ML102460401

ME3786, Letter - Issuance of Amendment to Renewed FOL SLMCPR

ML102460401
Person / Time
Site:	FitzPatrick
Issue date:	09/27/2010
From:	Bhalchandra Vaidya Plant Licensing Branch 1
To:	Entergy Nuclear Operations
vaidya b k
References
TAC ME3786
Download: ML102460401 (12)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 27, 2010 Vice President, Operations Entergy Nuclear Operations, Inc.

James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093

SUBJECT:

JAMES A. FITZPATRICK NUCLEAR POWER PLANT -ISSUANCE OF AMENDMENT RE: CHANGES TO THE SAFETY LIMIT MINIMUM CRITICAL POWER RATIO (TAC NO. ME3786)

Dear Sir or Madam:

The Commission has issued the enclosed Amendment No. 299 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 April 21, 2010 as supplemented by letters dated July 28, and September 2, 2010.

The amendment revised James A. FitzPatrick TS 2.0, "Safety Limits (SLs)." Specifically, TS 2.1.1.2 was revised to replace the listed safety limit minimum critical power ratio values of 1.07 for two recirculation loop operation and 1.09 for single recirculation loop operation with new values of 1.08 and 1.11, respectively.

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. 299 to DPR-59

2. Safety Evaluation cc w/encls: Distribution via Listserv

UNITED STATES NUCLEAR REGULATORY COMMISSION 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. 299 Renewed Facility Operating License No. DPR-59

1. The Nuclear Regulatory Commission (the Comrnisslon) has found that:

A. The application for amendment by Entergy Nuclear Operations, Inc. (the licensee) dated April 21, 2010 as supplemented by letters dated July 28, and September 2,2010, 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; 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 (il) 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 Renewed Facility Operating License No. DPR-59 is hereby amended to read as follows:

-2 (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment NO.299 ,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 its issuance and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION

~,~'i ~ ~r-4 Nancy L. Salgado, Chief 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: September 27, 2010

ATTACHMENT TO LICENSE AMENDMENT NO. 299 RENEWED FACILITY OPERATING LICENSE NO. DPR-59 DOCKET NO. 50-333 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 contains marginal lines indicating the areas of change.

Remove Page Insert Page 2.0-1 2.0-1

-3 (4) 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 ..

(5) 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.

C. 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:

(1) Maximum Power Level ENO is authorized to operate the facility at steady state reactor core power levels not in excess of 2536 megawatts (thermal).

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 29~ are hereby incorporated in the renewed operating license.

The licensee shall operate the facility in accordance with the Technical Specifications.

(3) 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 299

SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1 With the reactor steam dome pressure < 785 pslg or core flow

< 10% rated core flow:

THERMAL POWER shall be S 25% RTP.

2.1.1.2 With the reactor steam dome pressure ~ 785 psig and core flow

~ 10% rated core flow:

MCPR shall be ~ 1.08 for two recirculation loop operation or

~ 1.11 for single recirculation loop operation.

2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel.

2.1.2 Reactor Coolant System Pressure SL Reactor steam dome pressure shall be S 1325 psig.

2.2 SL Violations With any SL violation, the following actions shall be completed within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:

2.2.1 Restore compliance with all SLs; and 2.2.2 Insert all insertable control rods.

JAFNPP 2.0-1 Amendment 299

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 299 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 April 21, 2010 (Agencywide Documents Access and Management System (ADAMS) Package Accession No. ML101170218. Reference 1), as supplemented by letters dated July 28 and September 2,2010 (ADAMS Package Accession Nos. ML102140476 and ML102460107, respectively, References 2 and 3), Entergy Nuclear Operations, Inc. (the licensee) submitted a request for changes to the James A. FitzPatrick Nuclear Power Plant (JAFNPP) Technical Specifications (TS). The supplements dated July 28 and September 2, 2010, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the NRC staffs original proposed no significant hazards consideration determination.

The proposed amendment would revise JAFNPP TS 2.0, "Safety Limits (SLs)." Specifically, TS 2.1.1.2 would be revised to replace the listed safety limit minimum critical power ratio (SLMCPR) values of 1.07 for two recirculation loop operation and 1.09 for single recirculation loop operation with new values of 1.08 and 1.11, respectively for the JAFNPP Cycle 20 operation. The JAFNPP Cycle 20 core has 560 GE fuel assemblies, of which there are 200 fresh GNF2 bundles, 200 once burned GNF2 bundles, and 160 twice burned GE14 bundles.

2.0 REGULATORY EVALUATION

The following explains the use of general design criteria for JAFNPP. The construction permit for JAFNPP was issued by the Atomic Energy Commission (AEC) on May 20, 1970. and the operating license was issued on October 17, 1974. The plant design criteria for the construction phase are listed in the Updated Final Safety Analysis Report (UFSAR) Chapter 1.5, "Principal Design Criteria." The AEC published the final rule that added Appendix A to Title 10 of the Code of Federal Regulations (10 CFR) Part 50, "General Design Criteria (GDC) for Nuclear Power Plants," in the Federal Register (36 FR 3255) on February 20, 1971, with the rule effective on May 21, 1971. In accordance with a U.S. Nuclear Regulatory Commission (NRC) staff requirements memorandum from S. J. Chilk to J. M. Taylor, "SECY-92-223 - Resolution of Deviations Identified During the Systematic Evaluation Program," dated September 18, 1992 (ADAMS Accession No. ML003763736), the Commission decided not to apply the final GDC to plants with construction permits issued prior to May 21, 1971, which includes JAFNPP.

However, the JAFNPP UFSAR, Chapter 16.6, "Conformance to AEC Design Criteria," evaluates

- 2 JAFNPP against the 10 CFR Part 50 Appendix A GDC. Also, the initial AEC safety evaluation of JAFNPP, dated November 20, 1972, Chapter 14.0, stated "Based on our evaluation of the design and design criteria for the James A. FitzPatrick Nuclear Power Plant, we conclude that there is reasonable assurance that the intent of the General Design Criteria for Nuclear Power Plants, published in the Federal Register on May 21, 1971 as Appendix A to 10 CFR Part 50, will be met." Therefore, the NRC staff reviews amendments to the JAFNPP license using the 10 CFR Part 50 Appendix A GDC unless there are specific criteria identified in the UFSAR.

The purpose of the SLMCPR is to ensure that specified acceptable fuel design limits (SAFDLs) are not exceeded during steady state operation and analyzed transients. The fuel cladding is one of the physical barriers that separate the radioactive materials from the environment. The integrity of this cladding barrier is related to its relative freedom from perforations or cracking.

Fuel cladding perforations can result from thermal stresses, which can occur from reactor operation significantly above design conditions. Since the parameters that result in fuel damage are not directly observable during reactor operation, the thermal and hydraulic conditions that result in the onset of transition boiling have been used to mark the beginning of the region in which fuel cladding damage could occur.

The NRC staff used the following regulatory criterion and guidance document:

(1) Criterion 10, "Reactor Design," of Appendix A, General Design Criteria for Nuclear for Nuclear Power Plants, to 10 CFR Part 50 states, in part, that the reactor core and associated coolant, control, and protection systems shall be designed with appropriate margin to assure that SAFDLs are not exceeded.

(2) NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants," provides guidance on the acceptability of the reactivity control systems, the reactor core and fuel system design. Specifically, Section 4.2, "Fuel System Design," specifies all fuel damage criteria for evaluation of fuel designs to meet the requirements of SAFDLs. Section 4.4, "Thermal Hydraulic Design," provides guidance on the review of thermal-hydraulic design in meeting the requirements of GDC 10 and the fuel design criteria established in Section 4.2.

3.0 TECHNICAL EVALUATION

3.1 Description of Proposed Changes The licensee requested a change to the JAFNPP Facility Operating License in accordance with the provisions of 10 CFR 50.90. The revised TS 2.1.1.2 was proposed as follows:

The SLMCPR is proposed to change from 1.07 to 1.08 for two recirculation loop operation, and to change from 1.09 to 1.11 for single loop operation. These SLMCPR values are for the reactor steam dome pressure ~ 785 psig and core flow ~ 10 percent of rated core flow.

3.2 Discussion of Technical Evaluation The licensee described the methodology to calculate the new SLMCPR values for the TS in its submittal and supplements. The Cycle 20 SLMCPR analysis was performed by Global Nuclear Fuel (GNF) using the plant- and cycle-specific fuel and core parameters, NRC approved

-3 methodologies including GESTAR-II (NEDE-24011-P-A-16), NEDE-32505P-A, Revision 1 (R-Factor Calculation Method for GE 11, GE 12 and GE 13 Fuel), NEDC-3260'1P-A (Methodology and Uncertainties for Safety Limit MCPR Evaluations), NEDC-32694P-A (Power Distribution Uncertainties for Safety Limit MCPR Evaluation), and NEDO-10958-A (General Electric Boiling Water Reactor Thermal Analysis Basis (GETAB): Data, Correlation, and Design Application).

The licensee addressed the applicability of the above approved methodologies to the JAF Cycle 20 SLMCPR calculation (References 2 and 3) because there are 200 fresh and 200 once burned GNF2 fuels, whose data bases were not included in those approved methodologies.

The NRC staff reviewed the licensee's justification for applying these methodologies to the Cycle 20 SLMCPR calculation, as well as the NRC staff's report (ML081630579) on the "Global Nuclear Fuels (GNF) GNF2 Advanced Fuel Assembly Design GESTAR II Compliance Audit,"

based on the "GESTAR II compliance report for GNF2, NEDE-33270P, Revision 0, FLN-2007 011, March 14,2007." The NRC staff concluded that the justification is acceptable because GNF2 fuel meets the requirements as specified in limitations and conditions of the approved methodologies.

In the August 10. 2010, NRC staff audit and in the response to the staff request for additional information (RAts), (References 2 and 3), the licensee also addressed: (1) the final core loading pattern selection for the JAF Cycle 20 operation with respect to the combination of the input parameters such as cycle energy requirements, thermal limit margins, reactivity margins, discharge exposure limitations and other limits, desired control rod patterns, and channel distortion; (2) the SLMCPR calculation process with respect to the uncertainties associated with R-Factor, and core flow rate and random effective traversing in-core probe (TIP) reading; and (3) operating margin adjustments for the GNF2 fuel assembly corner rod flow wing manufacturing defect.

The NRC staff reviewed the information presented in the audit and the responses to the staff RAls and concluded that the licensee provided sufficient data and description (References 2 and 3) to satisfactorily answer the staff RAls. Therefore, the proposed TS changes to the SLMCPR values for JAF Cycle 20 operation from 1.07 to 1.08 for two recirculation loop operation and from 1.09 to 1.11 for single loop operation are acceptable because:

(1) Approved methodologies are used with acceptable justification for the method deviation and adjusted uncertainties relating to R-Factor and TIP reading; (2) The result of evaluation on the GNF2 bent spacer wing for JAF Cycle 20 core shows insignificant thermal-hydraulic impact on the statistically based MCPR evaluation; (3) GNF2 data points are shown in the acceptable bound in the figure of relationship between MCPR Importance Parameter (MIP) and Critical Power Ratio margin; (4) Qualitative descriptions of the final core loading pattern and critical power analysis are provided; and (5) Core map was provided and dominant fuel bundle locations were identified based on the Fitzpatrick Cycle 20 SLMCPR calculation in terms of the percent contribution to number of rods subject to boiling transition (NRSBT).

The NRC staff has also reviewed the justification for the SLMCPR value of 1.08 for two recirculation loop operation and 1.11 for single loop operation using the approach stated in GESTAR-II, Revision 16. Based on our review of the licensee's submittals and the response to the NRC staff's RAls (References 2 and 3), the NRC staff audit with respect to the final core design, the SLMCPR calculation process, and the impact on the SLMCPR value due to the

-4 GNF2 bent spacer wing during Cycle 20 operation, the NRC staff has concluded that the SLMCPR analysis for JAF Cycle 20 operation using the plant- and cycle-specific calculation in conjunction with the approved method is acceptable. The Cycle 20 SLMCPR will ensure that 99.9 percent of the fuel rods in the core will not experience boiling transition, which satisfies the requirements of GDC 10 of Appendix A to 10 CFR Part 50 regarding acceptable fuel design limits. Therefore, the staff has concluded that the justification for analyzing and determining the SLMCPR value of 1.08 for two recirculation loop operation and 1.11 for single recirculation loop operation for JAFNPP is acceptable since approved methodologies were used in conjunction with assumption of a higher R-Factor uncertainty, performance of a bounding calculation at rated core power and minimum core flow, and analysis of power shape for Cycle 20 operation resulting in no penalty for fuel axial power shape.

3.2 Conclusion - Technical Evaluation Based on the above discussion, the NRC staff concludes that the proposed TS changes involving the SLMCPR values in TS 2.1.1.2 for both two loop and single loop operation are acceptable for JAFNPP Cycle 20 operation because the changes were analyzed based on the NRC-approved methods using JAFNPP cycle-specific inputs and the fuel bundles in the core for Cycle 20 operation.

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. 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 33841). 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 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.

- 5

7.0 REFERENCES

(1) Letter (JAFP-1 0-0050) from Pete Dietrich to USNRC, "Proposed Change to the James A. FitzPatrick Nuclear Power Plant's Technical Specification Concerning the Safety Limit Minimum Critical Power Ratio, James A. FitzPatrick Nuclear Power Plant Docket 50-333, License No. DPR-59," April 21, 2010.

(2) Letter (JAFP-1 0-0096) from Pete Dietrich to USNRC, "Response to Request for Additional Information Re: James A. FitzPatrick Nuclear Power Plant's Technical Specification Concerning the Safety Limit Minimum Critical Power Ratio (TAC No.

ME3786), James A FitzPatrick Nuclear Power Plant Docket No. 50-333, License No.

DPR-59," July 28,2010.

(3) Letter (JAFP-10-0122) from Pete Dietrich to USNRC, "Response to Follow-up Request for Additional Information Re: James A. FitzPatrick Nuclear Power Plant Proposed Changes to the James A. FitzPatrick Nuclear Power Plant's Technical Specification Concerning the Safety Limit Minimum Critical Power Ratio (TAC No. ME3786),

September 2,2010.

Principal Contributor: T. Huang Date: September 27, 2010

September 27, 2010 Vice President, Operations Entergy Nuclear Operations, Inc.

James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093

SUBJECT:

JAMES A. FITZPATRICK NUCLEAR POWER PLANT - ISSUANCE OF AMENDMENT RE: CHANGES TO THE SAFETY LIMIT MINIMUM CRITICAL POWER RATIO (TAC NO. ME3786)

Dear Sir or Madam:

The Commission has issued the enclosed Amendment No. 299 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 April 21, 2010 as supplemented by letters dated July 28, and September 2,2010.

The amendment revised James A. FitzPatrick TS 2.0, "Safety Limits (SLs)." Specifically, TS 2.1.1.2 was revised to replace the listed safety limit minimum critical power ratio values of 1.07 for two recirculation loop operation and 1.09 for single recirculation loop operation with new values of 1.08 and 1.11, respectively.

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. 299 to DPR-59

2. Safety Evaluation cc w/encls: Distribution via Listserve DISTRIBUTION:

PUBLIC LPL1-1 R/F RidsNrrDorlLPL 1-1 RidsOGCMailCenter RidsNrrDirsltsb RidsAcrsAcnwMailCenter RidsNrrPMFitzPatrickResource RidsNrrLASLittle (paper copy) MGray, RI ADAMS A ccessron . N0.: ML102460401 (*) No su bsan t tlra I cham es In t he SEI nput Memo OFFICE LPL1-1\PM LPL1-1\LA NRRISRXB/BC OGC LPL1-1\BC LPL1-1\PM NAME B. K. Vaidya SLittie AUlses (*) STurk NSalQado B. K. Vaidva DATE 09/15/10 09/15/10 09/07/10 09/23/10 09/27/10 09/27/10