ML20046B261

Proposed Tech Specs Extending Instrument Calibr Intervals to 36 Months for Selected Instrumentation

ML20046B261
Person / Time
Site:	Fermi
Issue date:	07/29/1993
From:	DETROIT EDISON CO.
To:
Shared Package
ML19310D552	List: ML20046B261 NRC-93-0061, Application for Amend to License NPF-43,revising TS to Extend Instrument Calibr Intervals to 36 Months for Selected Instrumentation,Per BWROG Licensing Topical Rept NEDC-32160P,Dec 1992.GE Proprietary Rept Encl.Rept Withheld
References
NUDOCS 9308030422
Download: ML20046B261 (18)

Text

. _ - _

ENCLOSURE 3 PROPOSED TECHNICAL SPECIFICATION PAGE CHANGES 1

-i 9308030422 930729 TI PDR ADOCK 05000341 if P

PDR

[3 J

DEFINITIONS FRE0VENCY NOTATION 1.14 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1.

IDENTIFIED LEAKAGE 1.15 IDENTIFIED LEAKAGE shall be:

Leakage into collection systems, such as pump seal or valve packing a.

leaks, that is captured and conducted to a sump or collecting tank, or b.

Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of the leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE.

ISOLATION SYSTEM RESPONSE TIME 1.16 The ISOLATION SYSTEM RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its isolation actuation setpoint at the i

channel sensor until the isolation valves travel to their required positions.

Times shall include diesel generator starting and sequence i

loading delays where applicable.

The response time may be measured by any series of sequential, overlapping or total steps such that the entire response time is measured.

LIMITING CONTROL R0D PATTERN 1.17 A LIMITING CONTROL R0D PATTERN shall be a pattern which results in the core being on a. thermal hydraulic limit, i.e., operating on a limiting value for APLHGR, LHGR, or MCPR.

LINEAR HEAT GENERATION RATE 1.18 LINEAR HEAT GENERATION RATE (LHGR) shall be the heat generation per unit length of fuel rod.

It is the integral of the heat flux over the heat transfer area associated with the unit length.

LOGIC SYSTEM FUNCTIONAL TEST 1.19 A LOGIC SYSTEM FUNCTIONAL TEST shall be a test of all logic components, i.e., all relays and contacts, all trip units, solid state logic elements, etc., of a looic circuit, from as close to the sensor as practicable through and including the actuated device, to verify OPERABILITY.

The LOGIC SYSTEM FUNCTIONAL TEST may be performed by any series of sequential, overlapping or total system steps such that the entire logic system is tested.

MAXIMUM FRACTION OF LIMITING POWER DENSITY 120 The MAXIMUM FRACTION OF LIMITING POWER DENSITY (MFLPD) shall be the highest value of the FLPD which exists in the core.

MEMBERfS) 0F THE PUBLIC 1.21 MEMBER (S) 0F THE PUBLIC shall include all persons who are not occupationally associated with the plant.

This category does not include i

employees of the utility, its contractors or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational or other purposes not associated i

with the plant.

FERMI - UNIT 2 1-3 Amendment No.

I DEFINITIONS f

TABLE 1.1 SURVEILLANCE FRE00ENCY NOTATION NOTATION FRE00ENCY S

At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

D At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

t W

At least once per 7 days.

M*

At least once per 31 days.

Q At least once per 92 days.

SA At least once per 184 days.

A At least once per 366 days.

R At least once per 18 months (550 days).

T At least once per 36 months (1100 days)(a) l S/U Prior to each reactor startup.

P Prior to each radioactive release.

r NA Not applicable.

j b

I l-i (a) When applied to instrument calibrations, at least one half of the total l

channels for a functional unit shall be tested at least once per 18 months l

(550 days).

l-FERMI - UNIT 2 1-9 Amendment No.

L A

m3 TABLE 4.3.1.1-1 8

REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVElLLANCE REQUIREMENTS e5*

CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH FUNCTIONAL UNIT CHECK TEST CALIBRATION (a)

SURVEILLANCE RE0VIRED 1.

Intermediate Range Monitors:

a.

Neutron Flux - High S/U,S,(b)

S/U(c), W SA 2

S W

SA 3,4,5 b.

Inoperative NA W

NA 2,3,4,5 2.

Average Power Range Monitor (f):

a.

Neutron Flux -

S/U,S,(b)

S/U(c), W SA 2

High, Setdown S

W SA 3, 5 b.

Flow Biased Simulated

[

Thermal Power - High S

S/U(c),g g(d)(e),SA,R(h) 1 c.

Fixed Neutron Flux -

High S

S/U(c), q g(d), SA 1

d.

Inoperative NA Q

NA 1, 2, 3, 5 3

R 3.

Reactor Vessel Steam Dome 2

Pressure - High S

Q(k)

T 1, 2 E.

4.

Reactor Vessel Low Water 2

P Level - Level 3 S

Q(k)

T 1, 2 m?

5.

Main Steam Line Isolation Valve - Closure NA Q

R I

g 6.

Main Steam Line Radiation -

High S

Q R

1,2(i) 7.

Drywell Pressure - High S

Q(k)

T 1, 2

A TABLE 4.3.2.1-1 E

7 ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE RE0VIREMENTS E

CHANNEL OPERATIONAL Z

CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH m TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE RE0VIRED 1.

PRIMARY CONTAINMENT ISOLATION a.

Reac+or Vessel Low Water Level-1)

Level 3 S

Q T

1, 2, 3 2)

Level 2 S

Q T

1, 2, 3 3)

Level 1 S

Q T

1, 2, 3 b.

Drywell Pressure - High S

Q T

1, 2, 3 c.

Main Steam Line m

s

[

1)

Radiation - High S

Q R

1, 2, 3 i

A, 2)

Pressure - Low S

Q T

1 3)

Flow - High S

Q T

1, 2, 3 o

d.

Main Steam Line Tunnel Temperature - High S

Q T

1, 2, 3 e.

Condenser Pressure - High S

Q T

1, 2**, 3**

f.

Turbine Bldg. Area Temperature - High S

Q T

1, 2, 3

,s

[

g.

Deleted h.

Manual Initiation NA R

NA 1,2,3

?

D.

i

.~..

4 TABLE 4.3.2.1-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE RE0VIREMENTS SE CHANNEL OPERATIONAL CHANNEL CONDITIONS FOR WHICH CHANNEL FUNCTIONAL TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED

3 2.

REACTOR WATER CLEANUP SYSTEM ISOLATION a.

A Flow - High S

Q R

1, 2, 3 b.

Heat Exchanger / Pump /High Energy Piping Area Temperature - High S

Q T

1, 2, 3 c.

Heat Exchanger / Pump / Phase Separator Area Ventilation A Temperature - High S

Q T

1, 2, 3 d.

SLCS Initiation NA R

NA 1,2,3 w

3:

w e.

Reactor Vessel Low Water 4.

Level - Level 2 S

Q T

1, 2, 3 l

f.

Deleted g.

Manual Initiation NA R

NA 1, 2, 3 Ef 3.

REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION 9

a.

RCIC. Steam Line Flow - High 1.

Differential Pressure S

Q T

1, 2, 3 l

2.

Time Delay NA Q

R 1,2,3 E

b.

RCIC Steam Supply Pressure -

t*

Low S

Q T

1, 2, 3 2

c.

RCIC Turbine Exhaust Diaphragm Pressure - High S

Q T

1, 2, 3 l

u d.

RCIC Equipment Room Temperature - High S

Q T

1, 2, 3 e.

Manual Initiation NA' R

NA 1, 2, 3

i TABLE 4.3.2.1-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL OPERATIONAL 5

CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED 4.

HIGH PRESSURE COOLANT INJECTION SYSTEM ISOLATION a.

HPCI Steam Line Flow - High l

1.

Differential Pressure S

Q T

1, 2, 3 2.

Time Delay NA

-Q R

1, 2, 3 b.

HPCI Steam Supply Pressure - Low S

Q#

T 1, 2, 3 c.

HPCI Turbine Exhaust Diaphragm Pressure - High S

Q T

1, 2, 3 d.

HPCI Equipment Room Temperature - High S

Q T

1, 2, 3 e.

Manual Initiation NA R

NA 1, 2, 3 m

x

[

5.

RHR SYSTEM SHUTDOWN COOLING MODE ISOLATION a.

Reactor Vessel low Water Level -

U Level 3 S

Q T

1, 2, 3 b.

Reactor Vessel (Shutdown Cooling Cut-in Permissive Interlock)

Pressure - High S

Q T

1, 2, 3 c.

Manual Initiation NA R

NA 1, 2, 3 p

6.

SECONDARY CONTAINMENT ISOLATION g

a.

Reactor Vessel low Water level -

g Level 2 S

Q T

1, 2, 3, and

• g b.

Drywell Pressure - High S

Q T

1, 2, 3

'+

c.

Fuel Pool Ventilation Exhaust Radiation - High S

Q R

1, 2, 3, and

• zo d.

Manual Initiation NA R

NA 1, 2, 3, and

• i D.

• When handling irradiated fuel in the secondary containment, during CORE ALTERATIONS, and during operations with a potential for draining the reactor vessel.

• • May be bypassed under administrative control.

1. Includes verification of the trip setpoint of the trip unit.

TABLE 4.3.3.1-1 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL OPERATIONAL viy CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED 1.

CORE SPRAY SYSTEM c-a.

Reactor Vessel low Water Level -

T 1, 2, 3, 4*, 5*

5 Level 1 S

Q ##

b.

Drywell Pressure - High S

Q T

1, 2, 3 c.

Reactor Steam Dome Pressure -

T 1, 2, 3, 4*, 5*

Low S

Q d.

Manual Initiation NA R

NA 1, 2, 3, 4*, 5*

2.

LOW PRESSURE COOLANT INJECTION MODE OF RHR SYSTEM a.

Reactor Vessel Low Water Level -

Level 1 S

Q T

1, 2, 3, 4*, 5*

b.

Drywell Pressure - High S

Q T

1, 2, 3 c.

Reactor Steam Dome Pressure -

Low S

Q T

1, 2, 3, 4*, 5*

d.

Reactor Vessel Low Water R

Level - Level 2 S

Q T

1, 2, 3, 4*,

5*

e.

Reactor Steam Dome Pressure -

Y' Low S

Q T

1, 2, 3, 4*, 5*

f.

Riser Differential Pressure -

High S

Q T

1, 2, 3 g.

Recirculation Pump Differential Pressure - High S

Q T

1, 2, 3 h.

Manual Initiation NA R

NA 1, 2, 3, 4*, 5*

3.

HIGH PRESSURE COOLANT INJECTION SYSTEM #

a.

Reactor Vessel Low Water Level -

Level 2 S

Q T

1, 2, 3 E

b.

Drywell Pressure - High S

Q##

T 1, 2, 3 E

c.

Condensate Storage Tank Level -

E Low S

Q T

1, 2, 3 E

d.

Suppression Pool Water level -

High S

Q R

1, 2, 3 5

e.

Reactor Vessel High Water Level -

l Level 8 S

Q T

1, 2, 3 y

f.

Manual Initiation NA R

NA 1,2,3

I A

TABLE 4.3.3.1-1 (Continued) 5 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL OPERATIONAL Ep CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE RE0VIRED m

4.

AUTOMATIC DEPRESSURIZATION SYSTEM a.

Reactor Vessel Low Water Level -

T 1, 2, 3 Level 1 S

Q ##

b.

Drywell Pressure - High S

Q T

1, 2, 3 c.

ADS Timer NA Q

R 1, 2, 3 d.

Core Spray Pump Discharge Pressure - High S

Q T

1, 2, 3 e.

RHR LPCI Mode Pump Discharge Pressure - High S

Q T

1, 2, 3 f.

Reactor Vessel Low Water Level -

w T

1, 2, 3 1

Level 3 5

Q w

g.

Manual Initiation NA R

NA 1,2,3 d,

h.

Drywell Pressure - High Bypass R

1, 2, 3 Timer NA Q

~

i. Manual Inhibit NA R

NA 1, 2, 3 5.

LOSS OF POWER a.

4.16 kV Emergency Bus Under-p voltage (Loss of Voltage) g (Division 1 and Division 2)

NA M

R 1, 2, 3, 4**, 5**

5g b.

4.16 kV Emergency Bus Under-voltage (Degraded Voltage) g (Division 1 and Division 2)

NA M

R 1, 2, 3, 4**, 5**

U When the system is required to be OPERABLE per Specification 3.5.2.

M

• • Required OPERABLE when ESF equipment is required to be OPERABLE.

1. Not required to be OPERABLE when reactor steam dome pressure is less than or equal to 150 psig.

Includes verification of the trip setpoint of the trip unit.

k z

TABLE 4.3.4-1 b

ATWS RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS b

CHANNEL CHANNEL FUNCTIONAL CHANNEL

[

TRIP FUNCTION CHECK TEST CALIBRATION 1.

Reactor Vessel Low Water level -

S M

T Level 2 2.

Reactor Vessel Pressure - High S

M T

s.

K an m

u

-. ~..

e-

~ <

i..,,-

s...,,

.w-..

A TABLE 4.3.5.1-1 E

7 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS E

Q CHANNEL CHANNEL FUNCTIONAL CHANNEL m

FUNCTIONAL UNITS CHECK TEST CALIBRATION a.

Reactor Vessel Low Water Level - Level 2 S

Q T

b.

Reactor Vessel High Water S

Q T

Level - Level 8 c.

Condensate Storage Tank Level - Low S

Q T

w1 d.

Manual Initiation NA R

NA Y

8

1. ncludes verificatien of the trip setpoint of the trip unit.

I E

a an

-+re-+i.w-

• ww+--

--=

• r=

6 e~s+

b--em-e rm=,<-4 w-e-

e--

w, w

e-u

---e--

v - - -

-.,e

t

~4 TABLE 4.3.7.4-1 E

REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS E

m CHANNEL CHANNEL na INSTRUMENT CHECK CALIBRATION 1.

Reactor Vessel Pressure M

T 2.

Reactor Vessel Water Level M

T 3.

Suppression Chamber Water Temperature H

T 4.

Drywell Pressure M

T 5.

RHR Division I Hx Discharge Flow M

T 6.

RCIC Flow M

R 93 S?

F a

<a

+

E

-,,_,wn,,.

-w

,,.,vn a

v v er -~,.-~- - - -

e wr ----+

m

.m a.

-r

-+.-n~-.

4----

I.

TABLE 4.3.7.5-1 5'

ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS APPLICABLE-CHANNEL CHANNEL OPERATIONAL E

INSTRUMENT CHECK CALIBRATION CONDITIONS p

1.

Reactor Vessel Pressure M

T 1, 2 m

2.

Reactor Vessel Water Level a.

Fuel Zone M

T 1, 2 b.

Wide Range M

T 1, 2 3.

Suppression Chamber Water Level M

T 1, 2 4.

Suppression Chamber Water Temperature H

T 1, 2 5.

Suppression Chamber Air Temperature M

T 1, 2 6.

Suppression Chamber Pressure M

T 1, 2 y

7.

Drywell Pressure, Wide Range M

T 1, 2 8.

Drywell Air Temperature M

T 1, 2 9.

Drywell Oxygen Concentration M

R 1, 2 10.

Drywell Hydrogen Concentration M

Q*

1, 2

{

11.

Safety / Relief Valve Position Indicators M

R 1, 2 a

12. Containment High Range Radiation Monitor M'

R**

1,2,3 e

5 M

• Using sample gas containing:

a.

One volume percent hydrogen, balance nitrogen.

D b.

Four volume percent hydrogen, balance nitrogen.

• • CHANNEL CALIBRATION shall consist of an electronic calibration of the channel, not including the detector, for range decades above 10 R/hr and a one point calibration check of the detector below 10 R/hr with an installed or portable gamma source.

i TABLE 4.3.9.1-1

-n95 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE RE0VIREMENTS 5

CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH FUNCTIONAL UNIT CHECK _

TEST CALIBRATION SURVEILLANCE RE0VIRED a.

Reactor Vessel High Water Level -

Level 8 S

M T

1 5

Y it a

Et ar

.u-n

i 4

n m

TABLE 4.3.11.1-1 APPENDIX R ALTERNATIVE SHUTDOWN INSTRUMENTATION z

Z SURVEILLANCE REQUIREMENTS N

CHANNEL CHANNEL INSTRUMENT CHECK CALIBRATION 1.

CTG 11 Unit 1-Volts M

R 2.

CTG 11 Unit 1-Frequency M

R 3.

CTG 11 Unit 1-Watts M

R 4.

CTG 11 Unit 1-Vars M

R 5.

Condensate Storage Tank Level M

T I

6.

Standby Feedwater Flow M

R R

7.

Reactor Water Level M

T 8.

Reactor Pressure M

T y

9.

Torus Water Temperature M

T g

10. Torus Water Level M

T 11.

Primary Containment Temperature M

T E

a Bn

i REACTOR COOLANT SYSTEM SAFETY / RELIEF VALVES LOW-LOW SET FUNCTION l

LIMITING CONDITION FOR OPERATION 3.4.2.2 The low-low set function of the _following reactor coolant system safety / relief valves shall be OPERABLE with the following settings-Low-Low Set Function Low-Low Set Function l

Setooint (osia)

Allowable Value (osia)

Valve No.

Oge_n Close Open Close F013A 1017 905 1037 F013G 1047 935 1067 APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

a.

With the low-low set function of one of the above required reactor coolant system safety / relief valves inoperable, restore the inoperable low-low set function to OPERABLE status within 14 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b.

With the low-low set function of both of the above required reactor coolant system safety / relief valves inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and-in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE REOUIREMENTS 4.4.2.2 The low-low set functior pressure actuation instrumentation shall be demonstrated OPERABLE by performance of a:

a.'

CHANNEL FUNCTIONAL TEST at least once per 31 days.

b.

LOGIC SYSTEM FUNCTIONAL TEST and simulated automatic operation of i

the entire system at least once per 18 months.

c.

CHANNEL CALIBRATION at least once per 36 months. At least one half l

of the channels shall be calibrated at least once per 18 months.

i i

• Closing pressure must be at least 100 psi less than actual opening pressure.

i FERMI - UNIT 2 3/4 4-8 Amendment No.

n 1

I CONTAINMENT SYSTEMS i

MSIV LEAKAGE CONTROL SYSTEM LIMITING CONDITION FOR OPERATION

~

3.6.1.4 Two independent MSIV leakage control system (LCS) subsystems shall be OPERABLE with each subsystem comprised of a flow path from the associated control air division to the main steam lines.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

With one MSIV leakage control system subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 30 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVElllANCE RE0VIREMENTS F

4.6.1.4 Each MSIV leakage control system subsystem shall be demonstrated OPERABLE:

a.

At least once per 31 days by cycling each testable valve except the motor-operated MSIVs through at least one complete cycle of full travel.

b.

During each COLD SHUTDOWN, if not performed within the previous 31 days, by cycling each valve including the motor-operated MSIVs not testable during operation through at least one complete cycle of full travel.

c.

At least once per 18 months by performance of a functional test of the subsystem throughout its operating sequence, and verifying that each interlock operates as designed and each automatic valve actuates to its correct position, d.

By verifying the pressure control (pressure and Ap) instrumentation to be OPERABLE by performance of a:

1.

CHANNEL CHECK at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, 2.

CHANNEL FUNCTIONAL TEST at least once per 92 days, and 3.

CHANNEL CALIBRATION at least once per 36 months.

At least one l

half of the channels shall be calibrated at least once per 18 l

months.

l 1

r FERMI - UNIT 2 3/4 6-10 Amendment No.

CONTAINMENT SYSTEMS SURVEllLANCE REQUIREMENTS (Continuedi 1.

At least once per 5 minutes during testing which adds heat to the suppression chamber, by verifying the suppression chamber t

average water temperature is less than or equal to 105*F.

2.

At least once per hour when suppression chamber average water temperature is greater than or equal to 95"F, by verifying:

a) Suppression chamber average water temperature to be less than or equal to 110*F, and t

b) THERMAL POWER to be less than or equal to 1% of RATED THERMAL POWER after suppression chamber average water temperature has exceeded 95'F for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

c.

At least once per 30 minutes in OPERATIONAL CONDITION 3 following a scram with suppression chamber average water temperature greater 7

than or equal to 95'F, by verifying suppression chamber average water temperature less than or equal to 120*F.

f d.

By an external visual examination of the suppression chamber after safety / relief valve operation with the suppression chamber average water temperature greater than or equal to 160"F and reactor coolant system pressure greater than 200 psig.

e.

At least once per 18 months by a visual inspection of the accessible interior and exterior of the suppression chamber.

f.

By verifying eight suppression pool water temperature instrumentation channels OPERABLE by performance of a:

1.

CHANNEL CHECK at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, 2.

CHANNEL FUNCTIONAL TEST at least once per 31 days, and 3.

CHANNEL CALIBRATION at least once per 36 months, with the water l

high temperature alarm setpoint for s.105*F.

At least one-half l

the channels shall be calibrated at least once per 18 months.

g.

By verifying both narrow range suppression chamber water level i'

instrumentation channels OPERABLE by performance of a-l.

CHANNEL CHECK at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, 1

2.

CHANNEL FUNCTIONAL TEST at least once per 31 days, and

+

,, 3.

CHANNEL CALIBRATION at least once per 36 months, at least one-l half the channels shall be calibrated once per 18 months.

l With the water level alarm setpoint for:

i 1.

High water level s 14'8" 2.

Low water level 2 14'4" (TWMS Narrow Range) t h.

At least once per 18 months by conducting a drjwell-to-suppression chamber bypass leak test at an initial differential pressure of 1 psi and verifying that the differential pressure does not decrease by more than 0.20 inch of water per minute for a period of t

10 minutes.

If any drywell-to-suppression chamber bypass leak test fails to meet the specified limit, the test schedule for subsequent tests shall be reviewed and approved by the Commission.

If two consecutive tests fail to meet the specified limit, a test shall be performed at least every 9 months until two consecutive tests meet the specified limit, at which time the 18 month test schedule may be resumed.

FERMI - UNIT 2 3/4 6-17 Amendment No.