ML17054B085

Summary of 840925 Meeting W/Util,S&W & GE in Bethesda,Md Re Equipment Qualification.Handouts Encl

ML17054B085
Person / Time
Site:	Nine Mile Point
Issue date:	10/02/1984
From:	Haughey M Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8410160288
Download: ML17054B085 (74)

Text

iy, Docket No. 50-410 QcT 02 %R APPLICANT:

FACILITY:

SUBJECT:

Niagara Mohawk Power Corporation (NMPC)

Nine Mile Point Unit 2 (NMP2)

SUMMARY

OF MEETING WITH NMPC CONCERNING EQUIPMENT QUALIFICATION FOR NINE MILE POINT UNIT 2 On September 25, 1984 the NRC staff met with representatives from NMPC, Stone and Webster Engineering Corporation (SWEC),

and General Electric (GE) to discuss equipment qualification for Nine Mile Point Unit 2.

The equipment qualification master list and the Equipment Qualification Data Report are scheduled to be submitted in December 1984.

Approximately 705 of the BOP qualification paperwork and 80-90K of the NSSS qualification paperwork was complete at the time of the meeting.

The installation level of equipment was not known.

The NRC stated that installation levels should be included in the information to be submitted in December.

The master list to be submitted in December will include instrumentation under Regulatory Guide 1.97.

The NRC staff requested that the methodology used to determine the completeness of the Equipment Qualification list be provided in detail in the December submittal.

In addition the correlation to Table 3.2.1 in the FSAR should be included.

Seismic margins for NSSS equipment are at least 10K.

Seismic margins for BOP equipment are generally lOX but this is not a design requirement.

SWEC will review seismic design margins for equipment to assure any margins less than 10%

are justified.

Plant Specific profiles will be used for inside containment (included in FSAR).

NMPC does not intend, at this time, to request exemption for any equipment required to be qualified under 10CFR 50.49.

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The NRC staff stated the maintenance and surveillance program should be included in the environmental submittal.

Also I 5 E notices and bulletins that pertain to equipment qualification and the applicant's evaluation of these. documents should be included and retrievable in the applicant's file.

This will be verified as part of the equipment qualification audits.

NMPC was requested to submit sample qualification packages for SgRT (Seismic gualification Review Team) and PVORT (Pump and Valve Operability Review Team) to be reviewed by NRC consultants.

NRC staff stated that equipment to be identified for audit will be identified subsequent to scheduling an audit, approximately 6 weeks prior to the audit.

Typically 25 pieces are reviewed as part of the SgRT and 10 pieces as part of the PVORT.

NMPC gave a presentation on the equipment qualification program for Nine Mile Point 2.

Enclosure I includes a copy of the information presented during that presentation.

Enclosure 2 is a copy of a handout on "Equipment gualification for Hydrodynamic Loads" provided during the meeting.

A list of meeting attendees is included as Enclosure 3.

Enclosures:

As stated cc:

All NRC meeting attendees LB¹2/D P

LB¹ DL/BC MHaughey/lb ASchwencer 10// /84 10/( /84

~CioGI 8Kgagg by)

Mary F. Haughey, Project Manager Licensing Branch No.

2 Division of Licensing Distribution:

Doc et i

e.'RC PDR Local PDR PRC System NSIC LB¹2 Reading EHylton MHaughey Bordenick ACRS (16)

EJordan NGrace

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Nine Mile Point 2

Mr. B. G. Hooten Executive Director, Nuclear Operations Niagara Mohawk Power Corporation 300 Erie Boulevard West

Syracuse, New York 13202 CC:

Mr. Troy B. Conner, Jr.,

Esq.

Conner 8 Wetterhahn Suite 1050 1747 Pennsylvania

Avenue, N.W.

Washington, D.C.

20006 Richard Goldsmith Syracuse University College of Law E. I. White Hall Campus

Syracuse, New York 12223 Ezra I. Bialik Assistant Attorney General Environmental Protection Bureau New York State Department of Law 2 World Trade Center New York, New York 10047 Resident Inspector Nine Mile Point Nuclear Power Station P. 0.

Box 99

Lycoming, New York 13093 Mr. John W. Keib, Esq.

Niagara Mohawk Power Corporation 300 Erie Boulevard West

Syracuse, New York 13202 Jay M. Gutier rez, Esq.

U. S. Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, Pennsylvania 19406 Norman Rademacher, Licensing Niagara Mohawk Power Corporation 300 Erie Boulevard West

Syracuse, New York 13202

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AGENDA NINE NILE POINT UNIT 2 EQUIPMENT QUALIFICATION PROGRAt". PRESENTATION DATE:

SEPTEMBER 25, 1984 TIME:

1:00 4:00 P,M, LOCATION:. 'NRC OFFICES'ETHESDA,. MD, I:NT;RODUCTI.ON PROGRAM OVERVIEW ENVIRONMENTAL CONDITIONS ENVIRONMENTAL QUALIFICATION METHODOLOGY MILD'NVIRONMENT HARSH ENVIRONMENT BOP + NSSS ELECTR ICAL MECHANICAL SE I SM IC/DYNAMI C CONDITIONS SEISMIC QUALIFICATION METHODOLOGY PUMP AND VALVE OPERABILITY ASSURANCE QUAL IF I CATION DOCUMENTATION QUESTION AND ANSNER SESSION

I 1

4

GENERAL DESCRIPTION FOR NINE MILE POINT UNIT 2 (NMP2) o BWR/5 MARK I I CONTAINMENT DESIGN (3323 MN')

o NSSS AND. TURBINE-GENERATOR SUPPLIER GENERAL ELECTRIC CO, k

o BOP IS DESIGNED AND, CONSTRUCTED BY A/E STONE AND WEBSTER -

o

.LOCATED 33 MILES. NNW OF

SYRACUSE, NEW YORK 1

o UTILIZES LAKE ONTARIO FOR ITS MAJOR WATER REQUIREMENTS

NMP2 MILESTONES CP ISSUANCE FSAR DOCKETED (SRP NUREG.-75/087)

SER ISSUANCE FSAR

. UPDATE.

FULI ACRS MEETING JUNE 1974 APRIL 1983 DECEMBER 1984 (S)

DECEMBER 1984 JANUARY 1985 (S)

EQ/SQRT/PVORT AUDITS EQB SER SUPPLEMENT MAY 1985 OCTOBER 1985 FUEL LOAD

~ COMMERCIAL OPERATION FEBRUARY 1986 (S)

OCTOBER 1986 (S)

(S)

SCHEDULED

~ ~

a IV NMP2 COMMITMENTS IEEE STANDARD 323-1970 "QUALIFYING'LASS 1E EQUIPMENT FOR NuCLEAR POWER GENERATING STATIONS"

~ NUREG-0588 CATEGORY II PLANT 4

,"INTERIM STAFF POS ITI'ON'N.

ENVI'RONMENTAL'UALIFICATION OF SAFETY RELATED ELECTRICAL EQUIPMENT" IEEE STANDARD*30/4-1975 "SEISMIC QUALIFICATION'F'LASS 1E Eau I PMENT FOR NUCL'EAR POWER GENERATING STATIONS" 10CFR 50,09 FSAR QUES F 270.,3 MECHANICAL EQUIPMENT

J a

BASES FOR ENVIRONMENTAL CONDITIONS NORMALrABNORMAL> ACCIDENT CRITERIA TEMPERATURE.'RESSURE, HUMIDITY REG GUIDE 1;.Q6 MEB 3 1

APCSB 3 - 1 LOOP CHEMICAL ENVIRONMENT NO CHEMICAL., ADDITIVES SUBMERGENCE AND SPRAYS-RADIATION NUREG 0016 NUREG 0588 RECIRCULATING LOCA FLUIDS SOURCE TERMS REG GU IDE 1, 89 +

NUREG 0737

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RADIATION ENVIRONMENT DEFINITIONS FOR EQUIPMENT QUALIFICATION'RITERIA RADIATION SOURCES.

METHODOLOGY-

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RADIATION SOURCES NORMAL o.,: DESIGN BASIS, FAILED FUEL-SOURCES.

=,

ACC IDENT/POST-ACC IDENT GOVERNED BY LOCA SOURCES CASE-SPECIFIC ACCIDENT SCENARIOS HIGH ENERGY LINE BREAK CONTROL ROD DROP ACCIDENT FUEL-HANDLING ACCIDENT ANTICIPATED TRANSIENT WITHOUT SCRAM

NETHODOLOGY SOURCE DISTRIBUTION o'NSTANTANEOUS NIXING BETWEEN DRYWELL AND WETWELL o TINE-DEPENDENT TRANSPORT NODELS ARE. USED. TO

'DISTRIBUTE ACTIVITY TO STRUCTURES OUTSIDE" THE CONTANIMENT o

EFFECT OF=- VENTILATION PRIMARY AND SECONDARY CONTAINMENT NO EXHAUSE VENTILATION OTHER BUILDINGS NAXIMUM EXHAUST VENTILATION FROM CONTAINMENT

METHODOLOGY (CONTD)

TREATMENT OF'Al.OGENS DRYNELL/NETMELL (PRIMARY CONTAINMENT)

GAMMA - DOSE IS CALCULATED AS THE LARGER OF EITHER AN AIRBORNE OR PLATEOUT'OURCE IN ADDITION TO'HE DOSES FROM THE SUPPRESSION POOL AND RECIRCULATING REACTOR COOLANT BETA - DOSE IS CALCULATED ASSUMING THAT'HE 50 PERCENT OF THE; CORE INVENTORY THAT IS INITIALLYAIRBORNE IS PLATED OUT HALOGENS'ECONTAMINATION FACTOR OF 10 IS APPLIED FOR SUPPRESSION POOL SCRUBBING EFFECTS

METHODOLOGY (CONTD)

DOSE CALCULATION MODELS GAMMA AIRBORNE PRIMARY CONT'AINMENT -,CYLINDRICAL.MODEL. (GAD MOD COMPUTER CODE)

SECONDARY CONTAINMENT FINITE HEMISPHERE MODEL BASED ON EQUIVALENT BUILDING VOLUME F r,

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GAMMA WATERBORNE ACTUAL PIPING CONFIGURATIONS ARE MODELED IN PRIMARY CONTAINMENT A CONSERVATIVE MODEL HAS B'EEN USED IN THE SECONDARY CONTAINMENT BETA AIRBORNE SEMI -INFINITE CLOUD MODEL PLATEOUT' INFINITE PLANAR SOURCE MODEL

ACCIDENT/POST-ACCIDENT SOURCE TERMS PRIMARY CONTAINMENT ATMOSPHERE,.

INSTANTANEOUS RELEASE 100 PERCENT CORE NOBLE GASES O'-'50 PERCENT CORE HALOGENS SUPPRESS ION POOL/RECIRCULATING REACTOR COOLANT, INSTANTANEOUS RELEASE 50 PERCENT CORE HALOGENS O

1 PERCENT'ORE CE'S I VMS

'EQUIRED'0 PERCENT CORE CESIUMS GOAL 1 PERCENT REMAINING FISSION PRODUCTS

ENVIRONMENTAL. QUALIFICATION 'MILD ENVIRONMENT A MILD ENVIRONMENT IS LOCATED OUTSIDE OF PRIMARY AND SECONDARY CONTAINMENT AND IS NOT. SUBJECT TO ACCIDENT ENVIRONMENTS DUE TO A LOCA OR PIPE BREAKS A MILD ENVIRONMENT IS AN ENVIRONMENT THAT WOULD AT

. NO'IME BE SIGNIFICANTLY MORE SEVERE THAN THE ENVIRONMENT THAT, WOULD OCCUR DURING NORMAL PLANT.

f+

. OPERATION>

INCLUDING ANTICIPATED OPERATIONAL OCCURRENCES

'O COMMON MODE ENVIRONMENTAL CHANGES DUE TO ACCIDENT

ENVIRONMENTAL QUALIFICATION MILD ENVIRONMENT SERVICE CONDITIONS AND SAFETY FUNCTION MUST BE SPECIFIED AND ENVELOPED BY DESIGN MANUFACTURER. MUST CERTIFY. EQUIPMENT) AGAINST.

SPEC I F I'CATION

I BOP HARSH ELECTRICAL EQ PROGRAM DEFINITION:

ALL PLANT AREAS NOT DEFINED AS MILD ENVIRONMENT AREAS A,

10 CFR 50,49 REQUIREMENTS O SAFETY-RELATED ELECTRICAL EQUIPMENT CLASS 1E NONSAFETY-RELATED ELECTRICAL EQUIPMENT WHOSE

--..FAI,LURE COULD PREVENT'HE FUNCTION OF SAFETY;,.

RELATED ELECTRICAL EQUIPMENT ASSOCIATED

. EQUIPMENT',G, 1,75 o

POST-ACCIDENT.

MONITORING EQUIPMENT " R,G, 1.97 B,

NUREG 0588 (CATEGORY I-I GUIDELINES)

C, 10 CFR 21 D,

PROCUREMENT SPECIFICATION IEEE 525. 1974 (Seer)

4 \\

E, VENDOR DOCUMENTS 1,

TEST PLANS 2,

TEST REPORTS r'.

CHECKLIST

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F, SWEC DOCUMENTATION 2,.

SUPPLIER DOCUMENT DATA FORM (SDDF) 3, SYSTEM COMPONENT EVALUATION WORK (SCEW)

SHEETS

I I QUALIFICATION METHODS A.

TYPE TESTING IDENTICAL EQUIPMENT B.,

TYPE TESTING SIMILAR EQUIPMENT 1.

ADDITIONAL=ANALYSI S REQU IRED C,

EXPERIENCE; WITH IDENTICAL OR SIMILAR EQUIPMENT

""(INDUST:RY DATA).-.

1.

SIMILAR CONDITIONS OF SERVICE 2,

ADDITIONALANALYSIS MAY BE REQUIRED D,

ANALYSIS OF IDENTICAL OR SIMILAR EQUIPMENT SUPPORTED BY TYPE TEST DATA

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III METHODOLOGY A.

AGING 1,

ARRHENIUS METHODOLOGY 2.

OTHER METHODS IF ADEQUATELY JUSTIFIED 3,

PRIOR TO SEISMIC AND/OR DBA EVENT 4.

SYNERGYSTIC EFFECTS (NHERE IDENTIFIED) 5.

MAINTENANCE AND/OR REPLACEMENT SCHEDULES B:."

TEST SEQUENCE '(IF TYPE TEST

'USED)'PECIFIED SEQUENCE 1,

IEEE 323-74 -'AME UNIT 2,

ALTERNATE IF JUSTIFIED C..

MARGIN 1,

DIFFERENCE BETMEEN MOST SEVERE SPECIFIED SERVI.CE CONDITIONS AND CONDITIONS.. IN. TYPE TESTING 2,

MINIMUM 1 HOUR QUALIFICATION TEST TIME

D.

RADIATION 1.

GAMMA RADIATION 2,

BETA RAD IAT,I.ON NEUTRON RADIATION LOCATION SPECIFIC CALCULATIONS (IF REQUIRED)

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I NSSS HARSH ELECTRICAL EQ PROGRAM A,

IEEE-323-1974 B.

ANSI N45,2 C,

IEEE-344-1975 D.

NUREG 0588 E.

NEDE- - 24326-1-P II QUALIFICATION METHODS A,

TESTING IS PREFERRED B.

OTHER APPLICABLE APPROACHES 1,

PARTIAL TEST WITH ANALYSIS

.2, OPERATING-EXPERIENCE 3,

ANALYSIS

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ENVIRONMENTAL QVALIFICATION OF NECHANICAL FQUIPKNT IN HARSH ENVIRONMENTS I.

NSSS

+ BOP PROGfVN A.

FSAR QUESTION 270,3 B.

THE NECHANICAL EQUIPMENT QUALIFICATION PROGRAM ESTABLISHES THE QUALIFIED LIFE OF SAFETY RELATED NONMETALLIC COMPONENTS I I.

QUALIFICATION METHODS A.

DEVELOP ENVIRONMENTAL CONDITIONS B.

IDENTIFICATION OF SAFETY RElATED f.ECHANICAL EQUIPMENT C.

IDENTIFICATION OF ORGANIC MATERIALS D.

DEVELOPMENT OF COMPONENT.THERMAL SERVICE LIFE E.

DEVELOPMENT OF COMPONENT RADIATION SERVICE LIFE F.

REV IEM MECHANICAL ENVIRONMENTAL CONDITIONS VERSUS CAPABILITY G,

DOCUMENT REVIEW

I

. Irr 'DOCUMENTATION l.

QUALIFiCATION REPORT

SUMMARY

2, SUBCOMPONENT DATA SHEETS ENGINEERING ANALYSIS SHEETS RADIATION RESISTANCE'F, MATERIALS 5.

THERMAL AGING ANALYSIS

I 4

0 I.

SE ISMI C/DYNAMIC QUALIFICATION PROGRAM.

A, CRITERIA 1,

NUREG-0800 REVISION 2

. 2, NUREG-0484'EVISION 1 (LOAD COMBINATION) 3.

REGULATORY GUIDES 1.29 (CLASSIFICATION OF SEISMIC CATEGORY I STRUCTURES'YSTEMS AND COMPONENTS) 1.48 (CRITERIA FOR ASME COMPONENTS) 1,60 (DEVELOPMENT OF GROUND RESPONSE SPECTRA) 1,61 (DAMPING) 1,92 (SPATIAL AND MODAL RESPONSE COMBINATION) 1.100 (SEISMIC QUALIFICATION OF CLASS 1E EQU IPMENT) 1,122 (MODIFtCATION OF

RESPONSE

SPECTRA)i 1 148 (RBCT SPEC FOR ACTIVE VALVES )

4, IEEE 344-1975 5.

ASME CODEX'ECTION III (PRESSURE BOUNDARY) 6, ADD.ITIONAL REQUIREMENTS FOR HYDRODYNAMIC LOADS (NRC LETTER)

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B.

SCOPE 1,

SAFETY-RELATED MECHANICAL EQUIPMENT PUMPS (ACTIVE'ONACTIVE)

VALVES (ACTIVE'ONACTIVE)

OTHER MECHANICAL EQUIPMENT (I,E,i CRANES'VACi ETC,)

2, ELECTRICAL EQUIPMENT AND INSTRUMENTATION SW ITCHGEAR MOTOR CONTROL'ENTERS'TANDBY BATTERIES AND BATTERY CHARGERS STANDBY DIESEL GENERATOR SYSTEM MISCELLANEOUS CONTROL AND RELAY BOARDS INSTRUMENTATION (I,E,>

TRANSMITTERS.

SWITCHES>

RTD'S, ETC,)

(

II, QUALIFICATION METHODS A.

ANALYSIS 1.

STATIC ANALYSIS'- RIGID AND FLEXIBLE (EQUIVALENT STATIC) EQUIPMENT 2..

DYNAMIC ANALYSIS MODAL ANALYSIS'IME HISTORY 3.

STRESS CYCLES'UMULATIVE USAGE FACTOR I

1 4,

SUPPLEMENTAL ANALYSIS FOR EQUIPMENT PREVIOUSLY: -

QUALIFIED'OR SEISMIC'OADS ONLY B.

TESTING 1,

MULTIFREQUENCY.. MULTIAXIS 2,

SINGLE FREQUENCY'- SINGLE AXIS WHERE -JUSTIFIED (REG 1,100) 3, VIBRATION AGING OBE, HYDRODYNAMIC MARGIN - GENERALLY 10K C,

COMB I NED ANALYSI.S/TESTING SIMILARITYANALYSIS

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QUALIFICATION METHODOLOGY A

EXAMPLE LIST'QUIPMENT.

POLAR CRANE VALVES PUMPS HVAC (MISCELLANEOUS' FIRE DAMPER

. '"-;.'.HIGH DENS.ITY FUEL. RACKS,.

", HEAT EXCHANGERS-TANKS HYDROGEN RECOMBINER I 8 C DEVICES ELECTRICAL PENETRATIONS MOTORS'(MISCELLANEOUS)

MOTOR CONTROL CENTERS'M ITCHGEAR BATTERIES AND RACKS BATTERY CHARGERS TRANSFORMERS (MISC. )

DUCT HEATERS DIESEL GENERATOR SYSTEMS ANALYSIS X

X X

X X

X X

TEST X

X X

X X

X X

X X

X X

'NINTERRUPTIBLE PONER-SUPPLY PANELS'AND RACKS: (MISC. ) '

B, EQUIPMENT SUPPORT INTERACTION INTERMEDIATE SUPPORT STRUCTURE IS DESIGNED TO BE RIGID TO PRECLUDE DYNAMIC INTERACTION IF IMPRACTICAl TO DESIGN RIGID STRUCTUREi QUALIFICATION ANALYSIS INCLUDES SUPPORT STIFFNESS'

i

C, PUMP AND VALVE OPERABILITY ASSURANCE PROGRAM 1,

ACTIVE VALVES LOADS - SEISMIC>

HYDRODYNAMICS FLUID TRANSIENTS ANALYSIS STRESS p DEFLECTION DYNAMIC TESTING -

COMPONENTS (OPERATOR LIMIT SWITCH'OLENOID VALVE)

STATIC/DYNAMIC TESTING OF ASSEMBLY SPECIFIC PROGRAMS - MSIVi PURGE VALVES>

FEEDWATER CHECK VALVES 2,

ACTIVE PUMPS LOADS - SEISMIC ANALYSIS STRESS, DEFLECTION, LOWER ALLOWABLE LIMITS PROTOTYPE TESTING OF MOTORS (IEEE 334) 3.

SUPPLEMENTAL PROGRAMS PRE INSTALLATION/POST INSTALLATION TESTING A.

PERFORMANCE TESTING B

PREOP, TESTING PERIODIC TESTING AND INSPECTION A

ISI PLN/TECH SPECS B

PREVENTATIVE MAINTENANCE

D, SQRT/PVORT FORM NRC RECOMMENDED FORMAT COMPREHENSIVE PRESENTATION OF QUALIFICATION RESULTS "ROADMAP" TO QUALIFICATION DOCUMENTATION DOCUMENTED EVIDENCE, OF.QUALIFICATION REVIEW SQRT/PVORT FORMS WILL BE PREPARED AS REQUESTED BY THE NRC LS-5/15/8Q

dl 4

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. QUALIFICATION DOCUMENTATION MASTER LIST A,

WILL BE PROVIDED FOR:

10CFR50.49 EQUIPMENT-(SCEW SHEET)

SAFETY-RELATED MECHANICAL EQUIPMENT SEISMIC CATEGORY I EQUIPMENT B,

LI'STS EQUIPMENT BY NARK NUMBER C,

.IDENTIFIED MANUFACTURER AND MODEL. NUMBER D,

PROVIDES STATUS OF QUALIFICATION AND INSTALLATION,

a

EQUIPMENT QUALIFICATION FOR HYDRODYNAMIC LOADS NINE MILE POINT - UNIT 2 ESTABLISHMENT OF STRESS CYCLES AND DETERMINATION OF TEST DURATIONS Establishment of Stress clc Re uircments The hydrodynamic loadings.

which contribute significantly to the potential fatigue damage are those due to SRV actuations and LOCA loadings A total of 5200 SRV events and 1000 chugs are postulated during the 40-year plant life.

Stress cycles for both SRV and LOCA loadings werc calculated as follows:

a.

b.

The responses of several SDOF systems were calculated by sub-jecting them to acceleration time-history motions at representa-tive reactor building locations.

SDOF

systems, ranging in frequency from 2 to 100 Hz, at no morc than 1/3-octave

spacing, vere analyzed.

h total of 21 time-histories at five different locations of the reactor building for the critical loading cases of the SRV actuation were considered.

Ten time-histories of LOCA-chugging loading, and nine time-histories of LOCA-Basic Conden-sation Oscillation (Basic CO) loading Crom four different locations were considered in'he analysis.

For each response time-history obtained in Step a above, the equivalent number of stress

cycles, normalized to the peak

response, vere determined.

Co d.

For each SDOF

system, an equivalent stress cycle number vas established.

This number is based on a 99-percent confidence limit for the mean of all data analyzed.

Of all the SDOF systems

analyzed, the highest equivalent stress cycle number from Step c 'above is taken to be.the equivalent stress cycle for the loading event, i.e.,

one SRV actuation or one chug.

eo Due to the stochastic nat'ure of the loading, not. all the 5200 SRV actuations and 1000 chugs are expected to occur at their respective peak magnitudes.

Since the peak magnitudes are used as the design loads for equipment qualification, equivalent occurrence factors (EOFs) for both SRV and chugging are deter-mined.

The methodology and the basis are documented in Refer-ence a.

c

h/ ~

f.

The total aumber of equivalent stress

cycles, Neq, for SRV, chugging and Basic CO are calculated as:

From t:he above Neq (SRV)

Neq (chugging)

Neq (Basic CO)

(Number of postulated events) z (number of stress cycles from Step d) x (EOF) equation:

~ 5950 cycles

~ 1125 cycles 200 cycles These numbers compare favorably vith the numbers from Iimerick, Grand Gulf, and LaSelle nuclear stations, which have been pre-viously accepted by the NRC staff.

The cycles for loading combination of various dynamic events vere established by considering how many cycles of a particular loading can occur concurrently vith an equal number of cycles of another loading..

The remaining cycles of a

load that cannot simultaneously occur vith another load are addressed as cycles for that individual load case.

Determination of Test Duration The objective in determiaing test durations vas that the, expected fatigue damage from the tests equals or exceeds the fatigue damage due to the postulated loading.

The same method discussed above vas used in determining the expected stress cycles from test table motions.

Eleven different random multifrequency test input motions from tvo different test facilities vere analyzed.

Here

again, the equivalent stress cycles from the responses of several SDOF systems of frequencics up to 100 Hz vere calculated, when subjected to these time-histories. It vas concluded that vhen conducting a test in which spectra due to hydrodynamic loads (having frequency content typically in the range 10 to 100 Hz) are enveloped, a 30-second duration test using random multifrequency input.

motion vill result ia a minimum of 200 equivalent stress cycles cor-responding to thc required response level of the equipment.

The results are similar to those from Reference b, vhich recommends 190 equivalent peak stress cycles induced by stationary random motion, for a

filtered motion center frequency of 40 Hz.

In addition, the expected stress cycles in the equipment response due to siagle fre-quency test input motions, c.g.,

sine

beat, were also determined.

Having established the expected stress cycles from a specific test, test plans were developed which vould yield equivalent stress cycles equal to or greater thaa the required stress cycles from all the dynamic loads and load combinations.

For cquipmcat already tested for seismic

loading, the expected fatigue cycles from these tests were compared vith thc required cycles to dcterminc whether the existing tests vere adequate or whether additional testing vould be needed.

C4/14764/15/4YX

References a.

Mark II'Generic Techniques for Fatigue Evaluation. of the SRVDI,s and Somcomers in the Vetvell.

Prepared by the -Mark II Sub-

. coaeittee on Structural/Mechanical

Problems, August 13, 1981.

.b.

Recouaaended Practices for Seismic Qualification of Class 1E Equipment for Nuclear Poser Generating

Stations, 4th draft of IEEE Standard 344-198(-) dated March 1984.

C4/14764/15/4YX

H A

P

Enclosure 3

September 25, 1984 Meeting on Equipment gualification Nine Mile Point - Unit 2 List of Attendees-NRC Sary F. Haughey A. S. Masciantonio Robert J. Wright Norman D.

Romney Goutam Bagchi George Hubbard NMPC doorman Rademacher Don Hill A. Loveland D. L. Pike R. L. Anderson (NYSEG)

GE H. P. Williams P.

C. Yin Noel Shirley Richard W. Hardy SWEC Kiic ard H. Pinney Michel S. Stocknoff T. L. Wang M. K. Allen L. Illy D. L. Hobman S.

M. Feldman Narendra Moni

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I F