ML052210039
| ML052210039 | |
| Person / Time | |
|---|---|
| Site: | Millstone  (DPR-065, NPF-049) |
| Issue date: | 09/15/2005 |
| From: | Nerses V NRC/NRR/DLPM/LPD1 |
| To: | Christian D Dominion Nuclear Connecticut |
| Nerses V, NRR//DLPM, 415-1484 | |
| References | |
| TAC MC4746, TAC MC4747 | |
| Download: ML052210039 (13) | |
Text
September 15, 2005 Mr. David A. Christian Sr. 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 OF AMENDMENT RE: TECHNICAL SPECIFICATION CHANGES ASSOCIATED WITH THE CONSOLIDATED QUALITY ASSURANCE PROGRAM DESCRIPTION (TAC NOS. MC4746 AND MC4747)
Dear Mr. Christian:
The Commission has issued the enclosed Amendment No. 288 to Facility Operating License No. DPR-65, and Amendment No. 226 to Facility Operating License No. NPF-49, for the Millstone Power Station, Unit Nos. 2 and 3, respectively, in response to your application dated September 8, 2004, as supplemented by letters dated May 5 and July 27, 2005.
The amendments modify the Technical Specifications by revising selective administrative controls to support the implementation of the proposed Dominion Nuclear Facility Quality Assurance Program Description.
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/
Victor Nerses, Senior Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-336 and 50-423
Enclosures:
- 1. Amendment No. 288 to DPR-65
- 2. Amendment No. 226 to NPF-49
- 3. Safety Evaluation cc w/encls: See next page
Mr. David A. Christian Sr. 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 OF AMENDMENT RE: TECHNICAL SPECIFICATION CHANGES ASSOCIATED WITH THE CONSOLIDATED QUALITY ASSURANCE PROGRAM DESCRIPTION (TAC NOS. MC4746 AND MC4747)
Dear Mr. Christian:
The Commission has issued the enclosed Amendment No. 288 to Facility Operating License No. DPR-65, and Amendment No. 226 to Facility Operating License No. NPF-49, for the Millstone Power Station, Unit Nos. 2 and 3, respectively, in response to your application dated September 8, 2004, as supplemented by letters dated May 5 and July 27, 2005.
The amendments modify the Technical Specifications by revising selective administrative controls to support the implementation of the proposed Dominion Nuclear Facility Quality Assurance Program Description.
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/
Victor Nerses, Senior Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-336 and 50-423
Enclosures:
- 1. Amendment No. 288 to DPR-65
- 2. Amendment No. 226 to NPF-49
- 3. Safety Evaluation cc w/encls: See next page DISTRIBUTION:
PUBLIC PDI-2 R/F CHolden DRoberts VNerses GWunder CRaynor OGC GHill (2)
PKrohn, RI ACRS Accession Number: ML052210039 OFFICE PDI-2/PM PDI-2/PM PDI-2/LA OGC PDI-2/SC NAME VNerses GWunder CRaynor SBrock DRoberts DATE 9/13/05 9/14/05 9/12/05 8/30/05 9/14/05 Official Record Copy
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. John Markowicz Co-Chair Nuclear Energy Advisory Council 9 Susan Terrace 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. David W. Dodson 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
DOMINION NUCLEAR CONNECTICUT, INC.
DOCKET NO. 50-336 MILLSTONE POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 288 License No. DPR-65 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Dominion Nuclear Connecticut, Inc. (the licensee) dated September 8, 2004, as supplemented May 5 and July 27, 2005, 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 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. 288, 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 be implemented by February 28, 2006.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Darrell J. Roberts, Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: September 15, 2005
ATTACHMENT TO LICENSE AMENDMENT NO. 288 FACILITY OPERATING LICENSE NO. DPR-65 DOCKET NO. 50-336 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 6-1 6-1 6-2 6-2 6-3 6-3 6-4 6-4 6-5 6-5
DOMINION NUCLEAR CONNECTICUT, INC.
DOCKET NO. 50-423 MILLSTONE POWER STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 226 License No. NPF-49 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Dominion Nuclear Connecticut, Inc. (the licensee) dated September 8, 2004, as supplemented May 5, and July 28, 2005, 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 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. 226, 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 be implemented by February 28, 2006.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Darrell J. Roberts, Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: September 15, 2005
ATTACHMENT TO LICENSE AMENDMENT NO. 226 FACILITY OPERATING LICENSE NO. NPF-49 DOCKET NO. 50-423 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 6-1 6-1 6-4 6-4 6-5 6-5
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 288 TO FACILITY OPERATING LICENSE NO. DPR-65 AND AMENDMENT NO. 226 TO FACILITY OPERATING LICENSE NO. 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 September 8, 2004 [see Agencywide Documents Access Management System (ADAMS) Accession No. ML042530271], as supplemented by letters dated May 5, and July 27, 2005 (ADAMS Accession Nos. ML051300508 and ML052080357, respectively), Dominion Nuclear Connecticut, Inc. (DNC) submitted a request to modify the Millstone Power Station, Unit Nos. 2 and 3 (MPS2 and MPS3) Technical Specifications (TSs) by revising selective administrative controls to support the implementation of the proposed Dominion Nuclear Facility Quality Assurance Program Description (NFQAPD). Specifically, the proposed changes are administrative in nature and are required to support the implementation of the proposed Dominion NFQAPD. The proposed changes are consistent with the intent of NUREGs-1431 and 1432, Standard Technical Specifications for Westinghouse and Combustion Engineering plants, respectively.
The supplements dated May 5 and July 27, 2005, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the Nuclear Regulatory Commission (NRC or the Commission) staffs original proposed no significant hazards consideration determination as published in the Federal Register on January 18, 2005 (70 FR 2888).
2.0 BACKGROUND
DNC and Virginia Electric and Power Company (the licensees) submitted their NFQAPD Topical Report (DOM-QA-1) by letter dated August 24, 2004 (ADAMS Accession No. ML042470014), for NRC review and approval in accordance with the provisions of Title 10 of the Code of Federal Regulations (10 CFR) Section 50.54(a)(4). The quality assurance (QA) topical report would replace and consolidate the current site-specific QA programs for MPS 1,2 and 3, North Anna Power Station Unit Nos. 1 and 2, and Surry Power Station Unit Nos. 1 and 2.
By letter dated September 9, 2005 ( ADAMS Accession No. ML052490337), the NRC approved the NFQAPD Topical Report. DNC has proposed administrative TS changes to support implementation of the proposed NFQAPD at MPS2 and 3.
3.0 REGULATORY EVALUATION
The Commissions regulatory requirements related to the content of TSs are set forth in 10 CFR 50.36. This regulation requires that the TSs include items in five specific categories, including: 1) safety limits, limiting safety system settings and limiting control settings, 2) limiting conditions for operation, 3) surveillance requirements, 4) design features, and 5) administrative controls.
Specifically, 10 CFR 50.36(c)(5) describes administrative controls as provisions relating to organization and management, procedures, recordkeeping, review and audit, and reporting necessary to assure operation of each facility in a safe manner. The specific content of the administrative controls section of the TSs is, therefore, that information that the Commission deems essential for the safe operation of the facility that is not already adequately covered by other regulations.
4.0 TECHNICAL EVALUATION
Administrative (non-technical) modifications to TSs are intended to incorporate human factors principles into the form and structure of the TSs so plant operations personnel can more easily and effectively use them. These modifications are editorial in nature or involve the reorganization or reformatting of TS requirements without affecting technical content or operational restrictions.
The following table provides a summary description of the proposed administrative changes.
Plant TS Section Summary MPS2/MPS3 6.1.3 Replaces the phrase Quality Assurance Program Topical Report with appropriate administrative documents.
MPS2/MPS3 6.3.1 Replaces except for: with Exceptions to this requirement are specified in the Quality Assurance Program.
MPS2/MPS3 6.3.1.a Revised numbering to become Section 6.3.2 MPS2 MPS3 6.3.1.c 6.3.1.b Deletes the section that specifically describes the qualification requirements of the Radiation Protection Manager. These requirements are covered by the wording contained in TS 6.3.1 (MPS2 and MPS3).
MPS2 6.3.1.b Deletes this section that specifically describes the education and qualification requirements for the Shift Technical Advisor (STA). The STA education requirements are contained in Table 6.2-1.
MPS2 Table 6.2-1 Note (1)
Replaces the phrase Senior Reactor or Senior Reactor Operator Limited to Fuel Handling individual supervision with Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling individual supervising.
Plant TS Section Summary MPS2 Table 6.2-1 Note (4)
Replaces the phrase requirements of Specification 6.3.1.b.1 with Shift Technical Advisor qualifications of the Commission Policy Statement on Engineering Expertise on Shift.
MPS2 6.4 Replaces the phrase and recommendations of Section 5.5 of ANSI [American National Standards Institute] N18.1-1971*
with as specified in the Quality Assurance Program. The associated footnote, *, is deleted since it is no longer required.
MPS3 6.2.4.1 Deletes the sentence The Shift Technical Advisor shall have a bachelors degree or equivalent in a scientific or engineering discipline and shall have received specific training in the response and analysis of the unit for transients and accidents, and in unit design and layout, including the capabilities of instrumentation and controls in the control room. STA education requirements are contained in Table 6.2-1.
MPS3 6.4.1 Replaces the phrase and recommendations of Section 5.5 of ANSI N18.1-1971* with as specified in the Quality Assurance Program.
The NRC staff reviewed the administrative and editorial changes proposed by DNC. The staff confirmed that the appropriate information, discussed above, was captured correctly in the proposed QA program. The staff concludes that the proposed TS changes (1) satisfy the guidance with regard to the content of TSs, (2) conform to the models provided in NUREGs-1431 and 1432, (3) do not result in any change in operating requirements, (4) and are consistent with the Commissions regulations.
5.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Connecticut State official was notified of the proposed issuance of the amendments. The Connecticut State official agreed with the NRC staffs conclusion as stated in Section 7 of this Safety Evaluation.
6.0 ENVIRONMENTAL CONSIDERATION
The amendments change selective administrative controls within the restricted area as defined in 10 CFR Part 20. 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 (70 FR 2888). 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.
7.0 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 Commissions 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: R. Pelton K. Kavanagh Date: September 15, 2005