ML20043A171
| ML20043A171 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 04/27/1990 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20043A167 | List: |
| References | |
| NUDOCS 9005180150 | |
| Download: ML20043A171 (5) | |
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j UNITED STATES 8"
NUCLEAR REGULATORY COMMISSION e
- l' WASHINGTON D. C.20655
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CHAHA PUBLIC POWER DISTRICT l
l DOCKET NO. 50-285 i
FORT CALHOUN STATION, UNIT NO. 1-l AMENDMENT TO FACILITY OPERATING LICENSE 3
Amendment No.129 License.No. DPR-40 1.
The Nuclear Regulatory Comission-(the Comission) has found that:
- A.
~ The application for amendwnt by: the Omaha Public Power District (the licensee) dated January 24,.1990 as: supplewnted March 29, 1990, i
complies with the-standards and requirements of the Atomic Energy Act of.1954, as amended (the Act), and the Comission'sirules and regula-'
tions set forth in 10 CFR Chapter I, i
B.
The facility will operate in conformity with the application,-as amended, the provisions of the Act and the rules and regulations of the Comission.
C.
There is reasonable assurance:. (1) that thc activities authorized by this amendment can be conducted without endangering.the health; and safety of the public,-and-(ii) that such activities will be L
conducted in compliance with the Comission's regulations;~
D.
The issuance of this license 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 amendw nt is in'accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirewnts have been satisfied, i
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1 900518015o 900427 FDR ADOCK 05000285 P
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2.
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Accordingly, Facility Operating License No. DPR-40 is amended by changes to the Technical Specifications as indicated in the attachment to this
~ license' amendment, and paragraph 3.B. of Facility Operating License No..
OPR-40_is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Apsendix A, as revised through-Amendnent No.129 -, are here>y incorporated in the license. The licensee sha11' operate;the facility in l
accordance with-the Technical Specifications.
4 3.
The-license amendment is effective as of its-date of issuance.
FOR THE NUCLEAR-REGULATORY COMMISSION 9Mq./C Frederick'J. Heb on,-Director Project Directorate IV Division of Reactor. Projects. III, IV, V and Special. Projects.
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:-April 27, 1990
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'l ATTACHMENT. TO LICENSE AltENDMENT NO.129 FACILITY OPERATING LICENSE NO. DPR 40 DOCKET NO. 50-285
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i Revise Appendix "A" Technical Specifications as indicated b'elow. The revised l
pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove Pages Insert Pages 3-0a 3-Da' 3-Ob 3-Ob s
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3.0 SURVEILLANCE RE0VIREMENTS 3.0.1.
Each surveillance requirement shall be performed within the specified t
L surveillance interval with a maximum allowable extension not to exceed L
25 percent of the specified surveillance interval.
3.0.2 The surveillance: intervals are defined as follows:
Notation J,j,11g Frecuency i
S Shift <
At least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> i
D Daily' At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> W
Weekly At least once per 7 days-
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BW Biweekly At least once:per 14 days 1
M Monthly At least once per 31 days Q
Quarterly At least once per 92 days-1 SA Semiannual-At least once per 184-days A
Annually At least once per 366 days R -
Refueling' At least once per-plant operating cycle P
Startup Prior to Reactor Startup, if not completed in the previous week.
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Exception to these intervals are stated in the individual Specifications.
3.0.3 The provisions of Specifications 3.0.1 and 3.0.2 are applicable to.all' codes and standards. referenced within the-Technical Specifications.
The requirements of the. Technical Specifications shall have precedence over the requirements of the codes and standards referenced within the 1
Technical Specifications, l
3.0.4 Failure to perform a Surveillance Requirement within the allowed j
surveillance interval, defined by Specifications 3.0.1 and 3.0.2, shall constitute noncompliance with the OPERABILITY requirements for the corresponding. Limiting Condition for Operation.
The time limits of the ACTION requirements are applicable at the time it is identified that a i
Surveillance Requirement has not.been performed. The ACTION 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 requirements are less than~24. hours.
Surveillance Requirements do not have to be performed on inoperable equipment.
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3-Ca Amendment No. JJ2,129 h
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Y 3.0L SURVEILLANCE RE0VIREMENTS r
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- r BASIS Specifications 3.0.1 through 3.0.4 establish the general requirements i
applicable to Surveillance Requirements, These requirements are based' on.the Surveillance Requirements stated in the Code of Federal Requirements, 10 CFR 50.36(c)(3):
" Surveillance requirements are requirements relating to test,-
I calibration, or inspection to ensure that the necessary quality of systems and components is maintained, that facility operation will be within s_afety limits, and that the limiting condition of
't operation will be met."
Specification 3.0.1 establishes the limit for which the specified time interval for Surveillance Requirements may be extended, it permits an allowable extension of the normal surveillance interval to facilitate 1 surveillance scheduling and consideration of plant operating conditions that may not be suitable for conducting the surveillance; e.g.,
transient-conditions or other ongoing surveillance or maintenance activities.
It also provides flexibility to accommodate the: length of-a fuel cycle for surveillances that are performed at each refueling outage and are specified with an 18 month surveillance interval.
It:is-not intended that this provision be=used repeatedly:as a convenience'to extend surveillance intervals beyond that.specified for surveillance that are not performed during refueling outages.
The linitation of
-Specification 3.0.1 is based on engineering judgment and the t
recognition that the most probable result of any particular.
i surveillance being performed is the. verification of conformance with the Surveillance Requirements.
This provision is sufficient-to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond that obtained from-the specified-surveillance interval.
The provisions'of Specification-3.0.2 define the surveillance intervals for use in the Technical Specifications.
This clarification is' provioed to ensure consistency in surveillance: intervals throughout*the f
Technical Specifications. A few surveillance requirements lhave-uncommon intervals, for example, Table 3-9 requires. sampling of fish.
L once per season.
In such a case the surveillance interval shall be performed as defined by the individual specifications.
l Specification 3.0.3 extends the testing interval required by codes and standards referenced by the Technical Specifications. 'This clarification is provided to remove any ambiguities relative to the frequencies for performing the required inservice inspection and testing activities. Under the terms of this specification,.the more restrictive requirements of the Technical Specifications take precedence over the codes and standards referenced therein.
Specification 3.0.4 establishes the failure to perform a Surveillance Requirement within the allowed surveillance interval, as defined by the provisions of Specifications 3.0.1-and 3.0.2, as a' condition that i
constitutes a failure to meet the OPERABILITY requirements for the corresponding Limiting Condition for Operation.
Under the provisions 3-Ob
/AmendmentNo..W,129
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