ML20113B708

Proposed Tech Specs for Unit 1 Cycle 14 & Unit 2 Cycle 11 Deleting SR for Manual SI Input to Reactor Trip Circuitry Until Next Unit Shutdown

ML20113B708
Person / Time
Site:	Farley
Issue date:	06/24/1996
From:	SOUTHERN NUCLEAR OPERATING CO.
To:
Shared Package
ML20113B694	List: ML20113B693 ML20113B708
References
NUDOCS 9606270273
Download: ML20113B708 (7)

Text

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l ATTACHMENT 2 l

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 I l

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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) - I Manual fu % bkeve ESF pw.Sfunctional c We ~4 % input p W4 check u not v every sy+e 18 montns.d MI 45 v*I -

(b) - Eacn train or logic c$nannel shall be tested at least every 62 days on a STAGGERED TEST BASIS.

1 (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

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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.

(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.

1 (4) -

Manual ESF functional input check every 18 months. For the l fourteenth operating cycle only, this test is not required until  !

the next Mode 3 entry. 1 (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. I l

(11) -

Independently verify OPERABILITY of the undervoltage and shunt I 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 i service.

(14) - Undervoltage trip via Reactor Protection System.

(15) -

Local manual shunt trip.

FARLEY-UNIT 1 .3/4 3-14 AMENDMENT NO.

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FNP Unit 2 Technical Specification Pages Page Change Instructions Page 3/4 3-14 Replace l

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• TABLE a.3-1 (continued) f'.' , , TABLE NOTATION i

i With the reactor trip system breakers closed and the control roc i

drive system capaole of roo witndetwal.

1 (1) - If not performed in previous 7 days.

4 i

j (2) - Heat balance only, above 155 of RATED THERMAL POWER. Adjust, channel if absolute difference is greater than 2 percent.

i A

{

(3) - Cogare incore to encore axial flux difference.every 31 EFpO.

j Recalibrate if the absolute difference is greater than or equal 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 4

days on a STAGGERED TEST BASIS.

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.

~

{

j (11) - Independently verify OPERASILITY cf the urarve1tage and shunt 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.

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j FARLEY - UNIT 2 3/4 3 14 AMDeMENT NO. 33, 31)Iy 2

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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.

(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.