ML20197A807

Proposed Tech Specs,Reviewing Tables 4.3-7,4.3.3.9c, 4.3.4.2c,4.4.6.lb,4.6.1.2d,4.7.13.6,4.8.1.1.2g.1 & 4.8.4a to Extend Time Allowed for Certain 18-month Surveillance Requirements to First Refueling Outage

ML20197A807
Person / Time
Site:	Catawba
Issue date:	05/05/1986
From:	DUKE POWER CO.
To:
Shared Package
ML20197A787	List: ML20197A782 ML20197A807
References
NUDOCS 8605120389
Download: ML20197A807 (10)

Text

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TABLE 4.3-7 9

5 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL INSTRUMENT CHECK CALIBRATION

] 1. Containment Pressure M R

[ 2.

Reactor Coolant Outlet Temperature - TM T (Wide Range) M R 3.

Reactor Coolant inlet Temperature - TCOLD (Wih Range) M R

4. Reactor Coolant Pressure - Wide Range M R

5. Pressurizer Water Level M R

6. Steam Line Pressure M R

7. Steam Generator Water Level - Narrow Range M w R a

co

8. Refueling Water Storage Tank Water Level M R

9. Auxiliary Feedwater Flow Rate M R

10. Reactor Coolant System Subcooling Margin Monitor M R

11. PORY Position Indicator M R**

12. PORY Block Valve Position Indicator M R* +

13. Pressurizer Safety Valve Position Indicator M R

14. Containment Sump Water Level (Wide Range) M R 8605120389 860505 PDR P

ADOCK 05000413 PDR

TA8tE 4.3-7 (Continued) '

n h ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 1

CHANNEL CHANNEL i e

INSIRUMENT (Continued) CHECK CALIBRATION l

15. In Core Thermocouples M R w 16. Unit Vent - High-High Range Area Monitor (EMF-54) M R o.

m 17. Steam Relief Valve Exhaust Radiation Monitor (IEMF-26, 27, 28 and 29 and 2 EMF-10, 11, 12 and 13) M R

18. Containment Area - High Range Radiation Monitor (EMF-53 A&8) M Ra,4 *

19. Reactor Vessel Water Level M R

{ 20. Reactor Coolant Radiation Level (EMF-48) M R T

S

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

$ k h

%ehai b4rebL3 (4h;s applies b unif 1 only.

.- . -. - . - .- _= _ _ . - - - . _ - . - - .

INSTRUMENTATION LOOSE-PART DETECTION SYSTEM LIMITING CONDITION FOR OPERATION 3.3.3.9 The Loose-Part Detection System shall be OPERA 8tE.

APPLICABILITY: MODES 1 and 2.

ACTION:

a.

With one or more Loose-Part Detection System channels inoperabie for more than 30 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the channel (s) to OPERABLE status.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS I

4.3.3.9 Each channel of the Loose-Part Detection Systems shall be demonstrated l OPERABLE by performance of:

a. A 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 />,

b. An ANALOG CHANNEL OPERATIONAL TEST except for verification of Setpoint at least once per 31 days, and

c. A CHANNEL CALIBRATION at least once per 18 months SwtTue fe6;3 L wc4 L E s 4 Ag @,s apa b MLcmly.

CATAWBA - UNITS 1 & 2 3/4 3-79 l

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c - . . - - _ .

INSTRUMENTATION 3/4.3.4 TUR8INE OVERSPEED PROTECTION LIMITING CONDITION FOR OPERATION 3.3.4 At least one Turbine Overspeed Protection System shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTION:

a. With one stop valve or one control valve per high pressure turbine steam line inoperable and/or with one intermediate stop valve or one intercept valve per low pressure turbine steam line inoperable, restore the inoperable valve (s) to OPERA 8LE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or close at least one valve in the affected steam line(s) or isolate the turbine from the steam supply within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,

b. With the above required Turbine Overspeed Protection System otherwise inoperable, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> isolate the turbine from the steam supply.

SURVEILLANCE REQUIREMENTS 4.3.4.1 The provisions of Specification 4.0.4 are not applicable. .

4.3.4.2 The above required Turbine Overspeed Protection System shall be demonstrated OPERABLE:

a. At least once per 7 days while in MODE I and while in MODE 2 with the turbine operating, by cycling each of the following valves through at least one complete cycle from the running position:

1) Four high pressure turbine stop valves,

2) Six low pressure turbine intermediate stop valves, and

3) Six low pressure turbine intercept valves.

b. At least once per 31 days while in MODE I and while in MODE 2 with the turbine operating, by direct observation of the movement of each of the above valves and the four high pressure turbine control valves, through one complete cycle from the running position,

c. At least once per 18 months by performance qf a CHANNEL CALIBRATION on the Turbine Overspeed Protection Systems *, and l

d. At least once per 40 months by disassembling at least one of each of the above valves (including the four high pressure turbine control valves) and performing a visual and surface inspection of valve seats, disks and stems and verifying no unacceptable flaws or corrosion.

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REACTOR COOLANT SYSTEM 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.6.1 The following Reactor Coolant System Leakage Detection Systems shall be OPERABLE:

a. The Containment Atmosphere Gaseous Radioactivity Monitoring System,

b. The Containment Floor and Equipment Sump Level and Flow Monitoring Subsystem, and

c. Either the Containment Ventilation Unit Condensate Drain Tank Level Monitoring Subsystem or the Containment Atmosphere Particulate

, Radioactivity Monitoring System.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

With only two of the above required Leakage Detection Systems OPERABLE, operation may continue for up to 30 days provided grab samples of the contain- g ment atmosphere are obtained and analyzed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the required Gaseous or Particulate Radioactivity Monitoring System is inoperable; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 4.4.6.1 The Leakage Detection Systems shall be demonstrated OPERABLE by:

a. Containment Atmosphere Gaseous and Particulate Monitoring System performance of CHANNEL CHECK, CHANNEL CALIBRATION, and ANALOG CHANNEL OPERATIONAL TEST at the frequencies specified in Table 4.3-3,

b. Containment Floor and Equipment Sump Level and Flow Monitoring Subsystemy- erformance of CHANNEL CALIBRATION at least once per 18 monthsT and , l

c. Containment Ventilation Unit Condensate Drain Tank Level Monitoring Subsystem performance of CHANNEL CALIBRATION at least once per 18 months.

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CATAWBA - UNITS 1 & 2 3/4 4-19

CONTAINMENT SYSTEMS 1

SURVEILLANCE REQUIREMENTS (Continued) l a.

Three Type A tests (Overall Integrated Containment Leakage Rate) shall be conducted at 40 2 10 month intervals during shutdown at either P,,14.68 psig, or (Unit 1) at Pt . . 4 ps g, ng each 10 year service period.

The third test of each set shall be con-ducted inspection; during the shutdown for the 10 year plant inservice

) b.

If any periodic Type A test fails to meet either 0.75 L, or (Unit 1) 0.75 Lg , the test schedule for subsequent Type A tests shall be reviewed and approved by the Commission. If two consecutive Type A tests fail to meet either 0.75 L, or (Unit 1) 0.75 L g, a Type A test shall be performed at least every 18 months until two consecutive Type A tests meet either 0.75 L, or (Unit 1) 0.75 Lg at which time the above test schedule may be resumed; c.

The which:

test accuracy of each Type A test shall be verified by a supplemental 1)

Confirms the accuracy of the test by verifying that the supple-mental test result, L , gminus the sum of the Type A and the L,, is equal toleak, (Unit 1) 0.25 L ; superimposed or less than 0.25 L, or g

2)

Has a duration sufficient to establish accurately the change in leakage and rate between the Type A test and the supplemental test;

3) Requires that the rate at which gas is injected into the i containment or bled from the containment during the supple-mental and 1.25test L . is between 0.75 L, and 1.25 L, or (Unit 1) 0.75 L g t

d.

i Type less than B and C tests P,, 14.68 shall psig, at intervals be conducted no greaterwiththangas at a pressure not

• 24 months except for tests involving:

1) Air locks,

2) Purge supply and exhaust isolation valves with resilient material seals, and l

3) Dual ply bellows assemblies on containment penetrations between the containment building and the annulus,

e. The combined bypass leakage rate shall be determined to be less than l

0.07 L,for pe3etrations which are not individually testablby app I

except e; penetra-tions not individually testable shall be determined to have no detect-able leakage when tested with soap bubbles while the containment is pressurized to P,, 14.68 psig, or (Unit 1) P t. 7.34 psig, during each j _ _

Type A test; CATAWBA - UNITS 1 & 2 3/4 6-3 4Tnis aveitta nce n<d m+ 6 performed. 4 G>se penetrahens M(,w/ m Ta Uc M- 4 L.____.__

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Table 3.6-la l Unit one penetrations (all are test type C) that need not be tested until prior to entering HOT SHUTDOWN following the Unit One first refueling.

PENETRATION RELEASE NUMBER SERVICE LOCATION M230 Nuclear Service Water from Reactor Auxiliary Coolant Pump and Lower Containment Building Ventilation Units.

M215 Breathing Air Auxiliary Building M219 Station Air Auxiliary Building M358 Refueling Water Pump Suction Auxiliary Building M356 Equipment Decontamination Line Auxiliary Building M345 Recycle Holdup Tank from Reactor Coolant Auxiliary Drain Tank (Valve IWL806 only) Building M204 Containment Air Addition Auxiliary Building M259 Reactor Makeup Water Flush Header Auxiliary Building E101-450 Electrical penetrations for various Auxiliary equipment Building M374 Containment Floor Sump and Incore Auxiliary Instrumentation Sump Pump Discharge Building CATAWBA - UNITS 1 & 2 3/4 6-7a

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 1.7.13.5 The Steam Turbine Driven Auxiliary Feedwater Pump and associated components shall be demonstrated OPERABLE at least once per 18 months by veri-fying that the system functions as designed from the Standby Shutdown System.

4.7.13.6 Each Standby Shutdown System instrumentation device shall be demonstrated OPERABLE by performance of a CHANNEL CHECK at least once per 31 days and a CHANNEL CALIBRATION at least once per 18 months?

6 D

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CAT M A - UNITS 1 & 2 3/4 7-42

ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

1) By verifying in accordance with the tests specified in ASTM-0975-81 prior to addition to the storage tanks that the sample has:

a) An API Gravity of within 0.3 degrees at 60*F, or a spectfic gravity of within 0.0016 at 60/60'F, when compared to the supplier's certificate, or an absolute specific gravity at 60/60*F of greater than or equal to 0.83 but less than or equal to 0.89, or an API gravity of greater than or equal to 27 degrees but less than or equal to 39 degrees; b) A kinematic viscosity at 40*C of greater than or equal to 1.9 centistokes, but less than or equal to 4.1 centistokes (alternatively, Saybolt viscosity, SUS at 100'F of greater than or equal to 32.6, but less than or equal to 40.1),

if gravity was not determined by comparison with the supplier's certification; c) A flash point equal to or greater than 125'F; and d) A clear and bright appearance with proper color when tested in accordance with ASTM-04176-82.

2) By verifying within 30 days of obtaining the sample that the other properties specified in Table 1 of ASTM-0975-81 are met when tested in accordance with ASTM-0975-81 except that the I

analysis for sulfur may be performed in accordance with ASTM-01552-79 or ASTM-02622-82.

f. At least once every 31 days by obtaining a sample of fuel oil in accordance with ASTM-02276-78, and verifying that total particulate contamination is less than 10 mg/ liter when checked in accordance with ASTM-02276-78, Method A;

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

1) Subjecting the diesel to an inspection in accordance with procedures prepared in conjunction with its manuf turer's recommendations for this class of standby service

2) Verifying the generator capability to reject a load of greater than or equal to 825 kW while maintaining voltage at 4160 1 420 volts and frequency at 60 + 1.2 Hz;

3) Verifying the generator capability to reject a load of greater than or equal to 5600 kW but less than or equal to 5750 kW without tripping. Tha ganerator speed shall not exceed 500 rpm during and following the load rejecticn;

4) Simulating a loss-of-offsite power by itself, and:

a) Verifying deenergization of the emergency busses and load shedding from the emergency busses, and t-Tnis sureknec ned n46 pdud unM por b en4 erin 3 b w o u)^)

-9 e % y L 6 4 t % r c e % H n3 9ha appl.as 4 as/ L oab).

CATAWA - UNITS 1 & 2 3/4 8-4

ELECTRICAL POWER SYSTEMS 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES LIMITING CONDITION FOR OPERATION 3.8.4 All containment penetration conductor overcurrent protective devices given in Tables 3.8-la and 3.8-Ib shall be OPERA 8LE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

With one or more of the containment penetration conductor overcurrent protective device (s) given in Tables 3.8-la and'3.8-lb inoperable:

a.

Restore the protective device (s) to OPERABLE status or de energize the circuit (s) by tripping the associated backup circuit breaker or racking out or removing the inoperable circuit breaker within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, declare the affected system or component inoperable, and verify the backup circuit breaker to be tripped or the inoper-able circuit breaker racked out or removed at least once per 7 days thereafter; the provisions of Specification 3.0.4 are not applicable to overcurrent devices in circuits which have their backup circuit breakers removed, or tripped, their inoperable cirCJit breakers racked out, or b.

Be in at leastwithin SHUTDOWN HOTtheSTANDBY following 30within hours.the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SURVEILLANCE REQUIREMENTS 4.8.4 All containment penetration conductor overcurrent protective devices given in Tables 3.8-la and 3.8-lb shall be demonstrated OPERABLE:

a. At least once per 18 months:M

1) By verifying that the medium voltage (4-15 kV) circuit breakers j

are OPERABLE by selecting, on a rotating basis, at least 10% of the circuit breakers of each voltage level, and performing the following:

a) A CHANNEL CALIBRATION of the associated protective relays, b) An integrated protective system functional test which l

includes simulated automatic actuation of the system and

) verifying that each relay and associated circuit breakers j function as designed, and M 'Thrs surellance need oc,4 h prdermed und p rior do edrin hot SH470cuo fenoeg b kt L b4 ccbl.3 %5 9 65 4c dolf I on ),

CATAWBA - L' NITS 1 & 2 3/4 8-19 l

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