ML24208A045

OMB-3150-0011 Final 2024 Collection Renewal, 10 CFR Part 50 Domestic Licensing of Production and Utilization Facilities - Supporting Statement Section 4

ML24208A045
Person / Time
Issue date:	10/17/2024
From:	Office of Nuclear Reactor Regulation
To:	NRC/OCIO
Shared Package
ML24194A039	List: ML24208A038 ML24208A039 ML24208A040 ML24208A041 ML24208A042 ML24208A043 ML24208A044 ML24208A045
References
OMB-3150-0011, NRC-2023-0161
Download: ML24208A045 (15)

Text

1 FINAL SUPPORTING STATEMENT FOR 10 CFR PART 50 INSPECTIONS, RECORDS, REPORTS, NOTIFICATIONS SECTION 4 50.71(b), 50.76 & Appendix C Section III, Financial; 50.71(e), Updated FSAR; 50.72, 50.54(z) & Appendix E, Notification of Events; 50.72(a) & 50 Appendix E.VI, Emergency Response Data System; 50.73, (LERs) - (see OMB Clearance No. 3150-0104); 50.70, Team Inspections; 50.69, Risk-Informed Categorization of Structures, Systems, and Components 3150-0011 ABSTRACT The U.S. Nuclear Regulatory Commission (NRC) is authorized by Congress to have responsibility and authority for the licensing and regulation of nuclear power plants, research/test facilities, fuel reprocessing plants and other utilization and production facilities licensed pursuant to the Act. Once a facility has received a license, the licensee submits information and keeps records to allow the NRC to verify that activities are properly conducted and to ensure safe operations in accordance with NRC's regulations.

These regulations affect 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities licensees for operating nuclear power plants, licensed non-power production and utilization facilities (NPUF), other new technologies (ONTs), such as light (LWRs) and non-light-water reactors (non-LWRs), and power plants that are currently being decommissioned. Also, license and permit holders, and applicants under 10 CFR Part 52, Licenses, Certifications, and Approvals for Nuclear Power Plants. These entities total 195 respondents for the current clearance cycle. Licensees may voluntarily submit a request for an exemption to the Commission and maintain a record of that request. Licensees must perform certain tasks, maintain records and prepare reports to demonstrate their fulfillment of regulatory requirements.

This renewal incorporates information collection changes made as part of the Emergency Preparedness (EP) for Small Modular Reactors (SMR) and Other New Technologies (ONT)

Final Rule, approved by OMB on October 13, 2023. To allow maximum flexibility while continuing to provide adequate protection of public health and safety and the common defense and security, the NRC made the new EP requirements an alternative to the current requirements. Thus, existing SMR or ONT facilities or future facilities licensed after the effective date of the final rule will use either the new performance-based EP program or the existing deterministic EP requirements in 10 CFR Part 50.

The reporting and recordkeeping requirements pertain to financial reports, including certified financial statements; periodic update of the originally submitted Final Safety Analysis Report (FSAR), (describes important structure, systems and components at a licensed site); reactor event reports; electronic real-time transmittal of data during an alert or higher emergency at a nuclear power facility; copies of analyses, evaluations or documentation regarding the implementation and maintenance of the station fire protection program, including post-fire safe shutdown capability, fire protection compliance assessment, corrective actions, risk-related documents and license amendment applications.

2 A.

JUSTIFICATION

1.

Need for the Collection of Information In order to determine licensee compliance with the regulations set forth in 50.71(b) & Appendix C; 50.71(e); 50.72 & 50.54(z), Appendix E; 50.72(a); 50.73; 50.70; and 50.69. Details of these regulations can be found at the end of this supporting statement in Description of Requirements.

2.

Agency Use and Practical Utility of Information Applicants or licensees requesting approval to construct or operate utilization or production facilities are required by the Atomic Energy Act of 1954, as amended (the Act), to provide information and data that the NRC may determine necessary to ensure the health and safety of the public.

The NRC uses the records and reports required in this part to ascertain that licensees licensing the design, construction, operation, and decommissioning of commercial nuclear power plants and other nuclear facilities programs are adequate to protect public health and minimize danger to life and property and that licensees personnel are aware of and follow up on the information and steps needed to perform licensed activities in a safe manner. The reports and recordkeeping requirements allow NRC to determine whether to take actions, such as to conduct inspections or to alert other licensees to prevent similar events that may have generic implications and to ensure that the ERDS link is maintained for reliable communication of critical parameters during an emergency.

3.

Reduction of Burden Through Information Technology The NRC has issued Guidance for Electronic Submissions to the NRC which provides direction for the electronic transmission and submittal of documents to the NRC. Electronic transmission and submittal of documents can be accomplished via the following avenues: the Electronic Information Exchange (EIE) process, which is available from the NRC's Electronic Submittals Web page, by Optical Storage Media (OSM) (e.g. CD-ROM, DVD), or by e-mail. It is estimated that approximately 80% of the potential responses are filed electronically.

4.

Effort to Identify Duplication and Use Similar Information No sources of similar information are available. There is no duplication of requirements.

5.

Effort to Reduce Small Business Burden Not applicable.

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6.

Consequences to Federal Program or Policy Activities if the Collection is Not Conducted or is Conducted Less Frequently Applicants or licensees requesting approval to construct or operate utilization or production facilities are required by the Atomic Energy Act of 1954, as amended (the Act), to provide information and data that the NRC may determine necessary to ensure the health and safety of the public. If the information is not collected, NRC will not be in a position to assess whether licensees are operating within the specific safety requirements applicable to the licensing and operating activities for existing nuclear power reactors and research and test reactors. The information and required frequency from licensees that seek to licensee and operate nuclear power reactors and research and test reactors is essential to NRCs determination of whether the applicant has adequate equipment, training, funds and experience throughout the life of the licensee to protect the public health and safety.

7.

Circumstances which Justify Variation From OMB Guidelines Section 10 CFR 50.71(e)(1) The updated FSAR must be retained until the operating license is terminated in order for the NRC to ensure the health and safety of the public at all times, the staff must be certain of the current status of a facility's design and supporting analysis.

Section 10 CFR 50.72(a)(1) and 10 CFR 50.72(a)(2) Notification of significant events is needed within one to eight hours to ensure that the NRC promptly responds to situations with the potential to seriously impact public health and safety. Additionally, it allows the NRC to be informed of significant events in order to respond to public inquiries.

Section 10 CFR 50.70 Normally, this information collection will not vary from OMB guidelines. However, there may be occasions when the information will be requested in less than 30 days to ensure that the information is current.

8.

Consultations Outside the NRC Opportunity for public comment on the information collection requirements for this clearance package was published in the Federal Register on June 13, 2024 (89 FR 50381). Additionally, NRC staff contacted eight stakeholders via email. The stakeholders included operating reactor licensees, licensed and under construction non-power production and utilization facilities, as well as power reactors being decommissioned and industry representatives from Constellation Energy, Holtec International, Southern Nuclear Operating Co., Inc, SHINE Technologies, Abilene Christian University, Oregon State University, Texas A & M University, and Energy Solutions.

No responses or comments were received from the FRN publication or the staffs direct solicitation of comments related to this section.

9.

Payment or Gift to Respondents Not applicable.

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10.

Confidentiality of Information Confidential and proprietary information is protected in accordance with NRC regulations at 10 CFR 9.17(a) and 10 CFR 2.390(b).

11.

Justification for Sensitive Questions This regulation does not request sensitive information.

12.

Estimated Industry Burden and Burden Hour Cost The total estimated cost for information collection requirements in this section is estimated to be 126,925 hours0.0107 days <br />0.257 hours <br />0.00153 weeks <br />3.519625e-4 months <br /> at a cost of $38.077M (126,925 hours0.0107 days <br />0.257 hours <br />0.00153 weeks <br />3.519625e-4 months <br /> x $300/hr).

Total Burden and Responses Section 4 Hours Responses Reporting 78,661 35,795 Recordkeeping 48,264 94 TOTAL 126,925 35,889 Detailed burden estimates are included in the supplemental burden spreadsheet titled, Table 1 - Summary of Supporting Statements. The $300 hourly rate used in the burden estimates is based on the Nuclear Regulatory Commissions fee for hourly rates as noted in 10 CFR 170.20 Average cost per professional staff-hour.

For more information on the basis of this rate, see the Revision of Fee Schedules, Fee Recovery for Fiscal Year 2023 (88 FR 39120, June 15, 2023).

13.

Estimate of Other Additional Costs The quantity of records to be maintained is roughly proportional to the recordkeeping burden and therefore can be used to calculate approximate records storage costs.

Based on the number of pages maintained for a typical clearance, the records storage cost has been determined to be equal to.0004 times the recordkeeping burden cost. Therefore, the storage cost for this clearance is estimated to be

$5,792 (48,264 recordkeeping hours x $300 x.0004).

14.

Estimated Annualized Cost to the Federal Government The staff has developed estimates of annualized costs to the Federal Government related to the conduct of this collection of information. These estimates are based on staff experience and subject matter expertise and include the burden needed to review, analyze, and process the collected information and any relevant operational expenses.

The annualized estimated cost to the government is $12,388,500 (41,295 staff hours x

$300) as shown on the attached Summary Table.

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15.

Reasons for Changes in Burden or Cost The burden and number of responses have changed as described in the tables below:

Burden change 2021 estimates Current submission Change Reporting 70,036 78,661

+8,625 Recordkeeping 28,690 48,264

+19,574 Third Party Disclosure 0

0 Total 98,726 126,925

+28,199 Change in Responses 2021 estimates Current submission Change Reporting 34,190 35,795

+1,605 Recordkeeping 120 94

-26 Third Party Disclosure 0

0 0

Total 34,310 35,889

+1,579 External programs are contributing to the progression of advanced reactor designs, causing an influx of applications during this clearance cycle. Due to these programs, ongoing robust pre-application engagements (i.e., topical report reviews), and meetings, discussions and continuous contact with prospective stakeholders, the agency is expected to receive applications for, construction permits (CP), early site permits (ESP), standard design approvals (SDAs) and certifications, manufacturing license (MLs), combined licensees (COLs), for commercial nuclear power reactors, as well as operating licenses (OLs) related to the licensing processes that apply to light-water reactors (LWR) and non-light water reactors (NLWR). The effects if any of these projected applications on the requirements in this section are captured below.

Additionally, digitized electronic recordkeeping and advancement in technology has impacted the burden to maintain records. Staff has recognized these advancements and applied burden accordingly. The effects if any are captured below.

Overall, for this section, the burden increased from 98,726 to 126,925, a total of 28,199 hours0.0023 days <br />0.0553 hours <br />3.290344e-4 weeks <br />7.57195e-5 months <br />, thus affecting the following requirements:

6 Reporting Increases:

Section, 50.71(e), Updated FSAR (operating reactors), increased by 3 respondents, increasing the total burden 2,700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br />.

Section, 50.71(e), Updated FSAR (power reactors that have ceased operating), increased by 9 respondents, increasing the total burden 2,025 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />.

When a licensee makes a 10 CFR 50.72 ENS notification and later determines that the event or condition was not reportable, the licensee should retract the notification and explain the rationale for that decision, most retractions occur following completion of additional engineering and/or management review, it is expected that retractions would occur shortly after such review. In the previous cycle, staff inadvertently omitted these notifications, this has been corrected and the impact if any on the affected section(s) are outlined below:

Section, 50.72 & 50.54(z) (Notification of Events), decreased by 26 respondents and 52 responses that were inadvertently included in the requirement in the last cycle, however, staff increased the burden per response from 1 to 5.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> based on stakeholder interaction and understanding of effort needed by submitter, increasing the total burden 841 hours0.00973 days <br />0.234 hours <br />0.00139 weeks <br />3.200005e-4 months <br />.

Section, 50.72 & 50.54(z), Notification of Events (Retractions), accounts for retracted submissions when required, added 94 respondents and 376 hours0.00435 days <br />0.104 hours <br />6.216931e-4 weeks <br />1.43068e-4 months <br />.

Section, Appendix E, Paragraph E.9.d, Daily testing of the ENS system by the HOO, increased by 3 respondents due to an increase in sites, increasing the total burden 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br />.

Section, 50.72(a), based on plant drill participation, staff increased the projection by 18 respondents, increasing the total burden 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

Section, 50.70, Team Inspections, increased by 3 respondents due to an increase in sites, increasing the total burden 480 hours0.00556 days <br />0.133 hours <br />7.936508e-4 weeks <br />1.8264e-4 months <br />.

Section, 50.70, Other Inspections, increased by 3 respondents due to an increase in sites, increasing the total burden 135 hours0.00156 days <br />0.0375 hours <br />2.232143e-4 weeks <br />5.13675e-5 months <br />.

Reporting Decreases:

Section, Appendix E, VI.1 Periodic Testing, decreased by 26 respondents that were inadvertently included in the requirement in the last cycle and 208 hours0.00241 days <br />0.0578 hours <br />3.439153e-4 weeks <br />7.9144e-5 months <br />.

Recordkeeping Increases:

Section, 50.71(e), Updated FSAR (operating reactors), increased 3 recordkeepers due to an increase in sites, 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> per recordkeeper, and 3000 hours0.0347 days <br />0.833 hours <br />0.00496 weeks <br />0.00114 months <br /> to meet the requirements of Section 50.155(f) Documentation of Changes that are being maintained under this section.

Section, 50.71(h)(1), Fuel Load, requires no later than the scheduled date for initial loading of fuel, each holder of a combined license under subpart C of 10 CFR part 52 shall develop a level 1 and a level 2 probabilistic risk

7 assessment (PRA). The staff estimates 10 recordkeepers and 15,330 hours0.00382 days <br />0.0917 hours <br />5.456349e-4 weeks <br />1.25565e-4 months <br /> for during this clearance cycle.

Section, 50.71(h)(2), Fuel Load (Quadrennial), requires each holder of a combined license shall maintain and upgrade the PRA required by paragraph (h)(1) of this section. Staff anticipates this will include 5 recordkeepers and 1,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> during this clearance cycle.

Section, 50.72 & 50.54(z) Notification of Events (Retractions), When a licensee makes a 10 CFR 50.72 ENS notification and later determines that the event or condition was not reportable, the licensee should retract the notification and explain the rationale for that decision, it is expected that retractions would occur shortly after such review. In the previous cycle, staff inadvertently omitted these notifications, this has been corrected in this cycle, which added 94 recordkeepers and 9.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Section, Appendix E, VI.1 Periodic Testing, NRC staff increased the burden per recordkeeper from 0.2 to 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />, increasing the overall burden 23 hours2.662037e-4 days <br />0.00639 hours <br />3.80291e-5 weeks <br />8.7515e-6 months <br />.

Section, 50.72(a), increased by 18 recordkeepers, NRC staff increased the burden per recordkeeper from 0.4 to 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />, increasing the total burden 9.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.

Recordkeeping Decreases:

Section, 50.72 & 50.54(z), Notification of Events, decreased 26 recordkeepers and 21 hours2.430556e-4 days <br />0.00583 hours <br />3.472222e-5 weeks <br />7.9905e-6 months <br />, included entities not subject to the requirements in the previous cycle.

Section, Appendix E, VI.3 a&b, due to less burdensome digitized electronic recordkeeping, NRC staff decreased the burden per recordkeeper from 1.2 to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, decreasing the overall burden 1.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

16.

Publication for Statistical Use The information being collected is not expected to be published for statistical use.

17.

Reason for Not Displaying the Expiration Date The recordkeeping and reporting requirements for this information collection are associated with regulations and are not submitted on instruments such as forms or surveys. For this reason, there are no data instruments on which to display an OMB expiration date. Further, amending the regulatory text of the CFR to display information that, in an annual publication, could become obsolete would be unduly burdensome and too difficult to keep current.

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18.

Exceptions to the Certification Statement None.

B.

COLLECTIONS OF INFORMATION EMPLOYING STATISTICAL METHODS Not applicable.

9 Appendix A - Description Requirements Inspections, Records, Reports, Notifications 10 CFR 50.68(b)(8) requires licensees to comply with eight specific criticality accident requirements as an alternative to maintaining a monitoring system capable of detecting a criticality as described in 10 CFR 70.24. Should licensees elect to comply with 10 CFR 50.68(b), they are required to indicate that it has chosen to comply with 10 CFR 50.68 in lieu of 10 CFR 50.74 as part of its FSAR update (in accordance with 10 CFR 50.71(e)).

Burden for this requirement is included in 50.71 for FSAR updates.

Title 10 of the Code of Federal Regulations (10 CFR) Section 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors, became effective on December 22, 2004 (69 Federal Register (FR) 68008).

Section 10 CFR 50.69 provides a voluntary alternative set of requirements under which a licensee may obtain relief from some unnecessary regulatory burden for those SSCs that are determined through a risk-informed categorization process to be of low safety-significance.

The regulation is intended to provide more flexibility to licensees in the application of treatment requirements for low safety-significant SSCs, by replacing some of the prescriptive programmatic requirements with more general performance requirements. Requirements are included to specify the process for obtaining the Nuclear Regulatory Commission (NRC) approval for modifying licenses to establish programs to implement the alternative requirements and for licensee preparation of ongoing SSC performance evaluations against established standards. Recordkeeping and reporting requirements are modified only for those licensees or applicants who voluntarily choose to implement the alternative requirements of 10 CFR 50.69.

To use the alternative provisions of 10 CFR 50.69, a licensee or applicant must evaluate the safety significance of SSCs and categorize each SSC into one of four categories defined as risk-informed safety class (RISC)-1, RISC-2, RISC-3, and RISC-4. Section 10 CFR 50.69 establishes revised treatment and less prescriptive and burdensome information collection requirements for safety and non-safety SSCs categorized as performing low safety-significant functions (RISC-3 and RISC-4), but also contains requirements for on-going evaluations to ensure safety standards are maintained and that records of categorization decisions are maintained.

Within recent years, nearly 40% of power reactor sites have either adopted the provisions of 10 CFR 50.69 or have license amendment requests under NRC review to allow them to do so. As a result of increased licensee adoption of 10 CFR 50.69, risk-informed categorization inspection is performed as needed at all U.S. nuclear sites. Information requested for this inspection includes copies of procedures that describe the categorization and treatment process for Structures, Systems, and Components (SSCs), and analysis of SSCs that have been categorized.

Section 10 CFR 50.70 requires power-reactor licensees to permit inspection of licensee records, premises, activities, and licensed material as necessary for the NRC to ensure public health and safety. Inspection activities include performance of ROP Baseline Inspection (resident and team inspections), Supplemental Inspections, Special and Infrequently Performed Inspections, Temporary Instructions, and Reactive Inspections. Prior to conducting the inspection activity, the agency may request information from the licensees

10 to aid the inspector. This information typically consists of analysis records, maintenance records, program implementation documents, and corrective action documents. Licensees may submit this information via traditional mail, email, other electronic means such as information portals, or have such information readily assembled on site prior to conduct of an inspection.

Section 50.71(b) of 10 CFR requires licensees and holders of construction permits to file with the Commission annual financial reports, including certified financial statements. This requirement is also specified in 10 CFR 50 Appendix C, Section III, for holders of construction permits. The fundamental purpose of the financial qualifications provision is the protection of public health and safety and the common defense and security. A licensee's or holder's (including a co-owner's) financial resources may affect its ability to meet its responsibilities on safety matters.

Section 10 CFR 50.71(e)(1) requires licensees to submit revisions containing the updated FSAR information on a replacement-page basis, accompanied by a list which identifies the current pages of the FSAR following page replacement. This includes periodic updates and revisions to the Quality Assurance Program Description (QAPD) that do not represent a reduction in commitments as defined by 10 CFR 50.54(a)(3) and changes to QAPDs requiring prior approval from the Commission under 10 CFR 50.54(a)(4).

Section 10 CFR 50.71(e)(2) requires that FSAR-update submittals include a certification by a duly authorized official of the licensee that either the information accurately presents changes made since the previous submittal, necessary to reflect information and analyses submitted to or required by the Commission, or that no such changes were made; and an identification of changes made under the provisions of 10 CFR 50.59 but not previously submitted to the Commission.

Section 10 CFR 50.71(e)(3) requires a revision of the original FSAR containing those original pages that are still applicable plus new replacement pages to be filed with 24 months of either July 22, 1980, or the date of issuance of the operating license, whichever is later, and shall bring the FSAR up to date as of a maximum of 6 months prior to the date of filing the revision.

Section 10 CFR 50.71(e)(4) requires the filing of revisions annually or 6 months after each refueling outage provided the interval between successive updates to the FSAR does not exceed 24 months. The revisions must reflect all changes up to a maximum of 6 months prior to the date of filing. For nuclear power reactor facilities that have submitted 10 CFR 50.82(a)(1) certifications, subsequent revisions must be filed every 24 months.

Section 10 CFR 50.71(e)(5) requires each replacement page to include both a change indicator for the area changed, e.g., a bold line vertically drawn in the margin adjacent to the portion actually changed, and a page change identification (date of change or change number or both).

Section 10 CFR 50.71(e)(6) requires licensees to retain the updated FSAR until termination of the license.

Section 10 CFR 50.71(f) requires each person licensed to manufacture a nuclear power reactor under subpart F of 10 CFR 52 shall update the FSAR originally submitted as part of

11 the application to reflect any modification to the design that is approved by the Commission under 52.171 and any new analyses of the design performed by or on behalf of the licensee at the NRCs request. This submittal shall contain all changes necessary to reflect information and analyses submitted to the Commission by the licensee or prepared by the licensee with respect to the modification approved under 52.171 or analyses requested by the Commission.

Section 10 CFR 50.71(h)(1) requires no later than the scheduled date for initial loading of fuel, each holder of a combined license under subpart C of 10 CFR part 52 shall develop a level 1 and a level 2 probabilistic risk assessment (PRA). The PRA must cover those initiating events and modes for which NRC-endorsed consensus standards on PRA exist one year prior to the scheduled date for initial loading of fuel.

Section 10 CFR 50.71(h)(2) requires each holder of a combined license shall maintain and upgrade the PRA required by paragraph (h)(1) of this section. The upgraded PRA must cover initiating events and modes of operation contained in NRC-endorsed consensus standards on PRA in effect one year prior to each required upgrade. The PRA must be upgraded every four years until the permanent cessation of operations under § 52.110(a) of this chapter.

Section 10 CFR 50.71(h)(3) requires each holder of a combined license shall, no later than the date on which the licensee submits an application for a renewed license, upgrade the PRA required by paragraph (h)(1) of this section to cover all modes and all initiating events.

Section 10 CFR 50.54(z) makes it a license condition that each licensee licensed under Sections 103 or 104b of the Atomic Energy Act shall make the notifications specified in 10 CFR 50.72.

Section 10 CFR 50.72(a)(1) and 10 CFR 50.72(a)(2) require that each power reactor licensee notify the NRC of specified events via the Emergency Notification System (ENS). If the ENS is inoperable, the licensee shall make the notifications via commercial telephone or other means. Many of these events are also subject to follow-up written reports as required by 10 CFR 50.73. These written follow-up reports are covered by a separate Office of Management and Budget clearance, 3150-0104.

Section 10 CFR 50.72(a)(ii)(4) requires the licensee to activate the ERDS as soon as possible but not later than one hour after declaring an emergency class of alert, site area emergency, or general emergency.

Section 10 CFR 50.72(a)(3) specifies notification immediately after notification of State and local authorities and not later than one hour after the licensee declares one of the Emergency Classes. Activation of the ERDS, as required by 10 CFR 50.72(a)(4), is covered in Section 4 of this clearance.

Section 10 CFR 50.72(b)(1) requires notification as soon as practical and in all cases within one hour of the occurrence of any deviation from the plants Technical Specifications (TS) authorized pursuant to 10 CFR 50.54(x). Assuming that recognition of this could be mistaken, correcting and retracting this report would include drafting the retraction and calling the HOO.

Section 10 CFR 50.72(b)(2) requires notification as soon as practical and in all cases within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of events such as plant shutdown required by TS, an event that results or should have

12 resulted in an emergency core cooling system discharge into the reactor coolant, an event that results in actuation of the reactor protection system, or any event or situation related to the health and safety of the public or protection of the environment for which a news release is planned. Assuming that recognition of this could be mistaken, correcting and retracting this report would include drafting the retraction and calling the HOO.

Section 10 CFR 50.72(b)(3) requires notification as soon as practical and in all cases within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of events such as (1) an event or condition that results in the nuclear power plant or any of its principal barriers being seriously degraded or the nuclear plant being in an unanalyzed condition that degrades plant safety; (2) events or conditions that result in valid actuation of specified safety systems; (3) events or conditions that could have prevented fulfillment of the safety condition of structures and systems needed to shut down and maintain the reactor in a safe condition, remove residual heat, control the release of radioactive material, and mitigate the consequences of an accident; (4) hospitalization of contaminated personnel; and (5) any event that results in a major loss of communications or emergency assessment capability. The development and determination that the condition does NOT exist after making the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> window using engineering judgement or rough calculations to make the report would necessitate additional burden to refine calculations, consult additional experts, and justify a retraction. Correcting and retracting this report would also include drafting the retraction and calling the HOO.

Section 10 CFR 50.72(c) requires that during the course of the event, the licensee shall: (1) immediately report any further degradation, any change of Emergency Class, (2) the results of ensuing evaluations, the effectiveness of response or protective measures, or plant behavior that is not understood; and (3) maintain an open, continuous communication channel with the NRC Operations Center upon request by the NRC.

Section 50.76 requires that an electric utility licensee holding an operating license (including a renewed license) for a nuclear power reactor shall provide the NRC with the financial qualifications information that would be required for obtaining an initial operating license as specified in § 50.33(f)(2) within 75 days prior to ceasing to be an electric utility in any manner not involving a license transfer under § 50.80. The financial qualifications information must address the first full five years of operation after the date the licensee ceases to be an electric utility.

10 CFR Part 50, Appendix E, Paragraph E.9.d., requires each licensee to perform monthly testing from the control room, the technical support center and the emergency operations facility. Additionally, the ENS system is exercised each morning, usually between the hours of 0400 and 0800 Eastern Time, by the Headquarters Operations Officer's (HOOs) placement of a call to each licensed facility to collect voluntary reactor status and grid information.

10 CFR 50 Appendix E.VI, Emergency Planning and Preparedness for Production and Utilization Facilities 10 CFR 50 Appendix E.VI.1 requires that licensees test the ERDS periodically to verify system availability and operability. The frequency of ERDS testing is quarterly unless otherwise set by NRC based on demonstrated system performance.

10 CFR 50 Appendix E.VI.2.a requires that computer systems transmit in-plant data points

13 for pressurized water reactors or boiling water reactors if the data points are resident in the in-plant computer.

10 CFR 50 Appendix E.VI.2.b requires the selected parameter sets of data to be transmitted at time intervals of not less than 15 seconds or more than 60 seconds.

10 CFR 50 Appendix E.VI.2.c requires all link control and data transmission be established in a format compatible with the NRC receiving system.

10 CFR 50 Appendix E.VI.3.a requires that any hardware or software changes that affect the transmitted data points identified in the ERDS Data Point Library (site specific data base residing on the ERDS computer) must be reported to the NRC within 30 days after changes are completed.

10 CFR 50 Appendix E.VI.3.b requires that NRC be notified as soon as practicable and at least 30 days prior to any changes to computer hardware or software, with the exception of data point modifications, that could affect the transmission format and the ERDS computer communication protocol.

10 CFR 50 Appendix E.VI.4.a required the licensees to develop and submit an ERDS implementation program plan to the NRC by October 28, 1991.

The Reactor Oversight Process (ROP) defines the inspection program for power reactors in Inspection Manual Chapter 2515. Within the ROP, three types of inspections require extensive planning and preparation due to their scope and depth. In order to prevent inefficient use of licensee and NRC resources during these inspections certain relevant inspection information is need prior conducting on-site inspections. The recordkeeping requirement for licensees to maintain this relevant inspection information is established in 10 Code of Federal Regulations (CFR) 50.71 and the burden is included in each relevant section of this clearance. The three inspection procedures (IPs) are listed below along with a description of needed information.

IP 71111.21M Comprehensive Engineering Team Inspection and IP 71111.21N Focused Engineering Inspection (Program): Comprehensive Engineering Team inspections are performed every four years. Information requested to prepare for this inspection includes a list of recent system performance problems (includes recent corrective maintenance performed on safety-related equipment), corrective action documents, system modifications, and operability evaluations, self-assessments, selected information related to component design (design calculations, design basis), component and operator action risk, and licensing basis information, and a copy of selected system diagrams, operating and surveillance testing procedures. Additionally, for Focused Engineering Inspections, such as fire protection inspections, conducted using IP 71111.21N, information requested may include information needed to determine which components are within the scope of the engineering program selected for inspection as well as corrective and preventive maintenance associated with these components. This information is needed to assess whether a selected components or operator actions used to mitigate risk-significant accident sequences can be relied upon to meet functional requirements that would prevent damage to the reactor core during design basis events.

IP 71152 Problem Identification and Resolution: inspection is performed every two years.

However, an additional inspection may be performed at a site if warranted by either

14 declining plant performance (typically this triggers one additional inspection per year) or the need to follow-up on an independent safety culture assessment. Information requested to prepare for this inspection includes a list of recent equipment problems, self-assessments, licensee audits, root cause evaluations, and corrective action documents; and a copy of the corrective action program and equipment monitoring program procedures. This information is needed to gain insights regarding the licensees ability to promptly identify and resolve problems.

15 GUIDANCE DOCUMENTS FOR INFORMATION COLLECTION REQUIREMENTS CONTAINED IN INSPECTIONS, RECORDS, REPORTS, NOTIFICATIONS SECTION 4 50.71(b) & Appendix C, Financial; 50.71(e), Updated FSAR; 50.72 & 50.54(z), Notification of Events; 50.72(a), ERDS; 50.73, (LERs) - (see OMB Clearance No. 3150-0104);

50.70, Team Inspections; 50.69, Risk-Informed Categorization of SSCs 3150-0011 Title Accession number Regulatory Guide 1.174, An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis ML17317A256 Regulatory Guide 1.200, An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities ML20238B871 Regulatory Guide 1.201, Guidelines for Categorizing Structures, Systems, and Components in Nuclear Power Plants According to Their Safety Significance ML061090627