ML031220706
| ML031220706 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley (DPR-066, NPF-073) |
| Issue date: | 04/25/2003 |
| From: | Bezilla M FirstEnergy Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-03-072 A9.621B | |
| Download: ML031220706 (129) | |
Text
New: 1/2-ODC-2.03 Old: SECTION 3
A9.621B Beaver Valley Power Station Unit 1/2 II 1/2-ODC-2.03 ODCM: Radiological Environmental Monitoring Program Document Owner Manager, Health Physics Revision Number 0
Level Of Use General Skill Reference Safety Related Procedure Yes
Beaver Valley Power Station Noet ODC.N2 03 ml
Title:
Unit:
Level Of Use ODCM: Radiological Environmental Monitoring Program l/9 General Skill Reference Revision:
Page Number
-- 02 of 18 TABLE OF CONTENTS 1.0 PURPOSE...............................
3 2.0 SCOPE................
3.0 REFERENCES
AND COMMITMENTS............................
3 3.1 References................................
3 3.2 Commitments................................
3 4.0 RECORDS AND FORMS................................................................................................................3 4.1 Records...............................
3 4.2 Form s......................................................................................................................................4 5.0 PRECAUTIONS AND LIMITATIONS.............................
4 6.0 ACCEPTANCE CRITERIA.............................
4 7.0 PREREQUISITES...............................
4 8.0 PROCEDURE...............................
4 8.1 REMP Overview
.4 8.2 Sampling and Analysis Program
.4 8.3 Crosscheck Program...........................
5 8.4 Land Use Census Program.........................
6 8.5 Direct Radiation Monitoring Program
- 7 ATTACHMENT A EXPOSURE PATHWAY AND SAMPLING REQUIREMENTS........................
8 ATTACHMENT B LOCATION OF SAMPLING SITES.
12
BeavrV e
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SProcedure Number Beaver Valley Power Station1/2-ODC-2.03
Title:
Unit:
Level Of Use:
ODCM: Radiological Environmental Monitoring Program 1/2 General Skill Reference Revision:
Page Number.
_ 0 of 18 1.0 PURPOSE 1.1 This procedure provides the Radiological Environmental Monitoring Program (REMP) requirements from the Radiological Branch Technical Position.13 '1" 1.1.1 Prior to issuance of this procedure, these items were located in Section 3 of the old ODCM.
2.0 SCOPE 2.1 This procedure is applicable to all station personnel that are qualified to perform activities as described and referenced in this procedure.
3.0 REFERENCES
AND COMMITMENTS 3.1 References 3.1.1 Radiological Branch Technical Position, Revision 1, 1979.
3.1.2 Regulatory Guide 1.109, Calculation of Annual Dose to Man From Routine Releases of Reactor Effluents For the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Revision 1, 1977.
3.1.3 NUREG-1301, Offsite Dose Calculation Manual Guidance; Standard Radiological Effluent Controls for Pressurized Water Reactors (Generic Letter 89-01, Supplement No.
1).
3.1.4 Regulatory Guide 1.1 11, Methods For Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases From Light-Water-Cooled Reactors, Revision 1, July 1977.
3.1.5 1/2-ADM-1640, Control of the Offsite Dose Calculation Manual 3.1.6 1/2-ADM-0100, Procedure Writers Guide 3.1.7 1/2-ADM-0101, Review and Approval of Documents 3.2 Commitments 3.2.1 10 CFR 50 Appendix I 4.0 RECORDS AND FORMS 4.1 Records 4.1.1 Any calculation supporting ODCM changes shall be documented, as appropriate, by a retrievable document (e.g., letter or calculation package) with an appropriate RTL number.
Beaver Valley Power Staion edure Number.
Power Sation1/2..ODC2.203 Unit:
Level Of Use:
ODCM: Radiological Environmental Monitoring Program 1/2 General Skill Reference Revision:
Page Number:
4.2 Forms 4.2.1 None.
5.0 PRECAUTIONS AND LIMITATIONS 5.1 The specified detection capabilities are state-of-the-art for routine environmental measurements in industrial laboratories.
6.0 ACCEPTANCE CRITERIA 6.1 Any change to this procedure shall contain sufficient justification that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a and Appendix I to 10 CFR 50, and not adversely impact the accuracy or reliability of effluent dose or setpoint calculation.
6.1.1 All changes to this procedure shall be prepared in accordance with 1/2-ADM-0100(3'16 and 1/2-ADM-1640(3-' 5).
6.1.2 All changes to this procedure shall be reviewed and approved in accordance with 1/2-ADM-0101(3.1.7 and 1/2-ADM-1640(3 IS).
7.0 PREREQUISITES 7.1 The user of this procedure shall be familiar with ODCM structure and format.
8.0 PROCEDURE 8.1 REMP Overview 8.1.1 Attachment A, Table 3.0-1 contains the site number, sector, distance, sample point description, sampling and collection frequency, analysis, and analysis frequency for various exposure pathways in the vicinity of the Beaver Valley Power Station for the REMP. Attachment B, Figures 3.0-1 through 3.0-6 show the location of the various sampling points.
8.2 Sampling and Analvsis Program 8.2.1 Environmental samples shall be collected and analyzed according to Attachment A, Table 3.0-1. Analytical techniques used shall be such that the detection capabilities in 1/2-ODC-3.03, Table 4.12-1 are achieved.
8.2.2 The results of the radiological environmental monitoring are intended to supplement the results of the radiological effluent monitoring by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways.
Procedure Number:
Beaver Valley Power Station 1/2-ODC-2.03
Title:
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ODCM: Radiological Environmental Monitoring Program l/2 General Skill Reference Revision:
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(
of Is 8.2.2.1 The specified environmental monitoring program provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of individuals resulting from the station operation.
8.2.2.2 The initial radiological environmental monitoring program should be conducted for the first 3 years of commercial operation (or other period corresponding to a maximum burnup in the initial core cycle). Following this period, program changes may be proposed based on operational experience.
8.2.3 Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons.
8.2.3.1 IF specimens are unobtainable due to sampling equipment malfunction, THEN' every effort shall be made to complete corrective action prior to the end of the next sampling period.
8.2.3.2 All deviations from the sampling schedule shall be documented in the annual REMP report.
8.3 Crosscheck Program 8.3.1 The laboratories of the licensee and licensee's contractors which perform analyses shall participate in the Environmental Protection Agency's (EPA's) Environmental Radioactivity Laboratory Intercomparisons Studies (Crosscheck) Program or equivalent program.
8.3.1.1 This participation shall include all of the determinations (sample medium-radionuclide combination) that are offered by EPA and that also are included in the monitoring program.
8.3.1.2 The results of analysis of these crosscheck samples shall be included in the annual REMP report. The participants in the crosscheck program may provide their program code so that the NRC can review the participant data directly in lieu of submission in the annual REMP report.
8.3.1.3 IF the results of a determination in the crosscheck program are outside the specified control limits, THEN the laboratory shall investigate the cause of the problem and take steps to correct it. The results of this investigation and corrective action shall be included in the annual REMP report.
8.3.2 The requirement for the participation in the crosscheck program, is based on the need for independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices as part of the quality assurance progrum for environmental monitoring in order to demonstrate the results are reasonably valid.
Beaver Valley Power Station P
ld/r ODCNm203
Title:
Ut Level Of Use.
ODCM: Radiological Environmental Monitoring Program 112 General Skill Reference Revision:
Pge Number 6
__O 6ofl 8.4 Land Use Census Program 8.4.1 A census shall be conducted annually during the growing season to determine the location of the nearest milk animal, and nearest garden greater than 50 square meters (500 sq. ft.) producing broad leaf vegetation in each of the 16 meteorological sectors within a distance of 8 km (5 miles).
8.4.1.1 For elevated releases as defined in Regulatory Guide 1.111(3.1.4), the census shall also identify the locations of all milk animals, and gardens greater than 50 square meters producing broad leaf vegetation out to a distance of 5 km (3 miles) for each radial sector.
8.4.1.2 IF it is learned from this census that the milk animals or gardens are present at a location which yields a calculated thyroid dose greater than those previously sampled, or if the census results in changes in the location used in ODCM dose calculations, THEN a written report shall be submitted to the Director of Operating Reactors, NRR (with a copy to the Director of the NRC Regional Office) within 30 days identifying the new location (distance and direction).
8.4.1.2.1 Milk animal or garden locations resulting in higher calculated doses shall be added to the surveillance program as soon as practicable.
8.4.1.3 The sampling location (excluding the control sample location) having the lowest calculated dose may then be dropped from the surveillance program at the end of the grazing or growing season during which the census was conducted. Any location from which milk can no longer be obtained may be dropped from the surveillance program after notifying the NRC in writing that they are no longer obtainable at that location.
8.4.1.4 The results of the land-use census shall be reported in the annual REMP report.
8.4.1.5 The census of milk animals and gardens producing broad leaf vegetation is based on the requirement in Appendix I of 10 CFR Part 50(3.2.i) to "Identify changes in the use of unrestricted areas (e.g., for agricultural purposes) to permit modifications in monitoring programs for evaluating doses to individuals from principal pathways of exposure." The consumption of milk from animals grazing on contaminated pasture and of leafy vegetation contaminated by airborne radioiodine is a major potential source of exposure. Samples from milk animals are considered a better indicator of radioiodine in the environment than vegetation.
8.4.1.5.1 IF the census reveals milk animals are not present or are unavailable for sampling, THEN vegetation must be sampled.
8.4.1.6 The 50 square meter garden, considering 20% used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and a vegetation yield of 2 kg/n 2, will produce the 26 kg/yr assumed in Regulatory Guide 1.109(3 1, for child consumption of leafy vegetation.
Beaver Valley Power Station 1/2PcDCrN2.03
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7 nof 1 8.5 Direct Radiation Monitoring Program 8.5.1 The increase in the number of direct radiation stations is to better characterize the individual exposure (mrem) and population exposure (man-rem) in accordance with Criterion 64 - monitoring radioactivity releases, of 10 CFR Part 50, Appendix A. The NRC will place a similar amount of stations in the area between the two rings designated in 1/2-ODC-3.03, Table 3.12-1.
-END -
TABLE 3.0-1 PROGRAM DETAILS EXPOSURE PATHWAY AND/OR SAMPLE
- 1. AIRBORNE Radioiodine and Particulates
- 2. DIRECT RADIATION SITE NO.
13 30 32 46.1 48 SECTOR' MILES2 11 1.4 4
0.5 15 0.8 3
2.3 10 16.3 SAMPLE POINT DESCRIPTION 3 Meyer's Fame Shippingport (S.S.)
Midland (S.S.)
Industry, Midway Dr.
Weirlon, W. Va., Weirton Water Tower, Collier Way<
SAMPLING AND COLLECTION FREQUENCY TYPE AND FREOUENCY OF ANALYSES Continuous sampler Radioiodine Cartridge:
operation with 1-131 analysis weekly.
collection at least weekly Particulate Sampler: Gross beta analysis following filter change5; Gamma isotopic analysis on composite (by location) quarterly.
Gamma dose quarterly.
10 3
1.0 Shippingport Boro 13 l 1 1.4 Meyer's Farm 14 11 2.5 llookstown 15 14 3.7 Georgetown Post Office 27 7
6.1 Brunton's 28 1
8.6 Sherman's Farm 29B 3
8.0 Beaver Valley Geriatric Center 30 4
0.5 Shippingport (S.S.)
32 15 0.8 Midland (S.S.)
45 5
2.2 Rt. 18 & Anderson Street 45.1 6
1.9 Raccoon Twp., Kennedy's Corner 46 3
2.5 Industry, Midway Drive 46.1 3
2.3 Industry, Rt. 86 - Garage 47 14 4.9 East Liverpool, OH Water Treatment Plant 48 10 16.3 Weirton, W. Va., Weirton Water Tower, Collier Way 51 5
8.0 Aliquippa (S.S.)
59 6
1.0 236 Green Hill Rd.
60 13 2.5 444 Hill Road 70 l
3.4 N. of Western. Beaver School-Engle Rd.
71 2
6.0 Brighton Twp., First Western Bank Continuous measurement with quarterly collection.
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TABLE 3.0-1 PROGRAM DETAILS EXPOSURE PATHWAY AND/OR SAMPLE
- 2. DIRECT RADIATION (continued)
ISITE SAMPLE POINT DESCRIPTION 3 SECTOR' MILES2 SAMPLING AND COLLECT0IN FREQUENCY Continuous measurement with quarterly collection.
TYPE AND FREQUENCY OP ANALYSES Gamma dose quarterly.
72 3
3.3 Industry, Logan Park 73 4
2.5 618 Squirrel Run Road 74 4
7.0 CCBC, 137 Poplar Avenue 75 5
4.1 117 Holt Road 76 6
3.8 Raccoon Elementary School 77 6
5.6 3614 Green Garden Road 78 7
2.7 Raccoon Municipal Building 79 8
4.4 Rt. 151 & Pross Ln.
80 9
8.2 Raccoon Park Office, Rt. 18 81 9
3.6 Millcreek United Presb. Church 82 9
6.9 Hanover Municipal Building 83 10 4.2 735 Mill Creek Road 84 11 8.3 Hancock Parks & Recreation Complex 85 12 5.7 Rts. 8 and 30 Intersection 86 13 6.2 East Liverpool, Oh., 1090 Ohio Avenue 87 14 7.0 Calcutta, Oh.- Calcutta Smith's Ferry Rd & Valley Drive 88 15 2.8 Midland Heights, 110 Summit Road 89 15 4.8 Ohioville, 488 Smith's Ferry Road 90 16 5.2 Opposite Fairview School 91 2
3.9 Pine Grove & Doyle Roads 92 12 2.8 Georgetown Road (S.S.)
93 16 1.1 Midland - Sunrise Hills 94 8
2.2 McCleary Road & Pole Cat Hollow Road 95 10 2.3 832 McCleary Road 0
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TABLE 3.0-1 (continued)
PROGRAM DETAILS EXPOSURE PATHWAY AND/OR SAMPLE
- 3. WATERBORNE a) Surface (River) b) Drinking Water c) Ground Water d) Shoreline Sediment
- 4. INGESTION a) Milk b) Fish c) Food Products (Leafy Vegetables)
SITE SECTORQ MLES2 SAMPLE POINT DESCRIPTrON3 49 3
5.0 Upstream side of Montgomery Dam4 2.1 14 1.5 Downstream, Midland - J&L 4
1 5 1.3 Midland Watcr Treatmcnt Plant 5
14 4.9 East Liverpool, Oh.,
Water Treatment Plant SAMPLING AND COLLECTIQN MQEUENCY Composite sample with sample collection at least monthly.
Compt)site sample with sample collection at least bi-weckly'.
TYPE ANDAFRESuENcy Gamma isotopic analysis monthly; tritium analysis on composite (by location) quarterly.
1-131 analysis bi-weckly; gamma isotopic analysis on composite (by location) monthly; tritium analysis on composite (by location) quarterly.
None required 7 trjm 0
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03.
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- 3 2A 13 0.2 BVPS Outfall Discharge a
CD W
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_-C1 90 b-I CD 0
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25 10 2.1
- 8 96 10 10.4 Searight's Farm Windsheimer's Farm4 Semi-annually.
At least bi-weekly when animals are on pasture; at least monthly at other times.
Semi-annually one sample of available species.
Gamma isotopic analysis semi-annually.
Gamma isotopic and 1-131 analysis on each sample.
Gamma isotopic analysis.
On edible portion.
2A 13 0.2 BVPS Outfall Discharge 49 3
5.0 Upstream side of Montgomery Dam ft S1
V.
ft a
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2.
C-) °
- c pa C at (A1 I
Three (3) locations within 5 miles of BVPS (Shippingport, Industry, and Georgetown )
One (1) control location (Weirton, W. Va. area)"
Annually at harvest Gamma isotopic and I-131 time.
analysis on edible portion.
I I "
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(
.7 I
TABLE 3.0-1 (continued) _
PROGRAM DETAILS EXPOSURE SITE SECTOR' MILES2 SAMPLE POINT SAMPLING AND TYPE AND FREQUENCY PATHWAY AND/OR NO.
DESCRIPTION 3 COLLECTION OF ANALYSES SAMPLE FREQUENCY 0
CD eMu.
t,
'Sector numbers I-16 correspond to the 16 compass direction sectors N - NNW.
0 2d 2Distance (in miles) is as measured from BVPS Unit I Containment Building.
All Sample Points, unless otherwise noted, are in the Commonwealth of Pennsylvania. Maps showing the approximate locations of the CD3l Sample Points are provided as Attachment B, Figures 3.0-1 through 3.0-6.
4This is a Control Station and is presumed to be outside the influence of BVPS effluents.
5 A gamma isotopic analysis is to be performed on each sample when the gross beta activity is found to be greater than 10 times the mean of the Control Station sample.
3 8 r +
6Composite samples are obtained by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. For the upstream surface water location site A
0 49, a weekly grab sample, composited each month based on river flow at time of sampling is also acceptable.
0 7Collection of Ground Water samples is not required as the hydraulic gradient or recharge properties are directed toward the river because of the high terrain in the river valley at the BVPS; thus, station effluents do not affect local wells and ground water sources in the area.
sThese Sample Points will vary and are chosen based upon calculated annual deposition factors (highest).
000 9 Exact location may vary due to availability of food products.
sn X
0
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Beaver Valley Power Station PCureNumber.
Title.
Unit Level Of Use:
ODCM: Radiological Environmental Monitoring Program 1/2 General Skill Reference Revision:
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0 I)of I ATTACHMENT B Page 1 of 7 LOCATION OF SAMPLING SITES FIGURE 3.0-2 AIR SAMPLING LOCATIONS Sector Site #
Distance (miles) Location I
13 1.4 Meyer's Farm 4
30 0.5 Shippingport (S. S.)
15 32 0.8 Midland (S.S.)
3 46.1 2.3 Industry, Rt. 68 Garage 10 48 16.4 Weinon, W. Va.,-Weirton Water Tower, Collier Way
Beaver Valley Power Station 1P2-ODC-2.03 Tritle:
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0 1?1 of 18 ATTACHMENT B Page 2 of 7 LOCATION OF SAMPLING SITES FIGURE 3.0-2 (continued)
¶RDLOCArIONS
Beaver Valley Power Station Proced Nume
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ATTACHMENT B Page 3 of 7 LOCATION OF SAMPLING SlTES FIGURE 3.0-2 (continued)
TLD LOCATIONS Southeast Sector Site # Distance Location lSector Site # Distance Location (miles)
(miles) 7 27 6.1 Brunton's Fm7 78 2.7 Raccoon Municipal Bldg 6
45.1 1.9 Raccoon Twp., Kennedy Corners 8
79 4.4 Rt. 151 & Pross Ln.
5 51 8.0 Aliquippa (S.S.)
9 80 8.2 Raccoon Park Office-Rt. 18 6
59 1.0 236 Green Hill Road 9
82 6.9 Hanover Municipal Building 6
76 3.8 Raccoon Elementary School 8
94 2.2 McCleary Road &
Pole Cat Hollow Road 6
77 5.6 3614 Green Garden Road Northwest Sector Site # Distance Location
_Sector Site # Distance Location (miles)
(miles)__
14 15 3.7 Georgetown Post Office 14 87 7.0 Calcutta, Oh. - Calcutta Smith's Ferry Rd & Valley Drive 15 32 0.8 Midland (S.S.)
15 88 2.8 Midland Heights - 110 Summit Rd 14 47 4.9 E. Liverpool, Oh.
15 89 4.8 Ohioville - 488 Smith's Ferry Road (Water Company) 13 60 2.5 Haney's Farm 16 90 5.2 Opposite Fairview Shool 13 86 6.2 E. Liverpool, Oh., 1090 Ohio 16 93 1.1 Midland - Sunrise Hills Avenue Northeast Sector Site # Distance Location Sector Site # lDistance Location (miles)
(miles) 4 10 1.0 Shippingport Boro 1
70 3.4 North of Western Beaver School -
' 28 8.6 S ' FE ngle R oad 1
28 8
Sherman'sFarr 2
71 6.0 Brighton Twp., First Western Bank 3
29B 8.0 Beaver Valley Geriatric Ctr.
3 72 3.3 Industry, Logan Park 4
30 0.5 Shippingport (S.S.)
4 73 2.5 618 Squirrel Run Road 5
45 2.2 Rt. 18 & Anderson Street 4
74 7.0 CCBC -137 Poplar Avenue 3
46 2.5 Industry, Midway Drive 5
75 4.1 117 Holt Road 3
46.1 2.3 Industry, Rt. 68-Gara e 2
91 3.9 lPine Grove Rd. & Doyle Rd.
Southwest Sector Site # Distance Location lsectorl Site # Distance Location (miles) I
_l_l_(miles) 11 13 1.4 Meyer's Farm l
11 84 8.3 Hancock Co. Parks & Recreation 1Complex l 14 2.5 Hookstown 12 85 5.7 Rts. 8 & 30 Intersection 10 48 16.3 Weirton, W. Va., - Weirton l
_12 _92 2.8
_Georgetown Road _
_______lWater Tower, Collier Way 1
1 9
81 3.6 MillcreekUnited Presb. Church 10 95 2.3 832 McClearyRoad 10 83 4.2 1735 Mill Creek Road
IS 4 i
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Beaver Valley Power Station PrdureNumber
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Page Number 5of Is ATTACHMENT B Page 4 of 7 LOCATION OF SAMPLING SITES FlGURE3.0-3 SHOREUNRSEDIMFNLSURFACEWATERANDDRNKINGWATERSAMPLINGLOCATIONS Mac 12.00 Water/Shoreline Sediment Sampling Locations Sample Type Sector Site #
Distance (miles)
Location Surface Water 14 2.1 15 Downstream, Midland - J&L Surface Water 3
49 5.0 Upstream side of Montgomery Dam Sediment 13 2A 0.2 BVPS Outfall Discharge Drinking Water 15 4
1.3 Midland Water Treatment Plant Drinking Water 14 5
1 4.9 E. Liverpool, Oh. Water Treatment Plant
Beaver Valley Power Station lo 1/2N DCub 2.03 1ritte:
Unit Level Of Use:
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f16 of 18 ATTACHBVENT B Page 5 of 7 LOCATION OF SAMPLING SIThS FIGURE 3.04 MLKSAMPLINGLOCATIONS Milk Sampling Locations Sector Site #
Distance (miles)
Location 10 25*
2.1 Searight's Farm 10 96 10A Windsheimer Farm
'Three dairies based on highest deposition factors.
e VProcedure Number Beaver Valley Power Station 1/2-ODC-2.03
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n 17 of' 18 ATTACHMENT B Page 6 of 7 LOCATION OF SAMPLING SITES FIGURE 3.0-5 FOODCROP SAMPLING LOCATIONS Food Sampling Locations Site #
Description 10 Shippingport Boro 15 Georgetown Post Office 46 Industry, Midway Dr.
48 Weirton, W. Va., - Weirton Water Tower, Collier Way
Beaver Valley Power Station ProcedONumber.
Title:
Unit; ULd Of L 3c.
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0 l Rnfl ATTACHMENT B Page 7 of 7 LOCATION OF SAMPLING SITES FIGURE 3.0-6
.qoX Fish Sampling Locations Sector Site#
Distance (miles)
Location 13 2A 0.2 BVPS Outfall Discharge 3
49 5.0 Upstream side of Montgomery Dam
New: 1/2-ODC-2.04 Old: SECTION 4
A9.621B Beaver Valley Power Station Unit 1/2 112-ODC-2.04 ODCM: Information Related to 40 CFR 190 Document Owner Manager, Health Physics II Revision Number 0
Level Of Use General Skill Reference Safety Related Procedure Yes
Beaver Valley Power Station Po2eu ODCNu.04 Ttle:Unit:
Level Of Use:
1/2 General Skill Reference ODCM: Information Related to 40 CFR 190 Revision:
Page Number:
02of6___
TABLE OF CONTENTS 1.0 PURPOSE....
3 2.0SOE........................................3.......
2.0 SCOPE.3
3.0 REFERENCES
AND COMMII ENTS.................................
3 4.0 RECORDS AND FORMS................................
3 5.0 PRECAUTIONS AND LIMITATIONS.................................
4 6.0 ACCEPTANCE CRITERIA................................
4.............
........... 4 7.0 PREREQUISITES..................................
4 8.0 PROCEDURE...............................
4 8.1 Information Related To 40 CER 190................................
.4 8.2 Inside The Site Boundary Radiation Doses
.5
Procedure Number:
Beaver Valley Power Station 1/2-ODC-2.04
Title:
Unit:
Level Of Use:
1/2 General Skill Reference ODCM: Information Related to 40 CFR 190 Resision:
Page Number.3 of 6 1.0 PURPOSE 1.1 This procedure provides the steps to be taken when the Total Dose of ODCM Control 4.11.4.1 exceeds twice the limit of any of the ODCM Controls specifying an Offsite Dose Limit. (3.1l2V 1.1.1 Prior to issuance of this procedure, these items were located in Section 4 of the old ODCM.
2.0 SCOPE 2.1 This procedure is applicable to all station personnel that are qualified to perform activities as described and referenced in this procedure.
3.0 REFERENCES
AND COMMITMENTS 3.1 References 3.1.1 40 CFR Part 190 3.1.2 1/2-ODC-3.03, ODCM: Controls for RETS and REMP Programs 3.1.3 1/2-ADM-1640, Control of the Offsite Dose Calculation Manual 3.1.4 1/2-ADM-0100, Procedure Writer's Guide 3.1.5 1/2-ADM-0101, Review and Approval of Documents 3.2 Commitments 3.2.1 Technical Specification 6.9.2f, Special Reports 3.2.2 NUREG-1301, Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors (Generic Letter 89-01, Supplement No.
1) 4.0 RECORDS AND FORMS 4.1 Records 4.1.1 Any calculation supporting ODCM changes shall be documented, as appropriate, by a retrievable document (e.g.; letter or calculation package) with an appropriate RTL number.
4.2 Forms 4.2.1 None
Proedure Number~
Beaver Valley Power Station,/2-ODC..201
Title:
Unit:
Level Of Use:
1/2 General Skill Reference ODCM: Information Related to 40 CFR 190 Revision:
Page Number:
_0 4of 6K 5.0 PRECAUTIONS AND LIMITATIONS 5.1 The Offsite Dose Limits used to show compliance to this procedure are as follows:
5.1.1 ODCM Control 3.11.2.a; Liquid Effluents: < 1.5 mrem/quarter Total Body or <5 mrem/quarter any Organ.
5.1.2 ODCM Control 3.11.2.b; Liquid Effluents: < 3 mrem/year Total Body or < 10 mremlyear any Organ.
5.1.3 ODCM Control 3.11.2.2.a; Gas Effluent-Noble Gas: < 5 mrad/quarter Gamma, or < 10 mrad/quarter Beta 5.1.4 ODCM Control 3.11.2.2.b; Gas Effluents-Noble Gas: < 10 mrad/year Gamma < 20 mrad/year Beta 5.1.5 ODCM Control 3.11.2.3.a; Gas Effluents-Particulates & lodines: < 7.5 mrem/quarter any organ 5.1.6 ODCM Control 3.11.2.3.b; Gas Effluents-Particulates & Iodines: < 15 mrem/year any organ 5.1.7 ODCM Control 3.11.4.1; All Fuel Cycle Sources: <25 mrem/yearTotal Body or any Organ, except the thyroid, which is limited to < 75 mrem/year 6.0 ACCEPTANCE CRITERIA 6.1 Any changes to this procedure shall contain sufficient justification that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302,40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR 50, and not adversely impact the accuracy or reliability of effluent dose or setpoint calculation.(3 6.1.1 All changes to this procedure shall be prepared in accordance with l/2-ADM-0100(3 l4 )
and 1/2-ADM-1640.(31.3) 6.1.2 All changes to this procedure shall be reviewed and approved in accordance with 1/2-ADM-0101(3 i')
and 1/2-ADM-1640.(3-'-3) 7.0 PREREQUISITES 7.1 The user of this procedure shall be familiar with ODCM structure and content.
8.0 PROCEDURE 8.1 Information Related To 40 CFR 190 8.1.1 CONTROL 3.11.4.1 requires that when the calculated doses associated with the effluent releases exceed twice the limits of ODCM CONTROL 3.11.1.2.a, 3.11.1.2.b, 3.11.2.2.a, 3.11.2.2.b, 3.11.2.3.a, or 3.11.2.3.b, the following shall be performed:
Procedure Number~
Beaver Valley Power Station Pc 2-ODur Nub
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1/2 l General Skill Reference ODCM: Information Related to 40 CFR 190 Revision:
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0 5 f I
I iii
. I 8.1.1.1 Calculations shall be made including direct radiation contributions from the units (including outside storage tanks, etc.) to determine whether the dose or dose commitment to any MEMBER OF THE PUBLIC from all facility releases of radioactivity and to radiation from uranium fuel cycle sources exceeds the limits of
- 25 mrem to the total body or any organ, except the thyroid, which is limited to <
75 mrem for a calendar year.
8.1.1.1.1 If any of these limits are exceeded, prepare and submit to the Commission within 30 days a Special Report pursuant to Technical Specification 6.9.2f. 3 2'l) The following shall be included in the Special Report:
8.1.1.1.1.1 Define the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the limits of ODCM CONTROL 3.11.4.1.
8.1.1.1.1.2 Include the schedule for achieving conformance within the limits of ODCM CONTROL 3.11.4.1.
8.1.1.1.1.3 Include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report.
8.1.1.1.1.4 Describe levels of radiation and concentrations of radioactive material involved, and the cause of exposure levels or concentrations.
8.1.1.1.1.5 If the estimated dose(s) exceeds the limits of ODCM CONTROL 3.11.4.1, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, include a request for a variance in accordance with the provisions of 40 CFR Part 190.
Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.
8.2 Inside The Site Boundary Radiation Doses 8.2.1 In regards to assessment of radiation doses (from Radioactive Effluents) to MEMBERS OF THE PUBLIC due to their activities inside the site boundary, the following is provided:
8.2.1.1 A separate assessment of radiation doses from radioactive effluents to MEMBERS OF THE PUBLIC due to their activities inside the site boundary is generally not necessary because the exposure time for individuals not occupationally associated with the plant site is minimal in comparison to the exposure time considered for the dose calculation at or beyond the site boundary.
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6of 6 8.2.1.2 For reporting purposes, separate guidance for calculating radiation doses to a MEMBER OF THE PUBLIC inside the site boundary is not needed because the dose assessments for an offsite MEMBER OF THE PUBLIC is also assumed to be for a MEMBER OF THE PUBLIC conducting activities onsite.
8.2.1.2.1 This is verified by showing that the ground release X/Q dispersion parameter used for dose calculation at the site boundary (0.352 miles NW) is greater than the XIQ dispersion parameter at the location where a MEMBER OF THE PUBLIC would most likely have the maximum exposure time (0-0.5 miles N and 0-0.5 miles NNW). A comparison of these X/Q dispersion parameters is as follows:
X/QUsedfcrDose XQWhe W an Assam d X/QRefimes Calculadton MEMBER OFTHEPUBLIC frim WWd Mst Likely Have the Maximum 2-ODC-202 ExpcureTXn-e SiteBwidaly InsidetheSite hisidedieSite See Attachmit F 0352 rniles NW Bmiday Bowday 0-05milesN 0.5-iesNNW 9.24E-5 SeC/n 3 233E-5 secrn3 5.47E-5 sei 3 Table 2.24 1.03E4sechn3 2.76E-5 sec& 3 6.01lE5 s=T 3 Table22-5 735E-5 secki3 244ESsec = 3 5.57E-5 sern3 Table 22-7 924E-5 secm 3 233E-5 sein 3
5.47E-5 secin3 Table2.2-8 924E5 secm 3 233E-5secm 3 5.47E-5 secn 3 Table 2.2-9 735E-5sein3 2.44E-Sseckm3 557E-5 se&
Table2.2-10
-END -
New: 1/2-ODC-3.01 Old: APPENDIX A & B
A9.621B Beaver Valley Power Station Unit 1/2 1/2-ODC-3.01 ODCM: Dispersion Calculational Procedure and Source Term Inputs Document Owner Manager, Health Physics Revision Number 0
Level Of Use General Skill Reference Safety Related Procedure Yes
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_2 of-2 TABLE OF CONTENTS 1.0 PURPOSE..............................................
3 2.0 SCOPE..............................................
3 3.0 REFEFERENCES AND COMMITMENTS..............................................
3 3.1 References..............................................
3 3.2 Commitments.......................
4 4.0 RECORDS AND FORMS.....................
4 4.1 Records.....................
4 4.2 Forms.....................
4 5.0 PRECAUTIONS AND LIMITATIONS..............................................
4 6.0 ACCEPTANCE CRITERIA..............................................
4 7.0 PREREQUISITES..............................................
4 8.0 PROCEDURE..............................................
5 8.1 Summary of Dispersion and Deposition Methodology...............................................
S 8.2 Summary of Source Term Inputs..............................................
7 8.2.1 Liquid Source Term Inputs...........................................
7 8.2.2 Gaseous Source Term Inputs...........................................
7 ATTACHMENT A BV-1 AND 2 RELEASE CONDITIONS.......................................
8 ATTACHMENT B LIQUID SOURCE TERM INPUTS......................................
9 ATTACHMENT C GASEOUS SOURCE TERM INPUTS
.11
v 7
_ n
- Procedure
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Beaver Valley Power Station Pmedur3ume
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1.0 PURPOSE 1.1 This procedure contains the basic methodology that was used for calculating dispersion (X/Q) and deposition (D/Q).
1.1.1 Prior to issuance of this procedure, these items were located in Appendix A of the old ODCM.
1.2 This procedure also contains the input parameters to the various computer codes used by the Licensee and its subcontractors for determination of the liquid and gaseous source term mixes.
1.2.1 Prior to issuance of this procedure, these items were located in Appendix B of the old l
ODCM.
2.0 SCOPE 2.1 This procedure is applicable to all station personnel (including subcontractors) that are qualified to perform activities as described and referenced in this procedure.
3.0 REFEFERENCES AND COMMITMENTS 3.1 References 3.1.1 NUS-2173,Development Of Terrain Adjustment Factors For Use At the Beaver Valley i
Power Station, For the Straight-Line Atmospheric Dispersion Model, NUS Corporation, l
June 1978 3.1.2 NUREG/CR-2919, XOQDOQ: Computer Program For The Meteorological Evaluation Of Routine Effluent Releases At Nuclear Power Stations, September, 1982 3.1.3 Regulatory Guide 1.23, Meteorological Measurement Program for Nuclear Power Plants 3.1.4 Regulatory Guide 1.111, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents In Routine Releases From Light-Water-Coded Reactors, Revision 1, July 1977 3.1.5 NRC Gale Code, 3.1.6 SWEC LIQ1BB Code, 3.1.7 SWEC GAS 1BB Code, 3.1.8 NUREG-1301, Offsite Dose Calculation Manual Guidance, Standard Radiological Effluent Controls for Pressurized Water Reactors (Generic Letter 89-01, Supplement No.
i 1) 3.1.9 1/2-ADM-1640, Control of the Offsite Dose Calculation Manual
I Beaver Valley Power Station Procedure Number B ea v r V a le y o w er1/2-OD C-3.01
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0 4 of12 3.1.10 1/2-ADM-0100, Procedure Writer's Guide 3.1.11 1/2-ADM-0101, Review and Approval of Documents 3.2 Commitments 3.2.1 None 4.0 RECORDS AND FORMS 4.1 Records 4.1.1 Any calculation supporting generation of dispersion, deposition, or source term mixes shall be documented, as appropriate, by a retrievable document (e.g.; letter or calculation package) with an appropriate RTL number.
4.2 Forms 4.2.1 None 5.0 PRECAUTIONS AND LIMITATIONS 5.1 This procedure contains the information that was previously contained in Appendix A and Appendix B of the previous BV-1 and 2 Offsite Dose Calculation Manual.
5.1.1 In regards to this, the Tables that were transferred from Appendix A and Appendix B to the appropriate ATTACHMVEENTS of this procedure will still contain a prefix denoting an "A" or "B.
6.0 ACCEPTANCE CRITERIA 6.1 Any change to this procedure shall contain sufficient justification that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302,40 CFR Part 190, 10 CFR 50.36a and Appendix I to 10 CFR 50, and not adversely impact the accuracy or reliability of effluent dose or setpoint calculation.
6.1.1 All changes to this procedure shall be prepared in accordance with 1/2-ADM-0100( 3 01 and 1/2-ADM-1640.13.1.9) 6.1.2 All changes to this procedure shall be reviewed and approved in accordance with 1/2-ADM-0101i3 1'3 and 1/2-ADM-1640.(31.9) 7.0 PREREQUISITES 7.1 The user of this procedure shall be familiar with ODCM structure and content.
Procedure Number:
Beaver Valley Power Station112-ODC-3.1
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12 8.0 PROCEDURE 8.1 Summary of Dispersion and Deposition Methodology 8.1.1 Annual average and grazing season average values of relative concentration (X/Q) and deposition (D/Q) were calculated for continuous and intermittent gaseous releases of activity from the site according to the straight-line airflow (Gaussian) model described in 8.1.1.1 Undecayed and undepleted sector average X/Q and DIQ values were obtained for each of sixteen 22.5-degree sectors at the site boundary and maximum individual receptors.
8.1.1.2 For an elevated release, (i.e.; occurring at a height that is twice the height or more of a nearby structure) credit was taken for the effective release height which is comprised of the physical release height plus momentum plume rise minus the terrain height at a given receptor.
8.1.1.3 A building wake correction factor was used to adjust calculations for ground-level releases.
8.1.1.4 Airflow reversals were also accounted for by applying site-specific terrain recirculation factors for both ground and elevated releases at the site.(3.' "
8.1.1.5 The methodology employed in the calculation of intermittent release XtQ and D/Q values is that described in NUREG/CR-2919.( 3'2 8.1.2 The site continuous gaseous release points that have been evaluated include the following:
8.1.2.1 PV-1/2: The Unit 1/2 Gaseous Waste/Process Vent attached to the Unit 1 natural draft cooling tower 8.1.2.2 CV-1 and CV-2: The Unit 1 Rx ContainmenttSLCRS Vented the Unit 2 SLCRS Filtered Pathway 8.1.2.3 VV-1 and VV-2: The Unit 1 Ventilation Vent and the Unit 2 SLCRS Unfiltered Pathway 8.1.2.4 TV-2: The Unit 2 Turbine Building Vent 8.1.2.5 CB-2: The Unit 2 Condensate Polishing Building Vent 8.1.2.6 DV-2: The Unit 2 Decontamination Building Vent 8.1.2.7 WV-2: The Unit 2 Gaseous Waste Storage Tank Vault Vent 8.1.3 The intermittent releases are from PV-1/2, VV-1, VV-2, CV-1 and CV-2.
I I
1rtf*
ODCM: Dispersion Calculational Procedure and Source 8.1.4 Only PV-1/2 was considered to be an elevated release with all other release points being treated as ground level releases. A summary of the release characteristics and their locations is given in ATTACHMENT A.
8.1.5 Onsite meteorological data for the period January 1, 1976 through December 31, 1980 were used as input for the annual-average calculations.
8.1.5.1 The grazing season was represented by a six-month period from May 1 through October 31 for each year of the 5-year meteorological data base. This grazing season corresponds reasonably well with the growing season.
8.1.5.2 The data were collected according to guidance in NRC RG-1.23-3 - as described in Section 2.3 of the BVPS-2 FSAR.
8.1.5.3 The parameters used in the X/Q and DIQ calculations consist of wind speed, wind direction, and AT as an indicator of atmospheric stability. The lower level winds (35 ft) and AT (150-35 ft) were used for all release points except the Process Vent which required the use of 500 ft winds and AT (500-35 ft) which are representative of the release height (510 ft).
8.1.6 The annual average and grazing season X/Q and D/Q values for the continuous and intermittent radioactive releases were calculated at the site boundary, nearest resident, nearest vegetable garden, nearest milk cow, nearest milk goat, and nearest meat animal.
8.1.6.1 In the case of the Process Vent releases, several of each receptor type were evaluated in each downwind sector to determine the maximum X/Q and D/Q values.
8.1.6.2 The distances of the limiting maximum individual receptors from the radioactive release points are given in ATTACHMENT E (Table 2.2-3) of 1/2-ODC-2.02.
8.1.6.3 The continuous release annual average XIQ values at the special locations for the Containment Vents, Ventilation Vents, Process Vent, Turbine Building Vents, Decontamination Building Vent, Waste Gas Storage Vault Vent, and Condensate Polishing Building Vent are given in ATTACHMENT F (Tables 2.2-4 through 2.2-10) of 1/2-ODC-2.02. Continuous release annual average X/Q's for these same release points are also given at ten incremental downwind distances of 0-5 miles.
8.1.6.4 Continuous release D/Q values for these same release points are given in ATTACHMENT K (Tables 2.3-21 through 2.3-27) of 1/2-ODC-2.02 for the same 0-5 mile incremental distances, and in ATTACHMENT L (Tables 2.3-28 through 2.3-34) of 1/2-ODC-2.02 for the special locations.
8.1.6.5 Due to their location adjacent to the Containment Building, the Decontamination Building and Gaseous Waste Storage Tank Vault X/Q's and D/Q's are the same as the Containment Vent X/Q's and D/Q's.
Ad
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Beaver Valley Power Station 1e2-ODC-3.01
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12 8.1.6.6 Likewise, the Turbine Building Vent X/Q's and DIQ's apply to the Condensate Polishing Building as well due to its location adjacent to the Turbine Building.
8.1.7 ATTACHMENT M (Tables 2.3-35 through 2.3-38) of 1/2-ODC-2.02 contain short term XIQ values for batch releases originating from the Containment Vent, Ventilation Vent, and Process Vent releases respectively. -
8.1.7.1 The values in these tables are based on 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> per year of Containment and Ventilation Vent purges and 74 hours8.564815e-4 days <br />0.0206 hours <br />1.223545e-4 weeks <br />2.8157e-5 months <br /> per year of Process Vent purges.
8.2 Summary of Source Term Inputs 8.2.1 Liquid Source Term Inputs 8.2.1.1 Inputs to the NRC Gale Code used for generation of BV-1 Liquid Source Term Mixes are shown in ATTACHMENT B (Table B:la).
8.2.1.2 Inputs to the SWEC LIQ1BB Code used for generation of BV-2 Liquid Source Tern Mixes are shown in ATTACHMENT B (Table B:lb) 8.2.2 Gaseous Source Tern Inputs 8.2.2.1 Inputs to the SWEC GAS1BB Code for generation of BV-1 Gaseous Source Term Mixes are shown in ATTACHMENT C (Table B:2a) 8.2.2.2 Inputs to the SWEC GAS1BB Code for generation of BV-2 Gaseous Source Term Mixes are shown in ATTACHMENT C (Table B:2b)
Beaver Valley Power Station 1/2-.ODC-N3.01
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Page Number ATTACHMENT A Page 1 of 1 BV-1 AND 2 RELEASE CONDITIONS TABLEA.1 VV-1 CV-1 RX PV-1/2 GASEOUS TV-2 TURBINE VENTILATION CONTAINMENT/
WASTE/PROCESS BUILDING VENT VENT (PAB SLCRS VENT VENT EXHAUST)
VV-2 SLCRS CV-2 RX UNFILTERED CON'TAINMENT/
PATHWAY SLCRS FILTERED PATHWAY TYPE OF RELEASE GROUND LEVEL GROUND LEVEL ELEVATED GROUND LEVEL LngTermAnd LongTennAnd LongTennAnd LongTeamAnd ShortTein ShottTenn ShctTcam ShottTemn Release Point Height 26 47 155 33 (m)
AcjntBuillng 19 44 155 33 Hzight (M)
ReladveLocationTo ESideOfPnmary TopCenterOf AtopCoolingTow TlbineBuding AcjajantShu-ties AuxiiaiyBldg ContahntDoen ExitVelocity(m/sec)
NA NA 9A NA IntenalStack NA NA 025 NA Dianm (m)
BulkingCko 1600 1600 NA NA Siechonal Area (m2)
RAWFiequeny*
32 32 74 NA RaReDuaftion 8
8 NA NA
- peaSe) o~p dShoitThm calculations only
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9o 12 ATFACHMENT B Page 1 of 1 LIQUID SOURCE TERM INPUTS TABLE B: la INPUTS TO GALE CODE FOR GENERATION OF BV-1 LIQUID SOURCE TERM MIXES BV-I PWR INPUTS VALUE Thermal Power Level (megawatts)
Plant Capacity Factor Mass Of Primary Coolant (thousand Ibs)
Percent Fuel With Cladding Defects Primary System Letdown Rate (gpm)
Letdown Cation Demineralizer Flow Number Of Steam Generators Total Steam Flow (million lbs/br)
Mass Of Steam In Each Steam Generator (thousand Ibs)
Mass Of Liquid In Each Steam Generator (thousand lbs)
Total Mass Of Secondary Coolant (thousand Ibs)
Mass Of Water In Steam Generator (thousand Ibs)
Blowdown Rate (thousand lbs/hr)
Primary To Secondary Leak Rate (lbs/day)
Fission Product Carry-Over Fraction Halogen Carry-Over Fraction Condensate Demineralizer Flow Fraction Radwaste Dilution Flow (thousand gpm) 2766.000
.800 345.000
.120 60.000 6.000 3.000 11.620 6.772 97.000 1296.000 291.000 33.900 100.000
.001
.010 0.000 22.500 I
BV-I LIQUID WASTE INPUTS COLLECTION DELAY DECONTAMINATION FLOW RATE FRACTION FRACTION TIME TIME FACTORS STREAM (gal/day)
OF PCA DISCHARGE (days)
(days)
I Cs OTHERS Shim Bleed Rate Equipment Drains 1.32E4 6.00E2 1.000 1.000 1.000 0.000 0.000 1.000 11.260 7.220 1E7 1E7 1E7 11.260 7.220 1E7 1E7 1E7 Clean Waste 7.50E1 Input 0.071 0.648 lE5 2E4 IE5 Dirty Waste Input 1.35E3 0.035 1.000 0.071 0.071 0.648 lE5 2E4 IE5 0.648 lE5 2E4 IE5 Blowdown 9.75E4 1.000 Untreated Blowdown 0.0
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Page Number 010 of 12 ATTACHMAENT B Page 2 of 2 LIQUID SOURCE TERM INPUTS TABLE B:lb INPUTS TO SWEC LIQ1BB CODE FOR GENERATION OF BV-2 LIQUID SOURCE TERM MIXES BV-2 PWR INPUTS VALUE Thermal Power Level (megawatts) 2766.000 Plant Capacity Factor
.800 Mass Of Primary Coolant (thousand Ibs) 385.000 Percent Fuel With Cladding Defects
.120 Primary System Letdown Rate (gpm) 57.000 Letdown Cation Demineralizer Flow 5.700 Number Of Steam Generators 3.000 Total Steam Flow (million lbs/hr) 11.600 Mass Of Steam In Each Steam Generator (thousand Ibs) 8.700 Mass Of Liquid In Each Steam Generator (thousand lbs) 100.000 Total Mass Of Secondary Coolant (thousand Ibs) 2000.000 Mass Of Water In Steam Generator (thousand Ibs) 298.000 Blowdown Rate (thousand lbslhr) 22.300 Primary To Secondary Leak Rate (lbs/day) 100.000 Fission Product Carry-Over Fraction
.001 Halogen Carry-Over Fraction
.010 Condensate Demineralizer Flow Fraction
.700 Radwaste Dilution Flow (thousand gpm) 7.800 BV-2 LIQUID WASTE INPUTS COLLECTION DELAY DECONTAMINATION FLOW RATE FRACTION FRACTION TIME TIME FACTORS STREAM (gal/day)
OF PCA DISCHARGE (hrs)
(hrs)
I CsRb OTHERS Containment 40 1.000 1.0 35.5 6.2 1E3 IE4 1E4 Sump Auxiliary 200 0.100 1.0 35.5 6.2 1E3 1E4 1E4 Building Sump Miscellaneous 700 0.010 1.0 35.5 6.2 1E3 1E4 1E4 Sources Rx Plant 35 1.000 1.0 35.5 6.2 1E3 1E4 IE4 Samples Lab Drains 400 0.002 1.0 35.5 6.2 IE3 1E4 IE4 Cond. Demin.
2685 1.1E4 1.0 35.5 6.2 1E3 1E4 1E4 Rinse Water CVCS 60 1.0 1300 173 1E4 4E3 IE5 Turbine
.7200 1.0 Bldg.Drains
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0 11 of 1 A1TACHMENT C Page 1 of 1 GASEOUS SOURCE TERM INPUTS TABLE B:2a INPUTS TO SWEC GASIBB CODE FOR GENERATION OF BV-I GASEOUS SOURCE TERM MIXES BV-1 PWR INPUTS Thermal Power Level (megawatts)
Plant Capacity Factor Mass Of Primary Coolant (thousand Ibs)
Percent Fuel With Cladding Defects Primary System Letdown Rate (gpm)
Letdown Cation Demineralizer Flow Number Of Steam Generators Total Steam Flow (million lbs/hr)
Mass Of Steam In Each Steam Generator (thousand Ibs)
Mass Of Liquid In Each Steam Generator (thousand Ibs)
Total Mass Of Secondary Coolant (thousand Ibs)
Mass Of Water In Steam Generator (thousand Ibs)
Blowdown Rate (thousand lbs/hr)
Primary To Secondary Leak Rate (lbs/day)
Fission Product Carry-Over Fraction Halogen Carry-Over Fraction Condensate Demineralizer Flow Fraction Radwaste Dilution Flow (thousand gpm)
VALUE 2766.000
.800 385.000
.120 57.000 5.700 3.000 11.600 8.700 100.000 2000.000 298.000 52.000 100.000
.001
' 010 0.000 15.000 BY-I GASEOUS WASTE INPUTS There Is Not Continuous Stripping Of Full Letdown Flow Hold Up Time For Xenon (days)
Hold Up Time For Krypton (days)
Primary Coolant Leak To Auxiliary Building (lb/day)
Auxiliary Building Leak Iodine Partition Factor Gas Waste System Particulate Release Fraction Auxiliary Building Charcoiodine Release Fraction Auxiliary Building Particulate Release Fraction Containment Volume (million cu-ft)
Frequency Of Primary Coolant Degassing (times/yr)
Primary To Secondary Leak Rate (lb/day)
There Is A Kidney Filter Containment Atmosphere Cleanup Rate (thousand cfm)
Purge Time Of Containment (hours)
There Is Not A Condensate Demineralizer VALUE 39.000 2.000 160.000 7.5E-3 0.000 1.000 1.000 1.800 2.000 100.000 2.000 8.000 Iodine Partition Factor (gas/liq) In Steam Generator Frequency Of Containment Building High Vol Purge (timeslyr)*
Containment Volume Purge Iodine Release Fraction Containment Volume Purge Particulate Release Fraction Steam Leak To Turbine Building (lbs/hr)
Fraction Iodine Released From Blowdown Tank Vent Fraction Iodine Released From Main Condensate Air Ejector There Is Not A Cryogenic Off Gas System 0.010 4.000 1.000 1.000 1700.000 0.000 0.440
- 2 cold and 2 hot purges
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0 I 12of 12 ATTACMENT C Page 2 of 2 GASEOUS SOURCE TERM INPUTS TABLE B:2b INPUTS TO SWEC GASIBB CODE FOR GENERATION OF BV-2 GASEOUS SOURCE TERM MIXES BV-2 PWR INPUTS VALUE Thermal Power Level (megawatts) 2766.000 Plant Capacity Factor
.800 Mass Of Primary Coolant (thousand Ibs) 385.000 Percent Fuel With Cladding Defects
.120 Primary System Letdown Rate (gpm) 57.000 Letdown Cation Demineralizer Flow 5.700 Number Of Steam Generators 3.000 Total Steam Flow (million lbslhr) 11.600 Mass Of Steam In Each Steam Generator (thousand Ibs) 8.700 Mass Of Liquid In Each Steam Generator (thousand Ibs) 100.000 Total Mass Of Secondary Coolant (thousand Ibs) 2000.000 Mass Of Water In Steam Generator (thousand Ibs) 298.000 Blowdown Rate (thousand lbslhr) 22.300 Primary To Secondary Leak Rate (lbs/day) 100.000 Fission Product Carry-Over Fraction
.001 Halogen Carry-Over Fraction
.010 Condensate Demineralizer Flow Fraction
.700 Radwaste Dilution Flow (thousand gpm) 7.800 BV-2 GASEOUS WASTE INPUTS VALUE There Is Not Continuous Stripping Of Full Letdown Flow Hold Up Time For Xenon (days) 45.800 Hold Up Time For Krypton (days) 2.570 Primary Coolant Leak To Auxiliary Building (lb/day) 160.000 Auxiliary Building Leak Iodine Partition Factor 7.5E-3 Gas Waste System Particulate Release Fraction 0.000 Auxiliary Building Charcoiodine Release Fraction 0.100 Auxiliary Building Particulate Release Fraction 0.010 Containment Volume (million cu-ft) 1.800 Frequency Of Primary Coolant Degassing (timeslyr) 2.000 Primary To Secondary Leak Rate (lb/day) 100.000 There Is A Kidney Filter Containment Atmosphere Cleanup Rate (thousand cfm) 20.000 Purge Time Of Containment (hours) 8.000 There Is Not A Condensate Demineralizer Iodine Partition Factor (gas/liq) In Steam Generator 0.010 Frequency Of Containment Building High Vol Purge (times/yr)*
4.000 Containment Volume Purge Iodine Release Fraction 1.000 Containment Volume Purge Particulate Release Fraction 1.000 Steam Leak To Turbine Building (lbs/hr) 1700.000 Fraction Iodine Released From Blowdown Tank Vent 0.000 Fraction Iodine Released From Main Condensate Air Ejector 0.270 There Is Not A Cryogenic Off Gas System
- 2 cold and 2 hot purges
New: 1/2-ODC-3.02 Old: APPENDIX D
A9.621B Beaver Valley Power Station Unit 1/2 1/2-ODC-3.02 ODCM: Bases For ODCM Controls Document Owner Manager, Radiation Protection a,
Revision Number 1
Level Of Use General Skill Reference Safety Related Procedure Yes
Beaver Valley Power Station Pzcu Nume 3o Tizfe Unit Leve Of Use ODCM: Bases For ODCM Controls 1/2 General Skill Reference Revision:
Page Number 1
2 of 13 TABLE OF CONTENTS 1.0 PURPOSE.......................................................................
3 2.0 SCOPE.......................................................................
3
3.0 REFERENCES
AND COMMITMENTS.......................................................................
3 3.1 References.......................................................................
3 3.2 Commitments.......................................................................
4 4.0 RECORDS AND FORMS.......................................................................
4 4.1 Records.........
4 4.2 Forms.........
4 5.0 PRECAUTIONS AND LLI[MTATIONS..........................................................................................5 6.0 ACCEPTANCE CRITERIA.......................................................................
5 7.0 PREREQUISITES.............................................................................................................................5 8.0 PROCEDURE.......................................................................
5 ATTACHMENT A BASES FOR ODCM CONTROLS: INSTRUMENTATION...............................
6 ATTACHEMENT B BASES FOR ODCM CONTROLS: LIQUID EFFLUENTS................................
7 ATTACHMENT C BASES FOR ODCM CONTROLS: GASEOUS EFFLUENTS...........................
9 ATTACHMENT D BASES FOR ODCM CONTROLS: TOTAL DOSE 12 ATTACHMENT E BASES FOR ODCM CONTROLS: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)......................................................................
13
Procedure Number:
Beaver Valley Power Station 1/2-ODC-3.02 rlu.e Unit Level Of Use:
ODCM: Bases For ODCM Controls 1/2 General Skill Reference Revision:
Page Number:
3 of 1 1.0 PURPOSE 1.1 This procedure contains the Bases for the ODCM Controls that were transferred from the Bases Section of the Technical Specification per Unit 1/2 Amendments IA-188/2A-70, and in accordance with Generic Letter 89-01 and NUREG-1301 (Generic Letter 89-01, Supplement No. 1).
3.2.10) 1.1.1 Prior to issuance of this procedure, these items were located in Appendix D of the old ODCM.
1.2 This procedure also contains the Bases for the ODCM Controls (for Radiation Monitoring Instrumentation) that were duplicated from the Bases Section of the Technical Specification per Unit 1/2 Amendments IA-246/2A-124, and in accordance with NUREG-143 1. (3. 1.3"-t) 1.3 This procedure also contains the Bases for the ODCM Controls (for Liquid Holdup Tank Activity Limits and for Gas Decay/Storage Tank Activity Limits) that were transferred from the Bases Section of the Technical Specification per Unit 1/2 Amendments lA-250/2A-130, and in accordance with NUREG-1431.(l" 3 2-1 2.0 SCOPE I
2.1 This procedure is applicable to all station personnel that are qualified to perform activities as described and referenced in this procedure.
3.0 REFERENCES
AND COMMITMENTS 3.1 References 3.1.1 1/2-ODC-2.01, ODCM: liquid Effluents 3.1.2 1/2-ODC-2.02, ODCM: Gaseous Effluents 3.1.3 1/2-ODC-3.03, ODCM: Controls for RETS and REMP Programs 3.1.4 1/2-ADM-1640, Control of the Offsite Dose Calculation Manual 3.1.5 Unit 1/2 Technical Specification 6.8.6, including Amendments IA-188/2A-70 (LAR IA-175/2A-37), Implemented August 7, 1995 3.1.6 Unit 1/2 Technical Specification 3.3.3.1, including Amendments IA-246/2A-124 (LAR IA-287/2A-159), Implemented April 11, 2002 3.1.7 Unit 1/2 Technical Specifications 3.11.1.4, 3.11.2.5 and 6.8.6, including Amendments IA-250/2A-130 (LAR IA-291/2A-163), Implemented August 7,2002 3.1.8 1/2-ADM-0100, Procedure Writer's Guide 3.1.9 1/2-ADM-0101, Review and Approval of Documents
Procedure Numbect Beaver Valley Power Station 1/2-ODC-3.02 I
- ftte Unic Lcvct Of Us:
ODCM: Bases For ODCM Controls 1/2 General Skifen Revisilon:
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4 4of 13 3.2 Commitments 3.2.1 10 CFR Part 20 3.2.2 10 CFR Part 50 3.2.3 40 CFR Part 141 3.2.4 40 CFR Part 190 3.2.5 Regulatory Guide 1.109, Calculation Of Annual Doses To Man From Routine Releases Of Reactor Effluents For The Purpose Of Evaluating Compliance With 10 CFR Part 50, Appendix I, Revision 1, October, 1977 3.2.6 Regulatory Guide 1.111, Methods For Estimating Atmospheric Transport And Dispersion of Gaseous Effluents In Routine Releases From Light-Water-Cooled Reactors, Revision 1, July, 1977 3.2.7 Regulatory Guide 1.113, Estimating Aquatic Dispersion Of Effluents From Accidental And Routine Reactor Releases For The Purpose Of Implementing Appendix L April, 1977 3.2.8 NUREG-0133, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, October 1978 3.2.9 NUREG-0737, Clarification of TMI Action Plan Requirements, October, 1980 3.2.10 NUREG-1301, Offsite Dose Calculation Manual Guidance. Standard Radiological Effluent Controls For Pressurized Water Reactors (Generic Letter 89-01, Supplement No. 1) 3.2.11 NUREG-1431, StandardTechnical Specifications - Westinghouse Plants Specifications 4.0 RECORDS AND FORMS 4.1 Records 4.1.1 Any calculation supporting ODCM changes shall be documented, as appropriate, by a retrievable document (eg; letter or calculation package) with an appropriate RTL number.
4.2 Forms 4.2.1 None
Pocedure Number:
Beaver Valey Power Station 112-ODC-3.02 lwltle:
Unit:
Level Of Use ODCM: Bases For ODCM Controls 1/2 General Skill Reference Revisioa:
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15 of 13 5.0 PRECAUTIONS AND LHMITATIONS 5.1 The numbering of each specific ODCM Bases contained in this procedure does not appear to be sequential. This is intentional, as all ODCM Bases numbers remained the same when they were transferred from the Technical Specifications. This was done in an effort to minimize the amount of plant procedure changes and to eliminate any confusion associated with numbering changes.
6.0 ACCEPTANCE CRITERIA 6.1 Any change to this procedure shall contain sufficient justification that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appenidx I to 10 CFR 50, and not adversely impact the accuracy or reliability of effluent dose or setpoint calculation.(3.2 0 6.1.1 All changes to this procedure shall be prepared in accordance with 1/2-ADM-O100&3 '
and 1/2-ADM-1640.( 1A) 6.1.2 All changes to this procedure shall be reviewed and approved in accordance with 1/2-ADM-0101(3 l9) and 112-ADM-1640.(3 4) 7.0 PREREOUISITES 7.1 The user of this procedure shall be familiar with ODCM structure and content.
8.0 PROCEDURE 8.1 See ATTACHMENT A for a complete description of Bases for ODCM Controls associated with Instrumentation.
8.2 See ATTACHMENT B for a complete description of Bases for ODCM Controls associated with Liquid Effluents.
8.3 See ATTACHMENT C for a complete description of Bases for ODCM Controls associated with Gaseous Effluents.
8.4 See ATTACHMENT D for a complete description of Bases for ODCM Controls associated with Total Dose.
8.5 See ATTACHMENT E for a complete description of Bases for ODCM Controls associated with the Radiological Environmental Monitoring Program (REMP).
Procedwe Nuimber Beaver Valley Power Station 112-ODC-3.02 Tunit Lev1 of use:
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-I6of ATTACHNT A Page 1 of 1 BASES FOR ODCM CONTROLS: INSTRUMENTATION 3/4.3.3.1 RADIATIONMONr RING INSTRUMFNTATION The OPERABILITY of the radiation monitoring channels ensures that: 1) the radiation levels are continually measured in the areas served by the individual channels; 2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded; and 3) sufficient information is available on selected plant parameters to monitor and assess these variables following an accident. This capability is consistent with the recommendations of NUREG-0737.t3-9 )
3/4.3.3.9 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm/trip setpoints for these instruments shall be calculated in accordance with Section 1 of this manual to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60,63, and 64 of Appendix A to 10 CFR Part 50.t3 l 3.2.2) 3/4.3.3.10 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm/trip setpoints for these instruments shall be calculated in accordance with Section 2 of this manual to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. This instrumentation also includes provisions for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the waste gas holdup system.
The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.(3 1 3-2-2)
Procedure Number~
Beaver Valley Power Station 1/2-ODC-3.02 imtle:
uni Level Of Use:
ODCM: Bases For ODCM Controls, 1/2 General Skill Reference Revision:
Page Number l
7 of 13 ATTACHMENT B Page 1 of 2 BASES FOR ODCM CONTROLS: LIQUID EFFLUENTS 3/4.11.1.1 LIQUID EFFLUENT CONCENTRATION This CONTROL is provided to ensure that the concentration of radioactive materials released in Liquid waste effluents from the site to unrestricted areas will be less than 10 times the ECs specified in 10 CFR Part 20, Appendix B (20.1001-20-2401), Table 2, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposure within (1) the Section IMA design objectives of Appendix I, 10 CFR Part 50, to an individual and (2) the limits of 10 CFR Part 20.1302 to the population. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.(3 2.1322) 3/4.11.1.2 LIQUID EFFLUENT DOSE This CONTROL is provided to implement the requirements of Sections ll.A, UI.A, and MV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section Ml.A of Appendix I. The ACIMON statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable." Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141. The dose calculations in the procedure 1/2-ODC-2.01 implement the requirements in Section UI.A of Appendix I that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in procedurel/2-ODC-2.01 for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, and Regulatory Guide 1.113. NUREG-0 133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.1 13.(3-'" 31.2.2.3.2.3.3.M2.53+/-7.
3.2.8)
This CONTROL applies to the release of liquid effluents for Beaver Valley Power Station, Unit No. 1 or Unit No. 2. These units have shared radwaste treatment systems.
the liquid effluents from the shared system are proportioned among the units sharing that system.
Beaver Valley Power Station Pocdu 12-ODC-3.02 fcUnit Lvel Of Use:
ODCM: Bases For ODCM Controls 1
G2 eGneral Skill Reference Revision:
Page Number 1
1 Rofl 3 ATTACHMENT B Page 2 of 2 BASES FOR ODCM CONTROLS: LIQUID EFFLUENTS 3/4.11.1.3 LIOUID WASTE TREATMENT SYSTEM The CONTROL that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept 'as low as is reasonably achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and design objective given in Section Ml.D of Appendix I to 10 CFR Part
- 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section IIA of Appendix 1, 10 CFR Part 50, for liquid effluents. This specification applies to Beaver Valley Power Station, Unit No. 1 or Unit No. 2.02 3/4.11.1.4 LIOUID HOLDUP TANKS Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks'contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B, Table 2, Column 2, at the nearest potable water supply and the nearest surface water supply in an unrestricted area.
Power Station Procedure Number:
Beaver Valley P..ower Station12-ODC-3.02 rimtl Unit Level Of Use:
ODCM: Bases For ODCM Controls 1/2 General Skill Reference Revision:
Page Number 1
9 of VA ATTACHMENT C Page 1 of 3 BASES FOR ODCM CONTROLS: GASEOUS EFFLUENTS 3/4.11.2.1 GASEOUS EFFLUENT DOSE RATE This CONTROL is provided to ensure that the dose at anytime at the site boundary from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an unrestricted area, either within or outside the site boundary, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)). For individuals who may at times be within the site boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the site boundary. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the site boundary to < 500 mrem/year to the total body or to
< 3,000 nirem/year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background of a child via the inhalation pathway to < 1,500 mrem/year. (3 l) 3/4.11.2.2 DOSE. NOBLE GASES This CONTROL is provided to implement the requirements of Sections ILB, M.A, and IV.A of Appendix L 10 CFR Part 50. The CONTROL implements the guides set forth in Section Il.B of Appendix L. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the release of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section L.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated. The dose calculations established in procedure 1/2-ODC-2.02 for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, and Regulatory Guide 1.111. The equations in procedure 1/2-ODC-2.02 are provided for determining the air doses at the exclusion area boundary, and are based upon the historical average atmospheric conditions. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.1 11. This specifications applies to the release of gaseous effluents from Beaver Valley Power Station, Unit No. 1 or Unit No. 2.1.2, 3.2.2.3.25.3.2.6.3.2.8)
Beavr ValeyPowe StaionProcedure Numbcr.
Beaver Valley Power Statin1/2-ODC-3.02
Title:
Unit:
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__I 1
0 Hof 13 ATTACHMENT C Page 2 of 3 BASES FOR ODCM CONTROLS: GASEOUS EFFLUENTS 3/4.11.2.3 DOSE. RADIOIODINES. RADIOACTIVE MATERIAL IN PARTICULATE FORM AND RADIONUCLIDES OTHER THAN NOBLE GASES This CONTROL is provided to implement the requirements of Sections ILC, lIl.A, and IV.A of Appendix I, 10 CFR Part 50. The CONTROLS are the guides set forth in Section Il.C of Appendix I.322)
The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." The calculational methods specified in the surveillance requirements implement the requirements in Section DILA of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The calculational methods in procedure 1/2-ODC-2.02 are for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, and Regulatory Guide 1.111. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for radioiodines, radioactive material in particulate form, and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathways which are examined in the development of these calculations are: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man. This CONTROL applies to radioactive material in particulate form and radionuclides other than noble gases released from Beaver Valley Power Station, Unit No. 1 or Unit No.2.(3 1.2 3-2-2
-2.S6.
317)
Proceduze Number~
Beaver Valley Power Station N
112-ODC-3.02 Titma Unit Level Of Use:
ODCM: Bases For ODCM Controls 1/2 General Skill Reference Revision:
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I 11 Of 13 ATTACHMENT C Page 3 of 3 BASES FOR ODCM CONTROLS: GASEOUS EFFLUENTS 3/4.11.2.4 GASEOUS RADWASTE TREATMENT SYSTEM The CONTROL that the appropriate portions of these systems be used when specified provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR'Part 50, and design objective Section I.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections IU.B and l.C of Appendix I, 10 CFR Part 50, for gaseous effluents. This specification applies to gaseous radwaste from Beaver Valley Power Station, Unit No. 1 or Unit No. 2 (3 *2, 3.2.2) 3/4.11.2.5 BV-I GASEOUS WASTE STORAGE TANKS Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting total body exposure to an individual located at the nearest exclusion area boundary for two hours immediately following the onset of the release will not exceed 0.5 rem. The specified limit restricting the quantity of radioactivity contained in each gas storage tank was specified to ensure that the total body exposure resulting from the postulated release remained a suitable fraction of the reference value set forth in 10 CFR 100.11 (a)(1).
3/4.11.2.5 BV-2 GASEOUS WASTE STORAGE TANKS Restricting the quantity of radioactivity contained in any connected group of gaseous waste storage tanks provides assurance that in the event of an uncontrolled release of the tanks'contents, the resulting total body exposure to an individual located at the nearest exclusion area boundary for two hours immediately following the onset of the release will not exceed 0.5 rem. The specified limit restricting the quantity of radioactivity contained in any connected group of gaseous waste storage tanks was specified to ensure that the total body exposure resulting from the postulated release remained a suitable fraction of the reference value set forth in 10 CFR 100.11 (a)(1). The curie content limit is applied individually to each gaseous waste storage tank and collectively to the number of unisolated gaseous waste storage tanks.
Beaver Valley Power Station edu
'2-ODC-3.02 Tifte:
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ODCM: Bases For ODCM Controls 1/2 General Skill Reference Revision:
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1 12 of l1i ATTACHMENT D Page 1 of I BASES FOR ODCM CONTROLS: TOTAL DOSE 3/4.11.4 TOTAL DOSE This CONTROL is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525. The CONTROL requires the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. For sites containing up to 4 reactors, it is highly unlikley that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the units (including outside storages tanks, etc.) are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 5 miles must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.405c, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in ODCM CONTROL 3.11.1.1 and 3.11.2.1. An individual is not considered a MEMBER OF THE PUBLIC during any period in which helshe is engaged in carrying out any operation that is part of the nuclear fuel cycle.' 3 3 3.2.2.3.2.4)
Procedure Number.
Beaver Valley Power Station 1/2-ODC-3.02 itle:
Unit:
Level Of Use:
ODCM: Bases For ODCM Controls 1/2 General Skdil Reference Revision.
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__.13 of 13 ATTACHMENT E Page 1 of 1 BASES FOR ODCM CONTROLS: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 3/4.12.1 MONITORING PROGRAM The radiological monitoring program required by this CONTROL provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides Which lead to the highest potential radiation exposures of MEMBER(S) OF THE PUBLIC resulting from the station operation. This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. The initially specified monitoring program will be effective for at least the first 3 years of commercial operation. Following this period, program changes may be initiated based on operational experience.
The detection capabilities required by ODCM Control 3.12.1, Table 4.12-1 are state-of-the-art for routine environmental measurements in industrial laboratories. The LLD's for drinking water meet the requirements of 40 CFR 14 1.(3 3.2.3) 3/4.12.2 LAND USE CENSUS ODCM CONTROL 3.12.2 is provided to ensure that changes in the use of unrestricted areas are identified and that modifications to the monitoring programs are made if required by the results of this census. The best survey information from the door-to-door survey, aerial survey, or by consulting with local agriculture authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than 500 square feet provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were used: 1) that 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/square meter. 3 313.3.2.2) 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM The ODCM CONTROL 3.12.3 for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of a quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.(31 l3)
New: 1/2-ODC-3.03 Old: APPENDIX C & E
RTL #A9.621B Beaver Valley Power Station Unit 1/2 1/2-ODC-3.03 ODCM: Controls for RETS and REMP Programs Document Owner Manager, Radiation Protection Revision Number 2
Level Of Use General Skill Reference Safety Related Procedure Yes
Beaver Valley Power Station 1redDCNum.
Title Unit Livel Of Us 1/2 General SkIll Reference ODCM: Controls for RETS and REMP Programs Revisiown.
Page Nmber 2
2of75 TABLE OF CONTENTS 1.0 PURPOSE.
3 2.0 SCOPE.
3
3.0 REFERENCES
AND COM l
ENTS.................................................................
3 3.1 References.
3 3.2 Commitments.
4 4.0 RECORDS AND FORMS..................................................................
5 4.1 Records.
5 4.2 Forms.
5 5.0 PRECAUTIONS AND LIMITATIONS..................................................................
5 6.0 ACCEPTANCE CRITERIA..................................................................
6 7.0 PREREQUISITES..................................................................
6 8.0 PROCEDURE..................................................................
6 ATTACHMENT A ODCM CONTROLS: OPERATIONAL MODES AND FREQUENCY NOTATION 7
ATTACHMENT B ODCM CONTROLS: DEFIRTONS..............................................................
9 ATTACHMENT C ODCM CONTROLS: APPLICABlIlTY AND SURVEILLANCE REQUIREMENTS................................................................. 12 A 'V'-
A
.YF AI 1 AlIVfli'=4 I I)
ATTACHMENT E EFFLUENTS ATTACHMENT F AT`TACHMENT G ATTACHMENT H ATTACHMENT I ATTACHM1NT J ATTACHMENT K ATTACHMENT L ATTACHMENT M ATTACHMENT N ATTACHMENT 0 ATTACHMENT P ATTACHMENT Q ATTACHMENT R ATTACHMENT S PROGRAM ATTACHMENT T ATTACHMEENT U uvDCM CONTROLS: RADIATION MONITORING INSTRUMENTATION.1; ODCM CONTROLS: RETS INSTRUMENTATION FOR LIQUID OD.M CONTROLS:
ODCM CONTROLS:
ODCM CONTROLS:
ODCM CONTROLS:
ODCM CONTROLS:
ODCM CONTROLS:
ODCM CONTROLS:
ODCM CONTROLS:
ODCM CONTROLS:
ODCM CONTROLS:
ODCM CONTROLS:
ODCM CONTROLS:
ODCM CONTROLS:
ODCM CONTROLS:
........................................................................................... 4.............................
z RETS INSTRUMENT FOR GASEOUS RELEASES...32 LIQUID EFFLUENT CONCENTRATION.................... 45 LIQUID EFFLUENT DOSE.....................................
50 LIQUID RADWASTE TREATMENT SYSTEM.......... 51 LIQUID HOLDUP TANKS.....................................
52 GASEOUS EFFLUENT DOSE RATE........................... 53 DOSE-NOBLE GASES.....................................
57 DOSE - RADIOIODINES AND PARTICULATES....... 58 GASEOUS RADWASTE TREATMENT SYSTEM..... 59 GAS STORAGE TANKS.....................................
60 TOTAL DOSE.....................................
61 REMP-PROGRAM REQUIREMENTS......................... 62 REMP - LAND USE CENSUS..................................... 70 REMP - INTERLABORATORY COMPARISON i
4 I
I i
i I
1 1
4 4
1 i
i z
II I
I.
I i
i i
t
........................................................................................................................... 71 ODCM CONTROLS: ANNUAL REMP REPORT............................................ 72 ODCM CONTROLS: ANNUAL REIS REPORTS........................................... 74
e Vl P
e S
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12 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision:
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_3 of 75 1.0 PURPOSE 1.1 This procedure includes selected Definitions and Tables as delineated in Section 1 of the Technical Specifications and selected Applicability and Surveillance Requirement statements as delineated in Section 3/4 of the Technical Specifications.
1.1.1 Prior to issuance of this procedure, these items were located in Appendix C of the old ODCM, and were added to this procedure for reference purposes, even though they are currently described in the Technical Specifications.
1.2 This procedure contains the controls for the Radiological Effluent Technical Specification (RETS) that were transferred from the Technical Specifications per Unit 1/2 Amendments 1A-188/2A-70, and in accordance with Generic Letter 89-01 and NUREG-1301.(3 2 -0 )
1.2.1 Prior to issuance of this procedure, these items were located in Appendix C of the old ODCM.
1.3 This procedure contains the reporting requirements for the Annual Radioactive Effluent Release Report and the Annual Radiological Environmental Report that were transferred from the Technical Specifications per Unit 1/2 Amendments IA-188/2A-70 and in accordance with Generic Letter 89-01 and NUREG-1301. (3.2-10) 1.3.1 Prior to issuance of this procedure, these items were located in Appendix E of the old ODCM.
1.4 This procedure contains the controls for Radiation Monitoring Instrumentation that were transferred from the Technical Specification per Unit 1/2 Amendments 246/124, and in accordance with NUREG-1431. (3.2.11) 1.5 This procedure contains the controls for Liquid Holdup Tank Activity Limits and for Gas Decay/Storage Tank Activity Limits that were transferred from the Technical Specification per Unit 1/2 Amendment 250/130, and in accordance with NUREG-1431. 3" 6' 6211) 2.0 SCOPE 2.1 This procedure is applicable to all station personnel that are qualified to perform activities as described and referenced in this procedure.
3.0 REFERENCES
AND COMMITMENTS 3.1 References 3.1.1 1/2-ODC-2.01, ODCM: Liquid Effluents 3.1.2 1/2-ODC-2.02, ODCM: Gaseous Effluents 3.1.3 1/2-ODC-3.02, ODCM: Bases for ODCM Controls
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Pae Number 2 I 4of 75 3.1.4 Unit 1/2 Technical Specification 6.8.6, including Amendments IA-188/2A-70 (LAR IA-17512A-137) Implemented August 7, 1995.
3.1.5 Unit 1/2 Technical Specification 3.3.3.1, including Amendments 1A-246/2A-142 (LAR IA-287/2A-159) Implemented April 11, 2002 3.1.6 Unit 1/2 Technical Specification 3.11.1.4, 3.11.2.5, 6.8.6 and 6.9.3, including Amendments 1A-250/2A-130 (LAR 1A-291/2A-163) Implemented August 7,2002 3.1.7 112-ADM-1640, Control of the Offsite Dose Calculation Manual 3.1.8 1/2-ADM-0100, Procedure Writer's Guide 3.1.9 1/2-ADM-0101, Review and Approval of Documents 3.1.10 CR 981489, ODCM Table 4.11-2 Row A (Waste Gas Storage Tank Discharge). CA-001, Revise Appendix C of the ODCM (Table 4.11-2) to add clarification as to where and when tritium samples are to be obtained for GWST discharges.
3.1.11 CR 981490, ODCM Table 4.11-2 Note e, and Related Chemistry Department Procedures. CA-001, Revise Appendix C of the ODCM (Table 4.11-2, Note e) to specify the proper tritium sample point.
3.1.12 CR 993021, Apparent failure to test RM-IDA-100 trip function as required by ODCM.
No ODCM changes are required for this CR.
3.1.13 CR 001682, ODCM Action 28 Guidance. CA-002, Revise Appendix C of the ODCM (Table 3.3-13, Action 28) to differentiate actions associated with Inoperable Process Flow Rate Monitors vs. Sample Flow Rate Monitors.
3.1.14 CR 02-05711, TS and ODCM changes not reflected in 10M.54.3.L5 Surveillance Log.
CA-001, Revise 1/2-ODC-3.03 to add a requirement for applicable station groups notification of pending ODCM changes.
3.2 Commitments 3.2.1 10 CFR Part 20 3.2.2 10 CFR Part 50 3.2.3 40 CFR Part 141 3.2.4 40 CFR Part 190 3.2.5 Regulatory Guide 1.109, Calculation Of Annual Doses To Man From Routine Releases Of Reactor Effluents For The Purpose Of Evaluating Compliance With 10 CFR Part 50, Appendix I, Revision 1, October 1977
~Procedure Number.
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3.2.6 Regulatory Guide 1.111, Methods For Estimating Atmospheric Transport And Dispersion Of Gaseous Eflfuents In Routine Releases From light-Water-Cooled Reactors, Revision 1, July 1977 3.2.7 Regulatory Guide 1.113, Estimating Aquatic Dispersion Of Effluents From Accidental And Routine Reactor Releases For The Purpose Of Implementing Appendix I, April 1977 3.2.8 NUREG-0133, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, October 1978 3.2.9 NUREG-0737, Clarification of TMI Action Plan Requirements, October 1980 3.2.10 NUREG-1301, Offsite Dose Calculation Manual Guidance; Standard Radiological Effluent Controls For Pressurized Water Reactors (Generic Letter 89-01, Supplement No. 1) 3.2.11 NUREG-1431, Standard Technical Specifications - Westinghouse Plants Specifications 4.0 RECORDS AND FORMS 4.1 Records 4.1.1 Any calculation supporting ODCM changes shall be documented, as appropriate, by a retrievable document (e.g.; letter or calculation package) with an appropriate RTL number.
4.2 Forms 4.2.1 None 5.0 PRECAUTIONS AND LIMITATIONS 5.1 The numbering of each specific ODCM Control, ODCM Surveillance Requirement and ODCM Table contained in this procedure does not appear to be sequential. This is intentional, as all ODCM Control, ODCM Surveillance Requirement and ODCM Table numbers remained the same when they were transferred from the Technical Specifications.
This was done in an effort to minimize the amount of plant procedure changes and to eliminate any confusion associated with numbering changes.
5.2 The numbering of each specific ODCM Report contained in this procedure does not appear to be sequential. This is intentional, as all ODCM Report numbers remained the same when they were transferred from the Technical Specifications. This was done in an effort to minimize the amount of plant procedure changes and to eliminate any confusion associated with numbering changes.
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2 6 of 75 6.0 ACCEPTANCE CRITERIA 6.1 Any change to this procedure shall contain sufficient justification that the charge will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR 50, and not adversely impact the accuracy or reliability of effluent dose or setpoint calculation. (3,2,'0 6.1.1 All changes to this procedure shall be prepared in accordance with 1/2-ADM-0100(3"l and 1/2-ADM-1640. (3.1.7) 6.1.2 Pending changes to this procedure shall be provided to applicable station groups. For example, IF Control 3.11.1.1 is being changed, THEN the proposed changes shall be provided to the applicable station groups (i.e.; owner of the procedures), identified in the MATRIX of ODCM procedure 1/2-ODC-1.01. This will allow the station groups to revise any affected procedures concurrent with the ODCM change.(3 '143 6.1.3 All changes to this procedure shall be reviewed and approved in accordance with 1/2-ADM-0101(i"9) and 1/2-ADM-1640. (3.1.7) 7.0 PREREQUISITES 7.1 The user of this procedure shall be familiar with ODCM structure and content.
8.0 PROCEDURE 8.1 See AT1ACHNvENTA for a Table of Operational Modes and a Table of Frequency Notation.
8.2 See ATTAC HMENT B for a list of defined terms used throughout the ODCM.
8.3 See ATTACHMENT C thru ATTACHMENT S for a complete description of all ODCM Controls.
8.4 See ATTACHBMENT T for a description of the Annual Report required by the REMP Controls.
8.5 See AITACENhENT U for a description of the Annual Report required by the RETS Controls.
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7of 75 ATTACHMENT A Page 1 of 2 ODCM CONTROLS: OPERATIONAL MODES AND FREQUENCY NOTATION TABLE 1.1 OPERATIONAL MODES REACTlVITY CONDITION, Keff
% RATED THERMAL POWER"'l AVERAGE COOLANT TEMPERATURE MODE
- 1. Power Operation
- 2. Startup
- 3. Hot Standby
- 4. Hot Shutdown
- 5. Cold Shutdown
- 6. Refueling(2) 2.0.99 20.99
<0.99
<0.99
<0.99
<0.95
>5%
<5%
0 0
0 0
Ž3500F n3500F
Ž3500F 3500F >Tavg
>200T
- 200 0F
<1400F (1)
Excluding decay heat.
(2)
Reactor vessel head unbolted or removed and fuel in the vessel.
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Rof 75 ATTACHIENT A Page 2 of 2 ODCM CONTROLS: OPERATIONAL MODES AND FREQUENCY NOTATION TABLE 1.2 FREVUENCY NOTATION NOTATION FREQUENCY S
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> D
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> W
At least once per 7 days M
At least once per 31 days Q
At least once per 92 days SA At least once per 184 days R
At least once per 18 months StU Prior to each reactor startup P
Completed prior to each release N.A.
Not applicable
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2 9 of 75 ATTACHMENT B Page 1 of 3 ODCM CONTROLS: DEFINiTIONS The defined terms of this section appear in capitalized type and are applicable throughout these CONTROLS.
ACTION shall be those additional requirements specified as corollary statements to each principal CONTROL and shall be part of the CONTROLS.
CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated.
CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.
CHANNEL FUNCTIONAL TEST shall be the injection of a simulated signal into the channel as close to the primary sensor as practicable to verify OPERABILITY including alarm and/or trip functions.
FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.2.
GASEOUS RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.
MEMBER(S) OF THE PUBLIC (10 CFR 20) means any individual except when that individual is receiving an occupational dose. This definition Is used to showv compliance to an ODCM Appendix C CONTROL that is based on 10 CFR Part 20.
MEMBER(S) OF THE PUBLIC (40 CFR 190) means any individual that can receive a radiation dose in the general environment, whether he may or may not also be exposed to radiation in an occupation associated with a nuclear fuel cycle. However, an individual is not considered a MEMBER OF THE PUBLIC during any period in which he is engaged in carrying out any operation which is part of the nuclear fuel cycle. This definition is used to show compliance to an ODCM CONTROL 3.11A.1 that is based on 40 CFR Part 190.
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10n f 75 ATTACHMENT B Page 2 of 3 ODCM CONTROLS: DEFINITIONS OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Technical Specification (TS) Section 6.8.6 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports that are also required by the Administrative Controls Section of the TS OPERABLEJOPERAll3TY A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s). Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, normal and emergency electric power sources, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function(s) are also capable of performing their related safety function(s).
OPERATIONAL MODE shall correspond to any one inclusive combination of core reactivity condition power level, and average reactor coolant temperature specified in ATTACHMENT A Table 1.1.
PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating conditions, in such a manner that replacement air or gas is required to purify the confinement.
RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 2689 MWt.
REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.
SHUTDOWN means reactor powe change to 0% power.
SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee. The Figure for Liquid Effluent Site Boundary is contained in 1/2-ODC-2.01.
The Figure for Gaseous Effluent Site Boundary is contained in 1/2-ODC-2.02.
STARTUP means reactor power change from 0% power.
SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.
THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
UNRESTRICTED AREA means any area access to which is neither limited nor controlled by the 1
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I I of7-5 ATTACHMENT B Page 3 of 3 ODCM CONTROLS: DEFINITIONS VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal absorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents). Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.
VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating conditions, in such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process.
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_917 n f 7 5 ATrACHMENT C Page 1 of 2 ODCM CONTROLS: APPLICABILITY AND SURVEILLANCE REQUIREMENTS CONTROLS: APPUCABILTY 3.0.1 Compliance with the ODCM CONTROLS in the succeeding ODCM CONTROLS is required during the OPERATIONAL MODES or other conditions specified therein; except that upon failure to meet the ODCM CONTROL, the associated ODCM ACTION requirements shall be met.
3.02 Non-compliance with a ODCM CONTROL shall exist when the requirements of the ODCM CONTROL and associated ODCM ACTION requirements are not met within the specified time intervals. If the ODCM CONTROL is restored prior to expiration of the specified time intervals, completion of the ODCM ACTION requirements is not required.
3.03 When a ODCM CONTROL is not met except as provided in the associated ODCM ACTION requirements, within one hour action shall be initiated to place the unit in a MODE in which the ODCM CONTROL does not apply by placing it, as applicable, in:
- 1.
At least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,
- 2.
At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and
- 3.
At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Where corrective measures are completed that permit operation under the ODCM ACTION requirements, the ODCM ACTION may be taken in accordance with the specified time limits as measured from the time of failure to meet the ODCM CONTROL Exceptions to these requirements are stated in the individual ODCM CONTROLS.
3.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made when the conditions for the ODCM CONTROL are not met and the associated ODCM ACTION requires a shutdown if they are not met within a specified time interval. Entry into an OPERATIONAL MODE or specified condition may be made in accordance with ODCM ACTION requirements when conformance to them permits continued operation of the facility for an unlimited period of time. This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ODCM ACTION requirements. Exceptions to these requirements are stated in the individual ODCM CONTROLS.
As zr t
Ts Ae
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13 of 75 ATTACHMENT C Page 2 of 2 ODCM CONTROLS: APPLICABILITY AND SURVEILLANCE REQUIREMENTS CONTROLS: SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL MODES or other conditions specified for individual ODCM CONTROLS unless otherwise stated in an individual ODCM Surveillance Requirement.
4.02 Each ODCM Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the ODCM surveillance interval.
4.03 Failure to perform a ODCM Surveillance Requirement within the allowed ODCM surveillance interval (defined by ODCM CONTROL 4.0.2), shall constitute non-compliance with the OPERABIL1IY requirements for a ODCM CONTROL The time limits of the ODCM ACTION requirements are applicable at the time it is identified that an ODCM Surveillance Requirement has not been performed. The ODCM ACTION requirements may be delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit the completion of the ODCM surveillance when the allowable outage time limits of the ODCM ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. ODCM Surveillance Requirements do not have to be performed on inoperable equipment.
4.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made unless the ODCM Surveillance Requirement(s) associated with the ODCM CONTROL has been performed within the stated ODCM surveillance interval or as otherwise specified. This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ODCM ACTION requirements.
I0l'a'
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'1 Beaver Valley Power Station urNumODCbe 3.03 Tilde Unit Level Of Use 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision:
Pf 75 ATTACHMNTl D Page 1 of 8 ODCM CONTROLS: RADIATION MONITORING INSTRUMENTATION CONTROLS: RADIATION MONITORING (HIGH RANGE INSTRUMENTATION) 3.3.3.1 The radiation monitoring instrumentation channels shown in Table 3.3-6 shall be OPERABLE with their alann/trip setpoints within the specified limits.
APPLICABILiTY:
As shown in Table 3.3-6.
ACTION:
- a.
With a radiation monitoring channel alarm/trip setpoint exceeding the value shown in ODCM Control 3.3.3.1, Table 3.3-6, adjust the setpoint to within the limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or declare the channel inoperable.
- b.
With one or more radiation monitoring channels inoperable, take the ACTION shown in ODCM Control 3.3.3.1, Table 3.3-6.
- c.
The provisions of ODCM Control 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.1 Each radiation monitoring instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the modes and at the frequencies shown in ODCM Control 3.3.3.1, Table 4.3-3.
I
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_15 of 75 ATTACHMENT D Page 2 of 8 ODCM CONTROLS: RADIATION MONITORING INSTRUMENTATION TABLE 3.3-6 BV-1 RADIATION MONITORING INSTRUMENTATION Pri = Primary Instruments, PMM = Preplanned Method of Monitoring MINIMUM NOMINAL CHANNELS APPLICABLE MEASUREMENT INSTRUMENT OPERABLE MODES SE INTRANG 1.Noble Gas Effluent Monitors - SPINGS(4
- a. Reactor Building/SLCRS (CV-1; Also called Elevated Release)
Mid Range Noble Gas (1)
- 1. 2. 3. & 4 Pri: (RM-IVS-1 1O Ch 7) 1st PMM: (RM-IVS-112 SA-10) 2nd PMM: (RM-IVS-107B) 3rd PMM: Grab Sampling every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> High Range Noble Gas (1)
Pri: (RM-IVS-llOCh9) 1st PMM: (RM-IVS-112 SA-9 2nd PMM: (RM-IVS-107B) 3rd PMM: Grab Sampling every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
- 798 cpm N/A 1, 2, 3,&4 b.Auxiliary Building Ventilation System (VV-1; Also called Ventilation Vent)
Mid Range Noble Gas (1) 1, 2,3, & 4
<669 cpm 1013_103 UCi/cc 2 10_1i0 3 UCi/CC(3 35 35 35 35 35 Pri: (RM-IVS-109Ch7) 1st PMM: (RM-lVS-I II SA-10) 2nd PMM: (RM-IVS-IOIB) 3rd PMM: Grab Sampling every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> High Range Noble Gas (1)
Pri: (RM-IVS-109 Ch 9)
IstPMM: (RM-IVS-IIISA-9) 2nd PMM: (RM-IVS-IOIB) 3rd PMM: Grab Sampling every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
- c. Gaseous Waste/Process Vent System (PV.112)
Mid Ranee Noble Gas (1)
Pri: (RM-IGW-109 Ch 7) lstPMM: (RM-IGW-.1OSA-10) 2nd PMM: (RM-IGW-108B) 3rd PMM: Grab Sampling every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 1, 2,3, &4 1,2,3, & 4 N/A NIA High Ranee Noble Gas Pri: (RM-IGW-109Ch9) 1stPMM: (RM-IGW-I lOSA-9) 2nd PMM: (RM-IGW-108B) 3rd PMM: Grab Sampling every 12 ho (1) 1,2,3,&4
< 1.83E 5 cpm l0r1_IO1 UCi/CC(31 35 I (a) Instruments or actions shown as PMM are the preplanned methods to be used when the primary instrument is inoperable. SIN the PMM instruments shown are not considered comparable alternate monitoring channels, THEN the ODCM Surveillance Requirements do not apply to the PMM. Therefore, the reporting requirement of Action 35b would still apply when inoperability of the primary instrument exceeds 30 days.
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16of 75 AlITACHIVIENT'D Page 3 of 8 ODCM CONTROLS: RADIATION MONITORING INSTRUMENTATION TABLE 3.3-6 (Continued)
BV-1 RADIATION MONITORING INSTRUMENTATION Pri = Primary Instruments, PMM = Preplanned Method of Monitoring(a)
MNMUM CHANNELS APPLICABLE INSTRUMENT OPERABLE MODES SETPOINT!
- 2.
Noble Gas Effluent Steam Monitors
- a. Atmospheric Steam Dump Valve and Code Safety Relief Valve Discharge Pri: (RM-IMS-100A)
(1) 1, 2,3, & 4
<_50 cpm PMM: (Form 1/2-HPP-4.02.009.FO1)
Pri: (RM-IMS-IOOB)
(1) 1, 2,3, & 4
<550 cpm PMM: (Form 1/2-HPP4.02.009.FO1)
Pri: (RM-IMS-100C)
(1) 1,2,3,&4
< 50cpm PMM: (Form 1/2-HPP-4.02.009.FOI) b.Auxilary Feedwater Pump Turbine Exhaust Pri: (RM-IMS-101)
(1) 1, 2,3, & 4 S 650 cpm PMM: (Form 1/2-HPP-4.02.009.FO1) 1)
NOMINAL MEASUREMENT RANGE 10'l-103 uCi/cc 10-l-103 UCi/CC 10'1_103 UCi/CC 10'l-103 uci/cc 35 35 35 35
') Instruments or actions shown as PMM are the preplanned methods to be used when the primary instrument is inoperable.
S the PMM instruments shown are not considered comparable alternate monitoring channels, THEN the ODCM Surveillance Requirements do not apply to the PMM. Therefore, the reporting requirement of Action 35b would still apply when inoperability of the primary instrument exceeds 30 days.
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Page Number ATFACHMENT D Page 4 of 8 ODCM CONTROLS: RADIATION MONITORING INSTRUMENTATION TABLE 3.3-6 (Continued)
BV-2 RADIATION MONITORING INSTRUMENTATION Pti = Primary Instruments, PMM = Preplanned Method of Monitoringa)
MINRAUM CHANNELS APPLICABLE MODES NOMINAL MEASUREMENT RAN INSTRUIENT ACTION
- 1. Noble Gas Effluent Monitors
- a. SLCRS Filtered Pathway (CV-2; Also called Elevated Release)
Midranae Noble Gas (Xe-133)
Pri: (2HVS-RQ109C)
(1) 1stPMM: (2HVS-RQ109D) 2nd PMM: (2HVS-RQ109B) 3rd PMM: Grab Sampling every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Hiah Rance Noble Gas (Xe-133)
Pri: (2HVS-RQ109D)
(I)
Ist PMM: (2HVS-RQ109C) 2nd PMM: (2HVS-RQl09B) 3rd PMM: Grab Sampling every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 1, 2, 3, &4 1,2,3,&4 N.A.
NA 104_102 pCi/cc lof-,-lo tCi/cc 35 35 iI
() Instruments or actions shown as PMM are the preplanned methods to be used when the primary instrument is inoperable.
SINCE the PMM instruments shown are not considered comparable alternate monitoring channels, EN the ODCM Surveillance Requirements do not apply to the PMM. Therefore, the reporting requirement of Action 35b would still apply when inoperability of the primary instrument exceeds 30 days.
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anORd.
r n racna
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/uiZuvi viuor Knln an ixtw rograms lReisioo l
of 75
(
1ATACHMENT D
Page 5 of 8
( 1 ODCM CONTROLS: RADIATION MONITORING INSTRUMENTATION TABLE 3.3-6 (Continued)
TABLE NOTATIONS (l)
Above background (2)
Nominal range for Ch 7 and Ch 9. The Alarm in set on Ch 7.
(3)
Nominal range for Ch 7 and Ch 9. The Alarm in set on Ch 9.
(4)
Other SPING-4 channels are not applicable to this ODCM Control.
ACTION STATEMENTS ACTION 35 With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, either restore the inoperable Channel(s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or a)
Initiate the preplanned alternate method of monitoring the appropriate parameter(s), and b)
Return the channel to OPERABLE status within 30 days, or, explain in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.
Procedure Number Beaver Valley Power Station 1/2-ODC-3.03 7Une:
unit:
Level Of Use:
1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision:
Page Number
- 0)
IO,,.
L ATTACHMENT D Page 6 of 8 ODCM CONTROLS: RADIATION MONITORING INSTRUMENTATION TABLE 4.3-3 (Continued)
BV-1 RADIATION MONlTORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Pri = Primary Instruments, PMM = Preplanned Method of Monitoringe')
CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE INSiI NT CHECK CALBRATION TEST
- 1. Noble Gas Effluent Monitors - SPINGS
- a. Reactor Building/SLCRS (CV-1; Also called Elevated Release)
Mid Range Noble Gas S
R M
1, 2,3, & 4 Pri: (RM-lVS-ll0 Ch 7) lstPMM: (RM-lVS-112SA-10) 2nd PMM: (RM-IVS-107B) 3rd PMM: Grab Sampling every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Hih Ranze Noble Gas S
R M
1, 2,3, & 4 Pri: (RM-lVS-llOCh9) lstPMM: (RM-lVS-112SA-9) 2nd PMM: (RM-lVS-107B) 3rd PMM: Grab Sampling every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
- b. Auxiliary Building Ventilation System (VV-1; Also called Ventilation Vent)
Mid Range Noble Gas S
R M
1, 2,3, & 4 Pri: (RM-lVS-109 Ch 7) 1stPMM: (RM-lVS-111 SA-10) 2nd PMM: (RM-IVS-1OlB) 3rd PMM: Grab Sampling every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Hieh Ranee Noble Gas S
R M
1,2,3, & 4 Pri: (RM-lVS-109 Ch 9) lstPMM: (RM-lVS-ill SA-9) 2nd PMM: (RM-lVS-1O1B) 3rd PMM: Grab Sampling every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
- c.
Gaseous Waste Process Vent System (PY-1,2)
Mid Ranee Noble Gas S
R M
1, 2,3, & 4 Pri: (RM-lGW-109 Ch 7) 1st PMM: (RM-IGW-110 SA-10) 2nd PMM: (RM-1GW-108B) 3rd PMM: Grab Sampling every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Hizh Ranze Noble Gas S
R M
1,2,3, & 4 Pri: RM-IGW-109 Ch 9) 1st PMM: (RM-lGW-1 1O SA-9) 2nd PMM: (RM-lGW-108B) 3rd PMM: Grab Sampling every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Instruments or actions shown as PMM are the preplanned methods to be used when the primary instrument is inoperable. SINCE the PMM instruments shown are not considered comparable alternate monitoring channels, THEN the ODCM Surveillance Requirements do not apply to the PMM. Therefore, the reporting requirement of Action 35b would still apply when inoperability of the primary instrument exceeds 30 days.
I
.Iue:
ODCM: Controls for RETS and REMP Programs I
2 I
runoffs ATTACHMENTIT D Page 7 of 8 ODCM CONTROLS: RADIATION MONITORING INSTRUMENTATION TAB3LE 4.3-3 (Continued)
BV-I RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Pri = Primary Instruments, PMM = Preplanned Method of Monitoring(a)
CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHEK CALIBRATION TEST RElOIIRE
- 2. Noble Gas Effluent Steam Monitors
- a. Atmospheric Steam Dump Valve and Code Safety Relief Valve Discharge Pi: (RM-IMS-IOOA)
S R
M 1,2.3, &4 PMM: (Form 1/2-HPP-4.02.009.FO1)
Pri: (RM-IMS-100B)
S R
M 1,2,3, &4 PMIM: (Form 1/2-HPP-4.02.009.FOI)
Pri: (RM-IMS-1OOC)
S R
M 1, 2,3,&4 PMM: (Form 1/2-HPP4.02.009XF01)
- b. Auxiliary Feedwater Pump Turbine Exhaust Pri: (RM-IMS-101i S
R M
1,2,3,&4 PMM: (Form 1/2-HPP-4.02.009J:OI)
(a)
Instruments or actions shown as PMM are the preplanned methods to be used when the primary instrument is inoperable. SlNCE the PMM instruments shown are not considered comparable alternate monitoring channels, THEN the ODCM Surveillance Requirements do not apply to the PMM. Therefore, the reporting requirement of Action 35b would still apply when inoperability of the primary instrument exceeds 30 days.
II
Procedmr Number~
Beaver Valley Power Station 1/2-ODC-3.03 Tide:
Unit:
Level Of Use:
1/2 IGeneral Skill Reference ODCM: Controls for RETS and REMP Programs Revision:
Page Numb=
ATTACHMENT D Page 8 of 8 ODCM CONTROLS: RADIATION MONTORING INSTRUMENTATION TABLE 4.3-3 (Continued)
BV-2 RADIATION MONiTORING INSTRUMENTATION SURVEILLANCE REQUIREMNTS Pri = Primary Instruments, PMM = Preplanned Method of Monitoring(a)
CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CALIBRATION TEST REOQI D
- 1. Noble Gas Effluent Monitors
- a. SLCRS Unfiltered Pathway (CV.2; Also called Elevated Release)
Mid Range Noble Gas S
R M
1, 2,3, & 4 Pri: (2HVS-RQ109C) 1stPMM: (2HVS-RQ109D) 2nd PMM: (2HVS-RQ109B) 3rd PMM: Grab Sampling every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Hifh Renee Noble Gas S
R M
1,2,3,&4 Pri: (2HVS-RQ109D) 1stPMM: (2HVS-RQ109C) 2nd PMM: (2HVS-RQ109B) 3rd PMM: Grab Sampling every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
'a)
Instruments or actions shown as PMM are the preplanned methods to be used when the primary instrument is inoperable. SThj the PMM instruments shown are not considered comparable alternate monitoring channels, EN the ODCM Surveillance Requirements do not apply to the PMM. Therefore, the reporting requirement of Action 35b would still apply when inoperability of the primary instrument exceeds 30 days.
Procedure Number Beaver Valley Power Station 1/2-ODC-3.03 ntlekn Level Of Use:
112 General Skill Referen ODCM: Controls for RETS and REMP Programs Rev2sion:2h of 7Nb ATTACHMENT E Page 1 of 10 ODCM CONTROLS: RETS INSTRUMENTATION FOR LIQUID EFFLUENTS CONTROLS: RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION t-1.
3.3.3.9 In accordance with BV-1 and BV-2 Technical Specification 6.8.6a, Item 1, the radioactive liquid effluent monitoring instrumentation channels shown in ODCM Control 3.3.3.9, Table 3.3-12 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of ODCM CONTROL 3.1 1.1.1 are not exceeded. The alarm/trip setpoints of the radiation monitoring channels shall be determined in accordance with 112-ODC-2.01.
Applicability: During releases through the flow path.
Action:
- a.
With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or correct the alarnm/trip setpoint.
- b.
With one or more radioactive liquid effluent monitoring instrumentation channels inoperable, take the ACTION shown in ODCM Control 3.3.3.9, Table 3.3-12 or conservatively reduce the alarm setpoint. Exert a best effort to return the channel to operable status within 30 days, and if unsuccessful, explain in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.
- c.
The provisions of ODCM CONTROL 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.9 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated operable by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in ODCM Control 3.3.3.9, Table 4.3-12.
Procedure Number Beaver Valley Power Station 1/2-ODC-3.03
Title:
Unit Level Of Use.
1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision:
Page Number
_2'3_of 75 ATTACHMENT E Page 2 of 10 ODCM CONTROLS: RETS INSTRUMENTATION FOR LIQUID EFFLUENTS TABLE33-12 BV-1 RADIOACTIVE LiDUID EFFLUENT MONITORING INSTRUMENTATION Pri = Primary Instruments, Alt = Alternate Instruments MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION
- 1. Gross Activity Monitors Providing Automatic Termination Of Release
- a. Liquid Waste Effluents Monitor (1) 23 Pri: (RM-1LW-104)
- b. Liquid Waste Contaminated Drain Monitor (1) 23 Pri: (RM-1LW-116)
- c. Auxiliary Feed Pump Bay Drain Monitor (1) 24 Pri: (RM-IDA-100)
- 2. Gross Activity Monitors Not Providing Termination Of Release
- a. Component Cooling-Recirculation Spray Heat (1) 24 Exchangers River Water Monitor Pri: (RM-1RW-100)
- 3. Flow Rate Measurement Devices a liquid Radlw eturi (1) 25 Pti: ER-ILW-104) fcr M-ILW-10Y.)
- b. liquid Waste Contaminated Drain line (1) 25 Pri: (FR-ILW-103) for (RM-1LW-116)
- c. Cooling Tower Blowdown Line (1) 25 Pri: (FT-lCW-101-1) or Alt: (FT-1CW-101) and (2CWS-FT-101)
- 4. Tank Level Indicating Devices (for tanks outside plant building)
- a. Primary Water Storage Tank (1) 26 Pri: (LI-1PG-1 15A) for (1BR-TK-6A)
- b. Primary Water Storage Tank (1) 26 PA: (LI-1PG-1 15B) for (1BR-TK-6B)
- c. Steam Generator Drain Tank (1) 26 Pri: (LI-1LW-1 10) for (1LW-TK-7A)
- d. Steam Generator Drain Tank (1) 26 Pd: (Ll-1,W-I l1) for (lLW-TK-7B)
Beaer ally PPr ocedur Number.
Beaver Valley Power Station l/2-ODC-3.03 tide:
Unit Ievd Of Ul 1/2 General Skill Reference ODCM: Controls for RBTS and REMP Programs Revisio Page Numbwr ATTACHMENT E Page 3 of 10 ODCM CONTROLS: RETS INSTRUMENTATION FOR LIQUID EFFLUENTS TABLE 3.3-12 (continued)
BV-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Pn = Primary Instruments, Alt = Alternate Instruments MENIMUM CHANNELS INSTRUMENT OPERABLE ACTION
- 1. Gross Radioactivity Monitor Providing Alarm And Automatic Termination Of Release
- a. Liquid Waste Process Effluent Monitor (1) 23 Pri: (2SGC-RQ100)
- 2. Gross Radioactivity Monitors Providing Alarm But Not Providing Termination Of Release
- a. None Required
- 3. Flow Rate Measurement Devices
- a. Liquid Radwaste Effluent (1) 25 Pi: (2SGC-FS100)
- b. Cooling Tower Blowdown Line (1) 25 Pri: (FI-lCW-101-1) or Alt: (FT-ICW-101) and (2CWS-FT101)
- 4. Tank Level Indicating Devices (for tanks outside plant buildings)
- a. None Required
Procedure Number.
Beaver Valley Power Station 1/2-ODC-3.03 Mtde:
Unit:
Level Of Use:
112 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision:
Page Number.
2 5of75 ATTACHMENT E Page 4 of 10 ODCM CONTROLS: REIS INSTRUMENTATION FOR LIQUID EFFLUENTS TABLE 3.3-12 (continued)
ACTION STATEMENTS Action 23 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may be initiated or resumed provided that prior to release:
- 1.
At least two independent samples are analyzed in accordance with ODCM SURVEILLANCE REQUIREMENT 4.1 1.1.1.1, and at least two technically qualified members of the Facility Staff independently verify the release rate calculations(" and discharge valving, or
- 2.
Initiate monitoring with the comparable alternate monitoring channel. ODCM Surveillance requirements applicable to the inoperable channel shall apply to the comparable alternate monitoring channel when used to satisfy this ODCM CONTROL requirement.
Otherwise, suspend release of radioactive effluents via this pathway.
Action 24 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided:
- 1.
That at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> grab samples are analyzed for gross radioactivity (beta or gamma) at a Lower Limit of Detection (LL.D) of at least 1E-7 uCi/ml, or
- 2.
Initiate monitoring with the comparable alternate monitoring channel. ODCM Surveillance requirements applicable to the inoperable channel shall apply to the comparable alternate monitoring channel when used to satisfy this ODCM CONTROL requirement.
(l) Since the computer software used for discharge permit generation automatically performs the release rate calculations, then the independent signatures on the discharge permit for "preparer" and "reviewer" satisfy the requirement for "...two technically qualified members of the Facility Staff independently verify the release rate calculations..."
Beaver Valley Power Station P/2dDC.Number Title Uni vel Of Use.
1/2 Genral Skill Reference ODCM: Controls for RETS and REMP Programs Revision:
PageNumber:
2 26of75 AWTACHMENT E Page 5 of 10 ODCM CONTROLS: RETS INSTRUMENTATION FOR LIQUID EFFLUENTS Table 3.3-12 (continued)
ACTION STATEMENTS Action 25 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided:
- 1.
The flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. (Pump curves may be used to estimate flow), or
- 2.
Initiate monitoring with the comparable alternate monitoring channel. ODCM Surveillance requirements applicable to the inoperable channel shall apply to the comparable alternate monitoring channel when used to satisfy this ODCM CONTROL requirement.
Action 26 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, liquid additions to this tank may continue provided:
- 1.
The tank liquid level is estimated during all liquid additions to the tank, or
- 2.
Initiate monitoring with the comparable alternate monitoring channel. ODCM Surveillance requirements applicable to the inoperable channel shall apply to the comparable alternate monitoring channel when used to satisfy this ODCM CONTROL requirement.
Pocedue Number Beaver Valley Power Station 1/2-ODC-3.03
Title:
Unit Level Of Use.
1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision:
Page Number.
2
'27 of 7-5 AITACHMENT E Page 6 of 10 ODCM CONTROLS: RETS INSTRUUMENTAMION FOR LIQUID EFFLUENTS TABLE 4.3-12 BV-1 RADIOACTIVE MUID EFFLUENT MONITORING INSTRUMENTATION SURVEIL-LANCE REOIIREMENTS Pri = Primary Instruments, Alt = Alternate Instruments CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CECK CALI3RATION TEST
- 1. Gross Beta or Gamma Radioactivity Monitors Providing Alarm And Automatic Termination Of Release
- a. Liquid Radwaste Effluent Line D
R3Q)
Pri: (RM-lLW-104)
- b. Liquid Waste Contaminated D
)
R3 Q(l)
Drain Line Pri: (RM-lLW-116)
- c.
Auxiliary Feed Pump Bay D
D R(3)
Q(l)
Drain Monitor Pri: (RM-lDA-100)
- 2. Gross Beta Or Gamma Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination Of Release
- a.
Component Cooling -Recirculation D
M?>
R0)
QM Spray Heat Exchangers River Water Monitor Pri: (RM-lRW-100)
- 3. Flow Rate Monitors
- a.
Liquid Radwaste Effluent Lines D(4)
NA R
Q Pri: (FR-lLW-104) for (RM-lLW-104)
- b. Liquid Waste Contaminated Drain Line D(4)
NA R
Q Pri: (FR-lLW-103) for (RM-ILW-116)
- c. Cooling Tower Blowdown Line D(4)
NA R
Q Pri: (FT-ICW-101-1) or Alt: (FT-ICW-101) and (2CWS-FP-101)
Beaver Valley Power Station edweNu2ODC-3.03
,lnfe Unit:
Level Of Use:
112 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision:
Page Number.
12
?8 of 7-5 ATTACHMENT E Page 7 of 10 ODCM CONTROLS: RETS INSTRUMENTATION FOR LIQUID EFLUENTS TABLE 4.3-12 (continued)
BV-1 RADIOACMIVE LIQUID EPFLUENT MONiTORING INSTRUMENTATIOIN SURVEILLANCE REQUIREMENTS Pri = Primary Instruments, Alt = Alternate Instruments CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUN CHD3E CHECK CALIBRATION TEST
- 4. Tank Level Indicating Devices (for tanks outside plant buildings)
- a.
Primary Water Storage Tank D*
NA R
Q Pri: (LI-lPG-115A) for (lBR-TK-6A)
- b.
Primary Water Storage Tank D*
NA R
Q Pri: (LI -IPG-l 15B) for (IBR-TK-6B)
- c.
Steam Generator Drain Tank D*
NA R
Q Pri: (LI-ILW-I 10) for (ILW-TK-7A)
- d.
Steam Generator Drain Tank D*
NA R
Q Pri: (LI-ILW-I 11) for (ILW-TK-7B)
- During liquid additions to the tank.
Procedure Number Beaver Valley Power Station 12-ODC-3.03
Title:
Unit:
Lvel Of Use General Skill Reference ODCM: Controls for RETS and RENP Programs R2on Pg 9 of 75 AITACHMENT E Page 8 of 10 ODCM CONTROLS: REIS INSTRUMENTATION FOR LIQUID EFFLUENTS TABLE 4.3-12 (continued)
BV-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REOUIREMENTS Pri = Primary Instruments, Alt = Alternate Instruments CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST
- 1. Gross Radioactivity Monitor Providing Alarm And Automatic Termination Of Release
- a. Liquid Waste Process Effluent D
p R
Q Pri: (2SGC-RQ100)
- 2. Flow Rate Measurement Devices
- a. Liquid Radwaste Effluent D(4t NA R
Q Pri: (2SGC-FS100) i
- b. Cooling Tower Blowdown Line Df4)
NA R
Q Pri: (Fr-ICW-101-1) or Alt: (Fr-ICW-101) and (2CWS-FT101)
- 3. Tank Level Indicating Devices (for tanks outside plant buildings)
- a.
None Required
Beaver Valley Power Station 1/2PoODCd3.N3ub Mde:
Unit:
Level Of Use:
1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision:
Page Nuber-
- 9.
I ATTACHMENT E Page 9 of 10 ODCM CONTROLS: RETS INSTRUMENTATION FOR LIQUID EFFLUENTS TABLE 4.3-12 (continued)
TABLE NOTATION The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and Control Room Alarm Annunciation occurs if any of the following conditions exist:
- 1.
Instrument indicates measured levels above the alarm/trip setpoint.
- 2.
Downscale failure.
- 3.
Instrument controls not set in operate mode.
(2)
The CHANNEL FUNCTIONAL TEST shall also demonstrate that Control Room Alarm Annunciation occurs if any of the following conditions exist:
- 1.
Instrument indicates measured levels above the alarm/trip setpoint.
- 2.
Downscale failure.
- 3.
Instrument controls are not set in operate mode.
The initial CHANNEL CALIBRATION for radioactivity measurement instrumentation shall be performed using one or more of the reference standards certified by the National Bureau of (Standards/NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBSINIST. These standards should permit calibrating the system over its intended range of energy and rate capabilities. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration should be used, at intervals of at least once per 18 months. This can normally be accomplished during refueling outages. (Existing plants may substitute previously established calibration procedures for this requirement).
(4)
CHANNEL CHECK shall consist of verifying indication of flow during periods of release.
CHANNEL CHECK shall be made at least once daily on any day on which continuous, periodic, or batch releases are made.
A SOURCE CHECK may be performed utilizing the installed means or flashing the detector with a portable source to obtain an upscale increase in the existing count rate to verify channel response.
Procedure Number.
Beaver Valley Power Station 12-ODC-3.03 Tritle.
Unit:
Leve Of Use:
1/2 General Skill Reference ODCM: Controls for RETS and REMIP Programs Rej s ion P5eN ATTACHMENT E Page 10 of 10 ODCM CONTROLS: RETS INSTRUMENTATION FOR LIQUID EFFLUENTS TABLE 4.3-12 (continued)
TABLE NOTATION The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and Control Room Alarm Annunciation occurs when the instrument indicates measured levels above the Alarm/Trip Setpoint.
The CHANNEL FUNCT[ONAL TEST shall also demonstrate that Control Alarm Annunciation occurs if any of the following conditions exists:
- 1.
Downscale failure.
- 2.
Instrument controls are not set in operate mode.
The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and Control Room Alarm Annunciation occurs if the instrument indicates measured levels above the alarm/trip setpoint.
(8 The CHANNEL CALIBRATION shall also demonstrate that Control Room Alarm Annunciation occurs if either of the following conditions exist:
- 1.
Downscale failure.
- 2.
Instrument controls are not set in operate mode.
I
Procedure Numnbez Beaver Valley Power Station 1/2.oDC-3.03 elt:
Unit Level Of Us=
General Skll Reference ODCM: Controls for RETS and REMP Programs Revision:
Page Numbce
"-I ATTACHMENT F Page 1 of 13 ODCM CONTROLS: RETS INSTRUMENT FOR GASEOUS RELEASES CONTROLS: RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 3.3.3.10 In accordance with BV-1 and BV-2 Technical Specification 6.8.6a, Item 1, the radioactive gaseous effluent monitoring instrumentation channels shown in ODCM Control 3.3.3.10, Table 3.3-13 shall be operable with their alarn/trip setpoints set to ensure that the limits of ODCM CONTROL 3.11.2.1 are not exceeded. The alarm/trip setpoints of the radiation monitoring channels shall be determined in accordance with 1/2-ODC-2.02.
Applicability: During releases through the flow path.
Action:
- a.
With a radioactive gaseous process or effluent monitoring instrumentation channel alarm/trip setpoint less conservative than a value which will ensure that the limits of ODCM CONTROL 3.11.2.1 are met, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel or correct the alarm/trip setpoint.
- b.
With one or more radioactive gaseous effluent monitoring instrumentation channels inoperable, take the ACTION shown in ODCM Control 3.3.3.10, Table 3.3-13 or conservatively reduce the alarm setpoint. Exert a best effort to return the channel to operable status within 30 days, and if unsuccessful, explain in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.
- c.
The provisions of ODCM CONTROL 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.10 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated operable by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the f
frequencies shown in ODCM Control 3.3.3.10, Table 4.3-13.
.j
r V e
P r Stat Procedure Number.
Beaver Valley Power Station 112-ODC-3.03 Tile:
Unit Level Of Use:
1/2 IGeneral Skill Reference ODCM: Controls for RETS and REMP Programs Revision:
Page Numberf I,
ATTACHMENT F Page 2 of 13 ODCM CONTROLS: RETS INSTRUMENT FOR GASEOUS RELEASES TABLE 3.3-13 BV-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Pri = Primary Instruments, Alt = Alternate Instruments CHANNELS ONSRUMNr OERABRE ACIPN
- 1. Gaseous Waste/Process Vent System (PV-1,2)
- a.
Noble Gas Activity Monitor (1) 27,29,30A,30B1 Pri: (RM-IGW-108B) or Alt For Continuous Release: (RM-1GW-109 Ch 5) This channel may only be used as the comparable alternate monitoring channel for continuous releases via this pathway.
Alt For Batch Releases: (See Action 27) RM-IGW-109 Ch 5 SHALL NOT be used as the comparable alternate monitoring channel for batch releases of the BV-1 GWDT's or the BV-2 GWST's. Specifically, S this channel does not perform the same automatic isolation function as the primary channel, THEN ACTION 27 shall be followed for batch releases of the BV-I GWDT's or the BV-2 GWST's via this pathway.
- b. Particulate and Iodine Sampler (1) 32 Pi: (Filter Paper & Charcoal Cartridge for RM-IGW-109) or 1st Alt: (Filter Paper & Charcoal Cartridge for RM-IGW-1 10) or 2nd Alt: (Continuous collection via RASP Pump) or 3rd Alt: (Grab samples every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />)
- c. System Effluent Flow Rate Measuring Device (1) 28A Pd: (FR-iGW-108) or Alt: (RM-IGW-109 Ch 10)
- d. Sampler Flow Rate Measuring Device Used for (1) 28B Sample Collection Pd: (RM-IGW-109 Ch 15) or Alt: (Rotometer: FM-lGW-101, and Vacuum Gauge: PI-1GW-13)
- 2. Auxiliary BuildingVentilationSystem (VV-I; Also called Ventilation Vent)
- a. Noble Gas Activity Monitor (1) 29,30A l
Pd: (RM-IVS-iOlB) or Alt: (RM-IVS-109 Ch 5)
- b. Particulate and Iodine Sampler (1) 32 Pri: (Filter Paper & Charcoal Cartridge for RM-IVS-109) or 1st Alt: (Filter Paper & Charcoal Cartridge for RM-IVS-111) or 2nd Alt: (Continuous collection via RASP Pump) or 3rd Alt: (Grab samples every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />)
- c.
System Effluent Flow Rate Measuring Device (1) 28A Pdi: (FR-IVS-101) or Alt: (RM-IVS-109 Ch 10)
- d. Sampler Flow Rate Measuring Device Used for (1) 28B Sample Collection Pri: (RM-IVS-109 Ch 15) or Alt: (Rotometer FM-1VS-102, and Vacuum Gauge: PI-IVS-659)
- During Releases via this pathway.
Beaver Valley Power Station 2OedD Numb.=
Tifle Unit Ued Of Use.
1/2 General Skill Reference ODCM: Controls for RETS and REMIP Programs ReYii Page N=ubr 214 n 75 ATTACHMENT F Page 3 of 13 ODCM CONTROLS: RETS INSTRUMENT FOR GASEOUS RELEASES TABLE 3.3-13 (continued)
BV-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Pri = Primary Instruments, Alt = Alternate Instruments NM lNSIRU OFABA ll ACTION
- 3. Reactor BuildingISLCRS (CV-1; Also called Elevated Release)
- a. Noble Gas Activity Monitor (1) 29,30A Pri: (RM-lVS-107B) or Alt: (RM-lVS-1 10Ch 5)
- b. Particulate and Iodine Sampler (1) 32 Pri: (Filter Paper & Charcoal Cartridge for RM-lVS-i 10) or 1st Alt: (Filter Paper & Charcoal Cartridge for RM-lVS-i 12) or 2nd Alt: (Continuous collection via RASP Pump) or 3rd Alt (Grab samples every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />)
- c. System Effluent Flow Rate Measuring Device (1) 28A Pri: (FR-IVS-i 12) or Alt: (RM-lVS-l 10 Ch 10)
- d. Sampler Flow Rate Measuring (1) 28B Device Used for Sample Collection Pri: (RM-IVS-1 10 Ch 15) or Alt: (Rotometer: FM-IVS-103, and Vacuum Gauge: PI-lVS-660)
-4
- During Releases via this pathway.
Beaver Valley Power Station ProcedureN 1itl:
Unit Level Of Use:
112 IGeneral Skill Reference ODCM: Controls for RETS and REMP Programs Revision:
Page Number 2
35of7 AITACEMENT F Page 4 of 13 ODCM CONTROLS: RETS INSTRUMENT FOR GASEOUS RELEASES TABLE 3.3-13 (continued)
BV-2 RADIOACTWE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Pri = Primary Instruments, Alt = Alternate Instruments MNM[RM OPERABIE APLI(M 1.SLCRS Unfiltered Pathway (VV-2; Also called Ventilation Vent)
- a. Noble Gas Activity Monitor (1) 29, 30B Pri: (2HVS-RQlOlB)
- b. Particulate and Iodine Sampler (1) 32 Pri: (Filter Paper & Charcoal Cartridge for 2HVS-RQ101) or 1st Alt: (Continuous collection via RASP Pump) or "A
2nd Alt: (Grab samples every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />)
- c.
Process Flow Rate Monitor (1) 28A Pri: (Monitor Item 29 for 2HVS-VP10)
- d. Sampler Flow Rate Monitor Used for Sample Collection (1) 28B Pri: (2HVS-FIT101)
- 2. SLCRS Filtered Pathway (CV-2; Also called Elevated Release)
- a.
Noble Gas Activity Monitor (1) 29, 30B Pri: (2HVS-RQ109B)
- b. Particulate and Iodine Sampler (1) 32 Pri: (Filter Paper & Charcoal Cartridge for 2HVS-RQ109 High Flow Path) or 1st Alt: (Continuous collection via RASP Pump) or 2nd Alt: (Grab samples every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />)
- c.
Process Flow Rate Monitor (1) t 28A Pri: (Monitor Item 29 for 2HVS-FR22) or 1st Alt: (2HVS-FI22A and F122C) or 2nd Alt (2HVS-FI22B and F122D)
- d. Sampler Flow Rate Monitor Used for Sample Collection (1) 28B Pri: (Monitor Items 28 and 72 for 2HVS-DAU109B)
- 3. Decontamination Building Vent (DV-2)
- a. Noble Gas Activity Monitor (1) a 29 Pri: (2RMQ-RQ301B)
- b. Particulate and Iodine Sampler (1) 32 Pri: (Filter Paper & Charcoal Cartridge for 2RMQ-RQ301) or 1st Alt: (Continuous collection via RASP Pump) 2nd Alt: (Grab samples every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />)
- c. Process Flow Rate Monitor None None None
- d. Sampler Flow Rate Monitor Used for Sample Collection (1) 28B Pd: (2RMQ-FIT301)
\\ I
- During Releases via this pathway.
I
Beaver Valley Power Station PAxo Number.
ritUi:
L~eve Of Use:
1/2 General Skill Reference ODCM: Controls for RETS and REX Programs Revision:
Page Numbe_
2 16of75 I
ATTACHMENT F Page 5 of 13 ODCM CONTROLS: RErS INSTRUMENT FOR GASEOUS RELEASES TABLE 3.3-13 (continued)
BV-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Pri = Primary Instruments, Alt = Alternate Instruments MRNMUM CHANMES OFIRFABLB APFUCABJUIY AffM
- 4. Condensate Polishing Building Vent (CB-2)
- a. Noble Gas Activity Monitor (1) 29 Pri: (2HVL-RQ1 12B)
- b. Particulate and Iodine Sampler (1) 32 Pri: (Filter Paper & Charcoal Cartridge for 2HVL-RQ1 12) 1st Alt (Continuous collection via RASP Pump) 2nd Alt: (Grab samples every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />)
- c.
Process Flow Rate Monitor None None None a
- d. Sampler Flow Rate Monitor Used for Sample Collection (1) 28B Pri: (2HVL-FITI 12)
- 5. Waste Gas Storage Vault Vent (WV-2)
- a. Noble Gas Activity Monitor (1) 29 Pri: (2RMQ-RQ303B)
- b. Particulate and Iodine Sampler (1) 32 Pri: (Filter Paper & Charcoal Cartridge for 2RMQ-RQ303) 1 st Alt: (Continuous collection via RASP Pump) 2nd Alt: (Grab samples every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />) j
- c. Process Flow Rate Monitor None None None
- d. Sampler Flow Rate Monitor Used for Sample Collection (1) 28B B1W)
P Pri: (2RMQ-F1T303)
- During Releases via this pathway.
Procedure Nwnbet Beaver Valley Power Station 1/2-ODC-3.03 Tide:
Unit Level Of Use:
1/2 General Skil Reference ODCM: Controls for RETS and REMP Programs Revision:
Page N Ofbcr.
ATTACHMENT F Page 6 of 13 ODCM CONTROLS: RETS INSTRUMENT FOR GASEOUS RELEASES TABLE 3.3-13 (continued)
ACTION STATEMENTS Action 27 APPLICABLE FOR BATCH RELEASES OF BV-1 GASEOUS WASTE DECAY TANKS OR BV-2 GASEOUS WASTE STORAGE TANKS With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the Unit 1 Gaseous Waste Decay Tanks (GWDT's) or the Unit 2 Gaseous Waste Storage Tanks (GWST's) may be released to the environment provided that prior to initiating the release:
- 1.
At least two independent samples of the tank's content are analyzed and at least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge valve lineup, or
- 2.
Initiate continuous monitoring with the comparable alternate monitoring channel.
ODCM Surveillance requirements applicable to the inoperable channel shall apply to the comparable alternate monitoring channel when used to satisfy this ODCM Control requirement.
Otherwise, suspend releases of radioactive effluents via this pathway.
Action 28A APPLICABLE FOR BV-1 SYSTEM EFFLUENT FLOW RATE MEASURING DEVICES OR BV-2 PROCESS FLOWRATE MONITORS With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided:
- 1.
The system/process flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> (or assumed to be at the ODCM design value(l)), or
- 2.
Initiate continuous monitoring with the comparable alternate monitoring channel.
ODCM Surveillance requirements applicable to the inoperable channel shall apply to the comparable alternate monitoring channel when used to satisfy this ODCM Control requirement.
(')
In lieu of estimating the system/process flow rate at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, the system/process flow rate can be assumed to be at the following ODCM design values:
1,450 cfm = BV-1 Gaseous Waste/Process Vent System (PV-1,2) 62,000 cfm = BV-1 Auxiliary Building Ventilation System (VV-1) 49,300 cfm = BV-1 Reactor Building/SLCRS (CV-1) 23,700 cfm = BV-2 SLCRS Unfiltered Pathway (VV-2) 59,000 cfm = BV-2 SLCRS Filtered Pathway (CV-2)
Beaver Valley Power Station Po2.NODCm.3.03 MlSe; Unit:
LaevR Of Use 1/2 General Skill Referenc-ODCM: Controls for RETS and REMP Programs Revisio Pape Number 2 I 38of 75 ATTACHMIVENT F Page 7 of 13 ODCM CONTROLS: RETS INSTRUMIENT FOR GASEOUS RELEASES TABLE 3.3-13 (continued)
ACTION STATEMENTS Action 28B APPLICABLE FOR BV-1 SAMPLER FLOW RATE MEASURING DEVICES OR BV-2 SAMPLER FLOWRATE MONITORS With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided:
- 1.
The sampler flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or
- 2.
Initiate continuous monitoring with the comparable alternate monitoring channel.
ODCM Surveillance requirements applicable to the inoperable channel shall apply to the comparable alternate monitoring channel when used to satisfy this ODCMX Control requirement.
Action 29 APPLICABLE FOR CONTINUOUS RELEASES With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided:
- 1.
Grab samples (or local monitor readings)(]) are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. If grab samples are taken, these samples are to be analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or
- 2.
Initiate continuous monitoring with the comparable alternate monitoring channel.
ODCM Surveillance requirements applicable to the inoperable channel shall apply to the comparable alternate monitoring channel when used to satisfy this ODCM CONTROL requirement.
(i)
For BV-2, there are situations where the local monitor (e.g.; the RM-80) is capable of performing the intended monitoring function, but the communications are lost to the Control Room. In this case, the local monitor can be read at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> in-lieu of obtaining grab samples at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Tt t
T o
n
@ProcedumreNumber.
Beaver Valley Power Station 1U2-ODC-3.03 TItle.
Unit:
Level Of Use 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revisioe:
Page Number.
2 19 of 75 ATTACHMENT F Page 8 of 13 ODCM CONTROLS: RETS INSTRUMENT FOR GASEOUS RELEASES TABLE 3.3-13 (continued)
ACTION STATEMENTS Action 30A APPLICABLE FOR THE INlAL BATCH PURGE OF THE BV-1 REACTOR CONTAINMENT With the number of channels OPERABLE less than required by minimum Channels OPERABLE requirement, immediately suspend PURGING of Reactor Containment via 0
this pathway if both RM-VS-104A and B are not OPERABLE with the purge/exhaust system in service. The following should also be noted:
- 1.
As stated, this Action is applicable for INOPERABLE monitors only when performing the initial batch purge of the reactor containment atmosphere (i.e.;
immediately after reactor containment atmosphere equalization).
- 2.
Since all other releases of reactor containment atmosphere (i.e.; after the initial batch purge) are considered continuous releases, then this Action is not applicable. Therefore, Action 29 is applicable for INOPERABLE monitors when performing a continuous release of the reactor containment atmosphere.
Action 30B APPLICAB LE FOR THE INHTIAL BATCH PURGE OF THE BV-2 REACTOR CONTAINMENT With the number of channels OPERABLE less than required by Minimum Channels OPERABLE requirement, immediately suspend PURGING of Reactor Containment via this pathway if both 2HVR-RQ104A and 104B are not OPERABLE with the purge/exhaust system in service. The following should also be noted:
- 1.
As stated, this Action is applicable for INOPERABLE monitors only when performing the initial batch purge of the reactor containment atmosphere (i.e.;
immediately after reactor containment atmosphere equalization).
- 2.
Since all other releases of reactor containment atmosphere (i.e.; after the initial batch purge) are considered continuous releases, then this Action is not applicable. Therefore, Action 29 is applicable for INOPERABLE monitors when performing a continuous release of the reactor containment atmosphere.
Action 32 APPLICABLE FOR CONTINUOUS RELEASES With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided samples are continuously collected with auxiliary sampling equipment as required in ODCM Control 3.11.2.1, Table 4.11-2, or sampled and analyzed once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Beaver Valley Power Station PrceurlNmoc
Title:
Unit Leve Of Ue 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs RI Page Numbef.
40___of__
_-__I ATTACHMENT F Page 9 of 13 ODCM CONTROLS: RETS INSTRUMENT FOR GASEOUS RELEASES TABLE 4.3-13 BV-1 RADIOACTIVE GASEOUS EFFLUENT MONT17ORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Pri = Primary Instruments, Alt = Alternate Instruments CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUME CHECK CALIBRATION TIST
- 1. Gaseous Waste/Process Vent System (PV-1,2)
- a.
Noble Gas Activity Monitor p
p(4)
R0" Q(I)
Pri: (RM-lGW-108B)
Alt For Continuous Release: (RM-lGW-109 ChS) This channel may only be used as the comparable alternate monitoring channel for continuous releases via this pathway.
AltFor Batch Releases: (See Action 27): RM-lGW-109 Ch 5 SHALL NOT be used as the comparable alternate monitoring channel for batch releases of the BV-I GWDrs or the BV-2 GWS7s. Specifically, SINC this channel does not perform the same automatic isolation function as the primary channel, TIHE ACTION 27 shall be followed for batch releases of the BV-1 GWDT's or the BV-2 GWSrs via this pathway
- b.
Particulate and Iodine Sampler W
NA NA NA Pri: (Filter Paper & Charcoal Cartridge for RM-IGW-109) or Ist Alt: (Filter Paper & Charcoal Cartridge for RM-IGW-I 10) or 2nd Alt: (Continuous collection via RASP Pump) or 3rd Alt: (Grab samples every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />)
- c.
System Effluent Flow Rate Measuring Device P
NA R
Q Pri: (FR-IGW-108) or Alt: (RM-IGW-109 Chl 10)
- d.
Sampler flow Rate Measuring Device D*
NA R
Q Used for Sample Collection Pri: (RM-IGW-109 Ch 15) or Alt: (Rotometer FM-IGW-101, and Vacuum Gauge: PI-IGW-13)
- 2. Auxiliary Building Ventilation System (W-1; Also called Ventilation Vent)
- a.
Noble Gas Activity Monitor D
R QO Pri: (RM-IVS-1OlB) or 4)***
Alt (RM-IVS-109 Ch 5)
- b.
Particulate and Iodine Sampler W
NA NA NA Pri: (Filter Paper & Charcoal Cartridge for RM-IVS-109) or ist Alt: (Filter Paper & Charcoal Cartridge for RM-lVS-I 11) or 2nd Alt: (Continuous collection via RASP Pump) or 3rd Alt: (Grab samples every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />)
- c.
System Effluent Flow Rate Measurement Device D
NA R
Q Pri: (FR-IVS-ll) or Alt: (RM-IVS-109 Ch 10)
- d.
Sampler Flow Rate Measuring Device D
NA R
Q Used for Sample Collection Pri: (RM-IVS-109 Ch 15) or Alt: (Rotometer: FM-I VS-102, and Vacuum Gauge: PI-IVS-659)
- During Releases via this pathway.
ark During purging of Reactor Containment via this pathway.
I
Procedure Nurnber Beaver Valley Power Station u
1jL u 12-ODC-3.03 Titde:
Level Of Use:
l2
/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision:
Page Number.
AITACHNIENT F Page 10 of 13 ODCM CONTROLS: RETS INSTRUIENT FOR GASEOUS RELEASES TABLE 4.3-13 BV-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Pri = Primary Instruments, Alt = Alternate Instruments CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSRUME C CK C CK CALIBRATION TEST
- 3. Reactor Building/SLCRS (CV-1; Also called Elevated Release)
- a.
Noble Gas Activity Monitor D
M(4)
R03 Qa Pri: (RM-IVS-107B)or p,4)***
Alt: (RM-IVS-1 10 Ch 5)
- b. Particulate and Iodine Sampler W
NA NA NA Ax Pri: (Filter Paper & Charcoal Cartridge for RM-lVS-1 10) or 1st Alt: (Filter Paper & Charcoal Cartridge for RM-IVS-112) or 2nd Alt: (Continuous collection via RASP Pump) or 3rd Alt: (Grab samples every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />)
- c. System Effluent Flow Rate D
NA R
Q Measuring Device Pri: (FR-IVS-1 12) or Alt: (RM-IVS-I 10 Ch 10)
- d. Sampler Flow Rate Measuring Device D
NA R
Q Used for Sample Collection Pri: (RM-IVS-i 10 Ch 15) or Alt: (Rotometer: FM-IVS-103, and Vacuum Gauge: PI-IVS-660)
- During releases via this pathway.
- During purging of Reactor Containment via this pathway.
Pwocedare Numbern Beaver Valley Power Station 1/2-ODC-3.03 I&le:
unit:
Level Of Use:
1/12 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision:
Page Numbcn 2
42of75 ATTACHEMENT F Page 11 of 13 ODCM CONTROLS: RETS INSTRUMENT FOR GASEOUS RELEASES TABLE 4.3-13 (continued)
BV-2 k
V GASEOUS EFFLUENT MONrrORINn STRUETATION SURVEILLANCE REOUMREMENTS Pri = Primary Instruments, Alt = Alternate Instruments CHANNEL SOURCE ilSTCUMECO 1.SLCRS Unfiltered Pathway (VV-2; Also called Ventilation Vent)
- a. Noble Gas Activity Monitor D
M(4),
Pri: (2HVS-RQIOIB) pt4)***
- b. Particulate and Iodine Sampler W
NA Pri: (Filter Paper & Charcoal Cartridge for 2HVS-RQ101) or 1st Alt: (Continuous collection via RASP Pump) or 2nd Alt: (Grab samples every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />)
- c.
Process Flow Rate Monitor D
NA Pri: (Monitor Item 29 for 2HVS-VP101)
- d. Sampler Flow Rate Monitor Used for D
NA Sample Collection Pri: (2HVS-FIT101) 2.SLCRS Filtered Pathway (CV.2; Also called Elevated Release)
- a.
Noble Gas Activity Monitor D
Pri: (2HVS-RQ109B)
PM**
- b. Particulate and Iodine Sampler W
NA Pri: (Filter Paper & Charcoal Cartridge for 2HVS-RQ109 High Flow Path) or 1st Alt (Continuous collection via RASP Pump) or 2nd Alt: (Grab samples every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />)
- c.
Process Flow Rate Monitor D
NA Pri: (Monitor Item 29 for 2HVS-FR22) or 1st Alt (2HVS-F122A and F122C) or 2nd Alt: (2HVS-F122B and F122D)
- d. Sampler Flow Rate Monitor Used for D
NA Sample Collection Pd: (Monitor Items 28 and 72 for 2HVS-DAU109B)
- 3. Decontamination Building Vent (DV-2)
- a.
Noble Gas Activity Monitor D
M(4)
Pri: (2RMQ-RQ301B)
- b. Particulate and Iodine Sampler W
NA Pri: (Filter Paper & Charcoal Cartridge for 2RMQ-RQ301) or 1st Alt: (Continuous collection via RASP Pump) or 2nd Alt (Grab samples every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />)
- c.
Process Flow Rate Monitor NA NA
- d. Sampler Flow Rate Monitor Used for D
NA Sample Collection Pri: (2RMQ-FIT301)
CHANNEL CHANNEL FUNCTIONAL CALIBRATION TEST R oX6)
Q(5)
NA R
I NA Q
Q Q(S)0 R3x)
NA R
R NA Q
Q Q(S)
NA NA Q
NA NA R
I 8keA-
Procedure Number.
Beaver Valley Power Station 1I2-ODC-3.03
'rtie unit Level Of Use:
General Skill Reference ODCM: Controls for RETS and REMP Programs R4visi7n:
P nub AITACHMENT F Page 12 of 13 ODCM CONROLS: RETS INSTRUMENT FOR GASEOUS RELEASES TABLE 4.3-13 (continued)
BV-2 RADIOACTIVE GASEOUS EFFLUENT MOORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Pri = Primary Instruments, Alt = Alternate Instruments CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CEC CE CALIBRATION TESI
- 4. Condensate Polishing Building Vent (CB-2)
- a. Noble Gas Activity Monitor D
Mm R (X6)
QM Pri: (2HVL-RQI 12B)
- b. Particulate and Iodine Sampler W
NA NA NA Pri: (Filter Paper & Charcoal Cartridge for 2HVL-RQ1 12) or 1st Alt: (Continuous collection via RASP Pump) or 2nd Alt: (Grab samples every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />)
- c. Process Flow Rate Monitor NA NA NA NA
- d. Sampler Flow Rate Monitor Used for D
NA R
Q Sample Collection Pri: (2HVL-FIT1 12)
- 5. Waste Gas Storage Vault Vent (WV-2)
- a. Noble Gas Activity Monitor D
M(4)
Rox Q
Pri: (2RMQ-RQ303B)
- b. Particulate and Iodine Samples W
NA NA NA Pri: (Filter Paper & Charcoal Cartridge for 2RMQ-RQ303) or 1st Alt: (Continuous collection via RASP Pump) or 2nd Alt (Grab samples every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />)
- c. Process Flow Rate Monitor NA NA NA NA
- d. Sampler Flow Rate Monitor Used for D
NA R
Q Sample Collection Pri: (2RMQ-F1T303) wL I1
Beaver Valley Power Station P/ocOdum Num lIte:
Unit:
Level Of Use:
General Skill Reference ODCM: Controls for RETS and REMP Programs Revision:
Pap Number ATTACHMENT F Page 13 of 13 ODCM CONTROLS: RETS INSTRUMENT FOR GASEOUS RELEASES TABLE 4.3-13 (continued)
TABLE NOTATION (X)
The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and Control Room Alarm Annunciation occurs if any of the following conditions exist:
- a.
Instrument indicates measured levels above the alarm/trip setpoint.
- b.
Downscale failure.
- c.
Instrument controls not set in operate mode.
(2)
The CHANNEL FUNCTIONAL TEST shall also demonstrate that Control Room Alarm Annunciation occurs if any of the following conditions exist:
- a.
Instrument indicates measured levels above the alarm/trip setpoint.
- b.
Downscale failure.
- c.
Instrument controls not set in operate mode.
(3)
The initial CHANNEL CALIBRATION for radioactivity measurement instrumentation shall be performed using one or more of the reference standards certified be National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards should permit calibrating the system over its intended range of energy and rate capabilities. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration should be used, at intervals of at least once per 18 months. This can normally be accomplished during refueling outages.
(4)
A SOURCE CHECK may be performed utilizing the installed means or flashing the detector with a portable source to obtain an upscale increase in the existing count rate to verify channel response.
(5)
The CHANNEL FUNCTIONAL TEST shall also demonstrate that Control Room Alarm Annunciation occurs if the instrument indicates measured levels above the alarnitrip setpoint.
(6)
The CHANNEL CALIBRATION shall also demonstrate that Control Room Alarm Annunciation occurs if either of the following conditions exist:
- 1.
Downscale failure.
- 2.
Instrument controls are not set in operate mode.
Beaver Valley Power Station PdreNum2bDc3.03 l
Unitl:
Level Of Use:
112 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision:
Page Nurnber ATTACHMENT G Page 1 of 5 ODCM CONTROLS: LIQUID EFFLUENT CONCENTRATION CONTROLS: LIQUID EFFLUENT CONCENTRATION 3.11.1.1 In accordance with BV-1 and BV-2 Technical Specification 6.8.6a, Items 2 and 3, the concentration of radioactive material released at any time from the site (see 1/2-ODC-2.01, Figure 5-1) shall be limited to 10 times the EC's specified in 10 CFR Part 20, Appendix B (20.1001-20.2401), Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. This is referred to as the ODCM Effluent Concentration Limit (OEC). For dissolved or entrained noble gases, the concentration shall be limited to 2E-4 uCi/ml total activity.
Applicability:
At all times.
Action:
- a.
With the concentration of radioactive material released from the site to unrestricted areas exceeding the above limits; immediately restore the concentration within the above limits, and
- b.
Submit a Special Report to the Commission within 30 days in accordance with 10 CFR 20.2203(a)(2)(v) and 10 CFR 50.4(b)(1).
- c.
The provisions of ODCM CONTROL 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of ODCM Control 3.11.1.1, Table 4.11-1*.
4.11.1.1.2 The results of radioactive analysis shall be used in accordance with 1/2-ODC-2.01 to assure that the concentration at the point of release are maintained within the limits of ODCM CONTROL3.11.1.1.
4.11.1.1.3 When BV-I primary to secondary leakage exceeds 0.1 gpm (142 gpd), samples of the Turbine Building Sump shall be obtained every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to ensure that the Turbine Building Sump concentration does not exceed 1 OEC. Once it is determined that an OEC is reached, the Turbine Building Sump shall be routed to the Chemical Waste Sump.
i -
Beaver Valley Power Station Procedm Nujc.
3 3
Tidle Unit Level Of Usc 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision:
Page Numbc.
'2 46 of 75 ATTACHMIENT G Page 2 of 5 ODCM CONTROLS: LIQUID EFFLUENT CONCENTRATION SURVEILLANCE REQUIREMENTS (continued) 4.11.1.1.4 When BV-2 primary to secondary leakage exceeds 0.1 gpm (142 gpd), samples of the Turbine Building Sump shall be obtained every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to ensure that the Turbine Building Sump concentration does not exceed 1 OEC. Once it is determined that an OEC is reached, the Turbine Building Sump shall be routed to Steam Generator blowdown hold tank (2SGC-TK21A or 2SGC-TK21B).
4.11.1.1.5 Prior to the BV-2 Recirculation Drain Pump(s) (2DAS-P215AIB) discharging to catch basin 16, a grap sample will be taken. The samples will be analyzed for gross activity at a sensitivity of at least 1E-7 uCi/ml. Water volume discharged shall be estimated from the number of pump operations unless alternate flow or volume instrumentation is provided.
- Radioactive liquid discharges are normally via batch modes. BV-1 and BV-2 Turbine Building Drains shall be monitored as specified in ODCM SURVEILLANCE REQUIREMENT 4.11.1.1.3 and 4.11.1.1.4. The BV-2 Recirculation drain pump discharge shall be monitored as specified in ODCM SURVEI LLANCE REQUIREMENT 4.11.1.1.5, respectively.
Procedur Number=
Beaver Valley Power Station 1/2-ODC-3.03 Titke Unit:
Level Of Use:
1/2 GenCral Skill ReferEncm ODCM: Controls for RETS and REMP Programs Revisim Page Number-.
2 47 of 75 ATTACHMENT G Page 3 of 5 ODCM CONTROLS: LIQUID EFFLUENT CONCENTRATION TABLE 4.1 1-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LOWER MINIMUM TYPE OF LIMIT OF LIQUID SAMP1iNG ANALYSIS ACIlVrTY DE CTION RELEASE TYPE FREQUENCYFREQUENCY ANALYSIS (LLD)
(uCi/ml)(a)
A. Batch Waste P
P Principal Gamma 5E-7 Release Tanks(d) Each Batch(h)
Each Batch(@)
Emitters"f)
M Dissolved And 1E-5 One Entrained Gases Batch/M(h)
(Gamma Emitters)
P M
Composite(b)
Gross Alpha 1E-7 P
Q Sr-89, Sr-90 5E-8 Each Batch(h)
Composite(b)
Fe-55 IE-6 B. Continuous Grab Sample(g W
Principal Gamma 5E-7 Releases(eg)
Composite()
Emitters(f)
I-131 IE-6 Grab Sampledg M
Dissolved And IE-5 Entrained Gases
_(Gamma Emitters)
Grab Sampletg M
Gross Alpha 1E-7 Grab Sampledg)
Sr-89, Sr-90 5E-8 Composite(c)
Procedure Number.
Beaver Valley Power Station 1/2-ODC-3.03 l
REac Runit Level Of Uo I
1/2 General Skill Reference ODCM: Controls for RETS and REM? Programs RevioD:
Page Number
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I Rof7 ATTACHMENT G Page 4 of 5 ODCM CONTROLS: LIQUID EFFLUENT CONCENTRATION TABLE 4.11-1 (continued)
TABLE NOTATION (a)
The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% 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=
4.66 Sb (E)(V)(2.22)(Y) exp(-XAI) where:
LLD is the lower limit of detection as defined above (as pCi 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 efficiency (as counts per transformation);
V is the sample size (in units of mass or volume);
2.22 is the number of transformations per minute per picocurie; Y is the fractional radiochemical yield (when applicable);
A is the radioactive decay constant for the particular radionuclide; AT is the elapsed time between sample collection (or end of the sample collection period) and time of counting (for environmental samples, not plant effluent samples).
The value of Sb used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. Typical values of E, V, Y and AT should be used in the calculations.
The LLD is defined as an a priori (before the fact) limit representing the capability of a m
measurement system and not as a posteriori (after the fact) limit for a particular measurement.
.4
Procedure Number.
Beaver Valley Power Station 1/2-ODC-3.03 Mtle:
Unit Level Of Us 1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revson:
Page Number:
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49 of 75 ATTACHMENT G Page 5 of 5 ODCM CONTROLS: LIQUID EFFLUENT CONCENTRATION TABLE4.11-1 (continued)
TABLE NOTATION A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.
(c)
To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected continuously in proportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.
F (d)
A batch release exists when the discharge of liquid wastes is from a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampling.
'e)
A continuous release exists when the discharge of liquid wastes is from a non-discrete volume; e.g., from a volume of a system having an input flow during the continuous release. Releases from the Turbine Building Drains and the AFW Pump Bay Drain System and Chemical Waste Sump are considered continuous when the primary to secondary leak rate exceeds 0.1 gpm (142 gpd).
()
The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be detected and reported.
Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LITD for the analyses should be reported as "less than" the nuclide's LLD, and should not be reported as being present at-the IJ.DI level for that nuclide. The "less than" values should not be used in the required dose calculations. When unusual circumstances result in LLD's higher than required, the reasons shall be documented in the Annual Radioactive Effluent Release Report.
When radioactivity is identified in the secondary system, a RWDA-L should be prepared on a monthly basis to account for the radioactivity that will eventually be discharged to the Ohio River.
(h" Whenever the BV-2 Recirculation Drain Pump(s) are discharging to catch basin 16, sampling will be performed by means of a grab sample taken every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during pump operation.
Beaver Valley Power Station ProCum Numbe Unit LveCl Of Use 1D2 GenPral Sedll Reference ODCM: Controls for RET S and REbP Programs Ngevii Number:
2
.50 of 75
-1 ATTACHMBNT H Page 1 of 1 ODCM CONTROLS: LIQUID EFFLUENT DOSE CONTROLS: LIQUID EFFLUENT DOSE 3.11.1.2 In accordance with BV-1 and BV-2 Technical Specification 6.8.6a, Items 4 and 5, the dose or dose commitment to MEEIBER(S) OF THE PUBLIC from radioactive materials in liquid effluents released from the reactor unit (see 1/2-ODC-2.01 Figure 5-1) shall be limited:
- a.
During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and
- b.
During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.
Applicability.
At all times.
Action:
- a.
With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to 10 CFR 20.2203(a)(2)(v) and 10 CFR 50.4(b)(1), a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce the releases, and the proposed corrective actions to be taken to assure the subsequent releases will be within the above limits. (This Special Report shall also include (1) the results of radiological analyses of the drinking water source and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR 141, Safe Drinking Water Act).*
- b.
The provisions of ODCM CONTROL 3.0.3 are not applicable.
SURVEIELLANCE REQUIREMENTS 4.11.1.2.1 Dose Calculations. Cumulative dose contributions from liquid effluents shall be determined in accordance with 1/2-ODC-2.01 at least once per 31 days.
- Applicable only if drinking water supply is taken from the receiving water body within three miles of the plant discharge (three miles downstream only).
Procedure Number.
Beaver ValleyPower Station 1/2-ODC-3.03
¶rtl.e Uit vel Of WC U
2 General SI Reference ODCM: Controls for RETS and REMP Programs Revision:
Page Number
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fl 51 of 7-5 ATTACHMENT I Page 1 of 1 ODCM CONTROLS: LIQUID RADWASTE TREATMENT SYSTEM CONTROLS: LIQUID RADWASTE TREATMENT SYSTEM 3.11.1.3 In accordance with BV-1 and BV-2 Technical Specification 6.8.6a, Item 6, the Liquid Radwaste Treatment System shall be used to reduce the radioactive materials in each liquid waste batch prior to its discharge when the projected doses due to liquid effluent releases from the reactor unit (see 1/2-ODC-2.01 Figure 5-1) when averaged over 31 days would exceed 0.06 mrem to the total body or 0.2 mrem to any organ.
Applicability:
At all times.
Action:
- a.
With liquid waste being discharged without treatment and exceeding the limits specified, prepare and submit to the Commission within 30 days pursuant to 10 CFR 20.2203(a)(2)(v) and 10 CFR 50.4(b)(1) a Special Report which includes the following information:
- 1.
Identification of the inoperable equipment or subsystems and the reason for inoperability.
- 2.
Action(s) taken to restore the inoperable equipment to operational status, and
- 3.
Summary description of action(s) taken to prevent a recurrence.
- b.
The provisions of ODCM CONTROL 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases shall be projected at least once per 31 days, in accordance with 1/2-ODC-2.01.
Procedure Numb=r Beaver Valley Power Station l/2-ODC-3.03 Mit:
Unit:
Level Of Use:
1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision:
Page Number.
__5___of_75__I 9
ATTACHMENT J Page 1 of 1 ODCM CONTROLS: LIQUID HOLDUP TANKS CONTROLS: LIQUID HOLDUP TANKS 3.11.1.4 In accordance with BV-1 and BV-2 Technical Specification 6.8.6c, the quantity of radioactive material contained in each of the following tanks shall be limited to the values listed below, excluding tritium and dissolved or entrained noble gases.
- a. < 10 Curies: BR-TK-6A (Unit 1 Primary Water Storage Tank)
- b. < 10 Curies: BR-TK-6B (Unit 1 Primary Water Storage Tank)
- c. < 10 Curies: LW-TK-7A (Unit 1 Steam Generator Drain Tank)
- d. < 10 Curies: LW-TK-7B (Unit 1 Steam Generator Drain Tank)
- e. < 4.2 Curies: QS-TK-1 (Unit 1 Refueling Water Storage Tank-RWST)
- f.
< 4.2 Curies: 2QSS-TK21 (Unit 2 Refueling Water Storage Tank-RWST)
- g. < 10 Curies: Unit 1 and Unit 2 miscellaneous temporary outside radioactive liquid storage tanks.
APPLICABILITY: At all times.
ACTION:
- a. With the quantity of radioactive material in any of the above listed tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit, and
- b. Submit a Special Report in accordance with 10 CFR 50.4 (b) (1) within 30 days and include a schedule and a descritpion of activities planned and/or taken to reduce the contents to within the specific limfits.
- c. The provisions ODCM Control 3.0.3 are not applicable.
SURVEILLANCE REQUIIEMENTS 4.11.1.4.1 The quantity of radioactive material contained in each of the above listed tanks (except the Unit 1 and 2 RWST's) shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.
4.11.1.4.2 SINCE additions of radioactive material to the Unit 1 and 2 RWST's are normally made at the end of a refueling outage (i.e.; drain down of the reactor cavity back to the RWST),
THEN compliance to this limit shall be performed as follows:
The quantity of radioactive material contained in the Unit 1 and 2 RWST's shall be determined to be within the above limit by analyzing a representative sample of the tank's contents within 7 days after transfer of reactor cavity water to the respective Unit's RWST.
v Procedure Number.
Beaver Valley Power Station 112-ODC-3.03 Tdlc:
Unit Level Of Use:
1/2 IGeneral Skill Reference ODCM: Controls for RETS and REMP Programs Revision:
Page Number ATTACHMENT K Page I of 4 ODCM CONTROLS: GASEOUS EFFLUENT DOSE RATE CONTROLS: GASEOUS EFFLUENT DOSE RATE 3.11.2.1 In accordance with BV-1 and BV-2 Technical Specification 6.8.6a, Items 3 and 7, the dose rate in the unrestricted areas (see 112-ODC-2.02 Figure 5-1) due to radioactive materials released in gaseous effluents from the site shall be limited to the following values:
- a.
The dose rate limit for noble gases shall be < 500 mrem/yr to the total body and <
3000 mrem/yr to the skin*, and
- b.
The dose rate limit, inhalation pathway only, for I-13 1, tritium and all radionuclides in particulate form (excluding C-14) with half-lives greater than eight days shall be < 1500 mrem/yr to any organ.
Applicability:
At all times.
Action:
- a.
With the dose rate(s) exceeding the above limits, immediately decrease the release rate to comply with the above limits(s), and
- b.
Submit a Special Report to the Commission within 30 days pursuant to 10 CFR 20.2203(a)(2)(v) and 10 CFR 50.4(b)(1).
- c.
The provisions of ODCM CONTROL 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.1.1 The dose rate due to noble gaseous effluents shall be determined to be within the above limits in accordance with 1/2-ODC-2.02.
4.11.2.1.2 The dose rate, inhalation pathway only, for I-131, tritium and all radionuclides in particulate form (excluding C-14) with half-lives greater than eight days in gaseous effluents, shall be determined to be within the above limits in accordance with the methods and procedures of the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in ODCM Control 3.11.2.1, Table 4.11-2.
- During containment purge the dose rate may be averaged over 960 minutes.
Beaver Valley Power Station c
1J/2-ODC-3.03 Title.
Unit Level Of Use:
1/2 General SMtaP Reference ODCM: Controls for RETS and REMP ProgramsRevision:
ftgeofum5w1 ATTACHMENT K Page 2 of 4 ODCM CONTROLS: GASEOUS EFFLUENT DOSE RATE TABLE 4.11-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM MINVIMUM LOWER LIMIT SAMPLING ANALYSIS TYPE OF OF DETECI1ON GASEOUS FREQUENCY FREQUENCY ACTIVITY (LLD) (uCi/ml)(a)
RELEASE TYPE ANALYSIS A. Waste Gas P
P Principal 1E4 Storage Tank Each Tank Each Tank Gamma Grab Sample Emitters(s)
Each Tank*
Each Tank* H-3*
1E-6 Grab Sample B. Containment P
P Principal Gamma 1E-4 Purge Each Purge(b) Each Purge(b)
Emitter(s)
Grab Sample H-3 1E-6 C. Ventilation Mb)(c)(e)
Principal Gamma 1E-4 Systems (h)
Grab Sample Emitters(s)
VV-1 H-3 1E,6 Cv-1 PV-1/2 VV-2 CV-2 DV-2 WV-2 CB-2
- The H-3 concentration shall be estimated prior to release and followed up with an H-3 grab sample from the Ventilation System during release.
Procedure Number.
Beaver Valley Power Station 1/2-ODC-3.03 Title.
Unit:
Level Of Use:
1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision:
Pae Numbe 12 ~
55 of75 ATTACHMENT K Page 3 of 4 ODCM CONTROLS: GASEOUS EFFLUENT DOSE RATE TABLE 4.11-2 (continued)
RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM MINIMUM TYPE OF LOWER lIMIT GASEOUS SAMPLING ANALYSIS ACTIVITY OF DETECTION RELEASE TYPE RQUNCY FREQUENCY ANALYSIS _ LLD) (uCi/ml) '
D. All Systems Continuousw W(d) 1-131 lE-12 Listed Above Charcoal 1-133 lE-10 Which Produce Sample Continuous
()
Vd Redease Continuous d
uWd)
P rincipal Gamma lE-1 1 Particulate Emitters(s)
Sample (1-131, Others)
Continuous(f)
M Gross Alpha lE-1 1 Composite Particulate Sample Continuous(Q Q
Sr-89, Sr-90 1E-l 1 Composite Particulate Sample Continuous(f)
Noble Gas Noble Gases 1E-6 Monitor Gross Beta And Gamma
Procedure Number.
Beaver Valley Power Station 1/2-ODC-3.03 Thde Unit:
Level Of Use.
-1/2 General SIMl Refeec ODCM: Controls for RETS and REMP Progam Revision:
Page Numben1 2 --
56 nf 715 ATTACHME:NT K Page 4 of 4 ODCM CONTROLS: GASEOUS EFFLUENT DOSE RATE TABLE 4.11-2 (continued)
TABLE NOTATION (a)
The Lower limit of Detection (LUD) is defined in Table Notation (a) of ODCM Control 3.11.1.1, Table 4.11-1 for ODCM Surveillance Requirement 4.11.1.1.
(b)
Sampling and analysis shall also be performed following SHUTDOWN, STARTUP, or a THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period. This requirement does not apply if (1) analysis shows that the Dose Equivalent I-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.
All samples or surveillances used to satisfy noteb above shall be obtained within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of reaching the intended steady state power level, and analyzed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of reaching the intended steady state power level.
(C)
Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (from the appropriate ventilation release path) when the refueling canal is flooded.
Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing, or after removal from sampler. Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days following each SHUTDOWN, STARTUP, or THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLIs may be increased by a factor of 10. This requirement does not apply if: (1) analysis shows that the DOSE EQUIVALENT 1-131 concentration in the reactor coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.
')
Tritium grab samples shall be taken at least once per 7 days (from the appropriate ventilation release path of the spent fuel pool area) whenever spent fuel is in the spent fuel pool.
The average ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with ODCM CONTROLS 3.11.2.1, 3.11.2.2, and 3.11.2.3.
(9)
The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LTLD for the analyses should not be reported as being present at the LI:D level for that nuclide. When unusual circumstances result in LLD's higher than required, the reasons shall be documented in the Annual Radioactive Effluent Release Report.
Only when this release path is in use.
Beaver Valley Power Station PeduNu/2ODC-3.03 seT
Unit:Of Use:
12 Geral Skil Referencc ODCM: Controls for RETS and REMP Programs Revision:
Papg Number=
_57__of 75 ATTACHMENT L Page 1 of 1 ODCM CONTROLS: DOSE-NOBLE GASES CONTROLS: DOSE-NOBLE GASES 3.11.2.2 In accordance with BV-1 and BV-2 Technical Specification 6.8.6a, Items 5 and 8, the air dose from the reactor unit in unrestricted areas (see 1/2-ODC-2.02 Figure 5-1) due to noble gases released in gaseous effluents shall be limited to the following:
- a.
During any calendar quarter, to < 5 mrad for gamma radiation and < 10 mrad for beta radiation.
- b.
During any calendar year, to < 10 mrad for gamma radiation and < 20 mrad for beta radiation.
Applicability:
At all times.
Action:
- a.
With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission with in 30 days, pursuant to 10 CFR 20.2203(a)(2)(v) and 10 CFR 50.4(b)(1), a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions taken to reduce the releases and the proposed corrective actions to be taken to assure the subsequent releases will be within the above limits.
- b.
The provisions of ODCM CONTROL 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.2.1 Dose Calculations. Cumulative dose contributions shall be determined in accordance with 112-ODC-2.02 at least once every 31 days.
fl,~ai~.i~1d21~,r Proedure Numba.
BeaverValley Power Station 1/2-ODC-3.03 Td.Uidt:
ULee Of U.=l 1/2_
General Skill Reference ODCM: Controls for RETS and REMP Programs Revision Page Numb 2
58of 75 ATTACHMENT M Page 1 of 1 ODCM CONTROLS: DOSE - RADIOIODINES AND PARTICULATES CONTROLS: DOSE-RADIOIODIES, RADIOACTIVE MATERIAL IN PARTICULATE FORM, AND RADIONUCLIDES OTHER THAN NOBLE GASES 3.11.2.3 In accordance with BV-1 and BV-2 Technical Specification 6.8.6a, Items 5 and 9, the dose to MEMBER(S) OF THE PUBLIC from radioiodines and radioactive materials in particular form (excluding C-14), and radionuclides (other than noble gases) with half-lives greater than eight days in gaseous effluents releases from the reactor unit (see 1/2-ODC-2.02 Figure 5-1) shall be limited to the following:
- a.
During any calendar quarter to S 7.5 mrem to any organ, and
- b.
During any calendar year to < 15 mrem to any organ.
Applicability:
At all times.
Action:
- a.
With the calculated dose from the release of radioiodines, radioactive materials in particulate form, (excluding C-14), and radionuclides (other than noble gases) with half-lives greater than eight days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to 10 CFR 20.2203(a)(2)(v) and 10 CFR 50.4(b)(1), a Special Report, which identifies the cause(s) for exceeding the limit and defines the corrective actions taken to reduce the releases and the proposed corrective actions to be taken to assure the subsequent releases will be within the above limits.
- b.
The provisions of ODCM CONTROL 3.0.3 are not applicable.
SURVEILLANCE REQUREMENTs 4.11.2.3.1 Dose Calculations. Cumulative dose contributions shall be determined in accordance with 1/2-ODC-2.02 at least once every 31 days.
Procedure Number.
Beaver Valley Power Station l/2w-ODC-3.03 Itle:
Unit:
Level Of Us 112 General Skill Refernce ODCM: Controls for RETS and REMP Programs Revison:
Page Number.
2 1
59 of75 ATTACHMENT N Page 1 of 1 ODCM CONTROLS: GASEOUS RADWASTE TREATMENT SYSTEM CONTROLS: GASEOUS RADWASTE TREATMENT SYSTEM 3.11.2.4 In accordance with BV-1 and BV-2 Technical Specification 6.8.6a, Item 6, the Gaseous Radwaste Treatment System and the Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases from the reactor unit (see 1/2-ODC-2.02 Figure 5-1), when averaged over 31 days, would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation. The appropriate portions of the Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases from the reactor unit (see 1/2-ODC-2.02 Figure 5-1) when averaged over 31 days would exceed 0.3 mrem to any organ.
Applicability:
At all times.
Action:
- a.
With gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to 10 CFR 20.2203(a)(2)(v) and 10 CFR 50.4(b)(1), a Special Report which includes the following information.
- 1.
Identification of the inoperable equipment or subsystems and the reason for inoperability,
- 2.
Action(s) taken to restore the inoperable equipment to operational status, and
- 3.
Summary description of action(s) taken to prevent a recurrence.
- b.
The provisions of ODCM CONTROL 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.4.1 Doses due to gaseous releases from the site shall be projected at least once per 31 days, in accordance with 1/2-ODC-2.02.
Beaver Valley Power Station I
.1 AreNu r
^>^
I (b\\-R
I XTie:Unxit Level Of Use:
1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Rcv2oD:
P fi of 75 ATTACHMENT O Page 1 of 1 ODCM CONTROLS: GAS STORAGE TANKS CONTROLS: GAS STORAGE TANKS 3.11.2.5 In accordance with BV-1 and BV-2 Technical Specification 6.8.6c, the quantity of radioactivity contained in the following gas storage tanks(s) shall be limited to the noble gas values listed below (considered as Xe-133).
- a.
<52,000 Curies: Each BV-1 Waste Gas Decay Tank (GW-TK-lA, or GW-TK-1B, or GW-TK-1C)
- b.
<19,000 Curies: Any connected group of BV-2 Gaseous Waste Storage Tanks (2GWS-TK25A thru 2GWS-TK25G)
APPLICABILITY:
At all times.
ACTION:
- a.
With the quantity of radioactive material in any gas storage tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit, nad
- b.
Submit a Special Report in accordance with 10 CFR 50.4 (b)(1) within 30 days and include a schedule and a description of activities planned and/or taken to reduce the contents to within the specified limits.
- c.
The provisions of ODCM Control 3.0.3 are not applicable.
SURVEILLANCE REQUIEMENTS 4.11.2.5.1 For BV-I Waste Gas Decay Tanks: The quantity of radioactive material contained in each BV-I Waste Gas Decay Tank shall be determined to be within the above limit at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when radioactive materials are being added to the tank.
Performance of this surveillance is required when the gross concentration of the primary coolant is greater than 100 uCi/ml.
For BV-2 Gaseous Waste Storage Tanks: The quantity of radioactive material contained in any connected group of BV-2 Gaseous Waste Storage Tanks shall be determined to be within the above limit at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when radioactive materials are being added to the tanks.
Beaver Valley Power Station cur12ODC3.03 nlde:.Unit Level Of Use:
1 2
General Skill Reference ODCM: Controls for RETS and REMP Programs Revision:
Page Number
?
fi61 of 75 ATTACHMENT P Page 1 of 1 ODCM CONTROLS: TOTAL DOSE CONTROLS: TOTAL DOSE 3.11.4.1 In accordance with BV-1 and BV-2 Technical Specification 6.8.6a, Item 10, the annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to < 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to < 75 mrems.
Applicability:
At all times.
Action:
- a.
With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of ODCM CONTROL 3.11.1.2a, 3.11.1.2b, 3.11.2.2a, 3.11.2.2b, 3.11.2.3a, or 3.11.2.3b, calculations shall be made including direct radiation contributions from the units (including outside storage tanks, etc.) to determine whether the above limits of ODCM CONTROL 3.11.4.1 have been exceeded. If such is the case, prepare and submit to the Commission within 30 days, pursuant to 10 CFR 20.2203(a)(2)(v) and 10 CFR 50.4(b)(1), a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR 20.405(c), shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose(s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.
- b.
The provisions of ODCM CONTROL 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.4.1.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with ODCM SURVEILLANCE REQUIR]EENTS 4.11.1.2.1, 4.11.2.2.1, and 4.11.2.3.1.
4.11.4.1.2 Cumulative dose contributions from direct radiation from the units (including outside storage tanks, etc.) shall be determined in accordance with 1/2-ODC-2.04. This requirement is applicable only under conditions set forth in Action a. of ODCM CONTROL 3.11.4.1.
Procedure Number~
Beaver Valley Power Station
/2.:ODC-3.03
Title:
unit.
Level Of Use:
1/2 General Skill Reference -
ODCM: Controls for RETS and REMP Programs Revision:
Page Number 6'2 o 75 ATTACHMENT Q Page 1 of 8 ODCM CONTROLS: REMP-PROGRAM REQUIREMENTS CONTROLS: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 3.12.1 In accordance with BV-1 and BV-2 Technical Specification 6.8.6b, Item 1, the radiological environmental monitoring program shall be conducted as specified in ODCM Control 3.12.1, Table 3.12-1.
Applicability. At all times.
Action:
- a.
With the radiological environmental monitoring program not being conducted as specified in ODCM Control 3.12.1, Table 3.12-1, prepare and submit to the Commission, in the Annual Radiological Environmental Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period.
- b.
With the level of radioactivity in an environmental sampling medium at one or more of the locations specified in ODCM Control 3.12.1, Table 3.12.1 exceeding the limits of ODCM Control 3.12.1, Table 3.12-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days from the end of affected calendar quarter a Special Report pursuant to 10 CFR 20.2203(a)(2)(v) and 10 CFR 50.4(b)(1) which includes an evaluation of any release conditions, environmental factors or other aspects which caused the limits of ODCM Control 3.12.1, Table 3.12-2 to be exceeded. This report is not required if the measured level of radioactive was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Report.
When more than one of the radionuclides in ODCM Control 3.12.1, Table 3.12-2 are detected in the sampling medium, this report shall be submitted if:
Concentration (1)
Concentration (2)
Limit Level (1)
+ Limit Level (2)
+... 21.0
- c.
With milk or fresh leafy vegetable samples unavailable from the required number of locations selected in accordance with ODCM CONTROL 3.12.2 and listed in the ODCM, obtain replacement samples. The locations from which samples were unavailable may then be deleted from those required by ODCM Control 3.12.1, Table 3.12-1 and the ODCM provided the locations from which the replacement samples were obtained are added to the environmental monitoring program as replacement locations, if available.
- d.
The provisions of ODCM CONTROL 3.0.3 are not applicable.
SURVEILLANCE REOUIREMENTS 4.12.1.1 The radiological environmental monitoring samples shall be collected pursuant to ODCM Control 3.12.1, Table 3.12-1 from the locations given in the ODCM and shall be analyzed
-pursuant to be requirements of ODCM Control 3.12.1, Tables 3.12-1 and 4.12-1.
Procedure Number.
Beaver Valley Power Station1/2-ODC-3.03 TitieE:
Unit Levl Of Use.
1 /2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision:
Page Nuber7
_63 of 75 AITACHMENT Q Page 2 of 8 ODCM CONTROLS: REMP-PROGRAM REQUIREMENTS TABLE 3.12-1 RADIOLOGICAL ENVIRONMENTAL MONiTORING PROGRAM EXPOSURE NUMBER OF SAMLING AND TYPE AND FREQUENCYz')
PATHWAY AND/OR SAMPLES AND COLLECTION OF ANALYSIS SAMPLE LOCATIONS FREQUENCY
- 1. AIRBORNE
- a. Radioiodine 5 locations Continuous operation Each radioiodine canister.
And Particulates of sampler with sample
- 1. One sample from a collection at least Analyze for I-131; control location weekly.
10-20 miles distant Particulate sampler.
and in the least Analyze for gross prevalent wind beta weekly (b);
direction Perform gamma isotopic
- 2. One sample from analysis on composite (by vicinity of location) sample at least community having quarterly.
the highest calculated annual average ground level D/Q.
- 2. DIRECI 40 locations Continuous Gamma dose, quarterly.
RADIATION measurement with 2Ž2 TLDs or a pres-collection at least surized ion quarterly.
chamber at each location.
(')Analysis frequency same as sampling frequency unless otherwise specified.
(b)Parculate samples are not counted for 2 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after filter change. Perform gamma isotopic analysis on each sample when gross beta is >10 times the yearly mean of control samples.
- Sample locations are given on figures and tables in 1/2-ODC-2.03.
Procedure Numnber Beaver Valley Power Station j1/2ODC-3b03
Title:
Unit:
Level Of U=
1/2 General Skill Reference ODCM: Controls for RETS and REMIP Programs RevisioD Page Numbenr 2
f64 olf 75 ATTACHMENT Q Page 3 of 8 ODCM CONTROLS: REMP-PROGRA M
REQUIREMENTS TABLE 3.12-1 (continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE NUMBER OFSAMPLING AND TYPE AND FREQUENCY&)
PATHWAY AND/OR SAMPLES AND COLLECTION OF ANALYSIS SAMPLE LOCATIONS**
FREQUENCY
- 3. WATERBORNE
- a. Surface 2 locations.
Composite* sample Gamma isotopic analysis of I. One sample collected over a period composite sample by location upstream.
not to exceed 1 month. monthly;
- 2. One sample Tritium analysis of downstream.
composite sample at least quarterly.
- b. Drinking 2 locations.
Composite" sample 1-131 analysis of each collected over a period composite sample; not to exceed 2 weeks.
Gamma isotopic analysis of composite sample (by location) monthly; Tritium analysis of composite sample quarterly.
- c. Groundwater NIA -
No wells in lower elevations between plant and river
- d. Sediment From 1 location.
f Semi-annually.
Gamma isotopic analysis Shoreline semi-annually.
(')Analysis frequency same as sampling frequency unless otherwise specified.
- Composite samples shall be collected by collecting an aliquot at intervals not exceeding two hours. For the upstream surface water location, a weekly grab sample, composited each month based on river flow at time of sampling, is also acceptable.
- Sample locations are given on figures and tables in 1/2-ODC-2.03.
Procedur Number~
Beaver Valley Power Station 1/2-ODC-3.03 Mitle:
Unit Level Of Use:
1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision:
Page Number ATTACHMNUT Q Page 4 of 8 ODCM CONTROLS: REMP-PROGRAM REQUIEMENTS TABLE 3.12-1 (continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE NUMBER OF SAMPLING AND TYPE AND FREQUENCY(')
PATHWAY AND/OR SAMPLES AND COLLECTION OF ANALYSIS SAMPLE LOCATIONS**
FREQUENCY
- 4. INGESTION
- a. Milc 4 locations.(b)
Atleast bi-weeldywhen Gamma isotopic and 1-131 animals are on pasture; analysis of each sample.
- 1. Three samples at least monthly at selected on basis of other times.
highest potential thyroid dose using milch census data.
- 2. One local large dairy.
- b. Fish 2 locations.
Semi-annual. One Gamma isotopic analysis on sample of available edible portions.
species.
- c. Food Products 4 locations.
Annually at time of Gamma isotopic analysis and (Leafy harvest.
I-131 analysis on edible Vegetables)
- 1. Three locations portion.
within 5 miles.
- 2. One control location.
a)Analysis frequency same as sampling frequency unless otherwise specified.
(b)Other dairies may be included as control station or for historical continuity. These would not be modified on basis of milch animal census.
- Sample locations are given on figures and tables in 1/2-ODC-2.03.
Procedue Number:
Beaver Valley Power Station 1/2-ODC-3.03 ODCM: Controls for RETS and REMP Programs Rcvisioi:
PeI OfNume Rev66on Pfe N 7be ATTACHMENT Q Page 5 of 8 ODCM CONTROLS: REMP-PROGRAM REQUIREMENTS TABLE 3.12-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES R PORTING LEVELS AIRBORNE BROAD LEAP WATER PARTICULATE OR FISH MILK VEGETABLES ANALYSIS (pCi/1)
GASES (pCi/m)
(pCi/kg, WE)
(pCi/I (pCi/kg, WET)
H-3 2E+4('
Mn-54 1E+3 3E+4 Fe-59 4E+2 1E+4 Co-S8 1E+3 3E+4 Co-60 3E+2 1E+4 Zn-65 3E+2 2E+4 Zr/Nb-95 4E+2 I-131 2(b) 0.9 3
1E+2 Cs-134 30 10 1E+3 60 1E+3 Cs-137 50 20 2E+3 70 2E+3 Ba/La-140 2E+2 3E+2
(') For drinking water sanples. This is a 40 CFR Part 141 value. If no drinking water pathway exists, a value of 3E+4 pCi/i may be used.
) If no drinking water pathway exists, a value of 20 pCill may be used.
Procedure Number:
Beaver Valley Power Station 1/2..ODC3.03
'ride:
Unit:
Level Of Use-112 General SkIll Reference ODCM: Controls for REMS and REMP Programs Revision:
Pa7eof 75 ATTACHMENT Q Page 6 of 8 ODCM CONTROLS: REMP-PROGRAM REQUIREMENTS TABLE 4.12-1 MAXIMUM VALUEFS FOR THE LOWER LMS OF DETECTION (LlDP)(e AIRBORNE PARTICULATE FOOD ANALYSIS WATER OR GAS FISH MILK PRODUCTS SEDIMENT (Pa/1)
(pCi/m3)
(pCi/kg, WET)
(pCi/l)
(pCi/kg, WET)
(pCi/kg, DRY)
Gross Beta 4
1E-2 H-3 20W0O4 Mn-54 15 130 Fe-59 30 260 Co-58,60 15 130 Zn-65 30 260 Zr-95 30(c)
Nb-95 15(c) 1-131 I(b) 7E-2 1
60 Cs-134 15 5E-2 130 15 60 150 Cs-137 18 6E-2 150 18 80 180 Ba-140 60(c) 60 La-140 15(c) 15
Pmoccdmr Number Beaver Valley Power Station 1/2-ODC-3.03 rode:euit Level Of U=
112 General Skill Reference ODCM: Controls for RETS and REMP Programs Reviain Page Numb=
68of7 ATTACHMENT Q Page 7 of 8 ODCM CONTROLS: REMP-PROGRAM REQUIREMENTS TABLE 4.12-1 (continued)
TABLE NOTATION (a) The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% 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 =
4.66 Sb (E)(V)(2.22)(Y) exp (-XA&')
where:
LLD is the lower limit of detection as defined above (as pCi 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 efficiency (as counts per transformation);
V is the sample size (in units of mass or volume);
2.22 is the number of transformations per minute per picocurie; Y is the fractional radiochernical yield (when applicable);
X is the radioactive decay constant for the particular radionuclide; AT is the elapsed time between sample collection (or end of the sample collection period) and time of counting (for environmental samples, not plant effluent samples).
The value of Sb used in the calculation of the LI]) for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate ) rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples (e.g., potassium40 in milk samples). Typical values of E, V, Y and AT should be used in the calculations.
Procedure Numbe=
Beaver Valley Power Station 1/2-ODC-3.03
Title:
Unit:
Level Of Use:
1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision Page Number:
2 69 of 75 ATfTACHNqT Q Page 8 of 8 ODCM CONTROLS: REMP-PROGRAM REQUIREMENTS TABLE 4.12-1 (continued)
TABLE NOTATION The LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as 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 interfering nuclides, or other uncontrollable circumstances may render these LLD's unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Report.
(b)
If no drinking water pathway exists, a value of 15 pCi/I may be used.
(e)
If parent and daughter are totaled, the most restrictive LU) should be applied.
(d)
If no drinking water pathway exists, a value of 3000 pCi/I may be used.
(e) This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall be identified in the Annual Radiological Environmental Report.
I Pro~cedure Number.
Beaver Valley Power Station 1/2-ODC-3.03
- 1e Unit:
Level Of Use:
.112 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision:
Page Numbec 70_of_7_5 1
I i
ATTACHMENT R Page 1 of 1 ODCM CONTROLS: REMP - LAND USE CENSUS II CONTROLS: RADIOLOGICAL ENVIRONMENTAL MONITORING - LAND USE CENSUS 3.12.2 In accordance with BV-1 and BV-2 Technical Specification 6.8.6b, Item 2, a land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 square feet producing broad leaf vegetation in each of the 16 meteorological sectors within a distance of five miles.
For elevated releases as defined in Regulatory Guide 1.111, (Rev. 1), July, 1977, the land use census shall also identify the locations of all milk animals and all gardens of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of three miles.
Applicability: At all times.
Action:
- a.
With a land use census identifying a location(s) which yields a calculated dose or dose commitment greater than the values currently being calculated in ODCM SURVEILLANCE REQUIMENT 4.11.2.3.1, prepare and submit to the Commission within 30 days, pursuant to 10 CFR 20.2203(a)(2)(v) and 10 CFR 50.4(b)(1), a Special Report, which identifies the new location(s).
T --
L -
t i
i
- b.
With a land use census identifying a milk animal location(s) which yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained in accordance with ODCM CONTROL 3.12.1 prepare and submit to the Commission within 30 days, pursuant to 10 CFR 20.2203(a)(2)(v) and 10 CFR 50.4(b)(1), a Special Report, which identifies the new location. The new location shall be added to the radiological environmental monitoring program within 30 days, if possible. The milk sampling program shall include samples from the three active milk animal locations, having the highest calculated dose or dose commitment. Any replaced location may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted.
- c.
The provisions of ODCM CONTROL 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.12.2.1 The land use census shall be conducted at least once per 12 months between the dates of June 1 and October 1 using that information which will provide the best results, such as by a door-to-door survey*, aerial survey, or by consulting local agriculture authorities.
- Confirmation by telephone is equivalent to door-to-door.
Beaver Valley Power Station cu 2-ODC-3.03 Tide:
Unit level Of Use:
1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision:
Page Number.
ATTACHMENT S Page 1 of 1 ODCM CONTROLS: REMP - INTERLABORATORY COMPARISON PROGRAM CONTROLS: RADIOLOGICAL ENVIRONMENTAL MONITORING - INTERLABORATORY COMPARISON PROGRAM 3.12.3 In accordance with BV-1 and BV-2 Technical Specification 6.8.6b, Item 3, analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program.
Applicability At all times.
Action:
- a.
With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Report.
- b.
The provisions of ODCM CONTROL 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.12.3.1 The results of analyses performed as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Report.
Procedure Number.
Beaver Valley Power Station 1/2-ODC-3.03 ITife Unit:
Level Of Use:
1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision:
Page Number.
272 of 75 ATTACHMENT T Page 1 of 2 ODCM CONTROLS: ANNUAL REMP REPORT CONTROLS: ANNUAL REMP REPORT ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (3) 6.9.2 (old TS 6.9.1.10)
The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 15 of each year.
The report shall include summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM) and in 10 CFR Part 50 Appendix I Sections IV.B.2, IV.B.3, and IV.C.
The annual radiological environmental reports shall include:
- Summaries, interpretations, and statistical evaluation of the results of the radiological environmental surveillance activities for the report period, including a comparison with pre-operational studies, operational controls (as appropriate), and previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment.
- The results of the land use censuses required by ODCM CONTROL 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.
- Summarized and tabulated results in the format of ODCM Control 6.9.1.10, Table 6.9-1 of all radiological environmental samples taken during the report period.
In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.
- A summary description of the radiological environmental monitoring program.
- A map of all sampling locations keyed to a table giving distances and directions from one reactor.
- The results of licensee participation in the Interlaboratory Comparison Program required by ODCM CONTROL 3.12.3.
(3)
A single submittal may be made for a multiple unit site. The submittal should combine those sections that are common to all units at the station.
C
(
(
Y TABLE 1
E:6.91 ENVIRONMENTaAL RADIOOGCAL MONITRIN PROGRAM
SUMMARY
0 0
0 0
'81 II Namoe Of Facility Docket No.
Reporting Petiod Location Of Facility (Coumty, state)
MEDIUM OF TYPE AND LOWER ALL LOCAONS0 WITH HGHST CONTROL NONROUTINE PATHWAYA S
M TOTALLNUME LIMTS OF INDICATOR ANNUALMEAN LOCATIONS REPORTED (UMTOF OF ANALYSES DUTECTION LOCATIONS NAME DI C
MEN R
MEASUREMUR PIhIED (lUD)
MANJ AND DIRCTIAON RMNC(e Nomin Lower limts of Dettion (.LD) s defined inT able Notston *fl Table 4.12.1 of ODCM CONTROL 3.11.1.1.
Mean and rnge based Mpondeble meaemet only. Fracdon of deteable easuemwn at specfi locao Is Indicaed In purendis (f).
0 0.
I 0Q E. A
..p,
EB I
- Beaver Valley Power Station 1/2-ODC-3.03 1/
Geneal Skil Reference-ODCM: Controls for RETS and REMP Programs Revsion:
74 ou S ATTACHMENT U Page 1 of 2 ODCM CONTROLS: ANNUAL RETS REPORTS CONTROLS: ANNUAL RETS REPORT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (4) 6.9.3 The Annual Radioactive Effluent Release Report (ARERR) covering the operation of the (old TS 6.9. 1.1 1) unit during the previous year shall be submitted prior to May 1 of each year in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM and Process Control Program (PCP) and in conformance with 10 CFR 50.36a and 10 CFR Part 50, Appendix I Section IV.B.1.
This report is prepared and submitted in accordance with 1/2-ENV-01.05, and at a minimum, shall contain the following:
- A summary of the quantities of radioactive liquid and gaseous effluent and solid waste released from the unit as outlined in Regulatory Guide 1.21, Revision 1, June, 1974, "Measuring, Evaluating, And Reporting Radioactivity In Solid Wastes And Releases Of Radioactive Materials In Liquid And Gaseous Effluents From Light-Water-Cooled Nuclear Power Plants," with data summarized on a quarterly basis following the format of Appendix B thereof.
- An assessment of radiation doses from the radioactive liquid and gaseous effluents released from the unit during each calendar quarter as outlined in Regulatory Guide 1.21. In addition, the unrestricted area boundary maximum noble gas gamma air and beta air doses shall be evaluated. The assessment of radiation doses shall be performed in accordance with this manual.
- Any licensee initiated changes to the ODCM made during the 12 month period.
- Any radioactive liquid or gaseous effluent monitoring instrumentation channels not returned to OPERABLE status within 30 days, and why the inoperability was not corrected in a timely manner. This applies to the liquid or gaseous effluent monitoring instrumentation channels required to be OPERABLE per ODCM CONTROLS 3.3.3.9 and 3.3.3.10.
- Any ODCM SURVEILLANCE REQUREMENT deficiencies. This applies to monitoring, sampling and analysis and dose projection.
- The reasons when unusual circumstances result in LLD's higher than required by ODCM CONTROL 3.11.1.1, Table 4.11-1 and ODCM CONTROL 3.11.2.1, Table 4.11-2.
(4)
A single submittal may be made for a multiple unit site. The submittal should combine those sections.that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.
Beaver Valley Power Station 1/dum3Number lUnit Level Of Use:
1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision Page Numb in27of7 ATTACHMENT U Page 2 of 2 ODCM CONTROLS: ANNUAL RETS REPORTS CONTROLS: ANNUAL RETS REPORT (continued)
The following information for each type of solid waste shipped offsite during the report period:
- container volume
- total curie quantity (determined by measurement or estimate)
-principal radionuclides (determined by measurement or estimate)
- type of waste (e.g., spent resin, compacted dry waste, evaporator bottoms) i
- type of container (e.g., LSA, Type A, Type B, Large Quantity)
- solidification agent (e.g., cement)
- classification and other requirements specified by 10 CFR Part 61
- An annual summary of hourly meteorological data collected over the previous year.
This annual summary may be either in the form of an hour-by-hour listing of wind speed, wind direction, atmospheric stability, and precipitation (if measured) on magnetic tape, or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability.
- An assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year.
- An assessment of the radiation doses from radioactive effluents to MEMBER(S) OF THE P`UBLIC due to their activities inside the site boundary see 1/2-ODC-2.01 Figure 5.1 and 1/2-ODC-2.02 Figure 5-1 during the report period. All assumptions used in making these assessments (e.g., specific activity, exposure time, and location) shall be included in these reports. The assessment of radiation doses shall be performed in accordance with 1/2-ODC-2.04.
- An assessment of radiation doses to the likely most exposed real individual from reactor releases for the previous calendar year to show conformance with 40 CFR 190, Environmental Radiation Protection Standards For Nuclear Power Operation.
Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Revision 1. The SKYSH]NE Code (available from Radiation Shielding Information Center, (ORNL)) is acceptable for calculating the dose contribution from direct radiation due to N-16.
- If quantities of radioactive materials released during the reporting period are significantly above design objectives, the report must cover this specifically.