ML19256G312: Difference between revisions

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Florida                                                                                                        -
Florida                                                                                                        -
Power CO M PO R A Y IO N December 10, 1979 File:          3-0-3-a-4
Power CO M PO R A Y IO N December 10, 1979 File:          3-0-3-a-4 Mr. J. P. O'Reilly Director U.S. Nuclear Regulatory Commission                                                                              ,-
                                                                                                                      .
                                                                                                                    <
Mr. J. P. O'Reilly Director U.S. Nuclear Regulatory Commission                                                                              ,-
Office of Inspection and Enforcement Suite 3100 101 Marietta Street Atlanta, GA 30303
Office of Inspection and Enforcement Suite 3100 101 Marietta Street Atlanta, GA 30303


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As indicated by the enclosed responses, no additional work is required for Crystal River Unit 3 to comply with the subject bulletin.
As indicated by the enclosed responses, no additional work is required for Crystal River Unit 3 to comply with the subject bulletin.
Please contact this office if you require any additional discussion concerning our response.                                ,
Please contact this office if you require any additional discussion concerning our response.                                ,
Very truly yours, FLOR}D POWER CORPORATION
Very truly yours, FLOR}D POWER CORPORATION l
                                                                              '
A. Hancock irector, Nuclear Operations g"e=h"8                                                    ,
l A. Hancock irector, Nuclear Operations
                      -
g"e=h"8                                                    ,
i660 239 cc: Director Division of Operating Reactors Office of Inspection and Enforement U.S. Nuclear Regulatory Commission                                                                _ , _ ,
i660 239 cc: Director Division of Operating Reactors Office of Inspection and Enforement U.S. Nuclear Regulatory Commission                                                                _ , _ ,
Washington, D.C. 20555                                                              Ci";~~';/ I ~
Washington, D.C. 20555                                                              Ci";~~';/ I ~
                                                                                                                                    -
General Office 3201 ininy lounn stree: soutn . P O Box 14042. St Petersburg. Florida 33733 e 813-866-5151 7912310 0 7
General Office 3201 ininy lounn stree: soutn . P O Box 14042. St Petersburg. Florida 33733 e 813-866-5151 7912310 0 7


      '
s RESPONSE ID IE BULLETIN 79-02, REVISION NO. 2 Item 2, 3rd Paragraph:
s
    ,
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  .
RESPONSE ID IE BULLETIN 79-02, REVISION NO. 2 Item 2, 3rd Paragraph:
               ". . . provided. The Bulletin factors of safety were intended for the maximum support load including the SSE."
               ". . . provided. The Bulletin factors of safety were intended for the maximum support load including the SSE."


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===Response===
===Response===
                                                  .
Concrete expansion anchors were not used to fasten seismic Category I systems to concrete block.
Concrete expansion anchors were not used to fasten seismic Category I systems to concrete block.
Item 6, 1st Paragraph:
Item 6, 1st Paragraph:
               " Determine the extent that pipe suppo,rts with expansion anchor bolts used structural steel shapes instead of base plates. The systems and lines reviewed must be consistent with the criteria of IE Bullettu No. 79-02, Revision 1."
               " Determine the extent that pipe suppo,rts with expansion anchor bolts used structural steel shapes instead of base plates. The systems and lines reviewed must be consistent with the criteria of IE Bullettu No. 79-02, Revision 1."
          .


===Response===
===Response===
                                                        -
The evaluation of pipe supports included those supports using structural steel shapes (angles, beams, channels) fastened with concrete expansion anchors. The evaluation was done using proven engineering principals and had demonstrated that the intent of the Bulletin has been complied with.
The evaluation of pipe supports included those supports using structural steel shapes (angles, beams, channels) fastened with concrete expansion anchors. The evaluation was done using proven engineering principals and had demonstrated that the intent of the Bulletin has been complied with.
JAHemhM08                                                    1660 240 D47
JAHemhM08                                                    1660 240 D47


.
  .
.
Item 7:
Item 7:
         "For those licensees . .  ."
         "For those licensees . .  ."
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Item 8:
Item 8:
Maintain documentation of any sampling inspection of anchor bolts required by Item 4 on-site and available for NRC inspection.
Maintain documentation of any sampling inspection of anchor bolts required by Item 4 on-site and available for NRC inspection.
    .


===Response===
===Response===
Documentation is maintained and will be available for NRC inspection at the Crystal River Unit 3 site.
Documentation is maintained and will be available for NRC inspection at the Crystal River Unit 3 site.
1660 241
1660 241 m                      ,
                                              ,
m                      ,
JAHemhM08 D47}}
JAHemhM08 D47}}

Latest revision as of 23:04, 1 February 2020

Forwards Response to IE Bulletin 79-02,Revision 2,re Pipe Support Base Plate Designs.During Field Testing All Wedge Type Concrete Expansion Anchors Torqued Per Manufacturer Recommendation for Original Installation
ML19256G312
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 12/10/1979
From: Hancock J
FLORIDA POWER CORP.
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
IEB-79-02, IEB-79-2, NUDOCS 7912310018
Download: ML19256G312 (3)


Text

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Florida -

Power CO M PO R A Y IO N December 10, 1979 File: 3-0-3-a-4 Mr. J. P. O'Reilly Director U.S. Nuclear Regulatory Commission ,-

Office of Inspection and Enforcement Suite 3100 101 Marietta Street Atlanta, GA 30303

Subject:

Cystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 I.E.Bulletin 79-02, Revision No. 2 Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts

Dear Mr. O'Reilly:

Enclosed is our response to I.E.Bulletin 79-02, Revision No. 2.

As indicated by the enclosed responses, no additional work is required for Crystal River Unit 3 to comply with the subject bulletin.

Please contact this office if you require any additional discussion concerning our response. ,

Very truly yours, FLOR}D POWER CORPORATION l

A. Hancock irector, Nuclear Operations g"e=h"8 ,

i660 239 cc: Director Division of Operating Reactors Office of Inspection and Enforement U.S. Nuclear Regulatory Commission _ , _ ,

Washington, D.C. 20555 Ci";~~';/ I ~

General Office 3201 ininy lounn stree: soutn . P O Box 14042. St Petersburg. Florida 33733 e 813-866-5151 7912310 0 7

s RESPONSE ID IE BULLETIN 79-02, REVISION NO. 2 Item 2, 3rd Paragraph:

". . . provided. The Bulletin factors of safety were intended for the maximum support load including the SSE."

Response

The governing load combination used is:

Deadweight + Thermal + (2.0) OBE Seismic + Occasional Mechanical Loads < Allowable Concrete Expansion Anchor Load The SSE load is conservatively considered to be equal to the term (2.0) OBE Seismic. Therefore, the applicable pipe supports at CR-3 have the required factor of safety for a SSE load.

Item 4, 6th Paragraph:

" Bolts which are found during the testing program not to be preloaded to a load equal to or greater than bolt design load must be properly preloaded . . ."

Response

During the field testing program, all wedge-type concrete expansion anchors were torqued per the manufacturer's recommendation for original installation, thus insuring that bolt preload exists.

Item 5:

" Determine the extent that expansion anchor bolts were used in concrete block (masonry) walls . . ."

Response

Concrete expansion anchors were not used to fasten seismic Category I systems to concrete block.

Item 6, 1st Paragraph:

" Determine the extent that pipe suppo,rts with expansion anchor bolts used structural steel shapes instead of base plates. The systems and lines reviewed must be consistent with the criteria of IE Bullettu No. 79-02, Revision 1."

Response

The evaluation of pipe supports included those supports using structural steel shapes (angles, beams, channels) fastened with concrete expansion anchors. The evaluation was done using proven engineering principals and had demonstrated that the intent of the Bulletin has been complied with.

JAHemhM08 1660 240 D47

Item 7:

"For those licensees . . ."

Response

Not applic.able.

Item 8:

Maintain documentation of any sampling inspection of anchor bolts required by Item 4 on-site and available for NRC inspection.

Response

Documentation is maintained and will be available for NRC inspection at the Crystal River Unit 3 site.

1660 241 m ,

JAHemhM08 D47