Letter Sequence Draft RAI |
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MONTHYEARRS-13-148, License Amendment Request - Use of Neutron Absorbing Inserts in Units 1 and 2 Spent Fuel Pool Storage Racks2013-07-16016 July 2013 License Amendment Request - Use of Neutron Absorbing Inserts in Units 1 and 2 Spent Fuel Pool Storage Racks Project stage: Request ML13241A5102013-08-29029 August 2013 Request for Supplemental Information Project stage: Other RS-14-039, Additional Information Regarding License Amendment Request Associated with Use of Neutron Absorbing Inserts in Spent Fuel Pool Storage Racks2014-01-22022 January 2014 Additional Information Regarding License Amendment Request Associated with Use of Neutron Absorbing Inserts in Spent Fuel Pool Storage Racks Project stage: Request ML14024A5622014-01-22022 January 2014 Attachment 4 and 5 to RS-14-039, HI-2104790, Rev. 1, Nuclear Group Computer Code Benchmark Calculations, and HI-2125245, Rev. 4, Licensing Report for Quad Cities Criticality Analysis for Inserts-Non Proprietary Version. Project stage: Request ML14066A1362014-02-24024 February 2014 NRR E-mail Capture - Draft RAI from TAC Nos.: MF2489 and MF2490 Review on Neutron Absorbing Inserts Project stage: Draft RAI ML14066A1352014-02-24024 February 2014 NRR E-mail Capture - FW: Draft Request for Additional Information for Use of Neutron Absorbing Inserts in Spent Fuel Pool Storage Racks (TAC Nos. MF2489 and MF2490) Project stage: Draft RAI ML14059A1562014-02-28028 February 2014 NRR E-mail Capture - Request for Additional Information for Use of Neutron Absorbing Inserts in Spent Fuel Pool Storage Racks (TAC Nos. MF2489 and MF2490) Project stage: RAI ML14090A0042014-03-29029 March 2014 NRR E-mail Capture - Request for Extension -- Quad Cities Rack Inserts RAI Responses Project stage: RAI ML14203A6132014-06-23023 June 2014 NRR E-mail Capture - FW: Draft RAI from TAC Nos.: MF2489 and MF2490 Review on Neutron Absorbing Inserts Project stage: Draft RAI ML14203A6752014-07-22022 July 2014 NRR E-mail Capture - Final RAI for Quad Cities Regarding Use of Neutron Absorbing Inserts (TAC Nos.: MF2489 and MF2490) Project stage: RAI RS-14-229, Additional Information Regarding License Amendment Request Associated with Use of Neutron Absorbing Inserts in Spent Fuel Pool Storage Racks2014-08-12012 August 2014 Additional Information Regarding License Amendment Request Associated with Use of Neutron Absorbing Inserts in Spent Fuel Pool Storage Racks Project stage: Request ML14128A5632014-09-0404 September 2014 Request for Withholding Proprietary Information from Public Disclosure Project stage: Other ML14311A8502014-11-10010 November 2014 November 10, 2014, Discussion Topics Regarding Rack Insert Surveillance Program Project stage: Other RS-14-329, Additional Information Regarding License Amendment Request Associated with Use of Neutron Absorbing Inserts in Spent Fuel Pool Storage Racks2014-11-11011 November 2014 Additional Information Regarding License Amendment Request Associated with Use of Neutron Absorbing Inserts in Spent Fuel Pool Storage Racks Project stage: Request ML14353A3152014-12-24024 December 2014 Request for Withholding Proprietary Information from Public Disclosure Project stage: Other ML14346A3062014-12-31031 December 2014 Issuance of Amendments Regarding (TAC Nos. MF2489 and MF2490)(RS-13-148) Project stage: Approval ML15128A4772015-08-14014 August 2015 Summary of November 10 2014 Public Meeting with Exelon Generation Company, LLC on Netco Snap-In Rack Insert License Amendment Request Project stage: Meeting 2014-02-24
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Category:E-Mail
MONTHYEARML23349A0362023-12-14014 December 2023 NRR E-mail Capture - Draft Request for Additional Information Re Quad Cities Emergency Amendment Related to Unit 1 Diesel Generator Inoperability ML23338A1192023-11-21021 November 2023 NRR E-mail Capture - Draft Request for Additional Information Quad Cities Relief Request I5R-26 ML23268A0022023-09-22022 September 2023 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of License Amendment Request to Adopt TSTF-264-A, Revision 0 ML23264A7992023-09-21021 September 2023 NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC Fleet Request License Amendment Request to Adopt TSTF-580, Revision 1 ML23262A7432023-09-19019 September 2023 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 Acceptance of Relief Request I5R-26 ML23186A1482023-07-0505 July 2023 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Requested Licensing Action Amendment to Adopt 10 CFR 50.69 ML23186A1412023-07-0505 July 2023 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Requested Licensing Action Amendment to Adopt TSTF-505 ML23163A2292023-06-12012 June 2023 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of License Amendment Request to Adopt TSTF-580, Revision 1 ML23118A1652023-04-28028 April 2023 NRR E-mail Capture - Request for Additional Information Quad Cities, Unit 2, Alternative Request I6R-11 ML23083B9572023-03-24024 March 2023 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Requested Licensing Action Amendment to Adopt TSTF-564 ML23055A0392023-02-24024 February 2023 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Amendment to Adopt TSTF-416 ML23052A0772023-02-21021 February 2023 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance Timely Renewal Exemption Request ML22357A0392022-12-23023 December 2022 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of I6R-10 Related to Repair of Penetration N-11B ML22354A2622022-12-20020 December 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of Request to Use Certain Provisions of the 2019 Edition of the ASME BPV Code, Section XI ML23004A0262022-12-16016 December 2022 NRR E-mail Capture - Draft Request for Additional Information - Quad Cities Alternative RV-04, Inservice Testing of High Pressure Coolant Injection Drain Pot Solenoid Valves (EPD L-2022-LLR-0070) ML22348A0452022-12-14014 December 2022 NRR E-mail Capture - Draft Request for Additional Information Regarding Quad Cities Alternative I6R-09 ML22301A0902022-10-28028 October 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of License Amendment Request to Adopt TSTF-301, Revision 2 ML22290A0662022-10-17017 October 2022 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Alternative RV-04 Related to HPCI Drain Pot Solenoid Valve Testing ML23079A0272022-10-0505 October 2022 Licensee Outline Submittal Email (Quad Cities, 2023) ML22256A0112022-09-12012 September 2022 NRR E-mail Capture - Request for Additional Information LaSalle County Station, Units 1 and 2 and Quad Cities Nuclear Power Station, Units 1 and 2 License Amendments Related to Fuel Storage ML22224A0222022-08-12012 August 2022 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Alternative I6R-09 Related to Use of Certain 2013 Edition ASME Code Requirements ML22200A0782022-07-19019 July 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request to Use Honeywell Mururoa V4F1 R Supplied Air Suits ML22206A0352022-07-13013 July 2022 NRR E-mail Capture - Draft RAI Quad Cities Alternative Related to Sblc Nozzle Inspection ML22193A0412022-07-11011 July 2022 NRR E-mail Capture - RAI Quad Cities License Amendment to Expand the Use of Prime Methods ML22187A1832022-07-0606 July 2022 NRR E-mail Capture - Completion of Activities Related to EPID L-2022-LLD-003, Quad Cities Potential NOED ML22182A1992022-07-0101 July 2022 NRR E-mail Capture - RAI Alternative RV-11, Code Case OMN-28 ML22164A7852022-06-13013 June 2022 NRR E-mail Capture - RAI Quad Cities Amendment for Spent Fuel Pool Storage Analysis ML22164A8562022-06-13013 June 2022 NRR E-mail Capture - RAI Quad Cities Alternative RV-08, Safety Relief Valves ML22164A8582022-06-13013 June 2022 NRR E-mail Capture - RAI Alternative RV-09, MSSVs ML22101A0932022-04-11011 April 2022 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Relief I6R-01 Related to SLC Nozzle Inner Radius Inspection ML22077A4122022-03-18018 March 2022 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Alternative RV-06 Related to MSSV Setpoint Testing ML22076A0322022-03-17017 March 2022 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Alternative RV-03 Related to PIV Leak Test Frequency ML22075A0752022-03-16016 March 2022 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Alternative RV-07 Related to MSIV Stroke Testing ML22068A0062022-03-0909 March 2022 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Alternative RV-11 Related to OMN-28, Valve Position Verification ML22068A0552022-03-0909 March 2022 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Alternative RV-09 Related to MSSV Testing ML22068A1512022-03-0909 March 2022 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Alternative RV-10 Related to Code Case OMN-28, MOV Testing ML22067A2172022-03-0808 March 2022 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Alternative Related to MSRV Testing ML22041B5362022-02-10010 February 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Request for Additional Information Regarding Fleet License Amendment Request to Adopt TSTF-541 ML22039A2042022-02-0808 February 2022 NRR E-mail Capture - Public Meeting Dresden/Quad Cities - Proposed Alternative to Use ASME Code Case N-921 ML22020A0642022-01-13013 January 2022 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative for Repair of Water Level Instrumentation Partial Penetration Nozzles ML21342A3842021-12-0808 December 2021 NRR E-mail Capture - Request for Additional Information: Quad Cities 1 & 2 License Amendment Request Transition to GNF3 Fuel ML21342A3402021-12-0808 December 2021 Acceptance Review: License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times ML21322A3112021-11-18018 November 2021 Acceptance Review: Quad Cities Units 1 and 2 - License Amendment Request New Fuel Vault Storage and Spent Fuel Pool Criticality Methodologies ML21312A5612021-11-0808 November 2021 Acceptance Review: Quad Cities, Units 1 and 2 - License Amendment Request Regarding Transition to GNF3 Fuel ML21301A0672021-10-28028 October 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Acceptance of License Amendment Request to Adopt TSTF-541 ML21256A1902021-09-10010 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21252A0482021-09-0707 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Fleet Alternative Request for Repair of Water Level Instrumentation Partial Penetration Nozzles ML21215A3502021-08-0303 August 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Acceptance of License Amendment Request to Adopt TSTF-554 ML21190A0192021-07-0808 July 2021 NRR E-mail Capture - Exelon Fleet - Request for Additional Information Regarding Adoption of TSTF-582 and TSTF-583-T ML21154A0112021-05-28028 May 2021 NRR E-mail Capture - Extension of Comment Period for the Exelon Generation Company, LLC License Transfer Application 2023-09-22
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NRR-PMDAPEm Resource From: Mozafari, Brenda Sent: Monday, June 23, 2014 2:05 PM To: Nicely, Ken M.:(GenCo-Nuc) (ken.nicely@exeloncorp.com)
Subject:
FW: Draft RAI from TAC NOS.: MF2489 AND MF2490 review on NEUTRON ABSORBING INSERTS
- Ken, Additional RAI -
By letter dated July 16, 2013, (Agencywide Documents Access and Management Systems Accession Number [ADAMS] ML13199A037), Exelon Generation Company, LLC. (the licensee),
submitted a license amendment request to revise the Quad Cities Nuclear Station, Units 1 and 2 Technical Specifications to support use of neutron absorbing inserts in spent fuel pool.
REQUEST FOR ADDITIONAL INFORMATION QUAD CITIES NUCLEAR POWER STATIONS, UNITS 1 AND 2 REGARDING USE OF NEUTRON ABSORBING INSERTS IN SPENT FUEL STORAGE RACKS DOCKET NOS.: 50-254 AND 50-265 TAC NOS.: MF2489 AND MF2490
- 1. RAI 1-3 indicated that it was possible for a coupon to degrade without failing the minimum areal density criteria, and requests further detail on how the surveillance program will guarantee that any degradation is addressed before the safety function of the inserts installed in the SFP is affected. The response briefly summarizes the planned testing and states that any changes in the material properties will be identified early. NRC staff interprets the response to imply that the intent of the surveillance program is to identify when degradation occurs and use the Corrective Action Program to address any degradation. As such, the goal of the proposed surveillance program is to confirm that degradation is not occurring, not to verify the acceptability of any degradation. If this interpretation is correct, then the acceptance criteria for the B-10 areal density in Table 3.9-3 in Attachment 1 to the License Amendment Request letter transmitted to the NRC on July 16, 2013 is not consistent with the intent of the surveillance program. A minimum areal density value is provided, but no criterion associated with a possible change in areal density is included. Please update Table 3.9-3 with an appropriate criterion, or explain why a minimum areal density value for the coupon is sufficient as an acceptance criterion for verifying acceptable performance of all inserts in the SFP.
- 2. In the spent fuel pool (SFP), the spent fuel stored in the racks must comply with the regulations to remain subcritical. In the case of Quad Cities, they are licensed under 10 CFR 50.68 Criticality Accident Requirements. This regulation states that:
If no credit for soluble boron is taken, the k-effective of the spent fuel storage racks loaded with fuel of the maximum fuel assembly reactivity must not exceed 0.95, at a 95 percent probability, 95 percent confidence level, if flooded with unborated water.
To demonstrate compliance with the regulation, the licensee has performed a nuclear criticality safety (NCS) analysis of record (AOR). In this NCS AOR, Quad Cities has credited neutron absorber material (NAM) in the analysis to help maintain subcriticality. In order to ensure that the NAM will remain within the assumptions used in the NCS AOR, a Surveillance Program to identify and monitor any degradation 1
is in place or is planned to be implemented in the near future. These programs will confirm that the NAM will perform as designed for in the NCS AOR.
The staff questions the amount of information described in Quad Cities proposed Technical Specifications (TS) in regard to the NAM and its Surveillance Programs. In particular, NAM need to be monitored and degradation mitigated in the SFP to ensure that the assumptions in the SFP NCS AOR and thereby the TS 4.3.1 are not challenged. Since the materials are integral to the compliance of the TS 4.3.1 and the regulations, the requirement to monitor the NAM should be reflected in the TS in addition to the areal density of the NAM.
Please provide a TS Surveillance for the SFP NAM that will confirm that the materials will perform as designed for in the NCS AOR.
Note: In justification for having a neutron absorbers and its surveillance programs in TS, please see 10 CFR 50.36 (c)(2)(ii)(B), where it states:
Criterion 2. A process variable, design feature, or operating restriction that is an initial condition of a design basis accident or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.
Furthermore 10 CFR 50.36(c)(2)(ii)(C) states:
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 wither assumes the failure of or presents a challenge to the integrity of a fission product barrier.
- 3. RAI 1-17 requested justification for the use of a code that had not yet been submitted for review by the NRC for reload analysis methods with the SVEA-96 Optima2 fuel assembly, in order to obtain isotopic data for use in the criticality analyses. No specific information was provided to allow NRC staff to determine if CASMO-4 isotopic composition predictions are acceptable for SVEA-96 type lattices. NRC staff agrees that for the most part, the SVEA-96 lattice is comparable to other fuel lattices already approved for use with CASMO-4 in the U.S. However, the water wings are a relatively unique feature, and the SVEA-96 calculation results show a much larger bias between CASMO-4 and MCNP than the GE14 calculations. Appendix C shows the difference between CASMO-4 and MCNP5 calculations to be less than two sigma for the GE14 fuel design, while comparison of Tables 7.1(a) and 7.2(a) shows that the difference can approach the 20-sigma threshold for the SVEA-96 fuel design. This suggests that the heterogeneities of the SVEA-96 Optima2 fuel lattice may require special modeling considerations or treatment that is substantially different from that of other fuel assembly designs.
Please provide evidence that the CASMO-4 code would be expected to compute isotopic quantities comparable to codes previously approved by the NRC for use in reload analysis of SVEA-96 Optima2 fuel.
- 4. The response to the RAIs does not appear to include an updated version of the proposed amendments to the Quad Cities Technical Specifications. The license amendment request (LAR) letter submitted on July 13, 2013 proposes the addition of TS 4.3.1.1.c, The combination of U-235 enrichment and gadolinia loading shall be limited to ensure fuel assemblies have a maximum k-infinity of 0.9131 as determined at 4°C (39.2°F) in the normal spent fuel pool in-rack configuration The k-infinity value of 0.9131 is from an earlier version of the criticality analysis that used a super-lattice. Since the super-lattice has been withdrawn, please update TS 4.3.1.1.c to use the limiting k-infinity value from the most recent version of the criticality analysis (0.8991) or provide a rationale for use of the 0.9131 value.
- 5. In the response to RAI 1-11, part b, there is a statement that any future reconstitutions will be explicitly modeled to confirm they are bounded by the HI-2125245 analysis and will be processed under 50.59.
However, no methodology is given in HI-2125245 for modeling reconstitutions or dealing with any biases or uncertainties specific to reconstituted fuel. As such, modeling of reconstituted fuel would meet the criteria of 10 CFR 50.59(c)(2)(viii) requiring a request for a license amendment pursuant to 10 CFR 2
50.90. If the licensee intends to use the 50.59 process to qualify future reconstituted fuel, please provide a description of the methodology that will be used to model reconstituted fuel, including any new assumptions, biases, or uncertainties.
If you require a call for clarification, let me know as soon as possible. Otherwise I will plan for a final response by July 28, 2014.
Thanks Brenda L. Mozafari Senior Project Manager, NRR/DORL U.S. Nuclear Regulatory Commission Dresden 2/3 and QuadCities 1/2 301-415-2020 email: brenda.mozafari@nrc.gov 3
Hearing Identifier: NRR_PMDA Email Number: 1439 Mail Envelope Properties (Brenda.Mozafari@nrc.gov20140623140400)
Subject:
FW: Draft RAI from TAC NOS.: MF2489 AND MF2490 review on NEUTRON ABSORBING INSERTS Sent Date: 6/23/2014 2:04:31 PM Received Date: 6/23/2014 2:04:00 PM From: Mozafari, Brenda Created By: Brenda.Mozafari@nrc.gov Recipients:
"Nicely, Ken M.:(GenCo-Nuc) (ken.nicely@exeloncorp.com)" <ken.nicely@exeloncorp.com>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 7975 6/23/2014 2:04:00 PM Options Priority: Standard Return Notification: No Reply Requested: Yes Sensitivity: Normal Expiration Date:
Recipients Received: ZZZ