ML20137C096
| ML20137C096 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/03/1986 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20137C076 | List: |
| References | |
| NUDOCS 8601160194 | |
| Download: ML20137C096 (5) | |
Text
r 3.1.4 REACTOR COOLANT SYSTEM ACTIVITY 3.1.4.1 LIMITING CONDITION FOR OPERATION The specific activity of the primry coolant shall be limited to:
a.
Less than or equal to 1.0 microcurie / gram DOSE EQUIVALENT I-131, and b.
Less than or equal to 100/E microcuries/ gram.*
3.1.4.2 APPLICABILITY: at all times except refueling.
3.1.4.3 ACTION:
MODES:
Power Operation, Start-up, Hot Standby l
a.
With the specific activity of the primary coolant greater than 1.0 microcurie / gram DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> **
during one continuous time interval or exceeding the limit line shown on Figure 3.1-2a, be in at least H0T SHUTDOWN within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
Power operation my continue when DOSE EQUIVALENT I-131 is below 1.0 microcuries/gra m.
l b.
With the specific activity of the prinary coolant greater than 100/E microcuries/ gram be in at least H0T SHUTDOWN within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
Power operation nay continue when priary coolant activity is less than 100/T microcuries/ gram.
MODES: At all times except refueling, g
c.
With the specific activity of the primary coolant greater than 1.0 microcurie / gram DOSE EQUIVALENT I-131 or greater than 100/E E
microcuries/ gram perform the sanpling and analysis requirements of Table 4.1-3 until the specific activity of the prinary coolant is restored to within its limits.
OD BASES SR mo The limitations on the specific activity of the prinary coolant ensure ex that the resulting 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> doses at the site boundary will be well within 3
the Part 100 limit following a steam generator tube rupture accident in C,
conjunction with an assumed steady state primary-to-secondary steam generator leakage rate of 1.0 GPM.
The values for the limits on specific 5
activity represent limits based upon a parametric evaluation by the NRC k
of typical site locations. These values are conservative, in that the specific site parameters of TMI-1, such as site boundary, location and meteorological conditions, were not considered in this evaluation.
- Yshall be the average (weighted in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and gamna energies per disintegration (in MeV) for isotopes, other than iodines, with half lives greater than 15 minutes, naking up at least 95% of the total non-iodine activity in the coolant.
- The time period begins from the time the sample is taken.
3-8 Amendment No.108'
The ACTION statement permitting POWER OPERATION to continue for limited time periods with the primary coolant's specific activity greater than 1.0 microcurie / gram DOSE EQUIVALENT I-131, but within the allowable limit shown on Figure 3.1-2a, accomt.,odates possible iodine spiking phenomenon which my occur following changes in THERMAL POWER.
Proceeding to HOT SHUTDOWN prevents the release of activity should a steam generator tube rupture since the saturation pressure of the primry coolant is below the lif t pressure of the atmospheric steam relief valves.
The surveillance requirements provide adequate assurance that excessive specific activity levels in the primary coolant will be detected in sufficient time to take corrective action.
Information obtained on-iodine spiking will be used to assess the parameters associated with spiking phenomena. A reduction in frequency of isotopic analyses following power changes nay be permissible if justified by the data obtained.
The NRC staff has performed a generic analysis of airborne radiation released via the Reactor Building Purge Isolation Valves.
The dose contribution due to the radiation contained in the air and steam released through the purge isolation valves prior to closure was found to be acceptable provided that the requirements of Specifications 3.1.4.1, 3.1.4.2 a nd 3.1.4.3 a re met.
3-9 Anendnent Ho. g
2.
The following inforation on aircraf t mvements at the Harrisburg International Airport:
a.
The total number of aircraf t movements (takeoffs and landings) at the Harrisburg International Airport for the previous twelve-month period.
b.
The total number of movements of aircraf t larger than 200,000 pounds at the Harrisburg International Airport for the previous twelve-month period, broken down into scheduled and non-scheduled (including military) takeoffs and landings, based on a current estimte provided by the airport anager or his designee.
3.
The following inforation from the periodic Leak Reduction Program tests shall be reported:
a.
Results of leakage measurements, b.
Results of visual inspections, and s
c.
Maintenance undertaken as a result of Leakage Reduction Program tests or inspections.
4.
The following inforation regarding pressurizer power operated relief valve and pressurizer safety valve challenges shall be reported:
a.
Date and time of incident, b.
Description of occurrence, and c.
Corrective measures taken if incident resulted from an equipment failure.
5 The following inforation regarding the results of specific activity analysis in which the primry coolent exceeded limits of Technical Specification 3.1.4.1 shall be reported:
a.
Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; b.
Results of the last isotopic analysis for radiofodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radiciodine activity was reduced to less than limit.
Each result should include date and time of sappling and the radioiodine concentra tions; 6-13 Amendment No. Ji, M, M, D(
_4 _ ' '
c.
Clean-up system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sanple in which the limit was exceeded; d.
Graph of the I-131 concentration and one other radiciodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and e.
The time duration when the specific activity-of the prinary coolant exceeded the radioiodine limit.
C.
Monthly Operating Reports.
Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the U.S. Nuclear Regulatory Commission at the address specified in R.G.
-10.1, no later than the fif teenth of each month following the calendar month covered by the report.
6.9.2 Reportable Occurrences Reportable Occurrences, including corrective actions and measures to preventJecurrence, shall be reported to the NRC. Supplemental reports pay be required to fully describe final resolution of an occurrence.
In case of corrected or supplemental reports, reference shall be nade to the original report date.
(These reporting requirener+s apply only to Appendix A Technical Specifications.)
A.
Pronpt Notification With Written Follow-Up. The types of events listed below shall be reported as expeditiously as possible, but 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, nailgram, telecopy or facsimile transmission to the Administrator of the NRC Region I Office, or his designate no later than the first working day following the event, with a written (Continued on Page 6-14) 6-13a
m (2) Stean Generator _ Tubs Insp:ction within 3 months af ter Program (Sto S:ction 4.19.5) conpletion of inspection.
(3) Containment Integrated Leak within 6 months af ter Rate Test completion of test.
(4) Inservice Inspection Program within 6 months af ter five years of operation.
(5) Radioactive Sealed Source Leakage within 90 days after Test revealing the presence of completion of test.
> 0.005 microcuries of Removable Contamination.
(6) Deleted 6.9.4 ANNUAL RADIOLOGICAL ENVIROW4 ENTAL OPERATING REPORT NOTE: A single submittal nay be nade for the station. The submittal should combine those sections that are common to both units at the station however, for units with separate radwaste systems, the submittal shall specif tfy the release of radioactive naterial from each unit.
6.9.4.1-Routine radiological environmental operating reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year.
6.9. 4. 2 The annual radiological environmental operating reports shall include. sumnaries, interpretations, and an analysis of trends of the results of the radiological environnental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as
. appropriate), and previous environmental surveillance reports and an assessnent of the observed impacts of the plant operation on the environment.
The reports shall also include the results of the land use censuses required by Technical Specification 3.23.2.
If harmful effects of evidence of irreversible danage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.
The annual radiological environmental operating reports shall include summarized and tabulated results in the fornet of the Radiological Assessment BTP on the REMP March 1978 of all radiological environmental sanples taken during the report period.
In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results.
The missing data shall be submitted as soon as possible in a supplementary report.
The reports shall also include the following: a sumnary description of the radiological environnental monitoring program; a nap of all sampling locations keyed to a table giving distances and directions from one reactor; and the results of licensee participation in the 6-17 Amendment Nos. %, {A, ?f, y/, J06'
.