ML20235F758
| ML20235F758 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 09/21/1987 |
| From: | Wigginton D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20235F761 | List: |
| References | |
| NUDOCS 8709290306 | |
| Download: ML20235F758 (10) | |
Text
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[ '_ '), ( 'k UNITED STATES NUCLEAR REGULATORY COMMISSION g-WASHINGTON, D. C. 20555 yi
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UNION ELECTRIC COMPANY CALLAWAY PLANT, UNIT 1 DOCKET N0. STN 50-483 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 27 License No. NPF-30 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment filed by Union Electric Company (the licensee)datedMarch 30, 1987 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will o>erate in conforinity with the application, the provisions of tie Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the
.l 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; j
and 1
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.
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. NPF-30 is hereby amended to read as follows:
8709290306 870921 PDR ADOCK 05000483 P
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l (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 27, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby. incorporated into the license. UE shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION i
O David L. Wigg nton, Acting Director Project Directorate III-3 Division of Reactor Projects
Attachment:
i Changes to the Technical Specifications Date of Issuance: September 21, 1987 i
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.i ATTACHMENT TO LICENSE AMENDMENT NO. 27 OPERATING LICENSE N0. NPF-30 DOCKET NO. 50-483 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change. Corresponding overleaf pages are provided to maintain document completeness.
i REMOVE INSERT i
3/4 4-25 5/4 4-25 3/4 4-26 3/4 4-26 1
B 3/4 4-6 8 3/4 4-6 6-18 6-18 1
6-18a I
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REACTOR COOLANT SYSTEM BASES q
OPERATIONAL LEAKAGE (Continued)
The 1 gpm leakage from any RCS pressure isolation valve is sufficiently low to ensure early detection of possible in-series check valve failure.
It is apparent that when pressure isolation is provided by two in-series check valves and when failure of one valve in the pair can go undetected for a sub-stantial length of time, verification of valve integrity is required.
Since these valves are important in preventing overpressurization and rupture of the ECCS low pressure piping which could result in a LOCA that bypasses con-tainment, 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 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 studies show that operation may be continued with contaminant concentration levels in excess of the Steady-State Limits, up to the Transient Limits, for 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 concentra-tions 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 B0UNDARY will not exceed an 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 Callaway site, such as SITE BOUNDARY location and meteorological conditions, were not considered in this evaluation.
CALLAWAY - UNIT 1 B 3/4 4-5
[2 ACTOR COOLANT SYSTEM 1
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BASES SPECIFICACTIVITY(Continued)
The ACTION statement permitting POWER OPERATION to continue for limited time periods with the reactor coolant's specific activity greater than 1 microcurie / gram DOSE EQUIVALENT I-131, but within the allowable limit shown on Figure 3.4-1, accommodates possible iodine spiking phenomenon which may occur following changes in THERMAL POWER.
l 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.
Infonnation obtained on iodine spiking sill be' used to assess the parameters associated with spiking phenomenon. 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 The temperature and pressure changes during heatup and cooldown are 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 limited in accordance with Figures 3.4-2 and 3.4-3 for the service 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 b.
Figures 3.4-2 and 3.4-3 define limits to assure prevention of non-ductile failure only. For normal operation, other inherent plant characteristics, e.g., pump heat addition and pressurizer heater capacity, may limit the heatup and cooldown rates that can be achieved over certain pressure-temperature ranges.
CALLAWAY - UNIT 1 B 3/4 4-6 Amendment No. 27
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6-REACTOR COOLANT SYSTEM 3/4.4.8 SPECIFIC ACTIVITY-LIMITING CONDITION FOR OPERATION 3. 4.'8 The specific activity of the reactor coolant shall be limited to:
Less than or equal to 1 microcurie per gram DOSE EQUIVALENT I-131, a.
and b.
'Less than or equal to 100/E microCuries per ~ gram of gross radioactivity.
APPLICABILITY: MODES'1, 2, 3, 4, and 5.
ACTION:
MODES 1, 2 and 3*:
I With the specific activity of.the reactor coolant greater than l
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 exceed 6ng the limit line shown on Figure 3.4-1, be in at least HOT STANDBY with T"V9 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 />; and
'b.
With the specific activity of the reactor coolant greater than 100/E l
microCuries per gram of gross radioactivity, be in at least HOT STANDBY with T,yg 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 />.
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- With T,yg greater than or equal to 500*F.
1 CALLAWAY - UNIT 1 3/4 4-25 Amendment No. 27
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- REACTOR COOLANT SYSTEM-LItilTING CONDITION FOR OPERATION
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1 ACTION (Continued):
j MODES 1, 2,.3, 4, -nd 5:
1 With the specific activity of the reactor coolant greater:than 1 micro-1 Curie per gram DOSE EQUIVALENT.1-131 or greater,than 100/E microCuries l
per gram of gross radioactivity, perform the sampling and analysis
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requirements of Item 4.a) of Table.4.4-4 until the specific activity i
of the reactor coolant is restored to within its limits, i
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l SURVEILLANCE REQUIREMENTS 1
4.4.8 The specific activity of the reactor coolant shall be determined to be within the limits by performance of the sampling and analysis program of I'
Table 4.4-4.
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1 CALLAWAY - UNIT 1 3/4 4-26 Amendment No. 27
ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAfts (Continued)
'l e.
Turbine Overspeed Protection Reliability Proaram A program to increase the assurance that the Turbine Overspeed Protection System functions, if challenged, and to assure structural integrity of turbine components which could result in missile gen-eration in the event of an actual overspeed occurrence. The pro-gram shall include the following:
1)
Periodic testing and inspection requirements, 2)
Specification of test and inspection intervals, and 3)
Administrative restrictions and procedural guidance for j
program implementation such as:
record keeping; reporting; evaluation and disposition of discrepancies; review and approval of revisions to the program; and authorization (s) 4 required to deviate from the program guidelines.
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6.9 REPORTING REQUIREMENTS t
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 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.
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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 or j
commencement of commercial power operation, or (3) 9 months following initial j
I criticality, whichever is earliest.
If the Startup Report does not cover all three events (i.e., initial criticality, completion of Startup Test Program, and
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resumption or commencement of comercial 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.
CALLAWAY - UNIT 1 6-17
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ADMINISTRATIVE CONTROLS ANNUAL REPORTS (Continued) 6.9.1.5 Reports required on an annual basis shall include a tabulation on an annual basis of the number of station, utility, and 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 mainte-nance (describe maintenance), waste processing, and refueling. The dose i
i assignments to various duty functions may be estimated based on pocket dosi-meter 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 functions.
1 The report shall also include 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 radiciodine 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 sampling and the radiciodine concentrations; (3) 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 sample in which the limit was exceeded; (4) Graph of the I-131 concentration and or,e 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 ENVIRONMEi4TAL 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 prior to May 1 of each year. The initial report shall te submitted prior to 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 and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of Land Use Censuses required by Specifica-tion 3.12.2.
I This tabulation supplements the requirements of 620.407 of 10 CFR Part 20.
- A single submittal may be made for a multiple unit station.
I CALLAWAY - UNIT 1 6-18 Amendment No. 27
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' ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (Continued) l The Annual Radiological Environmental Operating Reports shall include the results of analysis.of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the i
locations specified in the Table ar.d Figures'in the ODCMi as well as i
summarized and tabulated results of these analyses and measurements in' the format of the table in the. Radiological Assessment Branch Technical Position,-
Revision 1, November 1979.
In the event that some individual 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 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 one. reactor; the results of licensee participation in
- 0nemapshallcoverstatkonsneartheSITEBOUNDARY;asecondshall include the more distant stations.
CALLAWAY - UNIT 1 6-18a Amendment No. 27