ML18032A699

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Rev 0 to Civil Engineering Branch Instruction CEB-CI 21.97, Operability Criteria for Pipe & Pipe Supports on TVA Class I Seismic Piping - Browns Ferry.
ML18032A699
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 12/10/1987
From:
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18032A698 List:
References
CEB-CI-21.97, TAC-R00304, TAC-R00305, TAC-R00306, TAC-R00319, TAC-R304, TAC-R305, TAC-R306, TAC-R319, NUDOCS 8801250364
Download: ML18032A699 (26)


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'87 1210 002 UHdbH~fotikb COPY 841 TVA Tennessee TENNESSEE VAI LEY AUTHORITY Division of Nuclear fnglneerlng ilKI I \8 Valley NI, I 5 I Aut'horlty CIVIL ENGINEERING BRANCH INSTRUCTION CEB-CI 21.97, TITLE, OPERABILITY CRITERIA FOR PIPE AND PIPE SUPPORTS ON TVA CLASS I SEISMIC PIPING BROGANS FERRY THIS DOCPiIENT CONSISTS OF 4 PAGES.

REVISION RO R2 R3 R4 R5 ISSUE DATE DEC 10 >987 PREPARED SE REVIEWED APPROVED cc: RIMS,SL26C.K

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OPERABILIT CRITERIA FOR PIPE AND PIPE SUFPORTS ON REVISION LOG TUA CLASS I SEISNIC PIPING BROWNS FERRY

Title:

CEB-CI 2I.97 Revision Dote No.

DESCRIPTION OF REVISION Approved Original Issue TVA I 0534 (eN OKS 4.7$ )

OPERABILITY CRITERIA FOR PIPE AND PIPE SUPPORTS CEB-CI 21.97 ON TVA CLASS I SEISMIC PIPING BROWNS FERRY TABLE OF CONTENTS PAGE 1.0 PlJRPOSE ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 1 2.0 SCOPE...,..., ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 1 3.0 PIPE STRESS EVALUATION CRITERIA ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 1 4.0 PIPE SUPPORT EVALUATION CRITERIA ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 1 5.0 DOCUMENTATION ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 4 6.0 REFERENCE ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 4 TVA I0535 (EN DES-7-77)

0 ILITY CRITERIA OR PIPE AND PIPE SUPPORTS ON TVA CLASS I SEISMIC PIPING BROWNS FERRY i;EB-CI z1.97 1.0 PURPOSE The purpose of this instruction is to provide engineering guidelines for implementing Browns Ferry operability criteria as applicable to non-torus attached pipe and pipe support modifications for TVA Class I seismic piping.

2.0 SCOPE These guidelines shall apply to all piping and supports on TVA Class I seismic piping, for whi.ch pipe or pipe support modifications are required; i.e., any physical modification of pipe or pipe support required as a result of the inability to qualify according to Design Criteria BFN-50-C-7103 and BFN-50-C-7104 (Reference 1 6 2).

Modifications will be prioritized into two groups; those that require implementation for operability and those that require implementation for design criteria. Operability modifications are those piping and pipe support modifications that do not comply with the cri.teria in this document, Design criteria modifications are those piping and pipe supports modifications that comply with the requirements of this document but are necessary for design criteria compliance.

3.0 PIPE STRESS EVALUATION CRITERIA

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For piping systems that do not meet the design criteria BFN-50-C-7103 a case by case piping system, operability review maybe performed as follows.

For the emergency loading combinations and stress. intensification factors as defined in BFN-50-C-7103, evaluate. the piping to ensure that the primary stress in the piping is less than 2 Sy and the secondary

~ stress in the piping is less than .Sy or ASME Section 10 and ll allowables of reference 5.

III Equation In cases where piping secondary exceeds the secondary stress allowables of reference 5 they may be shown to meet an augmented Class 2 and 3 fatigue evaluation (Reference 7).

Alternatively, the piping strains shall not exceed the limits of Code Case N-47, Appendix T.

The adjacent pipe supports shall meet allowables given in this criteria document.

4.0 PIPE SUPPORT EVALUATION CRITERIA 4.1 Load Combinations and Pi in Movements For prioritization the proposed pipe support modifications shall be evaluated only for the emergency loading condition in accordance with BFN-50-C-7103.

TVA I0535 (EN OES-7-77) UNE4 3 141M

OPERASILLTY CRITERlA FOR PlPE AND PIPE SUPPORTS ON TVA CLASS I SEISMIC PIPING BKOMNS FERRY CEO-CI 21.97 4.2 Allowable Limits The following limits shall be used to establish priorities for pipe support modifications.

4.2,1 Linear Su orts:

I The support member stresses shall not exceed the lessor of 1.2 Sy and 0.7 Su for tensile and flexural stresses, and 90 percent of the critical buckling stress as defined in AISC specification (Reference 3) for compressive loads. Shear stresses shall not exceed 60 percent of allowable stress for tensi.le and flexure stresses.

4.2.2 Standard Su ort Com onents:

These shall meet the emergency allowables of BFN-50-C-7103.

4.2.3 ~Bo itin The stress allowables for bolting shall be the greater of 70 percent of the minimum specified tensile strength or the minimum specifi.ed yield stress of the bolt mater ial.

4.2.4 Concrete E ansion Anchors:

The minimum factors of safety for concrete expansion anchors (wedge 6 shell types) shall be 2.0. (Reference 6).

4.2.5 Pi e to Pi e Su ort Ga Supports with pipe to pipe support total gap which exceeds 1/2" shall be modified unless acceptable in accordance with the evaluation in 4.2.6. In addition,

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the first support adjacent to equipment nozzles, anchors, penetrations, and active valves and body or stem supported valves shall be modified if the total gap exceeds the installation requirement of 5/32 inch maximum total gap. (Reference 4) 4.2.6 Load Sharin Between Su orts:

For supports that do not meet the interim allowable stress criteria presented herein and are not adjacent to an equipment nozzle, an anchor, a penetration, an active valve, or a body/stem-supported valve, a ease-by-case evaluation may be performed that, considers redistribution of load to adjacent supports. The effect of load redistribution on piping stress shall be considered in accordance with section 3.0.

TVA I0535 (EN OES-7-77) DNE4 3141M

'PERABILITY CRITERIA FOR PIPE AND PIPE SUPPORTS ON TVA CLASS I SEISMIC PIPING - BROWNS FERRY CEB-CI 2L.97 The adjacent pi,pe supports shall meet the allowables contained in this criteria document.

4.2.7 -

Constant and Vari. able S rin Su orts:

Shall be evaluated to accommodate the "maximum pipe movement" without bottoming out.

4.2.8 Subs stem Evaluations Portions of a stress analysis math model may be decoupled and a local analysis may be performed, to assess the need for the modification, provided appropriate overlap on model boundaries is considered.

Hand calculations, new subsystem models, and scaling techniques may be utilized in addition to computer calculations, The following section provide guidance for the evaluation of modifications required due to thermal loading, 4.2.8.1 Modifications Due to Thermal Loadin Support flexibility for specific supports may be utilized in the subsystem evaluations in lieu of conservative computer code default values to more realistically predict thermal loading.

The effects of gaps may be considered where large thermal loads result from the constraint of small thermal growths due to opposing supports.

4.2.9 Thermal Monitorin Modifications identified due to exceeding the swing angle, binding, or other potential thermal interferences on snubber, strut, and spring supports need not be a design constraint and may be deferred,'if visual monitoring shows no thermal binding or restraint in the support assembly. Addi.tionally, supports requiring modification due to unrealistic thermal loads will be monitored with instrumentation to determine the actual thermal loads.

TVA 10535(EN OES-7-77) uNE4 3141M

OPERABILITY CRITER FOR PIPE AND PIPE SUPPOKTS ON TVA CLASS I SEISMIC PIPING BROWNE FEKRY CEB-CI 21.97 5.0 DOCUMENTATION Engineering evaluations performed to determine the priority of modifications shall be documented in calculations performed in accordance with the applicable QA requirements.

6.0 REFERENCE

1. Design Criteria for Structural Analysis and Qualification of Mechanical and Electrical Equipment BFN-50-C-7103.
2. Design Criteria for'esign of Supports BFN-50-C-7104.
3. Specification for the Design, Fabrication, and Erection of Structural Steel Buildings, AISC 7TH and 8TH Editions.
4. Letter from R. L. Cloud Associates to TVA "Position Paper on Pipe to Support Gap Limit, "Letter No. P154-3 L-020, August 25, 1987.
5. ASME Section III, Subsection NC, 1983.
6. IE Bulletin No. 79-02, Revision 1, Supplement 1 dated August 20, 1079, Pipe Support Base Plate Designs Using Concrete Anchor Bolts.
7. NUREG/CR-2343, DATED June 1983, Comparisons of ASME Code Fatigue Evaluation Methods for Nuclear Class 1 Piping with Class 2 or 3 Piping.

TVA I0535 (EN DES-7-77) DNE4 3141M

USE OF ARTIFICIAL T I ME HI STORY BACf GROUND SUBMITTAL TO NRC ON 5/26/87 IMPORTANCE OF TIMELY APPROVAL 79-14/02 SMALL BORE

BAOWNS FEAAY SE I SN I C DESIGN BASES ORIGINAL

1. PEAK GROUND ACCELERATION OBE O. I g 0. Ig DBE<SSE> 0.2g 0.2g VERT. 2/3 Horiz. 2/3 Horiz.
2. EARTHQUAKE COMPONENT 2-D 2-D
3. SITE DESIGN SPECTRUM "HOUSNER" "HOUSNER" BASED ON AVERAGE BASED ON AVERAGE OF 4 EARTHQUAKES OF 4 EARTHQUAKES 4.

=

TINE HISTORY INPUT NOTION FOR SE I SHI C SYSTEM ANALYSIS 1940 EL CENTRO EARTHQUAKE TINE HISTORY (N-S COMPONENT)

ENVELOPING HOUSNER SPECTRUM ARTIFICIAL TIME HISTORY ENVELOPING HOUSNER SPECTRUM t

I C

BROWNS FERRY UNIT 2 79- 14/'79-02 PROGRAM PROGRAM OVERVIEW SCOPE PROGRAM

SUMMARY

STATUS COMPLETION PLAN SCHEDULE MOD I F I CAT. I.OM .PR I OR I T I ZAT I ON CRITERIA SYSTEM OPERABILITY CRITERIA SEISMIC DESIGN BASIS PIPING AND SUPPORT DES I GN CRITERIA REVIEW SUBMI TTALS

SUMMARY

BROWNS FERRY,UN I T 2 79- 14/79-02 PROGRAM SCOPE NRC BULLETIN 79-02 NRC BULLETIN 79-14 APPROXIMATE QUANTITIES 30 SYSTEMS 240 STRESS PROBLEMS 4000 SUPPORTS COMPLETED TORUS AND CRD 20 STRESS PROBLEMS SOO SUPPORTS REMAINING 79-14 PROGRAM 220 STRESS PROBLEMS 3500 SUPPORTS

BROWNS--F ERRY- -UN I T 2 79- 14/79-02 PROGRAM PROGRAM

SUMMARY

INITIAL WALKDOWNS NO DISCREPANCY

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PHASE I YES EVALUATE DISCREPANCY ISSUE NODS INSTALL VER IF I CAT I ON MOOS WALKDOWNS

~HASE II STRESS AND SUPPORT RESTART UN I T '

ANALYSIS COMPLETE CALCULATION ISSUE NODS

'HASE III, INSTALL,NODS FINAL REPORT

BROWNS FERRY UN I T 2 79-14/79-02 PROGRAM STATUS PHASE I COMPLETED WALKDOWNS DEVELOPED DATA BASE OF SUPPORTS ASSEMBLED DATA PACKAGES IDENTIFIED APPROX 600 DISCREPANCIES (3 UNITS) 510 ACCEPTABLE OR MINOR 90 MODIFICATIONS RESOLVING AUDIT FINDINGS PHASE II

.I N I T I ATED VERIFICATION WALKDOWNS INITIATED ANALYSIS CONT I NU I NG DATA BASE ACT I V I T I ES

BAOWNS FEAAY UNIT 2 79-14/79-02 PAOGAAN 1988 1989 OCT JAN APA JULY OCT . JAN APA JULY OCT JAN APA JULY UNIT 2 UNIT 2 AESTAAT OUTAGE UNIT -2 OPEAAT I ON I ~

I l I

PHASE I I COMPLETE I I I

I I l

l I I PHASE I I I I I

I l I I I I I'

I 20K COMP SOW COMP SORY COMP PHASE II l INITAt ,'

J COMPLETE PHASE II I I I COMPLETE I I

CALCS 1 I PHASE III I COMPLETE I

PHASE III I I

INSTALL I I

MQDS I

~ BROWNS FERRY UN I 02 79-14/79-02 PROGRAM NOD IF I CAT ION PRI ORI T I ZRT ION 79-02/79-14 PHASE II CALCULATION IS A COMPLETE MOD I CAT I ON DESIGN BASIS REQUIRED? CALCULATION SYSTEM OPEAAB IL I TY CIPA I TEA I A DOES THE MOD NEED NO NEXT TO BE INS- OUTAGE TALLED NOW

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YES EVALUATE INSTALL MOD PAIOA GENEAIC TO RESTART OA DUPING IMPLICATIONS OPEAAT I ON

%I-IOWNS FEI:II-IY UNIT 2 79-14/79-02 PROGRAM

SUMMARY

SYSTEM OPERABILITY CRITERIA LOAD COMBINATIONS:

PIPE AND PIPE SUPPORT MODIFICATIONS TO BE EVALUATED FOR EMERGENCY LOAD CONDITION ONLY.

LINEAA SUPPOATS:

MEMBER STRESS IS. THE LESSER OF l. 2 SY L 0.7 SU FOA TENSION h FLEXURE AND 0. 9 ~CA FOR NEMBERS IN CONPRESSION.

STANDARD COMPONENTS:

NEET EMERGENCY ALLOWABLES IN DESIGN CAITEAIA.

NON-ST'ANDARD COMPONENT SUPPORT BOLTING:

ALLOWABLE STRESS IS NININUN SPECIFICED YIELD STRESS OR 0.7SU CONCRETE EXPANSION ANCHORS-'AFETY FACTOR NUST BE EQUAL TO OA GREATEA THAN 2. O.

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~BROGANS FERRY UNIT 2

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79-14/79-02 PROGRAM

SUMMARY

SYSTEM OPEPAB IL I TY CP I TEAI A (CONTINUED)

SPRINGS:

MUST NOT EXCEED LIMITS OF TRAVEL

, GAP BETWEEN PIPE h SUPPORT-'AY BE AS MUCH AS 0, SO IN. (EXCEPT WHEN ADJACENT TO EQUIPMENT).

xLOAD SHARING:

LOAD MAY BE REDISTRIBUTED TO ADJACENT SUPPORTS:

EFFECT ON PIPING STRESS MUST BE CONSIDERED.

  • PIPING SYSTEM OPERAB I L' TY ( JUST I F I CAT I ON FOR CONT I NUED N>:

-ASSUME PIPE SUPPORT FAILS

-PRIMARY STRESS IN PIPING NOT'TO EXCEED 2 SY

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-ADJACENT PIPE SUPPORTS MEET OPERABILITY CRITERIA

  • THESE CASES WILL BE USED ON A LIMITED BASIS.

8AOWNS FERRY UN I T 2 79-i4/79-02 PROGRAM P IP ING SE I SKI C DES I GN BASIS ORIGINAL 79-14/02 DES I GN BASIS CRITERIA

<EL CENTRO) IIIIF~ICIFL IIIF I. PIPING HISTORY)

DAMPING OBE 0. Si (SECT C. 3-2. 1) 0. Sr.

DBE IF

2. D I RECT I ONAL SRSS (SECT C. 3. 2. 1 ) SASS COMBINATIONS
3. MODAL COMB I NAT. I ONS SRSS ~SECT C.3.2. 1> SRSS
4. RIGID RESPONSE 20HZ (SECT C. 2. 1) 20HZ S. VERT I CAL 0.07g-OBE 2/3 HOR I Z I ONAL RESPONSE SPECTRA 0.13g-DBE GROUND RESPONSE

<ALL ELEVATIONS> SPECTRA S. HORIZONTAL DETERMINE DETERMINE RESPONSE BY DYNAMIC BY DYNAMIC SPECTRA ANALYSIS ANALYSIS FROM GROUND FROM GROUND RESPONSE SPECTRA RESPONSE SPECTRA

DESIGN CRITERIA USED AT BAOWNS FERRY 79-02/79-14 PHASE I PIPING' SUPPORT LOADING COMBINATIONS AND STPESS LIMITS LOADING COMP I NAT I ONS PIPING 1 SUPPOATS/ANCHOA BOLTS NORMAL PAIMAAY . DW+ P 1. 0 SH OA Y IELD 1. 0 AISC/FS>2 SECONDAAY TH SA OA YIELD PAIMAAY + DW+P + TH (SA+SH) OA YIELD 1. 5 AISC/FS>2 SECONDRAY UPSET PAIMAAY DW+P+OBg '. 2SH OA YIELD 1. 0 AISC/FS>2 PAIMAAY + DW+P+DBE 1. 6 A I SC/FS>2 SECONDAAY +TH EMERGENCY PRIMALLY DW+P+OBE l. 8SH OA Y I ELD 1. 33 A I SC/FS>2 DW+P+DBE 1. 6 AISC/FS>2 PAIMAAY+

SECONDAAY +TH SZ~S SH BASIC MATEAI AL ALLOWABLE SR: AT DESIGN TEMPEAATUAE SA ALLOWABLE EXPANSION STRESS 1 USE LAAGER OF CODE ALLOWABLE OA YIELD

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DESIGN CRITERIA USED AT BROMNS FERRY PIP ING AND SUPPOAT LOADING COMP INAT IONS AND STRESS LIMITS LOADING COMPINATIONS 79-14/79-02 PROGRAM PIPE SUPPOATS NORMAL PAIMAAY DWG+ P PAIMAAY + DWG+P + TH 1.0 AISC SECONDAAY UPSET Q~ 02 PAIMAAY DW+P+OBE 1 ~ 2SH/1.'5S H 1. 33 A I SC PAIMAAY + DW+P+DBE 1. 2 (SA+SH>

SECONDAAY +TH EMEAGENCY Q~ 02 PAIMAAY 1. 8SH/2. OSH 1.5 AISC OA .9 FY PRIMARY+ DW+P+DBE SECONDAAY 1 OPEAATING PRESSURE SH BASIC MATERIAL ALLOWABLE STRESS AT DESIGN TEMPEAATURF 2 MAXIMUM PRESSURE SA ALLOWABLE EXPANSION STRESS 3 ANCHOA BOLT F. S > 4y5

BROGANS FERRY UNIT 2 79- 14/79-02 PROGRAM SUB~ I TTALS DATE DESCRIPTION o JUNE 81 DESCRIPTION FOR 3-PHASE PROGRAM 0 AUG 86 NUCLEAR PERFORMANCE PLAN VOLUME 3, REVISION 0 0 APR 87 PROGRAM PROCEDURES 0 MAY 87 , USE OF ARTIFICIAL TIME HISTORY IN LIEU OF 1940 EL CENTRO 0 APR 87 SE I SMI C DESIGN I SSUE o JULY 87 NUCLEAR PERFORMANCE PLAN VOLUME 3. REV I S I ON 1

BRQWNS FERRY UNIT 2 79-14l79-02 PROGRAM

SUMMARY

REQUEST NRC APPROVAL:

USE OF ARTIFICIAL T I ME HISTORY FOR P I P ING 3-PHASE PLAN AND SCHEDULE FOR IMPLEMENTATION OF 79-02 AND'9- 14 PROGRAM USE OF ENGINEERING JUDGEMENT IN LIEU OF COMPLETE CALCULATION DOCUMENTATION IN PHASE I