ML20086R157
| ML20086R157 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 07/25/1995 |
| From: | WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | |
| Shared Package | |
| ML20086R152 | List: |
| References | |
| NUDOCS 9507310038 | |
| Download: ML20086R157 (2) | |
Text
4.,
/Attcchment IV to ET 95-0068 Page 2 of:3 APPHCABILITY SURVEILLANCE REQUIREMENTS p
- 4.0.1 Surveillance Requirements shall be met 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 surveillance interval with a maximum allowable extension not to exceed 25% of the specified interval.
4.0.3 Failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by Specification 4.0.2, shall constitute noncompliance with the OPERABILITY requirements for a Limiting Condition for Operation. The allowable outage time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed. The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit the completion of the surveillance when the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Surveillance Requirements do not have to be performed on ir operable equipment.
4.0.4 Entry into an OPERATIONAL MODE or oth er specified condition shall not be made unless the Surveillance Requirement (s) associated with a Limiting Condition of Operation has been performed within the stated surveillance interval or as otherwise specified. This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements.
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. 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 Part 50, Section 50.55a(g), rept etere r!Sc : 4.cn rel+eibc ben granted by t% Cemiccion-perent !c 10 CFR PM 50, Sr"^n M.552'g)(6)(i)i t
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WOLF CREEK - UNIT 1 3/4 0-2 AMENDMENT NO. 44,67 I
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9so7sioOss 950725 PDR ADOCK 05000482 P.
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~ Attachment IV to ET 95-0068 Page 3 of'3 BASES COLD OVERPRESSUEE (Continued)
RCP eliminates the possibility of a 50*F difference existing between indicated and actual RCS temperature as a result of heat transport effects. Considering instrutnent uncertainties only, an indicated RCS temperature of 350'F is sufficiently high to allow full RCS pressurization in accordance with Appendix G limitations. Should an overpressure event occur in these conditions, the pressurizer safety valves provide acceptable and redundant overpressure protection.
The Maximum Allowed PORV Setpoint for the Cold Overpressure Mitigation System will be updated based on the results of examinations of reactor vessel materlat irradiation surveillance specimens performed as required by 10 CFR Part 50, Appendix H.
3LLL10_STRUCIUR_ L INTEGRITY A
The inservice inspection and testing programs for ASME Code Class 1,2, and 3 components ensure that the structuralintegrity and operational readiness of these components will be maintained at an acceptable level throughout the life of the plant. These programs are in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR Part 50.55a(g)exceptwhere epecif:c writtemelismas beengranted by4he ComW 9 pursuan44040CFRPart40,55a(g)(6)(i),
Components of the Reactor Coolant System were designed to provide access to permit inservice inspections in accordance with Section XI of the ASME Boiler and Pressure Vessel Code,1974 Edition and Addenda through Summer 1975.
314.4.1 1 REACTOR COQlANT SYSTEM VENTS Reactor Coolant System vents are provided to exhaust noncondensible gases and/or steam from the Reactor Coolant System that could inhibit natural circulation core cooling. The OPERABILITY of a reactor vessel head vent path ensures the capability exists to perform this function.
The va!ve redundancy of the Reactor Coolant System vent paths serves to minimize the probability of inadvertent or irreversible actuation while ensuring that a single failure vont valve power supply or control system does not prevent isolation of the vent path.
The function, capabilities, and testing requirements of the Reac;or Coolant System vents are consistent with the requirements of item II.B.1 of NUREG-0737," Clarification of TMI Action Plan Requirements," November 1980.
WOLF CREEK - UNIT 1 B 3/4 4-15 Amendment No. 40,57 1
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