ML15223A318

NRC000191- Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations, 79 Fed. Reg. 15144 (Mar. 18, 2014)

ML15223A318
Person / Time
Site:	Indian Point
Issue date:	03/18/2014
From:	NRC/OGC
To:	Atomic Safety and Licensing Board Panel
SECY RAS
References
RAS 28156, ASLBP 07-858-03-LR-BD01, 50-247-LR, 50-286-LR
Download: ML15223A318 (14)

Text

NRC000191 Submitted: August 10, 2015 15144 Federal Register / Vol. 79, No. 52 / Tuesday, March 18, 2014 / Notices

• evaluate the accuracy of the

SUMMARY

The National Science Antarctic Specially Protected Area No.

agencys estimate of the burden of the Foundation (NSF) is required to publish 152, Western Bransfield Strait (Area proposed collection of information, a notice of permit applications received around Low Island).

including the validity of the to conduct activities regulated under the Dates methodology and assumptions used; Antarctic Conservation Act of 1978.

• enhance the quality, utility and NSF has published regulations under June 21, 2014 to October 21, 2014.

clarity of the information to be the Antarctic Conservation Act at Title Nadene G. Kennedy, collected; and 45 Part 670 of the Code of Federal

• minimize the burden of the Polar Coordination Specialist, Division of Regulations. This is the required notice Polar Programs.

collection of information on those who of permit applications received.

are to respond, including through the [FR Doc. 2014-05881 Filed 3-17-14; 8:45 am]

DATES: Interested parties are invited to use of appropriate automated, submit written data, comments, or BILLING CODE 7555-01-P electronic, mechanical, or other views with respect to this permit technological collection techniques or application by April 17, 2014. This other forms of information technology, application may be inspected by NUCLEAR REGULATORY e.g., permitting electronic submissions interested parties at the Permit Office, COMMISSION of responses. address below. [NRC-2014-0045]

III. Current Actions: The Department ADDRESSES: Comments should be of Labor seeks the approval for the addressed to Permit Office, Room 755, Biweekly Notice; Applications and extension of this currently approved Division of Polar Programs, National Amendments to Facility Operating information collection in order to Science Foundation, 4201 Wilson Licenses and Combined Licenses ensure the accurate payment of benefits Boulevard, Arlington, Virginia 22230. Involving No Significant Hazards to current and former Federal FOR FURTHER INFORMATION CONTACT: Considerations employees with recurring work-related Polly Penhale, ACA Permit Officer, at injuries. Background the above address or ACApermits@

Type of Review: Extension. Pursuant to Section 189a. (2) of the nsf.gov or (703) 292-7420.

Agency: Office of Workers Atomic Energy Act of 1954, as amended Compensation Programs. SUPPLEMENTARY INFORMATION: The National Science Foundation, as (the Act), the U.S. Nuclear Regulatory

Title:

Notice of Recurrences OMB Number: 1240-0009. directed by the Antarctic Conservation Commission (NRC) is publishing this Agency Number: CA-2a. Act of 1978 (Pub. L.95-541), as regular biweekly notice. The Act Affected Public: Individuals or amended by the Antarctic Science, requires the Commission to publish households. Tourism and Conservation Act of 1996, notice of any amendments issued, or Total Respondents: 258. has developed regulations for the proposed to be issued and grants the Total Annual Responses: 258. establishment of a permit system for Commission the authority to issue and Average Time per Response: 30 various activities in Antarctica and make immediately effective any minutes. designation of certain animals and amendment to an operating license or Estimated Total Burden Hours: 129. certain geographic areas a requiring combined license, as applicable, upon a Frequency: Annually. special protection. The regulations determination by the Commission that Total Burden Cost (capital/startup): establish such a permit system to such amendment involves no significant

$0. designate Antarctic Specially Protected hazards consideration, notwithstanding Total Burden Cost (operating/ Areas. the pendency before the Commission of maintenance): $126. a request for a hearing from any person.

Comments submitted in response to Application Details This biweekly notice includes all this notice will be summarized and/or 1. Applicant: Permit Application: 2014- notices of amendments issued, or included in the request for Office of 030 proposed to be issued from March 5 to Management and Budget approval of the Prof. Chi-Hing Christina Cheng March 18, 2014. The last biweekly information collection request; they will Department of Animal Biology, notice was published on March 4, 2014 also become a matter of public record. University of Illinois, Urbana- (79 FR 12241).

Dated: March 10, 2014. Champaign, IL ADDRESSES: You may submit comments Yoon Ferguson, Activity for Which Permit Is Requested by any of the following methods (unless Agency Clearance Officer, Office of Workers ASPA, Import into USA: This permit this document describes a different Compensation Programs, US Department of method for submitting comments on a Labor.

would allow entry into ASPA 153 Eastern Dallmann Bay and ASPA 152 specific subject):

[FR Doc. 2014-05981 Filed 3-17-14; 8:45 am]

Western Bransfield Strait for the

• Federal Rulemaking Web site: Go to BILLING CODE 4510-CH-P purpose of collecting a small number of http://www.regulations.gov and search icefish species via trawling and trapping for Docket ID NRC-2014-0045. Address for a study on freezing avoidance and questions about NRC dockets to Carol NATIONAL SCIENCE FOUNDATION evolutionary cold adaptation in Gallagher; telephone: 301-287-3422; Antarctic fishes. Some whole, frozen email: Carol.Gallagher@nrc.gov. For Notice of Permit Applications Received individuals as well as tissue samples technical questions, contact the emcdonald on DSK67QTVN1PROD with NOTICES Under the Antarctic Conservation Act would be imported back into the U.S.A. individual listed in the FOR FURTHER of 1978 (Pub. L.95-541) for physiological, biochemical, and INFORMATION CONTACT section of this AGENCY: National Science Foundation. molecular studies. Port of Entry is Port document.

Hueneme, CA.

• Mail comments to: Cindy Bladey, ACTION: Notice of Permit Applications Chief, Rules, Announcements, and Received Under the Antarctic Location Directives Branch (RADB), Office of Conservation Act of 1978, Public Law Antarctic Specially Protected Area Administration, Mail Stop: 3WFN 95-541.

No. 153, Eastern Dallmann Bay; and 44M, U.S. Nuclear Regulatory VerDate Mar<15>2010 18:34 Mar 17, 2014 Jkt 232001 PO 00000 Frm 00050 Fmt 4703 Sfmt 4703 E:\FR\FM\18MRN1.SGM 18MRN1

Federal Register / Vol. 79, No. 52 / Tuesday, March 18, 2014 / Notices 15145 Commission, Washington, DC 20555- identifying or contact information that the need to take this action will occur 0001. they do not want to be publicly very infrequently.

For additional direction on accessing disclosed in their comment submission. Within 60 days after the date of information and submitting comments, Your request should state that the NRC publication of this notice, any person(s) see Accessing Information and does not routinely edit comment whose interest may be affected by this Submitting Comments in the submissions to remove such information action may file a request for a hearing SUPPLEMENTARY INFORMATION section of before making the comment and a petition to intervene with respect this document. submissions available to the public or to issuance of the amendment to the SUPPLEMENTARY INFORMATION: entering the comment submissions into subject facility operating license or ADAMS. combined license. Requests for a I. Accessing Information and hearing and a petition for leave to Submitting Comments Notice of Consideration of Issuance of intervene shall be filed in accordance Amendments to Facility Operating with the Commissions Agency Rules A. Accessing Information Licenses and Combined Licenses, of Practice and Procedure in 10 CFR Please refer to Docket ID NRC-2014- Proposed No Significant Hazards Part 2. Interested person(s) should 0045 when contacting the NRC about Consideration Determination, and consult a current copy of 10 CFR 2.309, the availability of information regarding Opportunity for a Hearing which is available at the NRCs PDR, this document. You may access The Commission has made a located at One White Flint North, Room publicly-available information related to proposed determination that the O1-F21, 11555 Rockville Pike (first this action by the following methods: following amendment requests involve floor), Rockville, Maryland 20852. The

• Federal Rulemaking Web site: Go to no significant hazards consideration. NRC regulations are accessible http://www.regulations.gov and search Under the Commissions regulations in electronically from the NRC Library on for Docket ID NRC-2014-0045. § 50.92 of Title 10 of the Code of Federal the NRCs Web site at http://

• NRCs Agencywide Documents Regulations (10 CFR), this means that www.nrc.gov/reading-rm/doc-Access and Management System operation of the facility in accordance collections/cfr/. If a request for a hearing (ADAMS): You may access publicly with the proposed amendment would or petition for leave to intervene is filed available documents online in the NRC not (1) involve a significant increase in by the above date, the Commission or a Library at http://www.nrc.gov/reading- the probability or consequences of an presiding officer designated by the rm/adams.html. To begin the search, accident previously evaluated; or (2) Commission or by the Chief select ADAMS Public Documents and create the possibility of a new or Administrative Judge of the Atomic then select Begin Web-based ADAMS different kind of accident from any Safety and Licensing Board Panel, will Search. For problems with ADAMS, accident previously evaluated; or (3) rule on the request and/or petition; and please contact the NRCs Public involve a significant reduction in a the Secretary or the Chief Document Room (PDR) reference staff at margin of safety. The basis for this Administrative Judge of the Atomic 1-800-397-4209, 301-415-4737, or by proposed determination for each Safety and Licensing Board will issue a email to pdr.resource@nrc.gov. The amendment request is shown below. notice of a hearing or an appropriate ADAMS accession number for each The Commission is seeking public order.

document referenced in this document comments on this proposed As required by 10 CFR 2.309, a (if that document is available in determination. Any comments received petition for leave to intervene shall set ADAMS) is provided the first time that within 30 days after the date of forth with particularity the interest of a document is referenced. publication of this notice will be the petitioner in the proceeding, and

• NRCs PDR: You may examine and considered in making any final how that interest may be affected by the purchase copies of public documents at determination. results of the proceeding. The petition the NRCs PDR, Room O1-F21, One Normally, the Commission will not should specifically explain the reasons White Flint North, 11555 Rockville issue the amendment until the why intervention should be permitted Pike, Rockville, Maryland 20852. expiration of 60 days after the date of with particular reference to the publication of this notice. The following general requirements: (1) the B. Submitting Comments Commission may issue the license name, address, and telephone number of Please include Docket ID NRC-2014- amendment before expiration of the 60- the requestor or petitioner; (2) the 0045 in the subject line of your day period provided that its final nature of the requestors/petitioners comment submission, in order to ensure determination is that the amendment right under the Act to be made a party that the NRC is able to make your involves no significant hazards to the proceeding; (3) the nature and comment submission available to the consideration. In addition, the extent of the requestors/petitioners public in this docket. Commission may issue the amendment property, financial, or other interest in The NRC cautions you not to include prior to the expiration of the 30-day the proceeding; and (4) the possible identifying or contact information that comment period should circumstances effect of any decision or order which you do not want to be publicly change during the 30-day comment may be entered in the proceeding on the disclosed in your comment submission. period such that failure to act in a requestors/petitioners interest. The The NRC posts all comment timely way would result, for example in petition must also identify the specific submissions at http:// derating or shutdown of the facility. contentions which the requestor/

www.regulations.gov as well as entering Should the Commission take action petitioner seeks to have litigated at the emcdonald on DSK67QTVN1PROD with NOTICES the comment submissions into ADAMS. prior to the expiration of either the proceeding.

The NRC does not routinely edit comment period or the notice period, it Each contention must consist of a comment submissions to remove will publish in the Federal Register a specific statement of the issue of law or identifying or contact information. notice of issuance. Should the fact to be raised or controverted. In If you are requesting or aggregating Commission make a final No Significant addition, the requestor/petitioner shall comments from other persons for Hazards Consideration Determination, provide a brief explanation of the bases submission to the NRC, then you should any hearing will take place after for the contention and a concise inform those persons not to include issuance. The Commission expects that statement of the alleged facts or expert VerDate Mar<15>2010 18:34 Mar 17, 2014 Jkt 232001 PO 00000 Frm 00051 Fmt 4703 Sfmt 4703 E:\FR\FM\18MRN1.SGM 18MRN1

15146 Federal Register / Vol. 79, No. 52 / Tuesday, March 18, 2014 / Notices opinion which support the contention To comply with the procedural considered complete at the time the and on which the requestor/petitioner requirements of E-Filing, at least 10 documents are submitted through the intends to rely in proving the contention days prior to the filing deadline, the NRCs E-Filing system. To be timely, an at the hearing. The requestor/petitioner participant should contact the Office of electronic filing must be submitted to must also provide references to those the Secretary by email at the E-Filing system no later than 11:59 specific sources and documents of hearing.docket@nrc.gov, or by telephone p.m. Eastern Time on the due date.

which the petitioner is aware and on at 301-415-1677, to request (1) a digital Upon receipt of a transmission, the E-which the requestor/petitioner intends identification (ID) certificate, which Filing system time-stamps the document to rely to establish those facts or expert allows the participant (or its counsel or and sends the submitter an email notice opinion. The petition must include representative) to digitally sign confirming receipt of the document. The sufficient information to show that a documents and access the E-Submittal E-Filing system also distributes an email genuine dispute exists with the server for any proceeding in which it is notice that provides access to the applicant on a material issue of law or participating; and (2) advise the document to the NRCs Office of the fact. Contentions shall be limited to Secretary that the participant will be General Counsel and any others who matters within the scope of the submitting a request or petition for have advised the Office of the Secretary amendment under consideration. The hearing (even in instances in which the that they wish to participate in the contention must be one which, if participant, or its counsel or proceeding, so that the filer need not proven, would entitle the requestor/ representative, already holds an NRC- serve the documents on those petitioner to relief. A requestor/ issued digital ID certificate). Based upon participants separately. Therefore, petitioner who fails to satisfy these this information, the Secretary will applicants and other participants (or requirements with respect to at least one establish an electronic docket for the their counsel or representative) must contention will not be permitted to hearing in this proceeding if the apply for and receive a digital ID participate as a party. Secretary has not already established an certificate before a hearing request/

Those permitted to intervene become electronic docket. petition to intervene is filed so that they parties to the proceeding, subject to any Information about applying for a can obtain access to the document via limitations in the order granting leave to digital ID certificate is available on the the E-Filing system.

intervene, and have the opportunity to NRCs public Web site at http:// A person filing electronically using participate fully in the conduct of the www.nrc.gov/site-help/e-submittals/ the agencys adjudicatory E-Filing hearing. apply-certificates.html. System system may seek assistance by If a hearing is requested, the requirements for accessing the E- contacting the NRC Meta System Help Commission will make a final Submittal server are detailed in the Desk through the Contact Us link determination on the issue of no NRCs Guidance for Electronic located on the NRC Web site at http://

significant hazards consideration. The Submission, which is available on the www.nrc.gov/site-help/e-final determination will serve to decide agencys public Web site at http:// submittals.html, by email to when the hearing is held. If the final www.nrc.gov/site-help/e- MSHD.Resource@nrc.gov, or by a toll-determination is that the amendment submittals.html. Participants may free call at 1-866-672-7640. The NRC request involves no significant hazards attempt to use other software not listed Meta System Help Desk is available consideration, the Commission may on the Web site, but should note that the between 8 a.m. and 8 p.m., Eastern issue the amendment and make it NRCs E-Filing system does not support Time, Monday through Friday, immediately effective, notwithstanding unlisted software, and the NRC Meta excluding government holidays.

the request for a hearing. Any hearing System Help Desk will not be able to Participants who believe that they held would take place after issuance of offer assistance in using unlisted have a good cause for not submitting the amendment. If the final software. documents electronically must file an determination is that the amendment If a participant is electronically exemption request, in accordance with request involves a significant hazards submitting a document to the NRC in 10 CFR 2.302(g), with their initial paper consideration, then any hearing held accordance with the E-Filing rule, the filing requesting authorization to would take place before the issuance of participant must file the document continue to submit documents in paper any amendment. 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 emcdonald on DSK67QTVN1PROD 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 the NRC by courier, express mail, or expedited unless they seek an exemption in guidance available on the NRCs public delivery service upon depositing the accordance with the procedures Web site at http://www.nrc.gov/site- document with the provider of the described below. help/e-submittals.html. A filing is service. A presiding officer, having VerDate Mar<15>2010 18:34 Mar 17, 2014 Jkt 232001 PO 00000 Frm 00052 Fmt 4703 Sfmt 4703 E:\FR\FM\18MRN1.SGM 18MRN1

Federal Register / Vol. 79, No. 52 / Tuesday, March 18, 2014 / Notices 15147 granted an exemption request from Description of amendment request: tube, as the failure of a tube is not an initiator using E-Filing, may require a participant The proposed amendment would revise for any of these events. In the supporting or party to use E-Filing if the presiding Technical Specification (TS) 5.5.7, Westinghouse analyses, leakage is modeled as flow through a porous medium via the use officer subsequently determines that the Steam Generator (SG) Program, to of the Darcy equation. The leakage model is reason for granting the exemption from exclude portions of the SG tube below used to develop a relationship between use of E-Filing no longer exists. the top of the SG tubesheet from allowable leakage and leakage at accident Documents submitted in adjudicatory periodic inspections and plugging by conditions that is based on differential proceedings will appear in the NRCs implementing the H* alternate repair pressure across the tubesheet and the electronic hearing docket which is criteria. In addition, TS 5.6.7, Steam viscosity of the fluid. A leak rate ratio was available to the public at http://ehd1. Generator Tube Inspection Report, developed to relate the leakage at operating nrc.gov/ehd/;, unless excluded pursuant would also be revised to include conditions to leakage at accident conditions.

The fluid viscosity is based on fluid to an order of the Commission, or the additional reporting requirements.

temperature and it has been shown that for presiding officer. Participants are Basis for proposed no significant the most limiting accident, the fluid requested not to include personal hazards consideration determination: temperature does not exceed the normal privacy information, such as social As required by 10 CFR 50.91(a), the operating temperature. Therefore, the security numbers, home addresses, or licensee has provided its analysis of the viscosity ratio is assumed to be 1.0 and the home phone numbers in their filings, issue of no significant hazards leak rate ratio is a function of the ratio of the unless an NRC regulation or other law consideration, which is presented accident differential pressure and the normal requires submission of such below: operating differential pressure.

The leakage factor of 1.75 for IP2 for a-information. However, a request to 1. Does the proposed amendment involve postulated MSLB, has been calculated as intervene will require including a significant increase in the probability or shown in the supporting Westinghouse information on local residence in order consequences of an accident previously analysis. IP2 [Indian Point Unit 2] will apply to demonstrate a proximity assertion of evaluated? a factor of 1.75 to the normal operating interest in the proceeding. With respect Response: No. leakage associated with the tubesheet The proposed change excludes the lower to copyrighted works, except for limited portion of steam generator tubes from expansion region in the Condition excerpts that serve the purpose of the Monitoring Assessment and Operational inspection by implementing the alternate adjudicatory filings and would Assessment. Through application of the repair criteria H* and does not have a constitute a Fair Use application, limited tubesheet inspection scope, the detrimental impact on the integrity of any administrative leakage limit of 75 gpd participants are requested not to include plant structure, system, or component that

[gallons per day] provides assurance that copyrighted materials in their initiates an analyzed event. The proposed excessive leakage (i.e., greater than accident submission. change has no significant effect upon analysis assumptions) will not occur. No Petitions for leave to intervene must accident probabilities or consequences.

leakage factor will be applied to the Locked Of the applicable accidents previously be filed no later than 60 days from the evaluated, the limiting transients with Rotor or Control Rod Ejection due to their date of publication of this notice. short duration, since the calculated leak rate consideration to the proposed change to the Requests for hearing, petitions for leave steam generator tube inspection and repair ratio is less than 1.0. Therefore, the proposed to intervene, and motions for leave to criteria are the steam generator tube rupture change does not result in a significant increase in the consequences of these file new or amended contentions that (SGTR), the main steam line break (MSLB),

Locked Rotor and Control Rod Ejection. accidents.

are filed after the 60-day deadline will For the Condition Monitoring Assessment, not be entertained absent a At normal operating pressures, leakage from Primary Water Stress Corrosion the component of leakage from the prior determination by the presiding officer cycle from below the H* distance will be Cracking (PWSCC) below the proposed that the filing demonstrates good cause limited inspection depth is limited by both multiplied by a factor of 1.75 and added to by satisfying the three factors in 10 CFR the tube-to-tubesheet crevice and the limited the total leakage from any other source and 2.309(c)(1)(i)-(iii). crack opening permitted by the tubesheet compared to the allowable MSLB leakage For further details with respect to this constraint. Consequently, negligible normal limit. For the Operational Assessment, the license amendment application, see the operating leakage is expected from cracks difference in the leakage between the within the tubesheet region. allowable leakage and the accident induced application for amendment which is For the SGTR event, the required structural leakage from sources other than the tubesheet available for public inspection at the expansion region will be divided by 1.75 and NRCs PDR, located at One White Flint integrity margins of the steam generator tubes and the tube-to-tubesheet joint over the H* compared to the observed operational North, Room O1-F21, 11555 Rockville distance will be maintained. Tube rupture in leakage. As noted above, an administrative Pike (first floor), Rockville, Maryland tubes with cracks within the tubesheet is limit of 75 gpd has been established at IP2 20852. Publicly available documents precluded by the constraint provided by the to assure that the allowable accident induced created or received at the NRC are tube-to-tubesheet joint. This constraint leakage is not exceeded.

accessible electronically through results from the hydraulic expansion process, Based on the above, the performance ADAMS in the NRC Library at http:// thermal expansion mismatch between the criteria of NEI 97-06 and Regulatory Guide tube and tubesheet, and from the differential (RG) 1.121 continue to be met and the www.nrc.gov/reading-rm/adams.html.

pressure between the primary and secondary proposed change does not involve a Persons who do not have access to significant increase in the probability or side. The structural margins against burst, as ADAMS or who encounter problems in discussed in Regulatory Guide (RG) 1.121, consequences of an accident previously accessing the documents located in Bases for Plugging Degraded PWR Steam evaluated.

ADAMS, should contact the NRCs PDR Generator Tubes, (Reference 11) and NEI 2. Does the proposed amendment create Reference staff at 1-800-397-4209, 301- 97-06, Steam Generator Program the possibility of a new or different kind of emcdonald on DSK67QTVN1PROD with NOTICES 415-4737, or by email to pdr.resource@ Guidelines (Reference 3) are maintained for accident from any accident previously nrc.gov. both normal and postulated accident evaluated?

Entergy Nuclear Operations, Inc., conditions. Therefore, the proposed change Response: No.

results in no significant increase in the The proposed change excludes the lower Docket No. 50-247, Indian Point portion of steam generator tubes from probability of the occurrence of a SGTR Nuclear Generating, Unit 2, Westchester accident. inspection by implementing the alternate County, New York The probability of a Steam Line Break, repair criteria (H*). The proposed change Date of amendment request: January Locked Rotor, and Control Rod Ejection are does not introduce any new equipment, 16, 2014. not affected by the potential failure of a SG create new failure modes for existing VerDate Mar<15>2010 18:34 Mar 17, 2014 Jkt 232001 PO 00000 Frm 00053 Fmt 4703 Sfmt 4703 E:\FR\FM\18MRN1.SGM 18MRN1

15148 Federal Register / Vol. 79, No. 52 / Tuesday, March 18, 2014 / Notices equipment, or create any new limiting single NRC Branch Chief: Benjamin G. are performed by plant staff during all plant failures resulting from tube degradation. The Beasley. conditions.

proposed change does not affect the design Entergy Nuclear Operations, Inc., Therefore, the proposed change does not of the SGs or their method of operation. In Docket No. 50-255, Palisades Nuclear create the possibility of a new or different addition, the proposed change does not kind of accident from any previously Plant, Van Buren County, Michigan evaluated.

impact any other plant system or component.

Date of amendment request: June 25, 3. Does the proposed change involve a Plant operation will not be altered, and all safety functions will continue to perform as 2013, supplemented by letter dated significant reduction in a margin of safety?

previously assumed in accident analyses. August 7, 2013. Response: No.

Therefore, the proposed change does not Description of amendment request: The proposed change does not affect plant create the possibility of a new or different The proposed amendment would revise design or method of operation. Section kind of accident from any previously Palisades Nuclear Plant Site Emergency 50.47(b) and 10 CFR Part 50, Appendix E evaluated. Plan (SEP) to increase the staff establish emergency planning standards and

3. Does the proposed amendment involve augmentation response times for certain requirements that require adequate staffing, a significant reduction in a margin of safety? Emergency Response Organization satisfactory performance of key functional Response: No. areas and critical tasks, and timely positions from 30 to 60 minutes. Entergy The proposed change defines the safety augmentation of the response capability.

significant portion of the SG tubing that must Nuclear Organization has reviewed the Since the SEP was originally developed, be inspected and repaired. WCAP-17828-P proposed changes against the standards there have been improvements in the identifies the inspection depth below which in § 50.47(b) and the requirements in 10 technology used to support the SEP functions any type of degradation is shown to have no CFR Part 50, Appendix E. and in the capabilities of onsite personnel. A impact on the steam generator tube integrity Basis for proposed no significant functional analysis was performed on the performance criteria in NEI 97-06. The hazards consideration determination: effect of the proposed change on the proposed change does not affect tube design As required by 10 CFR 50.91(a), the timeliness of performing major tasks for the or operating environment. The proposed licensee has provided its analysis of the functional areas of SEP. The analysis change will continue to require monitoring of issue of no significant hazards concluded that an increase in staff the physical condition of the SG tubes but augmentation times would not significantly consideration, which is presented will limit inspection within the tubesheet to affect the ability to perform the required SEP the portion of the tube from the top of the below: tasks. Thus, the proposed change has been tubesheet to a distance H* below the top of 1. Does the proposed change involve a determined not to adversely affect the ability the tubesheet. significant increase in the probability or to meet the emergency planning standards as The proposed change maintains the consequences of an accident previously described in 10 CFR 50.47(b) and required structural margins of the SG tubes evaluated? requirements in 10 CFR Part 50, Appendix E.

for both normal and accident conditions. For Response: No. Therefore, the proposed change does not axially oriented cracking located within the The proposed extension of staff involve a significant reduction in a margin of tubesheet, tube burst is precluded due to the augmentation times has no effect on normal safety.

presence of the tubesheet. For plant operation or on any accident initiator.

The change affects the response to The NRC staff has reviewed the circumferentially oriented cracking, the supporting Westinghouse analyses define a radiological emergencies under the Palisades licensees analysis and, based on this length of degradation-free expanded tubing Nuclear Plant SEP. The ability of the review, it appears that the three that provides the necessary resistance to tube emergency response organization to respond standards of 10 CFR 50.92(c) are pullout due to the pressure induced forces, adequately to radiological emergencies has satisfied. Therefore, the NRC staff with applicable safety factors applied. been evaluated. Changes in the on-shift proposes to determine that the Application of the limited hot and cold leg organization, such as the addition of staff and amendment request involves no tubesheet inspection criteria will preclude reassignment of key on-shift emergency significant hazards consideration.

unacceptable primary to secondary leakage response functions, provide assurance of Attorney for licensee: William Dennis, during all plant conditions. The MSLB leak emergency response without competing or conflicting duties. An analysis was also Assistant General Counsel, Entergy rate factor for IP2 is 1.75. Multiplying the IP2 Nuclear Operations, Inc., 440 Hamilton administrative leak rate limit of 75 gpd/SG by performed on the effect of the proposed this factor shows that the primary-to- change on the timeliness of performing major Ave., White Plains, NY 10601.

secondary leak rate during a postulated SLB tasks for the major functional areas of the NRC Branch Chief: Robert D. Carlson.

is not exceeded. SEP. The analysis concluded that extension Entergy Nuclear Operations, Inc.,

Therefore, the proposed change does not of staff augmentation times would not Docket No. 50-255, Palisades Nuclear involve a significant reduction in any margin significantly affect the ability to perform the Plant, Van Buren County, Michigan of safety. required tasks. Date of amendment request:

Based on the above, Entergy concludes that Therefore, the proposed change does not December 11, 2013.

the proposed amendment to the Indian Point involve a significant increase in the Description of amendment request:

2 Technical Specifications presents no probability or consequences of an accident The proposed amendment would significant hazards consideration under the previously evaluated. modify Palisades Nuclear Plant standards set forth in 10 CFR 50.92(c), and 2. Does the proposed change create the possibility of a new or different kind of technical specifications (TS) accordingly, a finding of no significant requirements for unavailable barriers by hazards consideration is justified. accident from any accident previously evaluated? adding limiting condition for operation The NRC staff has reviewed the Response: No. (LCO) 3.0.9. The changes are consistent licensees analysis and, based on this The proposed change affects the required with the NRCs approved industry/

review, it appears that the three response times for supplementing onsite Technical Specification Task Force standards of 10 CFR 50.92(c) are personnel in response to a radiological (TSTF) Standard Technical emcdonald on DSK67QTVN1PROD with NOTICES satisfied. Therefore, the NRC staff emergency. It has been evaluated and Specification (STS) change TSTF-427, proposes to determine that the determined not to significantly affect the Allowance for Non-Technical ability to perform that function. It has no amendment request involves no Specification Barrier Degradation on effect on the plant design or on the normal significant hazards consideration. operation of the plant and does not affect Supported System OPERABILITY, Attorney for licensee: Jeanne Cho, how the plant is physically operated under Revision 2.

Assistant General Counsel, Entergy emergency conditions. The extension of staff Basis for proposed no significant Nuclear Operations, Inc., 440 Hamilton augmentation times in the SEP does not hazards consideration determination:

Avenue, White Plains, NY 10601. affect the plant operating procedures which The licensee has affirmed the VerDate Mar<15>2010 18:34 Mar 17, 2014 Jkt 232001 PO 00000 Frm 00054 Fmt 4703 Sfmt 4703 E:\FR\FM\18MRN1.SGM 18MRN1

Federal Register / Vol. 79, No. 52 / Tuesday, March 18, 2014 / Notices 15149 applicability of the model proposed postulated initiating events which may assuring the availability of the ultimate heat non-significant hazards consideration require a functional barrier are limited to sink and core cooling. As such, the proposed published on October 2, 2006 (71 FR those with low frequencies of occurrence, change does not increase the consequences of and the overall TS system safety function an accident previously evaluated.

58444), as part of the Consolidated Line would still be available for the majority of In addition, implementing this strategy Item Improvement Process, Notice of anticipated challenges. The risk impact of the eliminates the need for the exterior sluice Availability of the Model Safety proposed TS changes was assessed following gates to be safety class and allows for Evaluation. The licensee has the three-tiered approach recommended in continuous control of the intake cell level concluded that the findings presented in RG 1.177. A bounding risk assessment was during a design basis flood event. The that evaluation are applicable to PNP performed to justify the proposed TS proposed Updated Safety Analysis Report and is hereby referenced below: changes. This application of LCO 3.0.9 is (USAR) changes for implementing predicated upon the licensees performance modification EC 55394 allow for maintaining Criterion 1The Proposed Change Does Not of a risk assessment and the management of RW pump operation during a flooding event Involve a Significant Increase in the plant risk. The net change to the margin of at FCS.

Probability or Consequences of an Accident safety is insignificant as indicated by the Therefore, the proposed change does not Previously Evaluated anticipated low levels of associated risk involve a significant increase in the The proposed change allows a delay time (ICCDP and ICLERP) as shown in Table 1 of probability or consequences of an accident for entering a supported system technical Section 3.1.1 in the Safety Evaluation. previously evaluated.

specification (TS) when the inoperability is Therefore, this change does not involve a 2. Does the proposed amendment create due solely to an unavailable barrier if risk is significant reduction in a margin of safety. the possibility of a new or different kind of assessed and managed. The postulated accident from any accident previously The NRC staff has reviewed the initiating events which may require a evaluated?

licensees analysis and, based on this Response: No.

functional barrier are limited to those with low frequencies of occurrence, and the review, it appears that the three The proposed modification EC 55394 to overall TS system safety function would still standards of 10 CFR 50.92(c) are provide control of the intake cell level by be available for the majority of anticipated satisfied. Therefore, the NRC staff operation of the manual valves and the challenges. Therefore, the probability of an proposes to determine that the associated USAR changes do not alter the accident previously evaluated is not amendment request involves no safety limits or safety analysis assumptions significantly increased, if at all. The significant hazards consideration. associated with the operation of the plant.

consequences of an accident while relying on Attorney for licensee: William Dennis, Hence, the proposed changes do not the allowance provided by proposed LCO introduce any new accident initiators, nor do Assistant General Counsel, Entergy 3.0.9 are no different than the consequences they reduce or adversely affect the of an accident while relying on the TS Nuclear Operations, Inc., 440 Hamilton capabilities of any plant structure or system required actions in effect without the Ave., White Plains, NY 10601. in the performance of their safety function.

allowance provided by proposed LCO 3.0.9. NRC Branch Chief: Robert D. Carlson. The proposed amendment revises the USAR Therefore, the consequences of an accident Omaha Public Power District, Docket to include the necessary information to previously evaluated are not significantly No. 50-285, Fort Calhoun Station, Unit support the implementation of the affected by this change. The addition of a 1, Washington County, Nebraska modification allowing for maintaining RW requirement to assess and manage the risk Date of amendment request: August pump operation during an abnormal introduced by this change will further 16, 2013. operating procedure AOP-01 flooding event minimize possible concerns. Description of amendment request: at FCS.

Therefore, this change does not involve a The proposed amendment would revise Therefore, the proposed change does not significant increase in the probability or create the possibility of a new or different the design basis method in the Fort consequences of an accident previously kind of accident from any previously evaluated. Calhoun Station Updated Safety Analysis Report for controlling the raw evaluated.

Criterion 2The Proposed Change Does Not 3. Does the proposed amendment involve water intake cell level during periods of a significant reduction in a margin of safety?

Create the Possibility of a New or Different Kind of Accident from any Previously elevated river levels. Response: No.

Evaluated Basis for proposed no significant The proposed modification, which hazards consideration determination: provides control of the intake cell level by The proposed change does not involve a physical alteration of the plant (no new or As required by 10 CFR 50.91(a), the operation of the manual valves, and the different type of equipment will be installed). licensee has provided its analysis of the associated USAR changes do not alter the Allowing delay times for entering supported issue of no significant hazards safety limits or safety analysis assumptions system TS when inoperability is due solely consideration, which is presented associated with the operation of the plant.

to an unavailable barrier, if risk is assessed below: The proposed modification and associated and managed, will not introduce new failure USAR revisions ensure there is adequate

1. Does the proposed amendment involve protection to the RW pumps from an external modes or effects and will not, in the absence a significant increase in the probability or flood hazard thus assuring adequate of other unrelated failures, lead to an consequences of an accident previously protection during a flood. Providing RW accident whose consequences exceed the evaluated? pump intake cell level control during consequences of accidents previously Response: No. flooding conditions allows for adjustment of evaluated. The addition of a requirement to assess and manage the risk introduced by this The proposed modification engineering flow and control of the intake cell level change will further minimize possible change (EC) 55394, Raw Water [RW] Pump throughout the duration of the flood since the concerns. Operation and Safety Classification of new valves are located inside the intake Thus, this change does not create the Components during a Flood, installed intake structure; thereby ensuring the RW pumps possibility of a new or different kind of cell flood water inlet valves at Fort Calhoun remain operable during a flood condition and accident from an accident previously Station (FCS). The modification would will not adversely impact any margin of emcdonald on DSK67QTVN1PROD with NOTICES evaluated. employ the trash rack blowdown portion of safety.

the circulating water system to allow river Therefore, the proposed change does not Criterion 3The Proposed Change Does Not water to flow into four of those pipes and involve a significant reduction in a margin of Involve a Significant Reduction in the Margin then through four newly installed safety class safety.

of Safety. valves for control of cell level (RW pump The proposed change allows a delay time suction level) using river level as the driving The NRC staff has reviewed the for entering a supported system TS when the force. This modification EC 55394 enhances licensees analysis and, based on this inoperability is due solely to an unavailable the flood protection provided to the RW review, it appears that the three barrier, if risk is assessed and managed. The pumps for an external flooding event thus standards of 10 CFR 50.92(c) are VerDate Mar<15>2010 18:34 Mar 17, 2014 Jkt 232001 PO 00000 Frm 00055 Fmt 4703 Sfmt 4703 E:\FR\FM\18MRN1.SGM 18MRN1

15150 Federal Register / Vol. 79, No. 52 / Tuesday, March 18, 2014 / Notices satisfied. Therefore, the NRC staff thermal conductivity and oxidation crack exclusion allowance to Final proposes to determine that the progression and effects for the inorganic zinc Safety Analysis Report (FSAR) Standard amendment request involves no coating of the containment vessel is used to Plant Section 3.6.2.1.2.4, ASME eliminate non-mechanistic modeling of significant hazards consideration. inorganic zinc thermal conductivity in the

[American Society of Mechanical Attorney for licensee: David A. Repka, containment integrity analyses to show that Engineers] Section III and Non-Nuclear Esq., Winston & Strawn, 1700 K Street the value for inorganic zinc thermal Piping-Moderate-Energy, and FSAR NW., Washington, DC 20006-3817. conductivity used in the containment Standard Plant Table 3.6-2, Design NRC Branch Chief: Michael T. integrity analyses is conservative, but is not Comparison to Regulatory Positions of Markley. used to change any of the parameters used in Regulatory Guide 1.46, Revision 0, Southern Nuclear Operating the containment peak pressure analysis. The dated May 1973, titled Protection Company, Inc. Docket Nos.52-025 and change in methodology does not change the Against Pipe Whip Inside 52-026, Vogtle Electric Generating condition of containment; therefore, no new accident initiator is created. The containment Containment, in particular regard to Plant, Units 3 and 4, Burke County, the high-density polyethylene (HDPE) peak pressure analysis as currently evaluated Georgia is not affected, and the consequences piping installed in ASME Class 3 line Date of amendment request: previously reported are not changed. The segments of the essential service water November 21, 2013. new methodology does not change the (ESW) system. New Reference 25 would Description of amendment request: containment; therefore, no new fault or be added to FSAR Standard Plant The proposed change would amend sequence of events that could lead to Section 3.6.3 to cite the NRC-approved Combined License Nos. NPF-91 and containment failure or release of radioactive version of the HDPE requirements NPF-92 for the Vogtle Electric material is created.

covered by Relief Request I3R-10.

Generating Plant (VEGP) Units 3 and 4 Therefore, the proposed amendment does by departing from the approved AP1000 not create the possibility of a new or different Basis for proposed no significant Design Control Document (DCD) Tier 2 kind of accident. hazards consideration determination:

3. Does the proposed amendment involve As required by 10 CFR 50.91(a), the information as incorporated into the a significant reduction in a margin of safety?

Updated Final Safety Analysis Report licensee has provided its analysis of the Response: No.

(UFSAR) to allow use of a new issue of no significant hazards The proposed implementation of a methodology to determine the effective methodology which specifies an effective consideration, which is presented thermal conductivity resulting from thermal conductivity and oxidation below:

oxidation of the inorganic zinc (IOZ) progression and effects for the inorganic zinc 1. Does the proposed change involve a used in the containment vessel coating coating of the containment vessel is used to significant increase in the probability or system. eliminate non-mechanistic modeling of consequences of an accident previously inorganic zinc thermal conductivity in the evaluated?

Basis for proposed no significant containment integrity analyses to show that Response: No.

hazards consideration determination: the value for inorganic zinc thermal There are no new design changes As required by 10 CFR 50.91(a), the conductivity used in the containment associated with the proposed amendment.

licensee has provided its analysis of the integrity analyses is conservative, but is not All design, material, and construction issue of no significant hazards used to change any of the parameters used in standards that were applicable prior to this consideration, which is presented the containment peak pressure analysis. The amendment request, including those below: change in methodology does not change the standards in place following the NRC condition of the containment and the approval of using the HDPE piping, will

1. Does the proposed amendment involve integrity of the containment vessel is not a significant increase in the probability or continue to be applicable.

affected. The containment peak pressure The proposed change will not increase the consequences of an accident previously analysis as currently evaluated is not evaluated? likelihood of accident initiators or precursors affected, and the consequences previously or adversely alter the design assumptions, Response: No. reported are not changed. No safety analysis Implementation of a methodology which conditions, and configuration of the facility or design basis acceptance limit/criterion is or the manner in which the plant is operated specifies an effective thermal conductivity changed by the proposed change, thus no and oxidation progression for the inorganic and maintained with respect to such margin of safety is reduced. initiators or precursors.

zinc coating of the containment vessel is used to eliminate non-mechanistic modeling Therefore, the proposed amendment The proposed changes do not affect the of inorganic zinc thermal conductivity in the does not reduce the margin of safety. way in which safety-related systems perform containment integrity analyses to show that The NRC staff has reviewed the their functions.

the value for inorganic zinc thermal licensees analysis and, based on this All accident analysis acceptance criteria conductivity used in the containment review, it appears that the three will continue to be met with the proposed integrity analyses is conservative, but is not changes. The proposed changes will not standards of 10 CFR 50.92(c) are affect the source term, containment isolation, used to change any of the parameters used in those analyses. There is no change to any satisfied. Therefore, the NRC staff or radiological release assumptions used in accident initiator or condition of the proposes to determine that the evaluating the radiological consequences of containment that would affect the probability amendment request involves no an accident previously evaluated. The of any accident. The containment peak significant hazards consideration. proposed changes will not alter any pressure analysis as reported in the UFSAR Attorney for licensee: M. Stanford assumptions or change any mitigation actions is not affected; therefore, the previously Blanton, Balch & Bingham LLP, 1710 in the radiological consequence evaluations reported consequences are not affected. Sixth Avenue North, Birmingham, AL in the FSAR.

Therefore, the proposed amendment does 35203-2015. The applicable radiological dose not involve an increase in the probability or NRC Branch Chief: Lawrence J. acceptance criteria will continue to be met.

emcdonald on DSK67QTVN1PROD with NOTICES consequences of an accident previously Since the proposed change is based on a Burkhart.

evaluated. calculation that demonstrates that a moderate Union Electric Company, Docket No. energy crack in the ESW HDPE piping is

2. Does the proposed amendment create the possibility of a new or different kind of 50-483, Callaway Plant, Unit 1, unlikely, there are no impacts on the plants accident from any accident previously Callaway County, Missouri existing hazard analyses.

evaluated? Date of amendment request: The proposed change does not physically Response: No. December 6, 2013. alter safety-related systems or affect the way The proposed amendment to implement a Description of amendment request: in which safety-related systems perform their methodology which specifies an effective The amendment would add a new pipe functions per the intended plant design.

VerDate Mar<15>2010 18:34 Mar 17, 2014 Jkt 232001 PO 00000 Frm 00056 Fmt 4703 Sfmt 4703 E:\FR\FM\18MRN1.SGM 18MRN1

Federal Register / Vol. 79, No. 52 / Tuesday, March 18, 2014 / Notices 15151 As such, the proposed change will not alter review, it appears that the three 2. Does the proposed amendment create or prevent the capability of structures, standards of 10 CFR 50.92(c) are the possibility of a new or different kind of systems, and components (SSCs) to perform satisfied. Therefore, the NRC staff accident from any accident previously their intended functions for mitigating the evaluated?

proposes to determine that the consequences of an accident and meeting Response: No.

applicable acceptance limits. amendment request involves no The proposed changes will not alter the Therefore, the proposed change does not significant hazards consideration. requirement or function for systems required involve a significant increase in the Attorney for licensee: John ONeill, during accident conditions. The design probability or consequences of an accident Esq., Pillsbury Winthrop Shaw Pittman function of structures, systems and previously evaluated. LLP, 2300 N Street NW., Washington, components are not impacted by the

2. Does the proposed change create the DC 20037. proposed change. Evaluation SA-08-006 and possibility of a new or different kind of NRC Branch Chief: Michael T. Calculation WCNOC-CP-003 determined accident from any accident previously Markley. natural circulation is maintained and evaluated? Wolf Creek Nuclear Operating adequate core cooling is maintained. The Response: No. Corporation, Docket No. 50-482, Wolf fission product boundary integrity is not With respect to any new or different kind affected and safe shutdown capability is Creek Generating Station, Coffey of accident, there are no new design changes maintained.

being proposed nor are there any changes in County, Kansas Date of amendment request: Therefore, the proposed change does not the method by which any safety-related plant create the possibility of a new or different SSC performs its specified safety function. November 21, 2013.

kind of accident from any accident The proposed change will not affect the Description of amendment request: previously evaluated.

normal method of plant operation. No new The amendment would revise the 3. Does the proposed amendment involve transient precursors will be introduced as a approved Fire Protection Program as a significant reduction in a margin of safety?

result of this amendment. described in the Updated Safety Response: No.

The HDPE piping design change was Analysis Report, based on the reactor There will be no effect on the manner in previously approved by the NRC under Relief coolant system thermal hydraulic which safety limits or limiting safety system Request I3R-10. The proposed change in this settings are determined nor will there be any response evaluation of a postulated amendment request does not create the effect on those plant systems necessary to possibility of a new type of accident, rather control room fire, performed for changes to the alternative shutdown assure the accomplishment of protection the proposed change seeks to eliminate the functions. The revised alternative shutdown need to postulate an existing type of hazard methodology.

methodology provides the ability to achieve event (moderate energy piping leakage crack) Basis for proposed no significant and maintain safe shutdown in the event of for the subject HDPE piping which has been hazards consideration determination: a fire. Evaluation SA-08-006 and Calculation shown to experience such low stresses that As required by 10 CFR 50.91(a), the WCNOC-CP-003 determined natural such a crack, and the potential flooding for licensee has provided its analysis of the circulation is maintained and adequate core that hazard event, need not be postulated. issue of no significant hazards cooling is maintained.

The change does not have a detrimental consideration, which is presented Therefore, the proposed change does not impact on the manner in which plant involve a significant reduction in a margin of equipment operates or responds to an below:

safety.

actuation signal. 1. Does the proposed amendment involve The proposed change does not, therefore, a significant increase in the probability or The NRC staff has reviewed the create the possibility of a new or different consequences of an accident previously licensees analysis and, based on this accident from any accident previously evaluated? review, it appears that the three evaluated. Response: No. standards of 10 CFR 50.92(c) are

3. Does the proposed change involve a The design function of structures, systems satisfied. Therefore, the NRC staff significant reduction in a margin of safety? and components (SSCs) are not impacted by Response: No. the proposed deviations from [10 CFR Part proposes to determine that the There will be no effect on those plant 50] Appendix R, Sections III.L.1 and III.L.2, amendment request involves no systems necessary to assure the and Calculation XX-E-013. The proposed significant hazards consideration.

accomplishment of protection functions changes to the approved fire protection Attorney for licensee: Jay Silberg, Esq.,

associated with reactor operation or the program are based on the RCS [reactor Pillsbury Winthrop Shaw Pittman LLP, reactor coolant system. The design factor coolant system] thermal-hydraulic response 2300 N Street NW., Washington, DC (DF) of 0.50 discussed in ULNRC-05553 (Evaluation SA-08-006) for a postulated 20037.

dated October 9, 2008 has not changed. This control room fire performed for changes to NRC Branch Chief: Michael T.

DF was approved by the NRC in Relief the alternative shutdown methodology outlined in letter SLNRC 84-0109, Fire Markley.

Request 13R-10 (Reference 6.2 to this Evaluation). There will be no impact on the Protection Review. Drawing E-1F9915, Wolf Creek Nuclear Operating overpower limit, departure from nucleate Design Basis Document for OFN RP-017, Corporation, Docket No. 50-482, Wolf boiling ratio (DNBR) limits, heat flux hot Control Room Evacuation, Revision 5, Creek Generating Station, Coffey channel factor (FQ), nuclear enthalpy rise hot Evaluation SA-08-006, RETRAN-3D Post- County, Kansas channel factor (FDH), loss of coolant accident Fire Safe Shutdown (PFSSD) Consequence Date of amendment request:

peak cladding temperature (LOCA PCT), peak Evaluation for a Postulated Control Room December 17, 2013.

local power density, or any other limit and Fire, Revision 3, and Calculation WCNOC- Description of amendment request:

associated margin of safety. Required CP-003, VIPRE-01 MDNBR Analyses of Control Room Fire Scenarios, Revision 0 The amendment would revise Technical shutdown margins in the COLR [core Specification Surveillance Requirement operating limits report] will not be changed. demonstrate the adequacy of the revised The proposed change does not eliminate any alternative shutdown procedure, OFN RF- (SR) 3.7.10.1 and SR 3.7.13.1 to reduce surveillances or alter the frequency of 017. The proposed changes do not alter or the required run time for periodic emcdonald on DSK67QTVN1PROD with NOTICES surveillances required by the Technical prevent the ability of SSCs from performing operation of the control room Specifications. their intended function to mitigate the pressurization system filter trains and As such, the proposed change does not consequences of an initiating event within emergency exhaust system filter trains, involve a significant reduction in a margin of the assumed acceptance limits. with heaters on, from 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> to 15 safety as defined in any regulatory Therefore, the probability of any accident previously evaluated is not increased. minutes. The proposed amendment is requirement or guidance document. consistent with plant-specific options Equipment required to mitigate an accident The NRC staff has reviewed the remains capable of performing the assumed provided in the NRCs model safety licensees analysis and, based on this function. evaluation of Technical Specifications VerDate Mar<15>2010 18:34 Mar 17, 2014 Jkt 232001 PO 00000 Frm 00057 Fmt 4703 Sfmt 4703 E:\FR\FM\18MRN1.SGM 18MRN1

15152 Federal Register / Vol. 79, No. 52 / Tuesday, March 18, 2014 / Notices Task Force (TSTF) Traveler TSTF-522- proposed change is consistent with (PDR), located at One White Flint North, A, Revision 0, Revise Ventilation regulatory guidance. Room O1-F21, 11555 Rockville Pike System Surveillance Requirements to Therefore, it is concluded that this change (first floor), Rockville, Maryland 20852.

does not involve a significant reduction in a Operate for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> per Month. Publicly available documents created or margin of safety.

Basis for proposed no significant received at the NRC are accessible hazards consideration determination: The NRC staff has reviewed the electronically through the Agencywide As required by 10 CFR 50.91(a), the licensees analysis and, based on this Documents Access and Management licensee has provided its analysis of the review, it appears that the three System (ADAMS) in the NRC Library at issue of no significant hazards standards of 10 CFR 50.92(c) are http://www.nrc.gov/reading-rm/

consideration, which is presented satisfied. Therefore, the NRC staff adams.html. If you do not have access below: proposes to determine that the to ADAMS or if there are problems in amendment request involves no accessing the documents located in

1. Does the proposed change involve a significant hazards consideration.

significant increase in the probability or ADAMS, contact the PDRs Reference Attorney for licensee: Jay Silberg, Esq., staff at 1-800-397-4209, 301-415-4737 consequences of an accident previously evaluated?

Pillsbury Winthrop Shaw Pittman LLP, or by email to pdr.resource@nrc.gov.

Response: No. 2300 N Street NW., Washington, DC Dominion Nuclear Connecticut, Inc.,

The proposed change replaces existing 20037. Docket No. 50-423, Millstone Power Surveillance Requirements to operate the NRC Branch Chief: Michael T. Station, Unit 3, New London County, Control Room Emergency Ventilation System Markley. Connecticut (CREVS) and the Emergency Exhaust System Date of amendment request: October (EES) for a continuous 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> period with Notice of Issuance of Amendments to Facility Operating Licenses and 4, 2012, as supplemented by letters applicable heaters operating every 31 days, with requirements to operate these systems Combined Licenses dated January 4, April 17, and October for 15 continuous minutes with applicable 30, 2013.

During the period since publication of Description of amendment request:

heaters operating every 31 days. the last biweekly notice, the These systems are not accident initiators The proposed amendment would Commission has issued the following modify Technical Specifications by (i.e., their malfunction cannot initiate an accident or transient) and therefore, these amendments. The Commission has relocating specific surveillance changes do not involve a significant increase determined for each of these frequencies to a licensee controlled in the probability of an accident. The amendments that the application program with the adoption of Technical proposed system and filter testing changes complies with the standards and Specification Task Force (TSTF)-425, are consistent with current regulatory requirements of the Atomic Energy Act Revision 3, Relocate Surveillance guidance for these systems and will continue of 1954, as amended (the Act), and the to assure that these systems perform their Frequencies to Licensee Control[Risk-Commissions rules and regulations. Informed Technical Specification Task design function which may include The Commission has made appropriate mitigating accidents. Therefore, the change Force (RITSTF)] Initiative 5b.

findings as required by the Act and the Additionally, the change would add a does not involve a significant increase in the consequences of an accident. Commissions rules and regulations in new program, the Surveillance Therefore, it is concluded that this change 10 CFR Chapter I, which are set forth in Frequency Control Program (SFCP), to does not involve a significant increase in the the license amendment. Technical Specification Section 6, probability or consequences of an accident A notice of consideration of issuance Administrative Controls.

previously evaluated. of amendment to facility operating Date of issuance: February 25, 2014.

2. Does the proposed change create the license or combined license, as Effective date: As of the date of possibility of a new or different kind of applicable, proposed no significant issuance, and shall be implemented accident from any accident previously hazards consideration determination, evaluated? within 90 days.

and opportunity for a hearing in Amendment No.: 258.

Response: No.

The change proposed for these ventilation connection with these actions, was Renewed Facility Operating License systems does not change any system published in the Federal Register as No. NPF-49: Amendment revised the operations or maintenance activities. Testing indicated. License and Technical Specifications.

requirements will be revised and will Unless otherwise indicated, the Date of initial notice in Federal continue to demonstrate that the Limiting Commission has determined that these Register: December 11, 2012 (77 FR Conditions for Operation are met and the amendments satisfy the criteria for 73687).

system components are capable of categorical exclusion in accordance The supplemental letters dated performing their intended safety functions. with 10 CFR 51.22. Therefore, pursuant January 4, 2013, April 17, 2013, and The change does not create new failure to 10 CFR 51.22(b), no environmental October 30, 2013, provided additional modes or mechanisms and no new accident impact statement or environmental precursors are generated.

information that clarified the Therefore, it is concluded that this change assessment need be prepared for these application, did not expand the scope of does not create the possibility of a new or amendments. If the Commission has the application as originally noticed, different kind of accident from any accident prepared an environmental assessment and did not change the staffs original previously evaluated. under the special circumstances proposed no significant hazards

3. Does the proposed change involve a provision in 10 CFR 51.22(b) and has consideration determination.

significant reduction in a margin of safety? made a determination based on that The Commissions related evaluation Response: No. assessment, it is so indicated. of the amendment is contained in a emcdonald on DSK67QTVN1PROD with NOTICES The design basis for the ventilation system For further details with respect to the Safety Evaluation dated February 25, heaters in the EES and in the pressurization action see (1) the applications for 2014.

trains of the CREVS includes the capability amendment, (2) the amendment, and (3) No significant hazards consideration to heat the incoming air, reducing the relative humidity (and thereby increasing adsorber the Commissions related letter, Safety comments received: No.

efficiency). The heater testing change Evaluation and/or Environmental Duke Energy Carolinas, LLC, Docket proposed will continue to demonstrate that Assessment as indicated. All of these Nos. 50-369 and 50-370, McGuire the heaters are capable of heating the air and items are available for public inspection Nuclear Station, Units 1 and 2, will thus perform their design function. The at the NRCs Public Document Room Mecklenburg County, North Carolina VerDate Mar<15>2010 18:34 Mar 17, 2014 Jkt 232001 PO 00000 Frm 00058 Fmt 4703 Sfmt 4703 E:\FR\FM\18MRN1.SGM 18MRN1

Federal Register / Vol. 79, No. 52 / Tuesday, March 18, 2014 / Notices 15153 Date of application for amendments: The Commissions related evaluation heatup and cooldown curves (also April 16, 2013. of the amendments is contained in a referred to as pressure-temperature (P-Brief description of amendments: The Safety Evaluation dated February 27, T) limits) and low temperature amendments remove superseded 2014. overpressure protection (LTOP) temporary Technical Specification (TS) No significant hazards consideration requirements to cover a lifetime burnup requirements for McGuire Nuclear comments received: No. of 48 Effective Full Power Years (EFPY),

Station (MNS), Units 1 and 2, in Duke Energy Progress Inc., Docket which is an increase from the current accordance with a licensee commitment Nos. 50-325 and 50-324, Brunswick value of 29.2 EFPY.

described in a May 28, 2010, license Steam Electric Plant, Units 1 and 2, Date of issuance: March 5, 2014.

amendment request. Brunswick County, North Carolina. Effective date: As of the date of Date of issuance: February 28, 2014. Date of application for amendments: issuance, and shall be implemented Effective date: This license June 19, 2012, as supplemented by within 30 days.

amendment is effective as of its date of letters dated January 21, May 14, and Amendment No.: 274.

issuance and shall be implemented August 29, 2013, and January 22, 2014. Facility Operating License No. DPR-within 60 days of issuance. Brief description of amendments: The 26: The amendment revised the License Amendment Nos.: 272 and 252. amendments revised the Technical and the Technical Specifications.

Renewed Facility Operating License Specification (TS) to extend the Date of initial notice in Federal Nos. NPF-9 and NPF-17: Amendments Completion Time (CT) of TS 3.8.1 Register: April 2, 2013 (78 FR 19750).

revised the licenses and technical Required Action D.4 for an inoperable The supplemental letters dated July 9, specifications. diesel generator. A commensurate 2013, October 3, 2013, and February 24, Date of initial notice in Federal change is also made to extend the 2014, provided additional information Register: June 25, 2013 (78 FR 38081). maximum CT of TS 3.8.1 Required that clarified the application, did not The Commissions related evaluation Actions C.3 and D.4. The licensee will expand the scope of the application as of the amendments is contained in a to add a supplemental AC power source originally noticed, and did not change Safety Evaluation dated February 28, (i.e., a supplemental diesel generator) the NRC staffs original proposed no 2014. with the capability to power any significant hazards consideration No significant hazards consideration emergency bus within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from a determination as published in the comments received: No. Station Blackout event, and with the Federal Register.

Duke Energy Carolinas, LLC, Docket capacity to bring the affected unit to The Commissions related evaluation Nos. 50-269, 50-270, and 50-287, cold shutdown. of the amendment is contained in a Oconee Nuclear Station, Units 1, 2 and Date of issuance: February 24, 2014. Safety Evaluation dated March 5, 2014.

3, Oconee County, South Carolina Effective date: As of the date of No significant hazards consideration Date of application for amendments: issuance and shall be implemented comments received: No.

February 22, 2013, as supplemented on prior to startup from the 2014 Unit 1 Florida Power and Light Company, September 10, October 25, November refueling outage. Docket Nos. 50-250 and 50-251, Turkey 29, and December 16, 2013. Amendment Nos.: 264 and 292. Point Nuclear Generating, Units 3 and Brief description of amendments: The Facility Operating License Nos. DPR- 4, Miami-Dade County, Florida amendments revise Technical 62 AND DPR-71: Amendments revised Date of application for amendment:

Specification (TS) 3.4.3, to replace its the License and TSs. March 22, 2013.

current reactor coolant system pressure- Date of initial notice in Federal Brief description of amendment: The temperature (P-T) limits with new P-T Register: October 16, 2013 (77 FR amendments revised the Technical limits applicable to 54 effective full 63346). Specifications (TSs) to allow the use of power years. In addition, the The supplements dated January 21, Optimized ZIRLOTM as an approved amendments change the operational May 14, and August 29, 2013, and fuel rod cladding.

requirements for unit heatup and January 22, 2014, provided additional Date of issuance: February 20, 2014.

cooldown in TS Tables 3.4.3-1 and information that clarified the Effective date: As of the date of 3.4.3-2. application, did not expand the scope of issuance and shall be implemented Date of Issuance: February 27, 2014. the application as originally noticed, within 60 days of issuance.

Effective date: As of the date of and did not change the staffs original Amendment No.: 259 and 254.

issuance and shall be implemented proposed no significant hazards Renewed Facility Operating License within 60 days from the date of consideration determination as Nos. DPR-31 and DPR-41: Amendments issuance. published in the Federal Register. revised the licenses and the TSs.

Amendment Nos.: 384, 386, and 385. The Commissions related evaluation Date of initial notice in Federal Renewed Facility Operating License of the amendment is contained in a Register: August 20, 2013 (78 FR Nos. DPR-38, DPR-47, and DPR-55: Safety Evaluation dated February 24, 51219).

Amendments revised the license and 2014. The Commissions related evaluation the TSs. No significant hazards consideration of the amendments is contained in a Date of initial notice in Federal comments received: None. Safety Evaluation dated February 20, Register: April 16, 2013, 78 FR 22568. Entergy Nuclear Operations, Inc., 2014.

The supplemental letters dated Docket No. 50-247, Indian Point No significant hazards consideration September 10, October 25, November Nuclear Generating, Unit 2, Westchester comments received: No.

emcdonald on DSK67QTVN1PROD with NOTICES 29, and December 16, 2013, provided County, New York Luminant Generation Company LLC, additional information that clarified the Date of application for amendment: Docket Nos. 50-445 and 50-446, application, did not expand the scope of February 6, 2013, as supplemented by Comanche Peak Nuclear Power Plant, the application as originally noticed, letters dated July 9, 2013, October 3, Units 1 and 2 (CPNPP), Somervell and did not change the staffs original 2013, and February 24, 2014. County, Texas proposed no significant hazards Brief description of amendment: The Date of amendment request: August consideration determination as amendment changes the Technical 29, 2013, as supplemented by letter published in the Federal Register. Specifications by revising the reactor dated February 19, 2014.

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15154 Federal Register / Vol. 79, No. 52 / Tuesday, March 18, 2014 / Notices Description of amendment request: Technical Specifications (TS). and 2, San Luis Obispo County, The amendments revised Technical Specifically, the amendment revised the California Specification (TS) 3.4.17, Steam TS to allow the use of Optimized Date of amendment request: June 6, Generator (SG) Tube Integrity, TS ZIRLOTM as an approved fuel rod 2013.

5.5.9, Unit 1 Model D76 and Unit 2 cladding material. Description of amendment request:

Model D5 Steam Generator (SG) Date of issuance: March 5, 2014. The amendments revised Technical Program, and TS 5.6.9, Unit 1 Model Effective date: As of its date of Specification (TS) 3.7.10, Control D76 and Unit 2 Model D5 Steam issuance and shall be implemented Room Ventilation System (CRVS), and Generator Tube Inspection Report. The within 60 days. TS 5.6.5, Core Operating Limits Report changes address implementation issues Amendment No.: 139. (COLR), to incorporate editorial associated with inspection periods, and Facility Operating License No. NPF- changes. Specifically, the proposed address other administrative changes 86: The amendment revised the License amendments delete footnote (1) from the and clarifications. The amendment is and TS. TS 3.7.10 Condition A Completion consistent with NRC-approved Date of initial notice in Federal Time, and revise inconsistent wording Technical Specifications Task Force Register: August 20, 2013 (78 FR in TS 5.6.5a.4, TS 5.6.5a.5, and TS (TSTF) change traveler TSTF-510, 51228). 5.6.5a.9.

Revision 2, Revision to Steam The Commissions related evaluation Date of issuance: February 27, 2014.

Generator Program Inspection of the amendment is contained in a Effective date: As of its date of Frequencies and Tube Sample Safety Evaluation dated March 5, 2014. issuance and shall be implemented Selection, as part of the consolidated No significant hazards consideration within 60 days from the date of line item improvement process. comments received: No. issuance.

The amendments also incorporated Northern States Power Company Amendment Nos.: Unit 1217; Unit minor non-technical variations from the Minnesota (NSPM), Docket No. 50-263, 2219.

TS changes proposed in TSTF-510, Monticello Nuclear Generating Plant, Facility Operating License Nos. DPR-Revision 2. The TSs for CPNPP, Units 1 Wright County, Minnesota 80 and DPR-82: The amendments and 2 utilize different numbering and Date of application for amendment: revised the Facility Operating Licenses titles than the Standard Technical April 19, 2013. and Technical Specifications.

Specifications on which TSTF-510, Brief description of amendment: The Date of initial notice in Federal Revision 2, is based, since the steam amendment allows NSPM to adopt the Register: August 6, 2013 (78 FR 47791).

generators for CPNPP, Units 1 and 2, are NRCs approved Technical The Commissions related evaluation of different models. These differences Specifications Task Force (TSTF) of the amendments is contained in a are administrative in nature and do not Standard Technical Specifications Safety Evaluation dated February 27, affect the applicability of TSTF-510, Change Traveler TSTF-535, Revision 0, 2014.

Revision 2, to the TSs for CPNPP, Units Revise Shutdown Margin Definition to No significant hazards consideration 1 and 2. Address Advanced Fuel Designs, dated comments received: No.

Date of issuance: February 27, 2014. August 8, 2011. The amendment PPL Susquehanna, LLC, Docket Nos.

Effective date: As of its date of modifies the Technical Specification 50-387 and 50-388, Susquehanna issuance and shall be implemented definition of shutdown margin (SDM) Steam Electric Station, Units 1 and 2, within 90 days from the date of to require calculation of the SDM at a Luzerne County, Pennsylvania issuance. reactor moderator temperature of 68 °F Date of application for amendments:

Amendment No.: Unit 1161; Unit or higher, representing the most reactive June 6, 2013, as supplemented by letter 2161. state throughout the operating cycle. dated December 4, 2013.

Facility Operating License Nos. NPF- This change addresses newer boiling- Brief description of amendments: The 87 and NPF-89: The amendments water reactor fuel designs which may be amendments change the Technical revised the Facility Operating Licenses more reactive at shutdown temperatures Specifications (TSs) for Susquehanna and Technical Specifications. above 68 °F. Steam Electric Station, Units 1 and 2.

Date of initial notice in Federal Date of issuance: February 28, 2014. Specifically, these amendments change Register: October 1, 2013 (78 FR Effective date: This license TS 3.3.6.1, Primary Containment 60324). amendment is effective as of the date of Isolation Instrumentation, to add a The February 19, 2014, supplement issuance and shall be implemented footnote to Function 6.c. in TS Table did not expand the scope of the within 90 days from the date of 3.3.6.1-1, allowing only one Trip application as originally noticed, and issuance. System to be operable in MODES 4 and did not change the NRC staffs initial Amendment No.: 179. 5 for the Manual Initiation Function for proposed finding of no significant Renewed Facility Operating License Shutdown Cooling System isolation.

hazards consideration. No. DPR-22: The amendment revises Date of issuance: February 26, 2014.

The Commissions related evaluation the Renewed Facility Operating License Effective date: As of the date of of the amendment is contained in a and Technical Specifications. issuance and shall be implemented Safety Evaluation dated February 27, Date of initial notice in Federal within 30 days.

2014. Register: September 3, 2013 (78 FR Amendment Nos.: 259 and 240.

No significant hazards consideration 54285). Renewed Facility Operating License comments received: No. The Commissions related evaluation Nos. NPF-14 and NPF-22: The emcdonald on DSK67QTVN1PROD with NOTICES NextEra Energy Seabrook, LLC, of the amendment is contained in a amendments revised the license and the Docket No. 50-443, Seabrook Station, Safety Evaluation dated February 28, TS.

Unit. 1, Rockingham County, New 2014. Date of initial notice in Federal Hampshire No significant hazards consideration Register: December 10, 2013 (78 FR Date of amendment request: June 25, comments received: No. 74184).

2013. Pacific Gas and Electric Company, The supplemental letter dated Description of amendment request: Docket Nos. 50-275 and 50-323, Diablo December 4, 2013, provided additional The amendment revised the Seabrook Canyon Nuclear Power Plant, Units 1 information that clarified the VerDate Mar<15>2010 18:34 Mar 17, 2014 Jkt 232001 PO 00000 Frm 00060 Fmt 4703 Sfmt 4703 E:\FR\FM\18MRN1.SGM 18MRN1

Federal Register / Vol. 79, No. 52 / Tuesday, March 18, 2014 / Notices 15155 application, did not expand the scope of which are set forth in the license been issued and made effective as the application as originally noticed, amendment. indicated.

and did not change the staffs original Because of exigent or emergency Unless otherwise indicated, the proposed no significant hazards circumstances associated with the date Commission has determined that these consideration determination as the amendment was needed, there was amendments satisfy the criteria for published in the Federal Register. not time for the Commission to publish, categorical exclusion in accordance The Commissions related evaluation for public comment before issuance, its with 10 CFR 51.22. Therefore, pursuant of the amendments is contained in a usual notice of consideration of to 10 CFR 51.22(b), no environmental Safety Evaluation dated February 26, issuance of amendment, proposed no impact statement or environmental 2014. significant hazards consideration assessment need be prepared for these No significant hazards consideration determination, and opportunity for a amendments. If the Commission has comments received: No. hearing. prepared an environmental assessment South Carolina Electric and Gas For exigent circumstances, the under the special circumstances Company, South Carolina Public Commission has either issued a Federal provision in 10 CFR 51.12(b) and has Service Authority, Docket No. 50-395, Register notice providing opportunity made a determination based on that Virgil C. Summer Nuclear Station, Unit, for public comment or has used local assessment, it is so indicated.

Fairfield County, South Carolina media to provide notice to the public in For further details with respect to the Date of application for amendment: the area surrounding a licensees facility action see (1) the application for April 2, 2013 as supplemented by letter of the licensees application and of the amendment, (2) the amendment to Commissions proposed determination Facility Operating License or Combined dated May 16, 2013.

of no significant hazards consideration. License, as applicable, and (3) the Brief description of amendment: This The Commission has provided a Commissions related letter, Safety amendment revises the Technical reasonable opportunity for the public to Evaluation and/or Environmental Specifications requirements regarding comment, using its best efforts to make Assessment, as indicated. All of these steam generator tube inspections and available to the public means of items are available for public inspection reporting as described in TSTF-510, communication for the public to at the NRCs Public Document Room Revision 2, Revision to Steam respond quickly, and in the case of (PDR), located at One White Flint North, Generator Program Inspection telephone comments, the comments Room O1-F21, 11555 Rockville Pike Frequencies and Tube Sample have been recorded or transcribed as (first floor), Rockville, Maryland 20852.

Selection. appropriate and the licensee has been Publicly available documents created or Date of issuance: February 28, 2014. informed of the public comments. received at the NRC are accessible Effective date: This license In circumstances where failure to act electronically through the Agencywide amendment is effective as of the date of in a timely way would have resulted, for Documents Access and Management its issuance. example, in derating or shutdown of a System (ADAMS) in the NRC Library at Amendment No.: 196. nuclear power plant or in prevention of http://www.nrc.gov/reading-rm/

Renewed Facility Operating License either resumption of operation or of adams.html. If you do not have access No. NPF-12: Amendment revises the increase in power output up to the to ADAMS or if there are problems in License. plants licensed power level, the accessing the documents located in Date of initial notice in Federal Commission may not have had an ADAMS, contact the PDRs Reference Register: June 25, 2013 (78 FR 38083). opportunity to provide for public staff at 1-800-397-4209, 301-415-4737 The Commissions related evaluation comment on its no significant hazards or by email to pdr.resource@nrc.gov.

of the amendment is contained in a consideration determination. In such The Commission is also offering an Safety Evaluation dated February 28, case, the license amendment has been opportunity for a hearing with respect to 2014. issued without opportunity for the issuance of the amendment. Within No significant hazards consideration comment. If there has been some time 60 days after the date of publication of comments received: No. for public comment but less than 30 this notice, any person(s) whose interest days, the Commission may provide an may be affected by this action may file Notice of Issuance of Amendments to opportunity for public comment. If a request for a hearing and a petition to Facility Operating Licenses and comments have been requested, it is so intervene with respect to issuance of the Combined Licenses and Final stated. In either event, the State has amendment to the subject facility Determination of No Significant been consulted by telephone whenever operating license or combined license.

Hazards Consideration and possible. Requests for a hearing and a petition for Opportunity for a Hearing (Exigent Under its regulations, the Commission leave to intervene shall be filed in Public Announcement or Emergency may issue and make an amendment accordance with the Commissions Circumstances) immediately effective, notwithstanding Agency Rules of Practice and During the period since publication of the pendency before it of a request for Procedure in 10 CFR Part 2. Interested the last biweekly notice, the a hearing from any person, in advance person(s) should consult a current copy Commission has issued the following of the holding and completion of any of 10 CFR 2.309, which is available at amendments. The Commission has required hearing, where it has the NRCs PDR, located at One White determined for each of these determined that no significant hazards Flint North, Room O1-F21, 11555 amendments that the application for the consideration is involved. Rockville Pike (first floor), Rockville, emcdonald on DSK67QTVN1PROD with NOTICES amendment complies with the The Commission has applied the Maryland 20852, and electronically on standards and requirements of the standards of 10 CFR 50.92 and has made the Internet at the NRCs Web site, Atomic Energy Act of 1954, as amended a final determination that the http://www.nrc.gov/reading-rm/doc-(the Act), and the Commissions rules amendment involves no significant collections/cfr/. If there are problems in and regulations. The Commission has hazards consideration. The basis for this accessing the document, contact the made appropriate findings as required determination is contained in the PDRs Reference staff at 1-800-397-by the Act and the Commissions rules documents related to this action. 4209, 301-415-4737, or by email to and regulations in 10 CFR Chapter I, Accordingly, the amendments have pdr.resource@nrc.gov. If a request for a VerDate Mar<15>2010 18:34 Mar 17, 2014 Jkt 232001 PO 00000 Frm 00061 Fmt 4703 Sfmt 4703 E:\FR\FM\18MRN1.SGM 18MRN1

15156 Federal Register / Vol. 79, No. 52 / Tuesday, March 18, 2014 / Notices hearing or petition for leave to intervene intervene, and have the opportunity to support unlisted software, and the NRC is filed by the above date, the participate fully in the conduct of the Meta System Help Desk will not be able Commission or a presiding officer hearing. Since the Commission has to offer assistance in using unlisted designated by the Commission or by the made a final determination that the software.

Chief Administrative Judge of the amendment involves no significant If a participant is electronically Atomic Safety and Licensing Board hazards consideration, if a hearing is submitting a document to the NRC in Panel, will rule on the request and/or requested, it will not stay the accordance with the E-Filing rule, the petition; and the Secretary or the Chief effectiveness of the amendment. Any participant must file the document Administrative Judge of the Atomic hearing held would take place while the using the NRCs online, Web-based Safety and Licensing Board will issue a amendment is in effect. submission form. In order to serve notice of a hearing or an appropriate All documents filed in the NRC documents through the Electronic order. adjudicatory proceedings, including a Information Exchange System, users As required by 10 CFR 2.309, a request for hearing, a petition for leave will be required to install a Web petition for leave to intervene shall set to intervene, any motion or other browser plug-in from the NRCs Web forth with particularity the interest of document filed in the proceeding prior site. Further information on the Web-the petitioner in the proceeding, and to the submission of a request for based submission form, including the how that interest may be affected by the hearing or petition to intervene, and installation of the Web browser plug-in, results of the proceeding. The petition documents filed by interested is available on the NRCs public Web should specifically explain the reasons governmental entities participating site at http://www.nrc.gov/site-help/e-why intervention should be permitted under 10 CFR 2.315(c), must be filed in submittals.html.

with particular reference to the accordance with the NRCs E-Filing rule Once a participant has obtained a following general requirements: (1) The (72 FR 49139; August 28, 2007). The E- digital ID certificate and a docket has name, address, and telephone number of Filing process requires participants to been created, the participant can then the requestor or petitioner; (2) the submit and serve all adjudicatory submit a request for hearing or petition nature of the requestors/petitioners documents over the internet, or in some for leave to intervene. Submissions right under the Act to be made a party cases to mail copies on electronic should be in Portable Document Format to the proceeding; (3) the nature and storage media. Participants may not (PDF) in accordance with the NRCs extent of the requestors/petitioners submit paper copies of their filings guidance available on the NRCs public property, financial, or other interest in unless they seek an exemption in Web site at http://www.nrc.gov/site-the proceeding; and (4) the possible accordance with the procedures help/e-submittals.html. A filing is effect of any decision or order which described below.

To comply with the procedural considered complete at the time the may be entered in the proceeding on the requirements of E-Filing, at least 10 documents are submitted through the requestors/petitioners interest. The days prior to the filing deadline, the NRCs E-Filing system. To be timely, an petition must also identify the specific participant should contact the Office of electronic filing must be submitted to contentions which the requestor/

petitioner seeks to have litigated at the the Secretary by email at the E-Filing system no later than 11:59 proceeding. hearing.docket@nrc.gov, or by telephone p.m. Eastern Time on the due date.

Each contention must consist of a at 301-415-1677, to request (1) a digital Upon receipt of a transmission, the E-specific statement of the issue of law or identification (ID) certificate, which Filing system time-stamps the document fact to be raised or controverted. In allows the participant (or its counsel or and sends the submitter an email notice addition, the requestor/petitioner shall representative) to digitally sign confirming receipt of the document. The provide a brief explanation of the bases documents and access the E-Submittal E-Filing system also distributes an email for the contention and a concise server for any proceeding in which it is notice that provides access to the statement of the alleged facts or expert participating; and (2) advise the document to the NRCs Office of the opinion which support the contention Secretary that the participant will be General Counsel and any others who and on which the petitioner intends to submitting a request or petition for have advised the Office of the Secretary rely in proving the contention at the hearing (even in instances in which the that they wish to participate in the hearing. The petitioner must also participant, or its counsel or proceeding, so that the filer need not provide references to those specific representative, already holds an NRC- serve the documents on those sources and documents of which the issued digital ID certificate). Based upon participants separately. Therefore, petitioner is aware and on which the this information, the Secretary will applicants and other participants (or petitioner intends to rely to establish establish an electronic docket for the their counsel or representative) must those facts or expert opinion. The hearing in this proceeding if the apply for and receive a digital ID petition must include sufficient Secretary has not already established an certificate before a hearing request/

information to show that a genuine electronic docket. petition to intervene is filed so that they dispute exists with the applicant on a Information about applying for a can obtain access to the document via material issue of law or fact. digital ID certificate is available on the E-Filing system.

Contentions shall be limited to matters NRCs public Web site at http:// A person filing electronically using within the scope of the amendment www.nrc.gov/site-help/e-submittals/ the agencys adjudicatory E-Filing under consideration. The contention apply-certificates.html. System system may seek assistance by must be one which, if proven, would requirements for accessing the E- contacting the NRC Meta System Help emcdonald on DSK67QTVN1PROD with NOTICES entitle the petitioner to relief. A Submittal server are detailed in NRCs Desk through the Contact Us link requestor/petitioner who fails to satisfy Guidance for Electronic Submission, located on the NRC Web site at http://

these requirements with respect to at which is available on the agencys www.nrc.gov/site-help/e-least one contention will not be public Web site at http://www.nrc.gov/ submittals.html, by email to permitted to participate as a party. site-help/e-submittals.html. Participants MSHD.Resource@nrc.gov, or by a toll-Those permitted to intervene become may attempt to use other software not free call at 1-866-672-7640. The NRC parties to the proceeding, subject to any listed on the Web site, but should note Meta System Help Desk is available limitations in the order granting leave to that the NRCs E-Filing system does not between 8 a.m. and 8 p.m., Eastern VerDate Mar<15>2010 18:34 Mar 17, 2014 Jkt 232001 PO 00000 Frm 00062 Fmt 4703 Sfmt 4703 E:\FR\FM\18MRN1.SGM 18MRN1

Federal Register / Vol. 79, No. 52 / Tuesday, March 18, 2014 / Notices 15157 Time, Monday through Friday, Description of amendment request: For the Nuclear Regulatory Commission.

excluding government holidays. The amendments revise Technical Michele G. Evans, Participants who believe that they Specification (TS) Table 3.3.4-1, Director, Division of Operating Reactor have a good cause for not submitting Remote Shutdown System Licensing, Office of Nuclear Reactor documents electronically must file an Instrumentation and Controls as a result Regulation.

exemption request, in accordance with of an inoperable instrumentation [FR Doc. 2014-05645 Filed 3-17-14; 8:45 am]

10 CFR 2.302(g), with their initial paper function on Unit 2. Table 3.3.4-1 BILLING CODE 7590-01-P filing requesting authorization to specifies requirements for Function 3.b.,

continue to submit documents in paper Decay Heat Removal via Steam format. Such filings must be submitted Generators (SGs)Reactor Coolant NUCLEAR REGULATORY by: (1) First class mail addressed to the COMMISSION System (RCS) Cold Leg Temperature Office of the Secretary of the Loop A and B as 1 per loop. Loop A [Docket No. 5200027; NRC-2008-0441]

Commission, U.S. Nuclear Regulatory Commission, Washington, DC 20555- of this function is presently inoperable 0001, Attention: Rulemaking and on Unit 2 due to a failed resistance Inspections, Tests, Analyses, and Adjudications Staff; or (2) courier, temperature detector (RTD). Loop B of Acceptance Criteria; Virgil C. Summer express mail, or expedited delivery this function is operable with a reliable Unit 2 Combined License service to the Office of the Secretary, maintenance history. The failed RTD on Loop A cannot be replaced in the AGENCY: Nuclear Regulatory Sixteenth Floor, One White Flint North, Commission.

11555 Rockville Pike, Rockville, present operating mode of Unit 2 (Mode 1). Therefore, Duke Energy requested ACTION: Determination of inspections, Maryland, 20852, Attention:

Rulemaking and Adjudications Staff. the U.S. Nuclear Regulatory tests, analyses, and acceptance criteria Participants filing a document in this Commission (NRC) approval to allow (ITAAC).

manner are responsible for serving the Unit 2 to remain in Mode 1 until such

SUMMARY

The U.S. Nuclear Regulatory document on all other participants. time that the failed RTD can be Commission (NRC) staff has determined Filing is considered complete by first- replaced. The replacement would occur that the inspections, tests, and analyses class mail as of the time of deposit in in the next refueling outage or the next have been successfully completed, and the mail, or by courier, express mail, or outage that would facilitate that the specified acceptance criteria are expedited delivery service upon replacement, whichever occurs first. met for ITAAC 3.3.00.09, for the Virgil depositing the document with the Date of issuance: February 27, 2014. C. Summer Nuclear Station Unit 2.

provider of the service. A presiding Effective date: As of the date of ADDRESSES: Please refer to Docket ID officer, having granted an exemption request from using E-Filing, may require issuance and shall be implemented NRC-2008-0441 when contacting the a participant or party to use E-Filing if within 30 days from the date of NRC about the availability of the presiding officer subsequently issuance. information regarding this document.

determines that the reason for granting You may access publicly-available Amendment Nos.: 272 and 268. information related to this document the exemption from use of E-Filing no Renewed Facility Operating License using any of the following methods:

longer exists.

Documents submitted in adjudicatory Nos. NPF-35 and NPF-52: Amendments

• Federal Rulemaking Web site: Go to proceedings will appear in the NRCs revised the licenses and the technical http://www.regulations.gov and search electronic hearing docket which is specifications. for Docket ID NRC-2008-0441. Address available to the public at http://ehd1. Public comments requested as to questions about NRC dockets to Carol nrc.gov/ehd/, unless excluded pursuant proposed no significant hazards Gallagher; telephone: 301-287-3422; to an order of the Commission, or the consideration (NSHC): Yes. The NRC email: Carol.Gallagher@nrc.gov. For presiding officer. Participants are staff noticed the February 17, 2014, technical questions, contact the requested not to include personal application in the Rock Hill, SC local individuals listed in the FOR FURTHER privacy information, such as social newspaper, The Herald on Friday, INFORMATION CONTACT section of this security numbers, home addresses, or February 21, 2014, and Saturday, document.

home phone numbers in their filings, February 22, 2014. The notice provided

• NRCs Agencywide Documents unless an NRC regulation or other law an opportunity to submit comments on Access and Management System requires submission of such the Commissions proposed NSHC (ADAMS): You may access publicly information. However, a request to available documents online in the NRC determination. No comments have been intervene will require including Library at http://www.nrc.gov/reading-received.

information on local residence in order rm/adams.html. To begin the search, to demonstrate a proximity assertion of The Commissions related evaluation select ADAMS Public Documents and interest in the proceeding. With respect of the amendment, finding of exigent then select Begin Web-based ADAMS to copyrighted works, except for limited circumstances, state consultation, and Search. For problems with ADAMS, excerpts that serve the purpose of the final NSHC determination are contained please contact the NRCs Public adjudicatory filings and would in a safety evaluation dated February 27, Document Room (PDR) reference staff at constitute a Fair Use application, 2014. 1-800-397-4209, 301-415-4737, or by participants are requested not to include Attorney for licensee: Lara S. Nichols, email to pdr.resource@nrc.gov. The emcdonald on DSK67QTVN1PROD with NOTICES copyrighted materials in their Associate General Counsel, Duke Energy ADAMS accession number for each submission. Corporation, 526 South Church Street document referenced in this document Duke Energy Carolinas, LLC, et al., EC07H, Charlotte, NC 28202. (if that document is available in Docket Nos. 50-413 and 50-414, ADAMS) is provided the first time that NRC Branch Chief: Robert J. a document is referenced.

Catawba Nuclear Station, Units 1 and 2, Pascarelli.

• NRCs PDR: You may examine and York County, South Carolina Date of amendment request: February Dated at Rockville, Maryland, this 10th day purchase copies of public documents at 17, 2014. of March 2014. the NRCs PDR, Room O1-F21, One VerDate Mar<15>2010 18:34 Mar 17, 2014 Jkt 232001 PO 00000 Frm 00063 Fmt 4703 Sfmt 4703 E:\FR\FM\18MRN1.SGM 18MRN1