ML22217A044

Issuance of Amendment Nos. 292 and 288 Control Rod Scram Times

ML22217A044
Person / Time
Site:	Quad Cities
Issue date:	12/07/2022
From:	Robert Kuntz Plant Licensing Branch III
To:	Rhoades D Constellation Energy Generation, Constellation Nuclear
Kuntz R
References
EPID L-2021-LLA-0209
Download: ML22217A044 (15)

Text

December 7, 2022 Mr. David P. Rhoades Senior Vice President Constellation Energy Generation, LLC President and Chief Nuclear Officer Constellation Nuclear 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENT NOS. 292 AND 288 RE: CONTROL ROD SCRAM TIMES (EPID L-2021-LLA-0209)

Dear Mr. Rhoades:

The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 292 to Renewed Facility Operating License No. DPR-29 and Amendment No. 288 to Renewed Facility Operating License No. DPR-30 for Quad Cities Nuclear Power Station, Units 1 and 2, respectively. The amendments consist of changes to the technical specifications (TSs) in response to your application dated November 16, 2021, as supplemented by letter dated August 18, 2022.

The amendments revise control rod scram time limits in TS table 3.1.4-1 Control Rod Scram Times.

D. Rhoades A copy of the safety evaluation is also enclosed. The Notice of Issuance will be included in the Commissions monthly Federal Register notice.

Sincerely,

/RA/

Robert F. Kuntz, Senior Project Manager Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-254 and 50-265

Enclosures:

1. Amendment No. 292 to DPR-29

2. Amendment No. 288 to DPR-30

3. Safety Evaluation cc: Listserv

CONSTELLATION ENERGY GENERATION, LLC AND MIDAMERICAN ENERGY COMPANY DOCKET NO. 50-254 QUAD CITIES NUCLEAR POWER STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 292 Renewed License No. DPR-29

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

A. The application for amendment by Constellation Energy Generation, LLC (the licensee) dated November 16, 2021, as supplemented by letter dated August 18, 2022, 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.

Enclosure 1

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 Renewed Facility Operating License No. DPR-29 is hereby amended to read as follows:

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 292, are hereby incorporated into this renewed operating 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 during the Quad Cities Nuclear Power Station, Unit 1, spring 2023 refueling outage.

FOR THE NUCLEAR REGULATORY COMMISSION Digitally signed by Nancy Nancy L. L. Salgado Date: 2022.12.07 Salgado 10:09:30 -05'00' Nancy L. Salgado, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: December 7, 2022

CONSTELLATION ENERGY GENERATION, LLC AND MIDAMERICAN ENERGY COMPANY DOCKET NO. 50-265 QUAD CITIES NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 288 Renewed License No. DPR-30

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

A. The application for amendment by the Constellation Energy Generation, LLC (the licensee) dated November 16, 2021, as supplemented by letter dated August 18, 2022, 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.

Enclosure 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 Renewed Facility Operating License No. DPR-30 is hereby amended to read as follows:

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 288, are hereby incorporated into this renewed operating 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 during the Quad Cities Nuclear Power Station, Unit 1, spring 2023 refueling outage.

FOR THE NUCLEAR REGULATORY COMMISSION Digitally signed by Nancy Nancy L. L. Salgado Date: 2022.12.07 Salgado 10:10:02 -05'00' Nancy L. Salgado, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: December 7, 2022

ATTACHMENT TO LICENSE AMENDMENT NOS. 292 AND 288 RENEWED FACILITY OPERATING LICENSE NOS. DPR-29 AND DPR-30 QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 DOCKET NOS. 50-254 AND 50-265 Replace the following pages of the Renewed Facility Operating Licenses and Appendix A, Technical Specifications, with the attached pages. The revised pages are identified by amendment number and contain marginal lines indicating the area of change.

Remove Insert License DPR-29 License DPR-29 Page 4 Page 4 License DPR-30 License DPR-30 Page 4 Page 4 TSs TSs 3.1.4-3 3.1.4-3

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 292, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.

C. The licensee shall maintain the commitments made in response to the March 14, 1983, NUREG-0737 Order, subject to the following provision:

The licensee may make changes to commitments made in response to the March 14, 1983, NUREG-0737 Order without prior approval of the Commission as long as the change would be permitted without NRC approval, pursuant to the requirements of 10 CFR 50.59. Consistent with this regulation, if the change results in an Unreviewed Safety Question, a license amendment shall be submitted to the NRC staff for review and approval prior to implementation of the change.

D. Equalizer Valve Restriction Three of the four valves in the equalizer piping between the recirculation loops shall be closed at all times during reactor operation with one bypass valve open to allow for thermal expansion of water.

E. 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 the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined sets of plans1, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: Quad Cities Nuclear Power Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 2, submitted by letter dated May 17, 2006.

Constellation Energy Generation, LLC 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 CSP was approved by License Amendment No. 249 as modified by License Amendment No. 259.

1 The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan.

Renewed License No. DPR-29 Amendment No. 292

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 288, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.

C. The licensee shall maintain the commitments made in response to the March 14, 1983, NUREG-0737 Order, subject to the following provision:

The licensee may make changes to commitments made in response to the March 14, 1983, NUREG-0737 Order without prior approval of the Commission as long as the change would be permitted without NRC approval, pursuant to the requirements of 10 CFR 50.59. Consistent with this regulation, if the change results in an Unreviewed Safety Question, a license amendment shall be submitted to the NRC staff for review and approval prior to implementation of the change.

D. Equalizer Valve Restriction Three of the four valves in the equalizer piping between the recirculation loops shall be closed at all times during reactor operation with one bypass valve open to allow for thermal expansion of water.

E. 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 the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans1, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: Quad Cities Nuclear Power Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 2, submitted by letter dated May 17, 2006.

Constellation Energy Generation, LLC 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 CSP was approved by License Amendment No. 244 and modified by License Amendment No. 254.

1 The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan.

Renewed License No. DPR-30 Amendment No. 288

Control Rod Scram Times 3.1.4 Table 3.1.4-1 (page 1 of 1)

Control Rod Scram Times

---

NOTES ------------------------------------

1. OPERABLE control rods with scram times not within the limits of this Table are considered "slow."

2. Enter applicable Conditions and Required Actions of LCO 3.1.3, "Control Rod OPERABILITY," for control rods with scram times > 7 seconds to 90%

insertion. These control rods are inoperable, in accordance with SR 3.1.3.4, and are not considered "slow."

SCRAM TIMES(a)(b) (seconds) when REACTOR STEAM DOME PERCENT INSERTION PRESSURE 800 psig 5 0.45 20 0.85 50 1.80 90 3.00 (a) Maximum scram time from fully withdrawn position based on de-energization of scram pilot valve solenoids at time zero.

(b) Scram times as a function of reactor steam dome pressure when

< 800 psig are within established limits.

Quad Cities 1 and 2 3.1.4-3 Amendment No. 292/288231/227

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 292 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-29 AND AMENDMENT NO. 288 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-30 CONSTELLATION ENERGY GENERATION, LLC AND MIDAMERICAN ENERGY COMPANY QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 DOCKET NOS. 50-254 AND 50-265

1.0 INTRODUCTION

By letter to the U.S. Nuclear Regulatory Commission (NRC, the Commission) dated November 16, 2021 (Agencywide Documents Access and Management System (ADAMS)

Accession No. ML21320A195), as supplemented by letter dated August 18, 2022 (ML22230A807), Exelon Generation Company, LLC (the licensee) requested changes to the technical specifications (TSs), for the Quad Cities Nuclear Power Station (Quad Cities), Units 1 and 2. The proposed changes would revise TS 3.1.4, Control Rod Scram Times, to regain margin for reactor pressure vessel (RPV) overpressure. On February 1, 2022, Exelon became Constellation Energy Generation, LLC (ML22032A333).

The supplemental letter dated August 18, 2022, provided additional information that corrected the application. Therefore, the U.S. Nuclear Regulatory Commission (NRC) staff published a revised proposed no significant hazards consideration determination in the Federal Register on October 4, 2022 (87 FR 60213), superseding the one published on January 25, 2022; (87 FR 3847).

2.0 REGULATORY EVALUATION

2.1 Description of the Licensees Proposed Changes The license amendment request (LAR) proposed the changes to TS for Quad Cities, Units 1 and 2, to revise the control rod scram time limits TS table 3.1.4-1 to regain margin for RPV overpressure. The changes to table 3.1.4-1 would revise the scram times as follows:

Enclosure 3

for 5 percent insertion, scram time would be revised from 0.48 to 0.45 seconds, for 20 percent insertion, scram time would be revised from 0.89 to 0.85 seconds, for 50 percent insertion, scram time would be revised from 1.98 to 1.80 seconds, and for 90 percent insertion, scram time would be revised from 3.44 to 3.00 seconds.

2.2 Regulatory Requirements Under 10 CFR, 50.90, whenever a holder of a license wishes to amend the license, including technical specifications in the license, an application for amendment must be filed, fully describing the changes desired. Under 10 CFR 50.92(a), determinations on whether to grant an applied-for license amendment are to be guided by the considerations that govern the issuance of initial licenses or construction permits to the extent applicable and appropriate. Both the common standards for licenses and construction permits in 10 CFR 50.40(a), and those specifically for issuance of operating licenses in 10 CFR 50.57(a)(3), provide that there must be reasonable assurance that the activities at issue will not endanger the health and safety of the public.

The regulations at Title 10 of the Code of Federal Regulations (10 CFR) 50.36 require that TSs include items in the following categories: (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation (LCOs); (3) surveillance requirements (SRs); (4) design features; (5) administrative controls; (6) decommissioning; (7) initial notification; and (8) written reports.

The regulation at 10 CFR 50.36 (c)(2) states LCOs are the lowest functional capability or performance levels of equipment required for safe operation of the facility. The regulation at 10 CFR 50.36 (c)(3) states SRs are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the LCOs will be met.

2.3 Reasons for the Proposed Changes The TS LCOs on control rod operability, control rod scram times, and control rod scram accumulators ensure that the performance of the control rods in the event of a Design Basis Accident (DBA) or transient meets the assumptions used in the safety analyses.

The licensee plans for fuel transition from the ATRIUM 10XM fuel design to Global Nuclear Fuels America, LLC (GNF) GNF3 fuel. The licensee plans to load GNF3 in Quad Cities, Unit 1, during the spring of 2023 refueling outage and in Quad Cities, Unit 2, in the spring of 2024.

Therefore, a revised set of scram times are required to support the American Society of Mechanical Engineers (ASME) Code reactor vessel overpressure limit.

3.0 TECHNICAL EVALUATION

3.1 Description of the Revisions to Control Rod Scram Time Limits LAR, section 2.0, stated that modification to the scram speed profiles would be revised to regain overpressure margin. To ensure that the specified acceptable fuel design limits are not exceeded, the control rod drive system scram functions control the reactivity changes during anticipated operational occurrences. In the design-basis accident (DBA) and transient analysis, it is assumed that all control rods scram at a specified insertion rate.

The negative reactivity resulting from the control rod scram insertion determines the basis of plant thermal limits such as the minimum critical power ratio (MCPR). Other scram time distributions (e.g., several control rods scramming slower than the average time with several control rods scramming faster than the average time) can also provide sufficient scram reactivity. It is through the surveillance of each individual control rods scram time that sufficient scram reactivity is ensured for DBA and transient analyses.

Measurement of the scram times with reactor steam dome pressure 800 pounds per square inch gauge (psig) demonstrates acceptable scram times for the transients analyzed in the Quad Cities UFSAR. For pressures 800 psig, the negative reactivity is inserted at a fast enough rate controlled by the scram function to ensure that during the analyzed limiting power transient, the actual MCPR does not reach a level lower than the MCPR safety limit. For pressures 800 psig, during the control rod drop accident, the scram function provides protection against violating fuel design limits during reactivity insertion accidents. For the reactor vessel overpressure protection analysis, the scram function and the safety/relief valves, control the peak vessel pressure to be maintained within the applicable ASME Code limits.

Based on analysis completed by GNF scram speed profiles modifications can be used to regain overpressure margin. GNF also showed that these modifications do not affect the design, functional performance, normal operation of the facility and design or operation of any component in the facility leading to creation of new equipment failure modes.

To determine the revised TS scram speed limits, NRC-approved ODYN computer code, which involves General Electric (GE) transient calculation methodology, w used by the licensee (References 6.3, 6.4, and 6.5 in the LAR). The licensee applied an NRC-imposed uncertainty factor of 1.044 in their proposed revision of the TS scram time values described in Section 2.1 of this safety evaluation. The existing TS SRs for each individual control rods scram time which ensures meeting the scram reactivity assumed in DBA and transient analysis are sufficient for the current ODYN calculations operating limits for pressurization events. The revised TS scram times which result in the development of the fuel cycle dependent MCPR operating limits will be used in analyzing all cores containing GNF 3 fuel.

The NRC staff reviewed the proposed change in scram time testing and notes that the code used to develop the revised time is consistent with the Quad Cities, Units 1 and 2, licensing bass and therefore appropriate. The NRC staff considered the uncertainty factor imposed to determine the proposed change and finds that it is consistent with the approved methodology.

The NRC staff finds the proposed TS changes in the LAR and the revisions to control rod scram time limits were appropriately developed with adequate margin and are therefore acceptable.

3.2 Technical Evaluation Conclusion

The LAR proposed to modify control rod scram time limits in TS table 3.1.4-1 with no other changes to TS 3.1.4, Control Rod Scram Times. The proposed changes to control rod scram times are used to regain margin for RPV overpressure. The NRC staff concludes that the proposed TS changes are acceptable as the licensees calculations to revise TS scram speed limits were performed consistent with the NRC approved methodology and using appropriately conservative assumptions.

The NRC staff finds that the resulting TS changes meets the criteria in 10 CFR 50.36 (c)(2) and 10 CFR 50.36 (c)(3) because the LCO for scram times will continue to list the lowest functional capability or performance levels of equipment required for safe operation of the facility and the SRs will continue to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the LCO will be met.

4.0 STATE CONSULTATION

In accordance with the Commissions regulations, the Illinois State official was notified of the proposed issuance of the amendment on August 10, 2022. The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendments change the requirements with respect to installation or use of a facilitys components located within the restricted area as defined in 10 CFR Part 20 or a change to SRs.

The NRC staff has determined that the amendments involve 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 on October 4, 2022 (87 FR 60213), that the amendments involve no significant hazards consideration, and there has been no public comment on such finding. Accordingly, the amendments meet 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 amendments.

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 amendments will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor: Noushin Amini, NRR Date of Issuance: December 7, 2022

ML22217A044 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR//DSS/STSB/BC NRR/DSS/SNSB NAME RKuntz SRohrer VCusumano DWoodyatt (A)

DATE 8/5/2022 8/8/2022 8/19/2022 8/15/2022 OFFICE OGC NRR/DORL/LPL3/BC NRR/DORL/LPL3/PM NAME MWoods NSalgado RKuntz DATE 11/30/2022 12/7/2022 12/7/2022