ML20210R385
| ML20210R385 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/06/1986 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Metropolitan Edison Co, Jersey Central Power & Light Co, Pennsylvania Electric Co, GPU Nuclear Corp |
| Shared Package | |
| ML20210R390 | List: |
| References | |
| DPR-50-A-117 NUDOCS 8605160391 | |
| Download: ML20210R385 (8) | |
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UNITED STATES 9,,
8 NUCLEAR REGULATORY COMMISSION o
I
. WASHINGTON, D. C. 20686
.....J METROPOLITAN'EDIS0N COMPANY 4
JERSEY CENTRAL POWER AND LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY GPU NUCLEAR CORPORATION DOCKET.NO. 50-289 THREE MILE ISLAND NUCLEAR STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.ll7 License No. DPR-50 l
1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by GPU Nuclear Corporation, et al.
(the licensees) dated January 3, 1986, as supplemented January 31, l
1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's i
rules and regulations set forth in 10 CFR' Chapter I; 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.
C605160391 860506 i
PDR ADOCK 05000289 P
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2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.c.(2) of Facility Operating License No. OPR-50 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.117, are hereby incorporated in the license.
GPU Nuclear Corporation shall operate the facility in accordance with the lechnical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
- f. cst, /-
Jgin F. Stolz, Directo t
WR Project Directorate #6 Division of PWR Licensing-B
Attachment:
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Changes to the Technical Specifications Date of Issuance: May 6,1986
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e ATTACHMENT TO LICENSE AMENDMENT NO.117 FACILITY OPERATING LICENSE NO. DPR-50 DOCKET NO. 50-289
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Replace the following pages of the Appendix "A" Technical Specifications with the attached pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
i Remove Insert 3-8 3-8 3-9 3-9 3-9a 6-13 6-13 6-13a 6-17 6-17
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3.1.4 REACTOR COOLANT SYSTEM ACTIVITY 3.1.4.1 LIMITING CONDITION FOR OPERATION The specific activity of the prinary coolant shall be limited to:
4 a.
Less than or equal to 1.0 microcurie / gram DOSE E0VIVALENT I-131, and l
b.
Less than or equal to 100/E microcuries/ gram.*
3.1. 4. 2 APPLICABILITY: at all tines except refueling.
3.1.4.3 ACTION:
MODES: Power Operation, Start-up, Hot Standby l
'I a.
With the specific activity of the primry 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 /> **
j during one continuous time interval or exceeding the limit line shown on Figure 3.1-2a, be in at least HOT 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 j
microcuries/ gram.
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b.
With the specific activity of the prinary coolant greater than 100/E j
microcuries/ gram be in at least HOT SHUTDOWN within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Power F
operation nay continue when prinary coolant activity is less than 100/T microcuries/ gram.
MODES: At all times except refueling.-
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c.
With the specific activity of the primary ~ coolant greater Dan 1.0 l
microcurie / gram DOSE EQUIVALENT I-131 or greater than 100/E microcuries/ gram perform the sanpling and analysis requirements of Table 4.1-3 until the specific activity of the prinary coolant is l
restored to within its limits.
BASES j
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The limitations on the specific activity of the prinary coolant ensure j
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 the Part 100 limit following a steam generator tube rupture accident in conjunction with an assumed steady state primary-to-secondary steam generator leakage rate of 1.0 GPM. The values for the Ifmits on specific j
activity represent limits based upon a paranetric evaluation by the NRC of typical site locations. These values are conservative, in that the specific site parameters of TMI-1, such as site boundary, location and
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meteorological conditions, were not considered in this evaluation.
- Ishall be the average (weighted in proportion to the concentration of each j
radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and game energies per disintegration (in MeV) for 1
isotopes, other than todines, 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 Aandnent No.100,117
4 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, accommodates possible iodine spiking phenomenon which nay occur following changes in THERMAL POWER.
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Proceeding to HOT SHUTDOWN prevents the release of activity should a steam generator tube rupture since the saturation pressure of the 1
primary coolant is below the lif t pressure of the atmospheric steam relief valves.
1 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 paraneters 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 and 3.1.4.3 are met.
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3-9 Anendment No M 117
2.
The following inforation on aircraf t movements at the Harrisburg International Airport:
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a.
The total number of aircraf t evements (takeoffs and landings) at the Harrisburg International Airport for the previous l
twelve-m nth period.
i b.
The total number of mvements of aircraf t larger than 200,000 pounds at the Harrisburg International Airport for the previous twelve-mnth period, broken down into scheduled and non-scheduled (including military) takeoffs and landings, based on a current estinte provided by the airport arager or his designee.
3.
The following inforation from the periodic Leak Reduction Program tests shall be reported:
4 i
a.
Results of leakage measurements, 1
1 b.
Results of visual inspections, and 1
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c.
Maintenance undertaken as a result of Leakage Reduction Program tests or inspections.
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l 4.
The following inforation regarding pressurizer power operated j
relief valve and pressurizer safety valve challenges shall be i
reported:
a.
Date and time of incident, b.
Description of occurrence, and 4
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 coolant exceeded limits of Technical Specification 3.1.4.1 shall be reported:
l 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 as exceeded;.
1 b.
Results of the last isotopic analysis for radiciodine performed prior to exceeding the limit, results of analysis while limit j
was exceeded and results of one analysis after the radiofodine i
activi'ty was reduced to less than limit.
Each result should 1
include date and time of sanpling and the radiofodine j
concentra tions;
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6-13 Amendment No. )i, Pf, 7/, Pf,117 I
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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 radiofodine 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 primary coolant exceeded the radioiodine lindt.
C.
Monthly Operating Reports.
Routine reports of operating statistics and shutdown expertence 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 prevent recurrence, shall be reported to the NRC. Supplemental reports pay be required to fully describe final resolution of an occurrence.
In case of corrected or supplenental reports, reference shall be nade to the original report date.
(These reporting requirenents apply only to Appendix A Technical Specifications.)
A.
Prompt Notification With Written Follow-Up. The types of events
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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 transndssion 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
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(Continued on Page 6-14) l 6-13a Amendment No.117
i (2) Steaa Generator Tube Inspection within 3 months af ter Prograa (See Section 4.19.5) cogletion of inspection.
(3) Containment Integrated L'eak within 6 months af ter Rate Test cogletion of test.
(4) Inservice Inspection Program within 6 montih's af ter five years of operation.
(5) Radioactive Sealed Source Leakage within 90 days after Test revealing the presence of completion of test.
t 0.005 microcuries of Removable Contamination.
i (6) Deleted 6.9.4 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT NOTE: A single submittal my be unde for the station. The submittal should con 61ne those sections that are common to both units at the station however, for units with separate radweste systems, the submittal shall specifify the release of radioactive material from each unit.
6.9.4.1 Routine radiological environmental opera' ting reports covering the operation of the unit during the previous calendar year i
shall be submitted prior to May 1 of each year.
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6.9.4.2 The annual radiological environnental operating reports shall j
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
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appropriate), and previous environmental surveillance reports and an assessnent of the e served igacts of the plant j
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 or evidence of irreversible dange are detected by the penitoring, 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 sunmarized and tabulated results in the fornet of the J
Radiological Assessment BTP on the REMP March 1978 of all radiological environnental sagles 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 sumnery 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. 50, 44, 7/, 7/,19ti.117 n..