ML20053C641

Proposed Tech Specs Changes Modifying Language of Section 4.0.3 & 4.0 to Reflect Current Language in C-E STS

ML20053C641
Person / Time
Site:	Arkansas Nuclear
Issue date:	05/28/1982
From:	ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML20053C605	List: ML20053C604 ML20053C641
References
NUDOCS 8206020418
Download: ML20053C641 (4)

Text

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4 SURVEILLANCE STANDARDS Specified surveillance intervals may be adjusted plus or minus 25 percent to accommodate normal test and surveillance schedules. The maximum combined interval for any 3 consecutive tests shall not exceed 3.25 times the specified surveillance interval.

Performance of a surveillance requirement within the specified time interval shall constitute compliance with operability requirements for a Limiting Condition for Operation.

Failure to perform a surveillance requirement within the specified time interval shall require immediate action to initiate testing to verify the surveillance requirement. Failure to complete the surveillance requirement within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following discovery of non performance of the required testing shall constitute a failure to meet the operability requirements for the applicable Limiting Condition for Operation.

Exceptions to these reguirements are stated in the individual specifications. Surveillance requirements do not have to be performed on inoperable equipment.

Surveillance requirements are not applicable when the plant operating conditions are below those requiring operability of the designated component. However, the required surveillance must be performed prior to reaching the operating conditions requiring operability. For example, instrumentation requiring twice per week suiveillance when the reactor is critical need not have the required surveillance when the reactor is shutdown.

4.1 OPERATIONAL SAFETY ITEMS Applicability Applies to items directly related to safety limits and limiting conditions for operation.

Objective l

l To specify the minimum frequency and type of surveillance to be applied i to unit equipment and conditions.

67 8206020418 820528 PDR ADOCK 05000313 P PDR

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Specification

a. The minimum frequency and type of surveillance required for reactor protective system and engineered safeguards system instrumentation ,

when the reactor is critical shall be as stated in Table 4.1-1.

b. Equipment and sampling test shall be performed as detailed in Tables 4.1-2 and 4.1-3.

c. Discrepancies noted during surveillance testing will be corrected and recorded.

d. A power distribution map shall be made to verify the expected power distribution at periodic intervals at least every 10 effective full power days using the incore instrumentation detector system.

Bases

. Check Failures such as blown instrument fuses, defective indicators, faulted amplifiers which result in " upscale" or "downscale" indication can be easily recognized by simple observation of the functioning of an instrument or system. Furthermore, such failures are, in many cases, revealed by alarm or annunciator action. Comparison of output and/or state of inde)endent channels measuring the same variable supplements this type of auilt-in surveillance. Based on experience in operation of both conventional and nuclear plant systems, when the plant is in operation, the minimum checking frequency stats is deemed adequate for reactor system instrumentation.

Calibration Calibration shall be performed to assure the presentation and acquisition of accurate information. The nuclear flux (power range) channels shall be calibrated at least twice weekly (during steady state operating conditions) against a heat balance standard to compensate for instrumentation drift. During non-steady state operation, the nuclear flux channels shall be calibrated daily to compensate for instrumentation drift and changing rod patterns and core physics parameters.

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l SURVEILLANCE REQUIREMENTS  !

4.0.1 Surveillance Requirements shall be applicable during the OPERATIONAL MODES or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement.

4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with:

a. A maximum allowable extension not to exceed 25% of the surveillance interval, and

b. A total maximum combined interval time for any 3 consecutive surveillance intervals not to exceed 3.25 times the specified surveillance interval.

4.0.3 Performance of a Surveillance Requirement within the specified time interval shall constitute compliance with OPERABILITY requirements for a Limiting Condition for Operation and associated ACTION statements.

Failure to perform a Surveillance Requirement within the specified time interval shall require immediate action to initiate testing to verify the Surveillance Requirement. Failure to complete the Surveillance Requirement within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following discovery of non performance of the required testing shall constitute a failure to meet the OPERABILITY requirements for the applicable Limiting Condition for Operation.

Exceptions to these requirements are stated in the individual specifications. Surveillance Requirements do not have to be performed on inoperable equipment.

4.0.4 Entry into an OPERATONAL MODE or other specified applicability condition shall not be made unless the Surveillance Requirement (s) associated with the Limiting Condition for Operation have been performed within the stated surveillance interval or as otherwise specified.

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4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2 and 3 components shall be applicable as follows:

a. During the time period:

1. From issuance of the Facility Operating License to the start of facility commercial operation, inservice testing of ASME Code Class 1, 2 and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code 1974 Edition, and Addenda through Summer 1975, except where specific written relief has been granted by the Commission.

2. Following start of facility commercial operation, inservice inspection of ASME Code Class 1, 2 and 3 components and inservice testing of ASME Code Class 1, 2 and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g)(6)(i).

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