ML19270G114: Difference between revisions

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SEOUENT! AL                        CCCUR R E NCE        REPORT                    REVISION
SEOUENT! AL                        CCCUR R E NCE        REPORT                    REVISION
_ EVENT YEAR                                  R EPORT NO.                            CCOE                TYPE                        N O.
_ EVENT YEAR                                  R EPORT NO.                            CCOE                TYPE                        N O.
,
                   @ ,"tj.q,5 r a R Ol7l9l 21          22 l-l 23
                   @ ,"tj.q,5 r a R Ol7l9l 21          22 l-l 23
[ 0 l 7lll26 24 l/l 27 10 l1 l 28        29 W
[ 0 l 7lll26 24 l/l 27 10 l1 l 28        29 W
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41 l42Y l@          l43A l@        lX    lQ !9 l9J@
41 l42Y l@          l43A l@        lX    lQ !9 l9J@
44            47 CAUSE CESCRIPTION AND CORRECTIVE ACTIONS h
44            47 CAUSE CESCRIPTION AND CORRECTIVE ACTIONS h
[:      3      l The anchor bolt testing orogram has been expanded to include 100% testine and/or                                                                                    I i  i      1 analyses of anchors on pipe hangers for those systems,or portions of system remif ved I i  2      1 to meet design basis accidents or required to being the plant to cold shutdown.                                                                                      I
[:      3      l The anchor bolt testing orogram has been expanded to include 100% testine and/or                                                                                    I i  i      1 analyses of anchors on pipe hangers for those systems,or portions of system remif ved I i  2      1 to meet design basis accidents or required to being the plant to cold shutdown.                                                                                      I 3      l (See Attachment)                                                                                                                                                      l i A      l                                                                                                                                                                      l 8 3                                                                                                                                                                      80 ST iJ3                % PC'".E
        .
                                               . R                      OTH ER STATUS                IS OV RY                              DISCOVERY DESCRIPTION t  5 U @ lnInInl@l    '                  '2        n 9.s u
3      l (See Attachment)                                                                                                                                                      l i A      l                                                                                                                                                                      l
    '
8 3                                                                                                                                                                      80 ST iJ3                % PC'".E
                                               . R                      OTH ER STATUS                IS OV RY                              DISCOVERY DESCRIPTION
    '
t  5
              '
U @ lnInInl@l    '                  '2        n 9.s u
l      [f,J@l Test Program 45        4                                                                  .a l
l      [f,J@l Test Program 45        4                                                                  .a l
A!T,v,Tv        CO TENT RELEASED OF RELEASE                            AMOUNT OF ACTIV!TY                                                          LOCATION CF RELEASE i  e L:Ll @ tz_1              @ lt                      NA                        I            I        ur                                                                I
A!T,v,Tv        CO TENT RELEASED OF RELEASE                            AMOUNT OF ACTIV!TY                                                          LOCATION CF RELEASE i  e L:Ll @ tz_1              @ lt                      NA                        I            I        ur                                                                I
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   /
   /
NRC USE ONLY            ,
NRC USE ONLY            ,
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* I I N I@$lCmPric.@
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           /                                                                      __  - . . _ .. __ __-_~.
           /                                                                      __  - . . _ .. __ __-_~.
      .  .
ALABAMA POWER COMPANY JOSEPH M. FARLEY NUCLEAR PLANT DOCKET NO 50-348 ATTACIDIENT TO LER 79-021/0lT-2 Facility:              Joseph M. Farley Unit 1 Report Date:          5/29/79 Eve nt Da te :        4/1 2/ 79 Iden tification of Event:
            .
* ALABAMA POWER COMPANY JOSEPH M. FARLEY NUCLEAR PLANT DOCKET NO 50-348 ATTACIDIENT TO LER 79-021/0lT-2 Facility:              Joseph M. Farley Unit 1 Report Date:          5/29/79
    ,
Eve nt Da te :        4/1 2/ 79 Iden tification of Event:
Potential for anchor bolt failures and the resultant possibility of hanger failure in certain systems.
Potential for anchor bolt failures and the resultant possibility of hanger failure in certain systems.
Conditions Prior to Event:
Conditions Prior to Event:
The unit was in mode 6 (refueling) .
The unit was in mode 6 (refueling) .
Description of Event:
Description of Event:
'
In response to IE Bulletin 79-02, Alabama Power Company initiated a program to randomly select and test a sample of anchor bolts installed in Seismic Category 1, Safety Related, 2hinch and greater piping systems. Initial results of that program revealed that statistical sampling would not be sufficient to provide a high probability of greater than 95% anchor bolt reliability. The potential for anchor bolt failures and the resultant possibility of hanger failure were reported to the NRC on 4/12/ 79 under the potential applicability of Technical Specification 6.9.1.8(1) .      Subject bolts were manufactured by Phillips Drill Co., Hilli Fastening Systems Incorporated and Wej-It Corporation.
In response to IE Bulletin 79-02, Alabama Power Company initiated a program to randomly select and test a sample of anchor bolts installed in Seismic Category 1, Safety Related, 2hinch and greater piping systems. Initial results of that program revealed that statistical sampling would not be sufficient to provide a high probability of greater than 95% anchor bolt reliability. The potential for anchor bolt failures and the resultant possibility of hanger failure were reported to the NRC on 4/12/ 79 under the potential applicability of
  '
Technical Specification 6.9.1.8(1) .      Subject bolts were manufactured by Phillips Drill Co., Hilli Fastening Systems Incorporated and Wej-It Corporation.
Designation of Aoparent Cause:
Designation of Aoparent Cause:
Under investigation.
Under investigation.
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2237 256
2237 256


    .
       /                                                                          _ .. ._.._____.
       /                                                                          _ .. ._.._____.
79-0 21/OlT-2 Corrective Action:
79-0 21/OlT-2 Corrective Action:
Line 100: Line 82:
This piping includes:
This piping includes:
: a. Seismic Category 1; Safety-Related 2-1/2 inch and above.
: a. Seismic Category 1; Safety-Related 2-1/2 inch and above.
  .
: b. Seismic Category 1; Safety-Related Class 1 under 2-1/2 inch.
: b. Seismic Category 1; Safety-Related Class 1 under 2-1/2 inch.
: c. Seismic Category 1; Safety-Related of other classes for which the designer performed detailed analysis.
: c. Seismic Category 1; Safety-Related of other classes for which the designer performed detailed analysis.
Line 107: Line 88:
: 1. Component Cooling Water System
: 1. Component Cooling Water System
: 2. Service Water System
: 2. Service Water System
'
: 3. Sampling System
: 3. Sampling System
: 4. Chemical Vclume and Control System
: 4. Chemical Vclume and Control System
Line 124: Line 104:


         /                                                                        -  . . . ._ _.
         /                                                                        -  . . . ._ _.
      .
    .
        .
79-021/0lT-2
79-021/0lT-2
   .            17. Containment Isolation System
   .            17. Containment Isolation System
Line 133: Line 110:
The results of the verification will be included in the evaluation covering all portions of all Seismic Category I systems required by IE Bulle tin 79-02.
The results of the verification will be included in the evaluation covering all portions of all Seismic Category I systems required by IE Bulle tin 79-02.
A supplemental LER will be submitted when corrective actions required have been identified. Farley Nuclear Plant will not return to power range reactor operation until such time as Alabama Power Company and NRC Region II mutually agree that potential safety questions have been satisfactorily resolved.
A supplemental LER will be submitted when corrective actions required have been identified. Farley Nuclear Plant will not return to power range reactor operation until such time as Alabama Power Company and NRC Region II mutually agree that potential safety questions have been satisfactorily resolved.
.
Failure Data:
Failure Data:
None 2237 258
None 2237 258
                                                                     .}}
                                                                     .}}

Latest revision as of 18:28, 1 February 2020

LER 79-021/01T-2 on 790412:initial Results of Test Program Revealed Statistical Sampling Would Not Provide Probability of Greater than 95% Anchor Bolt Reliability.Bolt Testing Program Expanded to Include 100% Testing
ML19270G114
Person / Time
Site: Farley Southern Nuclear icon.png
Issue date: 05/29/1979
From: Hairston W
ALABAMA POWER CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19270G113 List:
References
LER-79-021-01T, LER-79-21-1T, NUDOCS 7906040283
Download: ML19270G114 (4)
v • d • e


Text

. /

NRO FORM 333 U. S. NUCLE AR REGULATORY COMMISSION 17 77) .

LICENSEE EVENT REPORT CONTROL BLOCK: [

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EVEr4T DESCRIPTION AND PROBABLE .ONSEQUENCES h o 2 l Tn response to TE Rii11 a ri n 79-O L Alabama Power Company initiated a orocram to I o a i randomly select and test a sample of anchor bolts installed in Seismic Category 1, o 4 l Safety Relatad 215 " and greater piping systems. Initial results of that program I o s l revealed that statistical sampling would not be suf ficient to provide a high I o o l probability of greater than 95% anchor bolt reliability. The po tential for anchor I o 7 l bolt failures and the resultant possibility of hanger failure were reported to the NR)C o,a [ on 4/12/ 79 under the potential applicability of Tech. Spec. 6.9.1.8(1) . The health l 7 a9 so and safeg the gic igot affected.

CODE COCE SUSCOCE COYPC"-ENT CODE SUBCODE SUSCCCE 7

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SEOUENT! AL CCCUR R E NCE REPORT REVISION

_ EVENT YEAR R EPORT NO. CCOE TYPE N O.

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44 47 CAUSE CESCRIPTION AND CORRECTIVE ACTIONS h

[: 3 l The anchor bolt testing orogram has been expanded to include 100% testine and/or I i i 1 analyses of anchors on pipe hangers for those systems,or portions of system remif ved I i 2 1 to meet design basis accidents or required to being the plant to cold shutdown. I 3 l (See Attachment) l i A l l 8 3 80 ST iJ3  % PC'".E

. R OTH ER STATUS IS OV RY DISCOVERY DESCRIPTION t 5 U @ lnInInl@l ' '2 n 9.s u

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ALABAMA POWER COMPANY JOSEPH M. FARLEY NUCLEAR PLANT DOCKET NO 50-348 ATTACIDIENT TO LER 79-021/0lT-2 Facility: Joseph M. Farley Unit 1 Report Date: 5/29/79 Eve nt Da te : 4/1 2/ 79 Iden tification of Event:

Potential for anchor bolt failures and the resultant possibility of hanger failure in certain systems.

Conditions Prior to Event:

The unit was in mode 6 (refueling) .

Description of Event:

In response to IE Bulletin 79-02, Alabama Power Company initiated a program to randomly select and test a sample of anchor bolts installed in Seismic Category 1, Safety Related, 2hinch and greater piping systems. Initial results of that program revealed that statistical sampling would not be sufficient to provide a high probability of greater than 95% anchor bolt reliability. The potential for anchor bolt failures and the resultant possibility of hanger failure were reported to the NRC on 4/12/ 79 under the potential applicability of Technical Specification 6.9.1.8(1) . Subject bolts were manufactured by Phillips Drill Co., Hilli Fastening Systems Incorporated and Wej-It Corporation.

Designation of Aoparent Cause:

Under investigation.

Analysis of Event:

Alabama Power Company initiated a program to randomly select and test a sample of anchor bolts installed in Seismic Category I, Safety Related, 2 inch and grea ter piping systems. Initial results of that program revealed that statistical sampling would not be sufficient to provide a high probability of greater than 95% anchor bolt reliability. Also, it has been found that the hanger designers havt at had available to them an official transmittal of the revised loads for 281 supports on lines analyzed by Westinghouse. Po ten tial design, documentation and installation deficiencies exist on pipe hangers. The health and safety of the public is not affected.

2237 256

/ _ .. ._.._____.

79-0 21/OlT-2 Corrective Action:

The anchor bolt testing program has been expanded to include 100%

verification of acceptable anchors on pipe hangers for those systems or portions of systems required to meet design basis accidents and those required to bring the plant to cold shutdown.

This piping includes:

a. Seismic Category 1; Safety-Related 2-1/2 inch and above.
b. Seismic Category 1; Safety-Related Class 1 under 2-1/2 inch.
c. Seismic Category 1; Safety-Related of other classes for which the designer performed detailed analysis.
d. All piping through containment penetrations.

The systems involved in the above verification include the following.:

1. Component Cooling Water System
2. Service Water System
3. Sampling System
4. Chemical Vclume and Control System
5. Residual Heat Removal System
6. Main S team System
7. Containment Cooling System
8. Reactor Coolant System
9. Emergency Core Cooling System
10. Main Feedwater System
11. Emergency Diesel Generator with Fuel Oil System
12. Gaseous Waste System
13. Post Accident Containment Hydrogen Control System
14. Auxiliary Feedwater System
15. Containment Spray System
16. Condensate Storage Tank 2237 257

/ - . . . ._ _.

79-021/0lT-2

. 17. Containment Isolation System

18. Main Steam Safety and Relief Valve Systems The overall scope of the above verification program includes approximately 12,000 anchor bolts.

Engineering design organizations are participating in determining test acceptance criteria which will ensure proper anchor safety margins. Designers will verify the adequacy of Seismic supports or the inadequacies requiring correc tive measures . This will include an evaluation concerni.ng the 281 supports on which revised loads were not evaluated. The necessary corrective action will be accomplished on each system to ensure operability.

The results of the verification will be included in the evaluation covering all portions of all Seismic Category I systems required by IE Bulle tin 79-02.

A supplemental LER will be submitted when corrective actions required have been identified. Farley Nuclear Plant will not return to power range reactor operation until such time as Alabama Power Company and NRC Region II mutually agree that potential safety questions have been satisfactorily resolved.

Failure Data:

None 2237 258

.

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