ML19327B448

Proposed Tech Specs Covering Extending Surveillance Requirements Up to 25% to Accomodate Normal Test Schedules

ML19327B448
Person / Time
Site:	Arkansas Nuclear
Issue date:	10/19/1989
From:	ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML19327B447	List: ML19327B446 ML19327B448
References
NUDOCS 8910310212
Download: ML19327B448 (6)

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l l 4 SURVHILLANCE REQUIREMENTS ]

Specified surveillance intervals may be extended up to 25 percent to accommodate normal test and surveillance schedules. Surveillance l requirements are not applicable when the plant operating conditions are i below those requiring operability of the designated component. However, the j l requiren surveillance must be performed prior to recching the operating j conditions requiring operability. For example, instrumentation requiring  !

twice par week surveillance when the reactor is critical need not have the r required surveillance when the reactor is shutdown. j Inservice inspection of ASME Code Class 1, 2, 3 components shall be I performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50 Section 50.55n(g), except where specific written relief has been granted by the NRC pursuant to 10 CFR 50, Section 50.55a(g)(6)(1).

Failtre to perform a Surveillance Requirement within the specified time ,

intervs1 shall constitute a failure to meet the OPERABILITY requirements  :

for a Limiting Condition for Operation. Exceptions to these requirements i are stated in the individual specifications. Surveillance Requirements do not have to be performed on inoperable equipment.

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

Ob.iective 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 i 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 l Table 4.1-2 and 4.1-3.

c. Discrepancies noted during surveillance testing will be 1

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.

Amendment No. 25, 75, 77 67

o Bases The provisions of this specification set forth the criteria for i determination of compliance with the OPERABILITY requirements of the '

Limiting Cond'tions for Operation. Under these criteria, equipment,. i systems or components are assumed to be OPERABLE if the associated ,

surveillance activities have been satisfactorily performed within the -

specified time interval. Nothing in this provision is to be construed as i defining equipinent, systems or componentb OPERABLE, when such items are i found or known to be inoperable although still meeting the Surveillance  ;

Requirements. l 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 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 i instrumentation.

Calibration j 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 drif t,.  !

During nonsteady state operation, the nuclear flux channels shall be l calibrated daily to compensate for instrumentation drif t and changing rod patterns and core physics paramoters. i f

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h SURVEILLANCE REOUIREMENTS (Continued) _

4.0.1 Surveillance Requirements shall be applicable during the OPERATIONAL l L' MODES or other conditions specified for individual Limiting Conditions for l Operation unless otherwise stated in an individual Surveillance Requirement, i 4.0.2 Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval, s I l

4.0.3 Failure to perform a Surveillance Requirement within the specified time ,

interval shall constitute a failure to meet the OPERABILITY requirements l

for a Limiting Condition for Operation. Exceptions to these requirements  ;

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

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 within the stated surveillance interval or as otherwise specified.

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: I

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 1 Commission.

2. Following start of facility commercial operation, inservice I 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 l 50.55a(g)(6)(i).

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) ARKANSAS - UNIT 2 3/4 0-2 Amendment No. 42 l

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l. . APPLICABILITY BASES 4.0.1 This specification provides that surveillance activities necessary to insure the Limiting Conditions for Operation are met and will i

be performed during the OPERATIONAL MODES or other conditions for which the Limiting Conditions for Operation are applicable. Provisions for additional surveillance activities to be performed without regard to the applicable OPERATIONAL MODES or other conditions are provided in the individual Surveillance Requirements. Surveillance Requirements for Special Test Exceptions need only be performed when the Special Test Exception is being utilized as an exception to an individual specification.

4.0 2 Specification 4.0.2 establishes the limit for which the specified time interval for Surveillance Requirements may be extended. It permits an allowable extension of the normal surveillance interval to facilitate surveillanco scheduling and consideration of plant operating conditions that may not be suitable for conducting the surveillance; e.g. , transient conditinns or other ongoing surveillance or maintenanco activities. It also provides flexibility to accommodate the length of a fuel cycle for surveillances that are performed at each refueling outage and are specified with an 18-month surveillance interval. It is not intended that this provision be used repeatedly as a convenience to extend surveillance intervals beyond that specified for surveillances that are not performed during refueling outages.

The limitation of Specification 4.0.2 is based on engineering judgement and the recognition that the most probable result of any particular surveillance being performed is the verification of conformance with the Surveillance Requirer 6ents. This provision is sufficient to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond that obtained from the specified surveillance intervals.

4.0.3 The prc. visions 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 performer! within the specified time interval. Nothing in this provision is to be construed as defining equipment systems or components OPERABLE, when such items are found or known to be inoperable although still meeting the Surveillance Requirements.

4.0.4 This specification ensures that the surveillance activities associated with a Limiting Condition for Operation have been performed within the specified time interval prior to entry into an OPERATIONAL MODE or other applicable condition. The intent of this provision is to ensure that surveillance activities have been satisfactorily demonstrated on a current basis as required to meet the OPERABILITY requirements of the Limiting Condition for Operation.

ARKANSAS - UNIT 2 B 3/4 0-2 Amendment No.