NL-20-0793, Correction of Technical Specification Typographical Error
| ML20184A271 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 07/02/2020 |
| From: | Coleman J Southern Nuclear Company |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NL-20-0793 | |
| Download: ML20184A271 (8) | |
Text
3535 Colonnade Parkway Birmingham, AL 35243 205.992.5000 Regulatory Affairs July 2, 2020 Docket No.:
50-366 NL-20-0793 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Edwin I. Hatch Nuclear Plant, Unit 2 Correction of Technical Specification Typographical Error
References:
- 1. ML19337C322, Joseph M. Farley Nuclear Plant, Units 1 and 2; Edwin I.
Hatch Nuclear Plant, Unit Nos. 1 and 2; and Vogtle Electric Generating Plant, Units 1 and 2, Issuance of Amendments Regarding Revision to the Technical Specifications to Adopt TSTF-563, Revision 0, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program (EPID L-2019-LLA-0150), January 29, 2020
- 2. ML18123A368, Edwin I. Hatch Nuclear Plant, Unit Nos. 1 and 2 - Issuance of Amendments to Adopt TSTF-542, Revision 2, Reactor Pressure Vessel Water Inventory Control (CAC Nos. MF9662 and MF9663; EPID L-2017-LLA-0215), May 31, 2018
- 3. Proposed Guidance for Correction of Technical Specification Typographical Errors, SECY-96-238, November 19, 1996 Ladies and Gentlemen:
This letter requests Nuclear Regulatory Commission (NRC) approval of a correction of a typographical error in the Hatch Nuclear Plant (HNP) Unit 2 Technical Specifications (TS).
This error occurred during the processing of Unit 2 License Amendment 248 (Reference 1),
where a typographical error was inadvertently introduced in the definition of Drain Time that was added to the TS in License Amendment 235 (Reference 2). The error was neither addressed in the notice to the public nor reviewed by the NRC, and thus falls within the scope of the guidance provided by SECY-96-238 (Reference 3).
describes the typographical error and correction. Enclosure 2 provides the Amendment 248 page as-issued, with the requested correction noted. Enclosure 3 contains the corrected Amendment 248 page.
This letter contains no NRC commitments. If you have any questions, please contact Tim Enfinger at 205.992.7924.
U. S. Nuclear Regulatory Commission NL-20-0793 Page 2 Respectfully submitted, Jamie Coleman Nuclear Licensing Manager JMC/tle/scm
Enclosures:
- 1. Description of Technical Specification Typographical Error
- 2. Marked-up Technical Specification Page
- 3. Revised Technical Specification Page Cc: Regional Administrator, Region ll NRR Project Manager - Hatch Nuclear Plant Senior Resident Inspector - Hatch Nuclear Plant RTYPE: CHA02.004
Edwin I. Hatch Nuclear Plant, Unit 2 Correction of Technical Specification Typographical Error Description of Technical Specification Typographical Error
to NL-20-0793 Description of Technical Specification Typographical Error E1-1
- 1. Requested Action Consistent with the information contained in SECY-96-238, Southern Nuclear Operating Company (SNC) is requesting correction of a typographical error that was inadvertently introduced into the Hatch Nuclear Plant (HNP) Unit 2 Technical Specifications (TS). The error was introduced by SNC staff in development of the license amendment request (LAR) submitted to the Nuclear Regulatory Commission (NRC) for HNP Unit 2 License Amendment 248. The page provided did not correctly reflect a TS change previously approved by the NRC with the issuance of Amendment 235.
- 2. Typographical Error In the SNC application for Amendment 248, the Unit 2 definition of DRAIN TIME on TS page 1.1-2 had been inadvertently changed by SNC staff to read as follows (underline added to show the error):
DRAIN TIME The DRAIN TIME is the limit it would take for the water inventory The definition of DRAIN TIME should read as follows, identical to the Unit 1 definition:
DRAIN TIME The DRAIN TIME is the time it would take for the water inventory
- 3. Correction to Affected Page SECY-96-238 (Reference 3) provides guidance to correct inadvertent typographical errors in the Technical Specifications. The error described above was neither posted in the public notices nor was it reviewed by NRC as part of the license amendment process. Therefore, it may be corrected without a license amendment.
Edwin I. Hatch Nuclear Plant, Unit 2 Correction of Technical Specification Typographical Error Marked-up Technical Specification Page
Definitions 1.1 HATCH UNIT 2 1.1-2 Amendment No. 248 1.1 Definitions (continued)
CHANNEL A CHANNEL FUNCTIONAL TEST shall be the injection of a FUNCTIONAL simulated or actual signal into the channel as close to the sensor TEST as practicable to verify OPERABILITY, including required alarm, interlock, display, and trip functions, and channel failure trips. The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step.
CORE CORE ALTERATION shall be the movement of any fuel, sources, ALTERATION or reactivity control components within the reactor vessel with the vessel head removed and fuel in the vessel. The following exceptions are not considered to be CORE ALTERATIONS:
- a.
Movement of source range monitors, local power range monitors, intermediate range monitors, traversing incore probes, or special movable detectors (including undervessel replacement); and
- b.
Control rod movement, provided there are no fuel assemblies in the associated core cell.
Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.
CORE OPERATING The COLR is the unit specific document that provides cycle specific LIMITS REPORT parameter limits for the current reload cycle. These cycle specific (COLR) limits shall be determined for each reload cycle in accordance with Specification 5.6.5. Plant operation within these limits is addressed in individual Specifications.
DOSE DOSE EQUIVALENT I-131 shall be that concentration of I-131 EQUIVALENT (microcuries/gram) that alone would produce the same Committed I-131 Effective Dose Equivalent as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The dose conversion factors used for this calculation shall be those listed in Federal Guidance Report (FGR) 11, Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion, 1988.
DRAIN TIME The DRAIN TIME is the limit it would take for the water inventory in and above the Reactor Pressure Vessel (RPV) to drain to the top of the active fuel (TAF) seated in the RPV assuming:
- a.
The water inventory above the TAF is divided by the limiting drain rate;
- b.
The limiting drain rate is the larger of the drain rate through a single penetration flow path with the highest flow rate, or the sum of the drain rates through multiple penetration flow paths (continued) time
Edwin I. Hatch Nuclear Plant, Unit 2 Correction of Technical Specification Typographical Error Revised Technical Specification Page
Definitions 1.1 HATCH UNIT 2 1.1-2 Amendment No. 248 1.1 Definitions (continued)
CHANNEL A CHANNEL FUNCTIONAL TEST shall be the injection of a FUNCTIONAL simulated or actual signal into the channel as close to the sensor TEST as practicable to verify OPERABILITY, including required alarm, interlock, display, and trip functions, and channel failure trips. The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step.
CORE CORE ALTERATION shall be the movement of any fuel, sources, ALTERATION or reactivity control components within the reactor vessel with the vessel head removed and fuel in the vessel. The following exceptions are not considered to be CORE ALTERATIONS:
- a.
Movement of source range monitors, local power range monitors, intermediate range monitors, traversing incore probes, or special movable detectors (including undervessel replacement); and
- b.
Control rod movement, provided there are no fuel assemblies in the associated core cell.
Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.
CORE OPERATING The COLR is the unit specific document that provides cycle specific LIMITS REPORT parameter limits for the current reload cycle. These cycle specific (COLR) limits shall be determined for each reload cycle in accordance with Specification 5.6.5. Plant operation within these limits is addressed in individual Specifications.
DOSE DOSE EQUIVALENT I-131 shall be that concentration of I-131 EQUIVALENT (microcuries/gram) that alone would produce the same Committed I-131 Effective Dose Equivalent as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The dose conversion factors used for this calculation shall be those listed in Federal Guidance Report (FGR) 11, Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion, 1988.
DRAIN TIME The DRAIN TIME is the time it would take for the water inventory in and above the Reactor Pressure Vessel (RPV) to drain to the top of the active fuel (TAF) seated in the RPV assuming:
- a.
The water inventory above the TAF is divided by the limiting drain rate;
- b.
The limiting drain rate is the larger of the drain rate through a single penetration flow path with the highest flow rate, or the sum of the drain rates through multiple penetration flow paths (continued)