ML20003F248

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Systematic Evaluation Program Status Summary Report.Data as of March 1,1981.(Buff Book)
ML20003F248
Person / Time
Issue date: 03/31/1981
From:
NRC OFFICE OF MANAGEMENT AND PROGRAM ANALYSIS (MPA), Office of Nuclear Reactor Regulation
To:
References
NUREG-0485, NUREG-0485-V03-N04, NUREG-485, NUREG-485-V3-N4, NUDOCS 8104200466
Download: ML20003F248 (56)
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NUREG-0485 i

Vol. 3, No. 4 j

March 1,1981 1

l SYSTEMATIC EVALUATION PROGRAM STATUS

SUMMARY

REPORT l

UNITED STATES NUCLEAR REGULATORY COMMISSION ga arc,,

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,o William T. Russell, Chief Dennis M. Crutchfield, Chief ks Systematic Evaluation Program Branch Operating Reactors Branch 5 u fe Off ce of u ear Reactor Regulation ffice f R

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u s. NucLEra REcutAfoRy couwessioN BIBLIOGRAPHIC DATA SHEET fiUREG-0485 Vol. 3 fio. 4 4 itTLE ANO SU8 TITLE LAdd Vok,me IVe, of m,rme,aopp g

g,,,, ggy g 9 Systematic Evaluation Program Status Sumary Report a REciP'ENT S AccEssicw No.

7.AUTHORG' 5 DATE REPORT COMPLETED lvtam w oN T *e Ma rch 1981

9. PERFORWING OnGANf 2A180N N AVE AND V AILING ADORESS (lace or Ia Coael v

D ATE REPORT ISSUED Office of Management and Program Analysis vo% T e.

lvtAn March 1481 Office of fduclear Reactor Regulation s ae. e a.eas U.S. fLclear Regulatory Comission Washington, D.C.

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I February 2, 1481 thru March 1, 1981 IS SUTPLEVENTARY NOTES 14 (L e ne * * * /

16 AUSTR ACT C00 =oros'or lessf The Systematic Evaluation Program is intended to examine raany safety related aspects of eleven of the older light water reactors. This docurent provides the existing status of the review process ir:cluding individual topic and overall ccepletion status.

17 KE Y WORDs AND DOCUVE NT AN ALYS'S 17e DESCRIPtoRS l

--1 17b 'CENTIF 4E ns orEN ENDE D TE RYS l

18 AV AIL A8 f LITY $7 ATE VE NT 19 SE CUAtiv CLASS (Tos eportl 21 NO 08 P AGES Unclassified Unlinited 2q.Se cu aiT v cL ASS tra..,,,,i 22 eaicE unclassified s

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l TABLE OF CONTENTS l

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SECTIONI SECTION 11 i

i BIG ROCK POINT 2-2 to 2-5

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SEP TOPIC LIST 12 to 1-3 DRESDEN 1 2-6 to 2-9 DRESDEN 2 2-10 to 2-13 DESIGN BASIS EVENT GROUP DESCRIPTION 14 GINNA 2-14 to 2-17 HADDAM NECK 2-18 to 2-21 DEFINITIONS OF STATUS 1-5 LACROSSE 2-22 to 2-25 MILLSTONE 1 2-26 to 2-29 SEP TOPIC

SUMMARY

STATUS REPORT 1-6 OYSTER CREEK 2-30 to 2-33 PALISADES 2-34 to 2-37 l

INTEGRATED ASSESSMENT SCHEDULE 1-7 SAN ONOFRE 2-38 to 2-41

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YANKEE ROWE 2-42 to 2-45 i

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P90R ORIGINAL SYSTEMATIC EVALUATION PROGRAM TOFIC LIST e

  • d TOPIC #

Tg TOPIC f Tlftf Topit #

TI Ti t IV-2 iteactietty Control System including Functional 11-1 A. E sclusion Area Authority and Control gig.4 A. Tornado Missiles Desty and Protection Against Single Failures B. Population Distrtbut ton V-3 BWR Jet Pumps Operating Indications C. Potential Hazards or Changes In Potenttal

8. Iurbine Missiles Val Conpliance with Codes and 5tandards (10 CFR Hazards Due to Transportation, ins t it ut ional ladustrial, and Military Factitties 111-4 C. Internally Generated Misstles
  • 'I Il-2 A. Severe Weather Phenomena V-2 Appilcable Code Cases
8. Destte Meteorological Measurenents Program V-3 Overpressurtsation Protection C. Atsu> spheric Transport and Dit f usion Charac-V-4 Ptptng and Safe End Integrtty teristics f or Accident Analysts D. Site Frontetty Misstles (including Atrcraf t) p q

I D.

Availability of Meteorological Data to the

!!!.S A. Ef fects of Pipe Break on Structures, 53 stem Le*kage, Detection Control Room and Congonents inside Contatnment V

InteW

!!.3 A. Hydrologic Description

8. Pipe Break Outstde Containment M

P OwM 111-6 Setssic Desty Considerations P. Flooding Potential and Protectton Require.

V-8 Steam Generator (5f.) Integrity ment s I*9 Reactor Core Isolation Cooling System (BWR) 111-7 A. Inservice Inspection, including Prestressed 1.

Capability or Operating Plant to Cope Concrete Contatnnents with Either Grouted 0

A. RHR Heat DChanger Iuk laHums udh Cesign 8asts Ilooding Condit tens or Ung outed Tendons C. Saf ety-related Water supply (Ultimate Heat

8. Design Codes. Design Crtterta. Load
8. RHR Reliability Sink (UH5))

Con 6tnettons, and Reactor Cavity Dest @

y,

g Crtterta l

!!-4 Geology and Seismology Pressure Systems C. Delamination of Prestressed Concrete Con-i A. Tectonic Province tatnannt Structures

6. RHR Interlock Requtmarnts i
8. Prostetty of Capable Tectonic Structures D. Containment 5tructural Integrity Tests V-12 A. Water Purity of Bot ting Water Reactor in Plant Victatty Primary Coolant Ill-8 A. Loose Parts Monitoring and Core Barrel V-13 Water Hanser C. Historical Setsattity within 200 Miles of Vibration Monitorisig 1

Plant

8. Control Rod Drive Mechanism Integrity
  1. 1-1 Organic Materials and Post Accident C heat stry

]

D. 5tability of Slopes C. Irradiation Damage. Use of Sensitized Stainless Steel and f attgue Resistance II-2 A. Pressure-Suppression Type BWR Containments E. Das Integrity 8 Subcoapartment Analysts D. Core Supports and Fuel Integrity j

F. Settlement of f oundations and Burled C. Ice Condenser Contatnment Lquipae nt lit *9 Support Integrity D. Mass and Energy Release for Possible Pipe i

f 111-10 A. Thermal-Overload Protection for Motors of Break Inside Contatnment 118-1 Classification of Structures, Cogonents and Motor-operated Valves 5ystem (5ensmic and Quality)

8. Pung Flywheel Integrity VI-3 Containment Pressure and Heat Removal Wind and Tornado loadings Capabillty j

61.

A. [f fects of High Water Level on Structures tion PUTS and Discharge Valves VI-4 Containment Isolation System Ill-11 Copponent Integrity VI-5 Cowbustible Gas Control

8. Structural and Other Consequences (e.g.

4 f looding of Safety-Related (quipment in V I-6 Containment Leak Testing Sasenrnts) of f ailure of Underdrain System 111-12 Environmental Qualtf tcation of Saf ety Related Leutpment j

C. Inservtce Inspect ton of Water Control Struc-IV.1 A. Operatton with less Than All Loops in-$ervice tures 1-2

SYSTEMATIC EVALUATION PROGRAM TOPlc LIST top l( g

_1] Tg g TOPIC f ilft[

TOP!C f TITtt VI-1.A

1. (CCS Re-e valuation t o Account f or increated Vll.5 Instruments f or Monttoring Radiation and Process IV-5 Los. of normal Feeanater f low Wessel Head f eterature variables During Acctdents IV-6 Fee 6ater System Ptpe Breaks instde and Outside
2. Upper Plenum inject son y l l.t, f requency Decay Contatnnent (Pd)
3. (CC5 Actuet ton System VII-?

Acceptability of Swing Bus Design on 82-4 av-F Peactor Coolant Pug Rotor Setaure and Pla nts Reactor Coolant Pump Shaf t Breat

4. Core Spray hortle t f f ectiveness Vill-1 A. Potential Equiparnt Failures Associated with IV-8 Control Rod Mtsoperetton (System Malfunction V I-1.0 E 5f Swit chover f rom Inject son to Rect rculat ton a Degraded Grid Voltage or Operator Error) mode (Automet tc ICC5 Realt gn=ent)

Vlli-2 Onstte E mergency Power Systems - Diesel g y.9 Startup or an inactive Loop or Rectreulation V I-7.C ICC5 Single f atlure Criterton and Require.

Generator toop at an incorrect Tegerature, and Flow ments f or lock Ing Out Power to Valves Controller Malfunction Causing an Increase in lacluding Independence of Int erlock s on vill-3 A. Station Battery Capacity fest Requirements Be Core Flow Rate IV-10 Chemical and Volume Control System Malfunrtton

8. DC Power System Bus Voltage Monitoring and
1. Appendia E - E lectrical Instrumentation Annunc t at ion that Results in a Decrease in the Soron Concen-and Control (LIC) Re-reviews trMion in ne Ructor CoolM (P2)

Vill-4 Electrical Penetrations of Reactor Containment XV-11 Inadvertent Loadtag and Operation of a Fuel

2. Failure Mode Analys 6s - ICCS gg,j Assenely in an laproper Posttton
3. The If f ect of Pd ioop Isolat ton Valve XV-12 Spectrum of Rod EJectton Accidents (P2)

Closure During a LIK A on (LC5 Performance i

i 11-2 overhead Handling Systems - Cranes V I-7.D Lvng Tenn Cooling - Passive f atlures (e.g..

IV-13 Spectrum of Rod Drop Accidents (62)

Ilooding of Beaundant Cowonents) 11-3 Stat ten Service and Cooling Water Systems RV-14 Inadvertent Operetton of ECC5 and Chemical V !- 7.C ICC5 Su, Destgn and Test for Rectrculation in-4 Baron Addition System Mode E f f ectiveness and Volume Control System Malfunction that II-5 Ventilation Systems increases Reactor Coolant Inventory V I-1.F AC la solation Valves Power and Control XV-15 Inadvertent Opentag of a Psst Pressertzer safety-1-6 Fire Protect ton Reitef valve or a 84 Safety /Rettef valve VI 8 Control Room Habitability X

Auntilary f ee& vater System IV 6 RadiologtCaI Consequences of Fatlure of Small VI 9 Main Steam Line Isolation Seal system - Bd 11 1 Appendia i Ines am g man an OutsW Mam-ment V !- 10 A. Testing of Reactor irty System and Engineered a l-2 Radiological (Effluent and Process) Monttoring gy y ?

5 team Generator Safety f eatures Including Response Isme S yst ems les ting Tube Failure (PA)

Xill-1 Conduct of Operattons IV-18 Radtelogtcal Consequences of Main Steam

8. Shared [ngineered Saf ety f eatures, On-site Line Failure Outside Contatnnent (Be)

(mergency Power, and Service Systems for till-2 Saf eguards/ Industrial Security Mult spie Unit I acillttes IV-19 Loss-of-Coolant Accidents Resulting f rom IV-1 Vil-1 A. Isolat ton of Reactor Protect ton System f ro*

Decrease in Feecheater Tegerature. lacrease in Spectrum of Postulated Ptptng Breaks Wtthin S eedvater F low. Increase in Steam Flow and the Reactor Coolant Pressure Boundary Non-Saf ety Systems, including Qualif tcations inadvertent Opening of a Steam Generator Reltef of isolation Devices or Saf ety valve IV-20 Radtological Consequences of Tuel Damaging Accidents (Inside and Outside Containment)

8. Trig Uncertainty and Setpoint Anelysts Review X V.2 Spectrum of Steam System Piping Fallures Inside of Operating Data Base and Outside of Contatnnent (Peat)

IV-21 Spent Fuel Cask Drop Accidents VII.2 Engineered Saf ety f eatures (L5F ) System Control IV.3 Loss of E sternal Load, Turbine Trip, loss of Logic and Design Condenser Vacuum, Closure of Main Steam Isola-VII-3 Systems Required f or Saf e shutdown t ton Valve (BA), and Steam Pressure Regalator XV-23 Multtple Tube Failures in Steam Generators f ailure (Closed)

IV-24 Loss of All A-C Power Vll-4 t f fects of I at ture in Non-Saf ety Related

-f mergency A-C Power to the 5tation IVI Technical specifications Systems on Selected Engineered Safety Features XVII Operattonal QA Program A

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POS OMAL 1

DESIGN BASIS EVENT REVIEWS 1

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THIS SECTION DEFINES DESIGN BASIS EVENT (DBE) REVIEWS FOR THE ELEVEN SEP FACILITIES l

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TITLE C E. _E T O_P IC T_I TL E Gro4 1 Ib1 Decrease in f ees ater tercerature 4 0005 i

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(,ec rene in feed ater tepera tsre

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I V-1 Increase in feedmater flow F uym 1]-3 A Hydrologic description P-1.

Iv-l increase ta feed.ater f l on.

h-l increase in steam flom

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11-3.8 flooding potential and protection j

h-1 Increase in ster flo.

RV-9 Start up cf inactive loop and flow requirements (capabiltty of operettag a.1 Inadvertent opening of steam controller malfu ction plant to cope witn destgn basts flood ng n

i; generator relie*/ safety valve an 3 Inad,ertent closu e of main steam condi tion) r s -9 5 tert up of teactive loop tsolation valve

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$4'ety related water supply (ultimate I'

Systee malfu c tion cassing heat sink) 3.-17 n

Grog ~! !

Ib3 Loss of enternal load Tu cine trip h-3 Lou of concenser vaCue

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A*-3 Loss of enternal load h-3 Tu t ine trip M 15P:

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!!-4,5 Pronteity of capable tectonic strictures s v-3 34-3 Lou of condenser vaue.

R.-3 Steam preusre regulator f ailure rear plant r

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h3 Steet preuure regalator failu e R d-b Lou of feedwater flow

!l-4.C hntort(41 sef sattity within 200 miles r

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Lou of feedmater flow of plant j

A b -6 Feedmater syster pipe tresh Groq _!]I A t - 18 Radiological Consequences of a

!!-4.0 5tattlity of slopes i

Patn Steer Line Failure Outs sde Gr oq_ j_lj Id-2 5 ter line break teside cortateirent Contaiwat MIS $:.E GENERA!!04 !!!-4. A Tornado missiles I n-2 5 team lird breat outside containnent AND PROTICTION' ~ - ~ ~ 111-4.8 Turbine missiles Group h I s% 4 Lou of AC power to station

))]-4.C Internally generated missiles Grhi J 3*-4 Lou 08 A" po er to station aaniliaries

] ] !.4. 0 5tte pros teity sissiles (including l

a n t ii er ies AV-24 Loss of alt AC power aircraf t) l A s-24 Loss o# all AC power Prir.ary pu p rotor seizure" w!y}s

!!!-2 istad and tornado loading Loss of forced coolant flo j

Group V E s-7 j

Groy[ W 34-7 tess cf forced coolant flom Bi-7 m

4 IW-7 Prirery pu g roter seiture 47 Primary pu c shaf t brean a

m j

a v-7 Primary pep snaf t break Gro.sG Ib8 Uncontrolled rod asse41y withdramal irN

  • IbE Laccet elled rod assertly witn-at power drawal at power 3.4 Uncontrolled rcd esserely withdrawai i

h-8 Uncot: trolled rod auerely o ttn-low power start-up

.l drawal low ;ower start-wa Ie-B Coctrol rod etsoperation 76 8 Control rod eisoperettan N W-13 Spectre of rod drop acC tdeets Is 12 SDec tr# of rod ejec tion accidents Gfo4_ W_[!

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$pe-tr# of lou of coolant acC1 dents Groudj.1 s h -?1 Drop of cash or heavy equipreat Grog ylI!

I g. 21 Drop of cask or nesvy equipneat I v-N Radiological Consequences of Fuel I

3*-23 Radiolo11 Cal Consepences of f uel Lamaling Accidents (inside and DePagtng Accidents (Inside and Outside contrinrwat) outside contatwet)

Groq_~! i a d-li Inadverteet opening of SmR safe ty/

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relief valve GrM_!_8 8 15 Inad.ertent opening of Na prenurizer relief valve I

(arouL,R 1s-14 Inadvertent operation of [CC5 Gr.M_E R u-14 Inadvertent operattom of [CCS or i

i tvCs malfunction tnat canes an Gro 4_.n_I ss-11 Inadvertent loading and operation of j

increase In coolart inventory a fuel sueFely in an improper i

position i

Grpfli kut applicable to PwEs i

Grap III hat applicatle to 66.as l

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3,-17 Stege (,energgor Tube f ailu e

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STATUS DEFINITIONS i

G - Generic 3 - Question Flesponse Received by NRC These topics are being evaluated as part of on-going NRC generic review effort. Some of the The licensee has formally responded to the informa-generic topics will be resolved and implemented tion request issued by NRC regarding the topic.

indepindently of SE P activities, i.e., Unresolved Safety issues (N UR EG-0649), TMl Action Plan issues (N U R E G.0660). However, for the plants 4 - Draf t SE Received which are part of the SEP effort, the ongoing From Review Branch generic review and the SEP topic review will be closely integrated to improve the effectiveness This status is used for internal NRC tracking of and efficiency of these efforts and to minimize topic review progress. The status indicates that any impact on licensees. The status and conclu-a draft topic safety evaluation is under mange-sions of generic SEP tnpics will be incorporated ment review.

in the final sahty assessment for each plant.

5 - Draf t SE Sent to X - Deleted Utility These topics have been verified as not applicable A draft topic safety evaluation has been formally j

to the design of a specific plant.

transmitted to the licensee for their review and a

certification of the accuracy of the described facility. Licensees may comment upon N RC j

0 - Topic Not Started conclusions or propose alternatives to NRC posi-tions.

This status indicates that the review of the topic has not started.

l 6 - SE Response Received by NRC 1 - Questions Received 1

From Review S.anch The draft SE has been reviewed and licensee I

comments if any have been formally transmitted This status is used for internal NRC tracking to the N RC.

of topic teview progress. The status indicates that all information necessary to perform a l

topic evaluation is not available and that ques-7 - Topic Complete tions have been developed and sent to the SEP branch.

The NRC topic evaluation has been completed and a final safety evaluation issued. A topic is completed in several ways: (1) The licensee has responded 2 - Questions Sent to that the N RC draft safety evaluation (i.e. status 5)

Utility is torrect, or (2) the licensees comments on the NRC dra't safety evaluation (i.e. status 6) have been re-The questions developed in the previous status viewed and if appropriate incorporated into the have been formally transmitted to the licensea final safety evaluation, or (3) the licensee has not as a request for additional information.

responded in the time requested, thus concurring that the draft safety evaluation is correct.

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l INTEGRATED ASSESSMENT SCHEDULE j

mmMNNMM Topic Overall _f 3

Draft IA Draft

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Completion Status Plant Name 60% Topic 80% Topic Internal SER Remar ks As Of 03/01/81 Completion Completion Distribution 1/

Issue l

l 77 PALISADES 3/31/81 6/30/81 8/31/81 10/31/81 54 GINNA 6/30/81 7/31/81 9/30/81 11/30/81 This schedule reflects the 43 DRESDEN 2 6/30/81 8/31/81 10/31/81 12/31/82 direction of the program 38 OYSTER CREEK 6/30/81 9/30/81 11/30/81 1/31/82 which was provided in a 37 MILLSTONE 6/30/81 10/31/81 12/31/81 2/28/82 letter dated January 14, 43 SAN ONOFRE 6/30/81 12/31/81 2/28/82 4/30/82 to all SEP licensees.

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39 BIG ROCK POINT 6/30/81 1/31/82 3/31/82 5/31/82 35 HADDAM NECK 6/30/81 2/28/82 4/30/82 6/30/82 37 YANKEE ROWE 6/30/81 4/30/82 6/30/82 8/31/82 33 LACROSSE 6/30/81 5/31/82 7/31/82 9/30/82 35 DRESDEN 1 2/

Deferred Deferred Deferred Deferred MM l

.l./ Includes completion of all topics and the draft integrated assessment.

l 3/ The licensee has proposed deferring SEP review of Dresden 1. The facility is currently shutdown and will not restart until 1986.

Status Weighting Factor l' The plant topic overall completion status (percent complete)is calculated based upon the number of topic reviews to be performed (not including G, X Not included generic or deleted topics) and a weighted average of current topic review 0

0%

status. The calculation is performed using the following formula:

l 1,2 3 35%

l 4

80 %

Sum of Topics in Status X Weighting Factor of Status 5, 6 90%

(Percent Complete) =

7 100%

Sum of Topics 1-7 j

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BIG ROCK POINT i

FACILITY INFORMATION OP O.

S R N RKS FACILITY: BIG ROCK POINT 1 H-1 A.

7 CPCo to NRC 09/02/80 LICENSEE: CONSUMERS POWER 11 1 B.

7 CPCo to NRC 09/02/80 REGION / LOCATION: 4 MILES NORTH EAST OF CHARLEVOIS, MICH.

H1C.

7 CPCo to NRC 09/02/80 DOCKET NO.: 05000155 POWER CAPACITY: 0240(THERMAL) 06/(ELECTRICAL)

H 2 A.

6 CPCo to NRC 01/23/81 OL NUMBER: DPR-6 Il 2 B.

G NRC to CPCo 09/26/80 N.S.S.S.: GE.

A/E FIRM: BECH.

H-2 D.

G l NRC to CPCo 09/26/80 l

KEY PERSONNEL SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL ll-3 B-3 Site Visit 07/16/79 OPERATING REACTORS BRANCH CHIEF: D. CRUTCH FIE LD OPERATING REACTORS PROJECT MANAGER: W. PAULSON 81-3 B.1.

3 Site Visit 07/16/79 H-3 C.

3 NRC to CPCo 08/04/B0 KEY FOR STATUS CODES U4 5

NUREG/CR-1582 08/80 l

)

114 A.

5 NUREG/CR-1582 08/80 G - GENERIC 3 - QUESTION RESPONSE RECEIVED BY NRC 114 B.

5 NUREG/CR-1582 08/80 X - DELETED 4 - DRAFT SE RECEIVED H4 C.

5 NUREG/CR-1582 08/80 FROM REVIEW BRANCH O - TOPIC NOT 114 D.

2 NRC to CPCo 11/16/79 5 - DRAFT SE SENT TO UTILITY 1 - OUESTIONS RECEIVED 11-4 E.

X Site Visit 07/19/79 FROM REVIEW BRANCH j

6 - SE RESPONSE RECEIVED 114 F.

2 BY NRC 2 - OUESTIONS SENT TO UTILITY IU'1 1(SYSI 10/29/80 j

7 - TOPIC COMPLETE 5(Elec)

NRC to CPCo HI 2 3

CPCo to NRC 0848ds0 M.

2-2

l BIG ROCK POINT t

TOPIC NO.

STATUS RFMARKS TOPIC NO.

STATUS REMARKS f

Ill.3 A.

3 CPCo to NRC 08/09/80 til-10 B.

X NRC to CPCo 11/16/79

?

1113 B.

X NRC to CPCo 12/26/80 Ill-10 C.

X NRC to CPCo 11/16/79 l

{

1113 C.

O ll111 3

5 1114 A.

0 31112 3

CPCo to NRC 10/31/80 til4 B.

O IV.1 A.

7 NRC to CPCo 10/09/79 111-4 C.

O IV.2 2

NRC to CPCo 12/15/80 til4 D.

O IV.3 X

NRC to CPCo 11/16/79 111-5 A.

3 V.1 G

NRC to CPCo 11/16/79 l

111-5 B.

2 NRC to CPCo 01/04/20 V.2 X

NRC to CPCo 11/16/79 lil-6 3

CPCo to NRC 01/09/81 V.3 G

NRC to CPCo 11/16/79 111-7 A.

X NRC to CPCo 11/16/79 V4 G

NRC to CPCo 11/16/79 til-7 B.

3 CPCo to NRC 08/08/80 V-5 4

1117 C.

X NRC to CPCo 11/16/79 V-6 7

NRC to CPCo 03/05/80 l

l 1117 D.

3 NRC to CPCo 08/09/79 V-7 X

NRC to CPCo 11/16/79 i

l 111-8 A.

G NRC to CPCo 11/16/79 V-8 X

NRC to CPCo 11/16/79 i

l 111 8 B.

X NRC to CPCo 09/26/80 V-9 X

NRC to CPCo 11/16/79 i

j til-8 C.

7 NRC to CPCo 02/05/80 V.10 A.

7 NRC to CPCo 10/09/79 111-8 D.

G NRC to CPCo 11/16/79 V.10 B.

4(SYS) 111-9 G

NRC to CPCo 11/16/79 V-11 A.

6(Elec) CPCo to NRC 09/24/80 i

11110 A.

6 CPCo to NRC 09/24/80 V.11 B.

4(Sys) 5(Elec) Part of Vll.3 2-3 i

BIG ROCK POINT TOPIC NO.

STATUS HEMAHKS TOPIC No.

STATUS IIEMAHKS V-12 A.

7 NRC to CPCo 10/09/79 VI 7 D.

G NRC to CPCo 11/1699 V 13 G

NRC to CPCo 11/16/79 VI 7 E.

G NRC to CPCo 11/1699 VI-1 3

CPCo to NRC 07/12/79 VI 7 F.

X NRC to CPCo 11/16/79 VI-2 A.

X NRC to CPCo 11/1699 VI-8 G

NRC to CPCo 09/26/80 VI-2 B.

G NRC to CPCo 11/16/79 VI-9 X

NRC to CPCo 11/16/79 VI-2 C.

X NRC to CPCo 11/16/79 VI-10 A.

O VI 2 D.

3 CPCo to NRC 04/02/80 VI 10 B.

X NRC to CPCo 11/16/79 VI-3 3

CPCo to NRC 04/02/80 Vll1 A.

O Vl4 0(Sys)

Vil1 B.

G NRC to CPCo 11/16/79 2(Elec) NRC to CPCo 12/02/80 VI-5 0(Sys)

Vil 2 0

0(Elec)

V14 G

NRC to CPCo 11/16/79 Vil 3 4(Sys) 7(Elec) NRC to CPCo 10/29/80 VI 7 A.1.

X NRC to CPCo 11/16/79 Vil4 G

NRC to CPCo 11/16/79 V6 7 A. 2.

X NRC to CPCo 11/16/79 Vll-5 G

NRC to CPCo 11/16/79 Vl4 A. 3.

O Vil4 G

NRC to CPCo 11/16/79 VI 7 A. 4.

G NRC to CPCo 11/16/79 Vil 7 X

NRC to CPCo 11/16/79 VI 7 B.

O Vill 1 A.

G NRC to CPCo 11/16/79 VI-7 C.

O Vill-2 7

CPCo to NRC 09/24/80 VI 7 C.1.

7 CPCo to NRC 09/24/80 Vill 3 A.

7 VI-7 C. 2.

O Vill.3 B.

7 CPCo to NRC 09/24/80 VI-7 C. 3.

X NRC to CPCo 11/16/79 Vill 4 7

CPCo to NRC 09/24/80 24

l, l

l BIG ROCK POINT l

TOPIC NO.

STAIUS ItE M ARKS topic NO.

STATUS REM AR KS l

IX-1 0

NRC to CPCo 11/27/79 XV 10 X

NRC to CPCo 11/16/79 l

IX-2 G

NRC to CPCo 11/16/79 XV 11 0

IX 3 2

XV 12 X

NRC to CPCo 11/16/79 IX4 X

NRC to CPCo 11/16/79 XV 13 O!Sys)

O(Doses)

IX-5 0

XV-14 0

IX-6 G

NRC to CPCo 11/16/79 XV 15 0

X X

NRC to CPCo 11/16/79 XV-16 0

XI-1 G

NRC to CPCo 11/16/79 XV 17 X

NRC to CPCo 11/16/79 XI-2 G

NRC to CPCo 11/16/79 XV 18 0(Sys)

O(Doses)

Xill 1 G

NRC to CPCo 11/16/79 XV 19 O(Sys)

O(Doses) r f

X1112 G

NRC to CPCo 11/16/79 XV-20 0

i XV-1 0

XV 21 G

NRC to CPCo 11/16/79 l

XV2 X

NRC to CPCo 11/16/79 XV-22 G

NRC to CPCo 11/16/79 XV3 0

XV 23 X

NRC to CPCo 11/16/79 XV4 0

XV 24 G

NRC to CPCo 11/16/79 XV-5 0

XVI X

NRC to CPCo 11/05/80 XV-6 X

NRC to CPCo 11/16/79 XVil G

NRC to CPCo 11/16/79 XV-7 0

XV-8 0

XV-9 0

25 1

i

>RESDEN1 i

FACILITY INFORMATION OP O

S US IMRKS FACILITY: DRESDEN 1 Il 1 A.

0 LICENSEE: COMMONWEALTH EDISON REGION / LOCATION: 9 MILES E AST OF MORRIS, ILL.

1 DOCKET NO.: 05000010 11-1 C.

O POWER CAPACITY: 700(TH ERM AL) 200(ELECTRICAL) 6 CECO to NRC 01/22/81 11-2 A.

f OL NUMBER: DPR-2 18 2 B.

G NRC to CECO 09/11/80 Il 2 C.

O A/E FIRM: BECH.

i KEY PERSONNEL 112 D.

G NRC to Ceco 09/11/80 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD 133 B.

3 Site Visit 11/09/79 OPERATING _ REACTORS PROJECT MANAGER: P. O'CONNOR ll-3 B.1.

3 Site Visit 11/09/79 Il-3 C.

3 Site Visit 11/09/79 KEY FOR STATUS CODES 11 4 5

NUREG/CR-1582 08/80 G - GENERIC 3 - OUESTION RESPONSE 114 A.

5 NUREG/CR-1582 08/80 RECEIVED BY NRC H

B, 5

M W W 582 08M 5

X - DELETED 4 - DRAFT SE RECEIVED 114 C.

5 NUREG/CR-1582 08/80 t

0 - TOPIC NOT FROM REVIEW BRANCig I

ST ART ED 114 D.

0

)

5 - DRAFT SE SENT TO 1 - OUESTIONS RECEIVED UTILITY FROM REVIEW BRANCH I

6 - SE RESPONSE RECEIVED 114 F.

0 RY NRC 2 - OUESTIONS SENT TO IU' 7 - topic COMPLETE E

111-2 1

24

DRESDEN 1 I

i TOPIC NO.

STATUS REMARKS TOPIC NO.

STATUS REMARKS 111-3 A.

1 111-10 B.

X NRC to CECO 11/16/79 1113 B.

X NRC to CECO 11/16/79 11110 C.

X NHC to CECO 11/16/79 til 3 C.

O 111 11 0

j 1

1814 A.

0(AEB) 111-1 2 0

l 0(SEB) til4 B.

0(MTEB)

IV 1 A.

7 NRC to CECO 11/05/79 8

O(SEB) 1114 C.

0(AEB)

IV-2 2

NRC to CECO 12/15/80 O(RSB) 1114 D.

O IV-3 X

NRC to CECO 11/16/79 til-5 A.

2 NRC to CECO 01/04/80 V.1 G

NRC to CECO 11/16/79 I

111-5 B.

2 NRC to CECO 01/04/80 V2 X

NRC to Ceco 11/16/79 I

i 111-6 2

NRC to CECO 08/04/80 V-3 X

NRC to CECO 11/16/79 1817 A.

X NRC to CECO 11/16/79 V4 G

NRC to CECO 11/1609 i

Ill-7 B-1 V-5 6

CECO to NRC 09/02/80 i

lil-7 C.

X NRC to CECO 11/16/79 V-6 7

NRC to CECO 03/05/80

)

1117 D.

3 Ceco to NRC 08/05/80 V7 X

NRC to CECO 11/16/79 1118 A.

G NRC to CECO 11/16/79 V-8 X

NRC to CECO 11/16/79 111-8 B.

X NRC to Ceco 09/11/80 V-9 X

NRC to CECO 11/16/79 111-8 C.

6 CECO to NRC 03/10/80 V 10 A.

7 NRG to CECO 11/03/79 i

f 111-8 D.

G NRC to Ceco 11/16/79 V-10 B.

4(Sys) til-9 G

NRC to CECO 11/16/79 V.11 A.

6 CECO to NRC 09/26/80 11110 A.

7

' CECO to FUIC 10/06/80 V.11 B.

X NRC to CECO 09/11/80 2

1 i

2-7 i

i

i DRESDEN 1 topic No.

STATUS HEMAHKS TOPIC NO.

STATUS HEMAHKS a

}

V 12 A.

6 CECO to NRC 08/12/80 VI 7 D.

G NRC to CECO 11/16/79 j

V.13 G

NRC to CECO 11/16/79 VI 7 E.

G NRC to CECO 11/16/79 VI1 3

CECO to NRC 07/27/79 VI 7 F.

X NRC to Ceco 11/16/79 l

VI-2 A.

X NRC to CECO 11/16/79 VI-8 G

NRC to CECO 09/11/80 l

I VI 2 B.

G NRC to CECO 11/16/79 VI-9 X

NRC to CECO 09/11/80 i

VI 2 C.

X NRC to CECO 11/16/79 VI 10 A.

O VI 2 D.

2 VI 10 B.

6(Sys)

CECO to NRC 05/02/79 7(Elec)

VI 3 2

Vil1 A.

O Vl4 OGys)

Vll.1 B.

G NRC to CECO 11/16/79 1(Elec)

VI-5 1

Vll-2 0

j V14 G

NRC to CECO 11/16/79 Vil-3 4(Sys) j O(Elec)

VI 7 A.1.

X NRC to CECO 11/16/79 Vil4 G

NRC to Ceco 11/16/79 l

VI-7 A. 2.

X NRC to CECO 11/16/79 Vil 5 G

NRC to CECO 11/16/79 i

j VI 7 A. 3.

O Vila G

NRC to CECO 11/16/79 l

VI 7 A. 4.

G NRC to CECO 11/16/79 Vil-7 X

NRC to CECO 11/16/79

,i VI 7 B.

X NRC to CECO 11/16/79 Vill 1 A.

G NRC to CECO 11/16/79 VI 7 C.

O Vill 2 7

i VI-7 C.1.

7 Vill 3 A.

2 NRC to Ceco 10/10/80

I VI 7 C. 2.

7 Vill-3 B.

5 NRC to CECO 07/01/80 I

VI-7 C. 3.

X NRC to CECO 11/16/79 Vill 4 5

NRC to CECO 06/12/80 2-8

i' DRESDEN 1 i

l topic NO.

STAlus itE M AHKS TOPIC NO.

STATUS HEMARKS IX 1 3

CECO to NRC 06/02/80 XV-10 X

NRC to CECO 11/16/79 IX-2 G

NRC to CECO 11/16/79 XV 11 0

I IX 3 3

CECO to NRC 11/29/79 XV 12 X

NRC to CECO 11/16/79 IX4 X

NRC to Ceco 11/16/79 XV 13 0(Sys)

O(Doses) l IX-5 0

XV 14 0

f IX-6 G

NRCao CECO 11/16/79 XV-15 0

1 (I

X X

NRC to CECO 11/16/79 XV-16 0

j!

XI1 G

NRC to CECO 11/16/79 XV 17 X

NRC to CECO 11/16/79 t

4 l'

XI-2 G

N3C to CECO 11/16/79 XV-18 0(Sys) 0(Doses) i X1111 G

NRC to CECO 11/16/79 XV 19 0(Sys)

O(Doses)

X1812 G

NRC to Ceco 11/16/79 XV-20 7

NRC to CECO 08/12/80 XV-1 0

XV 21 G

NRC to CECO 11/16/79 XV 2 X

NRC to CECO 11/16/79 XV 22 G

NRC to CECO 11/16/79 XV-3 0

XV 23 X

NRC to CECO 11/16/79 XV4 0

XV 24 G

NRC to CECO 11/16/79 XV-S 0

XVI X

NRC to CECO 11/05/80 XV-6 X

NRC to CECO 11/16/79 XVil G

NRC to CECO 11/16/79 XV7 0

XV-8 0

XV-9 0

29

>RESDEN2 FACILITY INFORMATION

,gp FACILITY: DRESDEN 2 Il-1 A.

O LICENSEE: COMMONWEALTH EDISON H

B, o

REGION / LOCATION: 9 MILES EAST OF MORRIS, ILL.

DOCKET NO.: 05000237 11 1 C.

O POWER CAPACITY: 2527(THERMAL) 9794(ELECTRICAL) 112 A.

6 CECO to NRC 01/22/81 OL NUMBER: DPR 19

" I N.S.S.S.: GE.

l l

A/E FIRM: S&L 112 C.

O H2D.

G NRC to Ceco 09/11/80 l

KEY PERSONNEL i

fi MsYt SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL 01/09/79 l

OPERATING REACTORS BRANCH CHIEF: D. CRUTCH FIE LD 113 B.

3 CECO to NRC Site Visit 01/09/79 OPERATING REACTORS PROJECT MANAGER: P. O'CONNOR ll.3 B.1.

3 CECO to NRC Site Visit 01/09/79 H-3 C.

3 CECO to NRC E!te Visit 01/09ng KEY rdR STATUS CODES U4 5

NUREG/CR 1582 08/80 i

11-4 A.

5 NUREG/CR 1582 08/80 i

G - GENERIC 3-ES ()N RESP ( NSE 4 - Dil AFT SE flECEIVED l

U-4 C.

5 NUREG/CR 1582 08/80 FROM IIEVIEW Bil ANCll O - TOPIC NOT STARTED H 4 D.

O 5 - DRAFT SE SENT TO j

i 1 - OUESTIONS RECElVED UTILITY U

0 j

FilOM REVIEW IIR ANCil G - SE flESPONSE RECEIVED i

II"4 F-0 BY NilC 2 - OUESTIONS SENT TO I

UTILITY IU'l 1(Sys) l 7 - TOPIC COMPLE TE 3(Elec) Part of Vil-3 l

IH-2 3

2 10 d

i

i l

l DRESDEN 2 TOPIC NO.

STATUS REMARKS TOPIC NO.

STATUS REMARKS 1113 A.

3 CECO to NRC 09/2899 11110 B.

X NRC to CECO 11/16/79 l

1813 B.

X NRC to CECO 11/16/79 11110 C.

7 NRC to CECO 05/22/79 i

j l113 C.

O 11111 5

NRC to Ceco 01/30/81 l

lil4 A.

0(AEB) til12 3

Ceco to NRC 10/30/80 l

O(SEB) 1114 B.

0(MTEB)

IV 1 A.

7 NRC to CECO 11/13/79 0(SEB) lil-4 C.

0(ASB)

IV-2 2

NRC to CECO 12/15/80 y

l O(SEB) 1814 D.

O IV 3 G

NRC to CECO 11/16/79 111-5 A-2 NRC to CECO 01/04/80 V.1 G

NRC to CECO 11/16/79 181-5 B.

6 CECO to NRC 03/21/80 V-2 X

NRC to Ceco 11/16/79 118-6 5

NRC to Ceco 05/20/80 V-3 G

NRC to CECO 11/16/79 1117 A.

X NRC to CECO 11/16/79 V4 G

NRC to Ceco 11/16/79 j

til 7 B.

3 CECO to NRC 09/2899 V-5 6

CECO to NRC 09/02/80 1

1117 C.

X NRC to CECO 11/16/79 V-6 7

NRC to Ceco 03/05/80 l

l lil-7 D.

3 CECO to NRC 08/05/80 V-7 X

NRC to CECO 11/16/79 111-8 A.

G NRC to CECO 11/16/79 V-8 X

NRC to CECO 11/16/79 l

l 111-8 B.

G NRC to CECO 09/11/80 V9 X

NRC to CECO 11/16/79 I

lil-8 C.

6 CECO to NRC 03/10/80 V 10 A.

7 NRC to CECO 11/08/79

)

til 8 D.

G NRC to CECO 11/16/79 V-10 8.

5 NRC to CECO 11/14/80 k

111 9 G

NRC to CECO 11/1G/79 V 11 A.

7 CECO to NRC 09/30/80 I

11110 A.

7 mRC to CECO 01/26/81 V 11 B.

5(Sys) NRC to CECO 11/14/80

{

3(Elec) Part of vit-3 2-11 l

DRESDEN 2

i TOPIC No.

ST AT US HEMAHKS TOPIC NO.

STATUS HEMAHKS V 12 A.

6 CECO to NRC 08/12/80 VI-7 D.

G NRC to CECO 11/16/79 V 13 G

NRC to Ceco 11/16/79 VI 7 E.

x NRC to CECO 11/16/79 VI-1 3

CECO to NRC 07/27/79 VI 7 F.

X NRC to CECO 11/16/79 VI-2 A.

G NRC to Ceco 11/16/79 VI-8 G

NRC to Ceco 09/11/80 VI-2 B.

G NRC to CECO 11/16/79 VI-9 X

NRC to Ceco 11/16/79 VI 2 C.

X NRC to CECO 11/16/79 VI 10 A.

5 NRC to CECO 02/09/81 VI-2 D.

3 CECO to NRC 11/20/80 VI 10 B.

7(Sys)

CECO to NRC 05/02/79 7(Elec) NRC to CECO Oi/30/81 VI-3 Val 1 A.

2 NRC to CECO 10/22/80 3

CECO to NRC 11/20/80 VI4 0(Sys)

Vll-1 B.

G NRC to CECO 11/16/79 1(Elec)

VI-5 1

Vll-2 5

NRC to CECO 02/09/81 V14 G

NRC to CECO 11/16/79 Vil 3 5(sys)

NRC to CECO 11/14/80 3(Elec' VI-7 A.1.

X NRC to CECO 11/16/79 Vil4 G

NRC to CECO 11/16/79 VI 7 A. 2.

X NRC to CECO 11/1*/79 Val-5 G

NRC to CECO 11 " 6/79 VI-7 A. 3.

5 NRC to CECO 02/09/81 Vil4 G

NRC to CECO 11/16/79 VI 7 A. 4.

G NRC to CECO 11/16/79 Vll.7 X

NRC to CECO 11/16/79 VI 7 B.

X NRC to CECO 11/16/79 Vill 1 A.

G NRC to CECO 11/16/79 VI-7 C.

O Vill-2 7

NRC to CECO 12/31/80 VI-7 C.1.

4 Vill 3 A.

7 NRC to Ceco 11/08/79 VI-7 C. 2.

O Vill-3 B.

7 NRC to CECO 01[26/81 VI-7 C. 3.

X NRC to CECO 11/16/79 Vill 4 5

N RC to CECO 06/12/80 2 12

i t

DRESDEN 2 V

TOPIC NO.

STATUS HEMAHKS lOPIC NO.

STATUS HEMAHKS XV-10 X

NRC to CECO 11/16# 9 IX 1 3

CECO to NRC 06/02/80 XV 11 0

IX 2 G

NRC to CECO 11/1609 f

6 l

1 IX 3 3

CECO to NRC 11/29/79 XV 12 X

NRC to CECO 11/16/79 XV-13 o(sy,)

IX4 X

NRC to CECO 11/16/79 O(Doses)

XV 14 0

IX-5 0

XV-15 o

IX4 G

NRC to CECO 11/16/79 XV 16 3

CECO to NRC 08/18/80 j

X X

NRC to CECO 11/16/79 1

XV 17 X

NRC to CECO 11/16/79 XI1 G

NRC to Ceco 11/16/79 XV 18 XI-2 G

NRC to Ceco 11/16/79 O(Sys)

O(Doses)

XV 19 Xill 1 G

NRC to CECO 11/16/79 O(Sys) f O(Doses) l XV 20 0

Xill-2 G

NRC to CECO 11/16/79 XV 21 G

NRC to CECO 11/16/79 XV1 o

XV-22 G

NRC to CECO 11/16/79 XV-2 X

NRC to CECO 11/16/79 XV-23 X

NRC to CECO 11/16/79 XV3 o

l f

XV 24 G

NRC to CECO 11/16/79 XV4 o

l XVI X

NRC to CECO 11/05/80 l

XV-5 o

l XVil G

NRC to CECO 11/16/79 XV-6 X

NRC to CECO 11/16/79 XV-7 o

XV-8 o

I

(

XV-9 o

I 2 13 1

4 ilNNA i

FACILITY INFORMATION TOPIC NO.

STATUS REMARKS I

F

}

FACILITY: GINNA 111 A.

0 l

l LICENSEE: ROCHESTER GAS & ELECTRIC REGION / LOCATION: 15 MILES NORTH EAST OF ROCHESTER, NY.

DOCKET NO.: 05000244 111 C.

O i

POWER CAPACITY: 1520(THERMAL) 0490(ELECTRICAL)

Il-2 A.

6 RGE to NRC 01/19/81 OL NUMBER: DPR 18 112 B.

G NRC to RGE 10/01/80 5

I A/E FIRM: GIL 112 C-6 RGE to NRC 01/30/79 11-2 D.

G NRC to RGE 10/01/80 l

KEY PERSONNEL 4

1 11-3 A.

6 RGE to NRC 02/28/81 j

SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSE LL OPERATING REACTORS BRANCH CHIEF: D. CRUTCH FIELD 113 B.

6 RGE to NRC 02/28/81 OPERATING REACTORS PROJECT MANAGER: R. SNAIDER 11-3 B. 1.

6 RGE to NRC 02/28/81 11-3 C.

6 RGE to NRC 02/28/81 I

KEY FOR STATUS CODES 33-4 5

NUREG/CR 1582 08/80 1

11 A.

5 NUREG/CR-1582 08/80 G - GENERIC 3 - OUEST10N RESPONSE l

RECEIVED BY NRC H4 B.

5 NUREG/CR-1582 08/80 X - DELETED 4 - DRAFT SE RECEIVED 114 C.

5 NUREG/CR-1582 08/90 0 - TOPIC NOT FROM REVIEW BRANCil H

0 5 - DRAFT SE SENT TO 1 - OUESTIONS RECEIVED UTILITY FROM REVIEW BRANCH 6 - SE RESPONSE RECEIVED 2 - OUESTIONS SENT TO BY NRC UTILITY Ill.1 2(Sys) NRC to RGE 01/13/81 A

7 - TOPIC COMPLETE 6(Elec) RGE to NRC 01/23/81 111 2 4

l 2-14

GINNA i

TOPIC NO.

STATUS REMARKS TOPIC NO.

STATUS REMARKS l

111-3 A.

4 til 10 B.

7 RGE to NRC 08/2909 1914 B.

X NRC to RGE 12/31/80 til 10 C.

X NRC to RGE 11/16/79 1113 C.

O 11111 5

NRC to RGE 01/07/J1 l

l 1114 A.

0(AEB) lil 12 3

RGE to NRC 10/31/30 i

2(SEB) NRC to RGE 02/09/81 r

lit-4 B.

7 NRC to RGE 04/1809 IV 1 A.

7 NRC to RGE 05/29/79 l

1114 C.

O IV.2 3

RGE to NRC 01/19/81 1814 D.

0(AEB)

IV-3 X

NRC to RGE 11/16/79

)

2(SE B) NRC to RGE 02/09/81 l

111-5 A.

O V1 G

NRC to RGE 11/16/79 111-5 B.

6 RGE to NRC 08/07/80 V-2 X

NRC to RGE 11/16/73 til-6 5

NRC to RGE 01/07/81 V3 G

NRC to RGE 11/16/79 Ill7 A.

X NRC to RGE 11/16/79 V4 G

NRC to RGE 11/16/79 1117 B.

3 RGE to NRC 11/14/79 V-5 4

5 UI'7 E 2

V-6 7

NRC to RGE 03/05/80 NRC to RGE 02/09/81 til 7 D.

7 NRC to RGE 05/08/80 V-7 G

NRC to RGE 11/16/79 111-8 A.

G NRC to RGE 11/1609 V8 G

NRC to RGE 11/16/79 Ill-8 B.

X NRC to RGE 10/01/80 V9 X

NRC to RGE 11/16/79 Ill-8 C.

7 RGE to NRC 12/07/79 V.10 A.

7 NRC to RGE 02/02n9 i

lil 8 D.

G NRC to RGE 11/16/79 V.10 B.

6(Sys)

RGE to NRC 01/13/81 j

a 111-2 G

NRC to RGE 11/16/79 V 11 A.

7(Elec)

NRC to RGE 02/27/81 111-10 A.

S RGE to NRC 01/08/81 V.11 B.

6(Sys)

RGE to NRC 01/13/81 6(Elec)

RGE to NRC 01/08/81 j

i

}

215 1

l

GINNA TOPicNO.

ST AT US HLMAHKS TOPIC NO.

STATUS HEMAHKS l

V-12 A.

X NRC to RGE 11/16/79 VI 7 D.

G NRC to RGE 11/16/79 l

V.13 G

NRC to RGE 11/16/79 VI 7 E.

G NRC to RGE 11/16/79 VI1 1

VI 7 F.

6 RGE to NRC 01/08/81 VI 2 A.

X NRC to RGE 11/16/79 VI-8 G

NRC to RGE 10/01/80 VI-2 B.

G NRC to RGE 11/16/79 VI-9 X

NRC to RGE 11/16/79 VI-2 C.

X NRC to RGE 11/16/79 VI 10 A.

7 NRC to RGE 12/15/80 VI-2 D.

3 VI-10 B.

X NRC to RGE 11/16/79 VI3 3

Vll-1 A-7 RGE to NRC 01/28/81 V14 O(Sys)

Vll 1 B-G NRC to RGE 11/16/79

(

7(Elec) NRC to RGE 01/12/81 VI-5 0

Vil 2 6

RGE to NRC 01/23/81 V14 G

NRC to RGE 11/16/79 Vil-3 6(Sys)

RGE to NRC 01/13/81 6(Elec) RGE to NRC 01/n/R1 VI 7 A.1.

7 NRC to RGE 05/01/78 Vil4 G

NRC to RGE 11/16/79 VI 7 A. 2.

G NRC to RGE 11/16/79 Vil-5 G

NRC to RGE 11/16/79 l

VI-7 A. 3.

7 NRC to RGE 12/15/80 Vil4 G

NRC to RGE 11/16/79 VI 7 A. 4.

X NRC to RGE 11/16/79 Vlf 7 X

NRC to RGE 11/16/79 VI-7 B.

2 NRC to RGE 02/27/81 Vill 1 A.

G NRC to RGE 11/16/79 VI 7 C.

7 P'4C in RGE 02/20/81 Vill 2 6

RGE to NRC 01/30/81 VI-7 C.1.

7 NRC to RGE 02/27/81 Villa A-7 NRC to RGE 04/18/79 VI 7 C. 2.

7 NRC to RGE 02/20/81 Vill.3 B.

6 RGE to NRC 01/08/81 VI-7 C. 3.

X NRC to RGE 11/16/79 Vill-4 6

RGE to NRC 07/21/80 2 16

GINNA l

TOPIC NO.

STATUS itLMAllKS TOPIC NO-STATUS REMARKS f

' IX-1 0

XV 10 0

IX-2 G

NRC to RGE 11/16/79 XV 11 X

NRC to RGE 10/01/80 IX-3 3

XV 12 0(Sys)

O(Doses) l IX4 0

XV 13 X

NRC to RGE 11/16/79 IX-5 0

XV 14 0

I IX-6 G

NRC to RGE 11/16D9 XV-15 0

X 0

XV 16 3

RGE to NRC 06/18/80 l

XI-1 G

NRC to RGE 11/16/79 XV-17 0(Sys)

O(Dom)

XI-2 G

NRC to RGE 11/16/79 XV 18 X

NRC to RGE 03/11/80 l

Xill 1 G

NRC to RGE 11/16/79 XV-19 0(Sys)

{

O(Doses) i Xlil 2 O

NRC to RGE 11/16/79 XV-20 0

)

XV1 3

RGE to NRC 06/03/B0 XV 21 G

NRC to RGE 11/16/79 XV 2 3(Sys)

RGE to NRC 06/03/80 XV-22 G

NRC to RGE 11/16/79 O(Doses)

XV 3 3

RGE to NRC 06/03/80 XV-23 G

NRC to RGE 11/16fl9 XV4 0

XV 24 G

NRC to RGE 11/16/79 XV-5 0

XVI X

NRC to RGE 11/05/30 I

l XV-6 0

XVil G

NRC to RGE 11/16/79 b

3 XV7 3

RGE to NRC 06/03/80 XV-8 3

RGE to NRC 06/03/80 XV 9 0

1 4

2 17 4

1 1

IADDAM NECK n

FACILITY INFORMATION TOPIC NO.

STATUS REMARKS l

FACILITY: HADDAM NECK H-1 A.

0 l

LICENSEE: CONNECTICUT YANKEE ATOMIC POWER H 1 B.

O REGION / LOCATION: 13 MILES EAST OF MERIDEN, CT.

DOCKET NO.: 05000213 111 C.

O POWER CAPACITY: 1825(THERMAL 0575(ELECTRICAL) i 112 A.

6 CYAPCo to NRC 01/22/81

[

OL NUMBER: DPR-61 H-B.

G NRC to CYAPCo 10/01/80 N.S.S.S.: WEST.

A/E FIRM: S&W 112 C.

7 CYAPCo to NRC 02/16/79 i

11-2 D.

G NRC to CYAPCo 10/01/80 f

KEY PERSONNEL i

N I' SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSE LL OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIE LD 113 B.

3 Site Visit OPERATING RE ACTORS PROJECT MAN AGER: R. CARUSO 11-3 B. 1.

3 Site Visit I

f 11-3 C.

3 Site Visit j

KEY FOR STATUS CODES H4 5

NUREG/CR.1582 08/80 H4 A.

5 NUREG/CR.1582 08/80 G - GENERIC 3 - OUESTION RESPONSE RECEIVED RY NRC H4 B.

5 NUREG/CR.1582 08/80 X - DELETED 4 - DRAF1 SE RECElVED 114 C.

5 NUREG/CR.1582 08/80 O - TOPIC NOT FROM REVIEW BRANCH START E D l

H D.

0 5 - DRAFT SE SENT TO l

1 - OUESTIONS RECEIVED UTILITY l

H X

NRC to CYAPCo 04/16/79 FROM REVIEW BRANCH

)

6 - SE RESPONSE RECEIVED 114 F.

0 1

BY NRC l

2 - OUESTIONS SENT TO UTILITY H

3(sys)

CYAPCo to NRC 09/28/79 I

7 - TOPIC COMPLETE j

O(Elec) 111-2 3

CYAPCo to NRC 09/07/79 i

i 2 is i

I

}

l l

l HADDAM NECK i

TOPIC NO.

STATUS REMARKS TOPIC NO.

STATUS REMARKS 1113 A.

3 CYAPCo to NRC 09/07n9 111-10 B.

7 NRC to CYAPCo 09/26/80 f

1113 B.

O 11110 C.

X NRC to CYAPCo 04/16/79 j

111-3 C.

O 111 11 3

l i

i 1814 A.

0(AEB) 11112 3

CYAPCo to NRC 10/31/80 l

1(SEB) j lil4 B.

0(MTEB)

IV 1 A.

7 CYAPCo to NRC 06/25/79 j

O(SEB) l

!!14 C.

0(ASB)

IV-2 2

N RC to CYAPCo 12/15/80 0(SEB) j l

111-4 D.

O IV-3 X

NRC to CYAPCo 11/16/79 111-5 A.

?

CYAPCo to NRC 02/07/80 V-1 3

NRC to CYAPCo 04/16/79 l

{

1115 B.

3 V.2 X

NRC to CYAPCo 04/16/79 111-6 3

CYAPCo to NRC 08/05/80 V-3 G

NRC to CYAPCo 04/16/79 l

Ill-7 A.

X NRC to CYAPCo 11/16/79 V-4 G

NRC to CYAPCo 11/16/79 Ill-7 B.

3 CYAPCo to NRC og/07pg V-5 7

l lil-7 C.

X NRC to CYAPCo 04/16/79 V-6 7

NRC to CYAPCo 03/05/80 1117 D.

O V7 G

NRC to CYAPCo 04/16/79 Ill-8 A.

G NRC to CYAPCo 11/16/79 V-8 G

NRC to CYAPCo 04/16/79 111-8 8.

X NRC to CYAPCo 10/01/80 V-9 X

NRC to CYAPCo 11/16/79 1118 C.

6 CYAPCo to NRC 12/18/79 V-10 A.

7 NRC to CYAPCo 01/13/81 111-8 D.

G NRC to CYAPCo 11/16/79 V-10 8.

6(Sys)

CYAPCo to NRC 09/28/79 lit-9 G

NRC to CYAPCo 11/16/79 V 11 A.

7 CYAPCO to NRC 09/04/80 I

l 111-10 A.

7 CYAPCo to NRC 09/04/80 V 11 B.

6(Sys)

CYAPA to NRC 09/28/79 i

g 7(Elec)

Part of Vil 3 1

l i

2 19 i

i

l HADDAM NECK j

i topic NO, SIATUS HLMAHKS TOPIC NO.

STATUS HLMA11KS V 12 A.

X NRC to CYAPCo 04/16/79 VI 7 D.

G NRC to CYAPCo 11/16/79 V.13 o

NRC to CYAPCo 04/16/79 VI 7 E.

G NRC to CYAPCo 11/16/79 VI1 3

CYAPCo to NRC 10/31/79 VI 7 F.

X NRC to CYAPCo 04/16/79 j

VI 2 A.

X NRC to CYAPCo.- 04/16/79 VI-8 G

NRC to CYAPCo 10/01/80 l

VI 2 B.

g NRC to CYAPCo 04/16/79 VI-9 X

NRC to CYAPCo 11/16/79 VI 2 C.

X NRC to CYAPCo 04/16/79 VI 10 A.

O VI 10 B.

X NRC to CYAPCo 04/16/79 VI-2 D.

2 I

Vil1 A.

O I

VI-3 2

l Vll-1 B.

G NRC to CYAPCo 04/16/79 V14 O(Sys) l 7(Elec) CYAPCo to NRC 12/08/80 Vil 2 0

li VI-5 3

CYAPCo to NRC 11/05/80 1

Vie a

NRC to CYAPCo 11/16/79 Vil 3 6lSys)

NRC to CYAPCo 09/28/79 7(Elec) CYAPCo to NRC 01/22/81 VI 7 A.1.

7 NRL to CYAPCo 10/22/77 Vil4 G

NRC to CYAPCo 04/16/79 VI-7 A. 2.

X NRC to CYAPCo 04/16/79 Vil-5 G

NRC to CYAPCo 04/16/79 Vil4 G

NRC to CYAPCo 04/16/79 VI-7 A. 3.

O i

l l

VI 7 A. 4.

X NRC to CYAPCo 04/16/79 Vll 7 X

NRC to CYAPCo 04/16/79 I

l Vill 1 A-G NRC to CYAPCo 04/16/19 l

VI-7 B.

2 NRC to CYAPCo 02/27/81 Vill 2 6

CYAPCo to NRC 10/03/80 l

VI-7 C.

O l

Vill 3 A.

7 CYAPCo to NRC 02/16/79 i

VI 7 C.1.

7 CYAPCo to NRC 09/0480 Vill-3 B.

7 CYAPCo to NRC 01/22/81 VI 7 C. 2.

O Vill.4 0

vi 7 C. 3.

3 I

2-20

I i

HADDAM NECK TOPicNO.

STATUS RLMAHKS TOPIC NO.

STATUS REMAHKS IX-1 0

XV 10 0

I I

IX 2 G

NRC to CYAPCo 11/10/79 XV11 X

NRC to CYAPCo 10/01/80

\\

IX-3 2

XV-12 O(Sys) a O(Doses)

IX4 0

XV-13 X

NRC to CYAPCo 11/16/79 r

IX 5 0

XV 14 0

IX4 G

NRC to CYAPCo 04/16 # 9 XV-15 0

X 0

XV-16 3

CYAPCo to NRC 06/20/80 XI1 G

NRC to CYAPCo 04/16 # 9 XV 17 O(Sys) i O(Doses)

XI-2 G

NRC to CYAPCo 11/16/79 XV 18 x

NRC to CYAPCo 10/01/80 Xill-1 G

NRC to CYAPCo 11/16/79 XV-19 0(Sy;)

O(Doses)

XIll 2 G

NRC to CYAPCo 11/16 # 9 XV 20 0

XV1 0

NRC to WAN WM

(

XV 2 O(Sys)

XV 22 G

NRC to CYAPCo 04/16/79

{

O(Doses) l i

XV-3 0

XV-23 G

NRC to CYAPCo 11/16/79 l

XV4 0

XV 24 G

NRC to CYAPCo 11/16/79 t

f XV-5 0

XVI X

NRC to CYAPCo 11/05/80 I

XV-6 0

XVil G

NRC to CYAPCo 11/16/79 XV-7 0

l XV-8 0

XV-9 0

2-21 1

ACROSSE FACILITY INFORMATION TOPIC NO.

STATUS REMARKS FACILITY: LACROSSE n.1 A.

O LICF.NSEE: DAIRYLAND POWER 11 1 B.

O REGION / LOCATION: 19 MILES SOUTH OF LACROSSE, WISC.

H1C.

O DOCKET NO.: 05000409 POWER CAPACITY: 0165(THERMAL) 0050(ELECTRICAL) gg.2 A.

5 NRC to DPC 12/15/80 OL MBR DM 11-2 B.

G NRC to DPC 09/26/80 N.S.S.S.: AC.

A/E FIRM: S&L ll 2 D.

G NRC to DPC 09/25/80 KEY PERSONNEL 113 A.

O SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSE LL OPERATING REACTORS BRANCH CHIEF: D. CRUTCHFIELD OPERATING REACTORS PROJECT MANAGER: J. SHE A 11-3 B.1.

O 113 C.

O KEY FOR STATUS CODES 31 4 5

NUREG/CR 1582 08/80 H4 A-5 NUREG/CR 1582 08/80 3 - OUESTION RESPONSE G - GENERIC itECEIVED fly NRC NUREG/W582 08/M X - DELETED 4 - DR AF T SE ItECEIVED 114 C-5 NUREG/CR 1582 08/80 FROM REVIEW RH ANCll 0 - topic NOT H

D.

3 ste Msn 07/10M 5 - DRAFT SE SENT TO UTILITY 1 - OUESTIONS RECEIVED 114 E.

O FROM IIEVIEW RRANCil G - SE RESPONSE ItECEIVED p

RY NRC 2 - OUESTIONS SENT TO UTILITY gig.1 g gsys) 7 - Toric COMPLET E O(Elec) 111 2 2

NRC to DPC 08/09/79 2-22

1 l.ACROSSE l

I l

TOPIC NO.

STATUS REMARKS TOPIC NO.

STATUS REMARKS i

1113 A.

2 NRC to DPC 08/09/79 11110 B.

X NRC to DPC 10/29/79 j

til-3 B-X NRC to DPC 03/10/81 11110 C.

X NRC to DPC 10/29/79 j

til-3 C.

0 11111 3

DPC to NRC 06/11/79 l

1114 A.

0(AEB) 11112 3

DPC to NRC 10/31/80 L

O(SE B) 1114 B.

0(MTEB)

IV 1 A.

7 NRC to DPC 04/19/79 O(SEB) til4 C.

O IV-2 2

NRC to DPC 12/15/80 5

1814 D.

O IV 3 X

NRC to DPC 10/29/79 i

i

}

111-5 A.

2 DPC to NRC 01/04/80 V1 G

NRC to DPC 10/29/79 4

111-5 B.

2 NRC to DPC 01/04/80 V-2 X

NRC to DPC 10/29/79

[

t lil-6 3

DPC to NRC 1 0/14/80 V-3 X

NRC to DPC 10/29/79 I

I

)

111-7 A.

X NRC to DPC 10/29/79 V4 G

NRC to DPC 10/29/79 l

4 i

f ill 7 B.

2 NRC to DPC 08N9/79 V5 4

lil 7 C.

X NRC to OPC 10/29/79 V-6 7

NRC to DPC 03/05/80; 1187 D.

2 NRC to DPC 08/09/79 V7 X

NRC to DPC 10/29/79 L

1118 A.

G NRC to DPC 10/29/79 V-8 X

NRC to DPC 10/29/79 4

i 111-8 B.

X NRC to DPC 09/26/80 V9 X

NRC to DPC 10/29/79 l

i l

111-8 C.

5 NRC to DPC 12/15/80 V 10 A.

7 NRC to DPC 0147/81 l

1

]

Ill-8 D.

G NRC to DPC 10/29/79 V 10 B.

5(Sys)

NRC to DPC 12/22/80 i

111-9 G

NRC to DPC 10/29/79 V-11 A.

7 NRC to DPC 12/22/90 til 10 A.

7 NRC to DPC 07/10/80 V-11 B.

5(Sys)

NRC to DPC 12/22/80 0(Elec)

I 2-23 l

l 9

LACROSSE i

I TOPIC NO.

STATUS HEMARKS TOPIC NO.

STATUS HEMARKS V-12 A.

7 NRC to DPC 04/30/79 VI-7 D.

G NRC to DPC 10/29/79 i

V-13 G

NRC to DPC 10/29/70 VI-7 E.

X NRC to DPC 10/29/79 VI-1 3

DPC to NRC 08/23/79 VI-7 F.

X NRC to DPC 10/29/79 VI-2 A.

X NRC to DPC 10/29/79 VI-8 G

NRC to DPC 09/26/80 VI-2 B.

G NRC to DPC 10/29/79 VI-9 X

NRC to DPC 10/29/79 VI 2 C.

X NRC to DPC 10/29/79 VI-10 A.

O i

VI-2 D.

3 DPC to NRC 04/20/79 VI-10 B.

X NRC to DPC 10/29/79 VI-3 3

DPC to NRC 04/26/79 Vil-1 A.

0 l

l Vl4 0(Sys)

Vil1 B.

G NRC to DPC 10/29/79 d

1(Elec)

{

VI-5 1

Vil-2 0

i Vl4 G

NRC to DPC 10/29/79 Vil-3 5(Sys)

NRC to DPC 12/22/80 l

3(Elec) j VI-7 A.1.

X NRC to DPC 10/29/79 Vil4 a

NRC to DPC 10/29/79 VI-7 A. 2.

X NRC to DPC 10/29/79 Vil-5 G

NRC to DPC 10/29/79 1

VI-7 A. 3.

O Vil4 g

NRC to DPC 10/29/79 VI-7 A. 4.

X NRC to DPC 10/29/79 Vil 7 X

N9C to DPC 10/29/79 VI 7 8.

X NRC to DPC 10/29/79 Vill-1 A.

G NRC to DPC 10/29/79 VI-7 C.

O Vill-2 6

DPC to NRC 11/20/80

[

VI 7 C.1.

7 NRC to DPC 07/10/80 Vill 4 A.

7 NRC to DPC 06/05/79 l

VI-7 C. 2.

O Vill 3 B.

NRC to DPC 07/10/80 7

VI-7 C. 3.

X NRC to DPC 10/29/79 Vill 4 6

DPC to NRC 10/08/80

'l j

2-24 1

i i

\\

l f

l l

LACROSSE t

lOPIC NO.

STATUS ItEMAHKS TOPIC NO.

ST AT US HEMAHKS i

I IX 1 0

XV-10 X

NRC to DPC 10/29/79 i

j XV 11 0

l IX 2 G

NRC to DPC 10/29/79 IX-3 2

XV-12 X

NRC to DPC 10/29/79 i

I XV 13 0(Doses)

IX4 X

NRC to DPC 10/29/79 I

O(Sys) f XV 14 0

IX-5 0

XV-15 0

t IX4 G

NRC to DPC 10/29/?9 XV-16 0

X X

NRC to DPC 10/2909 XV 17 X

NRC to DPC 10/29/79 XI1 G

NRC to DPC 10/29U9 XV-18 O(ooses)

XI-2 G

NRC to DPC 10/29/79 O(Sys)

XV 19 O(poses)

Xill 1 G

NRC to DPC 10/29/79 O(Sys)

XV-20 0

Xill-2 G

NRC to DPC 10/29/79 f

XV-21 G

NRC to DPC 10/29/79 XV1 0

l XV-22 G

NRC to DPC 10/29/79 XV-2 X

NHC to DEC 10/29/79 XV-23 X

NRC to DPC 10/29/79 XVG 0

1 XV-24 G

NRC to DPC 10/28/79 l

XV4 0

I XVI X

NRC to DPC 11/05/80 XV-5 0

i XVil G

NRC to DPC 10/29/79 XV-6 X

NRC to DPC 10/29/79 XV7 0

XV-8 0

f xv.9 0

i 2-25 l

I

1 FACILITY INFORMATION TOPIC NO.

STATUS REMARKS FACILITY: MILLSTONE 1 LICENSEE: NORTHEAST NUCLEAR ENERGY 111 B.

O REGION / LOCATION: 5 MILES SOUTH WEST OF NEW LONDON, CONN.

DOCKET NO.: 05000245 111 C.

0 l

POINER CAPACITY: 2011(THERMAL) 0660(ELECTRICAL) 18-2 A 6

Wmm ME OL NUMBER: DPR-21 ll 2 B.

G NRC to NU 09/26/80 N.S.S.S.: GE.

H-2 C.

0 A/E FIRM: EBASCO l

l 18-2 D.

G NRC to NU 09/26/80 KEY PERSONNEL H-0 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSE LL OPERATING REACTORS BRANCH CHIEF: D. CRUTCH FIE LD 11-3 B.

O OPERATING REACTORS PROJECT MAN AGER: J. SHEA 11-3 B.1.

0 31-3 C.

O KEY FOR STATUS CODES 13 4 5

NUREG/CR-1582 08/80

[

114 A.

5 NUREG/CR 1582 08/80

[

G - GENERIC 3 - OUESTION RESPONSE RECEIVED BY NRC Ild B.

5 NUREG/CR-1S82 08/80 X - DELETED 4 - DRAFT SE RECEIVED 134 C.

5 NUREG/CR.1582 08/80 0 - TOPIC NGT FROM REVIEW BR ANCH STARTED H

D.

0 l

5 - DRAFT SE SENT TO 1 - OUESTIONS RECEIVED UTILITY I

FROM RCVIEW UR ANCH 6 - SE RESPONSE RECEIVED 114 F.

o i

2 - OUESTIONS SENT TO BY NRC UTILITY g g,j 7 - TOPIC COMPLEiE q3 Ill 2 3

NU to M3C 08/29/79 2-26 I

1 l

MILLSTONE 1 TOPIC NO.

ST AT US REMARKS TOPIC NO.

STATUS RE MA11KS i

111-3 A.

4 11110 B.

X NRC to NU 11/1609 I

l e

i j

Hi3 B-X NRC to NU 12/26/80 H

t C

08/2909 l

1 l

lil 3 C.

O Ill-11 3

l l

1814 A.

3(SEB)

NU to NRC 12/05/80 11112 3

NU to NRC 10/31/80 O(AEB) 1814 B-3(SEB)

NU to NRC 12/05/80 IV 1 A.

7 NU to NRC 02/12# 9 0(MTEB) 1814 C.

3(SEB)

NU to NRC 12/05/80 IV-2 2

NRC to NU 12/15/80 O(ASB) 1114 D.

O IV-3 G

NRC to NU 11/16/79 111-5 A-3 NU to NRC 11/08 # 9 V1 G

NRC to NU 11/16/79 l

l f

111-5 B.

1 V-2 X

NRC to NU 11/16/79 111-6 2

NRC to NU 09/02/d0 V-3 X

NRC to NU 11/1609 1117 A-X NRC to NU 11/16/79 V-4 G

NRC to NU 11/16/79 1817 B-3 NU to NRC 08/29/79 V-5 4

i ill-7 C.

X NRC to NU 11/16/79 V-6 7

NRC to NU 03/05/80 i

Hi 7 D.

V7 X

NRC to NU 11/16D9 7

NU to NRC 02/17/81 III 8 A-G NRC to NU 11/16 # 9 V8 X

NRC to NU 11/16 # 9 118-8 B.

G NRC to NU 09/26/80 V-9 X

NRC to NU 11/16 # 9 til-8 C.

6 NU to NRC 01/31/80 V-10 A.

7

. NU to NRC 03/05U9 f

383-8 D.

G NRC to NU 11/16/79 V.10 B.

5 NRC to NU 11/14/80 i

lil-9 G

NRC to NU 11/16/79 V-11 A.

5 NRC to NU 01/13/81 l

j 1112 A-5 NRC to NU 01/13/80 V 11 B.

5(Sys)

NRC to NU 11/14/80 j

0(Elec) 2-27 1

MILLSTONE 1 TOPIC NO.

STATUS HEMARKS TOPIC NO.

STATUS HEMARKS V 12 A.

7 NRC to NU 12/17/79 VI 7 D.

G NRC to NU 11/1609 V-13 G

NRC to NU 11/16/79 VI 7 E.

X NRC to NU 11/16/79 VI1 3

NU to NRC 10/10/80 VI-7 F.

X NRC to NU 11/1609 VI-2 A.

G NRC to NU 11/16/79 VI-8 G

NRC to NU 09/26/80 VI-2 B.

G NRC to NU 11/16/79 VI-9 X

NRC to NU 11/16D9 VI-2 C.

X NRC to NU 11/16/79 VI 10 A.

O VI-2 D.

2 VI 10 B.

6(Sys)

NU to NRC 04/27/79 7(Elec)

VI 3 2

Vil1 A.

2 NRC to NU 01/24/81 Vl4 O(Sys)

Vll 1 B.

G NRC to NU 11/16/79 2(Elect NRC to NU 12/08/80 VI-5 3

NU to NRC 11/28D9 Val-2 2

NRC to NU 01/24/81 Vl4 G

NRC to NU 11/16/79 Vil-3 5(SYs)

NRC to NU 11/14/80 O(Elec)

VI 7 A.1.

X NRC to NU 11/16/79 Vil4 G

NRC to NU 11/16/79 VI-7 A. 2.

X NRC to NU 11/16/79 Vil-5 G

NRC to NU 11/16/79 VI-7 A. 3.

O Vil4 G

NRC to NU 11/16/79 VI 7 A. 4.

G NRC to NU 11/16/79 Vil 7 X

NRC to NU 11/16/79 VI 7 8.

X NRC to NU 11/16/79 Vill 1 A.

G NRC to NU 11/16/79 VI 7 C.

o Vill-2 7

NRC to NU 02/13/81 VI-7 C.1.

5 NRC to NU 01/13/81 VillG A.

7 NRC to NU 04/18/79 VI 7 C. 2.

o Vill-3 B.

5 NRC to NU 01/13/81 VI-7 C. 3.

X NRC to NU 11/16/79 Vill 4 7

NU to NRC 01/29/81 2-28

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',i

OYSTER CREEK FACILITY INFORMATION TOPIC NO.

STATUS REMARKS t

FACILITY: OYSTER CREEK 1 111 A.

O LICENSEE: JERSEY CENTRAL POWER & LIGHT 111 B.

O REGION / LOCATION. 9 MILES SOUTH OF TOMS RIVER, NJ.

Il 1 C.

0 i

DOCKET NO.: 05000219 POWER CAPACITY: 1930(THERMAL) 0650(ELECTRICAL) 112 A.

5 NRC to JCPL 12/17/80 OL NUMBER: DPR 16 11-2 B.

C NRC to JCPL 09/26/80 N.S.S.S.: GE.

A/E FIRM: B&R ll-2 D.

G NRC to JCPL 09/26/80 KEY PERSONNEL H-3 A.

1 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL OPERATING REACTORS BRANf?1 CHIEF: D. CRUTCHFIE LD ll.3 B.

1 l

OPERATING REACTORS PROJECT MANAGER: W. PAULSON ll-3 B.1.

1 113 C.

1 KEY FOR STATUS CODES 11 4 5

NUREG/CR-1582 08/80 11-4 A-5 NUREG/CR-1582 08/80 G - GENE;n; 3 - OUESTION RESPONSE RECElVED BY NRC 114 B.

5 NUREG/CR 1582 08/80 X - DEIETED I

4 - DRAFT SE RECElVED 11-4 C.

5 NUREG/CR-1582 08/80 FROM REVIEW RRANCH j

0 - TOPIC NOT ST ART E D H4 D.

0

{

5 - DRAFT SE SENT TO UTILITY I

1 - OUESTIONS RECEIVED FROM REVIEW BRANCH G - SE RESPONSE RECEIVED

[

H O

RY NRC 2 - OUESTIONS SENT TO UTILITY Hi S

J l

7 - TOPIC COMPLETE E

111-2 3

JCPL to NRC 12/07/79 li 2 slo 1

OYSTER CREEK TOPIC NO.

STATUS REMARKS TOPIC NO.

STATUS REMARKS i

111-3 A.

3 JCPL to NRC 12/07/79 111-10 B.

X NRC to JCPL 11/16/79 118-3 B.

X NRC to JCPL 12/26/80 I

til 10 C.

O l

lil 3 C.

O 111 11 3

(

I i

IH4 A.

O Hl.12 3

JCPL to NRC 10/28/80 lil4 B-0 IV 1'A.

7 NRC to JCPL 07/10/79 1814 C.

2(ASB) NRC to JCPL 01/19/81 IV-2 2

NRC to JCPL 12/15/80 0(SEB)

{

181-4 D.

O IV 3 X

NRC to JCPL 11/1699 i

l IH 5 A.

1 V.1 G

NRC to JCPL 11/1609 Hi-5 B.

7 NRC to JCPL 07/10/80 V-2 X

NRC to JCPL 11/16/79 IH4 4

V-3 X

NRC to JCPL 11/16/79

)

Hi 7 A-X NRC to JCPL 11/1G/79 V-4 G

NRC to JCPi.

11/16/79 Hi 7 B.

3 JCPL to NRC 12/07/79 V-5 4

Ill 7 C-X NRC to JCPL 11/16/79 V-6 7

NRC to JCPL 03/05/80 i

Hl-3 JCPL to NRC 12/07/79 V7 X

NRC to JCPL 11/16D9 l

H1-8 A.

G NRC to JCPL 11/16/79 V-8 X

NRC to JCPL 11/16/79 1

i 111-8 B.

X NRC to JCPL 09/26/80 V9 X

NRC to JCPL 11/16/79 j

i 111-8 C.

7 NRC to JCPL 1'0/30/80 V 10 A.

7 JCPL to NRC 05/15/79 i

Hi-8 D.

G NRC to JCPL 11/16/79 V-10 B-7 NRC to JCPL 09/25/80 113-9 G

NRC to JCPL 11/1609 V-11 A.

7 NRC to JCPL

'12/15/80,

(

HI-10 A.

7 NRC to JCPL 12/15/80 V-11 B.

7(Sys)

NRC to JCPL 09/25/80 O(Elec) 2-31 e

0YSTER CREEK r

i topic t40.

STATUS REMAHKS TOPIC NO.

ST ATUS REMARKS

(

V-12 A.

4 VI-7 D.

G NRC to JCPL 11/16/79 l

V 13 G

NRC to JCPL 11/16n9 VI 7 E.

X NRC to JCPL 11/16/79 VI-1 2

NRC to JCPL 06/06/79 VI 7 F.

X NRC to JCPL 11/16/79 i

VI-2 A.

G NRC to JCPL 11/1609 VI-8 G

NRC to JCPL 09/26/80 l

VI-2 B.

G NRC to JCPL 11/16/79 VI-9 X

NRC to JCPL 11/16/79 I

i VI-2 C.

X NRC to JCPL 11/16/79 VI-10 A.

O VI 2 D.

2 VI 10 B.

X NRC to JCPL 11/16/79 I

VI-3 2

VI:-1 A.

2 NRC to JCPL 12/26/80 V14 O(Sys)

Vll.1 B.

G NRC to JCPL 11/16/79 2(Elec) NRCt o JCPL 12/08/80 VI-5 1

Val 2 0

Vl4 G

NRC to JCPL 11/16/79 Vll.3 7(sys)

NRC to JCPL 09/25/80 O(Elec)

VI 7 A.1.

X NRC to JCPL 11/16/79 Vil4 G

NRC to JCPL 11/16/79 VI 7 A. 2.

X NRC to JCPL 11/16/79 Vil-5 G

NRC to JCPL 11/16/79 VI-7 A. 3.

O Vil4 G

NRC to JCPL 11/16/79 VI 7 A. 4.

G NRC to JCPL 11/16/79 Vil 7 X

NRC to 'JCPL 11/16/79 VI 7 B.

X NRC to JCPL 11/16/79 Vill 1 A.

G NRC to JCPL 11/16/79 VI-7 C.

O Vill-2 7

NRC to JCPL 12/26/80 VI-7 C.1.

7 NRC to JCPL 12/15/80 Vill 3 A.

7 NRC to JCPL 01/16/81 Vl 7 C. 2.

7 Vill 3 B.

7 NRC to JCPL 12/15/80 VI 7 C. 3.

X NRC to JCPL 11/16/79 Vill 4 7

NRC to JCPL 12/15/80 2-32

OYSTER CREEK I

f I

l i

IOPIC NO.

STATUS itL M AltKS TOPIC NO.

STATUS ItE M Alt KS XV 10 X

NRC to JCPL 11/16/79 IX 1 3

JCPL to NRC 12/14/79 XV-11 0

IX-2 G

NRC to JCPL 11/16/79 IX 3 4

XV-12 X

NRC to JCPL 11/16/79 XV 13 O(Doses)

IX-4 X

NRC to JCPL 11/16/79 O(Sys)

IX-5 0

- XV 14 0

XV-15 0

IX4 G

NRC to JCPL 11/16/79 XV-16 0

X X

NRC to JCPL 11/16/79 XV-17 X

NRC to JCPL 11/16/79 XI-1 G

NRC to JCPL 11/16/79 XV 18 O(Doses)

XI-2 G

NRC to JCPL 11/16/79 O(Sys)

XV 19 O(doses)

Xill-1 G

NRC to JCPL 11/16/79 O(Sys)

XV-20 0

(

Xill-2 G

NRC to JCPL 11/16/79 XV-1 0

XV-21 G

NRC to JCPL 11/16/79 XV-22 G

NRC to JCPL 11/16/79 XV2 X

NRC to JCPL 11/16/79 XV3 o

XV 23 X

NRC to JCPL 11/16/79 L

XV4 0

XV-24 G

NRC to JCPL 11/16/79 XV-5 o

XVI X

NRC to JCPL 11/05/80 XVil G

NRC to JCPL 11/16/79 XV-6 X

NRC to JCPL 11/16/79 XV7 0

XV-8 o

XV-9 o

2-33 l

l

PALISADES FACILITY INFORMATION TOPIC NO.

SMTUS R N RKS FACILITY: PALISADES 11-1 A.

7 CECO to NRC 12/28/79 LICENSEE: CONSUMERS POWER REGION / LOCATION: 5 MILES SOUTH OF SOUTH HAVEN, MI.

f Il 1 C.

7 CPCo to NRC 12/28/79 FOCKET NO.: 05000255 POWER CAPACITY: 2530(THERM AL) 0805(ELECTRICAL) 18 2 A.

5 NRC to CPCo 11/21/80 OL NUMBER: DPR-20 112 B.

G NRC to CPCo 10/01/80 i

N.S.S.S.: CE l

R-t R

04M6D9 A/E FIRM: BECH.

18-2 D.

G NRC to CPCo 10/01/80 KEY PERSONNEL SYSTEMATIC EVALUATION PROGRAM ERANCH CHIEF: W. RUSSELL OPERATING REACTORS BRANCH CHIEF: D. CRUTCH FIELD 11-3 B.

4 OPERATING REACTORS PROJECT MANAGER: T.WAMBACH ll-J B.1.

4 11-3 C.

4 KEY FOR STATUS CODES 11 4 5

NUREG/CR-1582 08/80 114 A.

5 NUREG/CR-1582 08/80 3 - OUESTION RESPONSE f

G - GENERIC RECEIVED BY NilC i

X - DELETED 4 - DRAFT SE RECEIVED 114 C.

5 NUREG/CR-1582 08/80

[

FROM REVIEW BRANCll 0 - TOPIC NOT 5 - DRAFT SE SENT TO UTILITY 1 - OUESTIONS RECEIVED FROM REV;EW BRANCH G - SE RESPONSE 11ECEIVED F

3 BY NRC 2 - OUESTIONS SENT TO IH-1 Elec) NRC to CPCo 11/12/80 7(Sys) 7 - TOPIC COMPLF TE 2

NRC to CPCo 12/15/80 til 2 5

NRC to CPCo 02/27/81 2-34

l PALISADES TOPIC NO.

STATUS REMARKS TOPIC NO.

STATUS REMARKS I

]

lil3 A.

4 11110 B.

7 NRC to CPCo 12/31/80

)

i 1113 B.

X NRC to CPCo 12/26/80 11110 C.

X NRC to CECO 11/16/79 l

lil-3 C.

O 111 11 5

NRC to CPCo 01/19/81 l

l i

1114 A.

5(AEB) NRC to CPCo 03/04/81 Ill-12 3

CPCo to NRC 10/07/80 j

3(SEB) CPCo to NRC 12/04/80 l

111-4 B.

3(MTEB) CPCo to NRC 12/04/80 IV-1 A.

7 CPCo to NRC 02/08/79 l

3(SEB) CPCo to NRC 12/04/80 I

til-4 C.

2(RSB) NRC to CPCc 12/26/80 IV-2 2

l 3(SEB) CPCo to NRC 12/04/80 l

111-4 D.

5 NRC to CPCo 01/13/81 IV-3 X

NRC to CPCo 11/16/79 l

l 1115 A.

2 NRC to CPCo 01/11/79 V1 G

NRC to CECO 11/16/79 181-5 B.

1 V-2 X

NRC to CECO 11/16/79 lil-6 5

NRC to CPCo 01/19/81 V-3 G

NRC to CECO 11/16/79 i

til-7 A.

G NRC to CPCo 11/16/79 V-4 G

NRC to CECO 11/16/79 111-7 P-3 CPCo to NRC 12/14/79 V-5 4

1117 C.

3 CPCo to NRC 12/14/79 V-6 7

NRC to CECO 03/05/80 l

l 1117 D.

3 CPCo to NRC 12/14/79 V.7 G

NRC to CPCo 11/16/79 111-8 A.

G NRC to CPCo 11/16/79 V-8 G

NRC to CPCo 11/16/79 i

til-8 B.

X V9 X

NRC to CPCo 11/16/79 i

i i

t 111-8 C.

7 CPCo to NRC 12/28/79 V-10 A.

7 NRC to CPCo 04/21/79 I

i 111-8 D.

G NRC to CPCo 11/16/79 V-10 B.

7 NRC to CPCo 11/05/80 l

i 111-9 G

NRC to CPCo 11/16/79 V-11 A.

7 NRC to CPCo 09/15/80 l

111-10 A.

7 NRC to CPCo 12/31/80 y.11 B.

7(Sys) ~ NRC to CPCo 11/05/80 7(Elec) NRC to CPCo 09/15/80 l

j 2-35

PAllSADES TOPIC NO.

STATUS HiMAHKS TOPIC NO.

STATUS HEMAHKS W

V 12 A.

X NRC to CPCo 11/16/79 VI 7 D.

G NRC to CPCo 11/16/79 V 13 G

NRC to CPCo 11/16/79 VI-7 E.

G NRC to CPCo 11/16/79 i

VI1 4

VI 7 F.

7 NRC to CPCo 12/31/80 VI-2 A.

X N!iC to CPCo 11/16/79 VI-8 G

l i

VI-2 B.

G NRC to CPCo 11/16/79 VI-9 X

NRC to CPCo 11/16/79 1

VI-2 C.

X NRC to CPCo 11/16/79 VI 10 A.

7 NRC to CPCo 11/12/80 i

l l

VI-2 D.

3 CPCo to NRC 04/02/80 VI.10 B.

X NRC to CPCo 11/16/79 r

i VI-3 2

CPCo to NRC 04/02/80 Vil-1 A.

7 NRC to CPCo 11/12/80 1

I l

V14 4(El&C)

Vll1 B.

G NRC to CPCo 11/16/79 3(MECH) CPCo to NRC 10/16/80 VI 5 2

NRC to CPCo 04/30/79 Vll-2 7

NRC to CPCo 11s'2/80 t

7E a)

NRC to CPCo 11/05/80 l

Vl4 G

NRC to CPCo 11/16/79 Vll.3 5(Elec) NHC to CPCo 01/24/81 VI 7 A.1.

X NRC to CPCo 11/16/79 Vil4 G

NRC to CPCo 11/16/79 f

I j

Vl 7 A. 2.

X NRC to CPCo 11/16/79 Val-5 G

NRC to CPCo 11/16/79 l

VI-7 A. 3.

7 NRC to CPCo 11/12/80 Vil4 G

NRC to CPCo 11/16/79

]

l VI 7 A. 4.

X NRC to CPCo 11/16/79 Vll-7 X

NRC to CPCo 11/16/79 VI 7 B.

7(Elec) NRC to CPCo 11/12/80 Vill 1 A.

G NRC to CPCo 11/16/79 0(Sys) l VI 7 C.

7 NRC to CPCo 02/20/81 Vfil 2 7

NRC to CPCo 02/27/81 1

VI 7 C.1.

7 NRC to CPCo 11/18/80 Vill-3 A.

7 NRC to CPCo 01/28/81 1,

d VI 7 C. 2.

7 NRC to CPCo 02/20/81 Vill 3 B.

7 NRC to CPCo 12/31/80 VI 7 C. 3.

X CPCo to NHC 12/12/79 Vill 4 7

NRC to CPCo 12/31/80 I

2-36

l PALISADES

(

1 i

TOPIC NO.

STATUS HEMARKS lOPIC NO.

STATUS ItEMAHKS I

t j

IX 1 2

NRC to CPCo 01/29/81 XV 10 4

I IX 2 G

NRC to CPCo 11/16/79 XV 11 X

NRC to CPCo 10/01/80 j

IX-3 3

CPCo to NRC 12/27/79 XV 12 7(Doses) NRC to CPCo 01/29/80 4(Systl l

j IX4 2

NRC to CPCo 12,/ *RO XV 13 X

NRC to CPCo 11/16/79 l

j IX 5 2

NRC to CPCo 01/29/8 XV 14 4

l l

IX-6 G

NRC to CPCo 11/16/79 XV-15 4

X 4

XV 16 7

NRC to CPCo 12/31/80 l

XI-1 G

NRC to CPCo 11/16/79 XV-17 7(Doses) NRC to CPCo 01/29/80 4(Syst)

XI 2 G

NRC to CPCo 11/16/79 XV 18 X

NRC to CPCo 10/01/80 f

X1h d G

NRC to CPCo 11/16/79 XV 19 7(Doses) NRC to CPCo 11/21/80 l

i 4(Sym

)

l l

Xill 2 G

NRC to CPCo 11/16/79 XV 20 7

?tRC to CPCo 11/21/80 XV1 4

XV-21 G

NRC to CPCo 11/16/79 s

XV2 7(Doses) NRC to CPCo 01/29/80 XV-22 G

NRC to CPCo 11/16/79

)

4 l

XV 't 4

XV 23 G

NRC to CPCo 11/16/79 XV4 4

XV-24 G

NRC to CPCo 11/16/79 XV-5 4

XVI X

NRC to CPCo 11/05/80 I

XV-6 4

XVil G

NRC to CPCo 11/16/79 l

XV7 4

l l

(

XV-8 4

XV-9 4

l 23,

AN ON0FRE F ACILITY INFORMATION TOPIC M S W US R N RKS FACILITY: SAN UNOFRE 1 b-1 A.

7 NRC to SCE 11/0709 LICENSEE: SOUTHERN CALIFORNIA EDISON 811 B-7 NRC to SCE 11/0709 REGION / LOCATION: 5 MILES SOUTH OF SAN CLEMENTE, CA.

11-1 C.

3 SCE to NRC 05/07# 9 DOCKET NO : 05000206 POWER CAPACITY: 1347(THERMAL) 0430(ELECTRICAL) 11-2 A.

6 SCE to NRC 01/26/81 OL NUMBER: DPR-13 N.S.S.S.: WEST.

112 C.

6 SCE to NRC 12/07/79 H-2 D.

G NRC to SCB 10/01/3a KEY PERSONNEL 11-3 Site Visit 07/18/78 SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL OPERATING REACTOttS BRANCH CHIEF: D. CRUTCHFIE LD 113 B.

3 Site Visit 074 8/78 OPERATING REACTORS PROJECT MANAGER: S. NOWICKI 18-3 B.1.

?

Site Visit 07/18/78 i

113 C.

3 Site Visit 07/18/78 KEY FOR STATUS CODES 11 4 5

NUREG4712 12/80 l

l 114 A-5 NUREG4712 12/80 G - GENERIC 3 - OUESTION RESPONSE RECElVED RY NRC 114 B.

5 NUREG4712 12/80 X - DELETED 4 - DRAFT SE RECElVED H4 C.

5 NUREG4712 12/80 0 - TOPIC NOT FROM REVIEW BRANCll STARTED H4 D.

0 5 - DRAFT SE SENT TO 1 - OUESTIONS RECEIVED UllLITY H4 E.

X NRC to SCE 11/16/79 FROM REVIEW BRANCil 6 - SE RESPONSE RECEIVED H

O 2 - OUESTIONS SENT TO BY NRC UTILITY 113-1 3(Sys)

SCE to NRC 08/29/79 7 - TOPIC COMPLETE O(Elec:

Ill-2 3

SCE to NRC 09/08/80 2-38

1 i

AN ON0FRE j

TOrtC NO.

STATUS HEMAHKS TOPIC NO.

STATUS REMARKS I

l

{

1113 A.

3 SCE to NRC 09/08/80 11110 B.

7 NRC to SCE 11/08/79 l

l I

111-3 B.

X NRC to SCE 11/16/79 11110 C.

X NRC to SCE 11/16/79 I

111-3 C.

0 31111 3

lil4 A.

3 SCE to NRC 08/14/79 11112 3

SCE to NRC 10/31/80 til4 B.

6 SCE to NRC 03/05/79 IV 1 A.

7 NRC to SCE 07/19/79 i

1814 C.

0(ASB) ly.2 2

NRC to SCE 12/15/80 OlSEB) 1114 D.

O IV-3 X

NRC to SCE 11/16/79 i

1 l

111-5 A.

1 V1 G

NRC to SCE 11/16/79 l

)

Ill-5 B.

2 NRC to SCE 01/04/80 V.2

  • X NRC to SCE 11/16/79 l

lil-d 3

V-3 G

NRC to SCE 11/16/79 I

^

1117 A.

X NRC to SCE 11/16/79 v4 G

NRC to SCE 11/16/79 til 7 B.

3 SCE to NRC 09/08/80 V.5 4

1117 C.

X NRC to SCE 11/16/79 V-G 7

NRC to SCE 03/05/80 111-7 D.

O V-7 G

NRC to SCE 11/16/79 i

1 111-8 A.

G NRC to SCE 11/16/79 v.8 G

NRC to SCE 11/16/79 lil-8 B.

X NRC to SCE 10/01/80 v.9 X

NRC to SCE 11/16/79 181-8 C.

7 NRC to SCE 01/29/80 v.10 A.

7 NRC to SCE 01/07/81 til 8 D.

G NRC to SCE 11/16/79 V-10 B.

6(Sys)

SCE to NRC 07/31/80

]

lil-9 G

NRC to3CE 11/16/79 v.11 A.

5 NRC to SCE 01/07/81 11110 A.

7 SCE to NRC 09/22/80 V.11 8.

6(Sys)

SCE to NRC 07/31/80 1(Elec)

Part of Vll-3 2-39

SAN ON0FRE i

}

TOPIC NO.

ST ATtJS It[MAHKS TOPIC No.

STATUS H[MAHKS I

j V 12 A.

X NRC to SCE 11/16/79 VI 7 D.

G NRC to SCE 11/16/79 V-13 G

NRC to SCE 11/16/79 VI-7 E.

G NRC to SCE 11/16/79 i

i VI1 3

SCE to NRC 08/03/79 VI-7 F.

X NRC to SCE 11/16/79 i

VI-2 A.

X NRC to SCE 11/16/79 VI-8 G

NRC to SCE 10/01/80 VI-2 B.

G NRC to SCE 11/16/79 VI-9 X

NRC to SCE 11/16/79

)

VI 2 C.

X NRC to SCE 11/16/79 VI 10 A.

O VI-2 D.

2 VI 10 B.

7(Sys)

NRC to SCE 11/15/79 i

7(Elec)

NRC to SCE 11/15/79 l

I VI-3 2

Vil-1 A.

O V14 O(Mech)

Vll-1 B.

G NRC to SCE 11/16/79 l

7(Elec) l VI-5 1

Vil-2 0

V14 G

NRC to SCE 11/16n9 Val 3 6(Sys)

SCE to NRC 07/31/80 1(Eleci VI-7 A.1.

7 NRC to SCE 02/20/81 VI:4 G

NRC to SCE 11/16/79 l

?

l f

VI 7 A. 2.

X NRC to SCB 11/1609 Vil 5 G

NRC to SCE 11/16/79 VI-7 A. 3.

O Vale G

NRC to SCE 11/16/79 VI 7 A. 4.

X NRC to SCE 11/16/79 Vil-7 X

NRC to SCE 11/16/79 VI 7 B.

3(Sys)

Vill-1 A.

G NRC to SCE 11/16/79 2(Elec)

NRC to SCE 09/16/80 VI-7 C.

O Vill-2 4

VI-7 C.1.

7 SCE to NRC 09/22/80 Vill-3 A.

7 NRC to SCE 11/07/79 I

VI-7 C. 2.

O Vill-3 B.

7 NRC to SCE 01/28/81 i

VI 7 C. 3.

X NRC to SCE 11/16/79 Vil14 4

240

l l

l SAN ON0FRE I

f TOPicNO.

ST A T tis HEMARKS TOPIC NO.

STATUS HEMARKS IX 1 3

SCE to NRC 10/05/79 XV 10 0

I i

IX-2 G

NRC to SCE 11/16/79 XV 11 X

NRC to SCE-10/01/80 j

l i

i l

IX-3 2

XV 12 0(Sys) 7(Doses) NRC to SCE 01/29/80 l

I XV 13 X

NRC to SCE 11/16/79

}

IX4 0

l

{

IX 5 0

XV-14 0

l IX-6 G

NRC to SCE 11/1699 XV 15 0

i e

X 0

XV-16 1

i XI1 G

NRC to SCE 11/1699 XV-17 O(Sys) 7(Doses) NRC to SCE 01/29/80 3

XI-2 G

NRC to SCE 11/16/79 XV-18 X

NRC to SCE 10/01/80 I

i Xill-1 G

NRC to SCE 11/1699 XV-19 O(Sysl 7(Doses) NRC to SCE 01/29/80

(

Xill 2 G

NRC to SCE 11/1609 XV-20 7

NRC to SCE 03/28/80 XV1 0

XV-21 G

NRC to SCE 11/16 # 9 XV-2 O(Sys)

XV 22 G

NRC to SCE 11/16/79 7(Doses) NRC to SCE 01/29/80 XV-3 0

XV-23 G

NRC to SCE 11/1609 l

XV4 0

XV-24 G

NRC to SCE 11/16/79 l

XV-5 0

XVI X

NRC to SCE 11/05/80 l

XV-6 0

XVil G

NRC to SCE 11/16/79 l

XV-7 0

i I

XV-8 0

l a

1 XV-9 0

241

~ - ~ - - - - - -

L ANKEE R0WE I

FACILITY INFORMATION TOPIC NO.

STATUS REMARKS

?

l FACILITY: YANKEE ROWE 1 I

11-1 A.

O LICENSEE: YANKEE ATOMIC ELECTRIC y

H-1 B.

O REGION / LOCATION: 25 MILES NORTH EAST OF PITTSFIELD, MASS.

J j

DOCKET NO.: 05000029 111 C.

O POWER CAPACITY: 600(THE RMAL) 175(ELECTRICAL) 18-2 A.

6 YAEC to NRC 02/10/81 l

OL NUMBER: DPR-3 I! 2 B.

G NRC to YAEC 10/01/80 N.S.S.S.: WEST.

?

11-2 C, 0

{

A/E FIRM: S&W i

I ll-2 D.

G NRC to YAEC 10/01/80 l

KEY PERSONNEL _

i 11-3 A.

5 NRC to YAEC 02/09/81 i

l SYSTEMATIC EVALUATION PROGRAM BRANCH CHIEF: W. RUSSELL i

1 OPERATING REACTORS BRANCH CHIEF: D. CRUTCH FIE LD 11-3 B.

5 NRC to YAEC 02/09/81 I

OPERATING REACTORS PROJECT MANAGER: R.CARUSO Il 3 B.1-5 NRC to YAEC 02/09/81 KEY FOR STATUS CODES 11 4 5

NUREG/CR 1S82 08/80 l

114 A.

5 NUREG/CR-1582 08/80 j

G - GENERIC 3 - OUESTION RESPONSE RECEIVED BY NRC I

5 NUREG/CR4582 08M X - DELETED 4 - DRAFT SE RECEIVED 114 C.

5 NUREG/CR.1582 08/80 FROM REVIEW BRANCH l

0 - TOPIC NOT l

STARTED 114 D.

3 Site Visit j

5 - DRAFT SE SENT TO UIILITY 1 - OUESTIONS RECEIVED j

FROM REVIEW BRANCH 6 - SE RESPONSE RECEIVED 114 F.

3 Site Visit j

RY NRC 2 - OUESTIONS SENT TO t

I UTILITY 7 - TOPIC COMPLETE YAEC to NRC 01/31/79 Ill Z 3

YAEC to NRC 09/06/79 2-62

l i

I YANKEE R0WE e

TOPIC NO.

STATUS REMAllKS TOPIC NO.

STATUS REMARKS l

1 111-3 A.

3 YAEC to NRC 09/06/79 111-10 B.

X NRC to YAEC 11/16/79 1113 B.

X NRC to YAEC 12/26/80 til-10 C.

X NRC to YAEC 11/16/79 l

j til 3 C.

O lil11 3

l lil4 A.

0(AEB) 11112 3

YAEC to NRC 10/31/80 i

O(SEB) l 1114 B.

0(MTEB)

IV-1 A.

7 NRC to YAEC 04/18/79 O(SEB) 1914 C.

0(ASB)

IV 2 2

NRC to YAEC 12/15/80 O(SEB) 1814 D.

O IV 3 X

NRC to YAEC 11/16/79 i'

111-5 A.

2 NRC to YAEC 01/04/80 V1 G

NRC to YAEC 11/16/79 111-5 B.

1 V-2 X

NRC to YAEC 11/16/79 3

YAEC to NRC 02/02/80 V-3 G

NRC to YAEC 11/16/79 f

I 111-6 Ul'7 A X

NRC to YAEC 11/16/79 V4 G

NRC to YAEC 11/16/79 t

Ill 7 B.

3 YAEC to NRC 09/06/79 V5 S

NRC to YAEC 01/24/80 lil-7 C.

X NRC to YAEC 11/16/19 V-6 7

NRC to YAEC 03/05/80 til 7 D.

3 NRC to YAEC 11/16/79 V-7 G

NRC to YAEC 11/16/79 111-8 A.

G NRC to YAEC 11/16/79 V8 G

NRC to YAEC 11/16/79 1118 B.

X NRC to YAEC 10/01/80 V-9 X

NRC to YAEC 11/16/79

+

111-8 C.

7 NRC to YAEC 11/15/79 V 10 A.

7 NRC to YAEC 11/05/79 I

1118 D.

G NRC to YAEC 11/16/79 V 10 B.

6 YAEC to NRC 04/13/79 l

lil 9 G

NRC to YAEC 11/16/79 V-11 A.

7 NRC to i AEC 12/08/80 l

11110 A-7 NRC to YAEC 12/08/80 V 11 B.

6(Sys)

YAEC to NRC 04/13/79 l

0(Elec)

(

i 243

l YANKEE R0WE TOPIC NO.

ST AltJS HLMAHKS TOPIC NO.

STAitJS HEMAHKS I

l V-12 A-X NRC to YAEC 11/16/79 VI 7 D.

G Nhc to YAEC 11/1609 l

l V 13 G

NRC to YAEC 11/16/)g VI 7 E.

G NRC to YAEC 11/16/79 i

l i

VI-1 3

YAEC to NRC 06/26/79 VI-7 F.

7 NRC to YAEC 12/08/80 l

l VI-2 A.

X NRC to YAEC 11/16/79 VI-8 G

NRC to YAEC 10/01/80 VI-2 B-G NRC to YAEC 11/1609 VI-9 X

NRC to YAEC 11/16/79 j

VI-2 C.

X NRC to YAEC 11/1609 VI-10 A.

O VI 2 D.

2 VI-10 B.

X NRC to YAEC 11/16/79 VI-3 2

Vil-1 A.

O V14 O(Sys)

Vil1 B.

G NRC to YAEC 11/16/79 7(Elect NRC to VAEC 12/08/80 k

VI-5 2

NRC to YAEC 05/01/79 Vil-2 o

f 1

i Vl4 G

NRC to YAEC 11/16/79 Val 3 6(Sys)

YAEC to NRC 04/13/79

't O(Elec)

VI-7 A.1.

7 NRC to YAEC 01/10/77 Vil4 G

NRC to YAEC 04/16/79 VI 7 A 2.

X NRC to YAEC 11/16/79 Vil-5 G

NRC to YAEC 04/16/79 l

VI-7 A. 3.

o Vil4 G

NRC to YAEC 04/16/79 I

VI-7 A. 4.

X NRC to YAEC 11/16/79 Vil 7 X

NRC to YAEC 11/16/79 I

VI 7 B.

2 NRC to YAEC 02/27/81 Vill 1 A.

G NRC to YAEC 04/16/79 i

1 j

VI 7 C.

o Vill-2 NRC to YAEC 02/27/80 4

I l

VI 7 C.1.

7 NRC to YAEC 12/08/80 Vill 3 A.

7 NRC to YAEC 11/07/79 1

.i' VI-7 C. 2.

O Vill 3 B.

5 NRC to YAEC 12/15/80 VI-7 C. 3.

7 NRC to YAEC 07/24/80 Vill 4 0

244 l

f

l YANKEE R0WE l

l TOPIC NO.

STAIUS HEMAHKS TOPIC NO.

STATUS HEMAHKS l

[

j IX-1 0

XV-10 o

l l

l IX'2 I

G NRC to YAEC 11/16/79

,i XV 11 X

NRC to YAEC 10/01/80 1

IX 3 XV-12 g(sys) i 2

0(Doses) l i

I IX XV 13 X

NRC to YAEC 11/16/79 0

i l

IX-5 XV-14 o

I 0

IX

)

G NRC to YAEC 04/16/79 XV 15 0

1 f

X XV-16 o

l 0

  • I'l l

G NRC to YAEC 04/16/79 XV-17 O(Sys) 0' Doses)

I'2 XV 18 X

NRC to YAEC 10/01/80 G

NRC to YAEC 11/16/79

'U~l XV 19 o gsy,)

G NRC to YAEC 1 J/16/79 O(Doses)

XV-20 5

NRC to YAEC 03/07/80 G

NRC to YAEC 11/16/79

'I XV-21 G

NRC to YAEC 11/16/79 O

t XV-2 XV-22 G

NRC to YAEC 11/16/79 0(Sys) 0(Doses) j XVJ XV-23 G

NRC to YAEC 11/16/79 0

XV4 XV 24 G

NRC to VAEC 11/16/79 0

-5 XVI X

NRC to YAEC 11J05/80 0

W -6 0

XVil G

NRC to YAEC 11/16/79 XV-7 0

XV-8 0

XV-9 0

245

m e Rw m u.s. wucLaAn asoutATony conamsaiaN

<r irr BlDLIOGRAPHIC DATA SHEET NUREG-0485 Vol. 3 No. 4 1 TITLE AND SusTITLE (Add Voswme No., #f amPrapneel

2. (te.e eleit)

Systematic Evaluation Program Status Sumary Report

3. RECIPIENT'S ACCEsslON NO.
7. AUTHOR tSI S. DATE REPORT COMPLETED M ON T H l YEAR March 1981 0 PUFORMING ORGANIZATION N AME AND MAILING ADDRESS (tectum te Codel DATE REPORT ISSUED M ON T *+

l YEAR Office of Management and Program Analysis March 1981 Office of Nuclear Reactor Regulation a ae e men,*s U.S. Nuclear Regulatory Comission t!ashington, D.C.

20555 a ae.e u-ei

12. SPONSGalNG ORGANIZATION NAME AND MAILIPJG ADDRESS (factuar to Codel 10 PROJECT / TASK / WORK UNIT NO.

Office of Management and Program Analysis Office of Nuclear Reactor Regulation u CONTRACT NO U.S. Nuclear Regulatory Commission

!!ashington, D.C.

20555

13. TYPE OF REPORT PE Rion Covt RE D (tociussve aems/

February 2,1481 thru March 1,1981

15. SUPPLEMENTARY NOTES 14 (teme un'*J
16. ABSTR ACT 000 ivoras'or iessl 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 DOCUVENT AN ALYSIS 17e DESCRIPTORS 17b IDENTIFIERS /OPEN ENDE D TERMS
18. AV AILA8tLit Y ST ATEMENT
19. SECL'RITY CLASS (Th,s reporr/

21 NO. OF P AGES Unclassifina Un1imited 2Ynclassified EC_URITY CLASS (Thes pegr/

22. P RICE s

N Or: F ORU 33517-771

.

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