ML060550271
ML060550271 | |
Person / Time | |
---|---|
Site: | Millstone |
Issue date: | 06/28/2006 |
From: | Nerses V Plant Licensing Branch III-2 |
To: | Christian D Dominion Nuclear Connecticut |
Nerses V, NRR//DLPM, 415-1484 | |
Shared Package | |
ML061770060 | List: |
References | |
TAC MC6379, TAC MC6380 | |
Download: ML060550271 (16) | |
Text
June 28, 2006 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 AMENDMENTS RE: TECHNICAL SPECIFICATION CHANGE REQUEST FOR POSITIVE REACTIVITY ADDITIONS DURING SHUTDOWN OPERATIONS (TAC NOS. MC6379 AND MC6380)
Dear Mr. Christian:
The Commission has issued the enclosed Amendment No. 293 to Facility Operating License No. DPR-65 for the Millstone Power Station, Unit No. 2, and the enclosed Amendment No. 230 to Facility Operating License No. NPF-49 for the Millstone Power Station, Unit No. 3 in response to your application dated March 9, 2005, as supplemented by letter dated July 7, 2005. The amendments make various changes to the Technical Specifications to incorporate wording related to the reactor coolant system, electrical power system and refueling operations to provide operational flexibility during mode changes or addition of coolant during shutdown operations.
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 Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-336 50-423
Enclosures:
- 1. Amendment No. 293 to DPR-65
- 2. Amendment No. 230 to NPF-49
- 3. Safety Evaluation cc w/encls: See next page
June 28, 2006 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 AMENDMENTS RE: TECHNICAL SPECIFICATION CHANGE REQUEST FOR POSITIVE REACTIVITY ADDITIONS DURING SHUTDOWN OPERATIONS (TAC NOS. MC6379 AND MC6380)
Dear Mr. Christian:
The Commission has issued the enclosed Amendment No. 293 to Facility Operating License No. DPR-65 for the Millstone Power Station, Unit No. 2, and the enclosed Amendment No. 230 to Facility Operating License No. NPF-49 for the Millstone Power Station, Unit No. 3 in response to your application dated March 9, 2005, as supplemented by letter dated July 7, 2005. The amendments make various changes to the Technical Specifications to incorporate wording related to the reactor coolant system, electrical power system and refueling operations to provide operational flexibility during mode changes or addition of coolant during shutdown operations.
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 Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-336 50-423
Enclosures:
- 1. Amendment No. 293 to DPR-65
- 2. Amendment No. 230 to NPF-49
- 3. Safety Evaluation cc w/encls: See next page DISTRIBUTION:
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DOMINION NUCLEAR CONNECTICUT, INC.
DOCKET NO. 50-336 MILLSTONE POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 293 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 March 9, 2005, as supplemented on July 7, 2005, 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. 293, 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 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Darrell J. Roberts, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: June 28, 2006
ATTACHMENT TO LICENSE AMENDMENT NO. 293 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 XII XII 3/4 4-1a 3/4 4-1a 3/4 4-1b 3/4 4-1b 3/4 4-1d 3/4 4-1d 3/4 4-1e 3/4 4-1e 3/4 4-1f 3/4 4-1f 3/4 8-5 3/4 8-5 3/4 8-7 3/4 8-7 3/4 8-10 3/4 8-10 3/4 9-1 3/4 9-1 3/4 9-2 3/4 9-2 3/4 9-8 3/4 9-8 3/4 9-8a 3/4 9-8a 3/4 9-8b 3/4 9-8b
3/4 9-8c B 3/4 4-1d B 3/4 4-1d
B 3/4 4-1e B 3/4 8-1o B 3/4 8-1o B 3/4 8-1p B 3/4 8-1p B 3/4 9-1 B 3/4 9-1 B 3/4 9-2a B 3/4 9-2a B 3/4 9-2b B 3/4 9-2b
DOMINION NUCLEAR CONNECTICUT, INC.
DOCKET NO. 50-423 MILLSTONE POWER STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 230 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 March 9, 2005, as supplemented on July 7, 2005, 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. 230, 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 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Darrell J. Roberts, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: June 28, 2006
ATTACHMENT TO LICENSE AMENDMENT NO. 230 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 xv xv 3/4 3-6 3/4 3-6 3/4 3-82 3/4 3-82 3/4 4-2 3/4 4-2
3/4 4-2a 3/4 4-3 3/4 4-3 3/4 4-4 3/4 4-4 3/4 4-5 3/4 4-5 3/4 4-5a 3/4 4-5a 3/4 4-6 3/4 4-6 3/4 8-10 3/4 8-10 3/4 8-15 3/4 8-15 3/4 8-18 3/4 8-18 3/4 8-18a 3/4 8-18a 3/4 9-1 3/4 9-1 3/4 9-2 3/4 9-2 3/4 9-8 3/4 9-8 3/4 9-9 3/4 9-9 B 3/4 3-2 B 3/4 3-2 B 3/4 3-9 B 3/4 3-9 B 3/4 4-1f B 3/4 4-1f B 3/4 8-1c B 3/4 8-1c B 3/4 9-1 B 3/4 9-1 B 3/4 9-1a B 3/4 9-1a
B 3/4 9-1b B 3/4 9-3 B 3/4 9-3 B 3/4 9-4 B 3/4 9-4 B 3/4 9-6 B 3/4 9-6 B 3/4 9-7 B 3/4 9-7
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 293 AND 230 TO 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 March 9, 2005, as supplemented by letter dated July 7, 2005, (Agencywide Documents Access and Management System (ADAMS) accession numbers ML050770238 and ML051920247, respectively) Dominion Nuclear Connecticut, Inc. (the 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 make various changes to the TSs to incorporate wording related to the reactor coolant system, electrical power system and refueling operations to provide operational flexibility during mode changes or addition of coolant during shutdown operations. The proposed changes would limit the introduction of positive reactivity so that the TSs shutdown margin (SDM) and refueling boron concentration limits will be maintained.
Associated changes to the TS Bases are also included.
The supplement dated July 7, 2005, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the NRC staffs original proposed no significant hazards consideration determination as published in the Federal Register on May 24, 2005 (70 FR 29788).
2.0 REGULATORY EVALUATION
The proposed licensee changes adopt NRC-approved generic changes in the industrys Technical Specification Task Force Change Traveler (TSTF)-286, Revision 2, that were approved for incorporation into TSs by the NRC staff in a letter dated July 6, 2000. This TSTF revises the TS Required Actions that address suspension of operations involving positive reactivity additions, and also revises several limiting condition of operation (LCO) notes that address prevention of operations involving a reduction in reactor coolant system (RCS) boron concentration. The revisions limit the introduction into the RCS of reactivity that would be more positive than that necessary to meet the required SDM or refueling boron concentration, as applicable. TSTF-286 provides a model for licensees seeking to revise their plant TSs and, thus, clarify the limits on the introduction of reactivity such that the required SDM or refueling boron concentration will be satisfied.
The NRC staff has previously approved the type of changes addressed by TSTF-286 for other plants on a plant-specific basis. The previous approvals include, but are not limited to, H.B. Robinson, Unit 2, dated March 14, 2001 (ADAMS Accession No. ML010810282);
Callaway, Unit 1, dated May 1, 2002 (ADAMS Accession No. ML020220051); Wolf Creek,
dated July 29, 2002 (ADAMS Accession No. ML021290254); Catawba, Units 1 and 2, dated July 29, 2003 (ADAMS Accession No. ML032110122); and McGuire, Units 1 and 2, dated July 29, 2003 (ADAMS Accession No. ML032110073).
3.0 TECHNICAL EVALUATION
TSTF-286, Revision 2, approved the requested change in a generic manner, i.e., it is acceptable if the plant-specific conditions allow the implementation of the change. MPS2 is a Combustion Engineering (CE) plant, while MPS3 is a Westinghouse (W) plant. In the following evaluation, application of TSTF-286, Revision 2, will be examined for each Millstone unit.
3.1. MPS2 TS 3.4.1.2, Hot Standby
! Note a, replace: ... reduction of the Reactor Coolant System boron concentration ...
with ... introduction of coolant into the RCS with boron concentration less than required to meet the SDM of LCO 3.1.1.1 ...
Action b, replace: ... all operations involving a reduction of boron concentration of the Reactor Coolant System ... with ... operations that would cause introduction of coolant into the RCS with boron concentration less than required to meet the SDM of LCO 3.1.1.1 ...
TS 3.4.1.3, Hot Shutdown
! Note 1.a, replace: ... reduction of the Reactor Coolant System boron concentration ...
with ... introduction of coolant into the RCS with boron concentration less than required to meet the SDM of LCO 3.1.1.1 ...
Action c, replace: ... all operations involving a reduction in Reactor Coolant System boron concentration ... with ... operations that would cause introduction of coolant into the RCS with boron concentration less than required to meet SDM of 3.1.1.1 ...
TS 3.4.1.4, Cold Shutdown - Reactor Coolant Loops Filled
! Note 2.a, replace: ... reduction of the Reactor Coolant System boron concentration ...
and Action b, replace: ... all operations involving a reduction in Reactor Coolant System boron concentration ... with ... operations that would cause introduction of coolant into the RCS with boron concentration less than required to meet the SDM of LCO 3.1.1.1 ...
TS 3.4.1.5, Cold Shutdown - Reactor Coolant System Loops not Filled
! Note 2.a, replace: ... reduction of the Reactor Coolant System boron concentration ...
with ... introduction of coolant into the RCS with boron concentration less than required to meet the SDM of LCO 3.1.1.1 ...
Action b, replace: ... all operations involving a reduction in Reactor Coolant System boron concentration ... with ... operations that would cause introduction of coolant into the RCS with boron concentration less than required to meet the SDM of LCO 3.1.1.1 ...
The proposed changes in the notes in TSs 3.4.1.2, 3.4.1.3, 3.4.1.4 and 3.4.1.5 agree with the wording and intent of TSTF-286, Revision 2 that allows the introduction of coolant with lower boron concentration but greater than that required by the shutdown margin specified in TS 3.1.1.1, Shutdown Margin. For example, Note ?a to TS 3.4.1.2 now reads: No operations are permitted that would cause introduction of coolant into the RCS with boron concentration less than required to meet the SDM of LCO 3.1.1.1. The same holds true for the action statements. Therefore, these changes are acceptable.
TS 3.8.1.2, A.C. Sources, TS 3.8.2.2, A.C. Distribution, TS 3.8.2.4, D.C. Distribution TS 3.8.3.2 Onsite Power Distribution
! Shutdown Action statements, replace: ... or positive reactivity changes, or ... with ...
and positive reactivity additions that could result in loss of required SDM or boron concentration, and...
The proposed changes above agree with the wording and intent of TSTF-286-A, Revision 2 that permits operations introducing positive reactivity additions but prohibits the temperature change or overall boron concentration from decreasing below that required to maintain the specified SDM. Therefore, these changes are acceptable.
TS 3.9.1, Boron Concentrations
! Action statement, replace: ... or positive reactivity changes ... with ... and positive reactivity additions ...
The proposed change in the Action statement agrees with the wording in TSTF-286, Revision 2.
The statement allows positive reactivity addition from temperature fluctuations or inventory additions provided that the overall reactivity changes (when accounting for boron addition) maintain the required SDM. Therefore, these changes are acceptable.
TS 3.9.2, Instrumentation
! Action a, replace: ... or positive reactivity changes ... with ... and operations that would cause introduction of coolant into the RCS with boron concentrations less than required to meet the boron concentrations of LCO 3.9.1 ...
The proposed change in the Action statement agrees with the wording in TSTF-286, Revision 2.
The Action statement specifies the steps to be taken should one or more source range flux monitors not be operable. The statement allows positive reactivity addition from temperature fluctuations or inventory additions provided that the overall reactivity changes maintain the required SDM. Therefore, this change is acceptable.
TS 3.9.8.1, Shutdown Cooling and Coolant Recirculation - High Water Level
! Note 1, replace: ... a reduction in Reactor Coolant System boron concentration with
... introduction of coolant into the Reactor Coolant System with boron concentration less than that required to meet the minimum required boron concentration of LCO 3.9.1.
! Action a, replace: ... all operations involving a reduction in Reactor Coolant System boron concentration ... with ... operations that would cause introduction of coolant into the RCS with boron concentration less than required to meet the boron concentration of LCO 3.9.1.
The proposed changes in Note 1 and Action a, agree with the wording in TSTF-286, Revision 2.
The statements allow positive reactivity addition with lower boron concentration provided that the overall reactivity changes maintain the required SDM. Therefore, these changes are acceptable.
TS 3.9.8.2, Shutdown Cooling and Coolant Recirculation - Low Water Level
! Action b1, replace: ... all operations involving a reduction in Reactor Coolant System boron concentration ... with ... operations that would cause introduction of coolant into the RCS with boron concentration less than required to meet the boron concentration of LCO 3.9.1.
The proposed change in Action b1, agrees with the wording in TSTF-286, Revision 2. The statement allows positive reactivity addition with lower boron concentration provided that the overall reactivity changes maintain the required SDM. Therefore, this change is acceptable.
3.2 MPS3 TS 3.3.1, Table 3.3-1, Reactor Trip System Instrumentation
! Action 4, insert note prior to Action 4: Limited plant cooldown or boron dilution is allowed provided the change is accounted for in the calculated SDM.
The proposed note prior to Action 4, agrees with the wording in TSTF-286, Revision 2. The statement allows operations introducing positive reactivity additions but prohibits the overall boron concentration from decreasing below the specified SDM value. Therefore, this change is acceptable.
TS 3.3.5, Instrumentation - Shutdown Margin Monitor Action b, insert note for Action b: Plant temperature changes are allowed provided the temperature is accounted for the calculated SDM.
The proposed note for Action b, agrees with the wording in TSTF-286, Revision 2. The statement allows operations introducing positive reactivity additions but prohibits the overall boron concentration from decreasing below the specified SDM value. Therefore, this change is acceptable.
TS 3.3.5, Instrumentation - Shutdown Margin Monitor
! Action b, replace: ... positive reactivity changes ... with ... positive reactivity additions The proposed note for Action b, agrees with the wording in TSTF-286, Revision 2. The statement allows operations introducing positive reactivity additions but prohibits the overall boron concentration from decreasing below the specified SDM value. Therefore, this change is acceptable.
TS 3.4.1, Reactor Coolant System - Coolant Loops and Coolant Circulation TS 3.4.1.2, Hot Standby Note *(1), TS 3.4.1.3, Hot Shutdown Note *(1), TS 3.4.1.4.1, Cold Shutdown - Loops Filled, Note *a.(1), TS 3.4.1.4.2, Cold Shutdown - Loops not Filled, Note**(1)
! Replace: ... dilution of the Reactor Coolant system boron concentration ... with
... introduction of coolant into the RCS with boron concentration less than required to meet SDM of LCO 3.1.1.1.2 ...
TS 3.4.1.2, Hot Standby Action c, TS 3.4.1.3, Hot Shutdown Action c, TS 3.4.1.4.1, Cold Shutdown - Loops Filled, Action b, TS 3.4.1.4.2, Cold Shutdown - Loops not Filled, Action b
! Replace: ... all operations involving a reduction in boron concentration of the Reactor Coolant System ... with ... operation that would cause introduction of coolant into the RCS with boron concentration less than that required to meet SDM of LCO 3.1.1.1.2 ...
The proposed changes for the notes and actions agree with the wording in TSTF-286, Revision 2. The notes allow the introduction of coolant with lower boron concentration but greater than the minimum required by the SDM specified in TS 3.1.1.1.2. The action statements specify steps to be taken should one or more coolant loops not be operable.
Therefore, these changes are acceptable.
TS 3.8.1.2, A.C. Sources - Shutdown, Action Statement, TS 3.8.2.2, D.C. Sources - Shutdown
! Action statement, replace: ... positive reactivity changes ... with ... positive reactivity additions that could result in loss of required SDM or boron concentration ...
The wording change described above is consistent with TSTF-286, Revision 2. The action statements in this section specify steps to be taken should one or more electrical systems not be operable. The proposed change permits positive reactivity additions but prohibit boron concentration below that required to maintain SDM. Therefore, this change is acceptable.
TS 3.9.1.1, Boron Concentration
! Action a, replace: ... or positive reactivity changes ... with ... and positive reactivity additions ...
The wording change described above is consistent with TSTF-286, Revision 2. The proposed change for the action agrees with the wording in TSTF-286, Revision 2. Therefore, this change is acceptable.
TS 3.9.2, Instrumentation
! Action a, replace: ... or positive changes ... with ... and operations that would cause introduction of coolant into the RCS with boron concentration less than required to meet the boron concentration of LCO 3.9.1.1 ....
This action statement specifies steps to be taken should one or more source range flux monitors not be operable. The wording change described above is consistent with TSTF-286, Revision 2. Therefore, this change is acceptable.
TS 3.9.8.1, Residual Heat Removal and Coolant Circulation - High Water Level Note *, and TS 3.9.8.2, Residual Heat Removal and Coolant Circulation - Low Water Level Note*
! Replace: ... dilution of the RCS boron concentration ... with ... introduction of coolant into the RCS with boron concentration less than required to meet the boron concentration of LCO 3.9.1.1.
The notes allow the introduction of coolant with boron concentration greater than that specified in LCO 3.9.1.1. The proposed change for the notes agrees with the wording in TSTF-286, Revision 2. Therefore, these changes are acceptable.
TS 3.9.8.1, Residual Heat Removal and Coolant Circulation - High Water Level Action Statement, and TS 3.9.8.2, Residual Heat Removal and Coolant Circulation - Low Water Level Action Statement b.
! Action statement, replace: ... all operations involving a reduction in boron concentration of the Reactor Coolant System ... with ... operations that would cause introduction of coolant in the RCS with boron concentration less than required to meet the boron concentration in LCO 3.9.1.1 ...
The action statements specify steps to be taken should one or more shutdown cooling trains not be operable. The proposed change permits operations introducing positive reactivity
additions but prohibits temperature changes to decrease overall boron concentration below that specified in TS 3.9.1.1. Therefore, these changes are acceptable.
4.0
SUMMARY
The NRC staff has reviewed the licensees application with the supporting documentation.
Based on its review, the NRC staff concludes that the proposed TS changes are acceptable because the proposed Notes and Required Actions limit the introduction into the RCS of coolant with a boron concentration that is less than that required to meet the required SDM or refueling boron concentration. These changes are consistent with the approved TSTF-286, Revision 2, taking into account the plant-specific design differences of MPS2 and MPS3. The justification for TSTF-286, Revision 2, is applicable to MPS2 and MPS3 and continues to ensure that the required minimum SDM and boron concentration to preclude inadvertent criticality are met. Since the licensees proposed amendments will still require the minimum SDM and boron concentration to be maintained, the NRC staff concludes that the proposed amendments are acceptable.
5.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Connecticut State official was notified of the proposed issuance of the amendments. The State official had no comments.
6.0 ENVIRONMENTAL CONSIDERATION
The amendments change requirements with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. 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 29788). 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: L. Lois D. Nguyen Date: June 28, 2006
Millstone Power Station, Unit Nos. 2 and 3 cc:
Lillian M. Cuoco, Esquire Mr. Evan W. Woollacott Senior Counsel Co-Chair Dominion Resources Services, Inc. Nuclear Energy Advisory Council Building 475, 5th Floor 128 Terrys Plain Road Rope Ferry Road Simsbury, CT 06070 Waterford, CT 06385 Mr. Joseph Roy Edward L. Wilds, Jr., Ph.D. Director of Operations Director, Division of Radiation Massachusetts Municipal Wholesale Department of Environmental Electric Company Protection P.O. Box 426 79 Elm Street Ludlow, MA 01056 Hartford, CT 06106-5127 Mr. David W. Dodson Regional Administrator, Region I Licensing Supervisor U.S. Nuclear Regulatory Commission Dominion Nuclear Connecticut, Inc.
475 Allendale Road Building 475, 5th Floor King of Prussia, PA 19406 Roper Ferry Road Waterford, CT 06385 First Selectmen Town of Waterford Mr. J. Alan Price 15 Rope Ferry Road Site Vice President Waterford, CT 06385 Dominion Nuclear Connecticut, Inc.
Building 475, 5th Floor Charles Brinkman, Director Rope Ferry Road Washington Operations Nuclear Services Waterford, CT 06385 Westinghouse Electric Company 12300 Twinbrook Pkwy, Suite 330 Mr. Chris L. Funderburk Rockville, MD 20852 Director, Nuclear Licensing and Operations Support Senior Resident Inspector Innsbrook Technical Center Millstone Power Station 5000 Dominion Boulevard c/o U.S. Nuclear Regulatory Commission Glen Allen, VA 23060-6711 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