ML18143B713

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SRP 13.4, Rev 4, Operational Programs Redline/Strikeout
ML18143B713
Person / Time
Issue date: 08/30/2018
From: Mark Notich
NRC/NRO/DNRL
To:
Notich M
Shared Package
ML18141A364 List:
References
SRP 13.4, Rev 4
Download: ML18143B713 (17)
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NUREG-0800 U.S. NUCLEAR REGULATORY COMMISSION STANDARD REVIEW PLAN 13.4 OPERATIONAL PROGRAMS REVIEW RESPONSIBILITIES Primary - Licensing organization Secondary - Cognizant review organization per the SRP sections identified in the attached sample final safety analysis report (FSAR) Table 13.4-x.

I. AREA OF REVIEW The areas of review for this standard review plan (SRP) section hashave been changed to address review and implementation of operationoperational programs required by regulations for a combined license (COL) application. submitted under Title 10 of the Code of Federal Regulations (10 CFR), Part 52, 1 Licenses, Certifications, And Approvals For Nuclear Power Plants. The former content regarding the review of the applicants plan for conducting reviews of operating phase quality assurance activities that are important to safety is addressed in SRP sectionSection 17.5, Quality Assurance Program Description -- Design Certification, Early Site Permit and New License Applicants.

1 This section is not applicable to an application submitted in accordance with 10 CFR Part 50. In 2007, the NRC issued a revised SRP Section 13.4 to address operational programs in lieu of prospective submittals under 10 CFR Part 52. The content of former SRP Section 13.4, Draft Rev. 3, Operational Review, is addressed in SRP Section 17.5. This SRP Section is procedural in nature and provides guidance for treatment of operational programs.

Revision 3 - March 2007 Draft Revision 4 - September 2018 USNRC STANDARD REVIEW PLAN This Standard Review Plan, NUREG-0800, has been prepared to establish criteria that the U.S. Nuclear Regulatory Commission staff responsible for the review of applications to construct and operate nuclear power plants intends to use in evaluating whether an applicant/licensee meets the NRC's regulations. The Standard Review Plan is not a substitute for the NRC's regulations, and compliance with it is not required. However, an applicant is required to identify differences between the design features, analytical techniques, and procedural measures proposed for its facility and the SRP acceptance criteria and evaluate how the proposed alternatives to the SRP acceptance criteria provide an acceptable method of complying with the NRC regulations.

The standard review plan sections are numbered in accordance with corresponding sections in Regulatory Guide 1.70, "Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants (LWR Edition)." Not all sections of Regulatory Guide 1.70 have a corresponding review plan section. The SRP sections applicable to a combined license application for a new light-water reactor (LWR) are based on Regulatory Guide 1.206, "Combined License Applications for Nuclear Power Plants (LWR Edition)."

These documents are made available to the public as part of the NRC's policy to inform the nuclear industry and the general public of regulatory procedures and policies. Individual sections of NUREG-0800 will be revised periodically, as appropriate, to accommodate comments and to reflect new information and experience. Comments may be submitted electronically by email to NRO_SRP@nrc.gov.

Requests for single copies of SRP sections (which may be reproduced) should be made to the U.S. Nuclear Regulatory Commission, Washington, DC 20555, Attention: Reproduction and Distribution Services Section, or by fax to (301) 415-2289; or by email to DISTRIBUTION@nrc.gov. Electronic copies of this section are available through the NRC's public Web site at http://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr0800/, or in the NRC's Agencywide Documents Access and Management System (ADAMS), at http://www.nrc.gov/reading-rm/adams.html, under Accession No. ML070470463ML18131A304.

The specific area of review is as follows:

Operational Program Description and Implementation. For a COL application, the staff reviews the final safety analysis report (FSAR) Table 13.4-x to ensure that all required operational programs are included. The staff review of theeach operational program description and the proposed implementation milestones is performed within the identified substantive SRP sectionssection reviews.

The Review Interfaces The SRP sections referenced in the attached sample FSAR Table 13.4-x include the specific acceptance criteria and review procedures.

II. II. ACCEPTANCE CRITERIA Requirements There are no specific requirements for this SRP section. The applicable requirement for each operational program is identified in the attached sample FSAR Table 13.4-x.

SRP Acceptance Criteria The SRP sections referenced in the attached sample FSAR Table 13.4-x include SRP acceptance criteria for operational programs.

Technical Rationale In the Staff Requirements Memorandum on SECY-05-0197, the Commission provided the following directions regarding operational programs:

1. 1. Include license conditions forto govern the implementation of operational programs in the COL, where if implementation requirements are not specified in the regulations.
2. 2. Identify the list of operational programs required to be included in a COL application.
3. 3. Use of proposedthe generic emergency planning/emergency preparedness (EP) inspections, tests, analyses, and acceptance criteria (ITAAC) in Attachment 2 to SECY 0197 as a model for EP ITAAC to be included in COL applications, but review proposed plant-specific EP ITAAC on a case-by-case basis.

The required operational programs are referenced in the attached sample FSAR Table 13.4-x.

III. III. REVIEW PROCEDURES

1. 1. The licensing organization coordinates the overall review of operational programs.

The respective The staff performs the substantive review occurs within the of each operational program in accordance with the guidance in the SRP section identified for each 13.4-2 Revision 3 - March 2007 Draft Revision 4 - September 2018

program in the attached sample FSAR Table 13.4-x. The review ensures that the COL applicant fully describes theeach operational programsprogram required by regulations and theirits implementation, including emergency preparedness (EP) and security, each of which is listed in the attached sample FSAR Table 13.4-x. In addition, non-programmatic aspects of the EP, security, and the fire protection programprograms (e.g., fire detection/suppression systems and fire barriers), will be subject to ITAAC. The review of ITAAC is performed under SRP Section 14.3, Inspections, Tests, Analyses, Andand Acceptance Criteria.

In this context, fully described 2 indicates that the program is clearly and sufficiently described in terms of the scope and level of detail to allow a reasonable assurance finding of acceptability. Required programs should always be described at a functional level and at an increased level of detail when implementation choices could materially and negatively affect the program effectiveness and acceptability.

The

2. If an applicant included ITAAC in lieu of implementation information for a specific operational program, staff reviews the ITAAC information under SRP Section 14.3. The staff also notes that unique circumstances involving a particular application may raise an implementation issue on an operational program that is best resolved by an ITAAC. The staff expects such circumstances to be rare. Any The staff should inform the Commission of any such licensee-proposed ITAAC information will be reviewed under SRP Section 14.3.
3. 3. COL applicants may choose to use an operational program not explicitly required by regulation. For example, a COL applicant might adopt a sump strainer cleanliness program to satisfy the emergency core cooling system requirements in the regulations. In such instances, the COL applicant should add the operational program to its list of programs in Section 13.4-x of the FSAR and should fully describe the program and its implementation in the FSAR.

IV. IV. EVALUATION FINDINGS The staff should include in the SER evaluation findings similar to the following:

The staff of the U.S. Nuclear Regulatory CommissionNRC has reviewed FSAR Table 13.4-x and concludes that it is an accurate summary of the operational programs evaluated in the sections of the safety evaluation report noted in the table. The COL will contain suitable license conditions regarding those operational programs wherefor which implementation requirements are not specified in the regulations.

The license should include the following conditions:

1. (Name of the licensee) shall implement and maintain in effect the provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility (or as 2 Defined by the Commission in a May 14, 2004, SRM for SECY-04-0032, Programmatic Information Needed for Approval of a Combined License Application without Inspections, Tests, Analyses, and Acceptance Criteria.

13.4-3 Revision 3 - March 2007 Draft Revision 4 - September 2018

described in submittals dated ) and as approved in the SER dated (and Supplements dated ).

2. The licensee shall fully implement and maintain in effect all provisions of the physical security plan, security training and qualification plan, and safeguards contingency plan, and all amendments made pursuant to the authority of 10 CFR 50.90, 50.54(p), 52.97

[, and Section VIII of Appendix to Part 52] when fuel is first received onsite, and continuing until all nuclear fuel is permanently removed from the site.1 3.1. The licensee shall implement the programs or portions of programs identified in Table on or before the associated milestones in Table .

[The table referenced in this license condition will be included in the license. It will be as shown in the attached FSAR Table 13.4-x except it will specify only those operational programs that do not have implementation requirements in the regulations at the time the COL is issued. The resulting table will contain operational program milestones acceptable to the NRC staff. The number of implementation milestones would depend on whether the program waswill be implemented on a phased basis or all at once. For example, the staff expects that the radiation protection program will have 4 implementation milestones (radioactive sources on site, fuel on site, fuel load, and first shipment of waste) whereas the motor-operated valve (MOV) program will be fully implemented at a specific milestone before plant startup. The portion of the program implemented at a particular milestone would be described in the implementation section of the FSAR.]

4.2. Within 12 months after issuance of the COL or 12 months after the start of construction as defined at 10 CFR 50.10(a), whichever is later, (Name of the licensee) shall submit to the Director, (the identification of the NRC Headquarters office responsible for oversight of the COL after issuance), or the Directors designee, a schedule, 12 months after issuance for implementation of the COL, that supports planning for and conduct of NRC inspections of operational programs listed in [Table 13.x-xxx, the operational program FSAR table.],

including the associated estimated date for initial loading of fuel. The schedule[name of licensee] shall be updatedupdate the schedule every 6 months until 12 months before scheduled fuel loading, and every month thereafter until either the operational programs in the FSAR table have been fully implemented or the plant has been placed in commercial service, which ever comes first.

V. V. IMPLEMENTATION The staff will use this SRP section in performing safety evaluations of DC applications and license applications submitted by applicants pursuant to 10 CFR Part 52. Except when the applicant proposes an acceptable alternative method for complying with specified portions of the Commissions regulations, the staff will use the method described herein to evaluate conformance with Commission regulations.

The provisions of this SRP section apply to reviews of applications submitted six months or more after the date of issuance of this SRP section, unless superseded by a later revision.

VI. VI. REFERENCES 13.4-4 Revision 3 - March 2007 Draft Revision 4 - September 2018

1. SECY-05-0197U.S. Nuclear Regulatory Commission, Review of Operational Programs in Combined License Applications and Generic Emergency Planning Inspections, Tests, Analyses, and Acceptance Criteria, SECY-05-0197, October 28, 2005. (ADAMS Accession No. ML052770225)
2. Staff Requirements - SECY-05-0197 - U.S. Nuclear Regulatory Commission, "Review of Operational Programs in Combined License Applications and Generic Emergency Planning Inspections, Tests, Analyses, and Acceptance Criteria, Staff Requirements -

SECY-05-0197, February 22, 2006. (ADAMS Accession No. ML060530316)

PAPERWORK REDUCTION ACT STATEMENT TheThis Standard Review Plan contains voluntary information collections contained in the Standard Review Plan are covered by the requirements of 10 CFR PartParts 50 and 10 CFR Part, 52, and Part 100 that are subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). These information collections were approved by the Office of Management and Budget, approval number (OMB), under control numbers 3150-0011 and, 3150-0151, and 3150-0093, respectively. Send comments regarding this information collection to the Information Services Branch, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to Infocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0011, 3150-0151, and 3150-0093) Office of Management and Budget, Washington, DC 20503.

PUBLIC PROTECTION NOTIFICATION Public Protection Notification The NRC may not conduct or sponsor, and a person is not required to respond to, a request forcollection of information or an information collection requirement unless the document requesting document or requiring the collection displays a currently valid OMB control number.

13.4-5 Revision 3 - March 2007 Draft Revision 4 - September 2018

ATTACHMENT Sample FSAR Table 13.4--x Operational Programs Required by NRC Regulation and Program ImplementationRegulations FSAR Implementation Program Source (SRP Item Program Title ) Milestone Requirement (Required By)

Section2 Section3

1. Inservice Inspection 10 CFR 50.55a(g) 5.2.4 Prior to Commercial 10 CFR 50.55a(g)

Program 5.4.2.2 service ASME Section XI IWA 6.6 2430(b)

2. Inservice Testing Program 10 CFR 50.55a(f) 3.9.6 After main generator 10 CFR 50.55a(f) 10 CFR Part 50, Appendix A 5.2.4 on--line on nuclear ASME OM Code heat
3. Environmental 10 CFR 50.49(a) 3.11 None specifiedPrior to License Condition Qualification Program initial fuel load
4. Preservice Inspection 10 CFR 50.55a(g) 5.2.4 Completion prior to 10 CFR 50.55a(g)

Program 5.4.2.2 initial plant start-up ASME Code Section XI 6.6 IWB--2200(a)

5. Reactor Vessel Material 10 CFR 50.60; 5.3.1 None specified License Condition Surveillance Program 10 CFR Part 50, Appendix H
6. Preservice Testing 10 CFR 50.55a(f) 3.9.6 None specifiedPrior to License Condition P i iti l f l l d
7. Containment Leakage 10 CFR 50.54(o); 6.2.6 FuelPrior to initial fuel 10 CFR 50, Appendix J License Rate Testing Program 10 CFR Part 50, Appendix A load condition (GDC 32); Option A-Section III 10 CFR Part 50, Appendix Option B-Section III.A J;

10 CFR 52.47(a)(1)

8. Fire Protection Program 10 CFR 50.48 9.5.1 None specifiedPrior to fuel License Condition receipt for elements of the Fire Protection Program necessary to

FSAR Implementation Program Source (SRP Item Program Title ) Milestone Requirement (Required By)

Section2 Section3 support receipt and storage of fuel on-site.

Prior to initial fuel load for elements or the Fire Protection Program necessary to support fuel load and plant operation.

(portions applicable to 10 CFR 70.22 Prior to byproduct, 10 CFR 70.22(a) radioactive material)4 10 CFR 30.32 source, or special 10 CFR 70.23(a)(3)-(4) 10 CFR 40.31 nuclear materials 10 CFR 30.32(g)

(excluding Exempt 10 CFR 30.33(a)(2)

Quantities as 10 CFR 40.31(a) described in 10 CFR 10 CFR 40.32(j) 30.18) receipt for elements of the Fire Protection Program necessary to support receipt and storage of byproduct, source, or special nuclear materials

9. Process and Effluent Monitoring and Sampling Program:

(a) Radiological Effluent 10 CFR 20.1301 and 11.5 Prior to fuel load License Condition Technical 20.1302 20.1301(e) for 40 Specifications/Standar CFR Part 190 d Radiological Effluent 10 CFR 50.34a Controls (RETS/SREC) 10 CFR 50.36a 10 CFR Part 50, Appendix I,Section II, III, and IV

FSAR Implementation Program Source (SRP Item Program Title ) Milestone Requirement (Required By)

Section2 Section3 (b) Offsite Dose Same as above 11.5 Prior to fuel load License Condition Calculation Manual (ODCM)

(c) Radiological Same as above 11.5 Prior to fuel load License Condition Environmental Monitoring Program (REMP)

(d) Process Control Same as above 11.4 Prior to fuel load License Condition Program (PCP)

10. Radiation Protection 10 CFR 20.1101 12.5 License Condition Program (a) Radiation Protection 10 CFR 20.1101 Prior to receiving element reactor fuel (b) ALARA element 10 CFR 20.1101 Prior to initial loading of fuel in the reactor (c) Minimization of 10 CFR 20.1406 Prior to initial transfer, contamination transport or disposal of element radioactive materials (d) Source control 10 CFR 30, 40, 70 Prior to receipt of element4 10 CFR Part 37 Special Nuclear Material Prior to initial receipt of by-product, source, or special nuclear materials (excluding Exempt Quantities as described in 10 CFR 30.18) for those elements of the Radiation Protection

FSAR Implementation Program Source (SRP Item Program Title ) Milestone Requirement (Required By)

Section2 Section3 Program necessary to support such receipt

11. Non licensed Plant Staff 10 CFR 50.120 13.2.2 18 months prior to 10 CFR 50.120(b)

Training Program scheduled fuel load (portions applicable to 10 CFR 30.32 Prior to initial receipt of 10 CFR 30.32(a) radioactive material)4 10 CFR 40.31 byproduct, source, or 10 CFR 40.31(a) 10 CFR 70.22 special nuclear 10 CFR 70.22(a) materials (excluding Exempt Quantities as described in 10 CFR 30.18)

12. Reactor Operator Training 10 CFR 55.13; 18 months prior to License Condition Program 10 CFR 55.31; 13.2.1 initial fuel load 10 CFR 55.41; 10 CFR 55.43; 10 CFR 55.45
13. Reactor Operator 10 CFR 50.34(b); 13.2.1 Within 3 months after 10 CFR 50.54 (i-1)

Requalification Program 10 CFR 50.54(i); issuance of an 10 CFR 55.59 operating license or the date, the Commission makes the finding under 10 CFR 52.103(g)

14. Emergency Planning 10 CFR 50.47 13.3 Full participation 10 CFR Part 50, 10 CFR Part 50, Appendix E exercise conducted Appendix E.IV.F.2a(i) within 2 yrs. before the (10 CFR Part 50 issuance of first full applicant) power operating license.

Onsite exercise 10 CFR Part 50, conducted within 1 yr Appendix E.IV.F.2a(i) before issuance of full (10 CFR Part 50 applicant)

FSAR Implementation Program Source (SRP Item Program Title ) Milestone Requirement (Required By)

Section2 Section3 power operating license.

10 CFR Part 50, Applicants detailed Appendix E.V implementing (10 CFR Part 50 procedures for its applicant) emergency plan submitted no less than 180 days prior to scheduled issuance of an operating license.

Full participation 10 CFR Part 50, exercise conducted Appendix E.IV.F.2a(ii) within 2 yrs of scheduled date for initial loading of fuel.

10 CFR Part 50, Onsite exercise Appendix E.IV.F.2a(ii) conducted within 1 yr before the schedule date for initial loading 10 CFR Part 50, of fuel. Appendix E.V.

Applicants detailed implementing procedures for its emergency plan submitted no less than within 180 days prior to scheduled date for initial loading of fuel.

15. Security Program

FSAR Implementation Program Source (SRP Item Program Title ) Milestone Requirement (Required By)

Section2 Section3 (a) Physical Protection 10 CFR 73.1, 13.5.2.2.8 Prior to initial receipt of 10 CFR 73.1(a),

Program (applicable to 10 CFR 73.67 13.6 special nuclear 10 CFR 73.67 protection of special material nuclear material prior to the protected area being declared operational)

(b) Physical Security 10 CFR 73.55(b); 13.6 Prior to receipt of fuel 10 CFR 73.55(a)(4)

Program 10 CFR 73.55(c)(3); onsite (protected area) 10 CFR 73.56; 10 CFR 73.57 (c) Safeguards 10 CFR 73.55(c)(5); 13.6 Prior to receipt of fuel 10 CFR 73.55(a)(4)

Contingency Program 10 CFR 73.55(k); onsite (protected area) 10 CFR Part 73, Appendix C (d) Training and 10 CFR 73.55(c)(4); 13.6 Prior to receipt of fuel 10 CFR 73.55(a)(4)

Qualification Program 10 CFR 73.55(d)(3); onsite (protected area) 10 CFR Part 73,Appendix B (e) Fitness for Duty (FFD) 10 CFR 26.3(c) 13.7 Prior to initiating 10 10 CFR Part 26, Subpart Program for CFR Part 26 K Construction (workers construction activities and first-line supervisors)

(f) Fitness for Duty (FFD) 10 CFR 26.3(c) 13.7 Prior to initiating 10 10 CFR Part 26, Subparts Program for CFR Part 26 A-H, N, and O Construction construction activities (management and oversight personnel)

(g) FFD Program for 10 CFR 26.4(c)(3) 13.7 Prior to initiating 10 10 CFR Part 26, Subparts Security Personnel CFR Part 26 A-H, construction activities N, and O

FSAR Implementation Program Source (SRP Item Program Title ) Milestone Requirement (Required By)

Section2 Section3 Prior to the earlier of: 10 CFR Part 26, Subparts A. Licensees A-I, receipt of SNM in N, and O the form of fuel assemblies, or B. Establishment of a protected area, or C.The 10 CFR 52.103(g) finding (h) FFD Program for FFD 10 CFR 26.3(c); 13.7 Prior to initiating 10 10 CFR Part 26, Subparts Program personnel CFR Part 26 A, B, D- H, N, O, and C, construction activities per licensees discretion (i) FFD Program for 10 CFR 26.4(c) 13.7 Prior to the conduct of 10 CFR Part 26, Subparts persons required to the first full A-I, physically report to the participation N, and O, except for Technical Support emergency §§ 26.205-209 Center (TSC) or preparedness exercise Emergency Operations under 10 CFR Part 50, Facility (EOF) App. E, Section F.2.a Prior to the earlier of:

j. FFD Program for 10 CFR 26.4(a) and (b) 13.7 10 CFR Part 26, Subparts A. Establishment Operation A-I, of a protected area, N, and O, except for or individuals listed in B. The 10 CFR

§ 26.4(b), who are not 52.103(g) finding subject to §§ 26.205-209

k. Cyber Security 10 CFR 73.54(b); 13.6 Prior to receipt of fuel 10 CFR 73.55(a)(4)

Program 10 CFR 73.55(b)(8); onsite (protected area) 10 CFR 73.55(c)(6)

l. SNM Material Control 10 CFR 74, Subpart B (§§ 13.5.2.2.9 Prior to receipt of License Condition and Accounting 74.11 - 74.19, excl. § 74.17) special nuclear Program material
m. Security Program for 10 CFR 37.41(a)(1) 13.5.2.2.8 Prior to the 10 CFR 37.41(a)(1)

FSAR Implementation Program Source (SRP Item Program Title ) Milestone Requirement (Required By)

Section2 Section3 aggregated category 1 13.5.2.2.10 accumulation of or category 2 quantity 13.6 aggregated category 1 of radioactive material 11.4 or category 2 quantity (applicable to of radioactive material protection of aggregated quantity of radioactive material prior to fuel on site)

16. Quality Assurance 10 CFR 50.54(a); 17.5 30 days prior to 10 CFR 50.54(a)(1)

Program - Operation 10 CFR Part 50, Appendix A scheduled date for the (GDC 1); initial loading of fuel.

10 CFR Part 50, Appendix B

17. Maintenance Rule 10 CFR 50.65 17.6 Fuel load authorization 10 CFR 50.65(a)(1) per 10 CFR 52.103(g)
18. Motor-Operated Valve 10 CFR 50.55a(b)(3)(ii) 3.9.6 Prior to initial fuel load License Condition Testing 13.4-5 Revision 3 - March 2007

Item Program Title Program Source FSAR Implementation (Required By) (SRP)

Section2 Milestone Requirement

9. Process and Effluent Monitoring and Sampling Program:
  • Offsite Dose Calculation Same as above 11.5 None Specified License Condition manual (ODCM)
  • Radiological Environmental Same as above 11.5 None Specified License Condition Monitoring Program (REMP)

Same as above 11.4 None Specified License Condition

10. Radiation Protection Program 10 CFR 20.1101 12.5 None specified License Condition
11. Non licensed Plant Staff 10 CFR 50.120 13.2.2 18 months prior to 10 CFR 50.120(b)

Training Program 10 CFR 52.78 scheduled fuel load

12. Reactor Operator Training 10 CFR 55.13; 13.2.1 None specified License Condition Program 10 CFR 55.31; 10 CFR 55.41; 10 CFR 55.43; 10 CFR 55.45
13. Reactor Operator 10 CFR 50.34(b); 13.2.1 Within 3 months after 10 CFR 50.54 (i-1)

Requalification Program 10 CFR 50.54(i); issuance of an operating 10 CFR 55.59 license or the date, the Commission makes the finding under 10 CFR 52.103(g) 13.4-6 Revision 3 - March 2007

Item Program Title Program Source FSAR Implementation (Required By) (SRP)

Section2 Milestone Requirement

14. Emergency Planning 10 CFR 50.47 13.3 Full participation exercise 10 CFR Part 50, Part 50, Appendix E conducted within 2 yrs Appendix E.IV.F.2a(i) before the issuance of first (10 CFR Part 50 applicant) full power operating license.

Onsite exercise conducted within 1 yr before issuance 10 CFR Part 50 Appendix of full power operating E.IV.F.2a(i) license. (10 CFR Part 50 applicant)

Applicants detailed implementing procedures for 10 CFR Part 50, Appendix E.V its emergency plan (10 CFR Part 50 applicant) submitted no less than 180 days prior to scheduled issuance of an operating license.

Full participation exercise conducted within 2 yrs of 10 CFR 50, Appendix scheduled date for initial E.IV.F.2a(ii) loading of fuel. (10 CFR Part 52 applicant)

Onsite exercise conducted within 1 yr before the 10 CFR Part 50, Appendix schedule date for initial E.IV.F.2a(ii) loading of fuel. (10 CFR Part 52 applicant)

Applicants detailed implementing procedures for 10 CFR Part 50, Appendix E.V.

its emergency plan (10 CFR Part 52 applicant) submitted no less than within 180 days prior to scheduled date for initial loading of fuel.

13.4-7 Revision 3 - March 2007

Item Program Title Program Source FSAR Implementation (Required By) (SRP)

Section2 Milestone Requirement

15. Security Program: 10 CFR 50.34(c) 13.6.1 None specified Physical Security Program 10 CFR 73.55 License Condition 10 CFR 73.56 10 CFR 73.57 10 CFR 26 Safeguards Contingency Program 10 CFR 50.34(d) License Condition 10 CFR Part 73, Appendix C Training and Qualification Program 10 CFR Part 73, Appendix B License Condition
16. Quality Assurance Program - 10 CFR 50.54(a); 17.5 30 days prior to scheduled 10 CFR 50.54(a)(1)

Operation 10 CFR 50, Appendix A (GDC 1); date for the initial loading of 10 CFR 50, Appendix B fuel.

17. Maintenance Rule 10 CFR 50.65 17.6 Fuel load authorization per 10 CFR 50.65(a)(1) 10 CFR 52.103(g) 18 Motor-Operated Valve 10 CFR 50.55a(b)(3)(ii) 3.9.6 None specified License Condition Testing 19 Initial Test Program 10 CFR 50.34, 14.2 None specified License Condition 10 CFR 52.79(a)(28) 2 Additional3 Additional FSAR (SRP) sections may be identified under broad operational programs required by regulation (e.g., ISI, IST, etc.).).

4 If the COL applicant submits within the Part 52 application a request for Part 30, 40, and 70 licenses, the COL applicant should identify implementation milestones related to these licenses.

13.4-8 Revision 3 - March 2007 Draft Revision 4 - September 2018

SRP Section 13.4, Operational Programs Description of Changes The technical changes incorporated in Revision 4, dated August 2018, include incorporation of lessons learned from previous reviews to provide a more detail description of the program requirements and implementation milestones that should be encompassed by an application submitted under 10 CFR Part 52.

Descriptions of the changes in each SRP section are as follows:

I. AREAS OF REVIEW

1. Added footnote to clarify the applicability of this SRP section.

III. REVIEW PROCEDURES

1. Added text to address the review of a generic program template that has been accepted by the staff
2. Added text to address the possibility of an applicant relying on an operational program to meet a requirement.

IV. EVALUATION FINDINGS

1. Remove license condition text for Fire Protection Program, Physical Security, Training, and Qualification Plan, and Safeguards Contingency Plan because they are addressed in the sample table.

VI. REFERENCES

1. Added accession numbers.

ATTACHMENT

1. Updated the sample table to identified new operational programs and more detailed implementation milestones and requirements due to lessons learned from previous reviews or new regulations.

13.4-9 Revision 3 - March 2007 Draft Revision 4 - September 2018

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