ML20072A573
| ML20072A573 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 01/14/1983 |
| From: | ARKANSAS POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20072A551 | List: |
| References | |
| NUDOCS 8301240065 | |
| Download: ML20072A573 (3) | |
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 test shall not exceed 3.25 times the specified surveillance interval.
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 surveillance when the reactor is critical need not have the required surveillance when the reactor is shutdown.
Failure to perform a Surveillance Requirement within the specified time interval shall constitute a failure to meet the OPERABILITY requirements for a 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.
4.1 OPERATIONAL SAFETY ITEMS Applicability Applies to items directly related to safety limits and limiting conditions for operation.
Objective To specify the minimum frequency and type of surveillance to be applied to unit equipment and conditions.
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 l
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 l
10 effective full power days using the incore instrumentation detector system.
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l 67 8301240065 830114
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PDR ADOCK 05000313 P
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Bases The provisions of this specification set forth the criteria for determination of compliance with the OPERABILITY requirements of the Limiting Conditions for Operation.
Under this criteria, equipment, systems or components are assumed to be OPERABLE if the associated surveillance activities have been satisfactorily performed within the specified time i
interval.
Nothing in this provision is to be construed as defining equipment, systems or components OPERABLE, when such items are found or knawn to be inoperable although still meeting the Surveillance Requirements.
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 d*
independent channels measuring the same variable supplements this type of built-in surveillance.
Based on experience in operation of both conventional and nuclear plant systems, when the plant is in operation, the minimum checking frequency stated is deemed adequate for reactor system l
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 nonsteady 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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67a I
1 SURVEILLANCE REQUIREMENTS i
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 j
specified item interval with:
a.
A maximum allowable extension not to exceed 25% of the surveillance interval, and 2
i b.
A total maximum combined interval time for any 3 consecutive j
surveillance intervals not to exceed 3.25 times the specified surveillance interval.
4.0.3 Failure to perform a Surveillance Requirements within the specified time interval shall constitute a failure to meet the OPERABILITY requirements for a 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.
1 4.0.4 Entry into an OPERATIONAL 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 4
within the stated surveillance interval or as otherwise specified.
4 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:
l 1.
From issuance of the Facility Operating License to the start of facility commercial operation, inservice testing of ASME i
Code Class 1, 2 and 3 pumps and valves shall be performed in 1
acco. dance with Section XI of the ASME Boiler and Pressure j
Code 1974 Edition, and Addenda through Summer 1975, except where specific written relief has been granted by the Commission.
E 2.
Following start of (acility 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 l
the ASME Boiler and Pressure Vessel Code and applicable Addenda as requireo by 10CFR50, Section 50.55a(g),~except where lpecific written relief has been granted by the Commission pursuant to 10CFR50, Section 50.55a(g)(6)(i).
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