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Category:Letter type:NL
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NL-23-0889, Units 1 and 2 - License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times for Residual Heat Removal Service Water (RHRSW) and Plant Service Water (Psw) Systems2023-12-0606 December 2023 Units 1 and 2 - License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times for Residual Heat Removal Service Water (RHRSW) and Plant Service Water (Psw) Systems NL-23-0879, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation NL-23-0841, Update to Notice of Intent to Pursue Subsequent License Renewal2023-11-20020 November 2023 Update to Notice of Intent to Pursue Subsequent License Renewal NL-23-0658, Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal2023-08-11011 August 2023 Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal NL-23-0542, CFR 50.46 ECCS Evaluation Model Annual Report for 20222023-08-0909 August 2023 CFR 50.46 ECCS Evaluation Model Annual Report for 2022 NL-23-0624, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2023-08-0404 August 2023 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis NL-23-0566, ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use2023-07-13013 July 2023 ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use NL-23-0555, Request for Exemption from Physical Barrier Requirement2023-07-0707 July 2023 Request for Exemption from Physical Barrier Requirement NL-23-0444, Quality Assurance Topical Report Submittal2023-06-15015 June 2023 Quality Assurance Topical Report Submittal NL-23-0457, ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use2023-06-12012 June 2023 ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use NL-23-0422, Inservice Inspection Program Owner'S Activity Report for Refueling Outage 2R272023-05-30030 May 2023 Inservice Inspection Program Owner'S Activity Report for Refueling Outage 2R27 NL-23-0383, SNC Response to Regulatory Issue Summary 2023-01:Preparation And.2023-05-19019 May 2023 SNC Response to Regulatory Issue Summary 2023-01:Preparation And. NL-23-0372, Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 20222023-05-10010 May 2023 Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 2022 NL-23-0310, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20222023-04-25025 April 2023 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2022 NL-23-0019, GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2023-04-12012 April 2023 GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI NL-23-0263, Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report2023-04-0505 April 2023 Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report NL-23-0208, Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update2023-03-29029 March 2023 Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update NL-23-0014, Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding2023-03-29029 March 2023 Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding NL-23-0228, Nuclear Property Insurance Coverage as of April 1, 2023 and Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21)2023-03-20020 March 2023 Nuclear Property Insurance Coverage as of April 1, 2023 and Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21) NL-23-0179, National Pollutant Discharge Elimination System (NPDES) Permit Renewal2023-03-13013 March 2023 National Pollutant Discharge Elimination System (NPDES) Permit Renewal NL-23-0101, Cycle 28 Core Operating Limits Report Version 12023-02-23023 February 2023 Cycle 28 Core Operating Limits Report Version 1 NL-23-0069, Correction of Technical Specification Omission and Typographical Error2023-01-20020 January 2023 Correction of Technical Specification Omission and Typographical Error NL-23-0003, Response to Request for Additional Information Regarding License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 12023-01-20020 January 2023 Response to Request for Additional Information Regarding License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1 NL-22-0316, Emergency License Amendment Request for Technical Specification 3.7.2 Regarding One-Time Extension of Completion Time for Plant Service Water (Psw) Pump Inoperable2022-11-30030 November 2022 Emergency License Amendment Request for Technical Specification 3.7.2 Regarding One-Time Extension of Completion Time for Plant Service Water (Psw) Pump Inoperable NL-22-0850, Supplement to License Amendment Request to Revise the NFPA 805 Fire Protection Program2022-11-18018 November 2022 Supplement to License Amendment Request to Revise the NFPA 805 Fire Protection Program NL-22-0832, Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF .2022-10-27027 October 2022 Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF . NL-22-0800, Supplement to Authorized Relief Request HNP-ISI-RR-05-022022-10-27027 October 2022 Supplement to Authorized Relief Request HNP-ISI-RR-05-02 2024-07-09
[Table view] Category:Technical Specifications
MONTHYEARML24069A0012024-03-0909 March 2024 – Correction of Amendment No. 266 Regarding License Amendment Request Regarding Relocation of Specific Surveillance Frequencies to a Licensee-Controlled Program (TSTF-425, Revision 3) NL-24-0089, Correction of Technical Specification Omission2024-03-0909 March 2024 Correction of Technical Specification Omission ML22346A1482023-02-0909 February 2023 Issuance of Amendments 320 and 265, Regarding LAR to Revise Technical Specifications to Adopt TSTF-208 and Administrative Correction for Duplicate Technical Specifications 3.4.10 ML23018A0042023-01-24024 January 2023 Correction of Amendment Nos. 319 and 264 Regarding Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF ML22192A1992022-08-19019 August 2022 Issuance of Amendments Nos. 316 and 261, Regarding Request to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling ML22101A0942022-05-20020 May 2022 Issuance of Amendments Nos. 315 and 260, Regarding Request to Eliminate Automatic Main Steam Line Isolation on High Turbine Building Area Temperature NL-22-0335, Supplement to Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-208, Revision 0, Extension of Time to Reach Mode 2 in LCO 3.0.3 And.2022-05-17017 May 2022 Supplement to Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-208, Revision 0, Extension of Time to Reach Mode 2 in LCO 3.0.3 And. ML21349A5182022-02-0202 February 2022 Issuance of Amendments Regarding Revision to Technical Specifications to Adopt TSTF-554, Revise RCS Leakage ML21270A0862021-11-18018 November 2021 Issuance of Amendments Regarding Revision to Technical Specifications 5.7, High Radiation, Administrative Controls NL-21-0385, Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements2021-09-29029 September 2021 Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements ML21109A3592021-04-22022 April 2021 Issuance of Amendment No. 254, Regarding Revision to Technical Specifications for One-Time Extension of Completion Times Related to Residual Heat Removal System (Emergency Circumstances) ML20303A1812020-09-29029 September 2020 Rev. 117 to Technical Requirement Manual, Unit 1, Part 2 NL-20-1000, Responses to NRC Requests for Additional Information to License Amendment Request to Revise the Required Actions of Technical Specifications 3.8.1, AC Sources - Operating, for One-Time Extension of Completion Time2020-08-23023 August 2020 Responses to NRC Requests for Additional Information to License Amendment Request to Revise the Required Actions of Technical Specifications 3.8.1, AC Sources - Operating, for One-Time Extension of Completion Time NL-20-0793, Correction of Technical Specification Typographical Error2020-07-0202 July 2020 Correction of Technical Specification Typographical Error ML20066F5922020-06-11011 June 2020 Issuance of Amendments Nos. 304 and 249, Regarding License Amendment Request to Adopt NFPA-805 Performance Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (2001 Edition) ML19337C3222020-01-29029 January 2020 Issuance of Amendments Revision to Technical Specifications to Adopt TSTF-563 ML19212A0542019-09-20020 September 2019 Issuance of Amendments 299 and 244 Regarding Revision to Technical Specifications to Adopt Tstf-564, Safety Limit (Minimum Critical Power Ratio) MCPR ML19198A1042019-09-0404 September 2019 Issuance of Amendments Regarding Revision to Technical Specification 3.6.4.1 - Secondary Containment ML19164A0172019-06-21021 June 2019 Correction of Amendment No. 223 Multiple Technical Specification Changes (CAC Nos. MF5026 and MF5027) ML19091A2912019-04-30030 April 2019 Issuance of Amendments 296 and 241 to Revise Technical Specifications 3.6.2.5, Condition C, Residual Heat Removal Drywell Spray End State ML18222A2962018-08-29029 August 2018 Issuance of Amendments to Revise Technical Specification 3.7.7, ECCS - Operating (CAC Nos. MF9997 and MF9998; EPID L-2017-LLA-0263) NL-16-1617, Request for Addition of Surveillance Requirements Note for LCO 3.7.7 (NL-16-1617)2017-07-10010 July 2017 Request for Addition of Surveillance Requirements Note for LCO 3.7.7 (NL-16-1617) NL-17-0810, Transmittal of Marked-Up and Clean Technical Specifications Pages for Section 5.5.15 for HNP Implementation of TSTF-500, DC Electrical Rewrite.2017-05-11011 May 2017 Transmittal of Marked-Up and Clean Technical Specifications Pages for Section 5.5.15 for HNP Implementation of TSTF-500, DC Electrical Rewrite. NL-17-0841, Correction of Technical Specification Typographical Error2017-05-10010 May 2017 Correction of Technical Specification Typographical Error ML17076A4342017-03-23023 March 2017 TSTF-542 Marked-Up Technical Specifications and Bases for Hatch Nuclear Plant NL-16-2013, Transmittal of Revised Technical Specification Pages2016-10-26026 October 2016 Transmittal of Revised Technical Specification Pages NL-16-1564, Revised Technical Specifications Pages for Technical Specifications Revision Request to Implement TSTF-500, DC Electrical Re-Write.2016-09-20020 September 2016 Revised Technical Specifications Pages for Technical Specifications Revision Request to Implement TSTF-500, DC Electrical Re-Write. NL-16-1571, Supplemental Response Regarding Request to Adopt TSTF-222, Control Rod Scram Times2016-08-26026 August 2016 Supplemental Response Regarding Request to Adopt TSTF-222, Control Rod Scram Times ML16090A1742016-04-14014 April 2016 Issuance of Amendments Regarding Managing Gas Accumulation ML16062A0992016-03-23023 March 2016 Issuance of Amendments Regarding the Relocation of the Pressure Temperature Limit Curves Following TSTF-419 NL-15-1956, Adoption of TSTF-65-A, Rev. 1, Use of Generic Titles for Utility Positions2016-03-14014 March 2016 Adoption of TSTF-65-A, Rev. 1, Use of Generic Titles for Utility Positions ML16043A1012016-03-0707 March 2016 Edwin I Hatch Nuclear Plant, Unit Nos. 1 and 2, Issuance of Amendments Regarding Typographical Errors in the Facility Operating License and Technical Specifications (CAC Nos. MF6580 and MF6581) ML15342A3982016-01-29029 January 2016 Issuance of Amendment Regarding Minimum Critical Power Ratio NL-14-1075, Technical Specifications. Part 4 of 42015-12-15015 December 2015 Technical Specifications. Part 4 of 4 NL-14-1075, E.I. Hatch, Units 1 and 2 - Technical Specifications. Part 3 of 42015-12-15015 December 2015 E.I. Hatch, Units 1 and 2 - Technical Specifications. Part 3 of 4 ML15350A4112015-12-15015 December 2015 Technical Specifications. Part 3 of 4 ML15350A4102015-12-15015 December 2015 Technical Specifications. Part 2 of 4 ML15350A4092015-12-15015 December 2015 License Amendment Request for Adoption of TSTF-423-A, Rev. 1, Technical Specification End States, NEDC-32988-A, Using the Consolidated Line Item Improvement Process. Part 1 of 4 NL-14-1075, E.I. Hatch, Units 1 and 2 - Technical Specifications. Part 2 of 42015-12-15015 December 2015 E.I. Hatch, Units 1 and 2 - Technical Specifications. Part 2 of 4 NL-15-1881, Revised Technical Specification Page for Primary Containment Isolation Instrumentation2015-10-15015 October 2015 Revised Technical Specification Page for Primary Containment Isolation Instrumentation NL-15-1535, GNF-002N9964-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR - Hatch 1 Cycle 282015-08-31031 August 2015 GNF-002N9964-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR - Hatch 1 Cycle 28 NL-15-0407, Request to Revise Typographical Error in Unit 1 Operating License and in Unit 2 Technical Specifications, and to Add Staggered Test Basis to Unit 1 and Unit 2 Technical Specifications2015-08-0404 August 2015 Request to Revise Typographical Error in Unit 1 Operating License and in Unit 2 Technical Specifications, and to Add Staggered Test Basis to Unit 1 and Unit 2 Technical Specifications ML15180A3342015-08-0303 August 2015 Issuance of Amendments ML15054A4002015-02-24024 February 2015 (HNP-2), Correction for Amendments Regarding Reactor Core Safety Limits ML14349A7152014-12-23023 December 2014 Edwin I Hatch Nuclear Plant, Unit Nos. 1 and 2, Issuance of Amendments Regarding a Critical Instrumentation Bus ML14328A3232014-12-16016 December 2014 Edwin I Hatch Nuclear Plant, Unit Nos. 1 and 2, Issuance of Amendments for Degraded Voltage Protection Modification Schedule ML14279A2612014-12-10010 December 2014 Issuance of Amendments Regarding the Control Room Air Conditioning System ML14147A4102014-08-29029 August 2014 Issuance of Amendments Regarding Control Room Habitability NL-13-1751, Application to Revise Tech Specs to Adopt TSTF-535, Revise Shutdown Margin Definition to Address Advanced Fuel Designs.2014-03-17017 March 2014 Application to Revise Tech Specs to Adopt TSTF-535, Revise Shutdown Margin Definition to Address Advanced Fuel Designs. NL-12-1078, Edwin I. Hatch, Units 1 and 2, License Amendment Request to Revise the Minimum Water Level in the Plant Service Water Pump Well2012-07-0505 July 2012 Edwin I. Hatch, Units 1 and 2, License Amendment Request to Revise the Minimum Water Level in the Plant Service Water Pump Well 2024-03-09
[Table view] |
Text
~ Southern Nuclear J. J. Hutto Regulatory Affairs Director
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20:" 99.2 5H72 ld 20:\ \l1)2 -;r,o i fa x jjhutto(ri Hltht:m l.*n. ~om MAY 1 0 2017 Docket Nos.: 50-366 NL-17-0841 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. Joseph M. Farley Nyclear Plant, Units 1 and 2; Vogtle Electric Generating Plant, Units 1 and 2; and Edwin I. Hatch Nuclear Plant, Unit Nos. 1 and 2 -
Issuance of Amendments Regarding the Adoption of TSTF-65-A, Revision 1, "Use Of Generic Titles For Utility Positions" (TAC Nos. MF7466, MF7467, MF7468, MF7469, MF7470, And MF7471), January 13,2017
- 2. Edwin I. Hatch Nuclear Plant, Unit Nos. 1 And 2, Issuance of Amendments Regarding Revised Shutdown Margin (TAC Nos. MF3627 AND MF3628),
January 6, 2015
- 3. Proposed Guidance for Correction of Technical Specification Typographical Errors, SECY-96-238, dated 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 was inadvertently introduced during the processing of Unit 2 License Amendment 227 (Reference 1), and removed a TS change approved in License Amendment 217 (Reference 2}.
This 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 corrections. Enclosure 2 provides the Amendment 227 page as-issued, with the requested corrections noted. Enclosure 3 contains the corrected Amendment 227 page.
This letter contains no NRC commitments. If you have any questions, please contact Ken McElroy at 205.992.7369.
Respectfully submitted, J.J. Hutto Regulatory Affairs Director JJH/RMJ
U. S. Nuclear Regulatory Commission NL-17-0841 Page 2
Enclosures:
- 1. Description of Technical Specification Typographical Errors
- 2. Marked-up Technical Specification Page
- 3. Revised Technical Specification Page Cc: Regional Administrator, Region II 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 Enclosure 1 Description of Technical Specification Typographical Errors to NL-17-0841 Description of Technical Specification Typographical Errors
- 1. Requested Action Consistent with the information contained in SECY-96-238, Southern Nuclear Operating Company (SNC) is requesting corrections of a typographical error that was inadvertently introduced into the Hatch Nuclear Plant (HNP) Unit 2 Technical Specification (TS). The error was introduced by the SNC staff in development of revised pages provided to the Nuclear Regulatory Commission (NRC) for issuance of Amendment 227. The pages provided did not incorporate a TS change previously approved by the NRC with the issuance of Amendment 217.
- 2. Typographical Error The Unit 2 definition of "Shutdown Margin" on page 1.1-5 was changed in Amendment 217 to state the following (with underline added to show additions):
SHUTDOWN SDM shall be the amount of reactivity by which the reactor is subcritical MARGIN (SDM) or would be subcritical throughout the operating cycle assuming that:
- a. The reactor is xenon free;
- b. The moderator temperature is~ 68°F. corresponding to the most reactive state; and
- c. All control rods are fully inserted except for the single control rod of highest reactivity worth, which is assumed to be fully withdrawn.
With control rods not capable of being fully inserted, the reactivity worth of these control rods must be accounted for in the determination of SDM.
When this page was issued in Amendment 227, however, the revised definition was not incorporated.
- 3. Correction to Affected Pages SECY-96-238 (Reference 3) provides guidance to correct inadvertent typographical errors in the Technical Specifications. This 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.
E1-1
Edwin I. Hatch Nuclear Plant, Unit 2 Correction of Technical Specification Typographical Error Enclosure 2 Marked-up Technical Specification Page
Definitions 1.1 1.1 Definitions (continued)
PHYSICS TESTS PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation. These tests are:
- a. Described in Chapter 14, Initial Tests and Operation, of the FSAR;
- b. Authorized under the provisions of 10 CFR 50.59; or
- c. Otherwise approved by the Nuclear Regulatory Commission.
PRESSURE AND The PTLR is the unit specific document that provides the reactor vessel TEMPERATURE pressure and temperature limits, including heatup and cooldown rates, for LIMITS REPORT the current reactor vessel fluence period. These pressure and (PTLR) temperature limits shall be determined for each fluence period in accordance with Specification 5.6.7.
RATED THERMAL POWER (RTP) coolant of 2804 MWt.
REACTOR PROTECTION SYSTEM (RPS)
RESPONSE TIME SHUTDOWN SDM shall be the am l t of reactivity by which the reactor is subcritical MARGIN (SDM) or would be subcritical assuming that:
, corresponding to the
~
- a. The reactor is xenon free ; most reactive state
- b. The moderator temperature 1 68°F, and
- c. All control rods are fully inserted except for the single control rod of highest reactivity worth, which is assumed to be fully withdrawn .
With control rods not capable of being fully inserted, the reactivity worth of these control rods must be accounted for in the determination of SDM.
STAGGERED A STAGGERED TEST BASIS shall consist of the testing of one of the TEST BASIS systems, subsystems, channels, or other designated components during the interval specified by the Surveillance Frequency , so that all systems, subsystems, channels, or other designated components are tested during n Surveillance Frequency intervals, where n is the total number of systems, subsystems, channels, or other designated components in the associated function.
THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
(continued)
HATCH UNIT 2 1.1-5 Amendment No. 227
Edwin I. Hatch Nuclear Plant, Unit 2 Correction of Technical Specification Typographical Error Enclosure 3 Revised Technical Specification Page
Definitions 1.1 1.1 Definitions (continued)
PHYSICS TESTS PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation. These tests are:
- a. Described in Chapter 14, Initial Tests and Operation, of the FSAR;
- b. Authorized under the provisions of 10 CFR 50.59; or
- c. Otherwise approved by the Nuclear Regulatory Commission.
PRESSURE AND The PTLR is the unit specific document that provides the reactor vessel TEMPERATURE pressure and temperature limits, including heatup and cooldown rates, for LIMITS REPORT the current reactor vessel fluence period. These pressure and (PTLR) temperature limits shall be determined for each fluence period in accordance with Specification 5.6.7.
RATED THERMAL RTP shall be a total reactor core heat transfer rate to the reactor POWER (RTP) coolant of 2804 MWt.
REACTOR The RPS RESPONSE TIME shall be that time interval from when the PROTECTION monitored parameter exceeds its RPS trip setpoint at the channel SYSTEM (RPS) sensor until de-energization of the scram pilot valve solenoids. The RESPONSE TIME response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.
SHUTDOWN SDM shall be the amount of reactivity by which the reactor is subcritical MARGIN (SDM) or would be subcritical throughout the operating cycle assuming that:
- a. The reactor is xenon free;
- b. The moderator temperature is ;:: 68°F, corresponding to the most reactive state; and
- c. All control rods are fully inserted except for the single control rod of highest reactivity worth, which is assumed to be fully withdrawn.
With control rods not capable of being fully inserted, the reactivity worth of these control rods must be accounted for in the determination of SDM.
STAGGERED A STAGGERED TEST BASIS shall consist of the testing of one of the TEST BASIS systems, subsystems, channels, or other designated components during the interval specified by the Surveillance Frequency , so that all systems, subsystems, channels, or other designated components are tested during n Surveillance Frequency intervals, where n is the total number of systems, subsystems, channels, or other designated components in the associated function.
THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
(continued)
HATCH UNIT2 1.1-5 Amendment No. 227