|
---|
Category:Letter type:ULNRC
MONTHYEARULNRC-06853, Submittal of 2023 Fitness for Duty Performance Data Per Per 10 CFR 26.7172024-01-29029 January 2024 Submittal of 2023 Fitness for Duty Performance Data Per Per 10 CFR 26.717 ULNRC-06847, Supplement to Relief Request from Requirements of ASME BPV Code, Section XI, Subsection Iwl Regarding Examination and Testing of the Unbonded Post-Tensioning System (Relief Request C3R-01)2023-12-21021 December 2023 Supplement to Relief Request from Requirements of ASME BPV Code, Section XI, Subsection Iwl Regarding Examination and Testing of the Unbonded Post-Tensioning System (Relief Request C3R-01) ULNRC-06849, License Renewal Resolution for Commitments 34 and 35 Perform Evaluation of Crack Initiation and Propagation in Steam Generator Divider Plate and Tube-To-Tubesheet Welds2023-12-20020 December 2023 License Renewal Resolution for Commitments 34 and 35 Perform Evaluation of Crack Initiation and Propagation in Steam Generator Divider Plate and Tube-To-Tubesheet Welds ULNRC-06844, Request for Exemption from Specific Requirements in 2023 Security Rule, Enhanced Weapons, Firearms Background Checks, and Security Event Notification2023-12-0707 December 2023 Request for Exemption from Specific Requirements in 2023 Security Rule, Enhanced Weapons, Firearms Background Checks, and Security Event Notification ULNRC-06827, Supplement to License Amendment Request Regarding Support System Requirements for Residual Heat Removal and Control Room Air Conditioning Systems Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029)2023-11-20020 November 2023 Supplement to License Amendment Request Regarding Support System Requirements for Residual Heat Removal and Control Room Air Conditioning Systems Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029) ULNRC-06824, Response to Request for Additional Information Regarding Operating Quality Assurance Manual (Oqam) Revision 36A2023-08-17017 August 2023 Response to Request for Additional Information Regarding Operating Quality Assurance Manual (Oqam) Revision 36A ULNRC-06830, Transmittal of Updated Technical Specification Markup and Clean Pages for License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak2023-08-15015 August 2023 Transmittal of Updated Technical Specification Markup and Clean Pages for License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak ULNRC-06223, Minor Correction to License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies (LDCN 2020-0004)2023-07-25025 July 2023 Minor Correction to License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies (LDCN 2020-0004) ULNRC-06799, Submittal of Licensee Event Report 2022-003-01, Class 1E Electrical Air Conditioning System Thermal Expansion Valve Failure Resulted in Condition Prohibited by Technical Specifications2023-07-13013 July 2023 Submittal of Licensee Event Report 2022-003-01, Class 1E Electrical Air Conditioning System Thermal Expansion Valve Failure Resulted in Condition Prohibited by Technical Specifications ULNRC-06821, Post-Audit Follow-Up Information in Support of Callaway'S License Amendment Request and Proposed Exemption to Allow Use of Framatome Gaia Fuel (LDCN 22-0002) (EPID L-2022-LLA-0150 and EPID L-2022-LLE-00301)2023-06-21021 June 2023 Post-Audit Follow-Up Information in Support of Callaway'S License Amendment Request and Proposed Exemption to Allow Use of Framatome Gaia Fuel (LDCN 22-0002) (EPID L-2022-LLA-0150 and EPID L-2022-LLE-00301) ULNRC-06822, Additional Information Regarding Request for NRC Approval of Operating Quality Assurance Manual (Oqam) Revision 36a2023-06-14014 June 2023 Additional Information Regarding Request for NRC Approval of Operating Quality Assurance Manual (Oqam) Revision 36a ULNRC-06815, Request for NRC Approval of Operating Quality Assurance Manual, Revision 36a2023-06-0505 June 2023 Request for NRC Approval of Operating Quality Assurance Manual, Revision 36a ULNRC-06818, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate .2023-06-0505 June 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate . ULNRC-06816, Withdrawal of Previously Submitted Enclosures Regarding License Amendment Request for Adoption of Alternative Source Term and Revision of Technical Specifications (LDCN 21-0015)2023-05-0909 May 2023 Withdrawal of Previously Submitted Enclosures Regarding License Amendment Request for Adoption of Alternative Source Term and Revision of Technical Specifications (LDCN 21-0015) ULNRC-06812, Submittal of 2022 Annual Radiological Environmental Operating Report2023-04-27027 April 2023 Submittal of 2022 Annual Radiological Environmental Operating Report ULNRC-06806, Submittal of Radiological Emergency Response Plan, Revision 552023-04-12012 April 2023 Submittal of Radiological Emergency Response Plan, Revision 55 ULNRC-06807, Submittal of Single Positive Test Forms2023-04-0303 April 2023 Submittal of Single Positive Test Forms ULNRC-06798, Submittal of Status of Plant Decommissioning Funding and ISFSI Decommissioning Funding Plan2023-03-30030 March 2023 Submittal of Status of Plant Decommissioning Funding and ISFSI Decommissioning Funding Plan ULNRC-06801, CFR 50.46 Annual Report Regarding ECCS Evaluation Model Revisions2023-03-30030 March 2023 CFR 50.46 Annual Report Regarding ECCS Evaluation Model Revisions ULNRC-06804, Submittal of Nuclear Property Insurance Reporting2023-03-29029 March 2023 Submittal of Nuclear Property Insurance Reporting ULNRC-06751, Application to Revise Technical Specifications to Adopt TSTF-501-A, Rev. 1, Relocate Stored Oil & Lube Oil Volume Values to Licensee Control2023-03-29029 March 2023 Application to Revise Technical Specifications to Adopt TSTF-501-A, Rev. 1, Relocate Stored Oil & Lube Oil Volume Values to Licensee Control ULNRC-06803, Submittal of Response to Request for Additional Information Regarding Results of Steam Generator Tube In-Service Inspection2023-03-29029 March 2023 Submittal of Response to Request for Additional Information Regarding Results of Steam Generator Tube In-Service Inspection ULNRC-06805, Transmittal of Special Report 2023-02 Non-Functionality of Containment Hydrogen Analyzer Channel for Greater than 30 Days2023-03-21021 March 2023 Transmittal of Special Report 2023-02 Non-Functionality of Containment Hydrogen Analyzer Channel for Greater than 30 Days ULNRC-06802, Special Report 2023-01 (PAM Report); Non-Functionality of a Post-Accident Monitoring Instrument2023-03-0909 March 2023 Special Report 2023-01 (PAM Report); Non-Functionality of a Post-Accident Monitoring Instrument ULNRC-06795, Submittal of Fitness for Duty Reports for 2022, Including Single Positive Test Forms2023-01-24024 January 2023 Submittal of Fitness for Duty Reports for 2022, Including Single Positive Test Forms ULNRC-06794, Submittal of Fitness for Duty Program Data for 20222023-01-24024 January 2023 Submittal of Fitness for Duty Program Data for 2022 ULNRC-06787, Response to Request for Additional Information Regarding License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications (LDCN 21-0015)2022-12-0808 December 2022 Response to Request for Additional Information Regarding License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications (LDCN 21-0015) ULNRC-06781, License Amendment Request to Clarify Support System Requirements for the Residual Heat Removal System and Control Room Air Conditioning System Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029)2022-12-0101 December 2022 License Amendment Request to Clarify Support System Requirements for the Residual Heat Removal System and Control Room Air Conditioning System Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029) ULNRC-06780, Additional Supplement to License Amendment Request to Adopt TSTF-439 and TSTF-505, LDCN 20-0072022-11-30030 November 2022 Additional Supplement to License Amendment Request to Adopt TSTF-439 and TSTF-505, LDCN 20-007 ULNRC-06772, 10 CFR 50.59 and 10 CFR 72.48 Summary Report2022-11-23023 November 2022 10 CFR 50.59 and 10 CFR 72.48 Summary Report ULNRC-06777, Operating Quality Assurance Manual (Oqam) Revision 362022-11-16016 November 2022 Operating Quality Assurance Manual (Oqam) Revision 36 ULNRC-06779, ULNRC-06779: Contesting of Green NCV 05000483/2022010-03, Failure to Perform Required Inservice Testing of Residual Heat Removal Heat Exchanger Pneumatically (Air) Operated Outlet and Bypass Valves2022-11-14014 November 2022 ULNRC-06779: Contesting of Green NCV 05000483/2022010-03, Failure to Perform Required Inservice Testing of Residual Heat Removal Heat Exchanger Pneumatically (Air) Operated Outlet and Bypass Valves ULNRC-06765, License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Testing Frequencies (LDCN 2020-0004)2022-11-0303 November 2022 License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Testing Frequencies (LDCN 2020-0004) ULNRC-06773, Results of Steam Generator Tube In-Service Inspection2022-11-0101 November 2022 Results of Steam Generator Tube In-Service Inspection ULNRC-06775, Submittal of Non-Functionality of Loose-Part Detection System Channel for Greater than 30 Days2022-10-27027 October 2022 Submittal of Non-Functionality of Loose-Part Detection System Channel for Greater than 30 Days ULNRC-06771, Correction to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections (LDCN 21-0013)2022-10-25025 October 2022 Correction to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections (LDCN 21-0013) ULNRC-06770, Cycle 25 Commitment Change Summary Report2022-10-19019 October 2022 Cycle 25 Commitment Change Summary Report ULNRC-06766, Correction of Text Contained in Enclosures Provided with Supplements to Request for License Amendment and Regulatory Exemptions for a Risk-Informed Approach to Address GSI-191 and Respond to GL 2004-02 (LDCN 19-0014)2022-09-0808 September 2022 Correction of Text Contained in Enclosures Provided with Supplements to Request for License Amendment and Regulatory Exemptions for a Risk-Informed Approach to Address GSI-191 and Respond to GL 2004-02 (LDCN 19-0014) ULNRC-06767, Presentation Information for Pre-Application Meeting Regarding New License Amendment Request for Use of Framatome Fuel Assemblies2022-09-0606 September 2022 Presentation Information for Pre-Application Meeting Regarding New License Amendment Request for Use of Framatome Fuel Assemblies ULNRC-06764, Revised Response to Request for Additional Information Regarding License Amendment Request for Adoption Off Alternate Source Term and Revision of Technical Specifications (LDCN 21-0015)2022-09-0101 September 2022 Revised Response to Request for Additional Information Regarding License Amendment Request for Adoption Off Alternate Source Term and Revision of Technical Specifications (LDCN 21-0015) ULNRC-06763, Supplement to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspection (LDCN 21-0013)2022-09-0101 September 2022 Supplement to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspection (LDCN 21-0013) ULNRC-06762, Submittal of Owner'S Activity Reports (OAR-1 Forms) for Cycle/Refuel 252022-08-25025 August 2022 Submittal of Owner'S Activity Reports (OAR-1 Forms) for Cycle/Refuel 25 ULNRC-06758, Union Electric Co. - Renewed Facility Operating License NPF-30, Withdrawal of License Amendment Request and Exemption Request Regarding Transition to Framatome Fuel (LDCN 22-0002)2022-08-0404 August 2022 Union Electric Co. - Renewed Facility Operating License NPF-30, Withdrawal of License Amendment Request and Exemption Request Regarding Transition to Framatome Fuel (LDCN 22-0002) ULNRC-06755, Response to Requests for Additional Information for Proposed Revision to Radiological Emergency Response Plan Regarding Response and Notification Goals2022-07-13013 July 2022 Response to Requests for Additional Information for Proposed Revision to Radiological Emergency Response Plan Regarding Response and Notification Goals ULNRC-06754, Response to Request for Additional Information Regarding Licensee Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications2022-07-0505 July 2022 Response to Request for Additional Information Regarding Licensee Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications ULNRC-06739, Post-Audit Supplement to License Amendment Request to Adopt TSTF-439 and TSTF-505 (LDCN 20-0007)2022-06-30030 June 2022 Post-Audit Supplement to License Amendment Request to Adopt TSTF-439 and TSTF-505 (LDCN 20-0007) ULNRC-06752, Evacuation Time Estimates Report2022-06-27027 June 2022 Evacuation Time Estimates Report ULNRC-06753, Presentation Information for Pre-Submittal Meeting Regarding Updated Spent Fuel Criticality Safety Analysis2022-06-23023 June 2022 Presentation Information for Pre-Submittal Meeting Regarding Updated Spent Fuel Criticality Safety Analysis ULNRC-06750, Submittal of Cycle 26 Core Operating Limits Report (COLR)2022-06-13013 June 2022 Submittal of Cycle 26 Core Operating Limits Report (COLR) ULNRC-06735, Response to Request for Additional Information Regarding Request for License Amendment and Regulatory Exemptions for Risk-Informed Approach to Address GSI-191 and Respond to Generic Letter 2004-02 (LDCN 19-0014).2022-05-27027 May 2022 Response to Request for Additional Information Regarding Request for License Amendment and Regulatory Exemptions for Risk-Informed Approach to Address GSI-191 and Respond to Generic Letter 2004-02 (LDCN 19-0014). 2024-01-29
[Table view] |
Text
~~
~Ameren Callaway Plant MISSOURI October 31, 20 11 ULNRC-05822 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 10 CFR 50.55a Ladies and Gentlemen:
DOCKET NUMBER 50-483 CALLAWAY PLANT UNIT 1 UNION ELECTRIC CO.
FACILITY OPERATING LICENSE NPF-30 10 CFR 50.55a REQUEST: PROPOSED ALTERNATIVE TO ASME SECTION XI REQUIREMENTS REGARDING PERFORMANCE OF SECOND SUCCESSIVE EXAMINATION FOR INDICATION ON "C" COLD LEG SAFE-END TO ELBOW WELD Reference 1: AmerenUE letter ULNRC-051 00, "Transmittal of In service Inspection Summary Report for Refuel 13, and WCAP-16280-P, "Flaw Evaluation Handbook for Callaway Unit 1 Reactor Vessel Inlet Nozzle Safe-end Weld Region," May 2004 Pursuant to 10 CFR 50.55a(a)(3)(i), Union Electric Company (Ameren Missouri) hereby requests NRC approval of attached ReliefRequest BR-13 regarding paragraph IWB-2420(b) of the American Society ofMechanical Engineers (ASME) Boiler and Pressure Vessel Code, i.e.,Section XI. The Code Edition applicable to this request and to the current (third) 10-year Inservice Inspection interval for Callaway Plant is the 1998 Edition (up to and including the 2000 Addenda).
During Refuel 13 (Spring 2004), non-destructive (ultrasonic) examination of the reactor pressure vessel (RPV) nozzle safe-end welds at Callaway confirmed a small flaw in the safe-end to elbow weld ofthe RPV 'C' inlet (cold leg) nozzle. An evaluation to determine the acceptability ofthe flaw was promptly performed by Westinghouse Electric Company, LLC (Westinghouse) using the procedures and acceptance criteria for indications in austenitic piping pursuant to Paragraph IWB-3640 of ASME Section XI. That evaluation determined the flaw to be acceptable such that further service without repair was justified. This evaluation, including the methodology that was used, was provided as part of the RF-13 lSI Summary Report submitted to the NRC (per Reference 1).
PO Box 620 Fulton, MD 65251 AmerenMissouri.com
ULNRC-05822 October 3I, 20II Page2 Pursuant to IWB-2420(b), the area containing the identified flaw was scheduled to be examined during each of the three subsequent, successive inspection periods. The first successive examination was completed in 2007 during Refuel I5, and it confirmed no growth in flaw size. The attached I 0 CFR
- 50. 55(a) request (Attachment I) concerns performance of the second successive examination which was scheduled to be performed during the current, ongoing refueling outage (RF-I8). In lieu of performing the second successive examination during the current refueling outage, however, Ameren Missouri is requesting NRC approval of an alternative wherein the second successive examination will be performed during the next refueling outage (RF-I9).
Justification for the request is provided in Attachment I. Also attached, as Attachment 2, are the examination results obtained for the stainless steel "C" cold leg safe-end to elbow weld during Refuel I3 and Refueli5.
No new regulatory commitments have been made or identified in this letter or its attachment. Please contact me at 573-676-87I9 or Tom Elwood at 3I4-225-I905 for any questions you may have regarding this request.
Sincerely,
~.A. VV\f/
S.A.M~
Regulatory Affairs Manager BLM/TBE/nls Attachments I) 10 CFR 50.55(a) Request BR-13
- 2) Examination Results for RF-13 and RF-I5
ULNRC-05822 October 31, 2011 Page3 cc: Mr. Elmo E. Collins, Jr.
Regional Administrator U.S. Nuclear Regulatory Commission Region IV 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-4125 Senior Resident Inspector Callaway Resident Office U.S. Nuclear Regulatory Commission 820 I NRC Road Steedman, MO 65077 Mr. Mohan C. Thadani (2 copies)
Senior Project Manager, Callaway Plant Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop 0-8G 14 Washington, DC 20555-2738
ULNRC-05822 October 31, 2011 Page4 Index and send hardcopy to QA File A160.0761 Hardcopy:
Certrec Corporation 4200 South Hulen, Suite 422 Fort Worth, TX 76109 (Certrec receives ALL attaclunents as long as they are non-safeguards and may be publicly disclosed.)
Electronic distribution for the following can be made via Other Situations ULNRC Distribution:
A. C. Heflin F. M. Diya C. 0. Reasoner ill L. H. Graessle S. A. Maglio L. H. Kanuckel NSRB Secretary T. B. Elwood M.G. Hoehn Ms. Diane M. Hooper (WCNOC)
Mr. Tim Hope (Luminant Power)
Mr. Ron Barnes (APS)
Mr. Tom Baldwin (PG&E)
Mr. Wayne Harrison (STPNOC)
Ms. Linda Conklin (SCE)
Mr. John O'Neill (Pillsbury Winthrop Shaw Pittman LLP)
Missouri Public Service Commission to ULNRC-05822 Page 1 Attachment 1 10 CFR 50.55a Request IJR-13 Proposed Alternative In Accordance with 10 CFR 50.55a(a)(3)(i)
Alternative Provides Acceptable Level of Quality and Safety
- 1. ASME Code Components Affected ASME Code Class: Code Class 1
References:
Code Case N-578 Examination Category: R-A (was B-J)
Item Number: Rl.20 (was B5.10)
Description:
Loop C Cold Leg Stainless Steel Safe-End to Pipe Weld System: Reactor Coolant System Component(s): 2-BB-01-F302
2. Applicable Code Edition and Addenda
ASME Section XI, 1998 Edition with 2000 Addenda.
- 3. Applicable Code Reguirement IWB-2420(b) states, in part, "If a component is accepted for continued service in accordance with IWB-3132.3 or IWB-3142.4, the areas containing flaws or relevant conditions shall be reexamined during the next three inspection periods listed in the schedule ofthe inspection program ofiWB-2400."
- 4. Reason for Reguest This 10 CFR 50.55a request concerns an indication (flaw) in the stainless steel safe-end to pipe weld of the Loop C cold leg nozzle. The flaw in 2-BB-01-F302 was identified in conjunction with a reactor pressure vessel 10-year examination during Refuel 13 (2004). As reported in the lSI Summary Report for Refuel 13 (Reference 3), the indication that was identified exceeded IWB-3514 requirements. The flaw was evaluated in accordance with IWB-3600 by both Structural Integrity Associates and Westinghouse and determined to be acceptable. It is important to note that this indication is in the stainless steel safe-end to pipe weld (i.e., not in an Alloy 600 weld).
A root cause analysis was performed for the identified flaw, and as stated in the root cause analysis report, "The preponderance of evidence supports that this crack indication is from original plant construction." [This was documented in Callaway to ULNRC-05822 Page2 Action Request (CAR) 200403580 (Reference 2) under Callaway's Corrective Action Program]. The root cause analysis concluded that this indication was first identified in 2004 due to improved technology (performance demonstration initiative) which was not available during construction and earlier examinations.
Subsequent to Refuel13, 2-BB-01-F302 was re-examined in the next period (as required by IWB-2242(b)), in Refuel15, and the indication was determined to be unchanged in size, as expected.
- 5. Proposed Alternative and Basis for Use The second successive examination of2-BB-01-F302 was scheduled to be performed during Refuel 18 which is now ongoing at Callaway. Due to challenges experienced during the outage, but based on the stable nature and negligible impact of the noted flaw, Ameren Missouri proposes to not perform the required second successive examination during Refuel 18, but to instead perform the required examination during Refuel 19 (Spring 2013).
Basis for Use: The indication has been evaluated by Structural Integrities and Westinghouse and found to not pose a threat to the structural integrity of the reactor coolant system, nor is the flaw likely to grow to a size of concern within the lifetime of the plant. Additionally, the indication has been examined following one lSI period of operation and found to be unchanged in size. Based on these determinations, Callaway requests to defer the second successive examination from Refuel 18 (Interval 3, Period 2) to Refuel 19 (Interval 3, Period 3). (The third successive examination required by IWB-2242(b) would be rescheduled to Interval4, Period 1, thereby completing the three required successive examinations prior to returning to the inspection frequency required by Examination Category R-A, Item Number R1.20.) For the noted reasons, this alternative will still ensure an acceptable level of quality and safety.
- 6. Duration of Proposed Alternative This relief is requested for the duration of the operating cycle following Refuel 18.
Weld 2-BB-01-F302 will be examined in Refuel19 (Spring 2013).
- 7. References
- 1. ASME Section XI, 1998 Edition with 2000 Addenda
- 2. Callaway Corrective Action Report (CAR) 200403580
- 3. AmerenUE letter ULNRC-051 00, "Transmittal of Inservice Inspection Summary Report for Refuel13, and WCAP-16280-P, "Flaw Evaluation Handbook for Callaway Unit 1 Reactor Vessel Inlet Nozzle Safe-end Weld Region," May 2004.
to ULNRC-05822 Attachment 2 Examination Results for RF-13 and RF-15 (5 pages)
~~"-~~~~nE Page of INDICATION DATA SHEET# W247-2 Utility: I Ameren UE I Plant: I Callaway I Unit: 1 Outage: I RF15 Procedure No: I PDI-ISI-254-SE I Procedure Rev. No.: I 2 _I PARAGON Anal. Release: _I 6.3.0 Applicable Analysis Log Sheet No: Applicable Acquisition Log Sheet No: Applicable Sensitivity Calibration Data Sheet No:
W247-1 SE W247-1 SE-AXSIZE-01 Weld No: _I 2-BB-01-F302 Axial Scan Increment (deg): 0.515 I Axial Scan Increment (ln.): I 0.125 I Clrc. Scan Increment (ln.): I N/A UT Examiner Signature: I ~.,/tv/~ Level: jl: IDate: 4-13-07
, Center of Indication i
...0 r I![ i c~
~~ ~
11
- i.
"' I f.5 !-
g c
0
~
z 0 .!!
~
c(
Q(,) E4.'
CD-E ..
"' a. (I)
I J~Jr ~J :t_ ~~
'0
'II:
a.~
r~
a.-
cn:S I j
i_
~I s:.
c:n -i I
I FileName Disk
- =ao ~
.Sz u E
! !l E~ :d!
-ca
~it 11
.... ~
I Ji
=~
l~
N::.
c .
.3&.
- J e!'~
~ ._,;.
E ftl c:n
- J WN247SE-PRP-51Z26 HD 1 3 60 OUT p 8 45 38 0.4° 19.7" 130.7° 10" 0.39 4.75 0.32 0.15" **
WN247SE-PRP-51Z264A HD 2 1 45 OUT p 59 79 21 298.2" 309.2" 130.42" 304.1" 0.38 2.625 0.0
.87" *
- 0.12" RMSE Correction added to thru wall depth.
- Only one tip resolved therefore conservative 6 dB drop method used for through wall sizing.
Form 12.7 PDI-ISI-254-SE, Rev. 2
~ P.R~~P.YnE Page 1 of 1 INDICATION ASSESSMENT SHEET# W247-IND-1 utility: I Ameren UE I Plant: Callaway 1Unit: I 1 I Outage: R15 I PDI-181-254-SE I Procedure No:
UT Examiner Signature: /~I
\
r Level: Ill Procedure Rev. No.:
Date: 4/13/07 2
t /
"--""' Jr -. g.... . . *. ....
.5
= .. g ~z rn
.ft-. i'
._ 5" C::>
0 c:! ~
.5 e* 0 E
-!.g o
.=.. .o o ~ ._. "'":" c .... i5 1: rn o Ti =11:
c c aa ~o c;. i- .5 45 1
.a o J!
- FileName s:8 l' ~~ SA:~ tj ~ JJ ! ~ ~ ! o"S ~
- - 8~ ~ca ~~
~~
!i ~
,ac a.
a:tC!e ~:t ~ .e c
i ~
i* ~~ lu
~
.5=~~: m Gl ~
oJ! a.
>D. .: lie ii:._.
1&.
'C
- I rn tfl
~
- ,s* ....Jil ~.....
Jil~
o:E
=0,. u WN247SE-PRP.SIZ26 2-BB-01-F302 W~~~-2 60 OUT P 2.32 .32/.47 4.75 Sub .32 1 .15/.08 0.016 3.23 9.9 Y WN247SE-PRP.SIZ264A 2-BB-01-F302 Wr~-2 45 OUT P 2.32 0/.87 2.625 Surf. 0 0 .87 .33 37.5 11.0 N Notes:
Y= Allowable per ASME XI, 1998 Edition-2000 Addenda: IWB 3514-2 N= Non-allowable per ASME XI, 1998 Editlon-2000 Addenda: IWB 3514-2 Form 12.3 PDI-ISI-254-SE, Rev. 2
I ( --------------------------------------~
! I
~~.~!~YnE J~~ UA}/-1 Page \ of l INDICATION DATA SHEET# 247-SE-05 Utility: IAmerenUE l Plant: J Callaway I Unit: I 1 J Outage: I RF-13 Procedure No: I PDI-ISI-254-SE J Procedure Rev. No.: 1 5 JPARAGON Anal. Release: I 6.1.0 Applicable Analysis Log Sheet No: 247-SE-03 Applicable Acquisition Log 247-SE-01 Applicable Sheet No: Sensitivity UPSEAXSIZE01 THRU 04 Calibration Data Sheet No:
Weld No: I 2-BB-01-F302 Axial Scan Increment (deg): 0.515 l Axial Scan Increment (ln.): .125 I Clrc. Scan Increment (ln.): I N/A UT Examiner Signature: ~../'~ .J-... I Level: 11 I Date: 4-30-04 I
Center of Indication i e::= . I* i a
i Otl ill 0
~ z
'fi
... J ii -g
-i
~~ ~~
t:l.
J..c:
Ql ~~
c:: "5I "l _j
-~
j I r .... :r 0
II:
0 c :::. II:
Ic:: m
... ~J JJ ... _ si a:I Ji di ~~
Ill 8;;c; :::~! :II I ~~
FileName Disk E
.! -m e~~
- .5z 0 ~i!L 11
.c: c Cll WN247SEPRPSIZA s- 1 3 60 OUT p 181 218 38 355.57" 14.86" 130.5 9.64° 0.37 4.75 0.15" .. 0.30 p
WN247SEPRPSIZA 5" 2 1 45 OUT 56 76 21 296.92" 307.35" 130.15 302.13" 0.41 2.625 0.94". 0.0
- 0.12" RMSE Correction added to thru wall depth .
- Only one tip resolved therefore conservative 6dB drop method used for through wall sizing Form 12.7 PDI-ISI-254-SE, Rev. 1
(I
. . - - - -/ --------------------------------~
~ \V~,~~ynE d6d-1 UATA Page \ of f.
INDICATION ASSESSMENT SHEET# 247-SE-06 Utility: JAmerenUE I Plant: Callaway I Unit: I 1 I Outage: RF13 Procedure No: I PDI-151-254-SE Procedure Rev. No.: I 1 UT Examiner Signature: ~s~ ILevel: Ill Date: 4-30-Q4
,..c s.s
.. i .i ~
'II:
~~
0 l c:f
~~
0
~
~
~ ~
i I
.g ic 0
i!
j Q
- e. ~~
~
t
'.i 'iE i~
..¥
.. ~
FileName .!!
Q
'II:
15;:.
r~~=
c o( -~
i~ j li ~
0 0 E ~
.~- ~~
'i'
~
Q1 E J iS ii 11 ~~ J J~ 1-:-
'a Q
~E= ~~
'C I -0 u..! u::e 0
- I tn i- ;cs ~~;
WN247SEPRPSIZA 288 247-SE-05 60 OUT p 2.32 .30 I .45 4.75 Sub 0.30 1 .15/.08 .16 3.23 9.8 y s F302 (#1)
WN247SEPRPSIZA 288 247-SE-05 45 OUT p 2.32 0/.94 2.625 Surf 0 0 .94 .342 40.5 11.1 N
~ F302 (#2)
Notes:
Y =Allowable per ASME X1,1989 Edition; IWB 3514-2 N =Non-allowable per ASME XI, 1989 Edition; IWB 3514-2
~
Form 12.3 PDI-ISI-254-SE, Rev. 1
dt?'Jlj ;)/J m It of lndiCQ tlon
@ 302.13*
~-
2.32' :1 Thickness of IJelol ..........
2.82' = ""
2.625' 296.92° Note* 0.12' Must foe Qoldeol to the Qfoove MeQsured flQW depths cl1.1e to sizing IIMitQi:lons "' "'
of the UT procedure.
\o/eld 2- BB-Ol-F302 Indication #2
"' '\