ML19309A294
| ML19309A294 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 06/21/1977 |
| From: | SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| Shared Package | |
| ML19309A290 | List: |
| References | |
| NUDOCS 8003270656 | |
| Download: ML19309A294 (6) | |
Text
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' RANCHO SECO UNIT'1
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TECHNICAL SPECIFICATIONS
-e DEFINIT!03S D.
All automatic containment isolation valves are~ operable or closed
-in the safety, features position.
E.
~ The containment leakage satisfies Specification 4.4'1 and no known' changes have occurred.
1.8-REPORTABLE OCCURRENCE 53 Defined under Administrative Controls Section 6.9.4.
19 TIME PERIODS 1.9.1 Shift A time period covering eight (8) hours, three shifts equally dividing a twenty-four hour time period.
l.9.2 Daily A time period within a twenty four hour span from 0000 to 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br /> from Monday through Sunday.
l.9 3 Weekly A time period from Monday through Sunday spaced to occur fif ty-two times a year.
1.9.4 Monthly A time peri'od from the first to last day of
! calendar month spaced to occur twelve times a year.
1.9.5 Quarterly A time period of three calendar months spaced to occur four times a year.
1.9.6 Semi-Annually A time period from January I and July I covering the subsequent six months.
1.9 7 Blannually A time period of twenty-four calendar months spaced to occur once in two years.
1.10 SAFETY Safety as used in these Technical Specifications shall mean nuclear safety and shall encompass all systems and components that have or may have on ef fect on the health and safety of the general public.
1-5 Proposed Amendment No. 53 8003270f d
y ADMINISTRATIVE CONTROLS b.
The change is approved by two members of the plant management staff, at least one of whom holds a Senior Recctor Operator's License on the unit affected.
c.
The change is documented, reviewed by the PRC and approved by the Plant Superintendent within seven (7) days of implementation.
6.9 REPORTING RE0VIREMENTS 6.9.1 in addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Director of the Regional Office of Inspection and Enforcement unless otherwise noted.
STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) Receipt of an operating license; (2) amendment to the license involving a planned increase in power level: (3) instal-lation of fuel that has a different design or has been manufactured by a differelt fuel supplier; and (4) modifications that may have signifi-cantly altered the nuclear, thermal or hydraulic performance of the plant.
1he report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the 53 operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described.
Any additional specific details required in license conditions based on other comit-ments shall be included in this report.
6.9 1.2 Startup reports shall be submitted within (1) Ninety (90) days following completion of the startup test p rog ram; (2) Ninety (90) days following resumption or commencement of commercial power operation; or (3) Nine (9) months following initial criticality, whichever is earliest.
If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program and resumption or commencement of commerical power operation), supplementary reports shall be submitted at least every three (3) months until all three events have been' completed.
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6-12 Proposed Amendment 53
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ENVIRONMENTAL REPORT'
-e 6.9 2-The Environmental' Report required within Appendix B shall include-
'a tabulat on on an annual' basis of tthe number'of station, utility i
and other perso'nnel (including contractors) receiving exposures-greater. than 100 mrem /yr and their associated man rem exposure according to work and job ~ functions, e.g.,
reactor operations and su rve i l l ance,' inservice: Inspection, routine maintenance, special'
' maintenance,(describe maintenance), waste processing and refueling.
The dose assignment *to various. duty-functions 'may, be estimates
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. based on pocket dosimeter, TLD, or film badge measurements.
Small' exposures totaling less than 20% of the individual total dose need not be accounted for, in the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.
MONTHLY REPORT 6.9 3 Routine reports of operating statistics, including narrative summary of operating and shutdown experience, of major safety related maintcaance, and tabulations of facility. changes, tests or experiments required pursuant to 10 CFR 50.59(b), shall be submitted on a monthly basis to the Office
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l of inspection and Enforcement, U.S. Nuclear Regulatory Commission, Washington, D.C., 20555, with a copy to the Regional Office, postmarked no later than I
the tenth working day of each month followi,ng the calendar month covered-by the report.
REPORTABLE OCCURRENCES a
6.9.4 The REPORTABLE OCCURRENCES of Specifications 6.9.4.1 and 6.9.4.2 below, including corrective actions and measures to prevent recurrence, shall.
be' reported to the NRC.
Supplemental reports may be required to' fully describe final resolution of occurrence.
In case of corrected or supplemental reports, a licensee event report shall be completed and reference shall be made to the original ' report date.
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'6-12a Proposed AmendmentL53~
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L PROMPT NOTIFICATION VITH WRITTEN FOLLOWUP 6[9.4.1 The types of events listed below shall be reported within twenty-four (24) hours by telephone and confirmed by telegraph, mailgram or facsimile transmission to the Director of the Regional Of fice, or his designate, no later.than the first working day following the event, with a written followup report within two weeks. The written followup report shall include, as a minimum, a completed copy of a licensee event repor.t form.
Information provided on the-licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.
Failure of the reactor protection system or other systems a.
subject to limiting safety system settings to initiate the required protective function by the. time a monitored para-meter reaches the setpoint specified as the limiting safety 8
system sett ig in the Technical Specifications or failure to complete the required protective function.
b.
Operation of the unit or affected systems when any parameter or operation subject to a limiting condition for operation is less 53 conservative than the least conservative aspect 'of the limiting condition for cparation established in the technical specifica-tions.
Abnormal. degradation discovered in fuel cladding, reactor c.
l coolant pressure boundary, or primary containment.
d.
Reactlyity anomalies involving disagreement with the predicted value of reactivity balance under steady state conditions during power operation greater than or equal to 1% Ak/k; a calculated reactivity balance indicating a SHUTDOWN MARGIN less conservative than specified in the Technical Specifica-tions; short-term reactivity increases that correspond to a reactor period of less than five (5) seconds or, if sub-critical, an unplanned reactivity insertion of more than 0 5% Ak/k; or occurrence of any unplanned criticality.
Failure or malfunction of one or more components which prevents e.
or could prevent, by itsel f, the ful fillment of the funct ional requirements of system (s) used to cope with accidents analyzed in the SAR.
f.
Personnel error or procedural inadequacy which prevents or could prevent, by itself, the fulfillment of the functional require-ments of systems required to cope with a..cidents analyzed in the SAR.
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6-12b Proposed Amendment'53.
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PROMPT NOTIFICATION WITH' WRITTEN FOLLOWUP (continued) 6.9.4.1-
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Condi t ians' aris ing f rom na tural or ~ man-made_ events that, as a direct l result of-the event, require plant shutdown, operation of safety systems, or other protective measures required by_
technical specifications.
h.
Errors discovered' in the 'traasient or accident analyses or in the methods _used for such analyses:as described in the Safety Analysis Reportlor in the bases for the Technical Specifications that have or could have permitted reactor operation in a manner -
less conservative than assumed in the analyses.
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Performance of structures, systems, or components that requires remedial action or corrective measures to prevent _ operation in a manner less' conservative than assumed'in the accident analyses
'in the Safety Analysis Report or Technical Specifications bases; or discovery during plant life of conditions not specifically considered in the Safety Analysis Report or Technical Specif.ica-tions that require remedial action or corrective measures to prevent the existence or development of an unsafe condition.
THIRTY DAY WRITTEN REPORTS 6.9.4.2 The types of events listed below shall be the subject of written' I
reports to the Director of the Regional Office within thirty (30) 53 days of occurrence of the event.
The written report shall include, as a minimum, a completed copy of a licensee event report form.
Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.
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Reactor protection system or engineered safety feature instru-ment settings which are found to be l ass conservative than those established by the Technical Specifications but which do not prevent the fulfillment of the fun'ctional requirements of affected systems, b.
Conditions leading to operation in a degraded mode permitted by a limiting condition for operation or plant shutdown required by a limiting condition for operation.
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Observed inadequacies in the implementation of administrative or procedural controls which threaten to cause reduction of degree of redundancy provided in reactor protection systems
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or engineered safety featur e ' systems.
d.
Abnormal degradation of systems.other than those specified In 6.9.4.1.c' above designed. to contain radioact ive material resulting from the fission process.
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4 SPECIAL REPORTS
-c 6.9.5 Special reports shall be. submitted to the. Director of the Regulatory Operations Regional Of fice wi thin the time period specified 'for each report.
These reports shall.be submitted covering the-activities identified below pursuant to the requirement,s of the applicable reference specification:
A.
A one-time only,'" Narrative Summary of Operat ing Experience"'-
will be, submitted to cover the transition period (calendar.
53-year 1977).
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B.
A Reactor Building structural integrity report shall be.
submitted witnin nincty (90) days of completion of each of the following tests covered by Technical Specification 4.4.2 (the integrated leak rate test is covered in Technical Specificat' ion 4.4.1.1).
.1 Annual Inspection
.2 Tendon Stress Surveillance 3
End Anchorage Concrete Surveillance
.4 Liner Plate Surveillance C.
Inservice Inspection Program.
D.
Reserved for Proposed ' Amendment No. 43 d
6-12d Proposed Amendment 53 4
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