ML091900007
| ML091900007 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 07/29/2009 |
| From: | V Sreenivas Plant Licensing Branch II |
| To: | Heacock D Virginia Electric & Power Co (VEPCO) |
| Sreenivas V.NRR/DORL/LPL2-1 415-2597 | |
| References | |
| TAC ME0618, TAC ME0619, TSTF-511 | |
| Download: ML091900007 (13) | |
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July 29, 2(Uj
NORTH ANNA POWER STATION, UNIT NOS. 1 AND 2, -ISSUANCE OF AMENDMENT TO ELIMINATE WORKING HOUR RESTRICTIONS FROM TECHNICAL SPECIFICATIONS TO SUPPORT COMPLIANCE WITH 10 CFR PART 26, TSTF-511 (TAC NOS. ME0618 AND ME0619)
Dear Mr. Heacock:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment Nos. 256 and 237 to Renewed Facility Operating License Nos. NPF-4 and NPF-7 for the North Anna Power Station, Unit Nos. 1 and 2. The amendments change the Technical Specifications (TSs) in response to your application dated February 6, 2009.
The amendments delete those portions of the TSs superseded by Title 10 of the Code of Federal Regulations (10 CFR), Part 26, "Fitness for Duty Programs," Subpart I, "Managing Fatigue." The change is consistent with NRC-approved Technical Specification Task Force (TSTF) Improved Standard TS Change Traveler, TSTF-511, "Eliminate Working Hour Restrictions from TS 5.2-2 to Support Compliance with 10 CFR Part 26," Revision O.
A copy of the associated safety evaluation is enclosed. A Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely,
. Sreenivas, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-338 and 50-339
Enclosures:
- 1. Amendment No. 256 to NPF-4
- 2. Amendment No. 237 to NPF-7
- 3. Safety Evaluation cc w/encls: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-338 NORTH ANNA POWER STATION, UNIT NO.1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 256 Renewed License No. NPF-4
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company et aI., (the licensee) dated February 6,2009, 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 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
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-4 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 256, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented by October 1, 2009.
FOR THE NUCLEAR REGULATORY COMMISSION
~t~~v Undine Shoop, Acting Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to License No. NPF-4 and the Technical Specifications Date of Issuance: July 29, 2009
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-339 NORTH ANNA POWER STATION, UNIT NO.2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 237 Renewed License No. NPF-7
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company et aI., (the licensee) dated February 6,2009, 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 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
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-7 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 237, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented by October 1,2009.
FOR THE NUCLEAR REGULATORY COMMISSION U~{0c/C~
Undine Shoop, Acting Chief I
Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to License No. NPF-7 and the Technical Specifications Date of Issuance: July 29, 2009
ATTACHMENT TO LICENSE AMENDMENT NO. 256 RENEWED FACILITY OPERATING LICENSE NO. NPF-4 DOCKET NO. 50-338 AND TO LICENSE AMENDMENT NO. 237 RENEWED FACILITY OPERATING LICENSE NO. NPF-7 DOCKET NO. 50-339 Replace the following pages of the Licenses and the Appendix "A" Technical Specifications (TSs) with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Pages Insert Pages Licenses Licenses License No. NPF-4, page 3 License No. NPF-4, page 3 License No. NPF-7, page 3 License No. NPF-7, page 3 TSs TSs 5.2-2 5.2-2
-3 (2) Pursuant to the Act and 10 CFR Part 70, VEPCO to receive, possess, and use at any time special nuclear material as reactor fuel, In accordance with the limitations for storage and amounts required for reactor operation, as described in the Updated Final Safety Analysis Report; (3) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, VEPCO 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; (4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, VEPCO 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 component; and (5) Pursuant to the Act and 10 CFR Parts 30 and 70, VEPCO to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C. This renewed operating license shall be deemed to contain and is subject to the conditions specified In the following CommIssion regulations in 10 CFR Chapter I:
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; 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 VEPCO is authorized to operate the North Anna Power Station, Unit No.1, at reactor core power levels not in excess of 2893 megawatts (thermal).
(2) Technical Sgecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 256 are hereby incorporated in the renewed license. The licensee shall operate the facility In accordance with the Technical Specifications.
NORTH ANNA - UNIT 1 Renewed License No. NPF-4 ltrerrl:mt fu. 256
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(3) Pursuant to the Act and 10 CFR Parts 30, 40. and 70, VEPCO 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; (4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70. VEPCO 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 (5) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, VEPCO 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 the conditions specified in the Commission's regulations as set forth In 10 CFR Chapter I 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 VEPCO is authorized to operate the facility at steady state reactor core power levels not in excess of 2893 megawatts (thermal).
(2) TechnIcal Sgeclflcations The Technical Specifications contained In AppendiX A, as revised through Amendment No. 237 are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance wIth the Technical Specifications.
(3) Additional Conditions The matters specified in the following conditions shall be completed to the satisfaction of the Commission within the stated time periods following the Issuance of the condItion or within the operational restrictions indicated. The removal of these conditions shall be made by an amendment to the renewed license supported by a favorable evaluation by the Commission:
- a. If VEPCO plans to remove or to make significant changes in the normal operation of equipment that controls the amount of radioactivity in effluents from the North Anna Power Station, the NORTH ANNA ~ UNIT 2 Renewed License No. NPF~7 A:1Eluent ~b. 237
Organization 5.2 5.2 Organization 5.;~. 2 Unit Staff The unit staff organization shall include the follo~ing:
- a. An auxiliary operator shall be assigned to each reactor containing fuel and an additional auxiliary operator shall be assigned for each control room from which a reactor is operating in MODES 1, 2, 3, or 4.
Two unit sites with both units shutdown or defueled require a total of three auxiliary operators for the two units.
- b. Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(i) and 5.2.2.a and 5.2.2.f for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.
- c. A radiation protection technician shall be on site when fuel is in the reactor. The position may be vacant for not more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to provide for unexpected absence, provided immediate action is taken to fill the required position.
- d. Deleted North Anna Units 1 and 2 5.2-2 Itrenct!'1ent Nos.
256,,237
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 256 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-4 AND AMENDMENT NO. 237 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-7 VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION, UNIT NOS. 1 AND 2 DOCKET NOS. 50-338 AND 50-339
1.0 INTRODUCTION
By application dated February 6, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML090400465), Virginia Electric and Power Company (the licensee),
requested changes to the Technical Speci"flcations (TSs) for North Anna Power Station, Units 1 and 2 (NAPS Units 1 and 2).
The requested change is the adoption of Technical Specification Task Force (TSTF) Improved Standard Technical Specification Change Traveler, TSTF-511, Revision 0, "Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26." The proposed amendments would delete those portions of the TSs superseded by Title 10 of the Code of Federal Regulations (10 CFR) Part 26, Subpart I. The availability of the TS improvement was announced in the Federal Register on December 30, 2008 (73 FR 79923), as part of the Consolidated Line-Item Improvement Process (CLlIP).
2.0 REGULATORY EVALUATION
The history of U.S. Nuclear Regulatory Commission (NRC) regulations pertaining to prevention of worker impairment is summarized in the Federal Register notice containing the final rule that amended 10 CFR Part 26 (73 FR 16966, March 31, 2008). Part 26, Subpart I provides the regulatory requirements for managing worker fatigue at nuclear power plants.
The NRC's regulatory requirements related to the content of the TSs are contained in 10 CFR Part 50, Section 50.36. Section 50.36 requires that the TSs include items in the following categories: (1) safety limits, limiting safety systems settings, and limiting control settings; (2) limiting conditions for operation (LCOs); (3) Surveillance Requirements (SRs); (4) design features;
-2 and (5) administrative controls. The proposed change is within the fifth category. The administrative controls are the provisions relating to organization and management, procedures, recordkeeping, review and audit, and reporting necessary to assure operation of the facility in a safe manner.
The NRC's guidance for the format and content of licensee TSs can be found in NUREG-1430, Revision 3.0, "Standard Technical Specifications Babcock and Wilcox Plants," NUREG-1431, Revision 3.0, "Standard Technical Spedfications Westinghouse Plants," NUREG-1432, Revision 3.0, "Standard Technical Specifications Combustion Engineering Plants," NUREG-1433, Revision 3.0, "Standard Technical Specifications General Electric Plants, BWR/4," and NUREG-1434, Revision 3.0, "Standard Technical Specifications General Electric Plants, BWRl6," referred to as Standard Technical Specifications (STSs). Section 5 of the STSs contains administrative controls.
Paragraph d of Section 5.2.2 of STS contains requirements for administrative procedures to limit the working hours of personnel who perform safety-related functions. This paragraph represents NRC's guidance on how licensee TS requirements should address work hour controls.
Licensees adhere to the guidance to varying degrees due to minor administrative differences and differences in each licensee's current licensing basis. The inconsistent level of adherence to NRC guidance has lead to inconsistent TS interpretation and implementation. This has also made it difficult for the NRC to enforce the requirements.
The new requirements of 10 CFR Part 26, Subpart I supersede the guidance for requirements found in Paragraph d of Section 5.2.2 of all the STSs. Subpart I distinguishes between work hour controls and fatigue management and strengthens the requirements for both. Subpart I requires nuclear power plant licensees to ensure against worker fatigue adversely affecting public health and safety and the common defense and security by establishing clear and enforceable requirements for the management of worker fatigue. Licensees are required to implement Subpart I by October 1, 2009, as announced in the Final Rule that revised 10 CFR Part 26 (73 FR 16966, March 31,2008). TSTF-511 proposed a change to the STS that would delete paragraph d of STSs 5.2.2. This change was published in the Federal Register on December 30, 2008 (73 FR 79923).
2.1 Adoption of TSTF-511! Revision 0 Proper adoption of TSTF-511 and implementation of 10 CFR Part 26, Subpart I by NAPS Units 1 and 2 will provide a reasonable assurance that the licensee will maintain limits on the working hours of personnel who perform safety-related functions. NAPS Units 1 and 2 has committed to remove the plant-specific TS requirements concurrently with the implementation of the 10 CFR Part 26, Subpart I requirements.
3.0 TECHNICAL EVALUATION
Controls on work hours for personnel at nuclear power plants are necessary to prevent worker fatigue from adversely affecting public health and safety and the common defense and security.
Work hour controls for NAPS Units 1 and 2 are currently located in paragraph d of TS 5.2.2. When implemented, the regulatory requirements of 10 CFR 26, Subpart I will replace the plant-specific TS requirements found in paragraph d of the NAPS Units 1 and 2 TSs.
- 3 The licensee proposed deleting paragraph d of TS 5.2.2. The licensee committed to implement the new requirements of 10 CFR Part 26, Subpart I concurrently with the deletion of the TS requirements on work hour controls. This regulatory commitment will be completed by the licensee no later than October 1, 2009. The NRC staff finds that reasonable controls for the implementation and subsequent evaluation of proposed changes pertaining to the above regulatory commitments are best provided by the licensee's administrative processes, including its commitment management program (Regulatory Issue Summary 2000-017, "Managing Regulatory Commitments Made by Power Reactor Licensees to the NRC Staff'). The above regulatory commitments do not warrant the creation of regulatory requirements (items requiring prior NRC approval of subsequent changes).
The NRC staff evaluated the licensee's proposed change against the applicable regulatory requirements listed in Section 2. The NRC staff also compared the proposed change to the change made to the STSs by TSTF-511. The NRC staff considered the licensee's commitment to implement 10 CFR Part 26, Subpart I concurrently with the deletion of TS work hour control requirements in its evaluation of the proposed change. Given the licensee's commitment, there is reasonable assurance that the licensee will comply with the regulations for work hour controls, either through TS requirements or through the requirements of 10 CFR Part 26, Subpart I, at all times. Therefore, the licensee will continue to prevent worker fatigue from adversely affecting public health and safety and the common defense and security. Therefore, the staff finds the proposed changes acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Virginia State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments relate to changes in recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
6.0 CONCLUSION
The Commission has concluded, on the basis of 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 amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors: V Cusumano NRRlDIRS M Hamm, NRRlDIRS Date: July 29, 2009
ML091900007 ransml'ttedb d t d OFFICE NRRlLPL2-1/PM NRRlLPL2-1/PM NRRlLPL2-1/LA NRRlITSB/BC OGC 1NLO NRRlLPL2-1/(A)BC NAME VSreenivas:prb JStang (VSreenivas for)
MO'Brien RElliott*
JSuttenberg UShoop DATE 7/8/09 7/27/09 7/27/09 03/24/09 7127109 7/28/09