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{{#Wiki_filter:TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 5.0 ADMINISTRATIVE CONTROLS .......0-5.1 Responsibility | {{#Wiki_filter:TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 5.0 ADMINISTRATIVE CONTROLS ....... 0-5.1 Responsibility ...................... 5.0-l 5.2 Organization ...................... 5.0-2 5.3 Unit Staff Qualifications ...................... 5.0-5 5.4 Procedures ...................... 5.0-6 5.5 Programs and Manuals ........ 5.0-7 5.6 Reporting Requirements ...................... TS/5.0-19 5.7 High Radiation Area ...................... 5.0-27 TS1 TOC 3/23/06 SUSQUEHANNA - UNIT 1 TS /TOC -4 Amendment 18(, 2 yV, ?.33 | ||
...................... | |||
5.0-l 5.2 Organization | PPL Rev. 6 Reporting Requirements 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 50.4. | ||
...................... | 5.6.1 Not Used I 5.6.2 Annual Radiological Environmental Operating Report | ||
5.0-2 5.3 Unit Staff Qualifications | -NOTE. | ||
...................... | A single submittal may be made for both SSES units. The submittal should combine sections common to all units at the station. | ||
5.0-5 5.4 Procedures | The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, aid analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (continued) | ||
...................... | SUSQUEHANNA - UNIT 1 TS / 5.0-1 9 Amendment 17f, ° | ||
5.0-6 5.5 Programs and Manuals ........ 5.0-7 5.6 Reporting Requirements | |||
...................... | PPL Rev. 6 Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.4 Not Used 5.6.5 CORE OPERATING LIMITS REPORT (COLR) | ||
TS/5.0-19 5.7 High Radiation Area ...................... | : a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following: | ||
5.0-27 TS1 TOC 3/23/06 SUSQUEHANNA | : 1. The Average Planar Linear Heat Generation Rate for Specification 3.2.1; | ||
-UNIT 1 TS /TOC -4 Amendment | : 2. The Minimum Critical Power Ratio for Specification 3.2.2; | ||
SUSQUEHANNA | : 3. The Linear Heat Generation Rate for Specification 3.2.3; | ||
-UNIT 1 TS / 5.0-1 9 Amendment | : 4. The Average Power Range Monitor (APRM) Gain and Setpoints for Specification 3.2.4; | ||
: 1. The Average Planar Linear Heat Generation Rate for Specification 3.2.1;2. The Minimum Critical Power Ratio for Specification 3.2.2;3. The Linear Heat Generation Rate for Specification 3.2.3;4. The Average Power Range Monitor (APRM) Gain and Setpoints for Specification 3.2.4;5. The Shutdown Margin for Specification 3.1.1; and 6. Oscillation Power Range Monitor (OPRM) Trip Setpoints for Specification 3.3.1.1.b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC.When an initial assumed power level of 102 percent of rated power is specified in a previously approved method, this refers to the power level associated with the design basis analyses, or 3510 MWt. The power level of 3510 MWt is 100.6% of the rated thermal power level of 3489 MWt. The RTP of 3489 MWt may only be used when feedwater flow measurement (used as input to the reactor thermal power measurement) is provided by the Leading Edge Flow Meter (LEFM/ | : 5. The Shutdown Margin for Specification 3.1.1; and | ||
SUSQUEHANNA | : 6. Oscillation Power Range Monitor (OPRM) Trip Setpoints for Specification 3.3.1.1. | ||
-UNIT 1 TS / 5.0-21 Amendment 1M, 1.94, 2l, 217>, 2 233, TABLE: OF CONTENTS (TECHNICAL SPECIFICATIONS) 5.0 | : b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC. | ||
5.0-1 Responsibility....................................................................................... | When an initial assumed power level of 102 percent of rated power is specified in a previously approved method, this refers to the power level associated with the design basis analyses, or 3510 MWt. The power level of 3510 MWt is 100.6% of the rated thermal power level of 3489 MWt. The RTP of 3489 MWt may only be used when feedwater flow measurement (used as input to the reactor thermal power measurement) is provided by the Leading Edge Flow Meter (LEFM/ Tm) as described in the LEFMVrm Topical Report and supplement referenced below. When feedwater flow measurements from the LEFMVTM system are not available, the core thermal power level may not exceed the originally approved RTP of 3441 MWt, but the value of 3510 MWt (continued) | ||
5.0-1 Organization | SUSQUEHANNA - UNIT 1 TS / 5.0-21 Amendment 1M, 1.94, 2l, 217>, 2 233, | ||
...................... | |||
5.0-2 Unit Staff Qualifications | TABLE: OF CONTENTS (TECHNICAL SPECIFICATIONS) 5.0 ADMINISTRATIVE CONTROLS ...................... 5.0-1 5.1 Responsibility....................................................................................... 5.0-1 5.2 Organization ...................... 5.0-2 5.3 Unit Staff Qualifications ...................... 5.0-5 5.4 Procedures ...................... 5.0-i3 5.5 Programs and Manuals ...................... 5.0-7 5.6 Reporting Requirements ...................... TS/5.0-- 9 I 5.7 High Radiation Area ...................... TSt5.0-24 TS2 TOC 3/23/06 SUSQUE.HANNA - UNIT 2 TSITOC - 4 Amendment 1/1 ,1 i, 1f12,210 | ||
...................... | |||
5.0-5 Procedures | PP[. Rev. 4 Reporting Requirements 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 50.4. | ||
...................... | 5.6:. Not Used I 5.6.2 Annual Radiological Environmental Operating Report | ||
5.0-i3 Programs and Manuals ...................... | ---------------------------------------------- NOTE------------------------------------------------------------ | ||
5.0-7 Reporting Requirements | A single submittal may be made for both SSES units. The submittal should combine sections common to all units at the station. | ||
...................... | The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (continued) | ||
TS/5.0-- 9 High Radiation Area ...................... | SUSQUEHANNA - UNIT 2 TS /5.0-19 Amendment 1,d1,210 | ||
TSt5.0-24 | |||
-UNIT 2 TSITOC -4 Amendment 1/1 ,1 i, 1f12,210 PP[. Rev. 4 Reporting Requirements 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 50.4.5.6:. Not Used 5.6.2 Annual Radiological Environmental Operating Report | PPL Rev. 4 Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.4 Not Used I I | ||
NOTE------------------------------------------------------------ | 5.6.'5 CORE OPERATING LIMITS REPORT (COLR) | ||
A single submittal may be made for both SSES units. The submittal should combine sections common to all units at the station.The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (continued) | : a. Core operating limits shall be established prior to each reload cycle, or priDr to any remaining portion of a reload cycle, and shall be documented in the COLR for the following: | ||
SUSQUEHANNA | : 1. The Average Planar Linear Heat Generation Rate for Specification 3.2.1; | ||
-UNIT 2 TS /5.0-19 Amendment 1,d1,210 PPL Rev. 4 Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.4 Not Used I I 5.6.'5 CORE OPERATING LIMITS REPORT (COLR)a. Core operating limits shall be established prior to each reload cycle, or priDr to any remaining portion of a reload cycle, and shall be documented in the COLR for the following: | : 2. The Minimum Critical Power Ratio for Specification 3.2.2; | ||
: 1. The Average Planar Linear Heat Generation Rate for Specification 3.2.1;2. The Minimum Critical Power Ratio for Specification 3.2.2;3. The Linear Heat Generation Rate for Specification 3.2.3;4 The Average Power Range Monitor (APRM) Gain and Setpoints for Specification 3.2.4; and 5. The Shutdown Margin for Specification 3.1.1.6. The OPRM setpoints for Specification 3.3.1.3.b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC.When an initial assumed power level of 102 percent of rated power is specified in a previously approved method, this refers to the power level associated wi:h the design basis analyses, or 3510 MWt. The power level of 3510 MWt is 100.6% of the rated thermal power level of 3489 MWt. The RTP of 3489 MWt may only be used when feedwater flow measurement (used as input to the reactor thermal power measurement) is provided by the Leading Edge Flow Meter (LEFM' | : 3. The Linear Heat Generation Rate for Specification 3.2.3; 4 The Average Power Range Monitor (APRM) Gain and Setpoints for Specification 3.2.4; and | ||
SUSQUEHANNA | : 5. The Shutdown Margin for Specification 3.1.1. | ||
-UNIT 2 TS / 5.0-21 Amendment 166, 19% | : 6. The OPRM setpoints for Specification 3.3.1.3. | ||
: b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC. | |||
When an initial assumed power level of 102 percent of rated power is specified in a previously approved method, this refers to the power level associated wi:h the design basis analyses, or 3510 MWt. The power level of 3510 MWt is 100.6% of the rated thermal power level of 3489 MWt. The RTP of 3489 MWt may only be used when feedwater flow measurement (used as input to the reactor thermal power measurement) is provided by the Leading Edge Flow Meter (LEFM' Tm) as described in the LEFMV MTopical Report and supplement referenced below. | |||
When feedwater flow measurements from the LEFMVTM system are not available, the (continued) | |||
SUSQUEHANNA - UNIT 2 TS / 5.0-21 Amendment 166, 19% 19Z 210}} |
Latest revision as of 21:00, 23 November 2019
ML061010566 | |
Person / Time | |
---|---|
Site: | Susquehanna ![]() |
Issue date: | 04/06/2006 |
From: | Plant Licensing Branch III-2 |
To: | |
References | |
Download: ML061010566 (6) | |
Text
TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 5.0 ADMINISTRATIVE CONTROLS ....... 0-5.1 Responsibility ...................... 5.0-l 5.2 Organization ...................... 5.0-2 5.3 Unit Staff Qualifications ...................... 5.0-5 5.4 Procedures ...................... 5.0-6 5.5 Programs and Manuals ........ 5.0-7 5.6 Reporting Requirements ...................... TS/5.0-19 5.7 High Radiation Area ...................... 5.0-27 TS1 TOC 3/23/06 SUSQUEHANNA - UNIT 1 TS /TOC -4 Amendment 18(, 2 yV, ?.33
PPL Rev. 6 Reporting Requirements 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 50.4.
5.6.1 Not Used I 5.6.2 Annual Radiological Environmental Operating Report
-NOTE.
A single submittal may be made for both SSES units. The submittal should combine sections common to all units at the station.
The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, aid analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (continued)
SUSQUEHANNA - UNIT 1 TS / 5.0-1 9 Amendment 17f, °
PPL Rev. 6 Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.4 Not Used 5.6.5 CORE OPERATING LIMITS REPORT (COLR)
- a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:
- 1. The Average Planar Linear Heat Generation Rate for Specification 3.2.1;
- 2. The Minimum Critical Power Ratio for Specification 3.2.2;
- 3. The Linear Heat Generation Rate for Specification 3.2.3;
- 4. The Average Power Range Monitor (APRM) Gain and Setpoints for Specification 3.2.4;
- 5. The Shutdown Margin for Specification 3.1.1; and
- 6. Oscillation Power Range Monitor (OPRM) Trip Setpoints for Specification 3.3.1.1.
- b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC.
When an initial assumed power level of 102 percent of rated power is specified in a previously approved method, this refers to the power level associated with the design basis analyses, or 3510 MWt. The power level of 3510 MWt is 100.6% of the rated thermal power level of 3489 MWt. The RTP of 3489 MWt may only be used when feedwater flow measurement (used as input to the reactor thermal power measurement) is provided by the Leading Edge Flow Meter (LEFM/ Tm) as described in the LEFMVrm Topical Report and supplement referenced below. When feedwater flow measurements from the LEFMVTM system are not available, the core thermal power level may not exceed the originally approved RTP of 3441 MWt, but the value of 3510 MWt (continued)
SUSQUEHANNA - UNIT 1 TS / 5.0-21 Amendment 1M, 1.94, 2l, 217>, 2 233,
TABLE: OF CONTENTS (TECHNICAL SPECIFICATIONS) 5.0 ADMINISTRATIVE CONTROLS ...................... 5.0-1 5.1 Responsibility....................................................................................... 5.0-1 5.2 Organization ...................... 5.0-2 5.3 Unit Staff Qualifications ...................... 5.0-5 5.4 Procedures ...................... 5.0-i3 5.5 Programs and Manuals ...................... 5.0-7 5.6 Reporting Requirements ...................... TS/5.0-- 9 I 5.7 High Radiation Area ...................... TSt5.0-24 TS2 TOC 3/23/06 SUSQUE.HANNA - UNIT 2 TSITOC - 4 Amendment 1/1 ,1 i, 1f12,210
PP[. Rev. 4 Reporting Requirements 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 50.4.
5.6:. Not Used I 5.6.2 Annual Radiological Environmental Operating Report
NOTE------------------------------------------------------------
A single submittal may be made for both SSES units. The submittal should combine sections common to all units at the station.
The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (continued)
SUSQUEHANNA - UNIT 2 TS /5.0-19 Amendment 1,d1,210
PPL Rev. 4 Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.4 Not Used I I
5.6.'5 CORE OPERATING LIMITS REPORT (COLR)
- a. Core operating limits shall be established prior to each reload cycle, or priDr to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:
- 1. The Average Planar Linear Heat Generation Rate for Specification 3.2.1;
- 2. The Minimum Critical Power Ratio for Specification 3.2.2;
- 3. The Linear Heat Generation Rate for Specification 3.2.3; 4 The Average Power Range Monitor (APRM) Gain and Setpoints for Specification 3.2.4; and
- 5. The Shutdown Margin for Specification 3.1.1.
- 6. The OPRM setpoints for Specification 3.3.1.3.
- b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC.
When an initial assumed power level of 102 percent of rated power is specified in a previously approved method, this refers to the power level associated wi:h the design basis analyses, or 3510 MWt. The power level of 3510 MWt is 100.6% of the rated thermal power level of 3489 MWt. The RTP of 3489 MWt may only be used when feedwater flow measurement (used as input to the reactor thermal power measurement) is provided by the Leading Edge Flow Meter (LEFM' Tm) as described in the LEFMV MTopical Report and supplement referenced below.
When feedwater flow measurements from the LEFMVTM system are not available, the (continued)
SUSQUEHANNA - UNIT 2 TS / 5.0-21 Amendment 166, 19% 19Z 210