ML022000322
| ML022000322 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 09/17/2002 |
| From: | Richard Ennis NRC/NRR/DLPM/LPD1 |
| To: | Price J, Danni Smith Dominion Nuclear Connecticut |
| Ennis R, NRR/DLPM, 415-1420 | |
| References | |
| TAC MB3394, TAC MB3395, TAC MB3396 | |
| Download: ML022000322 (26) | |
Text
September 17, 2002 Mr. J. A. Price Site Vice President - Millstone Dominion Nuclear Connecticut, Inc.
c/o Mr. David A. Smith Rope Ferry Road Waterford, CT 06385
SUBJECT:
MILLSTONE POWER STATION, UNIT NOS. 1, 2, AND 3 - ISSUANCE OF AMENDMENTS RE: ADMINISTRATIVE AND EDITORIAL CHANGES (TAC NOS. MB3394, MB3395, AND MB3396)
Dear Mr. Price:
The Commission has issued the enclosed Amendment Nos. 111 , 270 and 212 to Facility Operating License Nos. DPR-21, DPR-65, and NPF-49 for the Millstone Nuclear Power Station, Unit Nos. 1, 2 and 3, respectively, in response to your application dated November 8, 2001, as supplemented August 14, 2002.
The amendments incorporate administrative and editorial changes into the Millstone Unit No. 1 (MP1) Permanently Defueled Technical Specifications (PDTS) and into the Millstone Unit Nos. 2 and 3 (MP2 and MP3) Technical Specifications (TSs). Specifically, the changes:
(1) relocate information not required to be retained in the TSs from Section 5.0, "Design Features," of the MP2 and MP3 TSs, to the respective units Final Safety Analysis Report (FSAR);
(2) revise TS 5.6.2, Technical Specifications Bases Control Program, in the MP1 PDTS consistent with a recent change to Title 10 of the Code of Federal Regulations (10 CFR)
Section 50.59; (3) add TS 6.23 for MP2 and TS 6.18 for MP3 to incorporate a TS bases control program within the MP2 and MP3 TSs; (4) add TS 6.19 to the MP3 TSs to define the program for tracking cyclic or transient limits and relocate these limits from TS 5.7 in the MP3 TSs to the MP3 FSAR; (5) revise the MP1 PDTS and the MP2 and MP3 TSs related to Radiological Environmental Monitoring Program (REMP) procedure processing to: (a) remove reference to an organization affiliated with Northeast Utilities (NU), the Production Operations Services Laboratory, which is no longer applicable following the change in ownership from NU to Dominion Nuclear Connecticut, Inc. (DNC); (b) replace the reference to the Radiological Assessment Branch (a Millstone DNC organization) with the organization responsible for the REMP for review/approval of changes to the REMP to avoid future TS changes due to a change in organizational titles; (c) correct an inconsistency within the MP1 PDTS which implies that REMP procedures are processed under the general procedure processing specification (i.e., TS 5.5.1), in addition to the specific specifications for processing REMP procedure changes (i.e., TSs 5.5.6 and 5.5.7); and
J. Price (6) make administrative changes to correct miscellaneous editorial issues and to achieve consistency between the TSs for each unit.
A copy of the related Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commissions biweekly Federal Register notice.
Sincerely,
/RA/
Richard B. Ennis, Senior Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-245, 50-336 and 50-423
Enclosures:
- 1. Amendment No. 111 to DPR-21
- 2. Amendment No. 270 to DPR-65
- 3. Amendment No. 212 to NPF-49
- 4. Safety Evaluation cc w/encls: See next page
- See previous concurrence OFFICE PDI-2/PM PDI-2/LA PDI-2/PM* PDIV-2/PM* RORP/SC* OGC* PDIV-2/SC PDI-2/SC(A)
NAME REnnis TClark VNerses JHickman RDennig RWeisman SDembeck JAndersen DATE 9/16/02 9/16/02 8/23/02 8/23/02 8/28/02 9/12/02 9/16/02 9/17/02 Millstone Power Station Units 1, 2, and 3 cc:
Ms. L. M. Cuoco Mr. P. J. Parulis Senior Nuclear Counsel Manager - Nuclear Oversight Dominion Nuclear Connecticut, Inc. Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Rope Ferry Road Waterford, CT 06385 Waterford, CT 06385 Edward L. Wilds, Jr., Ph.D. Ernest C. Hadley, Esq.
Director, Division of Radiation P. O. Box 1104 Department of Environmental West Falmouth, MA 02574-1104 Protection 79 Elm Street Mr. John Markowicz Hartford, CT 06106-5127 Co-Chair Nuclear Energy Advisory Council Regional Administrator, Region I 9 Susan Terrace U.S. Nuclear Regulatory Commission Waterford, CT 06385 475 Allendale Road King of Prussia, PA 19406 Mr. D. A. Smith Manager -Licensing First Selectmen Dominion Nuclear Connecticut, Inc.
Town of Waterford Rope Ferry Road 15 Rope Ferry Road Waterford, CT 06385 Waterford, CT 06385 Ms. Nancy Burton Mr. W. R. Matthews 147 Cross Highway Vice President and Senior Redding Ridge, CT 00870 Nuclear Executive - Millstone Dominion Nuclear Connecticut, Inc. Mr. D. J. Meekhoff Rope Ferry Road Unit 1 General Manager Waterford, CT 06385 Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Mr. Charles Brinkman, Manager Waterford, CT 06385 Washington Nuclear Operations ABB Combustion Engineering 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
Millstone Power Station Units 1, 2, and 3 cc:
Mr. G. D. Hicks Director - Nuclear Station Safety and Licensing Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385 Mr. Evan W. Woollacott Co-Chair Nuclear Energy Advisory Council 128 Terrys Plain Road Simsbury, CT 06070 Mr. D. A. Christian Senior Vice President - Nuclear Operations and Chief Nuclear Officer Innsbrook Technical Center - 2SW 5000 Dominion Boulevard Glen Allen, VA 23060 Mr. William D. Meinert Nuclear Engineer Massachusetts Municipal Wholesale Electric Company P.O. Box 426 Ludlow, MA 01056 Attorney Nicholas J. Scobbo, Jr.
Ferriter, Scobbo, Caruso, Rodophele, PC 75 State Street, 7th Floor Boston, MA 02108-1807 Mr. S. E. Scace Director - Nuclear Engineering Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385 Mr. M. J. Wilson Manager - Nuclear Training Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385
DOMINION NUCLEAR CONNECTICUT, INC.
DOCKET NO. 50-245 MILLSTONE POWER STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 111 License No. DPR-21
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Dominion Nuclear Connecticut, Inc. (the licensee) dated November 8, 2001, as supplemented August 14, 2002, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B. The facility will be decommissioned in conformity with 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 Commissions 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 Commissions 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-21 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 111, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. The license amendment is effective as of its date of issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Stephen Dembek, Chief, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: September 17, 2002
ATTACHMENT TO LICENSE AMENDMENT NO. 111 FACILITY OPERATING LICENSE NO. DPR-21 DOCKET NO. 50-245 Replace the following pages of 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 4.0-1 4.0-1 5.0-1 5.0-1 5.0-2 5.0-2 5.0-5 5.0-5 5.0-7 5.0-7 5.0-8 5.0-8 5.0-11 5.0-11 5.0-18 5.0-18 5.0-19 5.0-19
DOMINION NUCLEAR CONNECTICUT, INC.
DOCKET NO. 50-336 MILLSTONE POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 270 License No. DPR-65
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by the applicant dated November 8, 2001, as supplemented August 14, 2002, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions 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 Commissions 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 Commissions 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. 270, 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 within 60 days of issuance. The implementation of this amendment shall include the relocation of certain technical specification requirements to the Millstone Power Station, Unit No. 2 Final Safety Analysis Report as described in the licensees application dated November 8, 2001, as supplemented August 14, 2002, and evaluated in the staffs Safety Evaluation attached to this amendment.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
James W. Andersen, Acting 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 17, 2002
ATTACHMENT TO LICENSE AMENDMENT NO. 270 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 XV XV XVII XVII 3/4 7-14 3/4 7-14 5-1 5-1 5-2 5-2 5-3 5-3 5-4 5-4 5-5 5-5 5-6 5-6 6-1 6-1 6-2 6-2 6-3 6-3 6-4 6-4 6-15 6-15 6-16 6-16 6-17 6-17 6-22 6-22 6-23 6-23 6-28 6-28
DOMINION NUCLEAR CONNECTICUT, INC., ET AL.
DOCKET NO. 50-423 MILLSTONE POWER STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 212 License No. NPF-49
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by the applicant dated November 8, 2001, as supplemented August 14, 2002, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions 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 Commissions 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 Commissions 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. 212, 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 within 60 days of issuance. The implementation of this amendment shall include the relocation of certain technical specification requirements to the Millstone Power Station, Unit No. 3 Final Safety Analysis Report as described in the licensees application dated November 8, 2001, as supplemented August 14, 2002, and evaluated in the staffs Safety Evaluation attached to this amendment.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
James W. Andersen, Acting 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 17, 2002
ATTACHMENT TO LICENSE AMENDMENT NO. 212 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 xvii xvii xix xix 5-1 5-1 5-2 5-2 5-3 5-3 5-4 5-4 5-5 5-5 5-6a 5-6a 5-7 5-7 6-1 6-1 6-2 6-2 6-3 6-3 6-4 6-4 6-5 6-5 6-15 6-15 6-17a 6-17a 6-23 6-23 6-26 6-26
-- 6-27
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 111, 270 AND 212 TO FACILITY OPERATING LICENSE NOS. DPR-21, DPR-65 AND NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION, UNIT NOS. 1, 2, AND 3 DOCKET NOS. 50-245, 50-336 AND 50-423
1.0 INTRODUCTION
By application dated November 8, 2001, as supplemented August 14, 2002, Dominion Nuclear Connecticut, Inc. (DNC or the licensee) requested an amendment to Facility Operating License Nos. DPR-21, DPR-65 and NPF-49 for the Millstone Power Station, Unit Nos. 1, 2 and 3, respectively. The proposed amendment would incorporate administrative and editorial changes into the Millstone Unit No. 1 (MP1) Permanently Defueled Technical Specifications (PDTS) and into the Millstone Unit Nos. 2 and 3 (MP2 and MP3) Technical Specifications (TSs). The August 14, 2002, letter provided clarifying information that did not change the scope of the proposed action and did not change the staffs initial proposed no significant hazards consideration determination.
Specifically, the proposed changes would:
(1) relocate information not required to be retained in the TSs from Section 5.0, "Design Features," of the MP2 and MP3 TSs, to the respective units Final Safety Analysis Report (FSAR);
(2) revise TS 5.6.2, Technical Specifications Bases Control Program, in the MP1 PDTS consistent with a recent change to Title 10 of the Code of Federal Regulations (10 CFR)
Section 50.59; (3) add TS 6.23 for MP2 and TS 6.18 for MP3 to incorporate a TS bases control program within the MP2 and MP3 TSs; (4) add TS 6.19 to the MP3 TSs to define the program for tracking cyclic or transient limits and relocate these limits from TS 5.7 in the MP3 TSs to the MP3 FSAR;
(5) revise the MP1 PDTS and the MP2 and MP3 TSs related to Radiological Environmental Monitoring Program (REMP) procedure processing to: (a) remove reference to an organization affiliated with Northeast Utilities (NU), the Production Operations Services Laboratory, which is no longer applicable following the change in ownership from NU to DNC; (b) replace the reference to the Radiological Assessment Branch (a Millstone DNC organization) with the organization responsible for the REMP for review/approval of changes to the REMP to avoid future TS changes due to a change in organizational titles; (c) correct an inconsistency within the MP1 PDTS which implies that REMP procedures are processed under the general procedure processing specification (i.e., TS 5.5.1), in addition to the specific specifications for processing REMP procedure changes (i.e.,
TSs 5.5.6 and 5.5.7); and (6) make administrative changes to correct miscellaneous editorial issues and to achieve consistency between the TSs for each unit.
2.0 REGULATORY EVALUATION
Section 182a of the Atomic Energy Act (the Act) requires applicants for nuclear power plant operating licenses to include TSs as part of the license. The Commissions regulatory requirements that are related to the content of the TSs are contained in 10 CFR 50.36. That regulation requires that the TSs include items in five specific categories as follows: (1) safety limits, limiting safety systems settings, and limiting control settings (50.36(c)(1)); (2) limiting conditions for operation (LCO) (50.36(c)(2)); (3) surveillance requirements (50.36(c)(3));
(4) design features (50.34(c)(4)); and (5) administrative controls (50.36(c)(5)).
In general, there are two classes of changes to TSs: (1) changes needed to reflect modifications to the design basis (TSs are derived from the design basis), and (2) changes to take advantage of the evolution in policy and guidance as to the required content and preferred format of TSs over time. These amendments deal with only the second class of changes. In determining the acceptability of such changes, the staff interprets the requirements of the current version of 10 CFR 50.36, using as a model the accumulation of generically approved guidance in the improved Standard Technical Specification (STS) NUREGs. For this review we used NUREG-1433, Revision 2, Standard Technical Specifications, General Electric Plants, BWR/4, dated October 10, 2001 (for MP1, which is permanently defueled), NUREG-1432, Revision 2, Standard Technical Specifications, Combustion Engineering Plants, dated October 10, 2001 (for MP2), and NUREG-1431, Revision 2, Standard Technical Specifications, Westinghouse Plants, dated October 10, 2001 (for MP3). These NUREGs reflect the general guidance and LCO scoping criteria provided by the Commissions Final Policy Statement on Technical Specification Improvement for Nuclear Power Reactors, published in the FEDERAL REGISTER on July 22, 1993 (58 FR 39132) and incorporated in 10 CFR 50.36 effective August 18, 1995 (60 FR 36953).
Within this general framework, licensees may remove material from their TSs on two conditions: (1) the material is not required to be in the TSs based on the staffs interpretation of 10 CFR 50.36, including judgements about the level of detail required in the TSs; and (2) there exist suitable alternative regulatory controls for the relocated material (e.g., 10 CFR 50.59).
Licensees may revise the remaining TSs to adopt current improved STS format and content provided that plant-specific review supports a finding of continued adequate safety because:
(1) the change is editorial, administrative, or provides clarification (i.e., no requirements are
materially altered); (2) the change is more restrictive than the licensees current requirement; or (3) the change is less restrictive than the licensees current requirement, but nonetheless still affords adequate assurance of safety when judged against current regulatory standards. The detailed application of this general framework, and additional specialized guidance, are discussed in Section 3.0 in the context of specific proposed changes.
3.0 TECHNICAL EVALUATION
The proposed changes can be categorized as follows: (1) changes that remove design information from the TSs; (2) changes that revise or add TSs to reflect the guidance of the improved STS; (3) changes to TSs related to REMP procedure processing; and (4) miscellaneous administrative and editorial changes. The proposed changes for each of these four categories is evaluated in Sections 3.1, 3.2, 3.3, and 3.4, respectively.
3.1 Changes that Remove Design Information from the TSs Title 10 of the Code of Federal Regulations Section 50.36(c)(4), Design features, requires that TSs include design features of the facility such as materials of construction and geometric arrangements, which, if altered or modified, would have a significant effect on safety and are not covered in categories described in paragraphs (c)(1), (c)(2), or (c)(3), of 10 CFR 50.36.
Thus, information that is adequately covered by other sections of 10 CFR 50.36, or does not meet the fairly high threshold of significant to safety need not be in the TSs. Control of this removed material by other regulatory means is sufficient.
3.1.1 MP2 and MP3 - TS 5.1 Site, TS 5.1.1 Exclusion Area, TS 5.1.2 Low Population Zone; MP3 TS 5.1.3 Site Boundary for Liquid and Gaseous Effluents; MP2 - TS 5.1.3 Flood Control MP2 and MP3 TSs 5.1.1 and 5.1.2 and the corresponding TS figures provide maps of the site detailing the exclusion area boundary (EAB) and low population zone (LPZ). MP3 TS 5.1.3 and the corresponding TS figure provides a map of the site detailing the boundary for Liquid and Gaseous Effluents. MP2 TS 5.1.3 provides a reference to the FSAR regarding the design provisions for flood control.
The licensee proposes to: (1) rename TS 5.1 from Site to Site Location, (2) delete TSs 5.1.1, 5.1.2, and 5.1.3 including the associated figures, and (3) add a new paragraph under TS 5.1. The new paragraph would provide the location of the plant site and a text description of the site boundaries. The new paragraph would also provide restrictions on the sale or leasing of the property within the site boundary.
The staff finds that the removal of the design features information from the TSs that describes the EAB, LPZ, site boundary for liquid and gaseous effluents, and flood control, as proposed by the licensee, will have no impact on safety and, therefore, does not meet the criteria of 10 CFR 50.36(c)(4) for items to be included in the TSs. As discussed in the licensees submittal, the design features information proposed for deletion from the TSs is already provided in the respective units FSAR or referenced from the MP2 FSAR to the MP3 FSAR.
Therefore, future changes to the design features information that is being removed will be adequately controlled by 10 CFR 50.59. In addition, removing these TSs and figures and providing a text description of the site location is consistent with the content in the improved
STS (NUREG-1432 and NUREG-1431). Based on the preceding, the staff concludes that the proposed changes are acceptable.
3.1.2 MP2 and MP3 - TS 5.2 Containment, TS 5.2.1 Configuration, TS 5.2.2 Design Pressure and Temperature; MP2 - TS 5.2.3 Penetrations These TSs provide design parameters and information for the containment structures. The licensee proposes to remove these TS sections since all this information is already duplicated in the respective units FSAR with the exception of the equilibrium containment liner temperature contained in TS 5.2.2 for MP2. The licensees submittal stated that this design parameter would be added to the MP2 FSAR in conjunction with processing this amendment.
TS Section 3/4.6 Containment Systems contains the specifications relating to containment design parameters that are required to be in the TSs as LCOs by 10 CFR 50.36(c)(2). TS Section 3/4.6 provides the specifications necessary to maintain MP2 and MP3 containment integrity. The proposal is consistent with the guidance contained in the improved STS (NUREG-1432 and NUREG-1431). The staff concludes that relying on 10 CFR 50.59 to control the information contained in TSs 5.2, 5.2.1, 5.2.2, and 5.2.3 (once that information is relocated to the FSAR) is acceptable because TS Section 3/4.6 will still contain the information necessary to meet the requirements of 10 CFR 50.36. Therefore, the proposed changes are acceptable.
3.1.3 MP2 and MP3 - TS 5.4 Reactor Coolant System The licensee proposes to remove TS 5.4, Reactor Coolant, including sub-specifications 5.4.1, Design Pressure and Temperature, and 5.4.2, Volume. Design pressure, temperature, and volume parameters for the reactor coolant system (RCS) are found in the FSAR. TS 3/4.4, Reactor Coolant System, contains the specifications relating to RCS design parameters that are required to be in the TSs by 10 CFR 50.36(c)(2). TS 3/4.4 provides effective operational limits to ensure that the RCS temperature, pressure, and leakage are maintained below the respective design limits in addition to monitoring RCS degradation. The proposal is consistent with the guidance contained in the improved STS (NUREG-1432 and NUREG-1431). The staff concludes that relying on 10 CFR 50.59 to control the information contained in TS 5.4 (once that information is relocated to the FSAR) is acceptable because TS Section 3/4.4 will still contain the information necessary to meet the requirements of 10 CFR 50.36. Therefore, the proposed changes are acceptable.
3.1.4 MP2 - TS 5.5 Emergency Core Cooling Systems The current TS 5.5, Emergency Core Cooling Systems, states the following: The emergency core cooling systems (ECCS) are designed and shall be maintained in accordance with the design provisions contained in Section 6.3 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements. TS 5.5 only provides a reference to the FSAR; therefore, the information that TS 5.5 encompasses is already located outside the current TS. TS 3/4.5, Emergency Core Cooling Systems, contains the specifications relating to ECCS design parameters that are required to be in the TSs by 10 CFR 50.36(c)(2). TS 3/4.5 provides the specifications necessary for the ECCS to maintain the functional capability to mitigate the consequences of the design-basis accident. The proposal is consistent with the guidance contained in the improved STS (NUREG-1432). The staff concludes that relying on 10 CFR 50.59 to control the information to which TS 5.5 refers, and which is already in the
FSAR, is acceptable because TS Section 3/4.5 will still contain the information necessary to meet the requirements of 10 CFR 50.36. Therefore, the proposed changes are acceptable.
3.1.5 MP2 - TS 5.7 Seismic Classification The current TS 5.7, Seismic Classification, states the following: Those structures, systems and components identified as Category I Items in Section 5.1.1 of the FSAR shall be designed and maintained to the design provisions contained in Section 5.8 of the FSAR with allowances for normal degradation pursuant to the applicable Surveillance Requirements. The licensee proposes to delete TS 5.7 from the MP2 TSs.
The staff finds that the removal of design features information from the TSs that merely provides a reference to the FSAR will have no impact on safety and, therefore, does not meet the criteria of 10 CFR 50.36(c)(4) for items to be included in the TSs. The inclusion of this design information in the FSAR will ensure that any changes to the information being removed from the TSs is adequately controlled by 10 CFR 50.59. In addition, removing this TS is consistent with the content in the improved STS (NUREG-1432). Based on the preceding, the staff concludes that the proposed change is acceptable.
3.1.6 MP2 - TS 5.8 and MP3 - TS 5.5 Meteorological Tower Location TS 5.8 (MP2) and TS 5.5 (MP3) reference the location of the meteorological tower on TS Figures 5.1-1 and 5.1-3, respectively. The licensee proposes to remove TS 5.8 (MP2) and TS 5.5 (MP3) from their respective TSs. The referenced TS figures are also proposed for deletion as part of the proposed changes to TS 5.1 as discussed in Safety Evaluation Section 3.1.1.
The staff finds that the removal of the design features information from the TSs that describes the location of the meteorological tower will have no impact on safety and, therefore, does not meet the criteria of 10 CFR 50.36(c)(4) for items to be included in the TSs. The location of the meteorological tower is shown on Figure 1.2-1 in the MP2 FSAR and Figure 2.1-3 in the MP3 FSAR. Therefore, future changes to the design features information that is being removed will be adequately controlled by 10 CFR 50.59. In addition, removing these TSs is consistent with the content in the improved STS (NUREG-1432 and NUREG-1431). Based on the preceding, the staff concludes that the proposed changes are acceptable 3.2 Changes that Revise or Add TSs to Reflect the Guidance of the Improved STS The licensee proposes to revise the PDTS for MP1 and add TSs for MP2 and MP3 in order to maintain a consistent TS Bases Control Program for the three Units. Furthermore, the licensee proposes to add a Component Cyclic or Transient Limit Specification to the MP3 TS.
3.2.1 MP1 - PDTS 5.6.2 TS Bases Control Program The improved STS include a TS Bases Control Program that requires licensees to apply the provisions of 10 CFR 50.59 to any proposed Bases change to ensure that staff review is not required prior to making the change. The licensee based PDTS 5.6.2, TS Bases Control Program for MP1 on the previous edition of 10 CFR 50.59 which allowed changes without U.S.
Nuclear Regulatory Commission (NRC) approval if such changes did not result in an
unreviewed safety question. In 1999, the NRC revised 10 CFR 50.59, eliminating the term unreviewed safety question. In accordance with the STS guidelines, the licensee is proposing to revise PDTS 5.6.2 in order to maintain consistency with the revised 10 CFR 50.59. The staff has reviewed the licensee's proposed revisions to PDTS 5.6.2 and concludes that the proposed change is acceptable because it adopts guidance that is consistent with the revised 10 CFR 50.59 and is editorial or administrative in nature.
3.2.2 MP2 - TS 6.23 and MP3 - TS 6.18 TS Bases Control Program The licensee proposes to add TS 6.23 for MP2 and TS 6.18 for MP3, Technical Specifications (TS) Bases Control Program, consistent with the improved STS (NUREG-1432 and NUREG-1431). The staff concludes that the proposed changes are acceptable because they adopt the improved STS and are more restrictive than the current TSs since neither unit has a bases control program in the current TSs.
3.2.3 MP3 - TS 6.19 Component Cyclic or Transient Limit Specification The "Component Cyclic or Transient Limit specification, defined in each of the improved STS NUREGs, provides that licensees track cyclic and transient occurrences as described in the FSAR in order to ensure that components are maintained within their design limits. Currently, these limits are listed in MP3 TS 5.7, "Component Cyclic or Transient Limit," in addition to MP3 FSAR Section 3.N. The licensee proposes to delete TS 5.7 and add a new TS 6.19, "Component Cyclic or Transient Limit," to the MP3 TSs. The new TS would reference FSAR Section 3.N rather than including the actual limits within the TSs.
The staff finds that the addition of TS 6.19 provides the administrative controls necessary to ensure that the Component Cyclic or Transient Limit program will be implemented such that plant components will be maintained within their design limits. The deletion of the actual limits from the TSs is acceptable since any changes to the limits will be adequately controlled under 10 CFR 50.59. In addition, the proposed changes are consistent with the content in the improved STS (NUREG-1431). Based on the preceding, the staff concludes that the proposed changes are acceptable.
3.3 Changes to TSs Related to REMP Procedure Processing The licensee proposes to revise the MP1, MP2, and MP3 TSs related to REMP procedure processing in order to reflect the change in ownership from NU to DNC. Additionally, the licensee proposes to correct an inconsistency within the MP1 PDTS with regards to REMP processing. The requirements of 10 CFR 50.36(c)(5), Administrative controls, apply to this material. However, no substantive interpretation was necessary for this change request.
3.3.1 MP1 - PDTS 5.56 and 5.57, MP2 - TS 6.8.5 and MP3 - TS 6.8.6 REMP Procedures The current TSs state that the review of all procedures, procedure changes, and temporary changes to the REMP shall be reviewed by an individual (other than the author) who is from the Radiological Assessment Branch or the Production Operation Services Laboratory (POSL).
With the sale of the Millstone Units to DNC, DNC will no longer use the services of POSL,
which is affiliated with the former owner. The licensee proposes to remove the terms Production Operation Services Laboratory and POSL from the TSs. The staff has reviewed the proposed changes and concludes that these revisions are necessary in order to preserve the accuracy of the REMP TSs.
The licensee also is proposing to replace the term Radiological Assessment Branch with the organization responsible for the REMP. By doing this, the licensee will reduce future TS changes due to reorganizations that involve the organization responsible for REMP, while maintaining appropriate oversight of the REMP. By making this change the licensee is implementing guidance contained in Generic Letter (GL) 88-06, which addresses changes in organizations and position titles. The staff has reviewed the proposed changes and concludes that these revisions streamline the maintenance of this section of the TSs. Based on the above, the staff concludes that the proposed changes are acceptable.
3.3.2 MP1 - PDTS 5.5 Procedures The licensee provides the requirements for the MP1 REMP procedures in PDTS 5.5.6 and PDTS 5.5.7. During the development of the PDTS for MP1, the licensee modified the language related to the REMP program contained in PDTS 5.5.1, and changed the intent of the TS language. With this change, the PDTS now imply that the REMP procedures are processed under the specifications of PDTS 5.5.1 through PDTS 5.5.5 instead of the REMP related specifications, PDTS 5.5.6 and PDTS 5.5.7. In order to correct this inaccuracy, the licensee proposes to modify PDTS 5.5.1.d, PDTS 5.5.1.g, and PDTS 5.5.3 to clearly indicate that the REMP procedures should follow the requirements contained in PDTS 5.5.6 and PDTS 5.5.7.
The staff has reviewed the proposed changes and concludes that these revisions clarify the requirements for the REMP procedures. Therefore, the proposed changes are acceptable.
3.4 MP1, MP2, and MP3 - Miscellaneous Administrative and Editorial Changes The licensee has proposed administrative changes to correct miscellaneous editorial issues and to achieve consistency between the TSs for each unit. The proposed changes include the following: (1) changing organizational and position titles; (2) changing the title of the Quality Assurance Topical Report to the Quality Assurance Program Topical Report; (3) replacing the term health physics with radiation protection; (4) removing references to the Plant Operations Review Committee (PORC); (5) changing an incorrect reference to a Surveillance Requirement (SR); (6) changing a reference to the provider of meteorological information; (7) administrative corrections to reflect a previous amendment; and (8) revising PDTS 4.1 to correct two errors.
3.4.1 Changing Organization and Position Titles The licensee proposes to make the following changes:
(1) change Designated Officer to designated officer and Designated Senior Officer to designated senior officer in MP1 PDTSs 5.1.1, 5.2.1.c, 5.5.2, 5.5.3, 5.5.4, and 5.5.5.c; (2) change Designated Manager to designated manager in MP1 PDTSs 5.1.1, 5.2.1.b, 5.5.2, 5.5.3, 5.5.4, and 5.5.5.c;
(3) change Manager or Directors to managers or directors in MP2 TS 6.8.2.b and MP3 TS 6.8.2.b; (4) change SS to SM and Shift Supervisor to Shift Manager in MP2 TS 6.12.2 and MP3 TSs 6.2.4.1, 6.12.2 , and Table 6.2-1; and (5) change Operations Manager and Assistant Operations Manager to operations manager and assistant operations manager in MP1 PDTS 5.3.1.1, MP2 TS 6.3.1.a, and MP3 TS 6.3.1.a.
The proposed changes correct inconsistencies in capitalization and make changes to reflect current titles. The staff concludes that the proposed changes are editorial or administrative in nature, have no impact on safety, and are consistent with the guidance of GL 88-06 concerning changes in organization and position titles. Therefore, the proposed changes are acceptable.
3.4.2 Changing the Title of the Quality Assurance Topical Report to the Quality Assurance Program Topical Report The licensee proposes to change the title of the Quality Assurance Topical Report to the Quality Assurance Program Topical Report in MP1 PDTSs 5.1.3 and 5.2.1.a, MP2 TSs 6.1.3 and 6.2.1.a, and MP3 TSs 6.1.3 and 6.2.1.a.
The proposed changes correct the title for the DNC Quality Assurance Program Topical Report consistent with the current title. The staff concludes that the proposed changes are editorial or administrative in nature and have no impact on safety. Therefore, the proposed changes are acceptable.
3.4.3 Replacing the Term Health Physics with Radiation Protection The licensee proposes to make the following changes:
(1) change Health Physics Technician to radiation protection technician in MP2 TS 6.12.1 and Table 6.2-1, and MP3 TSs 6.2.2.d and 6.12.1; (2) change health physics or Health Physics to radiation protection in MP1 PDTSs 5.8.1 and 5.8.2, MP2 TSs 6.2.1.d and 6.12.2, and MP3 TSs 6.2.1.d and 6.12.2; (3) change Health Physics Manager to radiation protection manager in MP1 PDTSs 5.3.1.2, MP2 TSs 6.3.1.c and 6.12.1.c, and MP3 TSs 6.3.1.b and 6.12.1.c; (4) change An individual qualified in radiation protection procedures to A radiation protection technician in MP2 TS 6.2.2.d; and (5) add the date of Regulatory Guide (RG) 1.8 to MP1 PDTS 5.3.1.2 and MP2 TS 6.3.1.c.
The licensees submittal states that the proposed changes revise the TSs to reflect current industry practice for referring to the radiation protection function. In addition, the date of May 1977 is being added for RG 1.8 to reflect the specific RG revision that is the basis for the qualifications of the radiation protection manager. The staff concludes that the proposed
changes are editorial or administrative in nature, have no impact on safety, and are consistent with the guidance of GL 88-06 concerning changes in organization and position titles.
Therefore, the proposed changes are acceptable.
3.4.4 Removing References to the PORC The licensee proposes to remove references to the PORC in MP1 PDTSs 5.5.2, 5.5.4, and 5.5.5.c. The PORC was combined into the Site Operation Review Committee (SORC).
The references would refer solely to the SORC.
The staff concludes that the proposed changes are editorial or administrative in nature and have no impact on safety. Therefore, the proposed changes are acceptable.
3.4.5 Changing an Incorrect Reference to an SR MP2 TS 6.9.1.5.b currently references SR 4.4.5.5.b with respect to details of reports pertaining to steam generator tube inservice inspections. However, there is no SR 4.4.5.5.b within the MP2 TSs. The licensee proposes to correct this error to show the correct SR 4.4.5.1.5.b.
The staff concludes that the proposed change is editorial or administrative in nature and corrects an error in the TSs. Therefore, the proposed change is acceptable.
3.4.6 Changing a Reference to the Provider of Meteorological Information MP2 TS 3.7.5.1, Flood Level, specifies that at least one operable service water pump motor shall be protected against flooding if the water level exceeds plant grade level or certain meteorological conditions exist. SR 4.7.5.1.2 states, The above specified meteorological conditions shall be determined at least once per 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> when a hurricane eye is within 150 miles of the facility. The meteorological conditions shall be determined from forecasts obtained from the Connecticut Valley, Electrical Exchange (CONVEX) and from site meteorological instrumentation.
The licensee proposes to revise SR 4.7.5.1.2 to replace forecasts obtained from the Connecticut Valley, Electrical Exchange (CONVEX) and with weather service forecasts and/or so that commercial weather service providers could also be utilized.
The staff concludes that the proposed change is editorial or administrative in nature and has no impact on safety. Therefore, the proposed change is acceptable.
3.4.7 Administrative Corrections to Reflect a Previous Amendment MP2 TS 5.9, Shoreline Protection, was previously deleted as part of License Amendment No. 216 (note, the licensees submittal states that TS 5.9 was deleted as part of Amendment No. 189). However, several administrative corrections need to be made to properly reflect the previous deletion of TS 5.9. The licensee proposes to make the following changes:
(1) On Index page XV, under Section 5.9, replace the title SHORELINE PROTECTION with DELETED; and
(2) On TS page 5-6, after TS 5.8, add 5.9 DELETED.
The staff concludes that the proposed changes are editorial or administrative in nature and have no impact on safety. Therefore, the proposed changes are acceptable.
3.4.8 Revising PDTS 4.1 to Correct Two Errors In the submittal dated August 14, 2002, the licensee proposed the following changes to MP1 PDTS 4.1, Site Location:
(1) change the reference for where the definition of EAB is specified from 10 CFR 100.3(a) to 10 CFR 100.3; and (2) revise the distance from the elevated stack to the nearest site boundary from 1,620 feet to 1,627 feet.
These changes correct two errors in PDTS 4.1 and provide consistency between the descriptions of the site location for the TSs for MP1, MP2, and MP3. The staff concludes that the proposed changes are editorial or administrative in nature and have no impact on safety.
Therefore, the proposed changes are acceptable.
3.5 Evaluation Summary The staff reviewed the proposed changes for compliance with 10 CFR 50.36 and agreement with the guidance established in NUREG-1431, NUREG-1432, and NUREG-1433. Based on the preceding evaluation, the NRC staff concludes that the proposed 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 no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes recordkeeping, reporting, or administrative requirements.
Accordingly, the amendment meets 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 amendment.
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 Commissions 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: P. Hearn R. Ennis Date: September 17, 2002