ML20211M437
| ML20211M437 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 12/08/1986 |
| From: | Hood D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20211M441 | List: |
| References | |
| TAC-60423, TAC-60424, NUDOCS 8612170268 | |
| Download: ML20211M437 (12) | |
Text
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^g UNITED STATES 8
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WASHINGTON, D. C. 20555 DLTE PNER CCFPANY DOCKET h0. 50-369 PcGUIRE NUCLEAR STATION, UNIT 1 AMEhDMENT TO FACILITY OPERATING LICENSE Amendment No. 66 License No. NPF-9 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the McGuire Nuclear Station, Unit 1 (the facility) Facility Operating License No. NPF-9 filed by the Duke Power Company (the licensee) dater December 13, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity with the application, as amended, the provisions of the 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 health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common 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 appliceble requirements have been satisfied.
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Accordingly, the license is hereby arrended by page changes to the Technical Specifications as indicated in the attachments to this license amendment, and Paragraph 2.C.(2) of Facility Operating License fio. fiPF-9 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment flo.66, are hereby incorporated into the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environr. ental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR TIIE liUCLEAR REGULATORY COMMISSION
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Darl ifood, Project Manager PWR Project Directorate #4 Division of PWR Licensing-A
Attachment:
Technical Specification Changes Date of Issuance: December 8, 1986 g yf '3
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DUKE POWER COMPANY D0CKET NO. 50-370 t'cGblkE f.UCLEAR STATIOI;, UNIT 2 APENDPENT TO FACILITY OPERATING LICENSE Amendment No. 47 License No. NPF-17 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the McGuire Nuclear Station, Unit 2 (the facility) Facility Operating License No. NPF-17 filed by the Duke Power Company (the licensee) dated December 13, 1985, Act of 1954, as amended (the Act) quirements of the Atomic Energy complies with the standards and re and the Comission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity with the application, as amended, the provisions of the 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 health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; 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.
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2.
Accordingly, the license is hereby arrerded by page changes to the Technical i
Specifications as indicated in the attachments to this license arrendment, and Paragraph 2.C.(2) of Facility Operating License fio, fiPF-17 is hereby amended to read as follows:
(2) Technical Specificat_icns l
The Technical Specifications contained in Appendix A, as revised through Amendn;ent !!c.47, are hereby incorporated into the license.
The licensee shall cPerate the facility in accordance with the Technical Specifications and the Envircrr: ental Protection Plan.
3.
This license amendrcent is effective as of its date of issuance.
FOP, Tile fiUCLEAR REGULATORY COMMISSI0fi
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Parl Hood, Project Manager PWR Project Directorate #4 Division of PWR Licensing-A
Attachment:
Technical Specification Changes Date of Issuance: December 8, 1986 l
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ATTACHMENT TO LICENSE AMENDriENT NC. 66 FACILITY OPERATING LICENSE N0. NPF-9 DOCKET h0. 50-2f,9 AND TO LICENSE AhEhDI.ENT NO. 47 FACILITY OPERATING LICENSE h0. NPF-17 DOCKET NO. 50-370 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by /mendr4r.t renter and contain vertical lines indicating the areas of change.
Arended Page 3/4 4-25 3/4 4-26 3/4 4-29 B3/4 4-5 B3/4 4-6 6-17 6-17a (rew) i i
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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:
a.
Less than or equal to 1.0 microcurie per gram DOSE EQUIVALENT I-131, and I
b.
Less than or equal to 100/E microcuries per gram of gross specific activity.
APPLICABILITY:
MODES 1, 2, 3, 4, and 5.
ACTION:
MODES 1, 2 and 3*:
a.
With the specific activity of the reactor coolant greater than 1.0 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'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 />; i
i b.
With_the specific activity of the reactor coolant greater than 100/E microcuries per-gram, 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 c.
The provisions of Specification 3.0.4 are not applicable, i
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- With T,yg greater than or equal to 500*F.
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I Amendment No.47 (Unit 2)
McGUIRE - UNITS 1 and 2 3/4 4-25 Amendment No.66 (Unit 1) i i
REACTOR COOLANT SYSTEM ACTION:
(Continued)
MODES 1, 2, 3, 4, and 5:
With the specific activity of the reacter coolant greater than 1.0 microcurie per gram DOSE EQUIVALEN1 I-131 or greater than 100/E_
microCuries per gram of gross specific activity, perform the sampling and analysis requirements of Item 4.a) of Table 4.4-4 until the specific activity of the reactor coolant is restored to within its limits.
SURVEILLANCE REQUIREMENTS 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 Table 4.4-4.
Amendment No.66 (Unit 1)
McGUIRE - UNITS 1 and 2 3/4 4-26 Amendment No.47 (Unit 2)
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55 TABLE 4.4-4 (Continued) c El TABLE NOTATION E
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,Until the specific activity of the Reactor Coolant System is restored within its limits v'
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Sample to be taken after a minimum of 2 EFPD and 20 days of POWER OPERATION have elapsed since reactor was
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last subcritical for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or longer.
A gross radioactivity analysis shall consist of the quantitative measurement of the total specific activity oo of the reactor coolant except for radionuclides with half-lives less than 10 minutes and all radioiodines.
The total specific activity shall be the sum of the beta gamma activity in the sample within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after the sample is taken and extrapolated back to when the sample was taken.
Determination of the contributors to the gross specific activity shall be based upon those energy peaks identifiable with a 95% confidence level.
The latest available data may be used for pure beta emitting radionuclides.
RAR R
A radiochemical analysis for l shall consist of the quantitative measurement of the specific activity for each radionuclide, except for radionuclides with half-lives less than 10 minutes and all radiciodines, a
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which is identified in the reactor coolant.
The specific activities for these individual radionuclides y;
shall be used in the determination of E for the reactor coolant sample.
Determination of the contributors
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to E shall be based upon those energy peaks identifiable with a 95% confidence level.
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REACTOR COOLANT SYSTEM BASES 1
OPERATIONAL LEAKAGE (Continued)
PRESSURE BOUNDARY LEAKAGE of any magnitude is unacceptable since it may be indicative of an impending gross failure of the pressure boundary.
Therefore, the presence of any PRESSURE BOUNDARY LEAKAGE requires the unit to be promptly placed in COLD SHUTDOWN.
3/4.4.7 CHEMISTRY
.The limitations on Reactor Coclant 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.
Main-taining 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 4
concentration levels in excess of the Steady State Limits, up to the Transient Limits, for the specified limited time intervals without having a significant i
effect on the structural integrity of the Reactor Coolant System.
The time interval p9rmitting continued operation within the restrictions of the Transient L*mits provides time for taking corrective actions to restore the contaminant concentrations to within the Steady State Limits.
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The Surveillance Requirements provide adequate assurance that concentrations in excess of the limits will be detected in sufficient time to take corrective ACTION.
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3/4.4.8 SPECIFIC ACTIVITY The limitations on the specific activity of the reactor coolant ensure 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 not exceed an appropriately small fraction of Part 100 dose guideline values following a steam generator tube rupture accident in conjunction with an assumed steady j
state primary-to-secondary steam generator leakage rate of 1.0 gpm.
The values for the limits on specific activity represent limits based upon a parametric l
evaluation by the NRC of typical site locations.
These values are conservative in that specific site parameters of the McGuire site, such as site boundary location and meteorological conditions, were not considered in this evaluation.
The ACTION statement permitting POWER OPERATION to continue for limited time periods with the reactor coolant's specific activity greater than i
1.0 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.
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Amendment No. 66(Unit 1) i McGUIRE - UNITS 1 and 2 B 3/4 4-5 Amendment No. 47 (Unit 2)
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REACTOR COOLANT SYSTEM BASES SPECIFIC ACTIVITY (Continued)
The sample analysis for determining the gross specific activity and E can exclude the radiciodines because of the low reactor coolant limit of 1 micro-Curie / gram DOSE EQUIVALENT I-131, and because, if the limit is exceeded, the radioiodine level is to be determined every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
If the gross specific activity level and radioiodine level in the reactor coolant were at their limits, the radioiodine contribution would be approximately 1%.
In a release of reactor coolant with a typical mixture of radioactivity, the actual radio-iodine contribution would probably be about 20%.
The exclusion of radio-nuclides with half-lives less than 10 minutes from these determinations has been made for several reasons. The first consideration is the difficulty to identify short-lived radionuclides in a sample that requires a significant time to collect, transport, and analyze.
The second consideration is the predictable delay time between the postulated release of radioactivity from the reactor coolant to its release to the environment and transport to the SITE BOUNDARY, which is relatable to at least 30 minutes decay time.
The choice of 10 minutes for the half-life cutoff was made because of the nuclear characteristics of the typical reactor coolant radioactivity.
The radionuclides in the typical reactor coolant have half-lives of less than 4 minutes or half-lives of greater than 14 minutes, which allows a distinction between the radionuclides above and below a half-life of 10 minutes.
For these reasons the radionuclides that are excluded from consideration are expected to decay to very low levels before they could be transported from the reactor coolant to the SITE BOUNDARY under any accident condition.
Based upon the above considerations for excluding certain radionuclides from the sample analysis, the allowable time of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> between sample taking and completing the initial analysis is based upon a typical time necessary to perform the sampling, transport the sample, and perform the analysis of about 90 minutes.
After 90 minutes, the gross count should be made in a reproducible geometry of sample and counter having reproducible beta or gamma self-shielding properties.
The counter should be reset to a reproducible efficiency versus energy.
It is not necessary to identify specific nuclides.
The radiochemical determination of nuclides should be based on multiple counting of the sample with typical counting basis following sampling of less than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, about 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, about 1 day, about 1 week, and about 1 month.
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Amendment No. 66 (Unit 1)
McGUIRE - UNITS 1 and 2 B 3/4 4-6 Amendment No. 47 (Unit 2)
ADMINISTRATIVE CONTROLS STARTUP REPORT (Continued) 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 com-parison of these values with design predictions and specifications.
Any corrective actions that were required to obtain satisfactory cperation shall also be described.
Any additional specific details required in License con-ditions 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, or (2) 90 days following resumption or 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 REPORTSE 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.
6.9.1.5 Annual Reports shall include the activities of the unit as described below:
a.
Personnel Exposures Reports required on an annual basis shall include tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their p sociated man-rem exposure according to work and job functions,-
e.g., reactor operations and surveillance, inservice in-spection, routine maintenance, special maintenance (describe mainte-nance), waste processing, and refueling.
The dose 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 functions.
A single submittal may be made for a multiple unit station.
The submittal should combine those sections that are common to all units at the station.
MThis tabulation supplements the requirements of 620.407 of 10 CFR Part 20.
McGUIRE - UNITS 1 and 2 6-17 Amendment No.66 (Unit 1)
Amendment No.47 (Unit 2)
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ADMINISTRATIVE CONTROLS 1/
ANNUAL REPORTS b.
Primary Coolant Specific Activity Reports required on an annual basis shall 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 include:
- 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 radioiodine 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 radioiodine 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 one other radioiodine 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.
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McGUIRE - UNITS 1 and 2 6-17a Amendment No. 66 (Unit 1)
Amendment No. 47 (Unit 2)
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