ML19262C347

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Responds to IE Bulletin 80-01.Includes Data on Anchor Bolt Tests.Failures Were Analyzed & Repaired.Some Supports Originally Identified as Requiring Insp Not Inspected Because No Anchors or Vertical Uplift Loads Identified
ML19262C347
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 01/22/1980
From: Furr B
CAROLINA POWER & LIGHT CO.
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
IEB-80-01, IEB-80-1, NUDOCS 8002110315
Download: ML19262C347 (2)


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January 22, 1980 FILE: NG-3513 (B)

SERIAL: NO-80-07 h,q z

Mr. James P. O'Reilly, Director y

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U. S. Nuclear Regulatory Com=ission Region II 2_

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101 Marietta Street, Suite 3100

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BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 & 2 LICENSE NOS. DPR-71 AND DPR-62 DOCFET NOS. 50-325 AND 50-324

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SUPPLLMENTAL RESPONSE TO IE BULLETIN 7 9-02

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Dear Vr. O'Reilly:

The following information is provided as requested by Mr. Modenos during his exit meeting on July 27, 1979:

A.

Inspection of anchor bolts, as required by the subject bulletin, was conducted in two phases--supports for lines >2-1/2" diameter and supports for lines <2-1/2" diameter.

These results are:

ITEM UNIT 1 UNIT 2 TOTAL 1.

>2-1/2" Line Size:

Supports Tested 71 68 139 Base Plates 83 74 157 Anchors Tested 291 273 564 Anchors Failed 23 12 35 Percent Failed 7.9%

4.4%

6.2%

2.

<2-1/2" Line Size:

Supports Tested 188 168 356 Base Plates 210 173 383 Anchors Tested 458 389 847 Anchors Failed 14 26 40 Percent Failed 3.06%

6.68%

4.72%

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Combined Results:

Supports Tested 259 236 495 Base Plates 293 247 540 Anchors Tested 749 662 1411 Anchors Failed 37 38 75 Percent Failed 5%

5.74%

5.32%

B.

Supports which had failed anchors were identified as:

1.

>2-1/2" Line Size UNIT 1 UNIT 2 Support Failure Mode Support Failure Mode 1 Ell-14SPG421 Rotated 2 Ell-131PG364 Rotated 1 Ell-47PG513 Rotated 2 Ell-71SS393 Bad All Thread lEll-18SS447 Broke All Thread 2 Ell-109FS395 No Anchor lEll-2PG135 Broke All Thread 2 Ell-89SS480 Installation lE41-20SS196 Installation 2E51-42SS75 Installation lE41-20SS195 Installation 2G31-34PG130 Rotated lE51-42SS77 Broke All Thread 2C41-18FS17 Installation 1G31-50PG21 Installation 2G41-7PG120 Bent All Thread IC41-lVH22 Bad All Thread 2SGT-6PG34 Broke All Thread 1G41-12SS98 Installation ICAC-42PG14 Installation ISGT-2PGl9 Rotated 2.

<2-1/2" Line Size UNIT 1 UNIT 2 Support Failure Mode Support Failure Mode lE51-19PGlll Installation 2 Ell-99PG572 Broke All Thread 1G41-5SS152 Missing All Thread 2E21-22PG98 Anchor Rotated 1G41-45PG144 Anchor Pulled Out 2E21-9PG101 Anchor Rotated IG41-45PG142 Installation 2E51-99PG572 Broke All Thread 1SW-150PG251 Anchor Rotated 25W-152PG246 Broke All Thread 1SW-198A284 Broke All Thread 2SW-152PG247 Broke All Thread ISW-198PG282 Anchor Rotated 2SW-148PG248 Broke All Thread ISW-148PG248 Broke All Thread 25W-150PG250 Broke All Thread ISW-150PG250 Not Installed 25W-150PG251 Broke All Thread 1SW-151PG182 Not Installed 2SW-146PG252 Broke All Thread PS-3456 Installation 2SW-124FH262 Broke All Thread PS-3110 Installation 2SW-131FH268 Anchor Rotated PS-3106 Installation 2SW-151PG182 Broke All Thread PS-1460 Installation 25W-153PG184 Broke All Thread PS-1450 Installation 2SW-147FS186 Broke All Thread 2SW-147PG187 Broke All Thread 2SW-149FS188 Broke All Thread PS-3082 Installation PS-3076 Installation PS-3042 Broke All Thread PS-3000 Rotated PS-1498 Installation

C.

Failures were analyzed and repaired, where necessary. All repairs (for both phases) were completed by the dates committed to in our supplementary response of August 10, 1979.

D.

A number of supports originally identified by UE6C as requiring inspecticn did not, in fact, warrant inspection.

This is due to factors such as weld type attachment (no anchors used) or all compressive (no vertical up-lift) loads on the base plates.

These totaled 37 supports for the >2-1/2" line size supports and 28 supports for the <2-1/2" line size supports. The list of deleted supports will be maintained with the permanent results.

E.

A number of supports (18) were identified by the NRC (inspection by Mr. L.

Modenos, July 26-27, 1979) as having questionable data which was not eval-usted for possible failures. These supports were Phase 1 (>2-1/2" line size) supports.

Since no clear acceptance criteria for proper anchor installation were in use at the time the original inspection was conducted, all of the anchors for the Phase 1 supports were reinspected. Upon rein-spection, none of the eighteen supports were failures.

Several other anchors did fail the reinspection and are accounted for in the current results.

F.

All oth.r commitments made in the CP&L supplementary response of August 10, 1979, were met.

The result of the inspection will be placed in the vault for permanent storage.

Yours very truly, B. J. Furr Vice President Nuclear Operations RMP/CSB/eaj cc:

Mr. N. C. Moseley 1946 073