ML20198C699

Summary of 860507-08 Meetings W/Util & Consultants Re Seismic Design Margin Program Activities,Schedules & Manpower Requirements.Attendance List,Viewgraphs & Supporting Documentation Encl

ML20198C699
Person / Time
Site:	Maine Yankee
Issue date:	05/19/1986
From:	Sears P Office of Nuclear Reactor Regulation
To:	Thadani A Office of Nuclear Reactor Regulation
References
NUDOCS 8605230037
Download: ML20198C699 (31)

Text

. [pp uloq

. gr - jog UNITED STATES y p, NUCLEAR REGULATORY COMMISSION g ij 'VASHINGTON, D. C. 20555 )

g May 19, 1986 l

• • • 0ccket No. 50-309 -

1 MEMORANDUM FOR: Ashok C. Thadani, Director i PWR Project Directorate #8 Division of PWR Licensing-B FROM: Patrick M. Sears, Project Manager PWR Project Directorate #8 Division of PWR Licensing-B

SUBJECT:

MEETING ON MAY 7 & 8, 1986 CONCERNING MAINE YANKEE i SEISMIC DESIGN MARGIN PROGRAM The purpose of the meeting was to discuss Seismic Design Margin Program activities, schedules and manpower requirements. Attendees are listed in Enclosure 1. ,

I After opening remarks and introductions, Maine Yankee Atomic Power Company (MYAPCo) gave a presentation covering their plant location, plant features, and layout corporate structure and working relationship with Yankee Atomic Electric Company (YAEC). YAEC most often acts as MYAPCo's architect / engineer.

Enclosure 2 covers MYAPCo's presentation.

Next, D. Guzy of NRC/Research gave a brief history of the Seismic Design Margin Program, along with an outline of the tasks to be performed during a ll seismic margins review. Mr. Guzy also presented the organization chart for the Seismic Design Margins Review program. Mr. Guzy's presentation is included in Enclosure 3.

i R. Murray of Lawrence Livermore National Laboratory (LLNL) presented a list of items required of MYAPCo for this program. Those items are to be passed on to

. LLNL's contractors (EQE, Inc. and Energy, Inc.) for use during the review i program. Those items are included in Enclosure 4. MYAPCo agreed to provide i those items if the items were on file, that is on the condition that no

/ expenditures would be required to provide those items.

A scheduie for the project to which project participants agreed was discussed. That schedule is included as Enclosure 5. Plant walkdowns and information gathering dates were tentatively set as follows:  ;

I 8605230037 B6051939 PDR ADOCK O P

, >a b

. 1.' Information gathering at YAEC--June 11 & 12, 1986.

2. First Walkdown--July 16 thru 25, 1986.

.3. Second Walkdown--November 3 thru 7, 1986.~

9

/6 Patrick M. Sears, Project Manager PWR Project Directorate #8-Division of PWR Licensing-B

Enclosures:

As stated cc: See next page DPLB:PD8 DPLB:PD8 tzer PMSears:jch 3//s S QTA

' Mr. J. B. Randazza Maine Yankee Atomic Power Company Maine Yankee Atomic Power Station cc:

Charles E. Monty, President Mr. P. L. Anderson, Project Manager Maine Yankee Atomic Power Company Yankee Atomic Electric Company 83 Edison Drive 1671 Worchester Road Augusta, Maine 04336 Framingham, Massachusetts 07101 Mr. Charles B. Brinkman Mr. G. D. Whittier Manager - Washington Nuclear Licensing Section Head Operations Maine Yankee Atomic Power Company Combustion Engineering, Inc. 83 Edison Drive 7910 Woodmont Avenue Augusta, Maine 04336 Bethesda, Maryland 20814 John A. Ritsher, Esquire Ropes & Gray 225 Franklin Street Boston, Massachusetts 02110 State Planning Officer Executive Department 189 State Street Augusta, Maine 04330 Mr. John H. Garrity, Flant Manager Maine Yankee Atomic Power Company P. O. Box 408 Wiscasset, Maine 04578 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406 First Selectman of Wiscasset

, Municipal Building U.S. Route 1 Wiscasset, Maine 04578 Mr. Cornelius F. Holden Resident Inspector c/o U.S. Nuclear Regulatory Commission P. O. Box E Wiscasset, Maine 04578

MEETING

SUMMARY

DISTRIBUTION Licensee: Maine Yankee Atomic Power Company *

• Copies also sent to those people on service (cc) list for subject plant.

Ocket Fil R

Local PDR F. Miraglia A. Thadani -

D. Jaffe OELD E. Jordan B. Grimes ACRS-10 Memo File /3.4c NRC Participants P. Sears D. Guzy N. C. Chokshi Newt Anderson i

f 4

" Enclosure 1 May 7, 1986 Maine Yankee Meeting Concerning Seismic Design Margin Program Name Title Organization NRC Participants  !

P. Sears Project Manager NRC/NRR/PD#8 D. Guzy NRC/RES N. C. Chokshi Reliability & Risk NRC/NRR/RRAB Analyst Newt Anderson NRC/NRR/EIB Other Participants Robert Budnitz President Future Resources Associates, Inc.

M. K. Ravindra Senior Associate EQE Incorporated Pete Prassinos LLNL Garth Cummings Nuclear Systems Safety LLNL LLNL Program Leader Stephen P. Schultz Mgr, Nuclear Evaluation

& Support Group Yankee Atomic Electric Peter L. Anderson MY Project Manager Yankee Atomic Electric G. D. Whittier Mgr, Nuclear Engineering and Licensing Maine Yankee Atomic Power David Moore Project Manager Energy, Inc.

Allin Cornell Consultant to MY CAC, Inc.

Bob Murray LLNL Project Leader LLNL William J. Metevia Ass't Project Manager Maine Yankee /YAEC William E. Henries Lead Mech. Engineer Yankee Atomic Robert P. Kennedy -

RPK Structual/ Mechanics Consulting l

l I

I

.c _ ~ , s.__ . ._

, Enclosure 2 .

MAIE YANKEE ATDMIC POER COPANY

,0FFSITE ORGANIZATION - -

FIGURE 12.1-2 PRESIDENT PRESIDENT MfAPCO YAEC C < c- Yr 7 y , . t. t,4-1 I l l l l VIE PRESIDENT EXECUTIVE VIT PRESIDENT VIE PRESIDENT

• VICE PRESIDENTS FINANCE & VIE PRESIDENT ADMINISTRATION NUCLEAR SERVIE S YAEC TREASURER I il * " " i / v DIVISION NUCLEAR SERVICES

,9, ya .. yr DIVISION Vfcs a r' '

MANAGER OF EERATIONS

c. Fe/7?& mIE YAPKEE --

MELEAR SERVICES MANAGER PROJECT MANAER STAFF NUCLEAR ENGIEERING s' r2 -  : "-

Ato LIENSING ,

I) . o . ? . ' .* -

l _

TERATIONAL StPPORT MNAER I 6- e ', 9

/4 9 5'-* T Ici>u NUCLEAR SAFETY  ! " e " * " #r AUDIT REVIEW MNAER CONITTEE (NSARC)** W. ## '

ADMINISTRATION {

PLANT MANAER STAFF

• OE CORPORATE OFFICER OF YNSD IS PLANT ALSO A CORPORATE OFFICER OF MYAPC, ENGIEERING APO SHALL BE REFERRED TO IN TE U- N e A 'c 1 MANAE R l SPECIFICATIONS AS " VIE PRESIDENT l (YNSD)"

QUALITY ASSURANCE -

• • NSARC EMEERS DRAWN FROM YAM <EE ATOMIC ELECTRIC CO., MIE YAtKEE MANA ER ATOMIC POWER CO., OR OTER TRAINING AFFILIATED COWANIES

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1181t s

Enclosure 3 SEISMIC DESIGN MARGINS PROGRAM O INITIATED IN 1984

- NRC WORKING GROUP ON SEISMIC DESIGN MARGINS

- EXPERT PANEL ON THE QUANTIFICATION OF SEISMIC DESIGN MARGINS

- TECHNICAL SUPPORT BY LLNL AND SUBCONTRACTORS O REVIEWED CURRENT SEISMIC INFORMATION g 0 DEVELOPED WORKING DEFINITION OF " SEISMIC MARGIN ^ BASED QN CORE MELT PROBABILITY {

E.,

0 - THE EXPERT PANEL DEVELOPED A NEW APPROACH FOR ASSESSING SEISMIC MARGINS (NUREG/CR-4334, AUGUST 1985)

SCREENING CONCEPT HCLPF 0 LLNL AND ITS SUBCONTRACTORS DEVELOPED REVIEW GUIDES i

BASED ON THIS APPROACH (NUREG/CR-4482, MARCH 1986)

O PWR REVIEW TO BEGIN S00N

0 BWR SYSTEMS STUDY TO BE COMPLETED IN 1986  ;

l O BWR REVIEW IN 1987 0 GUIDELINES WILL BE UPDATED TO REFLECT REVIEW EXPERIENCE l l

AND TO INCORPORATE NEW FRAGILITY DATA l

1 d

1

. _ _ _ _ . _ _ _ . . _ _ _ _ _ _ _ _ . _ _ _ _____...___1______

- EXPERT PANEL ON QUANTIFICATION OF SEISMIC MAR R. BUDNITZ (CHAIRMAN), FUTURE RESOURCES ASSOCIATES, INC. ~

j P. AMICO, APPLIED RISK TECHNOLOGY CORP.

A. CORNELL, STANFORD UNIVERSITY W. HALL, UNIVERSITY OF ILLINDIS R. KENNEDY, NTS/SMA J. REED, J. R. BENJAMIN & ASSOCI ATES, INC. '

M. SHIN 0ZUKA, COLUMBIA UNIVERSITY TECHNICAL SUPPORT I

i R. MURRAY (LLNL PROJECT MANAGER), LLNL k

G. ,CUMMINGS, LLNL

, ~

P..

PRASSINOS, LLNL J. SAVY, LLNL M. RAVINDRA, EQE, INC.

J. JOHNSON, NTS/SMA MEMBERS OF NRC WORKING GROUP J. RICHARDSON (C0-CHAIRMAN)

J. KNIGHT (CO-CHAIRMAN)*

N. ANDERSON (CO-CHAIRMAN)

D. GUZY (NRC PROJECT MANAGER)

• L. BERATAN C. GRIMES l

G. LEAR

• P. NIYOGI L. REITER A. THADANI' G. BAGCHI N. CHOKSHI FORMER MEMBERS

CURRENT SEISMIC INFORMATION 0 NRC SEISMIC SAFETY MARGINS PROGRAM (SSMRP)

ZION, INDIAN POINT 2, 0 7 PUBLISHED SEISMIC PRA'S:

INDIAN POINT 3, MILLSTONE 3, LIMERICK, SEABROOK, AND OCONEE 0 KNOWLEDGE OF APPROXIMATELY 6 UNPUBLISHED PRA'S 0 SEISMIC TESTING E

0 EARTHQUAKE EXPERIENCE - FOSSIL FUEL PLANTS AND '

INDUSTRIAL FACILITIES FOR EARTHQUAKES UP TO 0.5G O SEISMIC QUALIFICATION UTILITIES GROUP (SQUG) 0 OTHER RESEARCH f.

f l

G p--- - - -- -

--7 -n, - --,ww----- - - - - - e - - - - -, - - - - , - ----,

METHODS TO EVALUATE SEISMIC PLANT BEHAVIOR ABOVE SSE O DETERMINISTIC CODE MARGIN STUDIES ,

i DESIGN CODE ALLOWABLE STRESSES LESS CONSERVATIVE RESPONSE PARAMETERS AND LOAD COMBINATidNS 0 NRC SYSTEMATIC EVALUATION PROGRAM (SEP)

REEVALUATED DESIGN ADE0VACY OF OLDER PLANTS l

h*

- DETAILED WALKDOWN INSPECTIONS, DOCUMENTATION [

REVIEW I .

REANALYSIS OF STRUCTURES AND EQUIPMENT WITH LESS CONSERVATIVE CRITERIA 0 SEISMIC PROBABILISTIC RISK ASSESSMENT l

SEISMIC HAZARD CURVES .

i -

BEST-ESTIMATE RESPONSE AND FAILURE PREDICTIONS PLANT SYSTEM AND ACCIDENT ANALYSIS ESTIMATES CORE MELT AND RISK PROBABILITIES 0 NEW SEISMIC MARGINS APPROACH l -

BASED ON INSIGHTS FROM THE METHODS AB0VE PLUS NEW EARTHOUAKE EXPERIENCE AND TEST DATA PLANT SEISMIC CAPACITY ASSESSED AGAINST A SINGLE l REFERENCE EARTHOUAKE HIGH CONFIDENCE OF LOW PROBABILITY OF FAILURE SCREENING CONCEPT i

t i

l SCREENING - SYSTEMS " FILTER" 0 EXPERT PANEL RECOMMENDS TO CONSIDER ONLY THOSE PLANT FUNCTIONS IMPORTANT TO MITIGATING REACTOR CORE MELT 0 FUNCTIONS IDENTIFIED FROM PRA STUDIES

0 FOR PWRS:

- REACTOR SUB-CRITICALITY

.' ~

EARLY EMERGENCY CORE COOLING FOR RWRS:

l FUNCTIONS WILL BE IDENTIFIED BASED ON NEW RESEARCH STUDY 6

e 1

l l

l l

SCREENING - COMPONENTS " FILTER" .

0 EXPERT PANEL DEVELOPED GENERIC INFORMATION TO SCREEN OUT INHERENTLY HIGH CAPACITY COMPONENTS 0 RECOGNIZED THAT:

DESIGN CAPACITY HAS BUILT-IN CONSERVATISMS y

MANY COMPONENTS HAVE INHERENT RUGGEDNESS ,

DUE TO NON SEISMIC LOADS  !

9' '

CAPACITY DEFINITION GENERALLY BELOW

- - . CATASTROPHIC COLLAPSE i

O GENERIC INFORMATION BASED ON:

SEISMIC PRA FRAGILITY ESTIMATES f EARTHOUAKE EXPERIENCE DATA SEISMIC TESTING l l 9

HIGH CONFIDENCE OF LOW PROBABILITY OF FAILURE = "HCLPF 0 FIGURE OF MERIT FOR SEISMIC MARGINS REVIEW

' CONSERVATIVE, HCLPF CONCEPT PROVIDES A LOWER B0UND j O

ON CAPACITY (IN TERMS OF PGA) FOR WHICH IT IS J

EXTREMELY UNLIKELY THAT FAILURE WILL 0CCUR )

0 IN SEISMIC PRA CONTEXT:

i

- HCLPF CORRESPONDS ROUGHLY TO A 95% CONFIDENCE g {

i THAT THE CONDITIONAL PROBABILITY OF FAILURE WILL BE LESS THAN 5%

-MEDIAN CAPACITY AT LEAST FACTOR OF 2 GREATER l

0 HOWEVER, DETERMINISTIC METHODS CAN BE USED TO DERIVE HCLPF VALUES

- CDFM METHOD

~0 HCLPF VALUES ARE DETERMINED AT 3 LEVELS J

1. COMPONENT - LOWER BOUND CAPACITY ESTIMATE

2. SYSTEM (OR FUNCTION) l  ; 3. PLANT - LOWER BOUND CORE MELT PROBABILITY ESTIM

.___-.,._.__.._...m.y,y- ..,m ,___.y - - . - - . . - _ - - , .m ,.m , _m-,, , y--,-, , ,.. , , . . ,. , ,- , . . ,,. ,---,----,. _ - - - , . , y n,_. - . , , . - , , . , w-

1.00 1 I l l 95% 50% 5%

0.80 -

e E - ...- ,

g 1-i g 0.60 -

x ,

- Fragility Curve e

B.

,l 0.40 -

.=

"O 8

o 0.20 -

/ 0.05 '

' I I I 0.00 0.80 1.20 1.60 2.00 O.00 0.26 0.40 i Peak ground acceleration (G) .

I I

I I

BCLPF

M2thod Cons 2rvntiva Detctninistic Foilure Margin (CDFM)

Normal + Earthquake Review Level Load Combination:

844 Non-Exceedence Probability Site-Specific Ground Response Spectrum:

Spectrum Damping:

Depending on the earthquake review level, the following are the conservative estimates of the median values:

Structure: 74 Piping: 54' Cable trays: 156 Structural Model: Best-estimate - median q Soil-Structure Interaction: Envelope expected parameter variation Material Strength:

954 exceedance actual strength Static Capacity Equations: 844 exceedance by test data or code equation Conservatively selected to be between 1.0 System Ductility:

(Inelastic Energy and 1.5. For shear wall structures, should Absorption) not be less than 1.3.

Floor Spectra Generation: Median damping value for equipment Frequency shif ting of floor spectra rather than peak broadening.

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_ , _ _ ~ _ - . . __ . . _ _ _, - . - _ _ . , . _ - - - . . _ . . . - . _ _ . _ _ . - . - - . _ . _

SEISM 0 LOGICAL ASPECTS OF SEISMIC MARGINS APPROACH 0 SEISMIC HAZARD CURVES ARE NOT DEVELOPED 0 FIRST STEP IN A MARGINS REVIEW IS TO SPECIFY A REFERENCE EARTHOUAKE O USE AVERAGE OF TWO HORIZONTAL PEAK GROUND ACCELERA-TION (PGA) VALUES AS PRIMARY DESCRIPT0R OF GROUND MOTION AGAINST WHICH MARGIN IS DEFINED IN DEVELOPING THEIR APPROACH, THE EXPERT PANEL k O

FOCUSED ON NUCLEAR PLANTS IN EASTERN U.S.

DESIGNED FOR 0.1G TO 0.25G SSE SUBJECTED TO GROUND MOTION WITH FOLLOWING CHARACTERISTICS:

- EARTHQUAKE MAGNITUDE RANGE: MS.5 TO M6.5 3 TO 5 STRONG MOTION CYCLES 10 To 15 SECONDS TOTAL DURATION AND LESSER STRONG DURATION

- BROAD BAND RESPONSE SPECTRA

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Start Time axis 1

Select an earthquake review level Gather information ',..**..**:*.

. Gather information on

• • • • the plant. Determine which on systems and sort , ,. . . . .; l, ' *

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Group A functions. / broad classes or youps of

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3 components have HCLPF

. : . JJ.*/< / values greater than the review

• • • • • • • • A level. Possibly identify plant-unique features.

' 1 First plant walkdown:

Concentrate on identification of problems.

1 4.* Emphasize systems interaction. Confirm (.

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applicability of screening tools. Complete i

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• identification of plant-unique features.

o Revision of systems )

KEY: Task is performed by: , ' .* * * *. 'i* ***  ; ,';l;*i,*

.. relationships established 7***

Systems Analyst ..,,.*. *, *

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in t, Step 2. Develop fsuit

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• .,' .* . ; ;,' *, .,* trees and event trees.

Fragility Analyst o

Both Second plant walkdown:

Primarily fragility analyst for checks.

6 Collect specific data (sire and other

, physicalcharacteristics) of components requiring detailed analysis.

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Determine minimal .. . I 5 ** *. * .**;* '.**.: *.

• ** Finalize HCLPF value for cut sets for end-

• /,..;*,7.,.l.* *"'"'"" "*' ""

• 8 (components not screened out).

point core melt.

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o Margin assessment complete SEISMIC MARGINS REVIEW

NRC SEISMIC DESIGN I MAINEYANKEETRfdLSEISMICMARGINSREVIEW i DRAFT ORGANIZATION CHART MARGINS WORKING GROUP APRIL 1986 J. Richardson, Cochefrman

! N. Anderson, Cochairman (Review program deliverables) i EXPERT PANEL ON QUANTIFICATION OF

, SEISMIC MARGINS ,

MAINE YANKEE NRC/NRR PROGRAM NRC/RES PROGRAM

) ATOMIC POWER CD. MANAGER _,

MANAGER R..Budnitz, Chairman (Review and critique only

G'. D. Whittier P. Sears D. Guzy the review Procedures)

I

! I ttyt YANKEE. ATOMIC PEER REVIEW GROUP f TEAM LEADER -- - - - t i

R. Budnitz I R. Murray L.W911e l

J. Reed l

' . M. Bohn J. Thomas

! FRAGILITY ANALYSIS TEAM SYSTEMS ANALYSIS TEAM R. Murray, LLNL Liaison

! P. Prassinos - LLNL Liaison (Review and critique all EQE program deliverables) -

l ENERGY INC.

J. Young, El Leader M.K. Ravindra EQE Leader D. Moore /

l /

M.-Quilici l Structural Equipment Earthquake

! Fragility Fragility Experience I P. Hashimoto G. Hardy S. Swan l N /

I 4. Kincaid S. Eder s .

Enclosure 4 The following assistance will be needed from Maine Yankee Atomic Power Company:

1. Identify a key contact and an alternate.

Supply name, address, and phone number of utility contact person and an alternate to the LLNL project manager.

2. Participate with the Expert Panel, Peer Review Team and Analyst Team in conducting the review ,

Attend meetings as scheduled by mutual agreement, and provide input to the schedule.

Be available for interaction throughout the project and serve as liaison with the utility staff and contracters.

l 3. Supply information requested to carry out the review.

2 Plant-specific information and data must be readily available for the plant under review. This information includes, for example, the Safety Analysis Report (SAR), system descriptions, plant configuration diagrams, piping and instrument diagrams (P& ids),

operating procedures, and any other supporting documentation that gives details of the configuration, actuation, operation and control of the safety systems, and their supporting systems at the plant.

This information will be required by both the Systems and Fragility

, Analysis Teams conducting the review.

4. Organize two plant walkdowns.

Provide acceptable date, clearance and guides to carry out first and second plant walkdowns.

5. Review the draft report summarizing the seismic margin review.

l Provide comments for inclusion in project report.

l 1

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INITIAL LIST OF SYSTEMS TO BE EXAMINED AND INFORMATION REQUIREMENTS -

Frontline Systems /Comoonents

1. High pressure safety injection and charging systems

2. Low pressure safety injection system

3. Accumulator system

4. Auxiliary feedwater system

5. Containment spray system

6. Boron injection systems

7. Instrument or control air system

8. PORVs and primary S/RVs

9. Steam generator atmospheric dump valves, relief valves, and safety valves 9

10. Reactor protection system (SCRAM)

Support Systems

1. AC power system (including diesel generators)

2. DC' power system i

3. Component cooling water system I i

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OB 1 of 3

14 Service water system

5. Actuation systems (Scram, SIAS, containment isolation actuation system, station blackout)

TyoicalInformation Required -

1. For Fluid Systems (Frontline and Support Systems):

a. Current system configuration, including:

pumps / fans in standby or normally operating test and surveillance intervals, maintenance intervals and duration for components valve / damper position (normal, power failure, and on actuation signals)

- Interlocks or permissives on valve or pump actuation, and isolation or trip signals <

- setpoints .

- indications or alarms in control room Indicating component / system failure or unavailability NPSH curves

b. Fluid system dependencies on support systems, including:

- component AC and DC power supplies pump cooling (seal, lube oil, motor, room) actuation signals to components

- instrument or control air supplies

c. Cross connects with other train (s), and with other systems (e.g., firewater) g d. Alternate power sources (NOTE: Generally this type of information is included in the FSAR and training manual system descriptions, P&lDs, and Technical Specifications.)

2. For electric power system: ,

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one line diagrams room cooling requirements and support systems

- load sequencer logic cross ties and lock outs

- diesel generator support systems (cooling, starting)

- test, surveillance and maintenance intervals and duration 1 OB 2 of 3

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3. Logic for Actuation Systems

4. Load lists for support systems (Electric power, Actuation, Component cooling water, Service water, Control air)

5. Location of systems / components

- plan elevation and layout drawings

- section and general arrangement drawings

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INITIAL LIST OF POTENTIALLY IMPORTANT OPERATOR PROCEDURES AND RECOVERY ACTIONS Emergency Procedures and Actions

1. Feed and bleed .

2. Secondary blowdown with RCS depressurization and low pressure injection

3. Turning off containment spray to reduce RWST consumption

4. Manual SCRAM and emergency boration during ATWS conditions

5. Feedwater recovery actions restart turbine driven AFW locally connect SWS to AFW suction connect firewater system to AFW

6. Component cooling water system cross connects

7. Service water system cross connects

8. Loss of power recovery actions 3

battery load shedding recovery of diesel generators manual operation of AFW (including room cooling) long term CST refill or firewater connection

9. Recovery of room cooling for ESFs i

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TypicalInformation Required

1. Written emergency procedures

2. Alarms, annunciators, displays and instrumentation

3. Timing considerations time action required time to perform action time of alarm / signal

4. Overall control room organization, manning, and responsibilities Test, Surveillance, Maintenance Procedures

1. Requirements for staggered test, calibration, surveillance, maintenance procedures, and independent verification

2. Maintenance policy with respect to unscheduled maintenance (comprehensive maintenance versus quick fix)

3. Administrative tagging procedure 1

i OC 2 of 2

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l SEISMIC MARGINS PROGRAM l TRIAL PLANT REVIEW .

)

INFORMATION NEEDS FOR FRAGILITY ANALYSIS l

s Review Earthquake Level l

- Peak Ground Acceleration

- Seismic Hazard Analysis Results (LLNL) 1 Ground Motion Spectrum Magnitude, Duration a FSAR Chapters 2 and if in Standard Format (i.e., Site Characteristics and Structural Design Criteria) e Safety Evaluation Report a Plant General Arrangement Drawings showing locations of Structures and Equipment a List of Structural Drawings including Tank Drawings a List of Piping and Instrument Diagrams for Safety Related Systems s List of Line Diagrams for Electrical Equipment a

hah List of Aditectural Drawings e Safety-related Equipment List (Mechanical and Electrical)

5. mvh List of Stengg An=19 a is(a' d Equipment Qualification Reports a Structural Project Design Criteria e Summaries of Material Test Data (i.e., concrete cylinder, steel yield strength, expansion anchors, etc.)

nb-86-120/tripintl.rpt 1

e Structural Models used in Seismic Response Analyses; Results of Analyses ,

a List of Design Calculation Packages e Isometeric View of the Plant a Contact Persons in CE and S & W 4

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d nb-86-120/tripintl.rpt 2

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Enclosure 5 '

$0ttuLt Fat falAL tusif attttif '

!' 3 4 5 8 7 8 9 l%o n A 5 S 1 2 ,

1. envelop detalled wert scope schedule  ?

and cost treetesus.

2. Sevelop review precedeces (seat te latc. 9

' tapert Panel, and Peer Revle ereap)

3. Develop usestandue of onderstanding with T ettllty (seat to IRC and ettlity) 4 Collect Informetlen E I S. First plant weitessa, pre e lkesun .

states summary (seat to NRC and peer I l

' Review Group)

Peer Review Itseting _&

6

7. Waltessa l Systems analysis

' 8.

g. letLPF calculattens

10. Secead plant saltdesa. pre-waltdemn status sumanary (seat to letC and Peer I Review Group)

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11. Peer Review Meeting

12. Weltdown 9

13. Report writing &

f Receive Sutcentracter reports

e I (distritete to IRC and peer

Review Group) i 14 Ovality asserence Start Time. Month 0. begins ahea subcontracts are la place.

RE7:  ? = Dellverable

!. & = Milestone f = Activity I

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