ML071990307
| ML071990307 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 08/16/2007 |
| From: | Boska J NRC/NRR/ADRO/DORL/LPLI-1 |
| To: | Balduzzi M Entergy Nuclear Operations |
| Boska J, NRR, 301-415-2901 | |
| References | |
| TAC MD3074, TAC MD3075, TSTF-485, FOIA/PA-2016-0148 | |
| Download: ML071990307 (18) | |
Text
August 16, 2007 Mr. Michael A. Balduzzi Sr. Vice President & COO Regional Operations, NE Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601
SUBJECT:
INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 - ISSUANCE OF AMENDMENTS RE: PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS: MISCELLANEOUS EDITORIAL CHANGES, INCLUDING TSTF-485 (TAC NOS. MD3074 AND MD3075)
Dear Mr. Balduzzi:
The Commission has issued the enclosed Amendment No. 252 to Facility Operating License No. DPR-26 for the Indian Point Nuclear Generating Unit No. 2 and Amendment No. 234 to Facility Operating License No. DPR-64 for the Indian Point Nuclear Generating Unit No. 3. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated September 25, 2006, as supplemented March 12, 2007.
The amendments revise the TSs by making typographical corrections, updating references, and deleting obsolete notes.
A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commission's next regular biweekly Federal Register notice.
Sincerely,
/RA/
John P. Boska, Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-247 and 50-286
Enclosures:
- 1. Amendment No. 252 to DPR-26
- 2. Amendment No. 234 to DPR-64
- 3. Safety Evaluation cc w/encls: See next page
August 16, 2007 Mr. Michael A. Balduzzi Sr. Vice President & COO Regional Operations, NE Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601
SUBJECT:
INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 - ISSUANCE OF AMENDMENTS RE: PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS: MISCELLANEOUS EDITORIAL CHANGES, INCLUDING TSTF-485 (TAC NOS. MD3074 AND MD3075)
Dear Mr. Balduzzi:
The Commission has issued the enclosed Amendment No. 252 to Facility Operating License No. DPR-26 for the Indian Point Nuclear Generating Unit No. 2 and Amendment No. 234 to Facility Operating License No. DPR-64 for the Indian Point Nuclear Generating Unit No. 3. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated September 25, 2006, as supplemented March 12, 2007.
The amendments revise the TSs by making typographical corrections, updating references, and deleting obsolete notes.
A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commission's next regular biweekly Federal Register notice.
Sincerely,
/RA/
John P. Boska, Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-247 and 50-286
Enclosures:
- 1. Amendment No. 252 to DPR-26
- 2. Amendment No. 234 to DPR-64
- 3. Safety Evaluation cc w/encls: See next page Package No.: ML072280510 Amendment No.: ML071990307 Tech Spec No.: ML
- See SE dated 1/17/07 OFFICE LPL1-1/PM LPL1-1/LA SPWB/BC EICB/BC ITSB/BC OGC LPL1-1/BC NAME JBoska SLittle JNakoski*
WKemper TKobetz BMizuno MKowal DATE 8/01/07 8/01/07 1/17/07 8/03/07 8/13/07 8/14/07 8/15/07 Official Record Copy
DATED: August 16, 2007 AMENDMENT NO. 252 TO FACILITY OPERATING LICENSE NO. DPR-26 INDIAN POINT UNIT 2 AND AMENDMENT NO. 234 TO FACILITY OPERATING LICENSE NO. DPR-64 INDIAN POINT UNIT 3 PUBLIC LPL1-1 R/F RidsNrrDorlLpl1-1 RidsNrrDirsItsb RidsNrrDeEicb RidsNrrPMJBoska RidsNrrLASLittle (paper copy)
ECobey, RI GHill (4) (paper copies)
JNakoski RidsOGCMailCenter RidsAcrsAcnwMailCenter cc: Plant Mailing list
Indian Point Nuclear Generating Unit Nos. 2 & 3 cc:
Mr. Michael R. Kansler President & CEO / CNO Entergy Nuclear Operations, Inc.
1340 Echelon Parkway Jackson, MS 39213 Mr. John T. Herron Sr. Vice President Entergy Nuclear Operations, Inc.
1340 Echelon Parkway Jackson, MS 39213 Sr. Vice President Engineering & Technical Services Entergy Nuclear Operations, Inc.
1340 Echelon Parkway Jackson, MS 39213 Mr. Fred R. Dacimo Site Vice President Entergy Nuclear Operations, Inc.
Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 Mr. Anthony Vitale - Acting General Manager, Plant Operations Entergy Nuclear Operations, Inc.
Indian Point Energy Center 450 Broadway P.O. Box 249 Buchanan, NY 10511-0249 Mr. Oscar Limpias Vice President Engineering Entergy Nuclear Operations, Inc.
1340 Echelon Parkway Jackson, MS 39213 Mr. Joseph P. DeRoy Vice President, Operations Support Entergy Nuclear Operations, Inc.
1340 Echelon Parkway Jackson, MS 39213 Mr. John A. Ventosa GM, Engineering Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. John F. McCann Director, Nuclear Safety & Licensing Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Ms. Charlene D. Faison Manager, Licensing Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. Ernest J. Harkness Director, Oversight Entergy Nuclear Operations, Inc.
1340 Echelon Parkway Jackson, MS 39213 Mr. Patric W. Conroy Director, Nuclear Safety Assurance Entergy Nuclear Operations, Inc.
Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 Mr. T.R. Jones - Acting Manager, Licensing Entergy Nuclear Operations, Inc.
Indian Point Energy Center 450 Broadway, GSB P. O. Box 249 Buchanan, NY 10511-0249 Mr. William C. Dennis Assistant General Counsel Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601
Indian Point Nuclear Generating Unit Nos. 2 & 3 cc:
Mr. Michael Balboni Deputy Secretary for Public Safety State Capitol, Room 229 Albany, NY 12224 Mr. John P. Spath New York State Energy, Research, and Development Authority 17 Columbia Circle Albany, NY 12203-6399 Mr. Paul Eddy New York State Department of Public Service 3 Empire State Plaza Albany, NY 12223-1350 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Senior Resident Inspectors Office Indian Point 2 U. S. Nuclear Regulatory Commission P.O. Box 59 Buchanan, NY 10511 Senior Resident Inspectors Office Indian Point 3 U. S. Nuclear Regulatory Commission P.O. Box 59 Buchanan, NY 10511 Mr. Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 Mr. Raymond L. Albanese Four County Coordinator 200 Bradhurst Avenue Unit 4 Westchester County Hawthorne, NY 10532 Mayor, Village of Buchanan 236 Tate Avenue Buchanan, NY 10511 Mr. William DiProfio PWR SRC Consultant 48 Bear Hill Road Newton, NH 03858 Mr. Garry Randolph PWR SRC Consultant 1750 Ben Franklin Drive, 7E Sarasota, FL 34236 Mr. William T. Russell PWR SRC Consultant 400 Plantation Lane Stevensville, MD 21666-3232 Mr. Jim Riccio Greenpeace 702 H Street, NW Suite 300 Washington, DC 20001 Mr. Phillip Musegaas Riverkeeper, Inc.
828 South Broadway Tarrytown, NY 10591 Mr. Mark Jacobs IPSEC 46 Highland Drive Garrison, NY 10524
ENTERGY NUCLEAR INDIAN POINT 2, LLC ENTERGY NUCLEAR OPERATIONS, INC.
DOCKET NO. 50-247 INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 252 License No. DPR-26
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Nuclear Operations, Inc. (the licensee) dated September 25, 2006, as supplemented on March 12, 2007, 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 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.
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-26 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 252 are hereby incorporated in the license. ENO shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Mark G. Kowal, Chief Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the License and Technical Specifications Date of Issuance: August 16, 2007
ATTACHMENT TO LICENSE AMENDMENT NO. 252 FACILITY OPERATING LICENSE NO. DPR-26 DOCKET NO. 50-247 Replace the following pages of the License with the attached revised pages. The revised pages are identified by amendment number and contains marginal lines indicating the areas of change.
Remove Page Insert Page 3
3 5a 5a 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 Pages Insert Pages Table of Contents Page iv Table of Contents Page iv 1.4-3 1.4-3 3.3.1-16 3.3.1-16 3.3.1-17 3.3.1-17 3.3.7-3 3.3.7-3 5.3-1 5.3-1 5.5-14 5.5-14
ENTERGY NUCLEAR INDIAN POINT 3, LLC ENTERGY NUCLEAR OPERATIONS, INC.
DOCKET NO. 50-286 INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 234 License No. DPR-64 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Nuclear Operations, Inc. (the licensee) dated September 25, 2006, as supplemented on March 12, 2007, 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 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.
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-64 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 234, are hereby incorporated in the license. ENO shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Mark G. Kowal, Chief Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the License and Technical Specifications Date of Issuance: August 16, 2007
ATTACHMENT TO LICENSE AMENDMENT NO. 234 FACILITY OPERATING LICENSE NO. DPR-64 DOCKET NO. 50-286 Replace the following page of the License with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
Remove Page Insert Page 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 Pages Insert Pages 1.4-2 1.4-2 3.3.1-19 3.3.1-19 3.3.1-20 3.3.1-20 3.7.11-1 3.7.11-1 3.8.7-3 3.8.7-3 5.0-5 5.0-5 5.0-6 5.0-6 5.0-24 5.0-24 5.0-30 5.0-30
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 252 TO FACILITY OPERATING LICENSE NO. DPR-26 AND AMENDMENT NO. 234 TO FACILITY OPERATING LICENSE NO. DPR-64 ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 DOCKET NOS. 50-247 AND 50-286
1.0 INTRODUCTION
By letter dated September 25, 2006, Agencywide Documents Access and Management System (ADAMS) Accession No. ML062780184, as supplemented by letter dated March 12, 2007, ADAMS Accession No. ML070790246, Entergy Nuclear Operations, Inc. (Entergy or the licensee) submitted a request for changes to the Indian Point Nuclear Generating Unit Nos. 2 and 3 (IP2 and IP3) Technical Specifications (TSs). The supplement dated March 12, 2007, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the NRC staff's original proposed no significant hazards consideration determination. The proposed changes are editorial in nature and include changes for IP2 and IP3.
Specifically, the proposed changes would:
(1)
Make typographical corrections for errors introduced via the incorporation of Technical Specification Task Force (TSTF) documents 359 and 339 and incorrect markups of NUREG 1431 during the IP2 and IP3 conversion to improved standard TS (ISTS),
(2)
Update references to be consistent with the most recently issued revision to the Quality Assurance Program Manual (QAPM),
(3)
Delete notes that have become obsolete due to their one-time nature or as a result of plant modifications, (4)
Revise the IP2 Table of Contents to add a header for the new section, 5.7 High Radiation Area which was previously added to the IP2 TSs by License Amendment No. 250, and (5)
Revise IP2 Facility Operating License Section M.3 to correct a typographical error.
2.0 REGULATORY EVALUATION
The Commissions regulatory requirements related to the contents of TS are set forth in Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36 and assures the TS-specified limiting conditions for operation are consistent with assumed values of the initial conditions in the licensees safety analyses. In accordance with 10 CFR 50.36, the NRC staff and the Westinghouse Owners group developed ISTS that meet 10 CFR 50.36(c)(2)ii and 10 CFR 50.36(c)(3) requirements. The licensee referred to the NRC staff-approved NUREG-1431, Revision 3, "Standard Technical Specifications Westinghouse Plants" when developing their revisions. On December 19, 2005, the task force issued TSTF-485 to NUREGs-1430, 1431, 1432, 1433, and 1434 in order to establish consistency within the requirements of Surveillance Requirement (SR) 3.0.4, which was previously revised by TSTF-359, Rev. 9. The editorial correction revised the text of Example 1.4-1 to add clarity and increase operator understanding.
NUREG-1431, Revision 2, corrected an erroneous inequality sign for the P' term used in the Overtemperature T expression of Table 3.3.1-1. The error was introduced with the incorporation of TSTF-339. Similarly, NUREG-1431, Revision 3, incorporated the correction of sign errors in the expression for f1(I), which is also used in the Overtemperature T expression of Table 3.3.1-1.
10 CFR 50.54(a)(3) allows licensees to make changes to their QAPM so long as those changes do not reduce the licensees commitments and the licensee submits a copy of the changes to the NRC pursuant to 10 CFR 50.34. In a letter dated May 15, 2006, Entergy submitted Revision 13 of the QAPM, which specified the use of ANSI/ANS 3.1-1978 standards for unit staff qualifications and Regulatory Guide (RG) 1.33, Revision 2, for the establishment, implementation, and maintenance of written procedures. The proposed revision to the IP2 and IP3 TSs updates references to be consistent with Revision 13 of the QAPM. NUREG-1431, Revision 3, and Entergy QAPM, Revision 13, verify the validity of the typographical corrections and reference updates proposed by the licensee. The deletion of obsolete notes is valid due to the expiration of the basis for these allowances as documented in IP2 License Amendment No. 232 and IP3 License Amendments Nos. 205, 206, 219, and 223.
3.0 TECHNICAL EVALUATION
3.1 Typographical Corrections The licensee proposes to make the following corrections:
(1) Correct SR Example 1.4-1 per TSTF-485 for IP2 and IP3, respectively; (2) Correct the sign applied to certain parameters in the expression for Overtemperature T for IP2 and IP3, respectively; (3) Correct the sign applied to the tau parameter used in the expression for Overpower T for IP 2 and IP3, respectively, and (4) Correct the units used in Table 3.3.7-1 for IP2.
These modifications incorporate corrections to errors introduced as a result of the incorporation of TSTFs 359 and 339 and incorrect markups of NUREG-1431 during the conversion of IP2 and IP3 to ISTS. The changes have the licensees TSs conform with the most current and correct source documents and do not require the correction of any field settings specified in plant documents.
The NRC staff concludes that the proposed changes are editorial in nature or correct errors in the TSs. As the proposed changes meet the requirements of 10 CFR 50.36, the changes are acceptable.
3.2 Reference Updates The licensee proposes to make the following corrections:
(5)
Update the reference specified for 5.3.1.b, Unit Staff Qualifications, to specify the use of ANSI/ANS 3.1-1978 as opposed to ANSI N18.1-1971 per the updated QAPM for IP2 and IP3, respectively, and (6)
Update the reference specified for 5.4.1.a, Procedures, to specify the use of Revision 2 of RG 1.33 in lieu of Revision 0 per the updated QAPM for IP3.
These changes modify IP2/IP3 TS Sections 5.3.1.b and IP3 TS Section 5.4.1.a in order to achieve agreement between the TSs and the QAPM and to provide the most current references.
The NRC staff concludes that the proposed changes are editorial in nature or revise the TSs to conform with the most current and correct source documents. As the proposed changes meet the requirements of 10 CFR 50.36, the changes are acceptable.
3.3 Deletion of Obsolete Notes The licensee proposes to make the following corrections:
(7)
Delete a one-time note regarding tracer gas testing for IP3; (8)
Delete the SR 3.8.7.1 note regarding frequency verification for inverter 34 for IP3; (9)
Delete the one-time note regarding the integrated leak rate testing test interval for IP2 and IP3, respectively, and (10)
Delete the note regarding the charcoal bed depth for the control room ventilation system for IP3.
Changes 7 and 9 remove one-time notes that are now outdated. Change 8 deletes the SR 3.8.7.1 note regarding frequency verification for inverter 34 for IP3 because frequency instrumentation for inverter 34 is now available. Similarly, Change 10 deletes the note regarding charcoal bed depth for the control room ventilation system for IP3 because Entergy completed the installation of new 2-inch beds in spring 2005, therefore, the note allowing temporary use of 1-inch beds is obsolete.
The NRC staff concludes that the proposed changes are editorial in nature or revise the TSs to conform with the most current and correct source documents or equipment configurations. As the proposed changes meet the requirements of 10 CFR 50.36, the changes are acceptable.
3.4 Technical Specifications Table of Contents Update The licensee proposes to make the following correction:
(11)
Revise the IP2 Table of Contents to add a header for the new section, "5.7 High Radiation Area." Section 5.7 was previously added to the IP2 TSs by License Amendment No. 250.
The NRC staff concludes that the proposed change is editorial in nature. As the proposed change meets the requirements of 10 CFR 50.36, the change is acceptable.
3.5 Operating License Typographical Corrections The licensee proposes to make the following correction:
(12)
Revise IP2 Facility Operating License Section M.3 to correct a typographical error.
The NRC staff concludes that the proposed change is editorial in nature and, therefore, is acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the New York 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 and changes SRs.
The NRC staff has determined that the amendment involves 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 amendment involves no significant hazards consideration, and there has been no public comment on such finding (71 FR 65142). Accordingly, the amendment meets 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 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.
7.0 REFERENCES
1.
Entergy Letter NL-06-099 to NRC, "Proposed Changes to Indian Point 2 and 3 Technical Specifications: Miscellaneous Editorial Changes, Including TSTF-485," dated September 25, 2006.
2.
NUREG-1431, Revision 3, "Standard Technical Specifications Westinghouse Plants,"
dated March 2004.
3.
Technical Specification Task Force Improved Standard Technical Specification Change Traveler, TSTF-485, dated December 19, 2005.
Principal Contributors: S. Cleavenger J. Boska Date: August 16, 2007