ML23104A443
| ML23104A443 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 04/14/2023 |
| From: | Marcia Carpentier, Licon E NRC/OGC |
| To: | Atomic Safety and Licensing Board Panel |
| SECY RAS | |
| References | |
| Download: ML23104A443 (0) | |
Text
April 14, 2023 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of VISTRA OPERATIONS COMPANY, LLC Comanche Peak Nuclear Power Plant, Units 1 and 2 Docket No. 50-445 and 50-446 Additional Citations for Reference in NRC Staffs Oral Argument on April 19, 2023 In response to the Atomic Safety and Licensing Boards Memorandum and Order (Scheduling Initial Prehearing Conference) of April 6, 2023, the NRC Staff intends to refer to the following documents in its oral argument on April 19, 2023. Citations from the Comanche Peak license renewal application (LRA)1 use the page numbering of the electronic file that can be downloaded from the NRC public web site at:
https://www.nrc.gov/reactors/operating/licensing/renewal/applications/comanche-peak.html.
LRA File Page #
Content Applicants Page #
Why Cited 418 Table 3.1.2-2: Reactor Vessel Internals - Summary of Aging Management Evaluation (2nd and 3rd lines) 3.1-91 Cited in Petition 426 Generic Notes for Table 3.1.2-2 3.1-99 Hyperlinked to 2nd and 3rd lines in table on p. 418 1439-1450 Aging Management Program -
PWR Vessel Internals B-54 to B-65 Hyperlinked to 2nd line in table on p. 418 1 Comanche Peak Nuclear Power Plant, Units 1 and 2, Docket Numbers 50-445 and 50-446, Facility Operating License Numbers NPF-87 and NPF-89, License Renewal Application (Oct. 3, 2023).
2 LRA File Page #
Content Applicants Page #
Why Cited 1417-1422 Aging Management Program -
Water Chemistry B-32 to B-B-37 Hyperlinked to 3rd line in table on p. 418 NUREG-1801, Rev. 2, Generic Aging Lessons Learned (GALL)
Report (Dec. 2010) (ADAMS Accession No. ML103490041)
Referenced on pp. 1442 and 1418 for the two aging management programs listed above EPRI, MRP-227, Revision 1-A, Materials Reliability Program:
Pressurized Water Reactor Internals Inspection and Evaluation Guidelines (Dec. 2019)
(ADAMS Accession No. ML19339G350)
Referenced on p. 1439 for the aging management program on pp. 1439-1450 1015 Section 3.5.2.2.1.5 - Cumulative Fatigue Damage 3.5-23 Not cited in Petition, but mentions seismic loads 1271-1274 Sections 4.6.1 and 4.6.2 - Time Limited Aging Analyses for the Containment Liner Plate and Containment Penetrations 4.6-1 to 4.6-4 Hyperlinked to Section 3.5.2.2.1.5 on p. 1015 1558-1561 Aging Management Program -
ASME Section XI, Subsection IWE B-173 to B-176 Hyperlinked to Section 3.5.2.2.1.5 on p. 1015 The NRC Staff does not intend to speak to the following additional examples at oral argument, but includes them here for the convenience of the Licensing Board and the other parties to this proceeding.
LRA File Page #
Content Applicants Page #
Why Cited 1029 Table 3.5-1 Summary of Aging Management Programs for Containment Building and Internal Structural Components (1st line) 3.5-37 Cited in Petition 1041-1042 Table 3.5-1 Summary of Aging Management Programs for Containment Building and Internal Structural Components 3.5-49 to 3.5-50 Cited in Petition 1577-1581 Aging Management Program -
Structures Monitoring B-192 to B-196 Hyperlinked to 1st line in table on p. 1029 and all lines in table on pp. 1041-1042
3 LRA File Page #
Content Applicants Page #
Why Cited 1044 Table 3.5-1 Summary of Aging Management Programs for Containment Building and Internal Structural Components (2nd line) 3.5-52 Cited in Petition 1024-1026 Section 3.5.2.2.2.3 - Aging Management of Inaccessible Areas for Group 6 Structures 3.5-32 to 3.5-34 Hyperlinked to 2nd line in table on p. 1044 1049 Table 3.5-1 Summary of Aging Management Programs for Containment Building and Internal Structural Components (1st line) 3.5-57 Cited in Petition 1582-1585 Aging Management Program -
RG 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants B-197 to B-200 Hyperlinked to 1st line in table on p. 1049 RG 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants (Feb. 2016)
(ADAMS Accession No. ML15107A412)
Referenced in aging management program on pp. 1582-1585 Respectfully submitted,
/Signed (electronically) by/
Marcia Carpentier Counsel for NRC Staff Mail Stop: O-14-A44 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Telephone: 301-287-9135 E-mail: marcia.carpentier@nrc.gov Executed in Accord with 10 CFR 2.304(d)
Ethan Licon Counsel for NRC Staff Mail Stop: O-14-A44 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Telephone: 301-415-1016 E-mail: ethan.licon@nrc.gov Dated in Rockville, MD this 14th day of April 2023
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of VISTRA OPERATIONS COMPANY, LLC Comanche Peak Nuclear Power Plant, Units 1 and 2 Docket No. 50-445 and 50-446 Certificate of Service Pursuant to 10 C.F.R §2.305, I hereby certify that copies of the foregoing Additional Citations for Reference in NRC Staffs Oral Argument on April 19, 2023, dated April 14, 2023, have been served upon the Electronic Information Exchange (the NRCs E-Filing System), in the captioned proceeding, this 14th day of April 2023.
/Signed (electronically) by/
Marcia Carpentier Counsel for NRC Staff Mail Stop: O-14-A44 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Telephone: 301-287-9135 E-mail: marcia.carpentier@nrc.gov Dated in Rockville, MD this 14th day of April 2023