ML030560496
| ML030560496 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 05/15/2003 |
| From: | Nerses V NRC/NRR/DLPM/LPD1 |
| To: | Price J Dominion Nuclear Connecticut |
| Nerses V, NRR//DLPM, 415-1484 | |
| Shared Package | |
| ML031360576 | List: |
| References | |
| TAC MB5087, TAC MB5088 | |
| Download: ML030560496 (17) | |
Text
May 15, 2003 Mr. J. A. Price Site Vice President - Millstone c/o Mr. David W. Dodson Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385
SUBJECT:
MILLSTONE POWER STATION, UNIT NOS. 2 AND 3 - ISSUANCE OF AMENDMENTS RE: CHANGES TO SELECTED RADIOLOGICAL-RELATED TECHNICAL SPECIFICATIONS (TAC NOS. MB5087AND MB5088 )
Dear Mr. Price:
The Commission has issued the enclosed Amendment Nos. 276 and 215 to Facility Operating License Nos. DPR-65 and NPF-49 for the Millstone Power Station, Unit Nos. 2 (MP2) and 3 (MP3), in response to your application dated May 13, 2002. It should be noted that this application also requested an amendment for Millstone Power Station, Unit No. 1 (MP1). The MP1 amendment was issued by separate letter.
The amendments revise the Technical Specifications (TSs) changing selected MP2 and MP3 radiological-related TSs. These changes are due to the revision to Part 20 of Title 10 of the Code of Federal Regulations 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/
Victor Nerses, Sr. Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-336 and 50-423
Enclosures:
- 1. Amendment No. 276 to DPR-65
- 2. Amendment No. 215 to NPF-49
- 3. Safety Evaluation cc w/encls: See next page
May 15, 2003 Mr. J. A. Price Site Vice President - Millstone c/o Mr. David W. Dodson Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385
SUBJECT:
MILLSTONE POWER STATION, UNIT NOS. 2 AND 3 - ISSUANCE OF AMENDMENTS RE: CHANGES TO SELECTED RADIOLOGICAL-RELATED TECHNICAL SPECIFICATIONS (TAC NOS. MB5087AND MB5088 )
Dear Mr. Price:
The Commission has issued the enclosed Amendment Nos. 276 and 215 to Facility Operating License Nos. DPR-65 and NPF-49 for the Millstone Power Station, Unit Nos. 2 (MP2) and 3 (MP3), in response to your application dated May 13, 2002. It should be noted that this application also requested an amendment for Millstone Power Station, Unit No. 1 (MP1). The MP1 amendment was issued by separate letter.
The amendments revise the Technical Specifications (TSs) changing selected MP2 and MP3 radiological-related TSs. These changes are due to the revision to Part 20 of Title 10 of the Code of Federal Regulations 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/
Victor Nerses, Sr. Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-336 and 50-423
Enclosures:
- 1. Amendment No. 276 to DPR-65
- 2. Amendment No. 215 to NPF-49
- 3. Safety Evaluation cc w/encls: See next page DISTRIBUTION:
Public RidsOgcRp PD1-2 Reading RidsAcrsAcnwMailCenter RidsNrrDlpmLpdi (SRichards)
RidsNrrDrip (RDennig)
RidsNrrDlpmLpdi-2 (JClifford)
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RidsNrrPMREnnis WBeckner (NRR/DRIP/RORP)
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RidsNrrLACRaynor BMcDermott (RGN-1/DRP/PB6)
RidsRgn1MailCenter (BPlatchek)
- See previous concurrence ADAMS Accession Numbers: Letter: ML030560496, TSs: ML, Package: ML OFFICE PDI-2/PM PDI-2/PM PDI-2/LA IEHB/SC*
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OGC*
PDI-2/SC NAME VNerses REnnis CRaynor RPedersen for KGibson RDennig SCole SRichards for JClifford DATE 4/30/03 4/28/03 4/30/03 4/1/03 4/3/03 4/22/03 5/1/03 OFFICIAL RECORD COPY
DOMINION NUCLEAR CONNECTICUT, INC., ET AL.
DOCKET NO. 50-336 MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 276 License No. DPR-65
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by the applicant dated May 13, 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. 276, 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 120 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA by SRichards for/
James W. Clifford, 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: May 15, 2003
ATTACHMENT TO LICENSE AMENDMENT NO. 276 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 XVII XVII 6-17 6-17 6-18 6-18 6-20 6-20 6-21 6-21 6-22 6-22 6-23 6-23 6-26 6-26 6-27 6-27 6-28 6-28
DOMINION NUCLEAR CONNECTICUT, INC., ET AL.
DOCKET NO. 50-423 MILLSTONE NUCLEAR POWER STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 215 License No. NPF-49
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by the applicant dated May 13, 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. 215, 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 120 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA by SRichards for/
James W. Clifford, 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: May 15, 2003
ATTACHMENT TO LICENSE AMENDMENT NO. 215 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 xix xix 6-18 6-18 6-19 6-19 6-21 6-21 6-22 6-22 6-23 6-23 6-25 6-25 6-26 6-26 6-27 6-27
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 276 TO FACILITY OPERATING LICENSE NO. DPR-65 AND AMENDMENT NO. 215 TO FACILITY OPERATING LICENSE NO. NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION, UNIT NOS. 2 AND 3 DOCKET NOS. 50-336 AND 50-423
1.0 INTRODUCTION
By letter dated May 13, 2002, Dominion Nuclear Connecticut, Inc. (licensee or DNC), submitted a license amendment request to amend the Millstone Power Station, Unit Nos. 2 (MP2) and 3 (MP3) Technical Specifications (TSs). The licensee requested the Nuclear Regulatory Commissions (NRC) approval to make changes to the following TSs:
Occupational Radiation Exposure Report (Unit No. 2 - TS 6.9.1.5.a and Unit No. 3 -
TS 6.9.1.2.a)
High Radiation Area Specification (Unit Nos. 2 and 3 - TSs 6.12.1 and 6.12.2)
Radioactive Effluent Controls Program (Unit No. 2 - TS 6.20 and Unit No. 3 - TS 6.15)
2.0 REGULATORY EVALUATION
Title 10 of the Code of Federal Regulations (10 CFR), Section 50.36, Technical Specifications, specifies the categories of items to be included in the plant TSs. These include safety limits, limiting safety system settings, limiting control settings, limiting conditions for operation, surveillance requirements, design features, and administrative controls. In addition, 10 CFR Part 20 and Appendix I of 10 CFR Part 50 provide requirements for radiological control.
Over the years, the NRC staff (staff) has published a number of guidance documents regarding TS requirements related to radiological control. These guidance documents provide such information as methods acceptable to the staff for implementing specific parts of the Commissions regulations. These include the following:
Regulatory Guide 8.38, Control of Access to High and Very High Radiation Areas in Nuclear Power Plants,
Generic Letter (GL) 89-01, Implementation of Programmatic Controls for Radiological Effluent Technical Specifications (RETS) in the Administrative Controls Section of the Technical Specifications and the Relocation of Procedural Details of RETS to the Offsite Dose Calculation Manual or to the Process Control Program,
NUREG-1301, Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors,
GL 95-01, Relocation of Selected Technical Specification Requirements Related to Instrumentation.
In addition to the above, the staff issued guidance to improve TSs. This guidance is located in:
NUREG-1431, Revision 2, Standard Technical Specifications, Westinghouse Plants,
NUREG-1432, Revision 2, Standard Technical Specifications, Combustion Engineering Plants
3.0 TECHNICAL EVALUATION
The staff has reviewed the licensees justification for the proposed license amendment as described in Attachment 1 of the licensees application dated May 13, 2002. The detailed evaluation below will support the conclusion that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
3.1 MP2 - TS Section 6.9.1.5.a, and MP3 - TS Section 6.9.1.2.a, Occupational Radiation Exposure Report a.
For consistency with 10 CFR Part 20, the licensee has proposed the following changes:
1.
Clarification of the requirement for the annual tabulation of personnel receiving exposures greater than 100 mrems (Deep dose equivalent) by indicating it applies only to those for whom monitoring was required to be performed.
2.
Revision of the annual tabulation of personnel from those receiving exposures greater than 100 mrems/yr and their associated man-rem exposure to apply to those receiving an annual deep dose equivalent
>100 mrems and the associated collective deep dose equivalent (reported in person-rem).
3.
Addition of a sentence clarifying that the annual tabulation supplements the requirements of 10 CFR Part 20.2206.
4.
Change the term pocket dosimeter to pocket ionization chamber.
5.
State that dose assignments can be estimated using electronic dosimeters.
6.
Change the term whole body dose to deep dose equivalent to reflect current 10 CFR Part 20 terminology.
7.
Change the required submittal date from March 1 to April 30.
The proposed changes are in accordance with the guidance and methodology contained in RG 1.16, GL 89-01 and NUREG-1431 and NUREG-1432, and therefore, satisfy the requirements of 10 CFR Part 50. Therefore, the staff considers the proposed changes are acceptable.
b.
The Licensee has proposed to revise MP2 - TS Section 6.9.1.5.a, and MP3 -
TS Section 6.9.1.2.a to incorporate changes for readability and to align specifications among units. The licensee has proposed the following changes:
1.
Add the title Occupational Radiation Exposure Report to correspond with Unit No. 1 Permanently Defueled Technical Specifications Section 5.7.1.
2.
Add the footnote stating, A single submittal may be made for a multiple unit station. as a note after the title for consistency in format within the Administrative Controls section.
The proposed changes are administrative in nature and have no impact on safety. The proposed changes are acceptable.
3.2 MP2 - TS Section 6.9.1.4, and MP3 - TS Section 6.9.1.2, Annual Reports a.
The licensee has proposed the following changes:
1.
Revise the sentence which specifies the submittal date for annual reports to state, Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted in accordance with 10 CFR 50.4.
2.
Delete the second sentence stating The initial report shall be submitted prior to March 1 of the year following initial criticality., as this condition is no longer applicable.
3.
Add the following sentence to the end of each paragraph for the renumbered MP2 TS Sections 6.9.1.5.b, 6.9.1.5.c and 6.9.1.5.d, and Unit No. 3 TS Sections 6.9.1.2.b, 6.9.1.2.c, The report covering the previous calendar year shall be submitted prior to March 1 of each year.
The proposed changes are in accordance with the guidance and methodology contained in GL 89-01 and NUREG-1431 and NUREG-1432, and therefore, satisfy the requirements of 10 CFR Part 50. Therefore, the staff considers the proposed changes are acceptable.
4.
Renumber Unit No. 2 TS Section 6.9.1.5 Items b., c., and d., as 6.9.1.5.b, 6.9.1.5.c and 6.9.1.5.d, and renumber MP3 TS Sections 6.9.1.2 Items b. and c., as 6.9.1.2.b, 6.9.1.2.c.
5.
Move the respective specification number within the Unit No. 3 TS for the Annual Radiological Environmental Operating Report and the Radiological Effluent Release Report to the front of the respective title.
The proposed changes are administrative in nature and have no impact on safety. The proposed changes are acceptable.
3.3 MP2 and MP3 - TS Sections 6.12.1 and 6.12.2, High Radiation Area a.
The licensee has proposed to revise MP2 and MP3 TS 6.12 to incorporate changes for consistency with the current 10 CFR Part 20 by adopting the wording of the High Radiation Area specification from the current revision (Revision 2) of NUREG-1431 and NUREG-1432, so that each program will reflect identical wording of requirements.
The proposed changes are in accordance with the guidance and methodology contained in GL 89-01 and NUREG-1431 and NUREG-1432 and therefore, satisfy the requirements of 10 CFR Part 50. Therefore, the staff considers the proposed changes are acceptable.
b.
The licensee has proposed to move MP2 and MP3 TS Sections 6.11, Radiation Protection Program, and 6.12, High Radiation Area, to the same page immediately after TS Section 6.10, eliminating empty space on the intervening pages and to renumber the pages accordingly.
The proposed changes are administrative in nature and have no impact on safety. The proposed changes are acceptable.
3.4 Unit No. 2 - TS Section 6.20, and Unit No. 3 - TS Section 6.15, Radioactive Effluent Controls Program a.
The licensee proposed to revise MP2 - TS Section 6.20.b, and MP3 - TS Section 6.15.b, to clarify that the program includes limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming to ten times the concentration values in Appendix B, Table 2, Column 2 to 10 CFR Part 20.1001-20.2402.
b.
The licensee proposed to revise MP2 - TS Section 6.20.g, and MP3 - TS Section 6.15.g, to clarify that the program includes limitations on the dose rate resulting from radioactive material released in gaseous effluents from the site to areas at or beyond the site boundary.
c.
The licensee proposed to revise MP2 - TS Section 6.20.j, and MP3 - TS Section 6.15.j, to clarify that the program includes limitations on the annual dose or dose commitment to any member of the public, beyond the site boundary, due to releases of radioactivity and to radiation from uranium fuel cycle sources.
d.
The licensee proposed to add a new paragraph to MP2 - TS Section 6.20.j, and MP3 - TS Section 6.15.j, to reflect that the 25% extension of the surveillance interval provisions of Specification 3.0.2 are applicable to the Radiological Environmental Controls Program (RECP) surveillance frequency. The provisions of Specification 3.0.3, which indicate that compliance with the requirements to declare a Limiting Condition of Operation (LCO) not met, may be delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from the time of discovery (when time limits of the Action are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) to permit completion of the surveillance, will also be included.
The provisions of Standard Technical Specifications (STS) Surveillance Requirement (SR) 3.0.2 are applied to the RECP surveillance frequencies of Section 6.20.j (MP2) and Section 6.15.j (MP3) to allow for scheduling flexibility. SR 3.0.2 permits a 25% extension of the interval specified in the Frequency (31 days).
As applied to the 31-day Frequency of Section 6.20.j (MP2), and Section 6.15.j (MP3),
STS SR 3.0.3 would allow up to 31 days to complete the surveillance (dose calculation) if it is discovered that the surveillance was not performed within 38 days and 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> (the specified interval plus the 25% extension). Allowing 31 days to complete the cumulative dose and projected dose calculation for the current quarter/year is acceptable because it will have no affect on the outcome of the calculations and has no impact on the risk associated with plant operation. In addition, operating experience has shown that the calculated dose is usually well within limits. Thus, it is considered unlikely that a potential greater time interval between dose calculations will result in inadvertent effluent releases exceeding the specified limits.
Section 6.20.j (MP2) and Section 6.15.j (MP3) require the RECP, which is contained in the Radiological Effluent Monitoring and Offsite Dose Calculation Manual (REMODCM), to include remedial measures established in the event dose limits are exceeded. Therefore, delaying implementation of these remedial measures for 31 days from the time of discovery of a missed dose calculation is acceptable. In the event the calculations are not completed within the time limits allowed by SR 3.0.2 and SR 3.0.3, these specifications direct the licensee take the RECP remedial measures.
e.
The licensee proposed to revise MP2 TS Section 6.20.e, and MP3 TS Section 6.15.e, to clarify the wording to require projected dose contributions as directed by the methodology of the REMODCM.
The proposed changes are in accordance with the guidance and methodology contained in GL 89-01 and NUREG-1431 and NUREG-1432 and therefore, satisfy the requirements of 10 CFR Part 50. Therefore, the staff considers the proposed changes are acceptable.
3.5
SUMMARY
The staff has reviewed the licensees submittal, and based on our review discussed above, the staff finds the proposed changes to be acceptable.
4.0 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.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10)(ii). 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.
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 Contributor: A. Hayes Date: May 15, 2003
Millstone Power Station Units 2 and 3 cc:
Ms. L. M. Cuoco Senior Counsel Dominion Resources Services, Inc.
Rope Ferry Road Hartford, CT 06385 Edward L. Wilds, Jr., Ph.D.
Director, Division of Radiation Department of Environmental Protection 79 Elm Street Hartford, CT 06106-5127 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 First Selectmen Town of Waterford 15 Rope Ferry Road Waterford, CT 06385 Mr. W. R. Matthews Senior Vice President - Nuclear Operations Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385 Mr. Charles Brinkman, Manager 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 Mr. P. J. Parulis Manager - Nuclear Oversight Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385 Mr. John Markowicz Co-Chair Nuclear Energy Advisory Council 9 Susan Terrace Waterford, CT 06385 Mr. D. A. Smith Manager - Licensing Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385 Ms. Nancy Burton 147 Cross Highway Redding Ridge, CT 00870 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
Millstone Power Station Units 2 and 3 cc:
Mr. William D. Meinert Nuclear Engineer Massachusetts Municipal Wholesale Electric Company P.O. Box 426 Ludlow, MA 01056 Mr. S. E. Scace Assistant to the Site Vice President 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 Mr. A. J. Jordan, Jr.
Director - Nuclear Engineering Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385 Mr. S. P. Sarver Director - Nuclear Station Operations and Maintenance Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385