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Summary of 871216 Meeting W/Util Re leak-before-break Piping Analysis & Amplified Response Spectra for Floors.List of Attendees & Presentation Slides on leak-before-break & Amplified Response Spectra Encl
	ML20149D740
Person / Time
Site:	Comanche Peak
Issue date:	02/01/1988
From:	Malloy M; NRC OFFICE OF SPECIAL PROJECTS
To:	; NRC OFFICE OF SPECIAL PROJECTS
References
	NUDOCS 8802090617
	Download: ML20149D740 (51)
	v • d • e

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~g UNITED STATES 8 n NJCLEAR REGULATORY COMMISSION 5 aj WASHINGTON, D. C. 20555

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/ February 1, 1988 Docket Nos. 50-445 and 50-446 APPLICANT: Texas Utilities Electric Company (TV Electric)

FACILITY: Comanche Peak Steam Electric Station (CPSES),

Units 1 and 2

SUBJECT:

SUMMARY

OF MEETING ON DECEMBER 16, 1987 - LEAK BEFORE BREAK PIPING ANALYSIS AND AMPLIFIED RESPONSE SPECTRA FOR FLOORS AT CPSES On December 16, 1987 NRC staff met with representatives of TU Electric to discuss three areas which are likely to generate future FSAR changes. The meeting notice (Enclosure 1) listed the first area to be discussed as "alternative application of ACI 359 for tangential sheer stress on the reactor containment." This agenda item was withdrawn at TV Electric's request because they had recently determined that they are able to meet current FSAR com-mitments and do not need to take advantage of later code changes. The meeting notice listed the second area of discussion as "new jet modeling to implement revised GDC 4." However, TU Electric proposed to generally discuss use of the new broad-scope GDC 4 rule (leak before break), and requested that the jet modeling topic be deferred to a future date. The staff agreed to accomodate this agenda change. The third agenda item listed in the meeting notice was "amplified response spectra for the service water structure." The list of attendees at this meeting is provided in Enclosure 2.

Implementation of GDC 4 Broad-Scope Rule Change for CPSES The broad-scope GDC 4 rule changes, published on October 27, 1987 (52 FR 41288),

allow the use of advanced fracture mechanics analysis for excluding dynamic effects of pipe ruptures in nuclear power plants from the design basis, provided it is demonstrated that the probability of pipe rupture is extremely low under conditions consistent with the design for the piping. TV Electric has contracted with R. L. Cloud and Associates to perform the required fracture mechanics analysis for CPSES, Unit 1 piping TU Electric representatives described the scope and methodology of the analysis which will be conducted over the next few months (see slides in Enclosure 3). The NRC staff advised TV Electric to closely follow the safety injection (SI) piping leak discovered in early December 1987 at Farley or any other leaks or breaks that may occur industry-wide. The staff indicated that in view of the Farley SI piping leak, SI system piping may not be able to be excluded for CPSES Unit I under the broad-scope rule changes. The staff requested TU Electric to provide additional information regarding welded attachments and its role in the determination in their analysis of the highest stress locations.

TU Electric anticipated that their analysis would be completed sometime in February 1988, identifying the equir nent and dynamic effects that can be {

eliminated and the necessary FSAR changes. TV Electric stated that they do not i expect equipment qualification to be affected by efforts in this area, l l

BBR298M1 Bi8Shp A

s s Sumary of Meeting on 12/16/87 Amplified Response Spectra (ARS)

TV Electric representatives described Stone and Webster Engineering Corpo-ration's (SWEC's) efforts to validate CPSES seismic building response spectra.

This validation was performed using existing design bases but using up-to-date analysis techniques since SWEC was unable to follow through previous calculations using the existing records. The staff stated its concern that these calculations were not reconstructed consistent with the FSAR, as would normally be the case for validated documents. The NRC staff recomended that TV Electric, as a min-imum, describe the validation process used by SWEC in this area in the Civil / Structural Project Status Report (PSR) and describe how all the licensing commitments have been satisfied.

SWEC's analysis has shown that the existing seismic response spectra were gen-erally acceptable and conservative with respect to the SWEC methodology, with the exception of the spectra for the service water intake structure and Category I make-up tanks. For these areas SWEC found they needed to develop new design spectra which will then be used to reanalyze the structures. A copy of the presentation slides used in the discussion of this area are provided in Enclosure 4. TU Electric stated that they do not intend to change any technical requirements of the FSAR with regard to ARS. However, they do anticipate amending the FSAR in early 1988 by removing material that was never used which is not ap-plicable to structures as finally designed.

The staff offered to meet again with TV Electric after the Civil / Structural PSR and the FSAR Amendment are issued to provide feedback on the ARS validation process.

Future Action:

1. Follow-up on and consider Farley SI system piping leak and other leaks or breaks industry-wide in the fracture mechanics analysis for CPSES piping. (TV Electric)

2. Provide additional information to the NRC staff regarding welded attach- i ments and the determination of the highest stress locations in piping with l welded attachments. (TV Electric)

3. Provide a description of SWEC's ARS validation process for CPSES seismic buildings in the Civil / Structural PSR. Consider including descriptions of the validation process used for other areas in other PSRs. (TV Electric)

4. Meet following issuance of the Civil / Structural PSR and FSAR Amendment to discuss the ARS validation ess. (NRC/T ectric)

WD linda Malloy, 4'h roject ager Comanche Peak Project Di sion Office of Special Projec.s

Enclosures:

1. Meeting Notice

2. List of Attendees

3. Presentation Slides on Leak-Before-Break

4. Presentation Slides on ARS cc: See next page

's s W. G. Counsil Comanche Peak Steam Electric Station Texas Utilities Electric Company Units I and 2 CC:

Jack R. Newman, Esq. Asst. Director for Inspec. Programs Newman & Holtzinger, P.C. Comanche Peak Project Division Suite 1000 U.S. Nuclear Regulatory Commission 1615 L Street, N.W. P. O. Box 1029 Washington, D.C. 20036 Granbury, Texas 76048 Robert A. Wooldridge, Esq. Regional Administrator, Region IV Worsham, Forsythe, Sampels & U.S. Nuclear Regulatory Commission Wooldridge 611 Ryan Plaza Drive, Suite 1000 l 2001 Bryan Tower, Suite 2500 Arlington, Texas 76011 Dallas, Texas 75201 Lanny A. Sinkin Mr. Homer C. Schmidt Christic Institute Director of Nuclear Services 1324 North Capitol Street Texas Utilities Electric Company Washington, D.C. 20002 Skyway Tower 400 North Olive Street, L.B. 81 Ms. Billie Pirner Garde, Esq.

Dallas, Texas 75201 Government Accountability Project Midwest Office Mr. Robert E. Ballard, Jr. 104 East Wisconsin Avenue Director of Projects Appleton, Wisconsin 54911 Gibbs and Hill, Inc.

11 Penn Plaza New York, New York 10001 David R. Pigott, Esq.

Orrick, Herrington & Sutcliffe 600 Montgomery Street Mr. R. S. Howard San Francisco, Califorr.ia 94111 Westinghouse Electric Corporation P. O. Box 355 Anthony Z. Roisman, Esq.

Pittsburgh, Pennsylvania 15230 Suite 600 1401 New York Avenue, NW Renea Hicks, Esq. Washington, D.C. 20005 Assistant Attorney General Environmental Protection Division Robert Jablon P. O. Box 12548. Capitol Station Bonnie S. Blair Austin, Texas 78711 Spiegel & McDiannid 1350 New York Avenue, NW i Mrs. Juanita Ellis, President Washington, D.C. 20005-4798 l Citizens Association for Sound Energy j 1426 South Polk George A. Parker, Chairman Dallas, Texas 75224 Public Utility Committee Senior Citizens Alliance Of 1 Ms. Nancy H. Willians Tarrant County, Inc. ;

CYGNA Energy Services 6048 Wonder Drive 2121 N. California Blvd., Suite 390 Fort Worth, Texas 76133 Walnut Creek, CA 94596 I

i

i s W. G. Counsil Comanche Peak Electric Station Texas Utilities Electric Company Units 1 and 2 cc:

Joseph F. Fulbright Fulbright 8 Jaworski 1301 McKinney Street Houston, Texas 77010 Roger D. Walker Manager, Nuclear Licensing Texas Utilities Electric Company Skyway Tower 400 North Olive Street, L.B. 81 Dallas, Texas 75201 Mr. Jack Redding c/o Bethesda Licensing Texas Utilities Electric Company 3 Metro Center, Suite 610 Bethesda, Marylano 20814 William A. Burchette, Esq.

Counsel for Tex-La Electric Cooperative of Texas Heron, Burchette, Puckert & Rothwell Suite 700 1025 Thomas Jefferson Street, NW Washington, D.C. 20007 1

James P. McGaughy, Jr.

GDS Associates, Inc.

Suite 720 4 1850 Parkway Place Marietta, Georgia 30067 Administrative Juoge Peter Bloch U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Elizabeth B. Johnson Administrative Judge Oak Ridge National Laboratory P. O. Box X, Building 3500 Oak Ridge, Tennessee 37830 ;

Dr. Kenneth A. McCollom 1 1107 West Knapp l Stillwater, Oklahoma 74075 l

Dr. Walter H. Jordan i c/o Carib Terrace Hotel 522 N. Ocean Boulevard Pompano Beach, Florida 33062 l i

., i ENCLOSURE 1 i

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UNITED STATES i

I g NUCLEAR REGULATORY COMMISSION !

a wasmorow.o.c. rosse i

December 14, 1987

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Docket Nos.: 50-445 and 50-446 MEMORANDUM FOR: Christopher I. Grimes , Director Comanche Peak Project Division Office of Special Projects FROM: Melinda Malloy, Project Manager Comanche Peak Project Division Office of Special Projects

SUBJECT:

FORTHCOMING MEETING WITH TV ELECTRIC Date & Time: Wednesday, December 16, 1987 8:30 - 10:30 AM Location: 4350 East-West Highway Room 319 Bethesda, MD 20810

Purpose:

For Applicant to discuss future FSAR changes as follows:

1. alternative application of ACI 359 for tangential sheer stress on reactor containment

2. new jet modeling to implement revised GDC 4

3. amplified response spectra for service water structure Participants *: NRC TO Electric C. Grimes 0. Lowe J. Lyons D. Woodlan, et al.

M. Malley 0, Norkin D. Terao

Meetir.gs between NRC technical staff and applicants for licenses are ooen for interested members of the public, petitioners, intervenors, or other parties to attend as observers pursuant to "Open Meetings and Statement of NRC Staff Policy," 43 Federal Register 28058, 6 78.

, ,e .

1

,f elinda Mal o , Pro ec anager Comanche Peak Project ision Office of Special Projects cc: See next page CONTACT (S): M. Malloy or Annette Vietti-Cook (301)492-7624 (301)492-4555

o, .yeeting Notice 12/16/87 ,, DISTRIBUTION Docket File NRC PDR Local PDR OSP Reading CPPD Reading SEbneter/JAxelrad CGrimes '

PMcKee JLyons RWarnick CJamerson BZalcman MMalloy AVietti-Cook CPPD Staff WLanning OGC-Bethesda FMiraglia EJordan JPartlow SMatthews JG11111and, PA/RIV GPA/"A ACRS(10)

Sherry y g_.-.~ -

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i i ENCLOSURE 2 NRC/TU Electric Meeting December 16, 1987 LIST OF ATTENDEES Name Affiliation Melinda fialloy NRC/CPPD

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ENCLOSURE 3 1

TU ELECTRIC PRESENTATION SLIDES ON LEAK-BEFORE-BREAK ANALYSIS FOR CPSES, UNIT 1

1 i

INTRODUCTION

LEAK BEFORE BREAK FOR CPSES-1

- ENGINEERING EVALUATION FOR ELIMINATION OF DYNAMIC EFFECTS

REGULATORY ACCEPTANCE

- BROAD SCOPE RULE

- SRP 3.6.3 (ISSUED FOR COMMENT)

- BV-2 PROGRAM COMPLETE

- SEVERAL IN-PROCESS PROGRAMS

^

PROGRAM EXPERIENCE

- BV-2 (RLCA, SWEC) - LEAD PLANT COMPLETED AND ACCEPTED

- VOGTLE (WEST.)

- SOUTH TEXAS (WEST.)

SCOPE

CLASS 1 STAINLESS STEEL PIPING ONLY

- RCS (INCLUDING SURGE LINE)

- SIS

- RHR

>,10" DIAMETER (INITIAL SCOPE)

PRIMARY LOOP (NARROW SCOPE RULE)

CURRENTLY IN DESIGN BASIS J

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PIPING SYSTEMS UNDER REVIEW PIPE SIZE PIPING SYSTEM FSAR INCH POSTULATED UNDER REVIEW FIGURE (MM) MATERIAL BREAKS RESTRAINTS SIS 52-55 10 SA 376, 16 14 (LO PRESS INJ) (254) TYPE 316 SIS 52-55 10 SA 376, 40 12 (LO PRESS IN-J (254) TYPE 316/304

& RHR SUPPLY)

HR 64 12 SA 376, 12 1 .

(RHR RETURN) (305) TYPE 316/304 RCS 65 14 SA 376, 4 10 (SURGE LINE) (356) TYPE 304 OTHER CANDIDATES SIS 49 6 SA 376, 6 0 (HI PRESS INJ) (152) TYPE 316

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! MOTIVATION FOR PROGRAM I

ALTERNATIVE TO EVALUATING DYNAMC EFFECTS

REDUCED OBSTRUCTIONS l

FACLITATION OF ISI I

NPROVED ALARA EXPOSURE FOR NORMAL l OPERATION AND MAINTENANCE

. ELMNATION OF SPURIOUS NECHAMCAL INTERFERENCE l

IMPROVED PLANT RELIABUTY 1

l l

-- K

! LBB METHODOLOGY

SCREENING CRITERIA i

STRESS INFORMATION

MATERIALS / PROPERTIES

LEAK DETECTION STRATEGY

FRACTURE MECHANICS

RELATED TOPICS l

)

1 r

1 i

Lines SRP 3.6.2 Requiring 4- (Except arbitrary Protection intermediate breaks) v Target and Interaction Evaluations ir Screening:

Industry Experience, Economics Leak Detectability Margin Material Highest Stress Properties > < Locations (Normal +SSE)

With Minimum Material Properties

,r Limiting Detectable Leak Rate Leak Rate x Margin a Calculations 4 Normal Loads ir _

Margin on m Crack Stability 2 Normal +SSE Crack Size Evaluation ,

Loads

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Bigh Loads Loads LBB METHODOLOGY e 8

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l FINAL PIPING SYSTEMS PASSING LBB ANALYSIS (BVPS-2)

HARDWARE PIPING PIPE SIZE POSTULATED SYSTEM INCH (MM) MATERIAL BREAKS RESTRAINT SHIELD RCS 8 SA 376, 6 6 0 (203) TYPE 304 RCS 14 SA 376 13 8 0 (356) TYPE 304 RHS 10 SA 376, 1 0 0 (254) TYPE 316 RHS 12 SA 376, 1 1 0 (305) TYPE 316 SIS 6 SA 376, 20 7 5 (152) TYPE 316 SIS 12 SA 376, 28 10 3 (305) TYPE 304 TOTAL 69 32 8 TOTAL 40 I

i SCREENihG PROCESS

EXCESSIVE CORROSION (NCLUDING K3 SCC)

EROSION / CORROSION

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EXCESSIVE WATER hah 5AER

. FALURE FROM INDRECT CAUSES

NDUSTRY EXPERENCE

ECONOh4CS

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- WELD METAL

- SAFE ENDS

TENSILE (STRESS-STRAIN) l

TOUGHNESS (J-R)

GENERIC INDUSTRY DATA BASE USED TO AVOID TESTING

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AS-BUILT CONFIGURATIONS

FORCES AND MOMENTS

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= DEADWEIGHT

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.

DETERMINE HIGHEST STRESS LOCATION, INCLUDE ALL NODE POINTS ANCHOR-TO-ANCHOR 1

LEAK DETECTION STRATEGY

= SHOW MINIMlZATION OF UNCERTAINTIES

- PLUGGING

- PREDICTION (PICEP VAUDATION)

- MEASUREMENT TECHNIQUES

- PERSONNEL. AND

- FREQUENCY OF MONITORING

SHOW RELIABILITY, REDUNDANCY AND SENSITIVITY

REG. GUIDE 1.45

MARGIN IS 10

LEAK RATE THRESHOLD IS BASIS OF LBB ANALYSIS

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ENCLOSURE 4 TV ELECTRIC PRESENTATION SLIDES ON AMPLIFIED RESPONSE SPECTRA VALIDATION FOR CPSES FLOORS V

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SEISMIC ANALYSES NETHODOLOGY AND CRITERIA Item Design Basis (1) Foundation Mass Included (2) Foundation Springs Uniform Foundation Stiffness (3) Variation in Foundation typically Springs K/4 - K - 2K (variation to cover range of measured values)

(4) Damping Translation 10% maximum Rotation 5% maximum (5) Embedment Included (6) Analysis Technique Artificial Eqs SRSS i

BASIC SEISMIC DESIGN CRITERIA SSE 0.12 (Horiz) 0.08 (vertical)

OBE 0.06g (Horiz) 0.04 (vertical)

Horizontal Spectrum Reg. Guide 1.60 l Vertical Spectrum Newmark tail off 33 Hz to 50 Hz and break point G 4 Hz rather than 3.5 Hz l

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TABLE 1: SEISMIC ANALYSES METHODOLOGY AND CRITERIA Item Design Basis Stone E Webster (1) ' Foundation mass Included Excluded (2) Foundation Springs Uniform Foundation Layered System .
Stiffness (3) Variation in Foundation generally Measured variation Springs K/4 - K - 2K with depth (variation to cover range of measured values)
(4) Damping Translation 10 % maximum Material 2 % +
Rotation 5 % maximum Geometric (5) Embedment included Included (6) Analysis Technique Artifical Eqs C LASSI/ FLOR A SRSS SRSS BASIC SEISMIC DESIGN CRITERIA SSE .12 (Horiz) 0.08 (vertical)
OBE 0.06 g (Horiz) 0.04 (vertical)
Horizontal Spectrum Reg Guide 1.60 Vertical Spectrum Newmark tail off 33 Hz to 50 I!z and break point 94 Hz
, rather than 3.5 Hz Damping (Structural) Reg. Guide 1.61 Artificial Earthquakes Design Basis One horizontal and one vertical
, based on the above; duration 10 +
seconds ~
Stone 6 Webster three components, statistically independent based on Reg. Guide 1.60; duration 15+ seconds Control Motion Input at foundation level 008
CONRNCHE PERM SEISMIC STUDY RRS FROM THE ARTIFICIRL TIME HISTORY. Y DIRECTION E.M. FUENTES !
RMPLIFIED RESPONSE SPECTRA BY TIME HISTORY DATE OF RUN 3 NRR 1987 0.020 05cILLAT0ft Omfetmo cate. isses-csecs-Otr.oof-0 REVISION O o ARS FR9R SOTM mftfiritset TIME MIS.80itE309 e'
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INDEPENDENT CONSULTANTS Dr. James J. Johnson, EQE, San Ramon, CA Prof. Eduardo Kausel, MIT i Prof. Jose M. Roesset Universi~ty of Texas at Austin ,
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VALIDATION PROCEDUEE FOR CATECORY l STEDCTURE SPECTRA (1) Develop structural models (2) Develop foundation stratigraphy at each structure (3) Analyze structure and foundation system with STRUDL program. Calculate modes and frequencies..
(4) Analyze structure and foundation system with CIASSI .
Calculate acceleration response spectra at floors due to 3 independent ground motions.
(5) Analyze system with FIDRA. Remove excess energy by ratioing the CIASSI spectra with the FLORA results.
(6) Generate "worst" location spectra and envelop (7) Compare floor response spectra with design spectra .
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OBE RESPONSE SPECTRA CPSES BLDC.= RUXILIRRY ELEY.= 900.0 FEET DIR.= E-U DRMP.= 2 PERCENT SDLID=IMPELL DRSHED= CIBBS AND HILL
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SSE FLOOR RESPONSE SPECTRA CPSES BLDC.= CONTRINMENT ELEV.= 1051.8 FT DIR.= E-U DRMP., PVRC SOLID =lMPELL DASHED =C RND H Floure C. 153
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OBE FLOOR RESPONSE SPECTRR 'CPSES SLDC.= INTREE+ ELEV.= 838.0 FEET DIR.= N-S DRMP.= J PERCENT SOLID =IMPELL DASHED =SWEC f.
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INTERNAL STRUCTURE OF R.B.
ELEVATION : 860.00 FT EQUIPMENT DAMPING : 0.02 o_ SSE EARTHQUAKE to AZ : N-S
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INTERNAL STRUCTURE OF R.B.
ELEVATION 860.00 F T EQUIPMEN T DAMPING 0.02 a_ SSE EARTHOUAKE to AY VERT
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INTERNAL STRUCTURE OF R.B.
ELEVATION 860.00 FT EQUI 4 MENT DAMPING 0.02 o _, SSE EARTHQUAKE s AX :E-V
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~~a .>~~
SPECTRA VALIDATION PROGRAM CONCLUSIONS A) Design Basis Spectra Acceptable for (1) Auxiliary Building (2) Electric Building (3) Containment Shell (4) Containment Internals (5) Fuel Building (6) Safeguards Building (7) Specific Location Spectra used by Westinghouse B) New Design Spectra Developed for:
(7) SWIS l (8) Category 1 Tanks l
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. 3 30TVT~ '
February l', 1988 Suninary of Meeting on 12/16/87 .3.-
DISTRIBUTION Docket File NRC PDR Local PDR-
-0SP Reading CPPD Reading SEbneter/JA elrad CGrimes '
PMcKee JLyons RWarnick JHWilson M4 alloy AVietti-Cook DNorkin DTerao RHennann Slee CCheng LMarsh JRichardson !
LShao J0'Brien AMurphy MVagins RBosnak GArlotto OGC-Bethesda FMiraglia EJordan JPartlow ACRS(10 m) 7CFP 9W PPD:0SP AD:CPP MMallo m ietti-Cook JHWils 02// /86 02/ / /88 02/ / /88
- , - , - - - , - - , _ . , , --..,---...-eg

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