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{{#Wiki_filter:-3'-neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required;D. Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form for sample analysis or instrument and equipment calibration or associated with radioactive apparatus or components; E. Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by operation of the facility.3. This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations: | {{#Wiki_filter:-3'- | ||
10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Section 50.54 and 50.59 of 10CFR Part 50, and Section 70.32 of 10 CFR Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below: A. Maximum Power Level The licensee is authorized to operate the facility at a steady state reactor core power level not in excess of 2339 megawatts thermal.B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 219 are hereby incorporated in the license.The licensee shall operate the facility in accordance with the Technical Specifications. | neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; D. Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form for sample analysis or instrument and equipment calibration or associated with radioactive apparatus or components; E. Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by operation of the facility. | ||
(1) For Surveillance Requirements (SRs) that are new in Amendment 176 to Final Operating License DPR-23, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 176. For SRs that existed prior to Amendment 176, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the Surveillance was last performed prior to implementation of Amendment 176.Renewed Facility Operating License No. DPR-23 Amendment No.219 CREFS 3.7.9 3.7 PLANT SYSTEMS 3.7.9 Control Room Emergency Filtration System (CREFS)LCO 3.7.9 Two CREFS trains shall be OPERABLE....................... | : 3. This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations: 10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Section 50.54 and 50.59 of 10CFR Part 50, and Section 70.32 of 10 CFR Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below: | ||
---- | A. Maximum Power Level The licensee is authorized to operate the facility at a steady state reactor core power level not in excess of 2339 megawatts thermal. | ||
The control room envelope (CRE) boundary may be opened intermittently under administrative control.APPLICABILITY: | B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 219 are hereby incorporated in the license. | ||
MODES 1, 2, 3, and 4 During movement of i rradiated fuel assemblies. | The licensee shall operate the facility in accordance with the Technical Specifications. | ||
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CREFS train A.1 Restore CREFS train 7 days inoperable for to OPERABLE status.reasons other than Condition G.B. Required Action and B.1 Be in MODE 3. 6 hours associated Completion Time of Condition A AND not met in MODE 1, 2, 3, or 4. B.2 Be in MODE 5. 36 hours C. Required Action and C.1 Place OPERABLE CREFS Immediately associated Completion train in emergency Time of Condition A pressurization mode.not met during movement of irradiated OR fuel assemblies. | (1) For Surveillance Requirements (SRs) that are new in Amendment 176 to Final Operating License DPR-23, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 176. For SRs that existed prior to Amendment 176, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the Surveillance was last performed prior to implementation of Amendment 176. | ||
C.2 Suspend movement of Immediately irradiated fuel assemblies.(continued) | Renewed Facility Operating License No. DPR-23 Amendment No.219 | ||
HBRSEP Unit 2 3.7-22 Amendment No. 219 CREFS 3.7.9 ACTIONS (continued) | |||
CONDITION REQUIRED ACTION COMPLETION TIME D. Two CREFS trains D.1 Suspend movement of Immediately inoperable during irradiated fuel movement of irradiated assemblies. | CREFS 3.7.9 3.7 PLANT SYSTEMS 3.7.9 Control Room Emergency Filtration System (CREFS) | ||
LCO 3.7.9 Two CREFS trains shall be OPERABLE. | |||
...................... NOTE ----------------------------- | |||
---- | |||
The control room envelope (CRE) boundary may be opened intermittently under administrative control. | |||
APPLICABILITY: MODES 1, 2, 3, and 4 During movement of i rradiated fuel assemblies. | |||
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CREFS train A.1 Restore CREFS train 7 days inoperable for to OPERABLE status. | |||
reasons other than Condition G. | |||
B. Required Action and B.1 Be in MODE 3. 6 hours associated Completion Time of Condition A AND not met in MODE 1, 2, 3, or 4. B.2 Be in MODE 5. 36 hours C. Required Action and C.1 Place OPERABLE CREFS Immediately associated Completion train in emergency Time of Condition A pressurization mode. | |||
not met during movement of irradiated OR fuel assemblies. | |||
C.2 Suspend movement of Immediately irradiated fuel assemblies. | |||
(continued) | |||
HBRSEP Unit 2 3.7-22 Amendment No. 219 | |||
CREFS 3.7.9 ACTIONS (continued) | |||
CONDITION REQUIRED ACTION COMPLETION TIME D. Two CREFS trains D.1 Suspend movement of Immediately inoperable during irradiated fuel movement of irradiated assemblies. | |||
fuel assemblies. | fuel assemblies. | ||
E. Two CREFS trains E.1 Restore at least one 48 hours inoperable for reasons CREFS train to other than Condition G OPERABLE status.in MODE 1, 2, 3, or 4.F. Required Action and F.1 Be in MODE 3. 6 hours associated Completion Time of Condition E AND not met in MODE 1, 2, 3, or 4. F.2 Be in MODE 5. 36 hours G. One or more CREFS G.1 Initiate action to Immediately trains inoperable due implement mitigating to inoperable Control actions.Room Envelope (CRE)Boundary in MODE 1, 2, AND 3, or 4.G.2 Verify mitigating 24 hours actions ensure CRE occupancy for design basis conditions. | E. Two CREFS trains E.1 Restore at least one 48 hours inoperable for reasons CREFS train to other than Condition G OPERABLE status. | ||
AND G.3 Restore CRE boundary 90 days to OPERABLE status.(continued) | in MODE 1, 2, 3, or 4. | ||
HBRSEP Unit 2 3.7-23 Amendment No. 219 CREFS 3.7.9 ACTIONS (continued) | F. Required Action and F.1 Be in MODE 3. 6 hours associated Completion Time of Condition E AND not met in MODE 1, 2, 3, or 4. F.2 Be in MODE 5. 36 hours G. One or more CREFS G.1 Initiate action to Immediately trains inoperable due implement mitigating to inoperable Control actions. | ||
CONDITION REQUIRED ACTION COMPLETION TIME H. Required Action and H.1 Be in MODE 3. 6 hours associated Completion Time of Condition G AND not met in MODE 1, 2, 3, or 4. H.2 Be in MODE 5. 36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.9.1 Operate each CREFS train for 2 15 minutes. 31 days SR 3.7.9.2 Perform required CREFS filter testing in In accordance accordance with the Ventilation Filter with VFTP Testing Program (VFTP).SR 3.7.9.3 Verify each CREFS train actuates on an 18 months actual or simulated actuation signal.SR 3.7.9.4 Perform required CRE maintenance and In accordance testing in accordance with the CRE with the CRE Habitability Program. Habitability Program HBRSEP Unit 2 3.7-24 Amendment No. 219 Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.16 Containment Leakage Rate Testing Program This program provides controls for implementation of the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions for Type A testing. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program," dated September 1995, as modified by the following exception: | Room Envelope (CRE) | ||
: a. NEI 94-01 -'1995, Section 9.3.2: The first Type A test performed after the April 9, 1992, Type A test shall be performed no later than April 9, 2007.Type B and C testing shall be implemented in the program in accordance with the requirements of 10 CFR 50, Appendix J, Option A.The peak containment pressure, Pa, is specified as the containment design pressure of 42 psig, which exceeds the peak calculated containment internal pressure for the design basis loss of coolant accident.The maximum allowable containment leakage rate, La, at Pa, shall be 0.1% of the containment air weight per day.Leakage rate acceptance criteria are: a. Containment leakage rate acceptance criteria is < 1.0 La.During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are < 0.60 La for the Type B and Type C tests, and< 0.75 La for Type A tests.The provisions of SR 3.0.3 are applicable to the Containment Leakage Rate Testing Program.5.5.17 Control Room Envelope Habitability Program A Control Room Envelope (CRE) Habitability Program shall be implemented to ensure that, with an OPERABLE Control Room Emergency Filtration System, CRE occupants can control the nuclear power unit safely following a radiological event, hazardous chemical release, or a smoke challenge. | Boundary in MODE 1, 2, AND 3, or 4. | ||
The program shall include the following elements: (continued) | G.2 Verify mitigating 24 hours actions ensure CRE occupancy for design basis conditions. | ||
HBRSEP Unit No. 2 5.0-22 Amendment No. 219 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.17 Control Room Envelope Habitability Program (continued) | AND G.3 Restore CRE boundary 90 days to OPERABLE status. | ||
: a. The definition of the CRE and the CRE boundary.b. Requirements for maintaining the CRE boundary in its design condition, including configuration control and preventive maintenance. | (continued) | ||
: c. Requirements for: Mi) determining the unfiltered air inleakage past the CRE boundary into the CRE in accordance with the testing methods and at the frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197,"Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors," Revision 0, May 2003, and (ii) assessing CRE habitability at the frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, Revision 0.The following exception is taken to Sections C.1 and C.2 of Regulatory Guide 1.197, Revision 0: 1. Unfiltered air inleakage testing shall include the ability to deviate from the test methodology of ASTM-E741. These exceptions shall be documented in the test report.d. Measurement, at designated locations, of the CRE pressure relative to external areas adjacent to the CRE boundary during the pressurization mode of operation by one train of the CREFS, operating at the flow rate required by the VFTP, at a frequency of 18 months on a STAGGERED TEST BASIS. The results shall be trended and used as part of the assessment of the CRE boundary.e. The quantitative limits on unfiltered air inleakage into the CRE. These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph | HBRSEP Unit 2 3.7-23 Amendment No. 219 | ||
For hazardous chemicals, inleakage rates shall be less than assumed in the licensing bases.f. The provisions of SR 3.0.2 are applicable to the frequencies for assessing CRE habitability, determining CRE unfiltered inleakage, and measuring CRE pressure and assessing the CRE boundary as required by paragraphs c and d, respectively. | CREFS 3.7.9 ACTIONS (continued) | ||
HBRSEP Unit No. 2 5.0-22a Amendment No. 219 APPENDIX B ADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO. DPR-23 Carolina Power & Light Company (the term licensee in to Carolina Power & Light Company) shall comply with conditions on the schedules noted below: | CONDITION REQUIRED ACTION COMPLETION TIME H. Required Action and H.1 Be in MODE 3. 6 hours associated Completion Time of Condition G AND not met in MODE 1, 2, 3, or 4. H.2 Be in MODE 5. 36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.9.1 Operate each CREFS train for 2 15 minutes. 31 days SR 3.7.9.2 Perform required CREFS filter testing in In accordance accordance with the Ventilation Filter with VFTP Testing Program (VFTP). | ||
Implementation of this amendment shall include the relocation of these requirements to the appropriate documents, as described in the licensee's letters dated September 10, 1997, and October 13, 1997, evaluated in the NRC staff's Safety Evaluation enclosed with this amendment. | SR 3.7.9.3 Verify each CREFS train actuates on an 18 months actual or simulated actuation signal. | ||
Upon implementation of the amendment adopting TSTF-448, Revision 3, the determination of control room envelope (CRE) unfiltered air inleakage as required by TS 5.5.17.c.(i), the assessment of CRE habitability as required by TS 5.5.17.c.(ii), and the measurement of CRE pressure as required by TS 5.5.17.d, shall be considered met.Following implementation: (a) The first performance of TS 5.5.17.c.(i), shall be within the specified Frequency of 6 years, plus the 18-month allowance of SR 3.0.2, as measured from January 27,2003, the | SR 3.7.9.4 Perform required CRE maintenance and In accordance testing in accordance with the CRE with the CRE Habitability Program. Habitability Program HBRSEP Unit 2 3.7-24 Amendment No. 219 | ||
HBRSEP Unit No. 2 1 Amendment No. 219 APPENDIX B ADDITIONAL CONDITIONS date of the most recent successful tracer gas test, or within the next 18 months if the time period since the most recent successful tracer gas test is greater than 6.years.(b) The first performance of the periodic assessment of CRE habitability, TS 5.5.17.c.(ii), shall be within the next 9 months.(c) The first performance of the periodic measurement of CRE pressure, TS 5.5.17.d, shall be within 18 months, plus the 138 days allowed by SR 3.0.2, as measured from the date of the most recent successful pressure measurement test.HBRSEP Unit No. 2 2 Amendment No. 219}} | Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.16 Containment Leakage Rate Testing Program This program provides controls for implementation of the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions for Type A testing. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program," dated September 1995, as modified by the following exception: | ||
: a. NEI 94-01 -'1995, Section 9.3.2: The first Type A test performed after the April 9, 1992, Type A test shall be performed no later than April 9, 2007. | |||
Type B and C testing shall be implemented in the program in accordance with the requirements of 10 CFR 50, Appendix J, Option A. | |||
The peak containment pressure, Pa, is specified as the containment design pressure of 42 psig, which exceeds the peak calculated containment internal pressure for the design basis loss of coolant accident. | |||
The maximum allowable containment leakage rate, La, at Pa, shall be 0.1% of the containment air weight per day. | |||
Leakage rate acceptance criteria are: | |||
: a. Containment leakage rate acceptance criteria is < 1.0 La. | |||
During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are < 0.60 La for the Type B and Type C tests, and | |||
< 0.75 La for Type A tests. | |||
The provisions of SR 3.0.3 are applicable to the Containment Leakage Rate Testing Program. | |||
5.5.17 Control Room Envelope Habitability Program A Control Room Envelope (CRE) Habitability Program shall be implemented to ensure that, with an OPERABLE Control Room Emergency Filtration System, CRE occupants can control the nuclear power unit safely following a radiological event, hazardous chemical release, or a smoke challenge. The program shall include the following elements: | |||
(continued) | |||
HBRSEP Unit No. 2 5.0-22 Amendment No. 219 | |||
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.17 Control Room Envelope Habitability Program (continued) | |||
: a. The definition of the CRE and the CRE boundary. | |||
: b. Requirements for maintaining the CRE boundary in its design condition, including configuration control and preventive maintenance. | |||
: c. Requirements for: Mi) determining the unfiltered air inleakage past the CRE boundary into the CRE in accordance with the testing methods and at the frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, "Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors," Revision 0, May 2003, and (ii) assessing CRE habitability at the frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, Revision 0. | |||
The following exception is taken to Sections C.1 and C.2 of Regulatory Guide 1.197, Revision 0: | |||
: 1. Unfiltered air inleakage testing shall include the ability to deviate from the test methodology of ASTM-E741. These exceptions shall be documented in the test report. | |||
: d. Measurement, at designated locations, of the CRE pressure relative to external areas adjacent to the CRE boundary during the pressurization mode of operation by one train of the CREFS, operating at the flow rate required by the VFTP, at a frequency of 18 months on a STAGGERED TEST BASIS. The results shall be trended and used as part of the assessment of the CRE boundary. | |||
: e. The quantitative limits on unfiltered air inleakage into the CRE. These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph c. The unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of DBA consequences. For hazardous chemicals, inleakage rates shall be less than assumed in the licensing bases. | |||
: f. The provisions of SR 3.0.2 are applicable to the frequencies for assessing CRE habitability, determining CRE unfiltered inleakage, and measuring CRE pressure and assessing the CRE boundary as required by paragraphs c and d, respectively. | |||
HBRSEP Unit No. 2 5.0-22a Amendment No. 219 | |||
APPENDIX B ADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO. DPR-23 Carolina Power & Light Company (the term licensee in Appendix B refers to Carolina Power & Light Company) shall comply with the following conditions on the schedules noted below: | |||
Amendment Additional Conditions Implementation Number Date 176 The licensee is authorized to relocate This amendment certain requirements included in is effective Appendix-A and the former Appendix B to immediately licensee-controlled documents. and shall be Implementation of this amendment shall implemented include the relocation of these within 90 days requirements to the appropriate documents, of the date of as described in the licensee's letters this dated September 10, 1997, and October 13, amendment. | |||
1997, evaluated in the NRC staff's Safety Evaluation enclosed with this amendment. | |||
219 Upon implementation of the amendment This amendment adopting TSTF-448, Revision 3, the is effective determination of control room envelope immediately (CRE) unfiltered air inleakage as required and shall be by TS 5.5.17.c.(i), the assessment of CRE implemented as habitability as required by TS specified. | |||
5.5.17.c.(ii), and the measurement of CRE pressure as required by TS 5.5.17.d, shall be considered met. | |||
Following implementation: | |||
(a) The first performance of TS 5.5.17.c.(i), shall be within the specified Frequency of 6 years, plus the 18-month allowance of SR 3.0.2, as measured from January 27,2003, the HBRSEP Unit No. 2 1 Amendment No. 219 | |||
APPENDIX B ADDITIONAL CONDITIONS date of the most recent successful tracer gas test, or within the next 18 months if the time period since the most recent successful tracer gas test is greater than 6.years. | |||
(b) The first performance of the periodic assessment of CRE habitability, TS 5.5.17.c.(ii), shall be within the next 9 months. | |||
(c) The first performance of the periodic measurement of CRE pressure, TS 5.5.17.d, shall be within 18 months, plus the 138 days allowed by SR 3.0.2, as measured from the date of the most recent successful pressure measurement test. | |||
HBRSEP Unit No. 2 2 Amendment No. 219}} |
Revision as of 17:45, 14 November 2019
ML081340323 | |
Person / Time | |
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Site: | Robinson ![]() |
Issue date: | 07/23/2008 |
From: | NRC/NRR/ADRO/DORL/LPLII-2 |
To: | |
Vaaler, Marlayna, NRR/DORL 415-1998 | |
Shared Package | |
ML081340311 | List: |
References | |
TAC MD6117 | |
Download: ML081340323 (8) | |
Text
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neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; D. Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form for sample analysis or instrument and equipment calibration or associated with radioactive apparatus or components; E. Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by operation of the facility.
- 3. This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations: 10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Section 50.54 and 50.59 of 10CFR Part 50, and Section 70.32 of 10 CFR Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
A. Maximum Power Level The licensee is authorized to operate the facility at a steady state reactor core power level not in excess of 2339 megawatts thermal.
B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 219 are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
(1) For Surveillance Requirements (SRs) that are new in Amendment 176 to Final Operating License DPR-23, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 176. For SRs that existed prior to Amendment 176, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the Surveillance was last performed prior to implementation of Amendment 176.
Renewed Facility Operating License No. DPR-23 Amendment No.219
CREFS 3.7.9 3.7 PLANT SYSTEMS 3.7.9 Control Room Emergency Filtration System (CREFS)
LCO 3.7.9 Two CREFS trains shall be OPERABLE.
...................... NOTE -----------------------------
The control room envelope (CRE) boundary may be opened intermittently under administrative control.
APPLICABILITY: MODES 1, 2, 3, and 4 During movement of i rradiated fuel assemblies.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CREFS train A.1 Restore CREFS train 7 days inoperable for to OPERABLE status.
reasons other than Condition G.
B. Required Action and B.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 AND not met in MODE 1, 2, 3, or 4. B.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 /> C. Required Action and C.1 Place OPERABLE CREFS Immediately associated Completion train in emergency Time of Condition A pressurization mode.
not met during movement of irradiated OR fuel assemblies.
C.2 Suspend movement of Immediately irradiated fuel assemblies.
(continued)
HBRSEP Unit 2 3.7-22 Amendment No. 219
CREFS 3.7.9 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME D. Two CREFS trains D.1 Suspend movement of Immediately inoperable during irradiated fuel movement of irradiated assemblies.
fuel assemblies.
E. Two CREFS trains E.1 Restore at least one 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> inoperable for reasons CREFS train to other than Condition G OPERABLE status.
in MODE 1, 2, 3, or 4.
F. Required Action and F.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 E AND not met in MODE 1, 2, 3, or 4. F.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 /> G. One or more CREFS G.1 Initiate action to Immediately trains inoperable due implement mitigating to inoperable Control actions.
Room Envelope (CRE)
Boundary in MODE 1, 2, AND 3, or 4.
G.2 Verify mitigating 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> actions ensure CRE occupancy for design basis conditions.
AND G.3 Restore CRE boundary 90 days to OPERABLE status.
(continued)
HBRSEP Unit 2 3.7-23 Amendment No. 219
CREFS 3.7.9 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME H. Required Action and H.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 G AND not met in MODE 1, 2, 3, or 4. H.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 /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.9.1 Operate each CREFS train for 2 15 minutes. 31 days SR 3.7.9.2 Perform required CREFS filter testing in In accordance accordance with the Ventilation Filter with VFTP Testing Program (VFTP).
SR 3.7.9.3 Verify each CREFS train actuates on an 18 months actual or simulated actuation signal.
SR 3.7.9.4 Perform required CRE maintenance and In accordance testing in accordance with the CRE with the CRE Habitability Program. Habitability Program HBRSEP Unit 2 3.7-24 Amendment No. 219
Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.16 Containment Leakage Rate Testing Program This program provides controls for implementation of the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions for Type A testing. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program," dated September 1995, as modified by the following exception:
- a. NEI 94-01 -'1995, Section 9.3.2: The first Type A test performed after the April 9, 1992, Type A test shall be performed no later than April 9, 2007.
Type B and C testing shall be implemented in the program in accordance with the requirements of 10 CFR 50, Appendix J, Option A.
The peak containment pressure, Pa, is specified as the containment design pressure of 42 psig, which exceeds the peak calculated containment internal pressure for the design basis loss of coolant accident.
The maximum allowable containment leakage rate, La, at Pa, shall be 0.1% of the containment air weight per day.
Leakage rate acceptance criteria are:
- a. Containment leakage rate acceptance criteria is < 1.0 La.
During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are < 0.60 La for the Type B and Type C tests, and
< 0.75 La for Type A tests.
The provisions of SR 3.0.3 are applicable to the Containment Leakage Rate Testing Program.
5.5.17 Control Room Envelope Habitability Program A Control Room Envelope (CRE) Habitability Program shall be implemented to ensure that, with an OPERABLE Control Room Emergency Filtration System, CRE occupants can control the nuclear power unit safely following a radiological event, hazardous chemical release, or a smoke challenge. The program shall include the following elements:
(continued)
HBRSEP Unit No. 2 5.0-22 Amendment No. 219
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.17 Control Room Envelope Habitability Program (continued)
- b. Requirements for maintaining the CRE boundary in its design condition, including configuration control and preventive maintenance.
- c. Requirements for: Mi) determining the unfiltered air inleakage past the CRE boundary into the CRE in accordance with the testing methods and at the frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, "Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors," Revision 0, May 2003, and (ii) assessing CRE habitability at the frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, Revision 0.
The following exception is taken to Sections C.1 and C.2 of Regulatory Guide 1.197, Revision 0:
- 1. Unfiltered air inleakage testing shall include the ability to deviate from the test methodology of ASTM-E741. These exceptions shall be documented in the test report.
- d. Measurement, at designated locations, of the CRE pressure relative to external areas adjacent to the CRE boundary during the pressurization mode of operation by one train of the CREFS, operating at the flow rate required by the VFTP, at a frequency of 18 months on a STAGGERED TEST BASIS. The results shall be trended and used as part of the assessment of the CRE boundary.
- e. The quantitative limits on unfiltered air inleakage into the CRE. These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph c. The unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of DBA consequences. For hazardous chemicals, inleakage rates shall be less than assumed in the licensing bases.
- f. The provisions of SR 3.0.2 are applicable to the frequencies for assessing CRE habitability, determining CRE unfiltered inleakage, and measuring CRE pressure and assessing the CRE boundary as required by paragraphs c and d, respectively.
HBRSEP Unit No. 2 5.0-22a Amendment No. 219
APPENDIX B ADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO. DPR-23 Carolina Power & Light Company (the term licensee in Appendix B refers to Carolina Power & Light Company) shall comply with the following conditions on the schedules noted below:
Amendment Additional Conditions Implementation Number Date 176 The licensee is authorized to relocate This amendment certain requirements included in is effective Appendix-A and the former Appendix B to immediately licensee-controlled documents. and shall be Implementation of this amendment shall implemented include the relocation of these within 90 days requirements to the appropriate documents, of the date of as described in the licensee's letters this dated September 10, 1997, and October 13, amendment.
1997, evaluated in the NRC staff's Safety Evaluation enclosed with this amendment.
219 Upon implementation of the amendment This amendment adopting TSTF-448, Revision 3, the is effective determination of control room envelope immediately (CRE) unfiltered air inleakage as required and shall be by TS 5.5.17.c.(i), the assessment of CRE implemented as habitability as required by TS specified.
5.5.17.c.(ii), and the measurement of CRE pressure as required by TS 5.5.17.d, shall be considered met.
Following implementation:
(a) The first performance of TS 5.5.17.c.(i), shall be within the specified Frequency of 6 years, plus the 18-month allowance of SR 3.0.2, as measured from January 27,2003, the HBRSEP Unit No. 2 1 Amendment No. 219
APPENDIX B ADDITIONAL CONDITIONS date of the most recent successful tracer gas test, or within the next 18 months if the time period since the most recent successful tracer gas test is greater than 6.years.
(b) The first performance of the periodic assessment of CRE habitability, TS 5.5.17.c.(ii), shall be within the next 9 months.
(c) The first performance of the periodic measurement of CRE pressure, TS 5.5.17.d, shall be within 18 months, plus the 138 days allowed by SR 3.0.2, as measured from the date of the most recent successful pressure measurement test.
HBRSEP Unit No. 2 2 Amendment No. 219