ML20113A814
| ML20113A814 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 06/21/1996 |
| From: | SOUTHERN NUCLEAR OPERATING CO. |
| To: | |
| Shared Package | |
| ML20113A813 | List: |
| References | |
| NUDOCS 9606250352 | |
| Download: ML20113A814 (6) | |
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1 Marked Uo Proposed Technical Specification Pages i
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TABLE a.3-1 (Centinuedl TABLE NOTATION Witn the reactor trip system creaters closed and tne control red crive system capaDie of rod witndrawal.
(1) - If not performed in pr.evious f days.
(2) - Heat talance only, aoove 15% of RATED THERMAL POWER. Adjust channel if assolute dif ference is greater tnan 2 percent.
(3) - Compare incore to excore axial flux difference every 31 EFPO.
decaliorate if tne absolute difference is greater tnan or equal to 3 percent.
(4) - Manual ESF functional input check every 18 montns fbe +k 4,4eer4k.per.Ay ey<4 onl, N4 its4 is nA rego cad ovM 4he. ntd Mac 3 enh,
y (b) - Eacn train or logic cnannel shall be tested at least every 62 days on a STAGGERED TEST BASIS.
(6) - Neutron detectors may be excluded f rom CHANNEL CALIBRATION.
(7) - Below t9e P-6 (Block of Source Range Reactor Trip) setpoint.
(8) - Logic only, if not performed in previous 92 days.
(9) - CHANNEL FUNCTIONAL TEST will consist of, verifying tnat eacn cnannel indicates a turoine trip prior to latcning the turoine and indicates no turnine trip prior to P-9.
3 (10) - If not performed in tne previous 31 days.
l (11) - Independently verify OPERABILITY of the undervoltage and shunt trip circuitry for the Manual Reactor Trip Function.
(12) - verify reactor trip breamer and reactor trip bypass breaker open upon actuation of each Main Control Board handswiten.
(13) - Local manual snunt trip prior to placing breater in service.
Local manual undervoltage trip prior to placing breaker in service.
.'i') - Undervoltage trip via Reactor Protection System.
- .3) - Local manual snunt trip.
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FARLEY - UNIT 1 3/4 3-14 AMENDMENT NO.28,#2.8A 57 d
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TA8LE 4.3 1 (Continued 1 TABLE NOTATION l
Witn the reactor trip system breakers closed and the control roo drive system capaole of rod witndetwal.
(1) -
If not performed in previous 7 days.
(2) - Heat balance only, aoove 155 of RATED THERMAL POWER. Adjust enannel if absolute difference is greater than 2 percent.
(3) -
Cogare incore to escore axial flux difference.every 31 EFPO.
Recalibrate if the absolute difference is greater than or equal to 3 percent.
l (4) -
Manual ESF functional input enect every 18 months. d l
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(5) - Each train or logic enannel sna11 be tested at least every 62 days on a STAGGERED TEST BASIS.
(ti) - Neutron detectors may be excluded from CHANNEL CALIBRATION.
(7) - Selow the P-4 (Block of Source Range Reactor Trip) setpoint.
(8) - Logic only, if not performed in previous 92 days.
l (9) - CHANNEL FUNCTIONAL TEST will consist of verifying that each l
channel indicates a turnine trip prior to latening the turnine and indicates no turnine trip prior to p.9.
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e (10) -
If. ct parfcmad in the przviou: 31 days.
(11) - Independently verify OpERASILITY of the undervoltage and saunt trip circuitry for the Manual Reactor Trip Function..
(12) - Verify reactor trip breaker and reactor trip bypass Dreater open upon actuatton of each Main Control Board handswitra.
(13) - Local manual shunt trip prior to placing breaker in service.
Local manual undervoltage trip prior to placing breaker in 4
service.
(la) - Undervoltage trip via Reactor Protection System.
(1:i) - Local manual shunt trip.
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FARLEY - UNIT 2 3/4 3 14 AMEleMENT No. 33, nfy 1
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Changed Technical Specification Pages l
e TABLE 4.3-1 (Continued)
TABLE NOTATION
- With the reactor trip system breakers closed and the controi rod drive system capable of rod withdrawal.
(1)
If not performed in previous 7 days.
(2)
Heat balance only, above 15% of RATED THERMAL POWER.
Adjust channel if absolute difference is greater than 2 percent.
(3)
Compare incore to excore axial flux difference every 31 EFPD.
Recalibrate if the absolute difference is greater than or equal to 3 percent.
(4)
Manual ESF functional input check every 18 months.
For the fourteenth operating cycle only, this test is not required until the next Mode 3 entry.
(5)
- Each train or logic channel shall be tested at least every 62 days on a STAGGERED TEST BASIS.
(6)
- Neutron detectors may be excluded from CHANNEL CALIBRATION.
Below the P-6 (Block of Source Range Reactor Trip) setpoint.
(7)
(8)
Logic only, if not performed in previous 92 days.
(9)
CHANNEL FUNCTIONAL TEST will consist of verifying that each channel indicates a turbine trip prior to latching the turbine and indicates no turbine trip prior to P-9.
(10)
If not performed in the previous 31 days.
(11)
Independently verify OPERABILITY of the undervoltage and shunt trip circuitry for the Manual Reactor Trip Function.
(12) - Verify reactor trip breaker and reactor trip bypass breaker open upon actuation of each Main Control Board handswitch.
(13) - Local manual shunt trip prior to placing breaker in service.
Local manual undervoltage trip prior to placing breaker in service.
(14) - Undervoltage trip via Reactor Protection System.
(15) - Local manual shunt trip.
FARLEY-UNIT 1 3/4 3-14 AMENDMENT NO. 67
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TABLE 4.3-1 (Continued)
TABLE NOTATION With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal.
l If not performed in provious 7 days.
(1) l (2)
Heat balance only, above 15% of RATED THERMAL POWER.
Adjust channel if absolute dif ference is greater than 2 percent.
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(3)
Compare incore to excore axial flux difference every 31 EFPD.
Recalibrate if the absolute difference is greater than or equal l
to 3 percent.
l (4)
Manual ESF functional input check every 18 months.
For the i
l eleventh operating cycle only, this test is not required until the next Mode 3 entry.
l (5)
Each train or logic channel shall be tested at least every 62 l
days on a STAGGERED TEST BASIS.
l (6)
Neutron detectors may be excluded from CHANNEL CALIBRATION.
l (7)
Below the P-6 (Block of Source Range Reactor Trip) setpoint.
l (8)
Logic only, if not performed in previous 92 days.
(9)
CHANNEL FUNCTIONAL TEST will consist of verifying that each j
channel indicates a turbine trip prior to latching the turbine l
and indicates no turbine trip prior to P-9.
(10)
If not performed in the previous 31 days.
(11)
Independently verify OPERABILITY of the undervoltage and shunt trip circuitry for the Manual Reactor Trip Function.
(12)
Verify reactor trip breaker and reactor trip bypass breaker I
open upon actuation of each Main Control Board handswitch.
(13)
Local manual shunt trip prior to placing brsaker in service.
Local manual undervoltage trip prior to placing breaker in service.
(14)
Undervoltage trip via Reactor Protection System.
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(15)
Local manual shunt trip.
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r FARLEY-UNIT 2 3/4 3-14 AMENDMENT NO. 59