ML19210C812
| ML19210C812 | |
| Person / Time | |
|---|---|
| Issue date: | 09/30/1979 |
| From: | NRC OFFICE OF MANAGEMENT AND PROGRAM ANALYSIS (MPA) |
| To: | |
| References | |
| NUREG-0485, NUREG-0485-V02-N02, NUREG-485, NUREG-485-V2-N2, NUDOCS 7911200141 | |
| Download: ML19210C812 (28) | |
Text
.
SEPTEMBER 30,1979 NUREG-0485 a
VOL. 2 NO. 2 6
REGULATORY LICENSING a
unirso states STATUS 5
!sG$ TORY
SUMMARY
N commission REPORT ca e8 m
SYSTEMKriC EVALUATION PROGRAM 7911200
^
SEPTEMBER 30,1979 NUREG-0485 m
VOL. 2 NO. 2 e
C REGULATORY LICENSING UNITED STATES STATUS
!EG$ TORY
SUMMARY
commission REPORT SYSTEMATIC EVALUATION PROGRAM
Available from GP0 Sales Program Division of Technical Information and Document Control U.S. Nuclear Regulatory Comission Washington, D.C.
20555 and National Technical Information Service Springfield, Virginia 22161 ON v1 CJ LT1 tra
TABLE OF CONTENTS t.D CD to so A
SECTION I SECTION 11 DESIGN BASIS EVENT GROUP DESCRIPTION 1-1 PALISADES 2-1 to 2-2 SEP TOPIC LIST 1-2 to 1-4 GINNA 2-3 to 2 4 DRESDEN 2 2-5 to 2-6 SEP TOPIC
SUMMARY
STATUS REPORT 1-5 OYSTER CREEK 2-7 to 2-8 MILLSTONE 1 2-9 to 2-10 HADDAM NECH 2-11 to 2-12 SAN ONOFRE 2-13 to 2-14 YANKEE ROWE 2-15 to 2-16 DRESDEN 1 2-17 to 2-18 BIG ROCK POINT 2-19 to 2-20 LACROSSE 2-21 to 2-22
950 E9El Z
O O
uJ 00
DESIGN BAS!S EVENT REVIEWS m
THIS SECTION DEFINES DESIGN BASIS EVENT (DBE) REVIEWS FOR THE ELEVEN SEP FACILITIES i tn Cm GROUP YL ACCIDENT AND T RANSIENT GROUPS:
UNCONTROLLED ROD ASSEMBLV WITHDRAWAL AT POWE R (TOPtC XV 13)
CROUP f fPWRL UNCONTROLLED ROD ASSEMBLY wtTMDRAW AL - LOW POWE R STARTUP (TOPIC ' W IJ) m DECRE ASE IN FEEDWATER TEMPERATURE (TOPtC XV 1)
CONTROL ROD MtSOPE RATION (TortC XV 4)
INCREME IN FEEDWATER FLOW (Toric XV il SPECTRUM OF ROD EJECTKEDROP ACCIDENTS (TortC XV IL 13)
INCRE ASE 6N STE AM FLOW (TOP 1C XV 1)
GROUPYH.
INADVERTENT OPENING OF STEAM GENERATOR RELitF/SAFETV V ALVE (TOPIC XV 1)
SPECTRUM OF LOSS OF COOLANT ACCIDENTS (TOPIC XV 19)
STARTUP OF INACTIVE LOOP (TortC XV g)
SYSTEM MALFUNCTION CAUSING SORON DtLUTION (TortC XV 10)
GROUP YML DROP OF CASM OR HE AVV EQUIPMENT (TOPtC XV 21) g gg DECREASE IN FEEDWATE R TEMPERATURE (topic XV 1)
INCREASP IN FEEDWATER FLOW (TOPIC XV 1)
Gh0VP I X.
ERE ASE IN STE AM FLOW (topic XV 1)
$^q"ga',"E TV ' E EF ALVE OP X 1 )
STARTUP OF INACTIVE LOOP (TOPIC XV II INADVERTENT CLOSURE OF MAIN STE AM ISOLATION V ALVE (TOPIC XV 3)
GROUPX INADVE RTENT OPE R ATION OF ECCS OR CVCS MAL FUNCTION THAT CAUSES AN INCRE ASE 6N COOLA%I INVENTORY (TOPIC XV 141 LOSS OF EXTERNAL LOAD (TOrtC XV 31 ptono(
TURBINE TRIP (TOPIC XV-3)
HYDROLOGIC DESCRIPTION ITOPIC Il 3 A)
LOSS OF CMDENSER V ACUUM (TOPIC XV 3)
FLOOrtNG POTENTIAL AND PROTECTION REOU.REMENTS (CAPAmstlTY STE AM PRESSURE REGULATOR F AILURE (TOPtC XV 3D 0,5 L^
0Pt 13 LOSS OF FE EDWATER FLOW (TOPIC XV 6)
SAFETY RELATED W ATER SUPPLY (ULTIMATE HE AT SINK) (TOPIC 16 SI)
FEEDWATER SYSTEM PlPE BRE AX (TOPeC XV4)
SEISMfC:
O N'
TECTONIC PROVINCE (TOPlc le4 Al STE AM LINE BREAK INSIDE CONTAINMENT (TortC XV 2)
STE AM LINE BREAK OUTSIDE CONTAINMENT (TOPtC XV 2)
ST A81LITY OF SLOPES (TOPIC et 4 Ol LOSSOF ACPOWER TOST % TION AUXtLIARIES(TOPICXV44 MISSILE GENE R Af TON AND PROTECTDON-LOSS OF ALL AC POWER (TOPIC XV 24)
M+NADO MIS $tLES (TOrtC IH 4 A)
TUR8tNE MISSILES (TOPIC tit 4 B)
GROUPY.
INTERNALLY GENE R ATED MIS $ ALES (TOrtC 8014 C)
LOSS OF FORCED COOLANT FLOW (TOP 6C XV 7)
X YW ES MWM AERAW WW Hi4 m PRIM ARY PUMF ROTOR SEIZURE (TOPIC XV 7)
PRIMARY PUMP SHAFT BREAK (TOPIC XV-7) w,NO AND TORN ADO LOADeNG- (TOPec HI 21 1-1
SYSTEMATIC EVALUATION PROGRAM TOPIC LIST THIS SECTION DEFINES THE SEP SAFETY AND ENVIRONMENTAL TOPICS Il SITE CHARACTERISTICS
'U 4 gy A. Tornado Menestes A. Eaciumon Area Authersty and Control B. Th MW B.
temNew C. Internally Generated Missiles
- C. Potential Harards or Changesin Potental Harards Due D. Sete Proewmty Messies (includmg Aercesft)
T toon, lastietsonal. Industriel. and Mahtery H2 Meteorotony A. Effects of Pope Break on Strucostes. Systems and e
ta lande contowwnent e A. Severs Westher Phenomena B. Pope Break Outade Con B. Onate '
_ Proilrom IHJ Catenorv i 6tructurse lnterity C. A
. _ ac Transport and Deffumon Characterietecs for Accidents Analyus A enes,, ice inspectson includmg Presteensed Concrete Con-e eth kather Grouted or Ungrouted Tendons D. Avesteheirry of -
Date in the Control Roon' B. Dessen Codes. Desegn Crescria. Load e sons, and Reactor Cavity Donsgn Crnere H3 Hydrolosiv C. Delammstmn of Pressessed Concrete Contsament Structres A. Hydrologic Description D. Contamment Structural entoyety Tests B. Flooding Potential and Protecteon Requwements e
its 8 Reortar Vesset internals fateerity Bases tsons A. Loose Ports Monetaring and Core Barrel vitwatson Momtorms C. Safetym Weter Supply (Ultsmets heet Smk (UHS))
g
,g u
C. Irrediatson Damage. Use of Senatsred Simnaess Stoes and Fatsipse Rosestance
'A. Tectams Provmes D. Core Supports and Fuelintegrrry
- 5. Proz6mery of Capable Tactonec Structres en Plant Vicamty C. Historical Sesamscety uthen 200 Miles of Plant HI-10 Pumps and Velves Interrev
,D. Statulity of Slopes A. Thermos Overload Protecimen for Motors of Motor 4perated E. Dam lntegrety Velves F. Serttement of Foundeteens arr! Burend Equipment B. Pump Flywheelintoyety lie DESIGN OP STRUCTURES COMPONENTS EQUIPMENT.
C. Survealiance Requwements on BWR Roewcuestson Pumps ANUsrsitus and Discharge Valves.l2) 115 1 Classification of Structures, Components and Systems
[SeismYancTUuWevj Hi12 Environmental Quahfication of Sofety Related Egepenent (H 2
- Wmd end Tornado Loadmes HI 3
.. _.._,, Londg ly REACTOR A. Effects of H@ Water Level on Seuctures IV 1 Thermal Hydrauhc Dessgend Performence
~~
s B. Strrctural and Other Consequences (e S. Floodma of Safety.
A. Operation with less Then AH Loops in Service Ralsted Equipenent en Basemests) of Feelure of Underdrosa C
Systems tv.2 Reacter% ontrollyste,ms factudme Functional Desean and Pr tectTon Koeinst smeT Fe7u'res g
C. Innervece Inspection of Water Connoi Structures sv.3 BWR Jet Purnos Operstme Ind cat ons g
- Reviewed as part of Deseyi Bases Event evoluetoon.
p i1 To be performed endepomdent of SEP as a Dnnsson of Operstmg Reactors generic stem.
N 1 *)
.2 Not appbcable to SEP tecihtees.
3 To be pertormed of SEP as NRR Category A technscal actnney.
L id i Completed.
OConeadoretson hems yven as deletme tapes from SEP revow.
SYSTEMATIC EVALUATION PROGRAM TOPIC LIST co tn CD tn V
RE ACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS
- 3. ECCS Actuation System 9V2 Apohcable Codleases
- 4. Core Spray Norrie iffectmeness 9V3 Overpresstereratinn Protectet 11.31
- 8. ESF Switchover frem enrection to Recwoulation Mode V4 Pipme and Safe End Inteerdy C. ECCS Sangle Feelure Creterson and Requirements for Locking V5 Reector Coolant Pressure Boundary (RCPBP Leeksee Detection Out Power oi Valves including :
of Interlocks on ECCS Va eos V6 Reactor Vesselintaanty 1.
a K Electricallastrumenteon and Control 9V7 Reactor Coolant Pume Overspeed 9VS
[ team Generator (SG)Intey2ty 81.3i
~
V9 Reactor Core isolation Coolme System (BWR)
- 3. The Effect of PWR Loop Isolation Valve Closure Dueene e LOCA on ECCS Perforinonce VN Residual Host Removal (RHR) System D. Long Term Cochng Posene Failures (e g., Flooding of Redundant Coms.onental(4)
A. RHR Host Eachanger Tube Feelures E. ECCS Sump Design and Test for Recreulation Mode B. RHR Rehabehty E ffectwenees V 11 High Pressure / Low Pressure interface F. Accumulator leolation valves Power and Control System A. Requwoments for isoletion of High and Low Pressure Systems VI 8 Control Poom Habitabshty B. RHR Interlock Requwernents VI 9 Mom Steam fiolation V 12 Reecer Water Cloenup System (BWR)
A. Mesa Stamm Line isolatson Seal System BWR A. Water Punty of Boehng Water Reactor Pnmary Coolant VI10 Selected Enemeered Safety Features (ESF) Aspects 9 V 13 Water Hammer (1.3)
A. Testme of Reactor Trip System and Engmeered Safety VI ENGINEERED SAFETY FEATURES Features including Roeponte Twne Testing
- 8. Shared E neered Safety Features. On site Energency VI 1 O_r2enec Matenals and Post Accident Chemrutry Power.
Service Systems for Multeple Unit Facahtes VI 2 Contamment Functional Deswyt A. Preneure Su
- Type SWP f.v.u Miranents 13) m Vil t Reactor Tno systems (IEEE 279)
A. Isolation of 9eactor Protection System from Non Safety 9 C. Not apphcable to the 11 fecehtsee-Systems, includeng (behficateons of Isolation Devices D Mass and Enersy Raleese for Possible Pepe Break inside
- 8. Tnp Uncertamtv and Setpoent Analysis Review of Operatmg Containment Data Base tel V8 3 contamment Pressure and Host Removal Capabihty Vil 2 Eineered Safety Features (ESF) System Control Looec and Dessen VI 4 Contemenent isoletenn System vi s Combustible G= Control Vil 3 S stems Requwed for Safe Shutdown Y
vi e Contamment Leek Tatme V '
$**g h'$'NgSan Reisted Systems on Seiected v6 7 Emereenev Co,e Coohne Sv ime y,,,
,,,,,,meo,,,,u,,,,,,,,,,,a,,,,,,,,,p,,c.,,y,n,3,,
A. Emerency Core Coohng System N -
- 1. ECCS Rewaluation to Account for increened Vessel Vil 6 Frequency _ Doc _at 11.31 Temperm 14.
Vil 7 Acceptability of SwmgBusA'2n on BWR 4 Plants "Revemed m part of Drugn Sm;s E vont evaluation.
II) To he performed indesendent of SE P as a Div.seon of Urwrateng Reactort yn. e stem.
(?) Not apphcahie to SE P f ar.hties
'4B Cnmpleted aQ
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SEP TOPIC STATUS
SUMMARY
- REPORT UNDER NOT NOT STARTED BUT INFORMATION INITIAL REVISED SEPARATE STARTED NO WRITTEN NEEDS IDENTI-ASSESSMENT ASSESSMENT COMPLETED APPLICABLE TOTAL GENERlh.
(NA)
NUMBER OF TOPICS (N)
OUTPUT FIED UNDERWAY UNDERWAY REVIEV (S)
(O)
(1)
(R)
(C)
(G) i O
C D
PALISADES 33 45 5
11 7
3 17 16 137 n
D GINNA 24 41 4
27 2
5 17 17 137 DRESDEN 2 27 30 20 4
3 1
24 28 137 OYSTER CREEK 55 14 5
15 0
3 15 30 137 MILLSTON E.1 51 12 7
14 7
1 16 29 137 HADDAM NECK 42 34 12 7
1 5
17 19 137 SAN ONOFRE 30 17 23 22 1
3 22 19 137 YANKEE ROWE 46 16 23 9
3 0
22 18 137 DRESDE N-1 32 27 22 4
2 1
20 29 137 BIG ROCK POINT 42 25 8
10 4
1 14 33 137 LA CROSSE 48 20 8
9 3
2 13 34 137 1-5
l90 E91l a
Z O
O uJ 00
PALISADES AS OF QUARTER ENDING SEPTEMBER 30,1979 FACILITY INFORMATION
SUMMARY
F ACILITY: PALISADES NEW SCHEDULE FOR SEP TOPICS HAVE BEEN ESTABLISHED TO REFLECT THE ASSIGNMENT OF DEDICATED REVIEWERS TO LONG TERM SEP ASSIGNMENTS. THE PROJECTED DATE FOR THE PALISADES REVIEW HAS BEEN CHANGED FROM LICENSEE: CONSUMFRS POWER 1/81 TO 3/81.
REGION / LOCATION:5 MILES S OF SOUTH HAVEN, Mr DOCKET NO.
05000255 POWER CAPACITY: { THERMAL) 2530, (ELEC) 0805 OL NUMBER: DPR 20 N.S.S.S.:
COMB A/E FIRM: BECH KEY PERSONNEL SYSTEMATIC EVALUATION P.M.:
J.WETMORE OPER ATING RE ACTOR B.C.:
D. ZIEMANN LIC. ASSISTANT:
H. SMITH CN t )i C
b N
2-1
SUMMARY
SCHEDULE PALISADES m
C CD Perform Any 1O Review Plant Additional Analyses C
Safety Analyses Required m
V12/9/79T Initial DBE Review Plant Review - Define Systems Assessment of Licensee Verify Management Review Systems and and Effect of 1
Functions Required Topics on Individual Plant Specifications Integrated and issue for All DBEs
[]
Systems
[]
Plant Review, Safety Assessment DBEs
/
~ V11/4/79 T
~ (j5/25/80 T
~
" V
~ V12/14/80T l 7/6/80T 8/17/80T 3/18/81T Resolve Safety j
Topics Which Effect......
g System Performance l
Resolve Safety Topics Which Have l
Indirect Effect on Complete Seismic j
System Performance Review C
l 7/6/80T I
I I
Complete Sito l
Hazards Review C
7/6/80T l
Qualitative Assessment g
of Probability of Occurrence of I
DBEs 7/6/80T 2-2
GINNA AS OF QUARTER ENDING SEPTEMBER 30,1979 FACILITY INFORMATION
SUMMARY
FACILITY: GINNA NEW SCHEDULE FOR SEP TOPICS HAVE BEEN ESTABLISHED TO REFLECT THE ASSIGNMENT OF DEDICATED REVIEWERS TO LONG TERM SEP ASSIGNMENTS.
LICENSEE: ROCHESTER GAS & ELECTRIC f/8 0 8 REGION / LOCATION:
15 MILES NE OF ROCHESTER, NY DOCKET NO.
05000244 POWER CAPACITY: (THERMAL 11520, (ELEC) 0490 OL NUMBER: DPR-18 N.S.S.S.: WEST A/E FIRM: GIL KEY PERSONNEL SYSTEMATIC EVALUAT!3N P.M.: T.WAMBACH OPERATING REACTOR B.C.:
D. 21EMANN LIC. ASSISTANT:
H. SMITH CB u.
2-3 g
Ch 4
SUMMARY
SCHEDULE GINNA u,
W CD Perform Any Review Plant Additional Analyses g
Safety Analyses Required C
V 12/9/79T e
initial DBE Review Plant Review - Define Systems Assessment of Licensee Verify Manager.,ent Review Systems and and Effect of 3
Functions Required Topics on Individual Plant Specifications Integrated and issue DBEs Plant Review Safety Assessment for All DBEs
[]
Systems
[]
/
V 11/4/79T
~ (js/25/80 T
~
~ V
~ V12/14/80T j
7/6/80T 8/17/80T 3/18/81T Resolve Safety g
Topics Which Ef f ect
_ j g
System Performance I
Resolve Safety Topics Which Have l
Indirect Effect on Complete Seismic l
System Performance Review I
l 7/6/80T l
l Complete Sito I
Hazards Review 7/6/80T I
Qualitative Assessment g
of Probability of Occurrence of l
DBEs 7/6/80T 74
DRESDEN 2 AS OF QUARTER ENDING SEPTEMBER 30,1979 8
' FACILITY INFORMATION
SUMMARY
FAC]LITY: DRESDEN 2 NEW SCHEDULES FOR THE COMPLETION OF SEP TOPICS HAVE BEEN ESTABLISHED TO REFLECT THE ASSIGNMENT OF DEDICATED REVIEWERS TO LONG TERM SEP ASSIGNMENTS. THE PROJECTED END DATE FOR THE DRESDEN 2 REVIEW HAS BEEN LICENSEE: COMMONWEALTH EDISON CHANGED FROM 01/81 TO 04/81.
REGION / LOCATION:
9 MILES E OF MORRIS, ILL DOCKET NO.
05000237 POWER CAPACITY: THERMAL) 2527, (ELEC) 794 OL NUMBER: DPR 19 N.S.S.S.:
GE A/E FIRM: S&L KEY PERSONNEL SYSTEMATIC EVALUATION PROGRAM MANAGER:
P.OCONNOR OPER ATING REACTOR B.C.:
D. ZIEMANN LIC. ASSISTANT:
H. SMITH G
w O
~
7W 25
SUMMARY
SCHEDULE G
DRESDEN UNIT 2 o
Ln C
Perform Any m
Review Plant Additional Analyses
~
Safety Analyses Required V1/9/80T Initial DBE Review PI'nt Review - Define Systems Assessment of Licensee Verify Manageme.... ;'eview Systems and and Effect of q
Functions Required Topics on Individual Plant Specifications Integrated and issue for All DBEs DBEs Plant Review Safety Assessment g
[]
Systems
[]
j (
(j6/25/80T V
~ V1/14/81T
/
V12/5/79T Resolve Safety 3 8/6/80T 9/17/80T 4/18/81T l
Topics Which Ef fect
_..... _ _ _ j g
System Performance Resolve Safety l
Topics Which Have l
Indirect Effect on Complete Seismic j
System Performance Review
=
I 8/6/80T I
I I
Complete Sito l
Hazards Review 3
8/6/80T l
Qualitative Assessment g
of Probability of Occurrence of I
DBEs 8/6/80T 2-6
OYSTER CREEK AS OF QUARTER ENDING SEPTEMBER 30,1979 FACILITY INFORMATION
SUMMARY
F'ACI LITY: OYSTER CREEK 1 NEW SCHEDULE FOT4 COMPLETION OF SEP TOPICS HAVE BEEN ESTABLISHED TO REFLECT THE ASSIGNMENT OF DEDICATED REVILWERS TO LONG TERM SEP LICENSEE: JERSEY CENTRAL POWER & LIGHT ASSIGNMENTS. THE PROJECTED END DATE FOR THE OYSTER CREEK REVIEW HAS BEEN CHANGED FROM 1/81 TO 4/81, REGION / LOCATION:
9 MILES S CF TOMS RIVER, NJ DOCKET NO.
05000219 POWER CAPACITY: (THERMAL) 1930, (ELEC) 0650 OL NUMBER: DPR 16 N.SSS i GE A/E FIRM: Bf
KEY PERSONNEL SYSTEMATIC EVALUATION P.M.:
T.WAMBAP*
OPER ATING REACTOR B.C.:
D. ZIEMANN LIC. ASSISTANT:
H. SMITH tJ C
CO 2-7
&e
SUMMARY
SCHEDULE ca OYSTER CREEK g
e C
Perform Any Review Plar.t Additional Analyses Safety Analyses Required V 1/9/80T Initial DBE Review Plant Review - Define Systems Assessment of Licensee Verify Management Review Systems and and Effect of 3
Functions Required Topics on Individual Plant Specifications Integrated andissue for All DBEs
[]
Systems
[] DBEs Plant Review Safety Assessment
/
' Ij l2/5/79T
~ (j6/25/80 T
~
~ V
~ V1/14/81T j
g /6/80T 9/17/80T 4/18/81:
8 Resolve Safety Topics Which Effect
_j g
System Performance Resolve Safety l
Topics Which Have l
Indirect Effect on Complete Seismic
]
System Performance Review I
I 8/6/80T I
I I
Complete Sito I
Hazards Review
=
8/6/80T I
Qualitative Assessment g
of Probability of Occurrence of l
DBEs 3
8/6/80T 2-8
MlLLSTONE 1 AS OF QUARTER ENDING SEPTEMBER 30, G79 FACILITY INFORMATION
SUMMARY
FACILITY: MILLSTONE 1 NEW SCHEDULES FOR COMPLETION OF SEP TOPICS HAVE BEEN ESTABLISHED TO REFLECT THE ASSIGNMENT OF DEDICATED REVIERS TO LONG TERM SEP ASSIGNMENTS. THE PROJECTED LICENSEE: NORTHEAST NUCLEAR ENERGY END DATE FOR THE MILLSTONE 1 REVIEW HAS BEEN CHANGED FROM 1/81 TO 4/81.
REGION / LOCATION:
5 MILES SW OF NEW LONDON, CONN DOCKET NO.
05000245 POWER CAPACITY: (THERMAL) 2011, (ELEC) 0600 OL NUMBER: DPR-21 N.S.S.S.:
GE A/E FIRM: EBASCO KEY PERSONNEL SYSTEMATIC EVALUATION P.M.:
J. WETMORE OPERATING REACTOR B.C.:
D. ZIEMANN LIC. ASSISTANT-H. SMITH a
u C~O 2-9 N
C~D
SUMMARY
SCHEDULE N
MILLSTONE UNIT 1 ca tn C
Perform Any A
Review Plant Additional Analyses Safety Analyses Required V1/9/80T Initial DBE Review Plant Review - Define Systems Assessment of Licensee Review Management Review Systems and and Effect of j
Functions Required Topics on Individual Plant Specifications integrated and issue for All DBEs DBEs Plant Review Safety Assessment
\\
[]
Systems
{
~
/
~ V12/5/79T g
(j6/25/80T Q
V 1/14/81T Resolve Safety g 8/6/80T 9/17/80T 4/18/81T I
Topics Which Effect
. _ j g
System Performance Resolve Safety l
Topics Which Have l
Indirect Effect on Complete Seismic l
System Performance Review
[
l 8/6/80T I
I I
Complete Sito l
Haiards Reviewr 8/6/80T I
Quelitative Assessment g
of Probability of Occurrence of l
w DBEs 3
8/6/80T 2-10
HADDAM NECK AS OF QUARTER ENDING SEPTEMBER 30,1979 FACILITY INFORMATION
SUMMARY
. F#CI LITY: HADDAM NECK NEW SACEDULJS FOR COMPLETION OF SEP TOPICS HAVE BEEN ESTABLISHED TO REFLECT THE ASSIGNMErdT OF DEDICATED REVIEWERS TO LONG TERM SEP ASSIGNMENTS. THE PROJECTED END DATE FOR THE HADDAM NECK REVIEW HAS BEEN CHANGED FROM 1/81 LICENSEE: CONNECTICUT YANKEE ATOMIC POWER TO 4/82.
REGION / LOCATION:
13 MILES E wT MERIDEN. CT DOCKET NO.
05000213 POWER CAPACITY: (THERMAL)1825. (ELEC) 0575 l
OL NUMBER: DPR 41 N.S.SA: WEST A/E FIRM: S&W KEY PERSONNEL SYSTEMATIC EVALUATION P.M.:
T. WAMBAC:1 GPERATING REACTOR B.C.:
D. ZIEMANN LIC. ASSISTANT:
H. SMITH s
Cb u;
2-11 g
N N
m No
SUMMARY
SCHEDULE HADDAM NECK in e
A Perform Any Review Plant Additional Analyses Safety Analyses Required
~ V12/7/80T Initial DBE Review Plant Review - Define Systems Systems and and Effect of J [ Assessment of Licensee Verify Management Review Functions Required Topics on Individual Plant Specifications Integrated and issue g
[]
Systems
[
DBEs Plant Review Safety Assessment for All DBEs
/
Q 10/19/80T
~ (j9/14/80T Q
V2/3/82T
~
Resolve Safety g 10/12/80T 11/23/81T 4/16/82T I
Topics Which Effect System Performance Resolve Safety l
Topics Which Have l
Indirect Effect on Complete Seismic I
System Performance Review I 10/12/81T I
I I
Complete Sito l
Hazards Review:
10/12/81T I
I Qualitative Assessment g
of Probability of Occurrence of I
=
10/12/81T 2-12
SAN ONOFRE AS OF QUARTER ENDING SEPTEMBER 30,1979 FACILITY INFORMATION
SUMMARY
FACILITY: SAN ONOFRE 1 NEW SCHEDULES FOR COMPLETION OF SEP TOPICS HAVE BEEN ESTABLISHED TO REFLECT THE ASSIGNMENT OF DEDICATED REVIEWERS TO LONG TERM SEP ASSIGNMENTS. THE LICENSEE: SOUTHERN CALIFORNIA EDISON PROJECTED END DATE FOR THE SAN ONOFRE REVIEW HAS BEEN CHANGED FROM 01/81 TO 04/82.
REGION / LOCATION:
5 MILES S OF SAN CLEMENTE, CA DOCKET NO.
05000206 POWER CAPACITY: (THERMAL 1347. (ELEC) 0430 OL NUMBER: OPR 13 N.S.S.S.: WEST A/E FIRM: BECH KEY PERSONNEL SYSTEIVATIC EVALUATION PROGRAM MANAGER:
P.W.OCONNOR OPER ATING REACTOR B.C.:
D. ZIEMANN LIC. ASSISTANT:
H. SMITH
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2-13
SUMMARY
SCHEDULE SAN ONOFRE C
6 CD Perform Any g
Review Plant Additional Analyses Safety Analyses Required 12/7/80 T Initial DBE Review Plant Review - Define Systems Assessment of Licensee Verify Management Review Systems and and Effect of q
Functions Required Topics on Individual Plant Specifications Integrated and issue DBEs Plant Review Safety Assessment for All DBEs
[]
Systems
[]
7 g
/
~
10/19/80T
~ (j 9/14/81 T
~
~V
~ Q 2/3/82T
~
j 10/12/81T 11/23/81T Egi/82T Resolve Safety i'
Topics Which Ef f ect
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System Perf orm.1ce l
Rhe SMew Topics Which Have l
Indirect Effect on Complete Seismic I
System Performance Review 110/12/81T l
l I
Complete Sito I
Hazards Review 10/12/81T I
I Qualitative Assessment g
of Probability of Occurrence of DDEs
\\
10/12/81T 2-14
YANKEE ROWE AS OF QUARTER ENDING SEPTEMBER 30,1979 FACILITY INFORMATION
SUMMARY
FACILITY: YANKEE ROWE 1 NEW SCHEDULES FOR COMPLETION OF SEP TOPICS HAVE BEEN ESTABLISHED TO REFLECT LICENSEE: YANKEE ATOMIC ELECTRIC THE ASSIGNMENT OF DEDICATED REVIEWERS TO LONG TERM SEP ASSIGNMENTS. THE PROJECTED END DATE FOR THE YANKEE ROWE REVIEW HAS BEEN CHANGED FROM 01/81 TO 04/82.
REGION / LOCATION:
25 MILES NE OF PITTSFIELD, MASS DOCKET NO.
05000029 POWER CAPACITY: (THE RMAL) 600 (ELEC) 175 OL NUMBER: DPR-3 N.S.SA: WEST A/E FIRM: S&W KEY PERSONNEL SYSTEMATIC EVALUATION PROGRAM MANAGER:
P.W. OCONNOR OPER ATING REACTOR B.C.:
D, ZIEMANN LIC, ASSISTANT:
H. SMITH Ch ui O
N 2-15 Ch
SUMMARY
SCHEDULE YANKEE ROWE n
CD Perform Any in Review Plant Additional Analyses o
Safety Analyses Required g
12/7/80 T initial DBE Review Plant Review - Define Systems Systems and and Effect of J[ Assessment of Licensee Verify Management Review Functions Required Topics on Individual Plant Specifications integrated and issue g
[]
Systems
[
for All DBEs DBEs Plant Review Safety Assessment Q10/19/80T
~ (j9/14/81T
~
Q
~ Q 2/3/82T j
Topics Which Effect
. d j
g 10/12/81T 11/23/81T 4/16/82.T Resolve Safety g
System Performance Rmin S%
l Topics Which Have l
Indirect Effect on Complete Seismic l
System Performance Review I 10/12/81T I
I I
Complete Sito I
Hazards Review 10/12/81T I
I Qualitative Assessment g
of Probability of Occurrence of l
DDEs C
10/12/81T 2-16
DRESDEN 1 AS OF QUARTER ENDING SEPTEMBE R 30,1979 FACILITY INFORMATION
SUMMARY
FACILITY: DRESDEN 1 LICENSEE: COMMONWEALTH EDISON NEW SCHEDULES FOR COMPLETION OF SEP TOPICS HAVE BEEN ESTABLISHED TO REFLECT REGION / LOCATION: 9 MILES E OF MORRIS
- Ibb THE ASSIGNMENT OF DTDICATED REVIEWERS TO LONG TERM SEP ASSIGNMENTS. THE PROJECTED END DATE FOR THE DRESDEN 1 REVIEW HAS BEEN CHANGED FROM 01/81 TO 05/82.
DOCMET NO.
05000010 POWER CAPACITY: (THERMAL) 700, (ELEC) 200 OL NUMBER: DPR-2 N.S.S.S.:
GE A/E FIRM: BECH KEY PERSONNEL SYSTEMATIC EVALUATION PROGRAM MANAGER:
P.OCONNOR OPERATING REACTOR B.C.:
D. ZIEMANN LIC, ASSISTANT:
H. SMITH
~
U Ch Ul O
N CO 2-17
SUMMARY
SCHEDULE DRESDEN UNIT 1 cr-N CD
^
Perform Any Review Plant Additional Analyses tO Safety Analyses Required W
~ V1/7/81T Initial DBE Review Plant Review - Define Systems j j ssessment of Licensee Review Management Review A
Systems and and Effect of Individual Plant Specifications Integrated and issue Functions Required Topics on for All DBEs DBEs Plant Review Safety Assessment g
[]
Systems
[]
j (
(j10/14/81T ~
~
~ V3/3/82T
/
V11/19/80T
~
11/12/81T 12/23/81T 5/16/82T Resolve Safety g
I Topics Which Effect g
System Performance Resolve Safety I
Topics Which Have l
Indirect Effect on Complete Seismic l
System Performance Review Z
l 11/12/81T I
I I
Complete Sito l
Hazards Review 11/12/81T I
I Qualitative Assessment
'~
g of Probability of Occurrence of I
=
11/12/81T
'~
2-18
BIG ROCK POINT AS OF QUARTER ENDING SEPTEMBER 30,1979 FACILITY INFORMATION
SUMMARY
FACILITY: BIG ROCK POINT 1 LICENSEE: CONSUMERS POWER NEW SCHEDULES FOR COMPLETION OF SEP TOPICS HAVE BEEN ES's ABLISHED TO REFLECT THE ASSIGNMENT OF DEDICATED REVIEWERS TO LONG TERM SEP ASSIGNMENTS. THE FACILITY: BIG ROCK POINT I PROJECTED END DATE FOR THE BIG ROCK POINT REVIEW HAS BEEN CHANGEO FROM 1/81 TO 5/82.
LICENSEE: CONSUMERS POWER REGION /LOCATICN:
4 MILES NE OF CHARLEVOIS. MICH.
DOCKET NO.
05000155 POWER CAPACITY: (THERMAL) 0?40. (ELEC) 067 OL NUMBER: DPR 4 N33.S.: GE A/E FIRM: BECH KEY PERSONNEL SYSTEMATIC EVALUATION P.M.: J.WETMORE OPERATING REACTOR B.C.:
D. ZlEMANN LIC. ASSISTANT:
H. SMITH Os v7 C
03 2-19 O
SUMMARY
SCHEDULE Cco BIG ROCK POINT in W
to Perform Any Review Plant Additional Analyses Safety Analyses Required
~ V 1/7/81T Initial DBE Review Plant Review - Define Systems Systems and and Effect of q[ Assessment of Licensee Verify Management Review Functions Required Topics on Individual Plant Specifications Integrated and issue for All DBEs
\\
[]
Systems
[] DBEs Plant Review Safety Assessment
/
V 11/19/80T
()10/14/81T V
V 3/3/82T j
Resolve Safety Topics Which Effect...
j
(
g 11/12/81T 12/23/81T 5/16/82T System Performance g
Resolve Safety l
Topics Which Have l
Indirect Effect on Complete Seismic l
System Performance Review
=
1 l 11/12/81T l
t Complete Sito I
Hazards Review C
11/12/81T I
I Qualitative Assessment g
of Probability of Occurrence of l
DBEs C
11/12/81T 2-20
0; LACROSSE AS OF QUARTER ENDING SEPTEMBER 30,1979 FACILITY INFORMATION
SUMMARY
FACILITY: LACROSSE LICENSEE: DAIRYLAND POWER p
p p
THE ASSIGNMENT OF DEDIC. ~5D REVIEWERS TO LONG TERM SEP ASSIGNMENTS. THE REGION / LOCATION: /19 MILES S OF LACROSSE. WISC PROJECTED END DATE FOR THE LACROSSE REVIEW HAS BEEN CHANGED FROM 1/81 TO 5/82.
DOCKET NO.
05000409 POWER CAPACITY: (THERMAL) 0165, (ELEC) 0050 OL NUMBER: DPR-45 N.S.S.S.:
AC A/E FlRM: S&L KEY PERSONNEL SYSTEMATIC EVALUATION P.M.: J.WETMORE OPER ATING REACTOR B.C.:
D. ZlEMANN LIC. ASSISTANT:
H. SMITH u
u:
O CO N
2-21
SUMMARY
SCHEDULE LACROSSE mco C
Perform Any n
Review Plant Additional Analyses Safety Analyses Required
~ V 1/7/81T Initial DBE Review Plant Review - Define Systems Assessment of Licensee Verify Management Review Systems and and Effect of 3
Functions Required Topics on Individual Plant Specifications Integrated and issue g
[]
Systems
[
DBEs Plant Review Safety Assessment for All DBEs
/
~ Q 11/19/80T
(
(jl0/14/81T Q
Q 3/3/82T
~
Resolve Safety 311/12/81T 12/23/81T 5/16/82T Topics Which Ef f ect _ _.
.. d g
System Performance Resolve Safety i
Topics Which Have l
Indi ect Effect on Complete Seistnic 1
System Performance Review 1 11/12/81T I
I I
Complete Sito I
Ha.rards Review {
11/12/81T I
I Qualitative Assessment g
of Probability of Occurrence of DBEs
?
11/12/81T 2-22
CO CD
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DISTRIBUTION LIST Office of the Commissioners 5
M Advisory Committee on Reactor Safeguards 24 Office of Inspector and Auditor 1
Office of Policy Evaluation 1
Office of the General Counsel 1
Office of Public Affairs 1
Office of Congressional Affairs 2
M Office of the Executive Director for Operations 5
Office of Administration 2
Office of the Executive Legal Director 1
Office of the Controller 1
M Office of International Programs 1
g Office of State Programs 1
Office of Management and Program Analysis 13 Q
Office of Standards Development 1
4 Office of Nuclear Materials Safety and Safeguards 5
Office of Nuclear Reactor Regulation 120 Office of Nuclear Regulatory Research 1
Office of Inspection and Enforcement 10 Public Document Room - H Street 1
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