ML20149E597

Proposed Tech Spec 3.6,consolidating Applicability Requirement for Containment Integrity in Applicability Statement

ML20149E597
Person / Time
Site:	Rancho Seco
Issue date:	01/06/1988
From:	SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:
Shared Package
ML20149E590	List: ML20149E588 ML20149E597
References
TAC-60162, NUDOCS 8801130399
Download: ML20149E597 (2)

Text

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.6 REACTOR BUILDING Acolicability 164-~ All modes from HEATUP-C00LD0HN thru POWER OPF. RATION, inclusive.

Objective To assure containment integrity during startup and operation.

Soecification 164- 3.6.1 Containment integrity shall be maintained.

Action Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour or be in at least HOT SHUT 00HN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD

- SHUTDOHN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

3.6.2 Containment integrity shall be maintained when the reactor coolant system is open to the containment atmosphere and the requirements for a refueling shutdown are not met.

3.6.3 Posith'e reactivity insertions which would result in the reactor being suurritical by less than 1 percent ok/k shall not be made by control .od motion or boron dilution whenever the contair. ment integrity is 30t intact.

3.t.4 The reactor shhl: not remain critical if the Reactor Building internal pressure axceeds 1.5 psig or vac':um exceeds -1.5 psig.

3.6.5 Prior to criticality following refueling shutdown, a check shall be made to confirm that all manual containment isolation valves which should be closed are -losed.

3.6.6 The safety features containment isolation valves specified in Table 3.6-1 shall be OPERABLE with closure times as shown in Table 3.6-1.

If, under reactor critical operating conditions an automatic containment isolation valve is determined to be inoperable, the other containment isolation valve in the line shall be tested to insure operability. If the inoperable valve is not restored within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the reactor shall be brought to the cold shutdown condition within an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or the valve will be placed in a safety features position.

8801130399 B90106 PDR ADOCK 0:000312 p PDR Proposed Amendment No. 164, Supplement 3 3-39

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 4.4 1.2 Local Leakage Rate Tests 4.4.1.2.1 Scope of Testing The local leak rate shall be measured for each of the following components:

(1) Persc,nel hatch (2) Emergency hatch (3) Equipment hatch seals (4) Fuel transfer tube seals (5) Fuel transfer tube shroud bellows (6) Reactor Building normal sump drain line (7) Reactor coolant pump seal water outlet line (8) Reactor coolant pump seal inlet line (9) Reactor Building equalizing line (10) Decay Heat Removal inlet lines (11) Reactor Building spray inlet lines (12) High pressure injection lines (13) Electrical penetrations (14) Reactor Building purge inlet line (15) Reactor Building purge outlet line (16) Reactor Building atmosphere sample lines (17) Letdown to purification demineralizer line (18) Pressurizer relief tank gas sample line (19) Reactor coolant system vent header (20) Pressurizer relief tank nitrogen supply line (21) Pressurizer sample line (22) Reactor coolant drain tank header l (23) Reactor Building hydrogen sample line (24) H2 recombiner penetration 164- (25) CRD cooling water supply (26) Reactor Building nitrogen supply header (27) Demineralized water (28) Service air (29) Core Flood Tank fill and nitrogen supply (30) Core Flood Tank drain and sample l

(31) Steam Generator drain (32) Auxiliary steam (33) Component cooling water inlet (34) Component cooling water outlet (35) CRD cooling water return Proposed Amendment No. 164, Supplement 3 4-17