RS-21-108, Application to Revise Technical Specification 3.1.4, Control Rod Scam Times

Application to Revise Technical Specification 3.1.4, Control Rod Scam Times

ML21320A195
Person / Time
Site:	Quad Cities
Issue date:	11/16/2021
From:	Simpson P Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RS-21-108
Download: ML21320A195 (12)

Text

4300 Winfield Road Warrenville, IL 60555 630 657 2000 Office 10 CFR 50.90 RS-21-108 November 16, 2021 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265

Subject:

Application to Revise Technical Specification 3.1.4, "Control Rod Scam Times"

Reference:

Public Pre-submittal Meeting Between Exelon Generation Company, LLC and the U.S. Nuclear Regulatory Commission, "Proposed License Amendment Request Associated with the Transition to a New Fuel Type and Vendor at LaSalle Station, Units 1 & 2 and Quad Cities Nuclear Power Station, Units 1 & 2,"

May 27, 2021 (ADAMS Accession Nos. ML21133A167 & ML21141A010)

In accordance with 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," Exelon Generation Company, LLC (EGC) requests an amendment to the Technical Specifications (TS) for Quad Cities Nuclear Power Station (QCNPS), Units 1 and 2.

The proposed change would revise control rod scram time limits in QCNPS TS Table 3.1.4-1 to regain margin for containment overpressure.

EGC participated in a pre-submittal meeting with the NRC (see Reference) regarding the planned transition from the Framatome ATRIUM 10XM fuel design to the Global Nuclear Fuels -

America, LLC (GNF) GNF3 fuel design at QCNPS. During this meeting, EGC's plan to submit this amendment request was discussed. provides a description and assessment of the proposed changes. Attachment 2 provides the existing TS pages marked-up to show the proposed TS changes. Attachment 3 provides revised (clean) TS pages. There are no TS Bases changes associated with the corresponding TS change.

The proposed change has been reviewed by the QCNPS Plant Operations Review Committee, in accordance with the requirements of the EGC Quality Assurance Program.

November 16, 2021 U.S. Nuclear Regulatory Commission Page 2 EGC requests approval of the proposed license amendment by November 16, 2022. Once approved, the amendment shall be implemented within 60 days.

In accordance with 10 CFR 50.91, "Notice for public comment; State consultation,"

paragraph (b), a copy of this application, with attachments, is being provided to the designated State Officials.

There are no regulatory commitments contained in this submittal. Should you have any questions concerning this submittal, please contact Ms. Rebecca L. Steinman at (630) 657-2831.

I declare under penalty of perjury that the foregoing is true and correct. This statement was executed on the 16th day of November 2021.

Respectfully, Patrick R. Simpson Sr. Manager Licensing Exelon Generation Company, LLC Attachments:

1. Evaluation of Proposed Changes

2. Mark-up of QCNPS, Units 1 and 2 Technical Specifications Pages

3. Clean QCNPS, Units 1 and 2 Technical Specifications Pages cc: NRC Regional Administrator, Region III NRC Senior Resident Inspector, Quad Cities Nuclear Power Station NRC Project Manager, Quad Cities Nuclear Power Station Illinois Emergency Management Agency - Division of Nuclear Safety

ATTACHMENT 1 Evaluation of Proposed Changes

Subject:

Application to Revise Technical Specification 3.1.4, "Control Rod Scam Times" 1.0

SUMMARY

DESCRIPTION 2.0 DETAILED DESCRIPTION

4.0 REGULATORY EVALUATION

4.1 Applicable Regulatory Requirements/Criteria 4.2 No Significant Hazards Consideration 4.3 Conclusion

6.0 REFERENCES

ATTACHMENT 1 Evaluation of Proposed Changes 1.0

SUMMARY

DESCRIPTION In accordance with 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," Exelon Generation Company, LLC (EGC) requests an amendment to the Technical Specifications (TS) for Quad Cities Nuclear Power Station (QCNPS), Units 1 and 2.

The proposed change would revise control rod scram time limits in QCNPS TS Table 3.1.4-1 to regain margin for containment overpressure.

2.0 DETAILED DESCRIPTION The proposed change would revise control rod scram time limits in QCNPS TS Table 3.1.4-1 as indicated below to regain margin for containment overpressure. The revision of the numerical values of the scram insertion speeds also results in a change to an input parameter to the NRC-approved ODYN based transient methodology (References 6.3, 6.4, and 6.5) for determining the Operating Limit Minimum Critical Power Ratio (OLMCPR). ODYN is a calculational model included in the General Electric Standard Application for Reactor Fuel (GESTAR-II, Reference 6.6). Since GESTAR-II is already part of the QCNPS licensing basis, this methodology change does not require a corresponding TS change.

CURRENT SCRAM TIMES REVISED SCRAM TIMES PERCENT INSERTION (seconds) (seconds) 5 0.48 0.45 20 0.89 0.85 50 1.98 1.80 90 3.44 3.00 contains a marked-up version of the QCNPS, Units 1 and 2 TS showing the proposed changes to Table 3.1.4-1. Attachment 3 provides the revised (clean) TS pages.

There are no corresponding changes to the TS Bases.

3.0 TECHNICAL EVALUATION

QCNPS plans to load GNF3 fuel into Unit 1 during the spring 2023 refueling outage and into Unit 2 the following spring. The fuel transition requires a new set of scram times to support improvements on the margin to the American Society of Mechanical Engineers (ASME) Code reactor vessel overpressure limit.

The scram function of the Control Rod Drive (CRD) System controls reactivity changes during anticipated operational occurrences (AOOs) to ensure that specified acceptable fuel design limits are not exceeded. The Design Basis Accident (DBA) and transient analyses assume that all control rods scram at a specified insertion rate. The resulting negative scram reactivity forms the basis for the determination of plant thermal limits (e.g., the minimum critical power ratio (MCPR)). Other distributions of scram times (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. Surveillance of each individual control rod's scram time

ATTACHMENT 1 Evaluation of Proposed Changes ensures the scram reactivity assumed in the DBA and transient analyses can be met.

At 800 psig, the scram function is designed to insert negative reactivity at a rate fast enough to prevent the actual MCPR from becoming less than the MCPR Safety Limit, during the analyzed limiting power transient. Below 800 psig, the scram function is assumed during the control rod drop accident to provide protection against violating fuel design limits during reactivity insertion accidents. For the reactor vessel overpressure protection analysis, the scram function, along with the safety/relief valves, ensure that the peak vessel pressure is maintained within the applicable ASME Code limits.

Based on the evaluations performed in an analysis carried out by Global Nuclear Fuels -

America, LLC (GNF), modifications to the scram speed profiles can be used to regain overpressure margin. The proposed changes do not affect the design, functional performance, or normal operation of the facility. Similarly, it does not affect the design or operation of any component in the facility such that new equipment failure modes are created.

The determination of the revised Quad Cities TS scram speed limits utilizes the General Electric (GE) transient calculation methodology involving the ODYN computer code (Reference 6.3).

This methodology was previously approved by the U.S. NRC in References 6.4 and 6.5. The methodology described in Reference 6.3 applies two scram time options in the calculation of the MCPR operating limits. The Option A analysis directly applies the TS scram time values and an NRC-imposed uncertainty factor and Option B applies a generic statistical scram time distribution. Licensees are required to demonstrate that the actual scram speeds bound the generic statistical scram times in Option B or operate with a higher limit (i.e., a penalty). The proposed revision of the TS scam time values described in Section 2 is based on the Option A method using a 1.044 code uncertainty penalty. The uncertainty consideration in the calculation of the OLMCPR ensures that less than 0.1% of the fuel rods will experience boiling transition during the transient (Reference 6.6).

Existing TS Surveillance Requirements (SRs) for each individual control rod's scram time ensures the scram reactivity assumed in the DBA and transient analyses can be met. These SRs are sufficient to ensure that the plant operates under the ODYN Option A or B operating limits for pressurization events.

All cores containing GNF3 fuel will be analyzed with the revised TS scram times resulting in the development of the fuel cycle dependent MCPR operating limits.

4.0 REGULATORY EVALUATION

4.1 Applicable Regulatory Requirements/Criteria TS 3.1.4, "Control Rod Scram Times" satisfies the following regulatory requirements:

10 CFR 50.36 (c)(2)(ii)(C) Criterion 3 A structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.

Page 3

ATTACHMENT 1 Evaluation of Proposed Changes 10 CFR 50 Appendix A, GDC 10 - Reactor Design The reactor core and associated coolant, control, and protection systems shall be designed with appropriate margin to assure that specified acceptable fuel design limits are not exceeded during any condition of normal operation, including the effects of anticipated operational occurrences.

The original design of QCNPS, Units 1 and 2 was reviewed and approved against the draft General Design Criteria (GDC) issued in July 1967. Updated Final Safety Analysis Report (UFSAR), Section 3.1, "Conformance with NRC General Design Criteria," provides an assessment against the 70 draft GDC published in 1967 and concluded that the plant specific requirements are sufficiently similar to the Appendix A GDC. Therefore, the equivalent draft GDC used at QCNPS is functionally equivalent to 10 CFR 50 Appendix A, GDC 10.

4.2 Precedent The Quad Cities scram speeds were previously revised to reflect using the GE methodology for specifying the TS time limits during a prior fuel transition to GE14 fuel in 2001 (ADAMS Accession Nos. ML003756771 and ML013390002). The current proposed revision of the values of the TS limits reflect the differences between GE14 and GNF3 fuel using the same NRC-approved GE methodology.

4.3 No Significant Hazards Consideration Overview Exelon Generation Company, LLC (EGC) requests an amendment to the Technical Specifications (TS) for Quad Cities Nuclear Power Station (QCNPS), Units 1 and 2. The proposed change would revise control rod scram time limits in QCNPS TS Table 3.1.4-1 with no other changes to TS 3.1.4, "Control Rod Scam Times." The proposed changes do not affect the design, functional performance, or normal operation of the facility. Similarly, it does not affect the design or operation of any component in the facility such that new equipment failure modes are created.

EGC has evaluated the proposed change against the criteria of 10 CFR 50.92(c) to determine if the proposed changes result in any significant hazards. The following is the evaluation of each of the 10 CFR 50.92(c) criteria:

1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?

Response: No The requested changes to the TS Table 3.1.4-1 scram times are based on ensuring that the analytical approach utilized by Global Nuclear Fuels - America LLC (GNF) is met. There are no other changes to TS 3.1.4 (e.g., the number of slow rods allowed is unchanged). A scram time slower than required might result in an increase in the consequences of an accident. The EGC proposed changes do not constitute an increase to any consequences to any accidents Page 4

ATTACHMENT 1 Evaluation of Proposed Changes because the revised allowed scram times are bounded by the GNF analysis which demonstrates that all required limits are met.

Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?

Response: No The proposed change does not affect the design, functional performance, or normal operation of the facility. Similarly, it does not affect the design or operation of any component in the facility such that new equipment failure modes are created. As such the proposed change will not create the possibility of a new or different kind of accident from any accident previously evaluated.

3. Does the proposed change involve a significant reduction in a margin of safety?

Response: No Sufficiently rapid insertion of control rods following certain accidents (scram time) will prevent fuel damage, and thereby maintain a margin of safety to fuel damage. The proposed change to the control rod scam time limits does not constitute a change in the operation of the facility and hence do not involve a significant reduction in the margin of safety.

4.4 Conclusion Based on the considerations discussed above: (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.

5.0 ENVIRONMENTAL CONSIDERATION

The proposed amendment would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or would change an inspection or surveillance requirement. However, the proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.

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ATTACHMENT 1 Evaluation of Proposed Changes

6.0 REFERENCES

6.1. Quad Cities Nuclear Power Station, Units 1 and 2 Technical Specifications 6.2. Quad Cities Nuclear Power Station Updated Final Safety Analysis Report (UFSAR),

Revision 16, dated October 2021 6.3. NEDO-24154, "Qualification of the One-Dimensional Core Transient Model for Boiling Water Reactors, dated October 1978 (ADAMS Accession No. ML19269C819) 6.4. Odar, F., "Safety Evaluation for the General Electric Topical Report: Qualification of the One-Dimensional Core Transient Model for Boiling Water Reactors," NEDO--24154 and, NEDE--24154--P, Volumes I, II, and III," dated June 1980 (ADAMS Accession No. ML03121015) 6.5. "Supplemental Safety Evaluation for the General Electric Topical Report: Qualification of the One-Dimensional Core Transient Model for Boiling Water Reactors," NEDO--24154 and, NEDE--24154--P, Volumes I, II, and III," dated January 1981 (ADAMS Accession No. ML031210226) 6.6. General Electric Licensing Topical Report NEDE-24011-P-A, "General Electric Standard Application for Reactor Fuel, (GESTAR II Base Document (NEDE-24011-P-A, ,

Main)," Revision 31, dated November 2020 (ADAMS Accession No. ML20330A199 for the non-proprietary version)

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ATTACHMENT 2 QUAD CITIES NUCLEAR POWER STATION UNITS 1 AND 2 Docket Nos. 50-254 and 50-265 Facility Operating License Nos. DPR-29 and DPR-30 MARK-UP OF QCNPS, UNITS 1 AND 2 TECHNICAL SPECIFICATIONS PAGES

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

Control Rod Scram Times

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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 0.48 0.45 20 0.89 0.85 50 1.98 1.80 90 3.44 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. 231/227

ATTACHMENT 3 QUAD CITIES NUCLEAR POWER STATION UNITS 1 AND 2 Docket Nos. 50-254 and 50-265 Facility Operating License Nos. DPR-29 and DPR-30 CLEAN QCNPS, UNITS 1 AND 2 TECHNICAL SPECIFICATIONS PAGES

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

Control Rod Scram Times

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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. 231/227