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Rev. 9 to ODCM: Radiological Environmental Monitoring Program
	ML19123A267
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Site:	Beaver Valley
Issue date:	01/22/2018
From:	; FirstEnergy Nuclear Operating Co
To:	; Office of Nuclear Reactor Regulation
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ML19123A268	List: L-19-113, Rev. 9 to ODCM: Radiological Environmental Monitoring Program; ML19123A260; ML19123A261; ML19123A262; ML19123A265; ML19123A266;
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RTL #A9.621B Beaver Valley Power Station Unit 1/2 l/2-0DC-2.03 ODCM: Radiological Environmental Monitoring Program Document Owner Manager, Nuclear Environmental and Chemistry Revision Number 9

Level Of Use General Skill Reference Safety Related Procedure Yes Effective Date 01/22/18

Beaver Valley Power Station Procedure Number:

l/2-0DC-2.03

Title:

Unit:

Level Of Use:

ODCM: Radiological Environmental Monitoring Program 1/2 General Skill Reference Revision:

Page Number:

9 2 C\\f?4 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 LIMITATIONS.......................................................................................... 4 5.1 Precautions............................................................................................................................. 4 5.2 Limitations.............................................................................................................................. 4 6.0 ACCEPTANCE CRITERIA............................................................................................................. 5 7.0 PREREQUISITES............................................................................................................................ 5 8.0 PROCEDURE........................................................................................................................... *........ 5 8.1 REMP Overview.................................................................................................................... 5 8.2 Sampling and Analysis Program............................................................................................ 5 8.3 Crosscheck Program............................................................................................................... 6 8.4 Land Use Census Program..................................................................................................... 7 8.5 Direct Radiation Monitoring Program.................................................................................... 8 ATTACHMENT A EXPOSURE PATHWAY AND SAMPLING REQUIREMENTS....................... 9 ATTACHMENT B LOCATION OF SAMPLING SITES.................................................................. 13

Beaver Valley Power Station Procedure Number:

l/2-0DC-2.03

Title:

Unit:

Level Of Use:

ODCM: Radiological Environmental Monitoring Program 1/2 General Skill Reference Revision:

Page Number:

9 3 nf?4 PURPOSE 1.0 1.1 This procedure provides documentation of the Radiological Environmental Monitoring Program (REMP) as specified in the Radiological Branch Technical Position.<3.1.1) 2.0 2.1 3.0 3.1 SCOPE This procedure is applicable to liquid and gaseous effluents at Beaver Valley Power Station.

REFERENCES AND COMMITMENTS References 3.1.1 Radiological Environmental Monitoring Program Requirements-Enclosing Branch Technical Position, Revision 1, (Generic Letter 79-65) 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 Gµidance; Standard Radiological Effluent Controls for Pressurized Water Reactors (Generic Letter 89-01, Supplement No. 1).

3.1.4 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.

3.1.5 1/2-ADM-1640, Control of the Offsite Dose Calculation Manual 3.1.6 l/2-ADM-0100, Procedure Writers Guide 3.1.7 1/2-ADM-0101, Review and Approval of Documents 3.1.8 CR 04-00149, Radiation Protection P~rformance Committee Actions Items. CA-12 required obtaining GPS satellite data for use in the REMP.

3.1.9 CR 05-01169, Chemistry Action Plan for transition of RETS, REMP and ODCM.

CA-17, revise procedure l/2-0DC-2.03 to convert Radiation Protection responsibilities to Nuclear Environmental and Chemistry.

3.1.10 CR 05-01390, Include GPS data in 2004 REMP Report and related 1/2-0DC and 1/2-ENV procedures. CA-02, revise ODCM procedure l/2-0DC-2.03 to include an update ofREMP sample locations (using the GPS Satellite data).

3.1.11 CR 10-77489, Fixed incorrect sample designations for TLD #94 and #95; changed sample point designation #49 to #49A; clarified garden sampling requirements.

3.1.12 CA G203-2011-97516-001, Retire TLD Station #88 and add Station #88A.

Beaver Valley Power Station Procedure Number:

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Title:

Unit:

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ODCM: Radiological Environmental Monitoring Program 1/2 General Skill Reference Revision:

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C) 4 of?.4 3.1.13 CR G203-2011-02332, Inability to meet ODCM requirements for REMP milk sampling in 2011 and CA G203-2011-02332-1, Make changes to the ODCM.

3.1.14 CR G203-2013-03554, Reduction in milk sample location, in 2013 Searight's Dairy farm stopped producing milk and permanently closed.

3.1.15 10 CFR 72.104, Criteria for Radioactive Materials in Effluents and Direct Radiation from an ISFSI or MRS.

3.1.16 CR-2016-10379, MS-C-16-08-02: 2014 and 2015 REMP Report Issues, Update REMP sample location maps.

3.1.17 SAP Notification 60101863 8, Task 10, Site 2.1, A TI Allegheny Ludlum - Closed.

I Revision 8 updates the waterborne surface sample location from #2.1 (A TI Allegheny Ludlum, Midland) to #5 (East Liverpool Water Department. Milk sample location #114, Covert residence, was added to Table 3.0-1 and the table corresponding to Figure 3.0-4.

Maps for these locations were updated with changes.

3.2 Commitments 3.2.1 10 Code of Federal Regulations (CFR) 50 Appendix I 4.0 RECORDS AND FORMS 4.1 Records 4.1.1 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 Precautions 5.1.1 None 5.2 Limitations 5.2.1 None

Beaver Valley Power Station Procedure Number:

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Title:

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ODCM: Radiological Environmental Monitoring Program 1/2 General Skill Reference 6.0

6.1 Revision

Page Number:

9 5 nf24 ACCEPTANCE CRITERIA Changes to this procedure shall contain sufficient justification that the change will maintain the level ofradioactive effluent control required by 10 CPR 20.1302, 40 CPR Part 190, 10 CPR 50.36a, 10 CPR 72.104 and Appendix I to 10 CPR 50, and not adversely impact the accuracy or reliability of effluent dose or alarm setpoint calculation.

6.1.1 Changes to this procedure shall be prepared in accordance with 1/2-ADM-0100, PROCEDURE WRITER'S GUIDE (3.1.6) and l/2-ADM-1640, CO;NTROL OF THE OFFSITE DOSE CALCULATION MANUAL. (3.u).

6.1.2 Changes to this procedure shall be reviewed and approved in accordance with NOP-SS-3001, PROCEDURE REVIEW AND APPROVAL (3.1.1) and 1/2-ADM-1640c3.1.s).

7.0 PREREQUISITES 7.1 None 8.0 PROCEDURE 8.1 REMP Overview 8.2 8.1.1 Attachment A, Table 3.0-1 presents the exposure pathways and sampling and monitoring requirements for Beaver Valley Power Station Radiological Environmental Monitoring Program (REMP). The attachment provides details on 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.

8.1.2 Attachment B, Figures 3. 0-1 through 3. 0-6 show the location of the various sampling points.

Sampling and Analysis Program 8.2.1 Environmental samples shall be collected and analyzed according to Attachment A, Table 3.0-1. Analysis methods used shall be capable of achieving the detection capabilities in l/2-0DC-3.03, Table 4.12-1.

8.2.2 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.

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.

Beaver Valley Power Station Procedure Number:

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ODCM: Radiological Environmental Monitoring Program 1/2 General Skill Reference 8.3 8.2.2.2 Revision:

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g 6 of'J.:1 The initial radiological environmental monitoring program should be conducted for the first three (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 from the required sampling schedule are acceptable if samples cannot be obtained because of hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment, and other legitimate reasons.

8.2.3.1 8.2.3.2 If samples cannot be obtained due to sampling equipment malfunction then every effort shall be made to complete corrective action to restore equipment prior to the end of the next sampling period.

All Deviations from the sampling schedule shall be documented in the annual REMP report.

Crosscheck Program 8.3.1 Laboratories performing analysis for the purposes of the Radiological Environment Monitoring (REMP) program shall participate in the Environmental Protection Agency's (EPA' s) Environmental Radioactivity Laboratory Intercomparisons Studies (Crosscheck) Program or equivalent program. Laboratories include those of the licensee and laboratories contracted by the licensee 8.3.1.1 8.3.1.2 8.3.1.3 Participation in the crosscheck program shall include all of the determinations (sample medium-radionuclide combination) that are offered by EPA and that also are included in the monitoring program.

The results of analysis of the crosscheck samples shall be included in the annual REMP report. The participants in the crosscheck program may provide their program code to the Nuclear Regulatory Commission (NRC) so that crosscheck data may be reviewed directly in lieu of submission in the annual REMP report.

If any results of the crosscheck program are outside the specified control limits, then the laboratory shall investigate the cause of the problem and take appropriate corrective action to resolve the discrepancy. The results of any investigation and corrective actions taken shall be included in the annual REMP report.

8.3.2 Participation in the crosscheck program is based upon the need to perform independent checks to validate precision and accuracy of the measurements ofradioactive material in environmental sample matrices. This participation is part of the quality assurance program for environmental monitoring in order to demonstrate the results are reasonably valid.

Beaver Valley Power Station Procedure Number:

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9 7 of?4 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 fifty (50) square meters (500 sq. ft.) producing broad leaf vegetation in each of the sixteen (16) meteorological sectors within a distance of eight (8) km (5 miles).

8.4.1.1 8.4.1.2 8.4.1.3 8.4.1.4 8.4.1.5 8.4.1.6 8.4.1.7 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 fifty (50) square meters producing broad leaf vegetation out to a distance of five (5) km (3 miles) for each radial sector.

If the land use census determines 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 land use census results in changes in the location used in Off site Dose Calculation Manual (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 thirty (30) days identifying the new location

( distance and direction).

Milk animal or garden locations resulting in higher calculated doses shall be added to the surveillance program as soon as practicable. 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.

The results of the land-use census shall be reported in the annual REMP report.

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*1) 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.

If the land use census reveals milk animals are not present or are unavailable for sampling then vegetation must be sampled.

The fifty (50) square meter garden, considering twenty (20) % used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and a vegetation yield of two (2) kg/m2, will produce the twenty-six (26) kg/yr assumed in Regulatory Guide 1.109 <3* 1 *2), for child consumption of leafy vegetation.

Beaver Valley Power Station Procedure Number:

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9 R of'?Ll.

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 l/2-0DC-3.03, Table 3.12-1.

-END-I

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TABLE 3.0-1 u~

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PROGRAM DETAILS

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MILES2 SAMPLE POINT DESCRIPTION3 SAMPLE NO.

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1. AIRBORNE 13 11 1.49 Old Meyer Farm Continuous Radioiodine Cartridge:

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0.43 Shippingport (Cook's Ferry S.S.)

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r.n 46.1 2/3 2.28 Industry, McKeel's Service - Rt. 68 least weekly Particulate Sampler:

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14 11 2.53 Hookstown Boro quarterly

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32 15 0.75 Midland (North S.S.)

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3.25 Ohioview Lutheran Church - Rear Continuous Gamma dose quarterly. *

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3.80 Raccoon Elementary School

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5.52 3614 Green Garden Road (1)

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4.46 106 Rt. 151 - Ted McWilliams

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89 15 4.72 488 Smith Ferry Rd., Ohioville 0

90 16 5.20 6286 Tuscarawas Rd.

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4. INGESTION 27 7

6.16 Brunton's (large local dairy)

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114 11 1.9 Covert Residence on pasture; at least C

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EXPOSURE PATHWAY AND/OR SAMPLE TABLE 3.0-1 (continued)

PROGRAM DETAILS SITE SECTOR1 MILES2 SAMPLE POINT NO.

DESCRIPTION3 1 Sector numbers 1-16 correspond to the 16 compass direction sectors N - NNW.

I SAMPLING AND COLLECTION FREQUENCY 2Distance (in miles) is as measured from the midpoint between Unit I and Unit 2 Containment Buildings.

TYPE AND FREQUENCY OF ANALYSES 3All Sample Points are in the Commonwealth of Pennsylvania and the states of Ohio and West Virginia. Maps showing the approximate locations of the Sample Points are provided as Attachment B, Figures 3.0-1 through 3.0-6 and Attachment C.

4This is a Control Station and is presumed to be outside the influence ofBVPS 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.

6Composite samples are obtained by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . For the upstream surface water location site 49A, a weekly grab sample, composited each month is also acceptable.

7 Collection 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.

8These Sample Points will vary and are chosen based upon calculated annual deposition factors (highest)..

9 Exact location may vary due to availability of food products.

10 When ODCM milk sample requirements are met, one type of broad leaf vegetation is to be sampled from the three (3) indicator locations and one (1) control location.

11 When there are not enough milk sample locations available to meet the ODCM requirements, three (3) different types of broad leaf vegetation are to be sampled at each of two (2) indicator locations based on the highest predicted annual average ground D/Q (as determined from the previous year's Land Use Census results), in addition to those samples described in Note 10. Three (3) different types of broad leaf vegetation shall also be sampled at one (1) control location when in this condition.

12 The primary sources of broad leaf vegetation are cabbage or lettuce. However, other acceptable substitutes are vegetables having leaves with large surface area, to be combined with the edible portion of the plant for analysis.

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Beaver Valley Power Station

Title:

ODCM: Radiological Environmental Monitoring Program

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[EQJ ATTACHMENT B Page 1 of 12 LOCATION OF SAMPLING SITES FIGURE 3.0-1 AIR SAMPLING LOCATIONS

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mn Weirton Control Site, #48 Sector 10 - 16.40 mi not shown.

Procedure Number:

l/2-0DC-2.03 Unit:

Level Of Use:

1/2 General Skill Reference Revision:

Page Number:

rn.m A

S mi plant radius

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9 14 nf24 ATTACHMENT B Page 2 of 12 LOCATION OF SAMPLING SITES FIGURE 3.0-1 (Continued}

AIR SAMPLING LOCATIONS Sector Site #

Distance (miles) Location 11 13 1.49 Old Meyer Farm 4

30 0.43 Shippingport (Cook's Ferry S.S.)

15 32 0.75 Midland (North S.S.)

2/3 46.1 2.28 Industry - McKeel's Service - Rt. 68 10 48 16.40 Weirton Water Tower, Collier Way

Beaver Valley Power Station

Title:

ODCM: Radiological Environmental Monitoring Program ATTACHMENT B Page 3 of 12 LOCATION OF SAMPLING SITES FIGURE 3.0-2 Weirton Control Site, #48 Sector 10 - 16.40 mi not shown 1LD LOCATIONS Procedure Number:

l/2-0DC-2.03 Unit:

Level Of Use:

l/2 General Skill Reference Revision:

Page Number:

A 5 mi plant radius

]Ni'

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9 16nf?4 ATTACHMENT B Page 4 of 12 LOCATION OF SAMPLING SITES FIGURE 3.0-2 (continued)

TLD LOCATIONS Southeast Sector Site# Distance Location Sector Site# Distance Location (miles)

(miles) 7 27 6.16 Brunton Farm 7

78 2.72 Raccoon Municipal Bldg.

6 45.1 1.92 Raccoon Twp., Kennedy Comers 8

79 4.46 106 Rt. 151-Ted McWilliams Auto Body 5

51 8.00 Aliquippa (Sheffield S.S.)

9 80 8.27 Raccoon Park Office, Rt. 18 6

59 0.99 236 Green Hill Road 9

82 6.99 2697 Rt. 18 6

76 3.80 Raccoon Elementary School 8

94 2.25 McCleary & Pole Cat Hollow Roads 6

77 5.52 3614 Green Garden Road Northwest Sector Site# Distance Location Sector Site # Distance Location (miles)

(miles) 14 15 3.75 Georgetown Post Office 14 87 7.04 50103 Calcutta Smith's Ferry Rd.

15 32 0.75 Midland (North S.S.)

15 88A 2.8 Route 168; Midland Hei_ghts 14 47 4.88 E. Liverpool Water Dept.

15 89 4.72 488 Smith Ferry Rd., Ohioville 13 60 2.51 444 Hill Road 16 90 5.20 6286 Tuscarawas Rd.

13 86 6.18 I 090 Ohio Avenue, E. Liverpool 16 93 1.10 I 04 Linden - Sunrise Hills Northeast Sector Site # Distance Location Sector Site# Distance Location (miles)

(miles) 3/4 10 0.94 Shippimmort Post Office I

70 3.36 236 Engle Rd.

1 28 8.60 Sherman Farm 2

71 6.01 Brighton Twp., Huntington Bank 3

29B 7.97 Friendship Ridge 3

72 3.25 Ohioview Luthem Church - Rear 4

30 0.43 Shiooimmort (Cook's Ferry S.S.)

4 73 2.48 618 Squirrel Run Rd.

5 45 2.19 Christian House Baptist 4

74 6.92 137 Poplar Ave. - CCBC Chapel - Rt 18 46 2.49 industry, Midway Dr.

5 75 4.08 117 Holt Rd.

.)

2/3

46. 1 2.28 Industry - McKeel's Service -

2 91 3.89 Pine Grove Rd. & Doyle Rd.

Rt68 Southwest Sector Site# Distance Location Sector Site# Distance Location (miles)

(miles) 11 13 1.49 Old Meyer Farm 11 84 8.35 Hancock Co. Senior Center 11 14 2.53 Hookstown Boro 12 85 5.73 2048 Rt. 30 10 48 16.40 Weirton Water Tower, Collier 12 92 2.8 1 Georgetown Rd. (Georgetown S.S.)

Way 9

81 3.69 Millcreek United Presbv. Church 10 95 2.37 832 McCleary Rd.

10 83 4.26 735 Mill Creek Rd.

Beaver Valley Power Station

Title:

ODCM: Radiological Environmental Monitoring Program ATTACHMENTB Page 5 of 12 LOCATION OF SAMPLING SITES FIGURE 3.0-3 Procedure Number:

l/2-0DC-2.03 Unit:

Level Of Use:

1/2 General Skill Reference Revision:

Page Number:

SHORELINE SEDIMENT, SURF ACE WA1ER, AND DRINKING WATER SAMPLING LOCATIONS

§)

I 5 mi plant radius

Beaver Valley Power Station Procedure Number:

l/2-0DC-2.03

Title:

Unit:

Level Of Use:

ODCM: Radiological Environmental Monitoring Program 1/2 General Skill Reference Revision:

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9 18 of ? 4 ATTACHMENT B Page 6 of 12 LOCATION OF SAMPLING SITES FIGURE 3.0-3 (Continued)

SHORELINE SEDIMENT, SURFACE WAIERAND DR1NKING WATERSAMPLlNG LOCATIONS Sample Type Sector Site# Distance (miles)

Location Surface Water 14 5

4.90 East Liverpool Water Dept.

Surface Water 3

49A 4.93 Upstream of Montgomery Dam Sediment 12 2A 0.31 BVPS Outfall Vicinity Sediment*

3 49A 4.93 Upstream of Montgomery Dam Drinking Water 15 4

1.26 Midland Water Dept.

Drinking Water 14 5

4.90 East Liverpool Water Dept.

Site added as control site

Beaver Valley Power Station

Title:

ODCM: Radiological Environmental Monitoring Program ATTACHMENT B Page 7 of 12 LOCATION OF SAMPLING SITES FIGURE 3.0-4 MILK SAMPLING LOCATIONS Windsheimer Farm Control Site, #96 Sector 10 - 10.48 mi not shown l!.l ppm po Procedure Number:

Unit:

1/2 Revision:

l/2-0DC-2.03 Level Of Use:

General Skill Reference Page Number:

CH A 5 mi plant radius N~

Beaver Valley Power Station Procedure Number:

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Title:

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Level Of Use:

ODCM: Radiological Environmental Monitoring Program 1/2 General Skill Reference Revision:

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9

?0 of ?4 ATTACHMENT B Page 8 of 12 LOCATION OF SAMPLING SITES FIGURE 3.0-4 (Continued)

MILK SAMPLING LOCATIONS Sector Site# Distance (miles)

Location 7

27 6.16 Brunton' s Dairy 10**

96 10.48 Windsheimer Farm 11 114 1.9 Covert Residence

Three dairies based on highest deposition factors.

- Control Location.

Beaver Valley Power Station

Title:

ODCM: Radiological Environmental Monitoring Program ATTACHMENT B Page 9 of 12 LOCATION OF SAMPLING SITES FIGURE 3.0-5 FOODCROP SAMPLING LOCATIONS I ook.. to Weirton Control Site, #48 Sector 10, 16.40 mi not shown Midi d Procedure Number:

l /2-0DC-2.03 Unit:

Level Of Use:

1/2 General Skill Reference Revision:

Page Number:

~

A 5 mi plant radius N

~

Beaver Valley Power Station Procedure Number:

l/2-0DC-2.03

Title:

Unit:

Level Of Use:

ODCM: Radiological Environmental Monitoring Program 1/2 General Skill Reference Revision:

Page Number:

ATTACHMENTB Page 10 of 12 LOCATION OF SAMPLING SITES FIGURE 3.0-5 (Continued)

FOODCROP SAMPLING LOCATIONS Site#

Description 10*

Shippingport Boro 15*

Georgetown Boro 46*

Industry Boro 48*

Weirton Area 9

Individual garden locations may change based upon availability. The requirements are met as long as one garden is sampled from each of these communities.

?? of?LI.

Beaver Valley Power Station

Title:

ODCM: Radiological Environmental Monitoring Program ATTACHMENT B Page 11 of 12 LOCATION OF SAMPLING SITES FIGURE 3.0-6 FISH SAMPLING LOCATIONS I oo sto ~

@)

Procedure Number:

l/2-0DC-2.03 Unit:

Level Of Use:

1/2 General Skill Reference Revision:

Page Number:

A 5 mi plant radius

Beaver Valley Power Station Procedure Number:

l/2-0DC-2.03

Title:

Unit:

Level Of Use:

ODCM: Radiological Environmental Monitoring Program 1/2 General Skill Reference ATTACHMENT B Page 12 of 12 LOCATION OF SAMPLING SITES FIGURE 3.0-6 (Continued)

FISH SAMPLING LOCATIONS Revision:

9 Sector Site# Distance (miles)

Location 12 2A 0.31 BVPS Outfall Vicinity Page Number:

24 of?4 3

49A 4.93 Upstream of Montgomery Dam

RTL#: A9.621B Beaver Valley Power Station*

Unit 1/2 l/2-0DC-2.04 ODCM: Information Related to 40 CFR 190 Document Owner Manager, Nuclear Environmental & Chemistry Revision Number 2

Level Of Use General Skill Reference Safety Related Procedure Yes Effective.Date 10/07/14

Beaver Valley Power Station Procedure Number:

l/2-0DC-2.04

Title:

Unit:

Level Of Use:

1/2 General Skill Reference ODCM: Information Related to 40 CFR 190 Revision:

2 Page Number:

2of6 TABLE OF CONTENTS 1.0 PURPOSE.......................................................................................................................................... 3 2.0 SCOPE.............................................................................................................................................. 3

3.0 REFERENCES

AND COMMITMENTS......................................................................................... 3 3.1 References.............................................................................................................................. 3 3.2 Commitments......................................................................................................................... 3 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............................................................................................................................ 5 8.0 PROCEDURE................................................................................................................................... 5 8.1 Information Related To 40 CFR 190...................................................................................... 5 8.2 Inside The Site Boundary Radiation Doses............................................................................ 6

Beaver Valley Power Station Procedure Number:

l/2-0DC-2.04

Title:

Unit:

Level Of Use:

1/2 General Skill Reference ODCM: Information Related to 40 CFR 190 Revision:

Page Number:

2 3 of6 PURPOSE 1.0 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.<3.1.2) 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 l/2-0DC-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 l/2-ADM-0101, Review and Approval of Documents 3.1.6 CR 05-01169, Chemistry Action Plan for Transition ofRETS, REMP and ODCM.

CA-18, Revise procedure l/2-0DC-2.04 to change document owner from Manager, Radiation Protection to Manager, Nuclear Environmental & Chemistry.

3.1. 7 10 CFR 72.104, Criteria for Radioactive Materials in Effluents and Direct Radiation from an ISFSI or MRS.

3.2 Commitments 3.2.l 10 CFR 20.405(c), 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)

Procedure Number:

Beaver Valley Power Station l/2-0DC-2.04

Title:

Unit:

Level Of Use:

1/2 General Skill Reference ODCM: Information Related to 40 CFR 190 Revision:

Page Number:

4.0 4.1 RECORDS AND FORMS Records 2

4 of6 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 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/quarterTotal Body or

_:s 5 mrem/quarter any Organ.

5.1.2 ODCM Control 3.11.2.b; Liquid Effluents:.::: 3 mrem/year Total Body or

.:::_10 mrem/year any Organ.

5.1.3 ODCM Control 3.11.2.2.a; Gas Effluent-Noble Gas:.::: 5 mrad/quarter Gamma, or

_:s 10 mrad/quarter Beta 5.1.4 ODCM Control 3.11.2.2.b; Gas Effluents-Noble Gas:.::: 10 mrad/year Gamma

_:s 20 mrad/year Beta 5.1.5 ODCM Control 3.11.2.3.a; Gas Effluents-Particulates & Iodines:.::: 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/year Total Body or any Organ, except the thyroid, which is limited to.:S 7 5 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, 10 CPR 72.104 and Appendix I to 10 CPR 50, and not adversely impact the accuracy or reliability of effluent dose or setpoint calculation. <3*2*2) 6.1.1 All changes to this procedure shall be prepared in accordance with 1/2-ADM-0100<3*1.4) and 1/2-ADM-1640.<3.13) 6.1.2 All changes to this procedure shall be reviewed and approved in accordance with 1/2-ADM-0101 <3.1.5) and 1/2-ADM-1640.<3-13)

Procedure Number:

l/2-0DC-2.04

Beaver Valley Power Station

Title:

Unit:

Level Of Use:

1/2 General Skill Reference ODCM: Information Related to 40 CFR 190 Revision:

Page Number:

7.0 7.1 2

PREREQUISITES The user of this procedure shall be familiar with ODCM structure and content.

5 of6 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:

8.1.1.1 Calculations shall be made including direct radiation contributions from the units (including outside storage tanks, the onsite Independent Spent Fuel Storage Installation (ISFSI), 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, which is considered to include the onsite Independent Spent Fuel Storage Installation (ISFSI), 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 10 CFR 20.405(c).<3-2.1) The following shall be included in the Special Report:

8.1.1.1.1.1 8.1.1.1.1.2 8.1.1.1.1.3 8.1.1.1.1.4 8.1.1.1.1.5 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.

Include the schedule for achieving conformance within the limits of ODCM CONTROL 3.11.4.1.

Include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, which is considered to include the onsite Independent Spent Fuel Storage Installation (ISFSI), including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report.

Describe levels of radiation and concentrations of radioactive material involved, and the cause of exposure levels or concentrations.

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.

l Beaver Valley Power Station Procedure Number:

l/2-0DC-2.04

Title:

Unit:

Level Of Use:

1/2 General Skill Reference ODCM: Information Related to 40 CFR 190 Revision:

Page Number:

6 of6 8.2 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 i,s 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.

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 x!Q 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!Q Used for Dose CalculaJion Site Boundaty 0.352milesNW 924E-5~

l.03E-4 'BIXlm.3 7.35E-5 'BIXlm.3 924E-5~

924E-5 'BIXlm.3 7.35E-5 'BIXlm.3 x!Q WhereanAssumed MEMBEROFIBEPUBUC WouldMostLikely Have the Maximum Exposure Time Inside the Site Inside the Site Boundary Boundmy 0-0.5 miles N 0-0.5 miles NNW 2.33E-5 'BIXlm.3 5.47E-5 'BIXlm.3 2.76E-5 'BIXlm.3 6.0lE-5 'BIXlm.3 2.44E-5 'BIXlm.3 5.57E-5 'BIXlm.3 2.33E-5~

5.47E-5~

2.33E-5 'BIXlm.3 5.47E-5 'BIXlm.3 2.44E-5 'BIXlrrf 5.57E-5 'BIXlm.3

-END-x!Q References from l/2-00C-2.02 See AttachmentF Table224 Table22-5 Table22-7 Table22-8 Table22-9 Table22-10

--- ~,-.

(Page 1 of

12)

RTL#: A9.621B Beaver Valley Power Station Unit 1/2 1/2-0DC-3.0l ODCM: Dispersion Calculation Procedure and Source Term Inputs Document Owner Manager, Nuclear Env~ronmental & Chemistry Revision Number I

Level Of Use General Skill Reference Safety Related Procedure Yes Effective Date 12/29/06

(Page 2 of

12)

Beaver Valley P,ower Station Procedure Number:

1/2-0DC-3.0l

Title:

Unit:

Level Of Use:

1/2 General Skill Reference ODCM: Dispersion Calculation Procedure and Source Term Inputs Revision:

1 Page Number:

2of12 TABLE OF CONTENTS 1.0 PURPOSE.................................................................................................................................... 3 2.0 SCOPE......................................................................................................................................... 3 3.0 REFEFERENCES AND COM1\\11Tl\\1ENTS............... *.................................................................. 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........................................................ 5 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

(Page 3 of 12)

Beaver Valley Power Station Procedure Number:

1/2-0DC-3.0l

Title:

Unit:

Level Of Use:

1/2 General Skill Reference ODCM: Dispersion Calculation Procedure and Source Term Inputs Revision:

1 Page Number:

3 of 12 1.0 PURPOSE 1.1 This procedure contains the basic methodology that was used for calqulating 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.

2.0 1.2.1 Prior to issuance of this procedure, these items were located in Appendix B of the old ODCM.

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 Power Station, For the Straight-Line Atmospheric Dispersion Model, NUS Corporation, 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 LIQlBB Code, 3.1. 7 SWEC GAS lBB 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. 1) 1 3.1.9 1/2-ADM-1640, Control of the Offsite Dose Calculation Manual

(Page 4 of

12)

Beaver Valley Power Station Procedure Number:

l/2-0DC-3.01

Title:

Unit:

Level Of Use:

1/2 General Skill Reference ODCM: Dispersion Calculation Procedure and Source Term Inputs Revision:

1 Page Number:

4 of12 3.1.10 1/2-ADM-0100, Procedure Writer's Guide 3.1.11 1/2-ADM-0101, Review and Approval ofDocuments 3.1.12 CR 05-01169, Chemistry Action Plan for Transition ofRETS, REMP and ODCM.

CA-19, Revise procedure l/2-0DC-3.01 to change document owner from Manager, Radiation Protection to Manager, Nuclear Environmental & Chemistry.

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 Off site Dose Calculation Manual.

5.1.1 In regards to this, the Tables that were transferred from Appendix A and Appendix B to the appropriate ATTACHMENTS 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 wil1 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 I

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.uo) and 1 /2-ADM-1640. (3.1.9>

6.1.2 All changes to this procedure shall be reviewed and approved in accordance with 1/2 ADM-OI01<3*1.11> and 1/2-ADM-1640.c3*1.9) 7.0 PREREQUISITES 7.1 The user of this procedure shall be familiar with ODCM structure and content.

(Page 5 of

12)

Beaver Valley Power Station Procedure Number:

l/2-0DC-3.01 ~ *

Title:

Unit:

Level Of Use:

1/2 General Skill Reference,'

Revision:

1 Page Number:

5 of12 ODCM: Dispersion Calculation Procedure and Source Term Inputs 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 RG-1.111. <3-I.4) 8.1.1.1 8.1.1.2 8.1.1.3 8.1.1.4 8.1.1.5 Undecayed and undepleted sector average x/Q and D/Q values were obtained for each of sixteen 22. 5-degree sectors at the site boundary and maximum individual receptors.

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.

A building wake correction factor was used to adjust calculations for ground-level releases.

Airflow reversals were also accounted for by applying site-specific terrain recirculation factors for both ground and elevated releases at the site.<3,l.l)

The methodology employed in the calculation of intermittent release XIQ and D/Q values is that described in NUREG/CR-2919.c3*.1.2) 8.1.2 The site continuous gaseous release points that have been evaluated include the following:

8.1.2.1 8.1.2.2 I

8.1.2.3 8.1.2.4 8.1.2.5 8.1.2.6 8.1.2.7 PV-1/2: The Unit 1/2 Gaseous Waste/Process Vent attached to the Unit I natural draft cooling tower CV-I and CV-2: The Unit I Rx Containment/SLCRS Vented the Unit 2 SLCRS Filtered Pathway W-1 and W-2: The Unit 1 Ventilation Vent and the Unit 2 SLCRS Unfiltered Pathway TV-2: The Unit 2 Turbine Building Vent CB-2: The Unit 2 Condensate Polishing Building Vent DV-2: The Unit 2 Decontamination Building Vent wv~2: The Unit 2 Gaseous Waste Storage Tank Vault Vent 8.1.3 The intermittent releases are from PV-1/2, W-1, W-2, CV-1 and CV-2.

(Page 6 of

12)

Beaver Valley Power Station Procedure Number:

l/2-0DC-3.01

Title:

Unit:

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1/2 General Skill Reference Revision:

1 Page Number:

6 of 12 ODCM: Dispersion Calculation.Procedure and Source Term Inputs 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 8.1.5.2 8.1.5.3 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.

The data were collected according to guidance in NRC RG-1.23<3.1*3) as described in Section 2.3 of the BVPS-2 FSAR.

The parameters used in the rJQ and D/Q 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 8.1.6.2 8.1.6.3 8.1.6.4 8.1.6.5 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.

The distances of the limiting maximum individual receptors from the radioactive release points are given in ATTACHMENT E (Table 2.2-3) of l/2-0DC-2.02.

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 l/2-0DC-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.

Continuous release D/Q values for these same release points are given in ATTACHMENT K (Tables 2.3-21 through 2.3-27) of l/2-0DC-2.02 for the same 0-5 mile incremental distances, and in ATTACHMENT L (Tables 2.J:.28 through 2.3-34) of l/2-0DC-2.02 for the special locations.

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.

(Page 7 of 12)

Beaver Valley Power Station Procedure Number:

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Title:

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Level Of Use:

1/2 General Skill Reference Revision:

1 Page Number:

7 of 12 ODCM: Dispersion Calculation Procedure and Source Term Inputs 8.2 8.1.6.6 Likewise, the Turbine Building Vent r./Q's and D/Q'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 l/2-0DC-2.02 contain short term xJQ 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 0.00889 hours 5.291005e-5 weeks 1.2176e-5 months per year of Containment and Ventilation Vent purges and 74 hours8.564815e-4 days 0.0206 hours 1.223545e-4 weeks 2.8157e-5 months per year of Process Vent purges.

Summary of Source Term Inputs 8.2.1 Liquid Source Term Inputs 8.2.1.1 8.2.1.2 Inputs to the NRC Gale Code used for generation ofBV-1 Liquid Source Term Mixes are shown in ATTACHMENT B (Table B:la).

Inputs to the SWEC LIQlBB Code used for generation ofBV-2 Liquid Source Term Mixes are shown in ATTACHMENT B (Table B: 1 b) 8.2.2 Gaseous Source Term Inputs 8.2.2.1 8.2.2.2 Inputs to the SWEC GAS1BB Code for generation ofBV-1 Gaseous Source Term Mixes are shown in ATTACHMENT C (Table B:2a)

Inputs to the SWEC GAS1BB Code for generation ofBV-2 Gaseous Source Term Mixes are shown in ATTACHMENT C (Table B :2b)

(Page 8 of

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1/2 General Skill Reference ODCM: Dispersion' Calculation Procedure and Source Term Inputs Revision:

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1 8 of 12 ATTACHMENT A Page 1 of 1 BV-1 AND 2 RELEASE CONDITIONS TABI.EAl W-1 CV-1 RX PV-1/2 GASEOUS TV-2 TURBINE VENTILATION CONTAINMENT/

WASTE/PROCESS BUILDING VENT VENT(PAB SLCRSVENT VENT EXHAUST)

W-2SLCRS CV-2RX UNFILTERED CONTAINMENT/

PATIIWAY SLCRS FIL 'J?ERED PATHWAY TYPE OF RELEASE GROUND LEVEL GROUND LEVEL ELEVATED GROUND LEVEL Long Term And LongTermAnd Long Term And Long Term And ShortTenn ShortTerm ShortTerm ShortTenn Release Point Heigbt 26 47 155 33 (m)

Adjacent Building 19 44 155 33 Height(m)

RelativeLocation To E. Side Ofl>rimmy TopCenterOf Atop Cooling Tower Tutbine Building Adjarent Structures Auxili Bldg my ContainmentDJme Exit Velocity(mlsec)

NA NA 9.4 NA Int:emal Stacie NA NA 025 NA Diameter(m)

Building Cross-Sediona1Area(m2) 1600 1600 NA NA PurgeFrequency*

32 32 74 NA (hours,'.Year)

Purge Duration 8

8 NA NA (hrs,'release)

Applitrl to Short renn calculations only

(Page 9 of

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Beaver Valley Power Station

Title:

ODCM: Dispersion Calculation Procedure and Source Term Inputs ATTACHMENT B Page 1 of2 LIQUID SOURCE TERM INPUTS TABLEB:la Procedure Number:

1/2-0DC-3. O 1 Unit:

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1 9 of 12 INPUTS TO GALE CODE FOR GENERATION OF BV-1 LIQUID SOURCE TERM MIXES BV-1 PWR INPUTS Thermal Power Level (megawatts)

Plant Capacity Factor Mass OfErimary Coolant (thousand lbs)

Percent Fuel With Cladding Defects Primary System Letdown Rate (gpm)

Letdown Cation Demincralizer Flow Number Of Steam Generators Total Steam Flow (million lbs/hr)

Mass Of Steam In Each Steam Generator (thousand lbs)

Mass Of Liquid In Each Steam Generator (thousand lbs)

Total Mass Of Secondary Coolant (thousand lbs)

Mass Of Water In Steam Generator (thousand lbs)

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)

BV-1 LIQUID WASTE INPUTS COLLECTION FLOW RA TE FRACTION FRACTION TIME STREAM (gal/day)

OFPCA DISCHARGE (days)

Shim Bleed 1.32E4 1.000 0.000 11.260 Rate Equipment 6.00E2 1.000 0.000 11.260 Drains Clean Waste 7.50El 1.000 1.000 0.071 Input Dirty Waste 1.35E3 0.035 1.000 0.071 Input Blowdown 9.75E4 1.000 0.071 Untreated 0.0 Blowdown DELAY TIME (days) 7.220 7.220 0.648 0.648 0.648 VALUE 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 DECONTAMINATION FACTORS I

Cs OTHERS 1E7 1E7 1E7 1E7 1E7 1E7 1E5 2E4 1E5 1E5 2E4 1E5 1E5 2E4 1E5

(Page 10 of 12)

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Title:

ODCM: Dispersion Calculation Procedure and Source Term Inputs ATTACHMENT B Page2 of2 LIQUID SOURCE TERM INPUTS TABLEB:lb Procedure Number:

l/2-0DC-3.01 Unit:

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1 10 of 12 INPUfS TO SWEC LIQIBB CODE FOR GENERATION OF BV-2 LIQUID SOURCE TERM MIXES BV-2 PWRINPUTS VALUE Thermal Power Level (megawatts)

Plant Capacity Factor Mass Of Primary Coolant (thousand lbs)

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 lbs)

Mass Of Liquid In Each Steam Generator (thousand lbs)

Total Mass Of Secondary Coolant (thousand lbs)

Mass Of Water In Steam Generator (thousand lbs)

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)

BV-2 LIQUID WASTE INPUTS COLLECTION DELAY FLOWRATE FRACTION FRACTION TIME TIME STREAM (gal/day)

OFPCA DISCHARGE (hrs)

(hrs)

Containment 40 1.000 1.0 35.5 6.2 Sump Auxiliary 200 0.100 1.0 35.5 6.2 Building Sump Miscellaneous 700 0.010 1.0 35.5 6.2 Sources Rx Plant 35 1.000 1.0 35.5 6.2 Samples Lab Drains 400 0.002 1.0 35.5 6.2 Cond. Demin.

2685 l.lE-4 1.0 35.5 6.2 Rinse Water eves 60 1.0 1300 173 Turbine 7200 1.0 f

Bldg.Drains 2766.000

.800 385.000

.120 57.000 5.700 3.000 11.600 8.700 100.000 2000.000 298.000 22.300 100.000

.001

.010

.700 7.800 DECONTAMINATION FACTORS I

CsRb OTHERS 1E3 IE4 1E4 1E3 1E4 1E4 1E3 1E4 1E4 1E3 1E4 1E4 1E3 1E4 1E4 1E3 1E4 1E4 1E4 4E3 1E5

(Page 11 of 12)

Beaver Valley Power Station

Title:

ODCM: Dispersion Calculation Procedure and Source Term Inputs ATTACHMENT C Page 1 of2 GASEOUS SOURCE TERM INPUTS TABLEB,2a Procedure Number:

1/2-0DC-3. O 1 Unit:

Level Of Use:

1/2 General Skill Reference Revision:

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1 11 of 12 INPUTS TO SWEC GASIBB CODE FOR GENERATION OF BV-1 GASEOUS SOURCE TERM MIXES BV-1 PWRINPUTS Thennal Power Level (megawatts)

Plant Capacity Factor Mass Of Primary Coolant (thousand lbs)

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 lbs)

Mass Of Liquid In Each Steam Generator (thousand lbs)

Total Mass Of Secondary Coolant (thousand lbs)

Mass Of Water In Steam Generator (thousand lbs)

Blowdown Rate (thousand lbs/hr)

Primary To Secondary Leak Rate (lbs/day)

Fission Product Cany-Over Fraction Halogen Carry-Over Fraction Condensate Demineralizer Flow Fraction Radwaste Dilution Flow (thousand gpm)

BV-1 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 Iodine Partition Factor (gas/liq) In Steam Generator Frequency Of Containment Building High Vol Purge (times/yr)*

Contaimnent Volume Purge Iodine Release Fraction Containment Volume Purge Particulate Release Fraction Steam Leak To Twbine Building (lbs/hr)

Fraction Iodine Released From Blowdown Tanlc Vent Fraction Iodine Released From Main Condensate Air Ejector There Is Not A Cryogenic Off Gas System

2 cold and 2 hot purges 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 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 0.010 4.000 1.000 1.000 1700.000 0.000 0.440

(Page 12 of 12) j I

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ODCM: Dispersion Calculation Procedure and Source Term Inputs ATTACHMENT C Page 2 of2 GASEOUS SOURCE TERM INPUTS TABLEB:2b Procedure Number:

l/2-0DC-3.01 Unit:

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1/2 General Skill Reference Revision:

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1 12 of 12 INPUTS TO SWEC GASIBB CODE FOR GENERATION OF BV-2 GASEOUS SOURCE TERM MIXES BV-2 PWR INPUTS.

Thennal Power Level (megawatts)

Plant Capacity Factor Mass Of Primary Coolant (thousand lbs)

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 lbs)

Mass Of Liquid In Each Steam Generator (thousand lbs)

Total Mass Of Secondary Coolant (thousand lbs)

Mass Of Water In Steam Generator (thousand lbs)

Blowdown Rate (thousand lbs/hr)

Primary To Secondary Leak Rate (lbs/day)

Fission Product Cany-Over Fraction Halogen Carry-Over Fraction Condensate Demineralizer Flow Fraction Radwaste Dilution Flow (thousand gpm)

BV-2 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 Iodine Part.ition Factor (gas/liq) In Steam Generator Frequency Of Containment Building High Vol Purge (times/yr)*

Containment Volume Purge Iodine Release Fraction Containment Volume Purge Particulate Release Fraction Steam Leak To Twbine 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

2 cold and 2 hot purges VALUE 2766.000

.800 385.000

.120 57.000 5.700 3.000 11.600 8.700 100.000 2000.000 298.000 22.300 100.000

.001

.010

.700 7.800 VALUE 45.800 2.570 160.000 7.5E-3 0.000 0.100 0.010 1.800 2.000 100.000 20.000 8.000 0.010 4.000 1.000 1.000

'1700.000 0.000 0.270

RTL#: A9.621B Beaver Valley Power Station Unit 1/2 l/2-0DC-3.02 ODCM: Bases For ODCM Controls Document Owner Manager, Nuclear Environmental and Chemistry Revision Number 3

Level Of Use General Skill Reference Safety Related Procedure Yes Effective Date 02/11/15

Beaver Valley Power Station Procedure Number:

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3 2 of 14 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...................................................................................................................................... 5 5.0 PRECAUTIONS AND LIMITATIONS.......................................................................................... 5 6.0 ACCEPTANCE CRITERIA..............................-............................................................................... 5 7.0 PREREQUISITES....... *..................................................................................................................... 5 8.0 PROCEDURE....................... ~........................................................................................................... 5 ATTACHMENT A BASES FOR ODCM CONTROLS: INSTRUMENTATION.............................. 7 ATTACHMENT B BASES FOR ODCM CONTROLS: LIQUID EFFLUENTS............................... 8 ATTACHMENT C.BASES FOR ODCM CONTROLS: GASEOUS EFFLUENTS........................ 10 ATTACHMENT D BASES FOR ODCM CONTROLS: TOTAL DOSE......................................... 13 ATTACHMENT E BASES FOR ODCM CONTROLS: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)................................................................ 14

Beaver Valley Power Station Procedure Number:

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Title:

Unit:

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ODCM: Bases For ODCM Controls 1/2 General Skill Reference Revision:

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3 3 of 14 PURPOSE 1.0 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 1A-188/2A-70, and in accordance with Generic Letter 89-01 and NUREG-1301 (Generic Letter 89-01, Supplement No. 1) [ITS] and T.S. 5.5.2.c3.1.5, 3.2.1o) 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 1A-246/2A-124, and in accordance with NUREG-1431.(3.1.6, 3*2*11) 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 1A-250/2A-130, and in accordance with NUREG-1431Y*1.7, 3.2.1r) 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 l/2-0DC-2.01, ODCM: Liquid Effluents 3.1.2 l/2-0DC-2.02, ODCM: Gaseous Effluents 3.1.3 l/2-0DC-3.03, ODCM: ~Controls for RETS and REMP Programs 3.1.4 1/2-ADM-1640, Control of the Offsite Dos~ Calculation Manual 3.1.5 Unit 1/2 Technical Specification 6.8.6, including Amendments 1A-188/2A-70 (LAR 1A-175/2A-37), Implemented August 7, 1995 3.1.6 Unit 1/2 Technical Specification 3.3.3.1, including Amendments 1A-246/2A-124 (LAR 1A-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 1A-250/2A-130 (LAR 1A-291/2A-163), Implemented August 7, 2002 3.1.8

l/2-ADM-0100, Procedure Writer's Guide 3.1.9 1/2-ADM-0101, Review and Approval of Documents

Beaver Valley Power Station Procedure Number:

l/2-0DC-3.02

Title:

Unit:

Level Of Use:

ODCM: Bases For ODCM Controls 1/2 General Skill Reference Revision:

Page Number:

3 4 of 14 3.1.10 CR 05-01169, Chemistry Action Plan for Transition ofRETS, REMP and ODCM.

CA-20, Revise procedure l/2-0DC-3.02 to change document owner from Manager, Radiation Protection to Manager, Nuclear Environmental and Chemistry. CR 05-03306, Incorporated Improved Technical Specifications (ITS).

3.1.11

[ITS] T.S. 5.5.2 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 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 ofTMI 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 ( eg; letter or calculation package) with an appropriate RTL number.

Beaver Valley Power Station Procedure Number:

l/2-0DC-3.02

Title:

Unit:

Level Of Use:

ODCM: Bases For ODCM Controls 1/2 General Skill Reference Revision:

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3 5 of 14 4.2 Forms 4.2.1 None 5.0 PRECAUTIONS AND LIMITATIONS 5.1 The numbering of each specific O DCM 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.

5.2 This procedure includes Improved Technical Specifications ([ITS]) information that is NOT applicable to current Technical Specifications ([CTS]) and [CTS] information that is NOT applicable in [ITS]. The [CTS] information shall be used prior to the [ITS] effective date.

The [ITS] information shall be used on or after the [ITS] effective date.

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.C3-2.1o) 6.1.1 All changes to this procedure shall be prepared in accordance with l/2-ADM-0100<3.1.s) and l/2-ADM-1640Y*L4) 6.1.2 All changes to this procedure shall be reviewed and approved in accordance with l/2-ADM-0101 <3.1.9) and l/2-ADM-1640.<3.1.4)

7.0 PREREQUISITES 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 I

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.

Beaver Valley Power Station Procedure Number:

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ODCM: Bases For ODCM Controls 1/2 General Skill Reference Revision:

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3 6 of 14 8.5 See ATTACHMENT E for a complete description of Bases for ODCM Controls associated with the Radiological Environmental Monitoring,Program (REMP).

-END-

Beaver Valley Power Station Procedure Number:

l/2-0DC-3.02

Title:

Unit:

Level Of Use:

ODCM: Bases,.f or ODCM Controls 1/2 General Skill Reference 3/4.3.3.1 3/4.3.3.9 3/4.3.3.10 ATTACHMENT A Page 1 of 1 Revision:

3 BASES FOR ODCM CONTROLS: INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION Page Number:

7 of 14 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-073 7. <3*2*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.<3*2*1, 3*2*2)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION I

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*2*1, 3*22)

Beaver Valley Power Station Procedure Number:

l/2-0DC-3.02

Title:

Unit:

Level Of Use:

ODCM: Bases For ODCM Controls 1/2 General Skill Reference 3/4.11.1.1 3/4.11.1.2 3/4.11.1.3 ATTACHMENT B Page 1 of 2 Revision:

3 BASES FOR ODCM CONTROLS: LIQUID EFFLUENTS LIQUID EFFLUENT CONCENTRATION Page Number:

8 of 14 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 EC's specified in 10 CFR Part 20, Appendix B (20.1001-20-2402), 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 II.A design objectives of Appendix I, 10 CFR Part 50, to an individual and (2) the limits of 10 CFR Part 20.13 02 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*1, 3*2*2)

LIQUID EFFLUENT DOSE This CONTROL is provided to implement the requirements of Sections II.A, III.A, and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.A of Appendix I. 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 rele~ses 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 l/2-0DC-2.01 implement the requirements in Section III.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 ofradioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, and Regulatory Guide 1.113. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.113. <3. I.I, 3.2.2, 3*23, 3*25, 3*2*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.

LIQUID WASTE TREATMENT SYSTEM

Beaver Valley Power Station Procedure Number:

l/2-0DC-3.02

Title:

Unit:

Level Of Use:

ODCM: Bases For ODCM Controls 1/2 General Skill Reference 3/4.11.1.4 ATTACHMENT B Page 2 of2 Revision:

3 BASES FOR ODCM CONTROLS: LIQUID EFFLUENTS Page Number:

9 of 14 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 CPR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and design objective given in Section 11.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid rad waste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I, 10 CPR Part 50, for liquid effluents.

This specification applies to Beaver Valley Power Station, Unit No. 1 or Unit No.

2.(3.2.2)

LIQUID 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.

Beaver Valley Power Station Procedure Number:

l/2-0DC-3.02

Title:

Unit:

Level Of Use:

ODCM: Bases For ODCM Controls 1/2 General Skill Reference 3/4.11.2.1 3/4.11.2.2 ATTACHMENT C Page 1 of 3 Revision:

3 BASES FOR ODCM CONTROLS: GASEOUS EFFLUENTS GASEOUS EFFLUENT DOSE RATE Page Number:

10 of 14 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 2, 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 2 of 10 CFR Part 20 (10 CFR Part 20.1301). 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 dose limit in any unrestricted area from external sources, exclusive of the dose contributions from patients administered radioactive material and released in accordance with§ 35.75, does not exceed 2 mrem in any one hour.

Previous 10 CFR Part 20.106(b) was incorporated into the Improved Standard Technical Specification, section 5.5.2 and still requires compliance. 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 mrem/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. C3-2.1)

DOSE, NOBLE GASES This CONTROL is provided to implement the requirements of Sections II.B, III.A, and IV.A of Appendix I, 10 CFR Part 50. The CONTROL implements the guides set forth in Section II.B of Appendix I. 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 III.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 l/2-0DC-2.02 for calculating the doses due to the actual release rates ofradioactive 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 l/2-0DC-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

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11 of 14 for" dose calculations consistent with Regulatory Guides 1.109 and 1.111. This specifications applies to the release of gaseous effluents from Beaver Valley Power Station, Unit No. 1 or Unit No. 2.<3.1.2, 3.2.2, 3.2.5, 3.2.6, 3.2.8)

DOSE, RADIOIODINES, RADIOACTIVE MATERIAL IN PARTICULATE FORM AND RADIONUCLIDES OTHER THAN NOBLE GASES This CONTROL is provided to implement the requirements of Sections II.C, III.A, and IV.A of AQpendix I, 10 CFR Part 50. The CONTROLS are the guides set forth in Sectio~ II.C o{Appendii l. <3-2-2)

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 ofradioactive 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 III.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 I

appropriate pathways is unlikely to be substantially underestimated. The calculational methods in procedure l/2-0DC-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 arid nidTcmudides other than noble gases released from Beaver Valley Power Station, Unit No. 1 or Unit No.2. <3.1.2, 3*2*2, 3.2.6, 3.2.7)

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12 of 14 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.II This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CPR Part 50, and design objective Section 11.D of Appendix I to 10 CPR 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 11.B and 11.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.c3.1.2, 3*2*2)

BV-1 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 CPR 100.11 (a)(l).

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 100.1 l(a)(l).

The curie content limit is applied individually to each gaseous waste storage tank and collectively to the number ofunisolated gaseous waste storage tanks.

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13 of 14 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 unlikely 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 he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.(3.1.3, 3.2.1, 3.2.2, 3.2.4)

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14 of 14 BASES FOR ODCM CONTROLS: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 3/4.12.1 3/4.12.2 3/4.12.3 MONITORING PROGRAM The radiological monitoring prograrp. 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 141. <3.u, 3*23)

LAND USE CENSUS ODCM CONTROL 3.12.2 is provided to ensure that changes in the use ofumestricted areas are identified and that modifications to the monitoring programs ~e 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.u, 3*2*2)

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.<3.u) r

RTL #A9.621B Beaver Valley Power Station Unit 1/2-l/2-0DC-3.03 ODCM: Controls for RETS and REMP Programs Document Owner Manager, Nuclear Environmental and Chemistry Revision Number 15 Level Of Use General Skill Reference Safety Related Procedure Yes Effective Date 09/lA-/18

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Vi 2 nfR1 TABLE OF CONTENTS 1.0 PURPOSE......................................................................................................................................... 3 2.0 SCOPE.............................................................................................................................................. 3

3.0 REFERENCES

AND COMMITMENTS......................................................................................... 4 3.1 References.............................................................................................................................. 4 3.2 Commitments......................................................................................................................... 7 4.0 RECORDS AND FORMS................................................................................................................ 8 4.1 Records................................................................................................................................... 8 4.2 Forms...................................................................................................................................... 8 5.0 PRECAUTIONS AND LIMITATIONS.......................................................................................... 9 6.0 ACCEPTANCE CRITERIA..................................................................................................... :....... 9 7.0 PREREQUISITES............................................................................................................................ 9 8.0 PROCEDURE................................................................................................................................. 10 ATTACHMENT A ODCM CONTROLS: OPERATIONAL MODES AND FREQUENCY NOTATION......................................................................................................... 11 ATTACHMENT B ODCM CONTROLS: DEFINITIONS............................................................... 13 ATTACHMENT C ODCM CONTROLS: APPLICABILITY AND SURVEILLANCE REQUIREMENTS............................................................................................... 16 ATTACHMENT D ODCM CONTROLS: RADIATION MONITORING INSTRUMENTATION 20 ATTACHMENT E ODCM CONTROLS: RETS INSTRUMENTATION FOR LIQUID ATTACHMENT F ATTACHMENT G ATTACHMENTH ATTACHMENT I ATTACHMENT J ATTACHMENTK ATTACHMENT L ATTACHMENT M ATTACHMENTN ATTACHMENT 0 ATTACHMENT P ATTACHMENT Q ATTACHMENT R ATTACHMENTS EFFLUENTS....................................................................................................... 28 ODCM CONTROLS: RETS INSTRUMENT FOR GASEOUS RELEASES... 38 ODCM CONTROLS: LIQUID EFFLUENT CONCENTRATION................... 51 ODCM CONTROLS: LIQUID EFFLUENT DOSE.......................................... 56 ODCM CONTROLS: LIQUID RADWASTE TREATMENT SYSTEM......... 57 ODCM CONTROLS: LIQUID HOLDUP TANKS........................................... 58 ODCM CONTROLS: GASEOUS EFFLUENT DOSE RATE.......................... 59 ODCM CONTROLS: DOSE-NOBLE GASES................................................. 64 ODCM CONTROLS: DOSE-RADIOIODINES AND PARTICULATES...... 65 ODCM CONTROLS: GASEOUS RADWASTE TREATMENT SYSTEM..... 66 ODCM CONTROLS: GAS STORAGE TANKS............................................... 67 ODCM CONTROLS: TOTAL DOSE................................................................ 68

. ODCM CONTROLS: REMP-PROGRAM REQUIREMENTS........................ 69 ODCM CONTROLS: REMP - LAND USE CENSUS...................................... 78 ODCM CONTROLS: REMP - INTERLABORATORY COMPARISON PROGRAM........................................................'.................................................. 79 ATTACHMENT T ODCM CONTROLS: ANNUAL REMP REPORT:.......................................... 80 ATTACHMENT U ODCM CONTROLS: ANNUAL RETS REPORTS.......................................... 82

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'i ofR'i 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 T.S. 3.0.

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. C3-2.1o) 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 Radioactive Effluent Release Report and the Annual Radiological Environmental Operating Report 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. C3-2*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 th;;it were transferred from the Technical Specification per Unit 1/2 Amendments 246/124, and in accordance with NUREG-1431. (3.2.1 1) 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. (3.1.6, 3*2*11) 1.6 This procedure provides the Radiological Effluent Controls and Reporting Requirements required for T.S. 5.5.1, T.S. 5.5.2, T.S. 5.5.8, T.S. 5.6.1, and T.S. 5.6.2.

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.

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3.0 REFERENCES

AND COMMITMENTS 3.1 References 3.1.1 l/2-0DC-2.01, ODCM: Liquid Effluents 3.1.2 1/2-0DC~2.02, ODCM: Gaseous Effluents 3.1.3 l/2-0DC-3.02, ODCM: Bases for ODCM Controls 3.1.4 Unit 1/2 Technical Specification 6.8.6, including Amendments 188/70 (LAR 1A-175/2A-137) Implemented August 7, 1995.

3.1.5 Unit 1/2 Technical Specification 3.3.3.1, including Amendments 246/124 (LAR 1A~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 250/130 (LAR 1A-291/2A-163) Implemented August 7, 2002 3.1.7 1/2-ADM-1640, Control of the Offsite Dose Calculation Manual 3.1.8 1/2-ADM-0100, Procedure Writer's Guide 3.1.9 NOP-SS-3001, Procedure Review and Approval 3.1.10 CR 981489, ODCM Table 4.11-2 Row A (Waste Gas Storage Tank Discharge). CA-01, 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-01, 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-lDA-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-02, 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.

3.1.15 CA-01, Revise l/2-0DC-3.03 to add a requirement for applicable station groups notification of pending ODCM changes.

CR 03-06123, Enhance Table 3.3-6 of l/2-0DC-3.03 to Add More Preplanned Method of Monitoring. CA-01, Revise Table 3.3-6 and Table 4.3-3 to allow use of Eberline SPING Channel 5 as an additional 2nd PMM when the Unit 1 Mid or High Range Noble Gas Effluent Monitors are Inoperable.

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~ of R1 3.1.16 CR 03-:-06281, Gaseous Tritium Sampling Required by ODCM (l/2-0DC-3.03) Unclear for Chemistry. CA-01, Revise procedure Attachment K Table 4.11-2 for RP &

Chemistry sampling of Gaseous Effluent Pathways to show which effluent pathways need sampled for compliance to ODCM Control 3.11.2.1 requirements.

3.1.17 CR 03-07487, Results ofNQA Assessment of the Radiological Effluents Program.

CA-01, Revise Calculation Package No. ERS-ATL-95-007 to clarify the term "Surface Water Supply" per guidance presented in NUREG-0800 SRP 15.7.3. CA-05, Revise 1/2-0DC3.03 Control 3.11.1.4 to update the activity limits for the outside storage tanks.

3.1.18. CR 03-07668, Benchmark Effluent & Environmental Programs VS Papers Presented at 13th REMP/RETS Workshop. CA-01, Evaluate procedure Attachment K Table 4.11-2 to reduce the amount of Effluent Samples obtained during a power transient.

3.1.19 CR 03-09288, LAR lA-321 & 2A-193, Increased Flexibility in Mode Restraints.

CA-19, Review LAR 1A-321/2A-193 to identify the affected Rad Effluent procedures, programs, manuals, and applicable plant modification documents that will need to be revised to support implementing the LAR.

3.1.20 CR 03-09959, RFA-Rad Protection Provide Clarification to ODCM 1/Day Air Tritium Sample. CA-01, Rey~e ODCM procedure l/2-0DC-3.03 Attachment K (Table 4.11-2 note c & note e) to allow sampling of the appropriate building atmosphere.

3.1.21 CR 03-11726, Typographical Error Found in ODCM 3.11.2.5. CA-01, Revise ODCM procedure l/2-0DC-3.03, AttacJ:nnent 0, Control 3.11.2.5 to correct a typographical error. Specifically, the final word in Action (a) needs changed from "nad" to "and".

3.1.22 CR 04-01643, Procedure Correction-Typographical Error in the ODCM. CA-01, Revise ODCM procedure l/2-0DC-3.03, Attachment F, (Table 3.3-13 and 4.3-13) to correct a typographical error. Specifically, the Asset Number for the Vacuum Gauge used fo;r measurement of sample flow (from the Alternate Sampling Device) needs changed from [PI-lGW-13] to [PI-lGW-135].

3.1.23 CR 04-0~275, Discrepancies in Table 3.3-13 of the ODCM. CA-01, Revise ODCM procedure l/2-0DC-3.03, Attachment F, (Table 3.3-13 and 4.3-13) to add clarification that the "Sampler Flow Rate Monitors are the devices used for "Particulate and Iodine Sampling".

3.1.24 Unit 1 Technical Specification Amendment No. 275 (LAR lA-302) to License No. DPR-66. This amendment to the Unit 1 license was approved by the NRC on July 19, 2006.

3.1.25 Vendor Calculation Package No. 8700-UR(B)-223, Impact of Atmospheric Containment Conversion, Power Uprate, and Alternative Source Terms on the Alarm Setpoints for the Radiation Monitors at Unit 1.

3.1.26 Engineering Change Package No. ECP-04-0440, Extended Power Uprate.

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h of ~n 3.1.27 CR 06-04908, Radiation Monitor Alarm Setpoint Discrepancies. CA-03; revise ODCM procedure l/2-0DC-3.03 to update the alann setpoints of [RM-lVS-110] and

[RM-lGW-109] for incorporation of the Extended Power Uprate per Unit 1 TS Amendment No. 275.

3.1.28 Calculation Package No. ERS-MPD-93-007, BVPS-1 Gaseous Radioactivity Monitor Emergency Action Levels.

3.1.29 SAP Order 200197646-0110: Revise ODCM procedure 1/20DC-3.03, l/2-HPP-3.06.001, l/2-ENV-05.01, Form l/2-HPP-3.06.001.F05 and Form 1/2-ENV-05.0l.F05 to incorporate revised outside liquid storage tank activity limits via Calculation Package No. ERS-ATL-95-007, R2.

3.1.30 CR 06-04944: ODCM 3.03 Attachment E conflict between Applicability and Action Statement. CA-01; revise ODCM procedure l/2-0DC-3.03, Attachment E to clarify Applicability for tank level indicating devices is during additions to the tank.

3.1.31 CR 05-03306: Incorporated Improved Technical Specifications. This includes transfer of programmatic controls for BV-2 Noble Gas Effluent Steam Monitors [2MSS-RQ101A], [2MSS-RQ101B] and [2MSS-RQ101C] from the Technical Specifications to ODCM procedure l/2-0DC-3.03 (Attachment D Tables 3.3-6 and 4.3-3). This was permitted via Unit 1/2 Technical Specification Amendments No. 278/161.

3.1.32 Unit 1 and 2 Technical Specifications: ITS 5.5.1, Offsite Dose Calculation Manual 3.1.33 Unit 1 and 2 Technical Specifications: ITS 5.5.2, Radioactive Effluent Controls Program 3.1.34 Unit 1 and 2 Technical Specifications: ITS, 5.5.8, Explosive Gas and Storage Tank Radioactivity Monitoring Program 3.1.35 Unit 1 and 2 Technical Specification: ITS 5.6.1, Annual Radiological Environmental Operating Report 3.1.36 Unit 1 and 2 Technical Specifications: ITS 5.6.2, Radioactive Effluent Release Report 3.1.37 SAP Order 200240681: Revise ODCM procedure l/2-0DC-3.03 (Attachment E Table 3.3-12) to add an alternate Action when the primary Flow Rate Measurement Device [FT-lCW-101-1] is not OPERABLE. The alternate Action (25A) uses local measurements (as described in lMSP-31.06-I) to determine a total dilution flow rate during liquid effluent releases.

3.1.38 CR 07-12924 and SAP Order 200247228-0410: Revise ODCM procedure l/2-0DC-3.03 (Attachment F Tables 3.3-13 and 4.3-13) to clarify the Functional Location of the Sampler Flow Rate Monitors for the BV-2 gaseous effluent release pathways.

Specifically, the procedure was changed to refer to Functional Location

[2HVS-FIT101-1] instead of [2HVS-FITI01], [2RMQ-FIT301-1] instead of

[2RMQ-FIT301], [2HVL-FIT112-l] instead of [2HVL-FIT112], and [2RMQ-FIT303-1]

instead of [2RMQ-FIT303].

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7 nfR1 3.1.39 SAP Order 200247228-0450: Revise l/2-0DC-3.03 Attachment E Table 3.3-12 and Attachment F, Tables 3.3-13 & 4.3-13 to provide added clarifications, as follows; (1) add the word "or" where'it is missing from Attachment F, Table 3.3-13 & 4.3-13, (2) remove grab samples from the list of alternates in Table 3.3-13 and 4.3-13, because a grab sample is an "action", not an "alternate", (3) add notations in Table 3.3-12 and 3.3-13 to indicate that Condition Report generation and reporting in the Radioactive Effluent Release Report (per Control 3.3.3.9 Action b and 3.3.3.10 Action b) do not apply when using an alternate to satisfy inoperability of the primary instrument beyond 30 days, and (4) remove surveillances for Preplanned Method of Monitoring (PMM) from Table 4.3-3, because surveillances only apply to instruments, not methods.

3.1.40 SAP Order 200240681-0020 and 0040: Revise l/2-0DC-3.03 Attachment E, Table 3.3-12, Table 4.3-12 and Action 25A to clarify the 1st and 2nd alternates to the flow rate measurement devices used for the cooling tower blowdown line.

3.1.41 SAP Order 200197646-0300 and CR07-31083: Revise ODCM procedure l/2-0DC-3.03 to add a definition for Channel Functional Test and revise the definition for Channel Operational Test to indicate that these definitions have the same requirements and, therefore, are considered equal.

3.1.42 CR 0203-2011-02332, Inability to meet ODCM requirements for REMP milk sampling in 2011 and CA G203-2011-02332-1, Make changes to the ODCM.

3.1.43 Engineering Change Package 10-0150: Replacement ofBVl Effluent Monitoring System Components 3.1.44 Engineering Change Package No. 16-0026: Pump/Motor Assembly Replacement 3.1.45 SAP Notification 601054826: Revise reference on l/2-HPP-4.02.009.FOl 3.1.46 CR-2017-04211, Lack of isokinetic sampling for ODCM requirements 3.1.47 CR-2018-02456, Rad. Effluents Inspection Preliminary Licensee Identified Green Non-cited Violation 3.1.48 Engineering Change Package No. 17-0112: Retire Unit 1 High Range Radiation Monitor SA 9/1 Os 3.2 Commitments 3.2.1 10 CFR Part 20, Standards for Protection Against Radiation 3.2.2 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities 3.2.3 40 CFR Part 141 3.2.4 40 CFR Part 190, Environmental Radiation Protection Standards For Nuclear Power Operations.

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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 I, April 1977 3.2.8

_NUREG-0133, Preparation of Radiological Effluent Technical Specifications for 1

Nuclear Power Plants, October 1978 3.2.9 NUREG-0737, Clarification ofTMI 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 3.2.12 NUREG-0800, Standard Review Plan, Postulated Radioactive Releases Due to Liquid-Containing Tank Failures, July 1981 3.2.13 Licensee Response to NRC Unresolved Item 50-334/83-30-05. The Radiation Monitor Particle Distribution Evaluation showed that the Licensee must continue to use C

correction factors to determine particulate activity in samples obtained from the effluent release pathways.

3.2.14 10 CFR 72.104 Criteria for Radioactive Materials in Effluents and Direct Radiation from an ISFSI or MRS.

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

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9 ofR'i 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.

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, 10 CFR 72.104 and Appendix I to 10 CFR 50, and not adversely impact the accuracy or reliability of°effluent dose or setpoint calculationY*2.1o) 6.1.1 All changes to this procedure shall be prepared in accordance with 1/2-ADM-0100C3.1.s) and 1/2-ADM-1640.C3*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 l/2-0DC-1.01. This will allow the station groups to revise any affected procedures concurrent with the ODCM change_C3.1.14) 6.1.3 All changes to this procedur~ shall be reviewed and approved in accordance with NOP-SS-3001 c3.1.9) and 1/2-ADM-1640.c3.1.7) 7.0 PREREQUISITES 7.1 The user of this procedure shall be familiar with O DCM structure and content.

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10 nf R1 8.0 PROCEDURE 8.1 See ATTACHMENT A for a Table of Operational° Modes and a Table of Frequency N~tation.

8.2 See ATTACHMENT B for a list of defined terms used throughout the ODCM.

8.3 See ATTACHMENT C thru ATTACHMENTS for a complete description of all ODCM Controls.

8.4 See ATTACHMENT T for a description of the Annual Report required by the REMP Controls.

8.5 See ATTACHMENT U for a description of the Annual Report required by the RETS Controls.

-END-

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ATTACHMENT A Page 1 of2 11 of R1 ODCM CONTROLS: OPERATIONAL MODES AND FREQUENCY NOTATION MODE J

2 3

4 5

6 TITLE Power Operation Startup Hot Standby Hot Shutdown Cb)

Cold Shutdown Cb)

RefuelingCc)

(a) Excluding decay heat: -

TABLE 1.1 MODES REACTIVITY

% RATED

-CONDITION THERMAL (keff)

POWER Ca)

~0.99

<0.99

<0.99 NA

>5

5 NA NA NA NA (b) All reactor vessei1iead closurebolts tulTy-tensioned.

( c) One or more reactor Vessel head -c1ostire-bolts-1essthan fully tensioned.

AVERAGE*

REACTOR COOLANT

--- -TEMPERATURE (OF)

NA NA

~350 350 > Tavg > 200 NA

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15 1? ofR'i ATTACHMENT A Page 2 of2 ODCM CONTROLS: OPERATIONAL MODES AND FREQUENCY NOTATION TABLE 1.2 FREQUENCY NOTATION NOTATION FREQUENCY s

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months D

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 SIU Prior to each reactor startup p

Completed prior to each release N.A.

Not applicable

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l'i 11 nf R1 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 OPERATIONAL 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.

SINCE these requirements are the same as those shown for CHANNEL OPERATIONAL TEST, THEN these definitions are considered equivalent.

CHANNEL OPERATIONAL 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.

SINCE these requirements are the same as those shown for CHANNEL FUNCTIONAL TEST, THEN these definitions are considered equivalent.

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 00 CFR 20 and/or 10 CFR 50) means any individual except when that individual is receiving an occupational dose. This definition is used to show compliance to ODCM CONTROL 3.11.1.1, 3.11.1.4, 3.11.2.1 and 3.11.2.5 that are based on 10 CFR Part 20. This definition is also used to show compliance to ODCM Controls 3.11.1.2, 3.11.1.3, 3.11.2.2, 3.11.2.3 and 3.11.2.4 that are based on 10 CFR Part 50.

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1.S 14 nf R1 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 3.11.4.1 that is based on 40 CFR Part 190.

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 (which is considered to include the onsite Independent Spent Fuel Storage Installation (ISFSI)), 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 T.S. 5.5.2 and (2) descriptions of the information that should be included in the Radiological Environmental Operating and Annual Radioactive Effluent Release Reports that are also required by T.S. 5.6.1 and T.S. 5.6.2.

OPERABLE/OPERABILITY 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).

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 2900 MWt.

REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to to CFR Part 50.

SHUTDOWN means reactor power change to 0% power.

SITE BOUNDARY shall be tha!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 l/2-0DC-2.01.

The Figure for Gaseous Effluent Site Boundary is contained in l/2-0DC-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.

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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 licensee.

VENTILATION EXHAUST TREATMENT SYSTEM is any system designed arid 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 (ESP) 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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16 nf R1 ATTACHMENTC*

Page 1 of 4 ODCM CONTROLS: APPLICABILITY AND SURVEILLANCE REQUIREMENTS CONTROLS: APPLICABILITY 3.0.1 ODCM CONTROLS shall be met during the MODES or other conditions specified in the Applicability; except as provided in ODCM CONTROL 3.0.2 i

3.02 Upon discovery of a failure to meet the ODCM CONTROL, the associated ODCM ACTION requirements shall be met, except as provided in ODCM CONTROLJ.0.5. If the ODCM CONTROL is met or no longer applicable prior to expiration of the specified time intervals, completion of the ODCM ACTION requirements is not required unless otherwise stated.

3.03 When an ODCM CONTROL is not met and the associated ODCM ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTIONS, the unit shall be placed in a MODE or other specified condition in which the ODCM CONTROL is not applicable. Action shall be initiated within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to place the unit, as applicable, in:

1.

MODE 3 within 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months ,

2.

MODE 4 within 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months , and

3.

MODE 5 within 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months .

Where corrective measures are completed that permit operation in accordance with the ODCM CONTROL or ACTIONS, completion of the actions required by ODCM CONTROL 3.0.3 is not required.

Exceptions to these requirements are stated in the individual ODCM CONTROLS.

3.0.4 When an ODCM CONTROL is not met, entry into an MODE or specified condition in the Applicability shall only be made:

I

a. When the associated ODCM ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time, or

b. After performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering the MODE or other specified condition in th.e Applicability, and establishment ofrisk management actions, if appropriate; exceptions to this ODCM CONTROL are stated in the individual ODCM CONTROLS, or

c. When an allowance is stated in the individual value, parameter, or other ODCM CONTROL.

This ODCM CONTROL shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ODCM ACTIONS or that are part of a shutdown of the unit.

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17 of 83 ODCM CONTROLS: APPLICABILITY AND SURVEILLANCE REQUIREMENTS 3.0.5 Equipment removed from service or declared inoperable to comply with ODCM ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an exception to ODCM CONTROL 3.0.1 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABiLITY.

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ATTACHMENT C Page 3 of 4 ODCM CONTROLS: APPLICABILITY AND SURVEILLANCE REQUIREMENTS CONTROLS: SURVEILLANCE REQUIREMENTS 4.0.1 4.02 Surveillance Requirements shall be met during the MODES or other conditions specified for individual ODCM CONTROLS unless otherwise stated in the ODCM Surveillance Requirement.

Failure to meet an ODCM Surveillance, whether such failure is experienced during the performance of the Surveillance or between performance of the Surveillance, shall be failure to meet the ODCM CONTROL. Failure to perform a Surveillance within the specified Frequency, shall be failure to meet the ODCM CONTROL except as provided in ODCM Surveillance Requirement 4.0.3. Surveillances do not have to be performed on inoperable equipment or variables outside specified limits.

The specified Frequency for each ODCM Surveillance Requirement is met if the Surveillance is performed within +/- 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met.

For Frequencies specified as "once," the above interval extension does not apply.

If a Completion Time requires periodic performance or "once per... " basis, the above Frequency extension applies to each performance after the initial performance.

Exceptions to this Specification are stated in the individual Specifications.

4.0.3 If it is discovered that an ODCM Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the ODCM CONTROL not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified surveillance interval, whichever is greater. This delay period is permitted to allow performance of the ODCM Surveillance. A risk evaluation shall be performed for any ODCM Surveillance delayed greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and the risk impact shall be managed.

If the ODCM Surveillance is not performed within the delay period, the ODCM CONTROL must immediately be declared not met, and the applicable ODCM ACTION(s) must be entered.

When the ODCM Surveillance is performed within the delay period and the ODCM Surveillance is not met, the ODCM CONTROL must immediately be declared not met, and the applicable ODCM ACTION(s) must be entered.

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15 1 Q onn ODCM CONTROLS: APPLICABILITY AND SURVEILLANCE REQUIREMENTS 4.0.4 Entry into a MODE or other specified condition in the Applicability of a ODCM CONTROL shall only be made when the ODCM Surveillances have been met within their allowed surveillance interval, except as provided by ODCM Surveillance Requirement 4.0.3. When an ODCM CONTROL is not met due to Surveillances not having been met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with ODCM CONTROL 3.0.4. This provision shall not prevent entry into MODES or other specified conditions in the Applicability, that are required to comply with ODCM ACTION requirements or that are part of a shutdown of the unit.

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20 nf 83 ATTACHMENT 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 alarm/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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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 OPERATIONAL TEST operations during the modes and at the frequen~ies shown in ODCM Control 3.3.3.1, Table 4.3-3.

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ODCM: Controls for RETS and REMP Programs Vi 21 nf81 ATTACHMENT D Page 2 of 8 ODCM CONTROLS: RADIATION MONITORING INSTRUMENTATION TABLE3.3-6 BV-1 RADIATION MONITORING INSTRUMENTATION Pri = Primary Instruments, PMM = Preplanned Method of Monitoring<a)

MINIMUM INSTRUMENT CHANNELS APPLICABLE SETPOINT (l)

OPERABLE

1. Noble Gas Effluent Monitors - PINGS <3>

MODES (b) a.Reactor Building/SLCRS (CV-1; Also called Elevated Release)

High Range Noble Gas (1) 1, 2, 3, & 4 Pri: (RM-lVS-110 HRNG Rel) 1st PMM: (RM-I VS-110 LRNG Rel) 2ndPMM: (RM-1VS-107B) 3rd PMM: Grab Sampling every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

1.56E+7 uCi/s b.Auxiliary Building Ventilation System (VV-1; Also called Ventilation Vent)

High Range Noble Gas (1) 1, 2, 3, & 4 NOMINAL MEASUREMENT RANGE lE-4 to 1E+5 uCi/cc<2>

Pri: (RM-IVS-109 HRNG Rel)

1.18E+7 uCi/slE-4 to IE+5 uCi/cc<2>

lstPMM: (RM-IVS-109 LRNG Rel) 2ndPMM: (RM-1VS-10IB) 3rd PMM: Grab Sampling every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

c. Gaseous Waste/Process Vent System (PV-1/2)

High Range Noble Gas (1) 1, 2, 3, & 4 Pri: (RM-IGW-109 HRNG Rel)

7.84E+9 uCi/slE-4 to IE+5 uCi/cc<2>

lstPMM: (RM-IGW-109 LRNG Rel) 2nd PMM: (RM-1GW-108B) 3rd PMM: Grab Sampling every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

\\

ACTION 35 35 35

<*l 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 ofthe primary-instrument exceeds 30 days,--- - --~-~

(b)

Setpoints are calculated in calculatio11_p_aclcage ERS-MJ:>D-93-001,

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?.2 nf 81 ATTACHMENT 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)

INSTRUMENT MINIMUM CHANNELS OPERABLE

2.

Noble Gas Effluent Steam Monitors APPLICABLE MODES SETPOINT <1)

a. Atmospheric Steam Dump Valve and Code Safety Relief Valve Discharge NOMINAL MEASUREMENT RANGE ACTION Pri: (RM-lMS-lOOA)

(1) 1, 2, 3, & 4

,:; 50 cpm lE-1 to 1E+3 uCi/cc 35 PMM: (Form 1/2-ENV-05.05.F07)

Pri: (RM-lMS-IOOB)

PMM: (Form 1/2-ENV-05.05.F07)

Pri: (RM-IMS-IOOC)

PMM: (Form 1/2-ENV-05.05.F07)

(I)

(I) t 1,2,3,&4 1,2,3,&4 b.Auxiliary Feedwater Pump Turbine Exhaust Pri: (RM-IMS-101)

(I)

I, 2, 3, & 4 PMM: (Form 1/2-ENV-05.05.F07)

,:; 50 cpm lE-1 to 1E+3 uCi/cc 35

,:; 170 cpm*

lE-1 to 1E+3 uCi/cc 35 (a)

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.

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?1 nfsn ATTACHMENTD Page 4 of 8 ODCM CONTROLS: RADIATION MONITORING INSTRUMENTATION TABLE 3.3-6 (Continued)

BV-2 RADIATION MONITORING INSTRUMENTATION Pri = Primary Instruments, PMM = Preplanned Method of MonitoringCa)

\\

INSTRUMENT

1. Noble Gas Effluent Monitors MINIMUM CHANNELS OPERABLE APPLICABLE MODES

a. SLCRS Filtered Pathway (CV-2; Also called Elevated Release)

Midrange Noble Gas (Xe-133)

SETPOINT <1l NOMINAL MEASUREMENT RANGE ACTION Pri: (2HVS-RQ109C)

(1) 1, 2, 3, & 4 NA lE-4 to 1E+2 µCi/cc 35 1st PMM: (2HVS-RQ109D) 2nd PMM: (2HVS-RQ109B) 3rd PMM: Grab Sampling every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months High Range Noble Gas (Xe-133)

Pri: (2HVS-RQ109D)

(1) 1, 2, 3, & 4 NA lE-1 to 1E+5 µCi/cc 35 1st PMM: (2HVS-RQ109C) 2nd PMM: (2HVS-RQ109B) 3rd PMM: Grab Sampling every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

2. Noble Gas Effluent Steam Monitors

a. Main Steam Discharge (Kr-88)

Pri: (2MSS-RQ101A) 1/SG 1, 2, 3, & 4 s 3.9E-2 µCi/cc lE-2 to 1E+3 µCi/cc 35 PMM: (Form l/2-ENV-05.05.F07)

Pri: (2MSS-RQ101B) 1/SG 1, 2, 3, & 4 s 3.9E-2 µCi/cc 1E~2 to 1E+3 µCi/cc 35 PMM: (Form l/2-ENV-05.05.F07)

Pri: (2MSS-RQ101C) 1/SG 1, 2, 3, & 4 s 3.9E-2 µCi/cc lE-2 to 1E+3 µCi/cc 35 PMM: (Form l/2-ENV-05.05.F07)

(a)

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, 1

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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(3)

ATTACHMENT D Page 5 of 8 ODCM CONTROLS:* RADIATION MONITORING INSTRUMENTATION Above background Nominal range for High.

TABLE 3.3-6 (Continued)

TABLE NOTATIONS Other PING 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 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , 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 generate a condition report and explain in the next Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

Beaver Valley Power Station Procedure Number:

l/2-0DC-3.03

Title:

Unit:

Level Of Use:

1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision:

Page Number:

?_.c; of R1 ATTACHMENTD Page 6 of 8 ODCM CONTROLS: RADIATION MONITORING INSTRUMENTATION TABLE 4.3-3 (Continued)

BV-1 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Pri = Primary Instruments, PMM = Preplanned Method of MonitoringCa)

INSTRUMENT CHANNEL CHANNEL CHANNEL CHECK CALIBRATION OPERATIONAL TEST

1.

Noble Gas Effluent Monitors - PINGS a.Reactor Building/SLCRS (CV-1; Also called Elevated Release)

High Range Noble Gas S

R M

Pri: (RM-lVS-110 HRNG Rel) lstPMM: (RM-lVS-110 LRNG Rel) 2ndPMM: (RM-IVS-107B) 3rd PMM: Grab Sampling every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

b.

Auxiliary Building Ventilation System (VV-1; Also called Ventilation Vent)

High Range Noble Gas S

R M

Pri: (RM-lVS-109 HRNG Rel) 1st PMM: (RM-1VS-109 LRNG Rel) 2nd PMM: (RM-lVS-lOlB) 3rd PMM: Grab Sampling every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

c.

Gaseous Waste Process Vent System (PV-1,2)

High Range Noble Gas S

Pri: RM-lGW-109 HRNG Rel) 1st PMM: (RM-lGW-109 LRNG Rel) 2nd PMM: (RM-1GW-108B) 3rd PMM: Grab Sampling every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months R

M MODES IN WHICH SURVEILLANCE REQUIRED 1, 2, 3, & 4 1, 2, 3, & 4 1, 2, 3, & 4 (a)

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.

Beaver Valley Power Station Procedure Number:

l/2-0DC-3.03

Title:

Unit:

Level Of Use:

1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision:

Page Number:

26 ofSn ATTACHMENTD Page 7 of 8 ODCM CONTROLS: RADIATION MONITORING INSTRUMENTATION TABLE 4'.3-3 (Continued)

BV-1 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Pri = Primary Instruments, PMM = Preplanned Method of Monitoring<a)

INSTRUMENT

2. Noble Gas Effluent Steam Monitors CHANNEL CHECK CHANNEL CHANNEL CALIBRATION OPERATIONAL TEST

a.

Atmospheric Steam Dump Valve and Code Safety Relief Valve Discharge Pri: (RM-lMS-lOOA)

S R

M PMM: (Form 1/2-ENV.05.05.F07)

Pri: (RM-lMS-lOOB) s R

M PMM: (Form 1/2-ENV.05.05.F07)

Pri: (RM-lMS-lOOC) s R

M PMM: (Form 1/2-ENV.05.05.F07)

b.

Auxiliary Feedwater Pump Turbine Exhaust Pri: (RM-lMS-101) s R

M PMM: (Form 1/2-ENV.05.05.F07)

MODES IN WHICH SURVEILLANCE REQUIRED 1, 2, 3, & 4 1, 2, 3, &4 1,2,3,&4 1,2,3,&4 (a)

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.

Beaver Valley Power Station Procedure Number:

l/2-0DC-3.03

Title:

Unit:

Level Of Use:

1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision:

15 Page Number:

?7 nfR1 ATTACHMENT D Page 8 of 8 ODCM CONTROLS: RADIATION MONITORING INSTRUMENTATION TABLE 4.3-3 (Continued)

BV-2 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Pri== Primary Instruments, PMM = Preplanned Method of Monitoring<a)

INSTRUMENT

1. Noble Gas Effluent Monitors CHANNEL CHECK CHANNEL,

CHANNEL CALIBRATION OPERATIONAL TEST

a.

SLCRS Unfiltered Pathway (CV-2; Also called Elevated Release)

Mid Range Noble Gas S

R Pri: (2HVS-RQ109C) 1st PMM: (2HVS-RQ109D) 2nd PMM: (2HVS-RQ109B) 3rd PMM: Grab Sampling every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months High Range Noble Gas S

Pri: (2HVS-RQ109D) 1st PMM: (2HVS-RQ109C) 2nd PMM: (2HVS-RQ109B) 3rd PMM: Grab Sampling every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

2. Noble Gas Effluent Steam Monitors

a.

Main Steam Discharge (Kr-88)

Pri: (2MSS-RQ101A) -

S PMM: (Form 1/2-ENV.05.05.F07)

Pri: (2MSS-RQ101B)

S PMM: (Form 1/2-ENV.05.05.F07)

Pri: (2MSS-RQ101C)

S PMM: (Form 1/2-ENV.05.05.F07)

R R

M M

M MODES IN WHICH SURVEILLANCE REQUIRED 1, 2, 3, & 4 1, 2, 3, & 4 1, 2, 3, & 4 1, 2, 3, &4 1, 2, 3, & 4 (al 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.

Beaver Valley Power Station Procedure Number:

l/2-0DC-3.03

Title:

Unit:

Level Of Use:

1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision:

Page Number:

'J~ of R1 ATTACHMENT E Page 1 of 10 ODCM CONTROLS: RETS INSTRUMENTATION FOR LIQUID EFFLUENTS CONTROLS: RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 3.3.3.9 In accordance with T.S. 5.5.2.a, 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 3.11.1.1 are not exceeded. The alarm/trip setpoints of the radiation monitoring channels shall be determined in accordance with l/2-0DC-2.01.

Applicability - During Releases Through the Flow Path:

a. For all Gross Activity (e.g.; Beta or Gamma) Radioactivity Monitors

b. For all Flow Rate Measurement Devices Applicability - During Liquid Additions to the Tanlc

a. For all Tank Level Indicating Devices 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 alarm/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, generate a Condition Report and explain in the next Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner. Ca)

'C.

The p!iovisions 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 OPERATIONAL TEST operations at the frequencies shown in ODCM Control 3.3.3.9, Table 4.3-12.

<*) Condition Report generation and reporting in the Radioactive Effluent Release Report (per Control 3.3.3.9 Action b) do not apply when using an alternate to satisfy inoperability of the primary instrument beyond 30 days.

Beaver Valley Power Station Procedure Number:

l/2-0DC-3.03

Title:

Unit:

Level Of Use:

1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision:

15 Page Number:

29 of ~n ATTACHMENT E Page 2 of 10 ODCM CONTROLS: RETS INSTRUMENTATION FOR LIQUID EFFLUENTS TABLE 3.3-12 BV-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Pri = Primary Instruments Alt= Alternate Instruments (a)

MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION

1. Gross Activity Monitors Providing Automatic Termination Of Release

a.

Liquid Waste Effluents Monitor (1) 23 Pri: [RM-lLW-104]

b. Liquid Waste Contaminated Drain Monitor (1) 23 Pri: [RM-lLW-116]

C.

Auxiliary Feed Pump Bay Drain Monitor (1) 24 Pri: [RM-lDA-100]

2. Gross Activity Monitors Not Providing Termination Of Release

a.

Component Cooling-Recirculation Spray Heat (1) 24 Exchangers River Water Monitor Pri: [RM-lRW-100]

3. Flow Rate Measurement Devices a

Liquid Radwaste Effluent Line (1) 25 Pri: [FR-lLW-104] for [RM-lLW-104]

b. Liquid Waste Contaminated Drain Line (1) 25 Pri: [FR-lLW-103] for [RM-lLW-116]

C.

Cooling Tower Blowdown Line (1) 25A Pri: [FT-lCW-101-1], or 1st Alt: [FT-lCW-101] and [2CWS-FT101], or 2nd Alt: Perform lMSP-31.06-I

4. Tank Level Indicating Devices (for tanks outside plant building)

a.

Primary Water Storage Tank (1) 26 Pri: [LI-1PG-115A] for [1BR-TK-6A]

b. Primary Water Storage Tank (1) 26 Pri: [LI-1PG-115B] for [1BR-TK-6B]

C.

Steam Generator Drain Tank (1) 26 Pri: [LI-lLW-110] for [1LW-TK-7A]

d.

Steam Generator Drain Tank (1) 26 Pri: [LI-lLW-111] for [1LW-TK-7B]

(a) Condition Report generation and reporting in the Radioactive Effluent Release Report (per Control 3.3.3.9 Action b) do not apply when using an alternate to satisfy inoperability of the primary instrument beyond 30 days.

/

Beaver Valley Power Station Procedure Number:

Title:

ODCM: Controls for RETS and REMP Programs ATTACHMENT E Page 3 of 10 Unit:

1/2 Revision:

1.-:;

l/2-0DC-3.03 Level Of Use:

General Skill Reference Page Number:

10 ofln ODCM CONTROLS: RETS INSTRUMENTATION FOR LIQUID EFFLUENTS TABLE 3.3-12 (continued)

BV-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Pri = Primary Instruments Alt = Alternate Instruments <*>

INSTRUMENT MINIMUM CHANNELS OPERABLE ACTION

1. Gross Radioactivity Monitor Providing Alarm, And Automatic Termination Of Release

a. Liquid Waste Process Effluent Monitor Pri: [2SGC-RQ100]

(1) 23

2. Gross Radioactivity Monitors Providing Alarm, But Not Providing Termination Of Release

a. None Required

3. Flow Rate Measurement Devices

a. Liquid Radwaste Effluent Pri: [2SGC-FS100]

b. Cooling Tower Blowdown Line Pri: [FT-lCW-101-1], or 1st Alt: [FT-lCW-101] and [2CWS-FT101], or 2nd Alt: Perform lMSP-31.06-I

4. Tank Level Indicating Devices (for ~anks outside plant buildings)

a. None Required (1) 25 (1) 25A

<*> Condition Report generation and reporting in the Radioactive Effluent Release Report (per Control 3.3.3.9 Action b) do not apply when using an alternate to satisfy inoperability of the primary instrument beyond 30 days.

Beaver Valley Power Station Procedure Number:

l/2-0DC-3.03

Title:

Unit:

Level Of Use:

1/2 General Skill Reference Revision:

15 Page Number:

11 of R1 ODCM: Controls for RETS and REMP Programs Action 23 Action 24 ATTACHMENT E Page 4 of 10 ODCM CONTROLS: RETS INSTRUMENTATION FOR LIQUID EFFLUENTS TABLE 3.3-12 (continued)

ACTION STATEMENTS 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 4.11.1.1.1, and at least two technically qualified members of the Facility Staff independently verify the release rate calculationsCI) 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.

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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months grab samples are analyzed for gross radioactivity (beta or gamma) at a Lower Limit of Detection (LLD) of at least lE-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.

(I) 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 Procedure Number:

l/2-0DC-3.03

Title:

Unit:

Level Of Use:

1/2 General Skill Reference Revision:

15 Page Number:

32 of 83 ODCM: Controls for RETS and REMP Programs ATTACHMENT E Page 5 of 10 ODCM CONTROLS: RETS INSTRUMENTATION FOR LIQUID EFFLUENTS Action25 Action25A Action26 Table 3.3-12 (continued)

ACTION STATEMENTS 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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.

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue by using the method required for the 1st Alternate, or by using the instruments required by the 2nd Alternate, as follows:

1. 1st Alternate: Initiate monitoring with the comparable alternate monitoring channel, which includes both [FT-lCW-101] and [2CWS-FTI01]. ODCM Surveillance requirements applicable to the inoperable channel shall apply to the comparable alternate monitoring channel when used to satisfy this ODCM CONTROL requirement, or

2. 2nd Alternate: The dilution flow rate is calculated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases using the methods described in procedure lMSP-31.06-I(l).

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.

(l) NOTE: This MSP requires local water height measurements to calculate the total cooling tower blowdown flow rate. As* a guide, the combined flow rate result of this procedure should be similar to the ODCM design value 22,800 gpm (i.e., BV-1 flow rate= 15,000 gpm, + BV-2 flow rate= 7,800 gpm) which assumes operation of a BV-1 Turbine Plant RW Pump, a BV-1 Rx Plant RW Pump, a BV-2 SWS Pump, and normal evaporation via the cooling tower plume.

Beaver Valley Power Station Procedure Number:

l/2-0DC-3.03

Title:

Unit:

Level Of Use:

1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision:

Vi Page Number:

'.n nfR1 ATTACHMENT E Page 6 of 10 ODCM CONTROLS: RETS INSTRUMENTATION FOR LIQUID EFFLUENTS TABLE 4.3-12 BV-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Pri = Primary Instruments, Alt= Alternate Instruments INSTRUMENT CHANNEL CHECK SOURCE CHECK CHANNEL CHANNEL CALIBRATION OPERATIONAL TEST

1. Gross Beta or Gamma Radioactivity Monitors Providing Alarm And Automatic Termination Of Release

a.

Liquid Radwaste Effluent Line D

p(5)

R<3)

Q(J)

Pri: (RM-lLW-104)

b.

Liquid Waste Contaminated Drain Line Pri: (RM-lLW-116)

c.

Auxiliary Feed Pump Bay Drain Monitor Pri: (RM-lDA-100)

D p(5)

D D

2. Gross Beta Or Gamma Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination Of Release

a.

Component Cooling - Recirculation Spray D

M<s)

R(3)

Q(2)

Heat Exchangers River Water Monitor Pri: (RM-lRW-100)

3. Flow Rate Monitors

a.

Liquid Radwaste Effluent Lines n<4)

NA R

Q Pri: (FR-lLW-104) for (RM-lLW-104)

b.

Liquid Waste Contaminated Drain Line n<4)

NA R

Q Pri: (FR-lLW-103) for (RM-lLW-116)

C.

Cooling Tower ~lowdown Line n<4l NA R

Q Pri: [FT-lCW-101-1), or 1st Alt: [FT-lCW-101] and [2CWS-FT101]

NOTE: SINCE the 2nd Alternate to the Cooling Tower Blowdown Line is a procedure, (i.e., lMSP-31.06-1),

THEN Surveillance Requir~ments do not apply to the 2nd Alternate.

Beaver Valley Power Station Procedure Number:

l/2-0DC-3.03

Title:

Unit:

Level Of Use:

1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision:

15 Page Number:

34 ofln

4.

a.

b.

c.

d.

ATTACHMENT E Page 7 of 10 ODCM CONTROLS: RETS INSTRUMENTATION FOR LIQUID EFFLUENTS TABLE 4.3-12 (continued)

BV-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Pri = Primary Instruments, Alt = Alternate Instruments INSTRUMENT CHANNEL CHECK SOURCE CHECK CHANNEL CHANNEL CALIBRATION OPERATIONAL TEST Tank Level Indicating Devices (for tanks outside plant buildings)

Primary Water Storage Tank D*

NA R

Q Pri: (LI-1PG-l 15A) for (1BR-TK-6A)

Primary Water Storage Tank D*

NA R

Q Pri: (LI -1PG-l 15B) for (1BR-TK-6B)

Steam Generator Drain Tank D*

NA R

Q Pri: (Ll-lLW-110) for (1LW-TK-7A)

Steam Generator Drain Tank D*

NA R

Q Pri: (Ll-lLW-111) for (1LW-TK-7B)

During liquid additions to the tank.

Beaver Valley Power Station Procedure Number:

l/2-0DC-3.03

Title:

Unit:

Level Of Use:

1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision:

Page Number:

1'5 of R1 ATTACHMENT E Page 8 of 10 ODCM CONTROLS: RETS INSTRUMENTATION FOR LIQUID EFFLUENTS TABLE 4.3-12 (continued)

BV-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Pri = Primary Instruments, Alt= Alternate Instruments CHANNEL CHANNEL CHECK SOURCE CHECK CHANNEL OPERATIONAL INSTRUMENT CALIBRATION TEST

1. Gross Radioactivity Monitor Providing Alarm And Automatic Termination Of Release

a.

Liquid Waste Process Effluent D

p(5)

RC7)(3)

Pri: (2SGC-RQ100)

2. Flow Rate Measurement Devices

a.

Liquid Radwaste Effluent Pri: (2SGC-FS100)

b.

Cooling Tower Blowdown Line Pri: [FT-lCW-101-1], or 1st Alt: [FT-lC::::W-101] and [2CWS-FT101]

DC4)

DC4l NOTE: SINCE the 2nd Alternate to the Cooling Tower Blowdown Line is a procedure, (i.e., lMSP-31.06-1),

THEN Surveillance Requirements do not apply to the 2nd Alternate.

3. Tank Level Indicating Devices (for tanks outside plant buildings)

a.

None Required NA R

NA R

Q Q

Beaver Valley Po:wer Station Procedure Number:

l/2-0DC-3.03

Title:

Unit:

Level Of Use:

1/2 General Skill Reference Revision:

15 Page Number:

16 of ~n ODCM: Controls for RETS and REMP Programs

(!)

ATTACHMENT E Page 9 of 10 ODCM CONTROLS: RETS INSTRUMENTATION FOR LIQUID EFFLUENTS TABLE 4.3-12 (continued)

TABLE NOTATION The CHANNEL OPERATIONAL TEST shall also demonstrate that automatic fsolation 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.

c2)

The CHANNEL OPERATIONAL TEST shall also demonstrate that Control Room Alarm Annunciation occurs if any of the following conditions exist:

(3)

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 Institute of Science and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. 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).

C4)

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.

C5)

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.

Beaver Valley Power Station

Title:

ODCM: Controls for RETS and REMP Programs ATTACHMENT E Page 10 of 10 Procedure Number:

l/2-0DC-3.03 Unit:

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1/2 General Skill Reference Revision:

Page Number:

17 ofSn ODCM CONTROLS: RETS INSTRUMENTATION FOR LIQUID EFFLUENTS TABLE 4.3-12 (continued)

TABLE NOTATION C6)

The CHANNEL CALIBRATION 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.

C7)

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 Procedure Number:

l/2-0DC-3.03

Title:

Unit:

Level Of Use:

1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision:

Page Number:

1R of R1 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 T.S. 5.5.2.a, the radioactive gaseous effluent monitoring instrumentation channels shown in ODCM Control 3.3.3.10, Table 3.3-13 shall be operable with their alarm/trip setpoints set to ensure that the limits ofODCM CONTROL 3.11.2.1 are not exceeded. The alarm/trip setpoints of the radiation monitoring channels shall be determined in accordance with l/2-0DC-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, generate a Condition Report and explain in the next 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 c4annel shall be demonstrated operable by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL OPERATIONAL TEST operations at the frequencies shown in ODCM Control 3.3.3.10, Table 4.3-13.

<*) Condition Report generation and reporting in the Radioactive Effluent Release Report (per Control 3.3.3.IO Action b) do not apply when using an alternate to satisfy inoperability of the primary instrument beyond 30 days.

Beaver Valley Power Station Procedure Number:

l/2-0DC-3.03

Title:

Unit:

Level Of Use:

1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision:

Page Number:

19 of R1

'* 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 INSTRUMENT

1. Gaseous Waste/Process Vent System (PV-1/2)

Alt = Alternate Instruments (a)

MINIMUM CHANNELS OPERABIB APPI1CABILIIY ACIION

a.

Noble Gas Activity Monitor Pri: [RM-1GW-108B], or (1) 27,29,30A,30B Alt For Continuous Release: [RM-lGW-109 LRNG Rel] may only be used as the comparable alternate monitoring channel for continuous releases via this pathway.

Alt For Batch Releases: [NONE, see Action 27]; For information, [RM-lGW-109 LRNG Rel] SHALL NOT be used as the comparable alternate monitoring channel for batch releases of the BV-1 GWDTs or the BV-2 GWSTs.

Specifically, SINCE 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-1 GWDTs or the BV-2 GWSTs via this pathway.

b.

Particulate and Iodine Sampler (1)

Pri: Filter Paper & Charcoal Cartridge for [RM-lGW-109], or 1st Alt: Filter Paper & Charcoal Cartridge for [RM-lGW-108] (b), or 2nd Alt: Continuous collection via RAS Pump

c.

System Effluent Flow Rate Measuring Device Pri: [FR-lGW-108], or Alt: [RM-1GW-109LRSTKFL]

d.

Sampler Flow Rate Measuring Device Used for Particulate and Iodine Sample Collection (see l.b)

Pri: [ABPM-lGW-109-PISFlow], or 1st Alt: Rotameter for [RM-lGW-108]

2nd Alt: RAS Pump Flow Instrument (1)

(1)

During Releases via this pathway.

32 28A 28B (a) Condition Report generation and reporting in the Radioactive Effluent Release Report (per Control 3.3.3.10 Action b) do not apply when using an alternate to satisfy inoperability of the primary instrument beyond 30 days.

(b) May be used as a sampled flow path provided flow is verified. Radiation monitor operability is not required.

Beaver Valley Power Station

Title:

ODCM: Controls for RETS and REMP Programs ATTACHMENT F Page 3 of 13 Procedure Number:

l/2-0DC-3.03 Unit:

Level Of Use:

1/2 General Skill Reference Revision:

Page Number:

1 'i LI.() nf 81 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 (a) lNS1RUMENT MINIMUM CHANNELS OPERABIB

2. Auxiliary Building Ventilation System (VV-1; Also called Ventilation Vent)

a.

Noble Gas Activity Monitor (1)

Pri: [RM-lVS-109 LRNG Rel], or Alt: [RM-lVS-lOlB]

b.

Particulate and Iodine Sampler (1)

Pri: Filter Paper & Charcoal Cartridge for [RM-1VS-109], or 1st-Alt: Filter Paper & Charcoal Cartridge for [RM-1 VS-101] (b), or 2nd Alt: Continuous collection via RAS Pump

c.

System Effluent Flow Rate Measuring Device (1)

Pri:, [FR-lVS-101] or Alt: [RM-1VS-109 LR STK FL]

d.

Sampler Flow Rate Measuring Device Used for (1)

Particulate and Iodine Sample Collection (see 2.b)

Pri: [ABPM-lVS-109-PISFlow], or 1st Alt: [FT-lRM-101] & [Fl-lRM-101]

2nd Alt: RAS Pump Flow Instrument 3.Reactor Building/SLCRS (CV-1; Also called Elevated Release)

a.

Noble Gas Activity Monitor Pri: [RM-lVS-110 LRNG Rel], or Alt: [RM-1VS-107B]

(1)

b.

Particulate and Iodine Sampler (1)

Pri: Filter Paper & Charcoal Cartridge for [RM-1 VS-110], or 1st Alt: Filter Paper & Charcoal Cartridge for [RM-lVS-107] (bl, or 2nd Alt: Continuous collection via RAS Pump

c.

System Effluent Flow Rate Measuring Device Pri:, [FR-1 VS-112] (b) or Alt: [RM-lVS-110 LR STKFL]

d.

Sampler Flow Rate Measuring Device Used for Particulate and Iodine Sample Collection (see 3.b)

Pri: [ABPM-lVS-110-PISFlow], or 1st Alt: Rotameter for [RM-1 VS-I 07]

2nd Alt: RAS Pump Flow Instrument (1)

(1)

During Releases via this pathway.

APPilCABILITY ACTION 29,30A 32 28A 28B 29,30A 32 28A 28B

<*) Condition Report generation and reporting in the Radioactive Effluent Release Report (per Control 3.3.3.10 Action b) do not apply when using an alternate to satisfy inoperability of the primary instrument beyond 30 days.

(b) May be used as a sampled flow path provided flow is verified. Radiation monitor operability is not required.

()0 er (M

~

Ii

Beaver Valley Power Station

Title:

ODCM: Controls for RETS and REMP Programs ATTACHMENT F Page 4 of 13 Procedure Number:

Unit:

1/2 Revision:

1.::;

l/2-0DC-3.03 Level Of Use:

General Skill Reference Page Number:

41 of R'i ODCM CONTROLS: RETS INSTRUMENT FOR GASEOUS RELEASES TABLE 3.3-13 (continued)

BV-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Pri = Primary Instmlllent_s Alt = Alternate Instruments Ca)

INSTRUMENT

-- MINIMUM CHANNELS OPERABIB APPUCABIU1Y ACTION

1. SLCRS Unfiltered Path'!'ay (VV-2; Also called Ventilation Vent)

a.

Noble Gas Activity Monitor (1)

Pri: [2HVS-RQ101B]

b.

Particulate and Iodine Sampler (1)

Pri: Filter Paper & Charcoal Cartridge for [2HVS-RQ101], or Alt: Continuous collection via RAS Pump

c.

Process Flow Rate Monitor Pri: Monitor Item 29 for [2HVS-VP101]

d.

Sampler Flow Rate Monitor Used for Particulate and Iodine Sample Collection (see 1.b)

Pri: [2HVS-FIT101-1], or Alt: RAS Pump Flow Instrument

2. SLCRS Filtered Pathway (CV-2; Also called Elevated Release)

(1)

a.

Noble Gas Activity Monitor (1)

Pri: [2HVS-RQ109B]

b.

Particulate and Iodine Sampler (1)

Pri: Filter Paper & Charcoal Cartridge for [2HVS-RQ109] High Flow Path, or Alt: Continuous collection via RAS Pump

c.

Process Flow Rate Monitor (1)

Pri: Monitor Item 29 for [2HVS-FR22], or 1st Alt: [2HVS-FI22A and FI22C], or 2nd Alt: [2HVS-FI22B and FI22D]

d.

Sampler Flow Rate Monitor Used for Particulate and Iodine Sample Collection (see 2.b)

Pri: l\\,1op.it9r ltem 28 & 72 fo![2_!IVS::Pb.U199B], or Alt: RAS Pump Flow Instrument

3. Decontamination Building Vent (DV-2)

a.

Noble Gas Activity Monitor Pd: [2RMQ-RQ301B]

(1)

b.

Particulate and Iodine Sampler (1)

Pri: Filter Pap_er_8l Cb!!I~Q~l_ Cwtridge for [2IW-[Q-R.Q3Jl_l], or__

Alt: Continuous collection via RAS Pump

c.

Process Flow Rate Monitor

d.

Sampler Flow Rate Monitor Used for Particulate and Iodine Sample Collection (see 3.b)

Pri: [2RMQ~FIT30I~1J,--or - -

Alt: RAS Pump Flow Instrument None (1)

During Releases via this pathway.

None

________ 29,_30B ____ _

32 28A 28B 29,30B 32 28A 28B 29 32 None 28B

<*) Condition Report generation and reporting in the Radioactive Effluent Release Report (per Control 3.3.3.10 Action b) do not apply when using an alternate to satisfy inoperability of the primary instrument beyond 30 days.

~

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11 I

Beaver Valley Power Station

Title:

ODCM: Controls for RETS and REMP Programs ATTACHMENT F Page 5 of 13 Procedure Number:

l/2-0DC-3.03 Unit:

Level Of Use:

1/2 General Skill Reference Revision:

Page Number:

1 'i 42 of~n ODCM CONTROLS: RETS INSTRUMENT FOR GASEOUS RELEASES TABLEJ.3-13 (continued)

BV-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Pri = Primary Instruments Alt= Alternate Instruments (a)

MINIMUM CHANNELS INSTRUMENT OPERABIB

4. Condensate Polishing Building Vent (CB-2)

a.

Noble Gas Activity Monitor (1)

Pri: [2HVL-RQ112B]

b.

Particulate and Iodine Sampler (1)

Pri: Filter Paper & Charcoal Cartridge for [2HVL-RQ112], or Alt: Continuous collection via RAS Pump

c.

Process Flow Rate Monitor None

d.

Sampler Flow Rate Monitor Used for Particulate (1) and Iodine Sample Collection (see 4.b)

Pri: [2HVL-FIT112-1], or Alt: RAS Pump Flow Instrument

5. Waste Gas Storage Vault Vent (WV-2)

a.

Noble Gas Activity Monitor (1)

Pri: [2RMQ-RQ303B]

b.

Particulate and Iodine Sampler (1)

Pri: Filter Paper & Charcoal Cartridge for [2RMQ-RQ303], or Alt: Continuous collection via RAS Pump

c.

Process Flow Rate Monitor None

d.

Sampler Flow Rate Monitor Used for Particulate and Iodine Sample Collection (see 5.b)

Pri: [2RMQ-FIT303-1], or Alt: RAS Pump Flow Instrument (1)

During Releases via this pathway.

APPUCABILITY None None ACIION 29 32 None 28B 29 32 None 28B I

<*) Condition Report generation and reporting in the Radioactive Effluent Release Report (per Control 3.3.3.10 Action b) do not apply when using an alternate to satisfy inoperability of the primary instrument beyond 30 days.

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Beaver Valley Power Station Procedure Number:

l/2-0DC-3.03

Title:

Unit:

Level Of Use:

1/2 General Skill Reference Revision:

15 Page Number:

41 of R1 ODCM: Controls for RETS and REMP Programs Action 27 ATTACHMENTF Page 6 of 13 ODCM CONTROLS: RETS INSTRUMENT FOR GASEOUS RELEASES TABLE 3.3-13 (continued)

ACTION STATEMENTS APPLICABLE FOR BATCH RELEASES OF BV-1 GASEOUS WASTE DECAY TANKS ORBV-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 ( or resuming) 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 ofradioactive 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ( or assumed to be at the ODCM design value Cl>), 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.

Cl)

In lieu of estimating the system/process flow rate at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , the system/process flow rate can be assumed to be at the following ODCM design values:

?

1,450 cfi.n = 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 Procedure Number:

l/2-0DC-3.03

Title:

Unit:

Level Of Use:

1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision:

15 Page Number:

44 of ~n ATTACHMENT F Page 7 of 13 ODCM CONTROLS: RETS INSTRUMENT FOR GASEOUS RELEASES TABLE 3.3-13 (continued)

ACTION STATEMENTS Action 28B APPLICABLE FOR BV-1 SAMPLER FLOW RA TE MEASURING DEVICES OR BV-2 SAMPLER FLOWRA TE 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , or

2.

Initiate yontinuous 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 29 APPLICABLE FOR CONTINUOUS RELEASES (1)

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)<1) are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . If grab samples are taken, these samples are to be analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months in-lieu of obtaining grab samples at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Beaver Valley Power Station Procedure Number:

l/2-0DC-3.03

Title:

Unit:

Level Of Use:

1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision:

Page Number:

4.'i of R1 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 INITIAL 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 this pathway if both RM-1 VS-104A and Bare 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 APPLICABLE FOR THE INITIAL BATCH PURGE OF THE BV-2 REACTOR CONTAINMENT Action 32 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 ofreactor 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.

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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Beaver Valley Power Station Procedure Number:

l/2-0DC-3.03

Title:

Unit:

Level Of Use:

1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision:

1.:;

Page Number:

46 nfR1 ATTACHMENT F Page 9 of 13 ODCM CONTROLS: RETS INSTRUMENT FOR GASEOUS RELEASES TABLE 4.3-13 BV-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Pri = Primary Instruments Alt = Alternate Instruments CHANNEL SOURCE CHANNEL INSTRUMENT CHECK CHECK CALIBRATION

1. Gaseous Waste/Process Vent System (PV-1/2)

CHANNEL OPERATIONAL TEST

a.

Noble Gas Activity Monitor P

p(4)

R(3)

Q(I)

Pri: [RM-1GW-108B], or Alt For Continuous Release: [RM-lGW-109 LRNG Rel] This channel may only be used as the comparable alternate monitoring channel for continuous releases via this pathway.

Alt For Batch Releases: [NONE, See Action 27]; For information, [RM-1GW-109 LRNG Rel] SHALL NOT be used as the comparable alternate monitoring channel for batch releases of the BV-1 GWDTs or the BV-2 GWSTs.

Specifically, SINCE 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-1 GWDTs or the BV-2 GWSTs via this pathway

b.

Particulate and Iodine Sampler W

NA NA NA Pri: Filter Paper & Charcoal Cartridge for [RM-lGW-109], or 1st Alt: Filter Paper & Charcoal Cartridge for [RM-1GW-108] (bl, or 2nd Alt: Continuous collection via RAS Pump

c.

System Effluent Flow Rate Measuring Device Pri: [FR-1GW-108], or Alt: [RM-1GW-109 LR STK FL]

d.

Sampler Flow Rate Measuring Device Used for Particulate and Iodine Sample Collection (see 1.b)

Pri: [ABPM-1GW-109-PISFlow], or 1st Alt: Rotameter for [RM-1GW-108]

2nd Alt: RAS Pump Flow Instrument p

D*

NA NA

During Releases via this pathway.

R Q

(b) May be used as a sampled flow path provided flow is verified. Radiation monitor operability is not required.

Beaver Valley Power Station Procedure Number:

l/2-0DC-3.03

Title:

Unit:

Level Of Use:

1/2 General Skill Reference Revision:

Page Number:

ODCM: Controls for RETS and REMP Programs 47 of R1 ATTACHMENT F Page 10 of 13 ODCM CONTROLS: RETS INSTRUMENT FOR GASEOUS RELEASES TABLE 4.3-13 BV-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Pri = Primary Instruments Alt= Alternate Instruments

2. Auxiliary Building Ventilation System (VV-1; Also called Ventilation Vent)

a.

Noble Gas Activity Monitor D

Pri: [RM-lVS-109 LRNG Rel], or Alt: [RM-1VS-10IB]

b.

Particulate and Iodine Sampler w

Pri: Filter Paper & Charcoal Cartridge for [RM-1VS-109], or 1st Alt: Filter Paper & Charcoal Cartridge for [RM-lVS-101] (bl, or 2nd Alt: Continuous collection via RAS Plimp

c.

System Effluent Flow Rate Measurement D

Device Pri: [FR-lVS-101], or Alt: [RM-lVS-109 LR STK FL]

d.

Sampler Flow Rate Measuring Device Used D

for Particulate and Iodine Sample Collection (see 2.b)

Pri: [ABPM-lVS-109-PISFlow], or 1st Alt: [FT-lRM-101] & [FI-lRM-101]

2nd Alt: RAS Pump Flow Instrument

3. Reactor Building/SLCRS (CV-1; Also called Elevated Release)

a.

Noble Gas Activity Monitor D

Pri: [RM-lVS-110 LRNG Rel], or Alt: [RM-1VS-107B]

b.

Particulate and Iodine Sampler W

Pri: Filter Paper & Charcoal Cartridge for [RM-1 VS-11 O], or 1st Alt: Filter Paper & Charcoal Cartridge for [RM-1 VS-107] (bl, or 2nd Alt: Continuous collection via RAS Pump

c.

System Effluent Flow Rate D

Measuring Device Pri: [FR-1 VS-112] (bl, or Alt: [RM-IVS-110 LR STK FL]

d.

Sampler Flow Rate Measuring Device Used for Particulate and Iodine Sample Collection (see 3.b)

Pri: [ABPM-IVS-110-PISFlow], or 1st Alt: Rotameter for [RM-1 VS-107]

2nd Alt: RAS Pump Flow Instrument D

M(4) p(4)***

NA NA NA M(4) p(4)***

NA NA NA

- - During purging of Reactor Containment via this pathway.

R(3l NA R

R NA R

R (b) May be used as a sampled flow path provided flow is verified. Radiation monitor operability is not required.

NA Q

Q NA Q

Q

Procedure Number:

Beaver Valley Power _Station l/2-0DC-3.03

Title:

ODCM: Controls for RETS and REMP Programs ATTACHMENT F Page 11 of 13 Unit:

1/2 Revision:

15 Level Of Use:

General Skill Reference Page Number:

4R of~-::t ODCM CONTROLS: RETS INSTRUMENT FOR GASEOUS RELEASES TABLE 4.3-13 (continued)

BV-2 RADIOACTIVE GASEOUS EFFLUENT MONITORJNG INSTRUMENTATION SURVEILLANCE REQUIREMENTS Pri = Primary Instruments Alt = Alternate Instruments CHANNEL SOURCE CHANNEL INSTRUMENT CHECK CHECK CALIBRATION i

1.SLCRS Unfiltered Pathway (VV-2; Also called Ventilation Vent)

a.

Noble Gas Activity Monitor D

M(4)

R(3)(6)

Pri: [2HVS-RQ101B]

p(4h**

b.

Particulate and Iodine Sampler w

NA NA Pri: Filter Paper & Charcoal Cartridge for [2HVS-RQ101], or Alt: Continuous collection via RAS Pump

c.

Process Flow Rate Monitor D

NA R

Pri: (Monitor Item 29 for [2HVS-VP101]

d.

Sampler Flow Rate Monitor Used for Particulate D

NA R

and Iodine Sample Collection (see 1.b)

Pri: [2HVS-FIT101-l], or Alt: RAS Pump Flow Instrument

2. SLCRS Filtered Pathway (CV-2; Also called Elevated Release)

a.

Noble Gas Activity Monitor D

M(4)

R(3)(6)

Pri: [2HVS-RQ109B]

p(4)***

b.

Particulate and Iodine Sampler w

NA NA Pri: Filter Paper & Charcoal Cartridge for [2HVS-RQ109] High Flow Path, or Alt: Continuous collection via RAS Pump

c.

Process Flow Rate Monitor D

NA R

Pri: Monitor Item 29 for [2HVS-FR22], or 1st Alt: [2HVS-FI22A and FI22C], or 2nd Alt: [2HVS-FI22B and FI22D]

d.

Sampler Flow Rate Monitor Used for Particulate D

NA R

and Iodine Sample Collection (see 2.b)

Pri: Monitor Items 28 and 72 for [2HVS-DAU109B], or Alt: RAS Pump Flow Instrument

3. Decontamination Building Vent (DV-2)

a.

Noble Gas Activity Monitor D

M(4)

R(3)(6)

Pri: [2RMQ-RQ301B]

b.

Particulate and Iodine Sampler w

NA NA Pri: Filter Paper & Charcoal Cartridge for [2RMQ-RQ301], or Alt: Continuous collection via RAS Pump

c.

Process Flow Rate Monitor NA NA NA

d.

Sampler Flow Rate Monitor Used for Particulate D

NA

R and Iodine Sample Collection (see 3.b)

Pri: [2RMQ-FIT301-1], or Alt: RAS Pump Flow Instrument

- - During purging of Reactor Containment via this pathway.

CHANNEL OPERATIONAL TEST Q(5)

NA Q

Q Q(5)

NA Q

Q Q(5)

NA NA Q

!9

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~

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Beaver Valley Power Station Procedure Number:

l/2-0DC-3.03

Title:

Unit:

Level Of Use:

1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision:

. 15 Page Number:

4g ofR1 ATTACHMENT F Page 12 of 13 ODCM CONTROLS: RETS INSTRUMENT FOR GASEOUS RELEASES TABLE 4.3-13 (continued)

BV-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Pri = Primary Instruments Alt= Alternate Instruments CHANNEL SOURCE CHANNEL INSTRUMENT CHECK CHECK CALIBRATION

4. Condensate Polishing Building Vent (CB-2)

a.

Noble Gas Activity Monitor D

M(4)

R(3)(6)

Pri: [2HVL-RQ112B]

b.

Particulate and Iodine Sampler w

NA NA Pri: Filter Paper & Charcoal Cartridge for [2HVL-RQ112], or Alt: Continuous collection via RAS Pump

c.

Process Flow Rate Monitor NA NA NA

d.

Sampler Flow Rate Monitor Used for Particulate D

NA R

and Iodine Sample Collection (see 4.b)

Pri: [2HVL-FIT112-1], or Alt: RAS Pump Flow Instrument

5. Waste Gas Storage Vault Vent (WV-2) a.

Noble Gas Activity Monitor D

M<4)

R(3)(6)

. Pri: [2RMQ-RQ303B]

b.

Particulate and Iodine Samples w

NA NA Pri: Filter Paper & Charcoal Cartridge for [2RMQ-RQ303], or Alt: Continuous collection via RAS Pump

c.

Process Flow Rate Monitor NA NA NA

d.

Sampler Flow Rate Monitor Used for Particulate D

NA R

and Iodine Sample Collection (see 5.b)

Pri: [2RMQ-FIT303-l], or Alt: RAS Pump Flow Instrument CHANNEL OPERATIONAL TEST Q(5)

NA NA Q

Q(5)

NA NA Q

~

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cr--

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cr--

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I.;..

I 0-

Beaver Valley Power Station Procedure Number:

l/2-0DC-3.03

Title:

Unit:

Level Of Use:

1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision:

15 Page Number:

'sf\\ of R1 ATTACHMENT F Page 13 of 13 ODCM CONTROLS: RETS INSTRUMENT FOR GASEOUS RELEASES TABLE 4.3-13 (continued)

TABLE NOTATION (l)

The CHANNEL OPERATIONAL 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.

CZ)

The CHANNEL OPERATIONAL 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.

C3)

The initial CHANNEL CALIBRATION for radioactivity measurement instrumentation shall be performed using one or more of the reference standards certified be National Institute of Science

~{')<)-',

and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. 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.

(S)

The CHANNEL OPERATIONAL TEST shall also demonstrate that Control Room Alarm Annunciation occurs if the instrument indicates measured levels above the alarm/trip 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 Procedure Number:

l/2-0DC-3.03

Title:

Unit:

Level Of Use:

1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision:

Vi Page Number:

.S1 ofR1 ATTACHMENT G Page 1 of 5 ODCM CONTROLS: LIQUID EFFLUENT CONCENTRATION CONTROLS: LIQUID EFFLUENT CONCENTRATIO:t-f 3.11.1.1 In accordance with T.S. 5.5.2.b and T.S. 5.5.2.c, the concentration ofradioactive material released at any time from the site (see l/2-0DC-2.01, Figure 5-1) shall be limited to 10 times the EC's specified in 10 CFR Part 20, Appendix B (20.1001-20.2402), 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)(l).

c.

The provisions ofODCM CONTROL 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.1.1 4.11.1.1.2 4.11.1.1.3 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 *.

The results ofradioactive analysis shall be used in accordance with l/2-0DC-2.01 to assure that the concentration at the point of release are maintained within the limits of ODCM CONTROL 3.11.1.1.

When BV-1 primary to secondary leakage exceeds 0.1 gpm (144 gpd), samples of the Turbine Building Sump shall be obtained every 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 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.

()0 1+/-

I 0-

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<52 of ~n ATTACHMENT G Page 2 of 5 ODCM CONTROLS: LIQUID EFFLUENT CONCENTRATION SURVEILLANCE REQUIREMENTS (continued) 4.11.1.1.4 4.11.1.1.5 When BV-2 primary to secondary leakage exceeds 0.1 gpm (144 gpd), samples of the Turbine Building Sump shall be obtained every 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to ensur.e 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).

Prior to the BV-2 Recirculation Drain Pump(s) (2DAS-P215A/215B) discharging to catch basin 16, a grab sample will be taken. The samples will be analyzed for gross activity at a sensitivity of at least 1 E-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 specifieq 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 SURVEILLANCE REQUIREMENT 4.11.1.1.5, respectively.

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',1 r.f' S;!".l ATTACHMENT G Page 3 of 5 ODCM CONTROLS: LIQUID EFFLUENT CONCENTRATION TABLE 4.11-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LIQUID SAMPLING MINIMUM TYPE OF LOWER LIMIT OF ANALYSIS ACTIVITY DETECTION (LLD)

RELEASE TYPE FREQUENCY FREQUENCY ANALYSIS (uCi/mL) (a)

A. Batch Waste p

p Principal Gamma Release Tanks<d)

Each Batch<h)

Each Batch(h)

Emitters< f) 5E-7 I-131 lE-6 p

M Dissolved and One Batch/M(h)

Entrained Gases lE-5 (Gamma Emitters) p M

H-3 lE-5 Each Batch<h)

Composite<b)

Gross Alpha lE-7 p

Q Sr-89, Sr-90 5E-8 Each Batch<h)

Composite<b)

Fe-55 lE-6 B. Continuous Grab Sample<g) w Principal Gamma Releases<e)(g)

Composite<c)

Emitters< f) 5E-7 I-131 lE-6 Grab Sample<g)

M Dissolved and

. Entrained Gases lE-5 (Gamma Emitters)

Grab Sample<g)

M H-3 lE-5 Composite<c)

Gross Alpha lE-7 Grab Sample<g)

Q*

Sr-89, Sr-90 5E-8 Composite<c)

Fe-55 lE-6

('

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~.1. of R1 ATTACHMENT G Page 4 of 5 ODCM CONTROLS: LIQUID EFFLUENT CONCENT~TION 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(-'"A,/1 T) 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);

Eis the counting efficiency (as counts per transformation);

V is the sample size (ii). 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; 11 T 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 ofE, V, Y and ~T _should be used in the calculations.

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.

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(c)

(d)

(e)

(f)

(g)

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ATTACHMENT G Page 5 of 5 ODCM CONTROLS: LIQUID EFFLUENT CONCENTRATION TABLE 4.11-1 (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.

To be representative of the quantities and concentrations ofradioactive 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.

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.

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 O.1 gpm ( 14 2 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 LLD for the analyses should be reported as "less than" the nuclide's LLD, and should not be reported as being present at the LLD 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 Radioactive Effluent Release Report.

When radioactivity is identified in the secondary system, a RWDA-L should pe prepared on a monthly basis to account for the radioactivity that will eventually be discharged to the Ohio River.

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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during pump operation.

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S6 of ~1 ATTACHMENT H Page 1 of 1 ODCM CONTROLS: LIQUID EFFLUENT DOSE CONTROLS: LIQUID EFFLUENT DOSE 3.11.1.2 In accordance with T.S.5.5.2.d and T.S. 5.5.2.c, the dose or dose commitment to MEMBER(S) OF THE PUBLIC from radioactive materials in liquid effluents released from the reactor unit (see l/2-0DC-2.01 Figure 5-1), which is considered to include the onsite ISFSI, 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, which is considered to include the onsite ISFSI, 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)(l), 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.

SURVEILLANCE REQUIREMENTS 4.11.1.2.1 Dose Calculations. Cumulative dose contributions from liquid effluents, which is considered to include the onsite ISFSI, shall be determined in accordance with l/2-0DC-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).

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57 of R1 ODCM CONTROLS: LIQUID RADWASTE TREATMENT SYSTEM CONTROLS: LIQUID RADWASTE TREATMENT SYSTEM 3.11.1.3 In accordance with T.S.5.5.2.f, 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 l/2-0DC-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)(l) a Special Report which includes the following information:

1.

Identification of the inoperable equipment or subsystems and the reason for in operability.

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 ofODCM 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 l/2-0DC-2.01.

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'°58 of 81 ATTACHMENT J Page 1 of 1 ODCM CONTROLS: LIQUID HOLDUP TANKS CONTROLS: LIQUID HOLDUP TANKS 3.11.1.4 In accordance with T.S.5.5.8, 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.

18 Curies: 1BR-TK-6A. (Unit 1 Primary Water Storage Tank)

b.

18 Curies: 1BR-TK-6B (Unit 1 Primary Water Storage Tank)

c.

7 Curies: 1LW-TK-7A (Unit 1 Steam Generator Drain Tank)

d.

7 Curies: 1LW-TK-7B (Unit 1 Steam Generator Drain Tank)

e.

6 Curies: lQS-TK-1 (Unit 1 Refueling Water Storage Tank-RWST)

f.

62 Curies: 2QSS-TK21 (Unit 2 Refueling Water Storage Tank-RWST)

g.

10 Curies: Unit 1 and 2 miscellaneous temporary outside radioactive liquid storage tanks.

APPLICABILITY: At all times.

ACTION:

a. With the quantity of radioactive material in the tank exceeding the limit, perform calculations to determine compliance to the limits of 10 CFR Part 20, Appendix B, Table 2, Column 2. These calculations shall be performed at the nearest potable water supply, and the nearest surface water supply in the unrestricted area (i.e.; at the entrance to the Midland Water Treatment Facility). IF the limits of 10 CFR Part 20 are determined to be exceeded, THEN immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents to within the limits set forth in 10 CFR Part 20, and

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 limits set forth in 10 CFR Part 20.

c. The provisions ODCM Control 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.4.1 4.11.1.4.2 The quantity ofradioactive'material contained in each of the above listed tanks (except the Unit 1 and 2 R WST'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.

SINCE additions ofradioactive 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 ofradioactive 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 ofreactor cavity water to the respective Unit's RWST.

l

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'i9 of sn ATTACHMENTK Page 1 of 5 ODCM CONTROLS: GASEOUS EFFLUENT DOSE RATE CONTROLS: GASEOUS EFFLUENT DOSE RATE 3.11.2.1 In accordance with T.S.5.5.2.c and T.S. 5.5.2.g, the dose rate in the unrestricted areas (see l/2-0DC-2.02 Figure 5-1) due to radioactive materials released in gaseous effluents, which is considered to include the onsite ISFSI, from the site shall be limited to the following values:

a.

The dose rate limit for noble gases shall be s 500 mrem/yr to the total body and s 3000 mrem/yr to the skin*, and

b.

The dose rate limit, inhalation pathway only, for I-131, tritium and all radionuclides in particulate form (excluding C-14) with half-lives greater than eight days shall bes 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)(l).

c.

The provisions of ODCM CONTROL 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.1.1 4.11.2.1.2 The dose rate due to noble gaseous effluents, which is considered to include the onsite ISFSI, shall be determined to be within the above limits in accorda,nce with 1/2-0DC-2.02.

I 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, which is considered to include the onsite ISFSI, 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.

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60 of 83 ODCM CONTROLS: GASEOUS EFFLUENT DOSE RATE TABLE 4.11-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM GASEOUS RELEASE TYPE A. Waste Gas Storage Tank B. Containment Purge C. Ventilation SystemsCh)

VV-1 (UJ PABNentilation Vent)

CV-1 (Ul Rx Cont/SLCRS Vent)

PV-1/2 (UJ/2 GW/Process Vent)

VV-2 (U2 SLCRS Unfiltered Path)

CV-2 (U2 SLCRS Filtered Path)

DV-2 (U2 Decon Bldg Vent)

WV-2 (U2 Waste Gas Vault Vent)

CB-2 (U2 Cond Pol Bldg Vent)

SAMPLING FREQUENCY p

Each Tank Grab Sample Each Tank*

Grab Sample p

Each PurgeC b)

Grab Sample M(b)(c)(e)

Grab Sample

-MINIMUM ANALYSIS FREQUENCY p

Each Tank Each Tank*

p Each PurgeC b)

M(b)

TYPE OF ACTIVITY ANALYSIS Principal Gamma EmittersCg)

H-3*

Principal Gamma EmittersCg)

H-3 Principal Gamma EmittersCg)

H-3 LOWER LIMIT OF DETECTION (LLD)

(uCi/mL) (a) lE-4 lE-6 lE-4 lE-6 lE-4 lE-6

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.

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61 of R'i ATTACHMENT K Page 3 of 5 ODCM CONTROLS: GASEOUS EFFLUENT DOSE RATE TABLE 4.11-2 (continued)

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM I

GASEOUS SAMPLING MINIMUM RELEASE FREQUENCY ANALYSIS TYPE FREQUENCY D. All Ventilation Continuous<f) w<ct)

Systems Listed Above (in C.)

Charcoal Which Produce Sample Continuous Continuous<f) w<ct)

Release Particulate Sample Continuous<f)

M Composite Particulate Sample Continuous<f)

Q Composite Particulate Sample Continuous<f)

Noble Gas Monitor TYPE OF ACTIVITY ANALYSIS 1-131 1-133 Principal Gamma Emitters<g)

(1-131, Others)

Gross Alpha Sr-89, Sr-90 Noble Gases Gross Beta and Gamma LOWER LIMIT OF DETECTION (LLD)

(uCi/mL) (a) lE-12 lE-10 lE-11 lE-11 lE-11 lE-6

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ATTACHMENTK Page 4 of 5 ODCM CONTROLS: GASEOUS EFFLUENT DOSE RATE TABLE 4.11-2 (continued)

TABLE NOTATION The Lower Limit of Detection (LLD) is defined in Table Notation (a) ofODCM Control 3.11.1.1, Table 4.11-1 for ODCM Surveillance Requirement 4.11.1.1.

Samples (grab particulate, iodine & noble gas) 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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.

Clarification: All samples shall be obtained within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of reaching the intended steady state power level, and analyzed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of reaching the intended steady state power level.

Applicability: Unit 1 Ventilation Systems (VV-1, CV-1 and/or PV-1/2), or Unit 2 Ventilation Systems (VV-2, CV-2 and/or PV-1/2), as appropriate. Specifically, sample the ventilation release path(s) that show a factor of 3 increase on the noble gas effluent monitor. (3.1.16) (3.1.18)

( c)

Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (from the appropriate ventilation release path of the refueling canal area) when the containment refueling canal is flooded. Sampling may be terminated after completion of vessel defueling. Sampling shall resume upon commencement of vessel refueling.

Applicability- (MODE 6): Unit 1 Ventilation System (VV-1 or CV-1), or Unit 2 Ventilation System (VV-2 or CV-2), that is aligned to the Reactor Containment Building atmosphere. In lieu of sampling the ventilation release path, samples may be obtained from the Reactor Containment Building atmosphere. (3.1.11) c3.1.l9)

. (d)

Part 1: Samples (continuous particulate & iodine) shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing, or after removal from sampler.

Applicability for Part 1: Unit 1 and Unit 2 Ventilation Systems (VV-1, CV-1, PV-1/2, VV-2, CV-2, DV-2, WV-2 & CB-2).

Part 2: Samples (continuous particulate & iodine) shall also be changed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing.

When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLDs 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.

Clarification: All samples shall be changed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of reaching the intended steady state power level, and analyzed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of reaching the intended steady state power level.

Applicability for Part 2: Unit 1 Ventilation Systems (VV-1, CV-1 and/or PV-1/2), or Unit 2 Ventilation Systems (VV-2, CV-2 and/or PV-1/2), as appropriate. Specifically, change out the continuous particulate, iodine samples for the ventilation release path(s) that show a factor of 3 increase on the noble gas effluent monitor. (3.1.16) (3.1.18)

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hi nf 81 ATTACHMENTK Page 5 of 5 ODCM CONTROLS: GASEOUS EFFLUENT DOSE RA TE (e)

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.

Applicability: Unit 1 Ventilation System (CV-1), or Unit 2 Ventilation System (CV-2) that is aligned to the Fuel Handling Building atmosphere. In lieu of sampling the ventilation release path, samples may be obtained from the Fuel Handling Building atmosphere. (3.1.11) (3.1.19)

(f)

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.

Clarification: The average ratio of the sample flow rate to the sampled stream flow rate can be determined, but it must not be used in dose and dose rate calculation. Specifically, use of this ratio would provide non-conservative dose calculations, and would compromise licensee response to NRC Unresolved Item 50-334/83-30-05. For information, a comprehensive three-year Radiation Monitor Particle Study was performed in response to the unresolved item's concern that the effluent monitors were not collecting representative samples per ANSI N13.l. The results of that study concluded that a correction factor (minimum CF of 2) must be applied to particulate sample volume calculations and subsequent dose and dose rate calculations.

Specifically, the minimum CF of 2 must be utilized in-lieu of actual ratios of sample flow rate to the sampled stream flow rate. In summary, the minimum CF of2 provides adequate compensation for any negative bias in particulate sample collection. c3.2.B)

Applicability: Unit 1 Ventilation Systems (VV-1, CV-1 & PV-1/2), and Unit 2 Ventilation Systems (VV-2 &

CV-2).

(g)

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 LLD for the analyses should not be reported as being present at the LLD 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.

(h)

Only when this release path is in use.

Applicability: Unit 1 and Unit 2 Ventilation Systems (VV-1, CV-1, PV-1/2, VV-2, CV-2, DV-2, WV-2 &

CB-2).

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64 nfR1 ATTACHMENT L Page 1 of 1 ODCM CONTROLS: DOSE-NOBLE GASES CONTROLS: DOSE-NOBLE GASES 3.11.2.2 In accordance with T.S. 5.5.2.e and T.S. 5.5.2.h,, the air dose from the reactor unit in unrestricted areas (see l/2-0DC-2.02 Figure 5-1), due to noble gases released in gaseous effluents, which is considered to include the onsite ISFSI, shall be limited to the following:

a.

During any calendar quarter, to s 5 mrad for gamma radiation and s 10 mrad for beta radiation.

b.

During any calendar year, to s 10 mrad for gamma radiation ands 20\\mrad for beta radiation.

Applicability:

At all times.

Action:

a.

With the calculated air dose from radioactive noble gases in gaseous effluents, which is considered to include the onsite ISFSI, 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)(l), 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 ofODCM 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 l/2-0DC-2.02 at least once every 31 days.

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hi;; of R1 ATTACHMENT M Page 1 of 1 ODCM CONTROLS: DOSE - RADIOIODINES AND PARTICULATES CONTROLS: DOSE-RADIOIODINES, RADIOACTIVE MATERIAL IN PARTICULATE FORM, AND RADIONUCLIDES OTHER THAN NOBLE,GASES 3.11.2.3 In accordance with T.S. 5.5.2.e and T.S. 5.5.2.i, 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 l/2-0DC-2.02 Figure 5-1), which is considered to include the onsite ISFSI, shall be limited to the following:

a.

During any calendar quarter to ::,; 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, which is considered to include the onsite ISFSI, 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 CPR 50.4(b)(l), 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 ofODCM CONTROL 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.3.1 Dose Calculations. Cumulative dose contributions shall be determined in accordance with l/2-0DC-2.02 at least once every 31 days.

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66 of Sn ATTACHMENTN Page 1 of 1 ODCM CONTROLS: GASEOUS RADWASTE TREATMENT SYSTEM CONTROLS: GASEOUS RADWASTE TREATMENT SYSTEM 3.11.2.4 In accordance with T.S. 5.5.2.f, 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 l/2-0DC-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 tq reduce radioactive materials in gaseous waste prior to their discharge

~ when the projected doses due to gaseous effluent releases from the reactor unit (see l/2-0DC-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)(l), 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 l/2-0DC-2.02.

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67 of ~n ODCM: Controls for RETS and REMP Programs ATTACHMENT 0 Page 1 of 1 ODCM CONTROLS: GAS STORAGE TANKS CONTROLS: GASSTORAGETANKS 3.11.2.5 In accordance with T.S. 5.5.8, the quantity ofradioactivity 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 (lGW-TK-lA, or lGW-TK-lB, or lGW-TK-lC)

b.

~19,000 Curies: Any connected group ofBV-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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents to within the limit, and

b.

Submit a Special Report in accordance with 10 CPR 50.4 (b)(l) 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 REQUIREMENTS 4.11.2.5.1 For BV-1 Waste Gas Decay Tanks: The quantity ofradioactive material contained in each BV-1 Waste Gas Decay Tank shall be determined to be within the above limit at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 ofradioactive material contained in any connected group ofBV-2 Gaseous Waste Storage Tanks shall be determined to be within the above limit at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when radioactive materials are being added to the tanks.

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68 nf 83 ATTACHMENT P Page 1 of 1 ODCM CONTROLS: TOTAL DOSE CONTROLS: TOTAL DOSE 3.11.4.1 In accordance with T.S. 5.5.2.j, the annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases ofradioactivity and to radiation from uranium fuel cycle sources, which is considered to include the onsite ISFSI, 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, which is considered to include the onsite ISFSI, exceeding twice the limits of ODCM CONTROL

3. l l.1.2a, 3. l l. l.2b, 3. l l.2.2a, 3. l l.2.2b, 3. l l.2.3a, or 3. l 1.2.3b, calculations shall be made including direct radiation contributions from the units (including outside storage tanks, the onsite ISFSI, etc.) to determine whether the above limits ofODCM CONTROL 3.11.4.1 have been exceeded. If such is the case, prepare and submit to the Commission within 3 0 days, pursuant to 10 CFR 20.2203(a)(2)(v) and 10 CFR 50.4(b)(l), a Special Report that defines the coµ-ective 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 ap. analysis that estimates the radiation

. exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources and the onsite ISFSI, 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 staffaction on the request is complete.

b.

The provisions ofODCMCONTROL 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.4.1.1 4.11.4.1.2 Cumulative dose contributions from liquid and gaseous effluents, which is considered to include the onsite ISFSI, shall be determined in accordance with ODCM SURVEILLANCE REQUIREMENTS 4.11.1.2.1, 4.11.2.2.1, and 4.11.2.3.1.

Cumulative dose contributions from direct radiation from the units (including outside storage tanks, the onsite ISFSI, etc.) shall be determined in accordance with l/2-0DC-2.04. This requirement is applicable only under conditions set forth in Action a. of ODCM CONTROL 3.11.4.1.

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69 of 81 ATTACHMENT Q Page 1 of 9 ODCM CONTROLS: REMP-PROGRAM REQUIREMENTS CONTROLS: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) representative measurements ofradioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The program shall (1) be contained in the ODCM (2) conform to the guidance of the Appendix I to 10 CFR Part 50, and (3) include the following:

1.

Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM,

2.

A Land Use Census to ensure that changes in the use of areas at and beyond the site boundary are identified and that modifications to the monitoring program are made if required by the results of the census, and

3.

Participation in an Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in the environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

3.12.1 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 ofODCM 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)(l) 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:

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70 nf 81 ATTACHMENT Q Page 2 of9 ODCM CONTROLS: REMP-PROGRAM REQUIREMENTS Concentration (l)

Concentration (2)

Limit Level (1)

+ Limit Level (2)

+... ~ 1.0

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 REQUIREMENTS 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.

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ODCM CONTROLS: REMP-PROGRAM REQUIREMENTS TABLE 3.12-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY AND/OR SAMPLE NUMBEROF -

SAMPLES AND LOCATIONS SAMPLING AND - *-

COLLECTION FREQUENCY

-TYPE AND-FREQUENGY OF -

ANALYSIS (a)

1. AIRBORNE a.--Radioiodine and -

Particulates

$-locations---*---

. -* -- ---. Gontinuous operation-of-EaGh-radioiodine canister.

2. DIRECT RADIATION

1. One sample from a control location 10-20 miles distant and in the least prevalent wind direction

2. One sample from vicinity of community having the highest calculated annual average ground level DIQ.

sampler with sample collection at least weekly.

40 locations Continuous measurement with

~ 2 TLDs or a collection at least pressurized ion chamber quarterly.

at each location.

(a) Analysis frequency same as sampling frequen~y unless otherwise specified.

Analyze for I-131;

. Particulate sampler.

Analyze for gross beta weekly (b);

Perform gamma isotopic analysis on composite (by location) sample at least quarterly.

Gamma dose, quarterly.

(bl Particulate samples ar_e not counted for ~ 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 l/2-0DC-2.03.

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72onn ODCM CONTROLS: REMP-PROGRAM REQUIREMENTS TABLE 3.12-1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY AND/OR SAMPLE

3. WATERBORNE

a. Surface

b. Drinking NUMBEROF SAMPLES AND LOCATIONS**

2 locations

1. One sample upstream.

2. One sample downstream.

2 locations SAMPLING AND COLLECTION FREQUENCY Composite* sample collected over a period not to exceed 1 month.

Composite* sample collected over a period not to exceed 2 weeks.

TYPEANDFREQUENCYOF ANALYSIS Cal Gamma isotopic analysis of composite sample by location monthly; Tritium analysis of composite sample at least quarterly.

I-131 analysis of each composite sample; 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 Shoreline I location Semi-annually.

Cal Analysis frequency same as sampling frequency unless otherwise specified.

Gamma isotopic analysis semi-annually.

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 l/2-0DC-2.03.

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71 of R1 ODCM CONTROLS: REMP-PROGRAM REQUIREMENTS TABLE 3.12-1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY AND/OR SAMPLE

4. INGESTION

a. Milk NUMBER OF SAMPLES AND LOCATIONS**

4 locations (b) (c)

1. Three samples selected on basis of highest potential thyroid dose using milch census data.

2. One local large dairy.

b. Fish 2 locations

c. Food Products 4 locations (c)

(Leafy Vegetables)

1. Three locations within 5 miles.

2. One control location.

3. Two locations based on highest predicted annual avg.ground D/Q when milk locations are unavailable. (c)

SAMPLING AND COLLECTION FREQUENCY Atleast biweeklywhen animals are on pasture; at least monthly at other times.

Semi-annual. One sample of available species.

Annually at time of harvest. (c)

(a) Analysis frequency same as sampling frequency unless otherwise specified.

TYPEANDFREQUENCYOF ANALYSIS (a)

Gamma isotopic and 1-131 analysis of each sample.

Gamma isotopic analysis on edible portions.

Gamma isotopic analysis and 1-131 analysis on edible portion.

(b) Other dairies may be included as control station or for historical continuity. These would not be modified on basis of milch animal census.

(c) When ODCM milk sample requirements are met, one type of broad leaf vegetation is to be sampled from the three (3) indicator locations and one (1) control location. When there are not enough milk sample locations available to meet the ODCM requirements, three (3) different types of broad leaf vegetation are to be sampled at each of two (2) indicator locations based on the highest predicted annual average ground D/Q (as determined from the previous year's Land Use Census), in addition to those samples described above. Three (3) different types of broad leaf vegetation shall also be sampled at one (1) control location when in this condition. The primary sources of broad leaf vegetation are cabbage or lettuce. However, other acceptable substitutes are vegetables having leaves with large surface area, to be combined with the edible portion of the plant for analysis.

- Sample locations are given on figures and tables in l/2-0DC-2.03.

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74 nHn ODCM: Controls for RETS and REMP Programs ATTACHMENT Q Page 6 of 9 ODCM CONTROLS: REMP-PROGRAM REQUIREMENTS TABLE 3.12-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES REPORTING LEVELS ANALYSIS WATER AIRBORNE PARTICULATE OR GASES (pCi/m3)

FISH (pCi/kg, WET)

MILK (pCi/L)

BROAD LEAF VEGETABLES (pCi/kg, WET)

H-3 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr/Nb-95 1-131 Cs-134 Cs-137 Ba/La-140 (pCi/L) 20,000 (a) 1,000 400 1,000 300 300 400 2 (b) 30 50 200 0.9 10 20 30,000 10,000 30,000 10,000 20,000 1,000 2,000 3

60 70 300 100 1,000 2,000 (a)

For drinking water samples. This is a 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/L may be used.

(b) If no drinking water pathway exists, a value of 20 pCi/L may be used.

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15 75 of 83 ATTACHMENTQ Page 7 of9 ODCM CONTROLS: REMP-PROGRAM REQUIREMENTS TABLE 4.12-1 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)Ca)(e)

WATER AIRBORNE FISH MILK FOOD SEDIMENT ANALYSIS (pCi/L)

PARTICULATE (pCi/kg, WET)

(pCi/L)

PRODUCTS (pCi/kg, DRY)

OR GAS (pCi/m3)

(pCi/kg, WET)

Gross Beta 4

0.01 H-3 2,000 (d)

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)

I-131 1 (b) 0.07 1

60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-140 60 (c) 60 La-140 15 (c) 15

-\\

1 (j

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76 of R1 ATTACHMENT Q Page 8 of,9 ODCM CONTROL~: REMP-PROGRAM REQUIREMENTS TABLE 4.12-1 (continued)

TABLE NOTATION Ca) The LLD is the smallest concentration ofradioactive 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(-"A/1 T) 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);

Eis 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; 11 T 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. 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., potassium-40 in milk samples). Typical values ofE, V, Y and fiT should be used in the calculations.

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77 '"'fR1 (b)

(c)

(d)

(e)

ATTACHMENT Q Page 9 of9 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.

If no drinking water pathway exists, a value of 15 pCi/L may be used.

If parent and daughter are totaled, the most restrictive LLD should be applied.

If no drinking water pathway exists, a value of 3000 pCi/L may be used.

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.

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7R of Sn ATTACHMENTR Page 1 of 1 ODCM CONTROLS: REMP - LAND USE CENSUS CONTROLS: RADIOLOGICAL ENVIRONMENTAL MONITORING-LAND USE CENSUS 3.12.2 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 REQUIREMENT 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)(l), a Special Report, which identifies the new location(s).

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)(l), 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.

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79 nf~n ATTACHMENTS Page 1 of 1 ODCM CONTROLS: REMP - INTERLABORATORY COMPARISON PROGRAM CONTROLS: RADIOLOGICAL ENVIRONMENTAL MONITORING - INTERLABORATORY COMPARISON PROGRAM 3.12.3 Applicability:

At all times.

Action: '

Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program.

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 ofODCM 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.

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srn of sn ATTACHMENT T Page 1 of2 ODCM CONTROLS: ANNUAL REMP REPORT CONTROLS: ANNUALREMPREPORT I

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT <3) 6.9.2 In accordance with T.S. 5.6.1, the 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 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 problen:i and a planned course of action to alleviate the problem.

\\

Summarized and tabulated results in the format of ODCM Control 6.9.2, 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.

C3 )

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.

TABl.E E:6.9-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

NllDle Of Facility -----------

1 DocketNo. ------

Location Of Facility ----------

Reporting Period ___

MEDIUM~F TYPE AND

!PATHWAYS TOTAL NUMBER (UNITOF OF ANALYSES MEASUREMENT)

PERFORMED LOWER LIMITS OF DETECTION" (LLD)

(County, State)

All.

INDICATOR LOCATIONS MEAN~t RANGE LOCATIONS WITH IIlGHF.81'.

ANNUALMEAN NAME DISTANCE AND DIRECl'ION MEAN(Fl RANGEb I

CONTROL LOCA"IjIONS MEAN(F)b~GEb l I

Nominal Lower limits of Detection (LLD) as defined in Table Notation* ofTable 4.12-1 of ODCM CONTROL 3.11.1.1.

b Mean and range based upon detectable measureinent only. Fraction of detectable measurement at specified locations is indicated in parenthesis (f).

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Beaver Valley Power Station Procedure Number:

l/2-0DC-3.03

Title:

Unit:

Level Of Use:

1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision:

Page Number:

R2 of ~n ATTACHMENTU Page 1 of2 ODCM CONTROLS: ANNUAL RETS REPORTS CONTROLS: RETSREPORT RADIOACTIVE EFFLUENT RELEASE REPORT <4 )

6.9.3 In accordance with T.S. 5.6.2, the Radioactive Effluent Release Report (RERR) covering the operation of the 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 gase9us 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, which is considered to include the onsite ISFSI, 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 REQUIREMENT 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 Procedure Number:

l/2-0DC-3.03

Title:

Unit:

Level Of Use:

1/2 General Skill Reference ODCM: Controls for RETS and REMP Programs Revision:

Vi Page Number:

~n of 83 ATTACHMENTU Page 2 of2 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)

- 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, which is considered to include the onsite ISFSI, released :from the unit or station during the previous calendar year.

An assessment of the radiation doses from radioactive effluents, which is considered to include the onsite ISFSI, to MEMBER(S) OF THE PUBLIC due to their activities inside the site boundary see l/2-0DC-2.01 Figure 5.1 and l/2-0DC-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 l/2-0DC-2.04.

An assessment ofradiationdoses_to theJikely most exposed real individual from

reactor releases, which is considered to include the onsite ISFSI, 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 SKYSHINE 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.

v t e Letter Sequence Request
CAC:MF3301, (Approved, Closed)
Initiation Request, Request, Request, Request Acceptance... Supplement, Supplement Administration Questions 3 March 2016 25 April 2016 9 October 2015 24 November 2015 7 April 2016 30 March 2016 2 December 2016 8 August 2017 Answers 27 May 2015 6 November 2015 21 December 2015 12 May 2016 30 January 2017 Results Approval, Approval, Approval Other: ML16158A002, ML18058A942, ML18058A953, ML18058A985, ML18058B072, ML18059A798, ML18099A232
MONTHYEAR2016-07-01 [Table View]

L-19-113, Rev. 9 to ODCM: Radiological Environmental Monitoring Program

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