ML19255H284

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NRR E-mail Capture - State Notification of Amendments to Oconee Nuclear Station, Units 1, 2 and 3 - Revise UFSAR Regarding Tornado Licensing Basis
ML19255H284
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 09/12/2019
From: Michael Mahoney
Plant Licensing Branch II
To: Nair-Gimmi A
State of SC, Dept of Health & Environmental Control
References
L-2018-LLA-0251
Download: ML19255H284 (5)
v • d • e


Text

1 NRR-DRMAPEm Resource From:

Mahoney, Michael Sent:

Thursday, September 12, 2019 11:06 AM To:

'Nair-Gimmi, Anuradha' Cc:

Klett, Audrey

Subject:

State Notification of Amendments to Oconee Nuclear Station, Units 1, 2 and 3 - Revise UFSAR Regarding Tornado Licensing Basis Attachments:

83 FR 31979.pdf; 83 FR 31193.pdf Mrs. Nair, We are near completion of amendments for the Oconee Nuclear Station (Oconee), Units 1, 2 and 3, to revise their Updated Final Safety Analysis Report (UFSAR). Specifically, the amendments would modify Oconees UFSAR regarding the tornado licensing basis to allow the Standby Shutdown Facility to mitigate a tornado with the assumed initial conditions of loss of all alternating current power to all units with significant tornado damage to one unit, the use of tornado missile probabilistic methodology, and the elimination of the spent fuel pool to high pressure injection flow path for reactor coolant makeup.

The application is September 14, 2018, (ADAMS Accession No. ML18264A018), as supplemented by letters dated January 24, 2019 (ADAMS Accession No. ML19036A625), and July 31, 2019 (ADAMS Accession No. ML19217A149).

The no significant hazards consideration determination was noticed in the Federal Register on July 3, 2018 (83 FR 31193), as corrected by a notice published on July 10, 2018 (83 FR 31979). Both are attached.

Please respond if you have any or no comments.

Thanks Mike Michael Mahoney McGuire and Catawba Project Manager, Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Desk: (301)-415-3867 Email: Michael.Mahoney@NRC.GOV

Hearing Identifier:

NRR_DRMA Email Number:

196 Mail Envelope Properties (SN6PR09MB3040D00C1B6A4099EF441489E5B00)

Subject:

State Notification of Amendments to Oconee Nuclear Station, Units 1, 2 and 3 -

Revise UFSAR Regarding Tornado Licensing Basis Sent Date:

9/12/2019 11:06:04 AM Received Date:

9/12/2019 11:06:05 AM From:

Mahoney, Michael Created By:

Michael.Mahoney@nrc.gov Recipients:

"Klett, Audrey" <Audrey.Klett@nrc.gov>

Tracking Status: None

"'Nair-Gimmi, Anuradha'" <nairgia@dhec.sc.gov>

Tracking Status: None Post Office:

SN6PR09MB3040.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 1368 9/12/2019 11:06:05 AM 83 FR 31979.pdf 50949 83 FR 31193.pdf 50206 Options Priority:

Standard Return Notification:

No Reply Requested:

No Sensitivity:

Normal Expiration Date:

Recipients Received:

31979 Federal Register / Vol. 83, No. 132 / Tuesday, July 10, 2018 / Notices proposed collection of information; (3) ways to enhance the quality, utility, and clarity of the information to be collected; and (4) ways to minimize the burden of the collection of information on respondents, including automated collection techniques or the use of other forms of information technology.

Comments submitted in response to this notice will be summarized and included in the request for OMB approval of this information collection. They will also become a matter of public record.

Gatrie Johnson, NASA PRA Clearance Officer.

[FR Doc. 2018-14703 Filed 7-9-18; 8:45 am]

BILLING CODE 7510-13-P NUCLEAR REGULATORY COMMISSION

[NRC-2018-0116]

Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing Sensitive Unclassified Non-Safeguards Information and Order Imposing Procedures for Access to Sensitive Unclassified Non-Safeguards Information Correction In notice document 2018-12919, appearing on pages 31190-31197 in the Issue of Tuesday, July 3, 2018, make the following correction:

On page 31180, in the third column, under the heading DATES:, the entry September 3, 2018 is corrected to read September 4, 2018.

[FR Doc. C1-2018-12919 Filed 7-9-18; 8:45 am]

BILLING CODE 1301-00-D NUCLEAR REGULATORY COMMISSION

[NRC-2016-0053, NRC-2014-0119, and NRC-2016-0158]

Program-Specific Guidance About Possession Licenses for Manufacturing and Distribution, Program-Specific Guidance About Well Logging, Tracer, and Field Flood Study Licenses, and Program-Specific Guidance About Possession Licenses for Production of Radioactive Material Using an Accelerator AGENCY: Nuclear Regulatory Commission.

ACTION: NUREG; issuance.

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) has issued Revision 1 to NUREG-1556, Volume 12, Consolidated Guidance About Materials Licenses: Program Specific Guidance About Possession Licenses for Manufacturing and Distribution; NUREG-1556, Volume 14, Consolidated Guidance About Materials Licenses: Program-Specific Guidance About Well Logging, Tracer, and Field Flood Study Licenses; and NUREG-1556, Volume 21, Consolidated Guidance About Materials Licenses: Program-Specific Guidance About Possession Licenses for Production of Radioactive material Using an Accelerator. NUREG-1556, Volumes 12, 14, and 21 have been revised to include information on updated regulatory requirements, safety culture, security of radioactive materials, protection of sensitive information, and changes in regulatory policies and practices. These volumes are intended for use by applicants, licensees, and the NRC staff.

DATES: NUREG-1556, Volume 14, Revision 1, was published in April 2018, and NUREG-1556, Volumes 12 and 21, Revision 1, were published in May 2018.

ADDRESSES: Please refer to Docket ID NRC-2016-0053 (NUREG-1556, Vol.

12, Rev. 1), Docket ID NRC-2014-0119 (NUREG-1556, Vol. 14, Rev. 1) and NRC-2016-0158 (NUREG-1556, Vol.

21, Rev. 1) when contacting the NRC about the availability of information regarding these documents. You may obtain publicly-available information related to these documents using any of the following methods:

Address questions about NRC dockets to Jennifer Borges; telephone: 301-287-9127; email: Jennifer.Borges@nrc.gov.

For technical questions, contact the individual listed in the FOR FURTHER INFORMATION CONTACT section of this document.

adams.html. To begin the search, select ADAMS Public Documents and then select Begin Web-based ADAMS Search. For problems with ADAMS, please contact the NRCs Public Document Room (PDR) reference staff at 1-800-397-4209, 301-415-4737, or by email to pdr.resource@nrc.gov. NUREG-1556, Volumes 12, 14, and 21, Revision 1, are located in ADAMS under Accession Numbers ML18136A704, ML18120A129, and ML18143A670, respectively. These documents are also available on the NRCs public website at http://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1556/ under Consolidated Guidance about Materials Licenses (NUREG-1556).

  • NRCs PDR: You may examine and purchase copies of public documents at the NRCs PDR, Room O1-F21, One White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852.

FOR FURTHER INFORMATION CONTACT:

Anthony McMurtray, Office of Nuclear Material Safety and Safeguards, U.S.

Nuclear Regulatory Commission, Washington, DC 20555-0001; telephone:

301-415-2746; email:

Anthony.McMurtray@nrc.gov.

SUPPLEMENTARY INFORMATION:

I. Discussion The NRC issued revisions to NUREG-1556, Volumes 12, 14, and 21, to provide guidance to existing materials licensees covered under these types of licenses and to applicants preparing an application for one of these types of materials licenses. These NUREG volumes also provide the NRC staff with criteria for evaluating these types of license applications. The purpose of this notice is to notify the public that the NUREG-1556 volumes listed in this Federal Register notice were issued as final reports.

II. Additional Information The NRC published notices of the availability of the draft report for comment in the Federal Register for NUREG-1556, Volume 12, Revision 1 on July 13, 2016 (81 FR 45308),

NUREG-1556, Volume 14, Revision 1 on June 11, 2014 (79 FR 33600), and NUREG-1556, Volume 21, Revision 1 on December 16, 2016 (81 FR 91206).

Each of these volumes were published for a public comment period that was at least 30 days. The public comment period for Volume 12 closed on August 26, 2016, for Volume 14 on July 11, 2014, and for Volume 21 on February 24, 2017. Public comments and the NRC staff responses to the public comments for NUREG-1556, Volume 12, Revision 1 are available under ADAMS Accession No. ML18010B155. Public comments and the NRC staff responses to the public comments for NUREG-1556, Volume 14, Revision 1 are available under ADAMS Accession No. ML18023B550. Public comments and the NRC staff responses to the public comments for NUREG-1556, Volume 21, Revision 1 are available under ADAMS Accession No. ML17334A206.

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31193 Federal Register / Vol. 83, No. 128 / Tuesday, July 3, 2018 / Notices participant can then submit adjudicatory documents. Submissions must be in Portable Document Format (PDF). Additional guidance on PDF submissions is available on the NRCs public website at http://www.nrc.gov/

site-help/electronic-sub-ref-mat.html. A filing is considered complete at the time the document is submitted through the NRCs E-Filing system. To be timely, an electronic filing must be submitted to the E-Filing system no later than 11:59 p.m. Eastern Time on the due date.

Upon receipt of a transmission, the E-Filing system time-stamps the document and sends the submitter an email notice confirming receipt of the document. The E-Filing system also distributes an email notice that provides access to the document to the NRCs Office of the General Counsel and any others who have advised the Office of the Secretary that they wish to participate in the proceeding, so that the filer need not serve the document on those participants separately. Therefore, applicants and other participants (or their counsel or representative) must apply for and receive a digital ID certificate before adjudicatory documents are filed so that they can obtain access to the documents via the E-Filing system.

A person filing electronically using the NRCs adjudicatory E-Filing system may seek assistance by contacting the NRCs Electronic Filing Help Desk through the Contact Us link located on the NRCs public website at http://

www.nrc.gov/site-help/e-submittals.html, by email to MSHD.Resource@nrc.gov, or by a toll-free call at 1-866-672-7640. The NRC Electronic Filing Help Desk is available between 9 a.m. and 6 p.m., Eastern Time, Monday through Friday, excluding government holidays.

Participants who believe that they have a good cause for not submitting documents electronically must file an exemption request, in accordance with 10 CFR 2.302(g), with their initial paper filing stating why there is good cause for not filing electronically and requesting authorization to continue to submit documents in paper format. Such filings must be submitted by: (1) First class mail addressed to the Office of the Secretary of the Commission, U.S.

Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention:

Rulemaking and Adjudications Staff; or (2) courier, express mail, or expedited delivery service to the Office of the Secretary, 11555 Rockville Pike, Rockville, Maryland 20852, Attention:

Rulemaking and Adjudications Staff.

Participants filing adjudicatory documents in this manner are responsible for serving the document on all other participants. Filing is considered complete by first-class mail as of the time of deposit in the mail, or by courier, express mail, or expedited delivery service upon depositing the document with the provider of the service. A presiding officer, having granted an exemption request from using E-Filing, may require a participant or party to use E-Filing if the presiding officer subsequently determines that the reason for granting the exemption from use of E-Filing no longer exists.

Documents submitted in adjudicatory proceedings will appear in the NRCs electronic hearing docket which is available to the public at https://

adams.nrc.gov/ehd, unless excluded pursuant to an order of the Commission or the presiding officer. If you do not have an NRC-issued digital ID certificate as described above, click cancel when the link requests certificates and you will be automatically directed to the NRCs electronic hearing dockets where you will be able to access any publicly available documents in a particular hearing docket. Participants are requested not to include personal privacy information, such as social security numbers, home addresses, or personal phone numbers in their filings, unless an NRC regulation or other law requires submission of such information. For example, in some instances, individuals provide home addresses in order to demonstrate proximity to a facility or site. With respect to copyrighted works, except for limited excerpts that serve the purpose of the adjudicatory filings and would constitute a Fair Use application, participants are requested not to include copyrighted materials in their submission.

Duke Energy Carolinas, LLC, Docket Nos. 50-269, 50-270, and 50-287, Oconee Nuclear Station, Unit Nos. 1, 2, and 3, Oconee County, South Carolina Date of amendment request: October 20, 2017. A publicly-available version is in ADAMS under Accession No. ML17299A125.

Description of amendment request:

This amendment request contains sensitive unclassified non-safeguards information (SUNSI). The amendments would revise the Updated Final Safety Analysis Report (UFSAR) to provide off-nominal success criteria for maintaining the reactor in a safe shutdown condition when using the Standby Shutdown Facility (SSF) to mitigate a Turbine Building (TB) flood occurring when an Oconee Nuclear Station unit is not at nominal full power conditions. The amendments would also revise the UFSAR to allow the use of the Main Steam (MS) Atmospheric Dump Valves (ADVs), when available, to enhance SSF mitigation capabilities.

Basis for proposed no significant hazards consideration determination:

As required by 10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below:

1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?

Response: No.

The proposed change provides off-nominal success criteria for SSF mitigated TB flood events occurring during off-nominal initial conditions. The proposed change does not impact the current success criteria for SSF events occurring during nominal full power initial conditions. The LAR [license amendment request] also requests NRC approval to use the MS ADVs, when available, to enhance SSF mitigation capabilities. The proposed change does not adversely impact containment integrity, radiological release pathways, fuel design, filtration systems, main steam relief valve set points, or radwaste systems. No new radiological release pathways are created.

During licensing of the SSF design, SSF performance was evaluated assuming the events that were to be mitigated by the SSF were initiated from nominal full power conditions. Duke Energy analyses demonstrate that SSF mitigated Turbine Building flood events occurring during off-nominal full power conditions can be mitigated acceptably when the proposed off-nominal success criteria are met. As such, the proposed change does not have a significant impact on the dose consequences of an accident previously evaluated. The SSF is not an event initiator; therefore, it does not affect the frequency of occurrence of accidents previously evaluated in the UFSAR. The use of off-nominal success criteria is not a precursor to a TB flood event; therefore, the proposed change does not involve a significant increase in the probability of any event requiring operation of the SSF. The proposed off-nominal success criteria will continue to ensure the SSF can maintain the unit(s) in a safe shutdown condition. As such, the proposed change does not involve a significant increase in the consequences of any event requiring operation of the SSF.

2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?

Response: No.

The proposed UFSAR change requests approval to modify the SSF licensing basis for off-nominal conditions by using off-nominal success criteria for SSF mitigated TB flood events occurring during off-nominal conditions. Duke Energy analyses demonstrate that meeting the off-nominal success criteria is an acceptable method of mitigating the TB flood event and does not create the possibility of a new or different VerDate Sep<11>2014 17:07 Jul 02, 2018 Jkt 244001 PO 00000 Frm 00077 Fmt 4703 Sfmt 4703 E:\\FR\\FM\\03JYN1.SGM 03JYN1 sradovich on DSK3GMQ082PROD with NOTICES

31194 Federal Register / Vol. 83, No. 128 / Tuesday, July 3, 2018 / Notices kind of accident. The LAR also requests NRC approval to use the main steam atmospheric dump valves, when available, to enhance the mitigation of SSF events. The proposed change does not change the design function or operation of the SSF. The SSF is designed with the capability to mitigate a TB flood and meet specific success criteria for the entire 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> mission time. These changes do not adversely affect this mission time.

The proposed change does not create the possibility of a new or different kind of accident since the proposed change does not introduce credible new failure mechanisms, malfunctions, or accident initiators not considered in the design and licensing bases.

3. Does the proposed amendment involve a significant reduction in a margin of safety?

Response: No.

The proposed change requests approval of an off-nominal set of success criteria for SSF mitigated TB flood events occurring during off-nominal power conditions. Duke Energy analyses demonstrate there is adequate margin to prevent lift of pressurizer safety valves while water-solid. The proposed change does not involve operating installed equipment (ADVs) in a new or different manner. The ADVs are periodically tested and have been used successfully for a plant cooldown. Use of the ADVs to enhance the mitigation of SSF events serves to improve plant safety by preventing the pressurizer from reaching water-solid conditions and by reducing the pressure at which the MS system is controlled. ADV use also allows plant stabilization to occur more quickly and at lower temperatures, and eliminates repeated cycling of the MS relief valves. The proposed change does not involve a change to any set points for parameters which initiate protective or mitigation action and does not have any impact on the fission product barriers or safety limits. Therefore, the proposed change does not involve a significant reduction in a margin of safety.

The NRC staff has reviewed the licensees analysis and, based on this review, it appears that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the amendment request involves no significant hazards consideration.

Attorney for licensee: Kate Nolan, Deputy General Counsel, Duke Energy Carolinas, 550 South Tryon Street, Charlotte, North Carolina 28202.

NRC Branch Chief: Michael T.

Markley.

NextEra Energy Duane Arnold, LLC, Docket No. 50-331, Duane Arnold Energy Center, Linn County, Iowa Date of amendment request:

December 15, 2017. A publicly-available version is in ADAMS under Accession No. ML17352A335.

Description of amendment request:

This amendment request contains sensitive unclassified non-safeguards information (SUNSI). The amendment would modify Technical Specification (TS) 3.6.1.7, Suppression Chamber-to-Drywell Vacuum Breakers, by revising the required number of operable vacuum breakers for opening from six to five.

Basis for proposed no significant hazards consideration determination:

As required by 10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below:

1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?

Response: No.

Operable suppression chamber-to-drywell vacuum breakers are required for accident mitigation. Failure of the vacuum breakers is not assumed as an accident initiator for any accident previously evaluated. Therefore, any potential failure of a vacuum breaker to perform when necessary will not affect the probability of an accident previously evaluated.

The proposed change maintains a sufficient number of operable vacuum breakers to meet the limiting design basis accident conditions. The consequences of an accident previously evaluated while utilizing the proposed change are no different than the consequences of an accident prior to the proposed change. As a result, the consequences of an accident previously evaluated are not significantly increased

[sic].

Therefore, the proposed TS change does not involve an increase in the probability or consequences of a previously evaluated accident.

2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?

Response: No.

The proposed change does not alter the protection system design, create new failure modes, or change any modes of operation.

The proposed change does not involve a physical alteration of the plant; and no new or different kind of equipment will be installed. Consequently, there are no new initiators that could result in a new or different kind of accident.

Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.

3. Does the proposed change involve a significant reduction in a margin of safety?

Response: No.

The proposed change to the minimum number of operable suppression chamber-to-drywell vacuum breakers for opening ensures that an excessive negative differential pressure between the suppression chamber and the drywell will be prevented during the most limiting postulated design-basis event.

The minimum number of operable suppression chamber-to-drywell vacuum breakers for opening is set appropriately to ensure adequate margin based on the number of available vacuum breakers not having an effect on the containment system analysis report. Therefore, the proposed change does not involve a significant reduction in a margin of safety.

The NRC staff has reviewed the licensees analysis and, based on this review, it appears that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the amendment request involves no significant hazards consideration.

Attorney for licensee: William Blair, P.O. Box 14000, Juno Beach, Florida 33408-0420.

NRC Branch Chief: David J. Wrona.

Union Electric Company, Docket No.

50-483, Callaway Plant, Unit No. 1, Callaway County, Missouri Date of amendment request: March 9, 2018. A publicly-available version is in ADAMS under Package Accession No. ML18068A685.

Description of amendment request:

This amendment request contains sensitive unclassified non-safeguards information (SUNSI). The amendment would revise the Technical Specifications (TSs) to add TS 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System, to the Callaway Plant TSs. This proposed change would enhance the capability of one Class 1E electrical equipment A/C train to provide adequate area cooling for both trains of Class 1E electrical equipment during normal and accident conditions.

Basis for proposed no significant hazards consideration determination:

As required by 10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below:

1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?

Response: No.

The safety-related Class 1E Electrical Equipment A/C system is designed to perform its area cooling function for the Class 1E electrical equipment during normal and accident conditions. Since the supported Class 1E electrical equipment is utilized and required to be available for accident mitigation, the Class 1E Electrical Equipment A/C system performs an accident mitigation function. The system itself, however, is not involved in the initiation of accidents previously evaluated in the FSAR [Final Safety Analysis Report]. That is, failure of the Class 1E Electrical Equipment A/C system itself is not an initiator of such accidents, and consequently, the proposed addition of TS 3.7.20 does not involve an increase in the probability of an accident previously evaluated.

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