ML19330B796: Difference between revisions
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{{#Wiki_filter:,m mm, , , ,m , m ,m mu, - . sum , m u n | {{#Wiki_filter:,m mm, , , ,m , m ,m mu, - . sum , m u n | ||
- ....._._~.....,,m | - ....._._~.....,,m | ||
._ . PART21IDENTIFICATIONN0.. Sfo - m -oo o COM%W N#1L GA< b'-e IRTE OF LEITER. % 2. /# e DOCKETNO. 3 a- 36v | ._ . PART21IDENTIFICATIONN0.. Sfo - m -oo o COM%W N#1L GA< b'-e IRTE OF LEITER. % 2. /# e DOCKETNO. 3 a- 36v | ||
~ | ~ | ||
Line 26: | Line 24: | ||
DISTRIBUTION: | DISTRIBUTION: | ||
h REACTOR @g3 FUEL CYCLE & | h REACTOR @g3 FUEL CYCLE & | ||
SAFEGtMRDS(S) tRTERIALS @ ~ | SAFEGtMRDS(S) tRTERIALS @ ~ | ||
{l _ | {l _ | ||
Line 36: | Line 33: | ||
REGIONSI,II,'III,IV,V VENDOR BR. R-IV | REGIONSI,II,'III,IV,V VENDOR BR. R-IV | ||
] VENDOR BR. R-IV. VENDOR BR. R-IV g LDEB / FPA' FNB 5715 NMSS/FCFS SS-396 NRR/ DOL 3p AEOD FNB 7602 - LOEB/FPA FNB5715 NPSS / SG SS-881 2 | ] VENDOR BR. R-IV. VENDOR BR. R-IV g LDEB / FPA' FNB 5715 NMSS/FCFS SS-396 NRR/ DOL 3p AEOD FNB 7602 - LOEB/FPA FNB5715 NPSS / SG SS-881 2 | ||
NRR/ DOE AEUD FNB7602 LDEB/FPA MiB 5715 | NRR/ DOE AEUD FNB7602 LDEB/FPA MiB 5715 NRR/DSI CENTPAL FILES - 016 AE0D FNB 7602 NRR/ DST CENTPAL FILES ( GRON) | ||
(BiTRAL FILES 016 l NRR/ DOL PDR CBffRAL FILES (GR0f0 rFNTRAI FIlR mR LPDR CENTPAL FILES SS-396 CENTRAL FILES (GR000 TERA PDR PDR LPDR | |||
NRR/DSI CENTPAL FILES - 016 AE0D FNB 7602 NRR/ DST CENTPAL FILES ( GRON) | |||
(BiTRAL FILES 016 l NRR/ DOL PDR CBffRAL FILES (GR0f0 rFNTRAI FIlR mR LPDR CENTPAL FILES SS-396 CENTRAL FILES (GR000 TERA PDR | |||
PDR | |||
LPDR | |||
.: LPDR TERA TERA ACTION: | .: LPDR TERA TERA ACTION: | ||
PRELIMINARY EVALUATION OF THE ATTACHED REPORT INDICATES LEAD RESPONSIBILITY FOR i | PRELIMINARY EVALUATION OF THE ATTACHED REPORT INDICATES LEAD RESPONSIBILITY FOR i FOLLOWUP AS SHOWN BELOW: . | ||
FOLLOWUP AS SHOWN BELOW: . | |||
-; IE 1 NRR IfES _ | -; IE 1 NRR IfES _ | ||
OEER l | OEER l | ||
1 _ | 1 _ | ||
k s8008070007 pf} REV:7/9/80 W :.- . | k s8008070007 pf} REV:7/9/80 W :.- . | ||
g ,g.j. ,.,,,. , | g ,g.j. ,.,,,. , | ||
. 5-- | . 5-- | ||
-,M.g ;.w>t Post Office Box 2641 | -,M.g ;.w>t Post Office Box 2641 | ||
--y ... .c, g 4{.$, , 6/.'33ypg5*g2=. - f- ., . C; . ^3 - | --y ... .c, g 4{.$, , 6/.'33ypg5*g2=. - f- ., . C; . ^3 - | ||
/- Birmingham. Alabarna35291 , --/: w~~ vg , -- - | /- Birmingham. Alabarna35291 , --/: w~~ vg , -- - | ||
C.cf ,, Telephone 205 323-5341, ;;7p ~ .' - | C.cf ,, Telephone 205 323-5341, ;;7p ~ .' - | ||
';tg. , r _ 7,:. r'~ | ';tg. , r _ 7,:. r'~ | ||
~ | ~ | ||
5.1 . | 5.1 . | ||
C .- | C .- | ||
L' - | L' - | ||
F. L. CLAYTON, JR. | F. L. CLAYTON, JR. | ||
.. senior v.c. er..ie.ni . | .. senior v.c. er..ie.ni . | ||
Alabama Power I~~' | Alabama Power I~~' | ||
July 22, 1980 rnesov:*em elecresystem | July 22, 1980 rnesov:*em elecresystem c | ||
Joseph M. Farley Nuclear Plant - Unit 2 | |||
: m. Docket No. 50-364 , - | : m. Docket No. 50-364 , - | ||
g sQ Q ,, Odd { | g sQ Q ,, Odd { | ||
[ ., Electrical Penetration, Air' Leakage 1_ . . | [ ., Electrical Penetration, Air' Leakage 1_ . . | ||
'?.R . ~~'==.y=3 =. f.L.~-; .-W 3..-- | '?.R . ~~'==.y=3 =. f.L.~-; .-W 3..-- | ||
- i =: *..=: .: -- - -- .: --- -- . .- | - i =: *..=: .: -- - -- .: --- -- . .- | ||
5&D =.2 .: : 3. ? - - | 5&D =.2 .: : 3. ? - - | ||
^ | ^ | ||
p- _ f'?.- .:5=[ 3. _ | p- _ f'?.- .:5=[ 3. _ | ||
f.[ _ __ | f.[ _ __ | ||
'f T Er. ' James P. O'Reilly'; . | 'f T Er. ' James P. O'Reilly'; . | ||
f | f | ||
{1,* ' ' U. S. Nuclear Regulatory Conni4sion ' ~ ~ ~ ~ | {1,* ' ' U. S. Nuclear Regulatory Conni4sion ' ~ ~ ~ ~ | ||
~ | ~ | ||
--- Office of Inspection and Enforcement hj.2 ' ; Region IIf ~ E- 2-W ''. | --- Office of Inspection and Enforcement hj.2 ' ; Region IIf ~ E- 2-W ''. | ||
~ I .~ - | ~ I .~ - | ||
J. - - | J. - - | ||
. Suite 3100~ ~9 : | . Suite 3100~ ~9 : | ||
: 7. ~ . . ~ | : 7. ~ . . ~ | ||
c ... | c ... | ||
: 9. ' | : 9. ' | ||
101 Marietta Street,3. W. c .; ~ | 101 Marietta Street,3. W. c .; ~ | ||
~ | ~ | ||
h~t- | h~t- | ||
' Atlanta, GA 30303 A ' | ' Atlanta, GA 30303 A ' | ||
~~ | ~~ | ||
2~- " ~ | 2~- " ~ | ||
C L .- ; - | C L .- ; - | ||
Line 141: | Line 90: | ||
==DearMr.O'Reilly.:== | ==DearMr.O'Reilly.:== | ||
(.['" ~ - | (.['" ~ - | ||
*, . .,'- l" '- | *, . .,'- l" '- | ||
. ;*- : | . ;*- : | ||
~ | ~ | ||
' Alitbama Power Company submits the attached deficiency (10CFR50.55(e)) | ' Alitbama Power Company submits the attached deficiency (10CFR50.55(e)) | ||
evaluation report on the problem associated with the GE medium voltage | evaluation report on the problem associated with the GE medium voltage | ||
', penetrations on Joseph M. Farley Nuclear Plant Unit 2. The attached is' i -. also, intended to meet reporting' requirements of 10CFR, Part 21. | ', penetrations on Joseph M. Farley Nuclear Plant Unit 2. The attached is' i -. also, intended to meet reporting' requirements of 10CFR, Part 21. | ||
'- Alaba=a Power Company reported the problem as a possible sigIEificant | '- Alaba=a Power Company reported the problem as a possible sigIEificant | ||
~ deficiency and-a possible defect to Mr. M. D. Hunt, U. S. NRC on June 26, 1980. | ~ deficiency and-a possible defect to Mr. M. D. Hunt, U. S. NRC on June 26, 1980. | ||
If you have any questions, please advise. | If you have any questions, please advise. | ||
1 Very truly yours, | 1 Very truly yours, 9 . | ||
9 . | |||
b.Clayton, FLCJr/TNE:aw Attachments s-cc: Mr. R.- A. Thomas Mr. . F. Trowbridge | b.Clayton, FLCJr/TNE:aw Attachments s-cc: Mr. R.- A. Thomas Mr. . F. Trowbridge | ||
. W. H. Bradford | . W. H. Bradford | ||
.r. Victor Stello, Jr., I&E Mr. M. D. Hunt, Region II | .r. Victor Stello, Jr., I&E Mr. M. D. Hunt, Region II | ||
g.s a | |||
g.s | |||
a | |||
C . | C . | ||
DEFICIENCY EVALUATION FOR ELECTRICAL PENETRATION, AIR LEAYdGE JULY 22, 1980 | DEFICIENCY EVALUATION FOR ELECTRICAL PENETRATION, AIR LEAYdGE JULY 22, 1980 Initial Report to NRC On June 6, 1980, Mr. W. C. Petty, Nuclear | ||
Initial Report to NRC On June 6, 1980, Mr. W. C. Petty, Nuclear | |||
_ . Design and Construction QA Manager for v . ' Alabama Power Company, notified Mr. W. M. Hunt F . | _ . Design and Construction QA Manager for v . ' Alabama Power Company, notified Mr. W. M. Hunt F . | ||
J' "of the NRC. Region Il concerning a problem on M ' | J' "of the NRC. Region Il concerning a problem on M ' | ||
~u ,, a - . the medium voltage electrical penetrations | ~u ,, a - . the medium voltage electrical penetrations | ||
- - ~ ~' | - - ~ ~' | ||
. at Farley Nuclear Plant Unit 2. | . at Farley Nuclear Plant Unit 2. | ||
.r. | .r. | ||
7 , | 7 , | ||
On June 23, 1980,, Mr. W. C. Petty notified. | On June 23, 1980,, Mr. W. C. Petty notified. | ||
,'. . - . Mr. W. M. Hunt that this problem was a | ,'. . - . Mr. W. M. Hunt that this problem was a | ||
~." | ~." | ||
..L : , possible 10CFR50.55(e) and a possible.10CFR21.- | ..L : , possible 10CFR50.55(e) and a possible.10CFR21.- | ||
4: . | 4: . | ||
%.3 - - | %.3 - - | ||
f; .-)- | f; .-)- | ||
, .2 , | , .2 , | ||
' Description of Occurrence | ' Description of Occurrence | ||
; - | ; - | ||
. _ \ . ;. . . . | . _ \ . ;. . . . | ||
A problem was discovered at Farley Unit 2 by the startup section on June 2, 1980 during Structural Integrity Testing (SIT). Air inside the con-tainment was found. to be escaping through three (3) of the 4160 volt penetration- | A problem was discovered at Farley Unit 2 by the startup section on June 2, 1980 during Structural Integrity Testing (SIT). Air inside the con-tainment was found. to be escaping through three (3) of the 4160 volt penetration- | ||
. modules, furnished by GE, into the auxiliary building. The path for the air leakage is through the cable into the penetration module and back out of the cable on the other side of the penetration. This leakage was not detected by the Local Leak Rate Test. A local Leak Rate Test of these penetrations, both | . modules, furnished by GE, into the auxiliary building. The path for the air leakage is through the cable into the penetration module and back out of the cable on the other side of the penetration. This leakage was not detected by the Local Leak Rate Test. A local Leak Rate Test of these penetrations, both before and after SIT, did not indicate any excessive leakage. . Subsequent tests revealed a leakage problem in all six (6) of the medium voltage penetrations. | ||
Analysis of' Safety Implications The electrical penetrations terminate in the auxiliary building. No credit is allowed in Chapter 15 accident analysis for the penetration room filtration system. Using an assumed leakage rate of 10sefm to 20 scfm, a. calculation was performed to see if any criteria was violated. Based upon this calculation, it appeared that 10CFR100 limits for thyroid exposure could pos.sibly be exceeded. Therefore, it.can b'e concluded that, under 10CFR50.55(e), the deficiency, if uncorrected, could have r.dversely affected the safety of operations of the nuclear power plant. | |||
before and after SIT, did not indicate any excessive leakage. . Subsequent tests | |||
revealed a leakage problem in all six (6) of the medium voltage penetrations. | |||
Analysis of' Safety Implications The electrical penetrations terminate in the auxiliary building. No credit is allowed in Chapter 15 accident analysis for the penetration room filtration system. Using an assumed leakage rate of 10sefm to 20 scfm, a. calculation was performed to see if any criteria was violated. Based upon this calculation, | |||
it appeared that 10CFR100 limits for thyroid exposure could pos.sibly be exceeded. Therefore, it.can b'e concluded that, under 10CFR50.55(e), the deficiency, if uncorrected, could have r.dversely affected the safety of operations of the nuclear power plant. | |||
Since a prototype of the GE Series 100 medium voltage penetrations was successfully tested, the Appendix B criteria, Design Control, is satisfied. | Since a prototype of the GE Series 100 medium voltage penetrations was successfully tested, the Appendix B criteria, Design Control, is satisfied. | ||
This criteria states "where a test program is used to verify the a.dequacy of a specific design feature, in lieu of other verifying or checking processes, it shall include suitable qualification testing of a prototype | This criteria states "where a test program is used to verify the a.dequacy of a specific design feature, in lieu of other verifying or checking processes, it shall include suitable qualification testing of a prototype unit under the most adverse design condition". The Series 100 penetrations successfully passed prototype testing. It cannot be concluded that, under 10CFR.55(e), there has been a significant breakdown of the quality assurance program. | ||
unit under the most adverse design condition". The Series 100 penetrations successfully passed prototype testing. It cannot be concluded that, under 10CFR.55(e), there has been a significant breakdown of the quality assurance program. | |||
The Series 100 med'ium voltage penetrations are designed to be zero leakage penetrations. The defects found in the penetrations will be corrected as. | The Series 100 med'ium voltage penetrations are designed to be zero leakage penetrations. The defects found in the penetrations will be corrected as. | ||
l described below. A l | l described below. A l | ||
Line 230: | Line 135: | ||
q | q | ||
*-o . | *-o . | ||
!L c-,. | !L c-,. | ||
: ed E- Corrective Action The following corrective action is being taken to resolve problems encountered with the 4kv electric penetrations in Unit 2: | |||
: ed E- Corrective Action | |||
The following corrective action is being taken to resolve problems encountered with the 4kv electric penetrations in Unit 2: | |||
(1) All penetration assemblies will have all cables (3 per-y assembly) determinated at both ends, thus exposing the . | (1) All penetration assemblies will have all cables (3 per-y assembly) determinated at both ends, thus exposing the . | ||
> bare conductor strands both in containment and outside . :;n - | > bare conductor strands both in containment and outside . :;n - | ||
Line 247: | Line 143: | ||
k . | k . | ||
'. . . , .... . c::.:. + | '. . . , .... . c::.:. + | ||
(2) A cap will be installed over the end of each penetration 7' assembly in containment, and the cap will be pressurized-iE. internally. This will simultaneously apply pressure to: ....- | (2) A cap will be installed over the end of each penetration 7' assembly in containment, and the cap will be pressurized-iE. internally. This will simultaneously apply pressure to: ....- | ||
i- , | i- , | ||
Line 256: | Line 151: | ||
(* | (* | ||
F- | F- | ||
. _ _ - internal _ module test volume will be monitored.to | . _ _ - internal _ module test volume will be monitored.to determine if any modules are leaking through this path. . | ||
determine if any modules are leaking through this path. . | |||
if | if | ||
- .- -T::_s - -- | - .- -T::_s - -- | ||
-- :;:n i (3) All leaking cables determined-above-will be sealed.by - , . .- | -- :;:n i (3) All leaking cables determined-above-will be sealed.by - , . .- | ||
f . : submerging:the containment end in epoxy and pressurizing .- - - - | f . : submerging:the containment end in epoxy and pressurizing .- - - - | ||
Line 270: | Line 160: | ||
, This procedure was proposed by the vendor (GE) and - | , This procedure was proposed by the vendor (GE) and - | ||
= approved by Bechtel.: L. .. . ... | = approved by Bechtel.: L. .. . ... | ||
(4) Following a minim'um epoxy cure period of 24 hours, the . | (4) Following a minim'um epoxy cure period of 24 hours, the . | ||
cap sill be reinstalled and a leak test at 54 psig will be performed. Following this test, a local leak test at the test connection yill be performed. Leakage for the three assemblies that were blocked during the ILRT will be added to the Type A integrated leakage in the ILRT Test Report. Any leakage through the other three assemblies will be reported in the ILRT Test Report for a information'. , | cap sill be reinstalled and a leak test at 54 psig will be performed. Following this test, a local leak test at the test connection yill be performed. Leakage for the three assemblies that were blocked during the ILRT will be added to the Type A integrated leakage in the ILRT Test Report. Any leakage through the other three assemblies will be reported in the ILRT Test Report for a information'. , | ||
(5) Following successfully completing leakage tests, each conductor will be subjected to an insulation resistance test and will then be reterminated. | (5) Following successfully completing leakage tests, each conductor will be subjected to an insulation resistance test and will then be reterminated. | ||
Summary and Conclusions In conclusion, it is believed that the leakage problem associated with the GE Series 100 medium voltage penetrations represents a significant deficiency. | Summary and Conclusions In conclusion, it is believed that the leakage problem associated with the GE Series 100 medium voltage penetrations represents a significant deficiency. | ||
. 6 m 2 | . 6 m 2 | ||
.4 L - 9 _M W}} | .4 L - 9 _M W}} |
Revision as of 18:14, 31 January 2020
ML19330B796 | |
Person / Time | |
---|---|
Site: | Farley |
Issue date: | 07/22/1980 |
From: | Clayton F ALABAMA POWER CO. |
To: | |
References | |
REF-PT21-80-262-000 NUDOCS 8008070007 | |
Download: ML19330B796 (3) | |
Text
,m mm, , , ,m , m ,m mu, - . sum , m u n
- ....._._~.....,,m
._ . PART21IDENTIFICATIONN0.. Sfo - m -oo o COM%W N#1L GA< b'-e IRTE OF LEITER. % 2. /# e DOCKETNO. 3 a- 36v
~
IRTE DISTRIBLITED 7/w/so ORIGIfML REPORT g SUPPLEFENTARY Y
DISTRIBUTION:
h REACTOR @g3 FUEL CYCLE &
SAFEGtMRDS(S) tRTERIALS @ ~
{l _
IE FILES IE FILES AD/ROI(2) IE FILES
- f. '. AD/SG
~9 AD/RCI(2) AD/FFFSI AD/RDI REGIONSI,II,III,IV,V REGIONSI,II,III,IV,V
~
}; .
REGIONSI,II,'III,IV,V VENDOR BR. R-IV
] VENDOR BR. R-IV. VENDOR BR. R-IV g LDEB / FPA' FNB 5715 NMSS/FCFS SS-396 NRR/ DOL 3p AEOD FNB 7602 - LOEB/FPA FNB5715 NPSS / SG SS-881 2
NRR/ DOE AEUD FNB7602 LDEB/FPA MiB 5715 NRR/DSI CENTPAL FILES - 016 AE0D FNB 7602 NRR/ DST CENTPAL FILES ( GRON)
(BiTRAL FILES 016 l NRR/ DOL PDR CBffRAL FILES (GR0f0 rFNTRAI FIlR mR LPDR CENTPAL FILES SS-396 CENTRAL FILES (GR000 TERA PDR PDR LPDR
.: LPDR TERA TERA ACTION:
PRELIMINARY EVALUATION OF THE ATTACHED REPORT INDICATES LEAD RESPONSIBILITY FOR i FOLLOWUP AS SHOWN BELOW: .
OEER l
1 _
k s8008070007 pf} REV:7/9/80 W :.- .
g ,g.j. ,.,,,. ,
. 5--
-,M.g ;.w>t Post Office Box 2641
--y ... .c, g 4{.$, , 6/.'33ypg5*g2=. - f- ., . C; . ^3 -
/- Birmingham. Alabarna35291 , --/: w~~ vg , -- -
C.cf ,, Telephone 205 323-5341, ;;7p ~ .' -
';tg. , r _ 7,:. r'~
~
5.1 .
C .-
L' -
F. L. CLAYTON, JR.
.. senior v.c. er..ie.ni .
Alabama Power I~~'
July 22, 1980 rnesov:*em elecresystem c
Joseph M. Farley Nuclear Plant - Unit 2
- m. Docket No. 50-364 , -
g sQ Q ,, Odd {
[ ., Electrical Penetration, Air' Leakage 1_ . .
'?.R . ~~'==.y=3 =. f.L.~-; .-W 3..--
- i =: *..=: .: -- - -- .: --- -- . .-
5&D =.2 .: : 3. ? - -
^
p- _ f'?.- .:5=[ 3. _
f.[ _ __
'f T Er. ' James P. O'Reilly'; .
f
{1,* ' ' U. S. Nuclear Regulatory Conni4sion ' ~ ~ ~ ~
~
--- Office of Inspection and Enforcement hj.2 ' ; Region IIf ~ E- 2-W .
~ I .~ -
J. - -
. Suite 3100~ ~9 :
- 7. ~ . . ~
c ...
- 9. '
101 Marietta Street,3. W. c .; ~
~
h~t-
' Atlanta, GA 30303 A '
~~
2~- " ~
C L .- ; -
- k. : '5TQ. l* 'T*. : L*
24
DearMr.O'Reilly.:
(.['" ~ -
- , . .,'- l" '-
. ;*- :
~
' Alitbama Power Company submits the attached deficiency (10CFR50.55(e))
evaluation report on the problem associated with the GE medium voltage
', penetrations on Joseph M. Farley Nuclear Plant Unit 2. The attached is' i -. also, intended to meet reporting' requirements of 10CFR, Part 21.
'- Alaba=a Power Company reported the problem as a possible sigIEificant
~ deficiency and-a possible defect to Mr. M. D. Hunt, U. S. NRC on June 26, 1980.
If you have any questions, please advise.
1 Very truly yours, 9 .
b.Clayton, FLCJr/TNE:aw Attachments s-cc: Mr. R.- A. Thomas Mr. . F. Trowbridge
. W. H. Bradford
.r. Victor Stello, Jr., I&E Mr. M. D. Hunt, Region II
g.s a
C .
DEFICIENCY EVALUATION FOR ELECTRICAL PENETRATION, AIR LEAYdGE JULY 22, 1980 Initial Report to NRC On June 6, 1980, Mr. W. C. Petty, Nuclear
_ . Design and Construction QA Manager for v . ' Alabama Power Company, notified Mr. W. M. Hunt F .
J' "of the NRC. Region Il concerning a problem on M '
~u ,, a - . the medium voltage electrical penetrations
- - ~ ~'
. at Farley Nuclear Plant Unit 2.
.r.
7 ,
On June 23, 1980,, Mr. W. C. Petty notified.
,'. . - . Mr. W. M. Hunt that this problem was a
~."
..L : , possible 10CFR50.55(e) and a possible.10CFR21.-
4: .
%.3 - -
f; .-)-
, .2 ,
' Description of Occurrence
- -
. _ \ . ;. . . .
A problem was discovered at Farley Unit 2 by the startup section on June 2, 1980 during Structural Integrity Testing (SIT). Air inside the con-tainment was found. to be escaping through three (3) of the 4160 volt penetration-
. modules, furnished by GE, into the auxiliary building. The path for the air leakage is through the cable into the penetration module and back out of the cable on the other side of the penetration. This leakage was not detected by the Local Leak Rate Test. A local Leak Rate Test of these penetrations, both before and after SIT, did not indicate any excessive leakage. . Subsequent tests revealed a leakage problem in all six (6) of the medium voltage penetrations.
Analysis of' Safety Implications The electrical penetrations terminate in the auxiliary building. No credit is allowed in Chapter 15 accident analysis for the penetration room filtration system. Using an assumed leakage rate of 10sefm to 20 scfm, a. calculation was performed to see if any criteria was violated. Based upon this calculation, it appeared that 10CFR100 limits for thyroid exposure could pos.sibly be exceeded. Therefore, it.can b'e concluded that, under 10CFR50.55(e), the deficiency, if uncorrected, could have r.dversely affected the safety of operations of the nuclear power plant.
Since a prototype of the GE Series 100 medium voltage penetrations was successfully tested, the Appendix B criteria, Design Control, is satisfied.
This criteria states "where a test program is used to verify the a.dequacy of a specific design feature, in lieu of other verifying or checking processes, it shall include suitable qualification testing of a prototype unit under the most adverse design condition". The Series 100 penetrations successfully passed prototype testing. It cannot be concluded that, under 10CFR.55(e), there has been a significant breakdown of the quality assurance program.
The Series 100 med'ium voltage penetrations are designed to be zero leakage penetrations. The defects found in the penetrations will be corrected as.
l described below. A l
l C
q
- -o .
!L c-,.
- ed E- Corrective Action The following corrective action is being taken to resolve problems encountered with the 4kv electric penetrations in Unit 2:
(1) All penetration assemblies will have all cables (3 per-y assembly) determinated at both ends, thus exposing the .
> bare conductor strands both in containment and outside . :;n -
fr containment. . . . . ... . . . _ ; ..
k .
'. . . , .... . c::.:. +
(2) A cap will be installed over the end of each penetration 7' assembly in containment, and the cap will be pressurized-iE. internally. This will simultaneously apply pressure to: ....-
i- ,
the. bare conduct' ors of all 3 cables in the assembly. _-r 1. ..
g;' Pressure will be maintained, for several hours to: allow - . ... ., . . . _ _ ,
any leaks to develop, then each cable will be checked .
+ ~ for leakage at ,the outer end by submergence .Also the
(*
F-
. _ _ - internal _ module test volume will be monitored.to determine if any modules are leaking through this path. .
if
- .- -T::_s - --
-- :;:n i (3) All leaking cables determined-above-will be sealed.by - , . .-
f . : submerging:the containment end in epoxy and pressurizing .- - - -
to about 60 psig to force the sealant through the leak. -
path. The cable will then be depressurized and cleaned. __.
, This procedure was proposed by the vendor (GE) and -
= approved by Bechtel.: L. .. . ...
(4) Following a minim'um epoxy cure period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the .
cap sill be reinstalled and a leak test at 54 psig will be performed. Following this test, a local leak test at the test connection yill be performed. Leakage for the three assemblies that were blocked during the ILRT will be added to the Type A integrated leakage in the ILRT Test Report. Any leakage through the other three assemblies will be reported in the ILRT Test Report for a information'. ,
(5) Following successfully completing leakage tests, each conductor will be subjected to an insulation resistance test and will then be reterminated.
Summary and Conclusions In conclusion, it is believed that the leakage problem associated with the GE Series 100 medium voltage penetrations represents a significant deficiency.
. 6 m 2
.4 L - 9 _M W