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| | number = ML14237A008 | | | number = ML14237A008 |
| | issue date = 08/27/2014 | | | issue date = 08/27/2014 |
| | title = Review of the Steam Generator Tube Inservice Inspection Report for the Fall 2013 Refueling Outage (TAC MF3355) | | | title = Review of the Steam Generator Tube Inservice Inspection Report for the Fall 2013 Refueling Outage |
| | author name = Pascarelli R J | | | author name = Pascarelli R J |
| | author affiliation = NRC/NRR/DORL/LPLII-1 | | | author affiliation = NRC/NRR/DORL/LPLII-1 |
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Category:Letter
MONTHYEARIR 05000413/20240032024-11-0404 November 2024 Integrated Inspection Report 05000413/2024003 and 05000414/2024003 ML24297A6222024-10-11011 October 2024 PCA Letter to NRC Catawba Hurricane Helene IR 05000413/20240112024-10-0101 October 2024 Biennial Problem Identification and Resolution Inspection Report 05000413/2024011 and 05000414/2024011 ML24255A8312024-09-23023 September 2024 Project Manager Assignment ML24261B9782024-09-19019 September 2024 Notification of an NRC Fire Protection Team Inspection NRC Inspection Report 05000413-2024010, 05000414-2024010 and Request for Information IR 05000414/20240912024-09-0505 September 2024 Final Significance Determination of a White Finding and Nov and Assessment Followup Letter-NRC Inspection Report 05000414-2024091 IR 05000413/20240052024-08-26026 August 2024 Updated Inspection Plan for Catawba Nuclear Station (Report 05000413/2024005 & 05000414/2024005) ML24235A1542024-08-22022 August 2024 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000413-2024402 and 05000414-2024402) IR 05000413/20240022024-08-0808 August 2024 Integrated Inspection Report 05000413-2024002 and 05000414-2024002 and Apparent Violation IR 05000413/20244032024-08-0101 August 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000413/2024403; 05000414/2024403 ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 ML24178A0552024-06-26026 June 2024 Requalification Program Inspection – Catawba Nuclear Station IR 05000414/20240902024-06-24024 June 2024 NRC Inspection Report 05000414/2024090 and Preliminary White Finding and Apparent Violation ML24170A8632024-06-11011 June 2024 Flowserve June 11, 2024, Part 21 Notification - Redacted Version for Publishing ML24149A1772024-05-28028 May 2024 NRC Response to Duke Energy 2025 FOF Schedule Change Request (Catawba and McGuire) ML24144A1162024-05-28028 May 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc IR 05000413/20240012024-05-10010 May 2024 Integrated Inspection Report 05000413/2024001 and 05000414/2024001 and Apparent Violation ML24095A1072024-04-0808 April 2024 – Review of the Spring 2023 Steam Generator Tube Inspection Report (C1R27) IR 05000413/20243012024-03-12012 March 2024 – Notification of Licensed Operator Initial Examination 05000413/2024301 and 05000414/2024301 ML24017A0652024-03-0808 March 2024 Issuance of Amendment Nos. 319 and 315 to Technical Specification 3.7.11, Control Room Area Chill Water System (Cracws) 05000414/LER-2024-001, Condition Prohibited by Technical Specifications and Loss of Safety Function Due to Failed Damper Controller for the 2A1 Emergency Diesel Generator Room Ventilation Fan2024-03-0404 March 2024 Condition Prohibited by Technical Specifications and Loss of Safety Function Due to Failed Damper Controller for the 2A1 Emergency Diesel Generator Room Ventilation Fan IR 05000413/20230062024-02-28028 February 2024 Annual Assessment Letter for Catawba Nuclear Station Units 1 and 2 - (NRC Inspection Report 05000413/2023006 and 05000414/2023006) IR 05000413/20230042024-02-0202 February 2024 – Integrated Inspection Report 05000413-2023004 and 05000414-2023004 ML24005A2512024-01-26026 January 2024 Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000413/20230102023-10-11011 October 2023 NRC Inspection Report 05000413/2023010 and 05000414/2023010 ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000413/20230052023-08-25025 August 2023 Updated Inspection Plan for Catawba Nuclear Station Units 1 and 2 (Report 05000413/2023005 and 05000414/2023005) ML23233A1692023-08-17017 August 2023 EN 56683 - Curtiss Wright, Interim Notification Report for PotentialPurt2l IR 05000413/20230022023-07-25025 July 2023 Integrated Inspection Report 05000413/2023002 and 05000414/2023002 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 ML23237A2672023-06-13013 June 2023 June 13, 2002 - Meeting Announcement - McGuire and Catawba Nuclear Stations 50-369, 50-370 and 50-413, 50-414 ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined IR 05000413/20230012023-05-0505 May 2023 Integrated Inspection Report 05000413/2023001 and 05000414/2023001 ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI IR 05000413/20230112023-04-25025 April 2023 Focused Engineering Inspection Report 05000413/2023011 and 05000414/2023011 ML23107A2542023-04-14014 April 2023 301 Examination Report Letter and Report (Merged) ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000413/20234012023-03-0101 March 2023 Security Baseline Inspection Report 05000413 2023401 and 05000414 2023401 IR 05000413/20220062023-03-0101 March 2023 Annual Assessment Letter for Catawba Nuclear Station, Units 1 and 2 (NRC Inspection Report 05000413/2022006 and 05000414/2022006) IR 05000413/20233012023-02-17017 February 2023 Operator Licensing Examination Approval 05000413/2023301 and 05000414/2023301 IR 05000413/20220042023-01-31031 January 2023 Integrated Inspection Report 05000413/2022004 and 05000414/2022004 IR 05000413/20220112022-12-15015 December 2022 Biennial Problem Identification and Resolution Inspection Report 05000413/2022011 and 05000414/2022011 ML22356A0512022-12-14014 December 2022 Curtiss-Wright Nuclear Division, Letter Regarding Potential Efect in a Configuration of the 11/2 Inch Quick Disconnect Connector Cable Assemblies Supplied to Duke Energy (See Attached Spreadsheet) for a Total of 460 of Connectors Only Suppl ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations IR 05000413/20224032022-11-17017 November 2022 Cyber Security Inspection Report 05000413/2022403 and 05000414/2022403 (Public) ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 ML22319A0942022-11-10010 November 2022 EN 56219 - Flowserve. 10 CFR Part 21 Report 38878-8 Solenoid Valve at Duke, Catawba Flowserve Evaluation 105 2024-09-05
[Table view] Category:Safety Evaluation
MONTHYEARML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 ML24017A0652024-03-0808 March 2024 Issuance of Amendment Nos. 319 and 315 to Technical Specification 3.7.11, Control Room Area Chill Water System (Cracws) ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 ML22242A0022022-09-12012 September 2022 Issuance of Amendments to Adopt TSTF 569, Revision 2, Revise Response Time Testing Definition ML22213A2532022-08-31031 August 2022 Authorization and Safety Evaluation for Alternative Request RA-21-0144 to Use Reactor Vessel Head Penetration Embedded Flaw Repair Method ML22164A0362022-07-19019 July 2022 Mcguire Nuclear Station, Units 1 and 2; Issuance of Amendments to Revise the Conditional Exemption of the End-Of-Cycle Moderator Temperature Coefficient Measurement Methodology (EPID L-2021-LLA-0198) Public ML22046A0222022-06-14014 June 2022 Issuance of Amendments to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML22010A2812022-03-0404 March 2022 Issuance of Amendments to Adopt TSTF-577, Rev. 1 Revised Frequencies for Steam Generator Tube Inspections (EPID L-2021-LLA-0161 ML22007A3452022-01-11011 January 2022 Proposed Alternative to Use the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-885 ML21266A0112021-10-0505 October 2021 Staff Evaluation Related to Aging Management Program and Inspection Plan of Reactor Vessel Internals Per MRP-227, Revision 1-A ML21253A0822021-09-20020 September 2021 Proposed Alternative Request RA-21-0145 to Use Reactor Vessel Head Penetration Embedded Flaw Repair Method ML21155A2132021-08-26026 August 2021 Plant ML21131A0262021-06-23023 June 2021 Issuance of Amendments to Change Technical Specification 3.8.1, to Reduce Emergency Diesel Generator Maximum Voltage ML21113A0132021-05-0606 May 2021 Request for Use of a Later Edition of ASME Boiler and Pressure Vessel Code, Section XI for Repair and Replacement Activities ML21029A3352021-02-16016 February 2021 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20300A2062020-11-0909 November 2020 Duke Fleet - Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20258A2712020-09-21021 September 2020 Correction Letter to Amendment Nos. 301, 329, 307, 303, 178, 317, 296, 416, 418, 417, and 268 ML20083F9272020-08-12012 August 2020 Issuance of Amendments to Relocate the Unit/Facility/Plant Staff Qualification Requirements to the Duke Energy Quality Assurance Program Description ML20174A0452020-08-0404 August 2020 Issuance of Amendment No. 306 to Revise Technical Specification 3.4.3, RCS (Reactor Coolant System) Pressure and Temperature (P/T) Limits ML19296D1192020-01-31031 January 2020 Issuance of Amendment Nos. 305 and 301 to Revise Technical Specification 3.0, Surveillance Requirement (SR) Applicability ML19254A6202019-09-17017 September 2019 Duke Energy Fleet (Brunswick, Catawba, Robinson, McGuire, Oconee, and Shearon Harris) - Alternative to Use Encoded Phased Array Ultrasonic Examination in Lieu of Radiography ML19212A6552019-08-27027 August 2019 Issuance of Amendment Nos. 304 and 300 to Technical Specification 3.8.1, AC Sources - Operating ML19191A0612019-07-15015 July 2019 Review of the Steam Generator Tube Inservice Inspection Report for the Fall 2018 Refueling Outage 24 ML19058A6322019-07-0101 July 2019 Issuance of Amendments to Revise Emergency Action Level Schemes to Incorporate Clarifications Provided by Emergency Preparedness FAQs ML19128A3262019-06-20020 June 2019 Alternative to Depth Sizing Qualification Examination of Welds ML19121A5512019-06-17017 June 2019 Issuance of Amendments Related to the Removal of Containment Valve Injection Water System Supply from Specified Containment Isolation Valves ML19050A2972019-04-18018 April 2019 McGuire Nuclear Station, Units 1 and 2, Shearon Harris Nuclear Power Plant, Unit 1, H B. Robinson Steam Electric Plant, Unit 2 - Issuance of Amendments Regarding Removal ML18275A2782018-11-28028 November 2018 Issuance of Amendments Related to the Nuclear Service Water System New Condition for Single Pond Return Header Configuration ML18172A1722018-08-15015 August 2018 Issuance of Amendments to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application ML18016A1782018-01-24024 January 2018 Request for Relief No. 17-CN-001, Regarding Category B-J Pressure Retaining Welds for the Third 10-Year Inservice Testing Interval (CAC Nos. MF9807 and MF9808; EPID L-2017-LLA-0032) ML17296A2082018-01-0404 January 2018 Issuance of Amendments Adopting Technical Specifications Task Force Traveler TSTF-197-A, Revision 2 (CAC Nos. MF8971 & MF8972, EPID L-2016-LLA-0026) ML17331A0862017-12-26026 December 2017 Alternative to Inservice Inspection Regarding Reactor Pressure Vessel Threads ML17254A1442017-10-23023 October 2017 Issuance of Amendments Adopting Technical Specifications Task Force Traveler TSTF-352-A, Revision 1 (CAC Nos. MF8969 and MF8970; EPID L-2017-LLA-0031) ML17261B2902017-10-23023 October 2017 Issuance of Amendment Nos. 296 and 292, Adopt TSTF-142-A, Revision 0, Increase the Completion Time When the Core Reactivity Balance Is Not within Limit (CAC Nos. MF8962 and MF8963); EPID L-2017-LLA-0024 ML17257A2972017-10-23023 October 2017 Issuance of Amendment Nos. 295 and 291, Adoption of TSTF-340-A, Revision 3, Allow 7-Day Completion Time for a Turbine-Driven AFW Pump Inoperable (CAC Nos. MF8979 and MF8980; EPID L-2017-LLA-0043) ML17249A1352017-09-29029 September 2017 Issuance of Amendments Adopting Technical Specifications Task Force Travelers TSTF-349-A, Revision 1, TSTF-361-A, Revision 2, and TSTF-438-A, Revision 0 ML17188A3872017-08-21021 August 2017 Issuance of Amendments Regarding Application to Consolidate Emergency Operations Facilities and Associated Emergency Plan Changes (CAC Nos. MF7650 Through MF7660) ML17172A4282017-07-26026 July 2017 Issuance of Amendments Adopting Technical Specification Task Force Traveler TSTF-315-A, Revision 0 ML17165A4412017-07-21021 July 2017 Issuance of Amendments Adopting Technical Specification Task Force Traveler TSTF-269-A, Revision 2 (CAC Nos. MF8983 and MF8984). 08/10/2017 ML17055A6472017-05-0808 May 2017 Brunswick, Catawba, McGuire, Shearon Harris, and H. B. Robinson - Issuance of Amendments to Revise Technical Specifications to Adopt TSTF-522, Revision 0 (CAC Nos. MF8422, MF8423, MF8424, MF8425, MF8426, MF8427, MF8428, and MF8429) ML17066A3742017-04-26026 April 2017 Issuance of Amendments Re. Application to Revise TSs to Adopt TSTF-427, Rev. 2, Using the Consolidated Line Item Improvement Process (CAC Nos. MF8039 Through MF8049) ML16137A3082017-02-0808 February 2017 Issuance of Amendments Regarding National Fire Protection Association Standard NFPA 805 ML16277A4042016-10-20020 October 2016 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML16208A2832016-08-0808 August 2016 Correction to Issuance of Amendments Regarding Use of Optimized Zirlo ML16159A3362016-07-19019 July 2016 Issuance of Amendments Regarding Request to Use an Alternate Fission Gas Gap Release Fraction (CAC Nos. MF6480 Through MF6486) 2024-07-12
[Table view] |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. K. Henderson Site Vice President Catawba Nuclear Station Duke Energy Carolinas, LLC 4800 Concord Road York, NC 297 45 August 27, 2014
SUBJECT:
CATAWBA NUCLEAR STATIQN, UNIT 2-REVIEW OF THE STEAM* GENERATOR TUBE INSERVICE INSPECTION REPORT FOR THE FALL 2013 REFUELING OUTAGE (TAG NO. MF3355)
Dear Mr. Henderson:
By letter dated January 13, 2014 (Agencywide Documents Access and Management System, (ADAMS) Accession No. ML 14016A 147), Duke Energy Carolinas, LLC (the licensee) submitted information summarizing the results of the 2013 Steam Generator (SG) tube inspections at the Catawba Nuclear Station, Unit No. 2. These inspections were performed during the end of cycle 19 refueling campaign.
The Nuclear Regulatory Commission (NRC) staff conducted a conference call with the licensee on May 27, 2014. The NRC staff has completed its review of the submittal and concludes that the licensee provided the information required by the plant's Technical Specifications.
No additional follow up is necessary at this time. The NRC staff's review of the SG inspection report is enclosed.
If you have any questions, please contact the Project Manager, G. Edward Miller at 301-415-2481 or via e-mail at ed.miller@nrc.gov.
Docket Nos. 50-414
Enclosure:
As stated ' cc w/encl: Distribution via ListServ Sincerely, Robert J. Pascarelli, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 STAFF EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO RESULTS OF THE 2013 STEAM GENERATOR TUBE INSPECTIONS DUKE ENERGY CAROLINAS, LLC CATAWBA NUCLEAR STATION. UNIT 2 DOCKET NO. 50-414 By letter dated January 13, 2014 (Agencywide Documents Access Management System Accession No. ML14016A147), Duke Energy Carolinas, LLC (the licensee), submitted information summarizing the results of their fall 2013 steam generator (SG) tube inspections, performed during refueling outage 19 at Catawba Nuclear Station (Catawba), Unit 2. Additional information provided by the licensee during a conference call on May 27, 2014, is summarized below. Catawba, Unit 2 has four Westinghouse Model D5 SGs, which are designated 2A through 2D. Each SG has 4,570 thermally treated Alloy 600 tubes with an outside diameter of 0. 750 inches and a nominal wall thickness of 0.043 inches. The tubes are hydraulically expanded for the full-depth of the tubesheet at each end. The tubes are supported by Type 405 stainless steel support plates with quatrefoil-shaped holes. The U-bend region of the tubes in Rows 1 through 9 was thermally treated after bending, in order to reduce stress. . The licensee provided the scope, extent, methods, and results of their SG tube inspections in the document referenced above. In addition, the licensee described corrective actions (i.e., tube plugging) taken in response to the inspection findings.
- On May 27, 2014, the licensee clarified the following during a conference call:
- At the end of operational cycle 17 {i.e., in refueling outage (RFO) 17), the replacement SGs had 20.13 cumulative effective full power years (EFPY) of operation.
In RF018, the replacement SGs had 21.50 EFPY of operation, and in RF019, the replacement SGs had 22.89 EFPY of operation.
- The seven tubes plugged in RF019 were located in SGs 2B and 2C. In SG 2B, the plugged tubes were located in row 28 column 24 (R28C24), R27C23, and R28C23. In SG 2C, the plugged tubes were located in R45C79, R47C78, R46C78, and R45C78. Enclosure
- No degradation was observed in any of the SG tube plug examinations or in the SG bowl cladding inspections.
- Other than the foreign object inspections of the secondary face of each SG tubesheet, secondary side inspections included the top of the uppermost tube support plate in SG 2A. Minor amounts of both scale and sludge were observed on this tube support plate. The quatrefoil holes were generally free of blockage from sludge and scale. o The trend of tube end indications found during the last few inspections has remained flat.
- No primary to secondary leakage was noted during operating cycle 19 and the calculated leakage rate from the portion of the tubes more than 14.01 inches from the top of the tubesheet was zero.
- The following numbers of indications were confirmed/provided by the licensee:
Tubes with anti-vibration bar indications SG A-75 tubes/134 indications SG B -22 tubes/33 indications SG C -48 tubes/69 indications SG D -69 tubes/1 02 indications Tubes with tube support plate indications SG A -8 tubes/1 0 indications SG B -14 tubes/15 indications SG C -5 tubes/5 indications SG D -3 tubes/3 indications Tubes with indications within the tubesheet SG A -1 tubes/1 indications SG B -154 tubes/154 indications SG C -11 tubes/11 indications SG D -5 tubes/5 indications Based on a review of the information provided in the SG Tube Inspection Report, the NRC staff concludes that the licensee provided the information required by their technical specifications.
In addition, the NRC staff concludes that there are no technical issues that warrant follow-up action at this time since the inspections appear to be consistent with the objective of detecting potential tube degradation and the inspection results appear to be consistent with industry operating experience at similarly designed and operated units.
Mr. K. Henderson Site Vice President Catawba Nuclear Station Duke Energy Carolinas, LLC 4800 Concord Road York, NC 297 45 August 27, 2014
SUBJECT:
CATAWBA NUCLEAR STATION, UNIT 2-REVIEW OF THE STEAM GENERATOR TUBE INSERVICE INSPECTION REPORT FOR THE FALL 2013 REFUELING OUTAGE (TAC NO. MF3355}
Dear Mr. Henderson:
By letter dated January 13, 2014 (Agencywide Documents Access and Management System, (ADAMS) Accession No. ML 14016A147), Duke Energy Carolinas, LLC (the licensee) submitted information summarizing the results of the 2013 Steam Generator (SG) tube inspections at the Catawba Nuclear Station, Unit No. 2. These inspections were performed during the end of cycle 19 refueling campaign.
The Nuclear Regulatory Commission (NRC) staff conducted a conference call with the licensee on May 27, 2014. The NRC staff has completed its review of the submittal and concludes that the licensee provided the information required by the plant's Technical Specifications.
No additional follow up is necessary at this time. The NRC staff's review of the SG inspection report is enclosed.
If you have any questions, please contact the Project Manager, G. Edward Miller at 301-415-2481 or via e-mail at ed.miller@nrc.gov.
Sincerely, /RAJ Robert J. Pascarelli, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-414
Enclosure:
As stated cc w/encl: Distribution via ListServ DISTRIBUTION:
Public Branch Reading RidsNrrDorllp12-1 Resource RidsNrrDeEgsb Resource RidsRgn2MaiiCenter Resource KKarwoski, NRR AJohnson, NRR GKulesa, NRR ADAMS Accession No.: Ml14237 A008 OFFICE NRR/DORULPL2-1
/PM NRR/DORULPL2-1/LA NRR/DE/ESGB/BC NAME GEMiller SFigueroa GKulesa DATE 08/26/14 08/26/14 06/12/14 OFFICIAL RECORD COPY NRR/DORLILPL2-1/BC RPascarelli 08/27/14