ML20155G504
| ML20155G504 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 10/05/1988 |
| From: | Calvo J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20155G507 | List: |
| References | |
| GL-85-19, NUDOCS 8810170126 | |
| Download: ML20155G504 (10) | |
Text
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UNITED STATES 3"
NUCLEAR REGULATORY COMMISSION h
,j WASHINGTON, D. C. 2055$
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KANSAS GAS & ELECTRIC COM!'AN_Y KANSAS CITY POKER AND LIGHT COMPANY KANSAS F.LECTRIC POWER _ _ COOPERATIVE, IE WOLF CREEK GENERATING STATION DOCKET NO. 50-482 AMEhDMENT TO FACILITY OPERATING LICENSE Amendnent No.18 License No. NPF-4?
1.
The Nuclear Regulatory Concission (the Cormission) has found that:
A.
The application for amendrrent to the Wolf Creek Generating Station (the facility) Facility Operating License No. NPF-42 filed by the Wolf Creek Nuclear Operating Corporation, dated July 6,1988, cenplies with the standards and requirenents of the Atomic Energy Act of 1954, as arrended (the Act), and the Cormission's rules and regula-tions set forth in 10 CFR Chapter I; B.
The facility will operate in conforniity with the application, as anended, the provisions of the Act, and the rules and regulations of the Conmission; C.
There is reasonable assurance:
(i) that the activities authorized by this arendtent can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in cortpliarce with the Consnission's regulations; D.
The issuance of this license amendirent 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 arrendtrent is in accordance with 10 CFR Part 51 of the Conmission's regulations and all applicable requirements have been satisfied.
I 8810170126 881005 PDR ADOCK 05000482 P
PNV
. 2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. NPF-42 is hereby amended to read as follows:
2.
Technical _ Spec _ifications The Technical Specifications contained in Appendix A, as revised through Amendnent No.18 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated in the license.
KG8E shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
The license amendnent is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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' c; (cav f,e,A. Calvo, Director Jos Project Directorate - IV Division of Reactor Projects - III, i
IV, Y and Special Projects t
Office of Nuclear Reactor Regulation Attachnent:
Changes to the Technical Specifications l
Cate of Issuance: October 5,1988 1
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ATTACHMENTT0, LICENSE,&ENp@q,NO._18 _
I FACILITY OPERATING LICENSE NO. NPF-42 00CKET f:0. 50-482 r
Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by anendment number and contain marginal lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain docunent j
completeness.
I REMOVE PAGES INSERT PAGES 3/4 4-25 3/4 4-25 3/4 4-26 3/4 4-26 i
B3/4 4-6 B3/4 4-6 6-10 6-18 6-18a i
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3/4.4.8 SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 3.4.8 The specific activity of the reactor coolant shall be limited to:
a.
Less than or equal to 1 microcurie per gram DOSE EQUIVALENT I-131, and b.
Less than or equal to 100 6 microCuries per gram of gross radioactivity.
APPLICABILITY:
MODES 1, 2, 3, 4, and 5.
ACTION:
MODES 1, 2, and 3*:
With the specific activity of the reactor coolant greater than
{
a.
1 microcurie per 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 3.4-1, be in at least HOT STANDBY with T less than 500*F i
within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; and avg b.
With the specific activity of the reactor coolut greater than 1006 l
f microCuries per gram of gross radioactivity, be in at least HOT STANDBY with T less than 500'F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
3yg i
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- With T,yg greater than or equal to 500'F.
WOLF CREEK - UNIT 1 3/4 4-25 Amendment No.18
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i LIMITING CONDITION FOR OPERATION ACTION (Continued)
MODES 1, 2, 3, 4, and 5-I With the specific activity of the reactor coolant greater than e
1 microcurie per gram DOSE EQUIVALENT I-131 or greater than 100/E l
microcuries per gram, perform the sampling and analysis requirements l
t of Item 4.a) of Table 4.4-4 until the specific activity of the reactor j
coolant is restored to within its limits.
t.
SURVEILLANCE REQUIREMENTS 2
4.4.8 The specific activity of the primary coolant shall be determined to be within the limits by performance of the sampling and analysis program of 1
Table 4.4-4.
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j WOLF CREEK - UNIT 1 3/4 4-26 Amendment No.18 i
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i REACTOR COOLANT BASES OPERATIONAL LEAKAGE (Continued) those valves are important in preventing overpressurization and rupture of the ECCS low pressure piping which could result in a LOCA that bypasses containment, I
these valves should be tested periodically to ensure low probability of gross failure.
The Surveillance Requirements for RCS pressure isolation valves provide added assurance of valve integrity thereby reducing the probability of gross valve failure and consequent intersystem LOCA.
Leakage from the RCS pressure isolation valves is IDENTIFIED LEAKAGE and will be considered as a portion of the allowed limit.
3/4.4.7 CHEMISTRY The limitations on Reactor Coolant System chemistry ensure that corrosion i
of the Reactor Coolant System is minimized and reduces the potential for Reactor Coolant System leakage or failure due to stress corrosion.
Maintaining the chemistry within the Steady-State Limits provides adequate corrosion protection to ensure the structural integrity of the Reactor Coolant System over the life of the plant.
The associated effects of exceeding the oxygen, chloride, and fluoride limits are time and temperature dependent.
Corrosion l
l studies show that operation may be continued with contaminant concentration levels in excess of the Steady-State Limits, up to the Transient Limits, for i
the specified limited time intervals without having a significant effect on the structural integrity of the Reactor Coolant System.
The time interval permitting continued operation within the restrictions of the Transient Limits provides time for taking corrective actions to restore the contaminant concentrations to within the Steady-State limits.
The Surveillance Requirements provide adequate assurance that concentrations in excess of the limits will be detected in sufficient time to take corrective action.
3/4.4.8 SPECIFIC ACTIVITY The limitations on the specific activity of the reactor coolant ensure that the resulting 2-hour doses at the SITE BOUNDARY will not exceed an J
appropriately small fraction of 10 CFR Part 100 dose guideline values following a steam generator tube rupture accident in conjunction with an assumed steady-state reactor-to-secondary steam generator leakage rate of 1 gpm.
The values for the limits on specific activity represent limits based upon a parametric evaluation by the NRC of typical site locations.
These values are conservative in that specific site parameters of the Wolf Creek Generating i
Station, such as SITE BOUNDARY location and meteorological conditions, were not considered in this evaluation.
l WOLF CREEK - UNIT 1 B 3/4 4-5 4
REACTOR COOLANT BASES 4
SPECIFIC ACTIVITY (Continued) 4 The ACTION statement permitting POWER OPERATION to continue for limited time periods with the reactor coolant's specific activity greater than I :.icroCurie/ gram DOSE EQ4IVALENT I-131, but within the allowable limit shown on Figure 3.4-1, accommodates possible iodine spiking phenomeno1 which may occur following changes in THERMAL POWER.
Reducing T,yg to less than 500*F prevents the release of activity should a steam generator tube rupture since the saturation pressure of the reactor coolant is below the lift pressure of the atmospheric steam relief valves.
The Surveillance Requirements provide adequate assurance that excessive specific activity levels in the reactor 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 may be permissible if justified by the data obtained.
3/4.4.9 PRESSURE / TEMPERATURE LIMITS l
The temperature and pressure changes during heatup and cooldown are 1
limited to be consistent with the requirements given in the ASME Boiler and Pressure Vessel Code,Section III, Appendix G:
1.
The reactor coolant temperature and pressure and system heatup and cooldown rates (with the exception of the pressurizer) shall be i
limited in accordance with Figures 3.4-2 and 3.4-3 for the service l
period specified thereon:
a.
Allowable combinations of pressure and temperature for specific temperature change rates are below and to the right of the limit lines shown.
Limit lines for cooldown rates between those presented may be obtained by interpolation; and WOLF CREEK - UNIT 1 B 3/4 4-6 Amendment No.18
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ADMINISTRATIVE CONTROLS 6.9 REPORTING REQUIREMENTS 4
ROUTINE REPORTS 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 Regional Administrator of the NRC Regional Office 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) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.
- 6. 9.1. 2 The Startup Report shall address each of the tests identified in the Final Safety Analysis Report FSAR and shall include a description of the measured values of the 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 commitments shall be included in this report.
6.9.1.3 Startup Reports shall be submitted within: (1) 90 days following completion of the Startup Test Program (2) 90 days following resumption of commencement of commercial power operation, or (3) 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 commercial operation) supplementary reports shall be submitted at least every 3 months until all three events have been completed.
ANNUAL REPORTS 6.9.1.4 Annual Reports covering the activities of the Unit as described below for the previous calendar year shall be submitted prior to March 1 of each year.
The initial report shall be submitted prior to March 1 of the year following initial criticality.
l 6.9.1.5 Reports required on an annual basis shall include:
Tabulation on an annu21 basis of the number of station, utility, and a.
other personnel (including contractors) receiving exposures greater than 100 mrems/yr and their associated man-rem exposure according to work and job functions,* e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special emaintenance (describe maintenance), waste processing, and refueling.
The dose
- This tabulation supplements the requirements of $20.407 of 10 CFR Part 20.
WOLF CREEK - UNIT 1 6-17 E
ADMINISTRATIVE CONTROLS t
ANNUAL REPORTS (Continued) assignments to various duty functions may be estimated 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 from external sources should be assigned to specific major work func-tions; and b.
Documentation of all challenges to the PORVs or safety valves.
2 c.
The results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3.4.8.
The following information shall be included:
(1) 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; (2) Results of the last isotopic analysis for radiciod.ine perfomed i
prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than limit.
Each result should include date and time of sampling and the radioiodine concentrations; (3) Clean-up i
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 sample in which the limit was exceeded; (4) 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 (5) The time duration when the specific activity of the primary coolant exceeded the radioiodine limit.
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1.6 Routine Annual Radiological Environmental Operating Reports covering the operation of the Unit during the previous calendar year shall be submitted by May 1 of each year.
The initial report shall be submitted by May 1 of the year following initial criticality.
The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, with operational controls 1
and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment.
The reports shall j
also include the results of the Land Use Census required by Specification 3.12.2.
The Annual Radiological Environmental Operating Reports include the results of analysis of all radiological environmental samples and of all j
environmental radiation measurements taken during the period pursuaat to the 3
locations specified in the table and figures in tho ODCM, as well as summarized j
and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, l
Navember 1979.
In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and j
explaining the reasons for the missing results.
The missing data shall be submitted as soon as possible in a supplementary report, l
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WOLF CREEK - UNIT 1 6-18 Amendment No. la
9 NOMINISTRATIVECONTROLS ANNUAL REPORTS (Continued)
The reports shall also include the following:
a summary description of the Radiological Environmental Monitoring Program; at least two legible maps
- covering all sampling locations keyed to a table giving distances and directions from the centerline of the reactor; the results of licensee participation in the Interlaboratory Comparison Program and the corrective actions being taken if the specified program is not being performed as required by Specification 3.12.3; reasons for not conducting the Radiological Environmental Monitoring Program as required by Specification 3.12.1 and discussion of all deviations from the sampling schedule of Table 3.12-1; discussion of environmental sample measure-ments that exceed the reporting levels of Table 3.12-2 but are not the result of plant ef fluents, pursuant to Specification 3.12.1; and discussion of all analyses in wnich the LLO required by Table 4.12-1 was not achievable.
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- 0ne map shall cover stations near the SITE BOUNDARY; a second shall include l
the more distant stations.
WOLF CREEK - UNIT 1 6-18a Amendment No. 18
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