ML20058E899
| ML20058E899 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 06/18/2020 |
| From: | Andrew Hon Plant Licensing Branch II |
| To: | Kapopoulos E Duke Energy Progress |
| Hon A | |
| References | |
| EPID L-2019-LLA-0119 | |
| Download: ML20058E899 (11) | |
Text
June 18, 2020 Mr. Ernest J. Kapopoulos, Jr.
Site Vice President H. B. Robinson Steam Electric Plant Duke Energy Progress, LLC 3581 West Entrance Road, RNPA01 Hartsville, SC 29550
SUBJECT:
H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 - ISSUANCE OF AMENDMENT NO. 267 REGARDING CHANGE TO SURVEILLANCE REQUIREMENT 3.8.2.1 (EPID NO. L-2019-LLA-0119)
Dear Mr. Kapopoulos:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 267 to Renewed Facility Operating License No. DPR-23 for the H. B. Robinson Steam Electric Plant, Unit No. 2. This amendment is in response to your application dated June 4, 2019, as supplemented by "RA-19-0386, Response to Request for Additional Information (RAI) Regarding License Amendment Request Proposing to Revise Technical Specification 3.8.2, AC Sources - Shutdown, [[SR" contains a listed "[" character as part of the property label and has therefore been classified as invalid..1|letter dated October 24, 2019]].
The amendment revises the Technical Specification (TS) 3.8.2, AC Sources - Shutdown, Surveillance Requirement (SR) 3.8.2.1. The SR change would reflect that SR 3.8.1.18 is not required to be met in the TS 3.8.2 Applicability.
A copy of our related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commissions biweekly Federal Register notice.
Sincerely,
/RA/
Andrew Hon, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-261
Enclosures:
- 1. Amendment No. 267 to DPR-23
- 2. Safety Evaluation cc: Listserv
DUKE ENERGY PROGRESS, LLC DOCKET NO. 50-261 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 267 Renewed License No. DPR-23
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Duke Energy Progress, LLC (the licensee),
dated June 4, 2019, as supplemented by "RA-19-0386, Response to Request for Additional Information (RAI) Regarding License Amendment Request Proposing to Revise Technical Specification 3.8.2, AC Sources - Shutdown, [[SR" contains a listed "[" character as part of the property label and has therefore been classified as invalid..1|letter dated October 24, 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.
- 2.
Accordingly, the license is amended by changes to the Technical Specifications, as indicated in the attachment to this license amendment. Paragraph 3.B. of Renewed Facility Operating License No. DPR-23 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 267 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented within 120 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Undine Shoop, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed License and Technical Specifications Date of Issuance: June 18, 2020 Undine S.
Shoop Digitally signed by Undine S. Shoop Date: 2020.06.18 11:26:28 -04'00'
ATTACHMENT TO LICENSE AMENDMENT NO. 267 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 RENEWED FACILITY OPERATING LICENSE NO. DPR-23 DOCKET NO. 50-261 Replace page 3 of Renewed Facility Operating License No. DPR-23 with the attached page 3.
Replace the following page of the Appendix A Technical Specifications with the attached revised page. The revised page is identified by amendment number and contain marginal lines indicating the area of change.
Remove Page Insert Page 3.8-15 3.8-15
3 Renewed Facility Operating License No. DPR-23 Amendment No. 267 D.
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; E.
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 operation of the facility.
- 3.
This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations: 10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Section 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
A.
Maximum Power Level The licensee is authorized to operate the facility at a steady state reactor core power level not in excess of 2339 megawatts thermal.
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 267 are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
(1)
For Surveillance Requirements (SRs) that are new in Amendment 176 to Final Operating License DPR-23, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 176. For SRs that existed prior to Amendment 176, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the Surveillance was last performed prior to implementation of Amendment 176.
AC Sources-Shutdown 3.8.2 HBRSEP Unit No. 2 3.8-15 Amendment No. 267 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued)
B.3 Suspend operations involving positive reactivity additions that could result in loss of required SDM or boron concentration.
AND B.4 Initiate action to restore required DG to OPERABLE status.
Immediately Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.2.1
NOTE---------------------------------
The following SRs are not required to be performed:
SR 3.8.1.3, SR 3.8.1.8, SR 3.8.1.9, SR 3.8.1.11 through SR 3.8.1.15.
For AC sources required to be OPERABLE, the SRs of Specification 3.8.1, "AC Sources-Operating,"
except SR 3.8.1.16, SR 3.8.1.17, and SR 3.8.1.18, are applicable.
In accordance with applicable SRs
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 267 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-23 DUKE ENERGY PROGRESS, LLC H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261
1.0 INTRODUCTION
By application dated June 4, 2019 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML19155A037), as supplemented by "RA-19-0386, Response to Request for Additional Information (RAI) Regarding License Amendment Request Proposing to Revise Technical Specification 3.8.2, AC Sources - Shutdown, [[SR" contains a listed "[" character as part of the property label and has therefore been classified as invalid..1|letter dated October 24, 2019]] (ADAMS Accession No. ML19299A010), Duke Energy (the licensee) requested a license amendment to revise the H. B. Robinson Steam Electric Plant, Unit 2 (HBRSEP), Technical Specification (TS) 3.8.2, AC Sources - Shutdown, Surveillance Requirement (SR) 3.8.2.1.
The SR change would reflect that HBRSEP SR 3.8.1.18 is not required to be met in the TS 3.8.2 Applicability.
2.0 REGULATORY EVALUATION
2.1 Electrical Power Distribution System Design and Operation The HBRSEP offsite power system includes the generator, the main power transformer, the 230 kilo-Volt (kV) and 115 kV switchyards, the unit auxiliary transformer (UAT), and startup transformers (SUTs). The offsite power system provides the capability to deliver power from HBRSEP to the transmission lines when the unit is generating power and for HBRSEP to receive power to the onsite power system when the unit is not generating power.
The HBRSEP is equipped with two SUTs (one 115 kV transformer and one 230 kV transformer),
which connect the multiple sources of offsite power to the onsite electric distribution system.
One of the HBRSEP offsite circuits includes the 115 kV SUT, which is supplied from the 115 kV switchyard and ultimately powers the 480 V engineered safety feature (ESF) bus E1 through its normal feeder breaker. The other HBRSEP offsite circuit includes the 230 kV SUT, which is supplied from the 230 kV switchyard and ultimately powers the 480 V ESF bus E2 through its normal feeder breaker. Both the 115 kV and 230 kV SUTs are capable of energizing emergency buses E1 and E2 independently. Should a failure of either SUT occur, the other SUT would be capable of supplying power to the onsite distribution system after a manual transfer to the alternate offsite circuit.
In its supplemental "RA-19-0386, Response to Request for Additional Information (RAI) Regarding License Amendment Request Proposing to Revise Technical Specification 3.8.2, AC Sources - Shutdown, [[SR" contains a listed "[" character as part of the property label and has therefore been classified as invalid..1|letter dated October 24, 2019]], the licensee explained that during normal operation, each SUT feeds one emergency bus as the normal offsite circuit. The 115 kV SUT is considered the normal offsite circuit for bus E1. The 230 kV SUT is considered the normal offsite circuit for bus E2. Regarding alternate circuits, the UAT is the alternate circuit for bus E1 if either the 115 kV SUT or the 230 kV SUT is out of service. The alternate circuit for bus E2 is the 115 kV SUT; and bus E2 is only transferred to the 115 kV SUT for a loss of the 230 kV SUT.
The licensee stated that offsite power remains available (uninterrupted) to at least one of the emergency buses while switching to the alternate offsite circuit during various switching operations, upon a loss of either 115 kV SUT or the 230 kV SUT.
2.2 Current Technical Specification Requirements HBRSEP TS 3.8.2, AC Sources - Shutdown, (LCO) 3.8.2.a requires One qualified offsite circuit between the offsite transmission network and onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.10, Distribution Systems - Shutdown.
The current SR 3.8.2.1 in TS 3.8.2, states as follows:
NOTE---------------------------------
The following SRs are not required to be performed:
SR 3.8.1.3, SR 3.8.1.8, SR 3.8.1.9, SR 3.8.1.11 through SR 3.8.1.15.
For AC sources required to be OPERABLE, the SRs of Specification 3.8.1, "AC Sources-Operating,"
except SR 3.8.1.16, and SR 3.8.1.17, are applicable.
SR 3.8.1.18 in TS 3.8.1, AC Sources - Operating, requires Verify manual transfer of AC power sources from the normal offsite circuit to each alternate offsite circuit. This SR is also applicable in TS 3.8.2, AC Sources - Shutdown, since this SR 3.8.1.18 is not exempted in SR 3.8.2.1.
2.3 Reason for the Proposed Change and Description of Proposed Change HBRSEP SR 3.8.1.18 is currently required to be performed as per TS SR 3.8.2.1. However, according to NUREG-1431, Standard Technical Specifications (STS) Westinghouse Plants, Revision 4, the equivalent SR 3.8.1.8 (Verify [automatic [and] manual] transfer of AC power sources from the normal offsite circuit to each alternate [required] offsite circuit.) is not required to be performed in STS SR 3.8.2.1. To align the HBRSEP TS with NUREG-1431, the licensee has proposed to list SR 3.8.1.18 as an additional exception in HBRSEP TS SR 3.8.2.1.
The licensee has proposed to modify SR 3.8.2.1 as follows (change is indicated in BOLD):
NOTE---------------------------------
The following SRs are not required to be performed:
SR 3.8.1.3, SR 3.8.1.8, SR 3.8.1.9, SR 3.8.1.11 through SR 3.8.1.15.
For AC sources required to be OPERABLE, the SRs of Specification 3.8.1, "AC Sources-Operating,"
except SR 3.8.1.16, SR 3.8.1.17, and SR 3.8.1.18, are applicable.
2.5 Regulatory Requirements The U.S. Nuclear Regulatory Commission (NRC) Staff applied the following NRC regulations for review of the license amendment request (LAR):
Title 10 of Code of Federal Regulations (10 CFR) 50.36, Technical specifications, establishes the requirements related to the content of the TS. Pursuant to 10 CFR 50.36(c) TS are required to include items in five specific categories related to station operation: (1) Safety limits, limiting safety system settings, and limiting control settings; (2) limited conditions of operation (LCOs); (3) Surveillance requirements (SRs);
(4) Design features; and (5) Administrative controls. The proposed change in this LAR relates to the SR category.
Section 50.36(c)(3) of 10 CFR, Surveillance requirements, requires surveillance relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met.
The staff also applied NUREG-1431, Standard Technical Specifications [STS], Westinghouse Plants, Revision 4.0 as regulatory guidance to review the LAR. The Abstract of NUREG-1431 states, in part, The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993 (58 FR 39132), which was subsequently codified by changes to Section 36 of Part 50 of Title 10 of the Code of Federal Regulations (10 CFR 50.36)
(60 FR 36953). Licensees are encouraged to upgrade their technical specifications consistent with those criteria and conforming, to the practical extent, to Revision 4 to the improved STS.
3.0 TECHNICAL EVALUATION
The staff finds that HBRSEP SR 3.8.1.18, which requires the licensee to Verify manual transfer of AC power sources from the normal offsite circuit to each alternate offsite circuit, was added to the TS 3.8.1 (when the licensee added a second qualified offsite circuit), per License Amendment No. 261, issued by the NRC staff on September 10, 2018 (ADAMS Accession No. ML18228A584). The addition of SR 3.8.1.18 to TS 3.8.1 in 2018 resulted in close alignment of the HBRSEP TS 3.8.1 to NUREG-1431, TS 3.8.1, but omitted the alignment with NUREG-1431, TS 3.8.2. The current proposal would align HBRSEP TS SR 3.8.2.1 with the NUREG-1431 TS SR 3.8.2.1. After the proposed change, HBRSEP TS SR 3.8.2.1 will not require SR 3.8.1.18 to be performed in TS 3.8.2, AC Sources - Shutdown, applicable for Modes 5 and 6, and during the movement of irradiated fuel assemblies.
In the LAR, the licensee stated the following:
With the proposed change to not require performance of SR 3.8.1.18 during shutdown modes, operability of the equipment specified in HBRSEP LCO 3.8.2 will continue to ensure the availability of sufficient AC sources to operate the unit in a safe manner and to mitigate the consequences of postulated events (e.g.,
fuel handling accidents). In the event of an accident during shutdown, the LCO will continue to ensure the capability to support systems necessary to mitigate the event and maintain the unit in the shutdown or refueling condition for an extended period, assuming either a loss of all offsite power or a loss of all onsite diesel generator power.
According to LCO 3.8.2, only one offsite circuit is required to be operable. Therefore, the current requirement of performing SR 3.8.1.18 (i.e., verification of manual transfer capability of AC power sources from the normal offsite circuit to each alternate offsite circuit), as part of SR 3.8.2.1 is not considered necessary. The staff finds the proposed change to TS SR 3.8.2.1 acceptable, because LCO 3.8.2 would continue to meet the power requirement of support systems necessary to mitigate the postulated events during the cold shutdown or refueling condition (Modes 5 and 6) for or during movement of irradiated fuel assemblies. The proposed change is also in alignment with the NUREG-1431, TS SR 3.8.2.1.
Based on the technical evaluation described in Section 3.0 above, the staff finds the proposed change to TS SR 3.8.2.1 acceptable. The staff also concludes that, with the proposed TS change, the licensee would continue to comply with the SR requirements of 10 CFR 50.36(c)(3).
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the State of South Carolina official was notified of the proposed issuance of the amendment on March 10, 2020. The State official did not provide any comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR Part 20 and changes the 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, published in the Federal Register on November 19, 2019 (84 FR 63898), 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: Vijay Goel Tarico Sweat Date: June 18, 2020
SUBJECT:
H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 - ISSUANCE OF AMENDMENT NO. 267 REGARDING CHANGE TO SURVEILLANCE REQUIREMENT 3.8.2.1 (EPID NO. L-2019-LLA-0119)
DATED JUNE 18, 2020 DISTRIBUTION:
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