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| | issue date = 07/02/2007 | | | issue date = 07/02/2007 |
| | title = License Amendment, Issuance of Amendment No. 272 Containment Spray Nozzle Technical Specifications Test Requirements | | | title = License Amendment, Issuance of Amendment No. 272 Containment Spray Nozzle Technical Specifications Test Requirements |
| | author name = Wang A B | | | author name = Wang A |
| | author affiliation = NRC/NRR/ADRO/DORL/LPLIV | | | author affiliation = NRC/NRR/ADRO/DORL/LPLIV |
| | addressee name = Mitchell T G | | | addressee name = Mitchell T |
| | addressee affiliation = Entergy Operations, Inc | | | addressee affiliation = Entergy Operations, Inc |
| | docket = 05000368 | | | docket = 05000368 |
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| =Text= | | =Text= |
| {{#Wiki_filter:July 2, 2007Mr. Timothy G. MitchellVice President, Operations Arkansas Nuclear One Entergy Operations, Inc. | | {{#Wiki_filter:July 2, 2007 Mr. Timothy G. Mitchell Vice President, Operations Arkansas Nuclear One Entergy Operations, Inc. |
| 1448 S. R. 333 Russellville, AR 72802 | | 1448 S. R. 333 Russellville, AR 72802 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| ARKANSAS NUCLEAR ONE, UNIT NO. 2 - ISSUANCE OF AMENDMENT RE: CONTAINMENT SPRAY NOZZLE TECHNICAL SPECIFICATIONS TEST REQUIREMENTS (TAC NO. MD4835) | | ARKANSAS NUCLEAR ONE, UNIT NO. 2 - ISSUANCE OF AMENDMENT RE: |
| | CONTAINMENT SPRAY NOZZLE TECHNICAL SPECIFICATIONS TEST REQUIREMENTS (TAC NO. MD4835) |
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| ==Dear Mr. Mitchell:== | | ==Dear Mr. Mitchell:== |
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| The Commission has issued the enclosed Amendment No. 272 to Facility Operating LicenseNo. NPF-6 for Arkansas Nuclear One, Unit No. 2. The amendment consists of changes to the Technical Specifications in response to your application dated March 15, 2007. The amendment revises the Surveillance Requirement (SR) 4.6.2.1.d to require verification thatcontainment spray nozzles are unobstructed following maintenance that could result in nozzle blockage, in lieu of the current SR of performing the test every 5 years.A copy of our related Safety Evaluation is also enclosed. The Notice of Issuance will beincluded in the Commission's next biweekly Federal Register notice.Sincerely,/RA/Alan B. Wang, Project ManagerPlant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-368 | | The Commission has issued the enclosed Amendment No. 272 to Facility Operating License No. NPF-6 for Arkansas Nuclear One, Unit No. 2. The amendment consists of changes to the Technical Specifications in response to your application dated March 15, 2007. |
| | The amendment revises the Surveillance Requirement (SR) 4.6.2.1.d to require verification that containment spray nozzles are unobstructed following maintenance that could result in nozzle blockage, in lieu of the current SR of performing the test every 5 years. |
| | A copy of our related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice. |
| | Sincerely, |
| | /RA/ |
| | Alan B. Wang, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-368 |
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| ==Enclosures:== | | ==Enclosures:== |
| : 1. Amendment No. 272 to NPF-62. Safety Evaluationcc w/encls:See next page | | : 1. Amendment No. 272 to NPF-6 |
| | : 2. Safety Evaluation cc w/encls: See next page |
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| Pkg ML071550002 (Amdt./License ML071550003, TS Pgs ML071550004)OFFICENRR/LPL4/PMNRR/LPL4/LADSS/SCVB/BCOGC - NLO subj to commentNRR/LPL4/BCNAMEAWangJBurkhardtRDennigJBonannoTHiltz DATE6/11/076/11/075/23/076/13/077/2/07 February 2007Arkansas Nuclear One cc:Executive Vice President | | Pkg ML071550002 (Amdt./License ML071550003, TS Pgs ML071550004) |
| & Chief Operating Officer Entergy Operations, Inc.
| | OFFICE NRR/LPL4/PM NRR/LPL4/LA DSS/SCVB/BC OGC - NLO subj to comment NRR/LPL4/BC NAME AWang JBurkhardt RDennig JBonanno THiltz DATE 6/11/07 6/11/07 5/23/07 6/13/07 7/2/07 Arkansas Nuclear One cc: |
| P.O. Box 31995 Jackson, MS 39286-1995General Manager PlantOperations Entergy Operations, Inc. | | Executive Vice President Section Chief, Division of Health |
| Arkansas Nuclear One 1448 SR 333 Russellville, AR 72802Director, Nuclear Safety AssuranceEntergy Operations, Inc. | | & Chief Operating Officer Emergency Management Section Entergy Operations, Inc. Arkansas Department of Health and P.O. Box 31995 Human Services Jackson, MS 39286-1995 4815 West Markham Street, Slot 30 Little Rock, AR 72205-3867 General Manager Plant Operations Senior Resident Inspector Entergy Operations, Inc. U.S. Nuclear Regulatory Commission Arkansas Nuclear One P.O. Box 310 1448 SR 333 London, AR 72847 Russellville, AR 72802 Regional Administrator, Region IV Director, Nuclear Safety Assurance U.S. Nuclear Regulatory Commission Entergy Operations, Inc. 611 Ryan Plaza Drive, Suite 400 Arkansas Nuclear One Arlington, TX 76011-8064 1448 SR 333 Russellville, AR 72802 County Judge of Pope County 100 W. Main Street Manager, Licensing Russellville, AR 72801 Entergy Operations, Inc. |
| Arkansas Nuclear One 1448 SR 333 Russellville, AR 72802Manager, LicensingEntergy Operations, Inc. | | Arkansas Nuclear One Vice President, Operations Support 1448 SR 333 Entergy Operations, Inc. |
| Arkansas Nuclear One 1448 SR 333 Russellville, AR 72802Director, Nuclear Safety & LicensingEntergy Operations, Inc. | | Russellville, AR 72802 P.O. Box 31995 Jackson, MS 39286-1995 Director, Nuclear Safety & Licensing Entergy Operations, Inc. |
| 1340 Echelon Parkway Jackson, MS 39213-8298Section Chief, Division of HealthRadiation Control Section Arkansas Department of Health and Human Services 4815 West Markham Street, Slot 30 Little Rock, AR 72205-3867Section Chief, Division of HealthEmergency Management Section Arkansas Department of Health and Human Services 4815 West Markham Street, Slot 30 Little Rock, AR 72205-3867Senior Resident InspectorU.S. Nuclear Regulatory Commission P.O. Box 310 London, AR 72847Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064County Judge of Pope County 100 W. Main Street Russellville, AR 72801Vice President, Operations SupportEntergy Operations, Inc. | | 1340 Echelon Parkway Jackson, MS 39213-8298 Section Chief, Division of Health Radiation Control Section Arkansas Department of Health and Human Services 4815 West Markham Street, Slot 30 Little Rock, AR 72205-3867 February 2007 |
| P.O. Box 31995 Jackson, MS 39286-1995 ENTERGY OPERATIONS, INC.DOCKET NO. 50-368ARKANSAS NUCLEAR ONE, UNIT NO. 2AMENDMENT TO RENEWED FACILITY OPERATING LICENSEAmendment No. 272Renewed License No. NPF-61.The Nuclear Regulatory Commission (the Commission) has found that:A.The application for amendment by Entergy Operations, Inc. (the licensee), datedMarch 15, 2007, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I;B.The facility will operate in conformity with the application, the provisions of theAct, and the rules and regulations of the Commission;C.There is reasonable assurance (i) that the activities authorized by thisamendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations;D.The issuance of this license amendment will not be inimical to the commondefense and security or to the health and safety of the public; and E.The issuance of this amendment is in accordance with 10 CFR Part 51 of theCommission's regulations and all applicable requirements have been satisfied. 2.Accordingly, the license is amended by changes to the Technical Specifications andparagraph 2.C.(2) of Renewed Facility Operating License No. NPF-6 as indicated in the attachment to this license amendment.3.The license amendment is effective as of its date of issuance and shall be implementedwithin 60 days from the date of issuance.FOR THE NUCLEAR REGULATORY COMMISSION/RA/Thomas G. Hiltz, ChiefPlant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
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| | ENTERGY OPERATIONS, INC. |
| | DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE, UNIT NO. 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 272 Renewed License No. NPF-6 |
| | : 1. The Nuclear Regulatory Commission (the Commission) has found that: |
| | A. The application for amendment by Entergy Operations, Inc. (the licensee), dated March 15, 2007, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied. |
| | : 2. Accordingly, the license is amended by changes to the Technical Specifications and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-6 as indicated in the attachment to this license amendment. |
| | : 3. The license amendment is effective as of its date of issuance and shall be implemented within 60 days from the date of issuance. |
| | FOR THE NUCLEAR REGULATORY COMMISSION |
| | /RA/ |
| | Thomas G. Hiltz, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation |
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| ==Attachment:== | | ==Attachment:== |
| Changes to the Renewed Facility Operating License No. NPF-6 and the Technical SpecificationsDate of Issuance: July 2, 2007 ATTACHMENT TO LICENSE AMENDMENT NO. 272RENEWED FACILITY OPERATING LICENSE NO. NPF-6DOCKET NO. 50-368Replace the following pages of the Renewed Facility Operating License No. NPF-6 andAppendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change. Operating LicenseREMOVEINSERT-3--3-Technical SpecificationsREMOVEINSERT3/4 6-113/4 6-11 3facility at the designated location in Pope County, Arkansas in accordancewith the procedures and limitations set forth in this renewed license;(3)EOI, pursuant to the Act and 10 CFR Part 70, to receive, possess and use atany time at the facility site and as designated solely for the facility, special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended;(4)EOI, pursuant to the Act and 10 CFR Parts 30, 40 and 70 to receive, possessand use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required;(5)EOI, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive,possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and(6)EOI, pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but notseparate, such byproduct and special nuclear materials as may be produced by the operation of the facility.C.This renewed license shall be deemed to contain and is subject to conditionsspecified in the following Commission regulations in 10 CFR Chapter 1; Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:(1)Maximum Power LevelEOI is authorized to operate the facility at steady state reactor core powerlevels not in excess of 3026 megawatts thermal. Prior to attaining this power level EOI shall comply with the conditions in Paragraph 2.C.(3).(2)Technical SpecificationsThe Technical Specifications contained in Appendix A, as revised throughAmendment No. 272 are hereby incorporated in the renewed lRenewed License No. NPF-6Amendment No. 272 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONRELATED TO AMENDMENT NO. 272 TORENEWED FACILITY OPERATING LICENSE NO. NPF-6ENTERGY OPERATIONS, INC.ARKANSAS NUCLEAR ONE, UNIT NO. 2DOCKET NO. 50-36 | | Changes to the Renewed Facility Operating License No. NPF-6 and the Technical Specifications Date of Issuance: July 2, 2007 |
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| | ATTACHMENT TO LICENSE AMENDMENT NO. 272 RENEWED FACILITY OPERATING LICENSE NO. NPF-6 DOCKET NO. 50-368 Replace the following pages of the Renewed Facility Operating License No. NPF-6 and Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change. |
| | Operating License REMOVE INSERT Technical Specifications REMOVE INSERT 3/4 6-11 3/4 6-11 |
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| | 3 facility at the designated location in Pope County, Arkansas in accordance with the procedures and limitations set forth in this renewed license; (3) EOI, pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time at the facility site and as designated solely for the facility, special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (4) EOI, pursuant to the Act and 10 CFR Parts 30, 40 and 70 to receive, possess and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5) EOI, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6) EOI, pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility. |
| | C. This renewed license shall be deemed to contain and is subject to conditions specified in the following Commission regulations in 10 CFR Chapter 1; Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below: |
| | (1) Maximum Power Level EOI is authorized to operate the facility at steady state reactor core power levels not in excess of 3026 megawatts thermal. Prior to attaining this power level EOI shall comply with the conditions in Paragraph 2.C.(3). |
| | (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 272 are hereby incorporated in the renewed l Renewed License No. NPF-6 Amendment No. 272 |
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| | SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 272 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-6 ENTERGY OPERATIONS, INC. |
| | ARKANSAS NUCLEAR ONE, UNIT NO. 2 DOCKET NO. 50-368 |
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| ==81.0INTRODUCTION== | | ==1.0 INTRODUCTION== |
| By application dated March 15, 2007 (Agencywide Documents Access and ManagementSystem (ADAMS) Accession No. ML070780351), Entergy Operations, Inc. (the licensee),
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| requested changes to the Technical Specifications (TSs) for Arkansas Nuclear One, Unit No. 2(ANO-2). The proposed changes would revise Surveillance Requirement (SR) 4.6.2.1.d to requireverification that containment spray nozzles are unobstructed following maintenance that could result in nozzle blockage in lieu of the current SR of performing the test every 5 years.
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| Specifically, the proposed change would change SR 4.6.2.1.d from "At least once per five years by performing an air or smoke flow test through each spray header and verifying each nozzle is unobstructed" to "verify each spray nozzle is unobstructed following maintenance which could result in nozzle blockage". This SR is required by TS 3/4.6.2, "Depressurization, Cooling, and pH Control Systems Containment Spray System."
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| ==2.0REGULATORY EVALUATION==
| | By application dated March 15, 2007 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML070780351), Entergy Operations, Inc. (the licensee), |
| Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix A contains GeneralDesign Criteria (GDC) for nuclear power reactors. In particular, GDC 40 requires that the containment heat-removal system be designed to permit periodic testing. The containment spray system is a containment heat-removal system. The Combustion Engineering Standard Technical Specifications, NUREG-1432, Volume 1, Revision 2, dated March 2003, specifies in SR 3.6.6.A.9 a testing frequency of 10 years for the nozzle blockage test. While this is not a requirement, it had been the U.S. Nuclear Regulatory Commission's (NRC's) and industry's judgment of an acceptable frequency for this test. The current TSs require ANO-2 to test the containment spray nozzles every 5 years.
| | requested changes to the Technical Specifications (TSs) for Arkansas Nuclear One, Unit No. 2 (ANO-2). |
| | The proposed changes would revise Surveillance Requirement (SR) 4.6.2.1.d to require verification that containment spray nozzles are unobstructed following maintenance that could result in nozzle blockage in lieu of the current SR of performing the test every 5 years. |
| | Specifically, the proposed change would change SR 4.6.2.1.d from At least once per five years by performing an air or smoke flow test through each spray header and verifying each nozzle is unobstructed to verify each spray nozzle is unobstructed following maintenance which could result in nozzle blockage. This SR is required by TS 3/4.6.2, Depressurization, Cooling, and pH Control Systems Containment Spray System. |
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| ==3.0TECHNICAL EVALUATION== | | ==2.0 REGULATORY EVALUATION== |
| The Containment Spray System (CSS) is an Engineered Safety Feature used in response to apostulated Loss-of-Coolant Accident (LOCA). The CSS is designed to:*Maintain reactor containment building pressure within design limits,
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| *Reduce the quantity of airborne iodine, and
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| *Establish the sump pH to retain elemental iodine.These functions are performed by subcooled water solution sprayed into the containmentatmosphere through nozzles from the spray headers located in the containment dome.The licensee requested a change to revise TS SR 4.6.2.1.d, from requiring "at least once perfive years by performing an air or smoke flow test through each spray header and verifying each spray nozzle is unobstructed" to requiring verification each CSS spray nozzle is free from obstruction following maintenance that could result in nozzle blockage (loss-of-foreign-material exclusion (FME) control).The CSS sprays have been tested every 5 years since original plant construction and thesetests have confirmed that the nozzles are free of obstructions that could have occurred following startup, operation, and maintenance of the system. The licensee stated that the containment spray nozzles are Sprayco model 1713A nozzles which have a swirl chamber design and have no moving parts in the nozzle to plug. The licensee also stated that the spray ring header is maintained dry and that the piping, ring headers, and nozzles are constructed of type 304 stainless steel. Therefore, the formation of corrosion products or loose parts that could cause nozzle plugging is unlikely.The licensee maintains an FME program which is implemented by Procedure EN-MA-118,"Foreign Material Exclusion." The procedure describes measures to be taken to ensure foreign material is not introduced into a system or component and describes measures to be taken if material or tool accountability is lost. This procedure applies to all station activities having the potential to introduce foreign material into systems or components which could impact plant safety. The requirements of the procedure apply when maintenance, modifications, repairs, inspections and operating activities are being conducted on open piping and equipment. The procedure establishes various levels for preventing the generation of debris when breaching a system and the removal of debris from the system if materials have entered a system. Pre-job briefs for FME are conducted prior to opening systems where foreign materials can be introduced. This procedure also requires personnel who are working on open components/systems receive FME training as part of their job qualifications. The procedure requires that when closing a system or component, an inspection be performed to ensure that all foreign material is removed. If FME is not maintained, a Condition Report is initiated requiring an assessment of the circumstances and implementation of the corrective actions to prevent reoccurrence.Due to its location at the top of the containment, introduction of foreign material into the sprayheader via the open nozzles is unlikely. Foreign material introduced as a result of maintenance is the most likely cause for obstruction; therefore, verification that no foreign material hasentered the system following such maintenance is sufficient to confirm that the nozzles are free from blockage. Therefore, the potential for unidentified nozzle obstruction is very low.The NRC staff reviewed the NRC Inspection Reports for Arkansas Nuclear One, Unit 1, andANO-2 for the years 2000 through 2006. There were no significant findings identified in those reports that would indicate lapses in the FME program. Based on a review of these reports, the FME program appears to be effective.The NRC staff previously approved, on a plant-specific basis, similar revisions to thisrequirement. The revisions require verification that each spray nozzle is unobstructed only following maintenance that could potentially result in nozzle blockage. This is based on the judgment that once the CSS nozzles are determined to be unobstructed, the only mechanisms that can cause nozzle blockage is foreign material introduced following maintenance and corrosion deposits. The first concern is addressed by the licensee's FME program. The second concern is addressed by the piping system being constructed out of corrosion-resistant materials.NUREG-1366, "Improvements to Technical Specifications Surveillance Requirements," (May1992) reported on an NRC staff review of industry experience which indicated that CSS' of similar design are highly reliable and are not subject to plugging after testing following construction. The NRC staff reviewed industry experience and found that, in general, once tested after construction, CSS have not been subject to blockage. There have been several exceptions. In the case of one pressurized-water reactor (PWR), a chemical added to the inner surface of a spray system pipe to eliminate corrosion detached and the loose material blocked some spray nozzles. The piping at ANO-2 is corrosion resistant; therefore, this failure mechanism is unlikely. The licensee for another PWR found debris, identified as constructiondebris, in the spray nozzle headers (Licensee Event Report 315/98-027). The fraction of blockage was not significant and the sprays remained functional. The debris was found by visual observation, not by an air flow test. The licensee states that the containment spray nozzles have been tested five times in addition to pre-operational tests. Pre-operational testing identified eight nozzles that had blocked flow. After removal of the blockage, air flow was verified through all containment spray nozzles. Subsequent in-place air flow tests have demonstrated unobstructed flow through each nozzle. Tests have confirmed that the system was free from construction debris and that no debris that could cause obstructions had entered the systems following startup and operation of ANO-2.Based on the NRC staff's review and assessment of the applicable information provided by thelicensee in its amendment request, the NRC staff concludes that the design of the ANO-2 CSS, the past history of these spray systems, and the licensee's FME controls provide reasonable assurance that the potential for nozzle obstruction is acceptably low. The FME controls provide reasonable protection from the introduction of foreign materials into open piping during maintenance or testing and require post-maintenance verification of system cleanliness and freedom from foreign materials. In addition, the NRC staff review of industry-wide experience has indicated that the licensee's proposed change is acceptable. Therefore, the NRC staff finds the amendment request acceptable.
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| ==4.0STATE CONSULTATION==
| | Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix A contains General Design Criteria (GDC) for nuclear power reactors. In particular, GDC 40 requires that the containment heat-removal system be designed to permit periodic testing. The containment spray system is a containment heat-removal system. The Combustion Engineering Standard Technical Specifications, NUREG-1432, Volume 1, Revision 2, dated March 2003, specifies in SR 3.6.6.A.9 a testing frequency of 10 years for the nozzle blockage test. While this is not a requirement, it had been the U.S. Nuclear Regulatory Commissions (NRCs) and industrys judgment of an acceptable frequency for this test. The current TSs require ANO-2 to test the containment spray nozzles every 5 years. |
| In accordance with the Commission's regulations, the Arkansas State official was notified of theproposed issuance of the amendment. The State official had no comments. | |
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| ==5.0ENVIRONMENTAL CONSIDERATION== | | ==3.0 TECHNICAL EVALUATION== |
| The amendment changes a requirement with respect to installation or use of a facilitycomponent located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. TheCommission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding published on April 24, 2007 (72 FR 20381). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), | | |
| | The Containment Spray System (CSS) is an Engineered Safety Feature used in response to a postulated Loss-of-Coolant Accident (LOCA). The CSS is designed to: |
| | * Maintain reactor containment building pressure within design limits, |
| | * Reduce the quantity of airborne iodine, and |
| | * Establish the sump pH to retain elemental iodine. |
| | These functions are performed by subcooled water solution sprayed into the containment atmosphere through nozzles from the spray headers located in the containment dome. |
| | The licensee requested a change to revise TS SR 4.6.2.1.d, from requiring at least once per five years by performing an air or smoke flow test through each spray header and verifying each spray nozzle is unobstructed to requiring verification each CSS spray nozzle is free from obstruction following maintenance that could result in nozzle blockage (loss-of-foreign-material exclusion (FME) control). |
| | The CSS sprays have been tested every 5 years since original plant construction and these tests have confirmed that the nozzles are free of obstructions that could have occurred following startup, operation, and maintenance of the system. The licensee stated that the containment spray nozzles are Sprayco model 1713A nozzles which have a swirl chamber design and have no moving parts in the nozzle to plug. The licensee also stated that the spray ring header is maintained dry and that the piping, ring headers, and nozzles are constructed of type 304 stainless steel. Therefore, the formation of corrosion products or loose parts that could cause nozzle plugging is unlikely. |
| | The licensee maintains an FME program which is implemented by Procedure EN-MA-118, Foreign Material Exclusion. The procedure describes measures to be taken to ensure foreign material is not introduced into a system or component and describes measures to be taken if material or tool accountability is lost. This procedure applies to all station activities having the potential to introduce foreign material into systems or components which could impact plant safety. The requirements of the procedure apply when maintenance, modifications, repairs, inspections and operating activities are being conducted on open piping and equipment. The procedure establishes various levels for preventing the generation of debris when breaching a system and the removal of debris from the system if materials have entered a system. Pre-job briefs for FME are conducted prior to opening systems where foreign materials can be introduced. This procedure also requires personnel who are working on open components/systems receive FME training as part of their job qualifications. The procedure requires that when closing a system or component, an inspection be performed to ensure that all foreign material is removed. If FME is not maintained, a Condition Report is initiated requiring an assessment of the circumstances and implementation of the corrective actions to prevent reoccurrence. |
| | Due to its location at the top of the containment, introduction of foreign material into the spray header via the open nozzles is unlikely. Foreign material introduced as a result of maintenance |
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| | is the most likely cause for obstruction; therefore, verification that no foreign material has entered the system following such maintenance is sufficient to confirm that the nozzles are free from blockage. Therefore, the potential for unidentified nozzle obstruction is very low. |
| | The NRC staff reviewed the NRC Inspection Reports for Arkansas Nuclear One, Unit 1, and ANO-2 for the years 2000 through 2006. There were no significant findings identified in those reports that would indicate lapses in the FME program. Based on a review of these reports, the FME program appears to be effective. |
| | The NRC staff previously approved, on a plant-specific basis, similar revisions to this requirement. The revisions require verification that each spray nozzle is unobstructed only following maintenance that could potentially result in nozzle blockage. This is based on the judgment that once the CSS nozzles are determined to be unobstructed, the only mechanisms that can cause nozzle blockage is foreign material introduced following maintenance and corrosion deposits. The first concern is addressed by the licensees FME program. The second concern is addressed by the piping system being constructed out of corrosion-resistant materials. |
| | NUREG-1366, Improvements to Technical Specifications Surveillance Requirements, (May 1992) reported on an NRC staff review of industry experience which indicated that CSS' of similar design are highly reliable and are not subject to plugging after testing following construction. The NRC staff reviewed industry experience and found that, in general, once tested after construction, CSS have not been subject to blockage. There have been several exceptions. In the case of one pressurized-water reactor (PWR), a chemical added to the inner surface of a spray system pipe to eliminate corrosion detached and the loose material blocked some spray nozzles. The piping at ANO-2 is corrosion resistant; therefore, this failure mechanism is unlikely. The licensee for another PWR found debris, identified as construction debris, in the spray nozzle headers (Licensee Event Report 315/98-027). The fraction of blockage was not significant and the sprays remained functional. The debris was found by visual observation, not by an air flow test. The licensee states that the containment spray nozzles have been tested five times in addition to pre-operational tests. Pre-operational testing identified eight nozzles that had blocked flow. After removal of the blockage, air flow was verified through all containment spray nozzles. Subsequent in-place air flow tests have demonstrated unobstructed flow through each nozzle. Tests have confirmed that the system was free from construction debris and that no debris that could cause obstructions had entered the systems following startup and operation of ANO-2. |
| | Based on the NRC staffs review and assessment of the applicable information provided by the licensee in its amendment request, the NRC staff concludes that the design of the ANO-2 CSS, the past history of these spray systems, and the licensees FME controls provide reasonable assurance that the potential for nozzle obstruction is acceptably low. The FME controls provide reasonable protection from the introduction of foreign materials into open piping during maintenance or testing and require post-maintenance verification of system cleanliness and freedom from foreign materials. In addition, the NRC staff review of industry-wide experience has indicated that the licensees proposed change is acceptable. Therefore, the NRC staff finds the amendment request acceptable. |
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| | ==4.0 STATE CONSULTATION== |
| | |
| | In accordance with the Commission's regulations, the Arkansas State official was notified of the proposed issuance of the amendment. The State official had no comments. |
| | |
| | ==5.0 ENVIRONMENTAL CONSIDERATION== |
| | |
| | The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding published on April 24, 2007 (72 FR 20381). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), |
| no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment. | | no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment. |
|
| |
|
| ==6.0CONCLUSION== | | ==6.0 CONCLUSION== |
| The Commission has concluded, based on the considerations discussed above, that: (1) thereis reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.Principal Contributor: B. Heida Date: July 2, 2007}} | | |
| | The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public. |
| | Principal Contributor: B. Heida Date: July 2, 2007}} |
Letter Sequence Approval |
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|
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MONTHYEARML0715500042007-07-0202 July 2007 Technical Specifications, Issuance of Amendment No. 272 Containment Spray Nozzle Technical Specifications Test Requirements Project stage: Approval ML0715500032007-07-0202 July 2007 License Amendment, Issuance of Amendment No. 272 Containment Spray Nozzle Technical Specifications Test Requirements Project stage: Approval 2007-07-02
[Table View] |
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Category:Letter
MONTHYEARML23326A0392024-01-24024 January 2024 Issuance of Amendment No. 281 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML24017A1582024-01-17017 January 2024 Submittal of Emergency Plan Revision 50 IR 05000313/20234202024-01-10010 January 2024 Security Baseline Inspection Report 05000313/2023420 and 05000368/2023420 IR 05000313/20234022024-01-0202 January 2024 Security Baseline Inspection Report 05000313/2023402 and 05000368/2023402 ML23354A0022023-12-21021 December 2023 Request for Withholding Information from Public Disclosure ML23349A1672023-12-21021 December 2023 Request for Withholding Information from Public Disclosure ML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology Slides and Affidavit for Pre-Submittal Meeting ML23352A0292023-12-13013 December 2023 Entergy - 2024 Nuclear Energy Liability Evidence of Financial Protection ML23340A1592023-12-13013 December 2023 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment IR 05000313/20234052023-12-12012 December 2023 Security Baseline Inspection Report 05000313/2023405 and 05000368/2023405 ML23341A0832023-12-11011 December 2023 Material Control and Accounting Program Inspection Report 05000313/368/2023404- Cover Letter ML23305A0922023-12-0707 December 2023 Summary of Regulatory Audit Regarding License Amendment Request to Revise Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b ML23333A1362023-11-29029 November 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23275A2072023-11-28028 November 2023 Issuance of Amendment No. 280 Removal of Technical Specification Condition Allowing Two Reactor Coolant Pump Operation ML23325A1412023-11-21021 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000313/20230032023-11-21021 November 2023 Revised - ANO Revised Integrated Inspection Report 05000313/2023003 and 05000368/2023003 and Independent Spent Fuel Storage Installation Inspection Report 07200013/ 2023001 ML23243B0452023-11-13013 November 2023 Request for Withholding Information from Public Disclosure ML23313A0962023-11-13013 November 2023 Integrated Inspection Report 05000313/2023003 and 05000368/2023003 and Independent Spent Fuel Storage Installation Inspection Report 07200013/2023001 ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV IR 05000313/20230112023-10-10010 October 2023 Commercial Grade Dedication Inspection Report 05000313/2023011 and 05000368/2023011 IR 05000313/20230052023-08-21021 August 2023 Updated Inspection Plan for Arkansas Nuclear One, Units 1 and 2 (Report 05000313/2023005 and 05000368/2023005) - Mid Cycle IR 05000313/20243012023-08-14014 August 2023 Notification of NRC Initial Operator Licensing Examination 05000313/2024301 IR 05000313/20230022023-08-11011 August 2023 Integrated Inspection Report 05000313/2023002 and 05000368/2023002 and Notice of Violation ML23209A6022023-08-0909 August 2023 Regulatory Audit Plan in Support of License Amendment Request to Revise Technical Specifications to Adopt Risk- Informed Completion Times IR 05000416/20230022023-08-0808 August 2023 Integrated Inspection Report 05000416/2023002 and Independent Spent Fuel Storage Installation Inspection Report 07200050/2023001 ML23208A2132023-08-0303 August 2023 Regulatory Audit Summary Concerning Review of License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation ML23208A2112023-07-27027 July 2023 Entergy Operations Inc., Application to Revise Technical Specifications to Adopt TSTF-205, Revision of Channel Calibration, Channel Functional Test, and Related Definitions ML23188A1732023-07-12012 July 2023 Request for Withholding Information from Public Disclosure ML23142A2022023-06-29029 June 2023 Issuance of Amendment Nos. 279 and 332 Emergency Plan Staffing Requirements IR 05000313/20234032023-06-28028 June 2023 Security Baseline Inspection Report 05000313/2023403 and 05000368/2023403 ML23178A0892023-06-26026 June 2023 August 2023 Emergency Preparedness Program Inspection-Request for Information ML23166B0902023-06-21021 June 2023 Request for Relief ANO1 ISI 036 Regarding Volumetric Examination Requirements ML23180A1082023-06-20020 June 2023 ANO Unit 1 SAR Amendment 31, TRM, TS Bases, 10 CFR 50.59 Report, and Commitment Change Summary Report IR 05000313/20234012023-06-13013 June 2023 Cyber Security Inspection Report 05000313/2023401 and 05000368/2023401 ML23130A2972023-05-17017 May 2023 Notification of Inspection (NRC Inspection Report 05000313/2023003) and Request for Information ML23121A3012023-05-10010 May 2023 Regulatory Audit Plan in Support of License Amendment Request to Revise Technical Specifications to Adopt Risk - Informed Completion Times ML23114A3572023-05-10010 May 2023 Regulatory Audit Summary Concerning Review of Request for Alternative ANO-CISI-002 Regarding Containment Inservice Inspection Frequency ML23130A2732023-05-10010 May 2023 and Waterford 3 Steam Electric Station - Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000313/20230012023-05-0909 May 2023 Integrated Inspection Report 05000313/2023001 and 05000368/2023001 ML23118A3202023-05-0808 May 2023 Notification of Biennial Problem Identification and Resolution Inspection and Request for Information (05000313;05000368/2023010) IR 05000368/20233012023-05-0101 May 2023 NRC Examination Report 05000368/2023301 ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML23108A1362023-04-24024 April 2023 Approval of Request for Half-Nozzle Repair of Reactor Vessel Closure Head Penetration No. 46 ML23110A1122023-04-20020 April 2023 Annual Report for Entergy Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d). Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G 2024-01-24
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML23326A0392024-01-24024 January 2024 Issuance of Amendment No. 281 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML23275A2072023-11-28028 November 2023 Issuance of Amendment No. 280 Removal of Technical Specification Condition Allowing Two Reactor Coolant Pump Operation ML23020A9362023-01-27027 January 2023 Audit Plan to Support Review of License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation ML22263A1912022-12-0909 December 2022 Issuance of Amendment No. 278 Revision to Technical Specifications 3.4.12 and 3.4.13 Based on Revised Dose Calculations (EPID L-2021-LLA-0181) - Non-Proprietary ML22291A2392022-10-28028 October 2022 Notice of Consideration of Issuance of Amendment to Renewed Facility Operating License, Proposed Nshcd, and Opportunity for a Hearing and Order Imposing Procedures for Document Access to SUNSI (EPID L-2021-LLA-0181) Letter ML22165A2442022-07-19019 July 2022 Issuance of Amendment No. 331 Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML22138A4312022-06-23023 June 2022 Issuance of Amendment No. 277 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML22104A2222022-05-12012 May 2022 Issuance of Amendments Revise Technical Specifications to Adopt TSTF 554 ML22083A1242022-04-28028 April 2022 Arkansas, Units 1 and 2; Grand Gulf Nuclear Station; River Bend Station; and Waterford Steam Electric Station - Issuance of Amendments Revise Technical Specifications to Adopt TSTF-541, Revision 2 ML22039A2822022-03-15015 March 2022 Issuance of Amendment Nos. 274 and 328 One-Time Change to Support Proactive Upgrade of the Emergency Cooling Pond Supply Piping ML21225A0552021-12-17017 December 2021 Issuance of Amendment No. 327 Addition of Technical Specification Limiting Condition for Operation 3.0.6 and Adoption of Safety Function Determination Program ML21341B2262021-12-13013 December 2021 Acceptance of Requested Licensing Action License Amendment Request to Revise Technical Specifications 3.4.12 and 3.4.13 Based on Revised Dose Calculations ML21313A0082021-12-0808 December 2021 Issuance of Amendments to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML21320A2122021-11-17017 November 2021 Supplemental Information Needed for Acceptance of Requested Licensing Action License Amendment Request Concerning Revised Dose Calculations ML21281A2542021-10-15015 October 2021 Audit Meeting Agenda & Audit Questions for LAR to Adopt 10 CFR 50.69,Risk-Informed Categorization and Treatment of Structures, System, and Components for Nuclear Power Reactors (EPIDs L-2021-LLA-0105, L-2021-LLA-0106 ML21208A4492021-09-20020 September 2021 Issuance of Amendment No. 325 Revise Loss of Voltage Relay Allowable Values and Number of Degraded Voltage Channels ML21088A4332021-04-14014 April 2021 Issuance of Amendment No. 324 Adoption of Technical Specification Task Force Traveler, TSTF-569, Revision 2, Revise Response Time Testing Definition ML21027A4282021-03-23023 March 2021 Issuance of Amendment No. 272 Replacement of Reactor Building Spray Sodium Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent ML21040A5132021-03-10010 March 2021 Issuance of Amendment No. 271 Revision to Loss of Voltage Relay Allowable Values ML20351A1532021-02-0808 February 2021 Issuance of Amendment No. 323 Technical Specification Deletions, Additions, and Relocations NUREG-1432, Issuance of Amendment No. 322 Technical Specification Changes Related to Revised Fuel Handling Accident Analysis and Adoption of Technical Specification Improvements Consistent with NUREG-14322020-10-30030 October 2020 Issuance of Amendment No. 322 Technical Specification Changes Related to Revised Fuel Handling Accident Analysis and Adoption of Technical Specification Improvements Consistent with NUREG-1432 ML20135H1412020-06-30030 June 2020 Issuance of Amendment Nos. 269 and 321 Request to Incorporate the Tornado Missile Risk Evaluator Into the Licensing Basis ML20160A1472020-06-30030 June 2020 Issuance of Amendment No. 270 to Adopt TSTF 563, Revision 0, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML20087L8032020-04-0808 April 2020 Issuance of Amendment No. 320 to Revise Control Element Assembly Drop Times ML19231A2972020-01-29029 January 2020 Issuance of Amendment No. 318 Addition of Technical Specification Actions to Address Inoperability of the Containment Building Sump ML19269B6722019-10-22022 October 2019 Issuance of Amendment Nos. 267 and 317 to Extend Implementation Dates for Amendment Nos. 263 and 314, Revision to Emergency Action Level Scheme ML19220A9382019-09-27027 September 2019 Issuance of Amendment No. 266 Adoption of Technical Specifications Task Force Traveler TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues ML19175A0422019-09-11011 September 2019 Arkansas Units 1 and 2; Grand Gulf, Unit 1; Indian Point 2 and 3; Palisades; River Bend, Unit 1; Waterford Unit 3 - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules ML19098A9552019-05-22022 May 2019 Issuance of Amendment No. 264 Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-425, Revision 3 ML19127A2992019-05-15015 May 2019 Correction to Amendment No. 315 Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-425, Revision 3 ML19063B9482019-04-23023 April 2019 Issuance of Amendment No. 315 Adoption of Technical Specification Task Force Traveler TSTF-425, Revision 3 ML18337A2472019-01-17017 January 2019 Issuance of Amendment Nos. 263 and 314 Revision to Emergency Action Level Scheme ML18317A3822018-12-19019 December 2018 Issuance of Amendment No. 313, Revise Technical Specification 3.3.3.6, Post-Accident Instrumentation ML18306A5132018-11-30030 November 2018 Issuance of Conforming Amendment Nos. 262, 312 and 215 Transfers of Renewed Facility Operating Licenses ML18298A0122018-11-27027 November 2018 Issuance of Amendment No. 311 Updating the Reactor Coolant System Pressure Temperature Limits ML18260A3392018-10-24024 October 2018 Issuance of Amendment No. 261 Revision to Technical Specification Bases Related to Emergency Feedwater Turbine-Driven Pump Steam Supply Valves ML18115A2822018-06-19019 June 2018 Issuance of Amendment No. 260 Technical Specification Changes Pursuant to Technical Specifications Task Force (TSTF) Traveler TSTF-412 Revision 3 (CAC No. MG0009; EPID L-2017-LLA-0267) ML18134A2532018-06-19019 June 2018 Issuance of Amendment No. 310 Technical Specification Changes to Provide Actions for Emergency Feedwater Pump Inoperability Consistent with NUREG-1432, Revision 4 (CAC No. MG0016; EPID L-2017-LLA-0268) ML18051A5892018-02-26026 February 2018 Issuance of Amendment No. 309 to Adopt TSTF-427, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability (CAC No. MG0131; EPID L-2017-LLA-0302) ML18033A1752018-02-26026 February 2018 Issuance of Amendment No. 259 to Adopt TSTF-427, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability (CAC No. MG0132; EPID L-2017-LLA-0301) ML18011A0642018-01-18018 January 2018 Issuance of Amendment No. 308 to Exclude Exercise of Control Element Assembly 4 with Respect to Surveillance Requirement 4.1.3.1.2 for the Remainder of Cycle 26 (Exigent Circumstances) ML17251A2112017-10-10010 October 2017 Issuance of Amendment No. 307 Revision of Steam Generator Technical Specifications to Reflect Adoption of Technical Specifications Task Force Traveler TSTF-510 (CAC MF9654; EPID L-2017-LLA-0222) ML17235A5192017-10-10010 October 2017 Issuance of Amendment No. 258 Revision of Steam Generator Technical Specifications to Reflect Adoption of TSTF-510 (CAC MF9653; EPID L-2017-LLA-0221) ML17096A2352017-05-12012 May 2017 Issuance of Amendment No. 306 Request to Revise the National Fire Protection Association (NFPA) Standard 805 Modifications ML16215A3712017-03-29029 March 2017 Issuance of Amendment No. 305 to Adopt Technical Specifications Task Force Traveler TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing... ML16165A4232017-03-10010 March 2017 Issuance of Amendment No. 257 Adoption of Technical Specifications Task Force Traveler TSTF-545, Revision 3, ML16267A1392016-12-29029 December 2016 Issuance of Amendment Revise Technical Specfications to Adopt TSTF-426, to Revise or Add Actions to Preclude Entry Into Lco 3.0.3 Ritstf Initiative 6b & 6c ML16223A4812016-10-0707 October 2016 Issuance of Amendment No. 256 Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with 10 CFR 50.48(c) (Cac No. MF3419) ML16027A1092016-02-24024 February 2016 Issuance of Amendment Nos. 255 and 303 Cyber Security Plan Implementation Schedule (CAC Nos. MF6258 and MF6259) ML15096A3812015-04-29029 April 2015 Issuance of Amendment No. 302, Revise Technical Specification Surveillance Requirement 4.1.3.1.2 Note to Eliminate Movement of Control Element Assembly 18 for Remainder of Operating Cycle 24 2024-01-24
[Table view] Category:Safety Evaluation
MONTHYEARML23326A0392024-01-24024 January 2024 Issuance of Amendment No. 281 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML23275A2072023-11-28028 November 2023 Issuance of Amendment No. 280 Removal of Technical Specification Condition Allowing Two Reactor Coolant Pump Operation ML23142A2022023-06-29029 June 2023 Issuance of Amendment Nos. 279 and 332 Emergency Plan Staffing Requirements ML23166B0902023-06-21021 June 2023 Request for Relief ANO1 ISI 036 Regarding Volumetric Examination Requirements ML23142A1062023-05-24024 May 2023 Authorization and Safety Evaluation for Alternative Request No. ANO1-ISI-035 ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML22342B1602023-01-10010 January 2023 Requests for Relief ANO2-ISI-023, -024, -025, -026, -027, and -028 to Permit Reduction of Inspection Area Due to Interference (EPIDs L-2022-LLR-0022,-0023, -0024, -0025, -0026, and -0027) ML22263A1912022-12-0909 December 2022 Issuance of Amendment No. 278 Revision to Technical Specifications 3.4.12 and 3.4.13 Based on Revised Dose Calculations (EPID L-2021-LLA-0181) - Non-Proprietary ML22236A5452022-08-26026 August 2022 Correction to Issuance of Amendment No. 331 Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML22138A4312022-06-23023 June 2022 Issuance of Amendment No. 277 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML22104A2222022-05-12012 May 2022 Issuance of Amendments Revise Technical Specifications to Adopt TSTF 554 ML22083A1242022-04-28028 April 2022 Arkansas, Units 1 and 2; Grand Gulf Nuclear Station; River Bend Station; and Waterford Steam Electric Station - Issuance of Amendments Revise Technical Specifications to Adopt TSTF-541, Revision 2 ML22039A2822022-03-15015 March 2022 Issuance of Amendment Nos. 274 and 328 One-Time Change to Support Proactive Upgrade of the Emergency Cooling Pond Supply Piping ML22007A3172022-01-18018 January 2022 1, River Bend Station 1, and Waterford Steam Electric Station 3 - Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI ML21225A0552021-12-17017 December 2021 Issuance of Amendment No. 327 Addition of Technical Specification Limiting Condition for Operation 3.0.6 and Adoption of Safety Function Determination Program ML21341B2262021-12-13013 December 2021 Acceptance of Requested Licensing Action License Amendment Request to Revise Technical Specifications 3.4.12 and 3.4.13 Based on Revised Dose Calculations ML21313A0082021-12-0808 December 2021 Issuance of Amendments to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML21208A4492021-09-20020 September 2021 Issuance of Amendment No. 325 Revise Loss of Voltage Relay Allowable Values and Number of Degraded Voltage Channels ML21132A2792021-05-19019 May 2021 Request for Approval of Change to the Entergy Quality Assurance Program Manual ML21088A4332021-04-14014 April 2021 Issuance of Amendment No. 324 Adoption of Technical Specification Task Force Traveler, TSTF-569, Revision 2, Revise Response Time Testing Definition ML21027A4282021-03-23023 March 2021 Issuance of Amendment No. 272 Replacement of Reactor Building Spray Sodium Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent ML21040A5132021-03-10010 March 2021 Issuance of Amendment No. 271 Revision to Loss of Voltage Relay Allowable Values ML20351A1532021-02-0808 February 2021 Issuance of Amendment No. 323 Technical Specification Deletions, Additions, and Relocations ML20288A8242020-11-16016 November 2020 Regulatory Audit Summary Concerning License Amendment Request to Replace the Reactor Building Spray Sodium Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent NUREG-1432, Issuance of Amendment No. 322 Technical Specification Changes Related to Revised Fuel Handling Accident Analysis and Adoption of Technical Specification Improvements Consistent with NUREG-14322020-10-30030 October 2020 Issuance of Amendment No. 322 Technical Specification Changes Related to Revised Fuel Handling Accident Analysis and Adoption of Technical Specification Improvements Consistent with NUREG-1432 ML20226A2722020-08-18018 August 2020 Request to Use a Provision of a Later Edition of the ASME BPV Code, Section XI ML20160A1472020-06-30030 June 2020 Issuance of Amendment No. 270 to Adopt TSTF 563, Revision 0, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML20135H1412020-06-30030 June 2020 Issuance of Amendment Nos. 269 and 321 Request to Incorporate the Tornado Missile Risk Evaluator Into the Licensing Basis ML20121A1932020-05-0606 May 2020 Alternative Requests for the Fifth 10 Year Interval Inservice Testing of Low Pressure Safety Injection Pumps and Service Water Valves ML20107J3172020-04-23023 April 2020 Relief Request ANO1-ISI-033 Related to ASME Code Case N-729-4 Supplemental Examination Requirements of Reactor Vessel Closure Head Penetration Nozzles ML20087L8032020-04-0808 April 2020 Issuance of Amendment No. 320 to Revise Control Element Assembly Drop Times ML20083J9682020-03-26026 March 2020 Approval of Request for Alternative ANO 2-PT-002 End-of-Internal System Leakage Test for Extended Reactor Coolant Pressure Boundary Piping ML19231A2972020-01-29029 January 2020 Issuance of Amendment No. 318 Addition of Technical Specification Actions to Address Inoperability of the Containment Building Sump ML19220A9382019-09-27027 September 2019 Issuance of Amendment No. 266 Adoption of Technical Specifications Task Force Traveler TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues ML19254A6032019-09-19019 September 2019 Units 2 and 3; Palisades Nuclear Plant; River Bend; and Waterford Steam Electric Station, Unit 3 - Relief Request No. EN-19-RR-1, Use of ASME Code Case N-831-1 ML19175A0422019-09-11011 September 2019 Arkansas Units 1 and 2; Grand Gulf, Unit 1; Indian Point 2 and 3; Palisades; River Bend, Unit 1; Waterford Unit 3 - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules ML19184A5542019-07-15015 July 2019 Request for Relief ANO1-ISI-032 from the ASME Code Section XI Visual Examination Requirements for the Fourth 10-Year Inservice Inspection Interval ML19156A4002019-06-11011 June 2019 Request for Alternative ANO2-ISI-021 to Permit Continued Application of the 2007 Edition Through the 2008 Addenda of ASME Code ML19098A9552019-05-22022 May 2019 Issuance of Amendment No. 264 Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-425, Revision 3 ML19063B9482019-04-23023 April 2019 Issuance of Amendment No. 315 Adoption of Technical Specification Task Force Traveler TSTF-425, Revision 3 ML18337A2472019-01-17017 January 2019 Issuance of Amendment Nos. 263 and 314 Revision to Emergency Action Level Scheme ML18346A3142019-01-0707 January 2019 Relief Nos. ANO1-ISI-027, -028, -029, -030, and -031 from ASME Code, Section XI, Examination Requirements for Fourth 10-Year Inservice Inspection Interval (EPID L-2018-LLR-0063, -0064, -0065, -0066, -0067) ML18317A3822018-12-19019 December 2018 Issuance of Amendment No. 313, Revise Technical Specification 3.3.3.6, Post-Accident Instrumentation ML18298A0122018-11-27027 November 2018 Issuance of Amendment No. 311 Updating the Reactor Coolant System Pressure Temperature Limits ML18260A3392018-10-24024 October 2018 Issuance of Amendment No. 261 Revision to Technical Specification Bases Related to Emergency Feedwater Turbine-Driven Pump Steam Supply Valves ML18192A1042018-08-15015 August 2018 Alternative to Examination of Reactor Pressure Vessel Flange Threads ML18173A0192018-06-27027 June 2018 Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule (CAC MG0244; EPID L-2017-LLL-0020) ML18115A2822018-06-19019 June 2018 Issuance of Amendment No. 260 Technical Specification Changes Pursuant to Technical Specifications Task Force (TSTF) Traveler TSTF-412 Revision 3 (CAC No. MG0009; EPID L-2017-LLA-0267) ML18134A2532018-06-19019 June 2018 Issuance of Amendment No. 310 Technical Specification Changes to Provide Actions for Emergency Feedwater Pump Inoperability Consistent with NUREG-1432, Revision 4 (CAC No. MG0016; EPID L-2017-LLA-0268) ML18128A0672018-06-0808 June 2018 Arkansas, Units 1 and 2; Grand Gulf, Unit 1; Indian Point Unit Nos. 2 and 3; Palisades; Pilgrim; River Bend Station, Unit 1; and Waterford, Unit-3 Relief Request No. EN-17-RR-1, Alternative to Use ASME Code Case N-513-4 2024-01-24
[Table view] |
Text
July 2, 2007 Mr. Timothy G. Mitchell Vice President, Operations Arkansas Nuclear One Entergy Operations, Inc.
1448 S. R. 333 Russellville, AR 72802
SUBJECT:
ARKANSAS NUCLEAR ONE, UNIT NO. 2 - ISSUANCE OF AMENDMENT RE:
CONTAINMENT SPRAY NOZZLE TECHNICAL SPECIFICATIONS TEST REQUIREMENTS (TAC NO. MD4835)
Dear Mr. Mitchell:
The Commission has issued the enclosed Amendment No. 272 to Facility Operating License No. NPF-6 for Arkansas Nuclear One, Unit No. 2. The amendment consists of changes to the Technical Specifications in response to your application dated March 15, 2007.
The amendment revises the Surveillance Requirement (SR) 4.6.2.1.d to require verification that containment spray nozzles are unobstructed following maintenance that could result in nozzle blockage, in lieu of the current SR of performing the test every 5 years.
A copy of our related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
Sincerely,
/RA/
Alan B. Wang, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-368
Enclosures:
- 1. Amendment No. 272 to NPF-6
- 2. Safety Evaluation cc w/encls: See next page
Pkg ML071550002 (Amdt./License ML071550003, TS Pgs ML071550004)
OFFICE NRR/LPL4/PM NRR/LPL4/LA DSS/SCVB/BC OGC - NLO subj to comment NRR/LPL4/BC NAME AWang JBurkhardt RDennig JBonanno THiltz DATE 6/11/07 6/11/07 5/23/07 6/13/07 7/2/07 Arkansas Nuclear One cc:
Executive Vice President Section Chief, Division of Health
& Chief Operating Officer Emergency Management Section Entergy Operations, Inc. Arkansas Department of Health and P.O. Box 31995 Human Services Jackson, MS 39286-1995 4815 West Markham Street, Slot 30 Little Rock, AR 72205-3867 General Manager Plant Operations Senior Resident Inspector Entergy Operations, Inc. U.S. Nuclear Regulatory Commission Arkansas Nuclear One P.O. Box 310 1448 SR 333 London, AR 72847 Russellville, AR 72802 Regional Administrator, Region IV Director, Nuclear Safety Assurance U.S. Nuclear Regulatory Commission Entergy Operations, Inc. 611 Ryan Plaza Drive, Suite 400 Arkansas Nuclear One Arlington, TX 76011-8064 1448 SR 333 Russellville, AR 72802 County Judge of Pope County 100 W. Main Street Manager, Licensing Russellville, AR 72801 Entergy Operations, Inc.
Arkansas Nuclear One Vice President, Operations Support 1448 SR 333 Entergy Operations, Inc.
Russellville, AR 72802 P.O. Box 31995 Jackson, MS 39286-1995 Director, Nuclear Safety & Licensing Entergy Operations, Inc.
1340 Echelon Parkway Jackson, MS 39213-8298 Section Chief, Division of Health Radiation Control Section Arkansas Department of Health and Human Services 4815 West Markham Street, Slot 30 Little Rock, AR 72205-3867 February 2007
ENTERGY OPERATIONS, INC.
DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE, UNIT NO. 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 272 Renewed License No. NPF-6
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Entergy Operations, Inc. (the licensee), dated March 15, 2007, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-6 as indicated in the attachment to this license amendment.
- 3. The license amendment is effective as of its date of issuance and shall be implemented within 60 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Thomas G. Hiltz, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License No. NPF-6 and the Technical Specifications Date of Issuance: July 2, 2007
ATTACHMENT TO LICENSE AMENDMENT NO. 272 RENEWED FACILITY OPERATING LICENSE NO. NPF-6 DOCKET NO. 50-368 Replace the following pages of the Renewed Facility Operating License No. NPF-6 and Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Operating License REMOVE INSERT Technical Specifications REMOVE INSERT 3/4 6-11 3/4 6-11
3 facility at the designated location in Pope County, Arkansas in accordance with the procedures and limitations set forth in this renewed license; (3) EOI, pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time at the facility site and as designated solely for the facility, special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (4) EOI, pursuant to the Act and 10 CFR Parts 30, 40 and 70 to receive, possess and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5) EOI, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6) EOI, pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C. This renewed license shall be deemed to contain and is subject to conditions specified in the following Commission regulations in 10 CFR Chapter 1; Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level EOI is authorized to operate the facility at steady state reactor core power levels not in excess of 3026 megawatts thermal. Prior to attaining this power level EOI shall comply with the conditions in Paragraph 2.C.(3).
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 272 are hereby incorporated in the renewed l Renewed License No. NPF-6 Amendment No. 272
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 272 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-6 ENTERGY OPERATIONS, INC.
ARKANSAS NUCLEAR ONE, UNIT NO. 2 DOCKET NO. 50-368
1.0 INTRODUCTION
By application dated March 15, 2007 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML070780351), Entergy Operations, Inc. (the licensee),
requested changes to the Technical Specifications (TSs) for Arkansas Nuclear One, Unit No. 2 (ANO-2).
The proposed changes would revise Surveillance Requirement (SR) 4.6.2.1.d to require verification that containment spray nozzles are unobstructed following maintenance that could result in nozzle blockage in lieu of the current SR of performing the test every 5 years.
Specifically, the proposed change would change SR 4.6.2.1.d from At least once per five years by performing an air or smoke flow test through each spray header and verifying each nozzle is unobstructed to verify each spray nozzle is unobstructed following maintenance which could result in nozzle blockage. This SR is required by TS 3/4.6.2, Depressurization, Cooling, and pH Control Systems Containment Spray System.
2.0 REGULATORY EVALUATION
Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix A contains General Design Criteria (GDC) for nuclear power reactors. In particular, GDC 40 requires that the containment heat-removal system be designed to permit periodic testing. The containment spray system is a containment heat-removal system. The Combustion Engineering Standard Technical Specifications, NUREG-1432, Volume 1, Revision 2, dated March 2003, specifies in SR 3.6.6.A.9 a testing frequency of 10 years for the nozzle blockage test. While this is not a requirement, it had been the U.S. Nuclear Regulatory Commissions (NRCs) and industrys judgment of an acceptable frequency for this test. The current TSs require ANO-2 to test the containment spray nozzles every 5 years.
3.0 TECHNICAL EVALUATION
The Containment Spray System (CSS) is an Engineered Safety Feature used in response to a postulated Loss-of-Coolant Accident (LOCA). The CSS is designed to:
- Maintain reactor containment building pressure within design limits,
- Reduce the quantity of airborne iodine, and
These functions are performed by subcooled water solution sprayed into the containment atmosphere through nozzles from the spray headers located in the containment dome.
The licensee requested a change to revise TS SR 4.6.2.1.d, from requiring at least once per five years by performing an air or smoke flow test through each spray header and verifying each spray nozzle is unobstructed to requiring verification each CSS spray nozzle is free from obstruction following maintenance that could result in nozzle blockage (loss-of-foreign-material exclusion (FME) control).
The CSS sprays have been tested every 5 years since original plant construction and these tests have confirmed that the nozzles are free of obstructions that could have occurred following startup, operation, and maintenance of the system. The licensee stated that the containment spray nozzles are Sprayco model 1713A nozzles which have a swirl chamber design and have no moving parts in the nozzle to plug. The licensee also stated that the spray ring header is maintained dry and that the piping, ring headers, and nozzles are constructed of type 304 stainless steel. Therefore, the formation of corrosion products or loose parts that could cause nozzle plugging is unlikely.
The licensee maintains an FME program which is implemented by Procedure EN-MA-118, Foreign Material Exclusion. The procedure describes measures to be taken to ensure foreign material is not introduced into a system or component and describes measures to be taken if material or tool accountability is lost. This procedure applies to all station activities having the potential to introduce foreign material into systems or components which could impact plant safety. The requirements of the procedure apply when maintenance, modifications, repairs, inspections and operating activities are being conducted on open piping and equipment. The procedure establishes various levels for preventing the generation of debris when breaching a system and the removal of debris from the system if materials have entered a system. Pre-job briefs for FME are conducted prior to opening systems where foreign materials can be introduced. This procedure also requires personnel who are working on open components/systems receive FME training as part of their job qualifications. The procedure requires that when closing a system or component, an inspection be performed to ensure that all foreign material is removed. If FME is not maintained, a Condition Report is initiated requiring an assessment of the circumstances and implementation of the corrective actions to prevent reoccurrence.
Due to its location at the top of the containment, introduction of foreign material into the spray header via the open nozzles is unlikely. Foreign material introduced as a result of maintenance
is the most likely cause for obstruction; therefore, verification that no foreign material has entered the system following such maintenance is sufficient to confirm that the nozzles are free from blockage. Therefore, the potential for unidentified nozzle obstruction is very low.
The NRC staff reviewed the NRC Inspection Reports for Arkansas Nuclear One, Unit 1, and ANO-2 for the years 2000 through 2006. There were no significant findings identified in those reports that would indicate lapses in the FME program. Based on a review of these reports, the FME program appears to be effective.
The NRC staff previously approved, on a plant-specific basis, similar revisions to this requirement. The revisions require verification that each spray nozzle is unobstructed only following maintenance that could potentially result in nozzle blockage. This is based on the judgment that once the CSS nozzles are determined to be unobstructed, the only mechanisms that can cause nozzle blockage is foreign material introduced following maintenance and corrosion deposits. The first concern is addressed by the licensees FME program. The second concern is addressed by the piping system being constructed out of corrosion-resistant materials.
NUREG-1366, Improvements to Technical Specifications Surveillance Requirements, (May 1992) reported on an NRC staff review of industry experience which indicated that CSS' of similar design are highly reliable and are not subject to plugging after testing following construction. The NRC staff reviewed industry experience and found that, in general, once tested after construction, CSS have not been subject to blockage. There have been several exceptions. In the case of one pressurized-water reactor (PWR), a chemical added to the inner surface of a spray system pipe to eliminate corrosion detached and the loose material blocked some spray nozzles. The piping at ANO-2 is corrosion resistant; therefore, this failure mechanism is unlikely. The licensee for another PWR found debris, identified as construction debris, in the spray nozzle headers (Licensee Event Report 315/98-027). The fraction of blockage was not significant and the sprays remained functional. The debris was found by visual observation, not by an air flow test. The licensee states that the containment spray nozzles have been tested five times in addition to pre-operational tests. Pre-operational testing identified eight nozzles that had blocked flow. After removal of the blockage, air flow was verified through all containment spray nozzles. Subsequent in-place air flow tests have demonstrated unobstructed flow through each nozzle. Tests have confirmed that the system was free from construction debris and that no debris that could cause obstructions had entered the systems following startup and operation of ANO-2.
Based on the NRC staffs review and assessment of the applicable information provided by the licensee in its amendment request, the NRC staff concludes that the design of the ANO-2 CSS, the past history of these spray systems, and the licensees FME controls provide reasonable assurance that the potential for nozzle obstruction is acceptably low. The FME controls provide reasonable protection from the introduction of foreign materials into open piping during maintenance or testing and require post-maintenance verification of system cleanliness and freedom from foreign materials. In addition, the NRC staff review of industry-wide experience has indicated that the licensees proposed change is acceptable. Therefore, the NRC staff finds the amendment request acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Arkansas State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding published on April 24, 2007 (72 FR 20381). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b),
no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: B. Heida Date: July 2, 2007