HNP-17-034, Response to Request for Additional Information Regarding License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106
| ML17115A311 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 04/25/2017 |
| From: | Hamilton T Duke Energy Progress |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| HNP-17-034 | |
| Download: ML17115A311 (12) | |
Text
Tanya M. Hamilton Vice President Harris Nuclear Plant 5413 Shearon Harris Road New Hill, NC 27562-9300 919.362.2502 10 CFR 50.90 April 25, 2017 Serial: HNP-17-034 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:
Response to Request for Additional Information Regarding License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106, and Delete Duplicate Reporting Requirements in Administrative Section of Technical Specifications Ladies and Gentlemen:
By letter dated December 2, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16337A249), Duke Energy Progress, LLC (Duke Energy),
submitted a license amendment request (LAR) for Shearon Harris Nuclear Power Plant, Unit 1 (HNP). The proposed license amendment requested to relocate specific Technical Specification (TS) parameters to the Core Operating Limits Report (COLR) in accordance with TSTF-339, Revision 2, to remove reference to plant procedure PLP-106, Technical Specification Equipment List Program and Core Operating Limits Report, as it pertains to the COLR, and delete duplicate reporting requirements from Administrative Controls section in TS.
The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the LAR and determined that additional information is needed to complete their review. Duke Energy received the request for additional information (RAI) from the NRC through electronic mail on March 22, 2017. Response to this request is required by April 25, 2017.
provides Duke Energys responses to the RAI question. The proposed TS changes provided in the Duke Energy letter dated December 2, 2016, were updated in as described in Attachment 1.
This additional information does not change the No Significant Hazards Determination provided in the original submittal. No regulatory commitments are contained in this letter.
In accordance with 10 CFR 50.91(b), HNP is providing the state of North Carolina with a copy of this response.
U.S. Nuclear Regulatory Commission Serial HNP-17-034 Page 2 of 2 Should you have any questions regarding this submittal, please contact Jeffery Robertson, Manager - Regulatory Affairs, at (919) 362-3137.
I declare under penalty of perjury that the foregoing is true and correct. Executed on April 25, 2017.
Sincerely, Tanya M. Hamilton Attachments:
- 1. Response to Request for Additional Information
- 2. Proposed Technical Specification Changes cc:
D. Retterer, NRC Sr. Resident Inspector, HNP W. L. Cox, Ill, Section Chief, N.C. DHSR M. Barillas, NRC Project Manager, HNP C. Haney, NRC Regional Administrator, Region II
U.S. Nuclear Regulatory Commission Page 2 of 2 Serial HNP-17-034 Should you have any questions regarding this submittal, please contact Jeffery Robertson, Manager - Regulatory Affairs, at (919) 362-3137.
I declare under penalty of perjury that the foregoing is true and correct. Executed on April 25, 2017.
Sincerely, Tanya M. Hamilton Attachments:
- 1. Response to Request for Additional Information
- 2. Proposed Technical Specification Changes cc:
D. Retterer, NRC Sr. Resident Inspector, HNP W. L. Cox, III, Section Chief, N.C. DHSR M. Barillas, NRC Project Manager, HNP C. Haney, NRC Regional Administrator, Region II
U.S. Nuclear Regulatory Commission Serial HNP-17-034 SERIAL HNP-17-034 ATTACHMENT 1 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 DOCKET NO. 50-400 RENEWED LICENSE NUMBER NPF-63
U.S. Nuclear Regulatory Commission Page 1 of 2 Serial HNP-17-034 By letter dated December 2, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16337A249), Duke Energy Progress, LLC (Duke Energy),
submitted a license amendment request (LAR) for Shearon Harris Nuclear Power Plant, Unit 1 (HNP). The proposed license amendment requested to relocate specific Technical Specification (TS) parameters to the Core Operating Limits Report (COLR) in accordance with TSTF-339, Revision 2, to remove reference to plant procedure PLP-106, Technical Specification Equipment List Program and Core Operating Limits Report, as it pertains to the COLR, and delete duplicate reporting requirements from Administrative Controls section in TS.
The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the LAR and determined that additional information is needed to complete their review. Duke Energy received the request for additional information (RAI) from the NRC through electronic mail on March 22, 2017. Response to this request is required by April 25, 2017. Duke Energys response is provided below.
RAI #1 Generic Letter (GL) 88-16 provides guidance for the analytical methods used to determine the core operating limits to be listed in the Administrative Controls section of the TS to ensure that each of the TS parameters relocated to the COLR are being determined using an NRC approved methodology. The LAR requests an update to the list of TS parameters that are being relocated to the COLR but there was no request to update the list of analytical methods for these additional core operating limits. The LAR did not identify that any of the analytical methods, currently listed in the TS, are used to determine these additional core operating limits.
Please identify the analytical methods that will be used to determine the additional core operating limits found in TS 6.9.1.6, Insert 3, of the LAR.
HNP Response:
The table below outlines the analytical methods, as listed in TS 6.9.1.6, that will be used to determine the additional core operating limits identified for relocation to the COLR in Insert 3 of the TS markup provided in the original submittal. Listed below the table are the applicable analytical methods as found in TS 6.9.1.6.2, of which the approved versions are specified in the COLR (current COLR - ADAMS Accession No. ML16293A594).
Parameter:
TS TS 6.9.1.6.2 Reference Letter (listed below)
DNB Limits 3/4.2.5 b, c, d, e, i, j, k, n OTT Setpoints 2.2.1 b, c, d, i, j, k, n OPT Setpoints 2.2.1 b, i, k, n Reactor Core Safety Limits 2.1.1 c, d, i, j, k
- b.
ANF-89-151(P)(A), "ANF-RELAP Methodology for Pressurized Water Reactors:
Analysis of Non-LOCA Chapter 15 Events," approved version as specified in the COLR.
- c.
XN-NF-82-21(P)(A), "Application of Exxon Nuclear Company PWR Thermal Margin Methodology to Mixed Core Configurations," approved version as specified in the COLR.
U.S. Nuclear Regulatory Commission Page 2 of 2 Serial HNP-17-034
- d.
XN-75-32(P)(A), "Computational Procedure for Evaluating Fuel Rod Bowing,"
approved version as specified in the COLR.
- e.
EMF-84-093(P)(A), "Steam Line Break Methodology for PWRs," approved version as specified in the COLR.
- i.
EMF-92-081(P)(A), "Statistical Setpoint/Transient Methodology for Westinghouse Type Reactors," approved version as specified in the COLR.
- j.
EMF-92-153(P)(A), "HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel," approved version as specified in the COLR.
- k.
BAW-10240(P)(A), "Incorporation of M5 Properties in Framatome ANP Approved Methods."
- n.
EMF-2310(P)(A), "SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors," approved version as specified in the COLR.
In keeping with the previous practice of identifying the Specifications for which these analytical methods apply, additional TS markups are provided in Attachment 2 that address the addition of Specifications 2.1.1, 2.2.1, and 3.2.5 to the list of impacted Specifications following their applicable analytical method in TS 6.9.1.6.2, as outlined in the table and list above.
U.S. Nuclear Regulatory Commission Serial HNP-17-034 SERIAL HNP-17-034 ATTACHMENT 2 PROPOSED TECHNICAL SPECIFICATION CHANGES SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 DOCKET NO. 50-400 RENEWED LICENSE NUMBER NPF-63 6 PAGES (INCLUDING COVER)
ADD: INSERT 3 ADD: INSERT 5 ADD: INSERT 4 ADD: INSERT 6 ADD: INSERT 6
ADD: INSERT 4 ADD: INSERT 6 ADD: INSERT 6
ADD: INSERT 4 ADD: INSERT 4 ADD: INSERT 4 ADD: INSERT 6 ADD: INSERT 6 ADD: INSERT 7
ADD: INSERT 5 ADD: INSERT 6
INSERT 3
- i.
Reactor Core Safety Limits Figure for Specification 2.1.1.
- j.
Overtemperature T and Overpower T setpoint parameters and time constant values for Specification 2.2.1.
- k.
Reactor Coolant System pressure, temperature, and flow Departure from Nucleate Boiling (DNB) limits for Specification 3/4.2.5.
INSERT 4 2.1.1 - Reactor Core Safety Limits, 2.2.1 - Reactor Trip System Instrumentation Setpoints, INSERT 5 2.2.1 - Reactor Trip System Instrumentation Setpoints, INSERT 6
, and 3.2.5 - DNB Parameters INSERT 7 3.2.5 - DNB Parameters,