ML20113A814

Proposed Tech Specs Table 4.3-1

ML20113A814
Person / Time
Site:	Farley
Issue date:	06/21/1996
From:	SOUTHERN NUCLEAR OPERATING CO.
To:
Shared Package
ML20113A813	List: ML20113A810 ML20113A814
References
NUDOCS 9606250352
Download: ML20113A814 (6)

Text

. . . _ . . . . . _ . . . - . . . . . - - . . ~ - . . . . . . . - . - - . . - . - _ . _ _ _ . - . _ -

l i

I I

Attachment 2  :

1 Marked Uo Proposed Technical Specification Pages i

l l

i l

l I

i l

4 s

9606250352 960621 i PDR ADOCK 05000340 i P PDR i

f l

o

- 1

~

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 only, N4 its4 is nA rego cad ovM 4he. ntd Mac 3 enh ,

(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. l

~

+

FARLEY - UNIT 1 3/4 3-14 AMENDMENT NO.28,#2.8A 57 d

O

• 1

, 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 to 3 percent.if the absolute difference is greater than or equal l (4) -

l Manual ESF functional

%r %e elevenw .pr-% 3 input enect every 18a months. d l

de, onip &is w,sr.5 not m i va+il 4W M M' %

(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. /

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.

l

! 1 l

. 1 FARLEY - UNIT 2 3/4 3 14 AMEleMENT No. 33, nfy 1

i

f '}

. l l l l

1 l

Attachment 3 )

i l

Changed Technical Specification Pages l

1 i

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.

(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 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

I a

TABLE 4.3-1 (Continued)

TABLE NOTATION l With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal.

l l

(1) -

If not performed in provious 7 days.  !

l (2) -

Heat balance only, above 15% of RATED THERMAL POWER. Adjust channel if absolute dif ference is greater than 2 percent.

1 I

(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. l (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. 1 1

l l (15) -

Local manual shunt trip.

l i

r FARLEY-UNIT 2 3/4 3-14 AMENDMENT NO. 59