ML20248E922

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Amend 102 to License DPR-54,changing Tech Specs to Permit one-time Extension for Certain Local Leak Rate Tests to Cycle 8 Refueling Outage & Revising Surveillance Period for Local Leak Rate Tests on DHR Suction Piping
ML20248E922
Person / Time
Site: Rancho Seco
Issue date: 03/29/1989
From: Knighton G
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20248E879 List:
References
NUDOCS 8904120403
Download: ML20248E922 (7)
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  1. j %91 UNITED STATES l' ec/'15 NUCLE AR REGULATORY COMMISSION WASHINGTON, D. C. 20555 5 /

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.,,..c k SACRAMENTO MUNICIPAL UTILITY DISTRICT DOCKET NO. 50-312 RANCHO SEC0 NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE b

Amendment No. 102 License No. DPR-54

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Sacramento Municipal Utility District (the licensee) dated December 30, 1988, as supplemented March 6,1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I;

- B. The f acility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's reguhtions and all applicable requirements have been satisfied.

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2. Accordicci) , the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-54 is hereby amended to read as follows:

(2)TechnicalSpecifications The Technical Specifications contained in Appendices A and C, as revised through Amendment No.102, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license atencment is effective as of its date of issuance.

FOR THE NUCLEAR REGUL TORY COMMISSION

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George/ 4. Knighton/ irector Project Directorate V Division of Reactor Projects - III, IV, V and Special Projects

Attachment:

Changes to the Technical Specifications Date of Issuance: March 29, 1989

ATTACHMENT TO LICENSE AMENDMENT N0. 102

3) FACILITY OPERATING LICENSE NO. DPR-54 dd,I DOCKET NO. 50-312 i

i Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

Remove Insert 4-0 4-0 4-17 4-17 4-18 4-18 4-32 4-32

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards

4. SURVEILLANCE STANDARDS 4.0 General Surveillance Requirements 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL HDDES or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement.

4.0.2 Failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by Specification 1.9, shall constitute noncompliance with the OPERABILITY requirements for a Limiting Condition for Operation. The time limits of the Action including time requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed. The Action including time 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 including time requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Exceptions to these requirements are stated in the individual specifications and Table 4.0-1.

4.0.3 Entry into an OPERATIONAL HDDE or other specified condition shall not be made unless the Surveillance Requirement (s) associated with the Limiting Condition for Operation have been performed within the stated surveillance interval or as otherwise specified.

Exceptions to these requirements are stated in the individual specifications and Table 4.0-1.

4.0.4 By special reference to this section, those surveillance which must be performed on or before August 1, 1989 and are designated as refueling interval or 24-month surveillance may be delayed until the beginning of the Cycle 8 refueling outage. For the specific surveiliances under this section, the time intervals required by Specification 1.9 will be determined with the new initiation date established by the surveillance date during the Cycle 8 refueling outage.

l Amendment No. 97,102 4-0

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS' i

Surveillance Standards 4.4.1.2 Local Leakace 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' l (7) Reactor coolant pump seal water outlet line (8) Reactor coolant pump seal inlet line (9) Reactor Building equalizing line (10) Deleted (11) Reactor Building spray inlet lines (12) Deleted (13) Electrical penetrations (14) Reactor Building purge inlet line (15) Reactor Building purge outlet line (15) Reactor Building atmosphere sample lines (17) Letdown to purification demueralizer line g (18) Pressurizer relief tank gas sacole line 1 (19) Reactor coolant system vent heaoer (20) Pressurizer relief tank nitrogen supply line J (21) Pressurizer sample line  !

(22) Reactor coolant drain tank header l (23) Reactor Building hydrogen sample line i (24) H2 recombiner penetration l (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 l (30) Core Flood Tank drain and sample l

(31) Steam Generator drain '

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

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  • The provisions of Specification 4.0.4 are applicable. l l Amendment No. II, 97, 101,102 4-17

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. RANCHO SECO. UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 4.4.1.2.2 Conduct of Tests 4

The contain ,=t.1eakage 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:** I (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 i 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 9.5 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 0.5 psig shall be extrapolated to the leak rate (La) that will occur at the calculated peak containment pressure of 52 psig l using the following formula:' l La = 5.2 Lt ,

l (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.

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    • The provisions of Specification 4.CL' are applicable to those items annotated in Specification 4.4.1.2.1.

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Amendment No. JJ, 49, 72, 97, 707.102 4-18 i

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RANCHO SECO UNIT 1 i

TECHNICAL SPECIFICATIONS

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Surveillance Standards 4.5.3 DECAY HEAT REMOVAL SYSTEM AND REACTOR BUILDING SPRAY SYSTEM LEAKAGE I Aeolicability i

Applies to Decay Heat Removal System and the Reactor Building Spray System 1eakage. )

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Obiettive J i

To prevent significant offsite exposures by maintaining a preventive. leakage rate for the Decay Heat Removal System and the Reactor Building Spray System. .'

Specification 4.5.3.1 Acceetance Limit The maximum allowable leakage from the components (which include i valve stems, flanges and pump seals) in the Decay Heat Removal System and the Reactor Building Spray System shall not exceed a sum total .of 6.0 gallons per hour for both systems.

, 4.5.3.2. A lut - Decav Hegt Removal System

1. During each refueling interval the portion of the Decay Heat Removal System, except as specified in (2), that is outside the containment shall be tested either by use in normal operation or by hydrostatically testing at 450 psig.
2. Once per 24 months, piping from the containment emergency I sump to the decay heat removal pump suction isolation valve shall be pressure tested at no less than 52 psig as a  ;

containment lock! leak rate test under paragraph 4.4.1.2.* l

3. During each refueling interval, visual inspection shall be l made for excessive leakage from components of the system. i Any excessive leakage shall be measured by collection and weighing or by another equivalent method.
l. 4.S.3.2.B Int - Reactor Buildino Serav System During each refueling interval, the following tests of the Reactor Building Spray System shall be conducted in order to determine leakage:

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  • The provisions of Specification 4.0.4 are applicable.

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Amendment No. 57,102 4-32 l

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