ML102910590: Difference between revisions
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{{#Wiki_filter:CrytNoRvemer Unth | {{#Wiki_filter:__O CrytNoRvemer 200 Unth November 5th 2009 Garry Miller JProgress Energy | ||
Tendon Pattern Tendon Pattern at time of cutting SGR Opening-Energized Tendon-- Removed Tendon Buttress (typical)4 Buttress #2 Buttress #3 Buttress #4 I I1 Drawing is | |||
IR Scans per PT 407T Complete Progress Energy Buttress #5 Buttress #6 Buttress #1-I -S --U -I -t --A B C A B C A B C D E F | Construction Opening (between Buttresses 3 and 4) 2 | ||
IR Scans per PT 407T Complete Root Cause Analysis -PH Metrics Un-refuted | |||
* Chemically or Environmentally Induced Aging E Inadequate Use of Concrete Materials* Inadequate Concrete Construction | A P,~S~d L~AE jo-Vir O 40F97TgTER -i6,~&o | ||
* Inadequate Concrete Design due to High Local | - "KOi *T- AVfOo- LuPJ~aR. | ||
R7,, TiEk 4 | |||
-Pr 70 46c-5jLIE - | |||
* 6cIS/COC4~E 5- L - 1eO -- | |||
t'M 7~- [.Mi#Y/,Sr CE =,,4A'IJ4 o . -h P W r-I C t4' 1-f ~~ ~ ~ ~ ~ReP-Auw ( /4tW-AUJ( | |||
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-. . . . . . | |||
Plan - | |||
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- - T - - | |||
T - - | |||
I | |||
- I | |||
- +/- | |||
I - -I I II View I I I tt l I | |||
0- L -J, I -I 0- - | |||
I ~VK 1 v.PAICTM¶ IOBA IMF L 0- - - - ~ | |||
-I -- ~ DTA-1*-II I IAP Do _n | |||
= t t J-l PWMA-161-114 | |||
; PT'DW | |||
-4 -- 4 CrOwrI it | |||
* I- -4 N | |||
Buttress # -I I | |||
4 - - - | |||
I i-i - -1 | |||
-2 6 I- - --I- I- - 1-1-7 (typical) | |||
Jj I I A- -4 | |||
--- r- - | |||
TI- | |||
- ~ | |||
51 I I 4-4-A-- | |||
I I TI I I 41 -- L I_ | |||
I | |||
____ | |||
I WWWRAW RO"C 4-A--A-Source Drawing: VI*4* ""AMn 101-112 SHOOO I I Construction Opening I I | |||
-* ROW=~ DCTLS SPWCMC0IM F RD.PROtEM#XWkO 3 - ,.. | |||
IW- 3-. | |||
--- 2 - r---I COWIMMATMo | |||
Tendon Pattern Tendon Pattern at time of cutting SGR Opening | |||
- Energized Tendon | |||
-- Removed Tendon Buttress (typical) 4 | |||
Buttress #2 Buttress #3 Buttress #4 I I1 e | |||
5 Drawing is NOT-TO-SCALE Core bore (locations are approximate) IR Scans per PT 407T Complete Progress Energy | |||
Buttress #5 Buttress #6 Buttress #1 ttress #2 | |||
- I - S - -U - I - t - - EL 250' A B C A B C A B C Pour 16 EL 240' D E F D E F D E F Pour 15 EL 230' G H G H G H I Pour 14 220' J L J K L J K L Pour 13 EL 210' M No 0 M N O M N 0 Pour 12 0 0 EL 200' P P Q R P Pour 11 Fuel Transfer Q R EL 190' Bldg Roof Q S T U S T U Pour 10 EL 200' 4" EL 180' R V W X V W X Pour 9 EL 170' Y Z AA Y Z AA Pour 8 EL 160' AB AC AD AB AC AD Pour 7 EL 150' Intermediate Intermediate Pour 6 Bldg Roof Bldg Roof EL 140' EL 149' 0" Pour 5 EL 149' 0" P-or- EL 130' Pour 4 EL 120' Pour 3 | |||
--- ---EL 110' | |||
--- | |||
Pour 2 EL 100' Pour 1 EL 90' | |||
* Core bore (locations are approximate) IR Scans per PT 407T Complete Progress Energy | |||
Root Cause Analysis - PH Metrics Un-refuted FailureModes as of Nov 3rd 2009 80 | |||
* External Events 70 Operational Events 60 Inadequate Containment Cutting 50 | |||
* Inadequate Concrete - tendon interactions 40 Shrinkage, Creep, and Settlement 30 | |||
* Chemically or Environmentally Induced Aging 20 E Inadequate Use of Concrete Materials 10 | |||
* Inadequate Concrete Construction | |||
* Inadequate Concrete Design due to 0 High Local Stress | |||
~ '! V 'b' V ~5 'o' ~V 'b ~ | |||
*.* Progress Energy 7 | |||
External Support Root Cause Analysis Performance Improvement International(PII) | |||
Bechtel Design Basis Analysis MPR Associates, Inc. | |||
Worley Parsons - 5os -- 4so, - s Condition Assessment Construction Technology Laboratories(CTL) (MeULS- Ef - | |||
MacTec Pg T Lo*s-* 7o , | |||
~~g ~Z~ | |||
ELS 6ijor 6.,#FE5rflJE ,Aj AmT Utility Involvement SCANA Exelon T | |||
* Southeem Company 8 | |||
Vlo2 Progress Energy | |||
Nuclear Safety Oversight Committee (NSOC) | |||
Sub-Committee Membership Bob Bazemore (PGN) VP - Audit Joe Donahue (PGN) VP - Nuclear Oversight Chris Burton (PGN) VP - Harris Nuclear Plant Greg Selby Technical Director - EPRI Dr. Shawn Hughes VP - Shaw Stone & Webster Dr. Paul Zia N. C. State University (retired) | |||
Hub Miller NRC (retired) | |||
Daryl Eisenhut NRC (retired) 7 rVl Progress Energy 9}} |
Revision as of 07:48, 13 November 2019
ML102910590 | |
Person / Time | |
---|---|
Site: | Crystal River |
Issue date: | 11/05/2009 |
From: | Geoffrey Miller Progress Energy Florida |
To: | Office of Information Services |
References | |
FOIA/PA-2010-0116 | |
Download: ML102910590 (10) | |
Text
__O CrytNoRvemer 200 Unth November 5th 2009 Garry Miller JProgress Energy
Construction Opening (between Buttresses 3 and 4) 2
A P,~S~d L~AE jo-Vir O 40F97TgTER -i6,~&o
- "KOi *T- AVfOo- LuPJ~aR.
R7,, TiEk 4
-Pr 70 46c-5jLIE -
- 6cIS/COC4~E 5- L - 1eO --
t'M 7~- [.Mi#Y/,Sr CE =,,4A'IJ4 o . -h P W r-I C t4' 1-f ~~ ~ ~ ~ ~ReP-Auw ( /4tW-AUJ(
+Tu~ -/tov 4L-L$e
! I I I I I
_ I_
.-- -- -- -- - -. - .
-. . . . . .
Plan -
II
- - T - -
T - -
I
- I
- +/-
I - -I I II View I I I tt l I
0- L -J, I -I 0- -
I ~VK 1 v.PAICTM¶ IOBA IMF L 0- - - - ~
-I -- ~ DTA-1*-II I IAP Do _n
= t t J-l PWMA-161-114
-4 -- 4 CrOwrI it
- I- -4 N
Buttress # -I I
4 - - -
I i-i - -1
-2 6 I- - --I- I- - 1-1-7 (typical)
Jj I I A- -4
--- r- -
TI-
- ~
51 I I 4-4-A--
I I TI I I 41 -- L I_
I
____
I WWWRAW RO"C 4-A--A-Source Drawing: VI*4* ""AMn 101-112 SHOOO I I Construction Opening I I
-* ROW=~ DCTLS SPWCMC0IM F RD.PROtEM#XWkO 3 - ,..
IW- 3-.
--- 2 - r---I COWIMMATMo
Tendon Pattern Tendon Pattern at time of cutting SGR Opening
- Energized Tendon
-- Removed Tendon Buttress (typical) 4
Buttress #2 Buttress #3 Buttress #4 I I1 e
5 Drawing is NOT-TO-SCALE Core bore (locations are approximate) IR Scans per PT 407T Complete Progress Energy
Buttress #5 Buttress #6 Buttress #1 ttress #2
- I - S - -U - I - t - - EL 250' A B C A B C A B C Pour 16 EL 240' D E F D E F D E F Pour 15 EL 230' G H G H G H I Pour 14 220' J L J K L J K L Pour 13 EL 210' M No 0 M N O M N 0 Pour 12 0 0 EL 200' P P Q R P Pour 11 Fuel Transfer Q R EL 190' Bldg Roof Q S T U S T U Pour 10 EL 200' 4" EL 180' R V W X V W X Pour 9 EL 170' Y Z AA Y Z AA Pour 8 EL 160' AB AC AD AB AC AD Pour 7 EL 150' Intermediate Intermediate Pour 6 Bldg Roof Bldg Roof EL 140' EL 149' 0" Pour 5 EL 149' 0" P-or- EL 130' Pour 4 EL 120' Pour 3
--- ---EL 110'
---
Pour 2 EL 100' Pour 1 EL 90'
Root Cause Analysis - PH Metrics Un-refuted FailureModes as of Nov 3rd 2009 80
- External Events 70 Operational Events 60 Inadequate Containment Cutting 50
- Inadequate Concrete - tendon interactions 40 Shrinkage, Creep, and Settlement 30
- Chemically or Environmentally Induced Aging 20 E Inadequate Use of Concrete Materials 10
- Inadequate Concrete Construction
- Inadequate Concrete Design due to 0 High Local Stress
~ '! V 'b' V ~5 'o' ~V 'b ~
- .* Progress Energy 7
External Support Root Cause Analysis Performance Improvement International(PII)
Bechtel Design Basis Analysis MPR Associates, Inc.
Worley Parsons - 5os -- 4so, - s Condition Assessment Construction Technology Laboratories(CTL) (MeULS- Ef -
MacTec Pg T Lo*s-* 7o ,
~~g ~Z~
ELS 6ijor 6.,#FE5rflJE ,Aj AmT Utility Involvement SCANA Exelon T
- Southeem Company 8
Vlo2 Progress Energy
Nuclear Safety Oversight Committee (NSOC)
Sub-Committee Membership Bob Bazemore (PGN) VP - Audit Joe Donahue (PGN) VP - Nuclear Oversight Chris Burton (PGN) VP - Harris Nuclear Plant Greg Selby Technical Director - EPRI Dr. Shawn Hughes VP - Shaw Stone & Webster Dr. Paul Zia N. C. State University (retired)
Hub Miller NRC (retired)
Daryl Eisenhut NRC (retired) 7 rVl Progress Energy 9