ML20247K681

Amend 104 to License DPR-54,deleting Tech Specs Re Reactor Vessel Matl Surveillance

ML20247K681
Person / Time
Site:	Rancho Seco
Issue date:	05/16/1989
From:	Knighton G Office of Nuclear Reactor Regulation
To:
Shared Package
ML20247K668	List: ML20247K662 ML20247K681 ML20247K687
References
NUDOCS 8906010361
Download: ML20247K681 (8)

Text

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a UNITED STATES Q- T NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 -

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SACRAMENTO MUNICIPAL-UTILITY DISTRICT

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DOCKET NO. 50-312 RANCHO SECO NUCLEAR GENERATING STATION ,

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AftENDMENT TO FACILITY OPERATING LICENSE Amendment No.104 License No. DPR-54

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

A. The application for amenoment by Sacramento Municipal Utility District (the licensee) dated October 14,1$85, and February 13, 1986, 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 facility will operate in conformity with the application, the provisions of the Act, and the regulations of the. Commission; C. There is reasonable assurance (1) 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 Connission's regulations; D. The issuance of this amendment will not be inimical to the connon 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 regulations and all applicable requirements have been satisfied.

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2. Accordingly, 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 B, as revised through Amendment No.104, are hereby incorporated in the license. The licensee shall operate the facility.in accordance with the Technical Specifications.

3. This amendment to the Technical Specification shall become effective within 30 days of the issuance date. The implementation delay.is provided to allow time for modification of affected procedures and promulgation of the changes to personnel.

FOR THE NUCLEAR REGULATORY COMMISSION j George . Knighto irector Project Directorate V Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: May 16, 1989 1

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i ATTACHMENT TO LICENSE AMENDMENT.NO.104 FACILITY.0PERATING. LICENSE.NO. DPR-54 DOCKET.NO. 50-312 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 IX IX 4-10 4-10 4-12 4-12 4-12a 4-12a 4-12b 4-12b l

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TEC W CAL SPECIFICATIONS LIST OF TABLES Section Eage l

1.2-1 OPERATIONAL PODES 1-2c i 1.9-1 FREQUENCY NOTATION 1-10 4 2.3-1 REACTOR PROTECTION SYSTEM TRIP SETTING LIMITS 2-9 3.0-1 APPLICABILITY OF SPECIFICATIONS 3.0.3 AND 3.0.4 3-Oa 3.3-1 PRIMARY COOLANT SYSTEM PRESSURE ISOLATION VALVES 3-22a 3.5.1-1 INSTRLNENTS OPERATING CONDITIONS 3-27 3.5.5-1 ACCIDENT M)NITORING INSTRLHENTATION OPERABILITY RE@IREMENTS 3-38e 3.5.7-1 EMERGENCY SiffTDOWN INSTRJiENTATION 3-3Sj 3.6-1 SAFETY FEATURES CONTAltNENT ISOLATION VALVES 3-40 3.7-1 VOLTAGE PROTECTION SYSTEM RELAY TRIP VALUES 3-41a 3.7-2 VOLTAGE PROTECTION SYSTEM LIMITING CONDITIONS 3 43b ,,

3.12-1 SAFETY RELATED HYRAULIC SNUBBERS 3-517.-e 3.14-1 FIRE DETECTION INSTRLNENTS FOR SAFETY SYSTEMS 3-55 3.14 -

WATER SUPPRESSION ZONES 3-56b,c 3.14-3 CARBON DIOXIDE SUPPRESSION ZONES 3-56d,e 3-14 4 FIRE HOSE STATIONS 3-57a.,b 3.15-1 RADI0 ACTIVE LI@ID EFFLUENT M)NITORING INSTRLhENTATION 3-61 3.16-1 RADI0 ACTIVE GASES EFFLUENT K)NITORING INSTRLNENTATION 3-64 3.22-1 RADIOLOGICAL ENVIRO?NENTAL M)NITORING PROGRAM 3-83 3.22-2 REPORTIfG LEVELS FOR RADID4CTIVITY CONCENTRATIONS 3-86 IN ENVIR0tNENTAL SAffLES l 3.29-1 METER 0 LOGICAL M)NITORING INSTRLNENTATION 3-95 l

4.0-1 APPLICABILITY OF SPECIFICATIONS 4.0.2 AND 4.0.3 4 Ca

'4.1-1 INSTRLNENT SURVEILLANCE RE@IREMENTS 4-3 4.1-2 MINIHN E@IPMENT TEST FRE@ENCY 4-8 4.1-3 MINIRN SAMPLItG FRE@ENCY 44 Amendment No. 26,55.I6.IIe76./7e00e iX 65,57,65,95,91 ,66 104

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r RANCHO-SECO UNIT 1 l TECHNICAL SPECIFICATIONS i.

Surveillance Standards

/4.2. SURVEILLANCE OF 'ASME CODE CLASS 1, 2 AND 3 SYSTEMS Applicability Applies to systems and components defined as ASME Code Class 1 Class 2, and Class 34 Obje'ctive j .- .To establish examinations whereby the integrity of ASME Code Class 1, 2 and 3 systems and components is monitored.

'4.2.1 This' paragraph- has been deleted.

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Amendment No. 75,76,104 4.jo l

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F RANCHO SECO UNIT 1 TECHNICAL SPECIFICATION Surveillance Standards jasgs Under the. terms of specification 4.2.2.1, the more restrictive requirements of> the Technical Specifications take precedence over the ASME Boiler and Pressure Vessel Code and applicable Addenda. For example, the ASME Boiler and Pressure Vessel Code allows pumps to be tested up to one week after return to normal operation and allows a valve to 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.

Where these provisions are in conflict with the Technical Specifications, the Technical Specifications provisions will govern.

. Testing a component subject to the provisions of Section XI is to be deferred as stated if the redundant component is inoperable. This is because test requirements frequently make the test component temporarily inoperable. In the event an accident should occur at this time, neither of the safety-related trains would be available to respond to the condition. The deferral of the test does not relieve the licensee of the responsibility for conducting the required testing in accordance with regulatory requirements governing the frequency of tests. The licensee should establish a test schedule that can accommodate'a reasonable number of inoperability events without violating required test frequencies.

A preoperational examination was made which included all the items in ASME

. Code Class 1 systems that would normally be completed throughout the Inspection interval. -This survey established initial system integrity and provided a baseline for future testing.

Specification 4.2.2.1 ensures that inservice inspection of ASME Code Class 1, 2 and 3 components and inservice testing of ASME Code Class 1, 2 and 3 pumps and valves will be performed in accordance with a periodically updatee version of Section XI~of the ASME Boiler and Pressure Yessel Code and Addenda as required by 10 CFR 50.55a. Relief from any of the above requirements has been provided in writing by the Commission and is not a part of these Technical Specifications.

Amendment No. 75,76,104 4-12 1

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Amendment No. 77, 104 4-12a t _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ - _ _ - - - - - _ - - .

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THIS PAGE HAS BEEN INTENTIONALLY DELETED.

Amendment No. /,75,75,104 4-12b

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