ML081750333
| ML081750333 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 07/25/2008 |
| From: | Dyer J NRC/NRR/ADRO/DORL/LPLII-2 |
| To: | Waldrep B Carolina Power & Light Co |
| SABA F, NRR/DORL/LPLI-2, 415-1453 | |
| Shared Package | |
| ML081750293 | List: |
| References | |
| TAC MD6336, TAC MD6337 | |
| Download: ML081750333 (19) | |
Text
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 248, are hereby incorporated in the license. Carolina Power & Light Company shall operate the facility in accordance with the Technical Specifications.
For Surveillance Requirements (SRs) that are new in Amendment 203 to Renewed Facility Operating License DPR-71, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 203. For SRs that existed prior to Amendment 203, 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 203.
(a) Effective June 30, 1982, the surveillance requirements listed below need not be completed until July 15, 1982. Upon accomplishment of the surveillances, the provisions of Technical Specification 4.0.2 shall apply.
Specification 4.3.3.1, Table 4.3.3-1, Items 5.a and 5.b (b) Effective July 1, 1982, through July 8, 1982, Action statement "a" of Technical Specification 3.8.1.1 shall read as follows:
ACTION:
- a. With either one offsite circuit or one diesel generator of the above required A.C. electrical power sources inoperable, demonstrate the OPERABILITY of the remaining A.A. sources by performing Surveillance Requirements 4.8.1.1.1.a and 4.8.1.1.2.a.4 within two hours and at least once per 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> thereafter; restore at least two offsite circuits and four diesel generators to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> and in COLD SHUTDOWN within the following 24 hours1 days <br />0.143 weeks <br />0.0329 months <br />.
(3) Deleted by Amendment No. 206.
D. The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans, including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: "Physical Security Plan, Revision 2," and "Safeguards Contingency Plan, Revision 2," submitted by letter dated May 17, 2006, and "Guard Training and Qualification Plan, Revision 0,"
submitted by letter dated September 30, 2004.
Renewed License No. DPR- 71 Amendment No. 248
- 3. Additional Conditions The Additional Conditions contained in Appendix B, as revised through Amendment No. 248, are hereby incorporated into this license. Carolina Power & Light Company shall operate the facility in accordance with the Additional Conditions.
FOR THE NUCLEAR REGULATORY COMMISSION IRA/
J. E. Dyer, Director Office of Nuclear Reactor Regulation Attachments:
- 1. Unit 1 - Technical Specifications - Appendices A and B Date of Issuance: June 26, 2006 Renewed License No. DPR-71 Amendment No. 248
CREV System 3.7.3 3.7 PLANT SYSTEMS 3.7.3 Control Room Emergency Ventilation (CREV) System LCO 3.7.3 Two CREV subsystems shall be OPERABLE.
-NOTE The main control room envelope (CRE) boundary may be opened intermittently under administrative control.
APPLICABILITY: MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel (OPDRVs).
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CREV subsystem A.1 Restore CREV subsystem 7 days inoperable for reasons other to OPERABLE status.
than Condition B.
B. One or more CREV B.1 Initiate action to Immediately subsystems inoperable due implement mitigating to inoperable CRE Boundary actions.
in Mode 1,2, or 3.
AND B.2 Verify mitigating actions 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> ensure CRE occupant exposures to radiological, chemical, and smoke hazards will not exceed limits.
AND B.3 Restore CRE boundary to 90 days Operable status.
(continued)
Brunswick Unit 1 3.7-11 Amendment No. 248
CREV System 3.7.3 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C. 1 Be in MODE 3. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> Ii associated Completion Time of Condition A or B not met AND in MODE 1, 2, or 3. I C.2 Be in MODE 4. 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> OR Two CREV subsystems inoperable in MODE 1, 2, or 3 for reasons other than Condition B.
D. Required Action and ----------------- 'NOTE -----------
associated Completion Time LCO 3.0.3 is not applicable.
of Condition A not met during movement of irradiated fuel assemblies in D.1 Place OPERABLE CREV Immediately I the secondary containment, subsystem in during CORE radiation/smoke protection ALTERATIONS, or during mode.
OR D.2.1 Suspend movement of Immediately irradiated fuel assemblies in the secondary containment.
AND D.2.2 Suspend CORE Immediately I ALTERATIONS.
AND D.2.3 Initiate action to suspend Immediately I OPDRVs.
(continued)
Brunswick Unit 1 3.7-12 Amendment No. 248
CREV System 3.7.3 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME E. Two CREV subsystems ------------- NOTE -----------
inoperable during movement LCO 3.0.3 is not applicable.
of irradiated fuel assemblies ---------------------------
in the secondary containment, during CORE E.1 Suspend movement of Immediately ALTERATIONS, or during irradiated fuel assemblies in OPDRVs. the secondary containment.
OR AND One or more CREV E.2 Suspend CORE Immediately subsystems inoperable due ALTERATIONS.
to an inoperable CRE boundary during movement AND of irradiated fuel assemblies in the secondary E.3 Initiate action to suspend Immediately containment, during CORE OPDRVs.
ALTERATIONS, or during OPDRVs.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 Operate each CREV subsystem for > 15 continuous 31 days minutes.
SR 3.7.3.2 Perform required CREV filter-testing in accordance In accordance with with the Ventilation Filter Testing Program (VFTP). the VFTP (continued)
Brunswick Unit 1 3.7-13 Amendment No. 248
CREV System 3.7.3 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.7.3.3 Perform required CRE unfiltered air inleakage testing In accordance with in accordance with the Control Room Envelope the Control Room Habitability Program. Envelope Habitability Program SR 3.7.3.4 Verify each CREV subsystem actuates on an actual or 24 months simulated initiation signal.
Brunswick Unit 1 3.7-14 Amendment No. 248
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.12 Primary Containment Leakage Rate Testing Program (continued)
- b. Air lock testing acceptance criteria are:
- 1) Overall air lock leakage rate is
- 0.05 La when tested at > Pa.
- 2) For each air lock door, leakage rate is < 5 scfh when the gap between the door seals is pressurized to _>10 psig.
The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program frequencies.
5.5.13 Control Room Envelope Habitability Program A Control Room Envelope (CRE) Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Control Room Emergency Ventilation (CREV) System, CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke challenge. The program shall ensure that adequate radiation protection is provided to permit occupancy of the CRE under design basis accident (DBA) conditions without personnel receiving radiation exposures in excess of 5 rem TEDE for the duration of the accident. The program shall include the following elements:
- b. Requirements for maintaining the CRE boundary in its design condition including configuration control and preventive maintenance.
- c. Requirements for (i) 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.
- 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 subsystem of the CREV System, 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.
(continued)
Brunswick Unit 1 5.0-17 Amendment No. 248 1
Programs and Manuals 5.5 5.5 Programs and Manuals Control Room Envelope Habitability Program (continued)
- 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. Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of CRE occupants to these hazards will be within the assumptions in the licensing basis.
- 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.
Brunswick Unit 1 5.0-17a Amendment No.248 I
APPENDIX B Additional Conditions Amendment Additional Conditions Implementation Number Date 203 The license is authorized to relocate certain This amendment is requirements included in Appendix A and the effective immediately former Appendix B to licensee-controlled and shall be documents. Implementation of this amendment implemented within 90 shall include the relocation of these days of the date of this requirements to the appropriate documents, as amendment.
described in the license's letters dated November 1, 1996, October 13, 1997, February 26, 1998, April 24, 1998, and May 22,1998 evaluated in the NRC staffs Safety Evaluation enclosed with this amendment.
248 Upon implementation of Amendment No. 248 As described in adopting TSTF-448, Revision 3, the paragraphs (a), (b), and determination of control room envelope (CRE) (c) of this Additional unfiltered air inleakage as required by SR Condition.
3.7.3.3, in accordance with TS 5.5.13.c.(i), the assessment of CRE habitability as required by Specification 5.5.13.c.(ii), and the measurement of CRE pressure as required by Specification 5.5.13.d, shall be considered met. Following implementation:
(a) The first performance of SR 3.7.3.3, in accordance with Specification 5.5.13.c.(i),
shall be within the specified Frequency of 6 years, plus the 18-month allowance of SR 3.0.2, as measured from June 11, 2004, the date of the most recent successful tracer gas test.
(b) The first performance of the periodic assessment of CRE habitability, Specification 5.5.13.c.(ii), shall be within the next 9 months.
(c) The first performance of the periodic measurement of CRE pressure, Specification 5.5.13.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.
Brunswick Unit 1 App. B-1 Amendment No. 248 I
as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use in amounts as required any byproduct, source, and special nuclear materials without restriction to chemical of physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; (5) Pursuant to the Act and 10 CFR Parts 30 and 70 to posses, but not separate, such byproduct and special nuclear materials as may be produced by the operation of Brunswick Steam Electric Plant, Unit Nos. 1 and 2, and H. B. Robinson Steam Electric Plant, Unit No. 2 (6) Carolina Power & Light Company shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility and as approved in the Safety Evaluation Report dated November 22, 1977, as supplemented April 1979, June 11, 1980, December 30, 1986, December 6, 1989, July 28, 1993, and February 10, 1994 respectively, subject to the following provision:
The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
C. This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; 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:
(1) Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 2923 megawatts (thermal).
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 276 , are hereby incorporated in the license. Carolina Power & Light Company shall operate the facility in accordance with the Technical Specifications.
Renewed License No. DPR-62 Amendment No. 276
- 3. Additional Conditions The Additional Conditions contained in Appendix B, as revised through Amendment No. 276, are hereby incorporated into this license. Carolina Power & Light Company shall operate the facility in accordance with the Additional Conditions.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
J. E. Dyer, Director Office of Nuclear Reactor Regulation Attachments:
- 1. Unit 2 - Technical Specifications - Appendices A and B Date of Issuance: June 26, 2006 Renewed License No. DPR-62 Admentment No. 276
CREV System 3.7.3 3.7 PLANT SYSTEMS 3.7.3 Control Room Emergency Ventilation (CREV) System LCO 3.7.3 Two CREV subsystems shall be OPERABLE.
NOTE ----------------------------------------
The main control room envelope (CRE) boundary may be opened intermittently under administrative control.
APPLICABILITY: MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel (OPDRVs).
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CREV subsystem A.1 Restore CREV subsystem 7 days inoperable for reasons other to OPERABLE status.
than Condition B.
B. One or more CREV B.1 Initiate action to Immediately subsystems inoperable due implement mitigating to inoperable CRE Boundary actions.
in Mode 1,2, or 3.
AND B.2 Verify mitigating actions 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> ensure CRE occupant exposures to radiological, chemical, and smoke hazards will not exceed limits.
AND B.3 Restore CRE boundary to 90 days Operable status.
(continued)
Brunswick Unit 2 3.7-11 Amendment No. 276
CREV System 3.7.3 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> I associated Completion Time I of Condition A or B not met AND in MODE 1, 2, or 3. I C.2 Be in MODE 4. 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> OR Two CREV subsystems inoperable in MODE 1, 2, or 3 for reasons other than Condition B.
D. Required Action and ----------------- NOTE -----------
associated Completion Time LCO 3.0.3 is not applicable.
of Condition A not met during movement of irradiated fuel assemblies in D.1 Place OPERABLE CREV Immediately the secondary containment, subsystem in during CORE radiation/smoke protection ALTERATIONS, or during mode.
OR D.2.1 Suspend movement of Immediately irradiated fuel assemblies in the secondary containment.
AND D.2.2 Suspend CORE Immediately ALTERATIONS.
AND D.2.3 Initiate action to suspend Immediately OPDRVs.
(continued)
Brunswick Unit 2 3.7-12 Amendment No. 276
CREV System 3.7.3 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME E. Two CREV subsystems ------------- NOTE -----------
inoperable during movement LCO 3.0.3 is not applicable.
of irradiated fuel assemblies ---------------------------
in the secondary containment, during CORE E.1 Suspend movement of Immediately I ALTERATIONS, or during irradiated fuel assemblies in OPDRVs. the secondary containment.
OR AND One or more CREV E.2 Suspend CORE Immediately subsystems inoperable due ALTERATIONS.
to an inoperable CRE boundary during movement AND of irradiated fuel assemblies in the secondary E.3 Initiate action to suspend Immediately containment, during CORE OPDRVs.
ALTERATIONS, or during OPDRVs.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 Operate each CREV subsystem for > 15 continuous 31 days minutes.
SR 3.7.3.2 Perform required CREV filter testing in accordance with In accordance with the Ventilation Filter Testing Program (VFTP). the VFTP (continued)
Brunswick Unit 2 3.7-13 Amendment No. 276
CREV System 3.7.3 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.7.3.3 Perform required CRE unfiltered air inleakage testing in In accordance with accordance with the Control Room Envelope Habitability Program. the Control Room Envelope Habitability Program SR 3.7.3.4 Verify each CREV subsystem actuates on an actual or 24 months simulated initiation signal.
Brunswick Unit 2 3.7-14 Amendment No. 276
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.12 Primary Containment Leakage Rate Testing Program (continued)
- b. Air lock testing acceptance criteria are:
- 1) Overall air lock leakage rate is < 0.05 La when tested at > P,.
- 2) For each air lock door, leakage rate is < 5 scfh when the gap between the door seals is pressurized to > 10 psig.
The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program frequencies.
5.5.13 Control Room Envelope Habitability Program A Control Room Envelope (CRE) Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Control Room Emergency Ventilation (CREV) System, CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke challenge. The program shall ensure that adequate radiation protection is provided to permit occupancy of the CRE under design basis accident (DBA) conditions without personnel receiving radiation exposures in excess of 5 rem TEDE for the duration of the accident. The program shall include the following elements:
- b. Requirements for maintaining the CRE boundary in its design condition including configuration control and preventive maintenance.
- c. Requirements for (i) 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.
- 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 subsystem of the CREV System, 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.
(continued)
Brunswick Unit 2 5.0-17 Amendment No. 276 I
Programs and Manuals 5.5 5.5 Programs and Manuals Control Room Envelope Habitability Program (continued)
- 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. Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of CRE occupants to these hazards will be within the assumptions in the licensing basis.
- 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.
Brunswick Unit 2 5.0-17a Amendment No. 276 1
APPENDIX B Additional Conditions Amendment Number Additional Conditions Implementation Date 233 The licensee is authorized to relocate certain This amendment is requirements included in Appendix A and the effective immediately former Appendix B to licensee-controlled and shall be documents. Implementation of this amendment implemented within shall include the relocation of these requirements 90 days of the date of to the appropriate documents, as described in the this amendment.
licensee's letters dated November 1, 1996, October 13, 1997, February 26, 1998, April 24, 1998, and May 22, 1998, evaluated in the NRC staffs Safety Evaluation enclosed with this amendment.
233 The End-Of-Cycle Recirculation Pump Trip system This amendment is instrumentation shall be maintained inoperable effective immediately (i.e., manually bypassed) during Mode 1, when and shall be thermal power is greater than or equal to 30% implemented within rated thermal power. Implementation of this 90 days of the date of amendment shall include this condition, as this amendment.
described in the licensee's letter dated March 13, 1998, evaluated in the NRC staffs Safety Evaluation enclosed with this amendment.
246 The licensee shall consistent with the applicable Prior to startup provisions of the BWR Owners' Group Report following the Unit 2 NEDC-31858P, Revision 2, as approved in the Cycle 16 Refueling NRC staff's Safety Evaluation dated March 3, Outage.
1999, completed the seismic verification walkdowns and modifications necessary to ensure seismic ruggedness of the alternate leakage treatment (ALT) piping and appendages.
246 The licensee shall, consistent with the licensee's Prior to startup letter dated September 27, 2001 (i.e., Serial: following the Unit 2 BSEP 01-0112), include ALT path motor-operated Cycle 16 Refueling valves MS-F038A, MS-F038B, MS-F038C, Outage.
MS-F038D, and MVD-F021 in an augmented inservice testing program.
251 The licensee shall include ALT path check valve Prior to startup MVD-V5009 in the facility check valve program. following the Unit 2 Cycle 16 Refueling Outage.
Brunswick Unit 2 App. B-1 Amendment No. 276
APPENDIX B Additional Conditions Amendment Number Additional Conditions Implementation Date 276 Upon implementation of Amendment No. 276 As described in adopting TSTF-448, Revision 3, the determination paragraphs (a), (b),
of control room envelope (CRE) unfiltered air and (c) of this inleakage as required by SR 3.7.3.3, in accordance Additional Condition.
with TS 5.5.13.c.(i), the assessment of CRE habitability as required by Specification 5.5.13.c.(ii), and the measurement of CRE pressure as required by Specification 5.5.13.d, shall be considered met. Following implementation:
(a) The first performance of SR 3.7.3.3, in accordance with Specification 5.5.13.c.(i),
shall be within the specified Frequency of 6 years, plus the 18-month allowance of SR 3.0.2, as measured from June 11, 2004, the date of the most recent successful tracer gas test.
(b) The first performance of the periodic assessment of CRE habitability, Specification 5.5.13.c.(ii), shall be within the next 9 months.
(c) The first performance of the periodic measurement of CRE pressure, Specification 5.5.13.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.
brunswick Unit 2 App. B-2 Amendment No. 276 I