ML100890188: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
| Line 34: | Line 34: | ||
Apr; 1 12, 2010 ATTACHMENT TO LICENSE AMENDMENT NO. RENEWED FACILITY OPERATING LICENSE NO. DOCKET NO. 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. | Apr; 1 12, 2010 ATTACHMENT TO LICENSE AMENDMENT NO. RENEWED FACILITY OPERATING LICENSE NO. DOCKET NO. 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 Page 3 Page 3 Replace the following page of the Appendix A Technical Specifications with the attached revised page. The revised page is identified by amendment number and contain marginal lines indicating the areas of change. Remove Page Insert Page 5.5-6 5.5-6 ENO pursuant to the Act and 10 CFR Parts 30, 40, and 70 to receive, possess, and use, at any time, any byproduct, source and special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration; or associated with radioactive apparatus, components or tools .. Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below: Maximum Power Level ENO is authorized to operate the facility at steady state reactor core power levels not in excess of 2536 megawatts (thermal). Technical Specifications The Technical Specifications contained in Appendix A , as revised through Amendment N0296, are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications. Fire Protection ENO shall implement and maintain in effect all provisions of the approved fire protections program as described in the Final Safety Analysis Report for the facility and as approved in the SER dated November 20, 1972; the SER Supplement No.1 dated February 1, 1973; the SER Supplement NO.2 dated October 4, 1974; the SER dated August 1, 1979; the SER Supplement dated October 3, 1980; the SER Supplement dated February 13, 1981; the NRC Letter dated February 24, 1981; Technical Specification Amendments 34 (dated January 31, 1978),80 (dated May 22, 1984), 134 (dated JUly 19, 1989), 135 (dated September 5, 1989), 142 (dated October 23, 1989), 164 (dated August 10, 1990), 176 (dated January 16, 1992), 177 (dated February 10, 1992), 186 (dated February 19, 1993),190 (dated June 29,1993),191 (dated July 7,1993),206 (dated February 28, 1994) and 214 (dated June 27, 1994); and NRC Exemptions and associated safety evaluations dated April 26, 1983, July 1, 1983, January 11, 1985, April 30, 1986, September 15, 1986 and September 10, 1992 subject to the following provision: | Remove Page Insert Page Page 3 Page 3 Replace the following page of the Appendix A Technical Specifications with the attached revised page. The revised page is identified by amendment number and contain marginal lines indicating the areas of change. Remove Page Insert Page 5.5-6 5.5-6 ENO pursuant to the Act and 10 CFR Parts 30, 40, and 70 to receive, possess, and use, at any time, any byproduct, source and special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration; or associated with radioactive apparatus, components or tools .. Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below: Maximum Power Level ENO is authorized to operate the facility at steady state reactor core power levels not in excess of 2536 megawatts (thermal). Technical Specifications The Technical Specifications contained in Appendix A , as revised through Amendment N0296, are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications. Fire Protection ENO shall implement and maintain in effect all provisions of the approved fire protections program as described in the Final Safety Analysis Report for the facility and as approved in the SER dated November 20, 1972; the SER Supplement No.1 dated February 1, 1973; the SER Supplement NO.2 dated October 4, 1974; the SER dated August 1, 1979; the SER Supplement dated October 3, 1980; the SER Supplement dated February 13, 1981; the NRC Letter dated February 24, 1981; Technical Specification Amendments 34 (dated January 31, 1978),80 (dated May 22, 1984), 134 (dated JUly 19, 1989), 135 (dated September 5, 1989), 142 (dated October 23, 1989), 164 (dated August 10, 1990), 176 (dated January 16, 1992), 177 (dated February 10, 1992), 186 (dated February 19, 1993),190 (dated June 29,1993),191 (dated July 7,1993),206 (dated February 28, 1994) and 214 (dated June 27, 1994); and NRC Exemptions and associated safety evaluations dated April 26, 1983, July 1, 1983, January 11, 1985, April 30, 1986, September 15, 1986 and September 10, 1992 subject to the following provision: | ||
Amendment 296 | Amendment 296 5.5 Programs and Manuals 5.5 Programs and Manuals 5.5.6 Primary Containment Leakage Rate Testing Program (continued) The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program. Nothing in these Technical Specifications shall be construed to modify the testing Frequencies required by 10 CFR 50, Appendix J. | ||
5.5.7 Inservice Testing Program This program provides controls for inservice testing of certain ASME Code Class 1, 2, and 3 pumps and valves. The program shall include the following: Testing Frequencies specified in the ASME OM Code and applicable Addenda are as follows: | |||
and Manuals 5.5 Programs and Manuals 5.5.6 Primary Containment Leakage Rate Testing Program (continued) The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program. Nothing in these Technical Specifications shall be construed to modify the testing Frequencies required by 10 CFR 50, Appendix J. | |||
Testing Program This program provides controls for inservice testing of certain ASME Code Class 1, 2, and 3 pumps and valves. The program shall include the following: Testing Frequencies specified in the ASME OM Code and applicable Addenda are as follows: | |||
ASME OM Code and applicable Addenda terminology for Required Frequencies inservice testing for performing inservice activities testing activities Quarterly or every 3 months At least once per 92 days Biennially or every 2 years At least once per 731 days The provisions of SR 3.0.2 are applicable to the above required Frequencies for performing inservice testing activities; The provisions of SR 3.0.3 are applicable to inservice testing activities; and (continued) 5.5-6 Amendment2..9.6..... | ASME OM Code and applicable Addenda terminology for Required Frequencies inservice testing for performing inservice activities testing activities Quarterly or every 3 months At least once per 92 days Biennially or every 2 years At least once per 731 days The provisions of SR 3.0.2 are applicable to the above required Frequencies for performing inservice testing activities; The provisions of SR 3.0.3 are applicable to inservice testing activities; and (continued) 5.5-6 Amendment2..9.6..... | ||
UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.296 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-59 ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 | UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.296 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-59 ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 | ||
| Line 51: | Line 46: | ||
-2and 2003 Addenda of the ASME OM Code pursuant to 10 CFR 50.55a(f)(4)(ii) as required by 10 CFR 50.55a(f)(4). | -2and 2003 Addenda of the ASME OM Code pursuant to 10 CFR 50.55a(f)(4)(ii) as required by 10 CFR 50.55a(f)(4). | ||
The regulatory requirements related to the content of TS are contained in 10 CFR 50.36. That regulation requires that the TS include items in the following specific categories: (1) safety limits, limiting safety systems settings, and limiting control settings, (2) limiting conditions for operation, (3) surveillance requirements, (4) design features, and (5) administrative controls. | The regulatory requirements related to the content of TS are contained in 10 CFR 50.36. That regulation requires that the TS include items in the following specific categories: (1) safety limits, limiting safety systems settings, and limiting control settings, (2) limiting conditions for operation, (3) surveillance requirements, (4) design features, and (5) administrative controls. | ||
The changes were reviewed for compliance with the requirements for 1ST as contained in 10 CFR 50.55a(f)( 4) for ASME Code Class 1, 2, and 3 pumps and valves. Guidance on the acceptability of the ASME OM Code is provided in Regulatory Guide 1.192, "Operations and Maintenance Code Case Acceptability, ASME OM Code," June 2003. | The changes were reviewed for compliance with the requirements for 1ST as contained in 10 CFR 50.55a(f)( 4) for ASME Code Class 1, 2, and 3 pumps and valves. Guidance on the acceptability of the ASME OM Code is provided in Regulatory Guide 1.192, "Operations and Maintenance Code Case Acceptability, ASME OM Code," June 2003. | ||
3.0 TECHNICAL EVALUATION 3.1 Specific Changes Reguested The licensee has proposed the following changes to the JAFNPP TS: For TS Section 5.5.7.a, the reference to Section XI of the ASME Code for 1ST requirements would be replaced with ASME OM Code. The weekly, monthly, semiannually or every 6 months, every 9 months, and yearly or annually 1ST frequencies in TS Section 5.5.7.a would be deleted. | |||
3.2 Basis for Changes TS 5.5.7.a establishes controls for 1ST of ASME Class 1,2, and 3 pumps and valves required to satisfy the requirements in 10 CFR 50.36. TS Section 5.5.7.a currently references Section XI of the ASME Code as the source of requirements for the 1ST of ASME Code Class 1, 2, and 3 pumps and valves. | |||
EVALUATION | |||
Changes Reguested The licensee has proposed the following changes to the JAFNPP TS: For TS Section 5.5.7.a, the reference to Section XI of the ASME Code for 1ST requirements would be replaced with ASME OM Code. The weekly, monthly, semiannually or every 6 months, every 9 months, and yearly or annually 1ST frequencies in TS Section 5.5.7.a would be deleted. | |||
for Changes TS 5.5.7.a establishes controls for 1ST of ASME Class 1,2, and 3 pumps and valves required to satisfy the requirements in 10 CFR 50.36. TS Section 5.5.7.a currently references Section XI of the ASME Code as the source of requirements for the 1ST of ASME Code Class 1, 2, and 3 pumps and valves. | |||
The regulations in 10 CFR 50.55a(f)( 4) establish the effective Code edition and addenda to be used by licensees for performing 1ST of pumps and valves. The regulations in 10 CFR 50.55a(f)(4)(ii) require licensees to update their 1ST program to the latest approved edition and addenda of the ASME OM Code incorporated by reference into 10 CFR 50.55a(b). The licensee states that the 1ST Program for the JAFNPP fourth interval was updated to comply with the appropriate revisions of the ASME OM Code and included the 2001 Edition with the 2002 and 2003 Addenda as the new Code of Record for performing 1ST at JAFNPP. As a consequence, the TS 5.5.7.a reference to Section XI of the ASME Code results in a reference to a deleted portion of the Code. The weekly, monthly, semiannually or every 6 months, every 9 months, and yearly or annually 1ST frequencies currently in TS Section 5.5.7.a are not applicable to the pumps and valves included in the JAFNPP TS and, therefore, can be deleted. | The regulations in 10 CFR 50.55a(f)( 4) establish the effective Code edition and addenda to be used by licensees for performing 1ST of pumps and valves. The regulations in 10 CFR 50.55a(f)(4)(ii) require licensees to update their 1ST program to the latest approved edition and addenda of the ASME OM Code incorporated by reference into 10 CFR 50.55a(b). The licensee states that the 1ST Program for the JAFNPP fourth interval was updated to comply with the appropriate revisions of the ASME OM Code and included the 2001 Edition with the 2002 and 2003 Addenda as the new Code of Record for performing 1ST at JAFNPP. As a consequence, the TS 5.5.7.a reference to Section XI of the ASME Code results in a reference to a deleted portion of the Code. The weekly, monthly, semiannually or every 6 months, every 9 months, and yearly or annually 1ST frequencies currently in TS Section 5.5.7.a are not applicable to the pumps and valves included in the JAFNPP TS and, therefore, can be deleted. | ||
-3 3.3 Evaluation In 1990, the ASME published the initial edition of the ASME OM Code, which provides requirements for 1ST of pumps and valves. The OM Code was developed and is maintained by the ASME Committee on Operation and Maintenance of Nuclear Power Plants. The ASME OM Code was developed in response to the ASME Board on Nuclear Codes and Standards directive that transferred responsibility for development and maintenance of rules for the 1ST of pumps and valves from the ASME Section XI Subcommittee on Nuclear Inservice Inspection to the ASME OM Committee. The ASME intended the ASME OM Code to replace Section XI rules for 1ST of pumps and valves, and the Section XI rules for 1ST of pumps and valves were deleted from Section XI in the 2000 Addenda. The JAFNPP fourth 1O-year interval 1ST program was updated to comply with the 2001 Edition with the 2002 and 2003 Addenda of the ASME OM Code as required by 10 CFR 50.55a(f)(4)(ii). As a consequence, the TS 5.5.7.a reference to Section XI of the ASME Code for 1ST requirements results in a reference to a deleted portion of the ASME Code. The TS changes do not eliminate any tests and do not relinquish the licensee of its responsibility to seek NRC authorization of alternatives to the Code or grant relief from Code test requirements when they are impractical. The proposed change will eliminate the ASME Code inconsistency between the 1ST program and the TSs; therefore, the NRC staff finds these proposed changes to be acceptable. The NRC staff also finds that deletion of the weekly, monthly, semiannually or every 6 months, every 9 months, and yearly or annually 1ST frequencies currently in TS Section 5.5.7.a acceptable. This TS change is administrative in nature and only deletes 1ST frequencies that are not applicable to the Class 1, 2, and 3 pumps and valves included in the JAFNPP TSs. | -3 3.3 Evaluation In 1990, the ASME published the initial edition of the ASME OM Code, which provides requirements for 1ST of pumps and valves. The OM Code was developed and is maintained by the ASME Committee on Operation and Maintenance of Nuclear Power Plants. The ASME OM Code was developed in response to the ASME Board on Nuclear Codes and Standards directive that transferred responsibility for development and maintenance of rules for the 1ST of pumps and valves from the ASME Section XI Subcommittee on Nuclear Inservice Inspection to the ASME OM Committee. The ASME intended the ASME OM Code to replace Section XI rules for 1ST of pumps and valves, and the Section XI rules for 1ST of pumps and valves were deleted from Section XI in the 2000 Addenda. The JAFNPP fourth 1O-year interval 1ST program was updated to comply with the 2001 Edition with the 2002 and 2003 Addenda of the ASME OM Code as required by 10 CFR 50.55a(f)(4)(ii). As a consequence, the TS 5.5.7.a reference to Section XI of the ASME Code for 1ST requirements results in a reference to a deleted portion of the ASME Code. The TS changes do not eliminate any tests and do not relinquish the licensee of its responsibility to seek NRC authorization of alternatives to the Code or grant relief from Code test requirements when they are impractical. The proposed change will eliminate the ASME Code inconsistency between the 1ST program and the TSs; therefore, the NRC staff finds these proposed changes to be acceptable. The NRC staff also finds that deletion of the weekly, monthly, semiannually or every 6 months, every 9 months, and yearly or annually 1ST frequencies currently in TS Section 5.5.7.a acceptable. This TS change is administrative in nature and only deletes 1ST frequencies that are not applicable to the Class 1, 2, and 3 pumps and valves included in the JAFNPP TSs. | ||
| Line 67: | Line 54: | ||
==4.0 STATE CONSULTATION== | ==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. | 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 surveillance requirements. 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 (75 FR 4117). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). | |||
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 surveillance requirements. 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 (75 FR 4117). 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. | 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. | ||
| Line 77: | Line 61: | ||
Based on the above discussion, the Commission has concluded 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. Principal S. Tingen, NRR V Cusumano, NRR Date: April 12, 2010 April 12, 2010 Vice President, Operations Entergy Nuclear Operations, Inc. | Based on the above discussion, the Commission has concluded 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. Principal S. Tingen, NRR V Cusumano, NRR Date: April 12, 2010 April 12, 2010 Vice President, Operations Entergy Nuclear Operations, Inc. | ||
James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093 JAMES A. FITZPATRICK NUCLEAR POWER PLANT - | James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093 JAMES A. FITZPATRICK NUCLEAR POWER PLANT - | ||
ISSUANCE OF AMENDMENT RE: REFERENCE TO CURRENT CODE OF RECORD IN TECHNICAL SPECIFICATION | ISSUANCE OF AMENDMENT RE: REFERENCE TO CURRENT CODE OF RECORD IN TECHNICAL SPECIFICATION 5.5.7 INSERVICE TESTING PROGRAM (TAC NO. ME2809) | ||
TESTING PROGRAM (TAC NO. ME2809) | |||
==Dear Sir or Madam:== | ==Dear Sir or Madam:== | ||
| Line 88: | Line 68: | ||
==Enclosures:== | ==Enclosures:== | ||
: 1. Amendment No. 296 to DPR-59 | : 1. Amendment No. 296 to DPR-59 | ||
: 2. Safety Evaluation cc w/encls: | : 2. Safety Evaluation cc w/encls: | ||
Distribution via Listserve DISTRIBUTION: PUBLIC LPL1-1 R/F RidsNrrDorlLPL1-1 RidsOGCMailCenter RidsNrrDirsltsb RidsAcrsAcnwMailCenter RidsNrrPMFitzPatrick RidsNrrLASLittle (paper copy) MGray, RI RidsNrrDciCptb STingen, NRR/CPTB VCusumano, NRR/ITSB ADAMS Accession No.: ML 100890188 (*) No substantial change to SE Input Memo OFFICE LPL 1-lIPM LPL 1-1/LA NRR/CPTB/BC(*) | Distribution via Listserve DISTRIBUTION: PUBLIC LPL1-1 R/F RidsNrrDorlLPL1-1 RidsOGCMailCenter RidsNrrDirsltsb RidsAcrsAcnwMailCenter RidsNrrPMFitzPatrick RidsNrrLASLittle (paper copy) MGray, RI RidsNrrDciCptb STingen, NRR/CPTB VCusumano, NRR/ITSB ADAMS Accession No.: ML 100890188 (*) No substantial change to SE Input Memo OFFICE LPL 1-lIPM LPL 1-1/LA NRR/CPTB/BC(*) | ||
NRR/ITSB/BC(*) | NRR/ITSB/BC(*) | ||
OGC LPL 1-1/BC LPL1-1/PM NAME BVaidya SLittie AMcMutray RElliot AJones NSalQado BVaidya DATE 04/05/10 040/5/10 12124/09 03/23/10 04/08/10 04/12/10 04/12/10 OFFICIAL RECORD COpy}} | OGC LPL 1-1/BC LPL1-1/PM NAME BVaidya SLittie AMcMutray RElliot AJones NSalQado BVaidya DATE 04/05/10 040/5/10 12124/09 03/23/10 04/08/10 04/12/10 04/12/10 OFFICIAL RECORD COpy}} | ||
Revision as of 04:02, 1 May 2019
| ML100890188 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 04/12/2010 |
| From: | Bhalchandra Vaidya Plant Licensing Branch 1 |
| To: | Entergy Nuclear Operations |
| vaidya B K, NRR/Dorl/lpl1-1, 415-3308 | |
| References | |
| TAC ME2809 | |
| Download: ML100890188 (11) | |
Text
UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 April 12, 2010 Vice President, Operations Entergy Nuclear Operations, Inc. James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093 JAMES A. FITZPATRICK NUCLEAR POWER PLANT -ISSUANCE OF AMENDMENT RE: REFERENCE TO CURRENT CODE OF RECORD IN TECHNICAL SPECIFICATION 5.5.7INSERVICE TESTING PROGRAM (TAC NO. ME2809)
Dear Sir or Madam:
The Commission has issued the enclosed Amendment N0296 to Renewed Facility Operating License No.
DPR-59 for the James A. FitzPatrick Nuclear Power Plant. The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated November 23, 2009, as supplemented by letter dated February 5, 2010. The amendment modified the TS 5.5.7, "Inservice Testing Program," by replacing the references from the American Society Of Mechanical Engineers Boiler and Pressure Vessel Code to the current Code of Record, ASME Operation and Maintenance Nuclear Power Plants Code (ASME OM Code), the Code of Record for the James A. FitzPatrick Nuclear Power Plant (JAFNPP). This is an administrative amendment to maintain the TS current with the NRC accepted Code of Record for JAFNPP Inservice Testing Program. 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,
/' . Bhalchandra K. Vaidya, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-333
Enclosures:
- 1. Amendment No. 296 to DPR-59 2. Safety Evaluation cc w/encls: Distribution via Listserv UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555*0001 ENTERGY NUCLEAR FITZPATRICK, LLC AND ENTERGY NUCLEAR OPERATIONS, INC. DOCKET NO. 50-333 JAMES A. FITZPATRICK NUCLEAR POWER PLANT AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment NO.296 Renewed Facility Operating License No. DPR-59 The Nuclear Regulatory Commission (the Commission) has found that: The application for amendment by Entergy Nuclear Operations, Inc. (the licensee) dated November 23, 2009, as supplemented by letter dated February 5, 2010, 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; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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; 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 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. 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 Renewed Facility Operating License No. DPR-59 is hereby amended to read as follows:
-2Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.296 ,are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications. This license amendment is effective as of the date of its issuance and shall be implemented within 30 days. FOR THE NUCLEAR REGULATORY COMMISSION Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance:
Apr; 1 12, 2010 ATTACHMENT TO LICENSE AMENDMENT NO. RENEWED FACILITY OPERATING LICENSE NO. DOCKET NO. 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 Page 3 Page 3 Replace the following page of the Appendix A Technical Specifications with the attached revised page. The revised page is identified by amendment number and contain marginal lines indicating the areas of change. Remove Page Insert Page 5.5-6 5.5-6 ENO pursuant to the Act and 10 CFR Parts 30, 40, and 70 to receive, possess, and use, at any time, any byproduct, source and special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration; or associated with radioactive apparatus, components or tools .. Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below: Maximum Power Level ENO is authorized to operate the facility at steady state reactor core power levels not in excess of 2536 megawatts (thermal). Technical Specifications The Technical Specifications contained in Appendix A , as revised through Amendment N0296, are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications. Fire Protection ENO shall implement and maintain in effect all provisions of the approved fire protections program as described in the Final Safety Analysis Report for the facility and as approved in the SER dated November 20, 1972; the SER Supplement No.1 dated February 1, 1973; the SER Supplement NO.2 dated October 4, 1974; the SER dated August 1, 1979; the SER Supplement dated October 3, 1980; the SER Supplement dated February 13, 1981; the NRC Letter dated February 24, 1981; Technical Specification Amendments 34 (dated January 31, 1978),80 (dated May 22, 1984), 134 (dated JUly 19, 1989), 135 (dated September 5, 1989), 142 (dated October 23, 1989), 164 (dated August 10, 1990), 176 (dated January 16, 1992), 177 (dated February 10, 1992), 186 (dated February 19, 1993),190 (dated June 29,1993),191 (dated July 7,1993),206 (dated February 28, 1994) and 214 (dated June 27, 1994); and NRC Exemptions and associated safety evaluations dated April 26, 1983, July 1, 1983, January 11, 1985, April 30, 1986, September 15, 1986 and September 10, 1992 subject to the following provision:
Amendment 296 5.5 Programs and Manuals 5.5 Programs and Manuals 5.5.6 Primary Containment Leakage Rate Testing Program (continued) The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program. Nothing in these Technical Specifications shall be construed to modify the testing Frequencies required by 10 CFR 50, Appendix J.
5.5.7 Inservice Testing Program This program provides controls for inservice testing of certain ASME Code Class 1, 2, and 3 pumps and valves. The program shall include the following: Testing Frequencies specified in the ASME OM Code and applicable Addenda are as follows:
ASME OM Code and applicable Addenda terminology for Required Frequencies inservice testing for performing inservice activities testing activities Quarterly or every 3 months At least once per 92 days Biennially or every 2 years At least once per 731 days The provisions of SR 3.0.2 are applicable to the above required Frequencies for performing inservice testing activities; The provisions of SR 3.0.3 are applicable to inservice testing activities; and (continued) 5.5-6 Amendment2..9.6.....
UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.296 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-59 ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333
1.0 INTRODUCTION
By letter dated November 23, 2009, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML09331 0429), as supplemented by letter dated February 5, 2010 (ADAMS Accession No. ML 100480039), Entergy Nuclear Operations, Inc. (the licensee) submitted a request for changes to the James A. FitzPatrick Nuclear Power Plant (JAFNPP) Technical Specifications (TS). The supplement dated February 5, 2010, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the staff's original proposed no significant hazards consideration determination as published in the Federal Register on January 26, 2010 (75 FR 4117). The proposed amendment would modify the TS 5.5.7, lnservice Testlnq Program, by replacing the references from the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code)Section XI, to the ASME Operation and Maintenance Nuclear Power Plants Code (ASME OM Code), the current Code of Record for the JAFNPP Inservice Testing Program (1ST). The proposed amendment would also remove certain testing frequencies in TS 5.5.7a that are not applicable to JAFNPP TSs and be consistent with the requirements of Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(f)(4) for 1ST of pumps and valves. This is an administrative amendment to maintain the TS current with the NRC accepted Code of Record for JAFNPP 1ST Program.
2.0 REGULATORY EVALUATION
In 1990, the ASME published the initial edition of the ASIVIEOM Code, which provides requirements for 1ST of pumps and valves. The ASME OM Gode was developed and is maintained by the ASIVIE Committee on Operation and Maintenance of Nuclear Power Plants. The ASME OM Code was developed in response to the ASf,1E Board on Nuclear Codes and Standards directive that transferred responsibility for development and maintenance of requirements for the 1ST of pumps and valves from the Section XI Subcommittee on Nuclear Inservice Inspection to the ASME OM Committee. The ASME intended the ASME OM Code to replace Section XI rules for 1ST of pumps and valves.Section XI requirements for 1ST of pumps and valves were deleted from Section XI in the 2000 Addenda. The JAFNPP fourth 10-year interval 1ST program was developed to meet the requirements of the 2001 Edition with the 2002
-2and 2003 Addenda of the ASME OM Code pursuant to 10 CFR 50.55a(f)(4)(ii) as required by 10 CFR 50.55a(f)(4).
The regulatory requirements related to the content of TS are contained in 10 CFR 50.36. That regulation requires that the TS include items in the following specific categories: (1) safety limits, limiting safety systems settings, and limiting control settings, (2) limiting conditions for operation, (3) surveillance requirements, (4) design features, and (5) administrative controls.
The changes were reviewed for compliance with the requirements for 1ST as contained in 10 CFR 50.55a(f)( 4) for ASME Code Class 1, 2, and 3 pumps and valves. Guidance on the acceptability of the ASME OM Code is provided in Regulatory Guide 1.192, "Operations and Maintenance Code Case Acceptability, ASME OM Code," June 2003.
3.0 TECHNICAL EVALUATION 3.1 Specific Changes Reguested The licensee has proposed the following changes to the JAFNPP TS: For TS Section 5.5.7.a, the reference to Section XI of the ASME Code for 1ST requirements would be replaced with ASME OM Code. The weekly, monthly, semiannually or every 6 months, every 9 months, and yearly or annually 1ST frequencies in TS Section 5.5.7.a would be deleted.
3.2 Basis for Changes TS 5.5.7.a establishes controls for 1ST of ASME Class 1,2, and 3 pumps and valves required to satisfy the requirements in 10 CFR 50.36. TS Section 5.5.7.a currently referencesSection XI of the ASME Code as the source of requirements for the 1ST of ASME Code Class 1, 2, and 3 pumps and valves.
The regulations in 10 CFR 50.55a(f)( 4) establish the effective Code edition and addenda to be used by licensees for performing 1ST of pumps and valves. The regulations in 10 CFR 50.55a(f)(4)(ii) require licensees to update their 1ST program to the latest approved edition and addenda of the ASME OM Code incorporated by reference into 10 CFR 50.55a(b). The licensee states that the 1ST Program for the JAFNPP fourth interval was updated to comply with the appropriate revisions of the ASME OM Code and included the 2001 Edition with the 2002 and 2003 Addenda as the new Code of Record for performing 1ST at JAFNPP. As a consequence, the TS 5.5.7.a reference to Section XI of the ASME Code results in a reference to a deleted portion of the Code. The weekly, monthly, semiannually or every 6 months, every 9 months, and yearly or annually 1ST frequencies currently in TS Section 5.5.7.a are not applicable to the pumps and valves included in the JAFNPP TS and, therefore, can be deleted.
-3 3.3 Evaluation In 1990, the ASME published the initial edition of the ASME OM Code, which provides requirements for 1ST of pumps and valves. The OM Code was developed and is maintained by the ASME Committee on Operation and Maintenance of Nuclear Power Plants. The ASME OM Code was developed in response to the ASME Board on Nuclear Codes and Standards directive that transferred responsibility for development and maintenance of rules for the 1ST of pumps and valves from the ASME Section XI Subcommittee on Nuclear Inservice Inspection to the ASME OM Committee. The ASME intended the ASME OM Code to replace Section XI rules for 1ST of pumps and valves, and the Section XI rules for 1ST of pumps and valves were deleted from Section XI in the 2000 Addenda. The JAFNPP fourth 1O-year interval 1ST program was updated to comply with the 2001 Edition with the 2002 and 2003 Addenda of the ASME OM Code as required by 10 CFR 50.55a(f)(4)(ii). As a consequence, the TS 5.5.7.a reference to Section XI of the ASME Code for 1ST requirements results in a reference to a deleted portion of the ASME Code. The TS changes do not eliminate any tests and do not relinquish the licensee of its responsibility to seek NRC authorization of alternatives to the Code or grant relief from Code test requirements when they are impractical. The proposed change will eliminate the ASME Code inconsistency between the 1ST program and the TSs; therefore, the NRC staff finds these proposed changes to be acceptable. The NRC staff also finds that deletion of the weekly, monthly, semiannually or every 6 months, every 9 months, and yearly or annually 1ST frequencies currently in TS Section 5.5.7.a acceptable. This TS change is administrative in nature and only deletes 1ST frequencies that are not applicable to the Class 1, 2, and 3 pumps and valves included in the JAFNPP TSs.
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 surveillance requirements. 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 (75 FR 4117). 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
Based on the above discussion, the Commission has concluded 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. Principal S. Tingen, NRR V Cusumano, NRR Date: April 12, 2010 April 12, 2010 Vice President, Operations Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093 JAMES A. FITZPATRICK NUCLEAR POWER PLANT -
ISSUANCE OF AMENDMENT RE: REFERENCE TO CURRENT CODE OF RECORD IN TECHNICAL SPECIFICATION 5.5.7 INSERVICE TESTING PROGRAM (TAC NO. ME2809)
Dear Sir or Madam:
The Commission has issued the enclosed Amendment No. 296 to Renewed Facility Operating License No. DPR-59 for the James A. FitzPatrick Nuclear Power Plant. The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated November 23, 2009, as supplemented by letter dated February 5, 2010.
The amendment modified the TS 5.5.7, "Inservice Testing Program," by replacing the references from the American Society Of Mechanical Engineers Boiler and Pressure Vessel Code to the current Code of Record, ASME Operation and Maintenance Nuclear Power Plants Code (ASME OM Code), the Code of Record for the James A. FitzPatrick Nuclear Power Plant (JAFNPP). This is an administrative amendment to maintain the TS current with the NRC accepted Code of Record for JAFNPP Inservice Testing Program. 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, /raJ Bhalchandra K. Vaidya, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-333
Enclosures:
- 1. Amendment No. 296 to DPR-59
- 2. Safety Evaluation cc w/encls:
Distribution via Listserve DISTRIBUTION: PUBLIC LPL1-1 R/F RidsNrrDorlLPL1-1 RidsOGCMailCenter RidsNrrDirsltsb RidsAcrsAcnwMailCenter RidsNrrPMFitzPatrick RidsNrrLASLittle (paper copy) MGray, RI RidsNrrDciCptb STingen, NRR/CPTB VCusumano, NRR/ITSB ADAMS Accession No.: ML 100890188 (*) No substantial change to SE Input Memo OFFICE LPL 1-lIPM LPL 1-1/LA NRR/CPTB/BC(*)
NRR/ITSB/BC(*)
OGC LPL 1-1/BC LPL1-1/PM NAME BVaidya SLittie AMcMutray RElliot AJones NSalQado BVaidya DATE 04/05/10 040/5/10 12124/09 03/23/10 04/08/10 04/12/10 04/12/10 OFFICIAL RECORD COpy