ML20148C568
| ML20148C568 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 10/03/1978 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20148C558 | List: |
| References | |
| NUDOCS 7811020087 | |
| Download: ML20148C568 (7) | |
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UNITED STATES o
4 NUCLEAR REGULATORY COMMIS310N
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WASHINGTON, D. C. 20655
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SACRAMENTO MUNICIPAL UTILITY DISTRICT DOCKET NO. 50-312 RANCHO SECO NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATIhG LICENSE Amendment No, 23 e
License No. DPR-54 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A. The application for amendment by Sacramento Municipal Utility District (the licensee) dated June 7, 1978, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter T; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.
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Accordingly, the license.is amended by changes to the. 'echnical 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:
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(2) Technical Specifications The Technical Specifications contained in Appendices
.A and B, as revised through Amendment No. 23. are l
. hereby incorporated in the license. The licensee i
I shall operate the facility in accordance with the Technical Specifications.
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This license amendment is effective as of the date of.its l
1ssuance.
l FOR THE NUCLEAR REGULATORY COMMISSION Y.
l o ert W. Reid, Chief
. Operating Reactors Branch #4 j
ls Division of Operating Reactors j
Attachment:
i Changes to the Technical l
Specifications Date of Issuance: October 3,1978 o
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ATTACHMENT TO LICENSE AMENDMENT NO.'23 FACILITY OPERATING LICENSE NO. DPR-54 DOCKET-NO. 50-312 Revise Appendix A as follows:
Remove Pages Insert Pages 1-5 & 1-6 1-5 1-6 4-1
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& 4-2 The-changes on the revised pages are shown by marginal lines.
Page 4-2' is unchanged and is included for convenience only.
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r RA?iCHO SECO UNIT l-1 TECHNICAL SPECIFICATIONS i
DEFINITIONS l
t D.
All automatic containment isolation valves are operable or closed in the safety features position.
.E.
The containment leakage <atisfies Specification 4.4.1 and io known changes have occurred.
REPORTABLE OCCURRENCE j
Defined under' Administrative Controls Section 6.9.4.
1.9 TIME PERIODS May be extended to a maximum of +25% to accommodate operations' scheduling.
The tctal maximum combined interval time for any three consecutive tests shall not exceed 3.25 times a single specified surveillance interval.
l.9.1 SHIFT-A time period covering at least once per twelve (12) hours.
l 1.9 2 OAILY A. time period spaced to occur at, least er twenty-four (24) hours.
1.9 3 WEEKLY A time period spaced to occur at least once per seven (7) days.
l 1 9.4 MONTHLY A time period spaced to occur.at least once per thirty-cne (31) days.
f 1.9.3 QUARTERLY A time period spaced to oc. cur at least once per ninety-two (92) days.
1 9.6 SEMI-ANiiUALLY l
A time period spaced to. occur at least once per six (6) months.
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1.9.7 ANNUALLY
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A time period' spaced to occur at least once per twelve (12) months.
l 1.9.8 BIANNUALLY t
A time period spaced to oc ur at least once in two (2) years.
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l.99-REFUELING INTERVAL A time. period spacec to occur at-least once per eignteen (13) months.
1.10 L SAFETY
.SafetyLas.used in these Technical Scecift ations shall mean nuclear
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safety.and-snali encomeass all syste s and cc conents that have or
'may have an effect on the. health and. safety of the general public.
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I AmendmentNo.)6,23',
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RANCHO SECO UNIT 1
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TECHNICAL SPECIFICATIONS DEFINIT 10NSL 1.11 FIRE SUPPRESSION SYSTEMS i
1.11.1 The FIRE SUPPRESSION WATER SYSTEM shall consist of water sources, pumps and distribution piping.with associated sectionalizing con-trol' of ~ isolation valves.
Such valves include yard hydrant' valves and the first valve ahead of the water flow alarm device on each sprinkler header, hose ' standpipe or spray system riser which pro'-
tect nuclear safety. components.
1.11.2 The FIRE SUPPRESSION CARBON DIOXIDE SYSTEM shall consist of. a i
C0f source and distribution piping with sectionalizing control valves which protect nuclear, safety components.
1.12 STAGGERED TEST BASIS A STAGGERED TEST BA515 shall consist of:
a.
A test schedule for n systems, subsystems, trains or des.
'Ignated comoonents obtained by dividing the specified test interval into'n equal subintervals.
b.
T'.e testing of one system. subsystem, train or designated' components during each subinterval.
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Amendment No.
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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS
-Surveillance. Standards
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. SURVEILLANCE STANDARDS 1
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j 4.1 OPERATIONAL SAFETY REVIEW l
Applicability Applies to items directly related to safety limits and limiting conditions-for operation.
Obj ective To specify the minimum frequency and type,of surveillance to be applied to unit equipment and conditions.
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Specification i
4.1.1 The minimum frequency and type of surveillance required for reactor protection system and safety feature protection system instrumentation when the reactor is critical shall be as stated in table 4.1-1.
4.1.2 Equipment 'and sampling test shall be performed as detailed in tables 4.1-2 and 4.1-3.'
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4.1.3 A power distribution map shall be made to verify the expected power' distribution at periodic intervals on approximately every 10 effec-tive full power days using the incore instrumentation detector system.
-1 Bases I
Check Failures such as blown instrument fuses, defective indicators, faulted ampli-fiers wh,1ch result in " upscale" or "downscale" indication can be easily recog--
nized by simple observation of the functioning of an instrument or system.
Furthermore, such f ailures are, in many cases, revealed by alarm or annun-ciator action.
Comparison of output and/or state of independent channels.
measuring the same variable supplements this type of built-in surveillance.
Based on experience in operation of both conventional and nuclear systems,
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-when the unit is in operation, theminimumcheckingflequencystated'is deemed adequate for reactor system instrumentation.
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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards Calibration Calibration shall be performed to assure the presentation and acquisition of accurate information. The nuclear flux (power range) channels amplifiers shall be calibrated (during steady state operating conditions) against a heat balance standard when the indicated neutron power and core thermal power differ by more than two percent. During non-steady state operation, the nuclear: flux channels amplifiers shall be calibrated daily to compen-sate for instrumentation drift and changing rod patterns and core physics parameters.
Channels subject only'to " drift" errors induced within the instrumentation itself and consequently, can tolerate longer Jatervals between calibrations.
Process system instrumentation errors induced by drift can be expected to remain within acceptable tolerances if recalioration is performed at the inter-vals of each refueling period.
Substantial calibration shifts within a channel (essentially a channel failure) will be revealed during routine checking and testing procedures.
Thus, minimum calibration frequencies set forth are considered acceptable.
Testing The frequency of on-line testing of reactor protective channels as shown in table 4.1-1 will assure the required level of performance.
The equipment testing and system sampling frequencies specified'in table 4.1-2 and table 4.1-3 are considered adequate to maintain the equipment and systems in a safe operational status.(1)
Power Distribution Mapping The incore instrumentation detector system will provide a means of assuring that axial *and radial power peaks and the peak locations are being controlled by the provisions of the Technical Specification within the limits employed in the safety analysis.
REFERENCES s
(1)
TSAR paragraph 1.4.12.
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