ML17324B119

Proposed Tech Specs Re Extension of Surveillances Performed During Shutdown

ML17324B119
Person / Time
Site:	Cook
Issue date:	10/31/1986
From:	INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17324B118	List: ML17324B117 ML17324B119
References
NUDOCS 8611070303
Download: ML17324B119 (11)

Text

Attachment 2 to AEP:NRC:0967R Proposed Revised Technical Specification Pages gggi070303 050003<~~'

'gl031'DR ADOCK PDR P

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nO0 pc TABLE 4.3-1 REACTOR TBII'YS'I'EN INSI'BIINI:N'I'A'I'lONSIIBVEII.LANCF BE UIBFHENTS 04 I'UNC'I'IONAI. tilll'I'

'Il ANN I'.I ~

('II I<< 'K ClI ANNI I.

Chl. I l<BA'I'

< IN CIIANNL'L FUN('.TIONAL TV.S'I'OOES IN HIIICII SUBVI I I.I.ANCE RE tll l<l:.I)

Manu<<l Be<<ct.<ir Trip A.

Sliunt 'I'ri(i Vu>>ct ion ll.

Un<lervol t<<ge 'I'rip Funct:ion N.h.

I'I.A.

W. h.

N.h.

S/U ( I )

S/U(>>

N.A.

N.A.

2.

I'<iwc <

l<<<ng<ti Neutron F)ux n( ), NA)

<<>><I Q (6) 2 Power B<<nge, Neut! <>>> Flux, tligl< I'osi Live l<<<te N.A.

B

((u) 1 ~

2 I owt. r i<ange, Neut'r<in I'lux, IIig1 ! Negative B<< t e N.h.

B (6) 1, 2

5.

I Ill.u'twire iate I<ange, Neutron Flux S/U (1) 2 and Source B<<ng>> i Neut

< o<l Vlux N and S/tl (1) 2 (7),

3 ( /),

4 and 5

7.

Overt.uxipe> at,ure Q 'I' I,

2 8.

Ove rpowe r 5'I',

2 Pn Pa Pressurizer Pressure--l.ow 10.

Pressurizer Pressure--Iligh 11.

Prc ssurizer W<<ter Level--lligl!

1, 2

1, 2

O 12.

I~ss ot Vlow Sin<lie l~cq>

+ The provisions of Specification 4.0.6 are applicable.

'I'AIII.I 4. 3-I

(( ont inuccl)

REACTOR Tlcl P.':Y."I'I:H INS'I'lcIIHIN'I'A1'ION Stll(VI ll.I.ANCE BE UIBFHFNTS FUNC'I'IONAI. IINI'II I ANNI I.

( III c'K c'IlhNNI;I.

CAI. I lclch'I'ON CIIANNEL FUNCTIONAL TEST HOllFS IN Wll]CH SIIBVI.1 LLANCE BEQII 1 lcED

]3.

I~ass col Flc>w - 1'wo I.oops Ic N.AD Steam Gene:r.cI c>>

W~t.<<r Level--

l.ow-l.ow I,

2 l5.

Steam/Yec!clwa(.<<rlow flismatclc and I.ow steam Ge<<orator Watt.r I.evel 16.

Under voltaic)e Beac tnr Cnc~l~nt Puml)s N.h.

] I.

Ilnclcrfrecluc ncy

Itc.~etcher c.oc I.cnt N h.

Puml)s lc

]II.

Turbi>>c Trifi A.

I.nw Flu>cl Ot 1

Inc:s..urc'l.

Turbicce Stctp V<<lvc Cl>>sur c:

N.h.

N ah.

N. h.

N.h.

S/U (1)

S/U (1) lc).

Safety

]ngectic~cr Input I rcm> l.'F 20.

Reactor Coolant Pump Ilreaker Position Tri>>

21.

Reactor 'I'rip Ilreaker A.

Shunt. Trip Yunct.inn B.

Undervoltacle Triii Fu>>ct.ion 22.

Au t.orna tic Trifi I.oclic Noh.

NBA.

N.h.

N.h.

N.h.

N.h.

N.A.

N.A.

N.A.

N.A H(4)

H(5) and S/U(l)

H(5) and S/U(1)

H(5)

],

2 N.h.

]

1 1,

2 2

+

The provisions of Specification 4.0.6 are applicable.

INSTRUMENTATION 3/4.3.2 ENGINEEREO SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2.1 The Engineered Safety Feature Actuation, System (ESFAS) instrumeta tion channels and interlocks shown in Table 3.3-3 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4 and with RESPONSE'IMES as shown in Table 3.3-5.

APPLICABILITY:

As shown in Table 3.3-3.

ACTION:

a.

with an ESFAS instrumentation channel trip setpoint less conserva-tive than the value shown in the Allowable Values column of Table.

3.3-4, declare the channel inoperable and apply the applicable ACTION requirement of Table 3.3-3 until the channel is restored to OPERABLE status with the trip setpoint adjusted consistent with the Trip Setpoint value.

b, With an ESFAS instrumentation channel inoperable, take the ACTION shown in Table 3.3-3.

SURVEILLANCE RE UIREMENTS 4.3.2.1.1 Each ESFAS instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the NODES and at the frequencies shown in Table 4.3-2.

4.3.2.1.2 The logic for the interlocks shall be demonstrated OPERABLE during the automatic actuation logic test.

The total interlock function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by interlock operation.

• 4.3.2.1.3 The ENGINEERED SAFETY FEATURES

RESPONSE

TIME of each ESFAS function shall be demonstrated to be within the limit at least once per 18 months.

Each test shall include at least one logic train such that both logic trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once per N times 18 months where N is the total number of redundant channels in a specific ESFAS function as shown in the "Total No. of Channels" Column of Table 3

~ 3 3e

• The provisions of Specification 4.0.6 are applicable.

0.

C.

COOK-UNIT 1

Amendment No.

TABLE 4.3-2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEti ItlSTRUMENTATION Cl C)

C) 7CI FUNCTIONAL UNIT l.

SAFETY INJECTION, TURBINE TRIP, FEED'ktATER ISOLATION, AND MOTOR DRIVEN AUXILIARYFEED'klATER PUtiPS CHAtlNEL CHECK CHANNEL CALIBRATION R

E I NCE RE U I EM TS CttANttEL FUNCTIONAL TEST MODES IN WHICH'URVEILLANCE RE UIRED O

a.

tlanua I Initiation b.

Automatic Actuation Logic c.

Containment Pressure-High d.

Pressurizer Pressure--Low e.

Differential Pressure Between Steam Lines--High f.

Steam Flow in-Two Steam Lines High Coincident with T

Low or Steam Line PN)sure Low 2.

COtlTAIt41EHT SPRAY a.

Manual Initiation b.

Automatic Actuation Logic c.

Containment Pressure High-High N.A.

H.A.

H.A.

H,A.

H.A.

H.A.

H.A.

tl.A.

ti(2)

M(3)

M(1)

N(2)

M(3) 1,2,3,4 1,2,3,4 1,2.3 1, 2, 3

1, 2, 3 1, 2, 3 1,2,3,4 1,2,3,4 1,2,3

+

The provisions of Spegification 4.0.6 are applicable.

TABLE 4.3-2 Continued ENGINEERED SAFETY FEATURE ACTUATION SYSTEH INSTRUHENTATION SURVEILLANCE RE UIREHENTS FUNCTIONAL UNIT 3.

CONTAINHENT ISOLATION a.

Phase "A" Isolation 1)

Hanual 2)

From Safety Injection Automatic Actuation Logic b.

Phase "0" Isolation 1)

Hanual 2)

Automatic Actuation Logic 3)

Containment Pressure--

High-High c.

Purge and Exhaust Isolation 1)

Hanual 2)

Containment Radio-ac t i v 1 ty-High CINNNEL CHECK N.A.

N.A.

N.A.

N.A.

N.A.

CHANNEL CALIBRATION N.A.

N.A.

N.A.

N.A.

N.A.

CHANNEL FUNCTIONAL TEST H(1)

H(2)

H(1)

H(2)

H(3)

H(l)

HODES IN WIIICH SURVE ILLANCE RE VIREO 1.2.3,4 1,2,3,4 1,2,3,4 1,2,3,4 1, 2, 3

1, 2, 3, 4

1, 2, 3, 4

+

The provisions of Specification 4.0.6 are applicable.

TA8LE 4.3-2 (Continued)

ENGINEERED SAFFTY FCAIURI ACTllhTION SYSTEM ItlSTRUHENThTION 3IIIIVHLLVNL'EII. IIIIIEMBT5 FUNCTIONAL UNIT 4.

STEAM LINE ISOLATION a.

Manual b.

Automatic Actuation Logic c.

Containment Pressure--

lligh-lligh d.

Steam Flow in Two Steam Lines--lligh Coincident with T -- Low-Low Pressure--Low CHANNI:I.

CHECK N.h.

CHANNEL CALIBRATION N.h.

tl.A.

CHANNEL F UNCT IOtlAL TEST M(2)

H(3)

MODES IN NIICII SURVEILLANCE RE UIRED 1,2,3 1,2,3 1,2,3 1,2,3 5.

TURBINE TRIP AND FEEDWhll.R ISOlhl lON a.

Steam Generator Water l.eve 1--lligh-tligb 6.

MOTOR DRIVEN AUXILIARY FEE'DWA1ER I'UHPS a.

S team Genera tor Wa ter S

Leve1-- Low-Low b.

4 kv Dus Loss of Voltage 1,2,3 1,2,3 1, 2, 3

c.

Safety Injection d.

Loss of Hain Feed Pumps N.A.

N.A.

N.A.

N.A.

M(2) 1,2,3 1,2,3

+ The provisions of Specification 4.0.6 are applicable.

TABLE 4.3-2 Continued EtlGItlEERED SAFETY FEATURE ACTUATION SYSTEH ItlSTRUNENTATIOtl S

RVEILLANCE RE UIREllEtlTS FUtlCTIONAL UNIT CllAtlNEL CllLCK CIIAtlllEL CIILIBIIIITION CHANtlEL FUNCTIONAL TEST liODES IN WHICH SURVEILLANCE RE UI RED 7.

TURBINE DRIVEN AUXILIARYFEEDWATER PUHPS a.

Steam Generator Water Level--Low-Low 1,2,3 b.

Reactor Coolant Pump Bus Undervoltage 8.

LOSS OF POWER a.

4 kv Bus Loss of Voltage b.

4 kv Bus Loss of Vol tage N.A.

l,2,3 1,2,3,4 l,2,3,4 The provisions of Specification 4.0.6 are-applicable.

TABLE 4.3-6 REHOTE SllUTOOWN MONITORING INSTRUHENTATION YuuRiKHXnNE hs HliÃSH INSTRUHENT I.

Reactor Trip Breaker Indlcatlon 2.

Pressurizer Pressure 3.

l'ressurlzer Level Steam Generator Level 5.

Steam Generator f'ressure ClIANNEL CNECK N.A.

CllANNEL CALIBRATION N.A.

+ The provision of Specification 4.0.6 are applicable

n C)

CD FC INSTRUtiENT TABLE 4.3-7 POST-ACCIOENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREHENTS CtlAHNEL CNECK CHANNEL CALIBRATION O

1.

Containment Pressure 2.

Reactor Coolant Outlet Temperature - TiiOT (Wide Range) 3.

Reactor Coolant Inlet Temperature - TCOLp (Wide Range) 4.

Reactor Coolant Pressure

- Wide Range 5".

Pressurizer Water Level 6.

Steam Line Pressure 7.

Steam Generator Water Level - Narrow Range 8.

RWST Water Level 9.

Boric Acid Tank Solution Level 10.

Auxiliary Feedwater Flow Rate 11.

Reactor Coolant System Subcooling Margin Monitor 12.

PORV Position Indicator - Limit Switches 13.

PORV Block Valve Position.Indicator - Limit Switches 14.

Safety Valve Position Indicator - Acoustic t'lonitor

• The provisions of Specification 4.0.6 are applicable.

REACTOR COOLANT SYSTEH RELIEF VALVES OP ERAT LIMITIHG CONOITIQN FOR OPERATION 3.4.U.

Three power operated re'lief valves (PORVs) and their associated block valves shall be OPERABLE.

APPLICABILITY:

MQOES 1, 2, and 3.

ACTION:

C.

V$th one cr acre PORV(s) inaoerabie, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the PORV(s) to OPERABL" status or close the associated block valve(s) and remove power fram the block valve(s)',

otherwise, be in at leas HQT STAHOBY wit1in the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in CGLQ SHUTDQW within the follmrtng 3Q hours.

'Arith one or mor black valve(s) inoperable, within 1 haur either (1) restore the block valve(s) to OPERABLE situs, or (Z) close the blcck valve(s) and remove power fram the block valve(s),

cr (3) close the associated PGRV(s) anc remove power from the associated solenoid valve(s);

otherwise',

be in at least HOT 5T5HD8Y wi hin the 'next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLO SHUTDQMH within the following 30 hcurs. "

Ine pravis ans c. Sceci.icaticn 3.0.4 are nat acplic&~ le.

V,"cVE L'1C"-

UIR 4 4 11 1

Each of the three PORVs shall be demonstrated OPERABLE:

b.

At least once per 31 days 5y performance cf a

CHAHHEL rdHCTIQHAL excluding valve "per ation, and At leas ance per 18 months by per formance of a CHAHHEL CALIBRATEQH. **

~hen ACTION 3. 4. 11.5. (3) is applied, no report pursuant ta Speciffcatian 6.9.1.9 is required for he FQRV.

• • The provisions of Specification 4.0.6 are applicable.

D. c. cooK - UNIT l 3/4 4-35 5eovAeav+

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