ML20206B002
| ML20206B002 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 04/01/1987 |
| From: | Jabbour K Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20206B004 | List: |
| References | |
| NUDOCS 8704080270 | |
| Download: ML20206B002 (13) | |
Text
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4 UNITED STATES 7
- 'n NUCLEAR REGULATORY COMMISSION
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VVASHINGTON, D. C. 20655 DUKE POWER COMPANY NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION SALUDA RIVER ELECTRIC COOPERATIVE, INC.
DOCKET N0. 50-413 CATAWBA NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE
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Amendment No. 25 e
License No. NPF-35 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the Catawba Nuclear Station, Unit 1 (the facility) Facility Operating License No. NPF-35 filed by the Duke Power Company acting for itself, North Carolina Electric Membershio.
Corporation and Saluda River Electric Coooerative, Inc., (licensees) dated December 13, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, 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 set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all apolitable requirements have been satisfied.
2.
Accordingly, the license is hereby amended 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 No. NPF-35 is hereby amended to read as follows:
1 (2) Technical Specifications and Environmental Protection Plan i
The Technical Specifications contained in Appendix A, as revised through Amendment No.
25, and the Environmental Protection Plan
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. contained in Appendix B. both of which.are attached hereto, are-hereby incorporated into this license.. Duke-Power Company shall operate the facility -in accordance with the. Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance..
FOR THE NUCLEAR REGULATORY COMMISSION Kahtan Jabbour, Project Manager PWR Project Directorate No. 4
- Division of PWR Licensing-A
Attachment:
Technical Specification Changes.
Date of' Issuance: April'1, 1987
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DUKE POWER COMPANY NORTH CAROLINA MUNICIPAL POWER AGENCY N0. 1 PIEDMONT MUNICIPAL POWER AGENCY DOCKET NO. 50-414 CATAWBA NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE
,s Amendment No.15 License No. NPF-52 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the Catawba Nuclear Station, Unit 2 (the facility) Facility Operating License No. NPF-52 filed by the Duke Power Company acting for itself, North Carolina Municipal Power Agency No. I and Piedmont Municipal Power Agency, (licensees) dated December 13, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations as set forth in 10 CFR Chapter I; B.
The frcility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; 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 l
in compliance with the Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to the l
common defense and security or to the health and safety of the public; 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 hereby amended 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 No. NPF-52 is hereby amended l
to read as follows:
l (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Apoendix A, as revised through Amendment No.15, and the Environmental Protection Plan
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- contained in Appendix.B. both of which are attached hereto, are
'hereby incorporated into this license. Duke Power Company shall operate the faci _lity in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3. 'This' license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION k
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Kahtan Jabbour Project Manager-PWR Project Directorate No. 4 Division of PWR Licensing-A
Attachment:
Technical Specifica' tion Changes Date of Issuance: April 1, 1987 ehy8+fy %o6) o*
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Or ATTACHMENT TO LICENSE-AMENDMENT NO. 25 FACILITY OPERATING LICENSE NO. NPF-35 DOCKET NO. 50-413 AND TO LICENSE AMENDMEf'T NO.15 FACILITY OPE 9aTING LICENSE NO. NPF-52 g
DOCKET N0. 50-414
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Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
Amended Page 3/4 4-27 3/4 4-28 B 3/4 4-5 B 3/4 4-6 6-16 6-17 6-18 6-19 l
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REACTOR COOLANT SYSTEM 3/4.4.8 SPECIFIC ACTIVITY LIMITING CONDITION FOR'0PERATION 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 specific activity.
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 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; avg b.
With_the gross specific activity of the reactor coolant greater than 100/E 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 />; and The provisions of Specification 3.0.4 are not applicable.
c.
"With T,yg greater than or equal to 500*F.
CATAWBA - UNITS 1 & 2 3/4 4-27 Amendment No.25 (Unit 1)
Amendment No.15 (Unit 2)
' LIMITING CONDITION FOR OPERATION ACTION (Continued)
MODES 1, 2, 3, 4, and 5:
With the specific activity of the reactor coolant greater than 1 microcurie per gram DOSE EQUIVALENT I-131 or greater than 100/E micro-curies per gram, 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.
CATAWBA - UNITS 1 & 2 3/4 4-28 Amendment No. 25 (Unit 1)
Amendment No.15 (Unit 2)
REACTOR COOLANT SYSTEM BASES 3/4.4.7 CHEMISTRY
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The limitations on Reactor Coolant System chemistry, ensure that corrosion of the Reactor Coolant System is minimized and reduces the potential for Reactor-
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-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
.3 of the Reactor Coolant System.
The time interval permitting continued operation within the restrictions of the Transient Limits provides time for taking correc-6 tive 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 appro-priately small fraction of Part 100 dose guideline values 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 limits on specific activity represent limits based upon a parametric eval-l uation by the NRC of typical site locations. These values are conservative l
in that specific site parameters of.the Catawba site,'such as SITE BOUNDARY location and meteorological conditions, were not considered in this evaluation.
i The ACTION statement permitting POWER OPERATION to continue for limited time periods with the reactor coolant's specific activity greater than 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.
I i
i CATAWBA - UNITS 1 & 2 8 3/4 4-5 Amendment No. 25 (Unit 1)
Amendment No.15 (Unit 2)
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RE' ACTOR 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 microcurie /
gram DOSE EQUIVALENT I-131, and because, if the limit is exceeded.the radiciodine 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_radiciodine level in the reactor coolant were at their limits,-the radiciodine 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 g
been made for several reasons. The first consideration is the difficulty to identify short-lived radionuclides in a sample that requires a significant a
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 I week, and about 1 month.
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CATAWBA - UNITS 1 & 2 B 3/4 4-6 Amendment No. 25 (Unit 1)
Amendment No.15 (Unit 2) l
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h ADMINISTRATIVE CONTROLS ANNUAL REPORTS M l
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 a tabulation on an annual basis of the number of station, utility, and other personnel (including contrac-tors) receiving exposures greater than 100 arem/yr and their associated man-rem exposure according to work and job functions E, e.g., reactor operations and o
j surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling. The dose assignments to various duty functions may be estimated based on pocket dosimeter, TLD, or i
film badge _ measurements.
Small exposures totalling less than 20% of the indi-vidual 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.
b.
Primary Coolant Specific Activity c
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 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 f,-
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
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one analysis after the radiciodine activity was reduced to less than t
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; r
- 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 radiciodine 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 prior to May 1 of each year. The initial report shall be submitted prior to i
May 1 of the year following initial criticality.
1/ 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.
2/ This tabulation supplements the requirements of 6 20.407 of 10 CFR Part 20.
- A single submittal may be made for a multiple unit station.
l CATAWBA - UNITS 1 & 2 6-16 Amendment No. 25 (Unit 1)
Amendment No.15 (Unit 2)
ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (Continued)
V 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 as appropriate, and with previous environmental surveillance reports, and an j.
assessment of the observed. impacts of the plant operation on the environment.
The reports shall also include the results of the land use census required by Specification 3.12.2.
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 and Figures in the ODCM, as well as summarized r
and tabulated results of these analyses and measurements in the format of the I
table in the Radiological Assessment Branch Technical Position, Revision 1, 1'
November 1979.
In the event that some individual results are not available i
for inclusion with the report, the report shall be submitted noting and i
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
- cover-
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ing all sampling locations keyed to a table giving distances and directions from the centerline of one reactor; the results of licensee participation in the Interlaboratory Comparison Program, required by Specification 3.12.3; discussion 4
of all deviations from the sampling schedule of Table 3.12-1; and discussion of all analyses in which the LLD required by Table 4.12-1 was not achievable.
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SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT **
6.9.1.7 Routine Radioactive Effluent Release Reports covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year. The period of the first re-F port shall begin with the date of initial criticality.
The Radioactive Efflu-l i
ent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined j
in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, 1
with data summarized on a quarterly basis following the format of Appendix B thereof.
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- 0ne map shall cover stations near the SITE BOUNDARY; a second shall include 3
the more distant stations.
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- 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;
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however, for units with separate radwaste systems, the submittal shall i
specify the releases of radioactive material from each unit.
i CATAWBA - UNITS 1 & 2 6-17 Amendment No. 25 (Unit 1) l Amendment No.15 (Unit 2) i 9
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ADMINISTRATIVE CONTROLS a.
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT (Continued) 4 The Radioactive Effluent Release Report to be submitted within 60 days l
after January 1 of each year shall include an annual summary of hourly meteoro-logical data collected over the previous year.
This annual summary may be either in the form of an hour-Dy-hour listing on magnetic tape of wind speed, wind 4
direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmos-pheric stability.* This same report shall include an assessment of the radia-tion doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year.
This same report shall also 4
include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (Figures 5.1-3 and 5.1.4) durin
- j used in making these assessments, i.e., g the report period. All assumptions l
specific activity, exposure time and i
location, shall be included in these reports.
The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents, as determined by sampling frequency and measurement, shall be used for determin-ing the gaseous pathway doses.
The assessment of radiation doses shall be per-4 formed in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (0DCM).
The Radioactive Effluent Release Report to be submitted 60 days after I
January 1 of each year shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent path-ways and direct radiation, for the previous calendar year to show conformance with 40 CFR Part 190, " Environmental Radiation Protection Standards for Nuclear Power Operation." Acceptable methods for calculating the dose contribution from l
liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1, October 1977.
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The Radioactive Effluent Release Reports shall include the following informa-l tion for each type of solid waste shipped offsite during the report period:
l Total Container volume, in cubic meters, a.
b.
Total Curie quantity (determined by measurement or estimate),
Prir.cipal radionuclides (determined by measurement or estimate),
c.
i d.
Type of waste (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms),
I e.
Number of shipments, and f.
Solidification agent or absorbent [e.g., cement or other approved agents (media)]
- In lieu of submission with the first half year Radioactive Effluent Release l
Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon i
request.
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l CATAWBA - UNITS 1 & 2 6-18 Amendment No.25 (Unit 1) j Amendment No.15 (Unit 2) 1=g-w 1
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ADMINISTRATIVE CONTROLS SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT (Continued)
The Radioactive Effluent Release Reports shall include a list and l
description of unplanned releases from the site to UNRESTRICTED AREAS of radio-active materials in gaseous and liquid effluents made during the reporting period.
The Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP) and to the OFFSITE DOSE CALCULATION MANUAL (ODCM), as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Specification 3.12.2.
MONTHLY OPERATING REPORTS 6.9.1.8 Routine reports of operating statistics and shutdown experience, in-ciuding documentation of all challenges to the PORVs or safety valves, shall e
be submitted on a monthly basis to the Director, Office of Resource Management, i
U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the NRC Regional Office, no later than the 15th of each month following the calendar month covered by the report.
RADIAL PEAKING FACTOR LIMIT REPORT 6.9.1.9 The W(z) functions for RAOC and Base Load operation and the l
ND (as required) shall be provided to the Director, Nuclear Reactor value for APL Regulation, Attention:
Chief, Core Performance Branch, U.S. Nuclear Regulatory Commission, Washington, D.C.
20555 at least 60 days prior to cycle initial criticality.
In the event that these values would be submitted at some other time during core life, it will be submitted 60 days prior to the date the values
+
would become effective unless otherwise exempted by the Commission.
Any information needed to support W(z), W(z)BL ND and APL will be by request i
from the NRC and need not be included in this report.
CATAWBA - UNITS 1 & 2 6-19 Amendment No. 25 (Unit 1)
Amendment No.15 (Unit 2)
.