ML20150D502

Provides List of Electric Equipment Items Chosen for Seismic Audit & Format of Audit.Requests Transmittance of Info to PG&E

ML20150D502
Person / Time
Site:	Diablo Canyon
Issue date:	04/23/1975
From:	Knight J Office of Nuclear Reactor Regulation
To:	Allison D Office of Nuclear Reactor Regulation
Shared Package
ML20150D429	List: IR 05000428/2005002 ML20150D427 ML20150D479 ML20150D502
References
FOIA-88-19 NUDOCS 8803240307
Download: ML20150D502 (1)

Text

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( ( .) v&14X 4 <u i April 23, 1975

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Dennis P. Allison .

Light Water Reactors I Project Branch 1-3 Division of Reactor Licensing S'JBJFET: Diablo Canyon Electrica) Equipment for MEB Seimuic Audit The following list of electric equipment itens are those chosen by the Mechanical Engineering Branch for the Diablo Canyon' Seismic Audit.

1. Diesel Generators

2. Ilot Shutdown Panel

3. Main Control Console

4. Nuclear Instrumentation (W)

5. Reactor Trip Switchgear (W)

6. Protective Relay Boards The *ormat of the audit will consist of a review of the follouing  ;

documents and a site visit to view the actual items of equipment. i

1. The purchase specification - portions concerning seismic requirements

2. Test Reports where available - including internal necios recording witness of tests g

~~

3. Manufacturers' certifications of seisaf.c qualifications ,

if provided j

4. Engineering drawings of the items actually installed '

where appropriate including drawings or descriptive literature of all appendices and accessories necessary il to the operability of the iten.  !

5. Analyses performed for seismic qualification if appropriate i It is requested that the above infortation be transmitted to PG 6 E so that they nsy be fully prepared by the time of our arrival.

J. P. Knight, Chief Mechanical Engineering Branch Division of Technical Review l cc: R. R. !!accary, TR NRR: Subject File , ,

H. L. Brammer, TR 'IR : MEB File /' '

R . J . Bo sna k, 'IR TR: Reading File P. Y . Chen , 'IR o+c i

• V. S. Noons, MEB:TR

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R. R. Maccary, Assistant Director for Engineering Division of Technical Review HIGHLIGHTS OF PG&E DIABLO CANYON PLANT SEISHIC DESIGN AUDIT .. j From April 20th to May 2nd,1975, the taembers of the Structural Engineering Branch and Mechanical Engineering Branch have per- i formed a seismic design audit of the Diablo Canyon Plant at the )

PG&E office in San Francisco. Present for the applicant were PGAE, Westinghouse and John A. Blume Associates engineering l s ta ff. In an earlier meeting held in Bethesda on April 4,1975

{

between the NRC staff and the applicant, general guidelines and  !

scope for the seismic design audit were discussed in considerable detail as part of the preparatory work for the subject audit.

A list of the attendees is enclosed, l The primary objective of the NRC staff was to conduct a seismic design audit of the subject plant. The results of the audit would then be used as basis for judging seismic design adequacy of the plant.

g liighlights of'the audit are sumarized below, j

1. NRC staff opened the meetings by first stating the objective of the audit program and defining the specific scope and depth of the week long audit plan.

2. PG&E, its NSSS vendor; Hostinghouse and PG&E consultant John A.

Blume Associates made presentations on the seismic design criteria, rethodology and procedures used in the subject plant.

The presentations generally followed the technical subjects included in the plant FSAR and wert judged as satisfactory by the NRC staff.

3. A sample list of Category I structures, systems and compor.c'Its of the Diablo Canyon plant covering safety functions similar to those included in Table X-1 of Appendix X to the Rasmussen Report was reviewed for their adequacy of seismic design qualification 099sCEk evn=aus &

DAT49 Forms ALC 31s (Rev. 913) AEC.M 0240 W v.e. oys.nu, ,,,,,,,.. ,,,,c,,,,,,,,,,,,,,

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R. R. Maccary gay 1 r 1975 and documentation. The audit staff found that all the Category I structures, systems and components included in the list were properly qualified (i.e.,100% successful qualification as com-pared to 27% failure to demonstrate adequacy indicated in Appendix X of the Rasmussen Report).

4. Following the above item 3 overall qualification audit, tip structures and four components and systems (i.e., containment building, turbine building, steam generators, reactor coolant pump, steam generator support ar.J pump support) were selected for detailed auditing by going through check list items. In addition, the analyses and test reports of six electrical equipment items (i.e., diesel generators, hot shutdown panel, main control console, nuclear instrumentation system, reactor trip switchgear and pro-tective relay board) were also selected for detailed auditing.

Except for the turbine building and a few missing data pertaining to the components and systems, which PG1E will provide in a future transmittal to the NRC staff for confirmatory review, the results of the detail audit of these structures, systems and components were found satisfactory and acceptablo.

5. Some of the audit staff took a field trip to inspect selected Category I systems and components. The group concluded that the selected components and systems had been qualified for service under seismic loads by acceptable testing and analyses. The cgg

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group also reconnended and PG&E agreed that the installation of field run Category I piping (2-1/2 inch diameter and snaller) be reviewed by the PG&E engineering staff to ensure that the accept-able field installation procedures were fully implemnted.

6. The audit staff also reviewed the applicant's and its vendor's design control programs. The methods of design control and co-ordination utilized by PG&E, Westinghouse and PG&E consultant (JAB) were reviewed and discussed. It was established that adequate control procedures were followed in <:hecking and approv-ing engineering calculations and drawings. The design control l program implemented in seismic design of Diablo Canyon was judged satisfactory and acceptable,

7. The ACRS questions related to seismic design of the Diablo '

i Canyon plant were discussed. The discussion yielded some technical viewpoints, which form part of the bases for formu-lating future response to the ACRS questions.

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R. R. Maccary 8. The NRC audit staff also reviewed various computer programs used for the design of Category I structures, systems and com-ponents by PG&E, JAB and Westinghouse. For programs that are not available in public domain the pmgram verification pro-cedures adopted by PG&E and its vendor / consultant were found to-follow the criteria acceptable to NRC staff. _ , .

9. A few items, for which additional information is required, have been identified during the course of the audit. The information pertaining to the items will be provided in two to four weeks by PG&E and its vendor / consultant for NRC staff confirmatory review.

At the closing of the audit meeting, NRC audit staff concluded that based on the above described results of the seismic design audit, the seismic design methodology, procedures and design controls implemented for the plant wem in general found satisfactory and acceptable. The audit staff also expressed their appreciation for the cooperation and support provided by the technical staff of PG&E and its vendor / consultant.

As a final note, the week long seismic audit effort was carried out in an expeditious manner with adequate depth of auditing. It is concluded that the objectives of the audit were properly implem3nted.  !

M J. Knight, Chief Mechanical Engineering Branch 1 Division of Technical Review I I

L. C. Shao, Chief l Structural Engineering Branch j Division of Technical Review f.nclosures:

1. List of Attendees

2. Diablo Canyon Seismic Audit Agenda

3. Seismic Category I Audit Check List

4. Detailed Seismic Audit Check List

5. Additional Information to be Provided by PGt.E and Westinghouse

6. Computer Program Verification cc (Next Page) n , g a "a

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."=* 5//6 /75 5/h>/75 5// 6 / 75 5//(,/75 Form A FC 510 ( Re. 915) /K'ai 0240 W u. s. o o v s n s , e n, =vi . .,,,c , . . ,,, ,,.. . ..

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I,%Y 1 f 1975 R. R. Maccary cc w/ enc 1:

D. Ruscle i

E. Case F. Schroeder A. Giambusso .

R. DeYoung .,.

V. Moore

11. Denton l' L. Davis i O. Parr i'

0, Allison O. Jeng l

G. Bagchi

P. Y. Chen l V. S. Noonan cc w/o encl:

SEG Members MEG tiembers i

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l ENCLOSURE 1 LIST OF ATTENDEES l

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ENCLOSURE 1 LI2T OF ATTENDEES NAME TITLE ORGANIZATION D. V. Kelly Ch. M & N Eng. PG & E M. J. Gormly Project Mech. Eng "

R. V. Bettinger Chief Civil "

V. J. Ghio Senior Civil a E. P. Wollak Supyg Civil & Proj. Civil "

F. W. Brady Civil Eng a V. S. Noonan Mech Eng NRC/MEB P. Y. Chen Mech. Eng "

J. P. Knight Chief. Mech Eng.Br. "

L. D. Davi s OELD NRC/ OELD D. C. Jeng Sec. Leader Structural NRC/SEB L. C. Shao Chief, Structural Eng. Br. "

G. Bagchi Structural Eng. "

1 W. J. Lindblad Project Eng. PG & E-D. Nielsen Senior Electrical & Proj. Eng. "

B. Young Senior Electrical "

R. Gallagher Vice Pres. JAB Ass.

D. Javeri Proj. Eng. "

G. T. Downs Supvsg Structural Analysis 1 Electro-Mech. .

R. M. Laverty Senior ME PG & E J. W. Dorrycott Proj. Mgr 1 W. C. Gangloff Proj. Mgr W T. E. Campbell Mgr Support Structure Design g D. F. Miller Mgr System Structural Analysis g P. G. Smith Mgr, Structural Development 1 (Tampa Div.)

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e ENCLOSURE 2 -

DIABLO CANYDN SEISMIC AUDIT AGENDA i

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. ENCLOSURE 2 DIABLO CANYON SEISPIC AUDIT AGENDA April 28, 1975 9 - 10: 30 SEB - General Briefing Seismic Design Methods & Procedures MEB - Cover the items in Sections 3.7.1, 3.7.2 and 3.10 of standard format

- PG & E information (not Westinghouse)

- Description of material on appendix B data lists (Rasmussen List); provide list 10: 30 - 12 SEB - Turbine building, intake structure and containment analyses 10:30 - 12 MEB - Specifications, analyses, etc. on selected equipment 1:00 - 5:00 SEB - General Briefing on PG & E design control methods &

procedures 1:00 - 3:30 MEB - Specifications, analyses, etc. on selected equipment I

3:30 MEB - Leave for San Luis Obispo l

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) . r AGENDA April 29, 1975 9 - 12 SEB - Further discussion of information on Appendix B data lists (Rasmussen lists) following overnight review I-5 SEB - Discussion of seismic related computer program verification

- Visit PG & E computer facilities 8:30 MEB - Tour site and look at selected equipment April 30,1975 9 - 12 SEB - General briefing on component seismic design adequacy

- Cover items in Sections- 3.7.3, 3.7.4 and 3.10 of standard format

- Westinghouse design control methods and procedures

- Steam generators & supports

- Reactor coolant pumps & supports 1-5 SEB - Material on appendix C, D & E data lists (Detailed B

information on certain selected componen'ts)

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AGENDA May 1, T975 9 - 10 SEB - NRC caucus MEB 10 - SEB - Containment liners bulge, Salt Water Cooling All day Pipes, ACRS questions, etc.

10 - MEB - Qualification of equipment of base slab and All day ground 1

May 2, 1975, AM - Completion of any outstanding items.

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QUALIFICATI0:1 1,

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BASIS '< FER? r

. Af!ALYSIS REPORT ESCRIPTIO:. (PAST O't FUTURE)

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. 6.3.7 Electric Power Distribution Systems .[

X ,  ! Yes P C+.E f

!6.3.7.2 Containment Penetrations General Electric  ?!ap1970 '

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Yes ,

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6.3.7.3 Cable Trays 4- 0-71 Unic #1 X j l . y p 6.3.7.4 4kV Vital Switchgear ' General Electric I i

, 1- 0-74 Unit #2 I X . X *

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Westinghouse  ;

480V A.C.

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a 6,3.8 Reactor and Engineered X I i Yes *'astinghouse Safeguard Protection Systems Westinghouse

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• Sensors and Logic Cabinets '

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~ EitCLOSURE 3 t SEISMIC CATEGORY I AUDIT CHECK LIST _ , / E

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I DATE l' METHOD OF SEISMIC QUAL.IFICATIC:

- ' QUALIFICATIO DATA '

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• 0T.ER 9 - MAILABLE?

lAE OR - QUA1.IFICATIO:2 TEST 1HERE C0!PLETED BASIS Arpendtx X sie;ct;;;tES OR C0::PONENTS

VENDOR (PAST O'l FuiME) ,

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. 1 6.3.1 Cont.ninme nt Structure

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. 1970 Blume Yes PC&E j 6.3.1.1 Soil-Structure Interaction X ,

Blume 1970 g PCE Yes l 6.3.1.2 Containnent Internal Str j i I 6.F,.1.4 Containment Polar Crane H. Jordan /Yuba s L '

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. Reactor Coolant System -

Yes P C *.i 6.3.2.0 . X ,

Westinghouse 1975 .

RCS Loop PCI.E 6.3.2.1 Yes {

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"Steam Generator & Pump Supports  : Yes 6.3.2.2 " 1975 x

Reactor Coolant Pump Nozzles f

6.3.2.3 .

Yes t%: :.

l Not Related to Seismic Design X FC.> r ..

6.3.2.4 Pipe Whip Restraints Westinghouse 1975 X  ! Yes i 1972  ; .

Paul-Munroe 6.3.2.5 Snubbers

• I PO&E i a . Yes i e Low tiead Safety Injection System X l

,, l 6.3.3 Blume 1972 ,

• k*c s t inghou s f Yes 6.3.3.1 Piping X

{ We s t inghou se 1972 Yes Ve stin;;hous 6.3.3.2 Pumps & Drives X {

, Westinghouse 1969-1975 ,

k'e s tinghou.

"' I Yes Valves  ;

6.3.3.3 1969-1975 X "

Wes tinghouse  ! Yes

! Wtor Operators X X j~ 6.3.3.4 1972 Blume F1 eld Test on PC&E Snubbers & Hangers Yes 6.3.3.5 Westinghouse Instr.' mount'ing f ,

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6.3.3.6 Instrumentation W

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QUALIFICATIO:t l

DATE METHOD OF~~SEISMIC

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1 QUALIFICATI0:1 l IAE OR i TEST *0THER - AVAILA3LE?.. '

VE:: DOR CO:' LETED i:P.ER- '

S.CTURE5 CR CC:'00NENTS REPCRT BASIS (PAST00, FUTURE) . . ANALYSIS , ..

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. 6.3.4 High itead Safety Injection System l  :

. Yes Westir.ghouse t 1975 X

Westinghouse.

! 6.3.4.1 Accumulator Tank Nozzle

, ks PCaE 1973 I X i i 5

Accumulator Piping Conn. Westinghouse

• 6.3.4.2 - a co RSC i Yes Vestinghouse(

X j 3' Westinghcuse 19,72

6. 3. t. Charging Pumps & Drives 1 3 -

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• i 6.3.5 Containrant Spray System *

• Westinghousc 1972  ; X *

[ Yes 6.3.5.1 Spray Pump Out side Containnent* Westinghouse,

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$ 6.3.5.2 Inside Containment .

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6.3.6 On-Site Electric Power System -

i I Yes PC'E m!. 1970 X

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Disel Generator Housing .Blume  ! i g I 6.3.6.1 . '

I (Turbire Buildi nst) .

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!  ! Yes PC&E I

hndor + PCSE 1975 .

6.3.6.2 Diesel Generators "

PC&E i

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Yes Vendor + PG&E 1975 f 3 6.3.6.3 Day Tanks .

PC&E .l X

l Yes PC&E 1975 J 6.3.6.4 Air Tanks PC&E X

Yes EXIDE PSD 8 11-72 ' ,.

l 6.3.6.5 Battery Charges Yes PC&E 4-27-71 Unit #1 Battery Rack. Batteries ih '

C&D, Inc.

Battery Rack & Batteries '8 29 72 Unit #2  :

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ENCLOSURE 4 DETAILED SEIST11C AUDIT CHECXLIST l

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Detailed Seismic At )t Checi:lis t - S tructures k .;.,' .

Type:

DitBlo Cauvon rouca eLasT O etant ..liame: ~

Cl/R Utili ty: P.candE Company PWR x

. NSSS: Westinghouse IIION A-E: PCandE Company , J. A. Blume & Associates,,

t Structure - flame: Con t ai nme n t -

Description (include si: etches): Exterior Shell_: 140'ID x 142'High x 3-l0 thick Cylindrical Wall, 140'ID x 2'-10 thick hemispherical dome roof. Interior Structure : 106'00 x 49'high x 3' thick cylindical crano wall, anchored into base slab, 34'oD x 8' thick x 11'high reactor wall. 4' thick fuc t transfer canal walls & floor. 3'-7' concrete main operating deck Structuralsecclannulus8Ocsigner: I tforms between ext. she ll and crantwall. Foundation: 15' reinforce Responsibl c ne m c basc' mat.

Stanlcy llanusiak - Roger Villatuya (JAB) i Responsible Checker and/or Reviewer: ,

2 David C. Landes (Reviewer), R. Y. Chandivala (JAB)

Pertinent Reference Drawings: 443231 thru 443237, 443239, 443240,'443241, lg 443243, 443251 thru 443254, 443272, 44327,3, 443276, 443277, 443283 thru y- 443285, 443286 thru 443287 .,

t Seismic Input - acceleration: 0.20g (DE) 0.40g (DDE) .

l Ground Response spectra location: Surf ace / foundation I '

! Time llistory: Hypthetical time history, developed to produce an envelope spectro jhichcombinesinput from time histories of !:srch 22,'57 San Francisco and July 21,' 52 Ta f t (Calif) <tarthquakes. In addition, to these tto time histories, arbitrary modifications were introduced following meetings with AEC Staf f, for the purpose of making the critoria more conse rva tive . .

l'.ethod of hgh/ sis -

Model type (ecch direction): Axisymmetric finite cictacnt model. The foundation rock mass pnd the containment structure are modeled as one structure system, to consider rock-structure interaction (FSAR Figurc 3.7-5)

"Dynamic Strc55 Analysis of Axisymmetric Structures under Arbitrary LopdingC W Uth pde: - ukmar Ghosh and Edward Wilson UC Report No. EERC 69-10 Soil Structure Interaction:

Soil is included in the model.

Soil damping:

• Struc tura f *dsping: 2% (DE), 5 (DDE)

Combination - 3 Ccnonents: Lartest ilorizontal component added.

to vertical .

Torsional censideration: -^xi cynne t ric St ruc tu're .

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i" Ibdal Shapes & frequencies: See FSAR - Fig. 3.7-6 Total Base Shear: 35,050k (DE)

Overall Response (shear & mor.cnt): ,

59,990k (DDE)

. Total 3.48x106 k ft (DE) 6 Floor Response Spectra (sketches)Overturnimg  : Moment: 5.62x10 k ft -(DDE)

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STRESSES Critical Load LOCATI0tl Combination Bearing Seismic Total Allowable Base Hat Daad Load + DDE 8.KSF 88KSF 96KSF 800KSF M.

(150 ks t)** '(158 ksf)**

• )Compr. Stren, of unconfiner

Samples l

- **)1alues in pa l . -

thesis are P Stability, obtained ign-

s. . ing passive -

) Factor of Safety - Sliding Not critical, seistaic force resisted by *i'fs fid ' '

y r,esistance of rock on vertical f ace of base slab.

i Overturning 1.2 (114)** -

! Critical Structural Elements:

b b 3 Governing Identification Location Load Combination Seismic To tal Allwahl Hoop reinforcing 12'above base C=1. 0Dio. 0$D+1. 5P+1. 0T" 0 55.8 ksi 57ksi Diag. reinforcing C=1. 0D +0. 05D+1. 0P+1. 0T+1. 0DDE 3 0.1 59.4 57ksi

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• liax Deflection: Amount Location 0.666" (DE)

, Top of Containment 1.063" (DDE) .

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Detailed Scisni_c Audit Chec': list - Components, ,

Plant - flane: Diablo canyon Units 1 and 2 . Type:

Utility: Pacific. Gas and Electric BWR Westinghouse Electric Corporation

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!!SSS:

A-E: Pacific cas and Electric HTGR Vendor: ,

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Component' - llame: steam cencrator supports

Description:

See attached t ,,

Z l Location (In-plant): containment sida.  ;

- Functional

Description:

Support the steam generator under all loading conditions Pertinent Reference Drawings: 438276, 438277 ,

Pertinent R2ference Dasign Specifications: .

_ Seismic Input - ,

Floor Response Spectra: .

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The lower supports for the steam generator consist of:

Four vertical pinned columns with bushings bolted to the bottom of the stcom generator support pad. ,

l A lateral support frame which is shiteed to transfer the load from the steam generator to the concrete.

n The upper lateral steam generator support consists of a ring band, around the steam generator shell. The ring is attached to concrete by four hydraulic shock suppressors and by four steel bumpers. Loads are transferred from the equipnient to the ring band by means of shims between the band and generator shell. ,

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. Test Seismic Qualification - Method analysis, : Analysis ,

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3 - DirCClionS: All three dlrections included l

l Accelerations: N.A._(Response Spectra Pc'sk DE 8.8g, DDE 14.2g Model Frequencies: n A, (S.c. Freq. 8.7, 8.8, 10 , 15. )

Critical Structural Elements:

Governing Stresses  !

Identification location Load Co.bs. Seismic Total A11cuable l S.C. Upper Support LOCA 6'DDE 657, 36.2 42.0  !

S.C. Lower Support LOCA & DDE 4 17. 41.5 50 l i

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Location: -

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If Qualification by Analysis, then Complete -

Method Of Analysis - Response Spectrum Methoa

- IDdel type (eaCh direction): Three dimension model of the Reactor Coolant Syst-j ' Computer Codes: trestdyne .

Structural Dar. ping: 1%

Support Considerations: Upper and lower supports considered in the onelysis  ;

Combination - 3 Components: SRSS combination of worst horizortal plus vertical  !

, Torsional Considerations: Incorporated in the raodel

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The supports are analyzed and included in the Reactor Coolant System analysis. For this analysis, the Design Earthquake and .

Double Design Earthquake Response Spectra curves obtained from Pacific Cas and Electric analysis of the Reactor Containment Building are utilized. The DE and DDE Floor Ecsponse Spectrum Curves corresponding to 1% critical damping at Liic highest elevation at whicTthe supported enm31cnt is attached to the containment, were conservatively used in the analysis for the .

Upset ' and Faulted Condition.

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. 5 j Detailed Soismic Audit Checklist - CO:nponents Plant - Name: Diablo canyon Units 1 and 2 Type: -

Utility: Pacific cas and Elcetric BWR I

NSSS: k'estinghouse Elcetric Corporation

• PWR _x A.E: Pacific cas and tiectric flTGR Vendor: . .

5 Component - Name: Reactor Coolant Pump Supports

Description:

See attached 5

location (In-plant): Containment Bldg. l Functional

Description:

support the reactor coolent pump under all loading l conditions 4

Pertinent Reference Drawings: 438278, 438279 ,

Pertinent Reference Design Specifications: .

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Seismic Input -

Floor Response Spectra:

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The reactor coolant pump support consists of a structural f rame. The frame is attached to the pump vertically by bolts. The t'rame is equipped with steel bumpers that are shimmed against the pump casing to transfer the lateral l o.i d s .

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( Test. )

Seismic Qualification - Method (analysis.): Analysis

( etc. * )

3 - Directions: All three directions included Accelerations: N.A. (Response Spectrum Pedk DE 3.lg DDE 4.98

. Model Frequencies: N.A. (RC Pump 6.7, 7.2, 10.7, 11.9, )

Critical Structural Elements:

Governing Stresses Identification Location Load Combs. Seismic Total Allouable RC Pump Supports LOCA & DDE- a 307, 98 115

\ 2 657, 30 36

.o 5 , Max. Deflection: .

f Location: .

EffpctUponFunction: -

, If Qualification by Analysis, then Complete -

hthod of Analysis - Response Spectrum' Nethod Model type (each direction): Three dimension model of the Reactor Coolant Syste:

Compute Codes: Westdyne . .

Sfructural Dacping: it .

Support Considerations: RCP supports considered in the model Combination - 3 Components: SRSS, combination of worst horizontal plus vertical Torsional Considerations: Incorporated in the model 5

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The supports are analyzed and included in the Reactor Coolant System analysis. For this-analysis, the Design Earthquake and Double Design Earthquake Response Spectra curves obtained from Pacific Cas and Elcetric analysis of the Reactor Containment Building are utilized. The DE and DDE Floor Response Spectrum Curves corresponding to 1% critical damping at the highest elevation at which the supported component is attached to the containment, were conservatively used in the analysis for the Upset and Faulted Condition.

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, 3 Datailed Soisnic Audit Chechils_t - Coryon,ents _

Plant - !!!.w: Diablo Canyon Units #1 and 2 Type:

UUP' Utility: Pacific Gas & Electric HSSS: Westinghouse E1cetric Corporation PilR a_ '

Pacific Gas 1 Electric IITGR A-E:

Vendor: Westinghouse,-Tampa Division ,

Coponent - Ibma: Steam Generator ,

Vertically oriented U-Tube Heat Exchanger  :

Description:

Locction(In-plant): Reactor Containnent Bldg.

Ft'acticn .) D:scription: Feedwater, heated by reactor coolant passing thrcuph U-Tubes, chLnges to a water-stecm mixture and flows upward through the tube butidic exiting, the unit cs, essentially, dry steem.

l'artincat Dforence Decuings: Cutline Dag. 717J360, Aeneral Astenbly Cag.1007J:

Pcrtinuit l'oferer.cc bsica S,92cifications: . Westinghouse Equipnent-Spec 67731:  ;

Soistic Ino'.tt -

Flcer D ponse Spectra: .

Design Earthquake and Double Design Earthquake Floor Response Spectra obtained i frce. Pacific Gas 5 Electric analysis of the reactor cordcinment buildirg.

Elevation corresponding to upper support elevation was used with 17, equir.T. ant dampinge , ,

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-- Test seitraic Quellitcatica . l'ethod analysis. : Analysis e tc.

• 3 - Dircctions: All three directions ovaltlated. ,

Acccierctions: Peaks on ficor response spectra design earthquake -

'8.8 9; double design carthquake 14.29 . t

- f.odel Frcquencies: 8. 7, 8. 0, 10. 0, 15. 0, . . . . . . .

. Critien1 Structurc.1 E1::ontc: _ __

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- Coveriting Stresses j

' Seisolc Toto! Alleua i identification Location L o a d C c:.h s . _-

Tubes U-Bond Design Press- 50% 34.9 ksi- 35.0 I Region ure + DE Shell Upper Design Press- 15% 37.0 ksi 40.0 Support ure + DE Tubes U-Bend DDE + LOCA 30% 68.6 ksi. 73.4 l

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Region 80.3 ksi 84,1  !

4

>- Shell Upper DDE + LOCA 30%

Support o3 Ikx. 00flectit.1: 1.96 inches for DDE. /

.' lctntion: Tubes in U-bend region.

• Effcet IPeoa Fu.'.ction: fione If Qualific tien by I.nclysis. than Completo I

. I'.ethod of latlysis - Response Spectru 1 ltethod )

Ib:'ai typa (et:h directicn): 3-dimensional lemped mass becm elce nt model with approximately 300 degroes of freedon, l e

Co:'put:r CC Os: SI:AKE, PESA:1 (Tampa Division Cedes)  ;

I Struc'ture.i Nying: 13 I ,

Suprart Q:nsid: rations: Upper and lever support stiffriesses included

! Co:nhination - 3 Ccy.ponents: SUSS ccr.:binatica of wo st horizontal en-i va i Yorsional Con:.iderations: ltedel incor; ort:tes torsional r.: odes of vib. cit

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Detailed Sci.e.nic Audit Chect: list - Co.100nents Plant - lure: Diablo Canyon Units #1 and #2 Type:

litility: Pacific Gas & Electric OflR NSSS: . Westinghouse Electric Corporation Pl!R y ,.

f.-E: Pacific Gas & Elcetric HTGR Vendor: Westinghouse Electromechariigal Division C00poncnt - HU.0: Reactor coolant pumps ,

Description:

See Attachment !!o.1 Lc.cctica(In-plant): Reactor containment building '

Functional

Description:

See Attachment No'. 1 s.

Pcrtinent I'ciercnco Drctiings: Outline De:g.' 61SJB50; /Assem,bly Dwg. 610JS61 Portinent ibfere::ce i'asign Specificctions: E-6/6574 Seismic Innut -

6 l

j floor Cnginsa Spectro: -

l Design Earthqual:e and Double Design Earthquake Floor Response Spectra obtained i from Pacific Gas 1 Electric analysis of the reactor containcant building. {

Equi mont dar. ping of 27, of critical damping used in the seismic analysis.

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( Test '

Soisraic Qualification - Method (analysis, : Analy.is  !

( etc. ' l 3 - Directions: yc3 j I,ccolcrations: Peak accelerations: 3.1 for DE arid 4.9 for DDE ,

Podel Frequencies: See Attachment t!o. 2

, .C.r._itic.?) Stri!_ctural Ele:mnts :

Coverning Stresses l

- Ic'catificat ion 1.ocction Load Cc, Tbs. Saistlic Total Allowable j

= _ _

i See Attachment rio. 3 l

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p ,*, 1.W Dhilection:

t.ateral - 0.80" Ve r ti c a l ' ,. 020."  ;

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- ll; cati 0n: Top of rc.otor ,

Who'ie Pump Eficct Upoa Function: ttone tione If Qualification by Analysis, then Complete Il?thed of Analysis - Response spectroaicethod h Ibtal tyio (ccch direct.ica): A 3-dir.:ensional r:odel incorporating leeped cass,  ;

beam, pipe, spring, dmper, and fluid coupling elements. I 1

Cor.wbr Ceec: Artsys l Structural int.;ilm: 2%

Sup urt Considorations: Support stif fness c atrix Fig. 5 of E-67574 P Fig. 4 of E-67574 00:... a in tMa - a, .c.:,._ 4ni:n.L5 iping s ti f fness matrix

'SRSS, io: .5 i c

c.c;.- b i na t i r n,irat1co 5 :of, th7 varst horizontal plus the vertital t! l. a. M ( .

N00 21 iiir.Yiid..s I.icc i co..1. .ies of vit.. c t.i on .

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AlTAChiENT !A 1 The Controlled Leakage. Scal P.eactor Coolant Pump is a vertical, single-stage, centrifugal purp designed to cove large volt,mes of reactor coolant at elevated temperatures and pressures.

The pump consists of three general areas: the hydraulics, the seals, and the tr.otor. .

The hydraulic parts primarily consist of an impeller, turning vana-dif fuser, diffuser t.dapter, and casing. The casing is permanently welded into the reactor cooling systen. Attached to the bottora of the shaf t is the impeller which is the prime rcover of the coolant. The coolant flows into the eye of the iupeller and a velocity head is imparted to the fluid. The coolant is then directed to the turning vane-diffuser assembly where the velocity head is converted to pressure head. Directly above the impeller is the thernal barr.er/ heat exchcnger.

During normal operation, the thercal barrier liraits the heat transfer from the hot coolant to the radial bearing, seal area, and other pump ccmponents.

}louever, if a loss of injection uater should occur, the component would then also function as a heat exchanger to cool the hot reactor coolant which would leak into the bearing and seal area, liigh-pressure injection water is introduced through a connection on the thermal barrier flange and fleus into the cavity between the main flange and the thennal barrier. The injection water flows downward to the radial bearing where it then divides into tuo fica paths. The upward flow travels past the radial

~ bearing and into thc seal area while the remainder flows down through the tnernal barrier labyrinth and past the cooling coils where it acts as a buf fer to prevent rcactor ccoiant from entering the radial bearing and seal section of the pu.r.?. Both the radial bearing and the seals are lubricated by the injection water.

The pump seals are water-lubricated and control the upward flow of the high-pressure injection water. The Icakage of the Number 1 seal is channeled to the plane chemical and volun.2 control syste n. The leakage of the I umber 2 seal ar.d the !!urr.ber 3 scal is directed to the reactor coolant drain tank.

The Reactor Coolant Pump is driven by a vertical, solid-shaf t, air-cooled, squirrel-cage induction- type motor. The motor is equipped with an oil-lubricated double Kit,gsbury-type thrust bearing, two oil-lubricated radial bearings, and a flywheel rhich is equipped with a ratchet-type anti-rever. e rotation de/ ice which prevents the rotor frca being turned in the reverse direction. The rotor and stator are of standard construction. Six resistance temperature detectors are located throughout the stator to sense the winding tcapera ture. The upper and louer bearing ter.:p3ratures 6re also monitored uith resistance teraperature detectors. l!ater-type heat exchang2rs are used to cool the lubricated oil. Further detailed dcscription of the cator is given in the n:otor uanufacturer's operating instructions for the Recctor Ccolant Pur.9 i'.otor.

An additional feature of the t'.odel !!-11003.- Al puup is the use of a sgol piece heturen th: 7 ma cnd rotor co:clines. Thir, 5c001 uicce ran be r: moved witM"t '

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ATTACllMENT l'O. 2 ',

Frequencies and Model Diablo Canyon RCP

' Max. Rotor j Rotor /Frcme ip _ Disp. l.oc llode No. Freq (Hz) Mode Shape Max 1 6. 7 Frame Z l.0 Flywheel i 2 7.2 frame X 1.0 Flywheel 3 10.7 Rotor-2 87. Impeller 4 11.9 Rotor X 64. Impeller 2.8  ;

, 5 20.1 Rotor / Frame Y ,

6 25.1 Rotor /frcme Z 3.4 Flywhcci 7 26.3 Rotor X 8.2 fly'. heel l 8 28.6 Rotor Z ' 6.3 Seal Area

.=

9 31.6 Rotor X .23. Seal Area 10 35.9 Rotor / Frame X 1.7 Seal Area i 11 35.9 Rotor /Frcae X l.7 Seal Area .

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Attachment No. 3 -

TA3LE I b.

SCC'.ARY OF RESULTS FOR PRESSURE BOUNDARY COMPONENTS -

.  ?

d OPERATING CONDITION STRESS INTENSITY Coironent ' tr:sa '

^

Anc,lyzed Cat 2gery' Chiculated Allowabic Calculated Allowabic Calculated A11ovable Calculated Allovalbe See: en 'e urane _ 14067 15300' 18215 37440 -

Nezzle ':m + 3end 16807 22950 3t.893 48672

. m :c 17787 46800 21795 46800 v

Discherge  ;.'3rane 15050 15300 21927 37440 Norele -c i- Ecad 20119 22?50 "

46584 43672 c :: 15746 46800, 22693

• 46800 C.r: ,e T.,eil Men 10702 22950 '

25234 48672 at . :st Me= +

27911 45900 Discherr.e  : > 1dary

v: ,- 26350

.:: 46800 30799 46800 st r. :: ,: + 3end 21045 22950 50329 r,,:r - e r ;.: 56100 4590 46800 23194 46800 -

c - . f. n g il Me:2 14803 22950 19612 48672 t.t csi Me= + 19295 45900 -

2: : r .: ndary .

Ic:: ' -, . -

'5070 46000 20443 46800 Cle.tre ---ene 39553 67480 40259 674SO 41183* 80776 E c ?. t -  :: -- Eerd -

9'.154 101220 97241 101220 .101359* ,121464 Sc-1 -

rane 16200 19000 17822 - 480c0 Fo . ' , . -:- T :rd 20514 27700 22594 62400

.e -

49440 60000 54393 60000 r- - .:- c 35165 65000 38632

"- 66000 3S632 79200

... d- T. n 1 l. ? 7 0 MCCO

,. .. 52767 99000 52767 113:R 0 M

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Detailed Seisnic Audit Checklist - Cecoonents Component - flame: Steam Generator Supports These sheets are currently being prepared end will be sent to PG&E durin9 the week of April 28. 1975.

'8 9

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lief ailed Seismic Audit Checklist - Components Component - Name: P.eactor Coolant Pump Supports lhese sheets are currently being prepared and will be sent to PG&E during the ucek of April 23, 1975, i

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ENCLOSURE 5 ADDIT 10ftAL INFORMATION TO BE PROVIDED BY PGSE AtlD WESTINGHOUSE 1

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ENCLOSURE 5 ADDITIONAL INFORMATION TO BE PROVIDED BY PG&E AND WESTINGHOUSE l l

At the close of the audit meeting, PG&E and Westinghouse comitted to provide the following information for NRC staff reviews:

PG&E PORTION

1) Report on design adequacy of Category I buried salt water pipe and buried piping connecting the diesel generator and diesel oil tank.

2) Report on method of combination of horizontal and vertical excitations of Category I piping due to earthquake loading (A clarification of the specific seismic load combination procedure adopted by the PG&E piping analysis computer code).

3) Report on seismic adequacy of turbine building due to the latest seismic load.

Statistical data for material strengths of steel and concrete for evaluation of as built structural capacity of the turbine building. (This information will not be needed if as built material strengths are not to be utilized in the structural capacity evaluation).

Detailed seismic audit check list for turbine building.

4) Report on inspection results and follow-up action, if any, of providing proper supports to field run Category I piping (21/2" D or less) by responsible engineer.

5) Description of assumptions used in the "DECON" program utilized by JAB for calculation of bedrock motion time history.

PG&E agreed to provide the above information within one month approx-imately.

WESTINGHOUSE PORTION

1) 'Four sets of detailed seismic audit check lists indicating use l of the absolute sum method to combine horizontal and vertical

,, earthquake loads and incorporating additional data as well as copies of applicable floor response spectra as agreed to in the audit meetings. Audit check lists apply to steam generator, reactor coolant pump, and their support systems.

2) Revisions to design control method (Seismic Error Mitigation Program) as applicable to the Diablo Canyon Plant of the following Westinghouse divisions: Pressurized Water P,eactor Systems Division, Westinghouse Electro-Mechanical Division, Westinghousse Tampa Division.

)

Westinghouse agreed to provide the required infonnation within two weeks.

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EllCLOSURE 6 '

l C0l1PUTER PROGRN1 VERIFICAT10tl l l

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ENCLOSURE *6 COMPUTER PROGRAM VERIFICATI0ll February 1, 1974 ,

Mr. Frank Brady Pacific Gas G Electric Co.

77 11cale Street Room 2613 San Francisco, CA 94105

Subject:

Diablo Canyon Final Safety Analysis Report Verification of Computer Programs

Dear Mr. Brady:

In accordance with your recent request, we have prepared des-criptions and verification documentation for each of the following computer programs: AXIDYM; DECON; iMPR,'; SMIS; PIPDYN; and PIPESD.

'Diese ucre used in our scisraic analysis work on the class 1 structures and piping of the Diablo Canyon plant.

A copy of this program documentation is attached herewith.

If we can be of any further assistance, please call.

Very truly yours, JOIN A. BLUME G ASSOCI ATES, ENGINEERS LbSJ4

.. .pf., w..d / //

Ronald P. Gallagher

• Project Engine'cr RPG/oc Engl .

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DLSchlPilotl5 AND VI:P.lfl.LAllutlS .OF

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COMPUTEli l'I'.0GRAl'.t. USED lil SLIStilC ANALYSES OF DIABLO CAtlV0ll SI: QlllC CLASS 1 STRUClVRES The purpose of this report is to transmit information regarding compulcr. .

programs which were utilized in the scismic analyscs of Diablo Canyon facilitics. All the programs discussed herein are maintained by URS/ John A. Blume 6 Associates, Engineers, and arc operative on the CDC/ '

.6600 SCOPE 3.2 Operating System at the Control Data Corporation Cybernet Data Center in Palo Alto, California. A brief description of the analytic techniques employed by cach program and a summary of the development his-tory and verification procedures used to insure accuracy and validity of the results are presented herein for the AXIDYll, SHIS, HATRAN, PIPESD, PiPDYN, and DEC011 programs. AXlDYN was used in the Containment Building analyses, ItATRAN and SMIS were used for the Auxiliary Building analyses, PIPESD and PIPDYli were used for the dead load and seismic response analyses, respectively, of the piping systems, and DEC0!! uas used to develop the base motion of the soil mass for the Containment Building.

i l

1. AX1DYll l

The AXIDYl1 program is a finite cicment method for the dynamic analysis of .l i

complex axisymmetric structures subjected to any arbitrary static or dynamic loading or base acceleration. The three-dimensional axisymmetric continuum f is represented by axisymmetric thin shells, by a solid of revolution, or as a combination of both. The axisymmetric shells are represented by conical frustrum-shaped elements and the axisymmetric solids are represented by an assemblage of toroids of triangular or quadrilateral cross section connected at thei r Modal circle points. Acceptable loadings are axisymmetric or are such that they can be developed into Fourier series form along the nodal circles (i.e. , as functions of rotational angic, t) .

AXIDYN was formulated and developed by Prof essor E. L. Wilson and S. Ghosh j of the University of California, Ucrkeley, Earthquake Engineering Research Center. AXIDYN is a recognized program in the public domain, is available to the general public through I'ational Information Service - Earthquake

' j

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Engineering (NISEC) of the University of California, and has 'had .suf ficient history of use to justify its applicability and validity. Further verifica- l tion in the form of con:parative solutions to a scrics of , test problems with '!

known solution is described in detail in Reference [1]. i

2. SMIS The SMis (Symbolic Matrix Interpretive S_ystem) program is a general purpose conmond language designed to perform a scrics of matrix operations under the direct control of the user. The program consists of a main "supervisor" routine and several user callable subroutines to execute specific matrix-operations such as addition, multiplication, inversion, cigenvalue extrac-tion, plotting, etc. Several special features are available which allow the program to be casily used for the static and dynamic analysis of complex structural systems.

SMIS was developed by Professor E. L.' Wilson of the University of California, Berkeley, in 1963 The program is a recognized program in'the public domain, is availabic to the public through National Information Service - Earthquake Engineering (NISEE) of the University of California, and has had suf ficient history of use to justify its cpplicability and validity without further demonstration. Versions of SMIS have been continually updated and maintained by URS/ John A. Blume 6 Associates, Engineers, since 1968. SMIS solutions to a series of test problems with accepted solutions are summarized in the SMIS user documentation, Reference [2].

3 MATRAN The MATRAN program is a ger.eral purpose command language for performing matrix operations, time series analyses, and static and dynamic analysos of linearly *' elastic structures. MATRAN was developed by URS/ John A. Blume &

Associates, Engineers, f rom the SMIS program with the purposes of (1) remov-Ing some of the limitations of the SMIS program, (2) adding additional opere-tive subroutines to the supervisor library, (3) modifying SMIS input / output routines to better meet specific user requirements, and (4) streamlining specific analysis operations ',o minimize the computer tiec required for exc-JOHN A OLUMt-: & ABGOCh ATCG. Cf 4MN " F J. 4

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• cution, lhus MATitAll can accurately be descr ibed a', a version of Sills .wi th' pic processor-and post processor additions.

Because itATRAll was developed from the Sills program and essentially provides identical matrlx operativc routines, arguments cited as verificalion of Sills can.bc applied to MATI!All. Throughout the developn.cnt of itATP.Ai! tes t problem ,

results were compared to SMIS results for the same probicos in order to insure validity of the ItATRAll program, itATRAN has had addltional verifIca-tion in the form of extensive use by URS/ John A. Blume c Associates, Engineers, since 1969

4. PIPESD l

The PIPESD (PIPE Static and Dynamic Analysis) program is designed to perforri linear clastic analysis of three-dirnensional piping systems subjected to sets of user prescribed static, thermal, and dynamic (carthquche) loadings.

PIPESD employs a finite cicment analysii technique using the direct stiff- l ness method for static analysis, Householder's QR method of cigenvalue ex-traction, and the response spectrum r..odal superposi tion tacthod for calculat- l ing scismic response. Stress calculations are also performed for Class 1 i and Class 2 piping components according to the requircrcents'of Section !!!,

"Nuclear Power Plant Components," ASME Boller and Pressure Vessel Code, 1971.

l The program was formulated by Professor G. H. Powell at the University of l California at Berkeley and has been extensively rr.odified and expanded by l URS/ John A. Blurra & Associates, Engineers. The program is a recognized co.1-puter program in the public domain available to the engineering corraunity through the Control Data Corporation CYGERNET network. Appendix F of the PIPESD User's Inferrr.ation Manual {3] cites several verification problems of PIPESD 'r'esults versus the ADLPIPE [4), ANSYS [5), and SAP [6] programs (all recognized programs in the public domain).

5. PIPDYN The PIPDYN (PlPe DYUamic Analysis) program is designed to perform scismic analysis of three :limensional piping sys tems by the response spect rum r..odr:1 superposition approach. PlPDYll is a forerunner to the PIPESD progrc.m and 3

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seismic analysis techniques employed by PIPi1Yil' arc identical to those used by PIPESD. Thus PIPDYll is in reality a st reamlined ver*, ion of PIPCSD de-signed solely for dynamic response analysle, of earthquahe: loadings in the horizontal and vertical directions and was.used because (1) It is more cost cffcctive than PIPESD and (2) PIPDYll. output forma t s wc r e modi f l ed to r ce t special criteria for the Diablo Canyon project. .

The proDram was or1 9 i nally developed by Professor G. 11. Powell of the Universi ty of California, Berkeley, an', has been maintained and rodified by ,

URS/ John A. Blume 6 Associates, Engineers, since 1968. Decause PIPDY!! re- ,

sults agree exactly with PlPESD results (for dynamic response analysis),

arguments cited as verification of the validi ty of PIPESD also apply to P I PDYll . A verification probico comparing PIPDYli results to PIPESD and SAP-IV resulcs is described in Appendix F of Reference [3).

1

6. DECON The t)EC0!! (DECOMvolution P'rocedure) prograra is used to calculate trotion at the base of a given soil mass for a given free field surface ground rotion.  :

The soil rnass is assumed to be elastic and rnay be n:odeled by various le/crs of soil with different material properties. DEC0!! uses a fast fourier transform technique to determine the time-history of the base of the soll column.

The DEC0!1 program was developed by URS/ John A. Dlume & Associates, Engineers, and is based on a Cooley-Tukui (7) fast fourier transform technique. -To insure validity of DECON results for the Diablo Canyon project, a scif-verificatio,n procedure was employed in which:

1. .,A finite etcment model of the soil mass is formed (without build- j ings) for the AXlDYt! program. A unit impulse base motion is sup-plied as input to AXIDYil and the resultant surface (Impulse) motion is derived.

2. The surface irepulse response derived in step 1 and the desired j free field ground motion arc input into DECON and the desired base  !

I motion is obtained. ,

1

-4 scmN A. rd.UMr; c4 An ;DC I AUf. r F ,'.> t**

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into AXIDYli (using the 3

The bl. Coll derived lea',e inotion is input original soll n,odel) and the surf ace ground rrot ion is derived.

is then compared to the This "calculated" surf ace ground root ion f ree field ground rnotion input into DEcoll.

A rnore complete explanation of this procedure is detailed in Reference (8]. .

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Et.* ' ,'.' s ,s REfLREllCES

1. Wilson, E. L. , and S. Ghosh,-"Dynanic S t ress Analys is of Axity:nnetric Structures Under Arbitrary Loading." Earthquake Enqineerinq Re<.carch Center Report No. EERC 69-10, University of California, Deri:cicy, September 1969

2. Wilson, E. L. , "SMis - The symbolic Matric Inter pretation System."

National Information Service - Earthquake' En_ gin,ecring Rer. ort _03-573_,

University of California, Berkcicy, California.

3 "PIPESD: Static, Thermal, Dynamic and Stress Analysis of Piping Sys-tems," John A. Blume & Associates, . Engineers, San Francisco, California, June 1973

4. "ADLPIPE Static-Thermal-Dynamic Pipe Stress Analysis," Arthur D. Little, Inc., Cambridge, Massachusetts, Janucry 1971.

5 Swanson, J. A., "ANSYS: Engineering Analysis Systen User's Manual,"

Swanson Analysis Systems, Inc., Elizabeth, Pennsylvania, 1972.

I'

6. Dathe, K. J., E. L. Wilson, and F. E. Peterson, "SAP IV -- A Structurci Analysis Program for Static and Dynamic Response of Linear Systems,"

Earthcuake Engineering Research Center Report flc. EERC 73-11_, University of California, Berkeley, California, 1973 7 Robinson, E. A. , Multichannel Time Series Analysis, Holden-Day, pp. 62-64, 1967

8. "Diablo Canyon Nuclear Power Plant Unit No. 1, Containment Structure -

Finite Element Model, Dynamic Scismic Analycis," Report No. JABE-PGC-0C-1, l by John A. Blume c Associates, Engineers, pp. 5-7, July 1970.

s JOHN A. F)LU M(- (1 AG90CIATF.C P N %,N

j [ f I l

,-. 4 JAN P 3 76 i I W. l t

1

• j Docket Nos.: (0-275/323 MS: 27-11 '

l R. C. DeYoung, Assistant Director , I

for Light Water Reactors, Croup 1 '

Division of Reactor Licensing i DIABLO CANYON SITE UNITS 1 & 2, DOCKET NOS. 50-275/323 i

Plant Name: Diablo Canyon Site, Units 1 and 2 l Docket Nos.: 50-275/323 Responsible RL Branch & Project Manager: LWR 1-3, D. Allison l Responsible SS Branch & Technical Reviewer: MEB, P. Chen Requested Coupletion Date: N/A Description of Response: Supplement to Safety Evaluation Report Review Status: Incomplete Information regarding the potential earthquaka ef fects of the Ibagri f ault zone was submitted by the applicant in Anandrent 37 to the FSAR and has been reviewed by the Mechanical Engineering Branch. The MED has also performed a selectivo sois nic design adoquacy audit of  !

mechanical and electrical components during the week from April 28th.  !

g to May 2nd., 1975. The attached supplement to the Safety Evaluation I Report contains the conclusion of tha audit and review.

)

\ l j R. R. Maccary, Assistant Director j

' for Engineering I l

Division of Systems Safety j f cc v/ enc 1: cc w/o eac1:

, 3. Eisenhut NRR R. Boyd, IL R. Heineman, SS W. Mcdonald, MIPC

, S. Varga, RL i M. Kahnemuyi, SS

0. Parr, RL D. Allison, RL Docket Files 50-275 & 323 6 J. Knight, SS NRR Reading File U. Brasumer, SS SS:MEB File P. Chen, SS

. o , ,,c . , SS:MEB SS:MEB SS:MEB SS:AD/E

.vaa-.* PYChen:jn_ HLBrammer _ _JPKnight _RRMaccary._ _

oars * .1/__E6 .l / ./Z6 _1/_/7.6 _1/_D6 ___

Form AEc.)le (Rev. 9 m AICM 0240 W v. s. oavs ma u s ar ramtme or rec o s m.m.a u

. L -

ierm9n yp. . -

5 (

< o SUPPLEMENT TO THE SAFETY EVALUATION REPORT DIABLO CANYON UNITS 16 2 DOCKET NOS. 50-275 AND 50-323 3.9 Mechanical System and Components 3.9.3 Seismic Design Audit A selective seismic design adequacy audit of safety related mechanical components was conducted at the applicant's office.

The audit consisted of an evaluation of the maximum credible earthquake on the Hosgri fault zone (0.5g maximum ground acceleration for the safe shutdown conditions) and its ef fects on existing safety related mechanical components. In addition, the applicant has submitted Amendment #37 to the Final Safety Analysis Report concerning the subject. The applicant has stated, and our audit has confirmed, that extra conservatism was built into the original input floor response spectra and the method of analysis for safety related mechanical components. in addition,  !

the applicant has complied with the ASME Code design limits in the design of these components. We therefore conclude tha t the seismic analyses and/or testing for the safety related mechanical components in the Diablo Canyon Units 1 & 2 haveprovided reasonable assurance that these components will function properly under the loads from vibratory forces imposed by the 0.5g maximum ground acceleration.

(

(

w .. o 3.10 Seismic Qualification of Category 1 Instrumentation and Electrical Equipment A selective seismic design adequacy audit of safety related instrumentation and electrical equipment was condue:cd at the applicant's office. The audit consisted of an evaluation of the i

maximum credible carthquake on the Hosgri f ault zone (0. 5g ' maximum ground acceleration for the safe shutdown conditions) and its l I

ef f ects on existing safety related instrumentation and electrical equipment. In addition, the applicant has submitted Amendment

1. 37 to the Final Saf ety Analysis Report concerning the subject.

i The applicant has stated, and our audit has confirmed , that extra conservatism was built into the original input floor response spectra i

and the method of analysis for safety related instruraentation and electrical equipment. In addition, the applicant has complied with the IEEE Standard 344, 1971 in the design of these components.

gg We therefore conclude that the seismic analyses and/or testing for the safety related instrumentation and electrical equipment  ;

in the Diablo Canyon Units 1 & 2 ha/c provided reasonable assurance that these components will function properly under the loads from 1

vibratory forces imposed by the 0.5g maximum ground acceleration. I l

l