ML20206G417
| ML20206G417 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 03/31/1987 |
| From: | Rubenstein L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20206G420 | List: |
| References | |
| NUDOCS 8704140546 | |
| Download: ML20206G417 (18) | |
Text
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'o UNITED STATES
~g NUCLEAR REGULATORY COMMISSION
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VIRGINTA ELECTRIC AND POWEP COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-338 NORTH ANNA POWER STATION,llNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 92 License No. NPF A 1.
The Nuclear Regulatory Comission (the Comissioni has found that:
A.
The application for amendment by Virginia Electric and Power Company, et al., (the licensee) dated November 25, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and reaulations 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; 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;
]
D.
The issuance of this amendment will not be inimical to the comon 3
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 requirements have been satisfied.
8704140546 870331 PDR ADOCK 05000338 PDR p
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2.
Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph ?.D.(2) of Fccility Operating License No. NPF-4 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 92, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective within 14 days from the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
>At e
_D Lester S. Rubenstein, Director PWR Pro.iect Directorate #7 Division of PWR Licensing-A Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications March 31, 1987 Date of Issuance:
p_. - - ~.
ATTACPMENT TO LICENSE AMENDul6T NO. 92 TO FACILITY OPERATING LICENSE NO. NPF 4 DOCKET NO. 50-338 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised paces are identified by amendment number and contain vertical lines indicating the area of change.
The corresponding overleaf paaes are also provided to maintain document completeness.
Page 3/4 12-4 3/4 12-9 3/4 12-10 3/4 12-1?
i i
1 I
(
l
TABLE 4.12-1 5
4 RADIOLOGICAL ENVIRONNENTAL MONITORING PROGRAM *
- n Number of Samples Sampling and Type and Frequency Y
and of Analysis E
Exposure Pathway Sample f.ocations*
Collection Frequency U
nnd/or Sample Camma done Quarterly 36 routine monitoring quarterly, 1.
DIRECT RADIATION-stations either vith two or more dosimeters or with one instrument for measuring and recording dose rate continuously to be placed as follows:
- 1) an inner ring of stations, one in each meteorological sector within the I
SITE BOUNDARY; an outer ring of stations, one in each meteorological sector within 8 km range from U
the balance of the the site; stations to be placed in special y
interest arean such as population centers, nearby residences, schools, w
and in 1 or 2 areas to serve as control stations.
2.
AIRBORNE Radioindine cannister:
Continuous sampler I-13l analysis weekly.
Radiciodine and Samples from 5 locations:
(2/3 running time E
Particulates cycle), operation 3 samples from close with sample collection a.
to the 3 SITE BOUNDARY Particulate Sampler:
weekly.
Cross beta radioactivity E
locations (in different nectors) of the highest analysis following calculated historien1 filter change;"
annuni average ground-Camma isotopic analysis level D/Q.
of compostte (by This table presents an
- The number, media. frequency, and location of sampics may vary from site to site. Local site characteristics must neceptable minimum program for a site at which each entry is applicable. covered by this tahic may s
)
he examined to determine if pathways not individunt'n done and should he included in the sampling program.
i
TABLE 4.12-1 (Continued)
. 5 RADIOLOGICAL ENVIRONMENTAL MONTTORING PROCRAM
' 5 x
l.
Number of Samples Sampling and Type and Frequency y
and of Analysis Collection Frequency _
g Exposure Pathway Sample Locations, and/or Sample y
location) quarterly.
4 b.
I sample from the vicinity of a community having the highest calculated annual average groundlevel D/Q.
I I sample from a control c.
location 15 40 km distant and in the least prevalent wind 10 direction.
w.
gs 3.
WATERBORNE Camma isotopic analysis Sample off upstream, I sample circulating downstream and monthly. Composite for a.
Surface a.
water discharge tritium analysis quarterly.
cooling lagoon.
Grab Monthly.
j d
Camma isotopic and tritium Crab analysis quarterly.
b.
Ground Samples from 1 or 2 nources Quarterly g-only if likely to be affected.
g d
Comma isotopic analysis n
Semiannually I snmple from downstream area nem1 annually.
E.i c.
Sediment with existing or potential 4;
recreational value.
O j
Eh, s
TABLE 4.12-2 E
REPORTINC LEVELS FOR RADIDACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES g
Reporting i,evels i
Fish Milk Food Products Water Airborne Particisigte l
I Analysis (pC1/1) or Cases (pCi/m )
(pCf/kg, wet)
(pC1/t)
(pci/kg, vet)
U H-3 20,000*
30,000 Mn-54 1,000 10,000 Fe-59 400 30,000 Co-58 1,000 i
10,000 R
Co-60 300 s~
20,000 C
Zn-65 300 Zr-Nb-95 400 3
100 a
I-131 2
0.9 Cs-134 30 10 1,000 60 1,000 i
Cs-137 50 20 2,000 70 2,000 300 Ba-La-140 200 5,,
l 4
- 2:
0
- For drinking water samples i
E
O TABLE 4.12-3_
5 DETECTION CAPARILITIES FOR ENVIRONMENTAL SAMPLE ANALYS 5
LOWER LIMIT OF DETECTION (LLD)b I
Sediment Food Products y
Hilk AirbornePartit3)ste (pC1/kg, vet)
(pC1/t)
(pC1/kg, wet)
(pC1/kg. dry)
Fish 1
Water or Cas (pC1/m U
Analysis (pCf / t) j 0.01 4
gross bets 2000 N-3 130 15 Mn-54 260 30 Fe-59 130 15 co-58,60 w
260 30 Zn-65 y
15 5
Zr-Nb-95 1
60 0.07 150 I-131 1.0c 60 15 130 0.05 180 15 80 Co-134 18 150 0.06 18
'd Cs-137 15 t$
15 y
Ba-I.a-140 18
= -
TABLE 4.12-3 (Continued)
TA3LE NOTATION 4
i
)
"This 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.
I 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):
1 4.66 sb LLD =
exp( 14t)
Y 2.22 V
E
.1 i
Where:
LLD is the "a priori" lower limit of detection as defined above, as
{;
picoeuries per unit mass or volume, is the standard deviation of the backgroun'd counting rate or cf sbthe counting rate of a blank sample as appropriate, as counts per
- minute, i
.'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, 1 is the radioactive decay constant for the particular radionuclide, t
and At for environmental samples is the elapsed time between sample collection, or end of the sample collection period, and time of l
counting Typical valves of E V, Y and at should be used in the calculation.
i j (
NORTH ANNA - UNIT 1 3/4 12-11 Amendment No. / /,63
)
TABLE 4.12-2 (Continued)
(
TABLE NOTATION i
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 Analysis shall be performed in such a manner that the measurement.
stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render 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.
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NORTH ANNA - UNIT 1 3/4 12-12 Amendment No. k N, 92 I
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/g oq'o, UNITED STATES
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y' j NUCLEAR REGULATORY COMMISSION W ASHINGTON, D. C. 20555 E
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VIRGINIA ELECTRIC AND p0WER COMPANY OLD DOMINTON ELECTRIC COOPEDATIVE DOCKET NO. 50-339 NORTH ANNA POWER STATION, UNIT NO. 2 AMENOMENT TO FACILITY OPERATING LICENSE Amendment No. 77 License No. NPF-7 1.
The Nuclear Regulatory Commission (the Commissioni has found that:
A.
The application for amendment by Virginia Electric and Power Company, et al., (the licensee) dated November 25, 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 Commission; t
C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endancering the health and safety of the public, and (111 that such activities will be conducted in compliance with the Commission's regulations; l
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 Commission's regulations and all applicable requirements have been satisfied.
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Accordinoly, the license is amended by changes to the Technical Speci-2.
fications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-7 is hereby amended to read as follows (2) Technical Specifications The Technical Specifications contained in Appendices A and P, as revised through Amendment No. 77
, are hereby incorporated The licensee shall operate the facility in in the license.
accordance with the Technical Specifications.
This license amendment is effective within 14 days from the the date of 3.
its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION w09 Lester S. Rubenstein, Director PWR Project Directorate #2 Division of PWR Licensing-A Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications
)
Date of Issuance: March 31, 1987 i
ATTACHMENT TO LICENSE AMENOMEf!T NO. 77 TO FACILITY OPERATING LICENSE NO. NPF-7 DOCKET NO. 50-334 Replace the following pages of the Appendix "A" Technical SpecificationsThe revised pag with the enclosed pages as indicated.
amendment number and contain vertical lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain document completeness.
Page 3/4 12-4 3/4 12-9 3/4 12-10 3/4 12-12 e
TABLE 4.12-1 5
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM *
- o
- x:
B Number of Samples Sampling and Type and Frequency Y
of Analysis and Collection Frequency _
N Exposure Pathway Sample Locations" Camma dose U
and/or Sample __
Quarterly l
1.
DIRECT RADIATION 36 routine monitoring quarterly.
stations either with two or more dosimeters or with one instrument for measuring and recording dose rate continuously to be placed as follows:
- 1) an inner ring of stations, one in each i
meteorological sector within the SITE B0lINDARY; an outer ring of stations, one in each meteorological sector within 8 km range from M
the balance of the the site; stations to be placed in special U
interest areas such as population O
centers, nearby residences, schools, and in I or 2 areas to serve as control stations.
Radiciodine Cannister:
2.
AIRBORNE Continuous sampler 1-131 analysis weekly.
Radiolodine and Samples from 5 locations:
(2/3 running time cycle), operation i
Particulates 3 samples from close with sample collection Particulate Sampler:
n.
O to the 3 SITE BOUNDARY weekly.
Gross beta radioactivity 0"
locations (in different j
E sectors) of the highest analysis following calculated historical filter change; annual average ground-Camma isotopic analysis 1
. level D/Q.
of compostte (by ca This table presents an frequency, and location of samples may vary from site to site. Local site characteristics must licable.
- The number, media, acceptable minimum program for a site at which each entry is app
~
ibute to an be examined to deteimine if pathways not covered by this table may significantly contr individual's dose ani should be included in the sampling program.
e
y
,m I
q TABLE 4.12-1 (Continued)_
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM _
5 E
ac Type and Frequency
- !i Number of Samples Sampling and of Analysis and Collection Frequency y
Exposure Pathway Sample Locations,_
location) quarterly.
g and/or Sample _
s I sample from the vicinity s
u b.
of a community having the highest calculated annual average groundlevel D/Q.
I sample from a control c.
location 15 40 km distant and in the least prevalent wind I
ti direction.
U Camma isotopic analysis 3
3.
WATERRORNE Sample off upstream, monthly. Composite for I sample circulating downstream and tritium analysis quarterly.
a.
Surface water discharge ecoling lagoon.
n.
Crab Monthly.
d Camma isotopic and tritium Grah analysis quarterly.
Samples from I or 2 sources Quarterly I
lI b.
Ground only if likely to be affected.
d f
u E.
Camma isotopic analysis M
Semiannually semiannually, I
I sample from downstream aren Sediment with existing or potential I
c.
z recreational value.
6 t'
d l
3 m
o t
TABLE 4.12-2 5
REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIRONMEN 5
Reporting Levels
- c Fish Milk Food Products L
Analysis (pC1/1) or Cases (pci/m )
(pCi/kg, wet)
(pC1/t)
(pC1/kg, wet) 8 Water Airborne Particulgte H-3 20,000*
30,000 Mn-54 1,000 10,000 Fe-59 400 30,000 Co-58 1,000 l
10,000 R
Co-60 300 s~
20,000 l
C Zn-65 300 Zr-Mb-95 400 3
100 0.9 I-131 2
60 1,000 1,000 10 Cs-134 30 70 2,000 2,000 Cs-137 50 20 300 m
Ba-La-140 200 I
U
- For drinking water samples E.
.Y d.
l l
~
n O
TABLE 4.I2-3_
E
- N DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS
=
LOWER LIMIT OF DETECTION (LLD)b Sediment Fish Milk Food Products y
E or Cas (pci/m )
(pC1/kg, wet)
(pC1/t)
(pci/kg, wet)
(pCf/kg. dry) e Airborne Partlegiate Water U
Analysis (pC1/t) 0.01 4
gross beta H-3 2000
,I 130 15
)
Mn-54 260 30 r
Fe-59 130 15 Co-58,60 w
260 s~
30 In-65 l
15 60 Zr-Nb-95 1
l J
C 0.07 150 I-131 1.0 60 15 130 i
0.05 Cs-134 15 180 80 150 18 0.06 18 Cs-137 I5 I
i Ba-l.a-140 15 8.,
t N.
i p
i*
I 4
TABLE 4.12-3 (Continued)
TABLE NOTATION
- This 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 l
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 :
l 4.66 s b LLD =
exp( lat)
Y 2.22 V
E Where:
LLD is the "a priori" lower limit of detection as defined above, as picoeuries per unit mass or volume.
is the standard deviation of the background counting rate or cf 6
l thecountingrateofablanksaepleasappropriate,ascountsper s
2
- minute,
.lE is the counting efficiency, as counts per disintegration.
V is the sample size in units of mass or volume,
)
1 2.22 is the number of disinte.grations per minute per picoeurie, Y is the fractional radiochemical yield, when applicable, 1 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 values of E, V, Y and at should be used in the calculation.
3/4 12-11 Amendment No. fyjf,47 NORTH ANNA - UNIT 2
(
TA3LE 4.12-2 (Continued)
(
TABLE NOTATION It should be recognized that the LLD is defined as an a priori (before d
the f act) limit representing the capability of a measurement system an not as an a posteriori (af ter the fact) limit for a particularAn Occasionally measurement.
stated LLDs vill be achieved under routine conditions.
background fluctuations, unavoidably small sample sizes, the presence interfering nuclides, or other uncontrollable circumstances may these LLDs unachievable. identified and described in the Annual Radiologica Operating Report pursuant to Specification 6.9.1.8.
This LLD value is for drinking water samples O
e e
i e
3/4 12-12 Amendment No. [Jg/,47,77 9
NORTH ANNA - UNIT 2
"