ML16159A259
| ML16159A259 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 09/06/2016 |
| From: | John Tappert Division of Decommissioning, Uranium Recovery and Waste Programs |
| To: | Dominion Nuclear Connecticut |
| References | |
| CAC L53121 | |
| Download: ML16159A259 (9) | |
Text
DOMINION NUCLEAR CONNECTICUT, INC., ET AL.
DOCKET NO. 50-245 MILLSTONE POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 117 License No. DPR-21
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application (Agencywide Documents Access and Management System Accession No. ML14093A028) dated March 28, 2014 and supplement (ADAMS Accession No. ML16153A234) dated May 23, 2016 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in Title 10 of the Code of Federal Regulations (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.
Enclosure 1
- 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. 117, 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/
John R. Tappert, Director Division of Decommissioning, Uranium Recovery and Waste Programs Office of Nuclear Material Safety and Safeguards
Attachment:
Changes to the License and Technical Specifications Date of Issuance:
ATTACHMENT TO LICENSE AMENDMENT NO. 117 FACILITY OPERATING LICENSE NO. DPR-21 DOCKET NO. 50-245 Replace the following page of the 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 3 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 Table of Contents i 5.0-5 5.0-5 5.0-7 5.0-7 5.0-8 5.0-8 5.0-9 5.0-9
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 117, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3) Deleted.
(4) Physical Protection The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which may contain Safeguards Information protected under 10 CFR 73.21, are entitled:
"Millstone Power Station Physical Security Plan," with revisions submitted through March 29, 1988; "Millstone Power Station Suitability, Training and Qualification Plan," with revisions submitted through July 21, 1986; and "Millstone Power Station Safeguards Contingency Plan," with revisions submitted through October 30, 1985. Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.
(5) On the closing date of the transfer of MP1 to DNC, DNC shall: 1) obtain from the Selling Owners of MP1 the decommissioni ng trust fund for MP1 in an amount no less than $268,300,000; and 2) receive a parent company guarantee pursuant to 10 CFR 50.75(e)(1)(iii)(B) (to be updated annually as required under 10 CFR 50.75(f)(1) and 50.82(a)(8)(iv), unless otherwise approved by the NRC) in an amount which, when combined with the decommissioning trust fund for MP1, equals a total of the site specific decommissioning funding cost as of the closing date of the transfer as estimated (in year 2000 dollars) in accordance with 10 CFR 50.82 (including the use of a 2 percent annual real rate of return as provided in 10 CFR 50.75(e)(1)(i)).
(6) The decommissioning trust agreement for Millstone, Unit No. 1 at the time the transfer of the unit to Dominion Nuclear Connecticut, Inc. is effected and thereafter, is subject to the following:
(a) The decommissioning trust agreement must be in a form acceptable to the NRC.
Amendment No. 117
PAGE i HAS BEEN INTENTIONALLY DELETED MILLSTONE UNIT 1 i License Amendment No. 117
Facility Staff Qualifications 5.3 ADMINISTRATIVE CONTROLS 5.3 Facility Staff Qualifications 5.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions. Exceptions to this requirement are specified in the Quality Assurance Program.
5.3.2 The operations manager or at least one operations middle manager shall be a CERTIFIED FUEL HANDLER.
MILLSTONE-UNIT 1 5.0-5 Amendment No. 117
Procedures 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Procedures 5.5.1 Written procedures shall be established, implemented, and maintained covering the following activities:
- a. The procedures applicable to the safe storage of irradiated fuel recommended in Appendix A of Regulatory Guide 1.33, February 1978;
- b. Fire Protection Program implementation;
- c. Cold Weather Operations;
- d. Quality Controls for effluent monitoring, using the guidance in Regulatory Guide 1.21, Rev. 1, June 1974;
- e. Liquid and gaseous radioactive effluent discharges from the unit for all operations involving offsite releases of radioactive effluents. These procedures shall specify the use of appropriate waste treatment utilizing the guidance provided in the REMODCM;
- f. Fuel handling operations;
- g. All programs specified in Specification 5.6, except for Section I.E.,
Radiological Environmental Monitoring of REMODCM, which is performed in accordance with Specifications 5.5.6 and 5.5.7.
- h. The designated manager, designated officer, or designated senior officer may designate specific procedures and programs, or classes of procedures and programs to be reviewed in accordance with the Station Qualified Reviewer Program in lieu of review by the FSRC. The review per the FSRC or Station Qualified Reviewer Program shall be in accordance with the Quality Assurance Program Topical Report.
5.5.2 Procedures listed in Specification 5.5.1, and changes thereto, shall be approved by the designated manager, or designated officer or by cognizant managers or directors who are designated as the Approval Authority by the designated manager, or designated officer as specified in administrative procedures. The Approval Authority for each procedure and program or class of procedure and program shall be specified in administrative procedures.
(continued)
Millstone - Unit 1 5.0-7 Amendment No. 117
Procedures 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Procedures (continued) 5.5.2 Each procedure of Specification 5.5.1, and changes thereto, shall be reviewed by the FSRC and shall be approved by the designated manager or designated officer, or be reviewed and approved in accordance with the Station Qualified Reviewer Program prior to implementation. Each procedure of Specification 5.5.1 shall be reviewed periodically as set forth in administrative procedures.
5.5.3 Temporary changes to procedures of Specification 5.5.1 above may be made provided:
- a. the intent of the original procedure is not altered;
- b. the change is approved by two members of the plant management staff, at least one of whom is a CERTIFIED FUEL HANDLER;
- c. the change is documented, reviewed by the FSRC or the Station Qualified Reviewer Program, as applicable, and approved by the designated manager, designated officer, or the Station Qualified Reviewer Program department manager within 14 days of implementation.
5.5.4 All procedures and procedure changes required for the Radiological Environmental Monitoring Program (REMP) of Specification 5.6.1 shall be reviewed by an individual (other than the author) from the organization responsible for the REMP and approved by appropriate supervision.
5.5.5 Temporary changes may be made for the Radiological Environmental Monitoring Program provided the intent of the original procedure is not altered and the change is documented and reviewed by an individual (other than the author) from the organization responsible for the REMP within 14 days of implementation.
(continued)
Millstone - Unit 1 5.0-8 Amendment No. 117
Procedures 5.6 5.0 ADMINISTRATIVE CONTROLS The following programs shall be established, implemented and maintained.
5.6.1 Radiological Effluent Monitoring and Offsite Dose Calculation Manual (REMODCM)
- a. The REMODCM shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip set points, and in the conduct of the radiological environmental monitoring program; and
- b. The REMODCM shall also contain the radioactive effluent controls and radiological environmental monitoring activities and descriptions of the information that should be included in the Annual Radiological Environmental Operating, and Radioactive Effluent Release, reports required by Specification 5.7.2 and Specification 5.7.3.
Licensee initiated changes to the REMODCM:
- a. Shall be documented and records of reviews performed shall be retained. This documentation shall contain:
- 1) sufficient information to support the change(s) together with the appropriate analyses or evaluations justifying the change(s), and
- 2) a determination that the change(s) will maintain the level of radioactive effluent control required by 10CFR20.1302, 40CFR Part 190, 10 CFR 50.36a and Appendix I to 10CFR50, and not adversely impact the accuracy or reliability of effluent, dose, or set point calculations;
- b. Shall become effective after review and acceptance by FSRC and the approval of the designated officer; and (continued)
Millstone - Unit 1 5.0-9 Amendment No. 117
DOMINION NUCLEAR CONNECTICUT, INC., ET AL.
DOCKET NO. 50-245 MILLSTONE POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 117 License No. DPR-21
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application (Agencywide Documents Access and Management System Accession No. ML14093A028) dated March 28, 2014 and supplement (ADAMS Accession No. ML16153A234) dated May 23, 2016 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in Title 10 of the Code of Federal Regulations (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.
Enclosure 1
- 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. 117, 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/
John R. Tappert, Director Division of Decommissioning, Uranium Recovery and Waste Programs Office of Nuclear Material Safety and Safeguards
Attachment:
Changes to the License and Technical Specifications Date of Issuance:
ATTACHMENT TO LICENSE AMENDMENT NO. 117 FACILITY OPERATING LICENSE NO. DPR-21 DOCKET NO. 50-245 Replace the following page of the 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 3 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 Table of Contents i 5.0-5 5.0-5 5.0-7 5.0-7 5.0-8 5.0-8 5.0-9 5.0-9
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 117, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3) Deleted.
(4) Physical Protection The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which may contain Safeguards Information protected under 10 CFR 73.21, are entitled:
"Millstone Power Station Physical Security Plan," with revisions submitted through March 29, 1988; "Millstone Power Station Suitability, Training and Qualification Plan," with revisions submitted through July 21, 1986; and "Millstone Power Station Safeguards Contingency Plan," with revisions submitted through October 30, 1985. Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.
(5) On the closing date of the transfer of MP1 to DNC, DNC shall: 1) obtain from the Selling Owners of MP1 the decommissioni ng trust fund for MP1 in an amount no less than $268,300,000; and 2) receive a parent company guarantee pursuant to 10 CFR 50.75(e)(1)(iii)(B) (to be updated annually as required under 10 CFR 50.75(f)(1) and 50.82(a)(8)(iv), unless otherwise approved by the NRC) in an amount which, when combined with the decommissioning trust fund for MP1, equals a total of the site specific decommissioning funding cost as of the closing date of the transfer as estimated (in year 2000 dollars) in accordance with 10 CFR 50.82 (including the use of a 2 percent annual real rate of return as provided in 10 CFR 50.75(e)(1)(i)).
(6) The decommissioning trust agreement for Millstone, Unit No. 1 at the time the transfer of the unit to Dominion Nuclear Connecticut, Inc. is effected and thereafter, is subject to the following:
(a) The decommissioning trust agreement must be in a form acceptable to the NRC.
Amendment No. 117
PAGE i HAS BEEN INTENTIONALLY DELETED MILLSTONE UNIT 1 i License Amendment No. 117
Facility Staff Qualifications 5.3 ADMINISTRATIVE CONTROLS 5.3 Facility Staff Qualifications 5.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions. Exceptions to this requirement are specified in the Quality Assurance Program.
5.3.2 The operations manager or at least one operations middle manager shall be a CERTIFIED FUEL HANDLER.
MILLSTONE-UNIT 1 5.0-5 Amendment No. 117
Procedures 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Procedures 5.5.1 Written procedures shall be established, implemented, and maintained covering the following activities:
- a. The procedures applicable to the safe storage of irradiated fuel recommended in Appendix A of Regulatory Guide 1.33, February 1978;
- b. Fire Protection Program implementation;
- c. Cold Weather Operations;
- d. Quality Controls for effluent monitoring, using the guidance in Regulatory Guide 1.21, Rev. 1, June 1974;
- e. Liquid and gaseous radioactive effluent discharges from the unit for all operations involving offsite releases of radioactive effluents. These procedures shall specify the use of appropriate waste treatment utilizing the guidance provided in the REMODCM;
- f. Fuel handling operations;
- g. All programs specified in Specification 5.6, except for Section I.E.,
Radiological Environmental Monitoring of REMODCM, which is performed in accordance with Specifications 5.5.6 and 5.5.7.
- h. The designated manager, designated officer, or designated senior officer may designate specific procedures and programs, or classes of procedures and programs to be reviewed in accordance with the Station Qualified Reviewer Program in lieu of review by the FSRC. The review per the FSRC or Station Qualified Reviewer Program shall be in accordance with the Quality Assurance Program Topical Report.
5.5.2 Procedures listed in Specification 5.5.1, and changes thereto, shall be approved by the designated manager, or designated officer or by cognizant managers or directors who are designated as the Approval Authority by the designated manager, or designated officer as specified in administrative procedures. The Approval Authority for each procedure and program or class of procedure and program shall be specified in administrative procedures.
(continued)
Millstone - Unit 1 5.0-7 Amendment No. 117
Procedures 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Procedures (continued) 5.5.2 Each procedure of Specification 5.5.1, and changes thereto, shall be reviewed by the FSRC and shall be approved by the designated manager or designated officer, or be reviewed and approved in accordance with the Station Qualified Reviewer Program prior to implementation. Each procedure of Specification 5.5.1 shall be reviewed periodically as set forth in administrative procedures.
5.5.3 Temporary changes to procedures of Specification 5.5.1 above may be made provided:
- a. the intent of the original procedure is not altered;
- b. the change is approved by two members of the plant management staff, at least one of whom is a CERTIFIED FUEL HANDLER;
- c. the change is documented, reviewed by the FSRC or the Station Qualified Reviewer Program, as applicable, and approved by the designated manager, designated officer, or the Station Qualified Reviewer Program department manager within 14 days of implementation.
5.5.4 All procedures and procedure changes required for the Radiological Environmental Monitoring Program (REMP) of Specification 5.6.1 shall be reviewed by an individual (other than the author) from the organization responsible for the REMP and approved by appropriate supervision.
5.5.5 Temporary changes may be made for the Radiological Environmental Monitoring Program provided the intent of the original procedure is not altered and the change is documented and reviewed by an individual (other than the author) from the organization responsible for the REMP within 14 days of implementation.
(continued)
Millstone - Unit 1 5.0-8 Amendment No. 117
Procedures 5.6 5.0 ADMINISTRATIVE CONTROLS The following programs shall be established, implemented and maintained.
5.6.1 Radiological Effluent Monitoring and Offsite Dose Calculation Manual (REMODCM)
- a. The REMODCM shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip set points, and in the conduct of the radiological environmental monitoring program; and
- b. The REMODCM shall also contain the radioactive effluent controls and radiological environmental monitoring activities and descriptions of the information that should be included in the Annual Radiological Environmental Operating, and Radioactive Effluent Release, reports required by Specification 5.7.2 and Specification 5.7.3.
Licensee initiated changes to the REMODCM:
- a. Shall be documented and records of reviews performed shall be retained. This documentation shall contain:
- 1) sufficient information to support the change(s) together with the appropriate analyses or evaluations justifying the change(s), and
- 2) a determination that the change(s) will maintain the level of radioactive effluent control required by 10CFR20.1302, 40CFR Part 190, 10 CFR 50.36a and Appendix I to 10CFR50, and not adversely impact the accuracy or reliability of effluent, dose, or set point calculations;
- b. Shall become effective after review and acceptance by FSRC and the approval of the designated officer; and (continued)
Millstone - Unit 1 5.0-9 Amendment No. 117