Source: https://www.federalregister.gov/documents/2014/05/27/2014-12018/biweekly-notice-applications-and-amendments-to-facility-operating-licenses-and-combined-licenses
Timestamp: 2017-11-21 16:10:19
Document Index: 23309151

Matched Legal Cases: ['art 2', 'art 50', 'art 50', 'art 50', 'art 50', 'art 50', 'art 50', 'art 50']

Comments must be filed by June 26, 2014. A request for a hearing must be filed by July 28, 2014.
79 FR 30184
30184-30191 (8 pages)
https://www.federalregister.gov/d/2014-12018 https://www.federalregister.gov/d/2014-12018
Pursuant to Section 189a. (2) of the Atomic Energy Act of 1954, as amended (the Act), the U.S. Nuclear Regulatory Commission (NRC) is publishing this regular biweekly notice. The Act requires the Commission to publish notice of any amendments issued, or proposed to be issued and grants the Commission the authority to Start Printed Page 30185issue and make immediately effective any amendment to an operating license or combined license, as applicable, upon a determination by the Commission that such amendment involves no significant hazards consideration, notwithstanding the pendency before the Commission of a request for a hearing from any person.
This biweekly notice includes all notices of amendments issued, or proposed to be issued from April 31, 2014 to May 14, 2014. The last biweekly notice was published on May 13, 2014.
Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2014-0122. Address questions about NRC dockets to Carol Gallagher; telephone: 301-287-3422; email: Carol.Gallagher@nrc.gov. For technical questions, contact the individual listed in the FOR FURTHER INFORMATION CONTACT section of this document.
Please refer to Docket ID NRC-2014-0122 when contacting the NRC about the availability of information regarding this document. You may access publicly-available information related to this action by any of the following methods:
Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2014-0122.
Please include Docket ID NRC-2014-0122 in the subject line of your comment submission, in order to ensure that the NRC is able to make your comment submission available to the public in this docket.
Within 60 days after the date of publication of this notice, any person(s) whose interest may be affected by this action may file a request for a hearing and a petition to intervene with respect to issuance of the amendment to the subject facility operating license or combined license. Requests for a hearing and a petition for leave to intervene shall be filed in accordance with the Commission's “Agency Rules of Practice and Procedure” in 10 CFR Part 2. Interested person(s) should consult a current copy of 10 CFR 2.309, which is available at the NRC's PDR, located at One White Flint North, Room O1-F21, 11555 Rockville Pike (first floor), Rockville, Maryland 20852. The NRC's regulations are accessible electronically from the NRC Library on the NRC's Web site at http://www.nrc.gov/​reading-rm/​doc-collections/​cfr/​. If a request for a hearing Start Printed Page 30186or petition for leave to intervene is filed by the above date, the Commission or a presiding officer designated by the Commission or by the Chief Administrative Judge of the Atomic Safety and Licensing Board Panel, will rule on the request and/or petition; and the Secretary or the Chief Administrative Judge of the Atomic Safety and Licensing Board will issue a notice of a hearing or an appropriate order.
Once a participant has obtained a digital ID certificate and a docket has been created, the participant can then submit a request for hearing or petition for leave to intervene. Submissions should be in Portable Document Format (PDF) in accordance with NRC guidance available on the NRC's public Web site at http://www.nrc.gov/​site-help/​e-submittals.html. A filing is considered complete at the time the documents are submitted through the NRC's E-Filing system. To be timely, an electronic filing must be submitted to the E-Filing system no later than 11:59 p.m. Eastern Time on the due date. Upon receipt of a transmission, the E-Filing system time-stamps the document and sends the submitter an email notice confirming receipt of the document. The E-Filing system also distributes an email notice that provides access to the document to the NRC's Office of the General Counsel and any others who have advised the Office of the Secretary that they wish to participate in the proceeding, so that the filer need not serve the documents on those participants separately. Therefore, applicants and other participants (or their counsel or representative) must apply for and receive a digital ID Start Printed Page 30187certificate before a hearing request/petition to intervene is filed so that they can obtain access to the document via the E-Filing system.
Date of amendment request: February 26, 2014. A publicly-available version is in ADAMS under Accession No. ML14077A265.
Description of amendment request: The amendments would revise technical specification (TS) requirements for mode change limitations in Limited Condition for Operation (LCO) 3.0.4 and Surveillance Requirements 4.0.4. The proposed changes would be consistent with the NRC approved Industry Technical Specification Task Force (TSTF) Standard TS change TSTF-359, “Increase Flexibility in Mode Restraints,” Revision 9.
The NRC issued a notice of opportunity for comment in the Federal Register (FR) on August 2, 2002 (67 FR 50475), on possible amendments concerning TSTF-359, including a model safety evaluation and model no significant hazards consideration (NSHC) determination, using the consolidated line item improvement process (CLIIP). Subsequently, on April 4, 2003, the NRC published the Notice of Availability for TSTF-359, Revision 8 in the Federal Register (68 FR 16579). That Notice announced the availability of this TS improvement through the CLIIP. The NRC subsequently made two modifications in response to comments, as well as one editorial change, which have been incorporated into TSTF-359, Revision 9. The changes proposed in the licensee's submittal are, therefore, based on TSTF-359, Revision 9. FPL affirmed the applicability of the following NSHC determination in its application dated February 26, 2014.
Basis for proposed no significant hazards consideration determination: As required by 10 CFR 50.91(a), an analysis of the issue of no significant hazards consideration, as was published in the Federal Register is presented below:
The proposed change allows entry into a mode or other specified condition in the applicability of a TS, while in a TS condition statement and the associated required actions of the TS. Being in a TS condition and the associated required actions is not an initiator of any accident previously evaluated. Therefore, the probability of an accident previously evaluated is not significantly increased. The consequences of an accident while relying on required actions as allowed by proposed LCO 3.0.4, are no different than the consequences of an accident while entering and relying on the required actions while starting in a condition of applicability of the TS. Therefore, the consequences of an accident previously evaluated are not significantly affected by this change. The addition of a requirement to assess and manage the risk introduced by this change will further minimize possible concerns.
The proposed change does not involve a physical alteration of the plant (no new or different type of equipment will be installed). Entering into a mode or other specified condition in the applicability of a TS, while in a TS condition statement and the associated required actions of the TS, will not introduce new failure modes or effects and will not, in the absence of other unrelated failures, lead to an accident whose consequences exceed the consequences of accidents previously evaluated. The addition of a requirement to assess and manage the risk introduced by this change will further minimize possible concerns.
The proposed change allows entry into a mode or other specified condition in the applicability of a TS, while in a TS condition Start Printed Page 30188statement and the associated required actions of the TS. The TS allow operation of the plant without the full complement of equipment through the conditions for not meeting the TS Limiting Conditions for Operation (LCO). The risk associated with this allowance is managed by the imposition of required actions that must be performed within the prescribed completion times. The net effect of being in a TS condition on the margin of safety is not considered significant. The proposed change does not alter the required actions or completion times of the TS. The proposed change allows TS conditions to be entered, and the associated required actions and completion times to be used in new circumstances. This use is predicated upon the licensee's performance of a risk assessment and the management of plant risk. The change also eliminates current allowances for utilizing required actions and completion times in similar circumstances, without assessing and managing risk. The net change to the margin of safety is insignificant.
Date of amendment request: March 7, 2014. A publicly-available version is in ADAMS under Accession No. ML14071A435.
Description of amendment request: The proposed amendment would revise the Donald C. Cook Nuclear Plant, Units 1 and 2, Technical Specification 5.5.14, “Containment Leakage Rate Testing Program,” by adopting Nuclear Energy Institute (NEI) 94-01 Revision 3-A, “Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J” (ADAMS Accession No. ML12221A202), as the implementing document for the performance-based Option B of 10 CFR Part 50, Appendix J.
The proposed revision to TS 5.5.14 changes the testing period to a permanent 15-year interval for Type A testing (10 CFR Part 50, Appendix J, Option B, ILRT). The current test interval of 10 years would be extended to 15 years from the last Type A test. The proposed extension to Type A testing does not involve a significant increase in the consequences of an accident since research documented in NUREG-1493, “Performance-Based Containment System Leakage Testing Requirements,” September 1995, has found that, generically, very few potential containment leakage paths are not identified by Type B and C tests. NUREG-1493 concluded that reducing the Type A testing frequency to one per twenty years was found to lead to an imperceptible increase in risk. A high degree of assurance is provided through testing and inspection that the containment will not degrade in a manner detectable only by Type A testing. The last Type A test (November 2006) shows leakage to be below acceptance criteria, indicating a very leak tight containment. Inspections required by the ASME Code Section Xl (Subsections IWE and IWL) and Maintenance Rule monitoring (10 CFR 50.65, “Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants[”]) are performed in order to identify indications of containment degradation that could affect that leak tightness. Types B and C testing required by [technical specifications (TSs)] will identify any containment opening such as valves that would otherwise be detected by the Type A tests. These factors show that a Type A test interval extension will not represent a significant increase in the consequences of an accident.
The proposed amendment involves changes to the [Donald C. Cook Nuclear Plant (CNP)] Units 1 and 2 10 CFR Part 50, Appendix J Testing Program Plan. The proposed amendment does not involve a physical change to the plant or a change in the manner in which the units are operated or controlled. The primary containment function is to provide an essentially leak tight barrier against the uncontrolled release of radioactivity to the environment for postulated accidents. As such, the containment itself and the testing requirements to periodically demonstrate the integrity of the containment exist to ensure the plant's ability to mitigate the consequences of an accident, and do not involve any accident precursors or initiators.
The proposed amendment adopts the [U.S. Nuclear Regulatory Commission (NRC)]-accepted guidelines of [Nuclear Energy Institute (NEI)] 94-01, Revision 3-A, for development of the CNP performance-based leakage testing program. Implementation of these guidelines continues to provide adequate assurance that during design basis accidents, the primary containment and its components will limit leakage rates to less than the values assumed in the plant safety analyses. The potential consequences of extending the [integrated leak rate testing (ILRT)] interval from 10 years to 15 years have been evaluated by analyzing the resulting changes in risk. The increase in risk in terms of person-rem per year resulting from design basis accidents was estimated to be acceptably small, and the increase in the [large early release frequency (LERF)] resulting from the proposed change was determined to be within the guidelines published in NRC [Regulatory Guide (RG)] 1.174. Additionally, the proposed change maintains defense-in-depth by preserving a reasonable balance among prevention of core damage, prevention of containment failure, and consequence mitigation. [Indiana Michigan Power Company (I&M)] has determined that the increase in [conditional containment failure probability (CCFP)] due to the proposed change would be very small.
The proposed revision to TS 5.5.14 changes the testing period to a permanent 15-year interval for Type A testing (10 CFR Part 50, Appendix J, Option B, ILRT[)]. The current test interval of 10 years, based on past performance, would be extended to 15 years from the last Type A test (November 2006). The proposed extension to Type A testing does not create the possibility of a new or different type of accident since there are no physical changes being made to the plant and there are no changes to the operation of the plant that could introduce a new failure mode creating an accident or affecting the mitigation of an accident.
The proposed revision to TS 5.5.14 changes the testing period to a permanent 15-year interval for Type A testing (10 CFR Part 50, Appendix J, Option B, ILRT[)]. The current test interval of 10 years, based on past performance, would be extended to 15 years from the last Type A test (November 2006). The proposed extension to Type A testing will not significantly reduce the margin of safety. NUREG-1493, “Performance-Based Containment System Leakage Testing Requirements,” September 1995, generic study of the effects of extending containment leakage testing, found that a 20 year extension to Type A leakage testing resulted in an imperceptible increase in risk to the public. NUREG-1493 found that, generically, the design containment leakage rate contributes about 0.1% to the individual risk and that the decrease in Type A testing frequency would have a minimal Start Printed Page 30189effect on this risk since 95% of the potential leakage paths are detected by Type C testing. Regular inspections required by the ASME Code Section Xl (Subsections IWE and IWL) and maintenance rule monitoring (10 CFR 50.65, “Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants[“]) will further reduce the risk of a containment leakage path going undetected.
The proposed amendment adopts the NRC-accepted guidelines of NEI 94-01, Revision 3-A, for development of the CNP performance-based leakage testing program, and establishes a 15-year interval for the performance of the primary containment ILRT. The amendment does not alter the manner in which safety limits, limiting safety system setpoints, or limiting conditions for operation are determined. The specific requirements and conditions of the 10 CFR Part 50, Appendix J Testing Program Plan, as defined in the TS, ensure that the degree of primary containment structural integrity and leak-tightness that is considered in the plant safety analyses is maintained. The overall containment leakage rate limit specified by the TS is maintained, and the Type A, B, and C containment leakage tests will continue to be performed at the frequencies established in accordance with the NRC-accepted guidelines of NEI 94-01, Revision 3-A. Containment inspections performed in accordance with other plant programs serve to provide a high degree of assurance that the containment will not degrade in a manner that is detectable only by an ILRT. In addition, CNP has a containment monitoring capability for the detection of gross containment leakage that may develop during power operation. This combination of factors ensures that evidence of containment structural degradation is identified in a timely manner. Furthermore, a risk assessment using the current CNP PRA model concluded that extending the ILRT test interval from 10 years to 15 years results in a very small change to the CNP risk profile.
Date of amendment request: April 18, 2014. A publicly-available version is in ADAMS under Accession No. ML14108A196.
Description of amendment request: The proposed license amendment request would revise the Updated Final Safety Analysis Report (UFSAR) in regard to Tier 2* information related to fire area boundaries. These changes add three new fire zones in the middle annulus to provide enclosures for the Class 1E electrical containment penetrations in accordance with UFSAR Appendix 9A, Subsection 9A.3.1.1.15. The addition of the three new fire zones extended the fire area boundaries for three existing fire areas and therefore constitutes a change to Tier 2* information. Additionally, the licensee proposed changes that require revisions to UFSAR Tier 2 information involving changes to plant-specific Tier 2* information.
The proposed middle annulus fire barrier reconfiguration for the electrical penetrations would not adversely affect any safety-related equipment or function. The modified configuration for the Class 1E electrical containment penetration enclosures will maintain the fire protection function (i.e., barrier) as evaluated in Updated Final Safety Analysis Report (UFSAR), thus, the probability of a Class 1E electrical containment penetration failure is not significantly increased. The safe shutdown fire analysis is not affected, and the fire protection analysis results are not adversely affected. The proposed changes do not involve any accident, initiating event or component failure; thus, the probabilities of previously evaluated accidents are not affected. The maximum allowable leakage rate specified in the Technical Specifications is unchanged, and radiological material release source terms are not affected; thus, the radiological releases in the accident analyses are not affected.
The addition of enclosures constructed of three-hour rated fire barriers to separate the fire zones in the middle annulus for the Class 1E electrical penetration assemblies will maintain the fire protection function as evaluated in the UFSAR. The addition of the fire barriers does not affect the function of the Class 1E electrical containment penetrations or electrical penetration assemblies, and thus, does not introduce a new failure mode. The addition of the fire barriers does not create a new fault or sequence of events that could result in a radioactive material release.
The use of enclosures constructed of three-hour rated fire barriers to separate the fire zones in the middle annulus for the Class 1E electrical penetration assemblies will maintain the fire protection function as evaluated in the UFSAR. The use of the fire barriers does not affect the ability of the Class 1E electrical containment penetrations, electrical penetration assemblies, or the containment to perform their design function. The Class 1E electrical containment penetrations and electrical penetration assemblies within the enclosures continue to comply with the existing design codes and regulatory criteria, and do not affect any safety limit. The use of fire barriers and enclosures to separate the Class 1E electrical penetration assemblies does not adversely affect any margin of safety.
A notice of consideration of issuance of amendment to facility operating license or combined license, as applicable, proposed no significant hazards consideration determination, Start Printed Page 30190and opportunity for a hearing in connection with these actions, was published in the Federal Register as indicated.
Date of application for amendments: October 30, 2012, as supplemented on January 21, June 11, September 3, October 21, and December 2, 2013.
Brief description of amendments: The amendments create new Technical Specification (TS) 3.7.19, “Spent Fuel Pool Cooling (SFPC) Purification System Isolation from Borated Water Storage Tank (BWST),” and 3.9.8, “Reverse Osmosis (RO) System Operating Restrictions for Spent Fuel Pool (SFP),” for the operation of an RO system to remove silica from the BWSTs and SFPs.
Date of Issuance: April 30, 2014.
Amendment Nos.: 385, 387, and 386. A publicly-available version is in ADAMS under Accession No. ML14106A418; documents related to these amendments are listed in the Safety Evaluation enclosed with the amendments.
Date of initial notice in Federal Register: November 26, 2013, 78 FR 70591.
The supplemental letters dated January 21, June 11, September 3, October 21, and December 2, 2013, provided additional information that clarified the application, did not expand the scope of the application as noticed, and did not change the staff's proposed no significant hazards consideration determination as published in the Federal Register.
The Commission's related evaluation of the amendments is contained in a Safety Evaluation dated April 30, 2014.
Date of application for amendments: June 10, 2013, as supplemented by letter dated November 6, 2013.
Brief description of amendments: The amendments modify the Technical Specifications (TSs) and Facility Operating Licenses (FOLs) to: (1) Increase the allowable as-found safety relief valve (SRV) and safety valve (SV) lift setpoint tolerance from ±1% to ±3%; (2) increase the required number of operable SRVs and SVs from 11 to 12; and (3) increase the Standby Liquid Control System pump discharge pressure from 1255 pounds per square inch gauge (psig) to 1275 psig.
Date of issuance: May 5, 2014.
Amendments Nos.: 290 and 293. A publicly-available version is in ADAMS under Accession No. ML14079A102; documents related to these amendments are listed in the Safety Evaluation enclosed with the amendments.
Renewed Facility Operating License Nos. DPR-44 and DPR-56: The amendments revised the FOLs and TSs.
Date of initial notice in Federal Register: December 26, 2013 (78 FR 78406). The letter dated November 6, 2013, provided clarifying information that did not change the initial proposed no significant hazards consideration determination or expand the application beyond the scope of the original Federal Register notice.
The Commission's related evaluation of the amendments is contained in a Safety Evaluation dated May 5, 2014.
Description of amendment: The license amendment revised Technical Specifications 5.3.1 and 6.9.1.7 to allow the use of Optimized ZIRLOTM as an approved fuel rod cladding material at the Point Beach Nuclear Plant, Units 1 and 2; added two approved analytical methods; and made minor corrections to the titles of two approved topical reports.
Date of issuance: May 9, 2014.
Effective date: As of the date of issuance and shall be implemented with 120 days.
Amendment Nos.: 249 and 253. A publicly-available version is in ADAMS under Accession No. ML14058B029; documents related to these amendments are listed in the Safety Evaluation enclosed with the amendments.
Facility Operating License Nos. DPR-24 and DPR-27: The amendment revised the Renewed Facility Operating License and the Technical Specifications.
Date of initial notice in Federal Register: October 29, 2013 (78 FR 64545).
The Commission's related evaluation of the amendment is contained in a Safety Evaluation dated May 9, 2014.
Date of application for amendment: January 4, 2013.
Brief description of amendment: The amendment revises the Technical Specification (TS) Surveillance Requirement (SR) 3.6.4.3.1 and SR 3.7.4.1 which currently require operating the standby gas treatment (SGT) and control room emergency filtration (CREF) systems for at least 10 continuous hours with the heaters operating every 31 days. The SRs are changed to require at least 15 continuous minutes of ventilation system operation without heaters operating every 31 days, and include TS Bases changes summarizing and clarifying the purpose of the TSs in accordance with TS Task Force (TSTF) Standard Technical Specifications Change Traveler TSTF-522, Revision 0, “Revise Ventilation System Surveillance Requirements to Operate for 10 hours Start Printed Page 30191per Month” (ADAMS Accession No. ML100890316). The amendment also removes the electric heater output testing requirement from TS 5.5.6, “Ventilation Filter Testing Program (VFTP).”
Date of issuance: May 2, 2014.
Effective date: This amendment is effective as of its date of issuance and shall be implemented within 120 days from the date of issuance.
Amendment No.: 181. A publicly-available version is in ADAMS under Accession No. ML14058A825; documents related to this amendment are listed in the Safety Evaluation enclosed with the amendment.
Facility Operating License No. DPR-22: This amendment revises the Renewed Facility Operating License and the Technical Specifications.
Date of initial notice in Federal Register: March 4, 2013 (78 FR 14134). The supplemental letter dated December 27, 2013, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the staff's original proposed no significant hazards consideration determination as published in the Federal Register.
The Commission's related evaluation of the amendment is contained in a Safety Evaluation dated May 2, 2014.
Date of amendment request: April 25, 2013, as supplemented by the letter dated November 21, 2013.
Brief description of amendment: The amendment revises Tier 2* and associated Tier 2 information, incorporated into the VEGP Units 3 and 4 Updated Final Safety Analysis Report (UFSAR). Specifically, the amendment revises the following information related to fire area boundaries: (1) Various Annex Building and Turbine Building layout changes, (2) Turbine Building Stairwell S08 changes to support egress functions, and (3) an Annex Building Heating, Ventilation and Air Conditioning shaft UFSAR figure clarification.
Date of issuance: May 1, 2014.
Amendment No.: 19. A publicly-available version is in ADAMS under Accession No. ML14050A445; documents related to these amendments are listed in the Safety Evaluation enclosed with the amendments.
Date of initial notice in Federal Register: July 9, 2013, 2013 (78 FR 41118).
The Commission's related evaluation of the amendment is contained in a Safety Evaluation dated May 1, 2014.
Dated at Rockville, Maryland, this 19th day of May 2014.
[FR Doc. 2014-12018 Filed 5-23-14; 8:45 am]