ML20214R255
| ML20214R255 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 11/25/1986 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML20214R229 | List: |
| References | |
| NUDOCS 8612050415 | |
| Download: ML20214R255 (16) | |
Text
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ATTACHMENT 1 PROPOSED TECHNICAL SPECIFICATIONS CHANGES Virginia Electric and Power Company 8612050415 861125
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DH ADOCK 05000338 PDR [_
TABLE 4.12-1 m
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
- zz Number of Samples Exposure Pathway and Sampling and Type and Frequency a
and/or Sample Sample Locations Collection Frequency of Analysis e
1.
DIRECT RADIATION 36 routine monitoring stations Quarterly Gamma dose either with two or more quarterly, dosimeters or with one instrurent for measuring and recording dose rate contin-uously to be placed as follows:
- 1) an inner ring of stations, one in each meteorological sector within the SITE LOUNDARY: an. outer ring of stations, one in each meteoro-logical sector within 8 km range from the site; the u
e balance of the stations to be placed in special interest 4
areas such as population centers, nearby residences, schools, and in 1 or 2 areas to serve as control stations.
2.
AIRBORNE Radioiodine and Samples from 5 locatior;s Continuous sampler Radioiodine Cannister:
Particulates (2/3 running time I-131 analysis weekly, a.
3 samples form close cycle), operation to the 3 SITE BOUNDARY with sample collection g
locations (in different weekly.
Particulate Sampler _:
g sectors) of the highest Gross beta radioactivity g
calculated historical analysis following a
E annual average ground-filter change;" Gamma z
level D/Q.
isotopic analysis of composite (by
- The number, media frequency, and location of samples may vary from site to site.
This table presents:
an acceptable minimum program for a site at which each entry is applicable.
Local site characteristics w must be examined to determine if pathway not covered by this table may significantly contribute to an individual's dose and should be included in the sampling program.
5 TABLE 4.12-1 (Continued)
$=
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM *
@s Number of Samples Exposure Pathway and Sampling and Type and Frequency, 2;
and/or Sample Sample Locations, Collection Frequency of Analysis c.
location)' quarterly,d s
b.
I sample from the vicinity
~~
of a community having the highest calculated annual average groundlevel D/Q.
c.
I sample from a control location 15-40 km distant and in the least prevalent wind direction.
wN 3.
WATERBORNE w
a.
Surface a.
I sample circulating Sample off upstream, Gamma isotopic analysis 5'
water discharge downstream and monthly. Composite for-cooling lagoon, tritium analysis quarterly.
Grab Monthly.
b.
Ground Samples from 1 or 2 sources Grab Gamma isotopic and tritium only if likely to be affected.
Quarterly analysis quarterly.
c.
Sediment 1 sample from downstream area Semiannually Gamma isotopic analysis with existing or potential semiannually.
recreational value.
w$
l TABLE 4.12-2 E>
REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES I
y Reporting Levels
~
Water-Airborne Particulgte Fish Milk Food Products Analysis (pCi/ t) or Gases (pCi/m )
(pCi/kg, wet)
(pCi/i)
(pCi/kg, wet) j H-3 20,000*
t
]
Mn-54 1,000 30,000 I
Fe-59 400 10,000
)
l Co-58 1,000 30,000 w3 Co-60 300 10,000
[
Y*
Zn-65 300 20,000 Zr-Nb-95 400 I-131 2
0.9 3
100 i
Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 i
Ba-La-140 200 300 i
i 1
- For drinking water samples I
4 f
4
k' E
- n TABLE 4.12-3 E
DETECTION CAPABILITIES FOR'ENVIRONhfENTAL SAMPLE ANALYSIS"
'~'
E 2
LOWER LIMIT OF DETECTION (LLD) s i
k Water Airborne Particulgte Fish Milk Food Products Sediment Analysis (pCi/t) or Gases (pCi/m )
(pCi/kg, wet)
(pCi/1)
(pCi/kg, wet)
(pCi/kg. dry) gross beta 4
0.01 l
H-3 2,000 Mn-54 15 130 u3 Fe-59 30 260
[
Co-58.60 15 130 l
O Zn-65 30 260 Zr-Nb-95 15 l
I-131 1.0" 0.07 1
60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 1801 Ba-La-140 15 15 G
9
TABLE 4.12-3 (Continued)
TABLE NOTATION It should be recognized that the LLD is defined as an jt priori (before the fact) limit representing the capability of a measurement system and not as an jt_ posteriori (after the fact) limit for a particular measurement. Analysis shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of these LLDs unachievable.
In such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.8.
c This LLD value is for drinking water samples k
NORTH ANNA - UNIT 1 3/4 12-12
TABLE 4.12-3 (Continued)
TABLE NOTATION aThis list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.8.
bThe LLD is defined, for purposes of these Specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only
. 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement
- system, which may include radiochemical separation:
b LLD =
E
- V
- 2.22
- Y
- exp(-lat)
Where:
LLD is the "a priori" lower limit of detection as defined above, as picocuries per unit mass or volume, s
is the standard deviation of the background counting rate or of the b
counting rate of a blank sample as appropriate, as counts per minute.
E is the counting efficiency, 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 at for environmental samples is the elapsed time between sample collection, or end of the sample collection period, and time of counring Typical valves of E, V, Y and at should be used in the calculation.
NORTH ANNA - UNIT 1 3/4 12-11
TABLE 4.12-1 z
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
- d Number of Samples E
Exposure Pathway and Sampling and Type and Frequency and/or Sample Sample Locations" Collection Frequency of Analysis i
1.
DIRECT RADIATION 36 routine monitoring stations Quarterly Gamma dose Q
either with two or more quarterly.
dosimeters or with one y
instrument for measuring and recording dose rate contin-uously to be placed as follows:
- 1) an inner ring of stations, one in each meteorological sector within the SITE BOUNDARY: an outer ring of stations, one in each meteoro-logical sector within 8 km range from the site; the i
u3 3:
balance of the stations to be placed in special interest 7
areas such as population centers, nearby residences, schools, and in 1 or 2 areas to serve as control stations.
2.
AIRBORNE Radioiodine and Samples from 5 locations Continuous sampler Radioiodine Cannister:
Particulates (2/3 running time I-131 analysis weekly.
a.
3 samples form close cycle), operation to the 3 SITE BOUNDARY with sample collection locations (in different weekly.
Particulate Sampler:
[
sectors) of the highest Gross beta radioactivity calculated historical analysis following annual average ground-filter change;" Gamma level D/Q.
isotopic analysis of composite (by 5
Y
- The number, media frequency, and location of samples may vary from site to site.
This table presents an y acceptable minimum program for a site at which each entry is applicable.
Local site characteristics must be m examined to determine if pathway not covered by this table may significantly contribute to an individual's dose and should be included in the sampling program.
g TABLE 4.12-1 (Continued) m RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
- Dy Number of Samples Exposure Pathway and Sampling and Type and Frequency and/or Sample Sample Locations, Collection Frequency of Analysis c:
33 location) quarterly.d H
b.
I sample from the vicinity of a community having the N
highest calculated annual average groundlevel D/Q.
c.
I sample from a control location 15-40 km distant and in the u
3:
least prevalent wind direction.
~n f
3.
WATEREORNE a.
Surface a.
I sample circulating Sample off upstream, Gamma isotopic analysis water discharge downstrean and monthly. Composite for cooling lagoon.
tritium analysis quarterly.
Grab Monthly.
b.
Ground Samples from 1 or 2 sources Grab Gamma isotopic and tritium only if likely to be affected.
Quarterly analysis quarterly.
c.
Sediment I sample from downstream area Semiannually Gamma isotopic analysis with existing or potential semiannually.
recreational value.
5 TABLE 4.12-3 y
=
DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS" g
N LOWER LIMIT OF DETECTION (LLD)
I E
A Water Airborne Particulgte Fish Milk Food Products Sediment y
Analysis (pCi/?)
or Gases (pCi/m )
(pCi/kg wet)
(pCi/1)
(pCi/kg, wet)
(pCi/kg. dry) gross beta 4
0.01 H-3 2,000 Mn-54 15 130 Fe-59 30 260
't Co-58,60 15 130 E
Zn-65 30 260 Zr-ht-95 15 I-131 1.0" 0.07 1
60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15 9
5 TABLE 4.12-2
}
REPORTING LEVELS FOR x19I0 ACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES s
Reporting Levels E:i Fish Milk Food Products Airborne Particulg)te (pCi/kg, wet)
(pCi/L)
(pCi/kg, wet)
Water or Gases (pCi/m Analysis (pCi/L) l H-3 20,000*
Mn-54 1,000 30,000
~l.
Fe-59 400 10,000 Co-58 1,000 30,000 w
Co-60 300 10.000
~n 1
Zn-65 300 20,000 Zr-Nb-95 400 I-131 2
0.9 3
100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 300 Ba-La-140 200
- For drinking water samples
T I
2-1-85 TABLE 4.12-3 (Continued)
TABLE NOTATION aThis list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.8.
The LLD is defined, for purposes of these Specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement
- system, which may include radiochemical separation:
LLD =
E
- V
- 2.22
- Y ' exp(-A6t)
Where:
LLD is the "a priori" lower limit of detection as defined above, as picocuries per unit mass or volume, s
is the standard deviation of the background counting rate or of the b
counting rate of a blank sample as appropriate, as counts per minute, E is the counting efficiency, 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 picoeurie, Y is the fractional radiochemical yield, when applicable, A is the radioactive decay constant for the particular radionuclide, and at for environmental samples is the elapsed time between sample collection, or end of the sample collection period, and time of counting Typical valves of E V, Y and at should be used in the calculation.
NORTH ANNA - UNIT 2 3/4 12-11 Amendment No. 47
TABLE 4.12-3 (Continued)
TABLE NOTATION It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori-(after the fact) limit for a particular measurement. Analysis shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasienally background fluctuations, unavoidably small sample sizes, the presence of these LLDs unachievable.
In such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.8.
"This LLD value is for drinking water samples.
NORTil ANNA - UNIT 2 3/4 12-12
ATTACHMENT 2 SAFETY EVALUATION Virginia Electric and Power Company
DISCUSSION Tech Spec Table 4.12-1 paragraph 2.c The propused changes to the Unit 1 and 2 Technical Specifications will correct an administrative error in Table 4.12-1, paragraph 2.c.
This table lists the sample point for offsite monitoring to be 15 to 30 kilometers from the site.
This specification came in existence when the radiological portion of the Enviromental Tech Specs were incorporated into the plant Tech Specs (Amendment 48 to Unit I and Amendment 31 to Unit 2 Tech Specs.)
The original Enviromental Tech Specs listed eight locations for continuous airborne sampling. There was 1 at the site, 3 on the site perimeter, 3 in nearby communities and 1 at the Orange District Office.
These locations are also specified in the Offsite Dose Calculation Manual (00CM) in accordance with Tech Spec requirements.
The 00CM lists site 24, the " Control" monitor at the Orange District Office, as being "22 miles" (35.4 km) from the site.
This monitoring site was placed in service in December, 1976 as a control location for the North Anna Station and has provided the station with a well established 10 year base of sampling data.
The location is secure from vandalism and assures a stable power source.
In order to correct this discrepancy, Tech Spec Table 4.12-1 paragraph 2.c will be changed to read "I sample from a control location 15-40 kilometers distant and in the least prevalent wind direction."
The change will also bring the Technical Specifications into agreement with the Offsite Dose Calculation Manual which has been approved by the NRC.
Tech Spec Table 4.12-2 and 4.12-3 Table 4.12-2 of North Anna Unit 1 and Unit 2 Technical Specifications list a reporting level of 30,000 pCf / liter for H.
This is to be changed to 20,000 3
pCi/ liter in accordance with NUREG 0472, Radiological Effluent Technical Soecifications for PWRs, Revision 3.
In addition there is a footnote being added which specifies the sample to be tested.
Table 4.12-3 of North Anna Unit 1 and Unit 2 Technical Specification 3/4.12.1, lists a Lower Limit of Detectability (LLO) for High Resolution Ge(Li) Gamma Spectroscopy Enviromental sample of 10 pCi/ liter for 1 and an LLD of 3000 131 pCi/ liter for H. These are to be changed to 1 pCi/ liter for 1 and 2000 for 3
131 H
in accordance with NUREG
- 0472, Radiological Effluent Technical SkcificationsforPWRs, Revision 3.
A footnote is being deleted from Table 4.12-3 which specifies that "The LLD for Gamma isotopic analysis shall be used." A footnote being added to Table 4.12-2 and 4.12-3 will state that "The LLD value is for drinking water samples."
(
BASIS FOR NO SIGNIFICANT HAZARDS DETERMINATION Tech Spec Table 4.12.1 The proposed changes does not require a significant hazards consideration because operation of North Anna Units 1 & 2 in accordance with this change would not:
(1) involve a significant increase in the probability of consequence of an accident previously evaluated because this change will continue to require the sampling of a satisfactory centrol location.
(2) create the possibility of a new or different kind of accident from any accident previously identified.
It has been determined that a new or different kind of accident will not be possible due to this change because this change will continue to require sampling of a satisfactory control location.
(3) involve a significant reduction in a margin of safety because this change will continue to require the sampling of a satisfactory control lacation.
Therefore, pursuant to 10 CFR 50.92, based on the above consideration, it has been determined that this change does not involve a significant safety hazards consideration.
Tech Spec Table 4.12-2 and 4.12-3 The proposed change does not require significant hazards consideration because operation of North Anna Units 1 & 2 in accordance with this change would not:
(1) involve a significant increase in the probability or consequence of an accident previously evaluated because this change imposes a more restrictive requirement and is being instituted to conform to NUREG 0472.
(2) create the possibility of a new or different kind of accident from any accident previously identified.
It has been determined that a new or different kind of accident will not be possible due to this change being instituted to conform to NUREG 0472.
(3) involve a significant reduction in a margin of safety because this change imposes a more restrictive requirement and is being instituted to conform to NUREG 0472.
Therefore, pursuant to 10 CFR 50.92, based on the above consideration, it has been determined that this change does not involve a significant safety hazards consideration.}