ML20237H995

Issuance of Amendment No. 341 Revision to Technical Specification 6.25, Pre-Stressed Concrete Containment Tendon Surveillance Program

ML20237H995
Person / Time
Site:	Millstone
Issue date:	09/29/2020
From:	Richard Guzman NRC/NRR/DORL/LPL1
To:	Stoddard D Dominion Energy Nuclear Connecticut
Guzman R
References
EPID L-2019-LLA-0288
Download: ML20237H995 (11)

Text

D. Stoddard September 29, 2020 Mr. Daniel G. Stoddard Senior Vice President and Chief Nuclear Officer Dominion Nuclear Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711

SUBJECT:

MILLSTONE POWER STATION, UNIT NO. 2 ISSUANCE OF AMENDMENT NO. 341 RE: REVISION TO TECHNICAL SPECIFICATION 6.25, PRE-STRESSED CONCRETE CONTAINMENT TENDON SURVEILLANCE PROGRAM (EPID L-2019-LLA-0288)

Dear Mr. Stoddard:

The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 341 to Renewed Facility Operating License No. DPR-65 for the Millstone Power Station, Unit No. 2 (Millstone 2), in response to your application dated December 17, 2019.

The amendment revises the Millstone 2 Technical Specification (TS) 6.25, Pre-Stressed Concrete Containment Tendon Surveillance Program, to replace the reference to Regulatory Guide 1.35 with a reference to Section XI, Subsection IWL of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code. Additionally, the provisions of Surveillance Requirement 4.0.2 in TS 6.25 are also deleted by the license amendment.

A copy of the related Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commissions biweekly Federal Register notice.

Sincerely,

/RA/

Richard V. Guzman, Senior Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-336

Enclosures:

1. Amendment No. 341 to DPR-65

2. Safety Evaluation cc: Listserv

DOMINION ENERGY NUCLEAR CONNECTICUT, INC.

DOCKET NO. 50-336 MILLSTONE POWER STATION, UNIT NO. 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 341 Renewed License No. DPR-65

1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Dominion Energy Nuclear Connecticut, Inc.

(the licensee) dated December 17, 2019, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.

Enclosure 1

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-65 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 341 are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of the date of issuance and shall be implemented within 90 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Digitally signed by James James G. G. Danna Date: 2020.09.29 Danna 08:16:25 -04'00' James G. Danna, Chief Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: September 29, 2020

ATTACHMENT TO LICENSE AMENDMENT NO. 341 MILLSTONE POWER STATION, UNIT NO. 2 RENEWED FACILITY OPERATING LICENSE NO. DPR-65 DOCKET NO. 50-336 Replace the following page of the Renewed Facility Operating License with the attached revised page. The revised page is identified by amendment number and contains a marginal line indicating the area of change.

Remove Insert 3 3 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert 6-29 6-29

---

6-29a

Connecticut, in accordance with the procedures and limitations set forth in this renewed operating license; (2) Pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (3) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form for sample analysis or instrument and equipment calibration or associated with radioactive apparatus or components; (5) Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter 1: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Section 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level The licensee is authorized to operate the facility at steady-state reactor core power levels not in excess of 2700 megawatts thermal.

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 341 are hereby incorporated in the renewed license.

The licensee shall operate the facility in accordance with the Technical Specifications.

Renewed License No. DPR-65 Amendment No. 341

ADMINISTRATIVE CONTROLS 6.24 DIESEL FUEL OIL TEST PROGRAM A diesel fuel oil testing program to implement required testing of both new fuel oil and stored fuel oil shall be established. The program shall include sampling and testing requirements, and acceptance criteria, all in accordance with applicable ASTM Standards. The purpose of the program is to establish the following:

a. Acceptability of new fuel oil for use prior to addition to storage tanks by determining that the fuel oil has:

1. An American Petroleum Institute (API) gravity or an absolute specific gravity within limits,

2. A flash point and kinematic viscosity within limits for ASTM 2D fuel oil, and

3. A clear and bright appearance with proper color or a water and sediment content within limits.

b. Within 31 days following addition of the new fuel oil to storage tanks, verify that the properties of the new fuel oil, other than those addressed in a., above, are within limits for ASTM 2D fuel oil, and

c. Total particulate concentration of the fuel oil is 10 mg/L when tested every 92 days.

The provisions of Surveillance Requirements 4.0.2 and 4.0.3 are applicable to the Diesel Fuel Oil Test Program test frequencies.

6.25 PRE-STRESSED CONCRETE CONTAINMENT TENDON SURVEILLANCE PROGRAM This program provides controls for monitoring any tendon degradation in pre-stressed concrete containments, including effectiveness of its corrosion protection medium, to ensure containment structural integrity. The program shall include baseline measurements prior to initial operations.

The Tendon Surveillance Program, inspection frequencies, and acceptance criteria shall be in accordance with Section XI, Subsection IWL of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55a, except where an exemption or relief has been authorized by the NRC.

The provisions of Surveillance Requirement 4.0.3 are applicable to the Tendon Surveillance Program inspection frequencies.

MILLSTONE - UNIT 2 6-29 Amendment No.277, 278, 313, 341

ADMINISTRATIVE CONTROLS 6.25 PRE-STRESSED CONCRETE CONTAINMENT TENDON SURVEILLANCE PROGRAM (CONTINUED)

Any abnormal degradation of the containment structure detected during the tests required by the Pre-stressed Concrete Containment Tendon Surveillance Program shall be reported to the NRC within 30 days. The report shall include a description of the tendon condition, the condition of the concrete (especially at tendon anchorages), the inspection procedures, the tolerances on cracking, and the corrective action taken. This Tendon Surveillance Report is an administrative requirement listed in Technical Specification 6.9.2, Special Reports.

MILLSTONE - UNIT 2 6-29a Amendment No.277, 278, 313, 341

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 341 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-65 DOMINION ENERGY NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION, UNIT NO. 2 DOCKET NO. 50-336

1.0 INTRODUCTION

By letter dated December 17, 2019 (Agencywide Documents Access and Management System Accession No. ML19353A022), Dominion Energy Nuclear Connecticut, Inc. (the licensee) submitted a license amendment request for the Millstone Power Station, Unit No. 2 (MPS2).

The license amendment request proposed to revise MPS2 Technical Specification (TS) 6.25, Pre-Stressed Concrete Containment Tendon Surveillance Program, to replace the reference to Regulatory Guide (RG) 1.35 with a reference to Section XI, Subsection IWL of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code). The proposed amendment would also delete the provisions of Surveillance Requirement (SR) 4.0.2 in TS 6.25. Additionally, the proposed amendment would align the MPS2 TSs with the requirements of Title 10 of the Code of Federal Regulations (10 CFR) 50.55a, Codes and standards, and the required containment inservice inspection (ISI) program.

2.0 REGULATORY EVALUATION

Containment ISI requirements originated with the issuance of RG 1.35, lnservice Surveillance of Ungrouted Tendons in Prestressed Concrete Containment Structures, in February 1973.

The final revision of RG 1.35, Revision 3, was issued in July 1990. In the Federal Register (61 FR 41303) dated August 8, 1996, the U.S. Nuclear Regulatory Commission (NRC, the Commission) amended 10 CFR 50.55a to incorporate by reference Subsections IWE and IWL of Section XI of the ASME Code. Subsection IWL includes the requirements for ISI of concrete containments and includes the guidance provided in RG 1.35. Therefore, RG 1.35 was made obsolete when the requirements of ASME Section XI, Subsection IWL, were incorporated by reference into 10 CFR 50.55a. The NRC withdrew RG 1.35 in August 2015.

Pursuant to 10 CFR 50.55a(g)(4), throughout the service life of a nuclear power facility, components that are classified as Class CC pressure retaining components must meet the requirements set forth in Section XI of the ASME Code, Subsection IWL, as incorporated by reference in 10 CFR 50.55a(a)(1)(ii), subject to the conditions listed in 10 CFR 50.55a(b)(2)(ix).

Section XI, Subsection IWL of the ASME Code provides rules for ISI and repair/replacement activities of the reinforced concrete and post-tensioning system components of Class CC Enclosure 2

containment structures. The appropriate edition of the code to be used for successive 120-month inspection intervals is determined pursuant to 10 CFR 50.55a(g)(4)(ii).

Paragraph 50.55a(g)(5)(ii) of 10 CFR requires that if a revised ISI program for a facility conflicts with the TSs for the facility, the licensee must apply to the Commission for amendment of the TSs to conform the TSs to the revised program.

Paragraph 50.36(c) of 10 CFR requires TSs to include items in the following categories:

(1) safety limits, limiting safety systems settings, and limiting control settings; (2) limiting conditions for operation; (3) SRs; (4) design features; (5) administrative controls; (6) decommissioning; (7) initial notification; and (8) written reports. Paragraph 50.36(c)(5) of 10 CFR states that [a]dministrative controls are the provisions relating to organization and management, procedures, recordkeeping, review and audit, and reporting necessary to assure operation of the facility in a safe manner.

3.0 TECHNICAL EVALUATION

The licensee proposed to revise MPS2 TS 6.25 to replace the reference to RG 1.35 with a reference to Section XI, Subsection IWL of the ASME Code. Specifically, the TS will be revised to state, in part:

The Tendon Surveillance Program, inspection frequencies, and acceptance criteria shall be in accordance with Section XI, Subsection IWL of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55a, except where an exemption or relief has been authorized by the NRC.

In addition, the licensee proposed to delete the applicability of SR 4.0.2 to the tendon surveillance program inspection frequencies.

The NRC staff reviewed the proposed TS changes and noted that RG 1.35 has been withdrawn by the NRC and that concrete containment ISI requirements are now captured in the ASME Code,Section XI, Subsection IWL, as incorporated by reference in 10 CFR 50.55a. Therefore, it is no longer appropriate to reference RG 1.35 in MPS2 TS 6.25; the proposed revision updates the TS to accurately reflect the MPS2 containment ISI program. MPS2 SR 4.0.2 requires that Each Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance time interval. The staff notes that the ASME Code,Section XI, Subsection IWL specifies how frequently inspections must occur and provides requirements for extending inspection frequencies. Therefore, it is no longer necessary for SR 4.0.2 to apply to TS 6.25.

Based on its review, the NRC staff finds that it is acceptable for the licensee to update MPS2 TS 6.25 to remove the references to RG 1.35 and SR 4.0.2 and to revise the TS to note that the Tendon Surveillance Program is in accordance with the ASME Code,Section XI, Subsection IWL. These changes align TS 6.25 with the requirements of 10 CFR 50.55a and continue to meet 10 CFR 50.36(c)(5) by providing administrative controls to assure operation of the facility in a safe manner.

4.0 STATE CONSULTATION

In accordance with the Commissions regulations, the Connecticut State official was notified of the proposed issuance of the amendment on August 25, 2020. The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendment changes a requirement with respect to the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20 or changes SRs.

The NRC staff has determined that the amendment involves no significant increase in the amounts and no significant change in the types of any effluents that may be released offsite and that there is no significant increase in individual or cumulative occupational radiation exposure.

The Commission has previously issued a proposed finding, which was published in the Federal Register on February 11, 2020 (85 FR 7790), that the amendment involves no significant hazards consideration, and there has been no public comment on such finding. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.

6.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributors: B. Lehman C. Tilton Date: September 29, 2020

ML20237H995 *by e-mail OFFICE NRR/DORL/LPL1/PM NRR/DORL/LPL1/LA NRR/DEX/ESEB/BC(A)*

NAME RGuzman SBennett/LRonewicz SKrepel DATE 08/26/2020 08/27/2020 04/03/2020 OFFICE NRR/DSS/STSB/BC OGC - NLO* NRR/DORL/LPL1/BC NAME VCusumano JWachutka JDanna DATE 09/11/2020 09/11/2020 09/29/2020 OFFICE NRR/DORL/LPL1/PM NAME RGuzman DATE 09/29/2020