ML062900458
| ML062900458 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 10/16/2006 |
| From: | Stephen Monarque NRC/NRR/ADRO/DORL/LPLII-1 |
| To: | Christian D Virginia Electric & Power Co (VEPCO) |
| Monarque, S R, NRR/DORL, 415-1544 | |
| Shared Package | |
| ML062900454 | List: |
| References | |
| TAC MD1838, TAC MD1839 | |
| Download: ML062900458 (12) | |
Text
October 16, 2006 Mr. David A. Christian Senior Vice President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
NORTH ANNA POWER STATION, UNIT NOS. 1 AND 2, ISSUANCE OF AMENDMENTS REGARDING THE CONSOLIDATED LINE ITEM IMPROVEMENT PROCESS FOR THE STEAM GENERATOR TUBE INTEGRITY (TAC NOS. MD1838 AND MD1839)
Dear Mr. Christian:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment Nos. 248 and 228 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 May 22, 2006.
These amendments revise the existing steam generator tube surveillance program to be consistent with the U.S. Nuclear Regulatory Commissions approved Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-449, Steam Generator Tube Integrity, Revision 4. TSTF-449 is part of the consolidated line item improvement process (CLIIP).
A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely,
/RA/
Stephen Monarque, Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-338 and 50-339
Enclosures:
- 1. Amendment No. 248 to NPF-4
- 2. Amendment No. 228 to NPF-7
- 3. Safety Evaluation cc w/encls: See next page
October 16, 2006 Mr. David A. Christian Senior Vice President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
NORTH ANNA POWER STATION, UNIT NOS. 1 AND 2, ISSUANCE OF AMENDMENTS REGARDING THE CONSOLIDATED LINE ITEM IMPROVEMENT PROCESS FOR THE STEAM GENERATOR TUBE INTEGRITY (TAC NOS. MD1838 AND MD1839)
Dear Mr. Christian:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment Nos. 248 and 228 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 May 22, 2006.
These amendments revise the existing steam generator tube surveillance program to be consistent with the U.S. Nuclear Regulatory Commissions approved Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-449, Steam Generator Tube Integrity, Revision 4. TSTF-449 is part of the consolidated line item improvement process (CLIIP).
A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely,
/RA/
Stephen Monarque, Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-338 and 50-339
Enclosures:
- 1. Amendment No. 248 to NPF-4
- 2. Amendment No. 228 to NPF-7
- 3. Safety Evaluation cc w/encls: See next page DISTRIBUTION: Public RidsOgcRp RidsNrrDorl Dpr LPL2-1 R/F RidsAcrsAcnwMailCenter RidsNrrDciCsgb(TBloomer)
RidsNrrDorlLpl2-1(EMarinos)
GHill(4 hard copies)
RidsNrrDorl(EThomas)
RidsNrrPMSMonarque(hard copy)
RidsNrrDirsLtsb(TKobetz)
RidsNrrLAMOBrien(hard copy)
RidsRgn2MailCenter(KLandis)
Package No. ML062900454 Tech Spec No. ML062900458 Amendment No. ML063000028 *date of memo transmitting safety evaluation OFFICE NRR/LPL2-1/PM NRR/LPD2-1/LA NRR/ITSB/BC NRR/CSGB/BC OGC NRR/LPL2-1/BC NAME SMonarque MOBrien TJKobetz*
TBloomer*
MBarkman EMarinos DATE 9/28/06 9/28/06 06/26/2006 06/26/2006 10/10/06 10/12/06 OFFICIAL RECORD COPY
VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-338 NORTH ANNA POWER STATION, UNIT NO. 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 248 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 al., (the licensee) dated May 22, 2006, 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.
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. 248, 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 within 180 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Evangelos C. Marinos, Chief Plant Licensing Branch II-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: October 16, 2006
VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-339 NORTH ANNA POWER STATION, UNIT NO. 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 228 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 al., (the licensee) dated May 22, 2006, 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.
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. 228, 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 within 180 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Evangelos C. Marinos, Chief Plant Licensing Branch II-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: October 16, 2006
ATTACHMENT TO LICENSE AMENDMENT NO. 248 RENEWED FACILITY OPERATING LICENSE NO. NPF-4 DOCKET NO. 50-338 AND TO LICENSE AMENDMENT NO. 228 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 ii ii 1.1-3 1.1-3 1.1-4 1.1-4 3.4.13-1 3.4.13-1 3.4.13-2 3.4.13-2 3.4.20-1 3.4.20-1 3.4.20-2 3.4.20-2 5.5-5 5.5-5 5.5-6 5.5-6 5.5-7 5.5-7 5.5-8 5.5-8 5.5-9 5.5-9 5.5-10 5.5-10 5.5-11 5.5-11 5.5-12 5.5-13 5.5-14 5.5-15 5.6-4 5.6-4 5.6-5 TSs TSs Bii Bii B3.4.4-2 B3.4.4-2 B3.4.5-3 B3.4.5-3 B3.4.5-4 B3.4.6-3 B3.4.6-3 B3.4.7-3 B3.4.7-3 B3.4.13-2 B3.4.13-2 B3.4.13-3 B3.4.13-3 B3.4.13-4 B3.4.13-4 B3.4.13-5 B3.4.13-5 B3.4.13-6 B3.4.13-6 B3.4.13-7 B3.4.20-1 B3.4.20-1 B3.4.20-2 B3.4.20-2 B.3.4.20-3 B.3.4.20-3 B.3.4.20-4 B.3.4.20-4 B.3.4.20-5 B.3.4.20-6 B.3.4.20-6 B.3.4.20-7 B.3.4.20-7 B.3.4.20-8 B.3.4.20-8
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 248 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-4 AND AMENDMENT NO. 228 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 letter dated May 22, 2006 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML061430062), Virginia Electric and Power Company (the licensee) submitted a request for changes to the North Anna Power Station, Unit Nos. 1 and 2 (North Anna 1/2), Technical Specifications (TSs). The proposed amendments are modeled after TS Task Force (TSTF) Change TSTF-449, Revision 4, Steam Generator Tube Integrity, and the model safety evaluation (SE) prepared by the Nuclear Regulatory Commission (NRC) and published in the Federal Register on March 2, 2005 (70 FR 10298) under the consolidated line item improvement process (CLIIP). In this regard, the scope of the application includes changes to the definition of leakage, changes to the primary-to-secondary leakage requirements, changes to the steam generator (SG) tube surveillance program (SG tube integrity), changes to the SG reporting requirements, and associated changes to the TS Bases.
2.0 REGULATORY EVALUATION
The background, description, and applicability of the proposed changes associated with the SG tube integrity issue and the applicable regulatory requirements were included in the NRC staffs model SE published in the Federal Register on March 2, 2005 (70 FR 10298). The Notice of Availability of Model Application Concerning Technical Specification; Improvement To Modify Requirements Regarding Steam Generator Tube Integrity; Using the Consolidated Line Item Improvement Process was published in the Federal Register on May 6, 2005 (70 FR 24126), which made the model SE available for licensees to reference.
3.0 TECHNICAL EVALUATION
3.1 Overview In its May 22, 2006, application, the licensee proposed changes to the TSs that are modeled after TSTF-449. There were minor differences between TSTF-449 and the licensee's application. These included differences associated with the facility having a different licensing basis (than that discussed in TSTF-449) and differences in TS numbering since the licensee has a different TS numbering sequence (than that assumed in TSTF-449). With respect to the differences in the facility licensing basis, the differences did not invalidate the technical evaluation of TSTF-449; rather they resulted in the licensee having to slightly deviate from some of the modifications discussed in TSTF-449. For example, in the Bases Section on Reactor Coolant System Operational Leakage, the licensee currently has more details concerning its accident analyses than what is present in the standard TSs (which were modified in TSTF-449). As a result, several of the changes discussed in TSTF-449 were not applicable.
This level of detail was also used in the new Bases Section on SG Tube Integrity. Since these differences were either administrative in nature or consistent with the plant's licensing basis, the NRC staff determined they were acceptable. The remainder of the application was generally consistent with or more conservative than TSTF-449. As a result, the NRC staff determined that the model SE is applicable to this review and finds the proposed changes acceptable.
Consistent with TSTF-449, the proposed TS changes include: (1) a revised definition of LEAKAGE in TS 1.1, (2) a revised TS 3.4.13, "RCS (Reactor Coolant System) Operational LEAKAGE," (3) a new TS 3.4.20, "Steam Generator (SG) Tube Integrity," (4) a revised TS 5.5.8, "Steam Generator (SG) Program," (5) a revised TS 5.6.7, "Steam Generator Tube Inspection Report," and (6) a revised Table of Contents pages to reflect the proposed changes.
3.2 Conclusion The proposed TS changes establish a programmatic, largely performance-based regulatory framework for ensuring SG tube integrity is maintained. The NRC staff finds that it addresses key shortcomings of the current framework by ensuring that SG programs are focused on accomplishing the overall objective of maintaining tube integrity. It incorporates performance criteria for evaluating SG tube integrity that the NRC staff finds to be consistent with the structural margins and the degree of leak tightness assumed in the current plant licensing basis. The NRC staff finds that maintaining these performance criteria provides reasonable expectation that the SGs can be operated safely without increase in risk.
The revised TSs will contain limited specific details concerning how the SG Program is to achieve the required objective of maintaining tube integrity; the intent being that the licensee will have the flexibility to determine the specific strategy for meeting this objective. However, the NRC staff finds that the revised TSs include sufficient regulatory constraints on the establishment and implementation of the SG Program such as to provide reasonable assurance that tube integrity will be maintained.
Failure to meet the performance criteria will be reportable pursuant to the requirements in Title 10 of the Code of Federal Regulations (10 CFR) Part 50 Sections 50.72 and 50.73. The NRC reactor oversight process provides a process by which the NRC staff can verify that the licensee has identified any SG Program deficiencies that may have contributed to such an occurrence and that appropriate corrective actions have been implemented.
In conclusion, the NRC staff finds that the TS changes proposed by the licensee in its May 22, 2006, application conform to the requirements of 10 CFR 50.36 and establish a TS framework that will provide reasonable assurance such that SG tube integrity is maintained without undue risk to public health and safety.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Virginia State official was notified of the proposed issuance of the amendments. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change requirements with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and change surveillance requirements. The NRC staff has determined that the amendments involve 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 amendments involve no significant hazards consideration, and there has been no public comment on such finding (71 FR 43537). Accordingly, the amendments meet 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 amendments.
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 amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: E. Thomas Date: October 16, 2006
North Anna Power Station, Units 1 & 2 cc:
Mr. C. Lee Lintecum County Administrator Louisa County Post Office Box 160 Louisa, Virginia 23093 Ms. Lillian M. Cuoco, Esq.
Senior Counsel Dominion Resources Services, Inc.
Building 475, 5 th floor Rope Ferry Road Waterford, Connecticut 06385 Dr. W. T. Lough Virginia State Corporation Commission Division of Energy Regulation Post Office Box 1197 Richmond, Virginia 23218 Old Dominion Electric Cooperative 4201 Dominion Blvd.
Glen Allen, Virginia 23060 Mr. Chris L. Funderburk, Director Nuclear Licensing & Operations Support Dominion Resources Services, Inc.
Innsbrook Technical Center 5000 Dominion Blvd.
Glen Allen, Virginia 23060-6711 Office of the Attorney General Commonwealth of Virginia 900 East Main Street Richmond, Virginia 23219 Senior Resident Inspector North Anna Power Station U. S. Nuclear Regulatory Commission P. O. Box 490 Mineral, Virginia 23117 Mr. Jack M. Davis Site Vice President North Anna Power Station Virginia Electric and Power Company Post Office Box 402 Mineral, Virginia 23117-0402 Dr. Robert B. Stroube, MD, MPH State Health Commissioner Office of the Commissioner Virginia Department of Health Post Office Box 2448 Richmond, Virginia 23218