14 Spe(ter of loss 08 coolart accideets
~
5pectr m of loss of coolset accideats GecqM.
s o-l'+
w Group ~M 1 a
~
s u- :9 Radiological Caesequences cf f uel GrNJJJ th-E Radtological Consequences of F.et Damag'ag Acc t$erts (1ende sad ou ts ide c on trive* * )
De 4; sag Accideets (1as tde and outside coetalameet)
Grag ~1
- a -li laad.erteet cocaiag of Sw8 saf ety w%; _!)
n li lasivertent oce**ag of N reitef valve pressartzer ret tef valve rot u ss 14 Inas.ertent operatior cf (CC5 or CvC5 malf e (tioa test ca.ses er Gr_oq R1 3b 11 laseverteat leedtag and operet ton of I
w n
l a f e1 asse80 y in an imsro##r 1 acreage f a cooisat trveetory petit 1on Is pq. 3}
%ot aGilicaole to ~Es r
Grwy Ij!
401 applicable to Bn95 Gryu11 s.1' Stea- :,e,rator rat e v a s tse 1-4 e
STATUS DEFINITIONS G - Generic 4a-Draf t SE Received From Review Branch These topics are being evaluated as part of on-going N RC generic review effort. The ongoing This status is used for internal N RC tracking of generic review and the SEP topic review will be topic review progress. The status indicates that closely integrated to improve the effectiveness a draft topic safety evaluation is under mange-and efficiency of these efforts and to minimize ment review.
any impact on licensees. The status and conclu-sions of generic SEP topics will be incorporated in the final safety assessment for each plant.
4b - SAR Received from Licensee Licensee has submitted a Safety Analysis Report X - Deleted (SAR)in accordance with SEP redirection. (See Eisenhut letter to SEP owners of January 14,1981)
These topics have been verified as not applicable The SAR is under review and a Final NRC safety to the design of a specific plant or ar being evaluation (status 7) is being prepared. Draf t SE Juplicated by the N RC TM1 Action Plan, will not be issued for topics with lirensee R A R **ehmattal.
Unresolved Safety issue or another SEP Topic per the May 7,1981 letter from G. Lainas to all SEP licensees.
5 - Draf t SE Sent to Utility 0 - Topic Not Started A draf t topic safety evaluation has been formally transmitted to the licensee for their review and This status indicates that the review of the topic certification of the accuracy of the described has not started.
f acility. Licensees may comment upon NRC conclusions or propose alternatives to NRC posi-tions.
1 - Questions Received From Review Branch 6 - SE Response Received This status is used for internal NRC tracking by NRC of topic review progress. The status indicates that all information necessary to perform a The draft SE has been reviewed and licensee topic evaluation is not available and that ques-comments if any have been formally transmitted tions have been developed and sent to the SEP to the N RC.
branch.
2 - Questions Sent to
~
Utility The NRC topic evaluation has been completed and a final safety evaluation issued. A topic is completed The questions developed in the previous status in several ways: (1) The licensee has responded have been formally transmitted to the licensee that the NR C draf t safety evaluation (i.e. status 5) as a request for additional information.
is correct, or (2) the licensees comments on the NRC draf t safety evaluation (i.e. status 6) have been re-3 - Question Response viewed and if appropriate incorporated into the Received by NRC final safety evaluation, or (3) the licensee has not responded in the time requested, thus concurring The licensee has formally responded to the informa.
that the draf t safety evaluation i2 correct.
tion request issued by N RC regarding the topic.
15
SEP TOPIC STATUS
SUMMARY
REPORT *
\\
NUMBER OF QUESTIONS QUESTION DRAFT SE SAR SE
\\
\\
TOPICS TOPIC RECEIVED QUESTIONS
RESPONSE
RECEIVED RECEIVED DRAFT SE
RESPONSE
TOPIC
\\
GENERIC DELETED NOT FROM SENT TO RECEIVED FROM FROM SENI TO RECEIVED CCMPLETE N
(G)
(X)
STARTED REVIEW UTILITY BY NRC REVIEW LICENSEE UTILITY BY NRC (7)
PLANT NAME N
(0)
BRANCH (2)
(3)
BRANCH (4b)
(5)
(6)
\\
(1)
(4a)
N PALISADES 0
47 0
0 0
1 0
0 0
89 GINNA 0
45 0
0 0
0 1
0 1
10 80 DRESDEN 2 3
50 1
0 1
7 3
7 7
3 55 OYSTER CREEK 2
54 5
1 3
1 3
11 to 5
42 MILLSTONE 1 4
51 1
0 0
5 2
12 6
4 52 SAN CHOFRE 4
48 3
0 2
to 1
10 12 1
46 BIG ROCK POINT 3
53 9
0 5
7 2
9 5
2 42 HADDAM NECK 5
47 5
0 1
6 9
25 4
1 34 YANKEE ROWE 3
48 5
0 0
8 2
26 7
2 36 LACROSSE 3
54 12 0
1 6
4 22 9
0 26 DRESDEN 1 l
TOTALS THIS MONTH 27 497 41 1
13 50 28 122 61 28 502 TOTALS LAST MONTH 28 497 68 1
15 56 30 112 48 38 477 l
W NOTE: Totals do not include Dresden 1,
see page 2-6.
Also included is May 7, 1981 deletion letter to all SEP licensees, see footnote page 1-3.
1-6
SYSTEMATIC EVALUATION PROGRAM GOAL PH ASE 111/
-1/ Not including Dresden 1 Progress Toward Complet, ion ACTUAL 100 %
100
^
p 7 1-82
/
,/
90 p
1 month 3
/
75%
79%
70%
76 %
d 72%*
70 67 61%
/
p W
s'
.Note: Pnor to November 30,1981 the z
60 60 %
y weighted percent did not include
' 30-81 e
f g
generic topics in the progress s
a-je toward completion, W
e' 54%
50 f
y 50%
j 47%
2"
, ' ' f 0
44%
w 40 42%
S se 40%
p
/
36%
30
- J 30 % lestimated)
The plant topic overall completion status (percent complete) is calculated Status Weighting Factor
~
based upon the number of topic reviews to be performed (not including X
Not Ir.c' led deleted topics) and a weighted average of current topic review status.
20 The calculation is performed using the following formula:
G.0 0%
1,2,3 35%
4a,4b 80%
Percent Complete = Sum of Topics in Status x Weighting Factor of Status 5.6 90%
7 100%
10 Sum of Topics 0
10 11 12 1
2 3
4 5
6 7
8 9
10 11 12 1
2 3
4 5
6 7
8 9
FY-81 FY-82 17
JDQW ZUm a
W<m Q.
m V
H&
C Q.
W E
TC GJ H
V L z
r
3 W
>M m
E os m
W LW g
A Q-e W
W v
m CC m
CD H CC oC HM
&W La<m W
Z
<C J
Q.
OW Hh eW H
Z m
j I
i i
SEP TOPIC STATUS I
by REVIEW DIVISION'
SUMMARY
TABLE PLANT PALISADES GINNA DRESDEN OYSTER ~
MILLSTONE SAN BIG HADDAM YANKEE LACROSSE TOTAL 2
CREEK 1
ONOFRE ROCK NECK ROWE POINT (IAPM) 1/
Michaels Wang Cwalina Fell Persinko McKenna Scholl Brown Boyle Michaels NO. OF TOPICS 137 137 137 137 137 137 137 137 137 137 1370 DELETED 2/
47 45 50 54 51 48 53 47 48 54 497 APPLICABLE 90 92 87 83 86 89 84 90 89 83 873 57
/
39
/
33
/
31
/
31
/
32
/
29
/
28
/
30
/
27
/
337 /
DL
/
/
/
/
/
/
/
/
/
/
/
/ 57
/ 39
/ 36
/ 35
/ 37
/ 40
/ 38
/ 38
/ 38
/ 35
/ 393 TECHNICAL
/
/
/
/
/
/
/
/
/
/
/
17
/
20
/
10
/
8
/
12
/
5
/
4
/
8
/
8
/
4
/
96
/
REVIEW DOE
/
/
/
/
/
. / 17
/ 16
/ 20
/ 20
/ 20
/ 190
/
/
/
/
/
/
/ 17
/ 20
/ 21
/ 19
/ 20 ASSIGNMENT 1/
/
/
/
/
/
/
/
/
/
/
/
16
/
33
/
25
/
21
/
21
/
23
/
18
/
12
/
9
/
8
/
186 /
DSI
/
/
/
/
/
/
/
/
_ 31
, 28
/ 290
)
/
/
/ 16
/ 33
/ 30
/ 29
/ 29
/ 32
/ 30
/ 32
/
/
/
/
/
/
/
/
/
/
/
/
90
/
92
/
68
/
60
/
64
/
60
/
51
/
48
/
47
/
39
/
619 /
COMPLETE
/
/
/
/
/
/
/
/-
/
/
/
./ 90
/ 92
/ 87
/ 83
/ 86
/ 89
/ 84
/ 90
/ 89
/ 83
/ 873
/
/
/
/
/
/
/
/
/
/
/
TARGET DATE -
ALL TOPICS JAN 82 JAN 82 OCT 82 MAY 82 JUN 82 DEC 82 JUL 82 OCT 82 AUG 82 NOV 82 TECHNICAL REVIEWS TO DL 1/ Division of Licensing Integrated Assessment Project Manager 2/ Deleted as not applicable, or duplicated by USI, TMI Action Plan, or another topic.
A/. These schedules and assignments are consistent with NRR FY 1982-1984 Operating Plan.
1
__/
- No. Completed / Ho. Assigned 1-9 STATUS AS OF MARCH 31, 1982'
PROGRESS OF TOPlc REVIEWS DIVIS!!DI E LICDE!aC ftFICS W-TMET
"~
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. = = "
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15 --
15 --
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SEP OCT NOV DEC JAN FEB MAR APR MAY JUN JUL AUG SEP OC f/JAN IOmt 5
11 13 9
6 8
4 5
T,yt PER MONTH 4
7 9
11 7
5 Actul 337 348 361 370 376 384 388 393 y,,,
CUMULATIVE 298 305 314 325 332 337 Actual PROGRESS OF TOPIC REVIEWS DIVIS!!DI F DEDEDI8E TIFICS 250 iAfET
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- p#*
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g SE P OCT NOV DEC JAN FEU MAR APR MAY JUN JUL AUG SEP OCT/JAN IOffM Tarpt 8
13 13 23 12 8
5 20 l
Actual 0
0 3
6 7
8 l
Tarpt 96 109 122 145 157 165 170 190 Actung 72 72 75 81 88 96
PROGRESS OF TOPIC REVIEWS D!vistDN (F SYSTEMS INTEGRATI:n TCPICS 358 TARET agg -..
ACTUAL 2W --
p#
- s#
238 -
158 --
ISS --
5g SEP OCT NOV DEC JAN FEB MAR APR MAY AUG SEP JUN JUL OCT/JAN I
Target 24 26 30 22 8
3 2
2 PER MONTH Actual 14 27 28 13 17 13 197 223 253 275 283 2%
288 290 Target
~
l CUMULATIVE Actual 88 115 143 156 173 186 PROGRESS OF TOPIC REVIEWS 5
tot =. r.OuT ftFICS 15 TAAIET
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g SEP OCT NOV DEC JAN FEB MAR APR MAY JUN JUL AUG SEP OCT/JAN 883ffH Target 37 50 56 54 26 19 11 27 Actual 18 34 40 30 31 26 30 31 Target 630 680 CUMULATIVE 736 790 816 835 856 873 Actuet 458 492 532 562 593 819
LICENSEE TOPIC SUBMITTALS DIv!SICM 7 LICD614 REu!TTALS 48 TurAT E5 --
p e**
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/
25 -~
, w *"*
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AM JtJL ALG liEP OCT KN KC JAN FtB MA APR MAY Jlm JtL /DEC MENT 4 T *
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2 4
1 3
0 3
PER MOMH Actual 0
3 1
1 4
6 1
0 5
22 24 28 29 32 32 35 CUMULATIVE Actual 0
3 4
5 9
15 16 16 21 2
l.ICENSEE TOPIC SUBMITTALS D!vil!(H 7 DCIEEP!4 RIMITTALS 79 TARET m****
,e es --
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8 Jim JUL AUG SEP OCT NDY DEC JAN FG MAR APR MY JtM JUL /DEC M[NTHS Target 3
2 1
1 1
1 PER MONTH 13 Actual 1
8 1
5 7
15 5
1 Target 56 59 61 62 63 64 65 CUMULATIVE Actual 1
9 10 15 22 37 42 43 56
LICENSEE TOPIC SUBMITTALS l
O!v!$10s y sysios gMTggiAtta.
I I
SEMIi1A&.S las -
,,am= ===
IMI
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0 M
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SEP OCT NOV DEC JAN FEB swt App my M
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~
~
~
~
~
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8 3
6 3
1 o
PER MONTH Actual 1
10 3
31 3
2 7
12 y
~
~
~
~
~
76 84 87 93 96 97 97 CUMULATIVE Actual 1
11 14 45 48 50 57 69 76 N+
l LICENSEE TOPIC SUBMITTALS rotu.,noxCr RepitfALS 2N
. = = '
fAKAT p # p a """
175 --
- p e=-==
I58 ~
AC E 125 --
las --
75 ---
se -
25 --
i i
e M
M OCT PCY DEC JAN FE3 w
ApR MY JUN JtA. /DE C MONTHS
~
~
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13 9
3 7
2 4
PE R MONTH Adual 2
21 5
37 14 23 13 13 25 Tarpt
~
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154 167 176 184 ggg ig3 997 COMULATi% E Aoual 2
23 28 65 79 102 115 128 153
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f
BIG ROCK POINT FACILITY: BIG ROCK POINT 1 TCPIC NO.
REVIEW STATUS REMARKS DIV/ER LICENSEE: CONSUMERS POWER REGIDH/LOCATIDH: 4 MILES NORTH EAST OF CHARLEVOI. MICH.
hRC 09 T2700 II-t B.
DL/SEPB 7
CPCo to NRC 09/02/03 DOCKET HO.: 05000155 11-1 C.
DL/SEPB 7
NRC to CPCo 05/13/31 POWER CAPACITY: 0240(THERMAL) 067(ELECTRICAL)
II-2 A.
DSI/AEB 7
NRC to CPCo 08/03/81 OL NUMBER: DPR-6 II-2 B.
X NRC to CPCo 05/07/81 N.S.S.S.
GE.
II-2 C.
DSI/AEB 0
A/E FIRM: BECH.
II-2 D.
X NRC to CPCo 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL II-3 A.
DE/HGEB 2
HRC to CPCo 01/11/82 OPERATING REACTORS BRANCH CHIEF:
D. CRUTCHFIELD II-3 B.
DE/HGEB 2
HRC to CPCo 01/11/82 OPERATING REACTORS PROJECT MANAGER:
R.
EMCH 11-3 B.
1 DE/HGEB 2
NRC to CPCo 01/11/82
!/
IHTEGRATED ASSESSMENT PROJECT MANAGER:
P.
SCHOLL II-3 C.
DE/HGEB 2
NRC to CPCo 01/11/82 II-4 DE/GSB 7
NRC to CPCo 06/e8/01 KEY FOR STATUS CODES II-4 A.
DE/GSB 7
NRC to CPCo 06/08/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.
DE/GSB 3
CPCo to NRC 10/10/80 FROM REVIEW BRANCH X - DELETED II-4 C.
DE/GSB 7
NRC to CPCo C6/08/81 4b-SAR RECEIVED FROM 0 - TOPIC NOT LICfHSEE II-4 D.
DE/HGEB Gb CPCo to NRC 10/05/81 STARTED S - DRAFT SE SENT II-4 E.
X NRC to CPCo 11/16/79 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.
DE/HGEB 4b CPCo to NRC 10/19/81 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC III-I DL/SEPB 3 Sys)
CPCo to NRC 12/29/81 TO UTILITY DL/SEPB 7(ELEC) Part of VII-3 08/19/81 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 3
CPCo to NRC 07/09/81 RECEIVED BY NRC l
(2-2)
BIG ROCK POINT TOPIC NO.
REVIEM STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR III-5 A.
DE/SEB 3
CPCo to NRC 08/09/80 111-10 B.
X NRC to CPCo 11/16/79 III-3 B.
X NRC to CPCo 12/26/80 III-10 C.
X NRC to CPCo 11/16/79 III-3 C.
DE/AGEB Gb CPCo to NRC 12/21/81 III-11 X
NRC to CPCO 05/07/81 III-4 A.
DSI/ASB 4B CPC0 TO NRC 03/16/82 III-12 X
HRC to CPCo 05/07/81 III-4 B.
DE/MTEB 0
IV-1 A.
DL/SEPB 7
NRC to CPCo 10/08/81 III-4 C.
DSI/ASB 0
IV-2 DSI/ICSB 7
CPCo to NRC 12/22/81 III-4 D.
DE/SAB 4b CPCo to NRC 12/14/81 IV-3 X
NRC to CPCo 05/04/81 III-5 A.
DL/SEPB 0
V-1 X
NRC to CPCo 11/27/81 III-5 B.
DL/SEPB 0
V-2 X
NRC to CPCo 11/16/79 III-6 DL/SEPB 2
NRC to CPCo 01/19/82 V-3 X
NRC to CPCo 05/07/81 III-7 A.
X NRC to CPCo 05/07/81 V-4 X
NRC to CPto 05/07/81 III-7 B.
DL/SEPB 3
CPCo to NRC 07/09/81 V-5 DL/SEPB 5
NRC TO CPC0 03/19/82 III-7 C.
X HRC to CPCo 11/16/79 V-6 DL/SEPB 7
NRC to CPCo 03/05/80 III-7 D.
DE/SEB 7
NRC TO CPCO 03/17/82 V-7 X
NRC to CPCo 11/16/79 III-8 A.
DSI 5
HRC TO CPCO 03/02/82 V-8 X
NRC to CPCo 05/07/81 III-8 B.
X HRC to CPCo 09/26/80 V-9 X
NRC to CPCo 11/16/79 III-8 C.
DL/SEPB 6
CPCo to NRC 12/29/81 V-10 A.
DL/SEPB 7
NRC to CPCo 10/09/79 III-8 D.
X HRC to CPCo 05/07/81 V-10 B.
DL/SEPB 7
NRC to CPCo 05/13/81 III-9 X
NRC to CPCo 05/07/81 V-11 A.
DL/SEPB 6(Elec) CPCo io NRC 11/12/81 III-10 A.
DL/SEPS 6
CPC0 TO NRC 02/26/82 V-11 B.
DL/SEPB 7(SVs)
HRC to CPCo 05/13/81 7(Elec) HRC to CPCo 08/19/81 (2-3)
BIG ROCK POINT l
TOPIC HO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/DR V-12 A.
DL/SEPB 7
NRC to CPCo 10/09/79 VI-7 D.
DL/SEPS 7
NRC to CPCo 03/1//18 V-13 X
NRC to CPCo 05/07/81 VI-7 E.
X NRC to CPCo 05/07/81 VI-1 DE/CEB 4B CPCO TO HRC 03/16/82 VI-7 F.
X NRC to CPCo 11/16/79 VI-2 A.
X NRC to CPCo 05/07/81 VI-8 X
NRC to CPCo 05/07/81 VI-2 B.
X NRC to CPCo 05/07/81 VI-9 X
NRC to CPCo 11/16/79 VI-2 C.
X NRC to CPCo 11/16/79 VI-10 A.
DL/SEPB 0
VI-2 D.
DSI/CSB 3
CPCo to NRC 04/02/80 VI-10 B.
X HRC to CPCo 11/16/79 VI-3 DSI/CSB 3
CPCo to NRC 04/02/80 VII-1 A.
DL/SEPB 5
NRC TO CPCO 03/05/82 VI-4 DSI/ CSS 4A(SYS) 03/24/82 VII-1 B.
DL/SEPB 7
NRC to CPCo 08/17/78 DL/SEPB 7(EIec) NRC to CPCo 11/24/81 VII-2 DL/SEPB 7
NRC to CPCo 02/01/82 VI-5 X
HRC to CPCo 05/07/81 VII-3 DL/SEPB 7(Sys)
NRC to CPCo 05/13/81 VI-6 DSI/CSB G
NRC to CPCo 05/07/81 DL/SEPB 7(Elec) HRC to CPCo 08/19/81 VI-7 A.
1 X
NRC to CPCo 11/16/79 VII-4 X
NRC to CPCo 05/07/31 VI-7 A.
2.
X NRC to CPCo 05/07/81 VII-5 X
NRC to CPCo 05/07/81 VI-7 A.
3, DL/SEPB 5
HRC to CPCo 02/22/82 VII-6 DL/SEPB 7
NRC to CPCo 09/21/81 VI-7 A.
4.
DSI/RSB 7
HRC to CPCo 04/10/79 VII-7 X
HRC to CPCo 11/16/79 VI-7 B.
DSI/RSB
'(EIec)
CPCo to NRC 10/21/81 VIII-I A.
DSI/PSB G
HRC to CPCo 05/07/81 Disys)
VIII-2 DL/SEPB 7
NRC to CPCo 08/28/88 VI-7 C.
DL/SEPB 7
HRC to CPCo 08/05/81 VIII-3 A.
DL/SEPB 7
CPCo to NRC 04/22/81 VI-7 C.
1 DL/SEPB 7
HRC to CPCo 02/22/82 VIII-3 B.
DL/SEPB 7
NRC to CPCo 02/22/82 VI-7 C. 2.
DL/SEPB 7
NRC to CPCo 08/05/81 VIII-4 DL/SEPB 5
NRC TO CPCO 07/01/80 VI-7 C. 3.
X HRC to CPCo 11/16/79 i
l l
l (2-4)
BIG ROCK POINT l
TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMAPKS DiV/BR DIV/BR IX-1 DSI/ASB 0
XV-10 X
NRC to CPCo 11/16/79 IX-2 X
NRC to CPCo 05/07/81 XV-11 DSI/CPB 7
NRC to CPCo 12/02/81 IX-3 DL/SEPB Gb CPCo to NRC 12/10/81 XV-12 X
NRC to CPCo 11/16/79 IX-4 X
NRC to CPCo 11/16/79 XV-13 DSI/CPB 7(Sys)
HRC to CPCo 12/02/81 DSI/AEB 7(DOSES) HRC to CPCo 01/12/82 IX-5 DL/SEPB 0
XV-14 DSI/RSB 7
NRC to CPCo 08/18/81 IX-6 DE G
NRC to CPCo 05/07/81 XV-15 DSI/RSB 7
NRC to CPCo 08/18/81 X
X NRC to CPCo 05/07/81 XV-16 DSI/AEB 7
NRC to CPCo 12/28/81 XI-1 X
NRC to CPCo 12/04/81 XV-17 X
NRC to CPCo 11/16/79 XI-2 X
NRC to CPCo 12/04/81 XV-18 DSI/AEB Sb NRC to CPCo 07/01/81 XIII-t X
NRC to CPCo 05/07/81 XV-19 DSI/RSB 7(Sys)
NRC to CPCo 08/18/81 XIII-2 DL/SSPB 7
NRC to CPCo 03/11/81 DSI/AEB 4b(Doses)CPCo to NRC 07/01/81 XV-1 DSI/RSS 7
NRC TO CPCO 03/04/82 XV-20 DSI/AEB 7
NRC to CPCo 01/12/82 XV-2 X
NRC to CPCo 11/16/79 XV-21 X
NRC to CPCo 05/07/81 XV-3 DSI/RSB 7
HRC to CPCo 10/16/81 XV-22 X
NRC to CPCo 05/07/&t XV-4 DSI/RSB 7
NRC to CPCo 10/16/81 XV-23 X
NRC to CPCo 05/07/81 XV-5 DSI/RSB 7
NRC to CPCo 02/08/82 XV-24 X
NRC to CPCo 05/07/81 XV-6 X
NRC to CPCo 11/16/79 XVI X
NRC to CPCo 11/05/80 XV-7 DSI/RSB 7
NRC TO CPC0 03/11/82 XVII DL 7
NRC to CPeo 08/17/78 XV-8 DSI/CPB 7
NRC to CPCo 12/31/81 XV-9 DSI/RSB 4A 03/24/82 (2-5)
DRESDEN1 FACILITY: DRESDEN 1 LICENSEE: COMMONWEALTH EDISON REGION /LGCATION: 9 MILES EAST OF MORRIS, ILL.
DOCKET NO.'
05000010 POWER CAPACITY: 700(THERMAL) 200(ELECTRICAL)
GE.
A/E FIRM: BECH.
SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD OPERATING REACTORS PROJECT MANAGER: P. O'CONNOR By letter dated December 31, 1980 Commonwealth Edison indi-cated that Dresden 1 was undergoing an e< tensive modifica-tion and was not scheduled for restart until June, 1986.
Also, by letter dated April 4, 1981, in response to the NRC's January 14, 1981 letter on SEP redirsction the lican-
.see stated that the Dresden 1 SEP review is not being actively pursued, i.e. defered.
l l
(2-6) i
DRESDEN 2 FACILITY: DRESDEN 2 TOPIC NO.
REVIEW STATUS REMARKS DIV/BR LICENSEE: COMMONWEALTH EDISON II-1 A.
DE/SAB 7
NRC to CECO 10/06/81 REGION / LOCATION: 9 MILES EAST OF MORRIS, ILL.
II-t B.
DE/SAB 7
NRC to CECO 10/06/81 DOCKET NO.
05000237 II-1 C.
DE/SAB 4b CECO to NRC 12/08/81 POWER CAPACITY: 2527(THERMAL) 0794(ELECTRICAL)
II-2 A.
DSI/AEB 7
NRC to Ceco 04/24/81 OL NUMBER: DPR-19 II-2 B.
X NRC to Ceco 05/07/81 H.S.S.S.'
GE.
II-2 C.
DSI/AEB 7
NRC to CPCo 08/26/81 A/E FIRM: 58L.
II-2 D.
X NRC to Ceco 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W.
RUSSELL II-3 A.
DE/HGEB 3
Ceco to NRC 31/04/82 OPERATING REACTORS BRANCH CHIEF:
D. CRUTCHFIELD II-3 B.
DE/HGEB 3
Ceco to NRC 01/04/82 OPERATING REACTORS PROJECT MANAGER: P.
O'CONNOR II-3 B.
1.
DE/HGEB 3
CECO to NRC 01/04/82 f
INTEGRITED ASSESSMENT PROJECT MANAGER:
G. CWALINA [/h et, II-3 C.
DE/HGEB 3
Ceco to NRC 01/04/82 KEY FOR STATUS CODES II-4 DE/GSB 7
NRC to Ceco 07/09/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 A.
DE/GSB 7
HRC to Ceco 06/08/81 FROM REVIEW BRANCH X - DELFTED II-4 B.
DE/GSB 5
HRC to Ceco 07/09/81 4b-SAR RECEIVED FROM 0 - TOPIC HOT LICENSEE II-4 C.
DE/GSB 7
NRC to Ceco 06/08/81 STARTED 5 - DRAFT SE SENT II-4 D.
DE/HGEB 4b Ceco to NRC 12/08/81 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 E.
DE/HGEB 5
NRC to CECO 02/09/82 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC II-4 F.
DE/HGEB 4b CECO to NRC 12/08/81 TO UTILITY 7 - TOPIC COMPLETE III-1 DL/SEPB 5(SYS)
HRC TO CECO 03/09/82 3 - QUESTION RESPONSE DL/SEPB 7(Elec) Part of VII-3 07/07/Cl RECEIVED BY NRC III-2 DL/SEPB 4B CECO TO NRC 02/22/82 (2-7)
DRESDEN 2
TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR III-3 A.
DE/SEB 4b CECO to NRC 12/08/81 III-10 B.
X NRC to Ceco 11/16/79 III-3 8.
X NRC to Ceco
'5/16/79 III-10 C.
DL/SEPB 7
NRC to Ceco 05/22/79 III-3 C.
DE/HGEB 4B CECO TO NRC 02/16/82 III-11 X
NRC to Ceco 05/07/81 III-4 A.
DSI/ASB 4B CECO TO NRC 12/08/81 III-12 X
NRC to Ceco 05/07/81 III-4 B.
DE/MTEB 3
CECO TO NRC 02/24/82 IV-1 A.
DL/SEPB 7
HRC to Ceco 10/26/81 III-4 C.
DSI/ASB 0
IV-2 DSI/ICSB 7
Ceco to NRC 12/04/81 III-4 D.
DE/SAB 7
HRC to Ceco 02/22/82 IV-3 DE/MTEB 7
NRC to Ceco 01/22/82 III-5 A.
DL/SEPB 2
NRC to CECO 01/04/80 V-1 X
HRC to Ceco 11/27/81 III-5 B.
DL/SEPB 6
CECO to NRC 03/21/80 V-2 X
NRC to Ceco 11/16/79 III-6 DL/SEPB 6
CECO to NRC 03/13/81 V-3 X
NRC to Ceco-05/07/81 III-7 A.
X NRC to Ceco 05/07/81 V-4 X
NRC to Ceco 05/07/81 III-7 8.
DL/SEPB 3
Ceco to NRC 09/28/79 V-5 DL/SEPB 5
NRC TO CECO 02/24/82 III-7 C.
X NRC to Ceco 11/16/79 V-6 DL/SEPB 7
NRC to CECO 03/05/80 III-7 D.
DE/SEB 4A 03/30/82 V-7 X
NRC to Ceco 05/07/81 111-8 A.
DSI 7
NRC to CECO 02/26/82 V-8 X
HRC to Ceco 05/07/81 III-8 8.
X NRC to Ceco 09/11/80 V-9 X
NRC to Ceco 11/16/79 i'
III-8 C.
DL/SEPB 6
CECO to NRC 03/10/80 V-10 A.
DL/SEPB 7
NRC to Ceco 11/08/79 III-8 D.
X NRC to Ceco 05/07/81 V-10 B.
DL/SEPB 7
HRC to Ceco 04/24/81
.I III-9 X
NRC to Ceco 05/03/81 V-tt A.
DL/SEPB 7
NRC to Ceco 07/10/81 III-10 A.
DL/SEPB 7
NRC to Ceco 06/26/81 V-11 B.
DL/SEPB 7(Sys)
NRC to Ceco 04/24.'81 DL/SEPB 7(Elec) HRC to Ceco 07/10/88 (2-8) i
.=
4..-.
..m_.
_._.._.m DRESDEN 2 TOPIC NO.
REVIEW - STATUS REMARKS TOPIC N0.
REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.
DL/SEPB 7
NRC to Ceco 04/16/81 VI-7 D.
DL/SEPB 7
NRC to CECO 08/17/78 V-13 X
NRC to Ceco 05/07/88 VI-7 E.
X NRC to Ceco 05/07/81 VI-t DE/CEB 3
CECO to NRC 07/27/79 VI-7 F.
X NRC to Ceco 11/16/79 VI-2 A.
X NRC to Ceco 05/07/81 VI-8 X
NRC to Ceco 05/07/81 VI-2 B.
X NRC to Ceco 05/07/81 VI-9 X
NRC to CECO 11/16/79 VI-2 C.
X NRC to CECO 11/16/79 VI-10 A.
DL/SEPB 7
NRC to Ceco 07/03/81 1 VI-2 D.
DSI/CSB 5
HRC to Ceco 12/28/81 VI-10 B.
DL/SEPB 7(Sys)
NRC to Ceco 06/20/81 i
DL/SEPB 7(Elec) Ceco to NRC 11/03/81 l
VI-3 DSI/CSB 5
NRC to Ceco 12/28/81 VII-t A.
DL/SEPB 7
NRC to Ceco 12/24/88 VI-4 DSI/CSB 5(Sys)
NRC to Ceco 12/18/81 DL/SEPB 5(Elec) NRC to CECO 12/15/81 VII-1 B.
DL/SEPB 7
NRC to Ceco 08/t7/78 t
i VI-5 X
NRC to Ceco 05/07/81 VII-2 DL/SEPB 7
Ceco to NRC-11/03/81 i
VI-6 DSI/CSB G
NRC to Ceco 05/07/81 VII-3 DL/SEPB 7(Sys)
NRC to Ceco 04/24/81 DL/SEPB 7(Elec) NRC to Ceco 07/07/81 i
VI-7 A.
1.
X NRC to Ceco 11/16/79 VII-4 X
NRC to Ceco 05/07/81 VI-7 A. 2.
X HRC to Ceco 05/07/81 VII-5 X
NRC to Ceco 05/07/81 VI-7 A. 3.
DL/SEPB 7
CECO to NRC 11/03/81 VII-6 DL/SEPB 7
NRC to CECO 08/26/81 VI-7 A.
4 DSI/RSB 7
NRC to Ceco 02/22/82 VII-7 X
NRC to Ceco 11/16/79 VI-7 B.
X NRC to Ceco 11/16/79 VIII-1 A.
DSI/PSB G
NRC to Ceco 05/07/81 VI-7 C.
DL/SEPB 7
NRC to Ceco 03/13/81 VIII-2 DL/SEPB 7
HRC to Ceco 06/26/81 VI-7 C.
1.
DSI/PSB 7
NRC TO CECO 02/05/82 VIII-3 A.
DL/SEPB 7
NRC to Ceco 07/07/81 l
VI-7 C. 2.
DL/SEPB 7
HRC to Ceco 03/13/81 VIII-3 B.
DL/SEPB 7
NRC to Ceco 06/26/81 1
VI-7 C. 3.
X HRC to CECO 11/16/79 VIII-4 DL/SEPB 7
HRC to Ceco 11/30/81 l
l l
I (2-9) i
. ~. - - - -
DRESDEN 2 TOPIC HO.
REVIEW STATUS REMARKS TOPIC HO.
REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 4A 03/26/82 XV-10 X
NRC to Ceco 11/16/19 IX-2 X
HRC to CECO 05/07/81 XV-11 DSI/CPB 7
HRC to Ceco 02/08/82 IX-3 DL/SEPB 7
CECO to NRC 11/03/81 XV-12 X
NRC to Ceco 11/16/79 I
IX-4 X
NRC to Ceco 11/16/79 XV-13 DSI/CPB 7(Sys)
HRC to CECO 02/08/82 DSI/AEB 7(Doses) HRC to Ceco 12/28/81 IX-5 DL/SEPB 4a 01/20/82 XV-14 DSI/RSB 7
NRC to Ceco 12/15/81 IX-6 DE/CEB G
NRC to (Eco 05/07/81 XV-15 DSI/RSB 7
NRC to Ceco 01/04/82 X
X HRC to Ceco 05/07/81 XV-16 DSI/AEB 7
CECO to NRC 10/20/85 XI-1 X
NRC to Ceco 12/04/81 XV-17 X
NRC to Ceco 11/16/79 XI-2 X
NRC to Ceco 12/04/81 XV-18 DSI/AEB 7
HRC to Ceco 02/05/82 XIII-1 X
NRC to Ceco 05/07/81 XIII-2 DL/SSPB 7
NRC to Ceco 03/11/81 XV-19 DSI/RSB 7(Sys)
NRC to Ceco 12/07/81 DSI/AEB 7(DOSES) CECO to NRC 0t/05/32 XV-1 DSI/RSB 7
NRC to CECO 12/29/81 XV-20 DSI/AEB 7
NRC to Ceco 11/20/81 XV-2 X
NRC to Ceco 11/16/79 XV-21 X
HRC to CECO 05/07/81 XV-3 DSI/RSB 7
NRC to CECO 12/04/81 XV-22 X
NRC to Ceco 05/07/81 XV-4 DSI/RSB 7
HRC to CECA 12/04/81 XV-23 X
NRC to Ceco 05/07/81 XV-5 DSI/RSB 7
NRC to Ceco 12/15/81 XV-24 X
NRC to Ceco 05/07/81 XV-6 X
HRC to Ceco 11/16/79 XVI X
HRC to Ceco 11/05/80 XV-7 DSI/RSB 7
NRC to CECO 01/04/82 XVII DL 7
NRC to Ceco 11/20/79 XV-8 RSI/CPB 7
NRC to Ceco 02/08/82 XV-9 DSI/RSB 7
NRC to Ceco 12/15/81 1
(2-10)
_._m
_.m__
GINNA FACILITY: GINNA TOPIC NO.
REVIEW STATUS REMARKS DIV/BR LICENSEE: ROCHESTER GAS 8 ELECTRIC-I1-1 A.
DE/SAB 7
NRC to RGE 07/17/81 REGION /L9 CATION: 15 MILES NORTH EAST OF ROCHESTER, NY.
II-t B.
DE/SAB 7
NRC to RGE 07/21/81 DOCKET HO.: 05000244 II-t C.
DE/SAB 7
NRC to RGE 09/29/88 POWER CAPACITY: IS20(THERMAL) 0490(ELECTRICAL)
II-2 A.
DSI/AEB 7
NRC to RGE 11/03/81 OL NUMBER: DPR-18 II-2 B.
X HRC to RGE 05/07/81 H.S.S.S.: WEST.
II-2 C.
DSI/AEB 7
NRC to RGE 09/24/89 A/E FIRM: GIL.
II-2 D.
X NRC to RGE 05/07/81
]
SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W.
RUSSELL II-3 A.
DE/HGEB 6
RGE to NRC 08/18/81 OPERATING REACTORS BRANCH CHIEF:
D. CRUTCHFIELD II-3 B.
DE/HGEB 6
RGE to NRC 08/18/81 OPERATING REACTORS PROJECT MAHAGER:
J.
LYONS II-3 B.
1.
DE/HGEB 6
RGE to NRC 08/18/81 INTEGRATED ASSESSMENT PROJECT MANAGER: A. WANG [@>V II-3 C.
DE/HGEB 7
RGE to NRC 04/10/81 II-4 DE/GSB 7
NRC to RGE 07/09/81 KEY FOR STATUS CODES II-4 A.
DE/GSB 7
NRC to RGE 06/08/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.
DE/GSB 7
NRC to RGE 07/09/81 FROM REVIEW BRANCH X - DELETED II-4 C.
DE/GSB 7
HRC to RGE 06/08/81 4b-SAR RECEIVED FROM 0 - TOPIC NOT LICENSEE II-4 D.
DE/AGEB 7
NRC to RGE 02/19/82 STARTED 5 - DRAFT SE SENT II-4 E.
X NRC to RGE 11/16/79 1 - QUESTIONS RECEIVED TO UTILITY 1
FROM REVIEW BRANCH II-4 F.-
DE/HGEB 7
NRC to RGE 02/19/82 6 - SE RESPDNSE RECEIVED 2 - QUESTI0HS SENT BY HRC III-t DL/SEPB 7(Sys)
HRC to RGE 12/17/81 L
TO UTILITY DL/SEPB 7(Elec) HRC to RGE 04/02/81 7 - TOPIC COMPLETE 3 - QUESTI0H RESPONSE III-2 DL/SEPB 6
RGE to NRC 02/19/82 RECEIVED BY NRC u - DATA FOR NEXT MONTH (NOVEMBER) l T.
i i
(2-11)
GINNA TOPIC NO.
REVIEW STATUS REMARKS TDPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR III-3 A.
DE/SEB 7
HRC TO RGE 03/03/82 III-10 B.
DL/SEPB 7
NRC to RGE 06/22/88 -1 III-3 B.
X NRC to RGE 12/31/80 III-10 C.
X NRC to RGE 11/16/79 III-3 C.
DE/HGEB 5
HRC to RGE 02/22/82 III-ft X
NRC to RGE 05/07/81 III-4 A.
DSI/AEB 6
RGE to NRC 02/18/82 III-12 X
NRC to RGE 05/07/81 III-4 B.
DE/MTEB 7
NRC to RGE 02/19/82 IV-1 A.
DL/SEPB 7
NRC to RGE 05/29/79 III-4 C.
DSI/ASB 7
NRC to RGE 02/17/82 IV-2 DSI/ICSB 7
HRC to RGE 05/26/81 III-4 D.
DE/SAB 7
NRC to RGE 07/21/81 IV-3 X
HRC to RGE 05/07/81 III-5 A.
DL/SEPB 7
NRC to RGE 02/22/82 V-1 X
NRC to RGE 11/27/81 III-5 B.
DL/SEPB 7
NRC to RGE 09/04/81 V-2 X
HRC to RGE 11/16/79 III-6 DL/SEPB 7
HRC to RGE 32/17/82 V-3 X
HRC to RGE 05/07/81 III-7 A.
DL/SEPB 6
RGE to NRC 02/18/82 V-4 X
NRC to RGE 05/07/81 III-7 B.
DL/SEPB 6
RGE to NRC 02/18/82 V-5 DL/SEPB 7
HRC to RGE 02/08/82 III-7 C.
DE/SEB 7
RGE to NRC 07/07/81 V-6 DL/SEPB 7
NRC to RGE 03/05/80 III-7 D.
DE/SEB 7
NRC to RGE 05/08/80 V-7 DSI/ASB 7
NRC to RGE 02/17/82 III-8 A.
DSI 7
NRC to RGE 02/t7/82 V-8 X
NRC to RGE 05/07/81 III-8 B.
X HRC to RGE 02 12 51 V-9 X
NRC to RGE 11/16/79 III-8 C.
DL/SEPB 7
RGE to NRC 12/07/79 V-10 A.
DL/SEPB 7
NRC to RGE 02/02/79 III-8 D.
X NRC to RGE 05/07/81 V-10 B.
DL/SEPB 7
RGE to NRC 09/29/81 III-9 X
NRC to RGE 05/07/81 V-11 A.
DL/SEPB 7
NRC to RGE 11/07/81 III-10 A.
DL/SEPB 7
HRC to RGE 08/03/81 V-st B.
DL/SEPB 7(Sys)
RGE to NRC 09/29/81 DL/SEPB 7(Elec) NRC to RGE 04/24/81 (2-12)
GINNA TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.
X NRC to RGE 11/16/79 VI-7 D.
DL/SEPB 7
NRC to RGE 08/17/78 V-13 X
NRC to RGE 05/07/81 VI-7 E.
X HRC to RGE 05/07/81 VI-1 DE/CEB 7
NRC to RGE 02/19/82 VI-7 F.
DL/SEPB 7
NRC to RGE 06/24/81 VI-2 A.
X NRC to RGE 05/07/81 VI-8 X
NRC to RGE 05/07/81 VI-2 B.
X NRC to RGE 05/07/81 VI-9 X
NRC to RGE 11/16/79 VI-2 C.
X NRC to RGE 11/16/79 VI-10 A.
DL/SEPB 7
NRC to RGE 11/27/81 VI-2 D.
DSI/CSB 6
RGE to NRC 02/01/82 VI-10 B.
X NRC to RGE 11/16/79 VI-3 DSI/CSB 6
RGE to NRC 02/01/82 VII-1 A.
DL/SEPB 7
NRC to RGE 07/30/81 VI-4 DSI/CSB 6(Sys)
RGE to NRC 12/30/81 VII-1 B.
DL/SEPB 7
NRC to RGE 08/17/78 DL/SEPB 7(ELEC) NRC TO RGE 03/19/82 VII-2 DL/SEPB 7
NRC to RGE 12/28/81 VI-5 X
NRC to RGE 05/07/81 VII-3 DL/SEPB 7(Sys)
NRC to RGE 09/29/81 VI-6 DSI/CSB 7
NRC to RGE 05/06/61 DL/SEPB 7(Elec) HRC to RGE 03/25/82 VI-7 A.
1 DL/SEPB 7
NRC to RGE 02/20/81 VII-4 X
NRC to RGE 05/07/81 e
VI-7 A.
2.
DL/SEPB 7
NRC to RGE 08/17/78 VII-5 X
HRC to RGE 05/07/81 j
VI-7 A. 3.
DL/SEPB 7
NRC to GGE 11/27/81 VII-6 DL/SEPB 7
NRC to RGE 06e24/81 VI-7 A.
4.
X NRC to RGE 05/07/81 VII-7 X
NRC to RGE 11/16/79 4
VI-7 B.
DSI/RSB 7(SYS)
NRC TO RGE 03/09/82 VIII-1 A.
DSI/PSB 7
NRC to RGE 03/26/81 DL/SEB 7(Elec) NRC to RGE 09/18/81 VIII-2 DL/SEPB 7
NRC to RGE 06/24/81 VI-7 C.
DL/SEPB 7
HRC to RGE 02/20/81 VIII-3 A.
DL/SEPB 7
NRC to RGE 07/31/81 VI-7 C.
1 DL/SEPB 7
HRC to RGE 11/27/81 VIII-3 B.
DL/SEPB 7
NRC to RGE 06/09/81 VI-7 C. 2.
DL/SEPB 7
NRC to RGE 02/20/81 VIII-4 DL/SEPB 7
RGE to NRC 10/08/81 VI-7 C.
3.
X NRC to RGE 11/16/79 i
I (2-13)
+--
GINNA TCPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 7
NRC to RGE 11/24/81 XV-10 DSI/RSB 7
NRC to RGE 09/04/81 IX-2 X
HRC to RGE 05/07/81 XV-1t X
HRC to RGE 10/01/80 IX-3 DL/SEPB 7
NRC to RGE 11/03/81 XV-12 Eil/CFB 7(Sys)
NRC to RGE 09/04/81 DEI /tEB 7(DOSES) NRC TO RGE 03/03/82 IX-4 DSI/RSB 7
HRC to RGE 08/26/81 XV-13 X
NRC to RGE 11/16/79 IX-5 DL/SEPB 7
RGE to NRC 03/29/82 XV-14 DSI/RSB 7
NRC to RGE 09/04/81 IX-6 4a 02/24/82 XV-15 DSI/RSB 7
HRC to RGE 09/04/81 X
X NRC to RGE 05/07/81 XV-16 DSI/AEB 7
NRC TO RGE 03/05/82 XI-1 X
NRC to RGE 12/04/81 XV-17 DSI/RSB 7(Sys)
HRC to RGE 09/04/81 XI-2 X
HRC to RGE 12/04/81 DSI/AEB 7(DOSES) NRC TO RGE 03/03/82 XIII-1 X
HRC to RGE 05/07/81 XV-18 X
NRC to RGE 03/11/80 XIII-2 DL/SEPB 7
HRC to RGE 03/26/81 XV-19 DSI/RSB 7(Sys)
NRC to RGE 10/02/81 DSI/AEB 7(DOSES) RGE TO NRC 03/C9/82 XV-1 DSI/R$B 7
NRC to RGE 09/04/81 XV-20 DSI/AEB 7
NRC TO RGE 03/03/82 XV-2 DSI/RSB 7(Sys)
HRC to RGE 09/04/81 DSI/AEB 7(DOSES) HRC TO RGE 03/03/82 XV-21 X
HRC to RGE 05/07/81 XV-3 DSI/RSB 7
NRC to RGE 09/04/81 XV-22 X
NRC to RGE 05/07/81 XV-4 DSI/R$B 7
HRC to RGE 09/04/81 XV-23 X
HRC to RGE 05/07/81 XV-5 DSI/RSB 7
HRC to RGE 09/04/81 XV-24 X
NRC to RGE 05/07/81 XV-6 DSI/RSB 7
NRC to RGE 09/04/81 XVI X
NRC to RGE 11/05/80 XV-7 DSI/RSB 7
NRC to RGE 09/04/81 XVII DL 7
NRC to RGE 03/17/78 l
XV-8 DSI/CPB 7
NRC to RGE 09/04/81 XV-9 DSI/RSB 7
RGE to NRC 10/16/81 (2-14)
HADDAM NECK FACILITY: HADDAM NECK TOPIC NO.
REVIEW STATUS REMARKS DIV/BR LICENSEE: CONNECTICUT YANKEE ATOMIC PCWER 11-1 A.
DE/SAB 4A 03/29/82 REGION / LOCATION: 13 MILES EAST OF MERIDEN, CT.
II-1 B.
DE/SAB 4A 03/29/82 DOCKET NO: 05000213 II-1 C.
DE/SAB 4A 03/29/82 POWER CAPACITY: 1825(THERMAL) 0575(ELECTRICAL)
II-2 A.
DSI/AEB 7
CYAPCo to NRC 01/22/81 OL NUMBER: DPR-61 II-2 B.
X HRC to CYAPCo 05/07/81 N.S.S.S.*
WEST.
II-2 C.
DSI/AEB 7
CYAPCo to NRC 02/16/79 A/E FIRM: S&W II-2 D.
X HRC to CYAPCo 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL II-3 A.
DE/HGEB 4b CYAPCo to NRC 12/14/81 OPERATING REACTORS BRANCH CHIEF:
D.
CRUTCHFIELD II-3 B.
DE/HGEB 4b CYAPCo to NRC 12/14/81 OPERATING REACTORS PROJECT MANAGER: C.
TROPF II-3 B.
1 DE/HGEB Gb CYAPCo to NRC 12/i4/81 INTEGRATED ASSESSMENT PROJECT MANAGER: S.
BROWN II-3 C.
DE/NGES 4b CYAPCo to NRC 12/14/81 II-4 DE/GSB 7
NRC to CYAPCo 06/08/81 KEY FOR STATUS CODES II-4 A.
DE/GSB 7
NRC to CYAPCo 06/08/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.
DE/GSB 3
HUREG/CR1582 08/04/80 FROM REVIEW BRANCH X - DELETED II-4 C.
DE/GSB 7
HRC to CYAPCo 06/08/81 4b-SAR RECEIVED FROM 0 - TOPIC HOT LICENSEE II-4 D.
DE/HGEB 4b CYAPCo to NRC 08/31/81 STARTED 5 - DRAFT SE SENT II-4 E.
X NRC to CYAPCo 04/16/79 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.
DE/HGEB 4b CYAPCo to NRC 12/18/81 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY HRC III-1 DL/SEPB 2(Sys)
HRC to CYAPCo 11/20/81 TO UTILITY DL/SEPB 7(Elec) Part of VII-3 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 4b CYAPCo to NRC 12/14/81 RECEIVED BY HRC (2-15)
lilAl[)l]LftfWI FIEi(:l(
TOPIC HO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR 111-3 A.
DE/SEB 4b CYAPCo to NRC 08/31/81 111-10 B.
DL/SEPB 7
NRC 10 CYAPCO 03/36/82 III-3 B.
DE/HGEB 0
III-10 C.
X HRC to CYAPCo 04/16/79 III-3 C.
DE/HGEB Gb CYAPCo to NRC 08/31/81 III-11 X
HRC to CYAPCo 05/07/81 III-4 A.
DSI/ASB 4a 12/28/81 III-12 X
HRC to CYAPCo 05/07/81 III-4 B.
DE/MTEB G
NRC to CYAPCo 05/07/81 IV-1 A.
DL/SEPB 7
CYAPCo to NRC 06/25/79 III-4 C.
DSI/ASB Eb CYAPCo to NRC 02/12/82 IV-2 DSI/ICSB 7
HRC to CYAPCo 02/22/82 III-4 D.
DE/SAB 4A 03/29/82 IV-3 X
NRC to CYAPCo 05/07/81 III-5 A.
DL/SEPB 3
CYAPCo to NRC 02/07/80 V-1 X
NRC to CYAPCo 11/27/81 III-5 B.
DL/SEPB 4b CYAPCo to NRC 10/02/81 V-2 X
NRC to CYAPCo 04/16/79 III-6 DL/SEPB 3
CYAPCo to NRC 06/11/81 V-3 X
NRC to CYAPCo 05/07/81 III-7 A.
X HRC to CYAPCo 05/07/81 V-4 X
NRC to CYAPCo 05/07/81 III-7 B.
DL/SEPB 3
CYAPCo to NRC 09/07/79 V-5 DL/SEPB 7
NRC to CYAPCo 02/22/82 III-7 C.
X HRC to CYAPCo 04/16/79 V-6 bl/SEPB 7
NRC to CYAPCo 03/05/80 III-7 D.
DE/SEB 7
NRC to CYAPCo 10/16/81 V-7 DSI/ASB 4a 11/05/81 III-8 A.
DSI 4a 02/09/82 V-8 X
NRC to CYAPCo 05/07/81 III-8 B.
X HRC to CYA PCo 10/01/80 V-9 X
NRC to CYAPCo 11/16/79 III-8 C.
DL/SEPB 7
HRC to CYA.PCo 01/29/82 V-10 A.
DL/SEPB 7
NRC to CYAPCo 01/13/81 III-8 D.
X NRC to CYtPCo 05/07/81 V-10 B.
DL/SEPB 7
NRC to CYAPCo 12/28/81 III-9 X
HRC to CYAPCo 05/07/81 V-11 A.
DL/SEPB 7
NRC to CYAPCo 11/03/31 III-10 A.
DL/SEPB 7
CYAPCo to NRC 09/21/81 V-11 B.
DL/SEPB 7(Sys)
NRC to CYAPCo 12/28/81 DL/SEPB 7(Elec) HRC TO CYAPCO 03/03/82 l
l (2-16)
HADDAM NECK TCPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.
X NRC to CYAPCo 11/16/79 VI-7 D.
DL/SEPB 7
NRC to CYAPCo 08/87/78 V-13 X
NRC to CYAPCo 05/07/81 VI-7 E.
X NRC to CYAPCo 05/07/81 VI-1 DE/CEB 4b CYAPCO to NRC 02/09/82 VI-7 F.
X NRC to CYAPCo 04/l6/79 VI-2 A.
X NRC to CYAPCo 05/07/81 VI-8 X
NRC to CYAPCo 05/07/81 VI-2 B.
X NRC to CYAPCo 05/07/81 VI-9 X
HRC to CYAPCo 11/16/79 VI-2 C.
X NRC to CYAPCo 04/16/79 VI-10 A.
DL/SEPB 0
VI-2 D.
DSI/CSB 3
CYAPCo to NRC 04/27/81 VI-10 B.
X NRC to CYAPCo 04/16/79 VI-3 DSI/CSB 3
CYAPCo to NRC 04/27/81 VII-1 A.
DL/SEPB 5
NRC TO CYAPCO 03/05/82 VI-4 DSI/CSB 0(Sys)
VII-t B.
DL/SEPB 7
NRC to CYAPCo 08/17/78 DL/ SEPP 7(Elec) NRC to CYAPCo 09/21/81 VII-2 DL/SEPB 5
NRC TO CYAPCO 03/05/82 VI-5 X
HRC to CYAPCo 05/07/81 VII-3 DL/SEPB 7(Sys)
HRC to CYAPCo 12/28/81 VI-6 DSI/CSB G
NRC to CYAPCo 05/07/81 DL/SEPB 7(Elec) NRC to CYAPCo 08/28/81 VI-7 A.
1.
DL/SEPB 7
NRC to CYAPCo 02/20/81 VII-4 X
NRC to CYAPCo 05/07/81 VI-7 A.
2.
X NRC to CYAPCo 05/07/81 VII-5 X
NRC to CYAPCo 05/07/81 VI-7 A.
3.
DL/SEPB 5
NRC to CYAPCo 02/11/82 VII-6 DL/SEPB 7
NRC to CYAPCo 08/28/81 VI-7 A.
4.
X NRC to CYAPCo 05/07/81 VII-7 X
NRC to CYAPCo 04/16/79 VI-7 B.
DSI/RSB 0(Sys)
VIII-I A.
DSI/PSB G
NRC to CYAPCo 05/07/81 DL/SEPB 7(Elec) HRC to CYAPCo 05/21/88 VIII-2 DL/SEPB 7
NRC to CYAPCo 08/2A/81 VI-7 C.
DL/SEPB 7
NRC to CYAPCo 03/13/81 VIII-3 A.
DL/SEPB 7
CYAPCo to NRC 02/16/79 VI-7 C.
1 DL/SEPB 7
CYPACO to NRC 01/11/82 VIII-3 B.
DL/SEPB 7
NRC to CYAPCo 08/28/81 VI-7 C.
2.
DL/SEPB 7
HRC to CYAPCo 03/13/81 VIII-4 DL/SEPB 5
NRC to CYAPCo 12/23/81 VI-7 C.
3.
DL/SEPB 7
CYAPCo to NRC 02/12/82 (2-17)
HADDAM NECK L
TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 7
hRC TO CYAPCO 03/01/82 XV-10 DSI/RSB 4A 03/29/82 IX-2 X
HRC to CYAPCo 05/07/81 XV-11 X
NRC to CYAPCo 10/01/80 IX-3 DL/SEPB 4b CYAPCo to NRC 12/14/81 XV-12 DSI/CPB 7(SYS)
HRC 10 CYAPCO 03/23/82 DSI/RSB 4b(Dosos)CYAPCo to NRC 09/30/81 IX-4 DSI/RSB 4b CYAPCo to NRC 10/02/81 XV-13 X
NRC to CYAPCo 11/16/79 IX-5 DL/SEPB Gb CYAPCo to NRC 12/14/81 XV-14 DSI/RSB 4b CYAPCo to HRC 09/30/81 IX-6 DE G
HRC to CYAPCo 05/07/81 XV-15 DSI/RSB 4b CYAPCo to HRC 09/30/81 X
X NRC to CYAPCo 05/07/81 XV-16 DSI/AEB 6
CYAPCo to NRC 09/28/81 XI-1 X
HRC to CYAPCo 12/04/81 XV-17 DSI/RSB 0(Sys)
XI-2 X
HRC to CYAPCo 12/04/81 DSI/AEB 0(Doses)
XIII-1 X
HRC to CYAPCo 05/07/81 XV-18 HRC to CYAPCo 10/01/80 XIII-2 DL/SSPB G
HRC to CYAPCo 05/07/81 XV-19 DSI/RSB 7(Sys)
NRC to CYAPCo 12/02/81 DSI/AEB 4b(Doses)CYAPCo to HRC 09/30/81 XV-1 DSI/RSB 4b CYAPCo to NRC 09/30/81 XV-20 DL/SEPB 7
HRC to CYAPCo 06/09/81 XV-2 DSI/R$B Gb(Sys) CYAPCo to HRC 09/30/81 DSI/AEB Ab(Doses)CYAPCo to NRC 09/30/81 XV-21 X
HRC to CYAPCo 05/07/81 XV-3 DSI/RSB 4A 33/09/82 XV-22 X
HRC to CYAPCo 05/07/81 XV"4 DSI/R$B 7
NRC to CYAPCo 12/17/81 XV-23 X
HRC to CYAPCo 05/07/81 XV-5 DSI/RSB Gb CYAPCo to NRC 09/30/81 XV-24 X
HRC to CYAPCo 05/07/81 XV-6 DSI/RSB 4b CYAPCo to HRC 09/30/81 XVI X
NRC to CYAPCo 11/05/80 XV DSI/RSB 4b CYAPCo to HRC 03/01/82 XVII DL 7
NRC to CYAPCo 08/17/78 XV-8 DSI/CPB 7
HRC TO CYAPCO 03/25/82 XV-9 DSI/RSB 4B CYAPCO TO HRC 09/30/81 (2-18)
LACROSSE FACILITY: LACROSSE TOPIC NO.
REVIEW STATUS REMARKS DIV/BR LICENSEE: DAIRLAND POWER II-1 A.
DE/SAB 4b DPC to NRC 06/23/81 REGION / LOCATION: 19 MILES SOUTH OF LACROSSE, WISC.
II-1 B.
DE/SAB 4b DPC to NRC 06/16/81 DOCKET NO.
05000409 II-1 C.
DE/SAB 4b DPC to NRC 07/15/81 POWER CAPACITY: 0165(THERMAL) 0050(ELECTRICAL)
II-2 A.
DSI/AEB 5
NRC to DPC 12/15/80 OL NUMBER: DPR-45 II-2 B.
X NRC to DPC 05/07/81 N.S.S.S.
AC.
II-2 C.
DSI/AEB 0
A/E FIRM: S&L 11-2 D.
X NRC to DPC 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL II-3 A.
DE/HGEB 4b DPC to NRC 06/16/81 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD II-3 B.
DE/HGEB 2
NRC to DPC 07/1,0/81 OPERATING REACTORS PROJECT MANAGER:
D. DUDLEY II-3 B.
1.
DE/HGEB 0
INTEGRATED ASSESSMENT PROJECT MANAGER: K. HERRING )
II-3 C.
DE/HGEB Gb DPC to NRC 06/26/81 II-4 DE/GSB 7
NRC to DPC 06/08/81 KEY FOR STATUS CODES II-4 A.
DE/GSB 7
HRC to DPC 06/08/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.
DE/GSB 3
DPC to NRC 07/11/79 FROM REVIEW BRANCH X - DELETED II-4 C.
DE/GSB 7
HRC to DPC 06/08/81 4b-SAR RECEIVED # ROM 0 - TOPIC NOT LICENSEE II-4 D.
DE/HGEB 0
STARTED 5 - DRAFT SE SENT II-4 E.
DE/HGEB 0
1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.
DE/HGEB 4B DPC TO NRC 03/09/82 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC III-1 DL/SEPB 3(Sys)
DPC to NRC 08/06/81 TO UTILITY DL/SEPB
$(ELEC) HRC TO DPC 03/09/82 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 4b DPC to NRC 03/05/82 RECEIVED BY NRC (2-19)
LACROSSE TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/ER DIV/BR III-3 A.
DE/SEB 4B DPC TO NRC 03/09/82 III-10 B.
X hRC to DPC 10/29/79 III-3 B.
X NRC to DPC 03/10/81 III-10 C.
X NRC to DPC 10/29/79 III-3 C.
DE/HGEB 4B DPC TO NRC 01/29/82 III-11 X
HRC to DPC 05/07/81 III-4 A.
DSI/ASB 0
III-12 X
NRC to DPC 05/07/81 III-4 B.
DE/MTEB 4B DPC TO NRC 03/05/82 IV-1 A.
DL/SEPB 7
NRC to DPC 04/19/79 III-4 C.
DSI/ASB 4B DPC TO NRC 03/05/82 IV-2 DSI/ICSB 7
NRC TO DPC 03/25/82 III-4 D.
DE/SAB Ab DPC to NRC 09/15/81 IV-3 X
NRC to DPC 05/07/81 III-5 A.
DL/SEPB 0
V-1 X
NRC to DPC 11/27/81 III-5 B.
DL/SEPB Gb DPC to NRC 06/29/81 V-2 X
HRC to DPC 10/29/79 III-6 DL/SEPB 3
DPC to NRC 06/12/81 V-3 X
NRC to DPC 05/07/81 III-7 A.
X NRC to DPC 05/07/81 V-4 X
NRC to DPC 05/07/81 III-7 B.
DL/SEPB 0
V-5 DL/SEPB 5
NRC TO DPC 03/17/82 III-7 C.
X NRC to DPC 10/29/79 V-6 DL/SEPB 7
NRC to DPC 03/05/80 III-7 D.
DE/SEB 4A 03/30/82 V-7 X
NRC to DPC 05/07/81 III-8 A.
DSI 5
NRC TO DPC 02/22/82 V-8 X
NRC to DPC 05'07/81 III-8 B.
X NRC to DPC 09/26/80 V-9 X
HRC to DPC 10/29/79 III-8 C.
DL/SEPB 7
DPC to NRC 03/03/81 V-10 A.
DL/SEPB 7
NRC to DPC 01/07/80 III-8 D.
X NRC to DPC 05/07/81 V-10 B.
DL/SEPB 5
HRC to DPC 12/22/80 III-9 X
NRC to DPC 05/07/81 V-11 A.
DL/SEPB 7
NRC to DPC 02/22/82 III-10 A.
DL/SEPB 7
NRC to DPC 09/22/81 V-11 B.
DL/SEPB 5(Sys)
HRC to DPC 12/22/80 DL/SEPB 7(ELEC) HRC TO DPC 03/04/82 (2-20)
LACROSSE TOPIC ND.
REVIEW STATUS REMARKS TDPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.
DL/SEPB 7
NRC to DPC 04/30/79 VI-7 D.
DL/SEPB 7
hkC to DPC 08/11/78 V-13 X
NRC to DPC 05/07/81 VI-7 E.
X HEC to DPC 05/07/81 VI-1 DE/CEB 48 DPC to NRC 02/19/82 VI-7 F.
X NRC to DPC 10/29/79 VI-2 A.
X NRC to DPC 05/07/81 VI-8 X
NRC to DPC 05/07/81 VI-2 B.
X HRC 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 Ga 02/16/82 VI-2 D.
DSI/CSB 3
DPC to NRC 04/26/79 VI-10 B.
X NRC to DPC 10/29/79 VI-3 DSI/CSB 3
DPC to NRC 04/26/79 VII-1 A.
DL/SEPB 5
NRC TO DPC 03/09/82 J VI-4 DSI/CSB 3(Sys)
CPC to NRC 08/17/81 VII-1 B.
DL/SEPB 7
NRC to DPC C8/17/78 DL/SEPB 7(Elec) HRC to DPC 01/05/82 VII-2 DL/SEPB 5
NT ? to DPC 05/07/81 VII-3 DL/SEPB 5(Sys)
NRC to DPC 12/22/80 VI-6 DSI/CSB C
NRC to DPC 05/07/81 DL/SEPB 5(ELEC) NRC TO DPC 03/09/82 VI-7 A.
1.
X NRC to DPC 10/29/79 VII-4 X
NRC to DPC 05/07/81 VI-7 A.
2.
X NRC to DPC 05/07/81 VII-5 X
NRC to DPC 05/07/81 VI-7 A.
3.
DL/SEPB 5
NRC to DPC 02/17/82 VII-6 DL/SEPB 7
NRC to DPC 09/21/81 VI-7 A.
4.
X HRC to DPC 05/07/81 VII-7 X
NRC to DPC 10/29/79 VI-7 B.
X HRC to DPC 10/29/79 VIII-1 A.
dst /PSB G
HRC to DPC 05/07/81 VI-7 C.
DL/SEPB 7
NRC to DPC 03/13/81 VIII-2 DL/SEPB 7
HRC to DPC 12/18/81 VI-7 C.
1 DL/SEPB 7
HRC to DPC 09/21/81 VIII-3 A.
DL/SEPB 7
NRC to DPC 06/05/79 VI-7 C. 2.
DL/3EPB 7
NRC to DPC 03/13/81 VIII-5 B.
DL/SEPB 7
NRC to DFC 08/28/81 VI-7 C.
3.
X NRC to DPC 10/29/79 VIII-4 DL/SEPB 7
NRC to DPC 09/09/81 (2-21)
LACROSSE TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 0
XV-10 x
NRC to OPC 10/29/1 I IX-2 X
NRC to DPC 05/07/81 XV-11 DSI/CPB 4A 03/26/82 IX-3 DL/SEPB 4B DPC TO HRC 03/05/82 XV-12 X
HRC to DPC 10/29/79 IX-4 X
HRC to DPC 10/29/79 XV-13 DSI/CPB 0(Doses)
DSI/AEB 4A(SYS) 03/25/82 IX-5 DL/SEPB 4B DPC TO NRC 03/15/82 XV-14 DSI/RSB 4b DPC to NRC 08/25/81 IX-6 DE G
HRC to DPC 05/07/81 XV-15 DSI/RSB 7
NRC to DPC 09/21/81 X
X NRC to DPC 05/07/81 XV-16 DSI/AEB 4B DPC TO NRC 03/09/82 XI-1 X
HRC to DPC 12/04/81 XV-17 X
HRC to DPC 10/29/79 XI-2 X
NRC to DPC 12/04/81 XV-18 DSI/AEB 0
XIII-1 X
NRC to DPC 05/07/81 XV-19 DSI/AEB 0(Doses)
XIII-2 DL/SSPB 7
HRC to DPC 03/11/81 DSI/RSB 0(Sys)
XV-1 DSI/RSB 4B DPC TO NRC 03/05/82 XV-20 DSI/AEB 0
XV-2 X
NRC to DPC 10/29/79 XV-21 X
NRC to DPC 05/07/81 XV-3 DSI/R$B 7
NRC to DPC 11/13/81 XV-22 X
NRC to DPC 05/07/81 XV-4 DSI/RSB 7
NRC to DPC 11/03/81 XV-23 X
NRC to DPC 05/07/81 XV-5 DSI/RSB 4B DPC TO HRC 03/05/82 XV-24 X
HRC to DPC 05/07/31 XV-6 X
NRC to DPC 10/29/79 XVI X
NRC to DPC 11/05/80 XV-7 DSI/R$8 4B DPC TO NRC 03/11/82 XVII DL 7
NRC to DPC 08/I7/78 XV-8 DSI/CPB 4A 03/25/82 XV-9 DSI/RSB Gb DPC to NRC 08/25/81 (2-22) l
MILLSTONE 1 FACILITY: MILLSTONE 1 TOPIC NO.
REVIEW STATUS REMARKS DIV/BR LICENSEE: HORTHEAST NUCLEAR ENERGY II-s A.
DE/SAB 7
NRC to NU 07/31/88 REGION /LOCATIGH: 5 MILES SOUTH WEST OF HEW LONDON, CONN.
II-1 B.
DE/SAB 7
NRC to NU 11/27/81 DOCKET NO.
05000245 II-t C.
DE/SAB 7
NRC to NU 11/27/81 POWER CAPACITY: 2011(THERMAL) 0660(ELECTRICAL)
II-2 A.
DSI/AEB 7
NRC to HU 03/30/81 OL NUMBER: DPR-21 II-2 B.
X NRC to NU 05/07/81 N.S.S.S.
GE.
II-2 C.
DSI/AEB 7
NRC to NU 12/23/81 A/E FIRM: EBASCO II-2 D.
X HRC to HU 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL II-3 A.
DE/HGEB 4b HU to NRC 06/25/81 OPERATING REACTORS BRANCH CHIEF:
D.
CRUTCHFIELD II-3 B.
DE/HGEB 4b HU to NRC 06/26/81 OPERATING REACTORS PROJECT MANAGER:
J.
SHEA II-3 B.
1 DE/HGEB 4b NU to HRC 06/25/81 II-3 C.
DE/HGEB 4b HU to NRC 04/28/81 INTEGRATED ASSESSMENT PROJECT MANAGER: D.PERSINK0][
II-4 DE/GSB 7
NRC to NU 06/08/81 KEY FOR STATUS CODES II-4 A.
DE/GSB 7
NRC to NU 06/08/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.
DE/GSB 5
HRC to NU 01/07/82 FROM REVIEW BRANCH X - DELETED II-4 C.
DE/GSB 7
NRC to NU 06/08/81 4b-SAR RECEIVED FROM 0 - TOPIC NOT LICENSEE II-4 D.
DE/HGEB 4b HU to NRC 08/31/81 STARTED 5 - DRAFT SE SENT II-4 E.
X HRC to NU 11/16/79 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.
DE/HGEB 4b NU to NRC 04/28/81 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC III-1 DL/SEPB 5(Elec) HRC TO NU 02/01/82 TO UTILITY DL/SEPB 4a(Sys) 01/29/82 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 3
HU to NRC 08/29/79 RECEIVED BY HRC (2-23)
- _. _. - _.. ~..-
. _ _ =.
l MILLSTONE 1 TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR l
I 111-3 A.
DE/SEB 5
NRC to NU 05/11/81 111-10 B.
X NRC to NU 11/16/79 i
III-3 B.
X HRC to NU 12/26/80 III-10 C.
DL/SEPB 7
NU to NRC 08/29/79 III-3 C.
DE/HGEB Gb NU to NRC 08/31/81 III-11 X
HRC to NU 05/07/81 III-4 A.
DSI/ASB Ab NU to NRC 08/31/81 III-12 X
NRC to NU 05/07/81 III-4 B.
DE/MTEB 4b HU to NRC 08/31/81 IV-1 A.
DL/SEPB 7
NU to NRC 02/12/79 III-4 C.
DSI/ASB 3
NU to NRC 12/05/80 IV-2 DSI/ICSB-46 NU to NRC 10/28/81 III-4 D.
DE/SAB 7
NRC to NU 11/27/81 IV-3 DL 7
HRC to NU 02/22/82 i
III-5 A.
DL/SEPB 0
V-1 X
HRC to NU 11/27/81 III-5 B.
DL/SEPB 4A 02/09/82 V-2 X
NRC to NU 11/16/79 III-6 DL/SEPB 5
NRC to NU 05/28/81 V-3 X
NRC to NU 05/07/81 III-7 A.
X NRC to NU
.05/07/81 V-4 X
NRC to NU 05/07/81 III-7 B.
DL/SEPB 3
HU to NRC 08/29/79 V-5 DL/SEPB 7
NRC to NU 08/28/81 III-7 C.
X NRC to NU 11/16/79 V-6 DL/SEPB 7
NRC to NU 03/05/80 III-7 D.
DE/SEB 7
HU to NRC 02/17/81 V-7 X
NRC to NU 05/07/81 III-8 A.
DSI 7
NRC TO NU 03/03/82 V-8 X
NRC to NU 05/07/81 III-8 8.
X NRC to NU 09/26/80 V-9 X
NRC to NU 11/16/79 III-8 C.
DL/SEPB 6
HU to NRC 01/31/80 V-10 A.
DL/SEPB 7
NU to NRC 03/05/79 I III-8 D.
X NRC to NU 05/07/81 V-10 B.
DL/SEPB 7
NU to NRC 07/22/81 III-9 X
NRC to NU 05/07/81 V-11 A.
DL/SEPB 7
HRC to NU 07/08/81 I
III-10 A.
DL/SEPB 7
NRC to NU 02/26/82 V-11 B.
DL/SEPB 7(Sys)
HU to NRC 07/22/81 DL/SEPB 5(Elec) HRC to NU 02/01/82 l
l l
l (2-24) r4, r
MILLSTONE 1 TOPIC NO.
REVIEW STATUS REMARKS TOPIC HO.
REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.
DL/SEPB 7
NRC to NU 12/17/79 VI-7 D.
DL/SEPB 7
NRC to NU 08/17/78 V-13 X
NRC to NU 05/07/81 VI-7 E.
X NRC to NU 05/07/81 VI-1 DE/CEB 7
HRC to NU 02/26/82 VI-7 F.
X NRC to NU 11/16/79 VI-2 A.
X NRC to NU 05/07/81 VI-8 X
NRC
+.o NU 05/07/81 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-10 A.
DL/SEPB 7
NRC to NU 10/08/81 VI-2 D.
DSI/CSB 3
NU to NRC 06/09/81 VI-10 B.
DL/SEPB 7
NU to NRC 08/05/81 VI-3 DSI/CSB 3
HU to NRC 06/09/81 VII-1 A.
DL/SEPB 7
NRC to NU 07/23/81 VI-4 DSI/CSB 5(Sys)
HRC to NU 12/09/81 DL/SEPB 6(Elec) HU to NRC 08/12/31 VII-1 B.
DL/SEPB 7
NRC to NU 08/17/18 VI-5 X
NRC to NU 05/07/81 VII-2 DL/SEPB 7
NRC to NU 02/01/82 bl-6 DSI/CSB G
NRC to NU 05/07/88 VII-3 DL/SEPB 7(Sys)
HU to NRC 07/22/81 DL/SEPB 5(Elec) NRC to NU 02/01/82 VI-7 A.
1 X
NRC to NU 11/16/79 VII-4 X
HRC to NU 05/07/81 VI-7 A.
2.
X NRC to NU 05/07/81 VII-5 X
NRC to NU 05/07/81 VI-7 A.
3.
DL/SEPB 7
NRC to NU 10/27/81 VII-6 DL/SEPB 7
NRC to NU GE/26/St VI-7 A.
4.
DSI/CPB 7
NRC TO NU 03/11/82 VII-7 X
NRC to NU 11/16/79 VI-7 B.
X NRC to NU 11/16/79 VIII-1 A.
D51/PSB G
NRC to NU 05/07/81 VI-7 C.
DL/SEPB 7
NRC to NU 03/29/81 VIII-2 DL/SEPB i
NRC to N'.1 09/30/81 VI-7 C.
1 DL/SEPB 7
Nu to NRC 11/02/81 VIII-3 A.
DL/SEPB 7
NRC to..U 08/26/81 VI-7 C.
2.
DL/SEPB 7
NRC to NU 03/29/81 VIII-3 B.
DL/SEPB 7
NRC to NU 07/23/81 VI-7 C.
3.
X NRC to NU 11/16/79 l l
VIII-4 DL/SEPB 7
NRC to NU 07/07/81 (2-25)
1 MILLSTONE 1 i
TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS l
DIV/BR DIV/BR I
IX-t DSI/ASB 7
NRC TO NU 03/09/82 XV-10 X
NRC to NU 11/16/19 IX-2 X
NRC to NU 05/07/81 XV-tt DSI/CPB 7
NRC to NU 10/14/89 l IX-3 DL/SEPB 4b NU to NRC 11/24/81 XV-12 X
NRC to NU tt/f6/79 IX-4 X
NRC to NU 11/16/79 XV-13 DSI/CPB 7(Sys)
NU to NRC 09/09/81 DSI/AEB 7(Doses) HRC to NU 11/03/89 IX-5 DL/SEPB 4b NU to NRC 11/19/81 XV-14 DSI/RSB 7
NRC to NU 09/18/81 IX-6 DE G
NRC to NU 05/07/81 XV-15 DSI/R$B 7
NRC to NU 10/28/81 X
X NRC to NU 05/07/81 XV-16 DSI/AEB 6
HU to NRC 01/93/82 XI-1 X
NRC to NU 12/04/81 XV-17 X
NRC to NU 11/16/79 XI-2 X
HRC to NU 12/04/81 XV-18 DSI/AEB 6
NU to NRC 01/13/82 XIII-1 X
HRC to NU 05/07/81 XV-19 DSI/RSB 7(Sys)
HRC to NU 08/26/89 XIII-2 DL/SSPB G
NRC to NU 05/07/81 DSI/AEB 6(Doses) HU to NRC 01/13/82 i
XV-1 DSI/RSB 7
NRC to NU 12/31/81 XV-20 DSI/AEB 7
HRC to NU 11/03/81 XV-2 X
NRC to NU 11/16/79 XV-21 X
NRC to NU 05/07/81 XV-3 DSI/R$B 7
NRC to NU 09/18/81 XV-22 X
NRC to NU 05/07/88 XV-4 DSI/RSB 7
NRC to NU 09/18/81 XV-23 X
NRC to NU 05/07/81 XV-5 DSI/RSS 7
NRC to NU 01/07/82 XV-24 X
NRC to NU 05/07/81 XV-6 X
NRC to NU 11/16/79 XVI X
NRC to NU 11/15/80 XV-7
'JSI/RSB 7
NRC to NU 12/04/81 XVII DL 7
NRC to NU 08/17/78 XV-8 DSI/CPB 7
NRC to NU 08/26/81 XV-9 DSI/R$B 7
NRC to NU 01/12/82 (2-26)
OYSTER CREEK FACILITY: OYSTER CREEK 1 TCPIC NO.
REVIEW STATUS REMARKS DIV/BR LICENSEE: JERSEY CENTRAL POWEP & LIGHT 11-1 A.
DE/SAB 7
NRC to JCPL 02/04/82 REGION / LOCATION: 9 MILES SOUTH OF TCMS RIVER, NJ.
II-I B.
DE/SAB 7
NRC to JCPL 02/04/82 DOCKET NO.-
05000219 II-1 C.
DE/SAB 7
NRC to NU 02/04/82 POWER CAPACITY: 1930(THERMAL) 0650(ELECTRICAL)
II-2 A.
DSI/AEB 7
NRC to JCPL 11/16/81 OL NUMBER: DPR-16 II-2 8.
X NRC to JCPL 05/07/88 N.S.S.S.*
GE.
II-2 C.
DSI/AEB 7
HRC TO JCPL 03/16/82 A/E FIRM: B&R II-2 D.
X NRC to JCPL 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF:
W.
RUSSELL II-3 A.
DE/HGEB 4B JCPL TO NRC 03/04/82 OPERATING REACTORS BRANCH CHIEF:
D. CRUTCHFIELD II-3 B.
DE/HGEB 4B JCPL TO NRC 03/04/82 OPERATING REACTORS PROJECT MANAGER:
J.
LOMBARDO II-3 B.
1.
DE/HGEB 4B JCPL TO NRC 03'04/82 INTEGRATED ASSESSMENT PROJECT MANAGER: R. FELL U II-3 C.
DE/HGEB 4B JCPL TO NRC 03/04/82 II-4 DE/GSB 7
NRC to JCPL 08/03/81 KEY FOR STATUS CODES II-4 A.
DE/GSB 7
NRC to JCPL 06/08/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.
Dd/GSB 5
NRC to GPU 08/03/81 l
FROM REVIE.J BR ANCH X - DELETED II-4 C.
DE/GSB 7
NRC to JCPL 06/08/89 f
4b-SAR RECEIVED FROM 0 - TOPIC NOT LICENSEE II-4 D.
DE/HGEB (b
JCPL to NRC 12/15/81 STARTED 5 - DRAFT SE SENT II-4 E.
X NRC to JCPL 11/16/79 i
1 - QUESTIONS RECEIVED TO UTILITY FPOM KEVIEW BRANCH II-4 F.
DE/HGEB 4b JCPL to NRC 11/04/81 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC III-t DL/SEPB 4a(Sys) 09/29/81 l
TO UTILITY DL/SEPB 7(Elec) NRC to JCPL 07/09/81 l
7-TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 2
NRC TO JCPL 11/18/81 i
I RECEIVED BY NRC l
(2-27)
,._. _ - ~.
-.c._--
_ -~
-. ~.
~
OYSTER CREEK TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR I
III-3 A.
DE/SEB 48 JCPL TO NRC 03/04/82 III-10 B.
X NRC to JCPL 11/16/19 III-3 B.
X NRC to JCPL 12/26/80 III-10 C.
X NRC to JCPL 11/16/79 l III-3 C.
DE/HGEB Gb JCPL to NRC 11/04/88 III-15 X
NRC to JCPL 05/07/81 I
i-III-4 A.
DSI/ASB 0
III-12 X
NRC to JCPL 05/07/81 III-4 B.
DE/MTEB 4b JCPL to NRC 12/07/89 IV-1 A.
DL/SEPB 7
NRC to JCPL 05/30/79 l l
III-4 C.
DSI/ASB 2
NRC to JCPL 01/19/81 IV-2 DSI/ICSB 2
NRC to JCPL 12/15/80
- ~
III-4 D.
DE/SAB 0
IV-3 X.
NRC to JCPL 05/07/81 III-5 A.
DL/SEPB 6
JCPL to NRC 11/12/88 V-1 X
NRC to JCPL 11/27/81 III-5 B.
DL/SEPB 6
JCPL to NRC 10/06/88 V-2 X
NRC to JCPL 11/16/79 III-6 DL/SEPB 6
JCPL to NRC 06/15/81 V-3 X
NRC to JCPL 05/07/88 III-7 A.
X NRC to JCPL 05/07/81 V-4 X
NRC to JCPL 05/07/81 III-7 8.
DL/SEPB 3
Site visit 05/12/81 V-5 DL/SEPB 7
NRC to JCPL 02/22/82 I
III-7 C.
X NRC to JCPL 11/16/79 V-6 DL/SEPB 7
NRC to JCPL 03/05/80 i
III-7 D.
DE/SEB 7
NRC TO JCPL 03/08/82 V-7 X
NRC to JCPL 05/07/81 l III-8 A.
DSI/CPB 5
NRC TO JCPL 02/29/82 V-8 X
NRC to JCPL 05/07/81 III-8 B.
X NRC to JCPL 09/26/80 V-9 X
NRC to JCPL 81/16/79 III-8 C.
DL/SEPB 7
NRC to JCPL 10/30/80 V-to A.
DL/SEPB 7
JCPL to NRC 05/15/79 i
III-8 D.
X HRC to JCPL 05/07/81 V-10 B.
DL/SEPB 7
NRC to JCPL 09/25/80 III-9 X
NRC to JCPL 05/07/81 V-11 A.
DL/SEPB 7
NRC to JCPL 07/08/88 I
III-10 A.
DL/SEPB 7
NRC to JCPL 06/29/81 V-tt B.
DL/SEPB 7(Sys)
HRC to JCPL 09/25/80 DL/SEPB 7(Elec) HRC to JCPL 07/09/88 1
(2-28)
0YSTER CREEK TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.
DL/SEPB 5
JCPL to NRC 03/16/81 VI-7 D.
DL/SEPB 7
HRC to JCPL 08/t7/78 V-13 X
HRC to JLPL 05/07/81 VI-7 E.
X HRC to JCPL 05/07/81 VI-t DE/CEB 2
HRC to JCPL 06/06/79 VI-7 F.
X NRC to JCPL 11/16/79 VI-2 A.
X NRC to JCPL 05/07/81 VI-8 X
HRC to JCPL 05/07/81 VI-2 B.
X NRC to JCPL 05/07/81 VI-9 X
HRC to JCPL 18/16/79 VI-2 C.
X HRC to JCPL 11/16/79 VI-10 A.
DL/SEPB 7
HRC to JCPL 08/18/81 VI-2 D.
DSI/CSB 5
NRC tc JCPL 12/10/81 VI-10 B.
X NRC to JCPL 11/16/79 VI-3 DSI/CSB 5
NRC to JCPL 12/10/81 VII-t A.
DL/SEPB 7
NRC to JCPL 07/30/81 VI-4 DSI/CSB 6(SYS)
JCPL TO NRC 03/10/82 VII-t B.
DL/SEPB 5
HRC to JCPL 12/28/81 DL/SEPB 7(Elec) HRC to JCPL 08/05/81 VII-2 DL/SEPB 6
JCPL to HRC 08/17/81 VI-5 X
HRC to JCPL 05/07/81 VII-3 DL/SEPB 7(Sys)
HRC to JCPL 09/25/80 VI-6 DSI/CSB 5
HRC TO JCPL 03/04/82 DL/SEPB 7(Elec) HRC to JCPL 07/09/8i VI-7 A.
1 X
HRC to JCPL 11/16/79 VII-4 X
NRC to JCPL 05/07/81 VI-7 A.
2.
X NRC to JCPL 05/07/81 VII-5 X
NRC to JCPL 05/07/81 VI-7 A.
3.
DL/SEPB 7
HRC to JCPL 07/30/81 VII-6 DL/SEPB 7
NRC to JCPL 08/29/81 VI-7 A.
4.
DSI/RSB G
HRC to JCPL 05/07/81 VII-7 X
HRC to JCPL 11/16/79 VI-7 B.
X HRC to JCPL 11/16/79 VIII-1 A.
DSI/PSB 7
HRC to JCPL 03/03/82 VI-7 C.
DL/SEPB 7
NRC to JCPL 03/13/81 VIII-2 DL/SEPB 7
HRC to JCPL 06/29/81 VI-7 C.
1 DL/SEPB 7
HRC to JCPL 06/29/81 VIII-3 A.
DL/SEPB 7
HRC to JCPL 06/29/81 VI-7 C.
2.
DL/SEPB 7
NRC to JCPL 03/13/81 VIII-3 B.
DL/sEPB 7
NRC t_
PL 06/29/81 VI-7 C.
3.
X HRC t, JCPL 11/16/79 VIII-4 DL/SEPB 5
HRC to %PL 03/26/81 (2-29) l
0YSTER CREEK TOPIC HO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 4B JCPL 10 NRC 03/22/82M XV-10 X
hRC to JCPL 11/16/79 IX-2 X
NRC to JCPL 05/07/81 XV-11 DSI/CPB 5
NRC to JCPL 04/09/81 IX-3 DSI/ASB 7
NRC to JCPL 11/13/81 XV-12 X
HRC to JCPL 11/16/79 IX-4 X
HRC to JCPL 05/07/81 XV-13 DSI/AEB 4a(Doses) 07/01/81 DSI/CPB 5(Sys)
HRC to JCPL 04/09/81 IX-5 DL/SEPB 0
XV-14 DSI/RSB 7
HRC to JCPL 07/16/81 IX-6 DE G
HRC to JCPL 05/07/81 XV-15 DSI/RSB 7
HRC to JCPL 12/04/81 X
X HRC to JCPL 05/07/81 XV-16 DSI/AEB Ab JCPL to NRC 1?/04/81 XI-1 X
NRC to JCPL 12/04/81 XV-17 X
HRC to JCPL 11/16/79 XI-2 X
HRC to JCPL 12/04/81 XV-18 DSI/AEB 4a 07/01/81 XIII-t X
HRC to JCPL 05/07/81 XV-19 DSI/AEB 0(Doses)
XIII-2 DL/SSPB 7
NRC to JCPL 09/25/80 DSI/RSB 7(Sys)
HRC to JCPL 09/04/81 XV-1 DSI/RSB 7
NRC to JCPL 12/07/81 XV-20 DSI/RSB 0
XV-2 X
HRC to JCPL 11/16/79 XV-21 X
HRC to JCPL 05/07/81 XV-3 DSI/RSB 7
NRC to JCPL 07/16/81 XV-22 X
NRC to JCPL 05/07/81 XV-4 DSI/RSB 7
HRC to JCPL 07/16/81 XV-23 X
HRC to JCPL 05/07/81 XV-5 DSI/RSB 7
NRC to JCPL 12/07/81 XV-24 X
NRC to JCPL 05/07/81 XV-6 X
NRC to JCFL 11/16/79 XVI X
HRC to JCPL 11/05/80 XV-7 DSI/RSB 7
HRC to JCPL 12/04/81 XVII DL 7
HRC to JCPL 08/17/78 XV-8 DSI/CPB 5
NRC to JCPL 03/31/81 XV-9 DSI/RSB 7
HRC to JCPL 01/07/82 (2-30)
PALISADES FACILITY: PALISADES TOPIC NO.
REVIEW STATUS REMARKS DIV/BR LICENSEE: CONSUMERS POWER II-1 A.
DL/SEPB 7
CPCo to NRC 12/28/79 REGION / LOCATION: 5 MILES SOUTH OF SOUTH HAVEN, MI.
II-1 B.
DL/SEPB 7
CPCo to NRC 12/28/79 DOCKET NO: 05000255 II-1 C.
DL/SEPB 7
CPCo to NRC 05/13/81 POWER CAPACITY: 2530(THERMAL) 0805(ELECTRICAL)
II-2 A.
DSI/AEB 7
HRC to CPCo 06/30/81 OL NUMBER: DPR-20 II-2 B.
X HRC to CPCo 05/07/81 N.S.S.S.*
C-E II-2 C.
DSI/AEB 7
HRC to CPCo 04/23/81 A/E FIRM: BECH.
II-2 D.
X NRC to CPCo 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL II-3 A.
DE/HGEB 7
NRC to CPCo 02/19/82 OPERATING REACTORS BRANCH CHIEF:
D.
CRUTCHFIELD II-3 B.
DE/HGEB 7
HRC to CPCo 02'/19/82 OPERATIHG REACTORS PROJECT MANAGER:
T. WAMBACH II-3 B.
1.
DE/HGEB 7
NRC to CPCo 02/19/82 INTEGRATED ASSESSMENT PROJECT MANAGER: T. MICHAELS p7n II-3 C.
DE/HGEB 7
NRC ta CPCo 02/19/82 t
II-4 DE/GSB 7
CPCo to HRC 07/22/81 KEY FOR STATUS CODES II-4 A.
DE/GSB 7
HRC to CPCo 06/08/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.
DE/GSB 7
CPCo to NRC 07/22/81 FROM REVIEW BRANCH X - DELETED II-4 C.
DE/GSB 7
NRC to CPCo 06/08/81 4b-SAR RECEIVED FROM 0 - TOPIC HOT LICENSEE II-4 D.
DE/HGEB 7
CPC; to NRC 06/01/81 STARTED 5 - DRAFT SE SEHT II-4 E.
X NR0 to CPCo 11/16/79 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.
DE/HGEB 7
CPCo to NRC 06/01/81 6 - SE RESPCHSE RECEIVEG 2 - QUESTIONS SENT BY NRC III-t DL/SEPB 7(Elec) HRC to CPCo 11/12/80 TO UTILITY DL/SEPB 7(Sys)
HRC to CPCo 02/08/82 7 - TOPIC COMPLETE 3 - QUE3 TION RESPONSE RECEIVED BY HRC (2-31)
PALISADES TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR III-2 DL/SEPB 7
NRC to CPCo 02/08/82 III-80 B.
DL/SEPB 7
NRC to CPCo 02/02/82 III-3 A.
DE/SEB 7
HRC to CPCo 08/26/81 III-10 C.
X HRC to CPCo 11/16/79 III-3 B.
X HRC to CPCo 12/26/80 III-11 X
NRC to CPCo 05/07/81 III-3 C.
DE/HGEB 7
HRC to CPCo 02/22/82 III-12 X
HRC to CPCo 05/07/81 III-4 A.
DSI/AEB 7
NRC to CPCo 02/02/82 IV-1 A.
DL/SEPB 7
CPCo to NRC 02/08/79 III-4.B.
DE/MTEB 7
HRC to CPCo 02/08/82 IV-2 DSI/ICSB 7
NRC to CPCo 02/08/82 III-4 C.
DSI/ASB 7
HRC to CPCo 09/21/81 IV-3 X
HRC to CPCo 05/07/81 III-4 D.
DE/SAB 7
CPCo to NRC 08/33/81 V-1 X
NRC to CPCo 11/27/81 III-5 A.
DL/SEPB 7
HRC to CPCo 02/08/82 V-2 X
NRC to CPCo 11/16/79 III-5=B.
DL/SEPB 7
HRC to CPCo 02/19/82 V-3 X
HRC to CPCo 05/07/81 III-6 DL/SEPB 7
CPCo to HRC 12/16/81 V-4 X
NRC to CPCo 05/07/81 III-7 A.
DL/SEPB 7
HRC to CPCo 02/10/82 V-5 DL/SEPB 7
HRC to CPCo 02/04/82 III-7 B.
DL/SEPB 7
NRC to CPCo 02/12/82 V-6 DL/SEPB 7
HRC to CPCo 03/05/80 III-7 C.
DE/SEB 7
HRC to CPCo 10/19/81 V-7 DSI/ASB 7
NRC to CPCo 11/16/81 III-7 D.
DE/SEB 7
CPCo to NRC 08/17/81 V-8 X
HRC to CPCo 05/07/81 III-8 A.
DSI
.7 HRC to CPCo 11/18/81 V-9 X
NRC to CPCo 11/16/79 III-8 B.
X NRC to CPCo 10/01/80 V-10 A.
DL/SEPB 7
HRC to CPCo 09/26/81 III-8 C.
DL/MTEB 7
CPCo to HRC 12/28/79 V-10 B.
DL/SEPB 7
CPCo to NRC 12/23/81 III-8 D.
X NRC to CPCo 05/07/81 V-11 A.
DL/SEPB 7
HRC to CPCo 11/09/81 III-9 X
NRC to CPCo 05/07/81 V-11 B.
DL/SEPB 7(Sys)
HRC to CPCo 12/23/81 i '
DL/SEPB 7(Elec) HRC to CPCo 12/24/81 III-10 A.
DL/SEPB 7
HRC to CPCo 05/19/81 t
i (2-32)
.., ~.
PALISADES l
TOPIC HO.
REVIFW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.
X NRC to CPCo 11/16/79 VI-7 D.
DL/SEPB 7
NRC to CPCo 08/97/78 b-13 X
NRC to CPCo 05/07/81 VI-7 E.
X NRC to CPCo 05/07/81 VI-1 DE/CEB 7
NRC to CPCo 08/03/81 VI-7 F.
DL/SEPB 7
NRC to CPCo 10/29/81 VI-2 A.
X NRC to CPCo 05/07/81 VI-8 X
NRC to CPCo 05/07/81 VI-2 B.
X NRC to CPCo 05/07/81 VI-9 X
'NRC to CPCo 11/16/79 VI-2 C.
X HRC to CPCo 11/16/79 VI-10 A.
DL/SEPB 7
HRC to CPCo 10/16/81 VI-2 D.
DSI/CSB 7
HRC to CPCo 11/16/81 VI-10 B.
X NRC to CPCo 11/16/79 VI-3 DSI/CSB 7
NRC to CPCo 11/16/81 VII-1 A.
DL/SEPB 7
NRC to CPCo 08/28/81 VI-4 DL/SEPB 7(Elec) CPCo to NRC 08/18/81 VII-1 B.
DL/SEPB 7
NRC to CPCo' 08/17/78 DCI/CSB 7(Sys)
NRC to CPCo 02/08/82 VII-2 DL/SEPB 7
VI-5 X
NRC to CPCo 05/07/81
'NRC to CPCo 05/19/81 VII-3 DL/SEPB 7(Sys)
CPCo to NRC 12/23/81 VI-6 DSI/CSB 7
NRC to CPCo 12/11/81 DL/SEPB 7(Elec) CPCo to NRC 12/31/81 VI-7 A.
1.
X NRC to CPCo 11/16/79 VII-4 X
NRC to CPCo 05/07/81 VI-7 A. 2.
X NRC to CPCo 05/07/81 VII-5 X
HRC to CPCo 05/07/81 VI-7 A.
3.
DL/SEPB 7
NRC to CPCo 12/18/8 1 VII-6 DL/SEPB 7
HRC to CPCo 05/19/81 VI-7 A.
4.
X NRC 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/PSB 7
NRC to CPCo 12/22/81 DSI/RSB 7(Sys)
HRC to CPCo 06/30/81 VIII-2 DL/SEPB 7
NRC to CPCo 10/29/81 VI-7 C.
DL/SEPB 7
NRC to CPCo 02/20/81 VIII-3 A.
DL/SEPB 7
NRC to CPCo 05/22/81 VI-7 C.
1 DL/SEPB 7
NRC to CPCo 10/14/81
~
VI-7 C. 2.
DL/SEPB 7
HRC to CPCo 02/20/81 VIII-4 DL/SEPB 7
NRC to CPCo 07/31/81 VI-7 C. 3.
X CPCo to NRC 12/12/79 (2-33)
PAllSADES TOPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 7
NRC to CPCo 02/08/82 XV-to DL/SEPB 7
NRC to CPCo 11/03/81
-IX-2 X
HRC to CPCo 05/07/81 XV-11 X
NRC to CPCo 10/01/80 IX-3 DL/SEPB 7
HRC to CPCo 02/22/82 XV-12 DL/SEP8 7(Doses) NRC to CPCo 12/04/81 DL/SEPB 7(Sys)
NRC to CPCo 11/03/81 IX-4 DSI/RSB 7
NRC to CPCo 02/08/82 XV-13 X
NRC to CPCo 11/16/79 IX-5 DL/SEPB-7 NRC to CPCo 02/1t/82 XV-14 DL/SEPB 7
NRC to CPCo 11/C!/81 IX-6 DE 4A 03/05/82 XV-15 DL/SEPB 7
NRC to CPCo 11/05/81 X
X NRC to CPCo 05/07/81 XV-16 DL/SEPB 7
NRC to CPCo 11/03/81 XI-t X
NRC to CPCo 12/04/81 XV-17 DL/SEPB 7(Doses) HRC to CPCo 11/03/81 XI-2 X
HRC to CPCo 12/04/81 DL/SEPB 7(Sys)
NRC to CPCo 11/03/81 XIII-1 X
NRC to CPCo 05/07/81 XV-18 X
NRC to CPCo 10/01/80 XIII-2 DL/SSPB 7
NRC to CPCo 10/01/80 XV-19 DL/SEPB 7(Doses) NRC to CPCo 11/03/81 4
DL/SEPB 7(Sys)
NRC to CPCo 11/03/81 XV-1 DL/SEPB 7
HRC to CPCo 11/03/81 XV-20 DL/SEPB 7
NRC to CPCo 11/03/81 XV-2 DL/SEPB 7(Doses) HRC to CPCo 11/03/81 DL/SEPB 7(Sys)
HRC to CPCo 11/03/81 XV-21 X
NRC to CPCo 05/07/81 XV-3 DL/SEPB 7
HRC to CPCo 11/03/81 XV-22 X
NRC to CPCo 05/07/81 XV-4 DL/SEPB 7
NRC to CPCo 11/03/81 XV-23 X
HRC to CPCo 05/07/81 XV-5 DL/SEPB 7
NRC to CPCo 11/03/81 XV-24 X
NRC to CPCo 05/07/81 XV-6 DL/SEPB 7
HRC to CPCo 11/03/81 XVI X
HRC to CPCo 11/05/80 XV-7 DL/SEPB 7
NRC to CPCo 11/03/81 XVII DL 7
NRC to CPCo 08/17/78 XV-8 DL/SEPB 7
NRC to CPCo 11/03/81 XV-9 DL/SEPB 7
NRC to CPCo 11/03/81 (2-34)
SAN ON0FRE FACILITY: SAN ONOFRE 1 TOPIC NO.
REVIEW STATUS REMARKS DIV/BR LICENSEE: SOUTHERN CALIFCRNIA EDISON 11-1 A.
DL/SEPB 7
NRC to SCE 11/07/79 REGION / LOCATION: 5 MILES SOUTH OF SAN CLEMENTE, CA.
II-1 B.
DL/SEPB 7
NRC to SCE 11/07/79 DOCKET HO.
05000206 II-1 C.
DE/SAB 4b SCE to NRC 11/12/81 POWER CAPACITY: 1347(THERMAL) 0430(ELECTRICAL)
II-2 A.
DSI/AEB 7
HRC to SCE 04/27/81 OL NUMBER: DPR-13 II-2 B.
X HRC to SCE 05/07/81 H.S.S.S.'
WEST.
II-2 C.
DSI/AEB 7
HRC to SCE 11/18/81 A/E FIRM: BECH.
II-2 D.
X HRC to SCE 05/07/81 SYSTEMATIC EVALUATION FROGRAM BRANCH CHIEF: W. RUSSELL II-3 A.
DE/HGEB 3
SCE TO HRC 03/15/82 OPERATING REACTORS BRANCH CHIEF:
D.
CRUTCHFIELD II-3 B.
DE/HGEB 3
SCE TO HRC 03/15/82 OPERATING REACTORS ""7)ECT MANAGER: W.
PAULSON II-3 B.
1 DE/HGEB 3
SCE TO HRC 03/15/82 MCKENHA['/ g 4 INTEGRATED ASSESSMENT PROJECT MANAGER: E.
II-3 C.
DE/HGEB 2
HRC to SCE 01/07/82 II-4 DE/GSB 5
HRC to SCE 03/15/81 KEY FOR STATUS CODES II-4 A.
DE/GSB 5
NUREG-0712 12/80 G - GEHERIC Ga-DRAFT SE RECEIVED II-4 B.
DE/GSB 5
HUREG-0712 12/80 FROM REVIEW BRANCH X - DELETED II-4 C.
DE/GSB 5
NUREG-0712 12/80 4b-SAR RECEIVED FROM 0- TOPIC HOT LICENSEE 11-4 D.
DE/HGEB 4b SCE to HRC 11/02/81 STARTED 5 - DRAFT SE SENT II-4 E.
X HRC to SCE 11/16/79 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.
DE/HGEB 4b SCE to NRC 11/02/81 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY HRC III-1 DL/SEPB 3(Sys)
SCE to NRC 08/29/79 TO UTILITY DL/SEPB 7(Elec) Part of VII-3 11/18/81 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 3
SCE to NRC 11/20/81 RECEIVED BY HRC (2-35)
m
~.
' SAN ONOFRE
- TOPIC NO.
REVIEW STATUS REMARKS TOPIC HO.
REVIEW STATUS REMARKS DIV/BR DIV/BR III-3 A.
DE/SEB 3
SCE to NRC 09/08/80 111-10 B.
DL/SEPB 7
NRC to SCE 11/08/79 III-3 B.
X NRC to SCE 11/16/79 III-10 C.
X NRC to SCE 11/16/79 III-3 C.
DE/NGEB 7
NRC to SCE 11/27/81 III-11 X
NRC to SCE 05/07/81 III-4 A.
DSI/ASB 3
SCE to NRC 08/14/79 III-12 X
HRC to SCE 05/07/81 III-4 B.
DE/MTEB G
NRC to SCE 05/07/81 IV-1 A.
DL/SEPB 7
NRC to SCE 11/13/79 III-4 C.
DSI/ASB 0
IV-2 DSI/ICSB 2
NRC to SCE 12/15/80 III-4 D.
DE/SAB 4b SCE to NRC 10/23/81 IV-3 X
NRC to SCE 05/07/81 III-5 A.
DL/SEPB 0
V-1 X
NRC to SCE 11/27/81
' III-5 B.
DL/SEPB 0
v-2 X
NRC to SCE 11/16/79 a
LIII-6 DL/SEPB 3
SCE to NRC 12/08/81 V-3 X
NRC to SCE 05/07/81 III-7 A.
X NRC to SCE 05/07/81 V-4 X
'NRC to SCE 05/07/81 III-7 B.
DL/SEPB 3-SCE to NRC 11/20/81 V-5 DL/SEPB 5
NRC to SCE 06/03/81 III-7 C.
X NRC to SCE 11/16/79 V-6 DL/SEPB 7
NRC to SCE 03/05/80 III-7 D.
DE/SEB 4b SCE to NRC 06/09/81 V-7 DSI/ASB 7
HRC to SCE 12/04/81' III-8 A.
DSI 7
NRC to SCE 12/21/81 V-8 X
HRC to SCE 05/07/81 III-8 B.
X NRC to SCE 10/01/80 V-9 X
NRC to SCE 11/16/79
~ III-8 C.
DL/SEPB 7
NRC to SCE 01/29/80 V-10 A.
DL/SEPB 7
'HRC to SCE 01/07/81 I
III-8 D.
X NRC.to SCE 05/07/81 V-10 B.
DL/SEPB 5
NRC to SCE 06/20/81 III-9 X
NRC to SCE 05/07/81 V-11 A.
DL/SEPB 7
NRC to SCE 08/03/81 III-10 A.
DL/SEPB 7
-SCE to NRC 07/24/81 V-11 B.
DL/SEPB 5(Sys)
HRC to SCE 06/20/81 DL/SEPB 7(EIcc) HRC to SCE 02/04/82 I
F i
i
\\
(2-36) r i
+
-n
-m e
,n-SAN ONOFRE TOPIC NO.
REVIEW STATUS' REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.
X NRC to SCE 11/16/79 VI-7 D.
DL/SEPB 7
NRC to SCE 08/17/78 V-13 X
NRC-to SCE OS/07/81 VI-7 E.
X NRC to SCE 05/07/81 VI-t 4b SCE to NRC 01/28/82 VI-7 F.
X NRC to SCE 11/16/79 VI-2 A.
X NRC to SCE 05/07/81 VI-8 X
NRC to SCE 05/07/81 VI-2 B.
X NRC to SCE 05/07/81 VI-9 X
NRC to SCE
.11/16/79 VI-2 C.
X NRC to SCE 11/16/79 VI-10 A.
DL/SEPB 7
NRC to SCE 08/28/81 VI-2 D.
DSI/CSB 5
NRC to SCE 01/12/32 VI-10 B.
DL/SEPB 7
NRC to SCE 11/15/79
-VI-3 DSI/CSB 5
NRC to SCE 01/12/82 VII-1 A.
DL/SEPB 7
NRC to SCE 09/09/81 VI-4 DSI/CSB 5(SYS)
HRC TO SCE 03/03/82 DL/SEPB 7(EIec) NRC to SCE 09/03/81 VII-1 B.
DL/SEPB 7
NRC to SCE 08/17/78 VI-5 X
NRC to SCE 05/07/81 VII-2 DL/SEPB 7
NRC to SCE 11/I7/81 VI-6 DSI/CSB G
NRC to SCE 05/07/81 VII-3 DL/SEPB 5(Sys)
NRC to SCE 06/20/88 DL/SEPB 7(Elec) HRC to SCE 11/18/88 VI-7 A.
1 DL/SEPB 7
NRC to SCE 02/20/81 VII-4 X
NRC to SCE 05/07/81 VI-7 A. 2.
X NRC to SCE 05/07/8I VII-5 X
NRC to SCE 05/07/81 VI-7 A.
3.
DL/SEPB 7
NRC to SCE 11/18/81 VII-6 DL/SEPB 7
NRC to SCE 08/28/81 VI-7 A.
4.
X NRC to SCE 05/07/81 VII-7 X
NRC to SCE 11/16/79 VI-7 B.
DSI/RSB 6(SYS)
SCE TO NRC 01/26/82 DL/SEPB 7(EIec) HRC to SCE 09/04/81 VIII-1 A.
DSI/RSB G
NRC to SCE 05/07/81 VI-7 C.
DL/SEPB 7
NRC to SCE 06/01/81 VIII-2 DL/SEPB 7
NRC to SCE 07/31/81 VI-7 C.
1 DL/SEPB 7
NRC to SCE 08/03/81 VIII-3 A.
DL/SEPB 7
NRC to SCE 11/07/79 f
?
VI-7 C.
DL/SEPB 7
NRC to SCE 06/01/81 VIII-3 B.
DL/SEPB 7
NRC to SCE 07/24/81 VI-7.C. 3.
X NRC to SCE 11/16/79 VIII-4 DL/SEPB 7
NRC to SCE 12/31/81 4
1 (2-37)
SAN ON0FRE TOPIC NO.
REVIEW STATUS REMARKS TOPIC HO.
REVIEW STATUS REMARKS DIV/BR DIV/BR 03/28/82 IX-1 DSI/ASB 3
SCE to hRC 10/05/79 XV-10 DSI/RSB 4A IX-2 X
NRC to SCE 05/07/81 XV-11 X
HRC to SCE 10/01/80 IX-3 DL/SEPB
- b SCE to HRC 11/02/81 XV-12 DSI/RSB 7(Sys)
HRC to SCE 11/19/81 DL/SEPB 7(Doses) HRC to SCE 01/29/80 IX-4 DSI/RSB 7
HRC to SCE 07/16/81 XV-13 X
NRC to SCE 11/16/79 IX-5 DL/SEPB 4b SCE to NRC 12/16/88 XV-14 DSI/RSB 7
NRC to SCE 05/07/81 XV-15 DSI/RSD 4b SCE to NRC 07/07/81 X
X NRC to SCE 05/07/81 XV-16 DSI/AEB 5
HRC to SCE 11/18/81 XI-1 X
HRC to SCE 12/04/8f XV-17 DSI/RSB 7(Sys)
HRC to SCE 12/07/81 XI-2 X
HRC to SCE 12/04/81 DSI/AEB 7(Doses) HRC to SCE 01/29/80 XIII-t X
NRC to SCE 05/07/81 XV-18 X
HRC to SCE 10/01/80 XIII-2 DL/SSPB 7
HRC to SCE Of/22/81 XV-19 DSI/RSB 7(Sys)
HRC to SCE 08/26/81 DL/SEPB 7(Doses) HRC to SCE 01/29/80 XV-1 DSI/RSB 7
NRC to SCE 10/27/81 XV-20 DL/SEPB 7
HRC to SCE 03/28/80 XV-2 DSI/RSB 7(Sys)
SCE to HRC 10/27/81 DL/SEPB 7(Doses) NRC to SCE 01/29/80 XV-21 X
HRC to SCE 05/07/81 XV-3 DSI/RSB 7
NRC to SCE 08/26/8I XV-22 X
hRC to SCE 05/07/81 XV-4 DSI/RSB 7
HRC to SCE 12/21/81 XV-23 X
HRC to SCE 05/07/81 XV-5 DSI/RSB 7
HRC to SCE 02/0f/82 XV-24 X
HRC to SCE 05/07/81 XV-6 DSI/RSB 7
HRC TO SCE 03/03/82 XVI X
NRC to SCE I1/05/80 XV-7 DCI/RSB 4b SCE to NRC 07/01/81 XVII DL 7
NRC to SCE ft/20/79 XV-8 DSI/CPB 7
NRC to SCE 11/19/83 XV-9 DSI/RSB 7
NRC to SCE 02/24/82 (2-38)
YANKEE FACILITY YANKEE NUCLEAR POWER STATION TOPIC NO.
REVIEW STATUS REMARKS DIV/BR LICENSEE
- YANKEE ATOMIC ELECTRIC 11-1 A.
DE/SAB 4B YAEC TO NRC 03/18/82 REGIDH/ LOCATION: 25 MILES NORTH EAST OF PITTSFIELD MASS.
II-t B.
DE/SAB 4b VAEC to NRC 05/01/81 DOCKET NO.: 05000029 II-t C.
DE/SAB Gb YEAC to NRC 04/09/81 POWER CAPACITY: 600(THERMAL) 165(ELECTRICAL)
II-2 A.
DSI/AEB 7
HRC to YAEC 08/03/81 OL NUMBER: DPR-3 II-2 B.
X NRC to YAEC 05/07/81 N.S.S.S.*
WEST.
II-2 C.
DSI/AEB 7
NRC to YAEC 09/04/81 4
A/E FIRM: S&W II-2 D.
X NRC to YAEC 05/07/81 SYSTEMATIC EVALUATICH PROGRAM BRANCH CHIEF:. W.
RUSSELL II-3 A.
DE/HGEB 6
YAEC to NRC 03/16/81 l
OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD II-3 B.
DE/HGEB 6
YAEC to NRC 03/16/81 OPERATING REACTORS PROJECT MANAGER:
R.
CARUSO II-3 B.
1.
DE/HGEB 5
NRC to YAEC 02/09/81 BOYLE$f)$qri, II-3 C.
DE/HGEB 3
Mtc Summary 11/27/81 INTEGRATED ASSESSMENT PROJECT MANAGER: M.
II-4 DE/GSB 7
NRC to YAEC 06/08/81 KEY FOR STATUS CODES II-4 A.
DE/GSB 7
NRC to YAEC 06/08/81 I
G - GENERIC 4a-DRAFT SE RECEIVED II-4 B.
DE/GSB 3
YAEC to NRC 06/26/81 FROM REVIEW BRANCH X - DELETED II-4 C.
DE/GSB 7
NRC to YAEC 06/08/81 4b-SAR RECEIVED FROM 0 - TOPIC NOT LICENSEE II-4 D.
DE/HGEB 4B YAEC TO NRC 02/26/82 STARTED 5 - DRAFT SE SENT II-4 E.
DE/HGEB 3
Mtg Summary 12/17/81 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F.
DE/HGEB 4b YAEC to NRC 08/31/81 4
6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC III-t DL/SEPB 5(Elec) HRC to YAEC 02/02/82
-TO UTILITY DL/SEPB 3(Sys)
YAEC to NRC 01/31/79 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 4B YAEC TO NRC 03/18/82 RECEIVED BY NRC (2-39)
YANKEE TCPIC NO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR III-3 A.
DE/SEB 4B YAEC TO HRC 03/18/82 III-10 B.
X NRC to YAEC 11/16/19 III-5 B.
X HRC to YAEC 12/26/80 III-10 C.
X HRC to YAEC 11/16/79 III-3 C.
DE/HGEB Ab (AEC to NRC 01/04/82 III-11 X
NRC to YaEC 05/07/81 III-4 A.
DSI/ASB 4B YAEC TO HRC 03/18/82 III-12 X
NRC to YAEC 05/07/81 III-4 B.
DE/NTEB 5
NRC to YAEC 02/08/82 IV-1 A.
DL/SEPB 7
NRC to YAEC 04/18/79 III-4 C.
DSI/ASB 4B YAEC TO HRC 03/18/82 IV-2 DSI/ICSB 5
NRC to YAEC 12/23/81 III-4 D.
DE/SAB 4b YAEC to NRC 06/30/81 IV-3 X
HRC to YAEC 05/07/81 III-5 A.
DL/SEPB 4B YAEC TO HRC 03/18/82 V-1 X
NRC to YAEC 11/27/81 III-5 B.
DL/SEPB 46 YAEC to NRC 01/21/82 V-2 X
HRC to YAEC 11/16/81 III-6 DL/SEPB 3
YAEC to NRC 06/30/81 V-3 X
HRC to YAEC 05/07/81 III-7 A.
X HRC to YAEC 05/07/81 V-4 X
HRC to YAEC 05/07/81 III-7 B.
DL/SEPB 3
YAEC to HRC 08/21/81 V-5 DL/SEPB 5
HRC to YAEC 03/11/82 III-7 C.
X HRC to YAEC 11/16/79 V-6 DL/SEPB 7
HRC to YAEC 03/05/80 III-7 D.
DE/SEB 7
HRC TO YAEC 03/18/82 V-7 X
HRC to YAEC 12/14/81 III-8 A.
DSI 7
HRC to YAEC 12/29/81 V-8 X
NRC to YAEC 05/07/81 III-8 B.
X HRC to YAEC 10/01/80 V-9 X
HRC to YAEC 11/16/79 III-8 C.
DL/SEPB 7
HRC to YAEC 11/15/79 V-10 A.
DL/SEPB 7
HRC to YAEC 11/05/79 III-8 D.
X NRC to YAEC 05/07/81 V-10 B.
DL/SEPB 7
NRC to YAEC 02/01/82 III-9 X
HRC to YAEC 05/07/81 V-11 A.
DL/SEPB 7
HRC to YAEC 02/01/82 III-10 m.
DL/SEPB 7
HRC to YAEC 09/22/81 V-11 B.
DL/SEPB 7(Sys)
HRC to YAEC 02/01/82 DL/SEPB 7(Elec) HRC to YAEC 02/01/82 (2-40)
YANKEE TOPIC HO.
PEVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR V-12 A.
X HRC to YAEC 11/16/79 VI-7 D.
DL/SEPB 7
HRC to YAEC 08/17/78 V-13 X
NRC to YAEC 05/07/81 VI-7 E.
X HRC to YAEC 05/07/81 VI-1 DE/CEB 3
YEAC to NRC 06/26/79 VI-7 F.
DL/SEPB 7
HRC to YAEC 08/28/81 VI-2 A.
X HRC to YAEC 05/07/81 VI-8 X
HRC to YAEC 05/07/81 VI-2 B.
X NRC to YAEC 05/07/81 VI-9 X
NRC to YAEC 11/16/79 VI-2 C.
X NRC to YAEC 11/16/79 VI-10 A.
DL/SEPB 7
NRC to YAEC 02/01/82 VI-2 D.
DSI/CSB 0
VI-10 B.
X HRC to YAEC 11/16/79 VI-3 DSI/CSB 0
VII-1 A.
DL/SEPB 7
HRC to YAEC 02/22/P2 VI-4 DSI/CSB 3(Sys)
YAEC to NRC 01/29/82 VII-1 B.
DL/SEPB 7
HRC to YAEC 08/17/78 DL/SEPI 7(Elec) HRC to YAEC 03/05/82 VII-2 DL/SEPB 7
hRC to YAEC 02/01/82 VI-5 X
HRC to YAEC 05/07/81 VII-3 DL/SEPB 7(Sys)
NRC to YAEC 02/01/82 VI-6 DSI/CSB G
HRC to YAEC 05/07/81 DL/SEPB 5(Elec) NRC to YAEC 02/02/82 VI-7 A.
1 DL/SEPB 7
HRC to YAEC 02/20/81 VII-4 X
NRC to YAEC 05/07/81 VI-7 A.
2.
X NRC to YAEC 05/07/81 VII-5 X
HRC to YAEC 05/07/81 VI-7 A.
3.
DL/SEPB 5
HRC to YAEC 02/08/82 VII-6 DL/SEPB 7
HRC to YAEC 08/28/81 VI-7 A.
4.
X HRC to YAEC 05/07/81 VII-7 X
HRC to YAEC 11/16/79 VI-7 B.
DSI/RSB 7(Elec) HRC to YAEC 06/04/81 VIII-1 A.
DSI/PSB G
HRC to YAEC 05/07/81 0(Sys)
VI-7 C.
DL/SEPB 7
HRC to YAEC 03/13/81 VIII-2 DL/SEPB 7
HRC to YAEC 09/03/81 VI-7 C.
1.
DL/SEPB 7
HRC to YAEC 09/14/81 VIII-3 A.
DL/SEPB 7
HRC to YAEC 11/07/79 VI-7 C.
2.
DL/SEPB 7
NRC to YAEC 03/13/81 VIII-3 B.
DL/SEPB 7
NRC to (AEC 08/28/81 VI-7 C.
3.
DL/SEPB 7
NRC to YAEC 07/24/80 VIII-4 DL/SEPB 5
HRC TO YAEC 07/01/80 l
(2-41)
YANKEE TOPIC HO.
REVIEW STATUS REMARKS TOPIC NO.
REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 4b YAEC to NRC 11/18/81 XV-10 DSI/RSB 4A 03/02/82 IX-2 X
NRC to YAEC 05/07/81 XV-11 X
HRC to YAEC 10/01/80 IX-3 DL/SEPB 4b YAEC to NRC 09/17/81 XV-12 DSI/CPB 4A 03/29/82 DSI/AEB 7(Doses) HRC to YAEC 12/29/81 IX-4 DSI/RSB 4b YAEC to NRC 08/31/81 XV-13 X
NRC to YAEC 11/16/79 IX-5 DL/SEPB 4b YAEC to NRC 11/18/81 XV-14 DSI/RSB 4b YAEC to NRC 06/30/81 IX-6 DE G
NRC to YAEC 05/07/81 XV-15 DSI/RSB 4b YAEC to NRC 06/30/81 X
X HRC to YAEC 05/07/81 XV-16 DSI/AEB 4b YAEC to NRC 02/01/82 XI-1 X
NRC to YAEC 12/04/81 XV-17 DSI/RSB 0(Sys)
XI-2 X
HRC to YAEC 12/04/81 DSI/AEB 4A(DOSES) 03/19/82 XIII-1 X
NRC to YAEC 05/07/81 XV-18 X
NRC to YAEC 10/01/80 XIII-2 DL/SSPB 7
HRC to YAEC 03/11/81 XV-19 DSI/RSB AbSys)
YAEC to NRC 11/18/81 DSI/AEB Gb(Dosos)YAEC to NPC 01/04/82 XV-1 DSI/RSB 4b YAEC to NRC 02/01/82 XV-20 DL/SEPB 7
NRC to YAEC 09/06/81 XV-2 DSI/RSB Gb(Sys) YAEC to NRC 06/30/81 DSI/AEB 0(Doses)
XV-21 X
NRC to YAEC 05/07/81 XV-3 DSI/RSB 7
NRC to YAEC 01/25/82 XV-22 X
HRC to YAEC 05/07/81 XV-4 DSI/RSB 4b YAEC to NRC 01/04/82 XV-23 X
NRC to YAEC 05/07/81 XV-5 DSI/RSB 7
HRC to YAEC 02/10/82 XV-24 X
NRC to YAEC 05/01/81 XV-6 DSI/RSB 4b YAEC to NRC 02/01/82 XVI X
HRC to YAEC 11/05/80 XV-7 DSI/RSB 4b YAEC to NRC 06/30/81 XVII DL 7
HRC to YAEC 11/20/19 XV-8 DSI/CPB 7
NRC TO YAEC 03/05/82 XV-9 DSI/R$B 4b YAEC to NRC 06/30/81 (2-42)
-m-l l
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LaJ C/)
....mm..
f*lLI.llSiRd0ll!!!
21 PAllSADES Ri1 4
SAR 1/
SER 2/
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE III-1 Classification of NONE 12/15/81C 111-8.A Loose Parts Monitoring and NDHE 11/03/81C (SYS)~
Structures Components and Core Barrel Vibration Systems (Seismic and Monitoring (NRR B-60, C-12)
Quality)
IV-2 Reactivity Control Systems 07/31/81R 10/16/81C III-5.A Effects of Pipe Break on 08/13/81R 12/04/81C and Protection Against Including Functional Design Structures, Systems and Components Inside Single Failures Containment V-7 Reactor Coolant Pump HONE 11/16/81C III-5.B Pipe Break Outside 08/25/81R 12/23/81C Overspeed 'NRR B-68)
Containment
~
VI-6 Containment Leak Testing NONE 08/05/81C III-7.A Inservice Inspection, NONE 08/25/81C (MP A-04)
Including Prestressed Concrete Containments with VIII-1.A Potential Equipment NONE 12/22/81C Either Grouted or Ungrouted Failures Associated with a Tendons Degraded Grid Voltage (MP B-23)
III-7.B Design Codes. Design NONE 11/16/81C Criteria, Load IX-1 Fuel Storage NONE 12/31/81C Combinations, and Reactor Cavity Design Criteria IX-4 Boron Addition System 10/09/81R 11/18/81C IX-6 Fire Protection (MP B-41)
NONE 03/05/82C El SAR J/
SER 2/
XI-1 Appendix I(MP A-02)
NONE DELETED TOPIC NO. TITLE SCHEDULE SCHEDULE XI-2 Radiological (Effluent NDHE DELETED III-3.C Inservice Inspection of 12/21/81R 02/12/82C and Process) Monitoring Water Control Structures Systems (NRR B-67)
III-4.B Turbine Missiles (MP B-46)
NONE 12/02/81C J/ SAR : Licensee Safety Analysis Report-Scheduled or Actual I
III-7.D
. Containment Structural NONE 08/17/81C (Actual (status 4b) when date is followed by R)
Integrity Tests 2/ SER : Staff Safety Evaluation Report -Scheduled or Actual V-1 Compliance with Codes and NONE DELETED (Actual (status 4a, 5, 7) when date is followed by C)
Standards (10 CFR 50.55a)
(MP A-01.A-14) 1/ Desiginated number of days from receipt of licensee SAR (Note: if Licensee SAR is received then date is from receipt of additional information requested)
(3-2)
i t
t
[
C ED
/
l lJ 0
6 m
i J
0 6
Y N
A 6
0 R
PA 0
6 R
AN SL D
0 6
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V B
T I
E T
E F
C I
0 6
E M
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BE N
S J
S A
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0 6
3 A
E P
T I
3 E
M C
(
E I
E
[
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U 0
1 6
6 N
S E
f L
C L
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I A
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1 6
L TC O
0 1
6 4
PE S
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3 0
6 3
E IA 2
2 3
3 S
l L
J A
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T I
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1 S
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GINNA D.L GINNA pil SAR 1/
SER 2/
SAR 1/
SER 2/
TOPIC HO. TITLE SCHEDULE SCHEDULE TOPIC HO. TITLE SCHEDULE SCHEDULE 111-1 Classification of Struct-NONE 12/29/81C III-4.C Internally Generated 01/11/82R 02/02/82C (SYS) ures Corponents and Systems Missiles (Sessmic and Quality)
III-8.A Loose Parts Monitoring and NDHE 11/03/81C III-2 Wind and Tornado loadings H0HE 09/23/81C Core Barrel Vibration Monitoring (NRR B-60 C-12)
III-7.A Inservice Inspection, HONE 12/28/81C V-7 Reactor Coolant Pump HOME 11/ 0 5/81C Including Prestressed Concrete Containments with Overspeed(NRR B-68)
Either Grouted or VI-2.D Nass and Energy Release for NONE 09/25/81C Ungrounded Tendons Possible Pipe Break Inside III-7.B Design Codes, Design NONE 12/31/81C Containment Criteria, Load Combinations, and Reactor VI-3 Containment Pressure and NDHE 09/25/81C Heat Removal Capability Cavity Design Criteria VI-7.C.1 Appendix K - Electrical NONE 11/18/81C VI-7.B ESF Switchover from NONE 12/18/81C Instrumentation and Control (SYS)
Injection to Recirculation Mode (Automatic ECCS (EIC) Re-reviews Realignment)
IX-S Ventilation Systems NONE 11/02/81C IX-1 Fuel Storage NDHE 11/24/81C IX-6 Fire Protection (MP B-41)
HONE 02/24/82C Q1 TOPIC NO. TITLE SCHEDULE SCHEDULE XI-1 Appendix I(MP A-02)
NONE DELETED 11-1.8 Population Distribution 04/15/81R 0 7 / 21/ 81 C XI-2 Radiological (Effluent H0HE DELETED and Process) Monitoring II-1.C Potential Hazards or 04/15/81R 07/01/81C Systems (NRR B-67)
Changes in Potential XV-9 Startup or an Inactive Loop HONE 10/16/81C Hazards Due to or Recirculation Loop at an Transportation, Institutional Industrial, Incorrect Temperature, and Flow Controller Malfunction and Military Facilities Causing an Increase in BWR II-4.D Stability of Slopes 06/30/81R 02/01/82C Core Flow Rate II-4.F Settlement of Foundations 06/30/81R 01/29/82C XV-19 Loss-of-Coolant Accidents NDHE 09/29/81C l
and Buried Equipment (DOSES)
Rosulting from Spectrum of (SYS)
Postulated Piping Breaks 10/02/81C III-3.C Inservice Inspection of 10/12/81R 02/09/82C Within the Reactor Coolant Water Control Structures Pressure Boundary Licensee Safety Analysis Report-Scheduled or Actual III-4.B Turbine Missiles (MP B-46)
N0HE 12/02/81C J/ SAR (actual (status 4b) when date is follwed by R)
III-4.D Site Proximity Missiles 0 4/16 /81R 07/21/81C Staff Safety Evaluation Report -Scheduled or Actual (Including Aircraft) 2/ SER :
(Actual (status 4a, 5, 7) when date is followed M'
C) j VI-1 Organic Materials and 11/06/81R 02/18/82C Post Accident Chemistry
}/ Desiginated number of days from receipt of licensen SAR l
(Note:
if Licensee SAR is received then date is from receipt of additional information requested)
(3-4)
LICENSEE SUBMITTALS GI44A SIBITTALS 48 TARGET 35 M--
25 pg 15 18 ALL SUBMITTALS RECEIVED 5
8 M
Jll AUG SEP OCT NOV DEC JAN FEB MAR APR MAY JIN JLL /DEC
[
Target 0
0 2
0 0
1 0
0 0
0 0
0 0
PER MONTH Actual 0
0 1
1 1
0 Target 0
0 2
2 2
3 3
3 3
3 3
3 3
CUMULATIVE Actual 0
0 0
1 2
3 (3-5) 1
i I)lRti!!il]fEilt 12
~2k DRESDEN 2 DE (Cont.)
SAR 1/
SER 2/
SAR 1/
SER 7/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE III-1 Classification of NONE 03/03/82C 11-3.8 Flooding Potential and NONE 06/10/82 (SYS)
Structures, Components and Protection Requirements Systems (Seismic and Quality)
II-3.B.1 Capability of Operating NONE 06/10/82 Plant to Cope with Design III-2 Wind and Tornado Loadings 02/22/82R 06/30/82 Basis Flooding Conditions III-5.A Effects of Pipe Break on 09/30/82 10/21/82 II-3.C Safety related Water NDHE 06/10/82 Structures, Systems and Supply (Ultimate Heat Sink Components Inside (UHS))
Containment II-4.D Stability of Slopes 12/08/81R 04/30/82 III-7 B Design Codes, Design NOME 06/15/82 Criteria, Load II-4.E Dam Integrity 12/08/81R 01/22/82C Combinations,.and Reactor Cavity Design Criteria II-4.F Settlement of Foundations 12/08/81R O'4 e.J /8 2 and Buried Equipment VI-4 Containment Isolation NONE 12/15/81C (ELEC)
System III-3.A Effects of High Water Level 12/08/81R 04/15/82 on Structures VII-1.A Isolation of Reactor NONE 08/05/81C Protection System from III-3.C Inservice Inspection of 02/16/82R 07/01/82 Non-Safety Systems, Water Control Structures Including Qualifications of Isolation Devices III-4.8 Turbine Missiles NDHE 04/15/82 VII-6 Frequency Decay NDHE 08/26/81C III-4.D Site Proximity Missiles 12/08/81R 02/05/82C (Including Aircraft)
IX-5 Ventilation Systems NONE 01/20/82C III-7.D Containment Structural 04/27/81R 03/30/82C Integrity Tests kk SAR 1/
SER 2/
V-1 Compliance with Codes NDHE DELETED TOPIC NO. TITLE SCHEDULE SCHEDULE and Standards (10 CFR 50.55a)(MP A-01,A-14)
II-1.A Exclusion Area Authority 06/ 01/81R 10/06/81C and Control VI-t Organic Materials and 04/15/82 05/30/82 Post Accident Chemistry II-1.B Population Distribution 04/27/81R 10/06/81C II-1.C Potential Hazards or 12/08/81R 05/31/82 Dil Changes in Potential SAR 1/
SER 2/
Hazards Due to TOPIC NO. TITLE SCHEDULE SCHEDULE Transportation.
Institutional Industrial, 11-2.C Atmospheric Transport and 03/20/81R 08/26/81C and Military Facilities Diffusion Characteristics II-3.A Hydrologic Description NONE.
06/10/82 III-4.A Tornado Missiles 12/08/81R 04/30/82 1
(3-6)
. DRESDEN 2 kil (Cont.)
211 (Cont.)
SAR 1/
SER 2/
SAR 1/
SER 2/
TCPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE III-4.C Internally Generated 04/15/82 06/15/82 XV-3 Loss of External Load.
10/15/81R 11/17/81C Missiles Turbine Trip, Loss of Condenser Vacuum, Closure III-8.A Loose Parts Monitoring NONE 02/09/82C of Main Steam Isolation and Core Barrel Vibration Valve (BWR), and Steam Monitoring (NRR B-60,C-12)
Pressure Regulator Failure (Closed)
IV-2 Reactivity Control Systems NONE 10/19/81C Including Functional Design XV-4 Loss of Non-Emergency A-C 10/15/81R 11/17/81C Power to the Station and Protection Against
{
Auxiliaries Single Failures l
VI-2.D Mass and Energy Release for NONE 12/P2/81C XV-5 Loss of Normal Feedwater 10/15/81R 12/04/81C l
Possible Pipe Break Inside Flow Containment XV-7 Reactor Coolant Pump Rotor 10/15/81R 12/18/81C VI-3 Containment Pressure and NONE 12/02/81C Seizure and Reactor Coolant Heat Removal Capability Pump Shaft Break 1
VI-4 Containment Isolation NONE 10/02/81C XV-8 Control Rod Misoperation 10/15/81R 01/27/82C l
(System Malfunction or I
(SYS)
System Operator Error) l l
l VI-6 Containment Leak Testing NONE 05/01/82 XV-9 Startup or an Inactive Loop 10/15/81R 12/07/81C l
l (MP A-04) or Recirculation Loop at an VI-7.A.4 Core Spray Nozzle NONE 02/09/82C Incorrect Temperature, and Flow Controller Malfunction Effectiveness (NRR A-16)
Causing an Increase in BWR l
VIII-1.A Potential Equipment NONE 05/01/82 Core Flow Rate l
Faileres Associated with a XV-11 Inadvertent Loading and 10/15/81R 01/25/82C l
Degraded Grid Voltage Operation of a Fuel (MP B-23)
Assembly in an Improper j
IX-1 Fuel Storage 02/02/82R 03/26/82C Position IX-6 Fire Protection (MP B-41)
NONE 06/30/82 XV-13 Spectrum of Rod Drop 10/15/81R 01/25/82C (SYS)
Accidents (BWR)
XI-1 Appendix I(MP A-02)
NONE DELETED (DOSES) 10/15/81R 12/14/81C XI-2 Radiological (Effluent and NONE DELETED XV-14 Inadvertent Operation of 10/15/81R 12/08/81C ECCS and Chemical and Process) Monitoring Systems Volume Control System (NRR B-67)
Malfunction that Increases I
XV-1 Increase in Feedwater 10/15/81R 12/14/81C Reactor Coolant Inventory Temperature. Increase in Feedwater Flow, Increase XV-15 Inadvertent Opening of a 10/15/81R 12/22/81C PWR Pressurizer Safety-in Steam Flow and Relief Valve or a BWR Inadvertent Opening of a Steam Generator Relief or Safety / Relief Valve Safety Valve (3-7)
DRESDEN 2 D11 (Cont.)
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE XV-18 Radiological Ccnsequences 10/15/81R 12/23/81C of Main Steam Line Failure Outside Containment (BWR)
XV-19 Loss-of-Coolant Accidents 10/15/81R 11/17/81C (SYS)
Resulting from Spectrum of (DOSES)
Postulated Piping Breaks 10/15/81R 12/15/81C Within the Reactor Coolant Pressure Boundary XV-20 Radiological Consequences 04/27/81R 11/20/81C of Fuel Damaging Accidents (Inside and Outside Containment 1/ SAR Licensee Safety Analysis Report-Scheduled or Actual (actual (status 4b) when date is followed by R)
Z/ SER : Staff Safety Evaluation Report -Scheduled or Actual (Actual (status 4a, 5, 7 ) when date is followed by C) 1/ Desicinated number of days from receipt of licensee SAR (Note:
i f Licensee S AR is received then date is from receipt of additional information requested)
(3-8)
C E
D
/
L 1
J 62 1
g M
5 0
2 Y
g AM 5
0 2
R f
PA 2
52 f
RAM S
3 L
2 3
0 1
2 AT f
B E
T F
2 2
I 0
1 2
2 M
B2 N
A UN f
J S
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9 SD T
1 S
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2 3
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7 2
1 NE V
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0 1
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4 1
1 PES 0
0 GUA 0
0 SL l
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5 8
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T A
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M UM R
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C P
0YSTER CREEK QL OYSTER CREEK R1 (Cont.)
SAR 1/
SER 2/
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE 111-1 Classification of NONE 01/29/82C III-4.B Turbine Missiles 12/07/81R 05/31/82 (SYS)
Structures, Components III-4.D Site Proximity Missiles 03/31/82 04/30/82 and Systems III-2 Wind and Tornado Loading 03/31/82 05/31/82 III-7.D Containment Structural 11/ 04/81R 02/25/82C Integrity Tests III-7.B Design Codes, Design NONE 04/30/82 Criteria, Load Combinations V-1 Compliance with Codes NONE DELETED and Structures and Reactor Cavity Design (MP A-01,A-14)
VII-6 Frequency Decay NONE 08/29/81C VI-1 Organic Materials and Post 07/30/82 08/31/82 IX-5 Ventilation System 02/28/82 05/30/82 Accident Chemistry VI-7.A-4 Core Spray Nozzle NONE 05/31/82 Effectiveness (MP D-12)
D11 SAR 1/
SER 2/
TOPIC HO. TITLE SCHEDULE SCHEDULE DL SAR 1/
SER 2/
Il-2.C Atmospheric Transport and 11/ 04 / 81 R 02/24/82C TCPIC NO. TITLE SCHEDULE SCHEDULE Diffusion Characteristics for Accident Analysis II-1.A Exclusion Area Authority 11/30/81R OS/18/82C III-4.A Tornado Missles 03/31/82 05/15/82 and Control II-1.B Population Distribution 11/30/51R 01/18/82C III-4.C Internally Generated 02/28/82 04/15/82 Missiles II-1.C Potential Hazards Due to 11/30/81R 01/18/82C Transportation, Industrial, III-8.A Loose Parts and Core NONE 02/09/82C and Military Facilities Barrel Monitoring (NRR B-60,C-12)
II-3.A Hydrologic Description 03/04/82R 07/05/82 IV-2 Reactivity Control Systems 02/28/82 04/15/82 II-3.B Flooding Potential and 03/04/82R 07/05/82 Protection Requirements VI-2.D Mass and Energy solease for NONE 11/20/81C Possible Pipe Braak Inside II-3.B-1 Capability to Cope with 03/04/82R 07/05/82 Containment Design Basis Flood VI-3 Containment Pressure and NONE 11/20/81C II-3.C Safety Related Water Supply 03/04/82R 07/05/82 Heat Removal Capability (Ultimate Heat Sink)
VI-4 Containment Isolation NONE 10/22/81C II-4.D Stability of Slopes 12/15/81R 06/01/82 System II-4.F Settlement of Foundation 11/04/81R 06/01/82 VI-6 Containment Leak Testing NONE 06/04/81C (MP A-04) and Buried Equipment III-3.A Effects of High Water 03/04/82R 04/15/82 VIII-1.A Potential Equipment NONE 10/16/81C Failures Associated with Level on Structures a Degraded Grid Voltage III-3.C Inservice Inspection of 11/12/81R 06/01/82 (MP B-23)
Water Control Structure (3-10)
0YSTER CREEK M (Cont.)
M (Cont.)
SAR 1/
SER 2/
SAR 1/
SER 2/
TOPIC HO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE IX-1 Fuel Storage 03/04/82R 04/15/82 XV-15 Inadvertent Opening of BWR 05/07/81R 11/19 / 81 C Safety / Relief Valve IX-6 Fire Protection (MP B-41)
H0HE 05/31/82 XV-16 Radiological Consequences 11/04/81R 03/15/82 of Failure of Small Lines XI-1 Appendix I(MP A-02)
NOHL DELETED Carrying Primary Coolant Outside Containment XI.2 Radiological (Effluent and HONE DELETED Process Monitoring Systems)
XV-18 Radiological Consequences 05/07/81R 0 7/ 01/81C (HRR B-67)
Main Steam Line Failure XV-1 Decrease in Feedwater 05/07/81R 12/07/81C Dutside Containment Temperature. Increase in Feedwater Flow, Increase in XV-19 Loss of Coolant Accidents 05/07/81R 09/04/81C Steam Flow, Inadvertent (SYS)
Resulting From Spectrum Opening of Steam Generator, Breaks Within Reactor Relief or Safety Valve (DOSES)
Coolant Pressure Boundary 02/28/82 04/30/82 XV-3 Loss of External Load, 05/07/81R 07/16/81C XV-20 Radiological Consequences 02/28/82 04/30/82 Turbine Trip, Loss of of Fuel Damaging Accidents Condenser Vacuum, Closure (In 8 Out of Containment) of Main Steam Isolation valve (BWR), Steam Pressure Regulatory Failure (closed)
J/ SAR : Licensee Safety Analysis Report-Scheduled or Actual XV-4 Loss of Non-Emergency A-C 05/07/81R 07/16/81C Power to the Station 2/ SER = Staff Safety Evaluation Report -Scheduled or Actual Auxiliaries (Actual (status 4a. 5, 7) when date is followed by C)
XV-5 Loss of Normal Feedwater 05/07/81R 11/30/81C 1/ Desiginated number of days from receipt of licensee SAR Flow (Note: if Licensee SAR is received then date is from XV-7 Reactor Coolant Pump Rotor 08/25/81R 12/07/81C Seizure and Reactor Coolant Pump Shaft Break XV-9 Startup or an Inactive Loop 05/07/81R 12/30/81C or Recirculation loop at Incorrect Temperature and Flow Controller Malfunction Causing an Increase in BWR Core Flow Rate XV-13 Spectrum of Rod Drop HOME 04/09/81C (sys)
Accident 05/07/81R 07/01/81C (doses)
XV-14 Inadvertent Operation of 05/07/81R 07/16/81C ECCS that Increases Reactor Coolant Inventory (3-11)
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SAR f/
SER 2/
SAR J/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE III-1 Classification of NONE 01/29/82C Il-3.A Hydrologic Description 06/25/81R 06/25/82 3
(SYS)
Structures, Components and Systems (Seismic and II-3.B Flooding Potential 8 06/26/81R 06/25/82 Quality)
Protection Requirements III-2 Wind and Tornado Loadings NONE 04/30/82 II-3.B.1 Capability of Operating 06/25/81R 06/25/82 Plant to Cope with Design III-5.A Effects of Pipe Break on 03/05/82 05/10/82 Basis Flooding Conditions Structures, Systems and Components Inside II-3.C Safety Related Water 04/28/81R 06/25/82 Containment Supply LUHS)
III-5.B Pipe Break Outside 12/04/81R 02/09/82C II-4.B Proximity of Capable NONE 12/30/81C Containment Tectonic Structures in Plant Vicinity III-7.5 Design Codes, Design NONE 05/30/82 Criteria, Load Combinations II-4.D Stability of Slopes 08/31/81R 06/01/82 and Reactor Cavity Design II-4.F Settlement of Foundations 04/28/81R 06/01/82 V-11.B RHR Interlock Requirements NONE 01/22/82C and Buried Equipment 4
(ELEC)
III-3.C Inservice Inspection of 08/31/81R 06/01/82 VII-3 Systems Required for Safe NONE 01/22/82C Water Control Structures (ELEC)
Shutdown III-4.B Turbine Missiles 08/31/81R 05/31/82 VII-6 Frequency Decay NONE 08/26/81C III-4.D Site Prximity Missiles 04/2t/81R 10/29/81C IX-3 Station Service and Cooling 11/24/81R 04/30/82 (Including Aircraft)
Water Systems IV-3 BWR Jat Pumps Operating NONE 02/22/82C IX-5 Ventilation Systems 11/19/81R 04/15/82 Indications XIII-2 Safeguards Industrial NDHE 06/30/82 V-1 Compliance with Codes and NONE DELETED Security (MP A-10)
Standards (10 CFR 50.55a)
(MP A-01.A-14)
I )g l~
VI-1 Organic Materials and Post 09/30/81R 01/28/82C s
SAR 1/
SER 2/
Accident Chemistry TOPIC NO. TITLE SCHEDULE SCHEDULE
,I ~
II-1.A Evciusion Ar ea Authority &
04/17/81R 0 7/ 31/81C Dil J
Control SAR 1/
SER 2/
+',
Population Distribution 05/19/81R 10/29/81C TOPIC HO. TITLE SCHEDULE SCHEDULE
. I_ I-1. 8 Il-2.C Atmospheric Transport and 05/19/81R 09/29/81C II-e.C Potential Hazards or 04/29/81R 10/29/81C Diffusion Characteristics Changes in, Potential for Accident Analysis Hazards Due to Transporta-tion. Institutional, and III-4.A Tornado Missiles 08/31/81R 03/31/82 Military Facilities e
(3-13) s
/~
s MILLSTONE 1 Ell (Cont.)
Ell (Cont.)
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE, ' SCHEDULE TOPIC NU. TITLE ~
SCHEDULE SCHEDULE III-4.C Internally Generated 03/05/82 I 05/01/82 XV-3 Loss of External Lord, 06/30/81R 09/18/81C Turbine Trip, Loss of Missiles Conde,ser Vacuum, Closure III-8.A Loose Parts Monitoriaq and NONE
~
02/)9/82C of Ma'a Steam Isolation Core Barrel Vibration Valv VRJ, and Steam Monitoring (NRR B-60,C-12)
Pre' legulator Failure (Clo IV-2 Reactivity Control Systems 10/28/81R 03/31/82 Including Functional Design XV-4 Loss on-Emergency A-C 06/30/81R 09/18/81C Power
.s the Station and Protection Against Auxiliaries Single Failures VI-2.D Mass and Energy Release for NONE 04/01/82 XV-5 Loss of Normal Feedwater 06/30/81R 12/23/81C Possible Pipe Break Inside Flow Containment XV-7 Reactor Coolant Ptmp 06/30/81R 11/18/81C VI-3 Containment Pressura and NONE 04/01/82 Rotor Seizure and Reactor Heat Removal Capability Coolant Pump Shaft Break VI-4 Containment Isolation NONE 11/16/81C XV-8 Control Rod Misoperation 06/30/81R d8/26/81C (System Malfunction or (SYS)
System Operator Error)
VI-6 Leak Testing (MP A-04)
NONE 05/31/82
~
XV-9 Startup or an Inactive Loop 06/30/81R 12/30/81C VI-7 A.4 Core Spray Nozzle NONE /
07/09/8;C or Recirculation Loop at an Incorrect Temperature, and Effectiveness (NRR A-16)
Flow Controller Malfunction
_f VIII-1.A Potential Equipment NONE 06/01/82 Causing an Increase in BWR Core Flow Rate
/
Failures Associated With a Degraded Grid Voltage
- XV-11 Inadvertent Loading and 06/30/81R 10/14/81C 08/31/81R 02/19/32C Operation of a Fuel IX-1 Fuel Storage
~ Assembly in an Improper IX-t Fjre Protection (MP B-41)
NDHE 06/30/52 Position XI - Appendix I(MP A-02)
NONE DELETED XV-13 Spectrum of Rod Drop 06/30/81R 09/09/81C (SYS)
Accidents (BWR)
XI-2 Radiological (Effluent 1 NONE DELETED (DOSES) 06/30/81R 09/21/81C Process) Monitoring Systems XV-14 Inadvertent Operation of 06/30/81R 09/18/81C l
, ' ~ '
(NRR B-67)
ECCS and Chemical and L-XV-1 Decrease in Feedwater 06/30/81R 12/15/81C Volume Control System L
Temperature, Increase in Malfunction that Increases I
Feedwater Flow, Increase in Reactor Coolant Inventory Steam Flow and Inadvertent XV-15 Inadvertent Opening of a 06/30/81R 10/28/81C Opening of a Steam Gener-PWR Pressurizer Safety ator Relief or safety Valve Relief Valve or a BWR L.
Safety Relief Valve (3-14)
4 MILLSTONE 1 211 (Cont.)
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE XV-16 Radiological Consequences 06/30/81R 09/21/81C of Failure of Small Lines Carr/ing Primary Coolant Outside Containment XV-18 Radiological Consequences 06/30/81R 09/21/81C of Main Steam Line Failure Outside Containment (BWR)
XV-19 Loss of Coolant Accidents 06/30/81R 08/26/81C (SYS)
Resulting from Spectrum of (DOSES)
Postulated Piping Breaks 06/30/ SIR 09/21/81C Within the Reactor Coolant Pressure Boundary l
XV-20 Radiological Consecuences 06/30/81R 09/21/81C of Fuel Damaging Accidents (Inside and Outside Containment) l/ SAR : Licensee Safety Analysis Report-Scheduled or Actual (actual (status 4b) when date is followed by R) 2/ SER : Staff Safety Evaluation Report -Scheduled or Actual i
(Actual (status 4a, 5, 7) when date is followed by C) 1/ Desiginated number of days from receipt of licensee SAR j
(Notes if !icensee SAR i s received then date is feom receipt of additional information requested)
(3-15)
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2 E
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SAN ONOFRE QL SAN ONOFRE SAR J/
SER 2/
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE IX-3 Station Service and Cooling 11/02/81R 06/30/82 111-1 Classification of NONE 05/07/82 Water Systems Steuctures, Components and Systems (Sei smic and IX-5 Ventilation Systems 12/16/81R 06/30/82 Quality)
III-2 Wind and Tornado Loadings 05/01/82 08/30/82 21 III-5.A Effects of Pipe Break on 12/01/82 01/15/83 TOPIC NO. TITLE SCHEDULE SCHEDULE Structures, Systems and Components Inside II-1.C Potential Hazards or 11/12/81R 05/31/82 Containment Changes in Potential Hazards Due to III-5.B Pipe Break Outside 12/01/82 12/16/82 Transportation.
Containment Institutional Industrial, III-6 Seismic Design NONE 08/30/82 Considerations II-3.A Hydrologic Description NONE 12/05/82 III-7.B Design Codes, Design NONE 08/31/82 II-3.8 Flooding Potential 8 HONE 12/05/82 Criteria. Load Protection Requirements Combinations, and Reactor Cavity Design Criteria II-3.5 1 Capability of Operating NONE 12/05/82 Plant to Cope with Design V-11.B RHR Interlock Requirements NONE 02/04/82C Basis Flooding Conditions (ELEC)
II-3.C Safety Related Water NDHE 12/03/82 VI-7.A.3 ECCS Actuation System NONE 11/18/81C Supply (UHS)
VI-7.B ESF Switchover from NONE 09/04/81C II-4.D Stability of Slopes 11/02/81R 11/01/82 (ELEC)
Injection to Recirculation Mode (Automatic ECCS II-4.F Sattlement of Foundations 11/02/81R 11/01/82 Realignment) and Buried Eculpment VI-10.A Testing of Reactor Trip NONE 08/28/81C III-3.A Effects of High Water Level 05/30/82 09/30/82 i
System and Engineertd on Structures l
Safety Features Including Response Time Testing III-4.B Turbine Missiles (MP B-46)
NONE 04/30/82 I
VII-1.A Isolation of Reactor NONE 09/09/81C III-4.D Site Proximity Missiles 10/23/81R 06/30/42 Protection Systems, (Including Aircraft)
Including Qualifications of Isolation Devices III-7.D Containment Structural 06/09/81R 04/15/82 Integrity Tests VII-2 Engineered Safety Features NONE 11/18/81C (ESF) System Control Logic V-1 Compliance with Codes and NONE DELETED and Design Standards (10 CFR 50.55a)
(MP A-01)
VII-3 Systems Required for Safe NONE 11/18/81C (ELEC)
Shutdown VI-1 Organic Materials and Post 01/28/82C 05/30/82 VII-6 Frequency Decay NONE 08/28/81C (3-17)
SAN ONOFRE Dil (Cont.)
211 SAR 1/
SER 2/
SAR 1/
SER g/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE III-4.A Tornado Missiles 05/01/82 06/15/82 XV-2 Spectrum of Steam System 0 7/ 01/8 t R 80/27/81C Piping Failures Inside and III-4.C Internally Generated 04/30/82 06/15/82 Outside of Containment (PWR)
Missiles XV-3 Loss of External Load.
0 7/ 01/81R 08/26/81C III-8.A Loose Parts Monitoring and NONE 12/07/81C Turbine Trip, Loss of Con-densor Vaccum, Closure of Core Barrel Vibration Main Steam Isolation Valve Monitoring (NRR B-60,C-12)
(BWR), and Steam Pressure IV-2 Reactivity Control Systems 04/30/82 06/15/82 Regulator Failure (Closed)
Including Functional Design XV-4 Loss of Non-Emergency A-C 08/18/81R 12/12/81C and Protection Against Power to the Station Single Failures Auxiliaries V-7 Reactor Coolant Pump NDHE 11/05/81C XV-5 Loss of Normal Feedwater 07/01/81R 01/25/82C Overspeed(NRR B-68)
Flow VI-2.D Mass and Energy Release for NONE 12/04/81C Possible Pipe Break Inside XV-6 Feedwater System Pipe 07/01/31R 02/19/82C Breaks Inside and Outside Containment Containment (PWR)
VI-3 Containment Pressure and NONE 12/04/81C XV-7 Reactor Coolant Pump Rotor 07/01/81R 05/01/82 Heat Removal Capability Seizure and Reactor Coolant VI-4 Containment Isolation NONE 01/29/82C Pump Shaft Break (SYS)
System XV-8 Control Rod Misoperation 07/01/81R 11/19/81C VI-6 Containment Leak Testing NONE 03/31/82 (System Malfunction or Operator Error)
(MP A-04)
VIII-1.A Potential Equipment Failure NONE 05/01/82 XV-10 Chemical and Volume Control 07/01/81R 03/28/82C Associated with a Degraded System Malfunction that Results in a Decrease in Grid Voltage (MP B-23) the Boron Concentration in IX-1 Fuel Storage 04/30/82 06/15/82 the Reactor Coolant (PWR)
IX-6 Fire Protection (MP B-41)
NONE 10/31/82 XV-12 Spectrum of Rod Ejection 07/01/81R 11/19/81C Accidents (PWR)
XI-1 Appendix I NONE DELETED XV-14 Inadvertent Operation of 0 7/ 01/81R 02/11/82C l
XI-2 Radiological (Effluent and NONE DELETED ECCS and Chemical and l
Volume Control System Process) Monitoring Systems l
Malfunction that Increases (NRR B-67)
Reactor Coolant Inventory I
XV-1 Decrease in Feedwater 0 7/ 01/81R 10/27/81C j
Temperature, Increase in Feedwater Flow, Increase XV-15 Inadvertent Opening of a 07/01/81R 04/01/82 I
PWR Pressurizer Safety-l in Steam Flow and Relief Valve of a BWR Inadvertent Opening of a Steam Generator Relief Safety / Relief Valve or Safety Valve (3-18)
SAN ON0FRE Ell (Cont.)
SAR 1/
SER Z/
TOPlc NO. TITLE SCHEDULE SCHEDULE XV-16 Radiological Consequences 08/04/81R 11/18/8 t C of Failure of Small Lines Carrying Primary Coolant Outside Containment XV-17 System Generator Tube NONE 12/07/81C (SYS)
Failure (PWR)
XV-19 Loss-of-Coolant Accidents 0 7/ 01/ 31 R 08/26/81C Resulting From Spectrum of Postulated Piping Breaks Within the Reactor Coolant Pressure Boundary J/ SAR: Licensee Safety Analysi s Report-Scheduled or Actual (Actual (status 4b) when date is followed by R)
Z/ SER Staff Safety Evaluation Report -Scheduled or Actual (Actual (status 4a, 5,
- 7) when date is followed by C) 1/ Desiginated number of days from receipt of licensee SAR (Note:
if Licensee SAR is received then date is from receipt of additional information requested) l l
l 1
(3-19)
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BIG ROCK POINT 2L BIG ROCK POINT QL (Cont.)
SAR 1/
SER 2/
SAR 1/
SER 2/
TOPIC NO. TITLE SCHECULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE III-1 Classification of Struct-NONE 04/30/82 IX-3 Station Service and 12/10/81R 05/30/82 (SYS) ures, Components and Sys-Cooling Water Systems tems (Seismic and Quality)
IX-5 Ventilation Systems 05/15/82 08/30/82 III-2 Wind and Tornado Loading 02/01/82 08/30/82 III-5.A Effects of Pipe Break on 05/01/82 09/21/82 21 Structures. Systems and SAR 1/
SER 2/
Components In si de TOPIC NO. TITLE SCHEDULE SCHEDULE Containment II
',.A Hydrologic Description NONE 08/10/82 III-5.B Pipe Break Outside 04/01/82 08/20/82 Containment II-3.B Flooding Potential and NONE 08/10/82 Protection Requirements III-6 Seismic Design NONE 09/30/82 Considerations II-3.B.1 Capability of Operating NONE 08/10/82 Plans tc Cope with Designs III-7.8 Design Codes, Design NONE 05/30/82 Basis Flooding Conditions Criterion. Load Combinations and Reactor II-3.C Safety-Related Water Supply NONE 08/10/82 i
Cavity Design Criter on (Ultimate Heat Sink UHS))
l VI-7.A.3 ECCS Actuation System NONE 01/29/82C II-4.B Proximity of Capable NONE 09/30/82 i
Tectonic Structures in i
VI-7.C ECCS Single Failure Cri-NONE 08/05/81C Plant Vicinity l
terion and Requirements for l
Lockinq Out Power to Valves II-4.D Stability of Slopes 10/05/81R 06/01/82 Including Independence i
l of Interlocks on ECCS Valve II-4.F Settlement of Foundations 10/19/81R 06/01/82 and Buried Equipment l
VI-7.C.2 Failure Mode Analysis ECCS NONE 08/05/81C III-3.A Effects of High Water 03/15/82 09/30/82 VI-10.A Testing of Reactor Trip 12/23/81 05/30/82 Level on Structures System and Engineered Safety Features, Including III-3.C Inservice Inspection of 12/21/81R 09/01/82 Response Time Testing Water Control Structures VII-1.A Isolation of Reacter NONE 02/16/82C III-4.B Turbine Missiles 06/30/82 07/31/82 Protection System From Non-Safety Systems, Including III-4.D Site Proximity Missiles 12/14/81R 05/15/82 Qualification of Isolation (Including Aircraft)
Devices III-7.D Containment Structural 12/29/81R 03/03/82C VII-2 Engineered Safety Features NONE 12/31/81C Integrity Tests (ESF) System Control Logic and Design V-1 Compliance with Codes and NONE DELETED Standards 110 CFR 50.55a)
VII-6 Frequency Decay NONE 09/21/81C (MP A-01,A-14)
VI-1 Organic Materials and Post 03/16/82R 05/15/82 Accident Chemsitry Accident Chemsitry 1
(3-21)
BIG ROCK POINT M
M (Cont.)
SAR 1/
SER 2/
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE 11-2.C Atmospheric Transport and 04/15/82-06/15/82 xv-t Decrease in Feedwater 07/15/8tR 02/18/82C Diffusion Characteristics Temperature Increase in Feedwater Flow, Increase for Accident Analysis in Steam Flow and III-4.A Tornado Missiles 03/16/82R 05/01/82 Inadvertent Opening of a Steam Generator Relief III-4.C Internally Generated 05/01/62 06/15/82 or Safety Valve Missiles XV-3 Loss of External Load.
07/15/81R 10/16/81C III-8.A Loose Parts Monitoring and NONE 02/09/82C Turbine Trip, Loss of Condenser Vacuum, Closure Core Vibration Monitoring of Main Steam Isolation (NRR B-60 C-12)
Valve (BWR), and Steam IV-2 Reactivity Control System NONE 12/07/81C Pressure Regulator Failure (Closed)
Including Functional Design and Protection Against XV-4 Loss of Non-Emergency A-C 07/15/81R 10/16/81C Single Failures Power to Use Station VI-2.D Mass and Energy Release for NONE 03/31/82 Auxiliaries Postulated Pipe Breaks Inside Containment XV-5 Loss of Normal Feedwater 07/15/81R 01/26/82C Flow VI-3 Containment Pressures and NONE 03/31/82 Heat Removal Capability XV-7 Reactor Coolant Pumps 07/15/8tR 02/25/f,2C Rotor Seizure and Reactor VI-4 Containment Isolation Sys.
H0riE 03/24/82C Coolant Pump Shaft Break VI-6 Containment Leak Testing NONE 04/30/82 XV-8 Control Rod Misoperation 09/23/81R 12/21/81C (MP 4-04)
(System Malfunction or Operator Error)
VI-7.B ESF Switchover from NONE 03/31/82 Injection to Recirculation XV-9 Startup of an Inactive Loop 07/15/81R 03/24/82C Mode (Automatic EECS or Recirculation loop at an Incorrect Temperature and Realignment)
Flow Controller Malfunction VIII-1.A Po6:atial Equipment NONE 07/01/82 Causing an Increase in BWR Failures Associated with Core Flow Rate Degraded Grid XV-11 Inadvertent Loading and 09/28/81R 11/20/81C IX-1 Fuel Storage NONE 07/31/82 Operation of a Fuel Assembly in an Improper IX-6 Fire Protection (MP B-41)
NONE 09/30/82 Position (BWR)
XI-1 Appendix I(MP A-02)
NONE DELETED XV-13 Spectrum of Rod Drop SYS 07/01/81R ff/20/8tC Accidents DOSES 07/01/81R 10/23/81C XI-2 Radiological (Effluent NONE DELETED and Process) Monitoring XV-14 Inadvertent Operation of 06/26/81R 08/18/8tC Systems (NRR B-67)
ECCS and Chemical and Volume Control System Malfunction that Increases Reactor Coolant Inventory (3-22)
BIG ROCK POINT
' E11 (Cont.)
SAR 1/
SER Z/
TOPIC NO. TITLE SCHEDULE SCHEDULE XV-15 Inadvertent Opening of a 06/26/85R 08/18/81C PWR Pressurizer Safety Relief Valve or a BWR Safety / Relief Valve XV-16 Radiological Consequences 0 7/ 01/81R 12/14/81C of Failure of Small Lines Carrying Primary Coolant Outside Containment XV-18 Radiological Consequences 07/01/81R 03/01/82 cf Main Steam Line Failure Outside Containment XV-19 Loss of Coolant Accidents 06/29/81R 08/18/81C (SYS)
Resulting From Spectrum of Postulated Piping Breaks (DOSES) within the Reactor Coolant No date 07/01/82 Pressure Boundary XV-20 Radiological Consequences 07/03/81R 10/23/81C of Fuel Damaging Accidents (Inside and Outside Containment) i 1/ SAR : Licensee Safety Analysis Report-Scheduled or Actual (Actual (Status 4b) when date is followed by R) 2/ SER.: Staff Safety Evaluation Report -Scheduled or Actual (Actual (status 4a, 5, 7) when date is followed by C) 1/ Desiginated number of days from receipt of licensee SAR (Note if Licensee SAR is received then date is from receipt of additional information requested)
(3-23)
C ED
/
t tJ 0
0 2
N y
JU
/
0 2
2
/
YAM 8
3
/
1 R
PA a..
5 2
1 RAM S
o L
1 2
3 t
A 1
B T
FE T
2 I
1 0
8 1
MT N
N BI J
S A
O UP H
T K
1 SC N
1 8
O 1
O M
m R
EG CE I
O EB S
3 7
N V
E ON C
I 4
0 L
TCO 2
4 PE S
2 2
GUA 0
0 L
S J
1 LA T
T I
0 M
0 W
~
N S
U J
~
8 5
5 g
5 0
5 B
4 3
2 p
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t la t
la eg u
p u
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a c
a c
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T A
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A G
U N
A L
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P
,f ll l
HADDAM NECK RL HADDAM NECK RL (Cont.)
l SAR t/
SER Z/
SAR 1/
SER Z/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE III-1 Classification of NONE 05/30/82 IX-5 Ventilation Systems 12/14/81R 05/15/82 (SYS)
Structures, Components and Systems (Seismic and XIII-2 Safeguards / Industrial NONE 06/30/82 l
Quality)
Security (MP A-10)
III-2 Wind and Tornado Loadings 12/14/81R 07/30/82 III-5 A.
Effects of Pipe Break 03/12/82 07/30/82 SLR t/
SER 2/
on Structures, Systems TOPIC NO. TITLE SCHEDULE SCHEDULE and Componets Inside Containment Il-1.A Exclusion Area Authority 04/27/81R 03/29/82C B. Pipe Break Outside-10/02/81R 04/12/82 II-1.B Population Distribution 08/31/81R 03/29/82C Containment II-1.C Potential Hazards or 06/30/81R 03/29/82C III-6 Seismic Design NONE 09/30/82 Changes in Potential Considerations Hazards Due to Transportation, III-7.B Design Codes, Design NONE 07/30/82 Institutional Industrial.
Criteria, Load and Military Facilities Combinations, and Reactor Cavity Design Criteria II-3.A Hydrologic Description 12/14/81R 10/08/82 VI-7.A.3 ECCS Actuation System NONE 01/29/82C II-3.B Flooding Potential and 12/14/81R 10/01/82 Protection Requirements l
VI-7.C.3 The Effect on PWR Loop NONE 12/14/81C Isolation Valve Closure II-3.B.1 Capability of Operating-12/14/81R 10/01/82 During a LOCA on ECCS Plant to Cope with Design Performance Basis Flooding Conditions VI-10.A Testing.of Reactor Trip NONE 04/30/82 II-3.C Safety-related Water Supply 12/14/81R 10/01/82 System and Engineered (Ultimate Heat Sink (UHS))
Safety Features Including Response Time Testing II-4.B Proximity of Capable NONE 04/30/82 Tectonic Structures in VII-1.A Isolation of Reactor NONE 02/16/82C Plant Vicinity Protection System from Non-Safety Systems, Including II-4.D Stability of Slopes 08/31/81R 07/01/82 Qualifications of Isolation Devices II-4.F Settlement of Foundations 12/18/81R 05/15/82 VII-2 Engineered Safety Features NONE 02/16/82C and Buried Equipment (ESP) System Control Logic and Design III-3.A Effects of High Water 08/31/81R 06/01/82 Level on Structures VII-6 Frequency Decay NONE 08/28/81C III-3.B Structural and Other NONE 10/01/82 VIII-4 Electrical Penetrations NONE 12/23/81C Consequences (e.g. Flooding of Reactor Containment of Safety-Related Equipment in Basements) of Failure of IX-3 Station Service and Cooling 12/14/81R 04/30/82 Underdrain Systems l
Water Systems l
(3-25) l I
1
HADDAM NECK Q11 (Cont.)
D1 (cont.)
SAR 1/
SER 2/
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC HO. TITLE SCHEDULE SCHEDULE 111-3.C Inservice Inspections of 0 2/12/82 R 07/01/82 VI-6 Containment Leak Iesting NONE 03/31/S2 (MP A-04)
Water Control Structures III-4.B Turbine Missiles (MP B-46)
NONE 04/30/82 VI.7.B ESF Switchover from NONE 04/01/82 (STS)
Injection to Recirculation III-4.D Site Proximity Missiles 06/25/81R 03/29/82C Mode (Automatic ECCS Realignment)
(Including Aircraft)
III-7.D Containment Structural 04/27/81R 10/16/81C VIII-1.A Potential Equipment NONE 10/01/82 Failures Associated with a Inteq-ity Tests Dograded Grid Voltage V-1 Compliance with Codes and NONE DELETED (MP B-23)
Standards (10 CFR 50.55a)
IX-1 Fuel Storage 08/31/81R 12/30/81C (MP A-01.A-14)
VI-1 Organic Materials and Post 02/09/82R 05/30/82 IX-4 Boron Addition Systems 10/02/81R 04/01/82 Accident Chemistry IX-6 Fire Protection (MP B-41)
NDHE 08/31/82 I
XI-1 Appendix I(MP A-02)
NONE DEL ET ED E31 TOPIC NO. TITLE SCHEDULE SCHEDULE XI-2 Radiological (Effluent NONE DELETED
,nd Process) Monitoring III-4.A Tornado Missiles 08/31/81R 12/28/81C Systems (NRR B-67)
III-4.C Internaly Generating 02/12/82R 03/15/82 XV-1 Decrease in Feedwater 09/30/81R 04/15/82 Temperatures. Increase in Mi ssiles Feedwater Flow. Increase in III-8.A Loose Parts Monitoring and NONE 02/09/82C Steam Flow and Inadvertent Opening of a Steam Genera-Core Barrel Vibration tor Relief or Safety Valve Monitoring (NRR B-60.C-12)
IV-2 Reactivity Control Systems 06/30/31R 12/23/81C XV-2 Spectrum of Steam System 09/30/81R 04/15/82 Piping Failures Inside and Including Functional Design Outside of Centainment(SYS) and Protection Against (PWR)
(DOSES) 09/30/81R 05/01/82 l
Single Failures l
V-7 Reactor Coolant Pump NONE 11/05/81C XV-3 Loss of External Load.
09/30/81R 03/09/82C Overspeed(NRR B-68)
Turbine Trip, Loss of VI-2.D Mass and Energy Release for NONE 05/01/82 Condenser vacuum, Closure of Main Steam Isolation Possible Pipe Break Inside Valve (BWR), and Steam Containment Pressure Regulator Failure I
VI-3 Containment Pressure and NONE 05/01/82 (Closed) i Heat Removal Capability XV-4 Loss of Non-Emergency A-C 09/30/81R 12/17/81C VI-4 Containment Isolation NONE 05/01/82 Power to the Station Auxiliaries System XV-5 Loss of Normal Feedwater 09/30/81R 04/15/82 Flow (3-26)
HADDAM NECK R11 (Cont.)
211 (Cont.)
SAR 1/
SER 2/
SAR 1/
SER 2/
TOPIC HO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE XV-6 Feedwater System Pipe 09/30/81R 04/15/82 XV-19 Loss of-Coolant Accidents 09/30/81R 1 1/10 / 81 C Breaks Inside and Outside Resulting from Spectrum of Containment (PWR)
Postulated Piping Breaks Within the Reactor Coolant XV-7 Reactor Coolant Pump Rotor 09/30/81R 04/15/82 Pressure Boundary (SYS)
Seizure and Reactor Coolant (DOSES) 09/30/81R 05/01/82 Pump Shaft Break XV-8 Control Rod Misoperation 09/30/81R 03/18/82C 1/ SAR = Licensee Safety Analysis Report-Scheduled or Actual (System Malfunction or (Actual (Status 4b) when date is followed by R)
Operator Error)
Z/ SER : Staff Safety Evaluation Report -Scheduled or Actual XV-9 Startup or an Inactive 09/30/81R 04/01/82 (Actual (status Aa, 5,
- 7) when date is followed by C)
Loop or Recirculation Loop at an Incorrect J/ Desiginated number of days from receipt of licensee SAR Temperature, and Flow (Notes if Licensee SAR is received then date is from Controller Malfunction receipt of additional information requested)
Causing an Increase in BWR Core Flow Rate XV-10 Chemical and Volume Control 09/30/81R 03/29/82C System Malfunction that Results in a Decrease in in Boron Concentration in the Reactor Coolant (PWR) i l
XV-12 Spectrum of Rod Ejection 09/30/81R 03/15/82C l
Accidents (PWR)
(SYS) l (DOSES) 09/30/81R 05/01/82 XV-14 Inadvertent Operation of 09/30/81R 04/15/82 i
ECCS and Chemical and Volume Control System Malfunction that Increases Reactor Coolant Inventory XV-15 Inadvertent Opening of a 09/30/81R 04/15/82 PWR Pressurizer Safety-Relief Valve or a BWR Safety / Relief Valve XV-16 Radiological Consequences NONE 09/28/81C of Failure of Small Lines Carrying Primary Coolant Outside Containment XV-17 Steam Generator (SYS) 02/26/82 05/01/82 Tube Failure (PWR) (DOSES) 02/26/82 05/01/82 (3-27)
I C
E D
/
LUJ 0
43 N
i J
t 0
43 YA i
M 0
43 R
i PA 4
0 3
i RAM S
1 0
4 2
L 3
3 A
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F T
1 2
3 2
I 3
3 M
N X
BC i
J S
A
)
UN H
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E R i
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0 S
8 3
N V
E i
ON C
2 0
2 I
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i CO 2
6 1
2 P
i ES 0
6 i
GUA 6
6 L
SL A
A T
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YANKEE 21 YANKEE NUCLEAR POWER STATION 21 (Cont.)
SAR 1/
SER 2/
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC HO. TITLE SCHEDULE SCHEDULE 111-1 Classification of Struct-NONE 05/30/82 IX-5 ventilation Systems 11/18/81R 04/15/82 ures, Components and Sys-tems (Seismic and Quality)
III-2 Wind and Tornado Loadings 03/18/82R 07/30/82 SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE III-5.A Effects of Pipe Break on 0 3/18/82R 06/08/82 Structures, Systems and II-1.A Exclusion Area Authority 03/18/82R 06/30/82 Components Inside and Control Containment II-1.8 Population Distribution 05/01/31R 06/30/82 III-5.5 Pipe Break Outside 01/21/82R 06/29/82 Containment II-1.C Potential Hazards or 04/09/81R 06/30/82 Changes in Potential III-6 Seismic Design NDHE 08/31/82 Hazards Due to Considerations Transportation.
Institutional Industrial.
III-7.3 Design Codes, Design NONE 06/30/82 and Military Facilities Criteria, Load Combinations, and Reactor II-3.C Safety-related Water NONE 09/05/82 Cavity Design Criteria Supply (Ultimate Heat Sink (UHS)
V-11.B RHR Interlock Requirements NONE 01/22/82C (ELEC)
II-4.B Proximity of Capable NONE 05/31/82 Tectonic Structures in VI-7.A.3 ECCS Actuation System 06/30/81R 01/29/82C Plant Vicinity (B-46)
VI-10.A Testing of Reactor Trip 06/30/81R 01/22/82C II-4.D Stability of Slopes 02/26/82R 10/01/82 System and Engineered Safety Features Including II-4.E Dam Integrity NONE 10/01/82 Safety Features Including j
Respor.se Time Testing II-4.F Settlement of Foundations 08/31/81R 10/01/82 1
and Buried Equipment VII-1.A Isoaltion of Reactor NONE 10/05/81C Protection System from III-3.A Effects of High Wator 03/18/82R 03/30/82 Hon-Safety Systems, Level on Structures Including Qualifications of Isolation Devices III-3.C Inservice Inspection of 01/04/82R 10/01/82 Water Control Structures VII-2 Engineered Safety Features NONE 10/19/81C (ESF) System Control Logic III-4.B Turbine Missiles (MP B-46)
NONE 02/08/82C and Design III-4.D Site proximity missiles 06/30/81R 06/30/82 VII-3 System Required for Safe NONE 01/22/82C (Including Aircraft)
(ELEC)
Shutdown III-7.D Containment Structural 11/18/81R 03/01/82C VII-6 Frequency Decay NDHE 08/28/81C Integrity Tests V-1 Compliance with Codes NONE DELETED IX-3 Station Service and Cooling 09/17/81R 04/15/82 and Standards (10 CFR Water Systems 50.55a)(MP A-01,A-14)
(3-29)
YANKEE Ell (Cont.)
EE (Cont.)
SfR 1/
SER 2/
SAR 1/
SER 2/
TOPIC HO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE VI-1 Organic Materials and 02/15/82 04/30/82 IX-1 Fuel Storage 11/18/81R 05/01/82 Post Accident chemistry IX-4 Baron Addition System 08/31/81R 05/15/82 IX-6 Fire Protection (MP B-41)
N0HE 08/31/82 Ell SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE XI-1 Appendix I(MP A-02)
NOME DELETED II-2.C Atmospheric Transport and 06/30/81R 09/04/81C XI-2 Radiological (Effluent NONE DELETED and Process) Monitoring Diffusion Characteristics for Accident Analysis Systems (NRR B-67)
III-4.A Tornado Missiles 03/18/82R 05/15/82 XV-1 Decrease in Feedwater 02/01/82R 06/30/82 Temperature. Increase in III-4.C Internally Generated 0 3/18/82R 05/15/82 Feedwater Flow, Increase in Steam Flow and Missiles Inadvertent Opening of a III-8.A Loose Parts Monitoring NONE 12/07/81C Steam Generator Relief and Core Barrel Vibration or Safety Valve Monitoring (NRR B-60,C-12)
XV-2 Spectrum of Steam System 06/30/81R 05/15/82 IV-2 Reactivity Control Systems 09/17/81R 12/23/81C (SYS)
Piping Failures Inside Including Functional Design (DOSES) and Outside of Containment No date 05/15/82 (PWR) and Protection Against Single Failures XV-3 Loss of External Load.
06/30/81R-01/09/82C V-7 Reacher Coolant Pump NONE DELETED Turbine Trip, Loss of Condenser Vacuum, Closure Overspeed(NRR B-68) of Main Steam Isolatiun VI-2.D Mass and Energy Release NONE 04/01/82 Valve (BWR), and Steam for Possible Pipe Break Pressure Regulator Failura (Closed)
Inside Containment VI-3 Containment Pressure and NONE 04/01/82 XV-4 Loss of Non-Emergency A-C 01/04/82R 06/01/82 Power to the Station Heat Removal Capability Auxiliaries VI-4 Containment Isolation NONE 04/01/82 XV-5 Loss of Normal Feedwater 06/30/81R 01/29/82C (SYS)
System Flow VI-6 Containment Leak Testing NONE 06/01/82 (MP A-04)
XV-6 feedvater System Pipe 02/01/82R 06/15/82 Breaks Inside and Cutside VI-7.B ESF Switchover from NONE 06/15/82 Containment (PWR)
(SYS)
Injection to Recirculation Mode (Automatic ECCS XV-7 Reactor Coolant Pump Rotor 06/30/81R 04/30/82 Seizure and Reactor Coolant Realignment)
Pump Shaft Break VIII-1.A Potential Equipment NONE 08/01/82 Failures Associated with XV-8 Control Rod Misoperation 01/04/82R 02/26/82C a Degraded Grid Voltage (System Malfunction or (MP B-23)
Operator Error)
(3-30) 1 l
YANKEE 211 (Cont.)
SAR 1/
SER 2/
TOPlc NO. TITLE SCHEDULE SCHEDULE xv-9 Startup or an Inactive 06/30/81R 06/15/82 Loop or Recirculation loop l
at an Incorrect Te-perature, and Flew 1
Controller Malfunction Causing an Increase in BWR Core Flow Rate l
XV-10 Chemical and Volume Control 06/30/81R 03/02/82C f
I System Malfunction that Results in a Decrease in the Baron Concentration in the Reactor Coolant (PWR) i i
XV-12 Spectrum of Rod Election 06/30/81R 03/29/82C (SYS)
Accidents (PWR)
(DOSES) 08/30/81R 12/18 /81 C XV-14 Inadvertent Operation of 06/30/81R 06/30/82 i
1 ECCS and Chemical and Volume Control System Malfunction that Increases Reactor Coolant Inventory XV-15 Inadvertent Opening of a 06/30/81R 05/01/82 PWR Pressurizer Safety-Related Valve or a BWR Savety/ Relief Valve XV-16 Radiological Consequences 02/01/82R 03/15/82 of Failure of Small Lines f
Carrying Primary Coolant l
Outside Containment i
XV-17 Steam Generator Tube HONE 06/3C/82 (S7S)
Failure (PWR)
(
(DOSES) 02/01/82R 03/19/82C 1
I XV-19 Loss of-Coolant Accidents 11/18/81R 06/30/82 l
(SYS)
Resulting from Spectrum of l
(DOSES)
Postulated Piping Breaks 01/04/82R 04/15/82 Within the Reactor Coolant i
Pressure Soundary 1/ SAR : Licensee Safety Analysis Report-Schedu?ed or Actual (Actual (Status 4b) when date is followed by R) 2/ SER : Staff Safety Evaluation Report -Scheduled or Actual (Actual (status 4a. 5, 7 ) when date is followed by C)
J/ Desiginated number of days from receipt of licensee SAR (Note:
if Licensee SAR is received then date is from receipt of additional information requested)
(3-31)
l C
E D
/
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0 2
N i
J I
5 0
2 e
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0 2
R i
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0 2
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5 8
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1 M
N B
i J
S A
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2
)
T SE N
5 0
3 3
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2 1
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3
(
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C Y
8 N
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H I
4 8
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0 P
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4 G
i UA 2
2 S
t L
t A
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0 0
4 B
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,1-
r LACROSSE QL LACROSSE DE SAR J/
SER Z/
SAR J/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC HO. TITLE SCHEDULE SCHEDULE 111-1 Classification of NONE 04/16/82 Il-1.A Execlusion Area Authority 06/22/81R 07/31/82
($YS)
Structures Components and and Control Systems (Seismic and quality)
II-1.B Population Distribution 06/16/81R 07/31/82 III-2 Wind and Tornado Loadings 08/06/81R 08/30.?2 II-1.C Potential Nazards or 07/15/81R 07/31/82 Changes in Potential III-5.A Effects of Pipe Break on 03/19/82 11/23/82 Harards Due to Structures. Systems and Transportation.
Components Inside Institutional Industrial, Containment and Military Facilities III-5.B Pipe Break Outside 06/29/81R 11/23/82 II-3.A Hydrolic Description 06/16/81R 11/15/82 Containment II-3.B Flooding Potential and 02/28/82 11/15/82 III-6 Seismic Design NONE 09/15/82 Protection Requirements Considerations II-3.B.1 Capability of Operating 02/28/82 11/15/82 III-7.B Design Codes, Design NONE 07/31/82 Plant to Cope with Design Criteria. Load Basis Flooding Conditions Combinations, and Reactor Cavity Design Criteria II-3.C Safety-related Water Supply 06/26/81R 11/15/82 (Ultimate Heat Sink (UHS))
V-11.B RHR Interlock Requirements NONE 03/04/82C (ELEC)
II-4.B Proximity of Capable NONE 06/30/82 Tectonic Structures in VI-7.A.3 ECCS Actuation System NONE 01/29/82C Plant Vicinity VI-10.A Testing of Reactor Trip 06/25/81R 02/16/82C II-4.D Stability of Slopes NONE 08/01/82 System and Engineered Safety Features Including II-4.E Dam Integrity NONE 08/01/82 Response Time Testing II-4.F Settlement of Foundations 03/09/82R 08/01/82 VII-1.A Isolation of Reactor NONE 03/09/82C and Buried Equipment Protection System from Non-Safety Systems, III-3.A Effects of High Water Level 03/09/82R 04/30/82 Including Qualifications of on Structures Isolation Devices III-3.C Inservice Inspection of ot/29/82R 10/01/82 VII-2 Engineered Safety Features NONE 03/11/82C Water Control Structures (ESF) System Control Logic and Design III-4.8 Turbine Missiles 03/05/82R 05/31/82 VII-3 Systems Required for Safe NONE 03/09/82C III-4.D Site Proximity Missiles 09/15/81R 07/31/82 (ELEC)
Shutdown (Including Aircrafts)
VII-6 Frequency Decay NONE 09/21/81C III-7.D Containment Structural 06/29/81R 03/30/82C Integrity Tests l
IX-3 Station Service and Cooling 03/05/82R 05/30/82 V-1 Compliance with Codes and NOME DELETED Water Systems itandards (10 CFR 50.55a)
IX-5 Ventilation Systems 03/09/82R 07/15/82 (MP A-01,A-14)
(3-33)
LACROSSE
~
21 (Cont.)
pil (Cont.)
SAR 1/
SER 2/
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC HO. TITLE SCHEDULE SCHEDULE VI-1 Organic Materials and Post 02/19/82R 04/30/82 XI-2 Radiological (Effluent and NONE DELETED Process) Monitoring Systems Accident Chemistry (NRR B-67)
XV-1 Decrease in Feedwater 03/05/82R 07/15/82 Ell SAR 1/
SER 2/
Temperature. Increase in TOPIC NO. TITLE SCHEDULE SCHEDULE Faedwater Flow. Increase in Steam Generator Relief II-2.C Atmospheric Iransport and 05/15/82 07/15/82 or Safety Valve Diffusion Characteristics for Accident Analysis XV-3 Loss of External Load.
06/26/81R 11/13/81C Turbine Trip, Loss of Con-III-4.A Tornado Missiles 04/02/82 05/30/82 denser Vacuum, Closure of Main Steam Isolation Valve III-4.C Internally Generated 03/05/82R 04/30/82 (BWR), and Stam pressure Regulator Failure (Closed)
Missiles III-8.A Loose Parts Moniroring and NONE 02/09/82C Core Barrel Vibration XV-4 Loss of Non-Emergency A-C 06/26/81R 10/21/81C Power to the Station Monitoring (NRR B-60,C-12)
Auxiliaries IV-2 Reactivity Control S+rstems NONE 12/10/81C Including Functional Design XV-5 Loss of Normal Feedwater 03/05/82R 07/15/82 Flow and Protection Against Single Failures XV-7 Reactor Coolant Pump Rotor 03/11/82R 07/15/82 VI-2.D Mass and Energy Release for NONE 05/15/82 Seizure and Reactor Coolant Possible Pipe Break Inside Pump Shaft Break Containments XV-8 Control Rod Misoperation 02/26/82R 03/25/82C VI-3 Containment Pressure and NONE 05/15/82 (System Malfunction or Heat Removal Capability Operation Error)
VI-4 Containment Isolation NONE 06/01/82 XV-9 Startup or an Inactive Loop 08/25/81R 06/01/82 or Recirculation Loop at an (SYS)
System Incorrect Temperature, and VI-6 Containment Leak Testing NONE 03/31/82 Flow Controller Malfunction (MP A-04)
Causing an Increase in BWR Core Flow Rate VIII-1.A A.
Potential Equipment NONE 02/28/82 Failures Associated with a XV-11 Inadvertment Loading and 02/26/82R 03/26/82C Degraded Grid Voltage Operation of a Fuel (MP B-23)
Assembly in an Improper Position IX-1 Fusi Storage 02/28/82 05/01/82 j
IX-6 Fire Protection (MP B-41)
NONE 09/30/82 (SYS)
Accidents (BWR)
(DOSES) 02/26/82R 05/01/82 XI-1 Appendix I(MP A-02)
NONE DELETED (5-34)
i I
LACROSSE Dil (Cont.)
SAR 1/
SER 2/
TOPIC NO. TITLE SCHEDULE SCHEDULE XV-14 Inadvertent Operation of 08/25/81R 06/01/82 ECCS and Chemical and Volume Control System Malfunction that Increases Reactor Coolant Inventory XV-15 Inadvertent Opening of a 06/30/81R 09/21/81C PWR Pressuring Safety-Relief Valve or a BWR Safety / Relief Valve XV-16 Radiological Consequences 03/09/S2R 05/01/82 of Failure of Small Lines Carrying Primary Coolant Outside Containment XV-18 Radiological Consequences 02/28/82 05/01/82 of Main Steam Line Failure Outside Containment (BWR)
XV-19 Loss-of-Coolant Accidents 02/28/82 07/15/82 (SYS)
Resulting from Spectrum cf (DOSES)
Postulated Piping Breaks 02/28/82 05/01/82 Within the Reactor Coolant Pressure Boundary XV-20 Radiological Consequences 03/12/82 05/01/82 j
of Fuel Damaging Accidents (Inside and Outside Containment) 1/ SAR = Licensee Safety Analysis Report-Scheduled or Actual (Actual (Status 4b) when date is followed by R)
Z/ SER Staff Safety Evaluation Report -Scheduled or Actual (Actual (status 4a, 5, 7) when date is followed by C) 1/ Desiginated number of days from receipt of licensee SAR (Note if Licensee SAR is received then date is from receipt of additional information requested)
(3-35)
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U.S. 80UCLE A*) HEGULATORY CGdhetW40N BIBLIOGRAPHIC DATA SHEET NUREG-0485 Vol. 4 No. 3 i TITLE AND SUBTITLE (A88 Van,me No., etaspraPr, ens
- 2. (Leere e/m*J Systematic Evaluation Program Status Summary Report
- 3. RECIPIENT'S ACCESSION NO.
- 7. AUTHoRfS)
- 5. DATE REPORT COMPLETED
" "'" April I"1982
- 9. PERFORMING ORGANIZATION N AME AND MAILING ADDRESS (tactude tea Codel DATE REPORT ISSUED Office of Management and Program Analysis
" " April I "'"1982 Office of Nuclear Reactor Regulation s_ g,,,, y,,.;
U.S. Nuclear Regulatory Commission t!ashington. D.C.
20555
- s. an, u.ani
- 12. SPONSORING ORGANIZATION NAME AND MAILING ADDRESS (include 1,0 CodrJ P
RK M @
Office of Management and Program Analysis Office of Nuclear Reactor Regulation
- n. CONTRACT NO.
U.S. Nuclear Regulatory Commission Washington, D.C.
20555
- 13. TYPE OF REPORT PE mioo cove mE D (teclusste dams /
March 1-31, 1982
- 15. SU7PLEMENTARY NOTES 14 (Leave c'ehl
- 16. ABSTR ACT 000 words'or less/
The Systematic Evaluation Program is intended to examine many safety related aspects of eleven of the older light water reactors. This document provides the existing status of the review process including individual topic and overall completion status.
I l
17, KE Y WORDS AND DOCUMENT AN ALYSIS 17a DESCRIPTORS 1
l l
17b IDENTIFIE RS/0 PEN ENDED TERMS 18 AV AILAttLITY STAYEMENT 19 SE CURITY CLASS (Thrs report) 21 NO OF P AGES Unclassified Unlimited 2Ynclassified EcuRiTv class (ra,s,,,ri 22 PaiCE 5
N mc POmu 338 (?-??)
- U.S. GOVERNMENT FRINTING OFFICE: 1982 361-302/522
UNITED ST ATES NUCLE AA CECULATO2Y COMMISSICN f
]
W ASHINGTON, D. C. 20665 I
Posvans ano pass paso OPPICI AL SU$lNESS u.s. MUCLs AR RsGULATORY FEN ALTY POR PRIVATE USE,4300 COMusesson L
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