RA-20-0178, Supplement to License Amendment Request to Revise Technical Specifications Related to Accident Monitoring Instrumentation, Refueling Operations Instrumentation, and Electrical Equipment Protective Devices
| ML20174A639 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 06/22/2020 |
| From: | Maza K Duke Energy Progress |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RA-20-0178 | |
| Download: ML20174A639 (5) | |
Text
Kim Maza Site Vice President Harris Nuclear Plant 5413 Shearon Harris Rd New Hill, NC 27562-9300 984-229-2512 10 CFR 50.90 June 22, 2020 Serial: RA-20-0178 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Shearon Harris Nuclear Power Plant, Unit 1 Docket No. 50-400 Renewed License No. NPF-63
Subject:
Supplement to License Amendment Request to Revise Technical Specifications Related to Accident Monitoring Instrumentation, Refueling Operations Instrumentation, and Electrical Equipment Protective Devices Ladies and Gentlemen:
By letter dated March 12, 2020 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML20072M618), Duke Energy Progress, LLC (Duke Energy),
submitted a license amendment request proposing changes to the Technical Specifications (TS) for the Shearon Harris Nuclear Power Plant, Unit 1 (HNP). The proposed amendment would revise TS 3.3.3.6, Accident Monitoring Instrumentation, to revise the allowed outage times for inoperable post-accident monitoring (PAM) instrumentation, eliminate the shutdown requirement for inoperable PAM instruments when the minimum required channels are operable, and add a provision that allows a separate action entry for each instrument function. Duke Energy also proposed a revision to TS 3.9.2, Instrumentation, to remove the audible indication requirement in Mode 6, as well as relocate the requirements for electrical equipment protective devices in TS 3.8.4.1, Containment Penetration Conductor Overcurrent Protective Devices, and TS 3.8.4.2, Motor-Operated Valves Thermal Overload Protection, from TS to licensee-controlled procedure PLP-106, Technical Specification Equipment List Program. Additionally, a revision was proposed to the Note in TS 3.9.2 to allow for the substitution of Wide Range Neutron Flux Monitors for both of the Source Range Neutron Flux Monitors required to be operable while in Mode 6.
The attachment to this supplemental correspondence provides an updated markup of a TS page provided in Enclosure 2 of the submittal dated March 12, 2020. Specifically, Index page xv is being resubmitted due to a discrepancy between the markup copy provided in the original submittal and the docketed authority file of the HNP TS (ADAMS Accession No. ML052860283).
The markup should have reflected the Index page associated with Amendment No. 116 (ADAMS Accession No. ML042300450), as this was the last time the NRC issued an amendment to this page.
U.S. Nuclear Regulatory Commission Serial: RA-20-0178 Page 2 The content of this supplemental correspondence does not change the No Significant Hazards Consideration provided in the original submittal and does not contain any regulatory commitments.
Please refer any questions regarding this submittal to 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 June 22, 2020.
Sincerely, Kim E. Maza Site Vice President Harris Nuclear Plant
Attachment:
Updated Markup of Technical Specification Index Page cc:
J. Zeiler, NRC Sr. Resident Inspector, HNP W. L. Cox, Ill, Section Chief, N.C. DHSR M. Mahoney, NRC Project Manager, HNP L. Dudes, NRC Regional Administrator, Region II
U.S. Nuclear Regulatory Commission Serial: RA-20-0178 Page 2 The content of this supplemental correspondence does not change the No Significant Hazards Consideration provided in the original submittal and does not contain any regulatory commitments.
Please refer any questions regarding this submittal to 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 June 22, 2020.
Sincerely, Kim E. Maza Site Vice President Harris Nuclear Plant
Attachment:
Updated Markup of Technical Specification Index Page cc:
J. Zeiler, NRC Sr. Resident Inspector, HNP W. L. Cox, III, Section Chief, N.C. DHSR M. Mahoney, NRC Project Manager, HNP L. Dudes, NRC Regional Administrator, Region II
U.S. Nuclear Regulatory Commission Serial: RA-20-0178 Attachment ATTACHMENT UPDATED MARKUP OF TECHNICAL SPECIFICATION INDEX PAGE SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 DOCKET NO. 50-400 RENEWED LICENSE NUMBER NPF-63 2 PAGES (INCLUDING COVER)
(DELETED)
BASES u
SECTION 3/4.7 PLANT SYSTEMS
. 3/4.7.1 *TURBINE CYCLE.:......... *................................
3/4.7.2 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION.........
3/4.7.3 COMPONENT COOLING WATER SYSTEM..........................
3/4.7.4 EMERGENCY SERVICE WATER SYSTEM..........................
3/4.7.5 ULTIMATE HEAT SINK.... ~.................................
3/4.7.6 CONTROL ROOM EMERGENCY FILTRATION SYSTEM................
3/4.7.7 REACTOR AUXILIARY BUILDING EMERGENCY EXHAUST SYSTEM.....
3/ 4. 7.8 SNUBBERS................................................
3/4.7.9 SEALED SOURCE CONTAMINATION.............................
3/4.7.10 (DELETED)...............................................
3/4.7.11 (DELETED)...............................................
3/ 4. 7.12 (DELETED)...............................................
3/4 7.13 ESSENTIAL SERVICES CHILLED WATER.SYSTEM.................
B 3/4 7-1 B 3/4 7-2 B 3/4 7-3 B 3/4 7-3 B 3/4 7-3 B 3/4 7-3 B 3/4 7-3a I B 3/4 7-4 B 3/4 7-5 B 3/4 7-5 B 3/4 7-5 B 3/4 7-5 B 3/4 7-5
~ 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1. 3/4.8.2~ AND 3/4.8.3 A.C. SOURCES. D.C. SOURCES. AND ONSITE POWtR DISTRIBUTION................................... B 3/4 8-1 3/4.8.4 ELECTRICAL [QUIPMOff PROTECTIVE DEVICES.* I B 3/4 8-3 3/4.9 REFUELING OPERATIONS 3/ 4. 9.1 BORON CONCENTRATION...........*........*......**........
3/4.9.2 INSTRUMENTATION.........................................
3/4. 9.3
<DELETED)...............................................
3/4.9.4 CONTAINMENT BUILDING PENETRATIONS.......................
3/4.9.5 (DELETED)...............................................
3/ 4. 9. 6 (DELETED)...............................................
3/ 4. 9. 7 (DELETED)...............................................
3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION...........
3/4.9.9 CONTAINMENT VENTILATION ISOLATION SYSTEM................
3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL AND NEW AND SPENT FUEL POOLS...........................................
3/4.9.12 FUEL HANDLING BUILDING EMERGENCY EXHAUST SYSTEM........
B 3/4 9-1 B 3/4 9-1 B 3/4 9-1 B 3/4 9-1 B 3/4 9-2 B 3/4 9-2 B 3/4 9-2 B 3/4 9-2 B 3/4 9-2 B 3/4 9-3 B 3/4 9-4 SHEARON HARRIS - UNIT 1 xv Amendment No. H-6