ML20076L385

Suppl to Independent Design Verification Program Initial Responses to First Set of Interrogatories.Certificate of Svc Encl.Related Correspondence

ML20076L385
Person / Time
Site:	Diablo Canyon
Issue date:	07/15/1983
From:	Raskin D LOWENSTEIN, NEWMAN, REIS, AXELRAD & TOLL
To:	Reynolds J, Strumwasser M CALIFORNIA, STATE OF, CENTER FOR LAW IN THE PUBLIC INTEREST
References
ISSUANCES-OL, NUDOCS 8307190153
Download: ML20076L385 (16)

Text

IUL*.TE COEIPc.EPONDEMI; law CFFsCES IDWENSTEIN, NzwxAN, REIS & AxzLnAn, P. C.

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1. N5w Michael J. Strumwasser, Esquire W W 3580 Wilshire Boulevard $-

Suite 600 Los Angeles, CA 90010 t N 131983 5 ) y / ,

C&ccr rwg Joel R. Reynolds, Esquire 'N ', d Center for Law in the Public ')J G'<

Interest

_f 10951 West Pico Boulevard Third Floor Los Angeles, CA 90064 Re: Pacific Gas and Electric Company (Diablo Canyon Nuclear Project, Units 1 and 2), Docket Nos.

50-275 OL, 50-323 OL

Dear Mr. Strumwasser and Mr. Reynolds:

The enclosed interrogatory responses supplement the

' Independent Design Verification Program's initial responses to your first set of interrogatories, which were filed by PGandE on May- 23, 1983. The enclosed responses answer Inter-rogatory One with respect to the three ITR's (46, 47 and 49) which have been issued since that date.

Sincerely, 4E David B. Paskin Attorney for the Independent Design Verification Program Enclosures cc: Service list B307190153 830715 PDR ADOCK 05000275 O PDR

- 1-46-1 ITR-46 Additional Verification of Selection of System Design Pressure and Temperature and Differential Pressure Across Power - Operated Valves

1. With respect to each ITR, including all revisions, except ITR 36 and 38, state:

a. What contractors and subcontractors to the IDVP worked on the ITR?

Answer:

Teledyne Engineering Services Stone & Webster Engineering Corporation (SWEC)

b. The person employed or retained by the IDVP or its subcon-tractors most knowledgeable about the ITR.

Answer:

John Edward Krechting, Project Engineer, SWEC

c. The person employed or retained by the IDVP or its subcon-tractors most knowledgeable about:

(i) data collection for the ITR; Answer:

Karl Andrew Swenson, Lead Power Engineer, SWEC (ii) analyses performed for the ITR; Answer:

! Karl Andrew Swenson l

(iii) the conclusions of the ITR;

! . Answer:

John Edward Krechting I

+ ~ - -

. ~ . .. - - .

a 2 1. - 1-46-2 p

(iv) documentation of the ITR.

Answer:

Karl Andrew Swenson

d. What reports the IDVP received from the DCP in connection l

-with the ITR - and, with respect to each, whether the IDVP b relied upon it.

! Answer:-

Relied Report On o FSAR Yes.

o Westinghouse System Description from Steam Systems Yes.

Design Manual-o Identification of revision dates to the applicable Yes.

i design codes for piping, valves, flanges, and equipment o DCNPP-1 Technical Specifications- Yes.

l o Basis for design pressure and temper,ature selection Yes.

including calculations o Minimum wall calculation for 24" safety valve headers Yes.

(Line numbers 1065,1066)

I o Main Steam Pressure vs. Plant Load Curve Yes.

I o- Information provided by Design Criteria Memorandum Yes.

M46 as it applies to-the CCW and MS Systems fo: Index for Design Criteria Memoranda No.

o Checklist of'all mechanical equipment, piping Yes.

fittings and components reviewed o Checklist of power - operated valves Yes.

l i

.c !. ,

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

1-46-3

e. In categorical terms, what other information the IDVP received from the DCP in connection with the ITR, and with respect to each category:

(i) whether the IDVP independently verified the information received; (ii) if it did, how it verified the information.

Answer:

Information Verification o Specifications or Specification No.

Data Sheets for all system equip-ment that includes rated tempera-ture and pressure o Set points and size of all pressure No.

or thermal relief valves o Specification Data Sheets for all No.

regulating valves, including infor-mation on maximum differential pressure for actuator sizing o All piping drawing showing equip- Yes; various components were ment and piping elevations field verified for elevation o' Notification to the IDVP that the No.

systems identified in section 4.2 of ITR 34 have been reviewed by the DCP and the results of that review are final l

0 Component cooling water pump curves No.

l

f. What computer models were employed in performing analyses in con-l.

! nection with the ITR:

Answer:

None. ,

l l

1-47-1 ITR-47 Additional Verification of Environmental Consequences of Postulated Pipe Ruptures Outside of Containment

1. With respect to each'ITR, including all revisions, except ITR-36 and ITR-38, state:

a. What contractors and subcontractors to the IDVP worked on the ITR?

Answer: .

Teledyne Engineering Services Stone & Webster Engineering Corporation (SWEC)

b. The person employed or retained by the IDVP or its subcon-tractors most knowledgeable about the ITR.

Answer:

John Edward Krechting, Project Engineer, SWEC 4

c. The person employed o'r retained by the IDVP or its. subcon-tractors most knowledgeable about:

(i) data collection for-the ITR; Answer:

Charles Frances Bergeron, Lead Nuclear Engineer, SWEC (ii) analyses performed for the ITR; j Answer:

Charles Frances Bergeron (iii) the conclusions.of the ITR; Answer:

! John Edward Krechting (iv) documentaticn of the ITR; 1

O n - r --

e

- - 1-47-2 Answer:

Charles Frances Bergeron

d. What reports the IDVP received from the DCP in connection with- the ITR and, with respect to each, whether the IDVP relied upon it.

Answer:

Relied Report On o PGandE completion package for E01 File 8001 Yes.

o ' Letter from AEC to PGandE, " General Information Yes. -

Required for Consideration of the Effects of a Piping System Break Outside Co'ntainment", 12-18-72 o Letter from AEC to PGandE, " General Information Yes.

Required for Consideration of the Effects of a Piping System Break Outside Containment",1-29-73 o Computer Program FLUD Description Yes.

o DCP calculation PT-2.1: Area GE/GW-Elevation 115', Yes.

Elevation 100', and Elevation 85', Pressure and Temperature Analysis in Compartments Due To Pipe Break Outside Containment o DCP calculation M-222: Compartment Characteristics Yes, for GE and GW Areas o DCP calculation M-287: GE/GW, Building Structural Yes.

Characterization i

o DCP Calculation M-221: Compartment Characteristics Yes.

for Turbine Building f

L o DCP calculation PT-1.1: Pressure and Temperature Yes.

AnalysisforTurbineBuilding(As-BuiltConditions)-

Computer Model, Echo Input, and Blowdown Data; Com-l partment Peak Pressure and Temperature Results -

l 0 DCP Calculation M-297 (sections 1, 2, & 3): Physical Yes.

Characteristics of Compartments.in the Auxiliary Building - Unit 1

l 1-47-3 Relied Report On o DCP calculation No. 2202: Circumferential Pipe Yes.

Break in Steam Supply Line to Auxiliary Feedwater Turbine o DCP calculation No. 2205: Flow Rates Through Pipe Yes.

Breaks in Lines; 112, 113, 1663, 26, 1749, 1750, and 593 o DCP calculation M-355: Pressure - Temperature Yes.

Analysis for the Auxiliary Building-(H, K, J, L) -

Assumptions on worst pipe and worst break in each compartment and deletions of vent paths o DCP calculation No. 2207: Auxiliary Building Yes.

Pressure / Temperature Transient (Area L) o DCP calculation No. 2206: Pressure and Temperature Yes.

in Auxiliary Building Compartments Due to Pipe Break o PGandE letter to NRC, dated 1/28/80, re: auxiliary Yes.

feedwater flow rate o Information from PGandE providing tu'rbine building Yes.

galbestos siding data o Information from PGandE providing data on bird Yes.

screen located in turbine building roof monitor l

o Information from PGandE that provided data on Yes.

blowout panel in area GW

e. In categorical terms, what other information the IDVP l

received from the DCP in connection with the ITR, and with respect to each category:-

(i) whether the IDVP independently verified the infor-l mation received; l

(ii)' if it did, how it verified the information.

l L

i

I I

1-47-4 Answer:

Information Verification o Equipment Location Yes; general locations of equipment, compartment ar-rangements, and compartment openings in areas GE, GW, and the turbine building (el 140') were field verified for development of geometric models.

o Concrete drawings Yes; same.

o Drawings which show building Yes; same.

penetrations o Main steam Yes; general location of main piping schematic steam system in areas GE, GW, and the turbine building were field verified for develop-m,ent of geometric models, o Piping and mechanical Yes; same.

drawings o Structural steel drawings Yes; general locations of steel and siding in areas GE, GW, and the turbine building (el 140') were field verified for development of geometric models, o Turbine building siding Yes; same.

drawings o PGandE Drawing No. 049021-18 No.

Piping Specification Index o Drawing No. 69-XA-25-9 No.

assembly of 28-inch x 24-inch x 28-inch Main Steam Line Valve i

1-47-5 Verification Information o PGandE Drawing No. 102040-9 No.

.Line Designation Table o CRVP system duct drawings Yes; field verified for general location of equipment ducts.

o PGandE Drawing No. 59650 Yes; field verified general Roof Access Details-Turbine location of opening in roof Building o Air Conditioning Control Room Yes; field verified general Pressurization System Ducting location in turbine building Details Drawings for development of geometric nodalization,

f. What computer models were employed in performing analyses in connection with the ITR:

(1) if the model was obtained from an outside source, Answer: .

None f.(ii) if the model was not obtained from an outside source,

- the identity of the person or persons having over-all responsibility for_ developing the model,

- the name or names by which the model is known, the general function of the model,

- the computer language in which the model was

. written, .

in general, what measures were taken to verify the accuracy of the model,

- the manufacturer and model number of - the computer or computers on -which the computer model was run in connection with the ITR.

l i

l

"Y

-*- 1-47-6 .

Answer:

- SWEC

- Version 12, Level 03, NU-092, Subcompartment Transient Response (THREED)

- The program calculates the transient pressure, temperature, and humidity in subcompartments following a postulated rupture in a moderate or high energy pipeline.

- FORTRAN IV - 98 percent ,

BAL - 2 percent

- Benchmarked with industry codes RELAP 4 Mod 5 and COMPARE Mod 0 and manual verification of various phenomena.

IBM 370/3033 t

4

,-o , - , - , - - - -

1-49-1 ITR-49 Additional Verification Circuit Separation and Single Failure Review of Safety-Related Electrical Equipment

1. With respect to each ITR, including all revisions, except ITR 36 and 38, state:

a. What contractors and subcontractors to the IDVP worked on the ITR7 Answer:

Teledyne Engineering Services Stone & Webster Engineering Corporation (SWEC)

b. The person employed or retained by the IDVP or its subcon-tractors most knowledgeable about the ITR.

Answer:

John Edward Krechting, Project Engineer, SWEC

c. The person employed or retained by the IDVP or its subcon-tractors most knowledgeable about:

-(i) data collection for the ITR; Answer:

Frank James Rezendes, Lead I&C Engineer, SWEC (ii) analyses performed for the ITR; Answer:

Frank James Rezendes (iii) the conclusions of the ITR; Answer:

John Edward Krechting

I .

1-49-2 (iv) documentation of the ITR.

Answer:

Frank James Rezendes 1

d. What reports the IDVP received from the DCP in connection with the ITR and, with respect to each, whether the IDVP relied upon it.

Answer:

Relied Report On o FSAR Yes.

o PGandE Resolution packages for E0I Files 8017 Yes.

and 8057.

e. In categorical terms, what other information the IDVP received from the DCP in connection with the ITR, and with respect to each category:

(i) whether the IDVP independently verified the information received; (ii) if it did, how it verified the information.

Answer:

Information Verification o Electrical schematics Yes; for selected sample sys-tems mutually redundant cir-cuits identified by DCP analy-sis o Electrical connection diagrams Yes; field verified separation for selected sample systems o Letter from PGandE. Yes; verified DCP circuit separation review for selected sample systems verified DCP performed o' DCP failure analysis Yes; single failure analysis

e 1-49-3

~ ,

i f. What computer models were employed in performing analyses in con-nection with the ITR:

Answer:

None.

4 2

1 4

0 3

0'

~

3 D

STATE OF MASSACHUSETTS SS:

COUNTY OF MIDDLESEX l

The undersigned, William E. Cooper, being duly sworn this 13th day of July,1983, upon his oath states that he is employed by Teledyne Engineering Services (TES) as a Consulting Engineer and is assigned as Project Manager for the DCNPP-1 IDVP for which Teledyne Engineering Services is the Program Manager, that he is informed en the matters of inquiry of Interrogatory 1 (a) through (f) of the First Set of Interrogatories Propounded to Pacific Gas and Electric Company by Governor Deuksejian and Joint Intervenors; that in answering the above and foregoing Interrogatory with respect to ITR's 46, 47 and 49, he has personally revicwed or caused others to review the files and records of Teltdyne Engineering Services and Stone & Webster Engineering Corporation; has caused information to be gathered from employees and of ficers of the above; and that the answers to the above and foregoing interrogatory are true and correct as he has been informed and verily believes.

$~  %

William E. Cooper July 13, 1983 f]maswt'/h . Z5m L -

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3 UNITED STATES OF AMERICA s

NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING APPEAL BOARD In the Matter of- )

)

PACIFIC' GAS AND ELECTRIC COMPANY ) Docket Nos. 50-275 OL

) 50-323 OL (Diablo Canyon Nuclear Power Plant ) i Units 1 and 2) )

CERTIFICATE OF SERVICE I hereby certify that copies of the Independent Design Verification Program's supplemental answers to Governor George Deukmejian's

' First Set of Interrogatories have been served on the following 4 by deposit in the United States mail, first class, postage pre-7 paid, this 15th day of July 1983: >

Dr. John H. Buck Dr. Jerry Kline i Atomic Safety and Licensing Appeal Administrative Judge Board Atomic Safety and Licensing U.S.. Nuclear Regulatory Commission Board Washington, D.C. ~20555 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 I 'Dr.=W. Reed Johnson

. Atomic Safety and Licensing Appeal Philip A. Crane., Jr., Esq.

Pacific Gas and Electric Company Board U.S. Nuclear Regulatory Commission P.O.. Box ~7442 Washington, D.C. 20555 San Francisco, CA 94120 Thomas S. Moore, Esq., Chairman Mr.. Frederick Eissler Atomic Safety and Licensing Appeal Scenic Shoreline Preservation Conference, Inc.

Board (U.S. Nuclear Regulatory Commission 4623 More Mesa Drive l

Washingtoni D.C. 20555 Santa Barbara, CA 93105 L

John F.' Wolf, Esq. Mrs. Raye Fleming

' Administrative Judge 1920 Mattie Road l

Atomic-Safety"and Licensing Board Shell Beach, CA 93449

'U.S. Nuclear Regulatory Commission Richard E. Blankenburg, p

Washington,.D.C. '20555 Co-publisher-I 1Mr. Glenn O. Bright Wayne:A. Soroyan, News' Reporter.

Administrative Judge South County Publishing Company

.P.O.-Box 460 Atomic Safety.and Licensing Board.' -Arroyo. Grande, CA 93420 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Michael J.:Strumwasser,-Esq.

Lawrence J.LChandler

. Susan L.'Durbin, Esq..

, Peter H.>Kaufman, Esq.

Office of Executive Legal Director ~3580 Wilshire. Blvd., Suite'600

BETH 042 Los Anaeles, CA 90010

'U.S. Nuclear Regulatory;Ccamission-zwashington,.D;C. '20555

_u__._a-______2 ___.s - . . . . . _ . - . . , , . , , . . . , _ . _ , v.m ..,y ., y p... , .,,4, _-

3 y., ,w,

Elizabeth Apfelberg Harry M. Willis

- 1415 Cozadero Seymour & Willis San Luis Obispo, CA 93401 601 California St., Suite 2100

• San Francisco, CA 94108 Mr. Gordon Silver Mrs. Sandra A. Silver Janice E. Kerr, Esq.

1760 Alisal Street Lawrence Q. Garcia, Esq.

San Luis Obispo, CA 93401 350 McAllister Street San Francisco, CA 94102 Joel R. Reynolds, Esq.

John R. Phillips, Esq. Mr. James O. Schuyler Center for Law in the Public Nuclear Projects Engineer Interest Pacific Gas and Electric Company 10951 West Pico Boulevard 77 Beale Street Third Floor San Francisco, CA 94106 Los Angeles, CA 90064 Paul C. Valentine, Esq.

Arthur C. Gehr, Esq. 321 Lytton Avenue Snell & Wilmer Palo Alto, CA 94302 3100 Valley Center Phoenix, AZ 85073 Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Mark Gottlieb Washington, D.C. 20555 California Energy Commission MS-18 Atomic Safety and Licensing Appeal 1111 Howe Avenue Board Sacramento, CA 95825 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Bruce Norton, Esq.

Norton, Burke, Berry & French, Docketing and Service Section P.C. U.S. Nuclear Regulatory Commission 2002 E. Osborn Road Washington, D.C. 20555 P.O. Bcx 10569 Phoenix, AZ 85064 Mr. Thomas H. Harris, Energy Writer San Jose Mercury News David S. Fleischaker, Esq. 750 Ridder Park Drive P.O. Box 1178 San Jose, CA 95190 Oklahoma City, OK 73101 John Marrs, Managing Editor Richard B. Hubbard San Luis Obispo County MHB Technical Associates Telegram-Tribune 1723 Hamilton Avenue - Suite K 1321 Johnson Avenue San Jose, CA 95125 P.O. Box 112 San Luis Obispo, CA 93406 lh $ Aw'

~ '

David'B. Raskih Attorney For The Independent Design Verification Program