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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 05000414/LER-2022-003, Manual Reactor Trip and Auxiliary Feedwater System Actuation2022-12-23023 December 2022 Manual Reactor Trip and Auxiliary Feedwater System Actuation 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 05000414/LER-2022-002, Indications Identified During Reactor Vessel Head Penetration Embedded Flaw Repair Surface Examination2022-12-0606 December 2022 Indications Identified During Reactor Vessel Head Penetration Embedded Flaw Repair Surface Examination 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 2024-09-05
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24197A1702024-07-15015 July 2024 Request for Additional Information Two Proposed Alternatives (RA-23-0242) for the Inspection of Reactor Vessel Closure Head Penetrations ML24150A1662024-05-29029 May 2024 Document Request for Catawba Nuclear Station Units 1 & 2 - Radiation Protection Inspection - Inspection Report 2024-03 ML23271A1792023-09-28028 September 2023 Request for Confirmation License Amendment Application to Revise Control Room Cooling TS 3.7.11 ML23151A3482023-05-30030 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML23142A2732023-05-22022 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) ML22336A0692022-11-28028 November 2022 Final 2023 Catawba Nuclear Station (CNS) Commercial Grade Dedication (CGD) Inspection Information Request ML22154A1312022-06-0303 June 2022 NRR E-mail Capture - Catawba Nuclear Station, Units 1 and 2 - Request for Additional Information Environmentally-Assisted Fatigue License Renewal Commitment ML22115A1412022-04-25025 April 2022 NRR E-mail Capture - Duke Common EOF Relocation - Request for Addition Information ML22102A2962022-04-13013 April 2022 Request for Withholding Information from Public Disclosure Response to Request for Additional Information ML22063B1782022-03-0909 March 2022 Request for Additional Information Regarding LAR for Revision to the Conditional Exemption of the End of Cycle Moderator Temperature Coefficient Measurement Methodology (EPID L-2021-LLA-0198) NON-PROPRIETARY ML22024A1122022-01-24024 January 2022 2022 CNS POV Inspection Information Request ML21354A8612021-12-15015 December 2021 NRR E-mail Capture - Request for Additional Information - Duke Fleet Request RA-19-0352 - Alternative for RPV Closure Stud Exams (L-2020-LLR-0156) ML21335A2252021-12-0101 December 2021 NRR E-mail Capture - Catawba Nuclear Station, Unit 2 - Request for Additional Information Spring 2021 Steam Generator Tube Inspection Report (L-2021-LRO-0043) ML21117A1232021-04-23023 April 2021 NRR E-mail Capture - Catawba Verbal Relief Request Request for Additional Information ML21075A0032021-03-12012 March 2021 Emergency Preparedness Exercise Inspection Request for Information for - Brunswick, Catawba, North Anna, Oconee, Vogtle 1 & 2 ML21049A2632021-02-0404 February 2021 NRR E-mail Capture - Request for Additional Information - Duke Energy Fleet License Amendment Request to Revise Emergency Plan ML20346A0212020-12-10010 December 2020 NRR E-mail Capture - Formal Release of RAIs - License Amendment to Change TS 3.8.1 Due Jan. 29, 2021 ML20338A3932020-12-0303 December 2020 Notification of Inspection and Request for Information ML20323A4072020-11-18018 November 2020 NRR E-mail Capture - Request for Additional Information - Brunswick License Exemption Request from 10CFR73 Annual Force on Force Exercise Requirements (EPIC L-2020-LLE-0180) ML20244A0462020-08-31031 August 2020 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML20073F3832020-03-13013 March 2020 NRR E-mail Capture - Request for Additional Information - Catawba Nuclear Station - SG Report (RA-19-0391) - C2R23 ML20050D3382020-02-21021 February 2020 Letter RAI 1 MAGNASTOR-Catawba and McGuire Exemptions with Enclosure ML20052E4282020-02-21021 February 2020 Notification of NRC Fire Protection Team Inspection (Fpti) (NRC Inspection Report 05000412/2020013 and 05000414/2020013) and Request for Information ML20003E5372020-01-0303 January 2020 NRR E-mail Capture - Catawba PT Limits LAR - RAIs ML19032A5842019-01-31031 January 2019 Emergency Preparedness Program Inspection Request for Information ML19011A1372019-01-10010 January 2019 NRR E-mail Capture - Duke Energy Fleet RAIs - Relief Request 18-GO-001 - Proposed Alternative for Depth Sizing Qualification Examination of Welds (L-2018-LLR-0117) ML19009A5412019-01-0909 January 2019 NRR E-mail Capture - Request for Additional Information - Catawba Nuclear Station, Units 1 and 2 - Esps LAR ML19007A3422018-12-21021 December 2018 NRR E-mail Capture - Duke Energy Fleet Draft RAIs - Relief Request 18-GO-001 - Proposed Alternative for Depth Sizing Qualification Examination of Welds (L-2018-LLR-0117) ML18068A5052018-03-0909 March 2018 NRR E-mail Capture - Request for Additional Information - Catawba Nuclear Station, Units 1 and 2 - Nsws Return Pond Header LAR (CACs MG0245 and MG0246, EPID L-2017-LLA-0297) ML18058B2062018-02-27027 February 2018 Notification of Inspection and Request for Information ML18057A2182018-02-23023 February 2018 Enclosurequest for Additional Information (Letter to A. Zaremba Request for Additional Information for Review of Duke Energy'S Decommissioning Funding Plan Update) ML17335A0972017-11-29029 November 2017 NRR E-mail Capture - Request for Additional Information - Catawba Nuclear Station, Units 1 and 2 - Relief Request 17-CN-001 (CACs MF9807 and MF9808, EPID L-2017-LLR-0032) ML17135A0302017-05-12012 May 2017 NRR E-mail Capture - Request for Additional Information - Catawba TSTF-197 ML17115A1422017-04-25025 April 2017 NRR E-mail Capture - Request for Additional Information - Catawba SG Report - RFO 21 ML16337A3322017-01-12012 January 2017 Request for Additional Information Regarding License Amendment Request for Electrical Power System Alignments for Shared Systems ML16355A3922016-12-29029 December 2016 Request for Additional Information Regarding License Amendment Request to Implement a Risk-Informed, Performance-Based Fire Protection Program ML16292A2252016-10-14014 October 2016 Emergency Preparedness Inspection and Request for Information ML16271A0752016-10-12012 October 2016 Request for Additional Information Regarding License Amendment Request for Electrical Power System Alignments for Shared Systems ML16222A7472016-08-0909 August 2016 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML16205A0022016-07-21021 July 2016 Notification of Inspection and Request for Information ML16187A0662016-07-0707 July 2016 Catawba Nuclear Station, Units 1 and 2 - Request for Additional Information Regarding License Amendment Request to Implement a Risk-Informed, Performance-Based Fire Protection Program (CAC Nos. MF2936 and MF2937) ML16111B2472016-04-28028 April 2016 Request for Additional Information Re. License Amendment Request to Revise TS 5.5.2 Containment Leakage Rate Testing Program ML16120A0872016-04-27027 April 2016 Notification of Inspection and Request for Information ML16113A0732016-04-22022 April 2016 Draft RAIs License Amendment Request to Revise TS Section 5.5.2 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML16007A1902016-01-20020 January 2016 Request for Additional Information Regarding License Amendment Request to Change the RCS Minimum Required Flow Rates ML16014A7102016-01-20020 January 2016 Request for Additional Information Regarding License Amendment Request to Revise Emergency Action Level Scheme ML15348A2602015-12-17017 December 2015 Request for Additional Information Regarding License Amendment Request to Use an Alternative Fission Gas Gap Release Fraction ML15320A3862015-11-19019 November 2015 RAI LAR to Adopt TSTF-523 ML15314A3562015-11-10010 November 2015 E-mail from J. Whited to A. Zaremba Duke Energy Draft RAIs License Amendment Request to Adopt TSTF-523 (CAC Nos. MF6413-MF6422) ML15314A3592015-11-10010 November 2015 Duke Energy Draft RAIs Request to Adopt TSTF-523 (CAC Nos. MF6413-MF6422) 2024-07-15
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Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 12, 2017 Mr. Kelvin Henderson Vice President Catawba Nuclear Station Duke Energy 4800 Concord Road I CN01VP York, NC 29745
SUBJECT:
CATAWBA NUCLEAR STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST FOR ELECTRICAL POWER SYSTEMS ALIGNMENTS FOR SHARED SYSTEMS (CAC NOS. MF7748 AND MF7749)
Dear Mr. Henderson:
By letter dated May 26, 2016 (Agencywide Documents Access and Management System Accession No. ML16147A105), Duke Energy, Inc. (the licensee) requested approval for an updated final safety analysis report (UFSAR) change for the Catawba Nuclear Station (CNS),
Units 1 and 2. CNS proposes to add descriptions to several sections of the UFSAR to clarify how a shutdown unit supplying either its normal or emergency power source may be credited for operability of shared components supporting the operating unit.
The U.S. Nuclear Regulatory Commission staff has reviewed the licensee's submittal and determined that additional information is needed in order to complete its review. Please provide your response to the enclosed request for additional information within 30 days of the date of this letter.
If you have any questions, please contact me at 301-415-3867 or by e-mail to Michael.Mahoney@nrc.gov.
!&A
~chael Mahoney, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-413 and 50-414
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO REVISE THE UPDATED FINAL SAFETY ANALYSIS REPORT TO REFLECT ELECTRICAL POWER SYSTEMS ALIGNMENTS FOR SHARED SYSTEMS DUKE ENERGY CAROLINAS. LLC CATAWBA NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-413 AND 50-414 By letter dated May 26, 2016 (Agencywide Documents Access and Management System Accession No. ML16147A105), Duke Energy, Inc. (the licensee) requested approval for an updated final safety analysis report (UFSAR) change for the Catawba Nuclear Station (CNS),
Units 1 and 2. CNS proposes to add descriptions to several sections of the UFSAR to clarify how a shutdown unit supplying either its normal or emergency power source may be credited for operability of shared components supporting the operating unit.
The U.S. Nuclear Regulatory Commission staff needs the following additional information to complete its review of the license amendment request (LAR).
Request for Additional Information (RAI) 5 With a single line diagram, please explain how the electrical systems for each unit (power sources (both alternating current (ac) and direct current (de), ac medium voltage buses and switchgears, distribution panels, load centers, motor control centers, and shared loads) are configured. For the following operating configurations, please identify (1) the applicable electrical-related technical specification (TS) requirements for each unit; (2) the operability of each shared structure, system, and component (SSC) (i.e., nuclear service water system (NSWS), control room area ventilation system (CRAVS), control room area chilled water system (CRACWS), and the auxiliary building filtered ventilation exhaust system (ABFVES)); and (3) the applicable TS required actions:
- a. When both units are in Modes 1-4;
- b. When both units are in Modes 1-4 and Train A of one unit is undergoing engineered safety feature (ESF) testing;
- c. When both units are in Modes 1-4 and Train A of both units is undergoing ESF testing, if performed;
- d. When one unit (Unit 1) is in Modes 1-4 and the other unit is in Modes 5-6; and Enclosure
- e. When one unit (Unit 1) is in Modes 1-4 and the other unit is in Modes 5-6 and undergoing ESF testing.
The regulation at Title 10 of the Code of Federal Regulations (1 O CFR) 50.36(c)(2)(ii)(C),
"Criterion 3," states that a TS Limiting Condition for Operation (LCO) must be established for:
A structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.
(1) Please review the following scenarios as an example:
- a. Both units are in Mode 1 requiring all four emergency diesel generators (EDGs) to be OPERABLE to meet TS 3.8.1 for each unit. CNS, Unit 2, suffers a loss of coolant accident (LOCA) and both units suffer a loss of offsite power (LOOP).
CNS, Unit 2, needs at least one CNS, Unit 1, EOG (either 1A or 1B) and the distribution systems to mitigate the LOCA, assuming a single failure of either 2A or 2B EDGs.
However, TS 3.8.1 for CNS, Unit 2, does not include the CNS, Unit 1, EDGs (i.e., TS 3.8.1 does not require all four EDGs), nor does TS 3.8.9 for CNS, Unit 2, include the CNS, Unit 1, power distribution systems. Even without postulating a single failure (i.e., EOG failure), CNS, Unit 2, still needs at least one of the CNS, Unit 1, EDGs to mitigate the LOCA.
Please explain how compliance with 10 CFR 50.36(c)(2)(ii)(C) is achieved in this scenario considering that a CNS, Unit 1, EOG is required to mitigate a CNS, Unit 2, LOCA, or provide proposed TS changes.
- b. CNS, Unit 1, is in Mode 5 with 1A EOG inoperable and meets TS 3.8.2. CNS, Unit 2, is in Mode 1 and meets TS 3.8.1 and TS 3.8.9. Neither unit is in a TS ACTION statement.
CNS, Unit 2, suffers a LOCA and both units suffer a LOOP. The 2B EOG fails, leaving only the 1B and 2A EDGs OPERABLE.
Depending on the lineup of the current power supply (both medium and low voltage buses) and valve lineup of the shared systems (NSWS, CRAVS, CRACWS, and ABFVES), CNS, Unit 2, may need the 1B EOG and associated distribution systems to mitigate the LOCA. However, TS 3.8.1 does not include the CNS, Unit 1, EDGs; TS 3.8.9 does not include any CNS, Unit 1, power distribution systems; nor are any required conditions for the shared systems in the CNS, Unit 2, TS.
Please explain how compliance with 10 CFR 50.36(c)(2)(ii)(C) is achieved in this scenario considering that a CNS, Unit 1, EOG is required to mitigate a CNS, Unit 2, LOCA, or provide proposed TS changes.
(2) Please provide a discussion of why the existing CNS TSs for electric systems (both ac and de) are conservative to support dual unit operation considering the operability requirements for shared systems when a CNS unit is operating or provide proposed TS changes in accordance with (10 CFR) 50.36(c)(2)(ii)(C).
RAI 7
UFSAR Section 8.3.1.1.2.3.2, "Periodic Testing," states, in part:
The normal and emergency AC [alternating current] power distribution systems for both units at Catawba are separate during normal operation. During testing on Unit 2, the power systems on Unit 1 will be lined up in their normal operating configurations, which will assure that cross-ties are not present which could affect availability of emergency power to Unit 1 during testing on Unit 2.
- a. Please clarify whether there are any cross-tie between CNS, Unit 1, and CNS, Unit 2, and between divisions within each unit. If cross-ties exist, explain how CNS meets 10 CFR Part 50, Appendix A, "General Design Criteria for Nuclear Power Plants," Criterion 5, "Sharing of structures, systems, and components."
- b. Please explain, with a diagram, how the above UFSAR statement is met during normal operation with ESF testing and also when one unit's emergency diesel generator (EOG) is inoperable.
During Train A load sequence testing, please state which shutdown unit's diesel generator would be credited as OPERABLE to support Train A equipment to satisfy the following proposed UFSAR statement:
The credited offsite power circuit and emergency diesel generator associated with the shutdown unit meet applicable TS 3.8.1 requirements ...
Please describe how this statement would avoid an "unnecessary TS 3.0.3 entry" if a Train B component was discovered inoperable on the operating unit.
Is CNS LCO 3.0.9 ever applied to the CNS safety related-electrical systems? If yes, please describe the circumstances.
RAI 10
The TS bases for the NSWS, CRAVS, CRACWS, and ABFVES currently state, in part,
A shutdown unit supplying its associated emergency source (1 EMXG/2EMXH) cannot be credited for OPERABILITY of components supporting the operating unit.
According the supplemental letter dated November 10, 2016 (ADAMS Accession No. ML16315A411), the licensee plans to remove the above statement from the TS bases upon approval of the LAR.
Please identify and discuss the reasons and intent for the TS bases statement above that does not allow crediting a shutdown unit supplying its associated emergency source (1 EMXG/2EMXH) to be credited for OPERABILITY of components supporting the operating unit.
ML16337A332 *Via Email OFFICE NRR/DORL/LPL2-1 /PM NRR/DORL/LPL2-1 /LA NRR/DE/EEEB/BC NRR/DORL/LPL2-1 /BC NAME MMahoney KGoldstein JZimmerman* MMarkley DATE 01/11/17 01/11/17 11/22/16 01/12/17 OFFICE NRR/DORL/LPL2-1 /PM NAME MMahoney DATE 01/12/17