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, Surveillance Requirement 3.8.2.1
| ML19299A010 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 10/24/2019 |
| From: | Kapopoulos E Duke Energy Progress |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RA-19-0386 | |
| Download: ML19299A010 (14) | |
Text
Ernest J. Kapopoulos, Jr.
H. B. Robinson Steam Electric Plant Unit 2 Site Vice President Duke Energy 3581 West Entrance Road Hartsville, SC 29550 O: 843 951 1701 F: 843 857 1319 Serial: RA-19-0386 10 CFR 50.90 October 24, 2019 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 H.B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261 RENEWED LICENSE NO. DPR-23
SUBJECT:
RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION (RAI)
REGARDING LICENSE AMENDMENT REQUEST PROPOSING TO REVISE TECHNICAL SPECIFICATION 3.8.2, AC SOURCES - SHUTDOWN, SURVEILLANCE REQUIREMENT 3.8.2.1 Ladies and Gentlemen:
By letter dated June 4, 2019 (ADAMS Accession No. ML19155A037), Duke Energy Progress, LLC (Duke Energy) submitted a license amendment request (LAR) for H.B. Robinson Steam Electric Plant, Unit 2 (HBRSEP). The proposed change would revise HBRSEP Technical Specification (TS) 3.8.2, AC Sources - Shutdown, Surveillance Requirement (SR) 3.8.2.1 to reflect that HBRSEP SR 3.8.1.18 is not required to be met in the TS 3.8.2 Applicability (i.e.,
Modes 5 and 6 and during movement of irradiated fuel assemblies).
By correspondence dated September 26, 2019 (ADAMS Accession No. ML19283A037), the Nuclear Regulatory Commission (NRC) staff requested additional information from Duke Energy to complete the LAR review.
The Enclosure to this letter provides Duke Energys response to the NRC RAI. The Attachment contains color highlighted electrical one-line diagrams that support the RAI response.
The conclusions of the original No Significant Hazards Consideration and Environmental Consideration in the original LAR are unaffected by this RAI response.
There are no regulatory commitments contained in this letter.
In accordance with 10 CFR 50.91, Duke Energy is notifying the State of South Carolina of this LAR by transmitting a copy of this letter and enclosure to the designated State Official.
( ~ DUKE ENERGY
U.S. Nuclear Regulatory Commission RA-19-0386 Page 2 If there are any questions or if additional information is needed, please contact Mr. Art Zaremba, Manager - Nuclear Fleet Licensing at 980-373-2062.
I declare under penalty of perjury that the foregoing is true and correct. Executed on October 24, 2019.
Sincerely, Ernest J. Kapopoulos, Jr.
Site Vice President EJK/jlv
Enclosure:
Response to NRG Request for Additional Information
Attachment:
Electrical One-Line Diagrams
U.S. Nuclear Regulatory Commission RA-19-0386 Page 3 cc (with Enclosure and Attachment):
L. Dudes, USNRC Region II - Regional Administrator M. Fannon, USNRC Senior Resident Inspector - RNP N. Jordan, NRR Project Manager - RNP A. Gantt, Chief, Bureau of Radiological Health (SC)
A. Wilson, Attorney General (SC)
S. E. Jenkins, Manager, Radioactive and Infectious Waste Management (SC)
U.S. Nuclear Regulatory Commission RA-19-0386 Page 1 H.B. Robinson Steam Electric Plant, Unit No. 2 Docket No. 50-261 / Renewed License No. DPR-23 Response to NRC Request for Additional Information (RAI) Regarding License Amendment Request Proposing to Revise Technical Specification 3.8.2, AC Sources - Shutdown, Surveillance Requirement 3.8.2.1 Enclosure Response to NRC Request for Additional Information
U.S. Nuclear Regulatory Commission RA-19-0386 Page 2 NRC Request for Additional Information By application dated June 4, 2019 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML19155A037, 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.
The U.S. Nuclear Regulatory Commission (NRC) staff has determined that the following additional information is needed to complete its review.
Regulatory Requirement Title 10 of Code of Federal Regulations (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 (SR), (4) Design features; and (5) Administrative controls. The proposed change in this LAR relates to the SR category.
Request for Additional Information (RAI) No. 1 In the LAR, Enclosure 1, Page 2, the licensee stated: Both the 115 kV and 230 kV startup transformers are capable of energizing Emergency Buses E1 and E2. Should a failure of either startup transformer occur, the other startup transformer would be capable of supplying power to the onsite distribution system. A manual transfer is made to the alternate offsite circuit upon a loss of either startup transformer.
The NRC staff has identified the following discrepancy:
The LAR does not clearly describe the alternate offsite circuits that would be used to supply power upon loss of a startup transformer. In addition, it is not clear that offsite power will remain available (uninterrupted) to at least one of the emergency buses while switching to alternate offsite circuit during various switching operations.
The staff requests the following information to address this discrepancy:
Please provide a description or highlighted drawings showing the offsite power circuits to the Emergency Buses E1 and E2 under following operating configurations when (a) Unit is operating at 100 percent power (b) Unit is tripped:
(i) Both 115 kV and 230 kV startup transformers available (ii) 115 kV startup transformer out-of-service (iii) 230 kV startup transformer out-of-service For each configuration, please explain which circuit (line-up) is considered a normal offsite circuit and which circuit (line-up) is considered an alternate offsite circuit. Also, please confirm whether offsite power will remain available (uninterrupted) to at least one of the emergency buses while switching to alternate offsite circuit during various switching operations.
U.S. Nuclear Regulatory Commission RA-19-0386 Page 3 Duke Energy Response to RAI No. 1 The Attachment to this submittal provides highlighted electrical drawings (i.e., one-line diagrams) for H.B. Robinson Steam Electric Plant, Unit No. 2 (HBRSEP) depicting the offsite power circuits supplying Emergency Buses E1 and E2 under the operating configurations specified in the RAI.
Figure 1 depicts the configuration when the unit is operating at 100 percent power and both the 115 kV and 230 kV startup transformers (SUTs) are available. 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 Unit Auxiliary Transformer (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.
Figure 2 depicts the final configuration when the unit is operating at 100 percent power and the 115 kV SUT is out-of-service. If the 115 kV SUT is lost, Bus E1 is temporarily powered from EDG-A after the loss of offsite power. Manual actions will transfer Bus E1 to the UAT, as shown in Figure 2. The 230 kV SUT will remain the uninterrupted source of offsite power for Bus E2.
Figure 3 depicts the final configuration when the unit is operating at 100 percent power and the 230 kV SUT is out-of-service. If the 230 kV SUT is lost, Bus E2 is temporarily powered from EDG-B after the loss of offsite power. Manual actions will transfer Bus E1 to the UAT, as shown in Figure 3. Power to Bus E1 is uninterrupted during the transfer process via circuit interlocks.
Additionally, if the UAT is subsequently lost, Bus E1 automatically transfers back to the 115 kV SUT without a power interruption via a fast bus transfer. Manual actions will transfer Bus E2 to the 115 kV SUT, as shown in Figure 3.
Figure 4 depicts the configuration when the unit is tripped and both the 115 kV and 230 kV SUTs are available. In this condition, Bus E1 remains uninterrupted on its normal offsite source (115 kV SUT) and Bus E2 remains uninterrupted on its normal offsite source (230 kV SUT).
Figure 5 depicts the configuration when the unit is tripped and the unit auxiliary transformer (UAT) and the 115 kV SUT are out-of-service. In this condition, the 230 kV SUT is the only available source of offsite power.
x Scenario with 115 kV SUT out-of-service prior to plant trip.
o Bus E1: For the postulated 115 kV SUT being out-of-service, Bus E1 would have been supplied by the UAT (Figure 2 configuration) prior to the unit trip. In the event of a unit trip, Bus E1 automatically transfers to the 230 kV SUT via a fast bus transfer. The power to Bus E1 is uninterrupted in this condition.
o Bus E2: The 230 kV SUT will remain the uninterrupted source of offsite power for Bus E2 throughout the event and transfer.
U.S. Nuclear Regulatory Commission RA-19-0386 Page 4 x
Scenario with 115 kV SUT out-of-service concurrent with plant trip.
o Bus E1: Bus E1 would have been supplied by the 115 kV SUT (normal Figure 1 configuration) prior to the unit trip. Bus E1 will be temporarily powered from EDG-A after the loss of offsite power via the 115 kV SUT. If loss of the 115 kV SUT was due to a transformer fault, manual actions will transfer Bus E1 to the 230k kV SUT. If the loss of the 115 kV SUT was due to a cause other than a transformer fault, then manual actions will transfer Bus E1 to the 230 kV SUT.
o Bus E2: The 230 kV SUT will remain the uninterrupted source of offsite power for Bus E2 throughout the event and transfer.
Figure 6 depicts the configuration when the unit is tripped and the UAT and the 230 kV SUT are out-of-service. In this condition, the 115 kV SUT is the only available source of offsite power.
x Scenario with 230 kV SUT out-of-service prior to plant trip.
o Bus E1: For the postulated 230 kV SUT being out-of-service, Bus E1 would have been supplied by the UAT (Figure 3 configuration) prior to the unit trip. In the event of a unit trip, Bus E1 automatically transfers to the 115 kV SUT via a fast bus transfer. The power to Bus E1 is uninterrupted in this condition.
o Bus E2: For the postulated 230 kV SUT being out-of-service, Bus E2 would have been supplied by the 115 kV SUT (Figure 3 configuration) prior to the unit trip.
After the unit trip, power to Bus E2 will remain uninterrupted on the 115 kV SUT (Figure 6 configuration).
x Scenario with 230 kV SUT out-of-service concurrent with plant trip.
o Bus E1: Bus E1 would have been supplied by the 115 kV SUT (normal Figure 1 configuration) prior to the unit trip. The 115 kV SUT will remain the uninterrupted source of offsite power for Bus E1 throughout the event.
o Bus E2: Bus E2 would have been supplied by the 230 kV SUT (normal Figure 1 configuration) prior to the unit trip. Bus E2 will be temporarily powered from EDG-B after the loss of offsite power via the 230 kV SUT. If loss of the 230 kV SUT was due to a transformer fault, manual actions via Plant Procedure AOP-037, will transfer Bus E2 to the 115 kV SUT. If loss of the 230 kV SUT was due to a cause other than a transformer fault, then manual actions will transfer Bus E2 to the 230 kV SUT.
Duke Energy confirms for HBRSEP that offsite power will remain available (uninterrupted) to at least one of the emergency buses while switching to the alternate offsite circuit during various switching operations. The discussion above considers a loss of offsite power, via the 115 kV SUT or the 230 kV SUT, as noted. Each section has identified the uninterrupted offsite power supply for each configuration. Each configuration identified has at least one uninterrupted offsite power source.
U.S. Nuclear Regulatory Commission RA-19-0386 H.B. Robinson Steam Electric Plant, Unit No. 2 Docket No. 50-261 / Renewed License No. DPR-23 Response to NRC Request for Additional Information (RAI) Regarding License Amendment Request Proposing to Revise Technical Specification 3.8.2, AC Sources - Shutdown, Surveillance Requirement 3.8.2.1 Attachment Electrical One-Line Diagrams
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184SHUMMl8LVO,SUITE175 STOHINGTOM, CT 06376 CHAAI.OTTE. NC28273 NN'ERVILLE. L 60583 ROBI NSON NUCLEAR PO WER CO.
ONE LINE DIAGRAM OF FINAL CO NFIG URATIO N NIA