ML030570728
| ML030570728 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 02/27/2003 |
| From: | Pulsifer R NRC/NRR/DLPM/LPD1 |
| To: | Thayer J Entergy Nuclear Vermont Yankee |
| Pulsifer R M, NRR/DLPM, 415-3016 | |
| References | |
| TAC MB6925 | |
| Download: ML030570728 (13) | |
Text
February 27, 2003 Mr. Jay K. Thayer Site Vice President - Vermont Yankee Entergy Nuclear Vermont Yankee, LLC P.O. Box 0500 185 Old Ferry Road Brattleboro, VT 05302-0500
SUBJECT:
VERMONT YANKEE NUCLEAR POWER STATION - ISSUANCE OF AMENDMENT RE: GENERIC POSITION TITLES AND OTHER ADMINISTRATIVE CHANGES (TAC NO. MB6925)
Dear Mr. Thayer:
The Commission has issued the enclosed Amendment No. 214 to Facility Operating License DPR-28 for the Vermont Yankee Nuclear Power Station, in response to your application dated December 10, 2002, as supplemented on January 20, 2003.
The amendment changes the diesel fuel specification to a more current revision in Technical Specification (TS) 4.10.C. The change also makes administrative revisions to reflect generic position titles in TS 6.0, correct page numbers and titles in the Table of Contents, and to delete the General Table of Contents. Bases pages were also revised to reflect the fuel specification revision as well as to make administrative changes to provide clarity and correct a misspelling.
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/
Robert M. Pulsifer, Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-271
Enclosures:
- 1. Amendment No. 214 to License No. DPR-28
- 2. Safety Evaluation cc w/encls: See next page
Vermont Yankee Nuclear Power Station cc:
Regional Administrator, Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. David R. Lewis Shaw, Pittman, Potts & Trowbridge 2300 N Street, N.W.
Washington, DC 20037-1128 Ms. Christine S. Salembier, Commissioner Vermont Department of Public Service 112 State Street Montpelier, VT 05620-2601 Mr. Michael H. Dworkin, Chairman Public Service Board State of Vermont 112 State Street Montpelier, VT 05620-2701 Chairman, Board of Selectmen Town of Vernon P.O. Box 116 Vernon, VT 05354-0116 Mr. Michael Hamer Operating Experience Coordinator Entergy Nuclear Vermont Yankee, LLC P.O. Box 250 Governor Hunt Road Vernon, VT 05354 G. Dana Bisbee, Esq.
Deputy Attorney General 33 Capitol Street Concord, NH 03301-6937 Chief, Safety Unit Office of the Attorney General One Ashburton Place, 19th Floor Boston, MA 02108 Ms. Deborah B. Katz Box 83 Shelburne Falls, MA 01370 Mr. Raymond N. McCandless Vermont Department of Health Division of Occupational and Radiological Health 108 Cherry Street Burlington, VT 05402 Mr. Gautam Sen Manager, Licensing Entergy Nuclear Vermont Yankee, LLC P.O. Box 0500 185 Old Ferry Road Brattleboro, VT 05302-0500 Resident Inspector Vermont Yankee Nuclear Power Station U. S. Nuclear Regulatory Commission P.O. Box 176 Vernon, VT 05354 Director, Massachusetts Emergency Management Agency ATTN: James Muckerheide 400 Worcester Rd.
Framingham, MA 01702-5399 Jonathan M. Block, Esq.
Main Street P.O. Box 566 Putney, VT 05346-0566 Mr. Michael R. Kansler Sr. Vice President and Chief Operating Officer Entergy Nuclear Operations, Inc.
Mail Stop 12A 440 Hamilton Ave.
White Plains, NY 10601 Mr. John J. Kelly Director, Licensing Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 1060
February 27, 2003 Mr. Jay K. Thayer Site Vice President - Vermont Yankee Entergy Nuclear Vermont Yankee, LLC P.O. Box 0500 185 Old Ferry Road Brattleboro, VT 05302-0500
SUBJECT:
VERMONT YANKEE NUCLEAR POWER STATION - ISSUANCE OF AMENDMENT RE: GENERIC POSITION TITLES AND OTHER ADMINISTRATIVE CHANGES (TAC NO. MB6925)
Dear Mr. Thayer:
The Commission has issued the enclosed Amendment No. 214 to Facility Operating License DPR-28 for the Vermont Yankee Nuclear Power Station, in response to your application dated December 10, 2002, as supplemented on January 20, 2003.
The amendment changes the diesel fuel specification to a more current revision in Technical Specification (TS) 4.10.C. The change also makes administrative revisions to reflect generic position titles in TS 6.0, correct page numbers and titles in the Table of Contents, and to delete the General Table of Contents. Bases pages were also revised to reflect the fuel specification revision as well as to make administrative changes to provide clarity and correct a misspelling.
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/
Robert M. Pulsifer, Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-271
Enclosures:
- 1. Amendment No. 214 to License No. DPR-28
- 2. Safety Evaluation cc w/encls: See next page DISTRIBUTION:
PUBLIC J. Clifford OGC ACRS Tech Branch PDI-2 R/F R. Pulsifer G. Hill (2)
J. Bobiak, RI C. Anderson, RI S. Richards C. Raynor W. Beckner F. Arner, RI Accession Number: Letter: ML030570728, Text Spec: ML, Package: ML OFFICE PDI-2/PM PDI-2/LA OGC PDI-2/SC NAME RPulsifer CRaynor SUttal JClifford DATE 02/24/03 02/24/03 2/24/03 2/26/03 OFFICIAL RECORD COPY
ENTERGY NUCLEAR VERMONT YANKEE, LLC AND ENTERGY NUCLEAR OPERATIONS, INC.
DOCKET NO. 50-271 VERMONT YANKEE NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 214 License No. DPR-28 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations, Inc. (the licensees) dated December 10, 2002, as supplemented on January 20, 2003, 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 3.B of Facility Operating License No. DPR-28 is hereby amended to read as follows:
(B)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 214, 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 its date of issuance and shall be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
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: February 27, 2003
ATTACHMENT TO LICENSE AMENDMENT NO. 214 FACILITY OPERATING LICENSE NO. DPR-28 DOCKET NO. 50-271 Replace the following page(s) of the Appendix A Technical Specifications with the attached revised page(s). The revised page(s) are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Insert i
i ii ii iii iii iv iv v
111b 111b 163 163 218 218 223 223 255 255 256 256 257 257 258 258 264 264
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 214 TO FACILITY OPERATING LICENSE NO. DPR-28 ENTERGY NUCLEAR VERMONT YANKEE, LLC AND ENTERGY NUCLEAR OPERATIONS, INC.
VERMONT YANKEE NUCLEAR POWER STATION DOCKET NO. 50-271
1.0 INTRODUCTION
By letter dated December 10, 2002, as supplemented on January 20, 2003, Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations, Inc. (the licensees) submitted a request to amend the Vermont Yankee Nuclear Power Station Technical Specifications (TSs).
The proposed amendment would revise the TSs to change the diesel fuel specification to a more current revision in TS 4.10.C. The amendment would also make administrative revisions to reflect generic position titles in TS 6.0, correct page numbers and titles in the Table of Contents, and to delete the General Table of Contents. Bases pages were also revised to reflect the fuel specification revision as well as to make administrative changes to provide clarity and correct a misspelling. The January 20, 2003, supplement did not expand the scope of the original Federal Register notice.
2.0 REGULATORY EVALUATION
The staff finds that the licensee in Attachment 1 of its submittal identified the applicable regulatory requirements for revising the plant specific personnel titles. The regulatory requirements for which the staff based its acceptance are ANSI N18.1-1971 or Regulatory Guide 1.8, Qualification and Training of Personnel for Nuclear Power Plants. In addition the staff used Regulatory Guide 1.137, Fuel Oil Systems for Standby Diesel Generators in the review of the diesel fuel oil specification change.
3.0 TECHNICAL EVALUATION
3.1 Position Title Changes The licensee proposes to change the position titles in the TS to generic titles as provided in ANSI N18.1-1971 or Regulatory Guide 1.8 instead of plant specific personnel titles. This change will make titles consistent with other Entergy Nuclear Operations, Inc. facilities. This change does not change any requirements, qualifications, or responsibilities of the individuals in these positions, and is strictly an administrative change. The plant specific titles will be identified in licensee-controlled documents such as the Technical Requirements Manual and the Quality Assurance Manual. The following are the proposed changes:
3.1.A The term Plant Manager is changed to plant manager in TS Sections 6.1.A and B, 6.2.A.2, and 6.7.B.1.b.
3.1.B The term Shift Supervisor is changed to shift supervisor in TS Sections 6.1.C and 6.5.B.
3.1.C The term operations superintendent is changed to operations manager and the term assistant operations superintendent is changed to assistant operations manager in TS Section 6.2.B.7.
3.1.D In TS Section 6.2.B.8, the term the Shift Engineer is changed to a shift engineer and the term Shift Supervisor (SS) is changed to shift supervisor.
3.1.E The term Shift Engineer in TS Section 6.2.C is changed to shift engineer.
3.1.F In TS Sections 6.5.A.3 and 6.5.B, the term Radiation Protection Manager is changed to radiation protection manager.
3.1.G In TS Section 6.2.A.3, change the text, corporate executive with direct responsibility for the plant to site vice president.
3.1.H In order to delineate where the plant-specific titles will be discussed, the licensee proposes to add the following statement to TS Section 6.2.A.1. The plant-specific titles of those personnel fulfilling the responsibilities of the positions delineated in these Technical Specifications shall be documented in the Technical Requirements Manual.
The changes involving the generic position titles and the location of the specific plant position delineation meet the intent of ANSI N18.1-1971 or Regulatory Guide 1.8 and are, therefore, acceptable.
3.2 Diesel Generator Fuel Oil The current TS Surveillance Requirement 4.10.C requires that once a month the diesel fuel oil be sampled for quality and that it meets applicable limits on Table I of ASTM D975-68. The licensee proposes to use the more current revision of this specification, specifically ASTM D975-02. This revision provides more information and guidance than the 1968 standard.
TS 4.10.C will be changed from ASTM D975-68 to ASTM D975-02. Changing this revision does not affect the safe operation of the diesels or affect the safety analysis and remains within the guidelines of NUREG 1.137. This change is acceptable because the more current revision provides up-to-date guidance and information regarding diesel fuel oil testing and meets the requirements of the applicable ASTM standard.
3.3 Administrative Changes Several administrative changes are being made to provide clarity and consistency between the Table of Contents and the text of the TS. These changes reflect TS Section titles, page numbers, spelling, and deletion of the general table of contents.
3.3.A Page i, Table of Contents General (TOCG) is being deleted from the current TS because it provides no additional information than that provided by the revised Table of Contents (TOC). The TOCG was incomplete and unnecessary. Line item 1.0, Definitions and Sections 6.1 thru 6.7 from the TOCG are being relocated to the TOC for completeness. The relocation of Sections 1.0 and 6.1 thru 6.7 from the TOCG and the deletion of the TOCG is acceptable because the TOCG was incomplete and is redundant to the revised TOC. With the deletion of the TOCG, all subsequent pages ii through v will be renumbered i through iv.
3.3.B Proposed page i
- 1. Current TS page ii will be renumbered i and the text (Continued) will be deleted with the deletion of TOCG discussed in 3.3.A which will make this page the first page of this section.
- 2. The title of line item 3.2.D of the TOC is being changed to reflect the correct title of Section 3.2.D in the TS which reads, Off-Gas System Isolation.
- 3. The title of line item 3.2.F of the TOC is being changed to reflect the correct title of Section 3.2.F in the TS which reads, Mechanical Vacuum Pump Isolation Instrumentation.
- 4. The page number for Section 3.2.G in the TOC is being changed from page 35 to 36 and the page number for Sections 3.2.I, J, and K are being changed from page 36 to 37. Sections 3.2.G, I, J, and K were moved in Amendment No. 212, dated September 18, 2002, and the TOC was not changed at that time to reflect those changes.
The changes to page i are acceptable because they are administrative changes that accommodate the change in 3.3.A, actual TS titles, and a previous amendment.
3.3.C Proposed page ii
- 1. The title of line item 3.4.C of the TOC is being changed to reflect the correct title of section 3.4.C in the TS which reads, Standby Liquid Control System Tank -
Borated Solution.
- 2. The title of line item 3.6.E of the TOC is being changed to reflect the correct title of Section 3.6.E in the TS which reads, Structural Integrity and Operating Testing.
- 3. The title of line item 3.7.B of the TOC is being changed to reflect the correct title of Section 3.7.B in the TS which reads, Standby Gas Treatment System.
- 4. The page number for Section 3.6.C in the TOC is being changed from page 119 to 118; the page number for Section 3.6, Bases, from page 139 to 138, and the page number for Section 3.7.D was changed from page 156 to 158.
Sections 3.6.C, 3.6 Bases, and 3.7.D were moved in Amendment No. 190, dated July 18, 2000, Amendment No. 203, dated May 4, 2001, and Amendment No. 197, dated March 23, 2001, respectively. The TOC was not changed at the time these amendments were issued to reflect those changes.
The changes to page ii are acceptable because they are administrative changes that accommodate actual TS titles and previous TS amendments.
3.3.D Proposed page iii
- 1. The number 4.9 under the column Surveillance for line item Section 3.9 in the TOC is being deleted because Sections 3.9 and 4.9 had been deleted in Amendment No. 193, dated August 24, 2000.
- 2. The title of Section 3.11.A of the TOC is being changed to reflect the correct title of Section 3.11.A which reads, Average Planar Linear Heat Generation Rate (APLHGR).
- 3. The title of Section 3.11.B of the TOC is being changed to reflect the correct title of Section 3.11.B which reads, Linear Heat Generation Rate (LHGR).
- 4. The title of Section 3.11.C of the TOC is being changed to reflect the correct title of Section 3.11.C which reads, Minimum Critical Power Ratio.
The changes to page iii are acceptable because they are administrative changes that accommodate actual TS titles in the TSs and a change from a previous amendment.
3.3.E The misspelling of the word reactor has been corrected on Bases page 111b for Section 3.5.G. This is an administrative change and the staff has no objection to this change.
3.3.F The text 1000 psig was changed to normal operating pressure in the Bases for Section 3.7.A to provide clarity and correctness of the basis for the pressure suppression chamber water volume. The staff has no objection to this change.
3.3.G In TS Section 6.2.4, there was an extra tab at the beginning of the paragraph that was removed to provide consistency with the format of the TS. This is acceptable because it is administrative in nature.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Vermont State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The amendment also changes recordkeeping, reporting, or administrative procedures or requirements. The NRC staff has determined that the amendment involves no significant increase in 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 amendment involves no significant hazards consideration, and there has been no public comment on such finding (68 FR 2802). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) and (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 Contributor: Robert Pulsifer Date: February 27, 2003