ML20042G263

Proposed Tech Specs Re Calibr of Instrument Channels & Testing Intervals for Pressure Suppression Chamber & Secondary Containment Capability Tests

ML20042G263
Person / Time
Site:	Oyster Creek
Issue date:	05/04/1990
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20042G261	List: ML20042G260 ML20042G262 ML20042G263
References
NUDOCS 9005140017
Download: ML20042G263 (10)

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i Technical Specification Change ,

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TABLE 4.1.1 (cont'd).

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InOtrument Chennel Check- Calibrate Test Remarks (Apolies to Test and Calibration) i.

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11. APRM Level N/A 1/3 d N/A Output adjustment using operational type heat balance during power operation APRM Scram Trips Note 2 ~ 1/wk. 1/wk.. Using built-in calibration equipment during power operation

12. APRM Rod Blocks Note 2 1/3 mo. 1/mo. Upscale and downscale 13.a. High Radiation in Main Steamline 1/s 1/3 mo. 1/mo. Using built-in calibration equipment during power operation

b. Sensors for 13(a) N/A Each re- N/A Using external radiation source fueling outage I

y 14. High Radiation in Reactor Building es Operating Floor 1/s 1/3 mo. 1/wk Using gamma source for calibration Ventilation Exhaust 1/s 1/3 mo. 1/wk. Using gamma source for calibration

15. High Radiation on Air Ejector 1/3 mo. 1/wk. Using built-in calibration equipment g Ejector Off-Gas 1/s Channel check j 1/sto. Source check g 1/24 mo. Calibration according to established station l.

g calibration procedures n 1/24 mo. Note a -l 2;

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16. IRM Level N/A Each N/A

, startup

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• IRM Scram Using built-in calibration equipment o

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1. ' TABLE 4.1.1 (cont'd)

%.r en . Remarks ( Apolies '"'o Test' and Calibration)

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Instrument channel Check Calibrate' Test

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$ .27. Scram Discharge Volume (Rod Block) '

y3 .By varying level in switch column

• . a) . Water level N/A Each re-

-fueling muac s high

-. outage N/A- N/A Each re-b) Scram Trip bypass fueling outage.

28. Loss of Power .l'--

a) 4.16 KV Daily 1/24 mos. 1/mo.

Emergency Bus Undervoltage (Loss of voltage) b) 4.16 KV Emergency l Bus Daily. 1/24 mos. 1/mo. .l co Undervoltage (Degraded Voltage)

N/A ~Each re- Each re-

29. Drywell High fueling- fueling Radiation outage outage 9st

n o 1/s and test 1/wk until no longer required.

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• Calibrate prior to startup and normal shutdown and thereafter check

m. c 9 N/A = Not Applicable; 1/s = Once per shift; 1/d = Once per day; 1/3d = Once per three days; 1/wk = Once per week; -

J Lecend:

- 1/3 mo = Once every 3 months; 1/18 mos. = Once-every 18 months, 1/24.= Once per 24' months l1

The tollowing notes are only for Item 15 of Table 4.1.1

A channel may be taken out of service for the purpose of a check, calibration, test or maintenance without declaring the u channel to be inoperable.

co Q a. The channel functional test shall also demonstrate that control room alarm annunciation occurs if any of the.following conditions exists:

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1) Instrument indicates meat uredl levels above the alarm setpoint.

2) Instrument indicates a downscale failure.

o' 3) Instrument controls not set'in. operate mode..

4) Instrument electrical power loss.  :

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, . 3. Functional test Oncs every 24 months 'l

4. Solution volume and once/ day temperature check

5. Solution Boron-lO Each refueling outage.

enrichment Enrichment ~ analyses shall be received no later than 30 days after startup from the refueling outage. If not received within 30 days, notify NRC (within 7 days) of plans to obtain test results.

F. At specific power operation conditions, the actual control rod configuration will be compared with the expected configuration based upon appropriately corrected pact data. This comparison shall be made every equivalent full power month. The initial rod inventory

-measurement performed with equilibrium conditions are established after a refueling or major core alteration will be used as base data for reactivity monitoring during subsequent power operation throughout the fuel cycle.

G. The scram discharge volume drain and vent valves shall be verified open at least once per 31 days, except in shutdown mode *, and shall be cycled at least.one complete cycle of full travel at least quarterly.

H. All withdrawn control rods shall be determined OPERABLE by demonstrating the scram discharge volume' drain and vent valves .

OPERABLE. This will be done at least once per refueling cycle by placing the-mode switch in shutdown and by vorifying that:

The drain and vent valves close within~30; seconde after receipt of-

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a signal for control rods to scram, and

b. The scram signal can be reset and the drain and vent valves open when the scram discharge volume trip is bypassed.

BASIS: The core reactivity limitation (Specification 3.2.A) requires that core reactivity be limited such that the core could oe made subcritical at any time during the operating cycle, with the e strongest operable control' rod fully withdrawn and all other operable rods fully inserted. Compliance with this requirement can be demonstrated conveniently only at the time of refueling.

Therefore, the demonstration must'be-such that it will apply to the entire subsequent fuel cycle. The demonstration is performed with the reactor core in the cold, xenon-free condition and will show.

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• These valves may be closed intermittently for testing under administrative control.

Corrected: 12/24/84 OYSTER CREEK 4.2-2 Amendment No.: 64, 74, 7$, 124 Chenge: 25

. D. : Precuency

1. Three Type "A" overall Integrated Containment Leakage Rate Teste shall be conducted at approximately 40 month intervals during scheduled shutdowns within each 10-year service period. The third test of each set shall be conducted during the shutdown for the 10-year plant inservice inspection.

2. If two consecutive periodic Type A tests fail to meet the acceptance criteria, the subsequent Type A test shall be performed at each shutdown for refueling or approximately every 18 months whichever occurs first. This schedule will remain in effect until two consecutive Type A testa meet the acceptance criteria, at which time the' frequency of testing noted in D.1 above may be resumed.

E. Tvoe "B" and "C" Local Leak Rate Tests (LLRT)

1. Primary contairment testable penetrations (Type "B" Test) and isolation valves (Type "C" Test), except as stated below, shall be tested at a pressure of least 35 peig (P,) at intervals not to exceed 24 months. l

2. The main steam line isolation valves shall be-tested at a

. pressure of at least 20 psig at intervals not to exceed 24 months to determine if corrective action is required.

3. Isolation valve, Type "C", tests shall have each valve closed by normal operation. (e.g. no preliminary exercising or tightening of valve after closures by valve motor).

-4. Bolted double gasketed seals shall be tested whenever the

- seal is closed af ter being opened, and at intervals not -

to exceed 24 months.

5. The drywell airlock'shall be demonstrated operable by performing the following tests:

i OYSTER CREEK 4.5-3 Amendment No.: 132 Change No.: 7

t f5 c, , 40' Reactor Buildina to Sucoression Chamber Vacuum Breakers i

a. The reactor building to suppression chamber vacuum breakers and' associated instrumentation, including setpoint, shall be checked for proper operation every three months.

'b. Once every 24 months each vacuum braaker shall be tested to- l E determine that the force required to open the vacuum breaker from closed to fully open does not exceed the force specified in Specification 3.5.A.4.a. Thw air-operated vacuum breaker instrumentation shall be calibrated once every 24 months. l S. Pressure Suooression Chamber - Drywell Vacuum Breakers

a. Periodic Operability Tests once each month and fol' lowing any release of energy which would tend to increase pressure to the suppression chamber, each operable suppression chamber - drywell vacuum breaker shall be exercised.- Operation of position switches, indicators and alarms shall be verified monthly by operation of each operable vacuum breaker.

b. Ieets - Once Every 24 Months (1) All suppression chamber - drywell vacuum breakers shall be tested to determine the force required to open each valve from fully closed to fully open.

(2) The suppression chamber - drywell vacuum breaker pcsition indication and' alarms systems shall be calibrated and functionally tested.

(3) At least four of the suppression chamber - drywell vacuum breakers shall be inspected. If deficiencies are found,.

all vacuum breakers shall be inspected and deficiencies corrected such that Specifications 3.5.A.5.a can be met.

c. Tests - Once Every 20 Months A drywell to suppression chamber leak rate test shall demonstrate that with an initial differential pressure of not less than 1.0 pai, the differential pressure decay rate shall not exceed the equivalent of air flow through a 2-inch orifice.

K. Reactor Buildino

1. Secondary containment capability tests shall be condstted after isolating the reactor building and placing either Standby Gas Treatment System filter train.in operation.

2. The teste shall be performed at least once per operating cycle and shall demonstrate the capability to maintain a inch of water vacuum under calm wind conditions with a Standby Gas Treatment System Filter train flow rate of not more than 4000 cfm.

OYSTER CREEK 4.5-6 Amendment No.: 14, 52, 132

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, , Q. Shock Sueoressors (Snubbers) '

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1. Each snubber shall be demonstrated operable by performance of the following inspection programs

a. Visual Inspections All snubbers shall be visually inspected in accordance with the following schedules s No. Inoperable Snubbers Subsequent Visual-Per Insoection Period Insoection Period * .4 0 24 months 1 25% l 1 12 months i 25% ,

2 6 months 1 25% r 3, 4 124 days 1 25%

5, 6, 7 62 days 1 25%

8 or more 31 days i 25% i

• The provisions of Technical Specification 1.24 are not applicable.

The required inspection interval shall not be lengthened more than one step at a time. The snubbers may be {

categorized into two groups: those accessible and those inaccessible during reactor operation. Each group may be inspected independently in accordance with the above Li schedule. ,

b. Visual Innoection Acceotance criteria Visual inspections shall verify.(1) that there are no visible indications of datuage or impaired OPERABILITY, (2) attachments.to the foundation or supporting structure are secure, and (3) in those locations where snubber movement can be manually' induced without  !

disconnecting the snubber, that the snubber has freedom of movement and is not seized. Snubbers which appear, inoperable as a result of visual inspections may be ,

determined OPERABLE for the purpose of establishing the

next visual inspection interval, providing that the affected snubber is functionally tested in the as-found-condition and determined operable per Specification 4.5.Q.d ori4.5.Q.e as applicable'and that the cause for g the rejection has been clearly astablished and remedied L for that particular snubber.

c. Functional Tests i

At least once every 24 months, a representative sample l  ;

(10% of the total of each type of snubber in use in the  !

plant) shall be functionally tested either in place or in a bench test. For each snubber that l

l OYSTER CREEK 4.5-9 Amendment No.: 18, as, SY,lDO, 132 l

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.x O. gggbanical Snubbers Functional Test Acceotance Criteria j s

The mechanical snubber functional test shall verify that:

1. The force that initiated free movement of the snubber rod in either tension or compression is less than the e specified maximum drag force.

2.; Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression.

3. Snubber release rate, where required, is within the ,

specified range in compression or tension. For snubbers specifically required not to displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified. i

f. Snubber Service Life Monitorina A record of the service life of each snubber, the date at which the designated eervice life commences and the installation and maintenance records on which the designated service life is based shall be maintained as required by Specification 6.10.2.1.

Concurrent with the first inservice visual inspection and at least once per 24 months thereafter, the insta'2ation and [

maintenance records for each snubber shall ba riewed to verify that tha indicated service life has n .oen exceeded l or will not be exceeded prior to the next scheduled snubber' i

-- service life review. If the indicated service life will be exceeded prior to the next scheduled snubber service life. .i

review, the snubber service life shall'txa re-evaluated or L the snubber shall be replaced or reconditioned so as to extend its cervice life beyond the date of the next scheduled servico life review.- This re-evaluation,

l. replacoment or reconditioning-shall be indicated in the records. Service life shall.not at any time affect l reactor 1 l

l operations.

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GX3TER CREEK 4.5-11 Amendment No.: 100, 132

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4.7 AUXILIARY ELECTRICAL POWER-Aeolicability - Applies.to surveillance requirements of the auxiliary electrical supply.

gbiective: To verify the availability of the auxiliary electrical supply.

goecifications ' A. Diesel Generator

1. Each diesel generator shall be started and loaded to not less than 20% rated power every two weeks.

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2. The two djesel generators shall be automatically actuated and functionally tested once every 24 '!

months. This shall include testing of the~ diesel l generator load sequence timers listed in Table p 3.1.1.

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3. Each diesel generator shall be given a thorough inspection at least once per 24 months during j l

shutdown. l

4. The diesel generators' fuel supply shall be checked j following the above tests. j i

5. The diesel generators' starting batteries shall be l tested and monitored the same as the station  !

batterios, Specification 4.7.b.

i B. Station Batteries  ;

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1. Weekly surveillance will be performed to verify the

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followings

a. The active metallic surface of the plates shall ,

L be fully covered with electrclyte in all  !

batteries, i n qua t 2O 1 e and  !

c. The overall battery voltage is greater than or j equal to 120 volts (Diosel battery; 112 volts).

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d. The pilot cell specific gravity, corrected to 77'F, is greater than or equal to 1.190.

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2. Quarterly Surveillance will be performed to verify the following:

a. The active metallic surface of the plates shall be fully covered with electrolyte in all ,

batteries.

b. The voltage of each connected cell is greater than or equal to 2.0 volte under float charge and OYSTER CREEK 4.7-1 Amendment No.: 15, 55, 60 .

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activities within the area snd who will perform periodic radiation surveillance at the frequency in the RWP. The surveillance frequency will be established by the Director responsible for Radiological Controls.

6.33.2 Specification 6.13.1 shall also apply to each high radiation area in which the intensity of radiation is greater than 1,000 mrem /hr. In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys'shall be maintained under the administrative control of operations and/or radiation protection supervision on duty.

6.14 ENVIRQFMENTAL OUALIFICATION A. By no later than June 30, 1982 all safety-related electrical equipment in j the facility shall be qualified in accordance with the provisions of: Division  ;

of Operating Reactors " Guidelines for Evaluating Environmental Qualification of  !

Claen IE Electrical Equipment in Operating Reactors" (DOR Guidelines); or, j NUREG-0588 " Interim Staff position on Environmental Qualification of

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Safety-Related Electrical Equipment," December 1979. Copies of these documento )

are attached to Order for Modification of License DPR-16 dated October 24, j 1980.  !

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n. By no later than December 1, 1980, complete and auditable records must be  !

available and maintained at a central location which describe the-environmental ] :

qualification method used for all safety-related electrical equipment in sufficient detail.to document the degree of compliance with the DOR Guidelinee or NUREG-0588. Thereafter, such records should be updated and maintained current as equipment is replaced, further tested, or otherwise further qualified.

6.15 INTEGRITY OF SYSTEMS OUTSIDE CONTAINMENT The licennee shall implement a program to reduce leakage from eyotema outside containment that would or could contain highly radioactive fluida during a serioun transient or accident to as low ao practical levelo. This program .}

shall include the followings l 1

1) Provisions ostablishing preventative maintenance and periodic-visual 1 inspection requiremento, and

2) System leak test requirements, to the extent permitted by system design and radiological conditione, for each system at a frequency of once every 24 months. The systems subject to this testing are (1) Core Spray, (2)  ;

Containment Spray, (3) Reactor Water Cleanup, (4) Isolation Condenser, and l

,(5) Shutdown Cooling.

6.16 IODINE MONITORING k

l The licenoce shall implement a program which will ensure the capability to s accurately determine the airborne iodine concentration in vital areno* under f accident conditions. This program chall include the following:

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a. Training of personnel, j

• Arene requiring personnel access for establishing hot shutdown condition.

OYSTER CREEK 6-16 Amendment No.: 6d,109,134 f

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