ML18038A896
| ML18038A896 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 09/12/1994 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18038A893 | List: |
| References | |
| NUDOCS 9409140140 | |
| Download: ML18038A896 (4) | |
Text
CORRECTION TO LICENSE AMENOMENT NO.
129 FACILITY OPERATING LICENSE NO.
OPR-68 DOCKET NO. 50-296 Revise the Appendix.A Technical Specifications by removing the pages identified below and inserting the enclosed pages.
The corrections to the pages are identified by the marginal lines.
Remove Insert 3.9/4.9-9 3.9/4.9-10 3.9/4.9-9 3.9/4.9-10 ENCLOSURE 9409140140 940912 PDR ADOCK 05000259 P
'PDR
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- 3. 9. B'.
Eg~mgg t 4.9.B.
3.
From and after the date that the 4-kV bus tie board becomes inoperable, REACTOR POWER OPERATION is permissible indefinitely provided'ne of the required offsite power sources is not supplied from the 161-kV system through the bus tie board.
3.
When a required offsite power source is unavai.lable because the 4-kV bus tie board or a start bus i.s INOPERABLE, all unit 3 diesel generators shall be demonstrated OPERABLE within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and power availabi.lity for the associated boards shall be verified within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter.
The remaining offsite source and associated buses shall be checked to be energized daily.
4.
When one unit 3 4-kV shutdown board is INOPERABLE, continued REACTOR POWER OPERATION is permissible for a period of 5 days provided that, 2 offsite power sources are available as specified in 3.9.A.l.c and the remaining uni.t 3 4-kV shutdown 'boards and associated diesel generators, CS, RHR (LPCI and containment cooling)
- systems, and all unit 3
'80-V emergency power boards are OPERABLE. If this requi.rement cannot be
- met, an orderly shutdown shall be initi.ated and the reactor shall be shut down and in the COLD SHUTDOWN CONDITION within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
4.
When one unit 3 4-kV shutdown board is found to be INOPERABLE, all diesel generators associated with the remaining 4-kV shutdown boards shall be demon-strated to be OPERABLE within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and power availabili.ty for the remaining 4-kV shutdown boards shall be verified wi.thin 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 8
hours thereafter.
BFN Unit 3 3.9/4.9-9 AMENOMEMTgo. 12 9
- 3. 9,B.
4.9.B.
5 ~
From and,.after the date that one of the 480-V, diesel auxiliary boards becomes INOPERABLE, REACTOR POWER OPERATION is permissible for a period of 5 days.
5.
When one 480-V diesel auxiliary board is found INOPERABLE, each unit 3 diesel shall be verified OPERABLE within 24
- hours, and power availability for the remaining diesel auxiliary board shall be verified within 1
'hour and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter.
6.
From and after the date that the 250-V shutdown board 3EB battery or one of the three 250-V unit batteries and/or its associated battery board is found to be INOPERABLE for any reason,.
continued REACTOR POWER OPERATION is permissible during the succeeding seven days.
Except for routine surveillance testing, the NRC shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the situation, the precautions to be taken during this period, and the plans to return the failed component to an OPERABLE state.
BFN Unit 3 7.
When one division of the logic system is INOPERABLE, continued REACTOR POWER OPERATION is permissible under. this condition for seven days, provided'he CSCS requirements listed in Specification 3.9.B.2 are satisfied.
The NRC shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the situation, the precautions to be taken during this period, and the plans to return the failed component to an OPERABLE state.
3.9/4.9-10 AMENDMBfTNO. y p g
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