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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARRS-23-121, Sixth Ten-Year Interval Inservice Testing Program2023-11-30030 November 2023 Sixth Ten-Year Interval Inservice Testing Program SVPLTR 23-0004, Owner'S Activity Report Submittal Dresden Nuclear Power Station 6500 North Dresden Road Morris, Il 60450 Fifth 10-Year Interval 2022 Refueling Outage Activities2023-02-10010 February 2023 Owner'S Activity Report Submittal Dresden Nuclear Power Station 6500 North Dresden Road Morris, Il 60450 Fifth 10-Year Interval 2022 Refueling Outage Activities ML21043A2532021-02-0303 February 2021 Owner'S Activity Report Submittal Fifth 10-Year Interval 2020 Refueling Outage Activities SVPLTR 20-0010, Fifth 10-Year Interval 2019 Refueling Outage Activities2020-02-13013 February 2020 Fifth 10-Year Interval 2019 Refueling Outage Activities RS-16-130, Inservice Inspection Interval Relief Request 15R-082016-06-30030 June 2016 Inservice Inspection Interval Relief Request 15R-08 ML16189A2182016-06-29029 June 2016 BWR Vessel and Internals Project - Vessel Internals Inspection Summaries for Fall 2015 Outages RS-15-126, Additional Information Supporting Relief Request I4R-17, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fourth Inservice Inspection Interval2015-05-21021 May 2015 Additional Information Supporting Relief Request I4R-17, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fourth Inservice Inspection Interval ML13316B8342013-11-0808 November 2013 Fifth (5 Th) Ten-Year Interval Inservice Testing Program RS-13-164, Clarification Regarding the Testing Frequency for Fifth Inservice Testing Interval Relief Request RV-23H2013-06-13013 June 2013 Clarification Regarding the Testing Frequency for Fifth Inservice Testing Interval Relief Request RV-23H SVPLTR 13-0008, Owner'S Activity Report Submittal, Fourth 10-Year Interval 2012 Refueling Outage Activities2013-03-0404 March 2013 Owner'S Activity Report Submittal, Fourth 10-Year Interval 2012 Refueling Outage Activities RS-13-005, Supplemental to Dresden and Quad Cities Fifth Inservice Inspection Interval Relief Request I5R-032013-01-10010 January 2013 Supplemental to Dresden and Quad Cities Fifth Inservice Inspection Interval Relief Request I5R-03 RS-12-155, Submittal of Relief Requests Associated with the Fifth Lnservice Testing Interval2012-10-30030 October 2012 Submittal of Relief Requests Associated with the Fifth Lnservice Testing Interval SVPLTR 11-0010, Owner'S Activity Report Submittal Fourth 10-Year Interval 2010 Refueling Outage Activities2011-02-18018 February 2011 Owner'S Activity Report Submittal Fourth 10-Year Interval 2010 Refueling Outage Activities SVPLTR 10-0010, Submittal of Owner'S Activity and Fourth 10-Year Interval 2009 Refueling Outage Activities Report2010-02-25025 February 2010 Submittal of Owner'S Activity and Fourth 10-Year Interval 2009 Refueling Outage Activities Report SVPLTR 08-0007, Owner'S Activity Report Submittal - Fourth 10-Year Interval 2007 Refueling Outage Activities2008-02-12012 February 2008 Owner'S Activity Report Submittal - Fourth 10-Year Interval 2007 Refueling Outage Activities ML0726305512007-09-20020 September 2007 Notification of NRC Inspection and Request for Information RS-07-058, Amergen/Exelon Nuclear - Request for Relief - Use of the Boiling Water Reactor Vessel and Internals Project (BWRVIP) Guidelines in Lieu of Specific ASME Code Requirements2007-04-19019 April 2007 Amergen/Exelon Nuclear - Request for Relief - Use of the Boiling Water Reactor Vessel and Internals Project (BWRVIP) Guidelines in Lieu of Specific ASME Code Requirements SVPLTR 05-0007, Owner'S Activity Report Submittal Fourth 10-Year Interval 2004 Refueling Outage Activities2005-03-0707 March 2005 Owner'S Activity Report Submittal Fourth 10-Year Interval 2004 Refueling Outage Activities SVPLTR 05-0008, Final Third 10-Year Interval Inservice Inspection (ISI) Summary Report2005-03-0707 March 2005 Final Third 10-Year Interval Inservice Inspection (ISI) Summary Report SVPLTR 04-0002, Owner'S Activity Report Submittal for Fourth 10-Year Interval 2003 Refueling Outage Activities2004-02-0909 February 2004 Owner'S Activity Report Submittal for Fourth 10-Year Interval 2003 Refueling Outage Activities SVPLTR 04-0001, Final Third 10-Year Interval Inservice Inspection (ISI) Summary Report2004-02-0909 February 2004 Final Third 10-Year Interval Inservice Inspection (ISI) Summary Report RS-03-157, Additional Information Regarding Inservice Testing Program Relief Requests2003-08-0606 August 2003 Additional Information Regarding Inservice Testing Program Relief Requests ML0302900902003-01-24024 January 2003 Inservice Inspection (ISI) Summary Report Fall 2002 Inservice Inspection Period ML0226107092002-09-0606 September 2002 Fourth Interval Inservice Inspection Program Plan, Attachment C ML0226101532002-09-0606 September 2002 Fourth Interval Inservice Inspection Program Plan, Attachments a and B ML0204506082002-02-0505 February 2002 Inservice Inspection (ISI) Summary Report Fall 2001 Inservice Inspection Period 2023-02-10
[Table view] Category:Letter
MONTHYEARIR 05000237/20230042024-02-0202 February 2024 Integrated Inspection Report 05000237/2023004 and 05000249/2023004 IR 05000010/20230012024-01-17017 January 2024 NRC Inspection Report 05000010/2023001 (Drss) ML23354A2812024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0031 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 RS-23-121, Sixth Ten-Year Interval Inservice Testing Program2023-11-30030 November 2023 Sixth Ten-Year Interval Inservice Testing Program SVPLTR 23-0037, Core Operating Limits Report for Cycle 292023-11-29029 November 2023 Core Operating Limits Report for Cycle 29 RS-23-119, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums RS-23-107, Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2023-11-0808 November 2023 Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval RS-23-102, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-16016 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23285A2342023-10-13013 October 2023 Confirmation of Initial License Examination RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans ML23279A0712023-10-0606 October 2023 Response to NRC Dresden Nuclear Power Station, Units 2 and 3 - Comprehensive Engineering Team Inspection Report 05000237/2023011 and 05000249/2023011 ML23269A0662023-09-28028 September 2023 Proposed Alternative Request RV-23H Associated with the Sixth 10-Year Inservice Testing Interval ML23265A1322023-09-27027 September 2023 Proposed Alternative Request RV-03 Associated with the Sixth 10-Year Inservice Testing Interval ML23205A1362023-09-20020 September 2023 Proposed Alternative Request RV-02D Associated with the Sixth IST Interval IR 05000237/20230112023-09-0606 September 2023 Comprehensive Engineering Team Inspection Report 05000237/2023011 and 05000249/2023011 RS-23-071, Application to Adopt TSTF-564, Safety Limit MCPR2023-08-30030 August 2023 Application to Adopt TSTF-564, Safety Limit MCPR RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs IR 05000237/20234022023-08-29029 August 2023 Security Baseline Inspection Report 05000237/2023402 and 05000249/2023402 IR 05000237/20230022023-08-0808 August 2023 Integrated Inspection Report 05000237/2023002 and 05000249/2023002 ML23212A9892023-08-0303 August 2023 Subsequent License Renewal Application Public Meeting Summary of Pre-Submittal Meeting ML23174A1502023-08-0303 August 2023 Issuance of Amendment Nos. 282 and 275 Control Rod Scram Times ML23193A0052023-07-28028 July 2023 Subsequent License Renewal Application Public Meeting Summary of Pre-Submittal Meeting ML23192A6292023-07-11011 July 2023 Correction Letter - Issuance of Amendment Nos. 281 and 274 Regarding Transition to GNF3 Fuel (EPID L-2022-LLA-0121) (Non-Proprietary) ML23144A3142023-07-0606 July 2023 Issuance of Amendment Nos. 281 and 274 Transition to GNF3 Fuel (EPID L-2022-LLA-0121) - Nonproprietary ML23187A0462023-07-0606 July 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000237/2023004 ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III SVPLTR 23-0021, Registration of Use of Casks to Store Spent Fuel2023-06-20020 June 2023 Registration of Use of Casks to Store Spent Fuel RS-23-078, Supplement to License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times2023-06-16016 June 2023 Supplement to License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000237/20233012023-05-30030 May 2023 NRC Initial License Examination Report 05000237/2023301; 05000249/2023301 RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling ML23132A0932023-05-17017 May 2023 Information Meeting (Public Open House) with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Dresden Power Station, Units 2 and 3 RS-23-070, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel2023-05-16016 May 2023 Supplement to License Amendment Request Regarding Transition to GNF3 Fuel SVPLTR 23-0018, Submittal of 2022 Annual Radiological Environmental Operating Report2023-05-15015 May 2023 Submittal of 2022 Annual Radiological Environmental Operating Report IR 05000237/20230012023-05-0404 May 2023 Integrated Inspection Report 05000237/2023001 and 05000249/2023001 SVPLTR 23-0019, ILT 22-1 (2023-301) Svpltr 23-0019 Post-Exam Submittal Letter (1)2023-05-0101 May 2023 ILT 22-1 (2023-301) Svpltr 23-0019 Post-Exam Submittal Letter (1) ML23118A3472023-05-0101 May 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Correction of Amendment No. 193 Adoption of TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration EPID L-2022-LLA-0143 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI IR 05000237/20234012023-04-26026 April 2023 Cyber Security Inspection Report 05000237/2023401 and 05000249/2023401 ML23081A0382023-04-25025 April 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Issuance of Amendments to Adopt TSTF-306, Rev. 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration IR 05000237/20235012023-04-21021 April 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000237/2023501 and 05000249/2023501 ML23110A3202023-04-21021 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection RS-23-057, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel2023-04-17017 April 2023 Supplement to License Amendment Request Regarding Transition to GNF3 Fuel SVPLTR 23-0014, Annual Dose Report for 20222023-04-15015 April 2023 Annual Dose Report for 2022 ML23088A2242023-04-0505 April 2023 Regulatory Audit Report Regarding License Amendment Request to Transition to GNF3 Fuel ML23087A0482023-03-28028 March 2023 Operator Licensing Examination Approval - Dresden Nuclear Power Station, April 2023 2024-02-02
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Exelon Generation-~ Dresden Nuclear Power Station 6500 North Dresden Road Moms, IL 60450 February 3, 2021 SVPLTR #21-0003 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Unit 3 Facility Operating License No. DPR-25 NRC Docket No. 50-249
Subject:
Owner's Activity Report Submittal Fifth 10-Year Interval 2020 Refueling Outage Activities This letter submits the Owner's Activity Report (i.e., Form OAR-1) for the Dresden Nuclear Power Station (DNPS) Unit 3 refueling outage (D3R26) that began on October 26, 2020 and was completed on November 7, 2020. This is the first refueling outage conducted in the Third (3 rd ) Inspection Period of the Fifth (5 th ) 10-Year Interval lnservice Inspection (ISi) Program for DNPS Unit 3. A copy of the Owner's Activity Report is provided and attached to this letter.
This Owner's Activity Report is submitted in accordance with American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Case N-532-5, "Repair/Replacement Activity Documentation Requirements and lnservice Summary Report Preparation and Submission*. Code Case N-532-5 requires an Owner's Activity Report Form OAR-1 to be prepared and certified upon completion of each refueling outage. In accordance with the conditions of Code Case N-532-5, this OAR-1 form.is being submitted within ninety (90) days of the completion of the refueling outage. The 10 CFR 50.55a(b)(2)(ix)(A)(2) evaluation of inaccessible areas is included in Attachment 2.
Should you have any questions concerning this letter, please contact Mr. Ryan Sprengel, Regulatory Assurance Manager at (815) 416-2800.
Respectfully, Peter J. Karaba Site Vice President Dresden Nuclear Power Station Page 1 of8
Attachment 1 Owner's Activity Report, Form OAR-1 FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number Refueling Outage D3R26 OAR-1 Plant Dresden Nuclear Power Station, 6500 North Dresden Road Manis, IL 60450 Unrt No. 3 Commeraal Service Date _ _ _ _1_1.L../1_6'-L./_19'-'7_1'---___ Refueling Outage Number _ _ _ D3_R2_6_ _
(If applicable)
CUTTe11t Inspection Interval 5th Inspedmn Interval (ISI), 3rd Inspection Interval (Containment)
(1 11, 200, Jnl, 4111, other)
Current Inspection Pencxl 3rd InspectJOn Period (!SI), 1st Inspection Period (Containment) c1 *, 200, Jn1 )
2007 Edition and 2008 Addenda (ISI),
Edrtlon and Acklenda of Secbon XI appllcable to the Insped:Jon Plans 2013 Edition (Containment)
Date and RevJSlon of Inspecbon Plans 08/25/2020 (ER-DR-330-1001 Rev. 0)
Edlbon and Addenda of Secbon XI applicable to repair/replacement acbvlbes, lf different than the inspection plans NA Code cases used: N-62-7, N-508-4, N-526, N-532-5, N-552-1, N-578-1, N-600, N-613-2, N-702, N-747, N-765, N-778, N-805, N-825, N-845 (If ap pf lea bf e, mcl ud1 rig cases modJf!ed by case N-532 and later revisions)
CERTIFICATE OF CONFORMANCE I certify that (a) the statements made m this report are correct; (b) the exam1nabons and tests, meet the Inspecbon Plan as required by the ASME Code, SectJon XI; and (c) the repair/replacement acbvltles and evaluations supporting the completion of D3R26 conform to the requirements of Section XI (refuelmg outage number)
Signed Matenal Programs Engineer/ Date o I {a.,(? /a,o ~I OWner or OWner's deslgriee. Tltl CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission 1SS1.Jed by the Nabonal Board of Bojler and Pressure Vessel Inspectors and and employed by The Hartford Steam Boller Inspection and Insurance Company of Hartford, Connecbcut have Inspected the rtems desaibed In this OWner's ActMty Report, and state that, to the best of my knowledge and belief, the ONner has perfonned all activibes represented by this report m accordance wrth the requirements of Secbon XI.
By signing thlS cert:Ificate neither the Inspector nor his employer makes any warranty, expressed or Implied, concenmng the repair/
replacement acbVTtles and evaluabon descnbed in thlS report. Furthermore, neither the Inspector nor his employer shall be liable In any manner for any personal inJury or property damage or a loss of any kind arlsmg from or connected with this lnspecbon.
___:.Jir-:::::_..:::~*-~-=~::::===:::::...______ Commissions NB10972 R N I Inspector's Signature (Nabonal Board Number and Endorsements)
Date Page 3 of8
Attachment 1 Owner's Activity Report, Form OAR-1 TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDmONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination category and Item Description Evaluation Description Item Number None None None Page 4 of8
Attachment 1 Owner's Activity Report, Form OAR-1 TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Code Item Description Date Repair/
Class Description Of Work Completed Replacement Plan Number Welded new flanges to pipe and installed pipe.
3 Repair CREVS Pipe Flanges 9/25/2019 3-19-007 (IR 04176499)
Install new slip on pipe flanges involving welding U3 EDGCWP Inlet flange on check valve 3-3930-3 due to wear. Includes repair of pitted areas if 4/22/2020 3-20-054 501 found. (IR 04336861)
Page 5 of8
ATTACHMENT 2 CONTAINMENT ISi (IWE) RESULTS Page 6 of 8
As required by 10 CFR 50.55a(b)(2)(ix)(A), "Metal containment examinations: First provision,"
for Class MC applications, the applicant or licensee must evaluate the acceptability of inaccessible areas when conditions exist in accessible areas that could indicate the presence of or could result in degradation to such inaccessible areas. For each inaccessible area identified for evaluation, the applicant or licensee must provide the following in the ISI Summary Report required by 1WA-6000:
(i) Description of the type and estimated extent of degradation, and the conditions that led to the degradation:
During the Unit 3 refueling outage (D3R26) visual examinations of the drywell basement moisture barrier were performed due to an extent of condition from the Unit 2 outage in 2019.
The Unit 2 inspection found more than 50% of Unit 2 Drywell moisture barrier to be degraded (Ref. 1). Therefore, it was recommended by the Responsible Individual to inspect the Unit 3 drywell basement moisture barrier (Ref. 2). The Unit 3 inspection in D3R26 found three locations with recordable indications to be relevant indications (Ref. 3). The cause of this condition is not directly tied to one event, but rather due to the work activities performed in the drywell basement since the application of the moisture barrier which could have introduced damage to the moisture barrier surface (e.g. moving equipment, building scaffold, etc.).
Inaccessible areas of the liner plate were made accessible by removing these portions of the moisture barrier. A supplemental VT-1 exam of liner behind moisture barrier was completed and found no recordable indications (Ref. 4). Due to finding no recordable indications on the underlying liner plate at the locations with the degraded moisture barrier the liner plate is acceptable for continued service by examination in accordance with IWE-3122.1 (Ref. 1). A technical evaluation of the inaccessible locations of the containment liner is further discussed in Engineering Change Evaluation (EC Eval 633181 - Ref. 6).
(ii) An evaluation of each area, and the result of the evaluation:
Both Dresden Unit 2 & 3 share the same Boiling Water Reactor (BWR) Mark I containment design. There were no recordable indications on the underlying containment liner examined during D3R26, therefore the conclusions from the Unit 2 evaluation (EC 629967 Ref. 7) have been conservatively used to accept Unit 3's conditions and conclude no degradation is occurring in the inaccessible areas. Furthermore, UT thickness measurements are performed on Unit 3 drywell steel liner sand pocket area, as part of Generic Letter 87-05 and in accordance with License Renewal program B 1.26, core bore holes are ultrasonically examined every outage to trend liner degradation. The thickness corrosion rate has been conservatively estimated based on the given data to be no greater than 7.2 mil/year, and this is less than the conservatively worst-case corrosion rate of 10 mil/year for fresh river water (Ref. 8). Based on this conservatively assumed corrosion rate, it was concluded that the effects of corrosion on liner stresses would remain below the ASME Code allowable stress limits until January of 2030.
Additionally, the concrete is very basic (high pH), which protects the steel in contact with it from rusting. The area of drywell steel that would have the highest exposure, and therefore vulnerability to moisture and oxygen would be at the location of the moisture barrier. The inaccessible portion of the drywell below the floor's surface could also be exposed to moisture, but it would not have as much exposure to oxygen, if at all. This line of highest vulnerability is Page 7 of8
typically observed with submerged steel, having rust at the water line but not above or below it.
The VT-I examination of the U3 containment liner (Ref. 4) indicated no evidence of corrosion in the areas where the moisture barrier has separated. Since this is the most likely area for corrosion, it can be concluded that the area beneath the level of the floor is in as good of a condition as the exposed areas, or better.
(iii) A description of necessary corrective actions:
Removal and replacement of degraded locations of the drywell basement moisture barrier was performed during D3R26 (Ref. 9). The moisture barrier will be inspected (VT-1) during the next inspections period (D3R27) in accordance with IWE-2420 (b) (Ref. 5). Since, the VT-I of the underlying containment liner had no recordables, the underlying containment is acceptable without additional repair or replacement activities per IWE-3122.1 (Ref. 5).
REFERENCES
- 1. Issue Report No. 04294208 - D2R26 Drywell Basement Moisture Barrier Relevant Conditions
- 2. Issue Report No. 04296902 - D3R26 Contingency WO for DW Moisture Barrier Replacement
- 3. Issue Report No. 04379976-D3R2 6 Drywell Basement Moisture Barrier Relevant Conditions
- 4. NDE Report 20-435 - (K) NDE Perform VT-1 Of Containment Liner WO 04999923
- 5. American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (BPVC),Section XI, 2013 Edition
- 6. EC 633181 Rev. 000 - D3R26 Engineering Evaluation for Moisture Barrier And Drywell Liner
- 7. EC Evaluation 629967 - D2R26 Engineering Evaluation For Moisture Barrier And Drywell Liner Degradation
- 8. EC 373104 Rev. 003 - Evaluation ofU3 Drywell Steel Liner NDE Data
- 9. Work Order No. 04999923 - Request D3R26 Contingency WO for DW Moisture Barrier Replacement Page 8 of8