ML20206J974
| ML20206J974 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 04/09/1987 |
| From: | Rubenstein L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20206J980 | List: |
| References | |
| NUDOCS 8704160231 | |
| Download: ML20206J974 (9) | |
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'e UNITED STATES 8
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NUCLEAR REGULATORY COMMISSION
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SOUTH CAROLINA ELECTRIC A GAS COMPANY l
SOUTH CAROLINA PURLIC SERVICE AUTHORITY DOCKET NO. 50-395 VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 64 License No. NPF-12 1.
The Nuclear Regulatory Comission (the Comission1 has found that:
A.
The application for amendment by South Carolina Electric A Gas e-
. Company and South Carolina Public Service Authority (the licensees) dated July 10, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's 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; l
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 (iil that such activities will be conducted in compliance with the Comission's reculations; 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 applicable reouirements 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 j
No. NPF-17 is hereby amended to read as follows:
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8704160231 870409 DR ADOCK 05000395 PDR
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(?) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 64 are hereby incorporated in the license, i
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This amendment is effective as of its date of issuance, and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION c
m h-
. a u ki v[
Lester S.
benstein, Director PWR Pro.iect Directorate 82 Division of PWR Licensing-A e._,
Office of Nuclear Reactor Regulation Attach'ent:
m Changes to the Technical Specifications Date of Issuance: April 9, 1987 4
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.
64 TO FACILITY OPERATING LICENSE NO. NPF-12 DOCKET NO. 50-395 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. Corresponding overleaf pages. are also provided to maintain document completeness.
Remove Pages Insert Pages 3/4 4-25 3/4 4-25 3/4 4-26 3/4 4-26 B3/4 4-6 B3/4 4-6 6-15 6-15
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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 primary coolant shall be limited to:
Less than or equal to 1.0 microcurie per gram DOSE EQUIVALENT I-131 a.
j and b.
Less than or equal to 2004 microcuries per gram.
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-APPLICABILITY: MODES 1, 2, 3, 4 and 5 ACTION:
MODES 1, 2 and 3*:
l With the specific activity of the primary coolant greater than
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l a.
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
' g.,
shown on Figure 3.4-1, be in at least HOT STAND 8Y with T"'9 less
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than 500*F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With the specific activity of the primary coolant greater than 1004 microcurie per gram, be in at least HOT STANDBY with T"VUless than 500*F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
MODES 1, 2, 3, 4 and 5:
With the specific activity of the primary coolant greater than.1.0 a.
microcurie per gram DOSE EQUIVALENT I-131 or greater than 100/E microcuries per gram, perform the sampling and analysis requirements of item 4a of Table 4.4-4 until the specific activity of the primary coolant is restored to within its limits.
SURVEILLANCE REQUIREMENTS 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 Table 4.4-4.
" With T,yg greater than or equal to 500*F.
SUP9tER - UNIT 1 3/4 4-25 Amendment No. 64
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THIS PAGE IS INTENTIONALLY LEFT BLANK f
i Amendment No. U,64 SUP9tER - UNIT 1 3/4 4-26
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REACTOR COOLANT SYSTEM BASES 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. There-fore, 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 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 otudies show that operation may be continued with contaminant concentration
. g.3 le nis in excess of the Steady State Limits, up to the Transient Limits, for the specified limited time intervals without having a significant effect on g-the structural integrity of the Reactor Coolant System.
The time interval 1
permitting continued operation within the restrictions of the Transient Limits provides time for taking corrective actions to restore the contaminant concen-trations to within the Steady State Limits.
l The surveillance requirements provide adequate assurance that' concentrations in excess of the limits will be detected in sufficient time to take corrective I
cetion.
H 3/4.4.8 SPECIFIC ACTIVITY The limitations on the specific activity of the primary 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 limits following a steam generator tube rupture accident in conjunction with an assumed steady state primary-to-l secondary steam generator leakage rate of 1.0 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 Virgil C. Summer site, such as site boundary location and meteorological conditions, were not considered in this evaluation, i
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SUMMER - UNIT I B 3/4 4-5
s REACTOR COOLANT SYSTEM BASES i
SPECIFIC ACTIVITY (Continued)
The ACTION statement permitting POWER OPERATION to continue for limited time periods with the primary coolant's specific activity greater than 1.0 microcuries/ 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.
Reducing T,yg to less than 500*F prevents the release of activity should a steam generator tabe rupture since the saturation pressure of the primary coolant is below the lift pressure of the atmospheric steam relief valves.
i The surveillance requirements provide adequate assurance that excessive specific activity levels in the primary coolant will be detected ir. sufficient time to take corrective action.
Information obtained on iodine spiking will be used l
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.
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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-.---
fressure 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.
a)
Allowable combinations of pressure and temperature for specific temperature change rates are below and to the right of the limit L
lines shown.
Limit lines for cooldown rates between those presented I
may be obtained by interpolation.
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l SumiER - UNIT 1 8 3/4 4-6 Amendment No. di, 64
.i ADMINISTRATIVE CONTROLS l
6.9.1.2 The startup report shall address each of the tests identified in the; Final Safety Analysis Report and shall include a description of the measured values of the operating conditions or characteristics obtained during the test i
program and a comparison of these values with design predictions and specifica-tions. 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.
j 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 i
commencement of commercial power operation, or (3) 9 months following initial I
criticality, whichever is earliest.
If the Startup Report does not cover all i
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 three months until all three events have been completed.
j ANNUAL REPORT j ',-
6.9.1.4 Annual reports covering the activities of the unit as described below iit
- 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.
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6.9.1.5 deports required on an annual basis shall. include a tabulation on an annual basis of the number of station, utility -and other personnel (including manrem exposure according to work and job functions,gyr and their assoc contractors) receiving exposures greater than 100 ar e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling. The dose assignments
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to various duty functions may be estimated based on pocket dosimeter, TLD, or film badge measurements.
Small exposures totalling less than 20 percent of the individual total dose need not be accounted for.
In the aggregate, at least 80 percent of the total whole body dose received from external sources should be assigned to specific major work functions.
This 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 f
of the last isotopic analysis for radiciodine performed prior to exceeding the 6
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
(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 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.
MThis tabulation supplements the requirements of $20.407 of 10 CFR Part 20.
SUMER - UNIT 1 6-15 Amendment No. M
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l ADMINISTRATIVE CONTROLS l
l ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT i
6.9.1.6 Routine radiological environmenal 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 May 1 of the year following initial criticality.
6.9.1.7 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, j
including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment i
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.
If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.
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The annual radiologi. cal environmental operating reports shall include summarized i
and tabulated results in the format of Regulatory Guide 4.8, December 1975 of M
"all radiological environmental samples taken during the report period.
In the eevent that some results are not available for inclusion with the report, the l
toport shall be submitted noting and explaining the reasons for the missing
. p asults..The missing data sha114e submitted as soon as possible in a
, % upplementary toport. --
j e-The reports shall also include the following: a summary description of the
. radiological environmental sonitoring program; a map of all sampling locations keyed to a table giving distances and directions from one reactor; and the results of licensee participation in the Interlaboratory Comparison Program, esquired by Specification 3.12.3.
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT I
6.9.1.8 Routine radioactive affluent release reports covering the operation
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i 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 report shall begin with the date of initial criticality.
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SUNiER - UNIT 1 6-16 l
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