ML24250A205
| ML24250A205 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 10/08/2024 |
| From: | Byrd T Plant Licensing Branch IV |
| To: | Dent J Nebraska Public Power District (NPPD) |
| Wengert T, NRR/DORL/LPLIV, 415-4037 | |
| References | |
| EPID L-2024-LLA-0063 | |
| Download: ML24250A205 (1) | |
Text
October 8, 2024 John Dent, Jr.
Executive Vice President and Chief Nuclear Officer Nebraska Public Power District 72676 648A Avenue P.O. Box 98 Brownville, NE 68321
SUBJECT:
COOPER NUCLEAR STATION - ISSUANCE OF AMENDMENT NO. 278 REGARDING REVISION TO TECHNICAL SPECIFICATION TABLE 3.3.2.1-1 AND TRANSFER OF MINIMUM CRITICAL POWER RATIO VALUES TO THE CORE OPERATING LIMIT REPORT (EPID L-2024-LLA-0063)
Dear John Dent:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 278 to Renewed Facility Operating License No. DPR-46 for Cooper Nuclear Station. The amendment consists of changes to the technical specifications (TSs) in response to your application dated May 9, 2024 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML24131A026).
The amendment revises TS table 3.3.2.1-1, Control Rod Block Instrumentation, to reference the core operating limits report and adds a reference to TS 5.6.5, Core Operating Limits Report (COLR).
J. Dent, Jr.
A copy of the related safety evaluation is also enclosed. Notice of Issuance will be included in the Commissions monthly Federal Register notice.
Sincerely,
/RA/
Thomas J. Byrd, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-298
Enclosures:
- 1. Amendment No. 278 to DPR-46
- 2. Safety Evaluation cc: Listserv
NEBRASKA PUBLIC POWER DISTRICT DOCKET NO. 50-298 COOPER NUCLEAR STATION AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 278 Renewed License No. DPR-46
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Nebraska Public Power District (the licensee) dated May 9, 2024, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-46 is hereby amended to read as follows:
(1)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 278, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
The license amendment is effective as of its date of issuance and shall be implemented October 30, 2024 to allow plant operation after the completion of refueling outage.
FOR THE NUCLEAR REGULATORY COMMISSION Jennivine K. Rankin, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to Renewed Facility Operating License No. DPR-46 and the Technical Specifications Date of Issuance: October 8, 2024 Jennivine K.
Rankin Digitally signed by Jennivine K. Rankin Date: 2024.10.08 11:01:31 -04'00'
ATTACHMENT TO LICENSE AMENDMENT NO. 278 RENEWED FACILITY OPERATING LICENSE NO. DPR-46 COOPER NUCLEAR STATION DOCKET NO. 50-298 Replace the following pages of Renewed Facility Operating License No. DPR-46 and 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.
Renewed Facility Operating License REMOVE INSERT Technical Specifications REMOVE INSERT 3.3-19 3.3-19 5.0-21 5.0-21
Amendment No. 278 (5) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by operation of the facility.
C. This 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; 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 The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 2419 megawatts (thermal).
(2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 278, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3) Physical Protection The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: Cooper Nuclear Station Safeguards Plan, submitted by letter dated May 17, 2006.
NPPD shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The NPPD CSP was approved by License Amendment No. 238 as supplemented by changes approved by License Amendments 244 and 249.
(4) Fire Protection NPPD shall implement and maintain in effect all provisions of the approved fire protection program that comply with 10 CFR 50.48(a) and 10 CFR 50.48(c), as specified in the license amendment request dated April 24, 2012 (and supplements dated July 12, 2012, January 14, 2013, February 12, 2013, March 13, 2013, June 13, 2013, December 12, 2013, January 17, 2014, February 18, 2014, and April 11, 2014), and as approved in the safety evaluation dated April 29, 2014.
Except where NRC approval for changes or deviations is required by 10 CFR 50.48(c), and provided no other regulation, technical specification, license condition or requirement would require prior NRC approval, the licensee may make changes to the fire protection program without prior approval of the Commission if
Control Rod Block Instrumentation 3.3.2.1 Table 3.3.2. 1-1 (page 1 of 1)
Control Rod Block Instrumentation FUNCTION 1.
Rod Block Monitor a.
Low Power Range - Upscale b.
Intermediate Power Range - Upscale c.
High Power Range - Upscale d.
lnop e.
Downscale 2.
- 3. Reactor Mode Switch - Shutdown Position APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS (a)
(d)
(e),(f)
(f),(g)
(f),(g)
(i)
REQUIRED CHANNELS 2
2 2
2 2
2 SURVEILLANCE REQUIREMENTS SR 3.3.2.1.1 SR 3.3.2.1.4 SR 3.3.2.1.5ib)(c)
SR 3.3.2.1.1 SR 3.3.2.1.4 SR 3.3.2.1.5Ib)(c)
SR 3.3.2.1.1 SR 3.3.2.1.4 SR 3.3.2.1.Slb)(c)
SR 3.3.2.1.1 SR 3.3.2.1.1 SR 3.3.2.1.5 SR 3.3.2.1.2 SR 3.3.2.1.3 SR 3.3.2.1.6 SR 3.3.2.1.8 SR 3.3.2.1. 7 U)
(j)
(j)
ALLOWABLE VALUE NA
- ,, 92/125 divisions of full scale NA NA (a) THERMAL POWER <.'. 27.5% and < 62.5% RTP and MCPR less than the limit specified in the COLR and no peripheral control rod selected.
{b) If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.
(c) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Limiting Trip Setpoint (L TSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the L TSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance procedures (Nominal Trip Setpoint) to confirm channel performance. The Limiting Trip Setpoint and the methodologies used to determine the as-found and the as-left tolerances are specified in the Technical Requirements Manual.
{d) THERMAL POWER<.'. 62.5% and< 82.5% RTP and MCPR less than the limit specified in the COLR and no peripheral control rod selected.
(e) THERMAL POWER<.'. 82.5% and< 90% RTP and MCPR less than the limit specified in the COLR and no peripheral control rod selected.
(f) THERMAL POWER<.'. 90% RTP and MCPR less than the limit specified in the COLR and no peripheral control rod selected.
(g) THERMAL POWER 27.5% and < 90% RTP and MCPR less than the limit specified in the COLR and no peripheral control rod selected.
(h) With THERMAL POWER s 9.85 RTP.
(i)
Reactor mode switch in the shutdown position.
U)
Less than or equal to the Allowable Value specified in the COLR.
Cooper 3.3-19 Amendment No. 278
5.6 Reporting Requirements (continued) 5.6.3 Radioactive Effluent Release Report Reporting Requirements 5.6 The Radioactive Effluent Release Report covering the operation of the unit shall be submitted in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODAM and the Process Control Program and in conformance with 1 O CFR 50.36a and 1 O CFR 50, Appendix I,Section IV.B.1.
5.6.4 (Deleted) 5.6.5 Core Operating Limits Report (COLR) a.
Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:
1.
The Average Planar Linear Heat Generation Rates for Specifications 3.2.1 and 3.7.7.
2.
The Minimum Critical Power Ratio for Specifications 3.2.2 and 3.7.7, and MCPR999% for Specification 3.2.2.
3.
The Linear Heat Generation Rates for Specifications 3.2.3 and 3. 7. 7.
4.
The three Rod Block Monitor Upscale Allowable Values for Specification 3.3.2.1.
5.
The power/flow map defining the Stability Exclusion Region for Specification 3.4.1.
6.
The Minimum Critical Power Ratios in Table 3.3.2.1-1 for Specification 3.3.2.1.
b.
The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in Cooper the following documents:
1.
NEDE-24011-P-A, "General Electric Standard Application for Reactor Fuel" (Revision specified in the COLR).
(continued) 5.0-21 Amendment No. 278
SAFETY EVALUATION BY THE OFFICE NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 278 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-46 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION DOCKET NO. 50-298
1.0 INTRODUCTION
By application dated May 9, 2024 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML24131A026), Nebraska Public Power District (the licensee) submitted a license amendment request (LAR) to the U.S. Nuclear Regulatory Commission (NRC, the Commission) for changes to the technical specifications (TSs) for Cooper Nuclear Station (Cooper).
The proposed changes would: (1) revise TS table 3.3.2.1-1, Control Rod Block Instrumentation, to reference the core operating limits report and (2) add a reference to TS 5.6.5, Core Operating Limits Report (COLR).
2.0 REGULATORY EVALUATION
2.1
System Description
In a boiling water reactor (BWR), steam is produced by the forced flow of water past fuel bundles. During steady-state operation in a BWR, most of the coolant in the core is in a flow regime known as annular flow. During annular flow a thin liquid film is pushed up the surface of the fuel rod cladding by the bulk coolant flow. The bulk coolant flow is mostly water vapor with some liquid water droplets. This type of flow provides effective heat removal from the cladding surface. However, under certain conditions the annular water film may dissipate. This phenomenon is known as boiling transition or dryout. Boiling transition reduces the heat transfer rate from the fuel. The reduced heat transfer rate results in an increase in fuel cladding surface temperature. The elevated surface temperatures that occur may cause fuel cladding damage or failure.
Because of the potential for damage, the goal during normal and transient operation is to maintain annular flow. The minimum critical power ratio (MCPR) provides an indication of how much margin is left before boiling transition will occur. A MCPR above 1.0 indicates that boiling transition is not predicted to occur.
Because the MCPR is dependent on the type and thermal power of fuel in the reactor core, it is calculated for each reload. Previously, the licensee submitted a LAR for Cooper with the updated MCPR for each reload. Generic Letter (GL) 88-16, Removal of Cycle-Specific Parameter Limit from Technical Specifications (ML031130447), allows a licensee to relocate cycle-specific values, such as a MCPR from the TSs to a licensee-controlled document called the COLR.
2.1.2 Description of the Proposed TS Changes The licensee proposes to revise Notes a, d, e, f, and g associated with TS table 3.3.2.1-1, to remove the numerical values for MCPR and replace them with less than the limit specified in the COLR.
The licensee also proposes to add the following to the end of TS 5.6.5.a:
- 6. The Minimum Critical Power Ratios in Table 3.3.2.1-1 for Specification 3.3.2.1 The licensee explains, in their submittal, that these changes will reduce licensee and agency burden for MCPR values that the licensee calculates using the methods in NEDE-24011-P-A, General Electric Standard Application for Reactor Fuel. The licensee further states in their submittal that the NRC previously approved the licensees use of NEDE24011-P-A, Revision 23, General Electric Standard Application for Reactor Fuel - GESTAR II, September 2016 (non-proprietary) (ML16250A047) in TS 5.6.5.b. The licensee reasons that the limits for control rod block instrumentation will continue to be calculated using this approved method but will be moved from the TSs to the COLR as described in GL 88-16.
2.2 Regulatory Requirements and Guidance Title 10 of the Code of Federal Regulations (10 CFR) Section 50.90, Application for amendment of license, construction permit, or early site permit, requires, in part, that whenever a licensee desires to amend the license, application for an amendment must be filed with the Commission, fully describing the changes desired, and following, as far as applicable, the form prescribed for original applications.
The regulations under 10 CFR 50.36, Technical specifications, establishes the regulatory requirements related to the content of TSs. The five categories of items required to be in the TSs are listed in 10 CFR 50.36(c) and include (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation; (3) surveillance requirements; (4) design features; and (5) administrative controls.
License amendments are generally required for each fuel cycle to update the values of cycle -specific core operating limits in TSs. In 1988, the NRC issued industry guidance in GL 88-16 allowing licensees to relocate cycle-specific core operating limits from TSs, provided that the values of these limits are included in the COLR and are determined using NRC approved methodologies, which are referenced in the TSs.
3.0 TECHNICAL EVALUATION
3.1 NRC Staff Evaluation of Revised TS Table 3.3.2.1-1 Notes The guidance in GL 88-16 allows for the relocation of cycle-specific values from the TSs to the COLR if an NRC -approved method is used. The proposed change would reference the control rod block instrumentation MCPR values in the Cooper COLR instead of values provided in the TS table 3.3.2.1-1 notes. The NRC staff has determined that the values for MCPR are calculated using the NRC -approved methods in NEDE-24011-P-A thus the MCPR values stated in a COLR for purposes of TS Table 3.3.2.1-1 calculated with this method will establish criteria sufficient to assure operability of the systems governed by this TS. TS 5.6.5.b requires the use of NEDE-24011-P-A for calculating the MCPR. The staff finds that the relocation of the MCPR values from the TS table 3.3.2.1-1 notes to the COLR is consistent with GL 88-16, and therefore acceptable.
3.2 NRC Staff Evaluation of Addition to TS 5.6.5 The proposed addition of item a.6 to TS 5.6.5 is for controlling the relocation of the control rod block instrumentation MCPR values to the COLR. The NRC staff has determined that the proposed relocation is similar to TS 5.6.5.a.2 currently in place to control the relocation of MCPR for TS 3.2.2 and 3.7.7. The staff has also determined that the proposed change is consistent with GL 88-16 requirements to control the relocation of cycle-specific values to the COLR. The staff finds this change acceptable.
3.3 Technical Conclusion The NRC staff reviewed the proposed changes to TS table 3.3.2.1-1 and TS 5.6.5 to relocate the control rod block instrumentation MCPR values to the COLR. The staff finds that the cycle -specific MCPR values would be determined using the NRC -approved methods in NEDE-24011-P-A. The approved methods are referenced in TS 5.6.5.b. Based on the above findings, the staff has determined that the proposed changes follow the GL 88-16 guidance and meet the regulatory requirements in 10 CFR 50.36. Therefore, the NRC staff concludes that the proposed changes are acceptable.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Nebraska State official was notified of the proposed issuance of the amendment on August 24, 2024. The State official had no comments.
5.0 ENVIRONMENTAL EVALUATION 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, published in the Federal Register on August 6, 2024 (89 FR 63992), and there has been no public comment on such finding. 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) there is reasonable assurance that such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: N. Denney, NRR Date: October 8, 2024
- concurrence via email NRR-058 OFFICE NRR/DORL/LPL4/PM* NRR/DORL/LPL4/LA*
NRR/DSS/STSB/BC*
NRR/DSS/SNSB/BC*
NAME TByrd PBlechman SMehta PSahd DATE 9/06/2024 9/10/2024 w/comments 9/16/2024 9/16/2024 OFFICE NRR/DEX/EICB/BC*
OGC - NLO*
NRR/DORL/LPL4/BC* NRR/DORL/LPL4/PM*
NAME FSacko RWeisman JRankin TByrd DATE 9/13/2024 10/02/2024 10/08/2024 10/08/2024