Text

Proposed Tech Specs Extending Surveillances Required to Be Performed by 880302 Until Unit 2 Refueling Outage in June 1988
	ML17326B306
Person / Time
Site:	Cook
Issue date:	01/11/1988
From:	; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	;
Shared Package
ML17326B305	List: ML17326B304; ML17326B306;
References
	NUDOCS 8801130231
	Download: ML17326B306 (18)
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Attachment 2 to AEP:NRC:0916AF Proposed Revised Technical Specification Pages 880 ii3023i 880iii

';i.-:.PDR, ADOCK 050003ih

.P PDR-

REACTIVITY CONTROL SYSTEMS POSITION INDICATOR CHANNELS-SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.3.3 At least one rod position indicator channel (excluding demand position indication) shall be OPERABLE for each shutdown or control rod not fully inserted.

APPLICABILITY:

MODES 3~~,

4~4 and 5~4 ACTION:

With less than the above required position indicator channel(s)

OPERABLE, immediately open the reactor trip system breakers.

SURVEILLANCE RE UIREMENTS 4.1.3.3 Each of the above required rod position indicator channel(s) shall be determined to be OPERABLE by performance of a CHANNEL FUNCTIONAL TEST at least once per 18 months.+

With the reactor trip system breakers in the closed position.

0 See Special Test Exception 3.10.5.

+ The provisions of Specification 4.0.7 are applicable.

D.

C.

COOK - UNIT 2 3/4 1-22 Amendment No.

3/4 3

ZNSTRUHENTAT ION 3]4 ~ 3 ] REACTOR TR P S YS -M ZNSTBL~

LZMZTZ~ CONDZTZON FOB OPERA CN 3,3 ~ 1 ~ 1 As a minimum, the eactor tr'p system instrumentation channels and intozlocks of Table 3.3-1 shall be OPEBABLE with BESPONSE TZMES as shown in Table 3+3 2 ~

APPLZCABZLZTY:

As shown in able 3.3-1.

ACTIONi As shown in Table 3.3-1.

SURVEZLLANCE RE UZBZ~TS 4

3 '

1 ~ 1

. >ach reac or t 'p system inst umenta ion channel shall be demonstrated OPEBABM. by the perfo~nce of the CHA5NZX CHECKS CIRE!IEL CALZBBATZON and CHÃ~ "-UNCTZONAL TEST opezations for the MODES and at the fzeqaencies shown in able 4.3-].+ ~*

4.3.1.1.2 The logic for the interlocks shall be==-nonstrated OPERABLE pzior to each.reactoz startup unless performed during the ". ceding 92 days.

The total interlock function shall be demonstrated OPERABLE *" least once per 18 months during CHANN L CALZBBATZCN testing o. each chan.".el a fected by interlock opezation.~

4.3.].].3 The

~~ CTCB BZP SYSTEM

RESPONSE

T ME of each reactor trip function shall be demonstrated to be within its limit at least once per 18 months.

Each test shall include at 'e st one logic train such that both 'ogic t"ains are tested at least once per 36 months and one channel pe func ion such that all channels are tested at least once every N times ]8 months where N 's the total number of zedhndant channels in a specific reactor trip unction as shown in the "Total No. of Channels" column of Table 3.3-].~*

J The pzovisions o

Spec'cat'on 4,0.6 are applicable.

The provisions of Specification 4.0.7 are applicab3.e.

D. C.

COOK UNZT 2 3/4 3a]

Amendment No ~

TAB)iL&a3=l BEMXQ(LTBI~YsTl'ti&HGTÃl(KHTMIQH5L>fLvL'ILIkHC~KQL>IBLUhL<XQ ZQ)KXIQHhhJBfLX CllhHNEL Cllti K CllhNHEL ChLIDl<>TIQH CllhNHEL FUNCTIONhL

~K5T HODES IN IRIICH SUAVEILLhNCE

~ERllM 1.

Hanual Reactor Trip

h. Shunt Trip Function ll. Undervoltage Trip Function 2.

Power Range, Neutron Flux H.h.

H.h.

N.h.

D(2,8) AH(3,8) and Q(6')

s/U(1)(lo) 5/U(>)(>0)

H and S/U(1) 3A 4*

5A

]

P 3A 4i 5A 1,

2 and

~

3.

Power Range, Neutron Flux, High Positive Rate i.

Power Range, Neutron Flux, High Hegativa Rata 5.

Xnteraediate

Range, Heutron Flux 6.

Source

Range, Neutron Flux H.h.

H.h.

R(6)

R(6 ~ 8)

R(6,8)

S/U (1)

H(8) and S/U(1) 2 1,

2 and e

>(>). ~(7l.

i and 5

7.

Ovarteaperature hT Overpower aT 9.

Pressurizer Pressure I~w

10. Pressurizer Pressure lligh

11. Pressurizer Hater Imvel--High S

12. loss ot Flow Single loop R(9)

R(9)

R A(8) 1 ~

2 1,

l~

2 1,

1 ~

+'Phn nvn~ii ci nnc nF Sppgj, fjcai inn ll 0 7 sva anni it'shia

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

APPLICABILITY:

As shown in Table 3.3-3.

ACTION:

With an ESFAS instrumentation channel trip setpoint less

.conservative 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 MODES 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 3.3-3.**

The provisions of Specification 4.0.6 are applicable.

The provisions of Specification 4.0.7 are applicable.

D.

C.

COOK - UNIT 2 3/4 3-14 Amendment No.

CDn TABLE 4.3-2 EHGIHEERED SAFETY FEATURE ACTUATIOH SYSTEM INSTRUMENTATION SURVElLLANCE RE UlREHENTS CD FC I4J CD FUNCTIONAL UNIT 1.

'AFETY INJECTION, TURBINE TRIP, FEED>IATER ISOLATION, AND HOTOR DRIVEN AUXILIARYFEEDMATER PUMPS a.

Manual Initiation 4.

Automatic Actuation Logic c.

Containment Pressure-High d.

Pressurizer Pressure--Low e.

Differential Pressure Between Steam Lines--High f.

Steam Line Pressure Low 2.

CONTAINMENT SPRAY a.

Manual Initiation b.

Automatic Actuation Logic c.

Containment Pressure High-High CHANNEL CIIECK H.A.

N.A.

H.A.

C((ANNEL CALIGRAT ION H.A.

N.A.

H.A.

CI(ANNEL FUNCTIONAL TEST H(1)

H(2)

H(3)

M(1)

M(2)

M(3)

MODES IN lQICH SURVEILLANCE

~RE IREE 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 O

The provisions of Specification 4.0.7 are applicable.

TAHLE 4. 3-2 Continued ENGINEEREO SAFETY FEATURE ACTUATION SYSTEH INSTRUHENTATION RVEI ANCE RE U AEHENTS FUNCTIONAL UM T 3.

CONTAItNENT ISOLATION a.

Phase "A" Isolation 1)

Hanual 2) from Safety In]ection Automatic Actuation Logic b.

Phase "8" Isolation l)

Hanual 2)

Automatic Actuation Logic 3)

Containment Pressure--

!iIgh-Iligh c.

Purge and Exhaust Isolation

)

Hanual 2)

Containment Radio-acti v ity-fligh CIIANNEL CIIECK H.A.

tl.A.

H.A.

N.A.

H.A.

CfflftfEL CALIBRATION H.A.

N.A.

H.A.

CflANNEL FUNCTIONAL TEST V(2)

Ii(3)

HODES IH QHICH SUAVEILLhffCK RE VIRID 1;2,3,4 1,2,3,4 1I 2 ~ 3 ~ 4 1,2,3,4 1,2,3 1o 2, 3, 4 1, 2, 3, 4

+ The provisions of Specification 4.0.7 are applicable.

E

C

~BATLl~MMITXQH S S

E S

0 ULHSBEm's T 0 i 8

I Hl8&~OE~U 4.

STEAM LINE ISOLATION CllAHHEL CHECK CllAHNEI.

CllANHEL FUNCTIONAL cQLTLl~QQLl MODES IH NllICll SURVEI LICENCE UT F a.

Hanua 1 Automatic Actuation Logic c.

Containment Prassura-High-1ligh H. A ~

H. A.

N ~ A ~

M(l)

H(2)

H(3) 1, 2, 3

l, 2, 3

1 ~ 2, 3

d.

Steam Plow in Two Steam LinesS

~

lligh Coincident with T Low-Low e.

Steam Line Pressure-Low 5 ~

TURBINE TRIP AND FEEDWATER ISOLATE'ON 1,

2s 3

1I 2I 3

a.

Steam Generator Mater Levellligh-lligh 6 ~

MOTOR DRIUEH AUXILIARYPEEDHATER PUMPS 1,

2 ~

3 an a.

Steam Generator Water Lave 1 Low-Low ll 2l 3

b.

4 kv Bus Loss of Voltage c.

Safaty In)action d.

Loss of Main Feed Pumps N.h.

N. h-N.h.

N. h.

M(2)

B 1, 2, 3

lg 2g 1,

+ VllP. AlAViSiAAS C)f RAPCi fiCatinn 4. 07 ~vn anni in>41 n

ImTRumemer REMOTE SHUTDOQI INSTR~TATION LIMITING CONDITION FOR OPERATION 3.3.3.5 The remote shutdown mon<torinq instrumentation channels Sho

]n Tab1e 3.3-9 shall be OPERABLK with readouts displayed external-to th control room.

APPLICASILITY:

HOOKS le 2 and 3.

ACTTON:

With the number of OPERABLE remote shutdown monitoring channels less than required by Table 3. 3-9, either restore the inoperable channel to OPKRABLE status within 30 days, or be

$ n HOT SRUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

The provisions of Specification 3.0. 4 are not applicable.

SURVEILLANCE RKOU?RKNKNTS

'. 3. 3...a(h r~ote shutdown moni tor ing instrument~:ion chanr o1 sha)l be "e~onstra:eC GPERABLE by performance of the CHANNEL CHECK and CHANNEL CAL:-"RAT:ON cperations at the frequencies shown in Tab'ie 4.3-6. *

The provisions of Technical Specification 4.0.7 are applicable.

D. C. CNK - UNIT 2 3)4 3-42 Amendment No.

C7 n

n C)

C) 7C INSTRUIIENT IIEIIOTE SIIUTI30MN HON ITORING INSTRUMENTATION SURVEILLANCE RE UIREHENTS CIIANNEL CIIECK CIIANNEL CALIl3RATION l.

Reactor Trip Oreaker Indication 2.

Pressurizer Pressure 3.

Pressurizer Level Steam Generator Level 5.

Steam Generator Pressure N.A.

N.A.

The provisions of Technical Specification 4.0.7 are applicable.

0

INSTRUMENTATION POST-ACCIDENT INSTRUMENTATION LIMITING CONDITION FOR OP=RATION 3.3.3.6 The post-accident monitoring instrumentation channels shown in Table 3.3-10 shall be OPERABLE.

APPLICABILITY:

MOOES 1,

2 and 3.

ACT)ON:

a.

b.

With the number of OPERABLE post-accident monitoring channels less than required by Table 3.3-10, either restore the inoperable channel to OPERABLE status within 30 days, or be in HOT SHUTOOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

The provisions of Specification 3,0. 4 are not applicable.

SURVE ILLA)'~CE REQUIREMENTS 4.3.3.6 Each post-accident monitoring

'nstrumen-.ation channel shall be demonstrated OPERABLE by oerformance of the CHA)lNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-10. *

The provisions of Specification 4.0.7 are applicable.

D.

C.

COOK - UNIT 2 3/4 3-45 MIENDMENT NO.

TABLE 4.3-10 POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE RE UI REMENTS INSTRUMENT CHANNEL CIIECK CHANNEL CALIBRATIOII l.

2.

3.

5.

6.

7 ~

8.

9.

10.

I 1.

12.

13.

14.

15.

16.

17.

18.

Containment Pressure Reactor Coolant Outlet Temperature

- TINT (Wide Range)

Reactor Coolant Inlet Temperature TCOHLD (Wide "<ange)

Reactor Coolant Pressure

- Wide Range Pressurizer Water Level Steam Line Pressure Steam Generator Water Level Narrow Range RWST Water Level Boric Acid Tank Solution Level Auxiliary Feedwater Flow Rate Reactor Coolant System Subcooling Margin Monitor PORV Position Indicator - Limit Switches PORV Block Valve Position Indicator - Limit Switches Safety Valve Position Indicator - Acous'c Monitor Incore Thermocouples (Core Exit Thermocouples)

(4)

Reactor Coolant Inventory Tracking System (Reactor Vessel Level Indication)

Containment Sump Level*

Containment Water Level*

h1 "1

M M

MI h1 M

M M

M M(2)

R R+

R+

R R

R R+

R R

R R(1)

R(3)+

(1)

Partial range channel calibration for sensor to be performed below P-12 in MODE 3.

(2)

With one train of geactor Vessel Level Indication inoperable.

Sobcooling Margin Indication and Core Exit Thermocouples may be used to perform a

CHANNEL CHECK to verify the remaining Reactor Vessel Indication train OPERABLE.

(3)

Completion of channel calibration for sensors to be performed billow P-12 in MODE:3.

(4)

The core exit thermocouples will not be installed until the 1988 refueling outage; therefore, survei 1-lances will not be required until that time.

See license amendment dated April 10, I987.

The requirements for these instruments will become effective after the level transmitters are modified or replaced and become operational.

The schedule for modification or replacement of the tranismitters is described in the Bases.

+ The provisions of Specification 4.0 '

are applicable.

Amendment No. 9g, 9$

(Am. 95 effective before startup following refueling outage currently scheduled in early 1988)

0 L'

>AT O

O~~~<-

OM icos -< uea C.

within 1 hou e'her (1) restore a

otal of at least two block valves to OP~~

LE status, or (2) close the block valves and remove power from the block valves, or (3) close the associated PORVs and remove power from their associated sol noid valves; and apply the portions of ACTION a.2 or a.3 above fo" inoperable PORVs, relating tn OP<MT ANAL..ODE, as appropriate.

t

~

Vith Vs a

d b~ock va> ~e not 'n the same line inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either (1) restore or (2) c'ose and de-energize the Apply the portions o

ACTION a.2 OPERATIONAL RODE, as appropriate unavailable.

the valves to OPERABLE status other valve in each line.

or a.3 above, relating to for two or three ~~

d.

The provisions of Spec fication 3.0.4 are not applicable, hf P

U

~>>~5 4,4.11.1 Each of the three PCRVs shall be demonst"ated OPERABLE:

a, At least once per 31 days by performance of a CHA~L FUNCTIONAL TEST, excluding valve operation, and b.

At least once per 18 months by perfo~nce of a CHANNEL.

CALIBRATION. **

4.4.11.2 Each of the three block valves shall be demonstrated OPERABLE at least once per 92 days by operating the valve through. one complete cycle of full travel.

The block valve(s) do not have to be tested when ACTION 3.4.11.a or 3.4.11.c is applied.

4.4.11.3 The emergency power supply for the PORVs and block valves shall be demonstrated OPERABLE at least once per 18 months by operating the valves through a complete cycle of full travel while the emergency buses are energized by the onsite d'esel generators and onsite plant batteries.

This testing can be performed in con)unction with the requirements of Specifications 4.8.1.1.2.c and 4.8.2.3.2.d. **

+ PORVs isolated to lim't RCS leakage through their seats and the block valves shut to isolate th's leakage are not considered inoperable.

- The provisions of spec

."ication 4.0.7 are applicable.

D.

C.

COOK - UNIT 2 3/4 4-33 AHEHDHEHT NO.

EHERGENCY CORE COOLING SYSTE>js d.

At least once per 18 months by:

1.

Verifying automatic isolation and interlock action of the RHR system from the Reactor Coolant System when the Reactor Coolant System pressure is above 600 psig.~

2.

A visual inspection of the containment sump and verifying that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks,

screens, etc.)

show no evidence of structural distress or corrosion.

e.

At least once per 18 months, during shutdown, by:

1.

Verifying that ea'ch automatic valve in the flow path actuates to its correct position on a Safety Injection test signal.

2.

Verifying that each of the following pumps start automatically upon receipt of a safety injection test signal:

a)

Centrifugal charging pump b)

Safety injection pump c)

Residual heat removal pump f.

By verifying that each of the following pumps develops the indicated discharge pressure on recirculation flow when tested pursuant to Specification 4.0.5:

1.

Centrifugal charging pump

> 2405 psig 2.

Safety Injection pump

> 1445 psig 3.

Residual heat removal pump 195 psig g.

By verifying the correct position of each mechanical stop for the following Emergency Core Cooling System throttle valves:

1.

Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months following completion of each valve stroking operation or maintenance on the valve when the ECCS subsystems are required to be OPERABLE.

The provisions of Specification 4.0.7 are applicable.

D.

C.

COOK

- UNIT 2 3/4 5-5 Amendment No.

EMERGENCY CORE COOLING SYSTEMS SUR~ZLLANCE RE UIREMENTS 4 ' ', 1 The ECCS subsystem shall be demonstrated OpERABLE per the applicable Suzveillance Requirements of 4.5 ' '

4.5.3.2 All charging pumps and sa ety njection pumps, except the above required OpERABLE charging

pump, sha' be demonstzated inoperable, by verifying that the motor cizcuit breakers have been removed from'heiz e]ectrlcal power supply circuits, at least ence per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months whenever the temperature of one or more of the RCS cold legs is 1ess than oz ecual to 152 F as determined at least once per hour when any RCS cold leg temperatuze is between 152 p and 200op The provisions of Spe '='c t'on 4.0.6 are appl'cable.

- The provisions of Specification 4.0.7 are applicable.

D. C.

COOK - UNET 2

3/4 5-8 Amendment No.

PLANT SYSTEMS 3/4.7.7 SNVBBERS LIMITING CONOITION POR OPERATION

. 1 All snubbers listed in Table 3.7-9 shall be OPERABLE.

APPL ICABLITY:

ACTION HOOES 1, 2, 3 and 4

(MODES 5 and 6 for snubbers located on systems required OPERABLE in those MOOES).

With one or more snubbers inoperable, within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months replace or restore the inoperable snubber(s) to OpERA8LE status and perform an engineering evaluation per Specification 4.7.7. 1.c on the suppor.ed component or declare the supported system inoperable and follow the appropriate ACTION statement for that system.

SURVEILLANCE RE UIREMENTS 4.7.7, 1

Each snubber shall be demonstrated OPERABLE by per ormance of the following augmented inservice inspection program and the requirements

'of Specification 4.0.5.*"

+

a.

Visual Inspect' The first inservice visual inspection of :"..':hers shall Ce performed after four

. cn-.hs but within 10 months of

=.-.eencing POWER OPERATION and shall includ all snubbers listed in

=.le 3.7-9.

If 'ess than

.wo (2) snubbers are fourd inoperable dur-. the first inservice visual inspec:icn, the second inservice vis.al inspection shall be performed 12 months

+ 25~ from the date of the first inspection.

Otherwise, subsecuent visual inspections shall be performed in accordance wi;h he follcwing schedule:

No.

Inoperabie Snubbers er Inspec:ion Period Subsequent Visual,>

Inscection Period*'

1 2

0 g4 5,6,7 8 cr more 18 months

'12 months 6 months 124 days 62 days 31 days

= 25

= 25 25

~ 25

= 25 The snubbers may be c tegorized into two groups:

Those accessible and those inaccessible during reactor operation.

Each group may be inspected independently in accordance with the above schedule.

gd<< l,i 1" gddd

The provisions of Specification 4.0.6 are applicable.

~The provisions of Specif'.cation 4.0.2 are not applicable.

The provisions of Specification 4.0.7 are applicable.

D. C. Cook Unit 2 3/4 7-20 Amendment No.

0 K

ML17326B306

Text

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