ML071380264
| ML071380264 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 05/31/2007 |
| From: | John Hughey NRC/NRR/ADRO/DORL/LPLI-2 |
| To: | Christian D Dominion Nuclear Connecticut |
| Miller G, NRR/DORL, 415-2481 | |
| Shared Package | |
| ML071380257 | List: |
| References | |
| TAC MD2570, TAC MD2571 | |
| Download: ML071380264 (14) | |
Text
May 31, 2007Mr. David A. ChristianSr. Vice President and Chief Nuclear Officer Dominion Nuclear Connecticut, Inc.
Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
MILLSTONE POWER STATION, UNIT NOS. 2 AND 3 - ISSUANCE OFAMENDMENTS REGARDING STEAM GENERATOR TUBE INTEGRITY (TAC NOS. MD2570 AND MD2571)
Dear Mr. Christian:
The Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 299 toFacility Operating License No. DPR-65 for the Millstone Power Station, Unit No. 2, and the enclosed Amendment No. 238 to Facility Operating License No. NPF-49 for the Millstone Power Station, Unit No. 3 in response to your application dated May 31, 2006, as supplemented by letters dated February 14, 2007, and April 26, 2007. The amendments revises the existing Steam Generator tube surveillance program consistent with the NRC-approved Technical Specification Task Force (TSTF) Standard TS Change Traveler, TSTF-449, "Steam Generator Tube Integrity," Revision 4. TSTF-449 is part of the consolidated line item improvement process. A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be includedin the Commission's biweekly Federal Register notice.Sincerely, /ra/John Hughey, Project ManagerPlant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-336 50-423
Enclosures:
- 1. Amendment No. 299 to DPR-65
- 2. Amendment No. 238 to NPF-49
- 3. Safety Evaluationcc w/encls: See next page May 31, 2007Mr. David A. ChristianSr. Vice President and Chief Nuclear Officer Dominion Nuclear Connecticut, Inc.
Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
MILLSTONE POWER STATION, UNIT NOS. 2 AND 3 - ISSUANCE OFAMENDMENTS REGARDING STEAM GENERATOR TUBE INTEGRITY (TAC NOS. MD2570 AND MD2571)
Dear Mr. Christian:
The Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 299 toFacility Operating License No. DPR-65 for the Millstone Power Station, Unit No. 2, and the enclosed Amendment No. 238 to Facility Operating License No. NPF-49 for the Millstone Power Station, Unit No. 3 in response to your application dated May 31, 2006, as supplemented by letters dated February 14, 2007, and April 26, 2007. The amendments revises the existing Steam Generator tube surveillance program consistent with the NRC-approved Technical Specification Task Force (TSTF) Standard TS Change Traveler, TSTF-449, "Steam Generator Tube Integrity," Revision 4. TSTF-449 is part of the consolidated line item improvement process. A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be includedin the Commission's biweekly Federal Register notice.Sincerely, /ra/John Hughey, Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-336 50-423
Enclosures:
- 1. Amendment No. 299 to DPR-65
- 2. Amendment No. 238 to NPF-49
- 3. Safety Evaluationcc w/encls: See next page DISTRIBUTION
- PublicRidsNrrDciCsgbRidsNrrDorlLpl1-2 RidsOgcRpRidsAcrsAcnwMailCenterRidsRgn1MailCenter LPL1-2 R/FGHill (4)RidsNrrPMJHughey RidsNrrLACSolaRidsNrrDirsItsbRidsNrrPMEMillerADAMS Accession Numbers: Tech Specs:ML071560531Package: ML071380257 Amendment: ML071380264 Tech Specs:ML071560555OFFICELPL1-2/PMLPL1-2/PMLPL1-2/LADCI/CSGB/BCDIRS/ITSB/BCOGCLPL1-2/BCNAMEGEMiller(JDH for)JHugheyRSolaAHiser (Bymemo dated)TKobetz (Bymemo dated)(Not Requiredfor CLIIP on HChernoffDATE5/31/075/31/075/22/0705/09/0705/14/07TSTF-449.)5/31/07OFFICIAL RECORD COPY DOMINION NUCLEAR CONNECTICUT, INC.DOCKET NO. 50-336MILLSTONE POWER STATION, UNIT NO. 2AMENDMENT TO FACILITY OPERATING LICENSEAmendment No. 299License No. DPR-651. The Nuclear Regulatory Commission (the Commission) has found that:A.The application for amendment by Dominion Nuclear Connecticut, Inc. (thelicensee) dated May 31, 2006, as supplemented by letters dated February 14, 2007, and April 26, 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 Title 10 of the Code of FederalRegulations (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 amendment will not be inimical to the common defense andsecurity 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 asindicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-65 is hereby amended to read as follows:(2)Technical SpecificationsThe Technical Specifications contained in Appendix A, as revised throughAmendment No. , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications. 3.This license amendment is effective as of the date of issuance, and shall beimplemented within 180 days of issuance. FOR THE NUCLEAR REGULATORY COMMISSION/ra/Harold K. Chernoff, ChiefPlant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to License No. DPR-65 and the Technical SpecificationsDate of Issuance: May 31, 2007 ATTACHMENT TO LICENSE AMENDMENT NO. 299FACILITY OPERATING LICENSE NO. DPR-65DOCKET NO. 50-336Replace page 3 of License No. DPR-65 with the attached revised page 3.Replace the following pages of the Appendix A, Technical Specifications, with the attachedrevised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change. RemoveInsertINDEX - IINDEX - IINDEX - VIINDEX - VI INDEX - XIIINDEX - XII INDEX - XVIIINDEX - XVII INDEX - XVIIIINDEX - XVIII 1-31-3 3/4 4-53/4 4-5 3/4 4-63/4 4-6 3/4 4-7----------
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6-31 DOMINION NUCLEAR CONNECTICUT, INC.DOCKET NO. 50-423MILLSTONE POWER STATION, UNIT NO. 3AMENDMENT TO FACILITY OPERATING LICENSEAmendment No. 238License No. NPF-491. The Nuclear Regulatory Commission (the Commission) has found that:A.The application for amendment by Dominion Nuclear Connecticut, Inc. (thelicensee) dated May 31, 2006, as supplemented by letters dated February 14, 2007, and April 26, 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 Title 10 of the Code of FederalRegulations (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 amendment will not be inimical to the common defense andsecurity 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 asindicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-49 is hereby amended to read as follows:(2)Technical SpecificationsThe Technical Specifications contained in Appendix A, as revised throughAmendment No. , and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated in the license. Dominion Nuclear Connecticut, Inc. shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. 3.This license amendment is effective as of the date of issuance, and shall beimplemented within 180 days of issuance. FOR THE NUCLEAR REGULATORY COMMISSION/ra/Harold K. Chernoff, ChiefPlant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to License No. NPF-49 and the Technical SpecificationsDate of Issuance: May 31, 2007 ATTACHMENT TO LICENSE AMENDMENT NO. 238FACILITY OPERATING LICENSE NO. NPF-49DOCKET NO. 50-423Replace page 4 of License No. NPF-49 with the attached revised page 4.Replace the following pages of the Appendix A Technical Specifications, with the attachedrevised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change. RemoveInsertINDEX - iINDEX - iINDEX - iiINDEX - ii INDEX - viiINDEX - vii INDEX - xixINDEX - xix 1-21-2 1-31-3 1-41-4 1-51-5 1-61-6 3/4 4-143/4 4-14 3/4 4-153/4 4-15 3/4 4-163/4 4-16 3/4 4-173/4 4-17 3/4 4-183/4 4-18 3/4 4-193/4 4-19 3/4 4-203/4 4-20 3/4 4-223/4 4-22 3/4 4-233/4 4-23
4-23a 6-17a6-17a
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6-17c 6-216-21
6-21a 6-226-22 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONRELATED TO AMENDMENT NOS. 299 AND 238TO FACILITY OPERATING LICENSE NOS. DPR-65 AND NPF-49DOMINION NUCLEAR CONNECTICUT, INC.MILLSTONE POWER STATION, UNIT NOS. 2 AND 3DOCKET NOS. 50-336 AND 50-42
31.0 INTRODUCTION
By letter dated May 31, 2006, as supplemented by letters dated February 14, 2007, andApril 26, 2007, Dominion Nuclear Connecticut, Inc. (DNC or licensee) submitted a request for changes to the Millstone Power Station, Unit Nos. 2 and 3 (MPS2 and MPS3) Technical Specifications (TSs) to the Nuclear Regulatory Commission (NRC or the Commission). The proposed amendments would revise the existing Steam Generator tube surveillance program consistent with the NRC-approved TS Task Force (TSTF) Standard TS Change Traveler, TSTF-449, "Steam Generator Tube Integrity," Revision 4. TSTF-449 is part of the consolidated line item improvement process. The supplements dated February 14, 2007, and April 26, 2007, provided additional informationthat clarified the application, did not expand the scope of the application as originally noticed, and did not change the staff's original proposed no significant hazards determination as published in the Federal Register on December 19, 2006 (71 FR 75992).
2.0REGULATORY EVALUATION
The background, description, and applicability of the proposed changes associated with the SGtube integrity issue and the applicable regulatory requirements were included in the NRC staff's model safety evaluation (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 Registeron May 6, 2005 (70 FR 24126), and made the model SE available for licensees to reference.
3.0 TECHNICAL EVALUATION
3.1Overview In its May 31, 2006 application, and February 14, 2007 and April 26, 2007 supplements, thelicensee proposed changes to the TSs that are modeled after TS Task Force (TSTF) Standard TS Change Traveler, TSTF-449, "Steam Generator Tube Integrity." There were minor differences between TSTF-449 and the licensee's application. These included differences in the facility licensing basis (than that discussed in TSTF-449) and differences in TS format and numbering. These differences are discussed below.With respect to the differences in the facility licensing basis, the differences did not invalidatethe technical evaluation on TSTF-449; rather they resulted in the licensee having to slightly deviate from some of the modifications discussed in TSTF-449, or they resulted in slight differences in the requirements. For example, the temperatures corresponding to the reactor operating modes (e.g., Hot Standby, Hot Shutdown) in the standard TSs (and in TSTF-449) differ from the temperatures corresponding to these modes at MPS2. These different temperatures were previously approved by the NRC staff and have no effect on the adequacy of the SG program; however, they do affect the temperatures at which the SG is operated.Other examples of differences are contained in the Bases section. In the SG Tube IntegrityBases section, the licensee indicates that the analysis of a SG tube rupture event assumes that the primary-to-secondary leak rate includes a leak rate equal to two times the operational leak rate limit in the TSs (rather than equal to the limit in the TSs as indicated in TSTF-449), plus the leakage rate associated with a double-ended rupture of a single tube. The text proposed to be included in the Bases to describe the SG tube rupture event is consistent with the licensee's current licensing basis. Another example is that the licensee indicated that the dose consequences are within the limits of Title 10 of the Code of Federal Regulatons (10 CFR)50.67 (rather than Part 100 as indicated in TSTF-449), since their current licensing basis is based on 10 CFR 50.67. Another example is that the licensee indicated in their Bases that the accident analyses for a SG tube rupture assumes the contaminated secondary fluid is released to the atmosphere via safety valves or atmospheric dump valves (rather than only being briefly released to the atmosphere via safety valves with the majority being discharged to the main condenser as indicated in TSTF-449). Since the licensee's accident analysis differs from that assumed in TSTF-449, they did not incorporate the text from TSTF-449, rather, they incorporated a sentence that reflects their accident analysis. Since these differences were minor in nature, they were consistent with the plant's licensing basis, or they were consistent with the intent of TSTF-449, the NRC staff determined they were acceptable.With respect to the differences in numbering of the TSs, these differences were administrativein nature and did not affect the technical adequacy of the submittal. As a result, the NRC staff determined they were acceptable. With respect to the differences in the format of the TSs, these differences resulted in listing the requirements in sentence format rather than tabular format and using slightly different terminology. Since these differences were administrative in nature and did not affect the technical adequacy of the submittal, the NRC staff determined they were acceptable. 3.2Changes Specific to MPS2In addition to the above, and specific to MPS2, the licensee proposed some changes that wentbeyond TSTF-449. For example, the licensee proposed changes to the requirements pertaining to reactor coolant system operational leakage to facilitate the adoption of TSTF-449 (e.g., consolidating the various definitions of leakage in TS 1.14, modifying the action statements in TS 3.4.6.2, and modifying surveillance requirements in TS 4.4.6.2.2). Since these proposed TS changes, including the changes to the Bases, were generally consistent with the standard TSs as modified to reflect the plant's licensing basis, the NRC staff determined that the proposed changes were acceptable. Another example is that the licensee proposed, in part, to limit accident induced leakage to 150 gallons per day per SG. Since this proposal was more restrictive than that required by TSTF-449 (which limited accident induced leakage, in part, to 1 gallon per minute (1440 gallons per day) per SG), the staff found it acceptable. In addition, the licensee proposed to increase their normal operating primary-to-secondary leakage limit from 0.035 gallons per minute (50 gallons per day) to 75 gallons per day. Since this limit is less than that discussed in TSTF-449 and is less than (or equal to) the value assumed in the licensee's accident analyses, the NRC staff finds this proposed increase acceptable. 3.3Changes Specific to MPS3 In addition to section 3.1, and specific to MPS3, the licensee proposed some changes that wentbeyond TSTF-449. For example, the licensee proposed changes to the requirements pertaining to reactor coolant system operational leakage to facilitate the adoption of TSTF-449 (e.g., consolidating the various definitions of leakage in TS 1.16, modifying action statements in TS 3.4.6.2, and modifying surveillance requirements in TS 4.4.6.2.1 and 4.4.6.2.2). Since these proposed TS changes, including the changes to the Bases, were generally consistent with the standard TSs as modified to reflect the plant's licensing basis, the NRC staff determined that the proposed changes were acceptable. Another example is that the licensee proposed, in part, to limit accident induced leakage to 500 gallons per day per SG. Since this proposal was more restrictive than that required by TSTF-449 (which limited accident induced leakage, in part, to 1 gallon per minute (1440 gallons per day) per SG), the NRC staff found it acceptable.The remainder of the application was consistent with, or more limiting than, TSTF-449.
In summary, the NRC staff determined that the model SE is applicable to this review and findsthe proposed changes acceptable.Consistent with TSTF-449, the proposed TS changes include: (1) a revised definition ofLEAKAGE, (2) a revised TS 3.4.6.2, "Reactor Coolant System Operational Leakage," (3) a new TS 6.26, "Steam Generator (SG) Program," (4) a revised TS 3.4.5, "Steam Generator Tube Integrity," (5) a new TS 6.9.1.9, "Steam Generator Tube Inspection Report," and (6) revised Table of Content pages to reflect the proposed changes. 3.4SummaryThe proposed TS changes establish a programmatic, largely performance-based regulatoryframework 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 tube integrity that the NRC staff finds 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 assurance 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 toachieve 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 in10 CFR Parts 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 itsMay 31, 2006 application, and February 14, 2007 and April 26, 2007 supplements conform to the requirements of 10 CFR 50.36 and establish a TS framework that will provide reasonable assurance that SG tube integrity is maintained without undue risk to public health and safety.The licensee included in its application the revised TS Bases to be implemented with the TSchange. The NRC staff finds that the TS Bases Control Program is the appropriate process for updating the affected TS Bases pages and has, therefore, not included the affected Bases pages with this amendment.
4.0STATE CONSULTATION
In accordance with the Commission's regulations, the Connecticut State official was notified ofthe proposed issuance of the amendment. The Connecticut State official provided no
comments.
5.0ENVIRONMENTAL CONSIDERATION
This 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 effluent 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(71 FR 75992). 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 NRC staff concludes that: (1) there is reasonable assurance that the health and safety ofthe public will not be endangered by operation in the proposed manner, (2) such activity 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 health and safety of the
public.Principal Contributors: J. McGuireL. Brown D. Nold D. Muller G. MakarDate: May 31, 2007 Millstone Power Station, Unit Nos. 2 and 3 cc:
Lillian M. Cuoco, EsquireSenior Counsel Dominion Resources Services, Inc.
Building 475, 5 th Floor Rope Ferry Road Waterford, CT 06385Edward L. Wilds, Jr., Ph.D.Director, Division of Radiation Department of Environmental Protection 79 Elm Street Hartford, CT 06106-5127Regional Administrator, Region IU.S. Nuclear Regulatory Commission
475 Allendale Road King of Prussia, PA 19406First SelectmenTown of Waterford 15 Rope Ferry Road Waterford, CT 06385Charles Brinkman, DirectorWashington Operations Nuclear Services Westinghouse Electric Company 12300 Twinbrook Pkwy, Suite 330 Rockville, MD 20852Senior Resident InspectorMillstone Power Station c/o U.S. Nuclear Regulatory Commission P. O. Box 513 Niantic, CT 06357Mr. J. W. "Bill" Sheehan Co-Chair NEAC 19 Laurel Crest Drive Waterford, CT 06385Ms. Nancy Burton147 Cross Highway Redding Ridge, CT 00870Mr. Evan W. WoollacottCo-Chair Nuclear Energy Advisory Council 128 Terry's Plain Road Simsbury, CT 06070Mr. Joseph RoyDirector of Operations Massachusetts Municipal Wholesale Electric Company P.O. Box 426 Ludlow, MA 01056Mr. David W. DodsonLicensing Supervisor Dominion Nuclear Connecticut, Inc.
Building 475, 5 th FloorRoper Ferry Road Waterford, CT 06385Mr. J. Alan Price Site Vice President Dominion Nuclear Connecticut, Inc.
Building 475, 5 th FloorRope Ferry Road Waterford, CT 06385 Mr. Chris L. FunderburkDirector, Nuclear Licensing and Operations Support Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711