ML23339A181

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Correction Letter Regarding License Amendment Request: More Restrictive Action for Technical Specification 3.1.9
ML23339A181
Person / Time
Site: Vogtle 
Issue date: 12/07/2023
From: Bill Gleaves
NRC/NRR/VPOB
To: Coleman J
Southern Nuclear Operating Co
Gleaves W
References
EPID L-2023-LLA-0072
Download: ML23339A181 (3)


Text

December 7, 2023 Ms. Jamie M. Coleman, Director Fleet Regulatory Affairs Southern Nuclear Operating Company, Inc.

3535 Colonnade Parkway, Bin N-274-EC Birmingham, AL 35243

SUBJECT:

VOGTLE ELECTRIC GENERATING PLANT, UNIT 4 - CORRECTION TO LICENSE AMENDMENT NO. 192 REGARDING MORE RESTRICTIVE ACTION FOR TECHNICAL SPECIFICATION 3.1.9 (EPID L-2023-LLA-0072)

Dear Ms. Coleman:

The U.S. Nuclear Regulatory Commission (NRC) issued Amendment Nos. 195 and 192 to Combined License (COL) Nos. NPF-91 and NPF-92, for Vogtle Electric Generating Plant (VEGP) Units 3 and 4, respectively, on November 28, 2023 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML23289A163). Following issuance, typographical errors were identified on page 7 of the COL for VEGP, Unit 4.

The attachment to Amendment No. 192 for Unit 4 was issued with inadvertent typographical errors on COL page 7. Specifically, under (7) Reporting Requirements, the numbering of paragraphs (a) and (b) were inadvertently changed to (c) and (d). Additionally, under (9)

Technical Specifications, paragraph (a), the word in was omitted between the words operating and plant. Further, in paragraph (9)(a) first bullet, TS 3.3.8, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Table 3.3.8-1, Function 15, Core Makeup Tank (CMT) Level - Low 3, was inadvertently changed to Function 14. With this letter, these errors to VEGP, Unit 4, COL page 7 are corrected.

The NRC staff concludes that the errors were introduced during the preparation of the license amendments and are entirely editorial in nature. The corrections do not change any of the conclusions in the safety evaluation associated with the amendments referenced above and do not affect the associated notices to the public. Please replace VEGP COL page 7 for Unit 4 with the enclosed corrected page.

If you have any questions regarding this matter, please contact me at (301) 415-5848, or via email at bill.gleaves@nrc.gov.

Sincerely,

/RA/

William (Billy) Gleaves, Senior Project Manager Vogtle Project Office Office of Nuclear Reactor Regulation Docket No: 52-026

Enclosure:

Corrected page 7 in Attachment to License Amendment No. 192 for COL No. NPF-92 cc: Listserv

7 Amendment No. 192 (7)

Reporting Requirements (a)

Within 30 days of a change to the initial test program described in UFSAR Section 14, Initial Test Program, made in accordance with 10 CFR 50.59 or in accordance with 10 CFR Part 52, Appendix D, Section VIII, Processes for Changes and Departures, SNC shall report the change to the Director of NRO, or the Directors designee, in accordance with 10 CFR 50.59(d).

(b)

SNC shall report any violation of a requirement in Section 2.D.(3),

Section 2.D.(4), Section 2.D.(5), and Section 2.D.(6) of this license within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Initial notification shall be made to the NRC Operations Center in accordance with 10 CFR 50.72, with written follow up in accordance with 10 CFR 50.73.

(8)

Incorporation The Technical Specifications, Environmental Protection Plan, and ITAAC in Appendices A, B, and C, respectively of this license, as revised through Amendment No. 192, are hereby incorporated into this license.

(9)

Technical Specifications The technical specifications in Appendix A to this license become effective upon a Commission finding that the acceptance criteria in this license (ITAAC) are met in accordance with 10 CFR 52.103(g) with the following exceptions:

(a)

Prior to initial criticality of the reactor core while operating in plant operational Mode 5 (Cold Shutdown) or Mode 6 (Refueling) the following TS are temporarily excluded from becoming effective:

TS 3.3.8, Engineered Safety Feature Actuation System (ESFAS)

Instrumentation, Table 3.3.8-1 o Function 14, RCS Wide Range Pressure - Low o Function 15, Core Makeup Tank (CMT) Level - Low 3 o Function 16, CMT Level - Low 6 o Function 18, IRWST Lower Narrow Range Level - Low 3 TS 3.3.9, Engineered Safety Feature Actuation System (ESFAS)

Manual Initiation, Table 3.3.9-1 o Function 1, Safeguards Actuation - Manual Initiation o Function 6, ADS Stages 1, 2 & 3 Actuation - Manual Initiation o Function 7, ADS Stage 4 Actuation - Manual Initiation o Function 8, Passive Containment Cooling Actuation - Manual Initiation o Function 9, Passive Residual Heat Removal Heat Exchanger Actuation - Manual Initiation

ML23339A181 NRO-002 OFFICE NRR/VPO/PM NRR/DORL/LPL3/LA NRR/VPO/D NAME BGleaves ABaxter LNist DATE 12/07/2023 12/06/2023 12/07/2023