ML17291A319

Proposed Tech Specs 4.0.5 Re Guideliness for Inservice Insp & Testing Program

ML17291A319
Person / Time
Site:	Columbia
Issue date:	08/08/1994
From:	WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
Shared Package
ML17291A318	List: ML17291A317 ML17291A319
References
NUDOCS 9408160297
Download: ML17291A319 (4)

Text

APPLICABILITY cow~oL<Eo co~v t SURVEILLANCE RE UIREHENTS 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL CONDITIONS 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 25K of the specified surveillance interval.4.0.3 Failure to perform a Surveillance Requirement within the allowed surveil-lance interval defined by Specification

4.0.2 shall

constitute noncompliance with the OPERABILITY requirements for a Limiting Condition for Opera~ion.

The 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 inoperable equipment.

4.0.4 Entry

into an OPERATIOHAL CONDITION or other specified applicable condition shall not be made unless the Surveillance Requirement(s) associated with the Limiting Condition for Operation have been performed within the applica.ble surveillance interval or as otherwise specified.

This provision shall not prevent passage through or to OPERATIONAL CONDITIONS as required to comply with ACTION requirements.

4.0.5 Surveillance

Requirements for inservice'inspection and testing of ASHE Code Class 1, 2, 5 3 components shall be applicable as follows: a.Inservice inspection of ASHE Code Class 1, 2, and 3 components and"'nservice testing of ASHE Code Class 1, 2, and 3 pumps and valves shall be performed in accordance with Section XI of the ASHE Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a b.Surveillance intervals specified in Section XI of the ASHE Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASHE Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:

ASHE Boiler and Pressure Vessel Code and'applicable Addenda~terminology for inservice ins ection and testin activities

.Meekly Honthly quarterly or every 3 months Semiannually or every 6 months Every 9 months Yearly or annua 8 i@~'n,ia,lip 4 i e<e~g MASHIHGTO T 0-2 9408ih0297 940808 PDR ADOCK 05000397 PDR , J Required frequencies for performing inservice~inspection and testing activities At least once Per 7 days At least once per 31 days At least once per 92 days At least once per 184 days At least once per 276 days e onep 6 h4'1~k>..7Si dy s Amendment o.8 CONTROLLED COPY APPLICABILITY BASES (Continued)

When a shutdown is required to comply with ACTION requirements, the provisions of Specification 4.0.4 do not apply because this would delay placing the facility in a lower CONOITIQN of operation.

Speci ication 4.0.5 es ablishes the requirement that inservice inspection of ASHE Code Class 1, 2, and 3 components and inservice tes ing of ASME Code Class 1, 2, and 3 pumps and valves shall be performed in accordance with a periodically updated version of Section XI of the ASHE Boiler and Pressure Vessel Code and Addenda as re uired b 10 CFR 50.55a.This specificatson includes a clarifica>on of the frequencies for per,orming the inservice inspection and testing activities required by Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda.This clarificat'.on is provided to ensure consistency in surveillance intervals throughout the Technical Specifications and to remove any ambiguities relative to the frequencies for performing the required inservice inspection and testing activities.

Under the terms of this specification, the more restrictive requirements of the Technical Specifications take precedence over the ASHE Boiler and Pressure Vessel Code and applicable Addenda.The requirements of'pecification 4.0.4 to perform surveillance activities before entry into an OPERATIONAL CONDITION or other specified condi ion takes precedence over the ASHE Boiler and Pressure Vessel Cade provision that allows pumps and valves to be tested up to one week after return to normal operation.

The Technical Specification definition of OPERABLE does not allow a grace period before a component, which is not capable of performing its specified function, is declared inoperable and takes precedence over the ASME Boiler and Pressure Vessel Code provision that allows a valve o be incapable of performing its specified function for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before being declared inoperable.

Zevi ee+:'/i<S<~i./l/.Co z-Pa-oyer"rP 7'~,,(/j'I'/Z~Zg</~;.../-//4;s peragr<elrvl<ai e impi/r F<c WASHINGTON NUCLEAR" UNIT 2 B 3/'4 0-5 Amendment No 88

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~REACTOR COOLANT SY I CONTROLLED COPY g BASES.PRESSURE/TEMPERATURE LIMITS (Continued)

The pressure-temperature limit lines shown in Figures 3.4.6.1 and 3.4.6.l.c for reactor criticality and for inservice leak and hydrostatic testing have been provided to assure compliance with the minimum temperature requirements of Appendix G to 10 CFR Part 50 for reactor criticality and for inservice leak and hydrostatic testing.3/4.4.7 HAIN STEAM LINE ISOLATION VALVES Oouble isolation valves are provided on each of the main steam lines to minimize the potential leakage paths from the containment in case of a line break.Only one valve in each line is required to maintain the integrity of the containment, however, single failure consider ations require that two valves be OPERABLE.The surveillance requirements are based on the operating history of this type valve.The maximum closure time has been selected to contain fission products and to ensure the core is not uncovered following line breaks.The minimum closure time is consistent with the assumptions in the safety analyses to prevent pressure surges.3/4.4.8 STRUCTURAL INTEGRITY The inspection programs for ASHE Code Class I, 2 and 3 components ensure that the structural integrity of these components will be maintained at an acceptable level throughout the life of the plant.Access to permit inservice inspections of components of the reactor coolant system is in accordance with Section XI of the ASME Boiler and Pressure Vessel Code 1974 Edition and Addenda through Summer 1975.The inservice inspection program for ASHE Code Class I, 2 and 3 compo-nents will be performed in accordance with Section XI of the ASME Boiler a d essur sel Code and a lic bi~den as required b 10 CFR 50.55 88A=g~R~.4.9 ESIOUAL HEAT REMOV A single shutdown cooling mode loop provides sufficient heat removal capability for removing core decay heat and mixing to assure accurate tempera-ture indication, however, single failure considerations require that two loops be OPERABLE or that alternate methods capable of decay heat removal be demonstrated and that an alternate method of coolant mixing be in operation.

WASHINGTON NUCLEAR-UNIT 2 B 3/4 4-5 Amendment No.~322