ML062500080
| ML062500080 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 09/01/2006 |
| From: | NRC/NRR/ADRO/DORL/LPLII-1 |
| To: | |
| Gratton C, NRR/DORL, 415-1055 | |
| Shared Package | |
| ML062360588 | List: |
| References | |
| TAC MC5863, TAC MC5864 | |
| Download: ML062500080 (7) | |
Text
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.1.45 and the Environmental Protection Plan contained inAppendix B, both of which are attached hereto, are hereby incorporated into this license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3) Southern Nuclear Operating Company shall be capable of establishing containment hydrogen monitoring within 90 minutes of initiating safety injection following a loss of coolant accident.
(4) DELETED (5) DELETED (6) DELETED (7) DELETED (8) DELETED (9) DELETED (10) Additional Conditions The Additional Conditions contained in Appendix D,as revised through Amendment No. 102, are hereby incorporated into this license. Southern Nuclear shall operate the facility inaccordance with the Additional Conditions.
D. The facility requires exempfions from certain requirements of 10 CFR Part 50 and 10 CFR Part 70.
These include (a) an exemption from the requirements of 10 CFR 70.24 for two criticality monitors around the fuel storage area, and (b)an exemption from the requirements of Paragraph Ill.D.2(b)(ii) of Appendix J of 10 CFR 50, the testing of containment air locks at times when containment integrity is not required. The special circumstances regarding exemption b are identified inSection 6.2.6 of SSER 5.
An exemption was previously granted pursuant to 10 CFR 70.24. The exemption was granted with NRC materials license No. SNM-1967, issued August 21, 1986, and relieved GPC from the requirement of having a criticality alarm system. GPC and Southern Nuclear are hereby exempted from the criticality alarm system provision of 10 CFR 70.24 so far as this section applies to the storage of fuel assemblies held under this license.
These exemptions are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security. The exemptions in items b and c above are granted pursuant to 10CFR 50.12. With Amendment No. 145 License No. NPF-68
C. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I 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.
(1) Maximum Power Level Southern Nuclear is authorized to operate the facility at reactor core power levels not in excess of 3565 megawatts thermal (100 percent power) in accordance with the conditions specified herein.
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A,as revised through Amendment No. 125 and the Environmental Prolection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
The Surveillance Requirements (SRs) contained in the Appendix A Technical Specifications and listed below are not required to be performed immediately upon implementation of Amendment No. 74. The SRs listed below shall be successfully demonstrated prior to the time and condition specified below for each:
a) DELETED b) DELETED c) SR 3.8.1.20 shall be successfully demnonstrated at the first regularly scheduled performance after implementation of this license amendment.
(3) Southern Nuclear Operating Company shall be capable of establishing containment hydrogen monitoring within 90 minutes of initiating safety injection following a loss of coolant accident.
(4) Additional Conditions The Additional Conditions contained in Appendix D,as revised through Amendment No. 80, are hereby incorporated into this license. Southern Nuclear shall operate the facility in accordance with the Additional Conditions.
D. The facility requires exemptions from certain requirements of 10 CFR Part 50 and 10 CFR Part 70.
These include (a) an exemption from the requirements of 10 CFR 70.24 for two criticality monitors around the fuel storage area, and (b) an exemption from the requirements of Paragraph III.D.2(b)(ii) of Appendix J of 10 CFR 50, the testing of containment air locks at times when containment integrity is not required. The special circumstances regarding exemption b are identified in Section 6.2.6 of SSER 8.
Amendment No.1 25 License No. NPF-81
RTS Instrumentation 3.3.1 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME R. One or more channels R.1 Verify interlock is in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inoperable, required state for existing unit conditions.
OR R.2 Be in MODE 3. 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> S. One or more channels S.1 Verify Interlock is'in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inoperable, required state for existing unit conditions.
OR S.2 Be in MODE 2. 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> T. One RTB train NOTE--
inoperable. One train may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing, provided the other train is OPERABLE.
T.1 Restore train to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> OPERABLE status.
OR T.2 Be in MODE 3. 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> (continued)
VogUe Units 1 and 2 3.3.1-7 Amendment No.145 (Unit 1)
Amendment No. 2 5 (Unit 2)
I 1
RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.3.1.4 This Surveillance must be performed on the reactor trip bypass breaker prior to placing the bypass breaker in service.
Perform TADOT. 62 days on a STAGGERED TEST BASIS SR 3.3.1.5 Perform ACTUATION LOGIC TEST. 92 days on a I STAGGERED TEST BASIS SR 3.3.1.6 NOTES
- 1. Not required to be performed until 7 days after THERMAL POWER is Žt 75% RTP.
- 2. Neutron detectors are excluded from CHANNEL CALIBRATION.
Calibrate excore channels to agree with Incore 92 EFPD detector measurements.
SR 3.3.1.7 NOTES
- 1. For the Source Range Instrumentation this surveillance shall Include verification that Interlocks P-6 and P-1 0 are in their required state for existing unit conditions.
- 2. Not required to be performed for Source Range Instrumentation prior to entering MODE 3 from MODE 2 until 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after entry Into MODE 3.
Perform COT. 184 days I (continued)
Vogtle Units I and 2 3.3.1-10 Amendment No.145 (Unit 1)
Amendment No1 25 (Unit 2) i °
ESFAS Instrumentation 3.3.2 SURVEILLANCE REQUIREMENTS S---NOTE-----------
Refer to Table 3.3.2-1 to determine which SRs apply for each ESFAS Function.
SURVEILLANCE FREQUENCY SR 3.3.2.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.2.2 Perform ACTUATION LOGIC TEST. 92 days on a STAGGERED TEST BASIS SR 3.3.2.3 Perform MASTER RELAY TEST. 92 days on a STAGGERED TEST BASIS SR 3.3.2.4 Perform COT. 184 days I 18 months SR 3.3.2.5 Perform SLAVE RELAY TEST.
SR 3.3.2.6 .. .. . ..-
Verification of setpoint not required for manual initiation functions.
Perform TADOT. 18 months (continued)
Vogtle Units I and 2 3.3.2-7 Amendment No.145 (Unit 1)
Amendment No.125 (Unit 2)
Containment Ventilation Isolation Instrumentation
.3.3.6 SURVEILLANCE REQUIREMENTS K^ nfrt
r~LJ I Refer to Table 3.3.6-1 to determine which SRs apply for each Containment Purge and Exhaust Isolation Function.
SURVEILLANCE FREQUENCY SR 3.3.6.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.6.2 Perform ACTUATION LOGIC TEST. 92 days on a STAGGERED TEST BASIS I
SR 3.3.6.3 Perform MASTER RELAY TEST. 92 days on a STAGGERED TEST BASIS SR 3.3.6.4 Perform COT. 92 days SR 3.3.6.5 Perform SLAVE RELAY TEST. 18 months SR 3.3.6.6 NOTE-Verification of setpoint not required.
Perform TADOT. 18 months SR 3.3.6.7 Perform CHANNEL CALIBRATION. 18 months SR 3.3.6.8 Verify RESPONSE TIMES are within limits. 18 months on a STAGGERED TEST BASIS Vogtle Units 1 and 2 3.3.6-4 Amendment NoI.45 (Unit 1)
Amendment No. 25 (Unit 2)
High Flux at Shutdown Alarm 3.3.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY
NOTE------
Not required to be performed prior to entering MODE 3 from MODE 2 until 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after entry into MODE 3.
SR 3.3.8.1 Perform COT. 184 days I SR 3.3.8.2 Perform CHANNEL CALIBRATION. 18 months Vogtle Units 1 and 2 3.3.8-2 Amendment No.145 (Unit 1)
Amendment No.1225 (Unit 2)