ML20008F208
| ML20008F208 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 02/25/1981 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20008F207 | List: |
| References | |
| NUDOCS 8103120493 | |
| Download: ML20008F208 (17) | |
Text
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UNITED STATES g
NUCLEAR REGULATORY COMMISSION y
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FLORIDA POWER CORPORATION
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CITY OF ALACHUA CITY OF BUSHNELL CITY OF GAINESVILLE CITY OF KISSIMMEE CITY OF LEESBURG CITY OF NEW SMYRNA BEACH AND UTILITIES COMMISSION, CITY OF NEW SMYRNA BEACH CITY OF OCALA ORLANDO UTILITIES COMMISSION AND CITY OF ORLANDO SEBRING UTILITIES COMMISSION SEMINOLE ELECTRIC COOPERATIVE, INC.
CITY OF TALLAHASSEE DOCKET NO. 50-302 CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 37 License No. DPR-72 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Florida Power Corporation, et al (the licensees) dated April 23, 1980, as supplemented December 31, 1980, 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; i
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; l
C.
There is reasonable assurance (i) that the activities authorized by this i
amendment can be conducted without endangering the health and safety i
of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common i
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 Commission's regulations and all applicable requirements have been satisfied.
-81081.20 /f 6
. 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. DPR-72 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Apperdices A and B, as revised through Amendment No. 37, are hereby incorporated in the license.
Florida Power Corporation shall operate the facility in accordance -
with the Technical Specifications.
3.
This license amendment is effective as of the date
<_f its issuance.
[
FOR THE NUCLEAR REGULATORY COMt11SSION
/
A Robert W. Reid, Chief Operating Reactors Branch #4 Division of Licensing
Attachment:
Changes to the Technical p
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Specifications Date of Issuance: February 25, 1981 i
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ATTACHttErlT TO LICEtlSE NIENDitEtlT NO. 37 FACILITY OPERATIflG LICENSE fl0. DPR-72 DOCKET fl0. 50-302 Replace the following pages of Appendix "B" Technical Specifications with the enclosed pages.
The revised pages are identified by Amend-ment number and contain vertical lines indicating the area of chanae.
The corresponding overleaf pages are also provided to maintain docu-ment completeness.
ii iv 3-2 3-3 3-4 3-5 3-G 3-7 5-11 5-12 l
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TABLE OF CONTENTS Page No.
1.0 DEFINITIONS 1-1 1.1 Frequency 1-1 1.2 Gross (8,y) Analysis 1.3 Point of Discharge (POD) 1-1 1.4 AT Across the Condenser 1-1 1-1 1.5 Unit 3 Mixing Zone t
1-1 1.6 Emergency Need for Power 1-1 1.7 Abnormal Power Operation 1.8 Known Radioactive Source 1-3 1-3 1.9 Intake Area 1-3 1.10 Discharge Area 1-3 1.11 Inner Bay 1-3 1.12 Outer Bay 1-3 1.13 Channel Calibration 1-3 1.14 Channel Check 1-3 1.15 Channel Functional Test 1-3 1.16 Dose Equivalent I-131 2.0 LIMITING CONDITIONS FOR OPERATION 2.1 Deleted 2-3 2.2 Hydraulic 2-3 2.3 Chemical 2.3.1 Biocides 2-3 2.3.2 Corrosion Inhibitors 2-4 2-4 2.4 Radioactive Effluents 2-5 2.4.1 Liquid Waste Effluents 2.4.2 Gaseous Waste Effluents 2-9 2.4.3 Solid Waste Handling and Disposal 2-16 3.0 ENVIRONMENTAL SURVEILLANCE 3-1 3.1 Nonradiological Surveillance Amendment No. y,
11 TABLE OF CONTENTS (Cont'd)
Page No.
3.1.1 Benthos in Discharge Area 3-2 3.1.2 Deleted 3-3 3.1.0 Deleted 3-4 3.1.4 General Ecological Survey 3-4 l
3.1.5 Deleted 3-5 3.2 Radiological Environmental Monitoring 3-!
3.2.1 Milk and Green Leafy Vegetables Census 3-26 3.2.2 Media Other Than External Radiation 3-27 3.2.3 External Radiation 3-27 3.2.4 Milk and Green Leafy Vegetables 3-27 4.0 SPECIAL SURVEILLANCE, RESEARCH, OR STUDY ACTIVITIES 4.1 Thermal Plume Determination During Unit 3 Operation 4-1 4.2 Intake Velocity Determination 4-2 4.3 Study of Erosion in the Discharge System 4-2 5.0 ADMINISTRATIVE CONTROLS 3.1 Organi:ation 5-1 5.2 Responsibility 5-1 5.3 Review and Audit 5-3 5.4 Action to Be Taken Limiting Condition for Operation is Exceeded 5-5 5.5 Procedures 5-5 5.6 Plant Reporting Requirements 5-6 5.6.1 Routine Reports 5-6 5.6.2 Non-routine Reports 5-8 5.6.3 Changes 5-11 l
3.7 Records Retention 5-11 5.6 Deleted 5-11 l
Amendment flo. 37
s iii LIST OF TABLES Page No.
No.
2.4-1 Radic sctive Liquid Sampling and Analysis 2-17 2.4-2 Radioactive Gaseous Waste Sampling and Analysis 2-19 Frequency 2.4-3 PWR-Liquid Waste System: Location of Process and Effluent Monitors and Samples Required by Technical Specifications 2-21 2.4-4 PWR-Gaseous Waste System: Location of Process and Effluent Monitors and Samples Required by Technical Specifications 2-22 2.4-5 Gamma and Be's Dose Factors for Crystal River Unit 3 2-23 3.2-1 Summary of Preoperational Environmental Surveillance Results 1971-1974 3-9 3.2-2 General Pathway Radiological Environmental Monitoring Program 3-15 3.2-3 Critical Pathway Radiological Environmental ~
Monitoring Program 3-18 3.2-4 Operational Sample Station Locations 3-19 3.2-5 Lower Limit of Detection 3-21 5.6-1 Environmental Radiological Monitoring Program Sumr.ary 5-9
iv List of Figures No.
Page No.
1.1-1 Point of Discharge 1-2 1.1-2 Inner and Outer Bays 1-4 3.1-1 Deleted 3-8 l
3.2-1 Environmental Media and Exposure Pathways 3-23 3.2-2 Offsite Sample Station Locations 3-24 3.2-3 Onsite Sample Station Locations 3-25 S.1-1 Organization for Implementing Environmental Technical Specifications 5-2 5.3-1 Organization for Independent Review and Audit 5-4 5.8-1 Deleted 5-12 l l
l Amendment No.
37
3-1 3.0 ENVIR0h?iENTAL SURVElLLANCE i
t 3.1 NONRADIOLOGICAL SURVEILLANCE Study Plan The ' estuary has been exposed to the influence of the operatien of Units 1 and 2 for approximately seven (7) years.
During this tbse, the systems in the area have adapted to this influence.
A preopera-tional surveillance program was designed to determine the exact nature of the new stabilized conditions relative to control areas adjacent to the plant site. This surveillance consisted of system modeling with measurements of biomass, productivity, respiration and diversity in all major compartments. The information derived will serve as a baseline for comparison with the data taken af ter Unit 3 becomes operational.
The operational surveillance program is designed to determine any significant environmental effects of the operation of the power plant, particularly unpredicted and catastrophic changes.
The pro, consists of 3 short-term intensive surveillance program elements and 2 long-term program elements.
A period of adjustment of the ecosystem is expected concurrent with Crystal River Unit 3's initial operation. This will be a localized perturbation limited to a portion of the inner bay associated with the higher water velocity,as well as the temperature increase resulting from the condenser discharge.
Any ecosystem which experiences a change in its environment will undergo a period of adaptation unlese, catastrophic conditions occur.
With.the small changes anticipated wi:h the addition of Unit 3, no catastrophic effects are expected. However, any changes in the environmental conditions of a system will normally cause it to oscillate. An example of the oscillation of a hypothetical system's productivity is shown below.
- p. Time to Perturbation i
Time to Minimum p
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- r. Approximate Time to Stabilization l
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Stabilized Level I
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Initial Level Productivi ty I
n Minimum L ael Time
-=-
Amendment No. 24
e 3-2 in this particular system the final stabilized level is higher than the initial level and is only obtained after a period of stabiliza-tion and after going through a suppressed level following the initial perturbation.
The recognition of this type of potential response is obviously important in considering any surveillance program.
The models of the systems involved at Crystal River along with the data availabic indicate that the approximate time to stabilization should not exceed one year. Therefore, the time frame for the intensive surveillance program ele =ents allows one year of conitoring to determine the transient response that the systems are experiencing.
An additional year of monitoring is required to indicate the new
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stabilized level.
If the second year's data indicate that the syste=s have not approached stabilization, the monitoring will be extended for an additional year.
It is anticipated that the intensive sur-veillance program elements should not be necessary beyond three years.
In addition to the short-term intensive surveillance program elements designed to determine how the systems have responded to the per-turbations, an on-going program element designed to obtain a diagnos-tic view of the condition of the environment will be continued during the operational life of the plant.
This indicator progras element consists of a number of si=ple measurements which will detect any major changes in the system. A second long-term program element involves chemical-industrial waste water monitoring.
3.1.1 Benthos in Discharge Area Objective To determine the ecological condition of the benthic system in the area directly affected by the thermal plume.
Specification Operational monitoring of diversity ant!
l biomass of'the benthic. system in,the area adjacent to and north of the discharge canal shall be measured on a quarterly basis until the system has approached stabilization.
Samples shall be taken by methods employed in the preoperational studies including harvesting quadrats, by sediment cores, and by venturi pumps. The number, frequency and location of Amendment No. [ 37
3-3 samples to be taken shall be determined f rom a critical review of the results of the preoperativnal research con-ducted in this area.
Samples shall be stratified by macrophyte dominance.
Reporting Requirement shall be reported Results of the data gathered in this program element in accordance with Section 5.6.1.
In the event that any parameter measured changes beyond two standard deviations of the value measured in the preoperational monitoring program, a report shall be submitted as specified in Section S.6.2.
Bases increase due In the discharge area adjacent to the canal, the biomass should If this parameter changes to an increased temperature of the cooling water.
(two standard deviation) of that measured during preoperational beyond 2a mon,ito ring, the system should be investigated for catastrophic result s.
3.1.2 Deleted i
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l Am2ndment ilo.J4', 37
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3-4 l
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I 3.1.3 Del eted i
4 3.1.4 General Ecological Survey i
Objective i
To detect changes which might occur and would be used to indicate areas requiring more detailed investigation.
Specifications A series of measurements shall be carried out during the 3
operational life of the plant to indicate the general con-dition of the environment. The areas to be monitored are:
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Amendment No. JE' 37 1
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3-5 I'
a.
Outer bay (plankton-dominated area). The percent of satura-tion of oxygen will be measured at dusk and dawn of consecutive days, twice monthly.
b.
Canals.
The percent of saturation of oxygen shall be measured at dusk and dawn twice monthly at the Point of Discharge.
c.
Marsh grasses.
Sten counts of grass within a quadrat will be made quarterly.
This measurement shall be correlated with biomass.
In addition, the number of < rah holes within a quadrant shall be observed as a biomass indicator.
Reporting Requirement Results of the data gathered in thiu program element will be reported in accordance with Section 5.6.1.
Bases The parameters to be measured were chosen to indicate general trends in the conditions of the environment and will be used to indicate areas where further investigations may be warranted if significant changes are detected.
3.1.5 Deleted l
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Amemsen i. _ no. n
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3.2 RADIOLOGICAL ENVIRONMENTAL MONITORING v
Obj ec t ive The radiological environmental monitoring program will provide informa-tion which can be used to assist in assessing the type and quantity of radiation exposure in unrestricted areas resulting from plant operation.
Background
Preoperational radiological environmental monitoring programs, to establish baseline environmental concentration values, were initiated in mid-1970. One program was operated by the State of Florida Department
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of liealth and Rehabilitative Services; another program was operated by I
the University of Florida.
l A summary of the preoperational surveillance results is shown in
- Table 3.2-1.
This summary includes median values of the observed i
environmental concentrations and 95 percentile values (i.e., values which exceed 95 percent of all the_ comparable measured values). These i
values will be taken as the preoperational baseline concentrations.
In some cases the values listed are smaller than the Lower Limit of Detection.(LLD).
4 The 95 percentile values indicate'the' random frequency of high measured values during the operation of the plant contributes negligibly to l
the environmental radioactivity. These 95 percentile values will be used during operation to assess the probability that any observed high concentration value is due to random fluctuations in measurements I
rather than to a true increase in environmental concentrations.
Speci_f,1 cat ion (Program) 4
[
Environmental media which are sampled and analyzed for radioactivity are shown by the two diagrams on Figure 3.2.-l.
F.ach box in the dia-grams contains the name of an environmental media which is sampled.
The upper' diagram shows the critical' pathways; the lower diagram shows the other monitored pathways.
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' Amendment No. 37
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s Figure 3.1-1 Deleted Amendaent IJo. 37
3-8 The operational radiological monitoring program shall consist of a continuation of the preoperational program of measurements of radio-activity in environmental media which is outlined in Table 3.2-2.
The critical pathway monitoring program which is included in Table 3.2-2 is also shown in Table 3.2-3.
Sample station locations are described on Table 3.2-4 and shown on maps on Figures 3.2-2 and 3.2-3.
Lower Limit of Detection (LLD) values are given on Table 3.2-5.
Deviations are permitted from the required sampling schedule if speci-mens are unobtainable due to hazardous conditions, vandalism, seasonal If unavailability or to malfunction of sutomatic sampling equipment.
the latter, every effort shall be made to complete corrective action prior to f.he end of the next sampling period.
All deviations from the sampling schedule shall be described in the annual report.
.m
5-11 5.6.3 Changes A report shall be made to the Director of Office of Nuclear A.
Reactor Regulation prior to i=plementation of a change in plant design, in plant operation, or in procedures described in Sec-tion 5.5 if the change would have, in the judgement of the applicant, a significant adverse effect on the environment or involses an environmental matter or question not previously reviewed and evaluated by the USNRC.
The report shall include a description and evaluation of the change and a supporting benefit-cost ;nalysis.
B.
Request f or changes in environmental technical specifications shall be submitted to the Director cf Office of Nuclear Reactor Regulation for review and authorization.
The request shall include an evaluation cf the impact on the change and a support-ing benefit-cost analysis.
5./
RECORDS RETENTION Records and logs relative to the following areas shall be retained for 5.7.1 the life of the plant:
Records and drawing changes reflecting plant design modifications a.
made to systems and ecuipment as described in Section 5.6.3.
b.
Records of environmental sur allance data.
c.
Records to denonstrate conpliance with the limiting conditions for operation in Section 2.0.
.ill ether records and logs relating to the envirenraental technical 5.~.:
specifications shcl1 be retained for five years.
5.8 Deleted Anwndman t No.
37
5-12 1
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Amendment No. 37 t
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