Text

Systematic Evaluation Program Status Summary Report.Data as of November 30,1981.(Buff Book)
	ML20039E492
Person / Time
Issue date:	12/31/1981
From:	; NRC OFFICE OF MANAGEMENT AND PROGRAM ANALYSIS (MPA), Office of Nuclear Reactor Regulation
To:	;
References
	NUREG-0485, NUREG-0485-V03-N13, NUREG-485, NUREG-485-V3-N13, NUDOCS 8201070360
	Download: ML20039E492 (115)
	v • d • e

{{#Wiki_filter:.. NUREG-0485 Vol. 3, No.13 November 30,1981 ,g SYSTEMATIC EVALUATION PROGRAM ho;m" %c e i N.k STATUS

SUMMARY

REPORT > !a e s.jd n u_ 9$0 s,a co UNITED STATES NUCLEAR REGULATORY COMMISSION ,, s " ". oq, h s..-

Available frorn NRC/GPO S.iles Prenp ain Snperintenif. nt of Documents Government Printing Of hte tVashington, D. C. 20402 A year's snbscription onsists of 12 issn, s for this pnblicatino. S,9 " copies nf this publication 1 are isva,'ablo from National Technical information Sorvire, Springfieltj VA 77jgj Microfit he of sin 9 e copigs a,e f available froin NRC/GPO Sales Prograrn (Va'.hington, D. C. 20555

NUREG-0485 Vol. 3, No.13 November 30,1981 l SYSTEMATIC EVALUATION PROGRAM l STATUS

SUMMARY

REPORT j Prepared for: 0FilCE OF NUCLEAR REACTOR REGULATION l Prepared By: 0FFICE OF MANAGEMENT AND PROGRAM ANALYSIS UNITED STATES NUCLEAR REGULATORY COMMISSION h 7. lh A n/irlri tl f l#f6f$ 5 i For Sy ma ic Eva u ' tion Program Branch Op igR r ranc O fi e f u lear Reactor Regulation O fi e of u ear eactor Regulation )

l l TABLE OF CONTENTS SECTION I SECTION ll SECTION Ill 1-2 to 1-3 BIG ROCK POINT 2-2 to 2-5 PALISADES 3-2 to 3-3 SEP TOPIC LIST DRESDEN 1 2-6 GINNA 3-4 to 3-6 DESIGN BASIS EVENT 14 DRESDEN 2 2-7 to 2-10 DRESDEN 2 3 7 to 3-10 GROUP DESCRIPTION GINNA 2-11 to 2-14 OYSTER CREEK 311 to 3-13 DEFINITIONS OF STATUS 1-5 HADDAM NECK 2-?5 to 2-18 MILLSTONE 1 3-14 to 3-17 LACROSSE 2-19 to 2-22 SAN ONOFRE 318 to 3-21 SEP TOPIC

SUMMARY

1-6 MILLSTONE 1 2-23 to 2-26 BIG ROCK POINT 3-22 to 3-25 STATUS REPORT OYSTER CREEK 2-27 to 2-30 HADDAM NECK 3-26 to 3-29 ALISADES 2-31 to 2-34 PROGRESS TOWARD 1-7 YANKEE ROWE 3-30 to 3-33 COMPLETION (Graph) SAN ONOFRE 2-35 to 2-38 LACROSSE 3-34 to 3-37 YANKEE ROWE 2-39 to 2-42 INTEGR ATED PLANT l-g SAFETY ASSESSMENT SCHEDULE SEP TOPIC STATUS BY 1-9 REVIEW DIVISION (Summary Table) SEP TOPIC STATUS BY 1-10 to 1-11 REVIEW DIVISION (Graphs) SEP TOPIC SUBMITTALS 1-12 thru 1-13 BY LICENSEES (Graphs)

Z O PO Lu &)

SYSTEMATIC EVALUATION PROGRAM TOPIC LIST N :( e f i r( E TylC e fif ti T'PIC e J Lill !.1 A. I sc los e ca area Awtwority r saa. or, r e i g g g,,

g. 7ornae mis. ilei 162 vesct tutty Control System including Functional Jestgn and Protection Against 51ngle f at tures

h. D ap t at ica 0 *stra t~t wn

,14-3 B+ Jet Pugs operating Indications . # ot emial *4a arS or (Pan#s s e Fut eet ist I nost r i a t. and a t t itary t ac ilit ie5 g, tut ne Mis s iles carach D.e t o f raaurt at ica. L ast it st,na l v-1 Cogliance alth (odes and $tandards (10 Cra 111 4 C. I nt erca lly Gea* rat ed "'ssil*% gg,gg,) 11-2

a. Severe.eatner Pee % eca 4-2 Applicable Code Cases

8. unsite "eteorological mesureynts Peg ar as 4-)'

Q verp ressert gation Protection C. Atacs;*eric Tranmet and C tf f ssioe (Parac. W-4 Plotng and Safe E nd Integrity teristics f or Accidert Acalys o t., g,te pecstaity missiles (laclude rig Aircraf t,' V-5 Reactor Coolant Pressure Boundary (RCP6) availaoility of Potearcicqtcal Lata ia the g gla a, g e f ects of e tge Brea6 en St ructures. System teak age. Oet ect ior. Coat rol 8 oom and Cos oneet5 1 ns i oc (ont a t noe nt ! !- 3 . Hydrologic Oescriot ton

g. P tpe Bream outside Coatainrent V-7 Peactor Coolant Purp Overspeed B. I loodi ng Potential and Protect ion Reg.tr,.

W-8 5tese Generator (5G) Integrity cent s !!!.1 A. Inservice Inspect ioc. Inc1 ding Prestressed V-9 Geactor Core isolatte,n Cooling System (Ban) Casabiltty of 0;eret teg Plant to Cope Concrete Containrent s with L itner Grouted with esign Basis F looding Condit u,M or Ungr%ted Tenen v.10 A. a.e4 Heat Eschanger Tube Fat tures m. 54f ety-related m ater 5.00 y Gltimate meet 1

s. Design Codes. Ces t gn Crtteria. Load

8. #MR Deliebtitty 51 '* ( A))

Coccinat %ns and kesctor Cavity Gesign Critert a W-11 A. Requireaents f or isolat te.t of Mt gn and Low !!-4 ,colog and Seismology Pressure Systems L. Celatinition of Prestressed Concrete Con-Tect onic Province taintret Struct res

8. RPR Interlock Requirenents B. Prostetty of Capable Tectonic St ratures C. Cor.t ai nment Structural integrity Tests V-12 A. kater Purity of Boiltag mater Reacto*

in Plant Wicinity Primary Coolant !!!-d A. (rose Parts Ponitoring and Lore Barrel C. wistorical Seiwic it y e st r i s < x, M i les r* 8-13, o ter Hammr P lent ,idration monit ori n g B. Contret R od Dri ve Meceantsa Integrity W!-1 Organic m tertals and Post Accident a 5t son lity of Sicori C hes* s t ry a C. Irradiat iovi Dama ge, use of Sensit szed 5tainless 5 teel a*d Isti9ue Neilsta"Ce

2

. A. P rebsure-$uppression Type Ball Coetainments L. C am ! *t e p t ty B. Subcovertsent Analysts . U. Core Lupsorts and f uel letegrity T. Sett ferret of Iou dat ions and Swriec n C. ice Condenser Containcent ( p et !!!-9, $wppcet Inteytty D. Pass and Energy Release for Possible Pipe Ill iG

a. Therae l-Overload Protection f or m tors of o

Breda Inside Contain+nt lli-l t isssif icat ion of St rt,ct res, tw4 crents and "ut or-op era t ed v a l vas ky%t e8is ( se ismic and h ali f y ) B. Piet e lywheel Integrit y V[.3 Contain"ent Pressure and heat Reamval Ill-2 e a ad aad Torfiado L udding Capability 111-3 A. E f f ect s of H iir mat er L evel on St ruct ures t 'n" Pu1 S **d L'i schar# V a l ves v i-4 Cont.inrent isolation System !!!-11 C oa onent I nt e gri t y VI-5* Coccustible Gas Coctrol

9. Structural and other C amequemes (e.9 i lvedi aq of laf et y-helated t yuieneat er V I-6 Coetatnwnt Leda Testing P awrat s ) Cf F ailure of uNerdra i n ),s t em i!!.f /

t nviron efital Qualtf ication of Saf ety Related t ga ?prieat

f. Inser vice I nspect ion of wat er topt rol 5true 18-1 8 4;cratlo" =1th t e's TPan All Loo;;s In-Service tu es r

M 12

SYSTEMATIC EVALUATION PROGRAM TOPIC LIST MCf II M tqp]C 4 tl t(( te ll # f l Ti t

1. [CCS s -e valuat ion to Accou t f or i nc reased ygg.g

!rstruments f or "onitoring Radiation and Process IV-5 L os s of N ormal F eem at er F low t l-1. A e n bessel Pead Iert eratu e verlaDies Daring Acciderts IV-6 f ee*ater System Pipe Break s Inside and Outside Containeent (PwR)

2. Upper P leaue i nject '""

Wil-e f redemy Cecay

3. ECCS Actuat ton System W il-F Acceptability of $ wing t!ui Design on l'#-4 yy.7 PeaCror Coolant PuT Rotor Seishre and Plant s Acactor Coolant Puy Snaf t Bream

4. C ore 5 tray 4 r t le i f f ect i veness 3

u l t i-l A. Pct ent tal t quipment F at lares Assm at eJ with E d-8 Control Rod Pisoperation (Systee Malfunction W!-l.B E 5F 5.*tchover f rom i n;*ct son t o Recircu lat ion a De9raded GriJ Volta 7 ar Uperator [rrer) ode ( Autoowt tc (CC5 sicalignent ) m v '! ?-? Ualite (wrgemy Pmer Systeer. - Diesel s v. 9 5t artup or en t rvctiet L oop or s ec t rcu lat ion v i-7.C iCC5 Single Failure C r i t er

oe a nd N ew re-(,ene r a t or L oop at an locorrect 1*rterature, and F low ments f or L ore tea mrt > "wer t o v al ves Controller Malfumtion Caustog an Imrease in including Indeper,ence d I nt erlock s on Will-3 A. Stat ion Battery Caracity f est Rew rcernts pa core F lom eate av-10 Chemical and volume Control System Malfw ctioi

8. DC Paner 5Fstem Bus volt ar M*itoring and that Results in a Occrease in the Boron Concen-Ann nc t at ion trat ton in the Reactor Coolant (Pead )

1. Appendia IL - F lect rical Instruentation u

and Control (LIC) lic-revlem a vill-4 1lectrical Penetrations cf Reactor Containarnt IV-11 Inadvertent Loading and Operatton of a Fuel 2 Failure mode Analysis - ICC5 Ancely in an Imroper Posttton

3. The i f f ect of G otl t oop !solatinn valve a v.12 Spectrum of Rod Ejection Accidents (PWR)

Closure During a t W A on [(L5 Perf orsence I s -2 Overnead Nandling Systems - Cranes v i-7.D Long Term Cooling - Pasu re F ailures (e.g.. 3 V -13 Spectrum ci Rod Drop Accidents (BWR) F looding of Redundant tors onents) 15-3 Station Service and Coultng heter Systems Iv-14 Inadvertent Operation of ICCS and Chemical W i-7.E FCC5 !vm Design and f est f or Rectrculation 11-4 Boron Addition System and Volume Control System Malf unction that e Pode t t f ect ivene% increases Reactor Coolant Inventory g v i-7.f Accumulator isolation Valves Power and Control 3W-15 , Inadvertent Opening of a N Pressurtaer Safety-

System Design

11-6 f ire Prot ect ion ggy gy v !-8 Coct rol Room H4Ditablitty a ian ec ter 5pdem IV-16 Radiological Coasequences of f atlure of $siall Ltnes Carry nng Pr mery Coolant Outside Contata-V !- 9

ain Stea9 L ine Isolat ion Seal System - IIS 31-3 APP'*d' ' I ment V !-13 A. Testing of Reactor T rip System and E ngt ecered g g.?

p a,1,ological (t f f luent an:t Prtwen) Panit oring IV-17 Steae Generator Saf et y f eatures Including Rewonse f

s ntems Tube Fa61ure (P R) l lesting l

1111-1 t anduct cf heret tans IV-18 Radiolog1 Cal Consequences of Matn Steae l [ B. Snared E ngineered Saf ety F eatures. On-s it 3 Line Fativre Outside Containent (BA) [mergency Power. and 5ervice Systelis f or agll.1 Saf e,ards/ indust rial Wu ity l r "ultiple Unit Facilities R W-19 Loss-of-Coolant Accidents Pesulting f rom AW-1 Decrease in F echa* cr Teterature, lacrease in Spectrue of Postulated Piping Breaks within Vil 1 A. Isolation of Reactor Protection System f ro* 6 ee*at er I low, lacrease in 5 team Flow and the Reactor Coolant Pressu e Boundary r Mon-5af ety Syste s, including Qualtf tcat to'Is i na dvert ent Opeaing of a 5teae uenerat or kelief m of Isolation Devices or saf ety v alve IW-20 Radtological Consequences of Fuel Damaging Accidents (Ins 4de and Outside Contatnaent) B. Trip Uncertaint y and Setpotat Analysts Revtew g g.2 .ect rum of Steam System P iping I ailu es e nside 21' $ pent f uel Can Drup Acctdents r I of Oterating Data Base a nd Out s i de of C ont a t uent (Pw) AV-Amichau ansunts met m an Vl!-2 [ngineered Saf ety Features (L5F ) System Control R W-3 t oss of ( sternal Load, f urtn ne Trip. L oss of t op c a nd Des i gn Condenser vacuum, C losure of pa.n Ste. 4 a sola-XV-23' Multiple Tube Fattures in Steam Generators t son valve (hea). and steam Pressu e Rewif ter r VII-3 System Required f or $4:e Shutdown l ailure (Closed) yy,7,' L, ,, g j g g,g p g,,, py A4 hn t o De P at ton ,]- KV1 Technical Specifications vil-4 I f f ect s of Failure in %9n-Saf et r kelated 3 'ystem on Selected I agineered saf ety s eatu es r IVil Operat ional CA Progras

Topic deleted from SEP program due *o duplication by Three Mile island (TMil NRC Action Plan. Unresolved Safety issue or other SEP Topic per May 7.1981 letter from G. Lainas to all SEP Lece 1-3

DES GN BAS S EVENT REVIEWS THIS SECTION DEFINES DESIGN BASIS EVENT (DBE) REVIEWS FOR THE ELEVEN SEP FACILITIES 4- 'J!'.!5* 9.E *:6! '5? %D L 'N* ?! 98:C LIS'. a 'r e"J 'e*1 **32. Aj :'ce t. aailrea.51_ert, 6*oun a ,,3 '.?J

n ",r:

':T E m ;r:; L s -~ wr.. I s i.1 Le:res,e ia f eedwa ter t eN e ra t ore rx e.-) Decredhe ir 'eew a t e r terpe stpe L a-3. !"c reate 16 B fe ec. a t e".f l >=

ycro to9'c of 5(riptio" prc tec tion JEs

..-3A Ja _ s e-lN eea5e *

f ees.ater f%

s.) 1%rease

e.... - fla

!-3 e f looding Detect'al and 8.-

A rea;e 1* s t es-f, s. a..a Ma' t.a C' 1c.as t i.e loor s' d f % <eavirer+ets (catability cf operetteg so-

a:vertert occateg cf stes-( c* t r:' ler ma l f ar: t t oe slaat to cope witn cestga basis floodin9 ge + atte rel'e'< 5a'et, va l ue a, 3 Iras erteat closgre cf main stes" c ond i t ion )

8cv St a't.. c' Ma:!$.e tec: tsclat ce valve

-3 C ta'ety related water supply (ultimate S n e- +a!'#t tior ceas m teet s'e6 )

s.- i ur 8.- kost Cf a s teraal 'Ca$ e <. 8.- . Si, 6. 8 en ter'a' ica: 3.-3 Turt tee trip ti : s r. l

-4 A

ec tor,1C p ro v i rt( e t.'

'#s tee t r $. s.-3 Losi of C C 'sceas ce v ac up I.4 B Pron iet ty of capatie tectonic struct res be 1 6245 C# c ae 3ea n er v a : sp a.< 5!,a" prei%wre reg.lat0F f ailure Pea r plant

e-i'ea' E reb 5/e reg a' at:r f aile'e Is

LC5% C# f f *$ water flom II-4 C se15 tor 1 Cal 6eib81 city witain 200 eiles Is'-

f e -f .. iC f eeJoste* f i O= o' pleet f f f 3 mat ** s 5te'" Di;f Dream i r; ; .g r s,- 4adi ?0gt;sl C0asehe'5(fi C# 4 4 $tattlity Cf S T 0ff 5 Wa t e $ t eam itre Fai'gre Cstg1de I". S t e a-l i e, c rea. -e t ue c a ta no c.. C oe t s i are r w; m r,t.pA!;a . s, m Tornaso wissiles 3 -2 5 tes" Ie t re en 0.t s Me c r t a ' a"e 2% PL ^* [ 5- ' ~ ? ;l-4 ( .ettreally generated ES 51t le% ('c wig. 84 Lost c' AC Dowe* t 3 5 t a t 1 De ?.s . :-4. C "v ting ot ss t les r 4 i.i 2_ Is*4 LO11 C' LC PDwer to Stati e s.m i i ' ad es l ] ].4. " Site premie 1ty eissfles (including a.m i li a< ici aircraf ti Gr.3, i n.- L Oi5 ef 4*:ed Cocl ea-t f'o* f r:e3 c0CT a't

1:e S..'

Pe t ra*y D/5 rotor 191 Z#t ^- lli-2 wind and toreado load 1*9 wNS l

- ty

.C5 5 C* 3 F.- Pr *a'f p#., PCtCr Sei2#e f-Fr Pa 'y P."'; 5' a #! treaa a Fr e*ary f a*; %* sit D re a.

K _e.

A.- tenCD*trc i led rgd a5geet ? y I thgeg.al f 4._ -a: C# '- silta r::0 ante : re a t DO=*

4 C rem a I *
Pow er re-

,a l

8e.

Jetrailt.2 rod ai$rtl a lt a 10m. : Ile2 ft ! e55ert y w i t*C*ama*

y power Start.wp d'ana 9 1% Dawe' 5 tart.g; 1,.a C or t *Ol *2d F'5Crerati0e r. C;r. ' rog * *5 Cpera t ' v e e in 1) 5:K tr# Of rod dec; a:C odem!1 SLP: tr J" C' rog e,e:!1 pe a: c i cert 3 r $3e tr# cf 105$ C# CoCle*! a Cide

ts e '.,g a

g ;.J _ e .,g. Er' Es 10 lag

Cal C0%

f Fuel .s n.2 4 el0;::al C0anepe-:es Ce re cd 4;wg Ace 13,e@eMCe$ Cets (tesise ae_ ) Oa~aitP; ACC f dert5 ( tatice a*C Det19 de Certriv'e** ) Dats ' de Coe tairree Grod '

a *ve' tert ODee leg Of Be7 l a #e

y -

a ,raSeer te*! 00ce'*9 C 4 g 8.- s 8 Na reI sef walve Drea5< r 7 2er relief ma've w' , s 3,. ]ra. erter! Operation cd ((;$ cc C o S e4t #w'5Clice t aa' C a Ae5 ar ."f si_3 j 36-Ira 3verter? ISaif ey s'id CDeration C8 inc reage in C00'a*? ' r:ve

t 3*y a f eel est e"t ly

'e a'i imf rLper o':.i.M %; t a;;11(a$ le tc Pm4 se'~ ~ ; i:1 st ac.licaele to B.4 w If _8.],, 's $ ted" *,**e

a to r 'st.e F a i t see e

l 14

STATUS DEFINITIONS G - Generic 4a-Draf t SE Received From Review Branch These topics are being evaluated as part of on-going NRC generic review effort. The ongoing This status is used for internal NRC tracking of generic review and the SEP topic review will be topic review progress. The status indicates that i clo:ely integrated to improve the effectiveness a draft topic safety evaluation is under mange-and efficiency of these ef forts 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 - Delete. (S A R) in accordance with SEP redirection. (See Eisenhut letter to SEP owners of January 14,1981) These topics have been verified as not applicable The SAR is under review and a Final N RC safety to the design of a specific plant or ar being evaluation (status 7)is being prepared. Draf t SE duplicated by the N RC TMI Action Plan, will not be issued for topics with licensee SAR submittal. Unresolved Safety issue or another SEP Topic per the May 7,1981 letter from G. Lainas to all SEP licensees. 5 - Draft SE Sent to litility 0 - Topic Not Started A draft topic safety evaluation has been formally transmitted to the licensee for their review and This status indicates that the review of the topic certification of the accuracy of the described has not started. f a cility. Licensees may comment upon N RC 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 draf t SE has been reviewed and licensee toqic evaluation is r.ot available and that ques-comments if any have been formally transmitted tions have been developed and sent to the SEP to the NRC. branch. 7 - Topic Complete 2 - Questions Sent to Utility The NRC topic evaluation has been completed and a final safety evaluation issued. A topic is completed The questions developed in the previous status in several ways: (1 ) The licensee has responded have been formally transmitted to the licensee that the N RC draf t safety evaluation (i.e. status 5) as a request for additional information. is correct, or (2) the licensees comments on the NRC l draf t safety evaluation (i.e. status 6) have been re-3 - Question Response viewed and if appropriate incorporated into the j Received by N RC final safety evaluation, or (3) the licensee has not res onded in the time requested, thus concurring The licensee has formally responded to the informa-that the draft safety evaluation is correct, tion request issued by N RC regarding the topic. 1-5

l { l l l l l i SEP TOPIC STATUS

SUMMARY

REPORT ' \\ \\ NUMBER OF QUESTIONS QUESTION DRAFT SE SAR SE N TOPICS TOPIC RECEIVED QUESTIONS

RESPONSE

RECEIVED RECEIVED DRAFT SE

RESPONSE

TOPIC \\ GENERIC DELETED NOT FROM SENT TO RECEIVED FROM FROM SENT TO RECEIVED COMPLETE N CG) (X) STARTED REVIEW UTILITY BY NRC REVIEW LICENSEE UTILITY BY NRC (7) PLANT NAME \\ (0) BRANCH (2) (3) BRANCH (4b) (5) (6) N (1) (Ga) N 'ALISADES 4 47 1 0 0 2 2 2 4 to 65 GINNA 4 45 1 0 0 3 5 4 1 17 57 DRESDEN 2 5 50 9 0 2 12 0 14 5 6 34 OYSTER CREEK 5 54 4 0 5 2 5 22 5 6 29 MILLSTONE 1 7 51 0 1 1 8 1 21 6 3 38 SAN GNOFRE 5 48 2 2 2 11 3 13 15 2 34 BIG ROCK POINT 4 53 12 0 3 16 3 9 3 2 32 HADDAM NECK 7 47 6 0 1 18 3 22 1 8 24 YANKEE ROWE 6 47 to 2 6 14 0 19 3 4 26 LACROSSE 4 54 20 1 10 6 3 12 2 1 24 DRESDEN 1 TOTALS THIS MONTH 51 496 65 6 30 92 25 138 45 59 363 TOTALS LAST MONTH 85 466 76 8 33 97 28 132 48 53 344 w NOTE: Totals do not include Dresden 1 see page 2-6. Also included i s May 7, 1981 deletion letter to all SEP licensees, see footnote page 1-3. 1-6

SYSTEMATIC EVALU ATION PROGRAM PH ASE lil/ G C A'~ -1/ Not including Dresden 1 Progress Toward Complet.ion ACTUAL 10,0% 100 [7 1-82 / ,/ 90 /p /, / 80

l3%

75% y 7I 1 month ~ 70% 70 67 72%

61 */

/ / H Note: Prior to November 30,1981 the 60 % weighted percent did not include 2 60 30-81 generic topics m the progress i j d /. gr f toward completion. W p- / 54% 50 f W / 50 % f p = 44% 9 f W 40 / 42% 5 / 40 % / 36% 30 - J 30% (estimated) The plant topic overall completion status (percent complete) is calculated Status Weighting Factor i-based upon the number of topic reviews to be performed (not including ~ X Not included deleted topics) and a weighted average of current topic review status. G,0 20 The calculation is performed using the following formula: 4a,4b 80 % 5,6 90 % Percent Complete = Sum of Topics in Status x Weighting Factor of Status 7 100% 4 10 Sum of Topics 4 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-82 FY 81 1-7

l l l E LU o D E HC S ) RAS P I ( TR O P E R dee T d r N i u E vt M ou ) S rF 8 S P E e 1 S eh ( S BT A on Y TI TE F AS TNA L P D E TAR G ET N I ff

SEP TOPIC SVATUS by QEVIEW DIVISION

SUMMARY

TABLE PLANT PALISADES GINHA DRESDEN OYSTER MILLSTONE SAN BIG HADDAM YANKEE LACROSSE TOTAL 2 CREEK 1 ONOFRE ROCK NECK RDWE POINT (IAPM) l/ Michaels Wang Cwalina Fell Persinko McKenna Scholl Brown Wang Michaels NO. OF TOPICS 137 137 137 137 137 137 137 137 137 137 1370 DELETED 2/ 47 45 50 54 51 48 53 47 47 54 496 APPLICABLE 90 92 87 83 86 89 84 90 90 83 874 e 54 / 36 / 31 / ' 31 / 27 / 31 / 26 / 23 / 25 / 21 / 305 / DL / / / / / / / / / / / / $7 / 39 / 36 / 35 / 37 / 40 / 38 / 38 / 38 / 35 / 393 TECHNICAL / / / / / / / / / / / 15 / 15 / 7 / 4 / 9 / 6 / 3 / 4 / 6 / 3 / 72 / REVIEW DOE / / / / / / / / / / / / 18 / 21 / 22 / 20 / 23 / 18 / 17 / 21 / 21 / 21 / 200 ASSIGNMENT 1/ / / / / / / / / / / / 13 / 29 / 8 / 17 / 15 / 14 / 9 / 4 / 2 / 4 / 115 / DSI / / / / / / / / / / / / 15 / 32 / 29 / 28 / 28 / 31 / 29 / 31 / 31 / 27 / 288 / / / / / / / / / / / 82 / 80 / 46 / 52 / 51 / 51 / 37 / 31 / 32 / 28 / 492 / COMPLETE / / / / / / / / / / / / 90 / 92 / 87 / 83 / 86 / 89 / 84 / 90 / 90 / 83 / 874 / / / / / / / / / / / VARGET 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 l/ Division of Licensing Integrated Assessment Project Manager 2/ Deleted as not applicable, or duplicated by USI TMI Action Plan, or another topic. 1/ These schedules and assignments are consistent with NRR FY 1982-1984 Operating Plan. l _/ l

No. Completed / No. Assigned l/

l 1-9 STATUS AS OF HOVEMBER 30, 1981 s

PROGRESS OF TOPIC REVIEWS DIVISitBI F LIGNi!IC T71C5 49 TMIET '~ g =,, - """ "" ~ MIS -- ,,.wa "'" # ACTUAL E 3W h 5-a-- 155 -- IN -- ag i e i JLM JLL ALE SEP (ET lef KC JAN FIB MAR APR MAY JtM Jul/Dec IOITH l 3 4 3 16 Tarpt 10 14 20 17 7 PER MONTH 1 10 3 4 7 ActW Tarpt 309 323 343 360 367 370 374 377 393 CUMULATIVE 281 291 294 298 305 cte PROGRESS OF TOPIC REVIEWS DIVISI(31 F DCIEDt!E TT!CS 250 TMtGET ~ ~ ~ g /, ='" e # ACTUAL is -- y / / / so -- ,/ .J 3 JtM JLL ate SEP KT IOf KC JAN FEB MAR APR MAY JtM Jul/Dec IOITH Target 2 2 40 36 21 6 2 7 11 FER MONTH 4 0 2 0 0 Actual Tarpt 75 77 117 153 174 180 182 189 200 UWM Actual 70 l 7 72 72 72 1

PROGRESS OF TOPIC REVIEWS DIVISION & SYSTEMS INTF'; RATION TOPICS 358 TARGET 388 -- ,====*#.w=* 258 --- p **** ACTUAL I /s' s' / 2ss -- / ]4 / ~ / 158 -- y ,/ ISS -- 58 -- i e i i e i i JLN J1L AUG SEP DCT MN DEC JAN FES MAR APR MAY Jim Jul/Dec Target 28 35 35 30 15 15 3 10 6 PER MONTH Actual 11 3 to 14 27 Target 132 167 202 232 247 262 265 275 281 CUMULATIVE Actual 61 64 74 88 115 PROGRESS OF TOPIC REVIEWS 5_ i l mat marr TT!CS 120 TAKET ~~ gg _. p **' j. ~ ~ ~ g.. p==" 7N -~~ p# / / aus -- p/ 3ss -- 3__ 15 -- i g D Jtt ALE SEP OCT MN [EI JAN FEB MAR APR MAY D Jul/Dec InffH Target 40 51 95 83 43 24 9 20 33 PER MONTH Actual 16 13 16 20 34 Target 516 567 662 745 788 812 821 841 874 CUMULATIVE Actual 412 425 441 458 492

LICENSEE TOPIC SUBMITTALS DIVIS!se OF LICD61NG SENITTALS 40 TARGET ~ g----- p" / m-- 7 / / ,5 -~ / ~ ~ / / 5-~ / = a e JLM JLA ALE SEP KT 90f N.C JAN FEB MAR AMt NAY Jtse JtL lem6 8 5 8 5 5 2 1 0 0 0 1 0 PER MONTH Actual 0 3 1 1 4 I 1 N 31 33 34 34 34 34 35 35 CUMULATIVE Actual 0 3 4 5 9 N h LICENSEE TOPIC SUBMITTALS DIVISION OF DCIESt!NG SLHeITTALS 78 TARCET g-- ACTim. /"/ ~ / 48 -- f 38 -~ [ / / / Jlse JtL AUG SEP OCT IOf DEC JAN FEB NAR APR MAy Jty jtg toeTHS Target 1 9 14 11 5 12 1 5 1 0 0 0 0 PER MONTH Actual 1 8 1 5 7 Target 1 10 24 35 40 52 53 58 59 59 59 59 59 CUMULATIVE Actual 1 9 10 15 22

LICENSEE TOPIC SUBMITTALS DIVISION OF SYSTOS INTEGRATION R as!TTALS 15 p"----- TAMEET / / W-- ( 48 -- 28 -- / Jth AL ALS SEP OCT NOV DEC JAN FEB MAR APR MAY JtM JtL IDfTHS 0 0 0 0 PER MONTH Actual 1 10 3 31 3 Target 1 15 61 68 78 88 91 94 94 94 94 94 94 Actual 1 11 14 45 48 i LICENSEE TOPIC SUBMITTALS Tofu. enoxCT 1 IMINITTALS 2N TAAGET l# 175 -- 158 -- [ g / 125 -- [ Ise -- / / ~ ~ J 25 -- Jtm JtL Aur. SEP OCT NDY DEC JAN FEB MAR AP:: MAY Jt34 Jtt DDffMS Target 2 31 65 26 20 27 4 8 4 0 o i o PE R MONTH Actual 2 21 5 37 14 Target 2 33 98 124 144 171 175 183 187 187 187 188 188 Adul 2 23 28 65 79

Z O O W 00

BIG ROCK POINT FACILITY: BIG ROCK POINT 1 TOPIC HO. REVIEW STATUS REMARKS DIV/SR LICENSEE: CONSUMERS PCWER 11-1 A. DL/SEPB 7 CPCo to NRC 07/02/30 REGION / LOCATION: 4 NILES NORTH EAST OF CHARLEVOI, MICH. II-1 B. DL/SEPB 7 CPCo to NRC 09/02/30 DOCKET NO. 05000155 II-1 C. DL/SEPB 7 NRC to CPCo 05/13/81 POWER CAPACITY: 0240(THERMAL) 067(ELECTRICAL) II-2 A. DSI/AEB 7 HRC to CPCo 08/03/81 OL NUMBER: DPR-6 II-2 B. X HRC to CPCo 05/07/81 H.S.S.S. GE. II-2 C. DSI/AEB 0 A/E FIRM: BECH. II-2 D. X HRC to CPCo 0S/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL II-3 A. DE/HGEB 3 CPCo to NRC 08/21/81 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD II-3 B. DE/HGEB 3 CPCo to NRC 08/21/81 OPERATING REACTORS PROJECT MANAGER: W. PAULSON II-3 B. 1. DE/HGEB 3 Site Visit 07/16/79 INTEGRATED ASSESSMENT PROJECT MANAGER: R. SCHOLL II-3 C. DE/HGEB 3 Site Visit 07/16/79 II-4 DE/GSB 7 NRC to CPCo 06/08/81 ELY FOR STATOS CODES l II-4 A. DE/GSB 7 NRC to CPCo G6/C8/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B. DE/GSB 3 l FRCM 'EVIEW BRANCH X - DELETED II-4 C. DE/GSB 7 NRC to CPCo 06/08/81 4b-SAR '.ECEIVED FROM C - TOPIC NOT LICrHSEE II-4 D. DE/HGEB 45 CPCo to N P. C 10/05/81 STARTED 5 - DRAFT SE SENT II-4 E. X NRC to CPCo 11/16/79 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F. DE/HGEB Gb CPCo to NRC 10/19/81 6 - SE RESPONSE RECEIVED j 2 - QUESTIONS SENT BY M2C III-1 DL/SEPB 2(Sys) NRC to CPCo 05/00/80 i TO UTILITY DL/SEPD 7(ELEC) NRC to CPCo 08/19/81 l 7 - TOPIC CCMPLETE 3 - CUESTION RESPONS: III-2 DL/SEPB 3 CPCo to NRC 07/09/81 RECEIVED BY NRC (2-2)

p y, ) y y iBIG ROCK POINT a /,._, b) a t ~#- TOPI?jMC#. REVIEW STAPUS / REMARKS

I?

TOPIC hl. ep DIV/BR REVIEW STATUS REMARKS DIV/BR [ *. 4 - fII-3 A. L E/ S Ef,. 3 CPCo to NRC, 08/09/80 .,121-10 8, X NRC to CPCo 11/16/79 ~ III-3 B. X 'NRC to CPCoe 12/26/80-fIII-10 C. X NRC to CPCo 11/16/79 l '[, ' ~' III-3 C. DE/AGEB 0 III-11 X NRC.to'CPCO 05/07/81 III-4 A. DSI/ASB 0 l' III-12 X NRC to CPCo. 05/07/8t ~- l III-4 B, DE/MTEB G IV-1 A. Dl/SEPB 7 hRC to CPCo 10/08/81 l II-4. C. -- DSI/ASB 0 IV-2 DSI/ICSB 3 HRC to CPCo 05/07/81 i 'IV-3 X NRC to CPCo 05/04/81 ITI-4 D. CE/SAB 0 ,j III-5 A. DL/SEPB 3 V-1 DE/MTEB X NRC to CPCo 11/27/81 III-5 B. DL/SEPB -2 NRC to CPCo .01/04/80 V X NRC to CPCo 11/16/79 ' III-6 DL/SEPB 3 CPCo to NRC 07/27/81 V-3 X NRC to CPCo 05/07/81 III-7 A. X NRC to CPCo 05/07/81 V-4 X NRC to CPCo 05/07/81-III-7 B. DL/SEPB 3 CPCo to NRC 07/09/81 V-5 DL/SEPB 7 NRC to CPCo 09/30/81 III-7'C. X NRC to CPCo 11/16/79 V-6 DL/SEPB 7 NRC to CPCo 03/05/80 III-7 D. DE/SEB 3 NRC to CPCo 08/09/79 V-7 X HRC to CPCo 11/16/79 III,-8 A.. DSI G NRC.to CPCo 05/07/81 V-8 X NRC to CPCo 05/07/81 III-8,B. X NRC to CPCo 09/26/80 V-9 X NRC to CPCo 11/16/79 III-8 C. DL/SEPB 7 NRC to CPCo 02/05/80 V-10 A. DL/SEEB 7 NRC to CPCo 10/09/79 III-8 L. X NRC to CPCo 05/07/81 V-10 B. DL/SEPB 5 NRC to CPCo 05/13/81 III-9 X NRC to CPCo 05/07/81 V-11 A. DL/SEPB 6(Elec) CPCo to NRC 11/11/81 III-10 A. DL/SEPB 7 NRC to CPCo 08/03/81 V-11 B. DL/SEPB 5(Sys) HRC to CPCo 05/13/81 7(Elec) NRC to CPCo 08/19/81 (2-3)

BIG ROCK P0 INT TCPIC ND. REVIEW STATUS 3.EMARKS TCPIC ND. REVIEW STATUS REMARKS DIV/ER DIV/BR V-12 A. DL/SEPB 7 NRC to CPCo 10/03/79 l VI-7 D. DL/SEP3 7 NPC to CPCo 03/1//18 I V-13 X NRC to CPCo 05/C7/81 l VI-7 E. X NRC to CPCo 05/C7/01 l l VI-1 DE/CEB 3 CPCo to NRC 07/12/79 l VI-7 F. X NRC to CPCo 11/10/79 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 l VI-2 C. X NRC to CPCo 11/16/79 VI-10 A. DL/SEPD 0 VI-2 D. DSI/ CSS 3 CPCo to NRC 04/02/80 VI-10 B. X NRC to CPCo 11/16/79 VI-3 DSI/CSB 3 CPCo to NRC 04/02/80 VII-1 A. DL/SEPB C VI-4 DSI/C'S C(Sys) l VII-1 B. DL/SEPB 7 HPC to CPCo 08/17/78 DL/SEP3 5(Elec) NDC to CPCo 11/24/81 l VII-2 CL/SEPB C VI-5 X NRC to CPCo 05/07/81 VII-3 DL/SEPS 5(Sys) NRC to CPCo c5/13/31 VI-6 DSI/CS3 G NRC to CPCo 05/07/81 DL/SEPS 7(Elec) NRC to CPCo 08/19/81 VI-7 A. 1 X NRC to CPCo 11/16/79 VII-4 X NRC to CPCo C5/07/81 VI-7 A. 2. X NRC to CPCo 05/07/81 VII-5 X NRC to CPCo 05/07/81 VII-6 DL/SEPB 7 NRC to CPCo 09/21/81 VI-7 A. 3 DL/SEP3 0 VI-7 A. 4 DST /RS3 7 NRC to CPCo 04/10/79 VII-7 X NRC to CPCo 11/16/79 VI-7 B. DSI/RSB 7(Elec) CPCo to NRC 10/21/81 VIII-1 L. DSI/PS3 G NRC to CPCo 05/07/81 0 ( sy d VIII-2 DL/SEP3 7 NRC to CPCo C3/28/81 VI-7 C. CL 5EP3 7 NRC to CPCc 08/05/81 VIII-3 A. DL/SEPS 7 CPCo to NRC 04/22/31 VI-7 C. 1 DL/SEPB 7 NRC to CPCo C8/05/81 VIII-3 B. DL/SEPB 7 NPC to CPCo 03/18/81 VI-7 C. 2. DL/SEPB 7 NRC to CPCo 08/05/31 1 VIII-4 DL/SEPB 2 NRC +o CPCO 03/31/81 i VI-7 C. 3. X NRC to CPCo 11/16/79 l l l (2-4)

BIG ROCK POINT TCPIC NO. REVIEW STATUS REMARKS TCPIC NC. REVIEN STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 0 XV-10 X NRC to CPCo 11/ 16//9 IX-2 X NRC to CPCo 05/07/81 XV-11 CSI/CPB Gb CPCo to NRC 09/28,81 IX-3 DL/SEPB 2 XV-12 X NRC to CPCo 11/16/79 IX-4 X NRC to CPCo 11/16/79 XV-13 DSI/CPB Gb(Sys) CPCo to NRC 07/01/81 DSI/AEB 4a(Doses) IX-5 DL/SEPB C 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 HRC to CPCo '05/07/81 XV-16 DSI/AEB 4b CPCo to NRC 07/01/31 XI-1 DSI/ETSB X NRC to CPCo 12/04/81 XV-17 X NRC to CPCo 11/16/79 XI-2 DSI/ETSB X NRC to CPCo 12/04/81 XV-18 DSI/AEB Gb NRC to CPCo 07/01/31 XIII-1 X NRC to CPCo 05/07/81 XV-19 DSI/RSB 7(!/3) HRC to CPCo Oce18/81 XIII-2 DL/SSPB 7 NRC to CPCo 03/11/81 DSI/AEB 4bfi'.oses)CPCo tc NRC 07/01/81 XV-1 DSI/RSB Gb CPCo to NRC 07/15/31 XV-20 DSI/AES 4a CPCo to NRC 07/03/81 XV-2 X HRC to CPCo 11/16/79 XV-21 X NRC to CPCo 05/07/81 XV-3 DSI/RSS 7 NRr to CPCo 10/16/81 XV-22 X NRC to CPCo 05/07/81 XV-4 DSI/RSB 7 NEC to CPCo 10/16/81 YV-23 X NRC to CPCo 05/07/81 XV-5 DSI/RSB Gb CPCo to NRC 07/15/81 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/RSS 'b CPCo to NRC 07/15/81 XVII DL 7 NRC to CPeo 08/17/78 XV-8 DSI/CPB Gb CPCo to NRC 09/23/81 XV-9 DSI/R$9 Gb CPCo to NRC 07/15/81 (2-5) ) ,v y y y.

DRESDEN1 i FACILITY: CRESOEN 1 l l' LICENSEE: CCM"CSWEALTH EDISCH REGION /LCCATICN: 9 MILES EAST CF MCERIS, ILL. DCCKET NC. 050GC010 PCWER CAPACITY: 700(THERMAL) 2CC(ELECTRICAL) CL NUMBER: DPR-2 N.S.S S. GE. A/E FIRM: BECH. SYSTEMATIC EVALUATIC1 PROGRAM BRANCH CHIEF W. RUSSELL CPERATING REACTCRS BRANCH CHIEF: D. CRUTCHFIELD CPERATING REACTORS PRCJECT MANAGER: P. O'CCNNCR l By letter dated Dece-be-31, 1980 Co-onwealth Edison indi-cated that Dresden 1 was undergoina an extensive modifica-tien ar.d wa s no t scheduled for restart until June, 1936. Also, by letter dated April 4, 1981, in rosconse to the NRC's January 14, 1931 letter en SEP redirection the licen-see stated that the Oresden 1 SEP review is not being actively pursued, i.e. defered. I I l l l l (2-6) l l h 4

DRESDEN 2 FACILITY: DRESDEN 2 TOPIC NO. REVIEW STATUS REMARKS DIV/BR LICENSEE: COMMONWEALTH EDISON 11-1 A. DE/SAB 7 HRC to CECc 10/06/81 REGIDH/ LOCATION: 9 MI.ES EAST OF MORRIS. ILL. II-1 B. DE/SAB 7 NRC to CECO 10/06/81 DOCKET NO. 05000237 II-1 C. DE/SAB 0 POWER CAPACITY: 2527(THERMAL) 0794(ELECTRICAL) II-2 A. DSI/AEB 7 NRC to Ceco 04/24/81 OL NUMBER: DPR-19 II-2 B. X NRC to Ceco 05/07/81 N.S.S.S. GE. II-2 C. DSI/AEB 7 NRC to CPCo 08/26/81 A/E FIRM: J4L. II-2 D. X NPC to CECO 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL II-3 A. DE/HGEB 3 Ceco to NRC 09/11/81 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD II-3 B. DE/HGEB 3 CECO to NRC 09/11/81 OPERATING REACTORS PROJECT MANAGER: P. O'CONNOR II-3 B. 1 DE/MGEB 3 CECO to NRC Site Visit 01/09/79 [(, INTEGRATED ASSESSMENT PROJECT MANAGER: G. CWALINA II-3 C. DE/HGEB 3 CECO to NRC Site Visit 01/09/79 KEY F0F STATUS CODES II-4 DE/GSB 7 NRC to Ceco 07/09/81 G - GENERIC 4a-DRAFT SE RECEIVED (I-4 A. DE/GSB 7 NRC to CECO 06/08/81 FROM REVIEW BRANCH X - DELETED II-4 B. DE/GSB 5 HRC to CECO 07/09/81 4b-SAR RECEIVED FROM 0 - TOPIC NOT LICENSEE II-4 C. DE/GSB 7 NRC to CECO 06/08/81 STARTED 5 - DRAFT SE SENT II-4 D. DE/HGEB 0 1 - QUESTIONS RECE7VED TO UTILITY FROM REVIEW BRANCH II-4 E. DE/HGEB 0 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY HRC II-4 F. DE/HGEB 0 TO UTILITY 7 - TOPIC COMPLETE III-1 DL/SEPB 3(sys) NRC to Ceco 05/26/81 3 - QUESTION RESPONSE DL/SEPB 7(Elec) Part of VII-3 07/07/81 RECEIVED BY NRC III-2 DL/SEPB 3 (2-7)

DRESDEN 2 TOPIC FD. REVIEW STATUS REMARKS TOPIC NO. REVIEW STATUS REMARKS DIV/BR DIV/BR III-3 A. DE/SEB 3 CECO to NRC 09/28/79 111-10 B. X NRC to CLCo 11/16/79 III-3 B. X NRC to CECO 11/16/79 III-10 C. DL/SEPB '7 NPC to CECO 05/22/79 III-3 C. DE/HGEB 0 III-11 X NRC to Ceco 05/07/81 III-4 A. DSI/ASB o III-12 X 'NRC to CECO 05/07/81 III-4 B. DE/MTEB 3 Site Visit 06/01/81 IV-1 A. DL/SEPB 7 NRC to Ceco 10/26/81 III-4 C. DSI/ASB 0 IV-2 DSI/ICSB 5 NRC to CECO 10/19/81 III-4 D. DE/SAB 0 IV-3 DE/MTEB 7 NRC to CECO 01/01/80 III-5 A. DL/SEPB 2 HRC to CECO 01/04/80 V-1 DE/MTEB X NRC to Ceco 11/27/81 III-5 B. DL/SEPB 6 CECO to NRC 03/21/80 V-2 X NRC to CECO 11/16/79 III-6 DL/SEPB 6 CECO to NRC 03/13/81 V-3 X NRC to Ceco 05/07/81 III-7 A. X NRC to Ceco 05/07/81 V-4 X NRC to Ceco 05/07/81 III-7 B. DL/SEPB 3 CECO to NRC 09/28/79 V-5 DL/SEPB 6 CECO to NRC 09/02/80 III-7 C. X HRr to CECO 11/16/79 V-6 DL/SEPB 7 HRC to CECO 03/05/80 III-7 D. DE/SEB 4b Ceco to NRC 04/27/81 V-7 X NRC to Ceco 05/07/81 III-8 A. DSI G HRC to CECO 05/07/81 V-8 X NRC to Ceco 05/07/81 III-8 B. X HRC to CECO 09/11/80 V-9 X NRC to CECO 11/16/79 l l l III-8 C. DL/SEPB 6 CECO to NRC 03/10/80 V-10 A. DL/SEPB 7 HRC to CECO 11/08/79 III-8 D. X HRC to Ceco 05/07/81 V-10 B. DL/SEPB 7 NRC to Ceco 04/24/81 1 III-9 X NRC to Ceco 05/07/81 V-11 A. DL/SEPB 7 HRC to CECO 07/10/81 III-10 A. DL/SEPB 7 HRC tc CECO 06/26/81 V-11 B. DL/SEPB 7(Sys) NRC to Ceco 04/24/81 DL/SEPB 7(Elec) NRC to CECO 07/10/81 (2-8) -- - - - - - - - - = - - - - - - - -

DRESDEN 2 I l' TCPIC ND. REVIEW STATUS REMARKS TCPIC NO. REVIEW STATUS REMARKS DIV/BR DIV/ER i V-12 A. DL/SEPB 7 NRC to CECO 04/16/81 VI-7 D. DL/SEPS 7 haC to CECO C8/17/78 V-13 X hRC to Ceco 05/07/81 VI-7 E. X NRC to CECc 03/07/81 VI-1 DE/CEB 3 CECO to NRC 07/27/79 VI-7 F. X NRC to CECO 11/16/79 VI-2 A. X NRC to CECO 05/07/81 VI-8 X NRC to CECc 05/07/8i VI-2 B. X NRC to Ceco 05/07/81 VI-9 X NRC to CECO 11/16/79 VI-2 C. X NRC to Ceco 11/16/79 VI-10 A. DL/SEPB 7 NRC to CECO 07/03/81 VI-2 D. DSI/CSB 3 Ceco to NRC 11/20/80 VI-10 B. DL/SEPB 7(Sys) hRC to CECO 06/20/81 DL/SEPB 7(Elec) NRC to CECO 07/07/81 VI-3 DSI/CSB 3 CECO to NRC 11/20/80 VII-1 A. DL/SEPB 5 NRC to Ceco 0B/05/81 VI-4 DSI/CSB Ga(Sys) DL/SEPB 1CElec) VII-1 B. DL/SEPS 7 NRC te CECO 08/17/78 VI-5 X NRC to CECO 05/07/81 VII-2 DL/SEPS 7 CECO to NPC 03/18/81 VI-6 DSI/CSB G hRC to CECO 05/07/81 VII-3 DL/SEPB 7(SVs) NRC to Ceco 04/24/81 DL/SEPB 7(Elec) NRC to CECO 07/07/81 1 VI-7 A. 1 X NRC to CECO 11/16/79 l VII-4 X NRC to CECO 05/07/81 l VI-7 A. 2. X NRC to CECO 05/07/81 VII-5 X NRC to CECO 05/07/81 VI-7 A. 3. CL/SEPB 7 Ceco te NRC 06/23/81 VII-6 DL/ SERB 7 NRC to CECc 08/26/81 VI-7 A. 4. DSI/RSB G NRC to Ceco 05/07/81 VII-7 X NRC to CECe 11/16/79 VI-7 B. X NRC to CECO 11/16/79 VIII-1 A. DSI/RSB G NRC to Ceco 05/07/81 VI-7 C. DL/SEPS 7 NRC to Ceco 03/13/81 VIII-2 DL/SEPB 7 NRC to CECO 06/26/81 VI-7 C. 1. DSI/PSB 6 Ceco to NRC 06/12/81 VIII-3 A. DL/SEPB 7 NRC to CECc 07/07/81 VI-7 C. 2. DL/SEPB 7 NRC to CECO 03/13/81 VIII-3 B. DL/SEPB 7 NRC to CECO 06/26/81 VI-7 C. 3. X NRC to CECO 11/16/79 VIII-4 DL/SEPB 6 CECO to NRC 06/25/81 (2-9) 1

l DRESDEN 2 TOPIC HD. REVIEW STATUS REMARKS TCPIC NO. REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 3 CECO to hRC 06/02/80 XV-10 X NRC to CLCo 11/16//9 IX-2 X HRC to Ceco 05/07/81 XV-11 DSI/CPB Gb Ceco to NRC 10/15/81 IX-3 DL/SEPB 5 HRC to CECO 06/30/81 XV-12 X NRC to Ceco 11/16/79 IX-4 X NRC to CECO 11/16/79 XV-13 DSI/CPB 4b(Sys) CECO to NRC 10/15/81 DSI/AEB 4b(Doses;.fCo to NRC 10/15/81 IX-5 DL/SEPB 0 XV-14 DSI/RSB 40 Ceco to NRC 10/15/81 IX-6 DE/CEB G NRC to CECO 05/07/81 XV-15 DSI/RSB Gb Ceco to NRC 10/15/81 X X HRC to Ceco 05/07/81 XV-16 DSI/AEB 7 CECO to NRC 10/15/81 XI-1 DSI/ET5B X HRC to CECO 12/04/81 XV-17 X NRC to Ceco 11/16/79 XI-2 DSI/ETSB X NRC to Ceco 12/04/81 XV-18 DSI/AEB 4b CECO to NRC 10/15/81 XIII-1 X NRC to Ceco 05/07/81 XIII-2 DL/SSPB 7 NRC to Ceco 03/11/81 XV-19 DSI/RSB Gb(Sys) CECO to NRC 10/15/81 DSI/AEB 4b(DOSES) CECO to NRC 10/15/81 XV-1 DSI/RSB 4b Ceco to NRC 10/15/81 XV-20 DSI/AEB 7 NRC to CECO 11/20/81 XV-2 X NRC to CECO 11/16/79 XV-21 X NRC to Ceco 05/07/81 XV-3 DSI/RSB Gb CECO to NRC 10/15/81 XV-22 X NRC to CECO 05/07/81 XV-4 DSI/RSB 4b CECO to NRC 10/15/81 XV-23 X NRC to Ceco 05/07/81 I XV-5 DSI/RSB 4b CECO to NRC 10/15/81 l XV-29 X NRC to CECO 05/07/81 XV-6 X HRC to CECO 11/16/79 XVI X NRC to CECO 11/05/80 XV-7 DSI/RSB Gb CECO to NRC 10/15/81 XVII DL 7 NRC to CECO 11/20/79 XV-8 RSI/CPB 4b Ceco to NRC 10/15/8 1 XV-9 DSI/RSB 4b CECO to NRC 10/15/81 (2-10)

GINNA FACILITf: GINNA TOPIC NO. REVIEW STATUS REMARKS DIV/BR LICENSEE: ROCHESTER GAS 3 ELECTRIC I1-1 A. DE/SAB 7 NRC to RGE 07/11/81 REGION / LOCATION: 15 MILES NORTH EAST OF ROCHESTER, NY. II-1 B. DE/SAB 7 NRC to RGE 07/21/81 DOCKET NO.: 05000244 II-1 C. DE/SAB 7 NRC to RGE 09/29/81 POWER CAPACITY: 1520(THERMAL) 0490(ELECTRICAL) II-Z A. DSI/AEB 6 REG to NRC 01/19/81 OL NUMBER: DPR-18 II-2 B. X NRC to RGE 05/07/81 H.S.S.S.: WEST. II-2 C. DSI/AEB 7 NRC to RGE 09/24/81 A/E FIRM: GIL. II-2 D. X NRC to RGE 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL II-3 A. DE/HGEB 6 RGE to NRC 08/18/81 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD II-3 B. DE/HGEB 6 RGE to NRC 08/18/81 OPERATING REACTORS PROJECT MANAGER: R. SNAIDER II-3 B. 1 DE/HGEB 6 RGE to NRC 08r18/81 INTEGRATED ASSESSMENT PROJECT MANAGER: A. WANG 07 II-3 C. DE/HGEB 7 RGE to NRC 04/10/81 i l II-4 DE/GSB 7 NRC to RGE 07/09/81 KEY FOR STATUS CODES II-4 A. JE/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 NRC to RGE 06/08/81 4b-SAR RECEIVED FROM 0 - TOPIC NOT LICENSEE II-4 D. DE/AGEB 4b RGE to NRC 06/30/81 STARTED 5 - DRAFT SE SENT II-4 E. X NRC to RGE 11/16/79 ( 1 - QUESTIONS RECEIVED TO UTILITY l FROM REVIEW BRANCH II-4 F. DE/HGEB 4b RGE to NRC 06/30/81 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC III-1 DL/SEPB 3(Sys) RGE to NRC 08/14/81 TO UTILITY DL/SEPB 6(Elec) RGE to NRC 01/23/81 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 4a RECEIVED BY.NRC M - DATA FOR NEXT MONTH ( t'0 V EMB ER ) (2-11)

f i l GINNA TOPIC NO. REVIEW STATUS REMARKS TCPIC NO. REVIEW STATUS REMARKS DIV/BR DIV/BR III-5 A. DE/SEB 6 RGE to NRC G 8 /18 / 81 III-10 B. DL/SEPB 7 NRC to RGE 06/22/51 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 Gb RGE to NRC 10/12/81 III-11 X NRC to RGE 05/07/81 III-4 A. DSI/AEB 5 NRC to RGE 09/28/81 III-12 X NRC to RGE 05/07/81 III-4 B. DE/NTES G NRC to RGE 05/07/81 IV-1 A. DL/SEPS 7 NRC to RGE 05/29/79 III-4 C. DSI/ASB C IV-2 DSI/ICSB 7 NRC to RGE 05/26/81 III-4 D. DE/SAB 7 NRC to RGE 07/21/81 IV-3 X NRC to RGE 05i07/81 III-5 A. DL/SEPB 6 RGE to NRC 08/05/81 V-1 DE/MTEB X NRC to RGE 11/27/81 III-5 B. DL/SEPB 7 NRC to RGE 09/04/81 V-2 X NRC to RGE 11/16/79 III-6 DL/SEPB 6 RGE to NRC 02/06/81 V-3 X NRC to RGE 05/07/81 III-7 A. DL/SEPB G NRC to RGE 05/07/81 V-4 X NRC to RGE 05/07/81 III-7 B. DL/SEPB 3 RGE to NRC 11/14/79 V-5 DL/SEPB 6 RGE to NRC 10/12/81 III-7 C. DE/SEB 7 RGE to NRC 07/07/81 V-6 DL/SEPB 7 NRC to RGE 03/05/80 III-7 D. DE/SEB 7 HRC to RGE 05/08/80 V-7 DSI/ASB 7 NRC to RGE 11/27/81 III-8 A. DSI G NRC to RGE 05/07/81 V-8 X NRC to RGE 05/07/81 III-8 3. X NRC to RGE 10/01/80 V-9 X NRC to RCE 11/16/79 III-8 C. DL/SEPB 7 RGE to NRC 12/07/79 V-10 A. DL/SEPB 7 NRC to RGE C2/02/79 III-8 D. X HRC to RGE 05/07/81 V-10 B. DL/SEPB 7 RGE to NRC 09/29/81 III-9 X NRC to RGE 35/07/81 V-11 A. DL/SEPB 7 NRC to RGE 07/22/81 III-lu A. DL/SEPB 7 NRC to RGE 08/03/81 V-11 B. DL/SEPB 7(Sys) RGE to NRC 09/29/81 DL/SEPB 7(Elec) NRC to RGE 04/24/81 (2-12)

GINNA TGPIC NO. REVIEW %TATUS REMARKS TGPIC NO. REVIEW STATUS REMARKS DIV/BR DIV/BR V-12.A. X NRC to RGE 11/16/79 VI-7 D. DL/SEPS 7 NRC to RGL 08/17/78 V-13 X NRC 1 RGE 05/07/81 VI-7 E. X NRC to RGE 05/07/81 VI-1 DE/CEB 3 RGE to NRC 11/06/81 VI-7 F. DL/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/CSD 5 NRC to RGE 11/03/81 VI-10 B. X NRC to kGE 11/16/79 VI-3 DSI/CSB 5 NRC to RGE 11/03/81 VII-1 A. DL/SEPB 7 1;RC to RGE 07/30/81 VI-4 DSI/CSB 5(sys) HRC to RGE 07/27/81 VII-1 B. DL/SEPB 7 NRC to RGE 08/17/78 DL/SEPB 6(Elec) RGE to NRC 03/02/81 VII-2 DL/SEPB 6 RGE to NRC 10/23/81 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 05/06/81 DL/SEPB 7(Elec) NRC to RGE 06/24/81 VI-7 A. 1. DL/SEPB 7 NRC to RGE 02/20/81 VII-4 X NRC to RGE 05/07/81 VI-7 A. 2. DL/SEPB 7 NRC to RGE 08/17/78 VII-5 X NRC to RGE 05/07/81 VI-7 A. 3. DL/SEPB 7 NRC to RGE 11/27/81 VII-6 DL/SEPB 7 NRC to RGE 06/24/81 VI-7 A. 4 X NRC to RGE 05/07/81 VII-7 X NRC to RGE 11/16/79 VI-7 B. DSI/RSB 7(Sys) RGE to NRC 08/18/81 VIII-1 A. DSI/PSB 7 NRC to RGE 03/26/81 DL/SEB 7(Elec) NRC to RGE 09/18/81 VIII-2 DL/SEPB 7 NRC to RGE 06/24/81 VI-7 C. DL/SEPB 7 NRC to RGE 02/20/81 VIII-3 A. DL/SEPB 7 MRC to RGE 07/31/81 VI-7 C. 1. DL/SEPB 7 NRC to RGE 11/27/81 VIII-3 B. 3L/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 (2-13)

i GINNA TOPIC NO. REVIEW STATUS REMARKS TCPIC NO. REVIEW STATUS REMARKS DIV/ER DIV/BR IX-1 DSI/ASB 7 NRC te RGE 11/24/81 XV-10 CSI/RSB 7 NRC to FGE 09/04/81 IX-2 X NRC to RGE 03/07/81 XV-11 X NRC to RGE 10/01/80 IX-3 DL/SEPB 7 NRC to RGE 11/03/31 XV-12 DSI/CPB 7(Sys) NRC to RGE 09/04/81 DSI/AES 6(Doses) RGE to NRC 11/04/81 IX-4 DSI/RSS 7 NRC to RGE 08/26/81 XV-13 X HRC to RGE 11/16/79 IX-5 DL/SEPB 4a XV-14 DSI/RSB 7 NRC to RGE 09/04/81 IX-6 G NRC te RGE 05/07/81 XV-15 DSI/RSB 7 NRC to RGE 09/04/81 X X NRC to RGE 05/07/81 XV-16 DSI/AEB 6 RGE to NRC 09/24/80 XI-1 DSI/ETSB X NRC to RGE 12/04/81 XV-17 DSI/RSB 7(Sys) NRC to RGE 09/04/81 XI-2 DSI/ETS3 X NRC to RGE 12/04/81 DSI/AEB 6(Doses) RGE to NRC 11/04/81 XIII-1 X NRC +o RGE 05/07/81 XV-18 X NRC to RGE C 3/11/8 0 XIII-2 JL/SEPB 7 NRC to RGE 03/26/81 XV-19 DSI/RSB 7(Sys) NRC to RGE 10/02/81 DSI/AE3 5(Doses) NRC to RGE 09/29/81 XV-1 DSI/RSB 7 NR; to RGE 09/04/81 XV-20 DSI/AEB 6 RGE to hRC 11/04/81 XV-2 DSI/RSS 7(Sys) HRC to RGE 09/04/81 DSI/AEB 6(Doses) RGE to NRC 11/04/81 XV-21 X NRC to RGE 05/07/81 XV-3 DSI/RSB 7 NRC to RGE 09/04/81 XV-22 X NRC to RGE 05/07/81 XV-4 DSI/RSB 7 NRC to RGE 09/04/81 XV-23 X NRC to RGE 05/07/81 XV-5 DSI/RSB 7 NRC to RGE 09/04/81 XV-24 X NRC to RGE 05/07/81 XV-6 DSI/RSG 7 NRC to RGE 09/04/81 XVI X NRC to RGE 11/05/80 XV-7 DSI/RSB 7 NRC to RGE 09/04/81 XVII DL 7 NRC to RGE 08/17/78 XV-8 DSI/CPB 7 NRC to RGE 09/04/81 XV-9 DSI/RSS 7 RGE to NRC 10/16/81 (2-14)

HADDAM NECK FACILITY: HADDAM NECK TOPIC HO. REVIEW STATUS REMARKS DIV/BR LICENSEE: CONNECTICUT YANKEE ATCMIC POWER 11-1 A. DE/SAB 4b CYAPCo to NRC 04/27/81 REGION / LOCATION: 13 MILES EAST OF MERIDEN, CT. Il-1 B. DE/SAB Gb CYAPCo to NRC 08/31/81 DOCKET NO: 05000213 II-1 C. DE/SAB 4b CYAPCo to NRC 06/30/81 POWER CAPACITY: 1825CTHERMAL) 0575(ELECTRICAL) II-2 A. DSI/AES 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. Il-2 C. DSI/AEB 7 CYAFCo to NRC 02/16/79 A/E FIRM: StW II-2 D. X NRC to CYAFCo 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL II-3 A. DE/HGEB 3 CYAPCo to NRC 08/23/81 OPERATING REACTORS BRAilCH CHIEF: D. CRUTCNFIELD II-3 B. DE/HGEB 3 CYAPCo to NRC 08/23/81 OPERATING REACTORS PROJiCT MANAGER: W. PAULSON II-3 B. 1. DE/HGEB 3 Site visit INTEGRATED ASSESSMENT PROJECT MANAGER: S. BROWN II-3 C. DE/HGEB 3 Site Visit II-4 DE/GSB 7 NRC to CYAPCo 06/08/81 KEY FOR STATUS CODES II-4 A. DE/GSB 7 HRC to CYAPCo 06/08/81 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B. DE/GSB 3 NUREG/CR1582 08/04/80 FROM REVIEW BRANCH X.- DELITED II-4 C. DE/GSB 7 HPC to CYAPCo 06/08/81 4b-SAR RECEIVED FROM 0 - TCPIC NOT LICENSEE II-4 D. DE/HGEB Ab CYAPCo to NRC 08/31/81 l STARTED l 5 - DRAFT SE SENT II-4 E. X NRC to CYAPCo 04/16/79 l 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F. DE/HGEB 4b CYAPCo to NRC 06/22/81 l 6 - SE RESPONSE RECEIVED l 2 - QUtSTIONS SENT BY HRC III-1 DL/SEPB 2(Sys) NRC to CYAPCo 11/20/81 TO UTILITY DL/SEPB 7(Elec) Part of VII-3 7 - 10PIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 3 CYAPCo to NRC 09/07/79 RECEIVED BY HRC (C-15)

HADDAM NECK TCPIC NO. REVIEW STATUS REMARKS TOPIC NO. REVIEW STATUS REMARKS DIV/BR DIV/3R III-3 A. DE/SEB 4b CYAPCo to hRC 08/31/31 III-10 B. bl/SLPB 6 CYAPCo to MRC 12/T]/50 III-5 3. DE/HGEB 3 III-10 C. X NRC to CYAPCo 04/16/79 III-3 C. DE/HGEB 46 CYAPCo to NRC 08/31/81 III-11 X NRC to CYAPCo 05/07/81 III-4 A. DSI/ASB Gb CYAPCo to NRC 08/31/81 III-12 X NRC to CYAPCo 05/07/81 III-4 B. DE/MIEB G NRC to CYAPCo 05/07/81 IV-1 A. DL/SEPB 7 CYAPCo to NRC 06/25/79 III-4 C. DSI/ASB 0 IV-2 DSI/ICSB 46 CYAPCo to NRC 06/30/81 III-4 D. DE/SAB Gb CYAPCo to NRC 06/25/81 IV-3 X NRC to CYAPCo 05/07/81 III-5 A. DL/SEPB 3 CYAPCo to NRC 02/07/80 V-1 DE/MTEB 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 NRC 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 6 CYAPCo to NRC 08/19/81 III-7 C. X NRC to CYAPCo 04/16/79 V-6 DL/SEPB 7 NRC to CYAPCo 03/05/80 III-7 D. DE/SEB 5 NRC to CYAPCo 10/16/81 V-7 DSI/ASB G NRC to CYAPCo 05/07/C1 III-8 A. DSI G NRC to CYAPCo 05/07/81 V-8 X NRC to CYAPCo 05/07/81 III-8 B. X NRC to CYAPCo 10/01/80 V-9 X NRC to CYAPCo 11/15/79 III-8 C. DL/SEPB 6 CYAPCo to NRC 12/18/79 V-10 A. DL/SEPB 7 NRC to CYAPCo 01/13/81 III-8 D. X NRC to CYAPCo 05/07/81 V-10 B. DL/SEPB 7 CYAPCo to NRC 11/10/81 III-9 X NRC to CYAPCo 05/07/81 V-11 A. DL/SEPB 6 CYAPCo to NRC 11/05/81 III-1J A. CL/SEPB 7 CYAPCo to NRC 09/21/81 V-11 B. DL/SEPB 7(Sys) CYAPCo to NRC 11/10/81 DL/SEPB 7(Elec) Part of VII-3 (2-16)

HADDAM NECK i TOPIC NO. REVIEM STAIL5 REMARKS I TOPIC NO. .'. 'V I E W STATUS PEMARKS DIV/BR DIV/OR V-12 A. X NRC to CYAPCo 11/16/79 VI-7 D. DL/SEPB 7 NRC to C(APCo 08/17//8 V-13 X NRC to CYAPCo 05/07/81 VI-7 E. X NRC to CYAPCo 05/G7/81 VI-1 DE/CEB 3 CYAPCC to NRC 10/31/79 VI-7 F. X NRC to CYAPCo 04/16/79 VI-2 A. X NRC to CYAPCo 05/07/81 VI-8 X NRC to CYAPCo C5/07/81 VI-2 B. X NRC to CYAPCo 05/07/81 VI-9 X NRC to CYAPCo 11/16/79 VI-2 C. X NRC to CYAPCo 04/16/79 VI-10 A. DL/SEPB 3 VI-2 D. DSI/CSB 3 CYAPCu to NRC 04/27/81 VI-10 B. X NRC to CYAPCo C 4/16 / 7 9 VI-3 DSI/CS3 3 CYAPCo to NRC 04/27/81 VII-1 A. DL/SEPB 3 CYAPCo to NRC 08/07/81 VI-4 DSI/CSB O(Sys) VII-1 B. DL/SEPB 7 NRC to CYAPCo 08/17/78 DL/SEPB 7(Elec) NRC to CYAPCo 09/21/81 VII-2 DL/SEPB 3 CYAPCo to NRC 08/07/81 VI-5 X NRC to CYAPCo 05/07/81 VII-3 7L/SEPB 7(Sys) CYAPCo to NRC 11/10/81 VI-6 DSI/CSB G NFC to CYAPCo 05/07/a1 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/SEPS 0 VII-6 DL/SEPS 7 NRC to CYAPCo 08/28/81 VI-7 A. 4. X NRC to CYAPCo 05/07/81 VII-7 X NRC to CYAPC9 04/16/79 VI-7 B. DSI/RS'. 0(Sys) VIII-1 A. DSI/PSB G NRC to CYAPCo 05/07/31 DL/SEPB 5(Elec) HRC to CYAPCo 05/21/81 VIII-2 DL/SEPB 7 NRC to CYAPCo 08/28/81 VI-7 C. DL/SEPB 7 NRC to CYAPCo 03/13/81 VIII-3 A. DL/SEPB 7 CYAPCo to NRC 02/16/79 VI-7 C. 1 DL/SEPB 7 NRC to CYPACo 08/28/81 VIII-3 B. DL/SEPB 7 NRC to CYAPCo 08/28/81 VI-7 C. 2. DL/SEPB 7 NRC to CYAPCo 03/13/81 VIII-4 DL/SEPB 2 NRC to CYAPCo 06/20/81 VI-7 C. 3. DL/SEPB 2 NRC to CYAPCo 06/26/81 1 (2-17)

HADDAM NECK l TCPIC NO. PEVIEW STATUS REMARKS TCPIC NO. REVIEW STATUS REMARKS r l DIV/ER D I '. 'E R IX-1 DSI/ASE 4b CYAPCo to NRC 08/31/81 XV-10 DSI/RSB 4b CYAPCo to hRC 09/30/81 IX-2 X NRC to CYAPCo 05/07/81 XV-11 X NRC to CYAPCo 10/01/80 IX-3 DL/EEPA 2 XV-12 DSI/CPB Gb(Sys) CYAPCo to NRC 09/30/81 DSI/RSB Ab(Dosos)CYAPCo to NEC 09/30/81 IX-4 DSI/RSB 4b CYAPCo to NRC 10/02/81 XV-13 X NRC to CYAPCo 11/16/79 IX-S DL/SEPB 3 XV-14 DSI/RSB 4b CYAPCo to NRC 09/30/81 IX-5 DE G NRC to CYAPCo 05/07/81 XV-15 DSI/RSB Gb CYAPCo to NRC 09/30/81 X X NRC to CYAPCo 03/07/81 XV-16 "s DSI/AEB 6 CYAPCo to NRC 09/28/81 XI-1 DSI/ETS~$ X NRC to CYAPCo 12/04/81 XV-17 DSI/RSS 0(Sys) XI-4 DSI/ETSB X NRC to CYAPCo 12/04/81 DSI/AES 0(Donos) XIII-1 X NRC to CYAPCo 05/07/81 XV-18 X NRC to CYAPCo 10/01/80 XIII-2 DL/SSPS G NRC to CYAPCo 05/07/81 XV-19 DSI/RSB 7(Sys) NRC to CYAPCo 12/02/81 DSI/AEB 4b(Dosos)CYAPCo to MRC 09/30/81 XV-1 DSI/RSB 4b CYAPCo to NRC 09/30/81 XV-20 DL/SE*B 7 NRC to CYAPCo 06/09/81 XV-2 DSI/RSB 4b(Sys) CYAPCo to NRC 09/30/81 DSI/AEB 4b(Doses)CYAPCo to NRC 09/30/81 XV-21 X NRC to CYAPCo 05/07/81 XV-3 DSI/RSB Gb CYAPCo to NRC 09/30/81 XV-22 X NRC to CYAPCo 05/07/81 XV-4 DSI/RSB Gb CYAPCo to NRC 09/30/81 XV-23 X NRC to CYAPCo 05/07/81 XV-5 DSI/RSB 4b CYAPCo to NRC 09/30/81 XV-24 X NRC to CYAPCo 05/07/81 XV-6 DSI/RSB Gb CYAPCo to NRC 09/30/81 XVI X NRC to CYAPCo 11/05/80 XV-7 DSI/RSS Gb CYAPCo to NRC 09/30/81 XVII DL 7 NRC to CYAPCo 08/17/78 XV-8 DSI/CPB 4b CYAPCo to NRC 09/30/81 XV-9 DSI/RSB Ab CYAPCo to NRC 09/30/81 ( 2-18 )

LACROSSE FACILITY: LACROSSE TOPIC NO. REVIEW STATUS REMARKS DIV/BR LICENSEE: DAIRLAND POWER 11-1 A. DE/SAB 4b DPC to NRC 06/23/81 REGION / LOCATION: 19 MILES SOUTH OF LACROSSE, WISC. II-1 B. DE/SAB 4b DPC to NRC 05/16/81 DOCKET NO.: 0 000409 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: $4L II-2 D. X NRC to DPC 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL II-3 A. DE/HGEB 4b DPC to NRC 06/16/81 OPERATING REACTORS BRAFCH CHIEF: D. CRUTCHFIELD II-3 B. DE/HGEB 2 NRC to DPC 07/10/81 OPERATING REACTORS PROJECT MANAGER: R. CARUSO II-3 B. 1 DE/HGEB 0 II-3 C. DE/HGEB 4b DPC to NRC 06/26/81 INTEGRATED ASSESSMENT PROJECT MANAGER: T. MICHAELS II-4 DE/GSB 7 NRC to DPC 06/08/81 KEY FOR STATUS CODES II-4 A. DE/GSB 7 NRC to DPC 06/08/81 G - GENERIC 4a-DRAFT Sd RECEIVED II-4 B. DE/GSB 3 FROM REVIEW BRANCH X - DELETED II-4 C. DE/GS3 7 NRC to DPC 06/08/81 4b-SAR RECEIVED FROM 0 - TOPIC NOT LICENSEE II-4 D. DE/HCEB 3 Site Visit 07/10/79 STARTED 5 - DRAFT SE SENT II-4 E. DE/HGEB 0 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F. DE/HGEB 2 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC III-1 DL/SEPB 3(Sys) DPC to NRC 08/06/31 l TO UTILITY DL/SEPB 0(Elec) 7 - TOPIC COMPLETE 3 - QUESTION RESPON!E III-2 DL/SEPB Gb CPC to NRC 03/06/81 RECEIVEO BY NRC l (2-19)

LACROSSE l TC=IC NO. REVIEW STATUS REMARKS ! TCPIC NO. REVIEW STATUS REMARKS DIV/BR DIV/BR III-3 A. DE/SEB 2 hRC to DPC C8/09/79 III-10 B. X NPC to DPC iO/J9//) III-3 3. X NRC to DPC 03/10/81 III-10 C. X NRC to DPC 10/29/79 III-3 C. DE/HCEB 0 III-11 X NRC to DPC 05/C7/81 i III-4 A. DSI/ASB C III-12 X NRC to DPC 05/07/81 III-4 B. DE/MTEB 0 IV-1 A. DL/SEPB 7 f;RC to DPC C ',/19/ 7 9 III-4 C. DSI/ASB 0 IV-2 DSI/ICSB 2 HRC to DPC 12/15/80 III-4 D. DE/ SAL Go DPC to NRC 09/15/81 IV-3 X NRC to DPC 05/07/81 III-5 A. DL/SEPB 2 NRC to DPC 01/04/80 V-1 X NPC to DPC 11/27/81 III-5 B. DL/SEPB Gb DPC to NRC 06/29/81 V-2 X NRC to DPC 10/29/79 III-6 DL/SEPB 3 DPr to NRC 06/12/81 V-3 X NRC to DPC 05/07/81 III-7 A. X NRC to DPC 05/07/31 V-4 X NRC to CPC 05/07/81 III-7 B. DL/SEPB 2 NRC to DPC 08/09/79 V-5 DL/SEPB Ga III-7 C. X HRC to DFC 10/29/79 V-6 DL/SEPB 7 NRC to DPC 03/05/80 III-7 D. DE/SEB 4b DPC to NRC 06/29/81 V-7 X NRC to DPC 05/07/81 l III-5 A. DSI G NRC to DPC 05/07/81 V-8 X N C to DPC 05/07/81 III-8 B. X NRC to DPC 09/26/80 V-9 X NoC 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 CPC 01/C7/81 III-8 D. X NRC to DPC 05/07/81 V-10 B. DL/SEPS 5 NRC to DPC 12/?2/80 III-9 X NRC to DPC 05/07/81 V-11 A. DL/SEPB 7 NRC to DPC 12/22/80 III-10 A. DL/SEPB 7 NRC to CPC 09/22/81 V-11 B. DL/SEPB 5(Sys) HRC to DPC 12/22/80 DL/SEPB 0(Elec) (2-20)

O LACROSSE l TCPIC ND. REVIEW STATUS REMARKS TCPIC NO. REVIEW STATUS REM /,RKS DIV/BR DIV/BR V-12 A. DL/SEPB 7 NRC to DPC 04/30/79 VI-7 D. DL/SEPB 7 NkC to DPC 03/17/78 V-13 X NRC to DPC 05/07/81 VI-7 E. X HRC to DPC 05/07/81 VI-1 DE/CtB 3 DPC to HRC 08/23/79 VI-7 F. X HRC to DPC 10/29/79 VI-2 A. X NRC to DPC 05/07/81 VI-8 X 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 N' C to CPC 10/29/79 VI-10 A. DL/SEPB 2 NRC to DPC 07/21/81 VI-2 D. DSI/CSB 3 DPc to NRC 04/26/79 VI-10 B. X NRC to DPC 10/29/70 VI-3 DSI/CSB 3 DPC to NRC 04/26/79 VII-1 A. DL/SEPB 2 NRC to CPC 10/06/81 VI-4 DSI/CSB 3(Sys) DPC to NRC 08/17/81 VII-1 B. DL/SEPB 7 NRC to DPC 08/17/78 DL/SEPB 6(Elec) DPC to NRC 08/26/81 VII-2 DL/SEPB 2 HRC to DPC 10/06/81 VI-5 X NRC to DPC 05/07/81 VII-3 DL/SEPR 5(Sys) NRC to DPC 12/22/C0 VI-6 DSI/CSB G NRC to DPC 05/07/81 CL/SEPB 3(Elec) VI-7 A. 1 X NRC to DPC 10/29/79 VII-4 X NRC to DPC 05/07/81 VI-7 A. 2. X NRC to DPC 05/07/81 VII-5 X HRC to DPC 05/C7/81 VI-7 A. 3. DL/SEPB 0 VII-6 DL/SEPB 7 HP.C to DPC 09/21/81 VI-7 A. 4. X NRC to DPC 05/07/81 VII-7 X NRC to DPC 10/29/79 l VI-7 B. X NRC to DPC 10/29/79 VIII-1 A. DSI/PSB G NRC to DPC 05/07/81 VI-7 C. DL/SEPB 7 NRC to DPC 03/13/81 VIII-2 DL/SEPB 6 DPC to NRC 11/20/80 VI-7 C. 1. DL/SEPB 7 NRC to DPC 09/21/81 VIII-3 A. DL/SEPB 7 NRC to DPC 06/05/79 l VI-7 C. 2. DL/SEPB 7 HRC to DPC 03/13/81 VIII-3 B. DL/SEPB 7 NRC to DPC 08/28/81 VI-7 C. 3. X NRC to CPC 10/29/79 VIII-4 DL/SEPB 7 NRC to DPC 09/09/C1 l l f (2-21)

LACROSSE TDPIC HD. REVIEW STATUS REMARKS TDPIC ND. REVIEW STATUS REMARKS DIV/BR DIV/DR IX-1 DSI/ASB 0 XV-10 X NRC to DPC 10/29//9 IX-2 X NRC to DPC 05/07/81 XV-11 DSI/CPB 0 IX-3 DL/SEPB 2 XV-12 X NRC to DPC 10/29/79 IX-4 X NRC to DPC 10/29/79 XV-13 DSI/CPB 0(Donos) DSI/AED 0(Sys) IX-5 DL/SEPB 0 XV-14 DSI/RSB 4b DPC to NRC 08/25/81 IX-6 DE G NRC to DPC 05/07/81 XV-15 DSI/RSB 7 NRC to DPC 09/21/81 X X NRC to DPC 05/07/81 XV-16 DSI/AEB 0 XI-1 DSI/ETSL X NRC to DPC 12/04/81 XV-17 X NRC to DPC 10/29'79 XI-2 DSI/ETSB X NRC to DPC 12/04/81 XV-18 DSI/AEB 0 XIII-1 X NRC to DPC 05/07/81 XV-19 DSI/AEB O(Doses) XIII-2 DL/SSPB 7 NRC to DPC 03/11/81 DSI/RSS O(Sys) XV-1 DSI/RSB 0 XV-20 DSI/AEB 0 XV-2 X NRC to DPC 10/29/79 XV-21 X NRC to DPC 05/07/81 XV-3 DSI/RSB 7 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 0 XV-24 X NRC to DPC 05/07/81 XV-6 X NRC to DPC 10/29/79 XVI X HRC to DPC 11/05/80 XV-7 DSI/RSB 0 XVII DL 7 NRC to DPC 08/17/78 XV-8 DSI/CPB 0 XV-9 DSI/RSB Gb DPC to NRC 08/25/81 (2-22)

MILLSTONE 1 FACILITY: MILLSTONE 1 TOPIC NO. REVIEW STATUS REMARKS DIV/BR LICENSEE: H3RTHEAST NUCLEAR ENERGY 11-1 A. DE/SAB 1 NRC to NU 0//31/81 REGION / LOCATION: 5 MILES SOUTH WEST OF NEW LONDON, CONN. 11-1 B. DE/SAB 4b NU to NRC 05/19/81 DOCKET NO. 05000245 II-1 C. DE/SAS Ab NU to NRC 04/29/81 POWER CAPACITY: 2011(THERMAL) 0660(ELECTRICAL) II-2 A. DSI/AEB 7 NRC to NU 03/30/81 OL NUMBER: DPR-21 II-2 B. X HRC to NU 05/07/81 H.S.S.S. GE. II-2 C. DSI/AEB 7 NRC to NU 09/29/81 A/E FIRM: EBASCO II-2 D. X NRC to NU 05/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL II-3 A. DE/HGEB 4b NU to NRC 06/25/81 OPERATING REACTORS BRANCH CHIEF: D. CfuTCHFIELD II-3 B. DE/HGEB 4b NU to NRC 06/26/81 OPERATING REACTORS PROJECT MANAGER: J. SHEA II-3 B. 1. DE/HGEB Gb NU to NRC 06/25/81 PERSINKO -{7() II-3 C. DE/HGEB Gb NU to NRC 04/28/81 INTEGRATED ASSESSMENT PROJECT MANAGER: D. II-4 DE/GSB 7 NRC to NU 06/03/81 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 3 NUREG/CR1582 08/03/80 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 Gb NU 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 REVI'W 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 2(Elec) NRC to NU 06/09/81 TO UTILITY DL/SEPB 3(Sys) NU to NRC 08/20/81 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 3 NU to NRC 08/29/79 RECEIVED BY NRC (2-23)

MILLSTONE 1 TDPIC NO. REVIEW STATUS REMARKS TDPIC 40. REVIEW STATUS REMARKS DIV/BR DIV/3R III-3 A. D E / '. E B 5 NRC to NU 05/11/81 111-10 B. X SRC to NU 11/16/79 III-3 B. X NRC to ;4U 12/26/80 III-10 C. DL/SEPB 7 NU to NRC 08/29/79 III-3 C. DE/HGCB 4b HU to NRC 08/31/81 III-11 X NRC to NU 05/07/81 III-4 A. DSI/ASB 4b HU to NRC 08/31/81 III-12 X NRC to NU 05/07/81 III-4 B. DE/MTEB 4b Nu to NRC 08/31/81 IV-1 A. DL/SEPB 7 NU to NRC 02/12/79 III-4 C. DSI/ASB 3 HU to NRC 12/05/80 IV-2 DSI/ICSB 4b NU to NRC 10/28/81 III-4 D. DE/SAB 4b NU to NRC 04/29/81 IV-3 DE/MTEB G HRC to NU 05/07/81 III-5 A. DL/SEPB 3 NU to NRC 11/08/79 V-1 X NRC to NU 11/27/81 III-5 B. DL/SEPB 1 V-2 X HRC to NU 11/16/79 III-6 DL/SEPB 5 HRC to NU 05/28/81 V-3 X NRC to NU 05/07/81 III-7 A. X NRC to NU 05/07/81 V-4 X NRC to NU 05/07/81 III-7 B. DL/SEPB 3 NU 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 HRC to NU 03/05/80 III-7 D. DE/SEB 7 NU to NRC 02/17/81 V-7 X NRC to NU 05/07/81 III-8 A. DSI G HRC to bu 05/07/81 V-8 X NRC to NU 05/07/81 III-8 B. X NRC to NU 09/26/80 V-9 X NRC to NU 11/16/79 III-8 C. DL/SEPB 6 NU to NRC 01/31/80 V-10 A. DL/SEPB 7 NU to NRC 03/05/79 III-8 D. X NRC to NU 05/07/81 V-10 B. DL/SEPS 7 NU to NRC 07/22/31 III 's X NRC to NU 05/07/81 V-11 A. DL/SEPB 7 NRC to NU 07/08/81 III-10 A. DL/SEPB 7 NRC to NU 06/28/81 V-11 B. DL/SEPB 7(Sys) NU to NRC 07/22/81 DL/SEPB 0(Elec) (2-24)

s MILLSTONE 1 TDPIC NO. REVIEW STATUS REMARKS TDPIC NO. 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 f40 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 4b NU to NRC 09/30/81 VI-7 F. X NRC to NU 11/16/79 VI-2 A. X NRC to NU 05/07/81 VI-8 X NRC to NU 05/07/81 VI-2 B. X NRC to NU 05/07/81 VI-9 X NRC to NU 11/16/79 VI-2 C. X NRC to NU 11/16/79 VI-10 A. DL/SEPB 7 NRC to NU 10/08/81 VI-2 D. DSI/CSB 3 NU to NRC 06/09/81 VI-10 B. DL/SEPB 7(Sys) NU to NRC 08/05/81 DL/SEPB 7(Elec) VI-3 DSI/CSB 3 NU to NRC 06/09/81 VII-1 A. DL/SEPB 7 NRC to NU 07/23/81 VI-4 DSI/CSB 4a(Sys) DL/SEPB 6(Elec) NU to NRC 08/12/81 VII-1 B. DL/SEPB 7 NRC to NU 08/17/78 VI-5 X NRC to NU 05/07/81 VII-2 DL/SEPB 7 NRC to NU 08/28/81 VI-6 DSI/CSB G NRC to NU 05/07/81 VII-3 DL/SEPB 7(Sys) NU to NRC 07/22/81 DI/SEPB 2(Elec) NRC to NU 06/09/81 VI-7 A. 1. X NRC to NU 11/16/79 yyI_4 X NRC to NU 05/07/81 V!-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 08/26/81 VI-7 A. 4. DSI/RSB G NRC to NU 05/07/81 VII-1 X NRC to NU 11/16/79 VI-7 B. X NRC to NU 11/16/79 VIII-1 A. DSI/RSB G HRC to NU 05/07/81 VI-7 C. DL/SEPB 7 NRC to NU 03'29/81 VIII-2 DL/SEPB 7 NRC to NU 09/30/81 l VI-7 C. 1. DL/SEPB 7 NU to NRC 11/02/81 VIII-3 A. DL/SEPB 7 NRC to hu 08/26/81 l VI-7 C. 2. DL/SEPB 7 NRC to NU 03/29/81 VIII-3 B. CL/SEPB 7 NRC to NU 07/23/81 VI-7 C. 3. X NRC to NU 11/16/79 VIII-4 DL/SEPB 7 NRC to NU 07/07/81 (2-25) I

MILLSTONE 1 TDPIC NO. REVIEW STATUS REMARKS TOPIC HD. REVIEW STATUS REMARKS DIV/BR DIV/BR IX-1 DSI/ASB 4b NU to NRC 08/31/81 XV-10 X NkC to NU 11/16/19 IX-2 X NRC to NU 05/07/81 XV-11 DSI/CPB 7 HRC to NU 10/14/8 1 IX-3 DL/SEPB Gb HU to NRC 11/24/81 XV-12 X NRC to NU 11/16/79 IX-4 X NRC to NU 11/16/79 XV-13 DSI/CPB 7(Sys) NU to NRC 09/09/81 DSI/AEB 5(Doses) NRC to NU 11/03/81 IX-5 DL/SEPS 4b NU to NRC 11/19/81 XV-14 DSI/RSB 7 NRC to NU 09/18/81 IX-6 DE G HRC to NU 05/07/81 XV-15 DSI/RSB 7 NRC to NU 10/28/31 X X NRC to NU 05/07/81 XV-16 DSI/AEB 5 NRC to NU 11/03/81 XI-1 DSI/ETSB X NR? to NU 12/04/81 XV-17 X NRC to NU 11/16/79 XI-2 DSI/ETSB X NT.C to NU 12/04/81 XV-18 DSI/AEB 5 NRC to NU 11/03/81 XIII-1 X NRC to t;U 05/07/81 XV-19 DSI/RSB 7(Sys) NRC to NU 08/26/81 XIII-2 DL/SSPB G NRC to NU 05/07/81 DSI/AEB 5(Doses) NRC to NU 11/03/81 XV-1 DSI/RSB 4b NU to NRC 06/30/81 XV-20 DSI/AEB 5 NRC 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/RS3 7 NRC to NU 09/18/81 XV-22 X NRC to NU 05/07/81 XV-4 DSI/RSB 7 HRC to NU 09/18/81 XV-23 X NRC to NU 05/07/81 XV-5 DSI/RSB Gb NU to NRC 06/30/81 XV-24 X NRC to NU 05/07/81 XV-6 X HRC to NU 11/16/79 XVI X HRC to NU 11/15/80 XV-7 DSI/RSB Gb NU to NRC 06/30/81 XVII DL 7 NRC to NU 08/17/78 XV-8 DSI/CPB 7 HRC to NU 08/26/81 XV-9 DSI/RSB Gb NU to NRC 06/30/81 (2-26)

OYSTER CREEK FACILITY: OYSTER CREEK 1 TOPIC NO. REVIEW STATUS REMARKS DIV/BR LICENSEE: JERSEY CENTRAL POWER 8 LIGHT 1I-1 A. D E/ S A B Gb JCPL to NRC 11/30/81 REGION / LOCATION: 9 MILES SOUTH OF TOMS RIVER, NJ. II ' B. DE/SAB 4b JCPL to NRC 11/30/81 DOCKET NO.+ 05000219 II-1 C. DE/SAB 4b JCPL to NRC 11/30/81 POWER CAPACITY: 1930(ThdRMAL) 0650(ELECTRICAL) II-2 A. DSI/AEB 5 NRC to JCPL 12/17/80 OL NUM"ER: DPR-16 II-2 B. X HRC to JCPL 05/07/81 N.S.S.S. GE. II-2 C. DSI/AEB 4b JCPL to NRC 11/04/81 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 05/07/81 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD II-3 B. DE/HGEB 4b JCPL to NRC 05/07/81 OPERATING REACTORS PROJECT MANAGER: J. LOMBARDO II-3 B. 1. DE/HGEB 4b JCPL to NRC 05/07/81 INTEGRAlED ASSESSMENT PROJECT MANAGER: R. FELL.f/g/ II-3 C. DE/HGEB 4b JCPL to NRC 05/07/81 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. DE/GSB 5 NRC to GPU 08/03/81 FROM REVIEW BRANCH X - Dt'LETED II-4 C. DE/GSB 7 HRC to JCPL 06/08/81 4b-SAR RECEIVED FROM 0 - TOPIC NOT lTCENSEE II-4 D. DE/HGEB 0 STARTED l l 5 - DRAFT SE SENT II-4 E. X NRC to JCPL 11/16/79 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F. DE/HGEB 4b JCPL to NRC 11/04/81 6 - SE RESPONSE RECEIVED 1 2 - QUESTIONS SENT BY NRC III-1 DL/SEPB 3(Sys) HRC to JCPL 02/21/79 I TO UTILITY DL/SEPB 5(Elec) NRC to JCPL 07/09/81 1 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB Gb JCPL to NRC 05/07/81 RECEIVED BY HRC (2-27)

l l l 0YSTER CREEK TOPIC NO. REVIEW STATUS REMARKS TOPIC NO. REVIEW STATUS REMARKS JIV/BR DIV/CR III-3 A. DE/SEB 4b JCPL to NRC 05/07/81 111-10 B. X NRC to JCPL 11/10/79 III-3 B. X NRC to JCPL 12/26/80 III-10 C. A NRC to JCPL 11/16/79 III-3 C. DE/HGEB Gb JCPL to NRC 11/04/81 III-11 X NRC to JCPL 05/07/81 III-4 A. DSI/ASB C III-12 X NRC to JCPL 05/C7/81 III-4 B. DE/MTEB 0 IV-1 A. DL/SEPB 7 NRC to JCPL 05/30/79 III-4 C. DSI/ASB 2 NRC to JCPL 01/19/81 IV-2 DSI/ICSB 2 NRC to JCPL 12/15/80 III-4 D. DE/SA3 4b JCPL to NRC 05/07/81 IV-3 X NRC to JCPL 05/07/81 III-5 A. DL/SEPB 5 NRC to JCPL 06/10/81 V-1 DE/MTEB X HRC to JCPL 11/24/81 III-5 B. DL/SEPB 6 JCPL to NRC 10/06/81 V-2 X NRC to JCPL 11/16/79 III-6 DL/SEPB 6 JCPL to NRC 06/15/81 V-3 X NRC to JCPL 05/07/81 III-7 A. X NRC to JCPL 05/07/81 V-4 X NRC to JCPL 05/07/81 III-7 B. DL/SEPB Ga V-5 DL/SEPB 6 JCPL to NRC 11/04/81 III-7 C. X NRC to JCPL 11/16/79 V-6 DL/SEPB 7 NRC to JCPL 03/05/80 III-7 D. DE/SEB Gb JCPL to NRC 11/04/81 V-7 X NRC to JCPL 05/07/81 III-8 A. DSI G HRC to JCPL 05/07/81 V-8 X NRC to JCPL 05/07/81 III-8 B. X NRC to JCPL 09/26/80 V-9 X NRC to JCPL 11/f6/79 III-8 C. DL/tEPB 7 NRC to JCPL 10/30/80 V-10 A. DL/SEPB 7 JCPL to llRC 05/15/79 III-8 D. X NRC to JCPL 05/07/81 V-10 B. DL/SEPB 7 NRC to JCPL 09/25/80 III-9 X HRC to JCPL 05/07/81 V-11 A. DL/SEPB 7 NRC to JCPL 07/08/81 III-10 A. DL/SEPB 7 HRC to JCPL 06/29/81 V-11 B. DL/SEPB 7(Sys) NRC to JCPL 09/25/80 DL/SEPB 7CElec) NRC to JCPL 07/09/01 (2-28)

OYSTER CREEK l TOPIC HD. REVIEW STATUS REMARKS TCPIC NO. REVIEW STATUS PEMARKS DIV/BR DIV/ER V-12 A. CL/SEPB 6 JCPL to SKC 11/ Q ' /81 VI-7 D. DL/SEPB 7 NRC to JCPL 02/17//8 V-13 X NRC to JCPL C5/07/81 VI-7 E. X NRC to JCPL CS/07/81 VI-1 DE/CEB 2 NRC to JCPL 06/06/79 VI-7 F. X NRC to JCPL 11/16/79 VI-2 A. X NPC to JCPL 05/07/81 VI-8 X HRC to JCPL 05/C7/81 VI-2 B. X NRC to JCPL 05/07/81 VI-9 x NRC to JCPL 11/16/79 VI-2 C. X NRC to JCPL 11/16/79 VI-10 A. DL/SEPB 7 NRC to JCPL 05/18/81 VI-2 D. DSI/CSB 2 VI-10 B. X HRC to JCPL 11/16/79 VI -3 DSI/ CSP ? VII-1 A. DL/SEPB 7 NRC to JCPL 07/30/81 VI-4 DSI/CSB 4a(Sys) VII-1 B. DL/SEPB 7 NRC to JCPL C8/t7/78 DL/SEPB 5(Elec) NRC to JCPL 08/05/81 VII-2 DL/SEPB 6 JCPL to NRC 08/17/8! r sVI-5 X NRC to JCPL 05/07/81 P VII-3 DL/SEPB 7(Sys) NRC to JC'l C9/25/80 7I-4 DSI/CSB G HRC to JCPL 05/07/81 DL/SEPB 7(Elec) HRC to JCPL 07/09/C1 VI-7 A. 1. X NRC to JCPL 11/16/79 VII-4 X NRC to JCPL 05/07/81 ,\\'fI-7A. 2. i X NRC to JCPL 05/07/81 VII-5 X NRC to JCPL 05/07/81 ]\\VI7A. 3. I'L / e E? 3 '7 HRC to JCPL 07/30/81 VII-6 DL/SEPB 7 NRC to JCPL 08/29/81 ' V!-7 A. 4. DSI/RSB G NRC to JCPL 05/07/81 VII-7 X NRC to JCPL 11/16/79 s VI-7 B. X NRC to JCPL 11/16/79 VIII-1 A. DSI/PSB G HRC to JCPL 05/07/81 VI-7 C. DL/SEPB 7 NRC to JCPL 03/13/81 VIII-2 DL/SEPB 7 NRC to JCPL 06/29/81 VI-7 C. 1 DL/SEFB 7 NRC 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 to JCPL 06/29/81 VI-7 C. 3. X NRC to JCPL 11/16/79 VIII-4 DL/SEPB 2 NRC to JCPL 03/26/80 i L 4 4 \\ s k (2-19) t es ~ !e / t-

3 ~. e s + s g.0YSTER CREEK, i h if0PIC NO. NEVAEbl STATUS REMARKS TOPIC NO. REVILW STATUS REMARKS g DIV/3Ps DIV/BR _ ws 3 (g IX-1 CSI/A.iB 3 JCPL to NRC 12/14/79 XV-10 X hRC to JCPL 11/i6/79 ' (X-2 X NRC to JCPL 05/07/81 XV-11 DSI/CPB 5 NRC to JCPL 04/09/81 IX-3 CSI/ASB' 6 JCPL to NRC 10/01/81 XV-12 X NRC to JCPL 11/16/79 IX-4 X NRC to JCPL 05/07/81 XV-13 DSI/AEB 4b(Doses)JCPL to NRC 11/04/81 DSI/CPB 5(Sys) 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 NRC to JCPL 05/07/81 XV-15 DSI/RSB Gb JCPL to NRC 11/04/81 X X NRC to JCP'. 05.',7/81 XV-16 DSI/AEB 4b JCPL to NRC 11/04/81 XI-1 DSI/ETSB X NRC to JCPL 12/04/81 XV-17 X NRC to JCPL 11/16/79 XI-2 DSI/ETSB X NRC to JCPL 12/04/81 XV-18 DSI/AEB Ga XIII-1 X NRC to JCPL 05/07/81 XV-19 DSI/AEB 4b(Doses)JCPL to NRC 11/04/81 XIII-2 CL/SSPB 7 NRC to JCPL 09/25/80 DSI/RSB 7(Sys) HRC to JCPL 09/04/81 XV-1 DSI/RSB 4b JCPL to NRC 11/04/81 XV-20 DSI/RSB 4b JCPL to NRC 05/07/81 XV-2 X NRC to JCPL 11/16/79 XV-21 X HRC to JCPL 05/07/81 XV-3 CSI/R$B 7 NRC to JCPL 07/16/81 XV-22 X NRC to JCPL 05/07/81 XV-4 DSI/RSB 7 NRC to JCPL 07/16/81 XV-23 X NRC to JCPL 05/07/8t XV-5 DSI/RSS 4b JCPL to NRC 05/07/81 XV-24 X NRC to JCPL 05/07/81 XV-6 X NRC to JCPL 11/16/79 XVI X NRC to JCPL 11/05/80 XV-7 DSI/RSB 46 JCPL to NRC 08/25/81 XVII DL 7 HRC to JCPL 08/17/78 XV-8 DSI/CPB 5 NRC to JCPL 03/31/81 XV-9 DSI/RSS 4b JCPL to NRC 11/04/81 (2-30)

l'J4Jl.lfsifil:Pli5s' ?

l FACILITY: PAL 4SADE%

TOPIC NO. REVIEW STATUS REMARKS 8 DIV/BR LICENSEE: CCHSUMERS PCWER __. A. DL/SEPB 7 CPCs to NRC 12/28//? 11-1 REGION / LOCATION: 5 MILES SCUTH OF SOUTH HAVEN. MI. l II-1 B. DL/SEPB 7 CPCo to NRC 12/23/7". f I DOCKET N0f 05000255 05/13/81 IT-1 C. DL/;EPB CPCo to nRC POWER CAPACI!v: 2530(THERMAL) 080SCELECTRICAL) II-2 A, DSI/AEB 7 NRC tu CPCo 06/30.'31 OL N'JNBER: DPR-20 II-2 B. X NRC t o CPCo CS/07/3i L N.S.S.A. C-E 17-2 C. D0i/A[b 7 NRC t) CPCs O',/23/81 A/C FIR 9: BECM. II-2 D. X F R f. to CPCo 05/07/01 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL II-3 A. DE/HGEB 6 CPCJ to NRC 03/13/31 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD II-3 B. DE/HGED 6 CPCo to NRC 08/13/31 CPERATING REACTORS PROJECT MANAGER: T. WAMBACH II-3 B. 1 DE/HGEB 6 CPCo to NRC 08/13/31 INTEGRATED ASSESSMENT PROJECT MANAGER: T. MICHAELS II-3 C. DE/HGEB 6 CPCo to NRC 05/13/81 II-4 DE/GSB 7 CPCo to NRC 07/04/01 KEY FOR STATUS CODES II-4 A. DE/GSB 7 NRC to CPCo 07/04/81 .1-4 B. DE/GSB 7 CPCo to NRC 07/22/81 G - GENERIC Ga-DRAFT SE RECEIVED i FROM REVIEW BRANCH l X - DELETED II-4 C. DE/GSB 7 NRC to CPCo 06/C8/21 4b-SAR RECEIVED FRCM 0 - TOPIC NOT LICENSEE II-4 D. DE/HGEB 7 CPCo to NRC 06/01ect STARTED 5 - DRAFT SE SENT II-4 E. X NRC to CPCo 11/16/79 1 - QUESTIONS RECEIV.iD TO UTILITY FROM REVIEW BRANCH II-4 F. DE/HGED 7 CPCo to NRC 06/01/81 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC III-1 DL/SEPB 7(Eicc) NRC to CPCo 11/12/80 TO UTILITY DL/SEPB 3(Sys) CPCo to NRC CC/17/S1 7 - TOPIC CCMPLETE 3 - QUcSTION RESPONSE RECEIVED BY NRC (2-31)

PAllSADES TCPIC NO. P,EVIEW STATUS REMARKS TCPIC M3. REVIEW STATUS REMARKS DIV/BR DIV/BR 111-2 DL/SEPB i hRC to CPCo 02/27/81 III-10 8. UL/SLPB 6 CPCo to tRC 0?/C2/c I III-3 A. DE/SEB 7 NRC to CPCo 08/26/81 III-10 C. X NRC to CPCo 71/?d/79 III-3 B. X NRC to CPCo 12/26/80 III-11 X NRC to CPCo 05/07/81 III-12 X HRC to CPCo 05/07/8? III-3 C. DE/HGEB 0 III-4 A. DSI/AEB 6 CPCo to NRC 10/09/81 IV-1 A. DL/SEPB 7 CPCo to NRC 02/08/79 III-4 B. DE/MTEB G N R r. to CPCo 05/07/81 IV-2 DSI/ICSB 5 NRC to CFCo 10/16/01 III-4 C. DSI/ASB 7 NP; to CPCo 09/21/81 IV-3 X NRC to CPCo 05/07/81 III-4 D. DE/SAB 7 CPCo to NRC 08/03/81 V-1 X NRC to CPCo 11/27/81 III-5 A. DL/SEPB 4b CPCo to NRC 08/13/31 V-2 X NRC to CPCo 11/16/79 III-5 B. DL/SEPB Gb CPCo to NRC 08/25/81 V-3 X NRC to CPCo 05/07/81 III-6 DL/SEPB 6 CPCo to NRC 07/13/81 V-4 X NRC to CPCo CS/07/81 III-7 A. DL/ SEPP 6 CPCo to NRC 11/13/31 V-5 DL/SEPB 6 CPCo to NRC 10/07/81 III-7 B. DL/SEPB 5 NRC to CPCo 11/16/81 V-6 DL/SEPB 7 NRC to CPCo 03/C5/80 III-7 C. DE/SEB 7 NRC to CPCo 10/19/81 V-7 DSI/ASB 7 NRC to CPCo t 1/16 /81 III-7 D. DE/SEB 7 CPCo f.o NRC 08/17/81 V-8 X NRC to CPCo 05/07/81 III-8 A. DSI 7 NRC to CPCo 11/18/81 V-9 X NRC to CPCo 11/16/79 III-8 B. X NRC to CPCo 10/01/30 V-10 A. DL/SEPB 7 NRC to CPCo 09/26/81 III-8 C. DL/MTEB 7 CPCo to NRC 12/28/79 V-10 B. CL/SEPB 7 NRC to CPCo 10/27/81 III-8 D. X NRC to CPCo 05/07/81 V-11 A. DL/SEPB 7 NRC to CPCo 11/09/81 III-9 X NRC to CPCo 05/07/81 V-11 B. DL/SEPB 7(S0) CPCo to NRC 10/27/81 DL/SEPB 7(Elec) NRC to CPCo C6/02/81 III-10 A. DL/SE'B 7 NRC to CPCo 05/19/81 (2-32)

PALISADES 1 1 TCPIC ND. REVIEW STATUS REMARG TCPIC N3. REVIEW STATUS R Ei:ADr5 1 DIV/B.? DIV/;R l v-12 A. X SkC to CFCC 11/16/79 VI-7 D. DL/5LPB 7 NPC to CPCo 08/1//18 V-13 X NRC to CPCo 05/07/81 VI-7 E. X NRC to CPCo 05/C7/81 VI-1 DE/CEB 7 NRC to C?Co C8/03/31 VI-7 F. DL/SEPB 7 NRC to CPCo 06/30/81 t VI-2 A. X NRC to CPCo 05/07/81 VI-8 X NRC to CPCo 05/07/81 1 i VI-2 B. X hRC to CPCo 05/07/81 VI-9 X N2C to CPCo 11/16/79 l 1 VI-2 C. X NRC to CPCo 11/16/79 VI-10 A. DL/SEPB 7 hPC to CPCo 06/19/81 VI-2 D. DSI/CSB 7 NRC to CPCo 11/16/81 VI-10 3. X NRC to CPCo 11/16/79 VI-3 DSI/CS3 7 NDC to CPCo 11/16/81 VII-1 A. DL/SE'B 7 NRC to CPCo C8/28/$1 VI-4 DL/SEP3 7(Ele:) CPCo to NRC C8/18/81 \\II-1 3. DL/SEPB 7 NRC to C?Co CS/17/73 DCI/CSB 6(Sys) CPCo to NRC 08/10/81 VII-2 DL/SEPB 7 NRC to CPCv 05/19/81 VI-5 X NRC to CPCo 0 5/ C 7/ 81 VII-3 DL/SEPB 7(Sys) CPCo +.o FRC 10/?7/C1 VI-6 DSI/CSB Ga DL/SEPS 7(EIce) CPCo to NRC 09/30/81 VI-7 A. 1. X NRC to CPCo 11/16/79 VII-4 X NRC to CPCo 05/C7/81 I l VI-7 . 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 10/29/81 VII-6 DL/SEPS 7 NRC to CPCo 05/11/81 VI-7 A. 4. X NRC to CPCo 05/07/81 VII-7 X N7C to CPCo 11/16/79 VI-7 B. DL/SEPB 7(EIcc) NRC to CPCo 05/19/01 VIII-1 A. DSI/PSB G NRC to CFCo C5/07/C1 CSI/RSS 7(Sys) NRC to CPCo Cf/30/81 VIII-2 DL/SEP3 7 NRC to CPCo 06/07/01 VI-7 C. DL/SEPB 7 NRC to CPCo 02/20/81 l VIII-3 A. DL/SEP3 7 NRC to CPCo C5/22/81 VI-7 C. 1 DL/SEPB 7 NRC to CPCo 11/18/80 VIII-3 B. CL/SEPB 7 NRC to CPCo 08/05/81 VI-7 C. 2. DL/SEF3 7 N?C to CPCo C2/20/81 1 1 VIII-4 DL/SEPB 7 Nr.C to CPCo 07/31/01 VI-7 C. 3. X CPCc to NRC 12/12/79 1 l (2-33)

PALISADES TCPIC NG. REVIEW STATUS REMARKS TCPIC ND. REVIEW STATUS REMARTS DIV/ER DIV/BR IX-1 CSI/ASB 3 CPCo to NRC 09/29/81 XV-10 CL/5EFS / re.C to crCo Ol/ti/L1 1 IX-2 X N'C to CPCo 05/07/81 XV-11 X NRC to CPCo 17/01/80 IX-3 DL/SEPB 7 NRC to CPCo 09/06/81 XV-12 DL/SEPB 7(Doces) N'O to CPCo 01/29/$0 DL/SEPB 7(Sys) HRC to CPCo 07/17/81 IX-4 DSI/RSB 5 NRC to CPCo 11/23/81 XV-13 X NRC to CPCo 11/16/79 IX-5 DL/SEPB 6 CFCo tc NRC 11/10/81 XV-14 DL/SEPB 7 NRC to CPCo 07/17/C1 IX-6 DE G NRC to CPCo 05/07/81 XV-15 DL/SEPB 7 NRC to CPCo 07/17/81 X X NRC to CPCo 05/07/81 XV-16 DL/SEPS 7 NRC to CPCo 12/31/80 XI-1 DSI/ET;; X HRC to CPCo 12/04/81 XV-17 DL/SEPB 7(Doses) t;RC to CPCo 01/29/80 XI-2 DSI/ETSB X NRC to CPCo 12/04/81 DL/SEPB 7(Sys) HRC to CPCo 07/17/31 XIII-1 X HRC 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) NPC to CPCo 11/21/80 DL/SEPB 7(Sys) NRC to CPCo 07/17/81 XV-1 DL/SEPS 7 NRC to CPCo 07/17/81 XV-20 DL/SEPB 7 NRC to CPCo 11/21/80 XV-2 DL/SEPB 7(Doses) HRC to CPCo 05/18/81 DL/SEPB 7(Sys) HRC to CPCo 07/17/01 XV-21 X NRC to CPCo 05/07/81 XV-3 DL/SEPB 7 HRC to CPCo 07/17/81 XV-22 X NRC to CPCo 05/07/81 XV-4 DL/SEPB 7 HRC to CPCo 07/17/81 XV-23 X NPC to CPCo 05/07/81 XV-5 DL/SE?B 7 NRC to CPCo 07/17/81 XV-24 X NTt C to CPCo 05/07/81 XV-6 DL/SEPB 7 NRC to CPCo 07/17/81 XVI X N'C to CPCo 11/05/80 XV-7 DL/SEPB 7 NRC to CPCo 07/17/81 XVII DL 7 NRC to CPCo 08/17/78 1 XV-8 DL/SEPB 7 NRC to C?Co 07/17/81 XV-9 DL/SEPB 7 NRC to CPCo 07/17/81 (2-34)

l SAN ON0FRE l FACILITY: SAN ONOFRE 1 TOPIC HO. REVIEW STATUS REMARKS I DIV/ER LICENSEE: SOUTHERN CALIFORNIA EDISON 11-1 A. DL/SEPB 7 NRC to SCE t t/07/79 REGION /LOCATIDH: 5 MILES SOUTH OF SAN CLEMEN"E, CA. II-1 B. DL/SEPB 7 NRC to SCE 11/07/79 DOCKET NO. 05000206 II-1 C. DE/SAB 4b SCE to NRC 11/12/81 POWER CAPACITY: 1347(THERMAL) 0430(ELECTRICAL) II-2 A. DSI/AEB 7 NRC to SCE 04/27/81 OL NUMBER: DPR-13 II-2 B. X HRC to SCE 05/07/81 II-2 C. OSI/AEB 7 NRC to SCE 11/18/81 , pp II-2 D. X NRC to SCE 0S/07/81 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL II-3 A. DE/HGES 3 SCE to NRC 11/17/81 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD II-3 B. DE/HGEB 3 SCE to NRC 11/17/81 OPERATING REACTORS PROJE/T MANAGER: S. NOWICKI II-3 B. 1. DE/HGEB 6 SCE to NRC 10/08/81 INTEGRATED ASSESSMENT PROJECT MANAGER: E.MCKENHAfk}'N( II-3 C. DE/HGEB Ga II-4 DE/GSB 5 NRC to SCE 03/15/81 KEY FOR STATUS CODES II-4 A. DE/GSB 5 NUREG-0712 12/20 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B. DE/GSB 5 NUREG-0712 12/80 FF0f1 REVIEW BRANCH X - DELETED II-4 C. DE/GSB 5 HUREG-0712 12/80 4b-SAR RECEIVED FROM 0 - TOPIC HOT LICENSEE II-4 D. DE/HGEB Gb SCE to NRC 1t/02/31 STARTED 5 - DRAFT SE SENT II-4 E. X SRC to SCE 11/16/79 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANCH II-4 F. DE/HGES 46 SCE to NRC 11/02/81 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC III-1 DL/SEPB 3(Sys) SCE to NRC 08/29/79 TO UTILITY DL/SEPB 0(Elec) 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 3 SCE to NRC 11/20/81 RECEIVED BY NRC (2-35)

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SAN ON0FRE TOPIC NO. REVIEW STATUS REMARKS TOPIC NO. REVIEM STATUS REMARKS DIV/BR DIV/ER v-12 A. X hRC to SCE 11/16/19 VI-7 D. DL/SEPB 7 hRC to SCE CS/17/78 V-13 X NRC to SCE 05/07/81 VI-7 E. X HRC to SCE 05/07/81 VI-1 3 SCE to NRC 08/03/79 VI-7 F. X NRC to SCE 11/16/79 VI-2 A. X NRC to SCE 05/07/81 VI-8 X NRC to SCE 05/07/8t VI-2 B. X NRC to SCE 05/07/81 VI-9 X HRC to SCE 11/16/79 VI-2 C. X NRC to SCE 11/16/79 VI-10 A. DL/SEPB 5 NRC to SCE 05/2C/81 VI-2 D. DSI/CSB 3 SCE to NRC 06/22/79 JI-10 B. UL/SEPB 7(Sys) HRC to SCE 11/15/79 DL/SEPB 7(EIuc) NRC to SCE 11/15/79 VI-3 DSI/CSB 3 SCE to NRC 06/22/79 VII-1 A. DL/SEPB 5 NRC to SCE 09/09/81 VI-4 DSI/CSh 3(Sys) SCE to NRC 11/18/81 DL/SEPB 7(Elec) HRC to SCE 09/03/81 VII-1 B. DL/SEPB 7 HRC to SCE 08/17/78 VI-5 X NRC to SCE 05/07/81 VII-2 DL/SEPB 5 NRC to SCE 11/17/81 VI-6 DSI/CSB G NRC to SCE 05/07/81 VII-3 DL/SEPB 5(Sys) NPC to SCE 05/20/81 DL/SEPB 5(EIcc) HRC to SCE 11/18/01 VI-7 A. 1 DL/SEPB 7 NRC to SCE 02/20/81 VII-4 X NRC to SCE 05/07/81 VI-7 A. 2. X NRC to SCE 05/07/81 VII-5 X NRC to SCE 05/07/81 VI-7 A. 3. DL/SEPB 5 NRC to SCE 11/18/81 VII-6 DL/SEPB 7 NPC to SCE C8/28/81 VI-7 A. 4. X NRC to SCE 05/07/81 VII-7 X HNC to SCE 11/16/79 VI-7 B. DSI/RSB 5(Sys) NRC to SCE 07/esesf DL/SEPB SCEIcc) NRC 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 t:RC to SCE 07/31/81 VI-7 C. 1. DL/SEPB 7 NRC to SCE 08/03/81 VIII-3 A. DL/SEPB 7 NRC to SCE 11/07/79 VI-7 C. 2. DL/SEPB 7 NRC to SCE 06/01/81 VIII-5 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 6 SCE to NRC 08/14/81 l t (2-37)

l SAN ON0FRE TCPIC NO. REVIEW STATUS REMARKS TCPIC NO. REVIEW STATUS REMARKS DIV/BP DIV/BR IX-1 DSI/ASB 3 SCE to NRC 10/05/79 XV-10 DSI/RSB 45 SCE to NRC 07/01/81 IX-2 X NRC to SCE 05/07/81 XV-11 X NRC to SCE 10/G1/80 IX-3 DL/SEPB 4b SCE to NRC 11/02/81 XV-12 DSI/P.SB 7(Sys) HRC to SCE 11/19/81 DL/SEPB 7(Dosos) NRC to SCE 01/29/80 IX-4 DSI/RSB 7 NRC to SCE 07/16/81 XV-13 X NRC to SCE 11/16/79 IX-5 DL/SEPB 0 XV-14 DSI/RSB 4b SCE to NRC 07/0t/81 IX-6 DE G NRC to SCE 05/07/81 XV-15 DSI/RSB Gb SCE to NRC 07/01/81 X X NRC to SCE 05/07/81 XV-16 DSI/AEB 7 NRC to SCE 11/18/81 XI-1 DSI/ETSB X NRC to SCE 12/04/81 XV-17 DSI/RS3 4a(Sys) XI-2 DSI/ETSB X NRC to SCE 12/04/81 DSI/AEB 7(Doses) hkC to SCE 01/29/80 XIII-1 X NRC to SCC 05/07/81 XV-18 X NRC to SCE 10/01/20 XIII-2 DL/SSPB 7 HRC to SCE 01/22/81 XV-19 DSI/RSB 7(Sys) NRC to SCE 08/26/81 DL/SEPB 7(Dosos) NRC to SCE 01/29/30 XV-1 DSI/RSB 7 NRC to SCE '0/27/81 XV-20 DL/SEPB 7 NRC to SCE 03/28/30 XV-2 DSI/RSB 7(Sys) SCE to NRC 10e?7/81 DL/SEPB 7(Doses) NRC to SCE 01/*9/80 XV-21 X HRC to SCE 05/07/81 XV-3 DSI/RSB 7 NRC to SCE 08/26/01 XV-22 X NRC to SCE 05/07/81 XV-4 DSI/RSB D SCE to NRC 08/18/81 XV-23 X HRC to SCE C5/07/81 XV-5 CSI/RSB 4b SCE to NRC 07/01/81 XV-24 X NRC to SCE 05/07/81 XV-6 DSI/RSB 4b SCE to NRC 07/01/81 XVI X NRC to SCE 11/05/80 XV-7 DSI/RSB 4b SCE to NRC 07/01/81 XVII DL 7 NRC to SCE 08/17/78 XV-8 DSI/CPB 7 NRC to SCE 11/19/81 XV-9 DSI/RSB 5 NRC to SCE 05/11/81 (2-38)

YANKEE R0WE FACILITY: YANKEE R0WE 1 TOPIC HO. REVIEW STATUS PEMARKS DIV/BR LICENSEE: YANKEE ATOMIC ELECTRIC 11-1 A. DE/SAB 0 REGIDH/LOCATICN: 25 MILES HORTH EAST OF PITTSFIELD, MASS. II-1 B. DE/SAB Gb YAEC to NRC 45/01/81 DOCKET NO. 05000029 II-1 C. DE/SAB 4b YEAC to NRC C4/09/81 POWER CAPACITY: 600(THER;1AL) 165(ELECTRICAL) II-2 A. CSI/AEB 7 NRC to YAEC 08/03/81 OL NUMBER: DPR-3 II-2 B. X NRC to YAEC C5/07/81 H.S.S.S. WEST. II-2 C. DSI/AEB 7 NRC to TAEC 09/04/81 A/E FIRM: $4W II-2 D. X NRC to YAEC 05/07/81 SYSTEMITIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL II-3 A. DE/HGEB 6 YAfC to NRC 33/16/81 OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD II-3 B. DE/HGEB t Ye':C to NRC 03/16/81 OPERATING REACTORS PROJECT MANAGER: R. CARUSO II-3 B. 1 DE/HGEB 5 NRC to YAEC 02/09/81 INTEGRATED ASSESSMENT PROJECT MANAGER: A. WANG bSI b II-3 C. DE/HGEB 3 Site Visit d II-4 DE/GSB 7 NRC to YAEC 06/08/81 KEY FOR STATUS C0011 G - GENERIC 4a-DRAFT SE RECEIVED II-4 B. DE/GSB 3 FRCM REVIEW BRANCH X - DELETED II-4 C. DE/GSB 7 NRC to YAEC 06/08/81 4b-SAR RECEIVED FROM 0 - TOPIC HOT LICENSEE II-4 D. DE/HGEB 3 Site Visit STARTED 5 - CRAFT SE SENT II-4 E. DE/HGEB 3 Site Visit 1 - QUESTIONS RECEIVED TO UTILITY FROM REVIEW BRANrH II-4 F. DE/HGEB 4b YAEC to NRC 08/31/81 6 - SE RESPONSE RECEIVED 2 - QUESTIONS SENT BY NRC III-1 DL/SEPB 0(Elec) TO UTILITY DL/SEPB 3(Sys) YAEC to NRC 01/31/79 7 - TOPIC COMPLETE 3 - QUESTION RESPONSE III-2 DL/SEPB 3 YAEC to NRC 08/21/81 RECEIVED BY HRC 3 (2-39)

l YANKEE R0WE TCPIC NO. REVIEW STATUS REMARKS TOPIC NO. REVIEW STATUS REMARKS DIV/BR DIV/BR III-3 A. DE/SEB 3 YAEC to hRC 09/06/79 III-10 B. X tEC to YAE.C 11/16/79 III-3 B. X NRC to YAEC 12/26/80 III-10 C. X NRC to YAEC 11/16/79 III-3 C. DE/HGEB D III-11 X NRC to YAEC 05/07/81 III-4 A. DSI/ASB D III-12 X NRC to YAEC 05/07/81 III-4 B. DE/MTEB G NRC to YAEC 05/07/81 IV-1 A. DL/SEPB 7 NRC to YAEC 04/18/79 III-4 C. DSI/ASB 0 IV-2 DSI/ICSB Gb YAEC to NRC 09/17/81 III-4 D. DE/SAE 4b YAEC to NRC 06/30/81 IV-3 X NRC to YAEC 05/07/81 III-5 A. DL/SEPE 2 NRC to YAEC 01/04/80 V-1 DE/MTEB X NRC to YAEC 11/27/81 III-5 B. DL.SEPB 1 V-2 X NRC to YAEC 11/16/81 III-6 DL/SEPB 3 YAEC to NRC 06/30/81 V-3 X NRC to YAEC 05/07/81 III-7 A. X NRC +.o YAEC 05/07/81 V-4 X NRC to YAEC 05/07/81 III-7 B. D L/ S Ei'B 3 YAEC to NRC 08/21/8i V-5 DL/SEPB 5 NPC to YAEC 01/24/80 III-7 C. X NRC to YAEC 11/16/79 V-6 DL/SEPB 7 NRC to YAEC 03/05/80 III-7 D. DE/SEB 4b YAEC to NRC 11/18/81 V-7 DSI/ASB G NRC to YAEC 05/07/81 III-8 A. DSI C NRC to YAEC 05/07/81 V-8 X NRC to YAEC 05/07/81 III-8 B. X NRC to YAEC 10/01/80 V-9 X NRC to YAEC 11/16/79 III-8 C. DL/$EPB 7 NRC to YAEC 11/15/79 V-10 A. DL/SEPB 7 NRC to YAEC 11/05/79 III-8 D. X NRC to YAEC 05/07/81 V-10 B. DL/SEPB 5 NRC to YAEC 09/06/81 III-9 X NRC to YAEC 05/07/81 V-11 A. DL/SEPB 7 NRC to YAEC 12/08/80 III-10 A. D L / S E I'B 7 NPC to YAEC 09/22/81 V-11 B. DL/SEPB 5(Sys) HRC to YAEC 09/06/81 DL/SEP3 0(Elec) (2-40)

YANKEE R0WE TOPIC HO. REVIEW STATUS REMARKS TCPIC NO. REVIEW STATUS REMARKS DIV/BR DIV/SR V-12 A. X NRC to YAEC 11/16/79 VI-7 D. DL/SEPB 7 MC to YAEC 03/17//E-V-13 X NRC to YAEC 05/07/81 VI-7 E. X NRC to YAEC 05/07/8 VI-1 DE/CEB 3 YEAC to NRC 06/26/79 'VI-7 F. DL/SEPB 7 NRC to YAEC 08/28/31 VI-2 A. X H R '. to YAEC 05/07/81 V!-8 X NRC to YAEC 05/07/81 VI-2 B. X NRC te YAEC 05/07/81 VI-9 X HRC to YAEC 11/16/79 VI-2 C. X NRC to YAEC 11/16/79 VI-10 A. DL/SEPB 3 YAEC to NRC 06/30/31 VI-2 D. DSI/CSB 2 VI-10 B. X HRC to YAEC tt/16/79 VI-3 DSI/CSB 2 VII-1 A. DL/SEPS 6 YAEC to NRC 11/24/81 VI-4 DSI/CSB 1(Sys) VII-1 B. DL/SEPB 7 NRC to YAEC 08/17/78 DL/SEPS 5(Elec) HRC to YAEC 10/16/81 VII-2 DL/SEPB 6 YAEC to NRC If/24/81 VI-5 X HRC to YAEC 05/07/81 VII-3 DL/SEPB 6(Sys) YAEC to NRC 11/24/81 VI-6 DSI/CSB G NRC to YAEC 05/07/81 DL/SEPB 0(Elec) VI-7 A. 1. DL/5EPB 7 NRC to YAEC 02/20/81 VII-4 X NRC to YAEC 05/07/81 VI-7 A. 2. X NRC to YAEC 05/07/81 VII-5 X NRC to YAEC 05/07/81 VI-7 A. 3. DL/SEPB 4b YAEC to NRC 06/30/81 VII-6 DL/SEPB NRC to YAEC 08/28/81 VI-7 A. 4. X HRC to YAEC 05/07/81 VII-7 X NRC to YAEC 11/16/79 VI-7 B. DSI/RSB 7(Elec) HRC to YAEC 06/04/81 VIII-1 A. DSI/PSB G NRC to YAEC 05/07/81 0(Sys) VI-7 C. DL/SEPB 7 NRC to YAEC 03/13/81 VIII-2 DL/SEPB 7 SRC to YAEC 09/03/81 i 1 VI-7 C. 1. DL/SEPB 7 HRC to YAEC 09/04/81 VIII-3 A. DL/SEPB 7 NRC to YAEC 11/07/79 VI-7 C. 2. DL/SEPB 7 NRC to YAEC 03/13/81 VIII-3 B. DL/SEPB 7 NRC to YAEC 08/28/81 VI-7 C. 3. DL/SEPB 7 NRC to YAEC 07/24/80 VIII-4 DL/SEPB 2 NRC to YAEC 06/23/31 (2-41)

YANKEE R0WE I TCPIC ND. REVIEW STtTUS REMARKS l TCPIC ND. REVIEW STATUS REMARKS DIV/ER DIV/ER IX-1 DSI/A33 4b YAEC to nkC 11/18/61 xv-10 D51/RSB 4b rAEC to NAC s s/30/ s t IX-2 X NRC to YAEC 05/07/81 XV-11 X NRC to YAEC 1C/01/80 t i IX-3 DL/SEPB Gb YAEC to NRC 09/17/81 XV-12 DSI/CP3 4b(Sys) YAEC to NRC C6/!0/81 DSI/AEB 4b(Doses)YAEC to NRC CE/51/31 IX-4 DSI/RS3 Ab YAEC to NRC C 8 / 31/ 81 l 1 XV-13 X NDC to YAEC 116/79 IX-5 DL/SEPB Gb YAEC to bRC 11/18/81 XV-14 DSI/RS3 Ab YAEC ;, NRC 06/ 20.'51 IX-6 DE G HRC to YAEC 05/07/81 XV-15 CSI/RSE 46 rafC 'o NRC 06/3C/81 X X NRC to YAEC C5/C7/81 XV-16 DSI/AES 0 h XI-1 DSI/ETSB X NRC to YAEC 12/04/81 XV-17 DSI/RS3 CCSys) XI-2 DSI/ETSB X NRC to YAEC 12/04/81 DSI/AE3 OCDosos) XIII-1 X NRC to YAEC 05/07/81 XV-18 X NRC to YAEC 10/01/80 XIII. DL/ SSP 3 7 NRC to YAEC C3/11/81 XV-19 DSI/RSS 4bSys) YAEC to NRC 11/18/81 DSI/AEB 0(Doses) XV-1 DSI/RS3 0 XV-20 DL/SEP3 7 NRC to YAEC 09/06/81 XV-2 DSI/RS3 Ab(Sys) YAEC to FRC 06/30/81 DSI/AE3 O(Doses) XV-21 X NRC to YAEC C5/07/81 XV-3 DSI/RS3 46 YAEC to NRC C6/3C/81 XV-22 X NRC to YAEC 05/07/81 l XV-4 DSI/RSS 0 l XV-23 X hRC to YAEC C5/07/?.1 i i l XV-5 DSI/RSS 4b YAEC to NRC C6/30/81 XV-24 X HEC to YAEC C5/C7/01 ! l XV-6 DSI/RSS 0 XVI X NRC to YAEC 11/C5/80 XV-7 OSI/RSS 46 YAEC to NRC 06/30/81 XVII DL 7 NRC to YAEC C2/17/78 XV-8 DSI/CP3 XV-9 DSI/RS3 Ab YA*_C to NRC C6/30/81 l (2-42)

y. ( m m O m O \\ Lu M

PALISADES Q1 PALISADES E11 ^ SAR 1/ SER 2/ SAR 1/ SER 2/ TOPIC HO. TITLE SCHEDUIE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE 111-1 Classification of NONE 12/18/81 III-8.A Loose Parts Monitoring and NONE 11/03/81C (SYS) Structures Components and Core Barrel Vibration Systems (Srismic and Monitoring (HRR 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 11/30/81 Including Functional Design Structures. Systems and and Protection Against Components Inside Single Failures Containment V-7 Reactor Coolant Pump NONE 11/16/81C III-5.B Pipe Break Outside 08/25/81R 12/30/81 Overspeed (NRR B-68) Containment VI-6 Containment Leak To-L?ng NONE 08/05/81C III-7.A Inservice Inspection. HONE 08/25/81C (MP A-04) Including Prectressed Concrete Containments with VIII-1.A Potential Equipment NONE 12/15/81 Either Grouted or Ungrouted Failures Associated with a Tendons Degraded Grid Volt qe (MP B-23) III-7.B Design Codes. Design NONE 11/16 / 81 C Critoria, Load IX-1 Fuel Storage NONE 11/15/81 Combinations, and Reactor Cavity Design Criteria IX-4 Boron Addition System 10/09/81R 11/18/81C XI-1 Appendix I(MP A-02) NONE DELETED DL SAR 1/ SER 2/ XI-? Radiological (Effluent NONE DELETED TCPIC NO. TITLE SCHEDULE SCHEDULE and Process) Monitoring Systems (NRR B-67) III-3.C Inservice Inspection of 09/30/81 R+30 J/ Water Control Structures 1/ SAR : Licenseo Safety Analysis Report-Scheduled or Actual III-4.B Turbine Missiles (MP B-46) NONE 11/30/81 (Actual (status 4b) when date is followed by R) III-7.D Containment Structural NONE 08/17/81C 2/ SER : Staff Safety Evaluation Report -Scheduled or Actual Integrity Tests (Actual (status 4a, 5,

7) when date is followed by C)

V-1 Compliance with Codes and NONE DELETED 3/ Desiginated number of days from receipt of licensee SAR Standards (10 CFR 50.55a) (Note: if Licensee SAR is received then date is from (MP A-01,A-14) receipt of additional information requested) IX-6 Fire Protection (MP B-02) 1 'ONE 01/31/82 I s (3-2)

LICENSEE SUBMITTALS i PALISADES SLBMITT/15 48 i TARGET 35 -- ACTUAL ~~ 'a WN 4 gg _ 15 -- 18 5-- / i JUN JUL AUG SEP OCT NOV DEC JAN FEB MAR APR-MAY JLN JUL MONTHS i Taraat 1 2 3 0-0 0 0 0 0 0 0 0 0 PER MONTH Actual 1 2 0 1 1 Target 1 3 6 6 6 6 6 6 6 6 6 6 6 CUMULATIVE Actual 1 3 3 4 5 (3-3)

1 l GINNA Li GINNA l ? 21 SAR le SER 2/ l SAR 1/ SER 2/ TCPIC hD. TITLE SCHE 00Li SCHEDULE i iDPIC NO. TITLE SCHEDULE SCHEDULE I11-1 Classification of Strict-SONE 12/18/81 (SYS) urns Cc ponents and Systems IX-6 Fire Protection (MP B-02) NCHE 01/04/81 (Seismic and Quality) III-2 Wind and Tornado Loadings NONE 09/23/81C 211 i SAR 1/l SER 2/ III-7.A Inservice Inspection, NCNE 12/18/81 TCPIC NO. TITLE SCHEDULE l SCHEDULE Inclucing Prestressed Concrete Contain ents with l III w.C Internally Generated 11/30/81 R+30 J/ Containments Grouted or i Missiles Ungrounded Tendons l l III-8.A Leose Parts Menitoring and NONE 11/30/81 III-7.B Design Codes, Design INO*E 12/23/81 Core Barrel Vibration Criteria, Load MonetoringthER B-60.C-12) Combinaticns, and Reactor Cavity Design Criteria V-7 Roactor Coolant Pump NONE 11/05/8tC Overspeec(NRR B-68) { VI-7.C.1 Appendix < - Electrical NCNE 11/18/81C Instrumentation and Control VI-2.D Mass and Energy Release for NONE 09/25/81C (EIC) Re-reviews Possible Pipe Break Inside Containment IX-5 Ventilation Systems NCHE 11/02/81Cl i VI-3 Containment Pressure and NCNE 09/25/81C Heat Removal Capability Li i I i SAR 2/ SER 2/ l VI-7.B ESF Switchover frem NONE 11/30/81 TCPIC N3. TITLE I SCHEDULE SCHEDULE (SYS) Injection to Recirculation Mode (Auto *atic ECOS 11-1.B Population Distributien C 4/13/81 R I 0 7/21/81C Realignecnt) II-1.C Potential Hazards or 04/15/8tR5 07/01/81C IX-1 Fuel Storace NONE 11/24/81C Chances in Potential l Hazards Due to l XI-1 Appendix ICMP A-02) lNCHE DELETED Transportatien. Institutional Industrial, XI-2 Radiological (Effluent NCHE DELETED and Military Facilities and Process) Monitoring Systems (NRR B-67) II-4.D Stability of Sleces 06/30/81R 01/31/82 l XV-9 Startuo or an Inactive Leop NONE tc/16/81C II-4.F Settle ent of Foundations 06/30/81RI 01/31/82 or Recirculation Loop at an and Buried Ecuicment Incorrcet Tr perature, and Flew Controller Malfunction III-3.C Inservice Inspection of 10/12/81R 12/23/81 Causing an Increase in BWR Water Control Structures Core Flow Rate III-4.B Turbine Missiles (MP B-46) NONE 12/31/31 XV-19 Loss of-Coolant Accidents NONE 09/29/8tC l (CGSES) Resulting fecm Spectrum of III-4.D Site Proximity Missiles "04/16/81R 07/21/81C) (SYS) Festulated Piping Breaks 10/0. -1C (Including Aircraft) Within the Reactor Coolant Pressure Boundary VI-1 Organic Meterials and 11/ 0 6/8 t R J1/30/81 Post Accident Chemistry (3-4)

GINNA l J/ SAR : Licensee Safety Analysis Report-Scheduled or Actual (actual (status 4b) when date is follwed by R) 2/ SER : Staff Safety Evaluation Report -Scheduled or Actual (Actual (status 4a. 5,

7) when date is followed by C)

}/ Desiginated number of days from receipt of licensee SAR (Note: if Licensee SAR is received then date is from receipt of additional information requested) (3-5) 1

O 4 r, O M g O n C n 3 O n -C t-i- si O n E "N Dw f< q n O u g n LLI O LD n 2 L1J N* LJ O e N N O V N \\ O O J O O O O t= 0 O O O -f' -k-f !~ = m m n m e j i I 3 4 3 5 5 l = E 8> a 5 g s, = 2 l E 3 g u

_m DRESDEN 2 EL DRESDEN 2 DX (Cont.) SAR 1/ SER 2/ SAR 1/ SER Z/ TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE 111-1 Classification of NONE 12/30/81 11-3.B Floodin1 Potential and NDHE R+45 (SYS) Structures. Components and Protection Requirements Systems (Seismic and Quality) II-3.B.1 Capability of Operating NONE R+45 Plant to Cope with Design III-2 Wind and Tornado Loadings 10/30/81 R+60 1/ Basis Flooding Conditions III-5 A Effects of Pipe Break on 06/30/82 10/12/82 II-3.C Safety-related Water NONE R+45 Structures, Systems and Supply (Ultimate Heat Sink Components Inside (UHS)) Containment III-7.B Deslan Codes. Design NONE 10/30/82 Criteria. Load II-4.E Dam Integrity 10/20/81 R+30 3 Combinations, and Reactor Cavity Design Criteria II-4.F Settlement of Foundations 09/30/81 R+30 and Buried Equipme.it VI-4 Containment Isolation NONE 11/30/81 (ELEC) System III-3.A Effects of High Water Level 10/20/81 03/31/82 on Structures VII-1.A Isolation of Reactor NONE 08/05/81C Protection System from III-3.C Inservice Inspection of 10/20/81 R+30 Non-Safety Systems. Water Control Structures Including Qualifications of Iso? ' ion Devices III-4.B Turbine Missiles NDHE 01/15/82 VII-6 Frequency Decay NDHE 08/26/8tC III-4.D Site Proximity Missiles 10/31/81 R+30 (Including Aircraft) IX-5 Ventilation Systems NONE 12/11/81 III-7.D Containment Structural 04/27/81R 03/31/82 Integrity Tests EE SAR 1/ SER R/ V-1 Compliance with Codes NONE DELETED i TOPIC NO. TITLE SCHEDULE SCHEDULE and Standards (10 CFR 50.55a)(MP A-01,A-14) Il-1.A Exclusion Area Authori ty 06/01/51R 10/06/81C and Control VI-1 Organic Materials and 10/31/81 R+45 Post Accident Chemistry II-1.B Population Distribution 04/27/81R 10/06/81C 1 IX-6 Fire Protection NONE 02/01/82 II-1.C Potential Hazards or 10/30/81 R+30 Changes in Potential Hazards Due to Dil Transportation, SAR 1/ SER 2/ Institutional Industrial. TOPIC NO. TITLE SCHEDULE SCHEDULE and Military Facilities II-2.C Atmospheric 1ransport and 03/20/8tR 08/26/81C ] II-3.A Hydrologic Description NONE R+45 Diffusion Characteristics for Accident Analysis III-4.A Tornado Missiles 10/31/81 R+30 (3-7) {

1 DRESDEN 2 Ell (Cont.) Dil (Cont.) SAR 1/ SER 2/ SAR 1/ SER 2/ TOPIC HO. TITLE SCHEDULE SCHEDULE TOPIC HO. TITLE SCHEDULE SCHEDULE III-4.C Internally Generated 10/31/81 R+30 XV-3 Loss of External Load, 10/15/81R 11/17/810 Missiles Turbino Trip, Los, of Condenser Vacuum. Closure III-8.A Loose Parts Fonitoring NONE 11/30/81 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 and Protection Against Power to the Station Single Failures Auxiliaries VI-2.D Mass and Encray Release for NONE 11/24/81 XV-5 Less of Normal Feedwater 10/15/81R 12/18/81 Possible Pipe Break Inside Flow Containment XV-7 Reactor Coolant Pump Rotor 10/15/81R 12/18/81 VI-3 Containment Pressure and NONE 11/24/81 Seizure and Reactor Coolant Heat Removal Capability Pump Shaft Break VI-4 Containment Isolation NONE 10/02/8tC XV-8 Control Rod Misoperation 10/15/81R 12/18/81 (SYS) System (System Malfunction or Operator Error) VI-6 Containment Leak Testing NCNE 11/30/81 (MP A-04) XV-9 Startup or an Inactive Loop 10/15/81R 12/18/81 or Recirculation Loop at an VI-7.A.4 Core Spray No :le NfNE 11/30/81 Incorrect Temperature, and Effectiveness (NRR A-i6) Flow Controller Malfunction Causing an Increase in BWR VIII-1.A Potential Equipment NONE 02/26/82 Core Flow Rate Failures Associated with a Degraded Grid Voltage XV-11 Inadvertent loading and 10/15/81R 12/18/81 (MP B-23) Operation of a Fuel Assembly in an Improper IX-1 Fuel Storage 09/15/81 R+30 Position XI-1 Appendix I(MP A-02) NONE DELETED XV-13 Spectrum of Rod Drop 10/15/81R 12/18/81 (SYS) Accidents (BWR) X1-2 Radiological (Effluent and NONE DELETED (DOSES) 10/15/81R 12/15/81 Process) Monitoring Systems (NRR B-67) XV-14 Inadvertent Operation of 10/15/81R 12/18/81 ECCS and Chemical and XV-1 Increase in Feedwater 10/15/81R 12/18/81 Volume Control System Temperature, Increase in Malfunction that Increases Foodwater Flow, Increase Reactor Coolant Inventory in Steam Flow and Inadvertent Opening of a XV-15 Inadvertent Opening of a 10/15/81R 12/18/81 Steam Generator Relief or PWR Pressuricer Safety-Safety Valve Relief Valve or a BWR Safcty/ Relief Valvo (3-8)

DRESDEN 2 Ell (Cont.) i SAR t/* SER ?/ TOPIC HO. TITLE SCHEDULE SCHEDULE XV-18 Radiological Conscauences 10 /15 / 81 R 12/15/88 of Main Steam Lino Failure Outside Containment (EWR) XV-19 Loss of-Coolant Accidents 10/15/81R 11/17/81C (SYS) Resulting from Spectrum of (DOSES) Postulated Piping Breaks 10/15/81R 12/15/81 Within the Reactor Coolant Pressure Boundary XV-20 Radiological Consequences 04/27/81R 1 1/ 2 0 /81 L of Fuel Damaging Accidents (Inside and Outside Containment 1/ SAR : Licensee Safety Analysis Report-Scheduled or Actual (actual (status 4b) when date is followed by R) 2/ SER : Staff Safety Evaluation Report -Scheduled or Actual (Actual (status 4a, S.

7) when date is followed by C) 1/ Desiginated number of days from receipt of licensco SAR (Hote: if Licenseo SAR is received then date is from receipt c f additional information requested)

(3-9)

ll l Ill ll1 R 5 0 2 I M 5 1 2 YA f M 0 52 R f PA 0 52 RA S f M L 5 0 2 AT B T f FE I 5 M 0 2 B2 N UN f J S A SD H ) E 0 S T 5 1 E N 0 2 R O 3 ED M ( C E I DE S 5 N 0 2 E V C f NO I L 5 4 0 0 2 1 T f CO / 5 4 9 4 2 1 [ 1 P ES / 6 / 0 6 0 1 1 / G I UA 0 0 0 0 SL T f R A T I MB L 0 0 0 0 M S ~ ~ 8 5 5 5 g 4 3 2 2 1 i t l t la e a e g u g u r t r t a c a c T A T A E T L V E A H G U I R T T T A C N A T A O L M UM R U E C P l l

0YSTER CREEK 21 OYSTER CREEK 21 (Cont.) SAR 1/ SER 2/ SAR 1/ SER R/ TOPIC HO. TITLE SCHECULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE 111-1 Classification of h05E 01/15/82 III-7.D Containment Structural 09/01/81 03/01/82 (SYS) Structures, Components Integrity Tests and Systems III-2 Wind and Tornado Loading 05/07/81R 01/31/82 V-1 Compliance with Codes NONE DELETED and Structures VII-6 Frequency Decay NONE 08/29/81C (MP A-01.A-14) VI-1 Organic Materials and Post 10/30/81 R+45 IX-5 Ventilation System 12/31/81 R+30 1/ l Accident Chemistry VI-7.A-4 Core Spray Nor le NONE 05/31/82 Effectiveness (MP D-12) IX-6 Fire Protection (MP A-02) NONE 05/01/82 D.f. Dil SAR 1/ SER 2/ SAR 1/ SER 2/ TOPIC H0. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE Il-1. A Exclusion Area Authority 05/07/81R C1/31/82 II2.C Atmospheric Transport and 09/30/88 11/20/81 and Control Diffusion Characteristics II-1.B Population Distribution 05/07/81R 01/31/82 III-4.A Tornado Missles 09/30/81 R+30 II-1.C Potential Hazards Due to 05/21/81R 01/31/82 Transportation, Industrial. III-4.C Internally Generated 02/28/82 R+30 and Military Facilitici Missiles II-3.A Hydrologic Description 05/07/81R R+45 III-8.A Loose Parts and Core NONE 11/30/81 Barrel Monitoring II-3.B Flooding Potential and 05/07/81R R+45 (NRR B-60.C-12) Protection Requirements II-3.B-1 Capability to Cope with 05/07/817 R+45 Design Basis Flood VI-2.D Mass and Encroy Release for NONE 11/2 0/81C Possible Pipe Break Inside II-3.C Safety Related Water Supply 05/07/81R R+45 Containment (Ultimate Heat Sink) VI-3 Containment Pressure and h0HE 11/20/81C II-4.D Stability of Slopes 10/15/81 R+30 Heat Removal Capability II-4.F Settlement of Foundation 10/15/81 R+30 VI-4 Containment Isolation NONE 10/22/81C and Buried Equipment System III-3.A Effects of High Water 05/07/81R 02/28/82 VI-6 Containment Leak Testing NONE 06/04/81C Level on Structuren (MP A-04) III-3.C Inservice Inspection of 11/12/81R R+45 VIII-1.A Potential Equipment NONE 10/16/81C Water Control Structure railures Associated with a Degraded Grid Voltage III-4.B Turbine Missiles 09/50/81 R+30 (MP B-23) III-4.D Site Proximity Missiles 05/07/81R 01/31/82 IX-1 Fuel Storage 11/15/81 R+30 d (3-11)

OYSTER CREEK kil (Cont.) DS1 (Cont.) SAR 1/ SER R/ SAR 1/ SER 2/ TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE XI-1 Appendix I(MP A-02) NONE DELETED XV-16 Radiological Consequences 09/01/81 R+30 of Failure of Small Lines XI-2 Radiological (Effluent and NONE DELETED Carrying Primary Coolant Process Monitoring Systems) Outside Containment (NRR B-67) XV-18 Radiological Consequences 05/07/81R 07/01/81C XV-1 Decrease in Feedwater 05/07/81R 11/30/81 Temperature, Increase in Main Steam Line Failure Feedwater Flow, Increase in Outside Containment Stoam Flow, Inadvertent Opening of Steam Generator, XV-19 Loss of Coolant Accidents 05/07/81R 09/04/81C Relief or Safety Valve (SYS) Resulting From Spectrum Broans Wit 5in Reactor XV-3 Loss of External Load. 05/07/81R 07/16/81C (DOSES) Coolant Pressure Boundary 05/07/81R R+30 Turbine Trip, Loss of Condensor Vacuum, Closure XV-20 Radiological Consequences 05/07/81R R+30 o f Main Steam Isolation of Fuel Damaging Accidents Valve (BWR), Steam Pressure (In & Out of Centainment) Regulatory Failure (closed) XV-4 Loss of Non-Emergency A-C 05/07/81R 07/16/81C 1/ SAR : Licensee Safety Analysis Report-Scheduled or Actual Power to the Station (actual (status 4b) when date is followod by R) Auxiliaries 2/ SER c Staff Safety Evaluation Report -Scheduled or Actual XV-5 Loss of Normal Feedwater 05/07/81R tt/30/81C (Actual (status Ga, 5, 7) when date is followed by C) Flow }/ Desiginated number of days from receipt of licensee SAR XV-7 Reactor Coolant Pump Rotor 08/25/81R 11/13/81C (Note: if Licensee SAR is received then date is from Seizure and Reactor Coolant receipt of additional information requested) Pump Shaft Break XV-9 Startup or an Inactive Loop 05/07/81R 11/30/81 or Rocirculation Looo at Incorrect Temperaturo and Flow Controller Malfunction Causing an Increase in BUR Core Flow Rate XV-13 Spectrum of Rod Drop NONE 04/09/81C (sys) Accident 05/07/81R 07/01/81C (doses) XV-14 Inadvertent Operation of 05/07/81R 07/16/81C ECCS that Increases Reactor Coolant Inventory XV-15 Inadvertent Opening of BWR 05/07/81R 11/19/81C Safety / Relief Valve (3-12)

t tJ 3 0 1 M J L 0 3 1 Y A M 0 3 1 R PA 0 3 1 R AM S 3 L 0 1 A T F B E T ~ 3 I 1 BM J S 1 M NA UC H ) 3 T SR I 0 2 1 O 1 3 ET I ( S C EY DE O p E S 2 1 1 NE VO /. C N I 1 3 1 2 1 L CT O 0 l 3 0 1 1 PE / S 7 0 7 1 / G UA 0 1 0 1 L S U L J A TT I 0 0 0 0 M I M L ,J S t 5 8 5 B 5 9 5 8 4 3 3 2 2 1 1 t l t is a p u p u r t r t a c a c T A T A E V H I T T T N A E G R O L M U AT M R U E C P l 4 i

MILLSTONE 1 l 21 MILLSTONE 1 21 (Cont.) SAR 1/ SER 2/ SAR t/ SER 2/ l TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE III-t Classification of NONE 01/22/82 11-3.A Hydrologic Description 06/25/81R R+45 (SYS) Structures. Components and Systems (Seismic and II-3.5 F1 coding Potential & 06/26/81R R+45 Cuality) Protection Requirements III-2 Wind and Tornado Loadings NONE 12/30/81 II-3.5.1 Capability of Operating 06/25/81R R+45 Plant to Cope with Design III-5.A Effects of Pipe Break on 09/30/81 02/10/82 Basis Flooding Conditions Structures, Systems and Components Inside II-3.C Safety Related Water 04/28/81R R+45 Containment Supply (UHS) III-5.B Pipe Break Outside 08/31/81 01/20/82 II-4.8 Proximity of Capable NONE 12/30/81 Containment Tectonic Structures in Plant Vicinity III-7.8 Design Codes, Design NONE 06/30/82 Criteria, Load Combinations II-4.D Stability of Slopes 08/31/81R 01/30/82 and Reactor Cavity Design II-4.F Settlement of Foundations 04/28/81R 01/30/82 V-11.5 RHR Interlock Requirements NCHE 11/30/81 and Buried Equipment (ELEC) III-3.C Inservice Inspection of 08/31/81R R+45 VII-3 Systems Required for Safe NONE 11/30/81 Water Control Structures j (ELEC) Shutdown i III-4.3 Turbine Missiles 08/31/81R R+30 VII-6 Frequency Decay NONE 08/26/81C III-4.D Site Prximity Missiles 04/29/81R 10/29/81C IX-3 Station Service and Cooling 09/30/81 R+30 1/ (Including Aircraft) Water Systems IV-3 BWR Jet Pumps Operating NONE 06/30/82 IX-5 Ventilation Systems 09/30/81 R+30 Indications XIII-2 Safecuards Industrial NONE 06/30/82 V-1 Compliance with Codes and NONE DELETED Security (MP A-10) Standards ( to CFR 50.55a) l (MP A-01,A-14) 21 VI-t Organic Materials and Post 09/30/81R 01/30/82 SAR 1/ SER 2/ Accident Chemistry TOPIC HO. TITLE SCHEDULE SCHEDULE IX-6 Fire Protection NONE 06/30/82 Il-1.A Exclusion Araa Authority 8 04/17/81R 07/31/8IC Control Dil II-1.B Population Distribution 05/19/81R 10/29/8tC SAR 1/ SER 2/ TCPIC NO. TITLE SCHEDULE SCHEDULE II-1.C Potential Hazards or 04/29/81R 10/29/8tC Changes in Potential II-2.C Atmospneric Transport and 05/19/ SIR 09/29/8tC Hazards Due to Transporta-Diffusion Characteristics tion, Institutional, and for Accident Analysis Military Facilities III-4.A Tornado Missiles 08/31/81R 12/30/81 C3-14) l

_ = MILLSTONE 1 D11 (Cont.) Dil (Cont.) SAR 1/ SER 2/ SAR 1/ SER 2/ TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC HO. TITLE SCHEDULE SCHEDULE 111-4.C Internally Generated 09/30/81 R+30 XV-3 Loss of External Lead, 06/30/81R 09/18/81C 4 Missiles Turbine Trip, Loss of Condenser Vacuum, Closure III-8.A Loose Parts Monitoring and NONE 12/31/81 of Main Steam Isolation Core Barrel Vibration Valve (BWR), and Steam Monitoring (NRR B-60 C-12) Pressure Regulator Failure (Closed) IV-2 Reactivity Control Systems 10/28/81R R+30 Including Functional Design XV-4 Loss of Non-Emeroency A-C 06/30/81R 09/18/81C and Protection Against Power to the Station Single Failures Auxiliaries VI-2.D Mass and Energy Release for NONE 12/01/81 XV45 Loss of hormal Feedwater 06/30/81R 12/31/81 1 Possible Pipe Break Inside Flow 4 ContainmerA-XV-7 s Reactor Coolant Pdmp OC/30/81R 11/18/31C' t VI-3 Containment Pressure a.d NONE 12/01/81 Rotor Seizure and %eactor Heat Removal Capabilit/ Coolant Pump Shaft Break. Control Rod.Misopera\\' ion's t , 05/Z6/8tc t f6e30/31RI . J~ VI-4 Containment Isolation NONE 11/16/L5C XV-8 t 7 (System Malfunction orr ' J .6 i (SYS) System d 'g s d 01/3D/F2 4 I Operator Error) J n E! VI-6 Leak Testing (MP. -04) NONE 06/30/81R 1?/31/81 ( ^ \\ XV-9 Startup o7 an Inactive Loco VI-7.A.4 Core Spray Nor le - HONE 12/3t/81 or Reefreolation Losp at an \\i< s i Incorrecq Temperature, and Effectiveness (NRR A-16) e , 1 I t. Flow Contaoller Malfunction 1 l 9 'VIII-1.A PotehtiaL'Eculement NONOs 05/31/82 L, ' ' x \\ Catsino an Increase in BWR i s Core Flow Rate wy. ' g Failures Associatect With a 3 a s i Deoraded Gr,id Voltage .XV*11 ina,dvertent Loading and' 06/30/81,R 10/14/810 s R+30 i Operati o% of a Furl., 'IX-t Fuel Storage 08/31/81R l' Assembiv is an: Imr,r s pe r XI-1 'Apperdix ICMP A-02) H0EE DELETED Posttfon ( .\\) 3 2 XI-2 Radiological (Effluent 8 NONE DELETED XV-t3 Spectrum of Rod Crop Process) Monitoring Systems (SYS) Accidents,(3WR) - 06(30/81R C9/09/81C !? , i A (NRR B-67) (DOSES)' 06/30/StR} 09/21/810 ,, i i XV-1 Decrease in Feedwater 06/30/81R 12/31/81 XV-14 Idadverter,t Opdration of 36/30/81R; 09/18/84C Temperature. Increase in ECCS and Chemica14cd I s Feedwater Flow, Increase in Volume Control SystJm; g Steam Flow and Inadvertent Malfunction that Increases ' Opening of a Steam Gener-Reactor Coolant' inventory-. E / ator Relief or safety Valve s XV-15 Inadvertent Openino'of.a ' cca30/81R .10/28/81C PWR Pressuri:er Safdty ~ a t Relief Valve or a BW?< i'" Safet/ Relief Valve, t a. 4 i gs i 4 L (3-15)' jag ; 1 .s, l }) - N, i ^ I' s 4' i o s g f X l ^ 1 [ ] l r'- m-

t s t 4 > s FWill.L!ilr()lsig: 1 N ] Lil (Cons;l LEP ?/ l SAR '/l I 'iL?It M3. TITLE S CH E C'!EE ' SCHEDL[E s x.: - i e Radic1cqical Ccnsecuences ~ iC6/30/teR 09/2*'81C s of Failure of Small Lines I g Carrying Primary Coolant j + Gutside Containment l I 1 I XV '8 . Radio!ccical Consecuences -06/3E/8tR 09/21/81C6 ' s of Mair. Steam Line Failure Outside Containment (B' R) 3 W s I 17-19 Lors of ;oolant Accicents C6/30/81R 38/16/L(C (SYS) Resulting frem Socctru of (DOSESJ Postulated Piping breaks 06/30/81R 3 9/21/81 C Within the Recutor toolant Prcssuro Bcureary XV-20 Radiological Consequences 06/3C/81R 09/21/81C of Fuel Damaging Accidents (Inside and Outside Containment) 1/ SAR : Licensee Safety An/,1ysis Report-Scheduled or Actual (actual (status 4b) when dite is followed by R) 2/ SER : Staff Safety Evaluation Report -Scheduled or Actual (Actual (status 4a. S.

7) when date is follcwed by C)

J/ Dosioinated number of days from receipt ef licensee SAR (Hcte: if Licensee SAR i s received then date is from receipt of additional information requested) l l (3-16)

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SAN ON0FRE kk SAN ONOFRE SAR 1/ 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 01/31/82 111-1 Classification of ___NONE 01/29/82 'Jater Systems Structures, Components and Systems (Seismic and IX-5 Ventilation Systems 10/30/81 R+30 Quality) III-2 Wind and Tornado Loadings 10/15/81 R+60 J/ D1 l l SAR 1/ SER 2/ III-5A Effects of Pipe Break on 10/15/31 03/26/82 TOPIC NO. TITLE SCHEDULE SCHEDULE Structures. Systems and Components Inside II-1.C Potential Hazards or 11/12/ 81 R 02/28/81 Containment Changes in Potential Hazards Due to III-5.B Pipe Break Outside 10/15/81 03/05/82 Transpertatien. I Containment Institutional Industrial, and Military Facilities III-6 Seismic Design NONE 12/31/82 Considerations II-3.A Hydrologic Description NONE 02/05/82 III-7.B Design Codes, Design NONE 12/31/82 II-3.B Flooding Potential 8 NONE 02.'95/82 Criteria, Load Protection Requirements Combinations, and Reactor Cavity Design Criteria II-3.C Safety Related Water NONE 02/05/82 Supply (UHS) V-11.B RHR Interlock Requirements NONE 11/30/81 (ELEC) II-4.D Stability of Slopes 11/ 02/81R 01/31/82 VI-7.A.3 ECCS Actuation System NONE 11/18/81C II-4.F Settlement of Foundations 11/02/81R 01/31/82 and Buried Equipment VI-7.B ESF Switchover from NONE 09/04/81C (ELEC) Injection to Recirculation III-3.A Effects of High Water Level 02/28/82 R+30 Mode (Automatic ECCS on Structures Realignment) III-4.B Turbine Missiles (MP B-46) NONE 12/31/81 VI-10.A Testing o/ Peac tor Trip NONE 08/28/81C System a nrf Eng.ncored III-4.D Site Proximity Missiles 10/23/81R 12/31/81 Safety Fcan ras Including (Including Aircraft) Response Time Testing III-7.D Containment Structural 06/09/81R 02/15/82 VII-1.A Isolation of Reactor NONE 09/39/81C Integrity Tests Protection Systems, Including Qualifications V-1 Compliance with Codes and NONE DELETED of Isolation Devices Standards (10 CFR 50.55a) (MP A-01) VII-2 Engineered Safety Features NDHE 11/18/81C (ESF) System Control Logic VI-1 Organic Materials and Post 11/15/81 R*45 and Design Accident Chemistry VII-3 Systems Required for Safe NONE 11/18/81C IX-6 Fire Protection (MP B-02) NONE 10/01/82 (ELEC) Shutdown l VII-6 Frequency Decay NONE 08/28/81C (3-18) 1

l l SAN ONOFRE l Dkk Q11 (Cont.) D SAR 1/ SER 2/ SAR 1/ SER 2/ TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE III-4.A Tornado Missiles 10/15/81 R+30 XV-3 Loss of External Load. 0 7 / 01/81R 08/26/81C Turbine Trip, Loss of Con-III-4.C Internally Generated 11/15/81 R+30 densor Vaccum, Closure of Missiles Main Steam Isolation Valve (BWR), and Steam Pressure III-8.A Loose Parts Monitoring and NONE 02/26/82 Regulator Failure (Closed) Core Barrel Vihration Monitoring (HRR B-60,C-12) XV-4 Loss of Non-Emergency A-C 08/18/81R 01/15/82 Power to the Station IV-2 Reactivity Control Systems 09/30/81 R+30 Auxiliaries Including Functional Design and Protection Against XV-5 Loss of Normal Feedwater 0 7/ 01/81R 02/15/82 Single Failures Flow V-7 Reactsr Coolant Pump NONE 11/ 0 5/81C XV-6 Feedwater System Pipe 0 7/ 01/81R 02/15/82 Overspeed(NRR B-68) Breaks Inside and Outside Containment (PWR) VI-2.D Mass and Energy Release for NONE 11/13/81 Possible Pipe Break Inside XV-7 Reactor Coolant Pump Rotor 07/01/81R 01/29/82 Containment Seizure and Reactor Coolant Pump Shaft Break VI-3 Containment Pressure and NONE 11/13/81 Hoat Removal Capability XV-E Control Rod Misoperation 07/01/81R !t/19/81C (System Malfunction or VI-4 Containment Isolation NONE 01/05/82 Operator Error) (SYS) System XV-10 Chemical and Volume Control 07/01/81R 02/15/82 VI-6 Containment Leak Testing NONE 03/21/77C System Malfunction that (MP A-04) Results in a Decrease in the Boron Concentration in VIII-1.A Potential Equipment Failure NONE 03/31/82 the Reactor Coolant (PWR) Associated with a Degraded Grid Voltage (MP B-23) XV-12 Spectrum of Rod Ejection 0 7/ 01/81R 11/19/81C Accidents (PWR) IX-1 Fuel Storage 12/15/81 R+30 XV-14 Inadvertant Operation of 0 7/ 01/81R 02/19/82 XI-1 Appendix I NONE DELETED ECCS and Chemical and Volume Control System XI-2 Radiological (Effluent and NONE DELETED Malfunction that Increases Process) Monitoring Systems Reactor Coolant Inventory (NRR B-67) XV-1 Decrease in Feedwater 07/01/81R 10/27/81C XV-15 Inadvertent Opening of a 07/01/81R 02/15/82 Temperature. Increase in PWR Prossurizor Safety-Feedwater Flow, Increase Relief Valve of a BWR in Steam Flow and Safety / Relief Valve Inadvertent Openinq cf a Steam Generator Relief XV-16 Radiological Conscouences 08/04/81R. 11/18/81C or Safety Valve of Failure of Small Lines Carrying Primary Coolant XV-2 Spectrum of Steam System 07/01/81R 10/27/81C Outside containment Piping Failures Inside and Outside of Containment (PWR) (3-19)

l SAN ON0FRE R11 (Cont.) SAR l' SER 2/ TOPIC HO. TITLE SCHEDULE-SCHEDULE XV-17 System Genarator Tube NONE 11/15/81 (SYS) Failure (PWR) XV-19 Loss-of-Coolant Accidents 07/01/81R 08/26/81C Resulting From Spectrum of Postulated Piping Breaks Within the Reactor Coolant Pressure Boundary 1/ SAR: Licensee Safety Analysi s Report-Scheduled or Actual (Actual (status 4b) when date is followed by R) 2/ SER : Staff Safety Evaluation Report -Scheduled or Actual (Actual (status 4a, 5, 7) when date is followed by C) 1/ Desiginated number of days from receipt of licenseo SAR (Note: i f Licensee S AR is received then date is from receipt of additional information requested) (3-20)

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BIG ROCK POINT Di BIG ROCK POINT DE SAR 1/ SER 2/ SAR 1/ SER 2/ TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE III-1 Classification of Struct-NONE 02/19/82 Il-3.A Hydrologic Description NONE R+45 (SYS) t-ns, Components and Sys-tems (Loismic and Quality) II-3.B Flooding Potential and NONE R+45 Protection Requirements III-2 Wind and Tornado Loading 02/01/82 R+60 II-3.B.1 Capability of Operating NONE R+45 III-5.A Effects or Pipe Break on 1;/01/81 05/10/82 Plans to Cope with Designs Structures. Systems and Basis Flooding Conditions Components Inside Con ainment II-3.C Safety-Related Water Supply NONE R+45 8 (Ultimate Heat Sink UHS)) III-5.B Pipe Break Outside 12/15/81 04/16/82 Containment II-4.B Proximity of Capable NONE 01/31/82 Tectonic Structures in III-6 Seismic Design NONE 07/31/82 Plant Vicinity Considerations II-4.D Stability of Slopes 10/05/81R 02/15/82 III-7.B Design Codes, Design NONE 07/31/82 Critorion, Load II-4.F Settlement of Foundations 10/19/81R 02/15/54 Combinations and Reactor and Buried Equipment Cavity Design Criterion III-3.A Effects of High Water 03/15/82 R+30 VI-7.A.3 ECCS Actuation System NONE 12/30/81 Level on Structures VI-7.C ECCS Single Failure Cri-NONE 08/05/81C III-3.C Inservice Inspection of 12/01/81 02/15/82 terion and Requirements for Water Control Structures locking Out Power to Valves Including Independence III-4.B Turbine Missiles 12/15/81 R+30 of Interlocks on ECCS Valve III-4.D Site Proximity Missiles 11/01/81 C3/31/82 VI-7.C.2 Failure Mode Analysis ECCS NONE 08/05/81C (Including Aircraft) VI-10.A Testing of Reactor Trip 12/23/81 R+30 III-7.D Containment Structural 09/20/81 03/31/82 System and Engineered Integrity Tests Safety Features, Including Response Time Testing V-1 Compliance with Codes and NONE DELETED Standards )?0 CFR 50.55a) VII-1.A Isolation of Reactor NONE 01/31/82 (MP A-01,A-14) Protection System From Hon-Safety Systems. Including VI-1 Organic Materials and Post 10/15/81 R+45 Qualification of Isolation Accident Chomsi try Devices Accident Chomsitry VII-2 Engineered Safety Features NONE 01/31/82 IX-6 Fire Protection (MP B-02) NONE 01/04/82 (ESF) Systen Control Logic and Design I E11 VII-6 Frecuency Decay NONE 09/21/81C SAR 1/ SER 2/ IX-3 Station Service and 11/15/81 R+30 TOPIC NO. TITLE SCHEDULE SCHEDULE Cooling Water Systems II-2.C Atmospheric Transport and 09/?5/81 R+30 IX-5 Ventilation Systems 01/15/82 R+30 Diffusion Characteristics for Accident Analysis (3-22)

BIG ROCK POINT l 251 (Cont.) DS1 (Cont.) l SAR 1/ SER 2/ SAR 1/ SER 7/ TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE I30 XV-3 Loss of External Load. 07/15/81R 10/16/81C Ill-4.A Tornado Missiles 03/15/82 R Turbine Trip, Loss of III-4.C Internally Generated 03/15/82 R+30 Condenser Vacuum, Closure Missiles of Main Steam Isolation Valve (BWR), and Steam III-8.A Loose Parts Monitoring and NONE 03/31/82 Pressure Regulator Failure Core Vib-ation Monitoring (Closed) (NRR B-60.C-12) XV-4 Loss of Non-Emergency A-C 07/15/81R 10/16/81C IV-2 Reactivity Control System '10/01/81 12/15/81 Power to Use Station Including Functional Design Auxiliaries and Protection Against Single Failures XV-5 Loss of Normal Feedwater 07/15/81R 03/15/82 Flow VI-2.D Mass and Energy Release for NONE 01/22/82 Postulated Pipe Breaks XV-7 Reactor Coolant Pumps 07/15/81R 03/15/82 Inside Containment Rotor Seizure and Reactor Coolant Pump Shaft Break VI-3 Containment Pressures and NONE 01/22/82 Heat Removal Capability XV-8 Control Rod Misoperation 09/23/81R 12/18/81 (System Malfunction or VI-4 Containment Isolation Sys. HONE 01/22/82 Operator Error) VI-6 Containment Leak Testing NONE 11/30/81 XV-9 Startup of an Inactive Loop 07/15/81R 03/30/82 (MP A-04) or Recirculation Loop at an Incorrect Temperature and VI-7.B ESF Switchover from NONE 03/01/82 Flow Controller Malfunction Injection to Recirculation Causing an Increase in BWR Mode (Automatic EECS Core Flow Rate Realignment) XV-11 Inadvertent Loading and 09/28/81R 11/ 2 0/81C VIII-1.A Potential Equipnent NONE 01/29/82 Operation of a Fuel Failures Associated with Assembly in an Improper Degraded Grid Position (BWR) IX-1 Fuel Storage 08/51/81 R+30 XV-13 Spectrum of Rod Drep SYS 07/01/81R 11/20/81C Accidents DOSES 07/01/81R 10/23/31C XI-1 Appendix I(MP A-02) NONE DELETED Accidents DOSES 0 7 / 01/ 81 R 10/23/81C XI-2 Radiological (Effluent NONE DELETED XV-14 Inadvertent Operation of 06/26/81R 08/18/81C and Process) Monitoring ECCS and Chemical and Systems (NRR B-67) Volume Control System Malfunction that Increases XV-1 Decrease in Feeduater 07/15/81R 03/15/82 Reactor Coolant Inventory Temperature Incr(ase in feedwater Flow. Increaso XV-15 Inadvertent Opening of a 06/26/81R 08/18/81C in Stram Flow and PWR Pressuricer Safety Inadvertent Opening of a Relief Valve or a BWR Steam Generator Relief Safety / Relief Valve or Safety Valve (3-23)

l l BIG ROCK POINT l l Ell (Cont.) l SAR 1/ SER 2/ TOPIC NO. TITLE SCHEDULE SC:iEDUEE XV-16 Radiological Consequences 07/01/81R R+30 of Failure of Small Lines i Carrying Primary Coolant Outside Containment XV-18 Radiological Consequences 07/01/81R 11/27/81 of Main Steam Line Failure Outside Containment XV-19 Loss of Coolant Accidents 06/29/81R 08/18/81C (SYS) Resulting From Spectrum of Postulated Piping Breaks (DOSES) within the Reactor Coolant 07/01/81R R+30 Pressure Boundary XV-20 Radiological Consequences 07/03/81R 10/23/81C of Fuel Damaging Accidents (Insista and Outside Containment) 1/ SAR : Licensee Safety Analysis Report-Scheduled nr Actual (Actual (Status 4b) when date is followed by R) 2/ SER Staff Safety Evaluation Report -Scheduled or Actual (Actual (status Ga, 5, 7) when date is followed by C) 1/ Desioinated number of days from receipt of licensee SAR (Note: if Licensee SAR is received then date is from receipt of additional information requested) (3-24)

LICENSEE SUBMITTALS BIG ROCK POINT SUBMITT8.LS 48 TARGET 35 -- ACTUAL ~~ 25 - - a 20 -- ,/ 15 -- 10 -- / 5-- I f f f f f f f I f 1 JUN JtA. AUG SEP OCT NOV DEC JAN FEB MAR APR MAY JUN JUL MONTHS Target 0 0 2 4 4 5 1 1 4 0 0 0 0 PER MONTH Actual 0 0 2 2 0 Target 0 0 2 6 10 15 16 17 21 21 21 21 21 CUMULATIVE Actuai 0 0 2 4 4 1 (3-25)

/E 2 /E 2 2 2 2 2 2 2 2 ?L 8 ?L 8 8 8 8 8 8 8 8 U / U / / / / / / / / RD 0 RD 0 0 0 5 0 8 8 5 1 EE 0 3 EE 3 3 3 5 5 4 5 3 2 2 2 3 SH 3 / SH / / / 4 4 + 4 / / / / / C + 0 C 4 4 4 + + R + 4 2 2 1 1 S R 1 S 0 0 0 R R R 0 0 0 0 0 /E /E R R R R R R 1L 1 JL 1 1 1 1 1 1 1 1 1 1 U 8 U 8 8 8 8 8 3 8 8 8 8 RD / RD / / / / / / / / / 1/ AE 0 AE 7 1 0 5 5 5 5 1 2 SH 3 E SH 2 3 3 1 1 1 1 E 3 2 3 E C / H C / / / / / / / N / / / N S 0 C S 4 8 6 2 2 2 2 O 8 6 8 O 1 N 0 0 0 1 1 1 1 N 0 0 0 N y gtf l) nno ns p) s ic y l gn pS n d t. e t n as s gi o uH o opr i o ic n dt nsi SU n i oiu l r i ri o nn iet ( i t r l ul a o t rl tt s i h u oa si i ae tDi r o at e rF qi t m a d ek l s s dn t s e Ea m r) t b i ul p l e rhn t n bo e ne ae h. F s c t0 u i st di i ar ot o ai ar p um Wr t gd m t s1 A r dn nc r ii Ow at l Fi ht et ot riC WS pu o op u O.ef e s u-t re .I a c t u y dA a s at on F s nq g dt Ccy S u gc d( a s S n c i zotol e ee fen ea ut fq iu n l) y IP r D aP iay D tR ooi t e fri f oE Hr asesS n /M A H et nr o od aH ot n o t eRt o s( n nuaoa c Pn yC o l Si td fS l c-nn i d n o liDtit i o t o ee y c y ne o anyei t ry o i a rti g gi iol rt t ci t ei n ret ma a at i t i ssoul o nt ltF - a iiV i mr so uueer l ui s a todpti l i c ym mn l eu t t qf sd E i gr E u l ngrsiM o de ibts ti iot i lB cl ceaar L t eu L l u enant r ot ani et xt n b t ee usSBe T n fc T c p t azasd d oo pas fl oca a td f v rn d I e ae I x o oharnn y l r al a aU rel t en f e t of nn T v SS T E P PCHTI a H FP CPB S( PTP S Sa EL SC oi U O O 1 N N A B. 2 A B C A ) C C B. B. C D F 3 3 3 t I 5 I I 1 1 l 3 3 3 3 4 4 4 n P I P I I o O X I O 1 I I I I I I I I I I I C T I X T 1 I I I I I I I I I I I ( L i D D ) 6 2 3 C ( /E 2 2 2 2 2 2 2 2 2 1 2 ?L 8 / 8 8 8 8 8 8 8 8 8 8 U / 3 / / / / / / / / / / RD 9 4 7 0 0 1 1 1 1 8 1 EE 1 0 2 2 3 3 3 3 0 3 3 2 3 0 SH / 6 / / / / / / 3 / / / / 3 C 3 + 6 5 0 S 0 R 0 0 1 0 1 1 + 1 1 8 1 + 1 0 0 R 0 0 0 0 R 1/E R L 1 1 1 1 1 U 8 8 3 8 8 RD / / / / / AE 1 0 2 1 0 SH E 3 3 0 E E E E 3 E E E E 3 C s / / / N N N N / N N N N / S a 2 9 0 O O O C 8 C O O O 0 E 1 0 1 N N N H 0 N N N N 1 lI - n g d n o sc n n s s r g ogi ei a g km o n Nnt rg i l n aee t e p i ia uo s o s i etd ca pr i d mdl tL nt o t d rsi e ai m ouS rdug ouo a on C nd a Bys d n er e osC T el n rrl s el ie en o Sn i g Ro t loc rci of cI Fo t m d na L e I s i t s lE eent t n r an n f o p. t s di y RC ocI s cmIf yt ri a opc o iss u e nr S M n

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HADDAM NECK l E51 (Cont.) D1 (cont.) SAR 1/l SER 7/ SAR 1/ SER 2/ TOPIC NO. TITLE SCHEDULE SCHEDULE TCPIC NO. TITLE SCHEDULE SCHEDULE l III-3.C Inservice Inspections of 08/31/81R 02/28/82 VI-6 Containment Leak losting NONE 11/30/81 Water Control Structures (MP A-04) III-4.B Turbine Missiles (MP B-46) NONE 12/31/81 VI 7.B ESF Switchover from NONE 04/01/82 (SYS) Injection to Recirculation III-4.D Site Proximity Missiles CS/25/81R 04/30/82 Mode (Automatic ECCS (Including Aircraft) Roalignment) III-7.D Containment Structural 04/27/81R 10/16/81C VIII-1.A Potential Equipment NONE 03/31/82 Integrity Tosts Failures Associated with a Dograded Grid Voltaqo V-1 Compliance with Codes and NONE DELETED (MP B-23) Standards (10 CFR 50.55a) (MP A-01,A-14) IX-1 Fuel Storage 08/31/81R 11/15/81 VI-1 Organic Materials and Post 01/31/82 R+45 IX-4 Boron Addition Systems 10/02/81R 04/01/82 Accident Chemistry XI-1 Appendix I(MP A-02) NONE DELETED IX-6 Fire Protection (MP B-02) NONE 07/01/82 l l XI-2 Radiological (Effluent NONE DELETED and Process) ffonitoring I Eli Systems (NRR B-67) SAR 1/ SER ?/ TOPIC HO. TITLE SCHEDULE SCHEDULE XV-1 Decrease in Feodwater 09/30/81R 04/09/82 Temperaturos. Increase in Ill-4.A lornado Missiles 0 8/ 31/ 81 R_ 11/30/81 Feedwater Flow. Increase in Steam Flow and Inadvertent III-4.C Internaly Generatinq 09/30/81 R+30 Opening of a Steam Genera-Missiles for Relief or Safety Valve III-8.A Loose Parts Monitoring and NONE 04/30/82 XV-2 Spectrum of Steam System 09/30/81R 04/15/82 Core Barrol Vibration Piping Failures Insido and Manitorinq(NRR B-60.C-12) Outsido of Containment (SYS) (PWR) (DOSES) 09/30/81R R+30 IV-2 Reactivity Control Systems 06/30/81R 01/31/82 (PWR) (DOSES) 09/30/81R R+30 Including Functional Design and Protection Against XV-3 Loss of External Load. 09/30/81R 03/17/82 Single Failurcs Turbine Trip, Loss of Condenser vacuum, Closure V-7 Reactor Coolant Pump HUNE 11/05/81C of Main Steam Isolation Overspood(NRR B-68) Valve (BUR), and Steam Pressuro Regulator Failure VI-2.D Mass and Energy Rolcaso for NONE 01/22/82 (Closed) Possible Pipo Break Insida Containment XV-4 Loss of Non-Emergency A-C 09/30/81R 12/15/81 Power to the Station VI-3 Containment Pressure and NONE 01/22/82 Auxiliarios Heat Removal Capability XV-5 Loss of Normal Feedwater 09/30/81R 04/20/82 VI-4 Containment Isolation NONE 01/22/82 Flow System (3-27)

HADDAM NECK ESI (Cont.) Q11 (Cont.) SAR J/ SER 2/ SAR 1/ SER 2/ TOPIC NO. TITLE SCHEDULE SCHEDULE TGPIC NO. TITLE SCHEDULE SCHEDULE XV-6 Feedwater System Pipe 09/30/81R 04/20/82 XV-19 Loss of-Coolant Accidents 09/30/81R 1 1/10 / 81 C Breaks Insido and Outside Resulting from Spectrum of Containment (PWR) Postulated Piping Breaks Within the Reactor Coolant XV-7 Reactor Coolant Pump Rotor 09/30/81R 01/15/82 Prossure Boundary (SYS) Scirure and Reactor Coolant (DOSES) 09/30/81R R+30 Pump Shaft Break XV-8 Control Rod Misoperation 09/30/81R 11/15/81 1/ SAR : Licensen Safety Analysis Report-Scheduled or Actual (System Malfunction or (Actual (Status 4b) when dato is followed by R) Operator Error) 2/ SER = Staff Safety Evaluation Report -Scheduled or Actual XV-9 Startup or an Inactive 09/30/81R 04/01/82 (Actual (status 4a, 5,

7) when date is followed by C)

Loop or Recirculation loop at an Incorrect 1/ Dosiqinated number of days from receipt of licensee SAR Temperature, and Flow (Note: if Licensee SAR is received then date i s f rom Contre 11er Malfunction receipt of additional information requested) Causing an Increaso in BWR Core Flow Rate XV-10 Chemical and Volume Control 09/30/81R 04/01/82 System Malfunction that Results in a Decrease in in Boron Concentration in the Reactor Coolant (PWR) XV-12 Spectrum of Rod Ejection 09/30/81R 11/15/81 Accidents (PWR) (SYS) (DOSES) 09/30/81R R+30 XV-14 Inadvertent Operation of 09/30/81R 04/15/82 ECCS and Chemical and Volumo Control System Malfunction that Increases Reactor Coolant Inventory XV-15 Inadvertent Opening of a 09/30/81R 04/16/82 PWR Pressuri ce Safety-Relief Valve or a BWR Safety / Relief Valvo XV-16 Radiological Consequences NONE 09/28/81C of Failure of Small Lines Carrying Primar, Coolant Outside Containment XV-17 Steam Generator (SYS) 09/30/81 04/30/82 Tube Failure (PWR) (DOSES) 09/30/81 R+30 (3-28)

LICENSEE SUBMITTALS V wxa m SUBMITTALS 48 TARGET I m-- l ACillAL ~~ [ 25 -- [ 20 -- / l "-~ / IB -- / s' l 5-- / i i i i i i i r i g JUN JUL AUG SEP OCT NOV DEC JAN FEB MAR' APR MAY JUN JUL MONTHS Tarpt 0 7 18 2 0 6 1 0 0 0 0 0 0 PER MONTH { Actual 0 6 0 16 0 Tarpt 0 7 25 27 27 33 34 34 34 34 34 34 34 CUMULATIVE Actual 0 6 6 22 22 (3-29) m

YANKEE R0WE QL YANKEE ROWE DL (Cont.) SAR 1/ SER R/ SAR J/ SER 2/ TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE 111-1 Classification of Struct-NONE 04/ 16/ 2 lx-5 Ventilation Systems 09/30/81 R+30 ures, Components and Sys-tems (Seismic and Quality) Illi III-2 Wind and Tornado Loadings 01/15/82 R+60 J/ SAR 1/ SER 2/ TOPIC HO. TITLE SCHEDULE SCHEDULE III-5.A Effects of Pipe Break on 10/30/81 08/10/82 ___02/15/82 06/30/82___ Structurcs, Systems and II-1.A Lxclusion Area Authority Components Inside and Control Containment II-1.B Pipulation Distrubution 05/01/81R 06/30/82 III-5.B Pipe Break Outside 10/30/81 07/16/82 Containment II-1.C Potential Hazards or 04/09/81R 06/30/82 Changes in Potential III-6 Seismic Design NONE 07/31/82 Hazards Due to Considerations Tran:portation, Institutional Industrial, III-7.B Design Codes. Design NONE 08/31/82 and Military Facilities Criteria, Load Combinations, and Reactor II-3.C Safety-related Water NONE 02/28/82 Cavity Design Criteria Supply (Ultimate Heat Sink (UHS) V-11.B RHR Interlock Requirements NONE 02/28/82 (ELEC) II-4.B Proximity of Capable NONE 06/30/8? Tectonic Structurcs in VI-7.A.3 ECCS Actuation System 06/30/81R 02/28/82 Plant Vicinity (B-46) VI-10.A Testing of Reactor Trip 06/30/81R 02/28/82 II-4.D Stability of Slopes 02/15/82 R+30 System and Engineered Safety Features Including II-4.E Dam Integrity NONE 02/28/82 Safety Features Including Response Time Testing II-4.F Settlement of Foundations 08/ 31/81 R 02/28/82 and Buried Equipment VII-1.A Isoaltion of Reactor NONE 10/05/81C Protection System from III-3.A Effects of High Water 02/15/82 R+30 Hon-Safety Systems, level on Structures Includinq Qualifications of Isolation Devices III-3.C Inservice Inspection of 12/31/81 02/28/82 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 12/31/81 and Design III-4.D Site proximity missiles 06/30/81R 06/30/82 VII-3 Svstem Required for Safe NONE 02/28/82 (Including Aircraft) (ELEC) Shutdown III-7.D Containment Structural 02/15/82 R+30 VII-6 Frequency Decay NONE 08/28/81C Integrity Tests VIII-4 Electrical Penetrations of NONE 02/28/82 V-1 Compliance with Codes NONE DELETED Reactor Containment and Standards (10 CFR 50.55a)(MP A-01.A-14) IX-3 Station Service and Coolinq 09/17/81R 11/30/81 Water Systems (3-30)

YANKEE R0WE Q1 (Cont.) ESl (Cont.) 1 SAR 1/ SER 2/ SAR 1/ SER 2/ TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE VI-1 Organic Materials and 02/15/82 ~Ei30 IX-1 Fuel Storage 12/31/81 R+30 Post Accident chemistry IX-4 Boron Addition System 08/31/81R 05/07/82 IX-6 Fire Protection (MP B-02) NONE 01/15/82 XI-1 Appendix I(MP A-02) NONE DELETED R11 XI-2 Radiological (Effluent NONE DELETED SAR 1/ SER 2/ and Process) Monitorinq TOPIC NO. TITLC SCHEDULE SCHEDULE Systems (NRR B-67) II-2.C Atmospheric Transport and~~ 06/30/81R 09/04/81C XV-1 Deercase in Feeduater 12/31/81 06/30/82 Diffusion Characteristics Temperature. Increase in for Accident Analysis Feedaater Flow. Increase in Steam Flow and III-4.A TornaJo Missiles 01/15/82 R+30 Inadvertent Opening of a Steam Generator Relief III-4.C Internally Generated 02/15/82 R+30 or Safety Valve Missiles XV-2 Spectrum of Steam System 06/30/81R 05/21/82 III-8.A Loose Parts Monitoring ' HONE 06/30/82 (SYS) Piping Failures Inside and Core Barrel Vibration (DOSES) and Outside of Containment 09/30/81 R+30 Monitoring (NRR B-60,C-12) (PWR) IV-2 Reactivity Control Systems 09/17/81R 02/15/82 XV-3 Loss of External load. 06/30/81R 01/08/82 Including Functional Design Turbine Trip, Loss of and Protection Aqainst Condenser Vacuum, Closure Single Failures of Main Steam Isolation Valve (BWR), and Steam V-7 Reactor Coolant Pump NONE 11/05/81C Pressure Regulator Failure Overspeed(NRR B-68) (Closed) VI-2.D Mass and Energy Release NONE 01/22/82 XV-4 Loss of Non-Emergency A-C 12/31/81 06/01/82 for Possible Pipe Break Power to the Station Inside Containment Auxiliaries VI-3 Containment Pressure and NONE 01/22/82 XV-5 Loss of Normal Feedwater 06/30/81R 02/05/82 Heat Removal Capability Flow VI-4 Containment Isolation NONE 04/01/82 XV-6 Feedwater System Pipe 12/31/81 06/16/82 (SYS) System Breaks Inside and Outside Containment (PWR) VI-6 Containment Leak Testing NONE 03/30/82 (MP A-04) XV-7 Reactor Coolant Pump Rotor 06/30/81R 12/31/81 Seizure and Reactor Coolant VI-7.B ESF Switchover from NONE 06/11/82 Pump Shaft Break (SYS) Injection to Recirculation Mode (Automatic ECCS XV-8 Control Rod Misoperation 12/31/81 R1 Realignment) (System Malfunction or Operator Errer) VIII-1.A Potential Equipment NONE 03/31/82 t Failures Associated with a Degraded Grid Voltage (MP B-23) (3-31)

YANKEE R0WE pil (Cont.) SAR 1/ SER 2/ TOPIC NO. TITLE SCHEDULE SCHEDULE XV-9 Startup or an Inactive 06/30/81R 06/15/82 Loop or Recirculation Loop at an Incorrect Temperature, and Flow Controller Malfunction Causing an Increase in BWR Core Flow Rate XV-10 Chemical and Volume Control 06/30/81R 03/01/82 Systcn Malfunction that Results in a Decrease in the Boron Concentration in the Reactor Coolant (PWR) XV-12 Spectrum of Rod Ejection 06/30/81R R+30 (SYS) Accidents (PWR) (DOSES) OS/30/81R 11/15/81 XV-14 Inadvertent Operation of 06/30/81R 06/30/82 ECCS and Chemical and Volume Control System Malfunction that Increases Reactor Coolant Inventory XV-15 Inadvertent Opening of a 06/30/81R 04/23/82 PWR Pressurizer Safety-Related Valve or a BWR Savety/ Relief Valve XV-16 Radiological Consequences 12/31/81 R+30 of Failure of Small Lines Carrying Primary Coolant Outside Containment XV-17 Steam Generator Tube 12/31/81 06/30/82 (SYS) Failure (PWR) (DOSES) 12/31/81 R+30 XV-19 Loss-of-Coolant Accidents 09/30/81 06/30/82 (SYS) Resulting from Spectrum of (DOSES' Postulated Pipina Breaks 09/30/81 R+3C '?i thin the Reactor Coolant Pressure Boundary 1/ SAR : Licensee Safety Analysis Report-Scheduled or Actual (Actual (Status 4b) when date is followed by R) 2/ SER : Staff Safety Evaluation Report -Scheduled or Actual (Actual (status 4a. S.

7) when date is followed by C) 1/ Desiginated number of days from receipt of licensee SAR (Note:

i f Licensee SAR is received then date is from receipt of additional information requested) (3-32)

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LACROSSE Di LACROSSE D1 SAR 1/ SER R/ SAR 1/ SER 2/ TOPIC NO. TITLE SCHEDULE SCHEDULE TOPIC NO. TITLE SCHEDULE SCHEDULE 111-1 Classification of NONE 05/14/82 II-1.A Execlusion Area Authority 06/22/81R 07/31/82 (SYS) Structures, Components and and Control Systems (Scismic and Quality) II-1.B Population Distribution 06/16/81R 07/31/82 III-2 Wind and Tornado Loadings 08/06/81R 02/28/82 II-1.C Potential Hazards or 07/15/81R 07/31/82 Changes in Potential III-5.A Effects of Pipe Break on 11/02/81 09/30/82 Harards Due to Structures, Systems and Transportation, Components Insido Institutional Industrial. Containment and Military Facilities III-5.B Pipe Break Outsido 06/29/81R 08/27/82 II-3.A Hydrolic Description 06/16/81R R+'O Containment II-3.B Finoding Potential and 09/01/81 R+45 III-6 Seismic Design NONE 11/30/82 Protection Requirements Considerations II-3.B.1 Capability of Operating 09/01/81 R+45 III-7.B Design Codes. Design NONE 11/30/82 Plant to Cope with Design Critoria. Load Basis Flooding Conditions Combinations, and Reactor Cavity Design Critoria II-3.C Safety-related Water Supply 06/26/81R R+45 (Ultinato Heat Sink (UHS)) V-11.B RHR Interlock Requirements NONE R+30 (ELEC) II-4.B Proximity of Capable NONE 07/31/82 Tectonic Structures in VI-7.A.3 ECCS Actuation System NONE 11/30/81 Plant Vicinity VI-10.A Testing of Reactor Trip 06/25/81R 02/28/82 II-4.D Stability of Slopes NONE R+30 System and Engineered Safety Features Including II-4.E Dam Integrity NONE R+30 Responso Time Testing II-4.F Settlement of Foundations 12/31/81 02/28/82 VII-1.A Isolation of Reactor NONE 11/30/81 and Buried Equipment Protection System from Non-Safety Systems, III-3.A Effects of High Water Level 12/31/81 R+30 Including Qualifications of on Structures Isolation Devicos III-3.C Inservice Inspection of 12/31/81 R+45 VII-2 Engineored Safety Features NONE 11/30/81 Water Control Structures (ESF) System Control Logic and Design III-4.B Turbine Missiles 09e01/81 R+30 VII-3 Systems Required for Safo NONE 01/31/82 III-4.D Site Proximity Missiles 09/15/81R 07/31/82 (ELEC) Shutdown (Including Aircrafts) VII-6 Frequoney Decay NONE 09/21/81C III-7.D Containment Structural 06/29/81R 02/01/82 Integrity Tests IX-3 Station Service and Cooling 11/02/31 R+30 Water Systems V-1 Compliance with Codes and NONE DELETED Standards (10 CFR 50.55a) IX-5 Ventilation Systems 11/02/81 R+30 (MP A-01, A-14 ) (3-34)

- _ _ - - - - - _ _ _ ~ ~. LACROSSE El (Cont.) Ell (Cont.) SAR 1/ SER 2/ SAR 1/ SER 2/ TOPIC HO. TITLE SCHEDULE . SCHEDU6E TOPIC NO. TITLE SCHEDULE SCHEDULE VI-1 Organic Materials and Post 12/31/88 R+30 XI-2 Radiological (Effluent and NONE DELETED Accident Chemistry Process) Monitoring Systems (NRR B-67) IX-6 Fire Protection (MP B-02) NONE 10/30/82 j XV-1 Decrease in Feodwater 08/21/81 07/31/82 i Temperature. Increase in D11 Feedwater Flow, Increase i SAR 1/ SER 2/ in Steam Generator Relief l TOPIC NO. TITLE SCHEDULE SCHEDULE or Safety Valve II-2.C Atmospheric Transport and 10/01/31 R+30 XV-3 Loss of External Load, 06/26/81R 11/13/81C Diffusion Characteristics Turbine Trip, Loss of Con-l for Accident Analysis denser Vacuum, Closure of Main Steam Isolation Valve III-4.A Tornado Missiles 11/02/81 R+30 (BWR), and Stam pressure Regulator. Failure (Closed) III-4.C Internally Generated 11/02/81 R+30 Missiles XV-4 Loss of Non-Emergency A-C 06/26/8tR 10/21/81C .III-8.A Loose Parts Moniroring and NONE 07/30/82 Power to the Station Core Barrel Vibration Auxiliaries i i Monitorinq(NRR B-60 C-12) 1 XV-5 Loss of Normal Feedwater 08/21/81 07/31/82 i IV-2 Reactivity Control Systems 11/02/81 02/28/82 Flow Including Functional Design and Protection Against XV-7 Reactor Coolant Pump Rotor 08/21/81 07/31/82 Single Failures Seizure and Reactor Coolant i Pump Shaft Break VI-2.D Mass and Energy Release for NONE 01/22/82 4 Possible Pipe Break Inside XV-8 Control Rod Misoperation 08/21/81 R+30 Containments (System Malfunction or ) Operation Error) VI-3 Containment Pressure and NONE 01/22/82 Heat Removal Capability XV-9 Startup or an Inactive Loop 08/25/81R 07/31/82 or Recirculation Loop at an + VI-4 Containment Isolation NONE 05/03/81 Incorrect Temperature, and (SYS) System Flow Controller Malfunction Oausing an Increase in BWR VI-6 Containment Leak Testing NONE 11/30/81 Core Flow Rate (MP A-04) XV-11 Inadvertment Leading and 12/31/81 R+30 VIII-1.A A. Potential Equipment NONE 03/31/81 Operation of a Fuel s Failures Associated with a Assembly in an Improper j Degraded Grid Voltage Position i (MP B-23) XV-13 Spectrum of Rod Drop 12/31/81 R+30 IX-1 Fuel Storage 11/02/81 R+30 (SYS) Accidents (BWR) (DOSES) 12/31/81 R+30 XI-1 Appendix I(MP A-02) NONE DELETED t (3-35) i 4 8

LACROSSE Dil (Cont.) SAR l/ SER 2/ TOPIC HO. 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 08/21/81 R+30 of' Failure of S.nall Lines Carrying Primary Coolant Outside Containment XV-18 Radiological Consequences 11/02/31 R+30 l of Main Steam Lino Failure Outside Containment (BWR) XV-19 Loss-of-Coolant Accidents 08/21/81 07/31/82 (SYS) Resulting frcm Spectrum of (DOSES) Postulated Piping Break s 08/21/81 R+30 Within the Reactor Coolant Pressure Boundary XV-20 Radiological Consequences 11/02/81 R+30 of Fuel Damaging Accidents (Inside and Outside Containment) l/ SAR : Licensoe Safety Analysis Report-Scheduled or Actual (Actual (Status 4b) when dato is followed by R) 2/ SER : Staff Safety Evaluation Report -Scheduled or Actual (Actual (status 4a. S.

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)

(3-36)

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[jC e m 335 " ' " ' ^ " ' u.c. NucLEA3 REOuLATORY COMMISSION BIBLIOGRAPHIC DATA SHEET NUREG-0485 Vol. 3 No. 13 i TITLE AND SUBTITLE (Add Vo4eme No.,,(appropresset

2. (Leave alm &1 Systematic Evaluation Program Status Summary Report

3. REclPIENT'S ACCESSION NO.

7. AUTHOR (Si

5. DATE REPORT COMPLETED December 1981

9. PERFORMING ORGANIZATION NAME AND MAILING ADDRESS (include Zep Codel DATE REPORT ISSUED Office of Management and Program Analysis

N 7a l YEAR December 1981 Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 8 (L'* * *'*a">

Washington, D.C. 20555

8. (Leave bimk1

12. SPONSORING ORGANIZATION NAME AND MAILING ADDRESS finclude Is Codel

10. PROJECT / TASK / WORK UNIT NO Office of Management and Program Analysis Office of Nuclear Reactor Regulation ti. CONT RACT NO.

U.S. Nuclear Regulatory Commission Washington, D.C. 20555 i i

13. TYPE OF REPORT PE RIOD COV E RE D (inclusere dams /

November 1 - 30, 1981

13. SUPPLEMENTARY NOTES 14 (Leave D/r*/

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.

17. KE Y WORDS AND DOCUME NT AN ALYSIS 17a DESCRIPTORS l

l l 17b IDENTIFIE RS/OPEN ENDED TERMS

18. AVAILABILITY ST ATEMENT 19 SECUR TY AS (Th,s recorrt 21 NO OF P AGES Unlimited 20 SE CURITY CLASS (TA,s papf 22 PRICE Unclassified s

NRC FORM 335 (7 771

UNITED STATES NUCLE AR REGULAfonY COMMISSION F WASHINGTON, D. C. 20555 ,3,7,,,,,, ,,,,,,,o OFFICI AL BUSINESS PEN ALTY FOR PRIV ATE USE, $3OO M L ""'"'" J i le s ; s ), .. 3 x ~, n -. 3 <, s in } l JL < c S.; 9 i l l 1}}

ML20039E492

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ML20039E492

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