ML20204G514

Audit for Mark I Containment Long-Term Program - Structural Analysis of Torus-Attached Piping,Enrico Fermi Unit 2, Technical Evaluation Rept

ML20204G514
Person / Time
Site:	Fermi
Issue date:	07/20/1983
From:	Subramonian N, Le A Franklin Research Ctr, Franklin Institute
To:	Shaw H Office of Nuclear Reactor Regulation
Shared Package
ML20204E983	List: ML20204E978 ML20204G514
References
CON-NRC-03-81-130, CON-NRC-3-81-130 TER-C5506-310, NUDOCS 8307220453
Download: ML20204G514 (32)

Text

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1 TECHNICAL EVALUATION REPORT AUDIT FOR MARK I CONTAINMENT LONG-TERM. PROG RAM STRUCTURAL ANALYSIS OF TORUS-ATTACHED PIPING ENRICO FERMI ATOMIC POWER PLANT UNIT 2 1

FRC PROJECT C5506 FRC ASSIGNMENT 9 NRCCONTRACTNO.NRL 03-81-130 FRCTASK 310 Preparedby Franklin Research Center Author: N. Subramonian, A. K. Le 20th and Race Streets Philadelphia, PA 19103 FRC Group Leader: N. Subramonian Preparedfor Nuclear Regulatory Commission Washington, D.C. 20555 Lead NRC Engineer: H. Shaw J.uly 20, 1983 .

This report was prepared as an account of work sponsorea by an agency of tile United States Government. Neither the United States Government nor any agency thereof, or any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for any third psrty's use, or the results of such use, of any information, appa-ratus, product or process disclosed in this report, or represents that its use by such third  :

party would not infringe privately owned rights. '

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. 0D.Franklin Research Center 20th and Race Streets, Phila.o Ps.19103 (215) 448-1000

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TER-C5506-310 i

1. INTRODUCTION .

.- l LTha c:pability of the boiling water reactor (BWR)' Mark I containment' f

!ppr raion chamber to withstand hydrodynamic loads was not considered in the iginal d: sign of the structures. The resolution of this issue was divided l

to' a 'absrt-term program and a'long-term program.

Based on the results of the short-term program, which verified that each rk I containment would maintain its integrity and functional capability when

bjected to .the loads induced by a design-basis loss-of-coolant accident -

K.A), th3 NBC staff granted an exemption relating to the structural- factor Esafcty requirements of 10CFR50, 55(a) .

Th3 objective of the long-term program was to restore the marginc of ifety in the Mark I containment structures to the originally intended .

'agins. The results of the long-term program are contained in NUREG-0661 .

I.], which describes the generic hydrodynamic load definition and structural

ceptanca criteria consistent with the requirements of the applicable codes ,

.d standads.

Th2 cbjective of this report is to present the results of an audit of the usi Unit 2 plant-unique analysis . (PUA) report with regard to structural ulysis of torus-attached piping and suppression chamber penetrations. The allt w:s performed using a moderately detailed audit procedure developed arlier [2] and attached .to this report as Appendix A. Results of the audit elated ta major modifications were presented in an earlier report [3] . The er items cf the audit procedure are obtained from " Mark I containment Program

.tructural Acceptance Criteria Plant Unique Analysis Application Guide" [4),

tich meets the criteria of Reference 1.

4

,, E a.

TER-C5506-310 I

i

2. AUDIT FINDINGS

- I i

A d; tailed presentation of the audit for Fermi Unit 2 is provided in i pendix A, which contains information with-regard to several key items ,  !

tlined in the audit procedure [2] . Based on this detailed audit, it is I

neluded that all items in the Fermi Unit 2 PUA reports [5, 6] indicate  !

apli:nca with the requirements of the criteria [4] .  !

I Th3 Licensee used the procedures outlined in References 1 and 7 for  ;

teining LOCA and SRV discharge loads. Because a load reduction factor was  !

ed f r the SRV air clearing load, the Licensee has made a commitment to trfrra o ceries of in-plant SRV tests at Fermi Unit 2 following fuel loading iconfira the conservatism in this approach. For loads not defined in tiercnc a 1 and 7, the Licensee used the methodology of the plant FSAR. The

.censen's analytical approach conforms to the requiremints of the criteria

-). Th3 results of the structural analysis for each load are used to

)

cluato cnveloping load combinations for piping, piping supports, equipment, l t9 suppracsion chamber penetrations in accordance with the requirements of Gcrcnccc 1 and 4. For selected piping systems, the Licensee used the square Gt cf' tha sum of the squares technique (SRSS) to combine dynamic responses a acc rdance with the NBC approval letter to the General Electric Company )

0] . Th3 Licensee did not perform a plant-unique analysis of fatigue effects a toru -sttached piping based on the conclusions of a generic study which slicated that the cumulative fatigue usage factors of torus-attacbed piping 6e les3 than 0.5 for typical plants. The Licensee compared the results of te piping and penetration analyses to the requirements of Reference 1 and anonstrcted that the actlal stresses are less than the allowables. For WiPnent and components such as valves and pumps, the resultant loads were 8EPared to the respective allowables specified by the equipment manufacturers

• reeveluation was performed using more rigorous analytical techniques that j ttisfy the requirements for operability and functionality. l I

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-. ..- -.- - -._ ._ - , .._________.L

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' TX 3..

TER-C5506-310

3. CONCLUSIONS Bacco on the audit of the structural analyses of torus-attached piping, proccion chamber penetrations, and associated equipment and components

)ctntsd in Reference 6, it is concluded that the Licensee of Fermi Unit 2 ,

) complied with the criteria requirements [4] in all respects. The Licensee i

' mada a commitment to perform a series of in-plant SRV tests following fuel sing et Fermi Unit 2 to confirm the conservatism in the assumed load i

Duction factor with regard to SRV discharge loads for air clearing. i j

i 1

M TER-C5506-310

4. REFERENCES

1. NUREG-0661

" Safety Evaluation Report, Mark I Containment Long-Term Program Resolution of Generic Technical Activity A-7" Office of Nuclear Reactor Regulation USNRC July 1980

2. Technical Evaluation Report Audit Procedure for Mark I Containment Long-Term Program - Structural Analysis Franklin Research Center, Philadelphia, PA June 1982, TER-C5506-308

3. Technical Evaluation Report Audit for Mark I Containment Long-Term Program - Structural Analysis Enrico Fermi Atomic Power Plant Unit 2 Franklin Research Center, Philadelphia, PA August 1983, TER-C5506-309

4. NEDO-24583-1

" Mark I Containment Program Structural Acceptance Criteria Plant Unique Analysis Application Guide" General Electric Co., San Jose, CA October 1979 5.

Enrico Fermi Atomic Power Plant Unit 2 Plant Unique Analysis Report, Volumes 1-5 Prepared by NUTECH Engineers, Inc.

April 1982

-6. i Enrico Fermi Atomic Power Plant Unit 2 Plant Unique Analysis Report for Torus Attached Piping and Suppression Chamber Penetrations Prepared by NUTECH Engineers, Inc.

June 1983

7. NEDO-21888 Revision 2 CMark I Containment Program Load Definition Report" Ceneral Electric Co., San Jose, CA November 1981 -

'8.

D. B. Vassallo (NRC)

Letter Subjects to H. C. Pfefferlen (GE)

March 1983 Combining Dynamic Responses in Mark I Piping Responses 1

-4 h _

1 .

l, ,, _,

(- : _

. 4 TER-C5506-310

9. American Society of Mechanical Engineers -

Boiler and Pressure Vessel Code,Section III, Division 1 -

" Nuclear Power Plant Components" N3w York: 1977 Edition and Addenda up to Summer 1977

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1. INTRODUCTION The key items used to evaluate the Licensee's general compliance with the requirements of NUREG-0661 [1] and specific compliance with the requirements cf CMark I Containment Program Structural Acceptance Criteria Plant Unique Analy0is Application Guide" [2] are contained in Table 2-1. This audit procedure is applicable to all Mark I containments, except the Brunswick containments, which have a concrete torus.

For each requirement listed in Table 2-1, several options are possible.

Id:Olly, the requirement is met by the Licensee, but if the requirement is not met, cn alternative approach could have been used. This alternative approach uill be reviewed and compared with the audit requirement. An explanation of why the approach was found conservative or unconservative will be provided. A '

column indicating " Additional Information Required" will be used when the

! infsraation provided by the Licensee is inadequate to make an assessment.

A few remarks concerning Tables 2-1 and 2-2 will facilitate their uses o A summary of the audit as detailed in Table 2-1 is provided in Table 2-2i highlighting major concerns. When deviations are identified, reference to appropriate notes are listed in Table 2-1.

O Notes will be used extensively in both tables under the various columns when the actual audits are conducted, to provide a reference that explains the reasons behind the decision. Where the criterion is satisfied, a check mark will be used to indicate compliance.

o When a particular requirement is not met, the specific reasons for noncompliance will be given.

I 9

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5ENMWW-- g NRC Contract N A NRC 03-81-130 Page b FRC Prolect No.C5506

!!r:nklin R: search Center FRC Assignment No. 9 g Q Dvs on of The Frankiminstaute FRCTask No. 31O 20th and Rac2 Streets. Phda.. Pa.19103 (215) 448 1000 Plant Name Fe.v m's h*d 2.

h2-1. Audit Procedure for Structural Acceptance Criteria of MarkiContainment Long-Term Program l

Licensee Uses Criteria Addtl. Attemate Approach -

Keyltems Conside' red NA Remarks in the Audit Not info.

Met Met Reqd. Conser- Unconser-vative vative

$ All thostructural vent system elements of and suppres-i I cien chamber must be considered in the review.

'Jh3 following pressure rotaining elements (and their supports) must be

! considered in the reviews A RtWried.fa'Ii47[J) o Torus shell with associ

• cted penetrations, I rainforcing rings, and Cupport attachments o Torus shs11 rupports to

• the containment structure o Vents betweet the drywell #

cnd the vent ring header (including penetrationa therein) o Region of drywell local *

• to vent penetrations ,

1 f

o Bellows between vents and

• l torus shell (internal,or j cxternal to torus) ,

o Vent ring header and the #

downcomers attached to it o Vent ring header supports A to the torus o Vacuum breaker valves /

attached to vent penetra-tions within the torus (where applicable) o Vacuum breaker piping systems, including vacuum y breaker valves attached to torus shell penetra-

~ Y *h*~rm1 x ..

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l Page V

NRC ContractNo.NRC-03-81-130 FRC Project No.C5506

>hw47 Fr:nk!!n Research Center FRC AssignmentNo. 9

.3 A Dwmen of The FrankhnInsatute 20th and Race Siruts. Phda,. Pa 19103(215)448-1000 FRCTaskNo.

PlantName 38oFarms Wad 2-ntLong-Term P.ogram .

Tabl321. AuditProcedure forStructural AcceptanceCriteria of Mark lContainme _

Licensee Uses .

Criterla_ Addtl. Alternate Approach NA Remarks )

Keyitems Considered Not Info.

' isction inthe Audit Reqd. Co nser- Unconser- vative Cd2) Met Met vative

(

l 1.2 (Cont.)

tions and to vent penetrations external to the torus (where applicable)

Piping systems, including V

o pumps and valves, internal to the torus, aEtached to l the torus shell and/or vent penetrations # Rchert.eJ ea.eleer DJ o All main steam system safety relief valve (SRV) piping o Applicable portions of t

the following piping systems:

V

- Active containment e system piping systems (e.g., emergency core  ;

cooling system (ECCS) and ..

other piping required to maintain core cooling .

after loss-of-coolant accident (IDCA))

V

- Piping systems which provide a drywell-to-wetwell pressure dif-forential (to alleviate ~

pool swell effects)

V

~ other piping systems, including vent drains Supports of piping systems v

o mentioned in previous item y

o Vent header deflectors including associated CE ,_ i I , t , I l

v=------- D NRC Contract N2. NRC-03-81 130 FRC Project N:.C5506 p:g3

@llll Franklin Research Center JU FRC Assignment No. cy A Dwoon of The Franklin insature 20th and Race Streets. Phda.. Pa. 19103 (215) 448 1000 FRCTaskNo. 3lc 4 Plant Name Fe.cm a 14 M 2.

iabl32-1. Audit Procedure for Structural Acceptance Criteria of MarkiContainment Long-Term Program a-Licensee Uses i Keyitems Considered Criteria Addtl. Alternate Approach '

Itlon NA Remarks o.[2] in the Audit Not Info. -

Met Met Reqd. Conser-vative Unconser-vative 1.2 (Cont. ) l A k Reporte.J earlear [ 3] l 0 Internal structur'al l elements (e.g. , monorails, catwalks, their supports) whose failure mi 9 at impair the containment function l1.3 c. ne structural .

acceptance criteria for existing Mark I containment systems are contained in the l

American Society of Mechanical Engineers l (ASME) Boiler and -

Pressure Vessel (B&PV) Code,Section III, Division 1 (1977 Edition) , with addenda through the Sunsner 1977 Addenda M1 to be referred herein as the Code. He alternatives to this criteria provided in ,

Beforence 2 are also acceptable'. .

b. When complete appli-cation of the criteria (item 1.3a) results in hardships or j unusual difficulties i without a compensa- -

ting increase in level of quality and safety, other structural acceptance criteria may be used after ~

approval by the Nuclear angulatory Commission.

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NRC Contract NO. NRC-03-81-130 d!y:lj Franklin Research Center FRC Project No.C5506 Page A Dnnsen cf The Frankhn institute FRC AssignmentNo. 9 20th and Race Streets. Phda.. Pa. 19103 (215)448-1000 FRCTask No. 31o 5 Plant Name F'n m e Lin'd 2.

Tabl22-1. Audit Procedure for Structural Acceptance Criteria of Mark iContainment Long-Term Program action Keyltems Considered Criterla Licensee Uses Addt!. Alternate Approach o.[2] in the Audit Not Info. NA Remarks -

Met Met Reqd. Conser- Unconser-vative vative 2.1 c. Identify the code A- # R4cdtJ Enrher [3]

or other classification of the structural element

b. Prepare specific

• dimensional boundary definition for the specific Mark I contain-ment systems (Note:

Welds connectiEg piping to a nozzle are piping welds, not Class MC welds) 2.2 Guidelines for classification of structural elements and boundary definition are as follows:

(Refer to Table 2-3 and Table 2-4 for non-piping and piping structural elements, respectively, and to item 5 -

in this table for row d: ignations used for d; fining limits of i boundaries)

c. Torus shell (Row 1) -

4F The torus membrane in combination with reinforcing rings, penetration elements within the NE-3334 l+1 limit of reinforce-ment normal to the torus shell, and attachment welds to the inner or outer surface of the above members but not to nozzles, is a Class MC (+] vessel. I l

fu Frrnk!!n Research Center NRC Contract No. N RC-03-81-1.10 FRC Project No. C5506 Pege A Divisen of The Franklin Insntute FRC Assignment No. 9 20th and Race Streets. Phda.. Pa. 19103 (215) 448 1000 FRCTaskNo. 31O 6 Plant Name Ferm unW 2.

31]2-1. Audit Procedure forStructural Acceptance Criteria of Mark 1 Containment Long-Term Program 3;) Keyitems Considered Critada Licensee Uses .

A dit. Alternate Approach SI in the Audit --

Not . NA Remarks Met Met Reqd. Conser- Unconser-

.vative vative

,2 (Cont.)

b. Torus shell supports AF

• steportcJ earlan(3 J (Pow 1) - Subsection NF

[4] support structures between the torus shell cnd the building otructure, exclusive of the attachment welds to the torus sSell; welded or mechanical attachments to the building structures (excluding en.bedments);

cnd seismic constraints between the torus shell cnd the building ctructure are Class MC

[4] supports.

c. External vents and

• vent-to-torus bellows (Row 1) - 2he external vents (between the cttadment weld to the I drywell and the cttachment weld to the bellows) including:

vent penetrations within the NE-3334 [4]

limit of reinforcement normal to the vent, internal or external cttachment welds to the cxternal vent but not to nozzles, and the vent-to-torus bellows (including attachment welds to the torus -

chell and to the cxternal vents) are Class MC [4] vessels.

. . . . . . . . . . . . . . . . .. - . ~ . . . - ~~ -. .

NRC Contract No. NRC-03-81-130 p[U Fcnk!!n Research Center FRC Project No.C5506 P ge A Den of The Franklin Institute FRC Assignment No. 9 20th cnd Race Streets. Phda.. Pa. 19103 1215) 448 1000 FRCTaskNo. 380 6 Plant Name Fe , ia w 2.

bl]2-1. Audit Procedure for Structural Acceptance Criteria of Mark i Containment Long-Term Program on Cdteria Licensee Uses .

Keyitems Considered dtl. Alternate Approach

^I S in the Audit ~ . ~

Not . NA Remarks Met Met Reqd. Conser. Unconser-vative vative 2 (Cont.)

b. 'rbrus shell supports # # Repe,tcJ esteluv(3 J (Row 1) - Subsection NF

[4] support structures between the torus shell cnd the building ctructure, exclusive of the attachment welds 1 to the torus sSell; I welded or mechanical attachments to the _

building structures (excluding embedments);

cnd seismic constraints betwsen the torus shell cnd the building structure are Class MC

[4] supports.

c. External vents and

• vent-to-torus bellows (Row 1) 'Jhe external vents (between the ,

cttachment weld to the '

drywell and the cttachment weld to the bellows) including: .

vent penetrations within the NE-3334 [+]

limit of reinforcement normal to the vent, internal or external Gttachment welds to the cxternal vent but not to nozzles, and the 3 vent-to-torus bellows (including attachment welds to the torus -

chell and to the crternal vents) are Class MC [4] vessels.

O NRC Contract N3. NRC 03-81-130

,ldin Rese:rch Center FRC Project No.C5506 Page e.on of The Frank!m insutute FRC AssignmentNo. Q

.nd Race Streets. Phda.. Pa. 19103 (215) 448 1000 FRCTaskNo. 310 7 Plant Name $:ey.,, un*J: 2 Audit Procedure for Structural Acceptance Criteria of Mark l Containment Long Term Program .

Criteria Addtl. Licensee Uses K:yitems Considered Alternate Approach -

in the Audit Not Info. NA Remarks Met Met Reqd. Conser- Unconser-vative vative mt.)

. Drywell-vent connection *

• KtF8'ked Earlid' C3 }

regien (Row 1) - Vent w;1d:d connections to th3 drywell (the drywell i

cnd -the drywell region  !

cf interest for this l

Prcgram is up to the NE-3334 f4] liiilt of rainforcement on the drywell shell) are Clas3 MC [4] vessels.

Int:rnal vents (Rows 2 #

cnd 3) - Are the continuation of the v:nts internal to the torus shell from the VCnt-bellows welds and includes the cylindrical shell, the closure head, pen trations in the cylindrical shell or 1 olorure head within the NE-3334 [4] limit of rainf:rcement normal to ,

th3 V nt, and attachment welds to inner or outer curftce of the vent but n;t to nozzles.

Vent ring header (Bows

• 4.cnd 5) and downcomers -

(Row 6) - Vent ring h;cder including the downconers and internal Cr Cxternal attachment welda to the ring i

hstd:r and the cttachment welds to the downcomers are Class MC

[4] v:ssels. .

E'M -,'.*.iE l .$ h M ^ M M 'MdLLEE2KIMEL'&hMf252m21.nlF= _ ,

i NRCContractN .NRC-03-81-130 i l 1 0 R:se:rch Center FRC Project No. C5506 o of The Frankhn Inunut. FRC AssignmentNo. 4 Page i Rac) Stres. PN!a.. Pa. 19103 (215) 448 1000 FRC Task No. 31O g Plant Name Fe.rm s u n*J: 2 1

Edit Procedure forStructural Acceptance Criteria of Mark i Containment Long-Term Program i Keyitems Considered Criteria ucensee us..

Addtl. Alternate Approach

- [1 in the Audit Not Info. NA Remarks Met Met Reqd. Consor. Unconser-vative vative 0)

_ W.

Re >srtc) E ulacr[3]

lowncom:r within the NE-3334 [4] limit of Bcinfere: ment normal to tho vcnt ring header and portion of the vent Bing h cder within E-3334 limit lif scinferecaent arc

onsid0 rcd under kw 5.

EDnt ring header #-

pupports (kw 7) -

Zbsection NF [4]

Epports, exclusive of B)o Ottachment welds to Go vcnt ring header ind to the torus shell, 60 Cicco MC [+]

cpporto.

bsentici (kws V

@ and 11) and ,

.on-e:ccatial (k ws pand13) piping '

ytems-Apiping .

jst:0 cr a portion .

9 it 10 casential ,

3 tho cyctem is ec sscry to assure integrity of rcactor coolant

$3curoboundary, gocapabilityto .

ut down the act:r cnd maintain in a shutdown

>ndition, or the

'pability to ev:nt cr mitigate concaquences of

L. 7< : .- 2 r z:vc; . ~,,:= ic; n rm:r =:::=~n: 'nw. ; u-m. xn  ;:weM :. a p . . .u-- -

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NRC Contract No. NRC-03-81-130

[r:nklin R: search Center FRC Project No. C5506 y DMson of The Frankhn Instnute FRC Assignment No. q Page i O l l th and Rac2 Streets. Phda.. Pa. 19103 (215)FRCTaskNo.

448 1000 380 4 Plant Name Fe m s Wih J,.

2-1. Audit Procedure for Structural Accaptance Criteria of Mark iContainment Long-Term Program 1

I i Keyitems Considered Criteria ucenseo uses -

in the Audit Addtl. Alternate Approach Not Info. NA Remarks Met Met Reed. Consor. Unconser-vative vative q 1

Cont.)

l cecidents which could result in potential off site i i

cxposures comparable to tho guideline exposure cf 10CFR100. ~ Piping .

t chould be considered l ccanntial if if performs a safety-r 10ted role at a later time during the event combi uttion being i conridered or during i any cubsequent event '

combination.

Active and inactive V component (Rows 10-13) - Active component is a pump or valve in an 1 casential piping cyct0m which is r quired to perform l o mechanical motion during the course cf cccomplishing a .

cyatta safety function.

Contcinment vacuum #

br0ckcra (Row 2) -

Vacuum breakers valves acuntsd on the vent intcrnal to the torus cr en piping associated oith the torus are Claso 2.[+] components.

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' Dmsaon of The Frankhn Institute -' FRC AssignmentNo. 9 hh cnd Racs Streets. Phala.. Pa. 19103 (215) 448 1000 FRCTatkNo. 530

• go i Plant Name Far me LinJ: 2.

2-1. Audit Procedure for Structural Accepbnce Criteria of MarklContainment Long-Term Program ,

Keyitems Considered Criterla Addtl. Alternat ' '

p ch in the Audit Not Info. NA Remarks Met Met .RM Conser- Unconser-vative vative -

(Cont.) v

k. External piping and cupports (Rows 10-13): V

- No Class 1 piping

- Piping external to end penetrating the tcrus or the external v nts, includliig the cttactunent weld to the tcrus or vent nozzle is M

'~

C1 css 2 [4] piping. Die .

cther terminal end of -

such external piping chould be determimd

ba:ed on its function cnd isolation capability.

- Subsection NF [+] V '

cupport for such /

cxternal piping c including welded or mechanical attachment to j

. ctructurer excluding any I

cttachment welds to the i piping or other pressure . . . .

r0taining component are ,

Class 2 [+] supports. ,

1. Internal. piping and V ,

supports (Hows .

10-13) - Are Class 2 or Class 3 piping and Class 2 or' Class 3 Component supports.

c. Internal structures # M Re>* rte 4 h h#r ( 3 '3 -

(Row 8) - Non-safety-r01ated elements which - i ~

cro not pressure , - -

l rotaining, exclusive of attachment welds to any ,

pecssure retaining

,9 .

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NRC Contract No. NRC-03-81-130 Fr:nklin Research Center FRC Project No. C5506 A Den of The Franklin Insenute FRCAssignmentNo. 9 Page 20th and Race Streets. PMa.. Pa. 19103 (215) 448 1000 FRCTaskNo. 330

__ 33 Plant Name Fe. cms un*d: 2 fa 21. Audit Procedure for Structural Acceptance Criteria of MarkiContainment Long-Term Program

~~~

G \ Keyltems Consid: red d in the Audit '

Criten.l Addtl .

Alte toApp ch Not Info. NA Remarks Met Met Reqd. Conser- Unconser-vative vative t (Cont.)

member (e.g. , ,

monorails. ladders, entwalks, and their cupports).

n.

Vent deflectors !2ow 9) #

• kkerteJ sarlur (3')

- Vent header flow dcflectors and" casociated hardware (not including attachment welds to Class MC v ssels) are internal -

Otructures.

Icad terminology used sh uld be based on Final Saf0ty Analysis Report (FSAR) for the unit Cr the Ioad Definition TapJrt LDR) [5] . In casa of

.l c(onflict, the LDR loads

'shall be used.

1 Consid: ration of all 1 cad /

combinations defined in Section 3 of the IDR [5]

shall be provided.

c. No reevaluation for limits set for design pr0ssure and design temperature values itu needed for present ctructural elements.

b. Decign limit /

requirements used for initial construction f:11owing normal prcctice tiith respect to load definition and

• cllowable stress shall be used for systems or i

f.; ____lr M # t_ C N ' " - --

'~ - - ~ '

r b NRC Contract N3. NRC-03-81 130 FRC Project No.C5506 Franklin Research Center Page

' A boon of The Frankhninsinute FRC Assignment No. 8I 20th and Race Streets. Phda.. Pa. 19103 (215) 448 1000 FRCTask No. 380 12 Plant Name Fem e un*d 2.

02-1. Audit Procedure for Structural Acceptance Criteria of Mark l Containment Long-Term Program Criteria Licensee Uses 0 Keyitems Considered Addtl. Alternate Approach - '

in the Audit Not Info. NA Remarks Met Met Reqd. Conser- Unconser- 7 vative vative (Cont.) l l l l

portions of systems

that are replaced and I

fcr new systems. ,

Service Limits and

• See definition De ign Procedures shall for Service na based on the Limits in B&PV Code, Section 'III, Section 4 of Civicion 1 including l

addenda up to Summer 1977 Reference R l Addenda [4], specifically:

I e M RebE rt,.J earlser (3l

( c. Class 11C l C!ntainment l v:ssels: Article l

NE-3000 [4]

b. Linear-type

• component (Class 2 l and 3) support -

with three modifications to tho Code l i l - For bolted

• connections, the r0quirements of Service Limits A l

cnd B shall be cyplied to Service

) Limits C and D

> without increase in the allowables above those cpplicable to Service Ievels A and B;

- NF-3231.1 (a) *

[4] is for primary plus secondary ctress range;

)dhb roe -T.2hhtailiLilb-ar 7 saw.- m.- .

~

NRC Contract Nr. NRC-03-81-130 nklin Research Center FRC Project NO.C5506 Page A DMsion of N Frenan Instuute FRC Assignment No. il 20th and Race Streets. PMa.. Pa. 19103 (215) 448 1000 FRCTaskNo. 31o g3 Plant Name Fe,m W a*4 2.

~

jible 2-1. Audit Procedure forStructural Acceptance Criteria of MarklContainment Long-Term Program 1

1 ilon Keyitems Considered Criteria Ocensee Uses Addtt. Alternate Approach .

i[2] In the AudM Not Info. NA Remarks Met Met Reqd. Conser. Unconser-vative vative

- All increases in M allowable stress permitted by Subsection NF [+] are limited by Appendix XVII-2110(b) f+] when buckling is a consideration.

c. Class 2 and 3 piping, V pumps, valves,"and internal structures (also Class MC)

'o3 Tho components, component * -

loadings, and service level cccignments for Class MC .

[4] components and internal otructures shall be as defined in Table 5-1 of Re f;rence 2 l 4 23 components, component * <

loadings, and service level l C0cignments for Class 2 and Class 3 piping systems sh:11 be defined in Table i 5-2 cf Reference 2.

05 23 definition of cperability is the ability to perform required techanical motion and functionality is the chility to pass rated flow,

c. Active components chall be proven cperable. Active components shall be considered operable if service Limits A or B or more conservative limits t (if the original design criteria I required it) are met.  ;

l

h NSbt NRC Contract No. NRC 03-81-130 FRC Project No.C5506 Page Frrnklire R: search Center FRC AssignmentNo. 9 A Dim.on of h Franklin insinute g4 FRCTask No. 31o

• 20th and Race Streets. Phila.. Pa. 19103 (2151 448 1000 Plant Name Ferene un4 2.

02-1. Audit Procedure for Structural Acceptance Criteria of MarkiContainment Long-Term Program Licensee Uses 0 Keyitems Considered Criteria Addtl. Alternate Approach

~

Not Info. NA Remarks In the Audit Met Met Reqd. Conser.vative Unconser-vative (Cont.)

Fiping components shall V b.

be proven functional in o manner consistent with the original design criteria.

. Analysis guidelines provided hereiii uhall cyply to all structural olements identified in .

item 1.2 of this table.

All loadiangs defined in M- See Section 3.3

c. of this table.

cubsection 3.2 of -

Reference 2. shall be considered *

• Reportel earl <r f 33

b. A summary technical report on the analysis chall be submitted to the NRC. a.

2 213 following general i guid lines shall be applied to cil structural elements -

annlyzed:

c. Perform analysis

• cccording to guideline defined herein for all loads defined in LDR I5). (rbr loads considered in origina'l design, but not redefined by LDR, previous analyses or new analyses may be used.)

b. Only limiting load

• combination events need be considered.

. . - 9 E

=+b*  % ~ Y=*

' " M ".' * - =Y W -

.,. $ .~a . .l. % bi? L _ - . - - -- .._ ._

- -- 1 j

NRC Cor. tract No. NRC-03-81-130 p0lj Fr:nklin Research Center FRC Project No.C5506 Page 0 FRC AssignmentNo. 9 A Dvwon of The Franklin Insutute -

20th and Race Streets. Phda.. Pa.19103 I215) 448-1000 FRCTaskNo. 31O l5 Plant Name F*ume unW 2 able 2-1. Audit Procedure for Structural Acceptance Criteria of MarkiContainment Long-Term Program Ucensee Uses ~

tion Keyitems Considered Critada 1. Alternate Approach in the Audit Not NA Remarks

<l2I .

_ Met Met Reqd. Conser- Unconser-utive vative f

i.2 (cont.)

c. Fatigue effects of all operational cycles shall be considered.

M M Repo<ted earineC 3 3

d. No further evaluation of structural elements for which combined effect of loads defined in LDR [5] produces stresses less than lot .

of allowable is required. Calculations demons trating conformance with the 10% rule shall be provided.

o. Damping values used in

• dynamic analyses shall be in accordance with NRC Regu34 tory Guide 1.61. ~~ .

. 1 5.3 Structural responses for loads resulting from the combination of two dynamic .

ph nomena shall be obtained in the following manners

c. Absolute sum of stress V components, or

b. Cumulative distribution /

function method if absolute sum of stress components does not satisfy the acceptance criteria.

6.4 Tbrus analysis shall consist of: .

.. . .n --

3 = x _ 3_ _ - _f

=_ .-

,g NRC Contract No. NRC-03-81 130 FRC Project No.C5506 Page ,

1

.!JUU Fr:nklin Research Center )

A Dwen of The Frankhn Institute FRC Assignment No. 4 l I FRCTask No. 38 O i6 '

2Dih and Race sneen. Phda.. Pa.19103 (2154 4481000 PlantName Feeine Wa*Jr 2-

'abl32-1. Audit Procedure for Structural Acceptance Criteria of Marki Containment Long-Term Program Ucensee Uses W

Keyitems Considered Moria Addtl. Alternate Approach b[2] in the Audit Not Info. NA Remarks Met MW RW. Conser. Unconser- vative vative 0 4 (Cont.)

O. Finite element analysis * * "*f"**I

• I'" U 3 for hydrodynamic loads (time history analysis) l and normal and other loads (static analysis) making up the load combinations shall be performed for Ehe most

• highly loaded segment of the torus, including the shell, ring, '

girders, and support.

b. Evaluation of overall #

effects of seismic and other nonsymmetric loads shall be provided using beam models (of at least 180* of the torus including columns and seismic restraints) by use of either dynamic load factors or i time history analysis.

c. Provide a non-linear .

time history analysis, using'a spring masa model of torus and support if net tensile forces are produced in columns due to upward

~

• phase of loading.

d. Bijlaard formulas shall V be used in analyzing each torus nozzle for effect of reactions .

produced by attached piping. If Bijlaard formulas are not

d NRC Contract NC. NRC-03-81-130 dbu Franklin Research Center FRC Project No.C5506 Page A Div. mon of The Frankhn Instause FRC AssignmentNo. 9 20th and Race Streets. Phda.. Pa.19103 (215) 4481000 FRCTask No. 310 17 e Plant Name Feret UnA 2- 1 Vabl]2-1. Audit Procedure for Structural Acceptance Criteria of Mark 1 Containment'Long-Term Program l

Licensee Uses etion Keyitems Considered Criteria Addtl. Alternate Approach D. [2] Not Info. NA Remarks get Met Reqd. Conser- Unconser-vative vative (6.4 (Cont.)

applicable for any nozzle, finite element analysis shall he performed.

l6.5 In analysis of the vent Jyatem (including vent (

penetration in drywell, l vant pipes, ring header, downcomers and their intersections, vent column cupports, vent-torus bellows, vacuum breaker penetration, and the vent deflectors), the following l guidelines shall be frilowed:

1. W- ReportcJ eelser [b]

O. Finite element model shall represent the most highly loaded portion of ring header shell in the "non-vent" .

bay with the downcomers

-. attached.

b. Finite element analysis M shall be performed to evaluate local effects l in the ring header shell and downcomer intersections. Use time history analysis ,

for pool swell transient and equivalent static analysis for downcomer lateral loads.

I

-wm - . ,

sk.7th 4.;n , d- trP-is{ & & E Je'1;g'I;rNhh4 v ~ ~ - w + - '-- - m --

NRC Contract N A NRC-03-81-130

.00) Franklin Research Center FRC Project No.C5506 Page A Dvison of The Frankhn institute FRC Assignment No. 81 20th and Race Seeets. PMa.. Pa. 19103 (215) 448-1000 FRCTaskNo. 31o g -

Plant Name Ft.r m s und 2.

'able 2-1. Audit Procedure for Structural Acceptance Criteria of MarkIContainment Long-Term Program tio ~= Keyitems Considered Crtteria Ucensee Uses Addtl. Alternate Approach -

12) in the Audit Not n o. NA Remarks Met Met Reed. Conser- Unconser-vative vative i.5 (Cont.)

1. W Report ed ariser E3 J

c. Evaluation of overall effects of seismic and other nonsymmetrical loads shall be provided using beam models (of at least 180* of the vent system including vent pipes, ring header and column suppcrts) by the use of either dynamic load factors or time history analysis.

M

d. Use beam models in analysis of vent deflectors.

o. Consider appropriate

• superposition of reactions from the vent deflectors and ring headers in evaluating the vent support .

columns for pool swell. '

06 c. Analysis of torus * .

internals shall include the catwalks with supports, monorails, and miscellaneous internal piping.

b. It shall be based on

• hand calculations or simple beam models and dynamic load factors and equivalent static analysis.

NRC C:ntract No. NRC-03-81-130 Page b FRC ProjectNo.C5506 Frrnklin R: search Center FRC AssignmentNo. 9 19 A Diwson of The Franidin Insuture FRCTaskNo. 380 20th cnd Race Strem. Phda.. Pa. 19103 1215) 448 1000 Plant Name FermiWW Z _

e 2-1. Audit Procedure for Structural Acceptance Criteria of MarkiContainment Long Term Program _.

Licensee Uses l Criteria Addt!. Alternate Approach -

j

'l Keyitems Considered NA.

• Remarks inthe Audit Not Info.

) Met Met Reqd. Conser- Unconser-  ;

vative vative 5 (Cont.)

• nyeAcJ urber (33

c. It shall consider Service Level D or E when specified by the ctructural acceptance criteria using a oimplified nonlinear cnalysis technique (e.g. , Bigg 's Method) .

7 Analysis of the torus cttached piping shall be performed as follows:

Designate in the V c.

summary technical report submitted all piping systems as essential or .

non-essential for each load combination, Analytical model shall V b.

represent piping and

' l supports from torus to  !

first rigid anchor (or where effect of torus 1 motion is insignificant) . I

c. Use response spectrum V or time history ,

analysis for dynamic effect of torus motion at the attachment point, except for piping systems less than 6" in diameter, for which equivalent static analysis (using appropriate amplification f actor) may be performed.

..n_. _ .. - -- - - - -

(

~.

NRC Contract NO. NRC-03-81 130 Ul.0 FranklinReseirchCenter FRC Project NO.C5506 Pcg2 A Dwision of The Frankhn Instuute FRC Assignment No. 9 20th and Race Streets. Phda.. Pa. 19103 (215) 448 1000 FRCTaskNo. 310 20 Plant Name Fr.r m : Wn*d 2.

Tabl02-1. Audit Procedure for Structural Acceptance Criteria of MarkiContainment Long-Term Program Criteria Addtl. Licensee Uses btlon Keyitems Considered Alternate Approach e.{2) in the Audit Not Info. NA Remarks -

Met Met Reqd. Conser- Unconser-utla 6.7 (Cont.)

d. Ef fact of anchor displacement due to torus motion may be neglected from Equation -

9 of NC or ND-3652.2 [+]

if considered in Equations 10 and 11 of i NC or ND-3652.3' [4] . I 6.8 Safety relief valve discharge piping shall be enalyzed as follows: .

i

c. Analyze each discharge # # Reverked egyher (3']

line.

b. Model shall represent #

piping and supports, from nozzle at main steam line to discharge in suppression pool, and include discharge device and its supports.

c. For discharge thrust

• loads, unie time history analysis.

d. Use spectrum analysis

• or dynamic load factors ,

for other dynamic loads.

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TER-C5506-310 Table 2-3. Non-Piping Structural Elements STRUCTURAL ELEMENT ROW

' External Class M_C

-- Torus, Bellows, 1 External Vent Pipe, Drywell (at Vent) ,

Attachment Welds, Torus Supports, Seismic Restraints .

Internals Vent Pipe General and 2 Attachment Welds at Penetration 3 (e.g., Header)

Vent Ring Header General and 4 Attachment Welds At Penetrations 5 (e.g., Downcomers) -

Downcomers General and 6i Attachment Welds  !

l Internals Supports 7 Internals structures i

General 8 ,

Vent Deflector 9 A_ _ _ _ _ _ _ _

' ~

E2M1EM~M'M-!222'i:. MJZr; aiRnas.Jn:2hrfmuu rz:=ma n .

TER-C5506-310 Table 2-4. Piping Structural Elements i-STRUCTURAL ELEMENT ROW

' Essential Piping Systems With IBA/DBA 10 With SBA 11 Nonessential Piping Systems With IBA/DBA 12 With SBA 13 1

1

TER-C5506-310

3. REFERENCES .

,1. NUREG-0661 .

" Safety Evaluation Report, Mark I Containment Iong-Term Program Resolution of Generic Technical Activity A-7" Office of Nuclear Reactor Regulation USNIC July 1980

2. MEDO-24583-1

" Mark I containment Program Structural Acceptance Criteria Plant Unique Analysis Application Guide" General Electric Co., San Jose, CA October 1979

3. Technical Evaluation Report Audit for Mark I Containment Long-Term Program . Structural Analysis Enrico Fermi Atomic Power Plant Unit 2 Franklin Research Center, Philadelphia, PA August 1983, TER-C5506-309

4. American Society of Mechanical Engineers Boiler and Pressure vessel Code,Section III, Division 1

" Nuclear Power Plant Components" New York: 1977 Edition and Addenda up to Summer 1977

5. NEDO-21888 Revision 2

" Mark I Containment Program Load Definition Report" General Electric Co., San Jose, CA November 1981 I

e Enkligeyerch Cen'er

L _

k.

L Mr.' B. Ralph Sylvia L Detroit Edison Company Fermi-2 Facility -

j-

"CC:

.Mr. Harry'H. Voigt, Esq. Ronald C. Callen -

LeBoeuf, Lamb, Leiby & MacRae~ Adv. Planning Review Section 1333 New Hampshire Avenue, N. W. Michigan Public Service Commission Washington, D. C. 20036 6545 Mercantile Way l P. D. Box 30221 l John Flynn, Esq. Lansing, Michigan 48909 Senior Attorney

Detroit Edison Company Regional Administrator, Region III 2000 Second Avenue U. S. Nuclear Regulatory Commission Detroit, Michigan 48226 -

799 Roosevelt Road Glen Ellyn, Illinois 60137 Mr. Dennis R. Hahn, Chief Nuclear Facilities and Environmental Monitoring Section Office Division of Radiological Health P. O. Box 30035 1

, Lansing, Michigan 48909 l

Mr. Steve Frost i Supervisor-Licensing Detroit Edison Company 'l' Fermi Unit 2 6400 North Dixie Highway l Newport, Michigan 48166 l Mr. Thomas Randazzo Director, Regulatory Affairs Detroit Edison Company Fermi Unit 2 6400 North Dixie Highway Newport, Michigan 48166 Mr. Walt Rogers U. S. Nuclear Regulatory Commission Resident Inspector's Office 6450 W. Dixie Highway i Newport, Michigan 48166 Monroe County Office of Civil Preparedness 963 South Raisinville Monroe, Michigan 48161

_ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . . _ _ _ _ . _ _ _