ML20113B708
| ML20113B708 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 06/24/1996 |
| From: | SOUTHERN NUCLEAR OPERATING CO. |
| To: | |
| Shared Package | |
| ML20113B694 | List: |
| References | |
| NUDOCS 9606270273 | |
| Download: ML20113B708 (7) | |
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l ATTACHMENT 2 Proposed Changes Page Technical Specifications Marked-up Pages Technical Specifications Typed Pages r
9606270273 960624 PDR ADOCK 05000348 PDR P
FNP Unit 1 Technical Specification Pages Page Change Instnictions Page 3/4 3-14 Replace l
l 4
TABLE a.3 1 (Centinued)
TABLE NOTATION Witn the reactor trip system oreakers closed and the control rod orive system capable of rod witndrawal.
(1) - If not performed in previous 7 days.
(2) - Heat balance only, above 15% of RATE 0 THERMAL POWER. Adjust enannel if aosolute difference is greater tnan 2 percent.
(3) - Compare incore to excore axial flux difference every 31 EFPO.
Neca11 orate if tne aosolute difference is greater enan or equal to 3 percent.
(4) - Manual ESF functional input check every 18 montns.d MI 45 v*I fu % bkeve pw.S c We ~4 % W4 u not v sy+e Eacn train or logic c$nannel shall be tested at least every 62 p
(b) -
days on a STAGGERED TEST BASIS.
(6) - Neutron detectors may be excluded from CHANNEL CALIBRATION.
(7) - Below the 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 that eacn cnannel indicates a turoine trip prior to latcning the turoine and indicates no turbine trip prior to P-9.
er (10) - If not performed in tne previous 31 days.
(11) - Independently verify OPERABILITY of the undervoltage and shunt trip circuitry for the Manual Reactor Trip Function.
(12) - verify reactor trip breater and reactor trip L, pass breaker open upon actuation of eacn Main Control Board handswiten.
(13) - Local manual snunt trip prior to placing breaker in service.
Local manual undervoltage trip prior to placing breaker in service.
l14) - Undervoltage trip via Reactor Protection System.
- .3) - Local manual shunt trip.
l FAdLEY - UNIT 1 3/4 3 14 AMENOMENT NO.25.#2.8% 67 O
e t-
i TABLE 4.3-1 (Continued)
TABLE NOTATION With the reactor trip system breakers closed and the control 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.
(7)
Below the 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 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 l
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.
t 0
FNP Unit 2 Technical Specification Pages Page Change Instructions Page 3/4 3-14 Replace l
TABLE a.3-1 (continued) f'.'
TABLE NOTATION i
i i
With the reactor trip system breakers closed and the control roc drive system capaole of roo witndetwal.
1 (1) - If not performed in previous 7 days.
4 i
(2) - Heat balance only, above 155 of RATED THERMAL POWER. Adjust, j
channel if absolute difference is greater than 2 percent.
i A
(3) - Cogare incore to encore axial flux difference.every 31 EFpO.
{
Recalibrate if the absolute difference is greater than or equal j
to 3 percent.
(4) - Manual ESF functional input eneck every 18 months.
& A stava.A.p4 A 4, +W wM M nW un% mt McAe 3 ch.
(5) -
Each train or logic cnannel shall be tested at least every 62 days on a STAGGERED TEST BASIS.
4 l
(5) - Neutron detectors may be excluded from CHANNEL CALIBRATION.
s (7) - Selow the P-6 (Block of Source Range Reactor Trip) setpoint.
(8) - Logic only, if not performed in previous 92 days.
i (9) - CHANNEL FUNCTIONAL TEST will consist of verifying that each channel indicates a turbine tMp prior to latening the turnine
/
ano indicates. no turnine trip prior to p-g.
e (10) - If nct parfc m d in the pr3vicus 31 days.
{
(11) - Independently verify OPERASILITY cf the urarve1tage and shunt
~
j trip circuitry for the Manual Reactor irtp Function..
'1 (12) - 'terify reactor trip breaker and reactor trip bypass breaker open i
upon actuation of each Main Control Board handswitch.
i e
(13) - Local manual shunt trip prior to placing breaker in service.
4 Local manual undervoltage trip prior to placing breaker in service.
(la) - Undervoltage trip via Reactor Protection System.
(1:i) - Local manual shunt trip.
1 4
i j
j FARLEY - UNIT 2 3/4 3 14 AMDeMENT NO. 33, 31)Iy 2
0 a
1 TABLE 4.3-1 (Continued)
TABLE NOTATION With the reactor trip system breakers closed and the control 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)
Compar6 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 eleventh 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.
(7)
Below the 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 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 React or 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 2 3/4 3-14 AMENDMENT NO.