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=Text=
=Text=
{{#Wiki_filter:prone DATE OF DOCUMENT:
{{#Wiki_filter:prone                                                         DATE OF DOCUMENT:             TE RECENED
TE RECENED N O.: '8*Fr***1it** 841***
'                                                                                                                            N O.:
7 July 30. 1971 1 Aug. ', 1971 Reeding, Fa.
8*Fr***1it** 841***                           7                     July 30. 1971           1 Aug. ', 1971 Reeding, Fa.           19603                                   u R.               - Eu O.               OR T.                     O TH u John C. stiller                                                   y TO:                                                           O rag.;             CC.               OTHER:
19603 u R.- Eu O.OR T.O TH u John C. stiller y TO: O rag.;CC.OTHER: Dr. Peter A. Morris 1 ACTION NECE$$ARY CONCURRENCE DATE AN$wERED:
Dr. Peter A. Morris                                               1 ACTION NECE$$ARY           CONCURRENCE               DATE AN$wERED:
NO Action NECESSART O CO--ENT O.v: CLASSaF: POST OF FACE FILE CODE.;
CLASSaF:
U 50-289 R EO . N O.
NO Action NECESSART O       CO--ENT             O   .v:
DESCn;PTION: (Must Se Unclassef.ed)
POST OF FACE             FILE CODE.;
REFERRED TO DATE RECENED BY DATE Ler trans the followin5:
U                     R EO . N O.
Long 8-2-] 1 v/9 cvs for ACTION ST2DUTION:
50-289 DESCn;PTION: (Must Se Unclassef.ed)                                       REFERRED TO           DATE             RECENED BY             DATE Ler trans the followin5:                                           Long                           8-2-] 1 v/9 cvs for ACTION EhCLOSU R E3; ST2DUTION:
EhCLOSU R E3; Summary Report entitled Three Mile
Summary Report entitled Three Mile
* Fila Cy[ Island Nuclear Station Fuel Edadling
* Fila Cy
#N OGC-Rm-P-506-A Building Concrete k'all cal-4192.....
[ Island Nuclear Station Fuel Edadling                                   #N Building Concrete k'all cal-4192.....                                 OGC-Rm-P-506-A
;< - i f =n s (2)
  ;                                                                       < - i f =n s (2)
!R. Price & Staff i n. Th-narm f,(1cyanelrec'd)
  !                                                                       R. Price & Staff i                                                                         n. Th-narm f,(1cyanelrec'd)                                                         Merris/Schroeder omrhai r gg            {t1{I)   "
Merris/Schroeder g g{t1{I).omrhai r-f" E.D. E. Hall l" i 1 CY LOCAL PDR RAnnissURG, PA.
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"*Y " "'E''' ''!.E.G. Case I DTII(Laughlin)
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1971-424 4 62 0**D*D'T j$'**o , 1 AliiL,.1584 243.*O 3 911070 b
                                                                                                                                '  ''
__ _.- -__' '!/VL22r722
                                                                          "*Y " "'E
',,,1_,,, Regulatory Fila Cy.METROPOLITAN EDISON COMPANY- -_POST OFFICE BOX 542 READING, PENNSYLVANI A 19603 TELEPHONE 215 - 929-3601 oIe O N cocgq?/6 Y2- July 30,1971
                                                                                                                                      '
' " 5 AUG 2 1971 " -
i
.&DV3 9 R$ctyII CtLE
                                                                                                                              '
%?CD tD Dr. Peter A. Morris, Director Division of Reactor Licensing U. S. Atomic Energy Commission Washington , D. C.
1 CY LOCAL PDR RAnnissURG, PA.
20545.'
  !                                                                     .E.G. Case I                                                                       DTII(Laughlin)                                               -
6 tes;Tc tanchansni         .                                          DL u.s. ATome Entsor commssioN                 M All CONTROL FORM FOR= AEc4 ass a U.S. GO V E RNMEN T P RIN TING O F F4 C E. 1971-424 4 62
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1584 243
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* O 3 911070 b
 
_        _ _.- -                     _
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                                              !/VL22r722
                      '
                                                      ,,,1_,,,                       Regulatory             Fila Cy.
METROPOLITAN EDISON COMPANY                                                               - -
_
POST OFFICE BOX 542 READING, PENNSYLVANI A 19603                                         TELEPHONE 215 - 929-3601 oIe O                   N cocgq?             /
                                                          ' "
6                           Y2- July 30,1971 5     AUG 2 1971 " -                               .
9        R
                                                                &DV3
                                                        $ctyII CtLE
                                                    %                   ?
CD     tD Dr. Peter A. Morris, Director Division of Reactor Licensing U. S. Atomic Energy Commission Washington , D. C. 20545
.'


==SUBJECT:==
==SUBJECT:==
THREE MILE ISLAND NUC~
THREE MILE ISLAND NUC~                     STATION UNIT 1 DOCKET NO. 50-289
STATION UNIT 1 DOCKET NO. 50-289
                                                                                                            '
'


==Dear Dr. Morris:==
==Dear Dr. Morris:==
Line 50: Line 76:
Enclosed please find a summary of the report which evaluated the concrete placed in the TMI #1 fuel pool wall in January 1971. This subject has also been discussed with compliance personnel. The summary was requested by your Mr. Arndt during a DRL meeting held in Bethesda on June 29, 1971.
Enclosed please find a summary of the report which evaluated the concrete placed in the TMI #1 fuel pool wall in January 1971. This subject has also been discussed with compliance personnel. The summary was requested by your Mr. Arndt during a DRL meeting held in Bethesda on June 29, 1971.
We trus t tha t this su= mary will adequately answer your questions concerning this problem.
We trus t tha t this su= mary will adequately answer your questions concerning this problem.
Very truly yours ,..~., John G Miller Vice President
Very truly yours ,
~JGM:DHR:mw Enclosure/\f-o. -s g '<;px-a ,?g & \u>c , t ., m,@, A$-j a-33 N'M O 1584 244//r sij gg*['lYC?_
                                                                                    .
.f 'y -v, , d ,x**y ,-v/y'-ge.m.--, ,-,s,. -..,.THREE MILE ISLAND NUCIIAR STATION
                                                                        .         ~.                     ,
''-,'FUEL HANDLING BUILDING CONCRETE WALL .
John G Miller Vice President
-' '/.g GAI - 4192
                                                                                        ~
,_ _ __..%+On January 8,1971 concrete was placed in a 5 foot thick reinforced concrete wall in the Fuel Handling Building. The ambient temperature was between 14-18* F.Die constructor had scheduled this concrete placement to be done under normal cold weather concrete conditions.
JGM:DHR:mw Enclosure f                    /\
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                                                                                              '
THREE MILE ISLAND NUCIIAR STATION     -                      ,
                                                                                              '
                                                                    -
FUEL HANDLING BUILDING CONCRETE WALL .
GAI - 4192                      ' '/.
g
_ _ __..
                                                                        ,
                                                                          %+
On January 8,1971 concrete was placed in a 5 foot thick reinforced concrete wall in the Fuel Handling Building. The ambient temperature was between 14-18* F. Die constructor had scheduled this concrete placement to be done under normal cold weather concrete conditions.
Recoind w,Ltr Dat# 'I'SO'7 [
Recoind w,Ltr Dat# 'I'SO'7 [
" Inadequate heating prior to concrete placanent resulted in in-place concrete surface temperatures varying from 2S* F. to 34* F.
                                                                                "
The GAI specification in reference to ACI 306, " Recommended Practice for Cold Weather Concreting', Table 1.4.1 for moderately massive section requires fresh concrete as placed to be no t les s than 45* F . In addition all surfaces to be in contact with the new concrete should be raised to as close as practical to the temperature
Inadequate heating prior to concrete placanent resulted in in-place concrete surface temperatures varying from 2S* F. to 34* F. The GAI specification in reference to ACI 306, " Recommended Practice for Cold Weather Concreting',
, of the new concrete, i.e. 45* F.
Table 1.4.1 for moderately massive section requires fresh concrete as placed to be no t les s than 45* F . In addition all surfaces to be in contact with the new concrete should be raised to as close as practical to the temperature                         ,
The west wall of the fuel storage pool is an interior wall and designed for the combined effect of dead load, hydrostatic pressure, and earthquake. This wall will therefore not be exposed to aircraf t impact. Specified minimum compressive s tr'ength of the concrete is ff = 5,000 psi. The maximum com-pressive bending stress in the concrete at the location of the constniction joint is 270 psi. The maximum shear stress at the same location is less than 10 psi.Die concrete was placed with crane and bucket and deposited through 10" diameter chutes located 3 ' on centers. The temperature of the fresh concrete as mixed varied between 56-67* F.; m2namum required is 55* F.
of the new concrete, i.e. 45* F.
The lowest temperature of fresh concrete as placed was 46* F.; minimum required is 45* F.
The west wall of the fuel storage pool is an interior wall and designed for the combined effect of dead load, hydrostatic pressure, and earthquake. This wall will therefore not be exposed to aircraf t impact. Specified minimum compressive s tr'ength of the concrete is ff = 5,000 psi. The maximum com-pressive bending stress in the concrete at the location of the constniction joint is 270 psi. The maximum shear stress at the same location is less than 10 psi.
The wall was covered with a tarp tent with propane heaters inside, maintaining a tempera ture varying between 54-62* F. for the following 3 days; minimum required is 45* F.
Die concrete was placed with crane and bucket and deposited through 10" diameter chutes located 3 ' on centers. The temperature of the fresh concrete as mixed varied between 56-67* F.; m2namum required is 55* F. The lowest temperature of fresh concrete as placed was 46* F.; minimum required is 45* F.
The form was lef t in place for an extend'ed period. The concrete placenent and curing conformed to the specification.
The wall was covered with a tarp tent with propane heaters inside, maintaining a tempera ture varying between 54-62* F. for the following 3 days; minimum required is 45* F. The form was lef t in place for an extend'ed period. The concrete placenent and curing conformed to the specification.
On7e.wn.C-,.  
                                                                                        .      On7e
....-2-.The critical part of this wall is the construction joint between the old and the new concrete. In order to evaluate the structural effect of the in-place concrete due to the low temperature of the old concrete surface, core drilled specimens were taken at the construction joint, which would be the primary location for any detrimental effect. The core drill specimens, approximately 4" in diame ter, were tes ted in compression and by tensile splitting. In addition microscopic examinations were performed in order to determine any signs of free:ing.
                                              -
                                                                      ,                        wn.C
                                                                                                      .
 
                                                                        .
  .         .
.
                                              .
The critical part of this wall is the construction joint between the old and the new concrete. In order to evaluate the structural effect of the in-place concrete due to the low temperature of the old concrete surface, core drilled specimens were taken at the construction joint, which would be the primary location for any detrimental effect. The core drill specimens, approximately 4" in diame ter, were tes ted in compression and by tensile splitting. In addition microscopic examinations were performed in order to determine any signs of free:ing.
The induced compressive stress in the concrete is low. The wall is under-reinforced and therefore not dependent upon developing its ultimate capacity, ff=5,000 psi. The 5 foot wall thickness was required for biological shielding. Compressive s trength of the core drilled specimen was 4,050 psi.
The induced compressive stress in the concrete is low. The wall is under-reinforced and therefore not dependent upon developing its ultimate capacity, ff=5,000 psi. The 5 foot wall thickness was required for biological shielding. Compressive s trength of the core drilled specimen was 4,050 psi.
Core. drilled concrete tes ts made to check adequacy of strength in-place must be interpreted with judgement.
Core. drilled concrete tes ts made to check adequacy of strength in-place must be interpreted with judgement. Ihe test results cannot be translated in terms of standard concrete test cylinders with any degree of confidence, nor should they be expected necessarily to exceed the specified s trength. Section 4.3.5.1 of the proposed revision of ACI 318-63, ACI Journal, February,1970, states that, n - - no single core should be less than 75% of ff". That is 0.75 x 5000 =
Ihe test results cannot be translated in terms of standard concrete test cylinders with any degree of confidence, nor should they be expected necessarily to exceed the specified s trength. Section 4.3.5.1 of the proposed revision of ACI 318-63, ACI Journal, February,1970, states that, n - - no single core should be less than 75% of ff". That is 0.75 x 5000 =
3,750 psi. Examining the fractured compressive stress specimen (af ter testing) showed that about 50% of the cons truction joint plane was exposed and the remaining fracture were in both the old and new concrete. This would indicate that the low temperature has no t affected the compressive s trength at this lo cation.
3,750 psi. Examining the fractured compressive stress specimen (af ter testing) showed that about 50% of the cons truction joint plane was exposed and the remaining fracture were in both the old and new concrete. This would indicate that the low temperature has no t affected the compressive s trength at this lo cation.
The entire shear can be resisted entirely by the cons truction joint shear key, withou t depending upon bond transfer between old and new eencrete.
The entire shear can be resisted entirely by the cons truction joint shear key, withou t depending upon bond transfer between old and new eencrete.
1he ability of this concrete to resist tensile stress is not a design require-men t.However, any indication of freezing would reduce the tensile bond normal to the constmetion joint. The tensile splitting tes t of the core drilled specimen will therefore only be used as a measure of the effect of free:ing on this joint. The core drill specimen, with the cons truction joint 1584 246.
1he ability of this concrete to resist tensile stress is not a design require-men t. However, any indication of freezing would reduce the tensile bond normal to the constmetion joint. The tensile splitting tes t of the core drilled specimen will therefore only be used as a measure of the effect of free:ing on this joint. The core drill specimen, with the cons truction joint 1584 246
i*.-3-.going through the vertical axis, was tested to develop maximum tengile stress normal to the joint. Ihe effect of free ing could reduce or even eliminate the tensile ability through this joint. The tensile splitting strength of
                                                                                      .
.the core drill specimen was 395 psi. Examining the fracture of the tensile splitting tes t specimen showed that a double split occurred during the tes t simultaneously; one in the construction joint and aaother approximately 1/2 inch parallel to the cons truction joint in the adjacent concrete. This would' indicate that the low temperature has not affected the tensile bond at this location .
* i
.The microscopic examnation of core specimens indicated no fros t printi or
  .                                                           .
*other indications of free:ing which wenld adversely aff ect the concrete bond.
going through the vertical axis, was tested to develop maximum tengile stress normal to the joint. Ihe effect of free ing could reduce or even eliminate
Bending and shear stresses at the location of this cons truction joint are , , small. Thersfore, the construction joint as designed far exceeds jts func tional requirements . Based on the above discussion it is our opinion that the wall will fullfil all the requirements in terms of service, dura-bility and safety.
.
*.e O e e o%=*O e O 1584 247.}}
the tensile ability through this joint. The tensile splitting strength of the core drill specimen was 395 psi. Examining the fracture of the tensile splitting tes t specimen showed that a double split occurred during the tes t simultaneously; one in the construction joint and aaother approximately 1/2 inch parallel to the cons truction joint in the adjacent concrete. This would' indicate that the low temperature has not affected the tensile bond at this location .
                                                                          .
The microscopic examnation of core specimens indicated no fros t printi or
* other indications of free:ing which wenld adversely aff ect the concrete bond.
Bending and shear stresses at the location of this cons truction joint are       , ,
small. Thersfore, the construction joint as designed far exceeds jts func tional requirements . Based on the above discussion it is our opinion that the wall will fullfil all the requirements in terms of service, dura-
* bility and safety.
                                                    .
e                                             e   e o             O
                      %
          =
* O e
O 1584 247
                                        .}}

Revision as of 13:02, 19 October 2019

Forwards Summary of Rept Evaluating Concrete Placed in TMI-1 Fuel Pool Wall in Jan 1971 in Response to Arndt 710629 Request During Meeting in Bethesda,Md
ML19210B352
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 07/30/1974
From: John Miller
METROPOLITAN EDISON CO.
To: Morris P
US ATOMIC ENERGY COMMISSION (AEC)
References
710730, NUDOCS 7911070680
Download: ML19210B352 (5)


Text

prone DATE OF DOCUMENT: TE RECENED

' N O.:

8*Fr***1it** 841*** 7 July 30. 1971 1 Aug. ', 1971 Reeding, Fa. 19603 u R. - Eu O. OR T. O TH u John C. stiller y TO: O rag.; CC. OTHER:

Dr. Peter A. Morris 1 ACTION NECE$$ARY CONCURRENCE DATE AN$wERED:

CLASSaF:

NO Action NECESSART O CO--ENT O .v:

POST OF FACE FILE CODE.;

U R EO . N O.

50-289 DESCn;PTION: (Must Se Unclassef.ed) REFERRED TO DATE RECENED BY DATE Ler trans the followin5: Long 8-2-] 1 v/9 cvs for ACTION EhCLOSU R E3; ST2DUTION:

Summary Report entitled Three Mile

  • Fila Cy

[ Island Nuclear Station Fuel Edadling #N Building Concrete k'all cal-4192..... OGC-Rm-P-506-A

< - i f =n s (2)

! R. Price & Staff i n. Th-narm f,(1cyanelrec'd) Merris/Schroeder omrhai r gg {t1{I) "

.

-

f" E.D. E. Hall l

'

"*Y " "'E

'

i

'

1 CY LOCAL PDR RAnnissURG, PA.

! .E.G. Case I DTII(Laughlin) -

6 tes;Tc tanchansni . DL u.s. ATome Entsor commssioN M All CONTROL FORM FOR= AEc4 ass a U.S. GO V E RNMEN T P RIN TING O F F4 C E. 1971-424 4 62

  • 0**D D 'T j$

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CD tD Dr. Peter A. Morris, Director Division of Reactor Licensing U. S. Atomic Energy Commission Washington , D. C. 20545

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SUBJECT:

THREE MILE ISLAND NUC~ STATION UNIT 1 DOCKET NO. 50-289

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Dear Dr. Morris:

Enclosed please find a summary of the report which evaluated the concrete placed in the TMI #1 fuel pool wall in January 1971. This subject has also been discussed with compliance personnel. The summary was requested by your Mr. Arndt during a DRL meeting held in Bethesda on June 29, 1971.

We trus t tha t this su= mary will adequately answer your questions concerning this problem.

Very truly yours ,

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John G Miller Vice President

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On January 8,1971 concrete was placed in a 5 foot thick reinforced concrete wall in the Fuel Handling Building. The ambient temperature was between 14-18* F. Die constructor had scheduled this concrete placement to be done under normal cold weather concrete conditions.

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Inadequate heating prior to concrete placanent resulted in in-place concrete surface temperatures varying from 2S* F. to 34* F. The GAI specification in reference to ACI 306, " Recommended Practice for Cold Weather Concreting',

Table 1.4.1 for moderately massive section requires fresh concrete as placed to be no t les s than 45* F . In addition all surfaces to be in contact with the new concrete should be raised to as close as practical to the temperature ,

of the new concrete, i.e. 45* F.

The west wall of the fuel storage pool is an interior wall and designed for the combined effect of dead load, hydrostatic pressure, and earthquake. This wall will therefore not be exposed to aircraf t impact. Specified minimum compressive s tr'ength of the concrete is ff = 5,000 psi. The maximum com-pressive bending stress in the concrete at the location of the constniction joint is 270 psi. The maximum shear stress at the same location is less than 10 psi.

Die concrete was placed with crane and bucket and deposited through 10" diameter chutes located 3 ' on centers. The temperature of the fresh concrete as mixed varied between 56-67* F.; m2namum required is 55* F. The lowest temperature of fresh concrete as placed was 46* F.; minimum required is 45* F.

The wall was covered with a tarp tent with propane heaters inside, maintaining a tempera ture varying between 54-62* F. for the following 3 days; minimum required is 45* F. The form was lef t in place for an extend'ed period. The concrete placenent and curing conformed to the specification.

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The critical part of this wall is the construction joint between the old and the new concrete. In order to evaluate the structural effect of the in-place concrete due to the low temperature of the old concrete surface, core drilled specimens were taken at the construction joint, which would be the primary location for any detrimental effect. The core drill specimens, approximately 4" in diame ter, were tes ted in compression and by tensile splitting. In addition microscopic examinations were performed in order to determine any signs of free:ing.

The induced compressive stress in the concrete is low. The wall is under-reinforced and therefore not dependent upon developing its ultimate capacity, ff=5,000 psi. The 5 foot wall thickness was required for biological shielding. Compressive s trength of the core drilled specimen was 4,050 psi.

Core. drilled concrete tes ts made to check adequacy of strength in-place must be interpreted with judgement. Ihe test results cannot be translated in terms of standard concrete test cylinders with any degree of confidence, nor should they be expected necessarily to exceed the specified s trength. Section 4.3.5.1 of the proposed revision of ACI 318-63, ACI Journal, February,1970, states that, n - - no single core should be less than 75% of ff". That is 0.75 x 5000 =

3,750 psi. Examining the fractured compressive stress specimen (af ter testing) showed that about 50% of the cons truction joint plane was exposed and the remaining fracture were in both the old and new concrete. This would indicate that the low temperature has no t affected the compressive s trength at this lo cation.

The entire shear can be resisted entirely by the cons truction joint shear key, withou t depending upon bond transfer between old and new eencrete.

1he ability of this concrete to resist tensile stress is not a design require-men t. However, any indication of freezing would reduce the tensile bond normal to the constmetion joint. The tensile splitting tes t of the core drilled specimen will therefore only be used as a measure of the effect of free:ing on this joint. The core drill specimen, with the cons truction joint 1584 246

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going through the vertical axis, was tested to develop maximum tengile stress normal to the joint. Ihe effect of free ing could reduce or even eliminate

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the tensile ability through this joint. The tensile splitting strength of the core drill specimen was 395 psi. Examining the fracture of the tensile splitting tes t specimen showed that a double split occurred during the tes t simultaneously; one in the construction joint and aaother approximately 1/2 inch parallel to the cons truction joint in the adjacent concrete. This would' indicate that the low temperature has not affected the tensile bond at this location .

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The microscopic examnation of core specimens indicated no fros t printi or

  • other indications of free:ing which wenld adversely aff ect the concrete bond.

Bending and shear stresses at the location of this cons truction joint are , ,

small. Thersfore, the construction joint as designed far exceeds jts func tional requirements . Based on the above discussion it is our opinion that the wall will fullfil all the requirements in terms of service, dura-

  • bility and safety.

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