ML19337B657
| ML19337B657 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 09/16/1980 |
| From: | Parker W DUKE POWER CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| IEB-79-02, IEB-79-2, NUDOCS 8010080449 | |
| Download: ML19337B657 (6) | |
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September 16, 1980 VeCf PettsOINT 5esam Paoovctiom ICLf DMQNCI ARE A 704 373-4083
/ Hr. J. P. O'Reilly, Director U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 Re: McGuire Nu ca N tation Docket No
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Subj ect: RII:JPO IE Bulletin 79-02, Revision 2
Dear Mr. O'Reilly:
Please find attached a supplemental response to IE Bulletin 79-02, Revision 2.
Note that this letter supplements previous Duke Power Company responses dated January 7, 1980, July 6, 1979 and August 20, 1979.
Very truly yours,
//jk O. 4 William O. Parker, Jr.
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? JB:scs Attachment ec: Director Director Office of Inspection & Enforcement Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission U. S. Nuclear Regulatory Commission Washington, D. C.
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MCGUIRE NUCLEAR STATION Responses to USNRC IE Bull Original:
etin 79-02, Revision 2 Revision 1:
July 6 1979 Revision 2:
Janua ry, 7 1980 September',16, 1980 McGuire Nuclear Station is i lowing is aerected in Unit #1 and a largecompletio n t #1.
number have been erected in U iEsse Company intends tosummary, by item, of R vision 2.
the extent and manner in whi satisfy Actions 1 through 9 of n t #2.s have been The fol-Response 1:
the IE Bulletin 79-02ch Duke Duke Power Company will ac gory I pipe support base platcalculation of ex count for base plate flexibilior t
calculation method
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element analysis or.which has been verified by es using either a c Cate-
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for a particular base plat a specific conservative hand including appropriate load di The models and boundary co d e.
anchors studies,and on work performed bused for the finite ele splacement characteristics of ysi tions,s n
which was sponsored by a gro y Teledyne Engineering Servinalys the to anchor support plates designedrespond to gener up of thirteen (13) utilities f sis methods are being reanaly cesBulletin 79-02.
if required to ormed prior to implementing theseAll expansion zed accordingly and will be modifi comply with allowable anchor b l Resoonse 2:
analy-design load and the boltThe minimum factors of s o t loadings.
ed ultimate capacity determined frety load tests, used in Duke's d Normal Conditionsesign of pipe supports, are as f or bolt
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om static Upset Conditions 4
o lows:
Faulted Conditions 4 These factors of 2 1/8 pansion anchors. safety are for wedge typeSo stages of McGuire constructio Nuclear Safety Related appli 1975 n.
re cations was discontinued in FebUs shell type anchors and the dDuke Power Company has viewed to assure that a minim or these supports has been ried esign of ruary mainta ined.
um factor of safety of five (5) ng McGuire Seismic Category I e-is restricted to normal weight expansion anchor installationsstr strengths normal weight concrete and ianufacturer's test based on m.
are e load capacities are recommendations for nstalled concrete i
strenq h
' McGuire Seismic Category Icou bolt spacing in recommendations.accordance with manu,fa eraction minimum roperly ac-cturer's test results andedge d Response 3:
Duke Power Company desi loadings including seis i thennal loads, etc, Agns pipe supports ating loads m c loads static or qu,asi-static loadhydro test loads, normalst all applicabl bination of the applicable loading resulting from the mostsupport is designe the expans oper-Company coion anchors are as specifi d
- s. 'The safety factors us dcritical com-Services to demonstrat sponsored tests performed b Nuclear Station wi e
in Response 2.
e for e that expansion anchors i (operating.oading (ll perform adequately under amplitude l The final test report wseismic) and high cycle /lo nstalled at McGuire USNRC for a)ll Duke Poww amplitude loadinglow ycle Mr W 0 Parker's c
Duke) letter to Mr J P 0'er Company Nuclear August as generically submitted t r(egardi 20, 1979 Duke Power Company has dng McGuire Nucle o
toonso 4:
Reilly n.
dated sufficient documentation t in Nuclear Safety Relat eveloped and is continuino verify t and type and are properly i ed pipe supports are the c facturer's recomendations.nstalled in accordinc documentation developed nchors used orrect siz testing of installed eIn February 1977. Duke P The following is a summe with manue ary of ower Company i formed in response to concerns dev lxpansion anchors.nitiated some r decided that a formal iimproper installation p e ping in the industry abThis testing o
ractices.
anchors nspection program for concBased on these te would be implemented out In March 1977, Constructi
. Duke rete wedge slee expansion inspec, tion. ve and self-drilling tyon Procedure CP-503 was is
- 2) perpendicularity There were four pe concrete sued for for self-drilling an,chors3) torque,riteria to be met: expansion anchor c
and 4 having documentation iprior to issu,e of
- 1) spacing In June 1977 enbedment depth, excep,t orque.
n acccrdance with CP-503All anchors for all to accordance with CP-503 and document d of attachments using expa of e supports not 4357 anchors were insp A sampling of other typwere inspecte e.
This inspection was nsion anchors was also mad ected, 2072 of which were pi completed in September 1978 In August 1977 es e.
A total CP-503 as the a, QA Procedure M-52 pe supports.
s pansion anchors.pplicable inspectio n procedure forwas issued which supersede 5/8" 0 required torqu M-52 stated
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all anchors e inspection and thisthat only anchors gre s
with a concrete specified torque greater th ex-was laterater than revised an 100 ft-lbs. to
the testing performed iThis reduction in torq n which only 2 ofnspection was based on t to meet torque requireme e results of nts.
the 4357 anchors failed In April 1975. Constructi vide control over the inst ll on Procedure Cp-308 was This procedure has been a
perien grams.ce gained by Duke through its insp updated periodically to reflect theanchors.
Self-drilling shell type ection and testing pro-ex cordanc shell is assured since the acedures.e Adequate embedment depth a d its own hole and the shell i e
ed in full expansion of theinstallat n
inspectewall in the final nchor shell itself is s driven installation step. below the surface ofused to drill snugness.d for size type, perpendicularity type anchors were Shell the Response, 2 indicated that D Seismic Category I pipe s implemented a uke has identified all, spacing a i
shell type anchor inspectioupports using shell with IE Bullet t
documentation. in 79-02, latest revisitype anchors ment, shell sho The parameters inspected n program in acco.
Duke on, to supplement existin bolt hole size,ulder to plug measurem rdance visually acceptable shell rigorous to identify anf d fconfirm th ent, perpendicularity and to type expansion anchors i g a 3% sample of on load carrying capability e iciency having apection program is suffici testing program is outliof cation MCS-1196.02-00-0003 the anchor.
ently This inspection andsignific spected at McGuire Unit 1A total of on Specifi-sample was completed with 8the re Generator Buildingfive.
Four 4 e Auxiliary Building. tor Building ands were in-e Reac self-drilling anchors were fsample anchors faile anchors being tested.The 3% pull. test 1
which had the potential fo u
test.
Thirteen (13 None of rying capability.
r degrading their ultimatound to have the of the 242 Plate bolt hole s c en e load carcies Duke expansion anc%e is hor inspection programspecifically not inspected a 1 of IE Bulletin 79-02 that plate bolt hole siziplates which utilized eith
, Duke inspected 331 s part of bolt holes in 104In response to the
. bolt holes were found to be sli h er sleeve or wedge a bolt hole sizes were acceto be slightly oversized 8
rom deg tly undersiz Seven (7confinn ptable. sign drawings.ed ~a.138 we)re found test sample provides rea pla te plate bolt hole size for All of Duke has concluded that thithe plate sonable and adequate assura wedge and sleeve type expan ince of proper s
s on anchors.
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' The supplemental Self-Drill Inspection Program implemented under
!!CS-1196.02-00-0003 identified 55 of 191 plate holes ins;:ected as oversized.
This oversizing was determined to be due to the self-drill anchor installation procedures. All oversized holes have been reviewed and modifications made where required.
In order to address the question of the relationship of cyclic /
load carrying capacity to installation procedure (anchor preload),
the tests referred to in Response 3, performed by Teledyne Engineering Services and sponsored by.the group of thirteen (13) utilities, have been performed on anchors installed in accordance with manufacturer's reconsnended installation procedures and have no more preload than is provided by the use of these procedures.
Based on Duke's understanding of the behavior of expansion anchors and on cyclic testing which has been performed Duke Power Company l
is confident that the anchors will perform adequately.
Response 5:
Nuclear Safety Related/ seismic pi being attached to block (masonry)pe supports are prohibited from walls using concrete expansion ancho rs.
In response to Revision 2 of IE Bulletin 79-02, Duke Power Company has conducted an on-site confimatory review at McGuire Unit 1 of Nuclear Safety Related/ seismic pipe supports
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to assure that no such installations exist.
Results of this re-view have confimed that there are no such installations of this type at McGuire Nuclear. Station Unit 1.
i Response 6:
The expansion anchor installation and inspection procedures uti-lized at McGuire Nuclear Station and described in Response 4 apply to all expans, ion anchors installed in Nuclear Safety Re-lated pipe supports. Each expansion anchor is inspected regard-less of the physical configuration of the steel members being connected to the concrete.
These supports are included in the actions being perfomed by Duke Power Company to satisfy the requirements of IE Bulletin 79-02.
Response 7:
McGuire Nuclear Station is currently under construction, there-fore Bulletin Iten 7 is not applicable.
Response 8:
McGuire Nuclear Station is currently under construction, there-
'.lletin Item 8 is not applicable.
Response 9:
Those pipe supports which have not been installed are included in actions performed to meet the requirements of IE Bulletin 79-02 as outlined in Responses 1 through 6.
Revision 2 of Item 2 of the Bulletin reauests verification by Duke Power Company that a unifom factor of safety was applied for all load combinations in the design of expansion anchors for McGuire Nuclear Station.
The expansion anchor design factors
on the normal, upset and faulted load combin structures subject to the same load combinatio ased The gradation ypes of Company did not meet the revised (R2) sec to its issuance.
u e Power n 4 prior 9
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