ML15173A007

NRR E-mail Capture - NRC Notification of State of Florida Regarding St. Lucie License Amendment - Remove RCS Chemistry from Technical Specifications

ML15173A007
Person / Time
Site:	Saint Lucie
Issue date:	06/19/2015
From:	Audrey Klett Plant Licensing Branch II
To:	Becker C State of FL, Dept of Health
References
Download: ML15173A007 (16)

Text

NRR-PMDAPEm Resource From: Klett, Audrey Sent: Friday, June 19, 2015 1:54 PM To: Becker, Cindy L (Cindy.Becker@flhealth.gov)

Cc: Buckberg, Perry; Saba, Farideh

Subject:

NRC Notification of State of Florida Regarding St. Lucie License Amendment - Remove RCS Chemistry from Technical Specifications Attachments: 79 FR 64225.pdf Good Afternoon Ms. Becker, The U.S. Nuclear Regulatory Commission (NRC) is about to issue license amendments for the St. Lucie Nuclear Plant, Units 1 and 2. In accordance with Title 10 of the Code of Federal Regulations, Section 50.91(b), I am notifying you of the proposed issuance of these amendments.

Please reply if the State of Florida has comments on the following licensing action submitted to the NRC by Florida Power & Light Company, et al. (the licensee): Application for Technical Specification Change to Remove RCS Chemistry Requirements and Relocate to Licensee-Controlled Documents, dated August 8, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14225A654).

Attached is the associated proposed no significant hazards consideration for this amendment request that was published in the Federal Register on October 28, 2014 (79 FR 64225, see attached).

Your response is requested by June 26, 2015. If you have any questions, please call me at (301) 415-0489.

Thank you, Audrey Klett Project Manager NRR/DORL/LPLII-2 301-415-0489 1

Hearing Identifier: NRR_PMDA Email Number: 2161 Mail Envelope Properties (Audrey.Klett@nrc.gov20150619135300)

Subject:

NRC Notification of State of Florida Regarding St. Lucie License Amendment -

Remove RCS Chemistry from Technical Specifications Sent Date: 6/19/2015 1:53:57 PM Received Date: 6/19/2015 1:53:00 PM From: Klett, Audrey Created By: Audrey.Klett@nrc.gov Recipients:

"Buckberg, Perry" <Perry.Buckberg@nrc.gov>

Tracking Status: None "Saba, Farideh" <Farideh.Saba@nrc.gov>

Tracking Status: None "Becker, Cindy L (Cindy.Becker@flhealth.gov)" <Cindy.Becker@flhealth.gov>

Tracking Status: None Post Office:

Files Size Date & Time MESSAGE 1147 6/19/2015 1:53:00 PM 79 FR 64225.pdf 284486 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received:

Federal Register / Vol. 79, No. 208 / Tuesday, October 28, 2014 / Notices 64219 NATIONAL ARCHIVES AND RECORDS NARA is soliciting comments ACTION: Biweekly notice.

ADMINISTRATION concerning the following information collection:

SUMMARY

Pursuant to Section 189a. (2)

[NARA-2015-006]

Title:

Request Pertaining to Military of the Atomic Energy Act of 1954, as Agency Information Collection Records. amended (the Act), the U.S. Nuclear Activities: Proposed Collection; OMB number: 3095-0029. Regulatory Commission (NRC) is Comment Request Agency form number: SF 180. publishing this regular biweekly notice.

Type of review: Regular.

The Act requires the Commission to AGENCY: National Archives and Records Affected public: Veterans, their Administration (NARA). authorized representatives, state and publish notice of any amendments local governments, and businesses. issued, or proposed to be issued and ACTION: Notice.

Estimated number of respondents: grants the Commission the authority to

SUMMARY

NARA is giving public notice 1,028,769. issue and make immediately effective that the agency proposes to request Estimated time per response: 5 any amendment to an operating license extension of a currently approved minutes. or combined license, as applicable, information collection used when Frequency of response: On occasion upon a determination by the veterans or other authorized individuals (when respondent wishes to request Commission that such amendment request information from or copies of information from a military personnel involves no significant hazards documents in military service records. record). consideration, notwithstanding the The public is invited to comment on the Estimated total annual burden hours: pendency before the Commission of a proposed information collection 85,731 hours30.458 days <br />4.351 weeks <br />1.001 months <br />. request for a hearing from any person.

pursuant to the Paperwork Reduction Abstract: The authority for this Act of 1995. This biweekly notice includes all information collection is contained in notices of amendments issued, or DATES: Written comments must be 36 CFR 1233.18(d). In accordance with rules issued by the Department of proposed to be issued from October 2, received on or before December 29, 2014 to be assured of consideration. Defense (DOD) and Department of 2014 to October 15, 2014. The last Homeland Security (DHS, US Coast biweekly notice was published on ADDRESSES: Comments should be sent Guard), the National Personnel Records October 14, 2014.

to: Paperwork Reduction Act Comments (ISP), Room 4400, National Archives Center (NPRC) of the National Archives DATES: Comments must be filed by and Records Administration, 8601 and Records Administration (NARA) November 28, 2014. A request for a Adelphi Rd, College Park, MD 20740- administers military service records of hearing must be filed by December 29, 6001; or faxed to 301-713-7409; or veterans after discharge, retirement, and 2014.

electronically mailed to death. When veterans and other tamee.fechhelm@nara.gov. authorized individuals request ADDRESSES: You may submit comments information from or copies of by any of the following methods (unless FOR FURTHER INFORMATION CONTACT: this document describes a different documents in military service records, Requests for additional information or method for submitting comments on a they must provide in forms or in letters copies of the proposed information specific subject):

certain information about the veteran collections and supporting statements and the nature of the request. Federal

• Federal Rulemaking Web site: Go to should be directed to Tamee Fechhelm agencies, military departments, http://www.regulations.gov and search at telephone number 301-837-1694, or veterans, veterans organizations, and for Docket ID NRC-2014-0239. Address fax number 301-713-7409.

the general public use Standard Forms questions about NRC dockets to Carol SUPPLEMENTARY INFORMATION: Pursuant (SF) 180, Request Pertaining to Military Gallagher; telephone: 301-287-3422; to the Paperwork Reduction Act of 1995 Records, in order to obtain information (Pub. L. 104-13), NARA invites the email: Carol.Gallagher@nrc.gov. For from military service records stored at technical questions, contact the general public and other Federal NPRC. Veterans and next-of-kin of agencies to comment on proposed individual listed in the FOR FURTHER deceased veterans can also use eVetRecs information collections. The comments INFORMATION CONTACT section of this (http://www.archives.gov/

and suggestions should address one or document.

research_room/vetrecs/) to order copies.

more of the following points: (a)

• Mail comments to: Cindy Bladey, Whether the proposed collection Dated: October 20, 2014.

Office of Administration, Mail Stop:

information is necessary for the proper Swarnali Haldar, 3WFN-06-A44M, U.S. Nuclear performance of the functions of NARA; Executive for Information Services/CIO.

Regulatory Commission, Washington, (b) the accuracy of NARAs estimate of [FR Doc. 2014-25581 Filed 10-27-14; 8:45 am] DC 20555-0001.

the burden of the proposed information BILLING CODE 7515-01-P collections; (c) ways to enhance the For additional direction on obtaining quality, utility, and clarity of the information and submitting comments, information to be collected; and (d) see Obtaining Information and NUCLEAR REGULATORY ways to minimize the burden of the COMMISSION Submitting Comments in the collection of information on SUPPLEMENTARY INFORMATION section of respondents, including the use of [NRC-2014-0239] this document.

asabaliauskas on DSK4SPTVN1PROD with NOTICES information technology; and (e) whether Biweekly Notice; Applications and FOR FURTHER INFORMATION CONTACT:

small businesses are affected by this Amendments to Facility Operating Shirley Rohrer, Office of Nuclear collection. The comments that are Licenses and Combined Licenses Reactor Regulation, U.S. Nuclear submitted will be summarized and Involving No Significant Hazards Regulatory Commission, Washington, included in the NARA request for Office Considerations DC 20555-0001; telephone: 301-415-of Management and Budget (OMB) 5411, email: Shirley.Rohrer@nrc.gov approval. All comments will become a AGENCY:Nuclear Regulatory matter of public record. In this notice, Commission. SUPPLEMENTARY INFORMATION:

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64220 Federal Register / Vol. 79, No. 208 / Tuesday, October 28, 2014 / Notices I. Obtaining Information and entering the comment submissions into and a petition to intervene with respect Submitting Comments ADAMS. to issuance of the amendment to the subject facility operating license or A. Obtaining Information II. Notice of Consideration of Issuance combined license. Requests for a of Amendments to Facility Operating Please refer to Docket ID NRC-2014- hearing and a petition for leave to Licenses and Combined Licenses and 0239 when contacting the NRC about intervene shall be filed in accordance Proposed No Significant Hazards the availability of information for this with the Commissions Agency Rules Consideration Determination action. You may obtain publicly- of Practice and Procedure in 10 CFR available information related to this The Commission has made a Part 2. Interested person(s) should action by any of the following methods: proposed determination that the consult a current copy of 10 CFR 2.309,

• Federal Rulemaking Web site: Go to following amendment requests involve which is available at the NRCs PDR, http://www.regulations.gov and search no significant hazards consideration. located at One White Flint North, Room for Docket ID NRC-2014-0239. Under the Commissions regulations in O1-F21, 11555 Rockville Pike (first

• NRCs Agencywide Documents § 50.92 of Title 10 of the Code of Federal floor), Rockville, Maryland 20852. The Access and Management System Regulations (10 CFR), this means that NRCs regulations are accessible (ADAMS): You may obtain publicly- operation of the facility in accordance electronically from the NRC Library on available documents online in the with the proposed amendment would the NRCs Web site at http://

ADAMS Public Documents collection at not (1) involve a significant increase in www.nrc.gov/reading-rm/doc-http://www.nrc.gov/reading-rm/ the probability or consequences of an collections/cfr/. If a request for a hearing adams.html. To begin the search, select accident previously evaluated, or (2) or petition for leave to intervene is filed create the possibility of a new or by the above date, the Commission or a ADAMS Public Documents and then different kind of accident from any presiding officer designated by the select Begin Web-based ADAMS accident previously evaluated; or (3) Commission or by the Chief Search. For problems with ADAMS, involve a significant reduction in a Administrative Judge of the Atomic please contact the NRCs Public margin of safety. The basis for this Safety and Licensing Board Panel, will Document Room (PDR) reference staff at proposed determination for each rule on the request and/or petition; and 1-800-397-4209, 301-415-4737, or by amendment request is shown below. the Secretary or the Chief email to pdr.resource@nrc.gov. The The Commission is seeking public ADAMS accession number for each Administrative Judge of the Atomic comments on this proposed Safety and Licensing Board will issue a document referenced (if it is available in determination. Any comments received ADAMS) is provided the first time that notice of a hearing or an appropriate within 30 days after the date of order.

it is mentioned in the SUPPLEMENTARY publication of this notice will be As required by 10 CFR 2.309, a INFORMATION section.

considered in making any final petition for leave to intervene shall set

• NRCs PDR: You may examine and determination. forth with particularity the interest of purchase copies of public documents at Normally, the Commission will not the petitioner in the proceeding, and the NRCs PDR, Room O1-F21, One issue the amendment until the how that interest may be affected by the White Flint North, 11555 Rockville expiration of 60 days after the date of results of the proceeding. The petition Pike, Rockville, Maryland 20852. publication of this notice. The should specifically explain the reasons B. Submitting Comments Commission may issue the license why intervention should be permitted amendment before expiration of the 60- with particular reference to the Please include Docket ID NRC-2014- day period provided that its final following general requirements: (1) The 0239 in the subject line of your determination is that the amendment name, address, and telephone number of comment submission, in order to ensure involves no significant hazards the requestor or petitioner; (2) the that the NRC is able to make your consideration. In addition, the nature of the requestors/petitioners comment submission available to the Commission may issue the amendment right under the Act to be made a party public in this docket. prior to the expiration of the 30-day to the proceeding; (3) the nature and The NRC cautions you not to include comment period should circumstances extent of the requestors/petitioners identifying or contact information that change during the 30-day comment property, financial, or other interest in you do not want to be publicly period such that failure to act in a the proceeding; and (4) the possible disclosed in your comment submission. timely way would result, for example in effect of any decision or order which The NRC posts all comment derating or shutdown of the facility. may be entered in the proceeding on the submissions at http:// Should the Commission take action requestors/petitioners interest. The www.regulations.gov as well as entering prior to the expiration of either the petition must also identify the specific the comment submissions into ADAMS. comment period or the notice period, it contentions which the requestor/

The NRC does not routinely edit will publish in the Federal Register a petitioner seeks to have litigated at the comment submissions to remove notice of issuance. Should the proceeding.

identifying or contact information. Commission make a final No Significant Each contention must consist of a If you are requesting or aggregating Hazards Consideration Determination, specific statement of the issue of law or comments from other persons for any hearing will take place after fact to be raised or controverted. In submission to the NRC, then you should issuance. The Commission expects that addition, the requestor/petitioner shall inform those persons not to include provide a brief explanation of the bases asabaliauskas on DSK4SPTVN1PROD with NOTICES the need to take this action will occur identifying or contact information that very infrequently. for the contention and a concise they do not want to be publicly statement of the alleged facts or expert disclosed in their comment submission. A. Opportunity To Request a Hearing opinion which support the contention Your request should state that the NRC and Petition for Leave To Intervene and on which the requestor/petitioner does not routinely edit comment Within 60 days after the date of intends to rely in proving the contention submissions to remove such information publication of this notice, any person(s) at the hearing. The requestor/petitioner before making the comment whose interest may be affected by this must also provide references to those submissions available to the public or action may file a request for a hearing specific sources and documents of VerDate Sep<11>2014 20:06 Oct 27, 2014 Jkt 235001 PO 00000 Frm 00058 Fmt 4703 Sfmt 4703 E:\FR\FM\28OCN1.SGM 28OCN1

Federal Register / Vol. 79, No. 208 / Tuesday, October 28, 2014 / Notices 64221 which the petitioner is aware and on To comply with the procedural complete at the time the documents are which the requestor/petitioner intends requirements of E-Filing, at least ten 10 submitted through the NRCs E-Filing to rely to establish those facts or expert days prior to the filing deadline, the system. To be timely, an electronic opinion. The petition must include participant should contact the Office of filing must be submitted to the E-Filing sufficient information to show that a the Secretary by email at system no later than 11:59 p.m. Eastern genuine dispute exists with the hearing.docket@nrc.gov, or by telephone Time on the due date. Upon receipt of applicant on a material issue of law or at 301-415-1677, to request (1) a digital a transmission, the E-Filing system fact. Contentions shall be limited to identification (ID) certificate, which time-stamps the document and sends matters within the scope of the allows the participant (or its counsel or the submitter an email notice amendment under consideration. The representative) to digitally sign confirming receipt of the document. The contention must be one which, if documents and access the E-Submittal E-Filing system also distributes an email proven, would entitle the requestor/ server for any proceeding in which it is notice that provides access to the petitioner to relief. A requestor/ participating; and (2) advise the document to the NRCs Office of the petitioner who fails to satisfy these Secretary that the participant will be General Counsel and any others who requirements with respect to at least one submitting a request or petition for have advised the Office of the Secretary contention will not be permitted to hearing (even in instances in which the that they wish to participate in the participate as a party. participant, or its counsel or proceeding, so that the filer need not Those permitted to intervene become representative, already holds an NRC- serve the documents on those parties to the proceeding, subject to any issued digital ID certificate). Based upon participants separately. Therefore, limitations in the order granting leave to this information, the Secretary will applicants and other participants (or intervene, and have the opportunity to establish an electronic docket for the their counsel or representative) must participate fully in the conduct of the hearing in this proceeding if the apply for and receive a digital ID hearing. Secretary has not already established an certificate before a hearing request/

If a hearing is requested, the electronic docket. petition to intervene is filed so that they Commission will make a final Information about applying for a can obtain access to the document via determination on the issue of no digital ID certificate is available on the the E-Filing system.

significant hazards consideration. The NRCs public Web site at http:// A person filing electronically using final determination will serve to decide www.nrc.gov/site-help/e-submittals/ the NRCs adjudicatory E-Filing system when the hearing is held. If the final getting-started.html. System may seek assistance by contacting the determination is that the amendment requirements for accessing the E- NRC Meta System Help Desk through request involves no significant hazards Submittal server are detailed in the the Contact Us link located on the consideration, the Commission may NRCs Guidance for Electronic NRCs public Web site at http://

issue the amendment and make it Submission, which is available on the www.nrc.gov/site-help/e-immediately effective, notwithstanding agencys public Web site at http:// submittals.html, by email to the request for a hearing. Any hearing www.nrc.gov/site-help/e- MSHD.Resource@nrc.gov, or by a toll-held would take place after issuance of submittals.html. Participants may free call at 1-866-672-7640. The NRC the amendment. If the final attempt to use other software not listed Meta System Help Desk is available determination is that the amendment on the Web site, but should note that the between 8 a.m. and 8 p.m., Eastern request involves a significant hazards NRCs E-Filing system does not support Time, Monday through Friday, consideration, then any hearing held unlisted software, and the NRC Meta excluding government holidays.

would take place before the issuance of System Help Desk will not be able to Participants who believe that they any amendment unless the Commission offer assistance in using unlisted have a good cause for not submitting finds an imminent danger to the health software. documents electronically must file an or safety of the public, in which case it If a participant is electronically exemption request, in accordance with will issue an appropriate order or rule submitting a document to the NRC in 10 CFR 2.302(g), with their initial paper under 10 CFR Part 2. accordance with the E-Filing rule, the filing requesting authorization to participant must file the document continue to submit documents in paper B. Electronic Submissions (E-Filing) using the NRCs online, Web-based format. Such filings must be submitted All documents filed in NRC submission form. In order to serve by: (1) First class mail addressed to the adjudicatory proceedings, including a documents through the Electronic Office of the Secretary of the request for hearing, a petition for leave Information Exchange System, users Commission, U.S. Nuclear Regulatory to intervene, any motion or other will be required to install a Web Commission, Washington, DC 20555-document filed in the proceeding prior browser plug-in from the NRCs Web 0001, Attention: Rulemaking and to the submission of a request for site. Further information on the Web- Adjudications Staff; or (2) courier, hearing or petition to intervene, and based submission form, including the express mail, or expedited delivery documents filed by interested installation of the Web browser plug-in, service to the Office of the Secretary, governmental entities participating is available on the NRCs public Web Sixteenth Floor, One White Flint North, under 10 CFR 2.315(c), must be filed in site at http://www.nrc.gov/site-help/e- 11555 Rockville Pike, Rockville, accordance with the NRCs E-Filing rule submittals.html. Maryland 20852, Attention: Rulemaking (72 FR 49139; August 28, 2007). The E- Once a participant has obtained a and Adjudications Staff. Participants Filing process requires participants to digital ID certificate and a docket has filing a document in this manner are asabaliauskas on DSK4SPTVN1PROD with NOTICES submit and serve all adjudicatory been created, the participant can then responsible for serving the document on documents over the internet, or in some submit a request for hearing or petition all other participants. Filing is cases to mail copies on electronic for leave to intervene. Submissions considered complete by first-class mail storage media. Participants may not should be in Portable Document Format as of the time of deposit in the mail, or submit paper copies of their filings (PDF) in accordance with NRC guidance by courier, express mail, or expedited unless they seek an exemption in available on the NRCs public Web site delivery service upon depositing the accordance with the procedures at http://www.nrc.gov/site-help/e- document with the provider of the described below. submittals.html. A filing is considered service. A presiding officer, having VerDate Sep<11>2014 20:06 Oct 27, 2014 Jkt 235001 PO 00000 Frm 00059 Fmt 4703 Sfmt 4703 E:\FR\FM\28OCN1.SGM 28OCN1

64222 Federal Register / Vol. 79, No. 208 / Tuesday, October 28, 2014 / Notices granted an exemption request from Conditions. This amendment also shutdown of the reactor, are not applicable using E-Filing, may require a participant proposes to extensively revise the CR- to a plant in a permanently defueled or party to use E-Filing if the presiding 3 Improved Technical Specifications condition. The third criterion is related to preventing or mitigating the consequences of officer subsequently determines that the (ITS) in order to create the CR-3 accidents that could result in potential offsite reason for granting the exemption from Permanently Defueled Technical exposures exceeding limits. However, after use of E-Filing no longer exists. Specifications (PDTS). the termination of reactor operations at CR-Documents submitted in adjudicatory Basis for proposed no significant 3 and the permanent removal of the fuel from proceedings will appear in the NRCs hazards consideration determination: the reactor vessel (following 4 years of decay electronic hearing docket which is As required by 10 CFR 50.91(a), the time after shutdown) and purging of the available to the public at http:// licensee has provided its analysis of the contents of the waste gas decay tanks, none ehd1.nrc.gov/ehd/, unless excluded issue of no significant hazards of the SSCs at CR-3 are required to be relied pursuant to an order of the Commission, consideration, which is presented on for accident mitigation. Therefore, none of or the presiding officer. Participants are the SSCs at CR-3 meet the definition of a below: safety-related SSC stated in 10 CFR 50.2 requested not to include personal 1. Does the proposed amendment involve (with the exception of the passive spent fuel privacy information, such as social a significant increase in the probability or pool structure).

security numbers, home addresses, or consequences of an accident previously The deletion of ITS definitions and rules home phone numbers in their filings, evaluated? of usage and application, that are currently unless an NRC regulation or other law Response: No. not applicable in a defueled condition, has requires submission of such CR-3 has permanently ceased operation. no impact on facility SSCs or the methods of information. However, a request to The proposed amendment would modify the operation of such SSCs. The deletion of intervene will require including CR-3 FOL and ITS by proposing to delete design features and safety limits not information on local residence in order certain License Conditions (LCs) and ITS that applicable to the permanently shutdown and are no longer applicable to a permanently defueled status of CR-3 has no impact on the to demonstrate a proximity assertion of defueled facility, while modifying the remaining DBA [design basis accidents] (the interest in the proceeding. With respect remaining portions to correspond to the Fuel Handling Accident in the Auxiliary to copyrighted works, except for limited permanently shutdown condition. Changes Building) or the proposed Radioactive Waste excerpts that serve the purpose of the proposed to LCs will make them consistent Handling Accident. The removal of LCOs adjudicatory filings and would with the non-operating status of CR-3. Other [Limiting Conditions for Operation] or SRs constitute a Fair Use application, proposed LCs changes will eliminate LCs that [Surveillance Requirements] that are related participants are requested not to include were designed for one time implementation only to the operation of the nuclear reactor copyrighted materials in their and have been satisfied, or are no longer or accidents do not affect mitigation of the submission. required due to changes to Part 50 or Part 73 applicable DBAs previously evaluated since Petitions for leave to intervene must regulations that accomplish the same result these DBAs are no longer applicable in the be filed no later than 60 days from the or eliminate the requirement for the LC. The defueled mode. The safety functions proposed changes to the ITS are consistent involving core reactivity control, reactor heat date of publication of this notice. with the criteria set forth in 10 CFR 50.36 for removal, reactor coolant system inventory Requests for hearing, petitions for leave the contents of ITS. control, and containment integrity are no to intervene, and motions for leave to Chapter 14 of the CR-3 Final Safety longer applicable at CR-3 as a permanently file new or amended contentions that Analysis Report (FSAR) described the design defueled plant. The analyzed accidents are filed after the 60-day deadline will basis accident (DBA) and transient scenarios involving damage to the reactor coolant not be entertained absent a applicable to CR-3 during power operations. system, main steam lines, reactor core, and determination by the presiding officer With the reactor in a permanently defueled the subsequent release of radioactive material that the filing demonstrates good cause condition, the spent fuel pool and its cooling are no longer possible at CR-3 by satisfying the three factors in 10 CFR systems are dedicated only to spent fuel Since CR-3 has permanently ceased storage. In this condition, the spectrum of operation, the generation of fission products 2.309(c)(1)(i)-(iii). credible accidents is much smaller than for has ceased and the remaining source term For further details with respect to an operational plant. As a result of the will decay. The radioactive decay of the these license amendment applications, certifications submitted by CR-3 in irradiated fuel since shutdown of the reactor see the application for amendment accordance with 10 CFR 50.82(a)(1), and the have reduced the consequences of the Fuel which is available for public inspection consequent removal of authorization to Handling Accident (FHA) to levels well in ADAMS and at the NRCs PDR. For operate the reactor or to place or retain fuel below those previously analyzed. The additional direction on accessing in the reactor vessel in accordance with 10 relevant parameter (water level) associated information related to this document, CFR 50.82(a)(2), the majority of the accident with the fuel pool provides an initial see the Obtaining Information and scenarios originally postulated in the FSAR condition for the FHA analysis and is Submitting Comments section of this are no longer possible and have been included in the PDTS.

removed from the FSAR under 10 CFR 50.59. The spent fuel pool water level, spent fuel document. The definition of safety-related structures, pool boron concentration, and spent fuel Duke Energy Florida, Inc. et al. (DEF), systems, and components (SSCs) in 10 CFR pool storage LCOs are retained to preserve Docket No. 50-302, Crystal River, Unit 50.2 states that safety-related SSCs are those the current requirements for safe storage of 3, Nuclear Generating Plant (CR-3), relied on to remain functional during and irradiated fuel.

following design basis events to assure: Fuel pool cooling and makeup related Citrus County, Florida 1. The integrity of the reactor coolant equipment and support equipment (e.g.,

Date of amendment request: October boundary; electrical power systems) are not required to 29, 2013, as supplemented by letters 2. The capability to shutdown the reactor be continuously available since there is dated May 7, 2014 and June 17, 2014. and maintain it in a safe shutdown condition; sufficient time to effect repairs, establish asabaliauskas on DSK4SPTVN1PROD with NOTICES Publicly-available versions are in or alternate sources of makeup flow, or establish ADAMS under Accession Nos. 3. The capability to prevent or mitigate the alternate sources of cooling in the event of a consequences of accidents which could loss of cooling and makeup flow to the spent ML13316C083, ML14139A006, and result in potential offsite exposures fuel pool.

ML14178B284. comparable to the applicable guideline The deletion and modification of Description of amendment request: exposures set forth in 10 CFR 50.34(a)(1) or provisions of the Administrative Controls do The amendment would revise the CR- 100.11. not directly affect the design of SSCs 3 Facility Operating License (FOL) to The first two criteria, integrity of the necessary for the safe storage of irradiated remove and revise certain License reactor coolant pressure boundary and safe fuel or the methods used for handling and VerDate Sep<11>2014 20:06 Oct 27, 2014 Jkt 235001 PO 00000 Frm 00060 Fmt 4703 Sfmt 4703 E:\FR\FM\28OCN1.SGM 28OCN1

Federal Register / Vol. 79, No. 208 / Tuesday, October 28, 2014 / Notices 64223 storage of such fuel in the fuel pool. Deletion possibility of a new or different kind of As required by 10 CFR 50.91(a), the of Programs are administrative in nature and accident. licensee has provided its analysis of the do not affect any accidents applicable to the Therefore, the proposed amendment does issue of no significant hazards safe management of irradiated fuel or the not create the possibility of a new or different kind of accident from any previously consideration, which is presented permanently shutdown and defueled condition of the reactor. evaluated. below:

The proposed LC revisions reflect the CR- 3. Does the proposed amendment involve 1. Operation of the facility in accordance 3 functions that are still authorized in the a significant reduction in a margin of safety? with the proposed amendment would not permanently defueled condition, and remove Response: No. involve a significant increase in the authorizations that suggest the reactor can be Because the 10 CFR Part 50 license for CR- probability of occurrence or consequences of placed in operation. LCs that are being 3 no longer authorizes operation of the an accident previously evaluated.

removed due to their one time applicability reactor or emplacement or retention of fuel The proposed TS changes do not involve being previously satisfied have no bearing on into the reactor vessel, as specified in 10 CFR a significant increase in the probability or future functions at CR-3. Other LCs are being 50.82(a)(2), the occurrence of postulated consequences of an accident previously removed that are not required by regulation accidents associated with reactor operation evaluated. There are no physical changes to for a permanently defueled and are no longer credible. The only remaining the plant being introduced by the proposed decommissioning plant. These changes credible accident is a FHA. The proposed changes to the heatup, cooldown and cannot increase the probability or amendment does not adversely affect the hydrostatic inservice leak testing limitation consequences of any accident that remains inputs or assumptions of any of the design curves. The proposed changes do not modify credible. The probability of occurrence of basis analyses that impact a FHA. the RCS pressure boundary. That is, there are previously evaluated accidents is not The proposed changes are limited to those no changes in operating pressure, materials, increased, since extended operation in a portions of the LCs and ITS that are not or seismic loading. The proposed changes do defueled condition is the only operation related to the safe storage of irradiated fuel. not adversely affect the integrity of the RCS currently allowed, and is therefore bounded The requirements for SSCs that have been pressure boundary such that its function in by the existing analyses. Additionally, the deleted from the CR-3 ITS are not credited the control of radiological consequences is occurrence of postulated accidents associated in the existing accident analysis for the affected. The heatup, cooldown and with reactor operation is no longer credible remaining applicable postulated accident; hydrostatic inservice leak testing limitation in a permanently defueled reactor. This and as such, do not contribute to the margin curves were established in compliance with significantly reduces the scope of applicable of safety associated with the accident the methodology used to calculate and accidents. analysis. Postulated DBAs involving the predict effects of radiation on embrittlement Therefore, the proposed amendment does reactor are no longer possible because the reactor is permanently shutdown and of RPV beltline materials and remain valid not involve a significant increase in the during vacuum fill.

defueled and CR-3 is no longer authorized to probability or consequences of an accident Consequently, the proposed changes do not operate the reactor.

previously evaluated. involve a significant increase in the Therefore, the proposed amendment does

2. Does the proposed change create the probability or the consequences of an not involve a significant reduction in a possibility of a new or different kind of accident previously evaluated.

margin of safety because the current design accident from any accident previously limits continue to be met for the accident of 2. Operation of the facility in accordance evaluated? concern. with the proposed amendment would not Response: No. create the possibility of a new or different The proposed changes have no impact on The NRC staff has reviewed the kind of accident from any accident facility SSCs affecting the safe storage of licensees analysis and, based on this previously evaluated.

irradiated fuel, or on the methods of review, it appears that the three The proposed TS changes do not create the operation of such SSCs, or on the handling standards of 50.92(c) are satisfied. possibility of a new or different kind of and storage of irradiated fuel itself. The Therefore, the NRC staff proposes to accident from any accident previously removal of ITS that are related only to the evaluated. No new modes of operation are determine that the amendment request operation of the nuclear reactor or only to the introduced by the proposed changes. The prevention, diagnosis, or mitigation of involves no significant hazards proposed changes will not create any failure reactor-related transients or accidents cannot consideration. mode not bounded by previously evaluated result in different or more adverse failure Attorney for licensee: Lara S. Nichols, accidents.

modes or accidents than previously 550 South Tryon Street, Charlotte NC Consequently, the proposed changes do not evaluated because the reactor is permanently 28202. create the possibility of a new or different shutdown and defueled, and CR-3 is no NRC Branch Chief: Douglas A. kind of accident, from any accident longer authorized to operate the reactor. Broaddus. previously evaluated.

The proposed deletion of requirements of 3. Operation of the facility in accordance the CR-3 ITS do not affect safe storage of Entergy Nuclear Indian Point 3, LLC, with the proposed amendment would not nuclear fuel. The proposed PDTS continue to Docket No. 50-286, Indian Point, Unit 3, involve a significant reduction in the margin require proper control and monitoring of Westchester County, NY of safety.

safety significant parameters. The proposed Date of amendment request: April 1, The proposed TS changes do not involve restriction on the fuel pool level is fulfilled a significant reduction in the margin of by normal operating conditions and 2014. A publicly-available version is in safety. The changes clarify that the heatup, preserves initial conditions assumed in the ADAMS under Accession No. cooldown and hydrostatic inservice leak analyses of the postulated DBA. The spent ML14099A333. testing limitation curves remain valid during fuel pool water level, spent fuel pool boron Description of amendment request: vacuum fill (to 0 psia) in accordance with concentration, and spent fuel pool storage The amendment would revise Technical current regulations. Because operation will LCOs are retained to preserve the current Specifications (TS) Figure 3.4.3-1, be within these limits, the RCS materials will requirements for safe storage of irradiated Heatup Limitations for Reactor Coolant continue to behave in a non-brittle manner fuel. System, Figure 3.4.3-2, Cooldown consistent with the original design bases.

asabaliauskas on DSK4SPTVN1PROD with NOTICES The proposed amendment does not result Limitations for Reactor Coolant System, Therefore, Entergy has concluded that the in any new mechanisms that could initiate and Figure 3.4.3-3, Hydrostatic and proposed changes do not involve a damage to the remaining relevant safety significant reduction in a margin of safety.

barriers for defueled plants (i.e., fuel Inservice Leak Testing Limitations for cladding and spent fuel cooling). Since Reactor Coolant System, to indicate that The NRC staff has reviewed the extended operation in a defueled condition is the curves are applicable for vacuum licensees analysis and, based on this the only operation currently allowed, and fill. review, it appears that the three therefore bounded by the existing analyses, Basis for proposed no significant standards of 10 CFR 50.92(c) are such a condition does not create the hazards consideration determination: satisfied. Therefore, the NRC staff VerDate Sep<11>2014 20:06 Oct 27, 2014 Jkt 235001 PO 00000 Frm 00061 Fmt 4703 Sfmt 4703 E:\FR\FM\28OCN1.SGM 28OCN1

64224 Federal Register / Vol. 79, No. 208 / Tuesday, October 28, 2014 / Notices proposes to determine that the 1. Does the proposed change involve a proposed change does not adversely affect amendment request involves no significant increase in the probability or any current plant safety margins or the significant hazards consideration. consequences of an accident previously reliability of the equipment assumed in the evaluated? safety analysis. Therefore, there are no Attorney for licensee: Jeanne Cho, Response: No. changes being made to any safety analysis Assistant General Counsel, Entergy The proposed change revises or adds assumptions, safety limits or limiting safety Nuclear Operations, Inc., 440 Hamilton Surveillance Requirements (SRs) that require system settings that would adversely affect Avenue, White Plains, NY 10601. verification that the Emergency Core Cooling plant safety as a result of the proposed NRC Branch Chief: Benjamin Beasley. System (ECCS), the Decay Heat Removal change.

(DHR)/Residual Heat Removal (RHR)/ Therefore, the proposed change does not Exelon Generation Company, LLC, Shutdown Cooling (SDC) System, the involve a significant reduction in a margin of Docket Nos. STN 50-456 and STN 50- Containment Spray (CS) System, and the safety.

457, Braidwood Station, Units 1 and 2, Reactor Core Isolation Cooling (RCIC)

System, as applicable, are not rendered The NRC staff has reviewed the Will County, Illinois inoperable due to accumulated gas and to licensees analysis and, based on this Exelon Generation Company, LLC, provide allowances which permit review, it appears that the three Docket Nos. STN 50-454 and STN 50- performance of the revised verification. Gas standards of 10 CFR 50.92(c) are 455, Byron Station, Units 1 and 2, Ogle accumulation in the subject systems is not an satisfied. Therefore, the NRC staff County, Illinois initiator of any accident previously proposes to determine that the evaluated. As a result, the probability of any requested amendments involve no Exelon Generation Company, LLC, accident previously evaluated is not Docket No. 50-461, Clinton Power significant hazards consideration.

significantly increased. The proposed SRs Station, Unit 1, DeWitt County, Illinois ensure that the subject systems continue to Attorney for licensee: J. Bradley be capable to perform their assumed safety Fewell, Esquire, Vice President and Exelon Generation Company, LLC, Deputy General Counsel, Exelon function and are not rendered inoperable due Docket Nos. 50-237 and 50-249, to gas accumulation. Thus, the consequences Generation Company, LLC, 4300 Dresden Nuclear Power Station, Units 2 of any accident previously evaluated are not Winfield Road, Warrenville, IL 60555.

and 3, Grundy County, Illinois significantly increased. NRC Branch Chief: Travis L. Tate.

Exelon Generation Company, LLC, Therefore, the proposed change does not involve a significant increase in the FirstEnergy Nuclear Operating Docket Nos. 50-373 and 50-374, LaSalle Company, et al., Docket Nos. 50-334 probability or consequences of an accident County Station, Units 1 and 2, LaSalle previously evaluated. and 50-412, Beaver Valley Power County, Illinois Does the proposed change create the Station (BVPS), Units 1 and 2, Beaver Exelon Generation Company, LLC, possibility of a new or different kind of County, Pennsylvania Docket Nos. 50-254 and 50-265, Quad accident from any accident previously evaluated? Date of amendment request:

Cities Nuclear Power Station, Units 1 September 4, 2014. A publicly-available Response: No.

and 2, Rock Island County, Illinois The proposed change revises or adds SRs version is available in ADAMS under Date of amendment request: July 14, that require verification that the ECCS, the Accession No. ML14247A512.

2014. A publicly-available version is in DHR/RHR/SDC System, the CS System, and Description of amendment request:

ADAMS under Accession No. the RCIC System, as applicable, are not The amendment proposes changes to rendered inoperable due to accumulated gas align the BVPS Emergency Planning ML14195A172. and to provide allowances which permit Description of amendment request: Zone (EPZ) boundary with the boundary performance of the revised verification. The that is currently in use by the The proposed amendment would revise proposed change does not involve a physical and add technical specification (TS) alteration of the plant (i.e., no new or emergency management agencies of the surveillance requirements to address the different type of equipment will be installed) three counties that implement public concerns discussed in NRC Generic or a change in the methods governing normal protective actions around BVPS.

Letter 2008-01, Managing Gas plant operation. In addition, the proposed Basis for proposed no significant Accumulation in Emergency Core change does not impose any new or different hazards consideration determination:

Cooling, Decay Heat Removal, and requirements that could initiate an accident. As required by 10 CFR 50.91(a), the The proposed change does not alter licensee has provided its analysis of the Containment Spray Systems, dated assumptions made in the safety analysis and January 11, 2008 (ADAMS Accession issue of no significant hazards is consistent with the safety analysis consideration, which is presented No. ML072910759). The proposed TS assumptions.

changes are based on NRC-approved TS below, along with NRC edits in square Therefore, the proposed change does not Task Force (TSTF) Traveler TSTF-523, create the possibility of a new or different brackets:

Revision 2, Generic Letter 2008-01, kind of accident from any accident 1. Does the proposed change involve a Managing Gas Accumulation, dated previously evaluated. significant increase in the probability or February 21, 2013 (ADAMS Accession 2. Does the proposed change involve a consequences of an accident previously significant reduction in a margin of safety? evaluated?

No. ML13053A075). The NRC staff Response: No. Response: No.

issued a Notice of Availability for The proposed change revises or adds SRs This amendment request would alter TSTF-523, Revision 2, for plant-specific that require verification that the ECCS, the portions of the outer EPZ boundary defined adoption using the Consolidated Line DHR/RHR/SDC System, the CS System, and in the BVPS EPP [Emergency Preparedness Item Improvement Process, in the the RCIC System, as applicable, are not Plan] to align with the EPZ boundaries Federal Register on January 15, 2014 rendered inoperable due to accumulated gas implemented by the Columbiana County, asabaliauskas on DSK4SPTVN1PROD with NOTICES (79 FR 2700). and to provide allowances which permit Hancock County, and Beaver County Basis for proposed no significant performance of the revised verification. The emergency management agencies. The proposed change adds new requirements to proposed amendment does not involve any hazards consideration determination:

manage gas accumulation in order to ensure modifications or physical changes to plant As required by 10 CFR 50.91(a), the the subject systems are capable of performing systems, structures, or components. The licensee has provided its analysis of the their assumed safety functions. The proposed proposed amendment does not change plant issue of no significant hazards SRs are more comprehensive than the current operations or maintenance of plant systems, consideration, which is presented SRs and will ensure that the assumptions of structures, or components. Nor does the below: the safety analysis are protected. The proposed amendment alter any BVPS EPP VerDate Sep<11>2014 20:06 Oct 27, 2014 Jkt 235001 PO 00000 Frm 00062 Fmt 4703 Sfmt 4703 E:\FR\FM\28OCN1.SGM 28OCN1

Federal Register / Vol. 79, No. 208 / Tuesday, October 28, 2014 / Notices 64225 facility or equipment. Changing the EPZ Florida Power and Light Company, et al. performance of the revised verification. The boundaries cannot increase the probability of (the licensee), Docket Nos. 50-335 and proposed change does not involve a physical an accident since emergency plan functions 50-389, St. Lucie Plant, Units 1 and 2, alteration of the plant (i.e., no new or would be implemented after a postulated different type of equipment will be installed)

St. Lucie County, Florida accident occurs. The proposed amendment or a change in the methods governing normal does not alter or prevent the ability of the Date of amendment request: July 14, plant operation. In addition, the proposed BVPS emergency response organization to 2014. A publicly-available version is in change does not impose any new or different perform intended emergency plan functions ADAMS under Accession No. requirements that could initiate an accident.

to mitigate the consequences of and to ML14198A074. The proposed change does not alter respond adequately to radiological Description of amendment request: assumptions made in the safety analysis and emergencies. The amendments would revise or add is consistent with the safety analysis Therefore, the proposed amendment does assumptions.

surveillance requirements (SRs) to not involve a significant increase in the Therefore, the proposed change does not verify that the system locations create the possibility of a new or different probability or consequences of an accident susceptible to gas accumulation are kind of accident from any accident previously evaluated. sufficiently filled with water and to previously evaluated.

2. Does the proposed change create the provide allowances that permit 3. Does the Proposed Change Involve a possibility of a new or different kind of performance of the verification. The Significant Reduction in a Margin of Safety?

accident from any accident previously Response: No.

evaluated?

licensee proposed the changes to address NRC Generic Letter 2008-01, The proposed change revises or adds SRs Response: No. that require verification that the ECCS, RHR This amendment request alters the EPZ Managing Gas Accumulation in System, SDC System, and CS System are not boundary described in the BVPS EPP. The Emergency Core Cooling, Decay Heat rendered inoperable due to accumulated gas proposed amendment does not involve any Removal, and Containment Spray and to provide allowances which permit design modifications or physical changes to Systems (ADAMS Accession No. performance of the revised verification. The the plant, does not change plant operation or ML072910759), as described in Revision proposed change adds new requirements to maintenance of equipment, and does not 2 of Technical Specification Task Force manage gas accumulation in order to ensure alter BVPS EPP facilities or equipment. The No. 523, Generic Letter 2008-01, that the subject systems are capable of proposed amendment to the BVPS EPP does Managing Gas Accumulation (ADAMS performing their assumed safety functions.

not alter any BVPS emergency actions that Accession No. ML13053A075). The proposed SRs are more comprehensive would be implemented in response to Basis for proposed no significant than the current SRs and will ensure that the postulated accident events. The proposed hazards consideration determination: assumptions of the safety analysis are amendment does not create any credible new protected. The proposed change does not As required by 10 CFR 50.91(a), the adversely affect any current plant safety failure mechanisms, malfunctions, or accident initiators not previously considered.

licensee has provided its analysis of the margins or the reliability of the equipment Therefore, the proposed change does not issue of no significant hazards assumed in the safety analysis. Therefore, create the possibility of a new or different consideration, which is presented there are no changes being made to any safety kind of accident from any previously below: analysis assumptions, safety limits, or evaluated. 1. Does the Proposed Change Involve a limiting safety system settings that would

3. Does the proposed change involve a Significant Increase in the Probability or adversely affect plant safety as a result of the significant reduction in a margin of safety? Consequences of an Accident Previously proposed change.

Response: No. Evaluated? The NRC staff has reviewed the This amendment request would alter Response: No. licensees analysis and, based on this portions of the EPZ boundary defined in the The proposed change revises or adds SRs that require verification that the Emergency review, it appears that the three BVPS EPP. The proposed amendment does standards of 50.92(c) are satisfied.

not involve any design or licensing basis Core Cooling Systems (ECCS), Residual Heat Removal (RHR) System, Shutdown Cooling Therefore, the NRC staff proposes to functions of the plant, no physical changes to the plant are made, does not impact plant (SDC) System, and Containment Spray (CS) determine that the amendment request operation or maintenance of equipment, and System are not rendered inoperable due to involves no significant hazards accumulated gas and to provide allowances consideration.

does not alter BVPS EPP facilities or which permit performance of the revised Attorney for licensee: William S.

equipment. This change does not alter any verification. Gas accumulation in the subject BVPS emergency actions that would be Blair, Managing AttorneyNuclear, systems is not an initiator of any accident implemented in response to postulated previously evaluated. As a result, the Florida Power & Light, 700 Universe accident events. The BVPS EPP continues to probability of any accident previously Blvd., MS LAW/JB, Juno Beach, Florida meet 10 CFR 50.47 and 10 CFR 50, Appendix evaluated is not significantly increased. The 33408-0420.

E requirements for emergency response. proposed SRs ensure that the subject systems NRC Acting Branch Chief: Lisa M.

Therefore, the proposed change does not continue to be capable of performing their Regner.

involve a significant reduction in a margin of assumed safety function and are not rendered safety. inoperable due to gas accumulation. Thus, Florida Power and Light Company, et the consequences of any accident previously al., Docket Nos. 50-335 and 50-389, St.

The NRC staff has reviewed the evaluated are not significantly increased. Lucie Plant, Units 1 and 2, St. Lucie licensees analysis and, based on this Therefore, the proposed change does not County, Florida review, it appears that the three involve a significant increase in the standards of 10 CFR 50.92(c) are probability or consequences of an accident Date of amendment request: August 8, satisfied. Therefore, the NRC staff previously evaluated. 2014. A publicly-available version is in

2. Does the Proposed Change Create the ADAMS under Accession No.

asabaliauskas on DSK4SPTVN1PROD with NOTICES proposes to determine that the Possibility of a New or Different Kind of ML14225A654.

amendment request involves no Accident from any Accident Previously significant hazards consideration. Description of amendment request:

Evaluated? The amendments would modify the Attorney for licensee: David W. Response: No.

The proposed change revises or adds SRs Technical Specifications by removing Jenkins, FirstEnergy Nuclear Operating TS 3/4.4.7, Chemistry, which Company, FirstEnergy Corporation, 76 that require verification that the ECCS, RHR System, SDC System, and CS System are not provides limits on the oxygen, chloride, South Main Street, Akron, OH 44308. rendered inoperable due to accumulated gas and fluoride content in the reactor NRC Branch Chief: Meena K. Khanna. and to provide allowances which permit coolant system to minimize corrosion.

VerDate Sep<11>2014 20:06 Oct 27, 2014 Jkt 235001 PO 00000 Frm 00063 Fmt 4703 Sfmt 4703 E:\FR\FM\28OCN1.SGM 28OCN1

64226 Federal Register / Vol. 79, No. 208 / Tuesday, October 28, 2014 / Notices The licensee requested that these Response: No. XST1A and was to expire on March 31, requirements be relocated to the Margin of safety is related to confidence in 2014.

Updated Final Safety Analysis Report the ability of the fission product barriers to The first 14-day CT was successfully perform their accident mitigation functions. completed, on October 14, 2013.

(UFSAR) and controlled in accordance The proposed change acts to remove current with 10 CFR 50.59, Changes, tests, and Reactor Coolant System (RCS) chemistry However, the licensee inadvertently cut experiments. limits and monitoring requirements from the the wrong offsite power cable during the Basis for proposed no significant TS and relocate the requirements to the second 14-day CT resulting in a total hazards consideration determination: UFSAR. The proposed change will maintain loss-of-offsite power (LOOP) to both As required by 10 CFR 50.91(a), the limits on RCS chemistry parameters and will units and the modification had to be licensee provided its analysis of the continue to provide associated monitoring abandoned. Due to the cut-cable event issue of no significant hazards requirements. The proposed change does not and the subsequent efforts to determine consideration, which is presented as physically alter any SSC. There will be no the causes and corrective actions, the effect on those SSCs necessary to assure the follows: accomplishment of protection functions.

modification could not be completed by

1. Does the proposed change involve a There will be no impact on the overpower March 31, 2014. The licensee has significant increase in the probability or limit, departure from nucleate boiling ratio requested an extension of the CT from consequences of an accident previously (DNBR) limits, loss of cooling accident peak 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> to 14 days on one-time basis evaluated? cladding temperature (LOCA PCT), or any to complete the plant modification.

Response: No. other margin of safety. The applicable Installation of the alternate ST XST1A The proposed change acts to remove radiological dose consequence acceptance will result in improved offsite power current Reactor Coolant System (RCS) criteria will continue to be met.

chemistry limits and monitoring system reliability.

Therefore, the proposed change does not Basis for proposed no significant requirements from the TS and relocate the involve a significant reduction in a margin of requirements to the UFSAR. Monitoring and safety.

hazards consideration determination:

maintaining RCS chemistry minimizes the As required by 10 CFR 50.91(a), the potential for corrosion of RCS piping and The NRC staff reviewed the licensees licensee has provided its analysis of the components. Corrosion effects are considered analysis and, based on this review, it issue of no significant hazards a long-term impact on RCS structural appears that the three standards of consideration, which is presented integrity. Because RCS chemistry will 50.92(c) are satisfied. Therefore, the below:

continue to be monitored and controlled, NRC staff proposes to determine that the relocating the current TS requirements to the 1. Does the proposed change involve a amendment request involves no significant increase in the probability or UFSAR will not present an adverse impact to the RCS and subsequently, will not impact significant hazards consideration. consequences of an accident previously the probability or consequences of an Attorney for licensee: William S. evaluated?

accident previously evaluated. Furthermore, Blair, Managing AttorneyNuclear, Response: No.

once relocated to the UFSAR, changes to RCS Florida Power & Light Company, 700 The proposed change will revise the CT for chemistry limits and monitoring Universe Blvd. MS LAW/JB, Juno the loss of one offsite source from 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> requirements will be controlled in Beach, Florida 33408-0420. to 14 days to allow a one-time, 14-day CT.

accordance with 10 CFR 50.59. NRC Acting Branch Chief: Lisa M. The proposed one-time extension of the CT Therefore, the proposed change does not Regner. for the loss of one offsite power circuit does involve a significant increase in the not significantly increase the probability of probability or consequences of any accident Luminant Generation Company LLC, an accident previously evaluated. The TS previously evaluated. Docket Nos. 50-445 and 50-446, will continue to require equipment that will

2. Does the proposed change create the Comanche Peak Nuclear Power Plant power safety related equipment necessary to possibility of a new or different kind of (CPNPP), Units 1 and 2, Somervell perform any required safety function. The accident from any accident previously one-time extension of the CT to 14 days does evaluated?

County, Texas not affect the design of the STs, the interface Response: No. Date of amendment request: July 1, of the STs with other plant systems, the The proposed change acts to remove 2014. A publicly-available version is in operating characteristic of the STs, or the current Reactor Coolant System (RCS) ADAMS under Accession No. reliability of the STs.

chemistry limits and monitoring ML14192A338. The consequence of a LOOP event has been requirements from the TS and relocate the Description of amendment request. evaluated in the CPNPP Final Safety Analysis requirements to the UFSAR. The proposed Report (Reference 8.1 [of the licensees letter change does not introduce new modes of The amendments would revise dated July 1, 2014]) and the Station Blackout plant operation and it does not involve Technical Specification (TS) 3.8.1, AC evaluation. Increasing the CT for one offsite physical modifications to the plant (no new [Alternating Current] Sources power source on a one-time basis from 72 or different type of equipment will be Operating, to extend, on a one-time hours to 14 days does not increase the installed). There are no changes in the basis, the Completion Time (CT) of consequences of a LOOP event nor change method by which any safety related plant Required Action A.3 from 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> to the evaluation of LOOP events.

structure, system, or component (SSC) 14 days. By letter dated September 18, Therefore, the proposed change does not performs its specified safety function. As 2013 (ADAMS Accession No. involve a significant increase in the such, the plant conditions for which the probability or consequences of an accident design basis accident analyses were ML13232A143), the NRC staff issued previously evaluated.

performed remain valid. Amendment No. 160 to Facility 2. Do the proposed changes create the No new accident scenarios, transient Operating License No. NPF-87 and possibility of a new or different kind of precursors, failure mechanisms, or limiting Amendment No. 160 to Facility accident from any accident previously single failures will be introduced as a result Operating License No. NPF-89 for evaluated?

asabaliauskas on DSK4SPTVN1PROD with NOTICES of the proposed change. There will be no CPNPP, Units 1 and 2, respectively. The Response: No.

adverse effect or challenges imposed on any amendments revised TS 3.8.1 to extend The proposed change does not result in a SSC as a result of the proposed change. the CT for Required Action A.3 on a change in the manner in which the electrical Therefore, the proposed change does not distribution subsystems provide plant create the possibility of a new or different one-time basis from 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> to 14 days. protection. The proposed change will only kind of accident from any accident The CT extension from 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> to 14 affect the time allowed to restore the previously evaluated. days was to be used twice while operability of the offsite power source

3. Does the proposed change involve a completing the plant modification to through a ST. The proposed change does not significant reduction in the margin of safety? install alternate startup transformer (ST) affect the configuration, or operation of the VerDate Sep<11>2014 20:06 Oct 27, 2014 Jkt 235001 PO 00000 Frm 00064 Fmt 4703 Sfmt 4703 E:\FR\FM\28OCN1.SGM 28OCN1

Federal Register / Vol. 79, No. 208 / Tuesday, October 28, 2014 / Notices 64227 plant. The proposed change to the CT will licensing basis analysis for waste gas This license amendment request proposes facilitate installation of a plant modification decay tank rupture. to revise the licensing basis waste gas decay which will improve plant design and will Basis for proposed no significant tank rupture analysis. The proposed analysis eliminate the necessity to shut down both hazards consideration determination: was updated to include the current fuel type, Units if XST1 fails or requires maintenance current fuel cycle lengths and plant operation As required by 10 CFR 50.91(a), the that goes beyond the current TS CT of 72 to sixty years.

hours. This change will improve the long- licensee has provided its analysis of the This revised analysis applies the same term reliability of the 138 [kiloVolt (kV)] issue of no significant hazards methodology as the original waste gas decay offsite circuit ST which is common to both consideration, which is presented tank rupture analysis. The original waste gas CPNPP Units. below: decay tank rupture analysis demonstrated There are no changes to the STs or the 1. Does the proposed amendment involve that the doses were a small fraction of the supporting systems operating characteristics a significant increase in the probability or regulatory guidelines and that the waste gas or conditions. The change to the CT does not consequences of an accident previously system design prevents release of undue change any existing accident scenarios, nor evaluated? amounts of radioactivity. The revised waste create any new or different accident Response: No. gas decay tank rupture analysis demonstrates scenarios. In addition, the change does not This license amendment request proposes that the doses are well within the regulatory impose any new or different requirements or to revise the licensing basis waste gas decay guidelines and that the waste gas system eliminate any existing requirements. The tank rupture analysis. The proposed analysis design continues to prevent release of undue change does not alter any of the assumptions was updated to include the current fuel type, amounts of radioactivity.

made in the safety analysis. current fuel cycle lengths and plant operation Therefore, the proposed licensing basis Therefore, the proposed change does not to sixty years. change does not involve a significant create the possibility of a new or different The proposed waste gas decay tank rupture reduction in a margin of safety.

kind of accident from any previously analysis changes are not accident initiators, evaluated. The NRC staff has reviewed the and therefore the proposed changes do not

3. Do the proposed changes involve a involve an increase in the probability of an licensees analysis and, based on this significant reduction in a margin of safety? accident. review, it appears that the three Response: No. The original waste gas decay tank rupture standards of 10 CFR 50.92(c) are The proposed change does not affect the analysis demonstrated that the doses were a satisfied. Therefore, the NRC staff acceptance criteria for any analyzed event small fraction of the regulatory guidelines proposes to determine that the nor is there a change to any safety limit. The and that the waste gas system design amendment requests involve no proposed change does not alter the manner prevents release of undue amounts of significant hazards consideration.

in which safety limits, limiting safety system radioactivity. The revised waste gas decay Attorney for licensee: Peter M. Glass, settings, or limiting conditions for operation tank rupture analysis demonstrates that the are determined. Neither the safety analyses doses are well within the regulatory Assistant General Counsel, Xcel Energy nor the safety analysis acceptance criteria are guidelines and that the waste gas system Services, Inc., 414 Nicollet Mall, affected by this change. The proposed change design continues to prevent release of undue Minneapolis, MN 55401 will not result in plant operation in a amounts of radioactivity, and thus the NRC Branch Chief: David L. Pelton.

configuration outside the current design proposed changes do not involve a basis. The proposed activity only increases a significant increase in the consequences of an PSEG Nuclear LLC, Docket Nos. 50-272 one-time pre-planned occurrence, the period accident. and 50-311, Salem Nuclear Generating when the plant may operate with one offsite Therefore, the proposed licensing basis Station (SNGS), Units 1 and 2, Salem power source. The margin of safety is change does not involve a significant County, New Jersey maintained by maintaining the ability to increase in the probability or consequences safely shut down the plant and remove of an accident previously evaluated. Date of amendment request: July 28, residual heat. 2. Does the proposed amendment create 2014. A publicly-available version is in Therefore, the proposed change does not the possibility of a new or different kind of ADAMS under Accession No.

involve a reduction in a margin of safety. accident from any accident previously ML14210A484.

The NRC staff has reviewed the evaluated? Description of amendment request:

Response: No. The proposed amendment would licensees analysis and, based on this This license amendment request proposes review, it appears that the standards of modify technical specification (TS) to revise the licensing basis waste gas decay requirements regarding steam generator 10 CFR 50.92(c) are satisfied. Therefore, tank rupture analysis. The proposed analysis the NRC staff proposes to determine that was updated to include the current fuel type, tube inspections and reporting as the request for amendments involves no current fuel cycle lengths and plant operation described in Technical Specification significant hazards consideration. to sixty years. Task Force (TSTF) traveler TSTF-510, Attorney for licensee: Timothy P. The proposed waste gas decay tank rupture Revision 2, Revision to Steam Matthews, Esq., Morgan, Lewis and analysis includes plant changes that have Generator Program Inspection previously been evaluated. This analysis Frequencies and Tube Sample Bockius, 1111 Pennsylvania Avenue applies the same methodology as the NW., Washington, DC 20004. Selection. In addition, the proposed previous analysis. The proposed revision to amendment would revise the SNGS, NRC Branch Chief: Michael T. the waste gas decay tank rupture analysis Markley. does not change any system operations or Unit 2, TSs 6.8.4.i, Steam Generator maintenance activities. The changes do not (SG) Program, TS 6.9.1.10, Steam Northern States Power Company involve physical alteration of the plant; that Generator Tube Inspection Report, and Minnesota, Docket Nos. 50-282 and 50- is, no new or different type of equipment will the bases section of 3/4.4.6, Steam 306, Prairie Island Nuclear Generating be installed. These changes do not create new Generator (SG) Tube Integrity, to Plant (PINGP), Units 1 and 2, Goodhue failure modes or mechanisms which are not remove unnecessary information related asabaliauskas on DSK4SPTVN1PROD with NOTICES County, Minnesota identifiable during testing and no new to the original Salem Unit 2 Date of amendment request: August accident precursors are generated. Westinghouse steam generators.

Therefore, the proposed licensing basis 21, 2014. A publicly-available version is Basis for proposed no significant change does not create the possibility of a in ADAMS under Accession No. new or different kind of accident from any hazards consideration determination:

ML14233A431. previously evaluated. As required by 10 CFR 50.91(a), the Description of amendment request: 3. Does the proposed amendment involve licensee has provided its analysis of the The proposed amendments would a significant reduction in a margin of safety? issue of no significant hazards revise the PINGP, Units 1 and 2, Response: No. consideration, which is presented VerDate Sep<11>2014 20:06 Oct 27, 2014 Jkt 235001 PO 00000 Frm 00065 Fmt 4703 Sfmt 4703 E:\FR\FM\28OCN1.SGM 28OCN1

64228 Federal Register / Vol. 79, No. 208 / Tuesday, October 28, 2014 / Notices below, along with NRC edits in square a heat transfer surface between the primary to UFSAR Tier 2 information involving brackets: and secondary systems such that residual changes to plant-specific Tier 2*

heat can be removed from the primary information.

1. Does the proposed change involve a system. In addition, the SG tubes also isolate significant increase in the probability or Basis for proposed no significant the radioactive fission products in the consequences of an accident previously hazards consideration determination:

primary coolant from the secondary system.

evaluated? In summary, the safety function of a SG is As required by 10 CFR 50.91(a), the Response: No. maintained by ensuring the integrity of its licensee has provided its analysis of the The proposed change revises the Steam tubes. issue of no significant hazards Generator (SG) Program to modify the consideration, which is presented Steam generator tube integrity is a function frequency of verification of SG tube integrity and SG tube sample selection. A steam of the design, environment, and the physical below:

condition of the tube. The proposed change generator tube rupture (SGTR) event is one of 1. Does the proposed amendment involve does not affect tube design or operating the design basis accidents that are analyzed a significant increase in the probability or environment. The proposed change will as part of a plants licensing basis. The consequences of an accident previously continue to require monitoring of the proposed SG tube inspection frequency and evaluated?

physical condition of the SG tubes such that Response: No.

sample selection criteria will continue to there will not be a reduction in the margin The proposed middle annulus fire barrier ensure that the SG tubes are inspected such of safety compared to the current reconfiguration for the electrical penetrations that the probability of a SGTR is not increased. The consequences of a SGTR are requirements. would not adversely affect any safety-related bounded by the conservative assumptions in The proposed changes to the Salem Unit 2 equipment or function. The modified the design basis accident analysis. The Technical Specifications (TS) that are not configuration for the Class 1E electrical proposed change will not cause the associated with TSTF-510, removing containment penetration enclosures will consequences of a SGTR to exceed those unnecessary information related to W* that is maintain the fire protection function (i.e.,

assumptions. only applicable to Westinghouse steam barrier) as evaluated in Updated Final Safety Therefore, it is concluded that this change generators, is an administrative change that Analysis Report (UFSAR), thus, the does not involve a significant increase in the does not involve a significant reduction in a probability of a Class 1E electrical probability or consequences of an accident margin of safety. containment penetration failure is not previously evaluated. Therefore, it is concluded that the significantly increased. The safe shutdown The proposed changes to the Salem Unit 2 proposed changes do not involve a fire analysis is not affected, and the fire Technical Specifications (TS) that are not significant reduction in a margin of safety. protection analysis results are not adversely associated with TSTF-510, removing The NRC staff has reviewed the affected. The proposed changes do not unnecessary information related to W* licensees analysis and, based on this involve any accident, initiating event or

[pronounced W star, which refers to the component failure; thus, the probabilities of length of the steam generator tube required review, it appears that the three previously evaluated accidents are not to be inspected within the hot-leg tube sheet] standards of 10 CFR 50.92(c) are affected. The maximum allowable leakage that is only applicable to Westinghouse satisfied. Therefore, the NRC staff rate specified in the Technical Specifications steam generators, is an administrative change proposes to determine that the is unchanged, and radiological material that does not involve a significant increase in amendment request involves no release source terms are not affected; thus, the probability or consequences of an significant hazards consideration. the radiological releases in the accident accident previously evaluated. Attorney for licensee: Jeffrie J. Keenan, analyses are not affected.

2. Does the proposed change create the PSEG Nuclear LLCN21, P.O. Box 236, Therefore, the proposed amendment does possibility of a new or different kind of not involve a significant increase in the Hancocks Bridge, NJ 08038. probability or consequences of an accident accident from any accident previously evaluated? NRC Branch Chief: Meena K. Khanna. previously evaluated.

Response: No. South Carolina Electric and Gas 2. Does the proposed amendment create The proposed changes to the Steam Company Docket Nos.52-027 and 52- the possibility of a new or different kind of Generator Program will not introduce any accident from any accident previously adverse changes to the plant design basis or 028, Virgil C. Summer Nuclear Station, evaluated?

postulated accidents resulting from potential Units 2 and 3, Fairfield County, South Response: No.

tube degradation. The proposed change does Carolina The addition of enclosures constructed of not affect the design of the SGs or their Date of amendment request: June 20, three-hour rated fire barriers to separate the method of operation. In addition, the fire zones in the middle annulus for the Class 2014, as supplemented by letter dated proposed change does not impact any other 1E electrical penetration assemblies will plant system or component. August 6, 2014. Publicly-available maintain the fire protection function as The proposed changes to the Salem Unit 2 versions are in ADAMS under evaluated in the UFSAR. The addition of the Technical Specifications (TS) that are not Accession Nos. ML14174B176 and fire barriers does not affect the function of associated with TSTF-510, removing ML14218A809. the Class 1E electrical containment unnecessary information related to W* that is Description of amendment request: penetrations or electrical penetration only applicable to Westinghouse steam The proposed license amendment assemblies, and thus, does not introduce a generators, is an administrative change that request (LAR) would revise the Updated new failure mode. The addition of the fire does not affect the design of the SGs or their Final Safety Analysis Report (UFSAR) barriers does not create a new fault or method of operation. sequence of events that could result in a Therefore, it is concluded that these in regard to Tier 2* information related radioactive material release.

changes do not create the possibility of a new to fire area boundaries. These changes Therefore, the proposed amendment does of different kind of accident from any add three new fire zones in the middle not create the possibility of a new or different accident previously evaluated. annulus to provide enclosures for the kind of accident.

3. Do the proposed changes involve a Class 1E electrical containment 3. Does the proposed amendment involve asabaliauskas on DSK4SPTVN1PROD with NOTICES significant reduction in a margin of safety? penetrations in accordance with UFSAR a significant reduction in a margin of safety?

Response: No. Appendix 9A, Subsection 9A.3.1.1.15. Response: No.

The SG tubes in pressurized water reactors The addition of the three new fire zones The use of enclosures constructed of three-are an integral part of the reactor coolant hour rated fire barriers to separate the fire pressure boundary and, as such, are relied extended the fire area boundaries for zones in the middle annulus for the Class 1E upon to maintain the primary systems three existing fire areas and, therefore, electrical penetration assemblies will pressure and inventory. As part of the reactor constitutes a change to Tier 2* maintain the fire protection function as coolant pressure boundary, the SG tubes are information. Additionally, the licensee evaluated in the UFSAR. The use of the fire unique in that they are also relied upon as proposed changes that require revisions barriers does not affect the ability of the Class VerDate Sep<11>2014 20:06 Oct 27, 2014 Jkt 235001 PO 00000 Frm 00066 Fmt 4703 Sfmt 4703 E:\FR\FM\28OCN1.SGM 28OCN1

Federal Register / Vol. 79, No. 208 / Tuesday, October 28, 2014 / Notices 64229 1E electrical containment penetrations, Basis for proposed no significant The change revises the STPNOC electrical penetration assemblies, or the hazards consideration determination: Emergency Action Levels to be consistent containment to perform their design As required by 10 CFR 50.91(a), the with the NRC endorsed EAL scheme function. The Class 1E electrical containment contained in NEI 99-01, Revision 6, licensee has provided its analysis of the Methodology for Development of penetrations and electrical penetration assemblies within the enclosures continue to issue of no significant hazards Emergency Action Levels, but does not alter comply with the existing design codes and consideration, which is presented any of the requirements of the Operating regulatory criteria, and do not affect any below: License or the Technical Specifications. In safety limit. The use of fire barriers and 1. Does the proposed amendment involve addition to replacing the current STP EALs, enclosures to separate the Class 1E electrical a significant increase in the probability or the new EAL scheme includes an EAL related penetration assemblies does not adversely consequence of an accident previously to the planned STP Independent Spent Fuel affect any margin of safety. evaluated? Storage Installation, and EALs related to Therefore, the proposed amendment does Response: No. planned changes to the Spent Fuel Pool level not involve a significant reduction in the The change revises the STPNOC [STP instrumentation that will address lessons margin of safety. Nuclear Operating Company] Emergency learned from Fukushima Daiichi. The Action Levels to be consistent with the NRC proposed change does not affect any of the The NRC staff has reviewed the endorsed EAL scheme contained in NEI 99- assumptions used in the accident analysis, licensees analysis, and based on this 01, Revision 6, Methodology for nor does it affect any operability review, it appears that the three Development of Emergency Action Levels, requirements for equipment important to standards of 10 CFR 50.92(c) are but does not alter any of the requirements of plant safety. Therefore, the proposed change satisfied. Therefore, the NRC staff the Operating License or the Technical will not result in a significant reduction in Specifications. In addition to replacing the the margin of safety in operation of the proposes to determine that the current STP EALs, the new EAL scheme facility as discussed in this license amendment request involves no amendment request.

significant hazards consideration. includes an EAL related to the planned STP Independent Spent Fuel Storage Installation, The NRC staff has reviewed the Attorney for licensee: Ms. Kathryn M. and EALs related to planned changes to the Sutton, Morgan, Lewis & Bockius LLC, licensees analysis and, based on this Spent Fuel Pool level instrumentation that review, it appears that the standards of 1111 Pennsylvania Avenue NW., will address lessons learned from Fukushima Washington, DC 20004-2514. Daiichi. The proposed change does not 10 CFR 50.92(c) are satisfied. Therefore, NRC Branch Chief: Lawrence J. modify any plant equipment and does not the NRC staff proposes to determine that Burkhart. impact any failure modes that could lead to the request for amendments involves no an accident. Additionally, the proposed significant hazards consideration.

STP Nuclear Operating Company, change has no effect on the consequences of Attorney for licensee: A. H.

Docket Nos. 50-498 and 50-499, South any analyzed accident since the change does Gutterman, Esq., Morgan, Lewis &

Texas Project (STP), Units 1 and 2, not affect any equipment related to accident Bockius, 1111 Pennsylvania Avenue Matagorda County, Texas mitigation. Based on this discussion, the NW., Washington, DC 20004.

proposed amendment does not increase the NRC Branch Chief: Michael T.

Date of amendment request: May 15, probability or consequence of an accident Markley.

2014, as supplemented by letter dated previously evaluated.

July 10, 2014. Publicly-available 2. Does the proposed amendment create III. Notice of Issuance of Amendments versions are in ADAMS under the possibility of a new or different kind of to Facility Operating Licenses and accident from any accident previously Combined Licenses Accession Nos. ML14164A341 and evaluated?

ML14282A185, respectively. Response: No. During the period since publication of Description of amendment request: The change revises the STPNOC the last biweekly notice, the The amendment would update the Emergency Action Levels to be consistent Commission has issued the following Emergency Action Levels (EALs) used at with the NRC endorsed EAL scheme amendments. The Commission has STP, Units 1 and 2 from the current contained in NEI 99-01, Revision 6, determined for each of these scheme based on Nuclear Management Methodology for Development of Emergency Action Levels, but does not alter amendments that the application and Resources Council, Inc. complies with the standards and any of the requirements of the Operating (NUMARC)/Nuclear Environmental License or the Technical Specifications. In requirements of the Atomic Energy Act Studies Project (NESP) report addition to replacing the current STP EALs, of 1954, as amended (the Act), and the NUMARC/NESP-007, Revision 2, the new EAL scheme includes an EAL related Commissions rules and regulations.

Methodology for Development of to the planned STP Independent Spent Fuel The Commission has made appropriate Emergency Action Levels, dated Storage Installation, and EALs related to findings as required by the Act and the January 1992 (ADAMS Accession No. planned changes to the Spent Fuel Pool level Commissions rules and regulations in ML041120174), to the NRC-endorsed instrumentation that will address lessons 10 CFR Chapter I, which are set forth in scheme contained in Nuclear Energy learned from Fukushima Daiichi. The proposed change does not modify any plant the license amendment.

Institute (NEI) 99-01, Revision 6, A notice of consideration of issuance equipment and there is no impact on the Development of Emergency Action capability of the existing equipment to of amendment to facility operating Levels for Non-Passive Reactors, dated perform their intended functions. No system license or combined license, as November 2012 (ADAMS Accession No. setpoints are being modified. No new failure applicable, proposed no significant ML12326A805). The EAL scheme in NEI modes are introduced by the proposed hazards consideration determination, 99-01, Revision 6 includes an EAL for change. The proposed amendment does not and opportunity for a hearing in Independent Spent Fuel Storage introduce any accident initiators or connection with these actions, was asabaliauskas on DSK4SPTVN1PROD with NOTICES Installations (ISFSI), which is needed in malfunctions that would cause a new or published in the Federal Register as order to implement dry cask storage different kind of accident. Therefore, the indicated.

proposed amendment does not create the operations at STP Units 1 and 2. Unless otherwise indicated, the possibility of a new or different kind of Additionally, there are three EALs that accident from any accident previously Commission has determined that these require Spent Fuel Pool level evaluated. amendments satisfy the criteria for instrument values which are designed to 3. Does the proposed amendment involve categorical exclusion in accordance address lessons learned from the a significant reduction in a margin of safety? with 10 CFR 51.22. Therefore, pursuant Fukushima Dai-ichi accident. Response: No. to 10 CFR 51.22(b), no environmental VerDate Sep<11>2014 20:06 Oct 27, 2014 Jkt 235001 PO 00000 Frm 00067 Fmt 4703 Sfmt 4703 E:\FR\FM\28OCN1.SGM 28OCN1

64230 Federal Register / Vol. 79, No. 208 / Tuesday, October 28, 2014 / Notices impact statement or environmental the application as originally noticed, Date of issuance: September 29, 2014.

assessment need be prepared for these and did not change the staffs original Effective date: As of the date of amendments. If the Commission has proposed no significant hazards issuance. For LSCS Unit 1, the prepared an environmental assessment consideration determination as amendment shall be implemented prior under the special circumstances published in the Federal Register. to entering MODE 4 following the spring provision in 10 CFR 51.22(b) and has The Commissions related evaluation 2016 refueling outage (L1R16). For made a determination based on that of the amendment is contained in a LSCS, Unit 2, the amendment shall be assessment, it is so indicated. Safety Evaluation dated October 10, implemented prior to entering MODE 4 For further details with respect to the 2014. following the spring 2015 refueling action see (1) the applications for No significant hazards consideration outage (L2R15).

amendment, (2) the amendment, and (3) comments received: No. Amendment No.: 209 and 196. A the Commissions related letter, Safety Entergy Nuclear Operations, Inc., publicly-available version is in ADAMS Evaluation and/or Environmental Docket No. 50-333, James A. FitzPatrick under Accession No. ML14252A913; Assessment as indicated. All of these Nuclear Power Plant, Oswego County, documents related to these amendments items can be accessed as described in New York are listed in the Safety Evaluation the Obtaining Information and enclosed with the amendment.

Submitting Comments section of this Date of amendment request: May 1, Facility Operating License Nos. NPF-document. 2014, as supplemented by letter dated 11 and NPF-18: Amendment revised the August 21, 2014. Facility Operating License and Duke Energy Progress, Inc., Docket No. Brief description of amendment: The Technical Specifications.

50-261, H. B. Robinson Steam Electric amendment revises Technical Date of initial notice in Federal Plant (HBRSEP), Unit 2, Darlington Specification 2.0, Safety Limits (SLs), Register: December 10, 2013 (78 FR County, South Carolina by changing the safety limit minimum 74182). The supplemental letter dated Date of application for amendment: critical power ratio for both single and June 30, 2014, provided additional September 30, 2013, as supplemented dual recirculation loop operation. information that clarified the by letter dated August 6, 2014. Date of issuance: September 30, 2014. application, did not expand the scope of Brief description of amendment: The Effective date: As of the date of the application as originally noticed, amendment implements the NRC- issuance, and shall be implemented and did not change the staffs original approved Technical Specification Task within [30] days.

Amendment No.: 307. A publicly- proposed no significant hazards Force (TSTF) Standard Technical consideration determination as available version is in ADAMS under Specification Change Traveler, TSTF- published in the Federal Register.

Accession No. ML14258B201; 491, Removal of Main Steam and Main The Commissions related evaluation documents related to this amendment Feedwater Valve Isolation Times from of the amendment is contained in a are listed in the Safety Evaluation Technical Specifications, via the Safety Evaluation dated September 29, enclosed with the amendment.

Consolidated Line Item Improvement Renewed Facility Operating License 2014.

Process. This amendment modifies the No significant hazards consideration No. DPR-59: The amendment revised current Technical Specifications (TSs) comments received: No.

the License and the Technical 3.7.2, Main Steam Isolation Valves and Specifications. Exelon Generation Company, LLC, 3.7.3, Main Feedwater Isolation Valves, Date of initial notice in Federal Docket No. 50-289, Three Mile Island Main Feedwater Regulation Valves and Register: August 5, 2014 (79 FR 45487). Nuclear Station, Unit (TMI-1), Dauphin Bypass Valves by relocating the specific The supplemental letter dated August County, Pennsylvania isolation time for the isolation valves 21, 2014, provided additional from the associated Surveillance Date of application for amendment:

information that clarified the Requirements (SRs). The isolation time May 7, 2014.

application, did not expand the scope of Brief description of amendment: The in the TS SRs is replaced with the the application as originally noticed, requirement to verify the valve isolation amendment revises Technical and did not change the NRC staffs time is within limits. The specific Specification (TS) Surveillance original proposed no significant hazards isolation times will be maintained in the Requirements (SRs) 4.12.1, Emergency consideration (NSHC) determination as HBRSEP, Unit 2, Technical Control Room Air Treatment System, published in the Federal Register.

Requirements Manual. The Commissions related evaluation and 4.12.4, Fuel Handling Building Date of issuance: October 10, 2014. of the amendment and final NSHC [Engineered Safety Feature] ESF Air Effective date: As of the date of determination is contained in a Safety Treatment System. The amendment issuance and shall be implemented Evaluation dated September 30, 2014. revised the TSs to replace the existing within 120 days of issuance. No significant hazards consideration SRs to operate ventilation systems with Amendment No.: 237. A publicly- comments received. No. charcoal filters for a 10-hour period at available version is in ADAMS under a frequency controlled in accordance Accession No. ML14252A221; Exelon Generation Company, LLC, with the Surveillance Frequency documents related to this amendment Docket Nos. 50-373 and 50-374, LaSalle Control Program (SFCP) with a are listed in the Safety Evaluation County Station (LSCS), Units 1 and 2, requirement to operate the systems for enclosed with the amendment. LaSalle County, Illinois greater than or equal to 15 continuous Renewed Facility Operating License minutes at a frequency controlled in asabaliauskas on DSK4SPTVN1PROD with NOTICES Date of amendment request:

No. DPR-23. Amendment revised the September 20, 2013, as supplemented accordance with the SFCP. These Facility Operating License and TSs. by letter dated June 30, 2014. changes are consistent with Technical Date of initial notice in Federal Brief description of amendment: The Specification Task Force (TSTF)

Register: December 10, 2013 (78 FR amendment revised the LSCS, Units 1 Traveler TSTF-522, Revision 0, Revise 74180). The supplemental letter dated and 2, allowable values for the loss of Ventilation System Surveillance August 6, 2014, provided additional voltage relay voltage setpoints in Requirements to Operate for 10 hours0.417 days <br />0.0595 weeks <br />0.0137 months <br /> information that clarified the Technical Specification Table 3.3.8.1-1, per Month.

application, did not expand the scope of Loss of Power Instrumentation. Date of issuance: October 14, 2014.

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Federal Register / Vol. 79, No. 208 / Tuesday, October 28, 2014 / Notices 64231 Effective date: As of its date of No significant hazards consideration documents related to these amendments issuance, and shall be implemented comments received: No. are listed in the Safety Evaluation within 60 days. enclosed with the amendments.

Southern Nuclear Operating Company Facility Combined Licenses Nos. NPF-Amendment No.: 282. A publicly-Docket Nos.52-025 and 52-026, Vogtle 91 and NPF-92: Amendment revised the available version is in ADAMS under Electric Generating Plant (VEGP), Units Facility Combined Licenses.

Accession No. ML14240A348; 3 and 4, Burke County, Georgia Date of initial notice in Federal documents related to this amendment are listed in the Safety Evaluation Date of amendment request: April 18, Register: May 13, 2014 (79 FR 27345).

enclosed with the amendment. 2014, as supplemented by the letter The Commissions related evaluation Renewed Facility Operating License dated July 30, 2014. of the amendment is contained in a No. DPR-50: Amendment revised the Brief description of amendment: The Safety Evaluation dated October 7, 2014.

license amendment revises the Updated No significant hazards consideration license and the technical specifications.

Final Safety Analysis Report (UFSAR) comments received: No.

Date of initial notice in Federal Register: August 5, 2014 (79 FR 45476). in regard to Tier 2* information related Tennessee Valley Authority, Docket The Commissions related evaluation to fire area boundaries. These changes Nos. 50-327 and 50-328, Sequoyah of the amendment is contained in a add three new fire zones in the middle Nuclear Plant, Units 1 and 2, Hamilton Safety Evaluation dated October 14, annulus to provide enclosures for the County, Tennessee 2014. Class 1E electrical containment penetrations in accordance with UFSAR Date of amendment request: April 29, No significant hazards consideration 2014. A redacted version was provided comments received: No. Appendix 9A, Subsection 9A.3.1.1.15.

Additionally, the license amendment by letter dated May 27, 2014.

Indiana Michigan Power Company, Brief description of amendment: The revises UFSAR Tier 2 information Docket Nos. 50-315 and 50-316, Donald amendments revised the Cyber Security involving changes to plant-specific Tier C. Cook Nuclear Plant (CNP), Units 1 Plan Implementation Milestone No. 8 2* information. completion date and the physical and 2, Berrien County, Michigan Date of issuance: October 8, 2014.

protection license condition.

Date of amendment requests: April 9, Effective date: As of the date of Date of issuance: September 29, 2014.

2014, as supplemented by letter dated issuance and shall be implemented Effective date: As of its date of August 15, 2014. within 30 days of issuance. issuance and shall be implemented Brief description of amendments: The Amendment No.: 25. A publicly- within 60 days.

amendments revised the CNP Technical available version is in ADAMS under Amendment Nos.: Unit 1-333 and Specifications (TSs) 3.4.3, [Reactor Accession No. ML14248A243; Unit 2-326. A publicly-available version Coolant System] RCS Pressure and documents related to this amendment is in ADAMS under Accession No.

Temperature Limits. The changes to are listed in the Safety Evaluation ML14245A179; documents related to TSs clarify that pressure limits are enclosed with the amendment. these amendments are listed in the Facility Combined Licenses No. NPF- Safety Evaluation enclosed with the considered to be met for pressures that 91 and NPF-92: Amendment revised the amendments.

are below 0 psig (i.e., up to and Facility Combined Licenses. Facility Operating License Nos. DPR-including full vacuum conditions).

Date of initial notice in Federal 77 and DPR-79. The amendments Vacuum fill operations for the RCS can Register: May 27, 2014 (79 FR 30189). revised the Operating License.

result in system pressures below 0 psig.

The Commissions related evaluation Date of initial notice in Federal Date of issuance: October 1, 2014. of the amendment is contained in a Effective date: As of the date of Register: July 8, 2014 (79 FR 38582).

Safety Evaluation dated October 8, 2014. The supplemental letter dated May 27, issuance and shall be implemented No significant hazards consideration within 60 days of issuance. 2014, provided additional information comments received: No. that clarified the application, did not Amendment Nos.: 323 (Unit 1) and Southern Nuclear Operating Company, expand the scope of the application as 306 (Unit 2). A publicly-available Docket Nos.52-025 and 52-026, Vogtle originally noticed, and did not change version is in ADAMS under Accession Electric Generating Plant (VEGP) Units the staffs original proposed no No. ML14259A549; documents related 3 and 4, Burke County, Georgia significant hazards consideration to these amendments are listed in the determination as published in the Safety Evaluation enclosed with the Date of amendment request: March Federal Register.

amendments. 27, 2014, as supplemented by the letter The Commissions related evaluation Facility Operating License Nos. DPR- dated July 23, 2014. of the amendment is contained in a 58 and DPR-74: Amendments revise the Brief description of amendment: The Safety Evaluation dated September 29, Facility Operating Licenses and amendment revises the VEGP Units 3 2014.

Technical Specifications. and 4 Emergency Plan and changes the No significant hazards consideration Date of initial notice in Federal combined licenses (COL), Appendix C, comments received: No.

Register: July 8, 2014 (79 FR 38591). plant-specific emergency planning The supplemental letter dated August inspections, tests, analyses, and Tennessee Valley Authority, Docket 15, 2014, provided additional acceptance criteria (ITAAC) to reflect Nos. 50-327 and 50-328, Sequoyah information that clarified the the relocation of the Operations Support Nuclear Plant (SQN), Units 1 and 2, application, did not expand the scope of Hamilton County, Tennessee asabaliauskas on DSK4SPTVN1PROD with NOTICES Centers and changes the description of the application as originally noticed, the plant monitoring system. Date of amendment request: April 29, and did not change the staffs original Date of issuance: October 7, 2014 2014. A redacted version was provided proposed no significant hazards Effective date: As of the date of by letter dated May 27, 2014.

consideration determination as issuance and shall be implemented Brief description of amendment: The published in the Federal Register. within 30 days of issuance. amendments revised the Cyber Security The Commissions related evaluation Amendment No.: 24. A publicly- Plan Implementation Milestone No. 8 of the amendment is contained in a available version is in ADAMS under completion date and the physical Safety Evaluation dated October 1, 2014. Accession No. ML14245A075; protection license condition.

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64232 Federal Register / Vol. 79, No. 208 / Tuesday, October 28, 2014 / Notices Date of issuance: September 29, 2014. The Commissions related evaluation Week of November 17, 2014Tentative Effective date: As of its date of of the amendment is contained in the SE dated September 29, 2014. Thursday, November 20, 2014 issuance and shall be implemented within 60 days. No significant hazards consideration 9:30 a.m. Briefing on Project Aim 2020 Amendment Nos.: Unit 1-333 and comments received: No. (ClosedEx. 2)

Unit 2-326. A publicly-available version Dated at Rockville, Maryland, this 16th day is in ADAMS under Accession No. of October 2014. Week of November 24, 2014Tentative ML14245A179; documents related to For the Nuclear Regulatory Commission. There are no meetings scheduled for these amendments are listed in the Michele G. Evans, the week of November 24, 2014.

Safety Evaluation enclosed with the Director, Division of Operating Reactor amendments. Licensing, Office of Nuclear Reactor Week of December 1, 2014Tentative Facility Operating License Nos. DPR- Regulation.

77 and DPR-79. The amendments [FR Doc. 2014-25357 Filed 10-27-14; 8:45 am]

There are no meetings scheduled for revised the Operating License. the week of December 1, 2014.

BILLING CODE 7590-01-P Date of initial notice in Federal * * * *

• Register: July 8, 2014 (79 FR 38582). The schedule for Commission The supplemental letter dated May 27, NUCLEAR REGULATORY meetings is subject to change on short 2014, provided additional information COMMISSION notice. For more information or to verify that clarified the application, did not the status of meetings, contact Glenn expand the scope of the application as [NRC-2014-0001]

Ellmers at (301) 415-0442 or via email originally noticed, and did not change at Glenn.Ellmers@nrc.gov.

the staffs original proposed no Sunshine Act Meeting Notice significant hazards consideration * * * *

• DATE: Weeks of October 27, November 3, determination as published in the The NRC Commission Meeting 10, 17, 24, December 1, 2014.

Federal Register. Schedule can be found on the Internet PLACE: Commissioners Conference The Commissions related evaluation at: http://www.nrc.gov/public-involve/

of the amendment is contained in a Room, 11555 Rockville Pike, Rockville, public-meetings/schedule.html.

Safety Evaluation dated September 29, Maryland.

2014. STATUS: Public and Closed.

The NRC provides reasonable No significant hazards consideration Week of October 27, 2014 comments received: No. accommodation to individuals with Wednesday, October 29, 2014 disabilities where appropriate. If you Tennessee Valley Authority, Docket No. need a reasonable accommodation to 50-390 Watts Bar Nuclear Plant, Unit 1, 9:00 a.m. Briefing on Security Issues (ClosedEx. 1) participate in these public meetings, or Rhea County, Tennessee need this meeting notice or the 1:30 p.m. Briefing on Security Issues Date of amendment request: April 29, (ClosedEx. 1) transcript or other information from the 2014, as supplemented by letter dated public meetings in another format (e.g.

May 27, 2014. Thursday, October 30, 2014 braille, large print), please notify Brief description of amendment: The 9:00 a.m. Briefing on Watts Bar Unit 2 Kimberly Meyer, NRC Disability amendment revised the Cyber Security License Application Review (Public Program Manager, at 301-287-0727, by Plan Implementation Milestone No. 8 Meeting) (Contact: Justin Poole, videophone at 240-428-3217, or by completion date and the physical 301-415-2048) email at Kimberly.Meyer-Chambers@

protection license condition. This meeting will be webcast live at nrc.gov . Determinations on requests for Date of issuance: September 29, 2014. the Web addresshttp://www.nrc.gov/ . reasonable accommodation will be Effective date: As of its date of made on a case-by-case basis.

Week of November 3, 2014Tentative issuance and shall be implemented * * * *

• within 30 days of issuance. Wednesday, November 5, 2014 Members of the public may request to Amendment No.: 97. A publicly- 1:00 p.m. Briefing on Small Modular receive this information electronically.

available version is in ADAMS under Reactors (Public Meeting) (Contact: If you would like to be added to the Accession No. ML14255A152; Rollie D. Berry, III, 301-415-8162) distribution, please contact the Office of documents related to this amendment This meeting will be webcast live at the Secretary, Washington, DC 20555 are listed in the Safety Evaluation (SE) the Web addresshttp://www.nrc.gov/ .

enclosed with the amendment. (301-415-1969), or send an email to Week of November 10, 2014Tentative Patricia.Jimenez@nrc.gov or Facility Operating License No. NPF-Brenda.Akstulewicz@nrc.gov.

90. Amendment revised the Operating Thursday, November 13, 2014 License. Dated: October 23, 2014.

Date of initial notice in Federal 9:30 a.m. Strategic Programmatic Glenn Ellmers, Register: July 8, 2014 (79 FR 38581). Overview of the Nuclear Material Policy Coordinator, Office of the Secretary.

The supplemental letter dated May 27, Users and the Fuel Facilities asabaliauskas on DSK4SPTVN1PROD with NOTICES Business Lines (Public Meeting) [FR Doc. 2014-25721 Filed 10-24-14; 4:15 pm]

2014, provided additional information that clarified the application, did not (Contact: Cinthya Roman, 301-287- BILLING CODE 7590-01-P expand the scope of the application as 9091) originally noticed, and did not change This meeting will be webcast live at the staffs original proposed no the Web addresshttp://www.nrc.gov/ .

significant hazards consideration 1:30 p.m. Discussion of Management determination as published in the and Personnel Issues (ClosedEx. 2 Federal Register. and 6)

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