ML20154J561

Proposed Tech Specs,Changing Local Leak Rate Test Requirements for Containment Penetrations

ML20154J561
Person / Time
Site:	Rancho Seco
Issue date:	09/19/1988
From:	SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:
Shared Package
ML20154J554	List: ML20154J552 ML20154J561
References
NUDOCS 8809230068
Download: ML20154J561 (4)

Text

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ATTAOINENT II Technical Specification Pages Affected by Proposed Amendment No. 172 Remove Insert 3-39 3-39 4-17 4-17 4-18 4-18 I

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS 1.imiting Conditions for Operation l 3.6 REACTOR BUILDIE l

l 6policability

- All modes from HEATUP-COOLDOHN through POWER OPERATION, inclusive. ,

Obiectilt l

To assure containment integrity. , l Scecification i I 3.6.1 Containment integrity shall be maintained.  !

b ACLLDD 4 i

/ Without primary CONTAINHENT INTEGRITY, restore CONTAINHENT INTEGRITY within I 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 d

SHUTDOWN within the fo110 wing 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.  ;

r 3.6.2 Containment integrity shall be maintained when the reactor coolant r 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 subtritical by less than 1 percent Ak/k shall not be made  :

4 by control rod motion or boron dilution when6ver the containment ,

i integrity is not intact. l t

! 3.6.4 The reactor shall not remain critical if the Reactor Building i internal pressure exceeds 1.5 psig or vacuum exceeds -1,5 psig, i l

! 3.6.5 Prior to criticality following refueling shutdown, a check shall be l made to confirm that all manual f.ontainment isolation valves which  !

should be closed are closed.

) 3.6.6 The safety features containment isolation valves specified in Table '

3.6-1 shall oe OPERABLE with closure times as shown in Table 3.6-1.

i If, under reactor critical operating conditions an automatic  !

containment isolation valvo is determined to be inoperable, the t i other r.ontainment isolation valve in the line shall be tested to i ensure operaollity. 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 I

! in a safety features position. t

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Proposed 1 Amendment No. 31, 97, 172 3-39

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 4.4.1.2 Local _ LtdJLge 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) Reactor coolant pump seal inlet line (9) Reactor Building equalizing line (10) Deleted (11) Deleted (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 line (18) Pressurizer relief tank gas sampit line (19) Reactor coolant system vent header (20) Pressurizer relief tank altrogen supply line (21) Pressurizer sample line (22) Reactor coolant drain tank header (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 (M) Core Flood Tank drain and sample i (31) Steam Generator drain  :

(32) Auxiliary steam (33) Component cooling water inlet (34) Component cooling water outlet (35) CR0 cooling water return i

Proposed ,

Amendment No. 11, 97, 172 1 4-17

T- . 1 RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance 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 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 />.

4.4.1.2.3 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' O-ring seals shall be 9.5 1 0.5 psig. (Appendix J of 10 CFR 50 is exempted)

(1) The leak rate (Lt) 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 contairment 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.  !

Proposed Amendment No. II, 49, 72, 97, 172 l 4-18

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