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-Carolina Power & Ught Company4

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(1 Brunswick Nuclear Project*

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Southport, NC 28461-0429March 22, 1990

PILE: B09-135100:r. SERIAL: BSEP/90-0244

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U U.S. Nuclear Regulatory CommissionATTN: Document Control Desk

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Washington.-DC 20555y-ji BRUNSWICK STEAM ELECTRIC PLANT UNITS 1 AND 2L DOCKET NOS. 50-324 & 50-325'

!- LICENSE NOS. DPR-62 & DPR-71F RESPONSE TO NRC IFI 50-325/88-36-02 AND 50-324/88-36-02s

Gentlemen:

[ The Final Summary Report for 15' Bulletin 79-02 is submitted in response to NRC..

Inspection Report 50-325/88-36 and 50-324/88-36, dated November 3, 1988. Item 44

s - of this| inspection report closed Pipe Support Base Plate Designs UsingConcrete Expansion Anchor Bolts - IEB 79-02, and opened Inspector Follow-up-

' Items 50-325/88-36-02 and 50-324/88-36-02, which stated that CP&L would submita Final Summary Report summarizing the bulletin requirements.and BSEP'sresponse. The review of Ililti Bolt allowables (Inspector Follow-up Item50-325/88-36-03:and 50-324/88-36-03) will be addressed at a later date, a

IE Bulletin 79-02 requirements coupled With appropriate CP&L actions are asfollows:

'1. Verify that pipe support base plate flexibility was accounted for in thecalculation'of anchor bolt loads.

CP&L action is as follows:

|' References:,

a. Details of NRC Exit Interview (dated 8/7/80)which reference LER 2-80-55

A b. Letter BSEP/81-0440 (dated 2/25/81)c. Letter BSEP/82-1616 (dated 7/26/82)

which provides a chronological account of CP&Ls actions taken toassure compliance of already installed base plates to the bulletinflexibility position.

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Relative to new design, in order to ensure that new base ~ plate designs.took-'

into account the flexibility position, Attachment'l to CP&L Letter,.Serial: -GD-79-1739 was adopted and issued as a part of Power DisciplineTechnical Bulletin 7B to be used as.a design _ guideline for base plate design, ,

:This was'later included in UE&C's H-21 evaluation criteria and later in, '

the Brunswick Engineering Support Unit's (BESU). Structural Design Guides 2and.7 which are the on-site guideline for pipe support design. |

'

o2 .- Verify that the concrete expansion anchor. bolts have the following

minimum-factor of safety between the bolt design. load.and the bolt; ,

4 ultimate capacity determined'from static tests which sim'ulate:the actualconditions of. installation. .,.

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CP&L action is as-follows:-i

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t References:

a. Letter GD-79-1739 (dated 7/12/79)'

'b. Letter GD-79-3130 (dated 12/6/79)c. Letter BSEP/80-2139 (dated 12/30/80) ;d. Letter BSEP/81-0440 (dated 2/25/81) '

e. Letter BSEP/82-1616-(dated 7/26/82)-f. Letter NLS 84-214 (dated 11/26/84) ,:

,

which discuss in detail CP&L's anchor bolt testing and reanalysis |programs which assure compliance of "in place" anchor bolts relative

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to the accepted factors of safety.

Power Discipline Technical Bulletin 7B covers the new design and was jwritten to include the factors of safety provided by Bulletin 79-02.Ae' stated before this information was used in UE&C's M-21 evaluationcriteria and in BESU's Structural Design Guides 2 and 7.

.

3. Describe the. design requirements, if applicabic,-for anchor bolts to !

withstand cyclic loads such as seismic' loads and high cycle' operating ;

loads,,

E CP&L. action is as. follows:t

References: :, !

a. Letter GD-79-1739 (dated 7/12/79) ;b. Letter BSEP/82-1616 (dated 7/26/82)c. Letter NLS-84-214-(dated 11/26/84) !

which explain the position taken by CP&L relative to cyclic loading.

and the torquing program that was adopted to ensure that existing ;

expansion anchors could withstand such loading.,

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j|A To ensure that e.'# design.is acceptable 1 relative to. cyclic loading*

.f -the same series of-design documents. listed under requirements i and 2 _. !

above nyre updated with the new pretensioning loads _ relative to the ;._

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design allowable as mentioned in CP&L's torquing program.; '

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~4. Verify from-existing QC documentation that design requirements have been>

met for anchor bolts relative to cyclic loading and bolt size and type.'

CP&L's compliance with this part of Bulletin 79-02/is. covered by'the= -|.

testing program as described in the letters referenced in Section11' j

above. That test program was used to check:for-indication of-incorrect- |

proload'and incorrect bolt size, type,.and embedment.

cf For nos design work- QC hold points were established-~as a part of site,'

installation specification BSEP 248-107, to ensure that these require-,

i monts were met'. i,

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5. Determine the extent that= expansion anchor bolts were used in-concrete" ' block (masonry)' walls to attach piping supports in Seismic Category-+

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1/ Safety Related systems. ]CP&L |did- noti use expansion anchors . to attach safety-related'systen s',

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to concrete block walls.

6', Determine:the extent that pipe supports with expansion" anchor' bolts used'N structural steel shapes instead of base. plates. 3

-As stated in CP&L Letter GD-79-3130, support.. meeting this criteriawere included in the inspection and reanalysis program which was-

,Iestablished.at the beginning of the bulletin compliance effort and

w continued until-program completion..

Relative:to new design work-the same criteria established in the

..design documents in Sections l', 2,-and 3 above' applies to supports. H

.

with' standard' structural steel shapes used in lieu of base plates, ["!~ although base plates are used almost exclusively for new design on

safety-related systems.t

N |Tho'remainderzof the requirements listed in IE Bulletin 79-02 refer to the- *

scheduling of requirement completion. ;,

' : Attachmcrit 1 provides a short synopsis'of those correspondences referred to inthis letter.

!

This report summarizes the correspondence between the Brunswick Steam Electric !Plant and the NRC pertaining to the requirements-of IE Bulletin 79-02.

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b i /, ' L ATTACllMENT 11

Q/,y:'y !$hesfollowing list is composed of pertinent letters and memorandums dealing-~

; with' tho' BSEP closure of IEB 79-02 along with the . appropriate actions taken to'gf. . resolve any'open items., --Note that this. list,is intended to deal with IEB-

'79-02_tnly, even though much of the information-included references IEB'79-07.-.and:IEB 79-14,

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-1. LLetter GD-79-1739 CP&L to NRC, dated July 12, 19794

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y This letter explained, item by item, CP&L's current position regarding -g- cach-facet of IEB 79-02. Safety-related~ piping base plates ' wore -

reanalyzedifor new loads per the.new IEB 79.-07. guidelines. This was' done-

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'by BSEP Plant ModAfications 79-123'and 79-124. Work was ongoing to-. .

J comply with the noe safety factors for expansion anchora. The nuts onif expansion anchorsJwere to be retorqued to satisfy the requirements for

cyclic loading. . An expansion alachor test program was initiated at.BSEP,.

y the results of which would be m31ntained on. site' for. NRC inspection.

2. Letter GD-79-3130, CP&L to NRC, dated December 6,1979m~

This letter stated that the requirements of IEB 79-02'had'been satisfied"' .by CP&L, -A few. inaccessible hangers were noted, butischeduled for

..

E completion during the next outage. Appropriate documentation was in the-plant vault available~.for NRC review.

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3.. Detall's-of:NRC Exit Interview, dated August 7, 1980

y,~ Due to-LER 2-80-55, it was realized that the CRD-linerb4se plates were'

not included in the base plate flexibility roanalysis. Because of this,

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the-Bulletin would remain open. 'A completion commitment date of3;j,"

LDecember 31,~1980, was given<by CP&L.

4. Letter BSEP/80-2139, CP&L to NRC, dated December- 30~ 1980'

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CP&L stated that approximately 300- additional supports per unit' had been-

(identified for expansion anchor testing. requiring.that the final IEBs79-02schedule be pushed forward. The final schedule would be presented-February-25, 1981.

,W 5. ~. Letter BSEP/81-0440, CP&L to NRC, dateel February 25,L 1981

' Flexure acolysis was completied for the essential-CRD base plates.Completion of base plate flexibility tecting relative to piping not- . ,

, essential to safe shutdown was scheduled as.a part of the Phase IIc j, ~f program.(March 51,.1982). Test.ing of the-accessiblo-portion of the 600-

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' additional supports (see above) was scheduled for completion by July 31,.o

p, 1981..

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6. ' Letter.BSEPL82-1616,- CP&L to NRC' dated July' 26,11982 ,

'%' CP&L stated that nonessential-portions of the CRD system (Phase II) are.

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not safety related;and, therefore, reanalysis is not-required. Also.*

7 stated was the fact that the. additional BSEP-2 support: testing was:.

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completed. -BSEP-1 testing-is essentially. complete with.the few: remainingsupports to be finished during the-upcoming' September 1982 outage.

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7. Letter NLS 84-214, CP&L to NRC,' dated November 26, 1984 .,

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c -This was the last submittal concerning'IEB.79-02.~ . It statedLthat the"-

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expansion anchor testing was completed. The BSEP-1-CRD support; fixes ;,

were' completed and BSEP-2 CRD supports'are to be completed pending'

-redesign of the Reactor Pressure-Vessel foundation wall window supports. ;.

The remaining work toL complete the obligation in Letter NLS -84-214 = (Item 7 - -

above) was done by;PlantiModification 82-147. This documents'the. completion,s

of the brunswick Steam Electric Plant. work pertinent to IE' Bulletin 79-02. .iBased onJthe information provided'to the NRC' relative to this Bulletin,' we- ?

irequest the closure.of-IEE 79-02.'

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