ML20205R868

Proposed Tech Specs Re Local Leakage Rate Tests & Reactor Bldg Containment Integrity

ML20205R868
Person / Time
Site:	Rancho Seco
Issue date:	11/04/1988
From:	SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:
Shared Package
ML20205R867	List: ML20205R863 ML20205R868
References
NUDOCS 8811100154
Download: ML20205R868 (4)

Text

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ATTACHMENT II Te',hnical Specificction Pages Affected by Proposed Amendment No. 172 Revision 1 BLmott IMtLt 3-39 3-39 4-17 4-17 4-18 4-18 l

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0311100154 FDR SG1104ADOCK F DC Ob000311 P

, .- 1 RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation

, . 6 MF J ^4G epolicahl. lit All modes f -

COOLDOHN through POWER OPERATION, inclusive.

Objectiv.g To assure containment integrity.

Soeci fica. tion 3.6.1 Containment integrity shall be maintained.

fC11Da  !

Without primary CONTAINHENT INTEGRITY, restore CONTAINHENT INTEGRITY within one hour or be in at least HOT SHUTDOHN 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 />, s 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 Positive reactivity insertions which would result in the reactor being subcritical by less than 1 percent ak/k shall not be made by control rod motion or boron dilution whenever the containment integrity is not intact.

3.6.4 The reactor shall not remain critical if the Reactor Building internal pressure exceeds 1.5 psig or vacuum exceeds -1.5 psig.

3.0.5 Prior to criticality following refueling shutdown, a check shall be made to confirm that all manual containment isolation valves which ,

should be closed are closed.  !

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

If, under reactor criticc.) operating conditions an automatic containment isolation valve is determined to be inoperable, the other containment isolation valve in the line sht11 be tested to ensure operability. If the inoperablo 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 reac ,r 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.

Proposed

. Amendment !l0. 31, 97,172. Rev. I

! 3-39

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) Personnel 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) Resctor coolant pump seal inlet line (9) Rwactor Building equalizing line (10) Delet3d l (11) Reactor Building spray inlet lines (12) Deleted (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 lint (18) Pressurizer relief tank gas sample line (19) Reactor coolant system vent header (20) Pressurizer relief tank nitrogen supply lire (21) Pressurizer sample line (22) Reactor coolant drain tank haader (23) Reactor Building hydrogen sample line (24) H2 recombiner penetration (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 (31) Steam Generator drain (32) Auxiliary steam (33) Component cooling water inlet (34) Component cooling water outlet ,

(35) CRD cooling water return l l

l Proposed j Amendment No. II, 97, 172 Rev. 1 .

4-17 l 1

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I RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillante' Standards 4.4.1.2.2 Conduct of Tests The containment leakage rates shall be demonstrated at the specified test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 50 using _

the methods and provisions of ANSI N45.4-1972 and a test pressure, Pa, of 52 psig with an acceptance criterion of 0.06 weight percent of the Reactor Building atmosphere held at that i pressure for a minimum of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. [

4.4.1.F.3 Test Frequency Local leak detection tests shall be performed at a frequency of not more than 24 months, except that: l (a) The equipment hatch and fuel transfer tube seals shall be additionally tested after each opening. This testing shall be done prior to containment integrity being required by Specification 3.6.1.

(b) the personnel and emergency hatches shall be tested between the inner and outer doors at a pressure not less than 52 psig semiannually.

(c) 'The personnel and emergency hatches' inner and outer door 0-ring seals shall be tested within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after each opening when containment integrity is required in Specification 3.6.1. Test pressure for the personnel and emergency hatches' 0-ring seals shall be 9.510.5 psig. (Appendix J of 10 CFR 50 is exempted) ,

(1) The leak rate (L t) established at the reduced pressure of 9.5 1 0.5 psig shall be extrapolated to the leak rate (La) that will occur at the calculated peak containment pressure of 52 psig using the following formula:

La - 5.2 Lt (2) The extrapolated leak rate (La) will be added to the local leak rates established for the other .

components and the total must meet the criterion of 4.4.1.2.2.

• Exemption to Appendix J of 10 CFR 50.

t Proposed Amendment No. 11, 49, 72, 97, 172, Rev. 1 4-18

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