ML19319C773
| ML19319C773 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 03/15/1977 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19319C772 | List: |
| References | |
| NUDOCS 8003040735 | |
| Download: ML19319C773 (5) | |
Text
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' ENCLOSURE N0, 1 SA"PLE TECHNICAL SPECIFICATIONS ADf11NISTRATIVE C0"TROLS 6.9 REPORTING REQUIRE"ENTS ROUTIME REPORTS A!iD REPORTABLE OCCURRENCES In addition to the aoplicable reporting cequirements of Title 10, 6. 9.1 Code of Federal Reculations, the followina reports shall be submitted to the Director of the Recional Office of Inspection and Enforcement unless otherwise noted.
STARTUP REPORT A summary report of plant startup cud power escalation testina' 6.9.1.1 shall be subnitted folicwina (1) receipt of en operatino license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has' a different desian or has been nanu-f actured by a different fuel sunplier, and (4) nodifications that may have sicnificar.tly altered the nuclear, therral, or hydraulic perfor-The reoort shall address each of the tests identified mance of the plant.
in the FSAR and shall include a description of the neasured values of the operatinq conditions or characteristics obtained durinq the test oronran and a comparison of chese values with desion predictions and specifica-Any corrective actions that were required to obtain satisfactory tions.
Any additional specific details operation shall also be described.
required in license conditions based on other commitments shall be in-cluded in this report.
Startuo reports shall be submitted within (1) 90 days followinn 6.9.1.2 completion of the startun test procram, (2) 90 days followina resumption nanths followino or commencement of commercial power operation, or (3) n initial criticality, whichever is earliest.
If the etartup Report does not cover all three events (i.e., initial criticality, conoletion of startup test pronram, and resumotion or conmencenent of cocnercial 6-14 l' arch 15,1977 All STS 8003040 7 %
ADMil;ISTRATIVE C0!iTROLS power operation), supplementary reports sh:ll be submitted at least every three months until all three events have been completed.
M AfiliUAL OpERATit;G REPORT 6.9.1.3 Routine operating reports covering.the operation of the unit during the previous calendar year shall be submitted prior to March 1 of cach year.
The initial report shall be submitted prior t;o March 1 of the year following initial criticality.
6.9.1.4 The annual operating reports shall provide a comprehensive sum. mary of the operating experience gained during the year, even though some repetition of previously reported information may be involved.
References in the annual operating report to previously submitted reports shall be clear.
6.9.1.5_
Each annual operating report shall include:
A narrative summary of operating experience during the report a.
period relating to safe operation of the facility, including safety-reldted maintenance not covered in 6.9.1.5.b.5 below.
For each outage or forced reduction in power E of over twenty b.
percent of RATED THERMAL POWER where the reduction extends for greater than four hours:
1.
The proximate cause and the system and major component involved (if the outage or forced reduction in power involved equipment malfunction);
2.
A brief discussion of (or reference to reports of) any reportable occurrences pertaining to the outage or power reductiun;
_l] A single subnittal may be made for a multiple unit station.
The submittal should combine those sections that are common to all units at the station.
-2/ The term " forced reduction in ~ power is defined as the occurrence of
'a component failure or other condition which requires that the load on the unit be reduced ior corrective action immediately or up to and' including the very next weekend.
!?ote that routine preventive maintenance, surveillance and calibration activities requiring power o
reductions are not covered by this section.
ALL STS 6 15 March 15, 1977 J
k
9 ADMINISTRATIVE CONTROLS Corrective action taken to reduce the probability of 3.
recerrence, if appropriate; 4.
Operating time lost as a result of the outagg or power use the reduction (for scheduled or forced outages,-
generator off-line hours; for forced reductions in power, use the approximate duration of operation at reduced power);
A description of major safety-related corrective main-5.
tenance performed during the outage or power reduction, including the system and component involved and identifica-tion of the critical path activity dictating the length of the outage or power reduction; and 6.
A report of any single release of radioactivity or radiation exposure specifically associated with the outage which accounts for more than 10% of the allowable annual values.
A tabulation on an annual basis of the number of station, c.
utility and other personnel (including contractors) receiving exposuresgreaterthan100 mrem /yrandtheirassogatedman.
rem exposure according to work and ich functions,-
e.g.,
reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance),
waste processing, and refueling.
The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements.
Small exposures totalling 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 frcm external sources sha!1 be assigned to specific major work functions.
Indications of failed fuel resulting from irradiated fuel d.
examinations, including eddy current tests, ultrasonic tests, or visual examinations completed during the report period.
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The term " forced outage" is defined as the occurrence of a component
-3/
failure or other condition which requires that the unit be removed from service for corrective action'immediately or up to and including the very next weekend.
4/ This tabulation supplements the requirements of 520.407 of 10 CFR -Part 20.
6-16 March 15, 1977 ALL STS m
1 ADMINISTRATIVE CONTROLS MONTHLY OPERATING REPORT _
Routine reports of operating statistics and shutdown experience hall be submitted on.2 monthly basis to the Office of Inspection and
. 9.1. 6 6
- 20555, nforcement, U.S. Nuclear Regulatory Commission, Was s
E f each month following the calendar month covered by the report.
w o
REPORTABLE OCCURRENCES The REPORTABLE OCCURRENCES of Specifications 6.9.1.8 and 6.9.1.9 below, including corrective actions and measures to prevent recurrence, 6. 9.1. 7 Supplemental reports may be required to shali be reported to the NRC.
In case of corrected or fully describe final resolution of occurrence.
supplemental reports, a licensee event report shall be completed and reference shall be made to the original report date.
PROMPT NOTIFICATION WITH WRITTEN FOLLOWUP The types of events listed below shall be reported within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and confirmed by telegraph, mailgram, or facsimile 6.9.1.8 transmission to the Director of the Regional Office, or his designate no later than the first working day following the event, with a written The written followup report shall followup report within two weeks. include, as a minimum, a completed co Information provided on the licensee event report form shall be supple-mented, as needed, by additional narrative material to previde complete explanation of the circumstances surrounding the event.
Failure of the reactor protection system or other systems subject to limiting safety system settings to initiate the a.
required protective function by the time a monitored para-meter reaches the setpoint specified as the limiting safety system setting in the technical specifications or failure to complete the required protective function.
Operation of the unit or affected systems when any parameter or operation subject to a limiting condition for operati b.
limiting condition for operation established in the technical specifications.
Abnormal degradation discovered in fuel cladding, reactor coolant pressure boundary, or' primary containment.
c.
March 15, 1977 6-17
- .ALL STS
__O
ADMINISTRATIVE CnNTROLS Reactivity anomalies involving disaqreenent with the predicted
_d.
value of reactivity balance under steady state conditions durinn power operation creater than or equal to 1% ok/k; a calculated reactivity balance indicatina a SHUTD0h'N MARGIN less conservative than specified in the technical specifica ;!
tions; short-term reactivity increases that correspond to a reactor period of less than 5 seconds or, if subcritical,,
an unplanned reactivity insertion of more than O'.5% ak/k; or occurrence of any unplanned criticality.
l i
Failure or nalfunction of one or nore components which prevents e.
or could prevent, by itself, the fulfillment of the functional requirenents of system (s) used to cope with accidents analyzed in the SAR.
.I Personnel error or procedural inadequacy which prevents or could f.
prevent, by itself, the fulfillment of the functional require-ments of systems required to cope with accidents analyzed in the SAR.
Conditions arising from natural or man-made events that, as a
~
9 direct result of the event require plant shutdown, operation of safety systems, or other protective measures required by technical soecifications.
Errors discovered in the transient or accident analyses or in h.
the methods used for such analyses as described in the safety analysis report or 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.
i.
Performance of structures, systems, or components that requires remedial action or corrective measures to prevent operation in a canner less conservative than assumed in the accident analyses in the safety analysis report or technical specifica-tions bases; or discovery during plant life of conditions not specifically considered in the safety analysis report or technical specifications that require remedial act on or cor-
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rective ceasures to prevent the existence or development of an unsafe condition.
THIRTY' DAY 4RITTEN REPORTS The types of events listed below shall be the subject of written
- 6. 9.1. 9 reports to the Director of the Recional nffice wit ~nia thirty days of-ALL-STS-
'6-18 March 15,1977 b
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