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| | number = ML070430454 | | | number = ML070430454 |
| | issue date = 03/29/2007 | | | issue date = 03/29/2007 |
| | title = Comanche Peak Steam Electric Station, Units 1 and 2, Technical Specifications, Issuance of Amendment Nos. 137 and 137 Reactor Coolant System Specific Activity (TAC Nos. MD0189 and MD0190) | | | title = Technical Specifications, Issuance of Amendment Nos. 137 and 137 Reactor Coolant System Specific Activity |
| | author name = | | | author name = |
| | author affiliation = NRC/NRR/ADRO/DORL/LPLIV | | | author affiliation = NRC/NRR/ADRO/DORL/LPLIV |
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| =Text= | | =Text= |
| {{#Wiki_filter:Definitions 1.1 1.1 Definitions (continued) | | {{#Wiki_filter:Definitions 1.1 1.1 Definitions (continued) |
| DOSE EQUIVALENT 1-131 DOSE EQUIVALENT XE-133 ENGINEERED SAFETY FEATURE (ESF) RESPONSE TIME DOSE EQUIVALENT 1-131 shall be that concentration of I-131 (microcuries per gram) that alone would produce the same dose when inhaled as the combined activities of iodine isotopes 1-131, 1-132, 1-133, 1-134, and 1-135 actually present.The determination of DOSE EQUIVALENT 1-131 shall be performed using thyroid dose conversion factors from Table III of TID-14844, AEC, 1962, "Calculation of Distance Factors for Power and Test Reactor Sites," or from Table E-7 of Regulatory Guide 1.109, Revision 1, NRC, 1977, or from ICRP-30, 1979, Supplement to Part 1, page 192-212, Table titled "Committed Dose Equivalent in Target Organs or Tissues per Intake of Unit Activity," or from Table 2.1 of EPA Federal Guidance Report No. 11, 1988, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion." DOSE EQUIVALENT XE-133 shall be that concentration of Xe-1 33 (microcuries per gram) that alone would produce the same acute dose to the whole body as the combined activities of noble gas nuclides Kr-85m, Kr-87, Kr-88, Xe-133m, Xe-133, Xe-135m, Xe-135, and Xe-138 actually present. If a specific noble gas nuclide is not detected, it should be assumed to be present at the minimum detectable activity. | | DOSE EQUIVALENT 1-131 DOSE EQUIVALENT 1-131 shall be that concentration of I-131 (microcuries per gram) that alone would produce the same dose when inhaled as the combined activities of iodine isotopes 1-131, 1-132, 1-133, 1-134, and 1-135 actually present. |
| The determination of DOSE EQUIVALENT XE-1 33 shall be performed using effective dose conversion factors for air submersion listed in Table 111.1 of EPA Federal Guidance Report No. 12, 1993, "External Exposure to Radionuclides in Air, Water, and Soil", or using the dose conversion factors from Table B-1 of Regulatory Guide 1.109, Revision 1, NRC, 1977.The ESF RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF actuation setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays, where applicable. | | The determination of DOSE EQUIVALENT 1-131 shall be performed using thyroid dose conversion factors from Table III of TID-14844, AEC, 1962, "Calculation of Distance Factors for Power and Test Reactor Sites," or from Table E-7 of Regulatory Guide 1.109, Revision 1, NRC, 1977, or from ICRP-30, 1979, Supplement to Part 1, page 192-212, Table titled "Committed Dose Equivalent in Target Organs or Tissues per Intake of Unit Activity," or from Table 2.1 of EPA Federal Guidance Report No. 11, 1988, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion." |
| The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured. | | DOSE EQUIVALENT XE-133 DOSE EQUIVALENT XE-133 shall be that concentration of Xe-1 33 (microcuries per gram) that alone would produce the same acute dose to the whole body as the combined activities of noble gas nuclides Kr-85m, Kr-87, Kr-88, Xe-133m, Xe-133, Xe-135m, Xe-135, and Xe-138 actually present. If a specific noble gas nuclide is not detected, it should be assumed to be present at the minimum detectable activity. The determination of DOSE EQUIVALENT XE-1 33 shall be performed using effective dose conversion factors for air submersion listed in Table 111.1 of EPA Federal Guidance Report No. 12, 1993, "External Exposure to Radionuclides in Air, Water, and Soil", or using the dose conversion factors from Table B-1 of Regulatory Guide 1.109, Revision 1, NRC, 1977. |
| In lieu of measurement, response time may be verified for selected components provided that the components and methodology for verification have been previously reviewed and approved by the NRC.(continued) | | ENGINEERED SAFETY The ESF RESPONSE TIME shall be that time interval from FEATURE (ESF) RESPONSE when the monitored parameter exceeds its ESF actuation TIME setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays, where applicable. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components and methodology for verification have been previously reviewed and approved by the NRC. |
| COMANCHE PEAK -UNITS 1 AND 2 1.1-3 Amendment No. 6-4, 137 RCS Specific Activity 3.4.16 3.4 REACTOR COOLANT SYSTEM (RCS)3.4.16 RCS Specific Activity LCO 3.4.16 APPLICABILITY: | | (continued) |
| RCS DOSE EQUIVALENT 1-131 and DOSE EQUIVALENT XE-133 specific activity shall be within limits.MODES 1, 2, 3, and 4 I I ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. DOSE EQUIVALENT 1-131 -----Note-not within limit. LCO 3.0.4.c is applicable. | | COMANCHE PEAK - UNITS 1 AND 2 1.1-3 Amendment No. 6-4, 137 |
| A. 1 Verify DOSE Once per 4 hours EQUIVALENT 1-131:5 60 pCi/gm.AND A.2 Restore DOSE EQUIVALENT 1-131 to 48 hours within limit.(continued) | | |
| COMANCHE PEAK -UNITS I AND 2 3.4-44 AmentfrnentNo.40R 137 RCS Specific Activity 3.4.16 ACTIONS (continued) | | RCS Specific Activity 3.4.16 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.16 RCS Specific Activity LCO 3.4.16 RCS DOSE EQUIVALENT 1-131 and DOSE EQUIVALENT XE-133 specific activity shall be within limits. I APPLICABILITY: MODES 1, 2, 3, and 4 I |
| CONDITION REQUIRED ACTION COMPLETION TIME B. DOSE EQUIVALENT | | ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. DOSE EQUIVALENT 1-131 ----- Note-not within limit. LCO 3.0.4.c is applicable. |
| -----Note-XE-133 not within limit. LCO 3.0.4.c is applicable. | | A. 1 Verify DOSE Once per 4 hours EQUIVALENT 1-131 |
| B.1 Restore DOSE 48 hours EQUIVALENT XE-133 to within limit.C. Required Action and C.1 Be in MODE 3. 6 hours associated Completion Time of Condition A or B AND not met.C.2 Be in MODE 5. 36 hours OR DOSE EQUIVALENT 1-131> 60 pCi/gm.SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.16.1 -NOTE- 7 days Only required to be performed in MODE 1.Verify reactor coolant DOSE EQUIVALENT XE-1 33 specific activity _ 500 pCi/gm.(continued) | | :5 60 pCi/gm. |
| COMANCHE PEAK -UNITS 1 AND 2 3.4-45 Amendment No. 64, 137 RCS Specific Activity 3.4.16 ACTIONS (continued) | | AND A.2 Restore DOSE EQUIVALENT 1-131 to 48 hours within limit. |
| SURVEILLANCE FREQUENCY SR 3.4.16.2 -.--NOTE-- --NO Only required to be performed in MODE 1.Verify reactor coolant DOSE EQUIVALENT 1-131 specific 14 days activity - 0.45 ;iCi/gm.AND Between 2 and 6 hours after a THERMAL POWER change of ý: 15% RTP within a 1 hour period SR 3.4.16.3 DELETED DELETED I COMANCHE PEAK -UNITS I AND 2 3.4-46 Amendn1W No. 442, 13 7}} | | (continued) |
| | COMANCHE PEAK - UNITS I AND 2 3.4-44 AmentfrnentNo.40R 137 |
| | |
| | RCS Specific Activity 3.4.16 ACTIONS (continued) |
| | CONDITION REQUIRED ACTION COMPLETION TIME B. DOSE EQUIVALENT ----- Note-XE-133 not within limit. LCO 3.0.4.c is applicable. |
| | B.1 Restore DOSE 48 hours EQUIVALENT XE-133 to within limit. |
| | C. Required Action and C.1 Be in MODE 3. 6 hours associated Completion Time of Condition A or B AND not met. |
| | C.2 Be in MODE 5. 36 hours OR DOSE EQUIVALENT 1-131 |
| | > 60 pCi/gm. |
| | SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.16.1 - NOTE- 7 days Only required to be performed in MODE 1. |
| | Verify reactor coolant DOSE EQUIVALENT XE-1 33 specific activity _ 500 pCi/gm. |
| | (continued) |
| | COMANCHE PEAK - UNITS 1 AND 2 3.4-45 Amendment No. 64, 137 |
| | |
| | RCS Specific Activity 3.4.16 ACTIONS (continued) |
| | SURVEILLANCE FREQUENCY SR 3.4.16.2 -.-- NOTE-- |
| | NO -- |
| | Only required to be performed in MODE 1. |
| | Verify reactor coolant DOSE EQUIVALENT 1-131 specific 14 days activity *- 0.45 ;iCi/gm. |
| | AND Between 2 and 6 hours after a THERMAL POWER change of ý: 15% RTP within a 1 hour period SR 3.4.16.3 DELETED DELETED I COMANCHE PEAK - UNITS I AND 2 3.4-46 Amendn1W No. 442, 13 7}} |
Letter Sequence Approval |
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MONTHYEARML0704304542007-03-29029 March 2007
Technical Specifications, Issuance of Amendment Nos. 137 and 137 Reactor Coolant System Specific Activity
Project stage: Approval
ML0704304172007-03-29029 March 2007
License Amendment, Issuance of Amendment Nos. 137 and 137 Reactor Coolant System Specific Activity
Project stage: Approval
2007-03-29
[Table View] |
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Category:Technical Specifications
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2024-02-09
[Table view] |
Text
Definitions 1.1 1.1 Definitions (continued)
DOSE EQUIVALENT 1-131 DOSE EQUIVALENT 1-131 shall be that concentration of I-131 (microcuries per gram) that alone would produce the same dose when inhaled as the combined activities of iodine isotopes 1-131, 1-132, 1-133, 1-134, and 1-135 actually present.
The determination of DOSE EQUIVALENT 1-131 shall be performed using thyroid dose conversion factors from Table III of TID-14844, AEC, 1962, "Calculation of Distance Factors for Power and Test Reactor Sites," or from Table E-7 of Regulatory Guide 1.109, Revision 1, NRC, 1977, or from ICRP-30, 1979, Supplement to Part 1, page 192-212, Table titled "Committed Dose Equivalent in Target Organs or Tissues per Intake of Unit Activity," or from Table 2.1 of EPA Federal Guidance Report No. 11, 1988, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion."
DOSE EQUIVALENT XE-133 DOSE EQUIVALENT XE-133 shall be that concentration of Xe-1 33 (microcuries per gram) that alone would produce the same acute dose to the whole body as the combined activities of noble gas nuclides Kr-85m, Kr-87, Kr-88, Xe-133m, Xe-133, Xe-135m, Xe-135, and Xe-138 actually present. If a specific noble gas nuclide is not detected, it should be assumed to be present at the minimum detectable activity. The determination of DOSE EQUIVALENT XE-1 33 shall be performed using effective dose conversion factors for air submersion listed in Table 111.1 of EPA Federal Guidance Report No. 12, 1993, "External Exposure to Radionuclides in Air, Water, and Soil", or using the dose conversion factors from Table B-1 of Regulatory Guide 1.109, Revision 1, NRC, 1977.
ENGINEERED SAFETY The ESF RESPONSE TIME shall be that time interval from FEATURE (ESF) RESPONSE when the monitored parameter exceeds its ESF actuation TIME setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays, where applicable. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components and methodology for verification have been previously reviewed and approved by the NRC.
(continued)
COMANCHE PEAK - UNITS 1 AND 2 1.1-3 Amendment No. 6-4, 137
RCS Specific Activity 3.4.16 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.16 RCS Specific Activity LCO 3.4.16 RCS DOSE EQUIVALENT 1-131 and DOSE EQUIVALENT XE-133 specific activity shall be within limits. I APPLICABILITY: MODES 1, 2, 3, and 4 I
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. DOSE EQUIVALENT 1-131 ----- Note-not within limit. LCO 3.0.4.c is applicable.
A. 1 Verify DOSE Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> EQUIVALENT 1-131
- 5 60 pCi/gm.
AND A.2 Restore DOSE EQUIVALENT 1-131 to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> within limit.
(continued)
COMANCHE PEAK - UNITS I AND 2 3.4-44 AmentfrnentNo.40R 137
RCS Specific Activity 3.4.16 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B. DOSE EQUIVALENT ----- Note-XE-133 not within limit. LCO 3.0.4.c is applicable.
B.1 Restore DOSE 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> EQUIVALENT XE-133 to within limit.
C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A or B AND not met.
C.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> OR DOSE EQUIVALENT 1-131
> 60 pCi/gm.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.16.1 - NOTE- 7 days Only required to be performed in MODE 1.
Verify reactor coolant DOSE EQUIVALENT XE-1 33 specific activity _ 500 pCi/gm.
(continued)
COMANCHE PEAK - UNITS 1 AND 2 3.4-45 Amendment No. 64, 137
RCS Specific Activity 3.4.16 ACTIONS (continued)
SURVEILLANCE FREQUENCY SR 3.4.16.2 -.-- NOTE--
NO --
Only required to be performed in MODE 1.
Verify reactor coolant DOSE EQUIVALENT 1-131 specific 14 days activity *- 0.45 ;iCi/gm.
AND Between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after a THERMAL POWER change of ý: 15% RTP within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period SR 3.4.16.3 DELETED DELETED I COMANCHE PEAK - UNITS I AND 2 3.4-46 Amendn1W No. 442, 13 7
