ML100431613
| ML100431613 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 03/08/2010 |
| From: | James Kim Plant Licensing Branch 1 |
| To: | Vermont Yankee |
| kim J, NRR/ADRO/DORL, 415-4125 | |
| References | |
| Download: ML100431613 (10) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March A, 2010 Site Vice President Entergy Nuclear Operations, Inc.
Vermont Yankee Nuclear Power Station P.O. Box 250 Governor Hunt Road Vernon, VT 05354
SUBJECT:
VERMONT YANKEE NUCLEAR POWER STATION -ISSUANCE OF AMENDMENT RE: SAFETY LIMIT MINIMUM CRITICAL POWER RATIO CHANGE (TAC NO. ME2462)
Dear Sir or Madam:
The Commission has issued the enclosed Amendment No. 243 to Facility Operating License DPR-28 for the Vermont Yankee Nuclear Power Station, in response to your application dated October 27,2009.
The proposed amendment would modify the Technical Specifications to provide revised values for the Safety Limit Minimum Critical Power Ratio for both single and dual recirculation loop operation.
A copy of the related Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely, James Kim, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation' Docket No. 50-271
Enclosures:
- 1. Amendment No.243 to License No. DPR-28
- 2. Safety Evaluation cc w/encls: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 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. 243 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 licensee) dated October 27,2009, 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
- 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. 2113, are hereby incorporated in the license. Entergy Nuclear Operations, Inc. 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
~/~
Nancy L.:. Salgado, Chief Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the License and Technical Specifications Date of Issuance: March R. 2010
ATTACHMENT TO LICENSE AMENDMENT NO. 2~3 FACILITY OPERATING LICENSE NO. DPR-28 DOCKET NO. 50-271 Replace the following page of the Facility Operating License with the attached revised page.
The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
Remove Insert 3
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 Insert 6
6
- 3 E.
Entergy Nuclear Operations, Inc., pursuant to the Act and 10 CFR Parts.30 and 70, to possess, but not to separate, such byproduct and special nuclear material as may be produced by operation of the facility.
- 3. This license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations: 10 CFR Part 20. Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Section 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR 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 below:
A.
Maximum Power Level Entergy Nuclear Operations, Inc. is authorized to operate the facility at reactor core power levels not to exceed 1912 megawatts thermal in accordance with the Technical Specifications (Appendix A) appended hereto.
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment NO.243 are hereby incorporated in the license. Entergy Nuclear Operations, Inc. shall operate the facility in accordance with the Technical Specifications.
C.
Reports Entergy Nuclear Operations, Inc. shall make reports in accordance with the requirements of the Technical Specifications.
D.
This paragraph deleted by Amendment No. 226.
E.
Environmental Conditions Pursuant to the Initial Decision of the presiding Atomic Safety and Licensing Board issued February 27, 1973, the following conditions for the protection of the environment are incorporated herein:
Amendment No.-200, 200, 226, ~, aso, 2J.+, ~, 233, 234, 235,236, 237, 238, 239,240,241,242,243
VYNPS 1.1 SAFETY LIMIT 1.I" FUEL CLADDING INTEGRITY Applicability:
Applies to the interrelated variable associated with fuel thermal behavior.
Objective:
To establish limits be'Low which the integrity of the fuel cladding is preserved.
Specification:
A.
Bundle Safety Limit (Reactor Pressure >800 psia and Core Flow
>10% of Rated)
When the reactor pressure is
>800 psia and the core flow is greater than 10% of rated:
- 1. A Minimum Critical Power Ratio (MCPR) of less than 1.09 (1.10 for Single Loop Operation) shall constitute violation of the Fuel Cladding Integrity Safety Limit (FCISL).
2.1 LIMITING SAFETY SYSTEM SETTING 2.1 FUEL CLADDING INTEGRITY Applicability:
Applies to trip setting of the instruments and devices which are provided to prevent the nuclear system safety limits from being exceeded.
Objective:
To define the level of the process variable at which automatic protective action is initiated.
Specification:
A.
Trip Settings The limiting safety system trip settings shall be as specified below:
- 1. Neutron Flux Trip Settings
- a.
APRM Flux Scram Allowable Value (Run Mode)
When the mode switch is in the RUN position, the APRM flux scram Allowable Value shall be:
Two loop operation:
S~ 0.33W+ 50.45% for 0% < W
~ 30.9%
S~ 1.07W+ 27.23% for 30.9% < W
~ 66.7%
S~ 0.55W+ 62.34% for 66.7% < W :5 99.0%
With a maximum of 117.0% power for W >
99.0%
Single loop operation:
S~ 0.33W+ 48.00% for 0% < W s 39.i%
S~ 1.07W+ 19.01% for 39.1% <.W s 61. 7%
S~ 0.55W+ 51.22% for 61.7% < W s 119.4%
With a maximum of 117.0% power for W >
119.4%
where:
S setting in percent of rated thermal power (1912 MWt)
Amendment No. ~, 4+, ~, %, -!f4,.~, ~, ~, H-6-,'.;H-+, ~, ~,243 6
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.243TO 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 October 27,2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML093070061), Entergy Nuclear Operations, Inc. (the licensee) submitted a request to amend the Vermont Yankee Nuclear Power Station (VY) Technical Specification (TS). The proposed amendment would increases the numeric values of Safety Limit Minimum Critical Power Ratio (SLMCPR) in TS Section 1.1.A.1 from 1.07 to 1.09 for two recirculation loop operation (TLO) and from 1.09 to 1.10 for single recirculation loop operation (SLO).
On the basis of the calculations for VY core reload analysis for Operating Cycle 28, the calculated SLMCPR increases from 1.07 to 1.09 for TLO and SLMCPR increases from 1.09 to 1.10 for SLO. Accordingly, VY TS Section 1.1.A.1 is revised to read as follows:
A Minimum Critical Power Ratio (MCPR) of less than 1.09 (1.10 for Single Loop Operation) shall constitute violation of the Fuel Cladding Integrity Safety Limit (FCISL).
2.0 REGULATORY EVALUATION
It is stated in Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36 that the Safety Limits (SL) are limits upon important process variables that are found to be necessary to reasonably protect the integrity of certain physical barriers that guard against the uncontrolled release of radioactivity. The SLMCPR is a SL that is required to be in TS to ensure that fuel design limits are not exceeded. VY TS 1.1.A.1 contains the unit SLMCPR limit, which can vary from cycle to cycle. A Nuclear Regulatory Commission (NRC) approved methodology, contained in GESTAR II, NEDE-24011-P-A, "General Electric Standard Application for Reactor Fuel,"
Amendment 22, is used to determine the cycle specific limit to be listed in TS 1.1.A.1.
NUREG-0800, "Standard Review Plan for the Review of Safety Analyses Reports for Nuclear Power Plants," Section 4.4, "Thermal and Hydraulic Design," states that the critical power ratio (CPR) is to be established such that at least 99.9 percent of fuel rods in the core would not be expected to experience departure from nucleate boiling or boiling transition during normal operation or anticipated operational occurrences.
- 2 The NRC staff considers that the information submitted by the licensee in support of the proposed license amendment is consistent with the regulatory requirements.
3.0 TECHNICAL EVALUATION
As stated earlier, the SLMCPR numeric values in VY TS 1.1.A.1 are SL. The SLMCPR limit is established such that at least 99.9% of the fuel rods in the core would not be expected to experience the onset of transition boiling as a result of normal operation and transients, which in turn ensures fuel cladding damage does not occur. The SLMCPR limit is established such that fuel design limits are not exceeded during steady state operation, normal operational transients, and abnormal operational transients. As such, fuel damage is calculated not to occur if the limit is not violated. However, because fuel damage is not directly observable, a step back approach is used to establish corresponding MCPR operating limits. The Operating Limit MCPR (OLMCPR) is established by summing the cycle-specific core reload transient analyses adders and the calculated SLMCPR values. The OLMCPR are required to be established and documented in the Core Operating Limits Report (COLR) for each reload cycle.
The absolute value of SLMCPR tends to vary cycle-to-cycle, typically due to the introduction of improved fuel bundle types, changes in fuel vendors, and changes in core loading pattern.
Following the determination of the cycle-specific SLMCPR values, the OLMCPR values are derived. The cycle-specific SLMCPR numeric values are listed in TS 1.1.A.1, and therefore, must be revised using the license amendment process.
Global Nuclear Fuel (GNF) performed the VY Cycle 28 SLMCPR calculation consistent with NRC-approved methodologies and uncertainties, as documented in licensing topical reports (LTRs), I\\JEDE-24011-P-A "General Electric Standard Application for Reactor Fuel," Revision 16 (GESTARII), and the following LTRs:
NEDC-3260'1P-A "Methodology and Uncertainties for Safety Limit MCPR Evaluations,"
August 1999.
f\\lEDC-32694P-A "Power Distribution Uncertainties for Safety Limit MCPR Evaluations,"
AUgust 1999.
NEDC-32505P-A "R-Factor Calculation Method for GE 11, GE 12 and GE 13 Fuel,"
Revision 1, July 1999.
NEDO-10958-A "General Electric BWR Thermal Analysis Basis (GETAB): Data, Correlation and Design Application," January 1977.
On the basis of the analysis performed by GNF, the licensee has proposed to amend the VY TS Section 1.1.A.1 to revise the SLMCPR for the Operating Cycle 28. Cycle 28 core design includes GNF2 and GE14 fuel types. Based upon the core loading and fuel design change, the cycle specific SLMCPR values were determined to be 1.09 for dual recirculation loop and 1.10 for single recirculation loop operation.
By letter dated August 29, 2008, GNF submitted to the NRC a report titled, "GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR II), NEDC-333270P, Revision 1." This NRC-approved report provides generic information relative to the GNF2 fuel design and analysis applicable to boiling-water reactors.
- 3 GNF's calculation of the revised plant-specific SLMCPR numeric values for VY Cycle 28 was performed as part of the reload licensing analysis for VY Cycle 28 and is based upon NRC approved methods, and it is acceptable. The NRC staff agrees that the available flow range at rated power, 99% to 100% rated core flow (as shown in the power vs. flow map), does not warrant analysis at the minimum core flow point.
For VY Cycle 28, the additional SLlVlCPR licensing condition that the SLMCPR shall be established by adding 0.02 to the cycle-specific TLO SLMCPR value calculated using the NRC approved methodologies documented in NEDE-24011-P-A has been applied. This addition of 0.02 does not apply to the cycle-specific SLO SLMCPR, because such operation would be limited by TS to less than the 1593 MWt power threshold.
In consideration of the information submitted by the licensee in support of the proposed license amendment, as summarized in this safety evaluation (SE), the NRC staff's SE has concluded that the licensee's proposed amendment to update the TS to include cycle-specific SLMCPR numeric values is consistent with the regulatory requirements, and is acceptable. The licensee is authorized to change the SLMCPR as existing in TS 1.1.A.1 from 1.07 to 1.09 for dual-loop recirculation, and from 1.09 to 1.10 for single-loop recirculation, at steam dome pressures greater than 785 psig and at core flows greater than 10 percent of rated core flow.
4.0 STATE CONSULTATION
In accordance with the Commission's 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 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 (75 FR 461). 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.
Principal Contributor: M. Razzaque Date: March 8, 2010
March 8, 2010 Site Vice President Entergy Nuclear Operations, Inc.
Vermont Yankee Nuclear Power Station P.O. Box 250 Governor Hunt Road Vernon, VT 05354
SUBJECT:
VERMONT YANKEE NUCLEAR POWER STATION - ISSUANCE OF AMENDMENT RE: SAFETY LIMIT MINIMUM CRITICAL POWER RATIO CHANGE (TAC NO. ME2462)
Dear Sir or Madam:
The Commission has issued the enclosed Amendment No. 243 to Facility Operating License DPR-28 for the Vermont Yankee Nuclear Power Station, in response to your application dated October 27, 2009.
The proposed amendment would modify the Technical Specifications to provide revised values for the Safety Limit Minimum Critical Power Ratio for both single and dual recirculation loop operation.
A copy of the related Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely, IRA!
James Kim, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-271
Enclosures:
- 1. Amendment No. 243 to License No. DPR-28
- 2. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION:
PUBLIC M. Razzaque, NRR RidsRgn1 MailCenter RidsN rrDorlLpl1-1 Resou rce RidsNrrLASUttle D. Jackson, RI RidsNrrDssSrxb Resource RidsNrrDorlDpr Resource RidsNrrPMVermontYankee RidsNrrDirsltsb Resource RidsAcrsAcnw_MailCenter Resource RidsOgcMailCenter Resource Accession N ML100431613
- See memo d t d F b a e e ruary 4 2010 0.:
OFFICE LPL 1-1/PM LPL 1-1/LA SRXB/BC OGC/NLO LPL 1-1/BC NAME
~IKim SLittie GCranston*
LSubin (w/comments)
NSalgado DATE 2/18/2010 2/18/2010 2/4/2010 2/24/2010 3/08/10 OFFICIAL RECORD COpy