Source: https://regulations.justia.com/regulations/fedreg/2020/06/24/2020-13651.html
Timestamp: 2020-08-04 15:43:39
Document Index: 51604617

Matched Legal Cases: ['art 51', 'art 50', 'art 50', 'art 50', 'art 50', 'art 50', 'art 50', 'art 50', 'art 50', 'art 50', 'art 50', 'art 50', 'art 50', 'art 50', 'art 50', 'art 50', 'art 50', 'art 50', 'art 50', 'art 50', 'art 50', 'art 50', 'art 50', 'art 50', 'art 50', 'art 50', 'art 50']

Exelon Generation Company, LLC and MidAmerican Energy Company Quad Cities Nuclear Power Station, Units 1 and 2, 37965-37968 [2020-13651] :: Nuclear Regulatory Commission :: Agencies And Commissions :: Regulation Tracker :: Justia
Justia Regulation Tracker Agencies And Commissions Nuclear Regulatory Commission Exelon Generation Company, LLC and MidAmerican Energy Company Quad Cities Nuclear Power Station, Units 1 and 2, 37965-37968 [2020-13651]
Exelon Generation Company, LLC and MidAmerican Energy Company Quad Cities Nuclear Power Station, Units 1 and 2, 37965-37968 [2020-13651]
Download as PDF Federal Register / Vol. 85, No. 122 / Wednesday, June 24, 2020 / Notices Written comments may be submitted during the draft EIS comment period as described in the ADDRESSES section of the document. The NRC cautions you not to include identifying or contact information that you do not want to be publicly disclosed in your comment submission. The NRC posts all comment submissions at https:// www.regulations.gov and enters all comment submissions into ADAMS. The NRC does not routinely edit comment submissions to remove identifying or contact information. If you are requesting or aggregating comments from other persons for submission to the NRC, then you should inform those persons not to include identifying or contact information that they do not want to be publicly disclosed in their comment submission because the NRC does not routinely edit comment submissions before making the comment submissions available to the public or entering the comment submissions into ADAMS. On March 20, 2020 (85 FR 16150), the NRC issued for public comment a draft EIS for Holtec’s application to construct and operate a CISF for SNF and GTCC waste. The draft EIS for Holtec’s license application includes the preliminary analysis that evaluates the environmental impacts of the proposed action and alternatives to the proposed action. After comparing the impacts of the proposed action (Phase 1) to the NoAction alternative, the NRC staff, in accordance with the requirements in part 51 of title 10 of the Codes of Federal Regulations, recommends the proposed action (Phase 1), which is the issuance of an NRC license for 40 years to Holtec to construct and operate a CISF for SNF at the proposed location. In addition, the Bureau of Land Management (BLM) staff recommends the issuance of a permit to construct and operate the rail spur. This recommendation is based on (i) the license application, which includes an environmental report and supplemental documents, and Holtec’s responses to the NRC staff’s requests for additional Date Time 7/09/2020 ........ 5:00 p.m. to 9:00 p.m. (EDT) or 3:00 p.m. to 7:00 p.m. (MDT) Persons interested in attending this meeting should monitor the NRC’s Public Meeting Schedule website at https://www.nrc.gov/pmns/mtg for additional information, agenda for the meeting, information on how to provide verbal comments, and access information for the meeting. Participants should register in advance of the meeting by visiting the website (https://usnrc.webex.com) and using the event number provided above. A confirmation email will be generated providing additional details and a link to the meeting. Those wishing to make verbal comments at the meeting should follow instructions listed on the NRC’s Public Meeting Schedule website. jbell on DSKJLSW7X2PROD with NOTICES II. Discussion Dated: June 18, 2020. For the Nuclear Regulatory Commission. Diana B. Diaz Toro, Acting Chief, Environmental Review Materials Branch, Division of Rulemaking, Environmental, and Financial Support, Office of Nuclear Material Safety, and Safeguards. [FR Doc. 2020–13590 Filed 6–23–20; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [Docket Nos. 50–254 and 50–265; NRC– 2020–0143] Exelon Generation Company, LLC and MidAmerican Energy Company Quad Cities Nuclear Power Station, Units 1 and 2 Nuclear Regulatory Commission. ACTION: Exemption; issuance. AGENCY: Jkt 250001 PO 00000 III. Meeting Information The NRC staff will hold a public webinar on July 9, 2020 to receive comments on the draft EIS for Holtec’s application to construct and operate a CISF. The webinar will be held online and will offer a telephone line for members of the public to submit comments. A court reporter will be recording all comments received during the webinar. The dates and times for the public webinar are as follow: WEBINAR INFORMATION: Webinar address: https://usnrc.webex.com/. Event Number: 199 943 8370. Password: HOLTEC. TELEPHONE ACCESS: Telephone number: 800–475–0220. Telephone passcode: 9575497. The U.S. Nuclear Regulatory Commission (NRC) has issued an exemption in response to a July 22, 18:20 Jun 23, 2020 information; (ii) consultation with Federal, State, Tribal, local agencies, and input from other stakeholders; (iii) independent NRC and BLM staff review; and (iv) the assessments provided in the EIS. The public comment period was originally scheduled to close on May 22, 2020. The NRC has decided to extend the public comment until September 22, 2020 to allow more time for members of the public to submit their comments. Comments of Federal, State, and local agencies, Indian Tribes or other interested persons will be made available for public inspection when received. Location SUMMARY: VerDate Sep<11>2014 37965 Frm 00146 Fmt 4703 Sfmt 4703 2019, request from Exelon Generation Company, LLC, from certain regulatory requirements in order to permit exclusion of main steam isolation valve (MSIV) leakage from the overall integrated leak rate Type A test measurement and MSIV pathway leakage contributions from the combined leakage rate of all penetrations and valves subject to Type B and Type C tests. DATES: The exemption was issued on June 18, 2020. ADDRESSES: Please refer to Docket ID NRC–2020–0143 when contacting the NRC about the availability of information regarding this document. You may obtain publicly-available information related to this document using any of the following methods: • Federal Rulemaking Website: Go to https://www.regulations.gov and search for Docket ID NRC–2020–0143. Address questions about NRC docket IDs in Regulations.gov to Jennifer Borges; telephone: 301–287–9127; email: E:\FR\FM\24JNN1.SGM 24JNN1 37966 Federal Register / Vol. 85, No. 122 / Wednesday, June 24, 2020 / Notices Jennifer.Borges@nrc.gov. For technical questions, contact the individual listed in the FOR FURTHER INFORMATION CONTACT section of this document. • NRC’s Agencywide Documents Access and Management System (ADAMS): You may obtain publiclyavailable documents online in the ADAMS Public Documents collection at https://www.nrc.gov/reading-rm/ adams.html. To begin the search, select ‘‘Begin Web-based ADAMS Search.’’ For problems with ADAMS, please contact the NRC’s Public Document Room (PDR) reference staff at 1–800–397–4209, 301– 415–4737, or by email to pdr.resource@ nrc.gov. The ADAMS accession number for each document referenced (if it is available in ADAMS) is provided the first time that it is mentioned in this document. FOR FURTHER INFORMATION CONTACT: Robert F. Kuntz, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001; telephone: 301–415– 3733, email: Robert.Kuntz@nrc.gov. SUPPLEMENTARY INFORMATION: The text of the exemption is attached. Dated: June 19, 2020. For the Nuclear Regulatory Commission. Russell S. Haskell, Project Manager, Plant Licensing Branch III, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. Attachment—Exemption NUCLEAR REGULATORY COMMISSION Docket Nos. 50–254 and 50–265 Exelon Generation Company, LLC and MidAmerican Energy Company Quad Cities Nuclear Power Station, Units 1 and 2 Exemption jbell on DSKJLSW7X2PROD with NOTICES I. Background Exelon Generation Company, LLC (EGC, the licensee) and MidAmerican Energy Company are the holders of Facility Operating License Nos. DPR–29 and DPR–30, which authorize operation of the Quad Cities Nuclear Power Station (QCNPS), Units 1 and 2. The licenses provide, among other things, that the facilities are subject to the rules, regulations, and orders of the U.S. Nuclear Regulatory Commission (NRC, the Commission) now or hereafter in effect. The facilities each consist of a boiling, light-water reactor located in Rock Island County, Illinois. II. Request/Action In its letter dated March 5, 2019 (Agencywide Documents and Access Management System (ADAMS) Accession No. ML19064B369), as supplemented by letters dated May 23, 2019 (ADAMS Accession No. ML19143A347), July 22, 2019 (ADAMS Accession No. ML19203A176), February 24, 2020 (ADAMS Accession No. ML20055E826), and March 31, 2020 VerDate Sep<11>2014 18:20 Jun 23, 2020 Jkt 250001 (ADAMS Accession No., ML20091H576) EGC requested a permanent exemption from the Part 50 of Title 10 of the Code of Federal Regulations (10 CFR), Appendix J, Option B, Section III.A requirements in order to permit exclusion of main steam isolation valve (MSIV) leakage from the overall integrated leak rate Type A test measurement, and from Option B, Section III.B, requirements in order to permit exclusion of the MSIV pathway leakage contributions from the combined leakage rate of all penetrations and valves subject to Type B and Type C tests. The letters also requested license amendments to revise Technical Specification (TS) 3.6.1.3, ‘‘Primary Containment Isolation Valves (PCIVs),’’ Surveillance Requirement (SR) 3.6.1.3.10 that would increase the single and combined MSIV leakage rate limits; add a new TS 3.6.2.6, ‘‘Residual Heat Removal (RHR) Drywell Spray,’’ to reflect the crediting of drywell spray for fission product removal; and revise TS 3.6.4.1, ‘‘Secondary Containment,’’ SR 3.6.4.1.1 to address shortduration conditions during which the secondary containment pressure may not meet the SR pressure requirement at QCNPS, Units 1 and 2. The license amendment requests are addressed separately. Under Part 50 of 10 CFR, paragraph 50.54(o), primary reactor containments for water-cooled power reactors are subject to the requirements of Appendix J to 10 CFR part 50. Appendix J specifies the leakage rate test requirements, schedules, and acceptance criteria for tests of the leak-tight integrity of the reactor containment, and systems and components that penetrate the containment. Option B of 10 CFR 50, Appendix J, ‘‘Performance-Based Requirements,’’ paragraph III.A, ‘‘Type A Test,’’ requires, among other things, that the overall integrated leakage rate must not exceed the allowable leakage rate (La) with margin, as specified in the TSs. The overall integrated leakage rate is defined in 10 CFR part 50, Appendix J, as ‘‘the total leakage rate through all tested leakage paths, including containment welds, valves, fittings, and components that penetrate the containment system.’’ This includes the contribution through the four main steam (MS) lines where each line contains two MSIVs in series. Paragraph III.B, ‘‘Type B and C Tests,’’ requires, among other things, that the sum of the leakage rates of Type B and Type C local leakage rate tests be less than the performance criterion (La) with margin as specified in the TSs. The allowable leakage rates set in the TSs ensure that the required dose limits, such as in 10 CFR 50.67, ‘‘Accident source term,’’ will not be exceeded. This requested exemption concerns the MS system, which penetrates containment. The licensee requested this exemption because the MS pathway leakage is treated separately from the remainder of the assumed leakage from primary containment in the design basis loss of coolant accident (LOCA) analysis. The radiological consequences of MSIV leakage are modeled as a separate primary containment release path to the environment that bypasses secondary containment, and therefore, it is not filtered through the standby gas treatment system like other PO 00000 Frm 00147 Fmt 4703 Sfmt 4703 containment leakage. The design basis LOCA dose calculation assumes all MSIV leakage migrates to the turbine building and then to the environment. By currently including the MS pathway leakage with the rest of the primary containment leakage test results, it is being accounted for twice—once as part of the actual containment leakage and again as part of the MSIV leakage used in the LOCA dose calculations. III. Discussion Pursuant to 10 CFR 50.12, the Commission may, upon application by any interested person or upon its own initiative, grant exemptions from the requirements of 10 CFR part 50 when (1) the exemptions are authorized by law, will not present an undue risk to public health or safety, and are consistent with the common defense and security; and (2) when special circumstances as described in 10 CFR 50.12(a)(2)(i)–(vi) are present. The licensee asserted that special circumstances are present under 10 CFR 50.12(a)(2)(ii) (stating that the application of the regulation in the particular circumstances would not serve the underlying purpose of the rule or is not necessary to achieve the underlying purpose of the rule). The licensee’s exemption request was submitted with license amendments request to increase the allowable MSIV leakage rate. The exemption and amendments together will permit an increase in allowable MSIV leakage rate that is excluded from the overall integrated leak rate Type A test measurement and excluded from the combined Type B and Type C test total. The licensee described its view on the special circumstances associated with the MSIV leakage path testing in its application dated July 22, 2019. A. The Exemption Is Authorized by Law This exemption permits exclusion of the MSIV pathway leakage contribution from the overall integrated leakage rate Type A test measurement and from the combined leakage rate of all penetrations and valves subject to Type B and Type C tests. As stated above, 10 CFR 50.12 allows the NRC to grant exemptions from the requirements of 10 CFR part 50. The NRC staff has determined that granting of the licensee’s proposed exemption will not result in a violation of the Atomic Energy Act of 1954, as amended, or the Commission’s regulations. Therefore, the exemption is authorized by law. B. The Exemption Presents No Undue Risk to Public Health and Safety Type A tests to measure the containment system overall integrated leakage rate must be conducted under conditions representing design basis LOCA containment peak pressure. Type B pneumatic tests to detect and measure local leakage rates across pressure retaining, leakage-limiting boundaries, and Type C pneumatic tests to measure containment isolation valve leakage rates, must be conducted to ensure the integrity of the overall containment system as a barrier to fission product release to reduce the risk from reactor accidents. In license Amendment Nos. 233 and Amendment 229 (ADAMS Accession No. ML062070290), the NRC approved the use of the alternative source term (AST) (as E:\FR\FM\24JNN1.SGM 24JNN1 Federal Register / Vol. 85, No. 122 / Wednesday, June 24, 2020 / Notices prescribed in 10 CFR 50.67) in the calculations of the radiological dose consequences of design basis accidents (DBAs), including the design basis LOCA, for QCNPS, Units 1 and 2. The NRC staff safety evaluation accompanying these amendments acknowledged that once fission products are dispersed in the primary containment, their release to the environment is assumed to occur through three pathways: (1) The leakage of primary containment atmosphere; (2) the leakage of primary containment atmosphere through MSIVs; and (3) the leakage from emergency core cooling systems that recirculate suppression pool water outside of the primary containment. As noted above, however, leakage through the MSIVs is considered a separate pathway and is calculated as a separate contributor to the dose consequence analysis. As such, the inclusion of MSIV leakage as part of Type A and as part of Type B and C test results is not necessary to ensure the actual radiological consequences of DBAs remain below the regulatory limit. The proposed exemption does not create any new accident precursors. Therefore, the probability of postulated accidents is not increased. Also, the consequences of postulated accidents are not significantly changed from the previously evaluated consequences associated with the design basis LOCA as described in the AST amendments. Therefore, there is no undue risk to public health and safety. jbell on DSKJLSW7X2PROD with NOTICES C. The Exemption Is Consistent With the Common Defense and Security The proposed exemption excludes the MSIV pathway leakage contribution from the overall integrated leakage rate Type A test measurement and from the combined leakage rate of all penetrations and valves subject to Type B and Type C tests. This change to accounting for leakage rate measurement has no relation to security issues. Therefore, the exemption is consistent with the common defense and security. D. Special Circumstances Under 10 CFR 50.12(a)(2)(ii) special circumstances include when, ‘‘[a]pplication of the regulation in the particular circumstances would not serve the underlying purpose of the rule or is not necessary to achieve the underlying purpose of the rule.’’ The test requirements in Appendix J to 10 CFR part 50 ensure that leakage through containments or systems and components penetrating containments does not exceed allowable leakage rates specified in the technical specifications, and integrity of the containment structure is maintained during its service life. Option B of Appendix J identifies the performance-based requirements and criteria for preoperational and subsequent periodic leakage-rate testing. The licensee has analyzed the MS pathway leakage separately from the overall containment integrated leakage; the local leakage across pressure-containing or leakage-limiting boundaries; and the containment isolation valve leakage in its dose consequence analyses. The dose consequences were found to be within the VerDate Sep<11>2014 18:20 Jun 23, 2020 Jkt 250001 applicable acceptance criteria in 10 CFR 50.67, ‘‘Accident source term,’’ and the guidance of NRC Regulatory Guide 1.183, ‘‘Alternative Radiological Source Terms for Evaluating Design Basis Accidents [DBAs] at Nuclear Power Reactors,’’ dated July 2000 (ADAMS Accession No. ML003716792). The staff has reviewed the licensee’s analysis and determined that the dose consequences of implementing the proposed change are below the applicable acceptance criteria and the containment leaks will continue to be limited by the QCNPS, Units 1 and 2, TSs. Therefore, because the underlying purposes of 10 CFR part 50, Appendix J, is still achieved, the special circumstances required by 10 CFR 50.12(a)(2)(ii) for the granting of an exemption from 10 CFR part 50, Appendix J, Option B, Sections lII.A and III.B, exist. E. Environmental Considerations The NRC staff determined that the issuance of the requested exemption meets the provisions of categorical exclusion 10 CFR 51.22(c)(25) because: (i) No significant hazards consideration; (ii) no significant change in the types or significant increase in the amounts of any effluents that may be released offsite; (iii) no significant increase in individual or cumulative public or occupational radiation exposure; (iv) there is no significant construction impact; (v) there is no significant increase in the potential for or consequences from radiological accidents; and (vi) the requirements from which an exemption is sought involve e.g., inspection or surveillance requirements. Therefore, in accordance with 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the NRC’s issuance of this exemption. The basis for the NRC staff’s determination is provided in the following evaluation of the requirements in 10 CFR 51.22(c)(25)(i)–(vi). Requirements in 10 CFR 51.22(c)(25)(i) To qualify for a categorical exclusion under 10 CFR 51.22(c)(25)(i), the exemption must involve ‘‘no significant hazards consideration.’’ The NRC staff evaluated whether the exemption involves no significant hazards consideration by using the standards in 10 CFR 50.92(c), as presented below: 1. Does the requested exemption involve a significant increase in the probability or consequences of an accident previously evaluated? Response: No. The proposed exemption would permit exclusion of the MSIV pathway leakage contribution from the overall integrated leakage rate Type A test measurement and from the sum of the leakage rates from Type B and Type C tests. The leakage of primary containment atmosphere through MSIVs is accounted for as a separate contributor to the design basis LOCA dose consequence analysis. This exemption will allow the leakage testing to be performed in a manner consistent with the way MSIV leakage is modeled in the revised radiological consequence analysis included as part of the related license amendment requests (LARs) PO 00000 Frm 00148 Fmt 4703 Sfmt 4703 37967 submitted in the letter dated March 5, 2019 as supplemented by the letters dated March 23, 2019, February 24, 2020, and March 31, 2020. This change to the leakage rate measurement does not increase the probability or consequences of an accident previously evaluated. Therefore, the exemption does not involve a significant increase in the probability or consequences of an accident previously evaluated. 2. Does the requested exemption create the possibility of a new or different kind of accident from any accident previously evaluated? Response: No. The proposed exemption does not involve a physical modification to the plant (i.e., no new or different type of equipment will be installed and there are no physical modifications to existing equipment associated with the proposed change). Similarly, it does not physically change any structures, systems, or components involved in the mitigation of any accidents. Therefore, the exemption does not create the possibility of a new or different kind of accident from any accident previously evaluated. 3. Does the requested exemption involve a significant reduction in a margin of safety? Response: No. The proposed exemption does not alter a design basis or safety limit nor cause a limit to be exceeded. The proposed exemption allows the results of the TS required MSIV leakage pathway tests to no longer be accounted for as part of the overall integrated leakage rate Type A test measurement and as part of the sum of the local leakage rates from Type B and Type C tests. This change only affects which leakage rates are included in the Types A, B, and C results. This exemption will allow the leakage testing to be performed in a manner consistent with the way MSIV leakage is modeled in the revised radiological consequence analysis submitted as part of the related LAR. Therefore, the exemption does not involve a significant reduction in a margin of safety. Based on the evaluation above, the NRC staff has determined that the proposed exemption involves no significant hazards consideration. Therefore, the requirements of 10 CFR 51.22(c)(25)(i) are met. Requirements in 10 CFR 51.22(c)(9)(ii) To qualify for a categorical exclusion under 10 CFR 51.22(c)(25)(ii), the exemption must result in ‘‘no significant change in the types or significant increase in the amounts of any effluents that may be released offsite.’’ The proposed exemption allows the results of the TS-required MSIV leakage pathway tests to be accounted for only as part of the design basis LOCA E:\FR\FM\24JNN1.SGM 24JNN1 37968 Federal Register / Vol. 85, No. 122 / Wednesday, June 24, 2020 / Notices consequence analysis. This change only affects the total in which the leakage rates are included and does not change the frequency or pressure at which the testing must be performed. The underlying purpose of 10 CFR part 50, Appendix J, is to demonstrate by periodic testing and visual inspection that the primary reactor containment will be able to perform its function of providing an essentially leak-tight barrier against uncontrolled release of radioactivity to the environment. The inclusion of the MSIV leakage testing results in the design basis LOCA serves the same purpose as the inclusion in the rate Type A test measurement and the sum of the leakage rates from Type B and Type C tests required by Appendix J, Option B, paragraphs III.A and III.B. Therefore, the proposed exemption will not significantly change the types of effluents that may be released offsite, or significantly increase the amount of effluents that may be released offsite. Therefore, the requirements of 10 CFR 51.22(c)(25)(ii) are met. Requirements in 10 CFR 51.22(c)(9)(iii) To qualify for a categorical exclusion under 10 CFR 51.22(c)(25)(iii), the exemption must result in ‘‘no significant increase in individual or cumulative public or occupational radiation exposure.’’ The proposed exemption permits the exclusion of the MSIV leakage pathway results from the Type A test measurement and the sum of the leakage rates from Type B and Type C tests required by Appendix J, Option B, paragraphs III.A and III.B, and has no impact on, or change to, fuel or core design. Additionally, the TSs still require that the MSIV leakage rates be tested and maintained below set limits. As such, the calculated public and occupational doses will remain essentially the same. Therefore, the proposed exemption will not significantly increase individual or cumulative public or occupational radiation exposure. Therefore, the requirements of 10 CFR 51.22(c)(25)(iii) are met. jbell on DSKJLSW7X2PROD with NOTICES Requirement in 10 CFR 51.22(c)(25)(iv) To qualify for a categorical exclusion under 10 CFR 51.22(c)(25)(iv), the exemption must result in ‘‘no significant construction impact.’’ The exemption does not propose any changes to the site, alter the site, or change the operation of the site. Therefore, there is no significant construction impact. Therefore, the requirements of 10 CFR 51.22(c)(25)(iv) are met. VerDate Sep<11>2014 18:20 Jun 23, 2020 Jkt 250001 Requirement in 10 CFR 51.22(c)(25)(v) To qualify for a categorical exclusion under 10 CFR 51.22(c)(25)(v), the exemption must involve ‘‘no significant increase in the potential for or consequences from radiological accidents.’’ The proposed exemption does not remove the requirement to perform leakage rate testing of the MSIVs. This exemption will allow the leakage testing to be performed in a manner consistent with the way MSIV leakage is modeled in the revised radiological consequence analysis submitted as part of the related LAR. Therefore, this change to the leakage rate measurement does not result in a significant increase in the potential for or consequences from radiological accidents. Therefore, the requirements of 10 CFR 51.22(c)(25)(v) are met. Requirement in 10 CFR 51.22(c)(25)(vi) To qualify for a categorical exclusion under 10 CFR 51.22(c)(25)(vi)(C), the exemption must involve inspection or surveillance requirements. The exemption seeks to permit exclusion of the MSIV leakage from the overall integrated leak rate Type A test measurement and the combined leakage rate of all penetrations and valves subject to Type B and Type C tests required by Appendix J to 10 CFR part 50. Appendix J specifies the leakage rate test requirements, schedules, and acceptance criteria for tests of the leaktight integrity of the reactor containment, and systems and components that penetrate the containment. Therefore, the exemption involves a surveillance requirement. Therefore, the requirements of 10 CFR 51.22(c)(25)(vi) are met. Conclusion Based on the above, the NRC staff concludes that the proposed exemption meets the eligibility criteria for the categorical exclusion set forth in 10 CFR 51.22(c)(25). Therefore, in accordance with 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the NRC’s issuance of this exemption. IV. Conclusions Accordingly, the NRC has determined that, pursuant to 10 CFR 50.12, the exemption is authorized by law, will not present an undue risk to the public health and safety, and is consistent with the common defense and security. Also, special circumstances are present. Therefore, the NRC hereby grants EGC a permanent exemption (1) from the requirements of 10 CFR part 50, Appendix J, Option B, Section III.A, to PO 00000 Frm 00149 Fmt 4703 Sfmt 4703 allow exclusion of the MSIV pathway leakage from the overall integrated leakage rate measured when performing a Type A test; and (2) from the requirements of 10 CFR part 50, Appendix J, Option B, Section III.B, to allow exclusion of the MSIV pathway leakage from the combined leakage rate of all penetrations and valves subject to Types B and C tests for QCNPS, Units 1 and 2. This exemption is effective upon issuance. Dated: 18th day of June 2020. For the Nuclear Regulatory Commission Craig G. Erlanger, Director, Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation. [FR Doc. 2020–13651 Filed 6–23–20; 8:45 am] BILLING CODE 7590–01–P POSTAL REGULATORY COMMISSION [Docket Nos. MC2020–179 and CP2020–203; MC2020–180 and CP2020–204] New Postal Products Postal Regulatory Commission. Notice. AGENCY: ACTION: The Commission is noticing a recent Postal Service filing for the Commission’s consideration concerning negotiated service agreements. This notice informs the public of the filing, invites public comment, and takes other administrative steps. DATES: Comments are due: June 25, 2020. SUMMARY: Submit comments electronically via the Commission’s Filing Online system at http:// www.prc.gov. Those who cannot submit comments electronically should contact the person identified in the FOR FURTHER INFORMATION CONTACT section by telephone for advice on filing alternatives. ADDRESSES: FOR FURTHER INFORMATION CONTACT: David A. Trissell, General Counsel, at 202–789–6820. SUPPLEMENTARY INFORMATION: Table of Contents I. Introduction II. Docketed Proceeding(s) I. Introduction The Commission gives notice that the Postal Service filed request(s) for the Commission to consider matters related to negotiated service agreement(s). The request(s) may propose the addition or removal of a negotiated service agreement from the market dominant or E:\FR\FM\24JNN1.SGM 24JNN1
[Federal Register Volume 85, Number 122 (Wednesday, June 24, 2020)]
[Pages 37965-37968]
[FR Doc No: 2020-13651]
[Docket Nos. 50-254 and 50-265; NRC-2020-0143]
Exelon Generation Company, LLC and MidAmerican Energy Company
Quad Cities Nuclear Power Station, Units 1 and 2
ACTION: Exemption; issuance.
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) has issued an
exemption in response to a July 22, 2019, request from Exelon
Generation Company, LLC, from certain regulatory requirements in order
to permit exclusion of main steam isolation valve (MSIV) leakage from
the overall integrated leak rate Type A test measurement and MSIV
pathway leakage contributions from the combined leakage rate of all
penetrations and valves subject to Type B and Type C tests.
DATES: The exemption was issued on June 18, 2020.
ADDRESSES: Please refer to Docket ID NRC-2020-0143 when contacting the
Federal Rulemaking Website: Go to https://www.regulations.gov and search for Docket ID NRC-2020-0143. Address
questions about NRC docket IDs in Regulations.gov to Jennifer Borges;
telephone: 301-287-9127; email:
[[Page 37966]]
ADAMS Public Documents collection at https://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``Begin Web-based ADAMS
by email to [email protected]. The ADAMS accession number for each
document referenced (if it is available in ADAMS) is provided the first
time that it is mentioned in this document.
FOR FURTHER INFORMATION CONTACT: Robert F. Kuntz, Office of Nuclear
Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC
20555-0001; telephone: 301-415-3733, email: [email protected].
SUPPLEMENTARY INFORMATION: The text of the exemption is attached.
Project Manager, Plant Licensing Branch III, Division of Operating
Reactor Licensing, Office of Nuclear Reactor Regulation.
Attachment--Exemption
Exelon Generation Company, LLC and MidAmerican Energy Company Quad
Cities Nuclear Power Station, Units 1 and 2
Exelon Generation Company, LLC (EGC, the licensee) and
MidAmerican Energy Company are the holders of Facility Operating
License Nos. DPR-29 and DPR-30, which authorize operation of the
Quad Cities Nuclear Power Station (QCNPS), Units 1 and 2. The
licenses provide, among other things, that the facilities are
subject to the rules, regulations, and orders of the U.S. Nuclear
Regulatory Commission (NRC, the Commission) now or hereafter in
effect. The facilities each consist of a boiling, light-water
reactor located in Rock Island County, Illinois.
In its letter dated March 5, 2019 (Agencywide Documents and
Access Management System (ADAMS) Accession No. ML19064B369), as
supplemented by letters dated May 23, 2019 (ADAMS Accession No.
ML19143A347), July 22, 2019 (ADAMS Accession No. ML19203A176),
February 24, 2020 (ADAMS Accession No. ML20055E826), and March 31,
2020 (ADAMS Accession No., ML20091H576) EGC requested a permanent
exemption from the Part 50 of Title 10 of the Code of Federal
Regulations (10 CFR), Appendix J, Option B, Section III.A
requirements in order to permit exclusion of main steam isolation
valve (MSIV) leakage from the overall integrated leak rate Type A
test measurement, and from Option B, Section III.B, requirements in
order to permit exclusion of the MSIV pathway leakage contributions
from the combined leakage rate of all penetrations and valves
subject to Type B and Type C tests. The letters also requested
license amendments to revise Technical Specification (TS) 3.6.1.3,
``Primary Containment Isolation Valves (PCIVs),'' Surveillance
Requirement (SR) 3.6.1.3.10 that would increase the single and
combined MSIV leakage rate limits; add a new TS 3.6.2.6, ``Residual
Heat Removal (RHR) Drywell Spray,'' to reflect the crediting of
drywell spray for fission product removal; and revise TS 3.6.4.1,
``Secondary Containment,'' SR 3.6.4.1.1 to address short-duration
conditions during which the secondary containment pressure may not
meet the SR pressure requirement at QCNPS, Units 1 and 2. The
license amendment requests are addressed separately.
Under Part 50 of 10 CFR, paragraph 50.54(o), primary reactor
containments for water-cooled power reactors are subject to the
requirements of Appendix J to 10 CFR part 50. Appendix J specifies
the leakage rate test requirements, schedules, and acceptance
criteria for tests of the leak-tight integrity of the reactor
containment, and systems and components that penetrate the
containment. Option B of 10 CFR 50, Appendix J, ``Performance-Based
Requirements,'' paragraph III.A, ``Type A Test,'' requires, among
other things, that the overall integrated leakage rate must not
exceed the allowable leakage rate (La) with margin, as
specified in the TSs. The overall integrated leakage rate is defined
in 10 CFR part 50, Appendix J, as ``the total leakage rate through
all tested leakage paths, including containment welds, valves,
fittings, and components that penetrate the containment system.''
This includes the contribution through the four main steam (MS)
lines where each line contains two MSIVs in series. Paragraph III.B,
``Type B and C Tests,'' requires, among other things, that the sum
of the leakage rates of Type B and Type C local leakage rate tests
be less than the performance criterion (La) with margin
as specified in the TSs. The allowable leakage rates set in the TSs
ensure that the required dose limits, such as in 10 CFR 50.67,
``Accident source term,'' will not be exceeded.
This requested exemption concerns the MS system, which
penetrates containment. The licensee requested this exemption
because the MS pathway leakage is treated separately from the
remainder of the assumed leakage from primary containment in the
design basis loss of coolant accident (LOCA) analysis. The
radiological consequences of MSIV leakage are modeled as a separate
primary containment release path to the environment that bypasses
secondary containment, and therefore, it is not filtered through the
standby gas treatment system like other containment leakage. The
design basis LOCA dose calculation assumes all MSIV leakage migrates
to the turbine building and then to the environment. By currently
including the MS pathway leakage with the rest of the primary
containment leakage test results, it is being accounted for twice--
once as part of the actual containment leakage and again as part of
the MSIV leakage used in the LOCA dose calculations.
Pursuant to 10 CFR 50.12, the Commission may, upon application
by any interested person or upon its own initiative, grant
exemptions from the requirements of 10 CFR part 50 when (1) the
exemptions are authorized by law, will not present an undue risk to
public health or safety, and are consistent with the common defense
and security; and (2) when special circumstances as described in 10
CFR 50.12(a)(2)(i)-(vi) are present. The licensee asserted that
special circumstances are present under 10 CFR 50.12(a)(2)(ii)
(stating that the application of the regulation in the particular
circumstances would not serve the underlying purpose of the rule or
is not necessary to achieve the underlying purpose of the rule).
The licensee's exemption request was submitted with license
amendments request to increase the allowable MSIV leakage rate. The
exemption and amendments together will permit an increase in
allowable MSIV leakage rate that is excluded from the overall
integrated leak rate Type A test measurement and excluded from the
combined Type B and Type C test total. The licensee described its
view on the special circumstances associated with the MSIV leakage
path testing in its application dated July 22, 2019.
This exemption permits exclusion of the MSIV pathway leakage
contribution from the overall integrated leakage rate Type A test
measurement and from the combined leakage rate of all penetrations
and valves subject to Type B and Type C tests. As stated above, 10
CFR 50.12 allows the NRC to grant exemptions from the requirements
of 10 CFR part 50. The NRC staff has determined that granting of the
licensee's proposed exemption will not result in a violation of the
Atomic Energy Act of 1954, as amended, or the Commission's
regulations. Therefore, the exemption is authorized by law.
Type A tests to measure the containment system overall
integrated leakage rate must be conducted under conditions
representing design basis LOCA containment peak pressure. Type B
pneumatic tests to detect and measure local leakage rates across
pressure retaining, leakage-limiting boundaries, and Type C
pneumatic tests to measure containment isolation valve leakage
rates, must be conducted to ensure the integrity of the overall
containment system as a barrier to fission product release to reduce
the risk from reactor accidents.
In license Amendment Nos. 233 and Amendment 229 (ADAMS Accession
No. ML062070290), the NRC approved the use of the alternative source
term (AST) (as
[[Page 37967]]
prescribed in 10 CFR 50.67) in the calculations of the radiological
dose consequences of design basis accidents (DBAs), including the
design basis LOCA, for QCNPS, Units 1 and 2. The NRC staff safety
evaluation accompanying these amendments acknowledged that once
fission products are dispersed in the primary containment, their
release to the environment is assumed to occur through three
pathways: (1) The leakage of primary containment atmosphere; (2) the
leakage of primary containment atmosphere through MSIVs; and (3) the
leakage from emergency core cooling systems that recirculate
suppression pool water outside of the primary containment. As noted
above, however, leakage through the MSIVs is considered a separate
pathway and is calculated as a separate contributor to the dose
consequence analysis. As such, the inclusion of MSIV leakage as part
of Type A and as part of Type B and C test results is not necessary
to ensure the actual radiological consequences of DBAs remain below
the regulatory limit.
The proposed exemption does not create any new accident
precursors. Therefore, the probability of postulated accidents is
not increased. Also, the consequences of postulated accidents are
not significantly changed from the previously evaluated consequences
associated with the design basis LOCA as described in the AST
amendments. Therefore, there is no undue risk to public health and
The proposed exemption excludes the MSIV pathway leakage
and valves subject to Type B and Type C tests. This change to
accounting for leakage rate measurement has no relation to security
issues. Therefore, the exemption is consistent with the common
defense and security.
Under 10 CFR 50.12(a)(2)(ii) special circumstances include when,
``[a]pplication of the regulation in the particular circumstances
would not serve the underlying purpose of the rule or is not
necessary to achieve the underlying purpose of the rule.''
The test requirements in Appendix J to 10 CFR part 50 ensure
that leakage through containments or systems and components
penetrating containments does not exceed allowable leakage rates
specified in the technical specifications, and integrity of the
containment structure is maintained during its service life. Option
B of Appendix J identifies the performance-based requirements and
criteria for preoperational and subsequent periodic leakage-rate
The licensee has analyzed the MS pathway leakage separately from
the overall containment integrated leakage; the local leakage across
pressure-containing or leakage-limiting boundaries; and the
containment isolation valve leakage in its dose consequence
analyses. The dose consequences were found to be within the
applicable acceptance criteria in 10 CFR 50.67, ``Accident source
term,'' and the guidance of NRC Regulatory Guide 1.183,
Accidents [DBAs] at Nuclear Power Reactors,'' dated July 2000 (ADAMS
Accession No. ML003716792). The staff has reviewed the licensee's
analysis and determined that the dose consequences of implementing
the proposed change are below the applicable acceptance criteria and
the containment leaks will continue to be limited by the QCNPS,
Units 1 and 2, TSs.
Therefore, because the underlying purposes of 10 CFR part 50,
Appendix J, is still achieved, the special circumstances required by
10 CFR 50.12(a)(2)(ii) for the granting of an exemption from 10 CFR
part 50, Appendix J, Option B, Sections lII.A and III.B, exist.
The NRC staff determined that the issuance of the requested
exemption meets the provisions of categorical exclusion 10 CFR
51.22(c)(25) because: (i) No significant hazards consideration; (ii)
no significant change in the types or significant increase in the
amounts of any effluents that may be released offsite; (iii) no
significant increase in individual or cumulative public or
occupational radiation exposure; (iv) there is no significant
construction impact; (v) there is no significant increase in the
potential for or consequences from radiological accidents; and (vi)
the requirements from which an exemption is sought involve e.g.,
inspection or surveillance requirements. Therefore, in accordance
with 10 CFR 51.22(b), no environmental impact statement or
environmental assessment need be prepared in connection with the
NRC's issuance of this exemption. The basis for the NRC staff's
determination is provided in the following evaluation of the
requirements in 10 CFR 51.22(c)(25)(i)-(vi).
To qualify for a categorical exclusion under 10 CFR
51.22(c)(25)(i), the exemption must involve ``no significant hazards
consideration.'' The NRC staff evaluated whether the exemption
involves no significant hazards consideration by using the standards
in 10 CFR 50.92(c), as presented below:
1. Does the requested exemption involve a significant increase
in the probability or consequences of an accident previously
The proposed exemption would permit exclusion of the MSIV
pathway leakage contribution from the overall integrated leakage
rate Type A test measurement and from the sum of the leakage rates
from Type B and Type C tests. The leakage of primary containment
atmosphere through MSIVs is accounted for as a separate contributor
to the design basis LOCA dose consequence analysis. This exemption
will allow the leakage testing to be performed in a manner
consistent with the way MSIV leakage is modeled in the revised
radiological consequence analysis included as part of the related
license amendment requests (LARs) submitted in the letter dated
March 5, 2019 as supplemented by the letters dated March 23, 2019,
February 24, 2020, and March 31, 2020. This change to the leakage
rate measurement does not increase the probability or consequences
of an accident previously evaluated.
Therefore, the exemption does not involve a significant increase
2. Does the requested exemption create the possibility of a new
The proposed exemption does not involve a physical modification
to the plant (i.e., no new or different type of equipment will be
installed and there are no physical modifications to existing
equipment associated with the proposed change). Similarly, it does
not physically change any structures, systems, or components
involved in the mitigation of any accidents.
Therefore, the exemption does not create the possibility of a
new or different kind of accident from any accident previously
3. Does the requested exemption involve a significant reduction
The proposed exemption does not alter a design basis or safety
limit nor cause a limit to be exceeded. The proposed exemption allows
the results of the TS required MSIV leakage pathway tests to no longer
be accounted for as part of the overall integrated leakage rate Type A
test measurement and as part of the sum of the local leakage rates from
Type B and Type C tests. This change only affects which leakage rates
are included in the Types A, B, and C results. This exemption will
allow the leakage testing to be performed in a manner consistent with
the way MSIV leakage is modeled in the revised radiological consequence
analysis submitted as part of the related LAR.
Therefore, the exemption does not involve a significant reduction
Based on the evaluation above, the NRC staff has determined that
the proposed exemption involves no significant hazards consideration.
Therefore, the requirements of 10 CFR 51.22(c)(25)(i) are met.
51.22(c)(25)(ii), the exemption must result in ``no significant change
in the types or significant increase in the amounts of any effluents
that may be released offsite.'' The proposed exemption allows the
results of the TS-required MSIV leakage pathway tests to be accounted
for only as part of the design basis LOCA
[[Page 37968]]
consequence analysis. This change only affects the total in which the
leakage rates are included and does not change the frequency or
pressure at which the testing must be performed. The underlying purpose
of 10 CFR part 50, Appendix J, is to demonstrate by periodic testing
and visual inspection that the primary reactor containment will be able
to perform its function of providing an essentially leak-tight barrier
against uncontrolled release of radioactivity to the environment. The
inclusion of the MSIV leakage testing results in the design basis LOCA
serves the same purpose as the inclusion in the rate Type A test
measurement and the sum of the leakage rates from Type B and Type C
tests required by Appendix J, Option B, paragraphs III.A and III.B.
Therefore, the proposed exemption will not significantly change the
types of effluents that may be released offsite, or significantly
increase the amount of effluents that may be released offsite.
Therefore, the requirements of 10 CFR 51.22(c)(25)(ii) are met.
51.22(c)(25)(iii), the exemption must result in ``no significant
increase in individual or cumulative public or occupational radiation
exposure.'' The proposed exemption permits the exclusion of the MSIV
leakage pathway results from the Type A test measurement and the sum of
the leakage rates from Type B and Type C tests required by Appendix J,
Option B, paragraphs III.A and III.B, and has no impact on, or change
to, fuel or core design. Additionally, the TSs still require that the
MSIV leakage rates be tested and maintained below set limits. As such,
the calculated public and occupational doses will remain essentially
the same. Therefore, the proposed exemption will not significantly
increase individual or cumulative public or occupational radiation
exposure. Therefore, the requirements of 10 CFR 51.22(c)(25)(iii) are
51.22(c)(25)(iv), the exemption must result in ``no significant
construction impact.'' The exemption does not propose any changes to
the site, alter the site, or change the operation of the site.
Therefore, there is no significant construction impact. Therefore, the
requirements of 10 CFR 51.22(c)(25)(iv) are met.
51.22(c)(25)(v), the exemption must involve ``no significant increase
in the potential for or consequences from radiological accidents.'' The
proposed exemption does not remove the requirement to perform leakage
rate testing of the MSIVs. This exemption will allow the leakage
testing to be performed in a manner consistent with the way MSIV
leakage is modeled in the revised radiological consequence analysis
submitted as part of the related LAR. Therefore, this change to the
leakage rate measurement does not result in a significant increase in
the potential for or consequences from radiological accidents.
Therefore, the requirements of 10 CFR 51.22(c)(25)(v) are met.
51.22(c)(25)(vi)(C), the exemption must involve inspection or
surveillance requirements. The exemption seeks to permit exclusion of
the MSIV leakage from the overall integrated leak rate Type A test
measurement and the combined leakage rate of all penetrations and
valves subject to Type B and Type C tests required by Appendix J to 10
CFR part 50. Appendix J specifies the leakage rate test requirements,
schedules, and acceptance criteria for tests of the leak-tight
integrity of the reactor containment, and systems and components that
penetrate the containment. Therefore, the exemption involves a
surveillance requirement. Therefore, the requirements of 10 CFR
51.22(c)(25)(vi) are met.
Based on the above, the NRC staff concludes that the proposed
exemption meets the eligibility criteria for the categorical exclusion
set forth in 10 CFR 51.22(c)(25). Therefore, in accordance with 10 CFR
need be prepared in connection with the NRC's issuance of this
Accordingly, the NRC has determined that, pursuant to 10 CFR 50.12,
the exemption is authorized by law, will not present an undue risk to
the public health and safety, and is consistent with the common defense
and security. Also, special circumstances are present. Therefore, the
NRC hereby grants EGC a permanent exemption (1) from the requirements
of 10 CFR part 50, Appendix J, Option B, Section III.A, to allow
exclusion of the MSIV pathway leakage from the overall integrated
leakage rate measured when performing a Type A test; and (2) from the
requirements of 10 CFR part 50, Appendix J, Option B, Section III.B, to
allow exclusion of the MSIV pathway leakage from the combined leakage
rate of all penetrations and valves subject to Types B and C tests for
QCNPS, Units 1 and 2.
Director, Division of Operating Reactor Licensing Office of Nuclear
Reactor Regulation.