ML081960312
| ML081960312 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 07/31/2008 |
| From: | Sanders C NRC/NRR/ADRO/DORL/LPLI-2 |
| To: | Christian D Virginia Electric & Power Co (VEPCO) |
| Sanders, Carleen, NRR/DORL 415-1603 | |
| Shared Package | |
| ml081960318 | List: |
| References | |
| TAC MD6113, TAC MD6114 | |
| Download: ML081960312 (14) | |
Text
July 31, 2008 Mr. David A. Christian President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
MILLSTONE POWER STATION, UNIT NOS. 2 AND 3 - ISSUANCE OF AMENDMENT RE: TECHNCIAL SPECIFICATION CHANGE FOR AMERICAN SOCIETY OF MECHANICAL ENGINEERS CODE UPDATE (TAC NOS.
MD6113 AND MD6114)
Dear Mr. Christian:
The Commission has issued the enclosed Amendment Nos. 304 and 241 to Renewed Facility Operating License No. DPR 65 for the Millstone Power Station, Unit No. 2, and to Renewed Facility Operating License No. NPF-49 for the Millstone Power Station, Unit No. 3, respectively, in response to your application dated July 2, 2007, as supplemented by letter dated May 5, 2008.
The amendment updates the Technical Specification (TS) Surveillance Requirement (SR) 4.0.5 to reference the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) instead of Section XI of the ASME Boiler and Pressure Vessel Code, extends the TS SR 4.0.2 25 percent time extension to other normal and accelerated frequencies specified as 2 years or less in the inservice testing program, and removes the reference to the inservice inspection program in TS 4.0.5 and updates the reference to the snubbers TS surveillance frequency.
A copy of the related Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely,
/ra/ (PBamford for)
Carleen J. Sanders, Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-336 and 50-423
Enclosures:
- 1. Amendment No. 304 to DPR-65
- 2. Amendment No. 241 to NPF-49
- 3. Safety Evaluation cc w/encls: See next page
July 31, 2008 Mr. David A. Christian President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
MILLSTONE POWER STATION, UNIT NOS. 2 AND 3 - ISSUANCE OF AMENDMENT RE: TECHNCIAL SPECIFICATION CHANGE FOR AMERICAN SOCIETY OF MECHANICAL ENGINEERS CODE UPDATE (TAC NOS.
MD6113 AND MD6114)
Dear Mr. Christian:
The Commission has issued the enclosed Amendment Nos. 304 and 241 to Renewed Facility Operating License No. DPR 65 for the Millstone Power Station, Unit No. 2, and to Renewed Facility Operating License No. NPF-49 for the Millstone Power Station, Unit No. 3, respectively, in response to your application dated July 2, 2007, as supplemented by letter dated May 5, 2008.
The amendment updates the Technical Specification (TS) Surveillance Requirement (SR) 4.0.5 to reference the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) instead of Section XI of the ASME Boiler and Pressure Vessel Code, extends the TS SR 4.0.2 25 percent time extension to other normal and accelerated frequencies specified as 2 years or less in the inservice testing program, and removes the reference to the inservice inspection program in TS 4.0.5 and updates the reference to the snubbers TS surveillance frequency.
A copy of the related Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely,
/ra/ (PBamford for)
Carleen J. Sanders, Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-336 and 50-423
Enclosures:
- 1. Amendment No. 304 to DPR-65
- 2. Amendment No. 241 to NPF-49
- 3. Safety Evaluation cc w/encls: See next page DISTRIBUTION:
PUBLIC LPLI-2 R/F RidsAcrsAcnw_MailCTR RidsNrrDirsltsb RidsNrrDorlDpr RidsNrrDorlLpl1-2 RidsNrrRElliott RidsTChan RidsNrrPMCSanders RidsNrrLAABaxter RidsOgcRp RidsRgn1MailCenter R GHill, OIS JCollins ALising
- By Memo Dated 12/19/2007 Accession Nos: Package/ML081960318; Letter & Amds./ML081960312; TS to Amd304/ML081960324; TS to Amd241/ML082130702 Office NRR/LPL1-2/PM NRR/LPL1-2/LA NRR/DCI/CPNB NRR/DIRS/ITSB OGC NRR/LPL1-2/BC Name CSanders SLittle TChan*
RElliot DRoth HChernoff (JLamb for)
Date 07/17/2008 07/17/2008 12/19/2007 07/21/08 **
07/21/08 7/31/08
- with comments Official Record Copy
DOMINION NUCLEAR CONNECTICUT, INC., ET AL.
DOCKET NO. 50-336 MILLSTONE POWER STATION, UNIT NO. 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 304 Renewed License No. DPR-65
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the applicant dated July 2, 2007, as supplemented by letter dated May 5, 2008, 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. DPR-65 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 304, 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 the date of issuance, and shall be implemented within 180 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/ra/ (JLamb for)
Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the License and Technical Specifications Date of Issuance: July 31, 2008
ATTACHMENT TO LICENSE AMENDMENT NO. 304 RENEWED FACILITY OPERATING LICENSE NO. DPR-65 DOCKET NO. 50-336 Replace the following page of the Renewed Facility Operating License with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
Remove Insert Page 3 Page 3 Replace the following pages of the 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.
Remove Insert 3/4 0-3 3/4 0-3 3/4 7-21 3/4 7-21
DOMINION NUCLEAR CONNECTICUT, INC., ET AL.
DOCKET NOS. 50-423 MILLSTONE POWER STATION, UNIT NO. 3 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 241 Renewed License No. NPF-49
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the applicant dated July 2, 2007, as supplemented by letter dated May 5, 2008, 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-49 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 241 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated into the license. DNC 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 be implemented within 180 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/ra/ (JLamb for)
Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the License and Technical Specifications Date of Issuance: July 31, 2008
ATTACHMENT TO LICENSE AMENDMENT NO. 241 RENEWED FACILITY OPERATING LICENSE NO. NPF-49 DOCKET NO. 50-423 Replace the following page of the Renewed Facility Operating License with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
Remove Insert Page 4 Page 4 Replace the following pages of the 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.
Remove Insert 3/4 0-2 3/4 0-2 3/4 0-3 3/4 0-3 3/4 7-22 3/4 7-22
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 304 and 241 TO RENEWED FACILITY OPERATING LICENSE NOS. DPR-65 AND NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION, UNIT NOS. 2 AND 3 DOCKET NOS. 50-336 AND 50-423
1.0 INTRODUCTION
By letter dated July 2, 2007, as supplemented by letter dated May 5, 2008, the Dominion Nuclear Connecticut, Inc. (DNC or the licensee), submitted a request for changes to the Millstone Power Station, Unit Nos. 2 and 3 (MPS2 and MPS3) Technical Specifications (TSs). The requested changes would modify the TS Surveillance Requirement (SR) 4.0.5 to reference the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) instead of Section XI of the ASME Boiler and Pressure Vessel Code (ASME Code). Specifically, the proposed amendment would update the inservice testing (IST) of ASME Code Class 1, 2, and 3 pumps and valves to reflect the requirements in the ASME OM Code. The changes would also extend the TS SR 4.0.2 25 percent time extension to other normal and accelerated frequencies specified as 2 years or less in the IST program. In addition, the ISI requirement in TS 4.0.5 is being proposed for removal, and the reference to the ISI program is being updated in the TS for snubbers surveillance frequency.
The supplement dated May 5, 2008, clarified the application, did not expand the scope of the application as originally noticed and did not change the initial proposed no significant hazards consideration determination.
2.0 REGULATORY EVELUATION Section 182a of the Atomic Energy Act requires applicants for nuclear power plant operating licenses to include TSs as part of the license. These TSs are derived from the plant safety analyses.
Section 50.55a(f)(4) of Title 10 of the Code of Federal Regulations (10 CFR), requires, in part, that ASME Class 1, 2, and 3 components must meet the requirements of the ASME Code.
Section 50.55a(f)(4)(ii) requires that IST programs be revised every 10 years (120-months) to comply with the requirements of the latest edition and addenda of the ASME Code that is incorporated by reference in 10 CFR 50.55a(b)(3). Section 50.55a(f)(5)(ii) requires that, if a revised IST program for a facility conflicts with the TS for that facility, the licensee shall apply to the Nuclear Regulatory Commission (NRC or Commission) for amendment of the TS to conform the TS to the revised program. The licensee is required to submit the application, at least 6 months before the start of the period during which the provisions become applicable, in
accordance with 10 CFR 50.55a(f)(4). The MPS2 and MPS3 fourth and third 10-year IST interval programs, respectively, will be updated to comply with the latest approved edition and addenda of the ASME Code pursuant to 10 CFR 50.55a(f)(4)(ii) as required by 10 CFR 50.55a(f)(4). The fourth and third 10-year IST intervals are scheduled to begin December 2, 2008.
The OM Code was initially incorporated by reference in 10 CFR 50.55a(b)(3) in a final rule dated September 22, 1999 (64 FR 51370). Prior to the final rule, IST programs were required to meet the requirements of Section XI, Division 1, of the ASME Code. The ASME deleted the rules for IST of pumps and valves from Section XI in the 2000 Addenda because the rules for the IST of pumps and valves were placed in the ASME OM Code. The licensee submitted this license amendment request (LAR) to revise Section 4.0.5 to reference the pump and valve IST requirements in the OM Code requirements and delete the reference to ASME Code,Section XI IST requirements. Currently, 10 CFR 50.55a(b)(3) references the 2003 Addenda.
Section 50.36(d)(3) of 10 CFR requires that the TSs include SRs that assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits and that the limiting conditions for operation will be met.
3.0 TECHNICAL EVELUATION 3.1 Specific Changes Requested The licensee proposed to adopt the administrative TS changes and the expansion of Standard Technical Specification (STS) SR 3.0.2 contained in Technical Specification Task Force (TSTF)
Traveler 479 and TSTF-497. The licensee has also proposed to reference the ASME OM Code instead of the ASME Code for TS SR 4.0.5, extend the applicability of SR 4.0.2 provisions for TS SR 4.0.5, and to remove ISI program requirements from TS SR 4.0.5. The proposed LAR also expands TS SR 4.7.8 to include the ISI program for MPS2 and TS SR 4.7.10 for MPS3. In addition, the LAR adds a specific reference to TS 4.0.3 in TS 4.0.5 to clarify the applicability of TS 4.0.3 to TS 4.0.5. MPS2 and MPS3 have custom TS, so the TS numbering differs from that of the STS. In the case of this LAR, MPS2 and MPS3 TS differ by one (e.g. MPS2 and MPS3 TS 4.0.5 is comparable to STS 3.0.5).
3.2 Evaluation By letter dated December 6, 2005, the NRC staff TSTF-479, Revision 0, Changes to Reflect Revision of 10 CFR 50.55a, by concluding that the proposed revision to adopt the changes in 10 CFR 50.55a was acceptable, since the requirements of 10 CFR 50.55a adequately provided for IST. By letter dated October 4, 2006, the NRC staff approved TSTF-497, Revision 0 (TSTF-497), Limit Inservice Testing Program SR 3.0.2 Application to Frequencies of 2 Years or Less, by concluding that the changes proposed enhance the intention to apply the 25 percent IST interval extension for STS SR 3.0.2 to test frequencies of 2 years or less. The NRC staff concluded that the proposed changes were acceptable TSTF-479 revised the IST Program located in Chapter 5 of the STS to reflect the latest approved version of the ASME OM Code, in lieu of the ASME Code,Section XI requirements, to be consistent with the requirements of 10 CFR 50.55a. The changes will eliminate the ASME
Code inconsistency between the IST program and the TS as required by 10 CFR 50.55a(f)(5)(ii).
The licensees proposed TS changes to Section 4.0.5 to reflect the latest approved version of the OM Code are consistent with the TSTF-479. To ensure consistency between the proposed changes and the TSTFs, the licensee is also proposing to remove the ISI program requirement and corresponding ASME Code,Section XI requirement references, from TS 4.0.5.
MPS2 and MPS3 are required by NRC regulation 10 CFR 50.55a(g)(4) to meet ISI requirements for ASME Code Class 1, 2, and 3 components set forth in the ASME Code,Section XI and Addenda incorporated by reference in 10 CFR 50.55a(b). MPS2 and MPS3 maintain (and make necessary changes to) their respective ISI programs in accordance with approved station manuals and procedures as required by 10 CFR 50.55a(g). The SRs that reference TS 4.0.5 are applicable to IST requirements and not ISI requirements, with the exception of the TS for snubbers at both facilities (TS 4.7.8 for MPS2 and TS 4.7.10 for MPS3). As part of the licensees proposed amendment, the reference to the ISI program will be removed from TS 4.0.5 and placed directly in the SR for snubbers.
Removal of ISI requirements from TS 4.0.5 will not relieve MPS2 and MPS3 of their responsibility to seek relief from Code requirements when they are impractical nor will it eliminate any ISI activities not covered by 10 CFR 50.55a. Based on this discussion, removal of the ISI program from TS 4.0.5 and adding it to the snubbers TS will maintain an appropriate SR such that the necessary quality will be maintained. The NRC staff finds that the proposed change will continue to meet 10 CFR 50.36(d)(3) and is, therefore, acceptable.
To clarify the applicability of the provisions of STS SR 3.0.2, TSTF-497 revised the sentence in paragraph b of Chapter 5 of the STS to state: The provisions of SR 3.0.2 are applicable to the above required frequencies and to other normal and accelerated Frequencies specified as 2 years or less in the Inservice Testing Program for performing inservice testing activities. This change clearly states that the provisions of STS SR 3.0.2 are applicable to IST frequencies of 2 years or less. This requirement referred to the testing frequencies in the table in paragraph a of STS 5.5.8, which only lists test frequency intervals of 2 years or less. The licensees proposed revision to MPS2 and MPS3 TS Section 4.0.5.c would apply the 25 percent time extension provided for in TS SR 4.0.2 to other normal and accelerated frequency specified as 2 years or less in the IST Program, in addition to those periods listed in the Section 4.0.5.b table.
This extension facilitates surveillance scheduling and considers plant operating conditions that may not be suitable for conducting the surveillance (e.g., transient conditions or other ongoing surveillance or maintenance activities). The 25 percent extension does not significantly degrade the reliability that results from performing the surveillance at its specified Frequency. This is based on the recognition that the most probable result of any particular surveillance being performed is the verification of conformance with the SRs. The 25 percent extension allows a nonconforming condition with respect to the ASME Code, however this is permitted for a limited period of time, for test frequency intervals of 2 years or less, as required by the TS based on NRC analysis and approval.
The licensees revision adopts TSTF-479 and TSTF-497 changes to Section 4.0.5 of MPS2 and MPS3 TS to reflect the latest approved version of the ASME Code, the applicability of the provisions of STS SR 3.0.2, and additional wording to clarify that the test frequency extension in the IST program applies only to test frequencies of 2 years or less.
3.3 Summary The licensee provided sufficient information in the proposed amendment to demonstrate proper implementation of NRC-approved TSTF-479 and TSTF-497. The changes identified by the licensee in Attachments 2 and 3 of the licensees letter dated July 2, 2007, remove reference to ASME Code,Section XI, for SRs for pumps and valves and cites the OM Code in 10 CFR 50.55a. Further, the changes identified to TS 4.0.5.c effectively implement TSTF-497.
The proposed changes eliminate the redundancy of ISI requirements from the TS which are already covered under 10 CFR 50.55a. The NRC staff finds these TS changes do not eliminate any ISI requirements that are required by 10 CFR 50.55a. The NRC staff also finds that these TS changes to not eliminate from the TS any item required by 10 CFR 50.36(d)(3).
Based on this review, the NRC staff concludes that the licensees proposed changes to the MPS2 and MPS3 TS requirements do not result in any substantive change in operating requirements and are consistent with the Commissions regulations, do not impact the safe shutdown of the plant, and conform to the requirements of 10 CFR 50.55a. On this basis, the NRC staff concludes that the proposed TS changes are acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Connecticut State official was notified of the proposed issuance of the amendment. The State official had comments which were discussed during a phone call and are incorporated into this Safety Evaluation.
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 and changes surveillance requirements. 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 (72 FR 68210). 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 the proposed changes maintain adequate safety, and 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 Contributors: J. Collins A. Jason Lising Date: July 31, 2008
Millstone Power Station, Unit Nos. 2 and 3 cc:
Lillian M. Cuoco, Esquire Senior Counsel Dominion Resources Services, Inc.
Building 475, 5th Floor Rope Ferry Road Waterford, CT 06385 Edward L. Wilds, Jr., Ph.D.
Director, Division of Radiation Department of Environmental Protection 79 Elm Street Hartford, CT 06106-5127 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 First Selectmen Town of Waterford 15 Rope Ferry Road Waterford, CT 06385 Charles Brinkman, Director Washington Operations Nuclear Services Westinghouse Electric Company 12300 Twinbrook Pkwy, Suite 330 Rockville, MD 20852 Senior Resident Inspector Millstone Power Station c/o U.S. Nuclear Regulatory Commission P. O. Box 513 Niantic, CT 06357 Mr. J. W. "Bill" Sheehan Co-Chair NEAC 19 Laurel Crest Drive Waterford, CT 06385 Ms. Nancy Burton 147 Cross Highway Redding Ridge, CT 00870 Mr. Evan W. Woollacott Co-Chair Nuclear Energy Advisory Council 128 Terrys Plain Road Simsbury, CT 06070 Mr. Joseph Roy Director of Operations Massachusetts Municipal Wholesale Electric Company P.O. Box 426 Ludlow, MA 01056 Mr. William D. Bartron Licensing Supervisor Dominion Nuclear Connecticut, Inc.
Building 475, 5th Floor Roper Ferry Road Waterford, CT 06385 Mr. J. Alan Price Site Vice President Dominion Nuclear Connecticut, Inc.
Building 475, 5th Floor Rope Ferry Road Waterford, CT 06385 Mr. Chris L. Funderburk Director, Nuclear Licensing and Operations Support Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711 Mr. David A. Sommers Dominion Resources Services, Inc.
5000 Dominion Boulevard Glen Allen, VA 23060-6711 Mr. David A. Christian President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711