ML20083C480
| ML20083C480 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 12/16/1983 |
| From: | FLORIDA POWER CORP. |
| To: | |
| Shared Package | |
| ML20083C469 | List: |
| References | |
| TAC-08985, TAC-8985, NUDOCS 8312230160 | |
| Download: ML20083C480 (13) | |
Text
.
TABLE 3.12-1 umm QS OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM E
b.
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Exposure Pathway Number of Samples Sampling /
Type / Frequency Om h and/or Sample and Locations Collection Frequency of Analysis 03 E!
oOU i
- 1. AIRBORNE One sample each:
Continuous sampler /
Radioiodine canister:
@fe Radioiodine and CO7, C18, C40, C41, Weekly collection M
particulates C46, and Control a) 1-131 analysis weekly cation C47 Particulate sampler:
u a)
Gross /at E 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> /
following weekly filter change.
b)
Composite gamma spectral analysis (by location)/
w3 quarterly. (Gamma Spectral Analysis shall also be 7
performed on individual samples if gross beta activity of any sample is greater than 1.0 p Ci/m3 and which is also greater than ten times the control sample activity.)
- 2. DIRECT RADIATION
- 1) Site Boundary:
Continuous Gamma exposure rate / quarterly
[
C60, C61, C62, C63, placement / Quarterly C64, C65, C6fi, C67, collection C68, C69, C41, C70, C27,C71,C72,C73
- 2) Five Miles:
C18, C03, C04, C74, C75, C76, C08, C77, C09, C78, Cl4G, C01, C79
- 3) Control Location:
C47
TABLE 3.12-1 (Continued)
El N
OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
- o E
!a
[
Exposure Pathway Number of Samples Sampling /
Type / Frequency and/or Sample and Locations Collection Frequency of Analysis a
- 3. WATERBORNE One sample each:
Seawater Cl3, C14H, C14G Grab sample / Monthly Gamma spectral (All Control analysis / monthly Locations)
Tritium analysis on each sample or on a quarterly composite of monthly samples u3 Ground water One sample:
g
'f C40 (Control Grab sample /
Gamma spectral and Location) semiannual Tritium analysis /each sample Drinking water One sample each:
C07, C10, CIS Grah sample / quarterly Gamma spectral and Tritium (All Control analysis /each sample Locations)
Shoreline sediment One sample each:
C14H, C14M, C14G Semiannual sample Gamma spectral analysis /each Control Location sample C09
- 4. INGESTION
[
Fish & Invertebrates One sample each:
Quarterly:
Gamma spectral analysis on C29, Control Location Oysters and carnivorous edible portions /each sample C30 fish
TABLE 3.12-1 (Continued) c)
OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM El k
i 5
si Exposure Pathway Number of Samples Sampling /
Type / Frequency 7
and/or Sample and Locations Collection Frequency of Analysis E
Food Products One sample each:
Monthly (when available):
Gamma spectral and I-131 C48a*, C48b*,
Three (3) types of broad analysis /each sample Control Location C47 leaf vegetation from each location One sample:
Annual during harvest:
Gamma spectral analysis /
C19 Citrus each sample
{
One sample:
Annual during harvest:
Gamma spectral analysis /
C04 Watermelon each sample Y
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1
- Stations C48a and C48b are located at or beyond the 4400 ft. site boundary for gaseous effluents in the two sectors which yield the highest historical annual average D/Q values.
TABLE 3.12-2 h
REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES n
M 5
N Water Airborne Particulate Fish Milk Food Products 5'
Analysis (pCF 2) or Gas (pCi/m3)
(pCi/Kg, wet)
(pCi/1)
(pCi/Kg, wet) 9 H-3 20,000(a)
M n-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 w3 Zn-65 300 20,000 Zr-Nb-95 (
400 I-131 2(c) 0.9 3
100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300 (a) or drinking water samples. This is 40 CFR Part 141 value. If no drin1<ing water pathway exists, a value of 30,000 pCi/l may be used.
(b) Total for parent and progeny assumed to be in equilibrium.
(c) For drinking water samples only.
9g TABLE 4.12-1 0e MAXIMUM VALUES FOR THE LO"!ER LIMITS OF DETECTION (LLD) a d
- n E
!3 Water Airborne Particulate Fish Milk Food Products Sediment h
Analysis (pCi/1) or Gases (pCi/m3)
(pCi/Kg, wet)
(pCi/I)
(pCi/Kg, wet)
(pCi/Kg, dry) z U
gross beta 0.01 m
3 2000 H
54 15 130 Mn 59 30 260 p
58 15 130 Co 60 15 130 Co 65 30 260 Zn 95 I5 Zr-Nb I
131; I
0.07*
I 60 134 15 0.05*
130 15 60 150 Cs 137 18 0.06*
150 18 80 180 Cs 140 I5 I5 Ba-La
TABLE 4.12-1 (Continued)
TABLE NOTATION
. v The LLD* is the smallest concentration of radioactive materialin a sample that will a.
be detected with 93% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal For a particular measurement system (which may include radiochemical separation):
LLD=
- b (E) (V) (2.22) (Y) (e4't )
Where:
LLD is the lower limit of detection.as defined above (as picocurie per unit mass or volume),
sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute),
E is the counting efficancy (as counts per disintegration),
V is the sample size (in units of mass or volume),
2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield (when applicable),
A is the radioactive decay constant for the particular radionuclide, and M is the elapsed time between sample collection (or end of the sample collection perod) and time ci counting (for environmental samples, not plant effluent samples).
Typical values of E, V, Y andd should.be used in the calculation.
- The LLD is defined as an a, priori (before the fact) limit representing the capability of the measurement systens and not as an a posteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLD's will be achieved under routine conditions. Occasionally, background fluctuations, unavoidable small sample sizes, the presence of interferring nuclides, or other uncontrollable circumstances may render these LLD's unachievable. In such cases, the contributin identified and described in the Annual Radiological Environmental Operatm,g factors shall be g Report.
CRYSTAL RIVER - UNIT 3 3/4 12-3
TABLE 4.12-1 (Continued)
TABLE NOTATION b.
LLD for drinking water. If no drinking water pathway exits, a value of 3000 pCi/l may be used.
c.
The specified LLD is for cn equilibrium mixture of parent and daughter nuclides which contains 15 pci/l of the parent nuclide.
d.
Other peaks which are measurable and identifiable, together with the radionuclides in Table 4.12-1, shall be identified and reported.
e.
1-131, Cs-134, and Cs-137 LLD's apply only to the quarterly composite gamma spectral analysis, not to analyses of single particulate filters.
f.
LLD for drinking water. If no drinking water pathway exists, the LLD of gamma isotopic analysis may be used.
CRYSTAL RIVER - UNIT 3 3/4 12-9 1
RADIOLOGICAL ENVIRONMENTAL MONITORING LAND USE CENSUS (Continued)
SURVEILLANCE REQUIREMENTS 4.12.1.2 The land use census shall be conducted at least once per 12 months during the growing season by a door-to-door survey, aerial survey, or by consulting local agriculture authorities, using that information which will provide adequate results.
CRYSTAL RIVER - UNIT 3 3/4 12-10a
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ADMINISTRATIVE CONTROLS REVIEW (Continued) g.
Events requiring 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification to the Commission.
h.
All recognized indications of an unanticipated deficiency in some aspect of design of operation of safety related structures, systems, or components.
1.
Reports and meetings minutes of the Plant Review Committee.
J.
Changes to the PROCESS CONTROL PROGRAM and to the OFFSITE DOSE CALCULATION MANUAL.
AUDITS 6.5.2.9 Audits of facility activities shall be performed under the cognizance of the NGRC. These audits shall encompass:
a.
The, conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.
'l b.
The performance, training, and qualifications of the entire facility staff at least once per 12 months.
c.
The results of actions taken to correct deficiencias occurring in facility equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months, d.
The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix B,10 CFR 50, at least once per 24
- months, e.
The Facility Emergency Plan and implementing procedures at least once per 24 months, f.
The radiological environmental monitoring program and the results thereof at least once per 12 months.
g.
The OFFSITE DOSE CALCULATION. MANUAL and implementing procedures
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at least once per 24 months, h.
The PROCESS CONTROL PROGRAM and implementing procedures for solidification of radioactive wastes at least once per 24 months.
i.
The performance of activities required by the Quality Assurance Program for effluent and environmental monitoring at least once per 12 months.
CRYSTAL RIVER - UNIT 3 6-10
ADMINISTRATIVE CONTROLS 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
a.
The facility shall be placed in at least HOT STANDBY within one hour.
b.
The Safety Limit violation shall be reported to the Commission, the Vice President, Nuclear Operations and to the NGRC within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
c.
A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the PRC.
This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures and (3) corrective action taken to prevent recurrence.
d.
The Safety Limit Violation Report shall be submitted to the Commission, the NGRC and the Vice President, Nuclear Operations within 14 days of the violation.
6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:
a.
The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, November,1972.
b.
Refueling operations.
c.
Surveillance and test activities of safety related equipment, d.
Security Plan implementation.
e.
Emergency Plan implementation.
f.
Fire Protection Program implementation.
g.
Systems Integrity Program implementation.
h.
Iodine Monitoring Program implementation.
i.
PROCESS CONTROL PROGRAM implementation.
j.
OFF-SITE DOSE CALCULATION MANUAL implementation, k.
Quality Assurance Program for effluent and environmental monitoring.
l CRYSTAL RIVER - UNIT 3 6-12
ADMINISTRATIVE CONTROLS ANNUAL AND SEMIANNUAL 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.
6.9.1.5 Reports required on an annual basis shall include:
a.
A tabulation of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrem /yr. and their associated man-rem exposure according to work and job functionsl e.g., reactor operations and surveillance, inservice inspection, routine maintenance,. special maintenance (describe maintenance), waste processing, and refueling. The dcse assignments 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.
b.
A list of the reactor vessel material surveillance capsules installed in the reactor at the end of the report period and a summary of any withdrawals or insertions of capsules during the report period.
In supplying this information, the ownership of each capsule shall be indicated and the irradiation location in the vessel of each capsule which was inserted during the report period shall be identified.
c.
A routine Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted prior to Mey 1 of each year.
TM Annual Radiologicel Environmental Operating Reports shall include suinmaries, interpretations, unachievable LLDs, and an analysis of trends l
of the results of the radiological environmental studies, and previous Annual Radiological Environmental Operating Reports and an assessment of any observed impacts of the plant operation on the environment. If harmful effects or IThis tabulation supplements the requirements of 20.407 of 10 CFR Part 20.
CRYSTAL RIVER - UNIT 3 6-14 y_
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ADMINISTRATIVE CONTROLS THIRTY-DAY WRITTEN REPORT 6.9.1.9 The types of events listed below shall be the subject of written reports to the Director of the Regional Office within 30 days of occurrence of the event. The written report shall include, as a minimum, a completed copy of a licensee event report form.
Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.
a.
Reactor protection system or engineered safety feature instrument settings which are found to be less conservative than those established by the technical specifications but which do not prevent the fulfillment of the functional requirements of affected systems, b.
Conditions leading to operation in a degraded mode permitted by a limiting condition for operation or plant shutdown required by a limiting condition for operation.
c.
Observed inadequacies in the implementation of administrative or procedural controls which threaten to cause reduction of degree of redundancy provided in reactor protection systems or engineered safety feature systems.
d.
Abnormal degradation of systems other than those specified in 6.9.1.8.c above, designed to contain radioactive material resulting from the fission process.
CRYSTAL RIVER - UNIT 3 6-17
.-