ML20012D976

Responds to Insp Repts 50-324/88-36 & 50-325/88-36 Re Util Response to IE Bulletin 79-02.Verification That Pipe Support Base Plate Flexibility Accounted for in Calculation of Anchor Bolt Loads Addressed

ML20012D976
Person / Time
Site:	Brunswick
Issue date:	03/22/1990
From:	Harness J CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BSEP-90-0244, BSEP-90-244, IEB-79-02, IEB-79-2, NUDOCS 9003290176
Download: ML20012D976 (6)

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4 Carolina Power & Ught Company

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• 1 Brunswick Nuclear Project p

P. O. Box 10429 .

Southport, NC 28461-0429 March 22, 1990 PILE: B09-135100:

r. SERIAL: BSEP/90-0244 U U.S. Nuclear Regulatory Commission ATTN: Document Control Desk ,

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

!- LICENSE NOS. DPR-62 & DPR-71 F

RESPONSE TO NRC IFI 50-325/88-36-02 AND 50-324/88-36-02 s

Gentlemen:

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

4 Inspection Report 50-325/88-36 and 50-324/88-36, dated November 3, 1988. Item 4 s- of thisl inspection report closed Pipe Support Base Plate Designs Using Concrete 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 submit a Final Summary Report summarizing the bulletin requirements.and BSEP's response. The review of Ililti Bolt allowables (Inspector Follow-up Item 50-325/88-36-03: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 as follows:

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

CP&L action is as follows:

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References:

a. Details of NRC Exit Interview (dated 8/7/80)

A which reference LER 2-80-55

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 to assure compliance of already installed base plates to the bulletin flexibility 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 Discipline Technical 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 2 and.7 which are the on-site guideline for pipe support design. l o

2 .- 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 actual

,. conditions of. installation. .

I i CP&L action is as-follows:-

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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 l

, programs which assure compliance of "in place" anchor bolts relative to the accepted factors of safety. '

Power Discipline Technical Bulletin 7B covers the new design and was j written to include the factors of safety provided by Bulletin 79-02.

Ae' stated before this information was used in UE&C's M-21 evaluation criteria 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:

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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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• 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  ;

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

~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= -l testing program as described in the letters referenced in Section11' j above. That test program was used to check:for-indication of-incorrect- l 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-ii ,

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- ,,

1/ Safety Related systems.

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, CP&L ldid- 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 criteria were included in the inspection and reanalysis program which was-

,I established.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, [

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although base plates are used almost exclusively for new design on t safety-related systems.

N lTho'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 in this 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/,

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y  !$hesfollowing list is composed of pertinent letters and memorandums dealing-

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'gf  ; with' tho' BSEP closure of IEB 79-02 along with the . appropriate actions taken to

. . 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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4 -1. LLetter GD-79-1739 CP&L to NRC, dated July 12, 1979 R

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

. . 'by BSEP Plant ModAfications79-123'and 79-124. Work was ongoing to-J comply with the noe safety factors for expansion anchora. The nuts on if 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 6,1979 m~

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-

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plant vault available~.for NRC review.

3.. Detall's-of:NRC Exit Interview, dated August 7, 1980 Due to-LER 2-80-55, it was realized that the CRD-linerb4se plates were

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y, not included in the base plate flexibility roanalysis. Because of this, 3;j,"

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the-Bulletin would remain open. 'A completion commitment date of LDecember 31,~1980, was given<by CP&L.

4. Letter BSEP/80-2139, CP&L to NRC, dated December- 30~ 1980 CP&L stated that approximately 300- additional supports per unit' had been (identified for expansion anchor testing. requiring.that the final IEBs79-02 schedule 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-j

, essential to safe shutdown was scheduled as.a part of the Phase IIc

~f program.(March 51,.1982). Test.ing of the-accessiblo-portion of the 600-o ' additional supports (see above) was scheduled for completion by July 31,.

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.

4 7 stated was the fact that the. additional BSEP-2 support: testing was: .

completed. -BSEP-1 testing-is essentially. complete with.the few: remaining supports to be finished during the-upcoming' September 1982 outage. -t

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

-This was the last submittal concerning'IEB.79-02.~ . It statedLthat the" c t 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 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. .i Based onJthe information provided'to the NRC' relative to this Bulletin,' we-  ?

request the closure.of-IEE 79-02. i P

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