L-05-072, Attachment 2, Beaver Valley Power Station - Units 1 & 2, Annual Radioactive Effluent Release Report 2004, Offsite Dose Calculation Manual Changes: Difference between revisions

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{{#Wiki_filter:Beaver Valley Power Station - Units 1 & 2 Annual Radioactive Effluent Release Report Calendar Year - 2004 Unit 1 and 2 Offsite Dose Calculation Manual Changes Attcihment2 Attached Is a complete copy of the ODCM that Includes:
{{#Wiki_filter:}}
Change (21) of the ODCM (Effective: November, 2004)
W Mi:AttCahlennt2 Cl rifca tion:;F ::;; - :-
A complete copy of the ODCM has been provided to the following offices:
United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 United States Nuclear Regulatory Commission Regional Administrator 475 Allendale Road King of Prussia, PA 19406 For a complete copy of the ODCM, contact Mr. Anthony T Lonnett at 724-682-7523.
 
RTL #A9.621B Beaver Valley Power Station Unit 1/2 1/2-ODC-1.01 ODCM: Index, Matrix and History of ODCM Changes Document Owner Manager, Nuclear Environmental and Chemistry Revision Number                                    4 Level Of Use              . Sd            General Skill Reference Y.
Safety Related Procedure                  ..      Yes I
 
Beaver            Valley Power Station
_________________________________________1/2-ODC-1.01                                  PodurNumbero
 
==Title:==
Unit:            Level Of Use:
1/2          General Skill Reference ODCM: Index, Matrix and History of ODCM Changes                                                                                    PageNumber.
4                      '2 of 72            --
TABLE OF CONTENTS 1.0' PURPOSE ...                                                                                                                                                  '4 3.0 'REFERENCES AND COMMITMENTS.................                                                                                                .................. 44................
3.1 References Used in This Procedure ...........                                                        ................................................ 44.................
3.2 'Summary of References Used Thiouighout Other Procedures of the ODCM                                                                                    5 3.3    Commitments ....................                                                    ..                                                              10 4.0 RECORDS AND FORMS                                                                    ....                                                                    11 4.1 Records                                                    ......                                                                                        ;11
                ~4.2 ...                        Forms                                                                                                                '
                                                                                                                                                                        ;;;;11 50PRECAUTIONS AND LIMITATIONS ; ................                                                                                                                                ;
        '.0ACCEPTANCE CRITERIA        ...............................                                                                                            1:;2 7.0 PREREQUISITESS                                                    ...............................                                                            I1
.8.0 PROCEREURE ............                                                                                                                                      12 8.1 Description of ODCM Structure .......................                                                                                                12 8.1.1            1/2-ODC-1.01, ODCM: Index, Matrix and History of ODCM changes.                                                                    12' 8.1.2            1/2-ODC-2.01, ODCM: Liquid Effluents .............................                                                                13 8.1.3            1/2-ODC-2.02, ODCM: Gaseous Effluents .14 8.1.4            1/2-ODC-2.03, ODCM: Radiological Environmental Monitoring Program .                                                                15 8.1.5            1/2-ODC-2.04, ODCM: Information Related to 40 CFR 190 ..                                                                          15 8.1.6            1/2-ODC-3.01, ODCM: Dispersion Calculational Procedure and Source Term' Inputs .15 8.1.7            1/2-ODC-3.02, ODCM: Bases for ODCM Controls .15
              -8.1.8            1/2-ODC-3.03, ODCM: Controls for RETS and REMP Programs .16 8.2 History Of ODCM Changes ....................                                                                                                          17 8.2.1            Change (1) of BV-1 ODCM (Issue 1, Effective January, 1984).17 8.2.2            Change (2) of BV-1 ODCM (Issue i, Revision 1, Effective October, 1984) .                                                          17 8.2.3            Change (3) of BV-1 ODCM (Issue 1, Revision 2, Effective July, 1986) .                                                              18 8.2.4            Change (4) of BV-1 ODCM (Issue 2, Effective July, 1987), and BV-2 ODCM (Issue 1, Revision 1, Effective July, 1987) .18 8.2.5            Change (5) of BV-1 ODCM (Issue 2, Revision I Effective December, 1987),
and BV-2 ODCM (Issue 1, Revision 2, Effective December, 1987) .19 8.2.6            Change (6) of BV-1 ODCM (Issue 2, Revision 2 Effective June, 1989), and BV-2 ODCM (Issue 1, Revision 3, .Effective June, 1989)                                                        .19 8.2.7            Change (7) of BV-1 and 2 ODCM (Issue 3, Effective August, 1995) ................. 21 8.2.8            Change (8) of BV-1 and 2 ODCM (Issue 3, Revision 1, Effective October, 1995)2 8.2.9            Change (9) of BV-1 and 2 ODCM (Issue 3, Revision 2, Effective May 1997)... 29 8.2.10          Change (10) of BV-1 and 2 ODCM (Issue 3, Revision 3, Effective June 1997). 30 8.2.11          Change (11) of BV-1 and 2 ODCM (Issue 3, Revision 4, Effective March 1998)30 8.2.12          Change (12).ofBV-1 and 2 ODCM (Issue 3, Revision 5, Effective November 1998) .32 8.2.13          Change (13) of BV-i and 2 ODCM (Issue 3, Revision 6, Effective May 1999).33 8.2.14          Change (14) of BV-1 and 2 ODCM (Revision 14, Effective March 2000) .                                                            -34 8.2.15          Change (15) of BV-1 and 2 ODCM (Revision 15, Effective August 2000) .                                                            35
 
Beaver Valley Power Station                                  P-        cdurc      Nu. ,              . .
Titlde:              .--                                                Unit:
* Lvel Of Use: - - - . -
1./2            General Skill Reference ODCM: Index, Matrix and History of ODCM Changes                          Revision:          PagcNumber 4            _of_72 TABLE OF CONTENTS 8.2.16    Change (16) of BV-I and 2 ODCM (Effective April 2002) ................................ 37 8.2.17    Change (17) of BV-1 and 2 OCDM (Effective August 2002) ............................ 39 ATTACHMENT A LIST OF ODCM TABLES              ..................            ;                                      47 ATTACHMENT B LIST OF ODCM FIGURES................5........................................3............ ............ 53 ATTACHMENT C ODCM CONTROLS PROCEDURE MATRIX .................................................... 54
                                                            -I I
 
                                                            =. .            .Procdumc      Nunbera
.                  Beaver Valley Power Station                                    Pe      - 1/2-ODCl0          -
 
==Title:==
Unit:        Level Of Use:
1/2    I General  Skill Reference ODCM: Index, Matrix and History of ODCM Changes                                    Reisson:    P    Numbe7.
1.0        PURPOSE                          .    '
1.1        This procedure provides an index for the entire"Offsite Dose Calculation Manual (ODCM).
1.2        This procedure also provides an historical description of all changes to the ODCM.
1.3        This procedure also contains a matrix of plant'procedure references for Radiological Effluent Technical Specifications (RETS), Radiological Environmental Monitoring Program (REMP) surveillances that were transferred from the Technical Specification Procedure Matrix to the ODCM via Change (8) and Change (16).
1.3.1      Prior to issuance of this procedure, these items were located in the Index and Appendix F of the old ODCM.
1.3.2      The numbering of each specific ODCM Controls, ODCM Surveillance Requiirements and ODCM Controls Tables contained in this procedure does not appear to be sequential.
This is intentional, as all ODCM Controls, ODCM Surveillance Requirements and ODCM Controls Tables numbers remained the same when they were'transferred from the Technical Specifications Procedure Matrix. This was done in an effort to minimize
    .' >  '      the amount of plant procedure changes and to eliminate any confusion associated with
                  'numberinig changes.
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 Used in This Procedure 3.1.1      NUREG-0472, Draft 7 for Rev. 3, Standard Radiological Effluent Technical Specifications For PWRs September, 1982.
3.1.2      NUREG-0133, Preparation Of Radiological Effluent Technical Specifications For Nuclear Power Plants, October, 1978.
3.1.3      Generic Letter 89-01, Implementation Of Programmatic Controls For Radiological Effluent Technical Specifications In The Administrative Controls Section Of The Technical Specifications And The Relocation Of Procedural Details Of RETS To The ODCM.Or To The PCP, January 31, 1989.
3.1.4      NUREG-1301, OffsiteDose Calculation Manual Guidance: Standard Radiological Effluent Controls For Pressurized Water Reactors, .Generic Letter 89-01, Supplement No.'1,April, 1991.
3.1.5      1/2-ODC-3.03, ODCM: Controls for RETS and REMP Programs
 
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Beaver' Va : ey'Po Wdr St-fN                  '          -I            1/2-ODC-f'.01
 
==Title:==
Leve ofrUni.
Use:. Ren
                                      '                                .I/2                  General Skill Reference.
ODCM: Index, Matrix and History of ODCM Changes                                Revision:      ageNuxber 3.1.6      1/2-ADM-1640, Control of the Offsite Dose Calculation Manual 3.1.7      1/2-ADM-0100, Procedure Writers Guide 3.1.8      NOP-SS-3001, Procedure Review and Approval 3.2        Summary of References Used Throughout Other Procedures of the ODCM 3.2.1      BVPS-1 and 2 UFSAR:
3.2.1.1    BVPS-1 UFSAR Section 11.2.3; Gaseous Waste Disposal System
        ' 3.2.1.2    BVPS-1 UFSAR Section 11.2.4; Liquid Waste Disposal System 3.2.1.3    BVPS-2 UFSAR Section 11.2; Liquid Waste Management Systems 3.2.1.4    BVPS-2 UFSAR Section 11.3; Gaseous Waste Management Systems 3.2.2      Condition Reports:
3.2.2.1    CR 971578, MEMBERS OF THE PUBLIC Discrepancies. CA-01, Revise Section                          -
4 of the ODCM to clarify how doses due to effluents for members of the public (conducting activities inside the site boundary) are derived and reported.
3.2.2.2    CR 980129, ODCM Procedure Matrix Discrepancies. CA-01, Revise Appendix F of the ODCM to correct discrepancies with 1/2-OM L5 Surveillance Logs.
3.2.2.3    CR 980353, EPMP 2.01 Discrepancies for Environmental Samnpling Locations.
CA-01, Revise Section 3 of the ODCM to correct REMP sample site distances and sectors.
3.2.2.4    CR 981488, Chemistry Related ODCM Procedures and ODCM Appendix F References. CA-01, Revise ODCM Appendix F to add Chemistry procedure' references.
3.2.2.5    CR 981489, ODCM Table 4.11-2 Row A (Waste Gas Storage Tank Discharge Tritium). CA-0l, Revise Appendix C ofthe ODCM (Table 4.1'1-2) to add clarification as to where and when tritium samples are to be obtained for GWST discharges.
3.2.2.6    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.
3.2.2.7    CR 982097, Liquid Discharge Post Release Review Methodology. CA-01, Revise                      K Section 1 of the ODCM to add clarification for calculation of radionuclide concentration when the Post Dose Correction Factor is >1.
 
Procedure Nunibcr.
Beaver Valley Power Station                              -              l/-OC-.0
 
==Title:==
Unit:          Level Of Use:
1/2        General Skill Reference ODCM: Index, Matrix and History of ODCM Changes                            Revision:      Page Number        .
3.2.2.8      CR 990025, Unnecessary Radiation Monitor Setpoint Change'After Waste Discharges. No ODCM changes are required for this CR.
3.2.2.9'    CR 992652,' Discrepancies' C6ncerning ODCM Surviellances of Unit 1 Gaseous Effluent Instrumentation. CA-02, Revise Appendix F of the ODCM to make proper reference to the HP Shift logs.'
3.2.2.10.'  CR 993021, Apparent Failure to Test RM-DA-100 Trip Function as Required by ODCM. No ODCM changesrare required for this CR.
3.2.2.11    CR 001682, ODCM Action 28 Guidance. CA-02, Revise Appendix C of the
                    ' ' 'ODCM (Table 3.3-13, Actiin'28) to differentiate actions associated with
          '        - Ioperable Process Flow Rate Monitors vs. Sample'Flow Rate Monitors.
3.2.2.12    CR02-05533, Procedure 1/2-ODC-3.03, ATTACHMENT E Missing Information.
CA-01, Revise ODCM procedure 1/2-ODC-3.03 (Table 3.3-12) to include minimum channels operable and associated actions when Flow Rate Measurement Device [FR-lLW-103] ii'in6perable.
3.2.2.13    CR02-05711, TS and ODCM changes not reflected in IOM-54.3.L5 Surveillance a2                    Log. CA-01, Revise 1/2-ODC-3.03 to add a requirement for applicable station groups notification of pending ODCM changes.
3.2.2.14'    CR02-06174, Tracking of Activities for Unit 1 RCS Zinc Addition Implementation. CA-13, Revise ODCM procedure 1/2-ODC-1.01 to include a discussion as to why Zn-65 is being added to the ODCM. CA-14, Revise ODCM procedure 1/2-ODC-2.01 (Tables'1.1l a and lb) to include the addition of Zn-65 to ODCM liquid source term.'
3.2.2.15    CR 03-02466, RFA-Radiation Protection Effluent Control Provide Recommendation on Processing when Performing Weekly Sample of [lLW-TK-7A/37B]. CA-02, Revise ODCM Procedure 1/2-ODC-2.01, (Attachment D) to show the liquid waste flow path cross-connect between Unit I and Unit 2.
3.2.2.16    CR03-04830, Containment Vacuum Pump Replacement Increases ODCM Source Term. CA-03, Revise Unit lContainment Vacuum Pump' Source-Term in ODCM' procedure 1/2-ODC-2.02, Attachment A, Table 2.1-la.
3.2.2.17    CR03-06123, Enhance Table 3.3-6 of 1/2-ODC-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 I Mid or High N                    Range Noble Gas Effluent Monitors are Inoperable.
3.2.2.18    CR03-06281, Gaseous Tritium Sampling Required by ODCM (1/2-ODC-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.
 
'ride:Unit:-
Beaver Valley Power Station                          -      P: - -u1/2uODC -
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0
                                                                                                      ^    -
1 1/2    General Skdll Reference -.
ODCM: Index, Matrix and History of ODCM Changes                            Revision:  Page Number 3.2.2.19    CR03-07487, Results of NQA 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-ODC3.03 Control 3.11.1.4 to update the activity limits for the outside storage tanks.
3.2.2.20    CR03-07668, Benchmark Effluent & Environmental Programs VS Papers Presented at 13P 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.                                                                    gi) 3.2.2.21  : CR03-09288, LAR 1A-321 & 2A-193, Increased Flexibility, in Mode Restraints.
CA-19, Review LAR IA-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.
3.2.2.22    CR03-09959, RFA-Rad Protection Provide Clarification to ODCM 1/Day Air Tritium Sample. CA-01, Revise ODCM procedure 1/2-ODC-3.03 Attachment K (Table 4.11-2 note c & note e) to allow sampling of the appropriate building atmosphere.
3.2.2.23    CR03-11726, Typographical Error Found in ODCM 3.11.2.5. CA-01, Revise ODCM procedure 1/2-ODC-3.03, Attachment 0, Control 3.11.2.5 to correct a typographical error. Specifically, the final word in Action (a) needs changed from "nad" to "and".
3.2.2.24    CR04-01643, Procedure Correction - Typographical Error in the ODCM. CA-01, Revise ODCM procedure 1/2-ODC-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 for measurement of sample flow (from the Alternate Sampling Device) needs changed from [PI-lGW-13] to [PI-1GW-135].
3.2.2.25    CRO4-02275, Discrepancies in Table 3.3-13 of the ODCM. CA-01, Revise ODCM procedure 1/2-ODC-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"'.
3.2.3    Calculation Packages:
3.2.3.1      ERS-ATL-83-027; Liquid Waste Dose Factor Calculation for HPM-RP 6.5, Issue 3 and Later 3.2.3.2      ERS-SFL-85-03 1; Gaseous Effluent Monitor Efficiency Data 3.2.3.3      ERS-ATL-86-008; ODCM Alarm Setpoint Revisions for Gaseous Monitors
 
Procedure Number.
            - Beaver Valley Power.Station                                              1/2-ODC-1.o1 Tite:                                                                      Unit:        Level Of Use:
1/2        General Skill Reference ODCM: Index, Matrix and History of ODCM Changes                            Revision:    PageNumba:
__  __  __ _ _ __ __ __ __ _  __  __  _  __  _  _      4 .              8of 72 3.2.3.4      ERS-HIIHM-87-014; Unit 1/2 ODCM Gaseous Effluent Monitor Alarm Setpoint Determinations 3.2.3.5      ERS-ATL-87-026; BVPS-1 and BVPS-2 ODCM T Factor Justification 3.2.3.6      ERS-ATL-89-014; Verification/Validation of ODCM R Values 3.2.3.7      ERS-ATL-90-021; Justification for Removal of Technical Specification Process
        ' '.      -    Flowrate Measurement Requirements for 2RMQ-RQ301, 2RMQ-RQ303 and 2HVL-RQ112                -
3.2.3.8      ERS-ATL-95-006; Re-evaluation of TS/ODCM SR's 4.11.1.1.3, .4.11.1.1.4 and
        - :*    !      Notes e'and g of TS/ODCM Table 4:11-1 3.2;3.9      ERS-ATL-95-007; Verification of Outside Storage Tank Activity Limit of TS 3.11.1.4 3.2.3.10    'Stone and Webster UR(B)-160; BVPS Liquid Radwaste Releases and Concentrations - Expected and Design Cases (Per Unit and Site) 3.2.4      Internal Letters:
3.2.4.1      DLC Response to NRC Unresolved Item 50-334/83-30-05, Radiation Monitor Study- Particle Distribution Evaluation, November 26, 1986.
3.2.4.2      NDISHP:776, BVPS-1 ODCM Table 2.2-2, Appendix B, February 12, 1988' 3.2.4.3      ND3NSM:3431; Technical Specification Verification Effort, August 11, 1988 3.2.4.4      NDLNSM:3522; Technical Specification Verification Effort Checklist, September 14, 1988 3.2.4.5      NDlNSM:3652; Technical Specification Verification Effort, November 21, 1988 3.2.4.6      NPD3SHP:2466; Self Assessment of the Liquid and Gaseous Effluent Processes at BVPS - Final Report, July-16, 1997 3.2;4.7      NPD3SHP:2257; ODCM Liquid Waste Recirculation Rates, February 11, 11998 3.2.4.8      NPD3SHP:2643; Action 28 of ODCM Appendix C Table 3.3-13, January 14, 1999 3.2.4.9      ND3MNO:4309; Response to Request for Technical Specification Interpretation, April 20, 1999.
3.2.5      Contractor Technical Evaluation Reports:
 
I
                                                                  - o        Procedure Numiber Beaver Valley Power StationDC-.I
'Title:    -'-                                                              Unit:          Level Ofu    *se- -
1/2        General SAMll Reference ODCM: Index, Matrix and History of ODCM Changes                              R7sion:*      of 77 - ' )
2  I                                    49                of 3.2.5.1    EGG-PHY-8194; Technical Evaluation Report for the Evaluation of ODCM Updated through Issue 2, Revision 1, Beaver Valley Power Station, Unit 1, September 1988 3.2.5.2    EGG-PHY-8217; Technical Evaluation Report for the Evaluation of ODCM updated through Issue 1, Revision 2, Beaver Valley Power Station, Unit 2, September 1988 3.2.5.3    NUS-2173; Development of Terrain Adjustment Factors For Use at the Beaver Valley Power Station for the Straight-Line Atmospheric Dispersion Model, June 1978 3.2.5.4'  UCRL-50564; Concentration Factors of Chemical Elements in Edible Aquatic Organisms, Revision 1, 1972 3.2.6    NRC Letters:
3.2.6.1    Unit I Technical Specification Amendment 66, March 28, 1983 3.2.6.2    Beaver Valley Unit 2 - Offsite Dose Calculation Manual, ODCM (TAC 63996),
July 14, 1987                                                                                  '
3.2.6.3    Beaver Yalley Units I and 2 - Acceptance of the Offsite Dose Calculation Manuals (TAC 93996 and 67421), March 2, 1989 3.2.6A    Unit 1/2 Technical Specification 6.8.6, including Amendments 1A-188/2A-70 (LAR IA-175/2A-37), Implemented August 7, 1995 3.2.6.5    Unit 1/2 Technical Specification 6.8.6, including Amendments 1A-194/2A-77 (LAR's IA-231/2A-101), Implemented December 1, 1995 3.2.6.6    Unit 1/2 Technical Specification Figure 5.1-2, including Amendments IA-202/2A-83 (LAR IA-234/2A-107, Implemented June 9, 1997 3.2.6.7    Unit 1/2 Techniical Specifications 6.9.1.10 and 6.9.2, including Amendments IA-220/2A-97 (LAR IA-246/2A-1 16), Implemented May 20, 1999 3.2.6.8    Unit 1/2 Technical Specification 3.3.3.1, including Amendments IA-246/2A-124 (LAR IA-287/2A-159), Implemented April 11, 2002 3.2.6.9  . Unit 1/2 Technical Specifications 3.11.1.4, 3.11.2.5, 6.8.6, and 6.9.2 including Amendments 1A-250/2A-130 (LAR      PA-291/2A-163), Implemented August 7, 2002            .                        '        '
 
====3.2.7 NUREG's====
 
                                                          ..  . . ...  . ProedureNumber:
Beaver Valley Power              Station                  -,'/N-ODC-              .
1 01
 
==Title:==
Unit:      Level Of Use:
1/2      General Skill Reference ODCM: -Index, Matrix and History of ODCM Changes                              Revision:  PageNumber
                                                            .4                                  .1()ofZ27 3.2.7.1      NUREG-0O 17, Calculation' bf Releases of Radioactive Materials in Gaseous and Liquid Effluents from Pressurized Water Reactors, (PWR- Gale Code), Revision 1,
                        -April 1985 3.2.7.2      NUREG 0133; Pieparation'of Radiological Effluent Technicai Specification for Nuclear Power Plants, October 1978 3.2.7.3      NUREG-0172; Age-Specific Radiation Dose Commitment Factors for a One-Year Chronic Intake, November 1977
          *3.2.7.4      NUREG-0324, XOQDOQ, Program for the Meteorological Evaluation of Routine
                      ; Releases at Nuclear Power Stations, September 1977 3.2.7.5      NUREG-0472; Radiological Effluent Technical Specifications for PWRt s.
3.2.7.6      NUREG-0800, Standard Review Plan, Postulated Radioactive Releases Due to Liquid-Containing TankFailures, July 1981 3.2.7.7      NUREG-1301;OffsiteDoseCalculationManuaiGuidance: StandardRadiological Effluent Controls for Pressurized Water Reactors (Generic Letter 89-01,'
Supplement No. 1), April 1991 3.2.7.8      NUREG-1431; Standard Technical Specification - Westinghouse Plants Specifications 3.2.7.9      NUREG/CR-2919; Meteorological Evaluation of Routine Effluent Releases At Nuclear Power Stations, September 1982 3.2.8      Regulatorv Guides:
3.2.8.1      RG-1.23; Meteorological Measurement Program For Nuclear Power Plants 3.2.8.2      RG-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, April 1977
          *3.2.8.3'    RG-1.11l; Methods For Estimating Atmospheric Transport And Dispersion of Gaseous Effluents In Routine Releases From Light-Water-Cooled Reactors, Revision 1,July 1977
      '    3.2.8.4      RG-1.113; Estimating Aquatic Dispersion of Effluents Fiom Accidental and Routine Reactor Releases For The Purpose of Irnplementing Appendix I, April 1977 3.3          Commitments 3.3.1      10 CFR Part 20, Standards for Protection Against Radiation
 
Beaver Valley PoweriStation'                                P1rocedureNUa2_DC'    101
 
==Title:==
Unit - -    Level Of Use:- -  -
1/2    General Skill Reference -
ODCM: Index, Matrix and History of ODCM Changes                                Revision:  Page Numb A
3.3.2      IOCFR20.1302, Compliance with Dose Limits for Individual Members of the Public.
3.3.3      10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities 3.3.4      10CFR50.36a, Technical Specifications on Effluents from Nuclear Power Reactors 3.3.5      Appendix I to 10 CFR Part 50, Numerical Guides For Design Objectives and Limiting Conditions For Operation to Meet The Criterion "As Low As Reasonably Achievable" For Radioactive Material in Light-Water-Cooled Nuclear Power Reactor Effluents
      .3.3.6      40 CFR Part 141                                                                              ;
3.3.7    40 CFR Part 190, Environmental Radiation Protection Standards For Nuclear Power Operations          :
3.3.8      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 correction factors to determine particulate activity in samples obtained from the effluent release pathways.;
4.0      RECORDS AND FORMS 4.1      Records 4.1.1      Any calculation supporting ODCM changes shall be documented, as appropriate, by a retrievable document (eg; letter or calculation package) with an appropriate RTL number.
4.2      Forms 4.2.1    None 5.0.      PRECAUTIONS AND LIMITATIONS 5.1      This OFFSITE DOSE CALCULATION MANUAL (ODCM) provides the information and methodologies to be used by Beaver Valley Power Station Unit I and Unit 2 (BV-1) and (BV-2) to assure compliance with the Administrative Controls Section of the operating Technical Specifications. They are intended to show complianice with 10 CFR 20.1302,(3.2l) 10 CFR 50.36a,( 3 Appendix I of 10 CFR Part 5              and 40 CFR Part 190.(32.4) 5.2      This ODCM is based on the NUREG's and Generic Letter documents from the United States Nuclear Regulatory Commission. (3132313314) Specific plant procedures for implementation of the ODCM are included in various site procedures and documents, and are utilized by the operating staff to assure compliance with Technical Specifications and the CONTROLS Procedure of the ODCM:( 3 l5 )
 
aeValyPower .Station
                            .B                                                                  l/2tODC-l1l.01re(
 
==Title:==
ODCM: Index, Matrix and Histoly~of ODCM Changes Unit:
1/2 Revision:
IGeneral Skillefrec Leve Of Ulse:
Page Number.
5.3        The ODCM has been prepared as'generica1, Yas possile inodrto miiie.teneo future versions. However, some changes to the ODCM may.be necessary in the future. 'Any' such changes will be properly prepared, review ed, and approved as indicated in the Administrative Control Section of the Technical Specifications.
5.3.1      An implementation procedure for control of the ODCM is included in 1/2-ADM-5.4        This procedure also contains information that was previously contained in Appendix F of the previous BV-1 and 2 Offsite Dose Calculation Manual.              .-
*5.4.1                In regards .o this, the Tables that were-transferred from Appendix Fto thep      apropriate ATTACHMENTS of this procedure will still contain a prefix denoting an "F".'
6.0        ACCEPTANCE CRITERIA 6.1-        All changes to' this procedure shall contain sufficient justification that the change will maintain the level of radioactive Effluent Control required by 10 CFR 20.1302,.40 CFR Part.
190, 10 CFR 50.36a and Appendix I to 10 CFR 50, and 'not-adverselyimpact the accuracy or reliability of effluent dose or alarm setpoint calculation. (3 . 7 6.1.1      All change to this proceduiie shall be prepared in acordanice with 1/2-AM00                3" and 1/2-ADM-1640.(316 SS-3boi(.15 and 1/2-ADM-1640.' 3 r 7.0        PREREQUISITES                .
7.1        The user of this procedure shall be familiar with ODCM structure and content.
8.0        PROCEDURE                                    (*        ....-
8.1        Description of QDCM Structure.
8.1.1      1/2-ODC-l.01. ODJCM:ri~dex. Matrix a'ndHistorv of ODC M changes (formerly: ODCM Index and Appendix F) 8.1.1.1    *History    ofOQDCM Changes 8.1.1.2        Sumnmaryof ODCM References 8.1.1.3        List of Tables (ATTACHMENT A) 8.1.1.4        List of Figures (ATTACHMENT B) 8.1.1.5        Matrix of Procedures Used to Meet ODCM Controls (ATTACHMENT C)
 
                        . - - _* . ,- d ............ n
* _tn.  ............--    _ProcdureNumbw- .......
Beaver      valley rower Station            .              .        d          n1/20DC-1.01
'itle      -                                                                      Un. ..    . L        Usie0tA:,
1/2      General Skill Reference. N ODCM: Index, Matrix and History of ODCM Changes                                    Revision:    ag            ofl72 l 8.1.1.5.1        BV-1 Radiation Monitor Surveillances' 8..1.L5.2        BV-1 Liquid Effluent Monitor Surveillances 8.1.1.5.3        BV-2 Liquid Effluent Monitor Surveillances -
8.1.1.5.4        BV-1 Gaseou Effluent Monitor Surveillances'.
8.1.1.5:5        BV-2 Gaseous Effluent Monitor Surveillances 8.1.1.5.6        BV-1 and 2 Liquid Effluent Concentratio'n' Surveillances 8.1.1.5.7.      BV-1I and 2 Liquid Effluent Dose Surveillances.
8.1.1.5.8.      BV-1 and 2 Liquid Effluent Treatment Surveillances 8.1.1.5.9        BV-1 and 2 Gaseous Effluent Air Dose Sur've-illances' 8.1.1.5.10,      BV-1 and 2 Gaseous Effluent Particulate and Iodine Surveillances 8.1.1.5.11      BV-1 and 2 Gaseous EffluientTreatmednt Surveillances 8.1.1.5.12      BV-1 and 2 Gaseous Effluent Total Dose Surveillances 8.1.1.5.13      BV-1 and2 Gaseous Effluent REM? Surveillances 8.1.1.5.14      BV-1 and 2 Gaseous Effluent Land Use Census Surveillances 8.1.1.5.15      BV- I and 2 Gaseous Effluent Interlaboratory Comparison Program Surveillances 8.1.2      1/2-ODC-2.01. ODCM: Liquid Effluents (formerly-, ODCM Sections I and 5) 8.1.2.1        Alarm Setpoints 8.1.2.1.1        BV-i Setpoint Determination Based On A Conservative Mix 8.1.2.1.2        BV-1 Setpoint Determination Based On Analysis Prior To Release 8.1.2.1.3        BV-2 Setpoint Determination Based On A Conservative Mix 8.1.2.1.4        BV-2 Setpoint Determination Based On Analysis Prior To Release 8.1.2.2        Compliance With 10 CFR 20 EC Limits 8.1.2.2.1        Batch Releases 8.1.2.2.2        Continuous Releases                          ' '*
 
  .  ,  . . - _ .. .            -  . 1 .-  . I . .
:. Procedure Number.
Beaver Valley. Power.Staton ./2-ODC-1.O1 Title.                                                                                Unit:        Level Of Use:
1/2        General Skill Reference ODCM: Index, Matrix and History of ODCM Changes                              '        Revision:-PageNumber:
                                                                ......        ....--        4      -        14of
                                                                                                              -. 77.
8.1.2.3          Compliance With 10 CFR 50 Dose Limits 8.1.2.3.1        -Cumulation Of Doses-s 8.1.2.3.2        Projection Of Doses  '.  ':  ''
8.1.2.4          Liquid Radwaste Treatment System' 8.1.2.4.1        BV-I Liquid Radwaste Treatment System Components 8.1.2.4.2        By-i Laundry and Contaminated Shower Drain System Components z.. .
8.1.2.4.3        BV-2 Liquid Radwaste Treatment System Components 8.1.2.5          Site Boundary for Liquid Effluents 8.1.2.5.1        Liquid Effluent Site Boundary, 8.1.3            1/2-ODC-2.02. ODCM: Gaseous Effluents:
(formerly, ODCM Sections 2 and 5) 8.1.3.1          AlarmnSetpoints 8.1.3.1.1        BV-I Setpoint Determination Based On A-Calculated Mix          -
8.1.3.1.2        BV-1 Setpoint Determination Based On Analysis Prior To Release 8.1.3.1.3        BV-2 Setpoint Determination Based On A Calculated Mix 8.1.3.1.4        BV-2 Setpoint Determination Based On Analysis Prior To Release 8.1.3.1.5        BV-1/2 Setpoint Determination Based On A Calculated Mix 8.1.3.1.6        BV-1/2 Setpoint Determination Based On Analysis Prior To Release 8.1.3.2          Compliance With 10 CFR 20 Dose Rate Limits 8.1.3.2.1        Dose Rate Due To Noble Gases 8.1.3.2.2        Dose Rate Due To Radioiodines And Particulates 8.1.3.3          Compliance With 10 CFR 50 Dose Limits 8.1.3.3.1        Doses Due To Noble Gases, 8.1.3.3.2        Doses Due To Radioiodines And Particulates 8.1.3.4          Gaseous Radwaste Treatment -System        j
 
__ . . ..        ...............        .v  Pmcedtue Nuffses - -      -  -  -
Beaver      ValleryP6wer Station
_________________________________________                [..          1  2-ODC-1.01 112ODC1.I T1ite:                                                                            Unit          Lel Of Usc:          -
1/2        General Skill Reference Revision:    Page Number:
ODCM: Index, Matrix and History of ODCM Changes
: 4.              15 of 79 8.1.3.4.1        BV-I Gaseous Radwaste Treatment System Components 8.1.3.4.2        BV-2 Gaseous Radwaste Treatment System Components 8.1.3.5      Site Boundary for Gaseous Effluents 8.1.4      1/2-ODC-2.03. ODCM: Radiological Environmental Monitoring Proraim (formerly", ODCM Sectionr3) 8.1.4.1      Program Requirements 8.1.5      1/2-ODC-2.04, ODCM: Information Related to 40 CFR 190 (formerly- ODCM Section 4).                          .    ,
8.1.5.1      Compliance with 40 CFR 190 Dose Limits, 8.1.5.2      Report Requirements 8.1.5.3      Inside the Site Boundary Radiation Doses 8.1.5.3.1        Gaseous Effluent Site Boundary j
8.1.6      1/2-ODC-3.01. ODCM: Dispersion Calculational Procedure and Source Term Inputs (forrnerly; ODCM Appendix A &B)                      . .;
8.1.6.1      Dispersion and Deposition Parameters 8.1.6.2      BV-1 and 2 Release Conditions
: 1.            8.1.6.3      BV-1 Liquid Source Tern Inputs 8.1.6.4      BV-2 Liquid Source Term Inputs I            .8.1.6.5      BV-1 Gaseous Source Term Inputs 8.1.6.6      BV-2 Gaseous Source Term Inputs 4
8.1.7      1/2-ODC-3.02, ODCM: Bases for ODCM Controls (formerly, ODCM Appendix D) 8.1.7.1      Bases 3.3.3.1: Radiation Monitoring Instrumentation 8.1.7.2      Bases 3.3.3.9: Radioactive Liquid Effluent Monitoring Instrumentation i          .8.1.7.3      Bases 3.3.3.10: Radioactive Gaseous Monitoring Instrumentation 8.1.7.4      Bases 3.11.1.1: Liquid Effluent Concentration I
8.1.7.5      Bases 3.11.1.2: Liquid Effluent Dose
 
  -.              Beaver Valley Power Station..                  . ..  :. Procedure Number.
1/2-ODC-1.O1
 
==Title:==
.Unit                                                                Level Of Use:
Tit-e.                                                              1/2        General Skill Reference ODCM: Index, Matrix and History of ODCM Changes`                              R    on:    Page Number-
        ' 8.1.7.6        Bases 3.11.1.3: Liquid Radwaste Treatment System' 8.1.7.7      Bases 3.11.1.4: Liquid Holdup Tanks 8.1.7.8      Bases 3.11.2.1: Gaseous Effluent Dose Rate 8.1.7.9      Bases 3.11.2.2: Dose-Noble Gases 8.1.7.10      Bases 3.11.2.3: Dose - Radioiodines, Radioactive Material in Particulate Form, and Radionuclides Otlier Than Noble Gases 8.1.7.11      Bases 3.11.2.4: Gaseous Radwaste Treatment Syste'm 8.1.7.12      Bases 3.11.2.5: -Gas Storage Tanks        '
8.1.7.13'    Bases 3.11.4.1: Total Dose 8.1.7.14      Bases 3.12.1: 'REMP Program Requirements' 8.1.7.15      Bases 3.12.2: REMP - Land Use Census 8.1.7.16      Bases 3.12.3: REMP - Interlaboratory Comparison Program' 8.1.8      1/2-ODC-3.03, ODCM: Controls for RETS'and REMP Programs (formerly, ODCM Appendix C)'-
8.1.8.1      Controls 3.0.1 thru 3.0.4 :Applicability 8.1.8.2-      Controls'4.0.1 thru 4.0.4: Surveillance'Requirements 8.1.8.3      Control 3.3.3.1: Radiation Monitoring Instrumentation 8.1.8.4      Control 3.3.3.9: Radioactive Liquid Effluent Monitoring Instrumentation 8.1.8.5      Control 3.3.3.10: Radioactive Gaseous Monitoring Instrumentation
        ' 8.1.8.6      Control 3.11.1.1: Liquid Effluent Concentration'.
8.1.8.7      Control 3.11.1.2: Liquid EffluentDose 8.1.8.8      Control 3.11.1.3- Liquid Radwaste Treatment System 8.1.8.9      Control 3.11.1.4: LiquidHolduplTanks 8.1.8.10      Control 3.11.2.1: Gaseous Effluent Dose Rate 8.1.8.11      Control 3.11.2.2: Dose- Noble' Gases'
 
jeav'er B            Valley  BSPower Station                        ..; I.- _      N1b2  OC10
 
==Title:==
Unit:  -      Leve Of Use,
                            . ..          .                                          ~~1/2        General Skill Refer'ence ...........
ODCM: Index, Matrix and History of ODCM Changes                    .      72m-    Revision:      Pg        r 8.1.8.12      Control 3.11.2.3: Dose - Radioiodines, Radioactive Material in Particulate Form, and Radionuclides Other Than Noble Gases 8.1.8.13      Control 3.11.2.4: Gaseous Radwaste Treatment System 8.1.8.14      Control 3.11.2.5: Gas Storage Tanks 8.1.8.15      Control3.11.4.1: TotalDose
      '    8.1.8.16      Control 3.12.1: REMP Program Requirements 8.1.8.17      Control 3.12.2:. REMP - Land Use Census 8.1.8.18      Control 3.12.3: REMP -Interlaboratory Comparison Program 8.1.8.19      Control 6.9.2: Annual REMP Report 8.1.8.20      Control 6.9.3: Annual RETS Report 8.2        History Of ODCM Changes 8.2.1    Change (I) of BV-1 ODCM (Issue 1.Effective January. 1984) 821.1        This is the initial issue of the BV-I ODCM, as prepared for implementation of the Radiological Effluent Technical Specificati6ns"(RETS). Implementation of this manual was commensurate with Amendment No. 66 to the Unit 1 Technical Specifications as approved by the NRC on Mairch28, 1983.
8.2.2    Change (2) of BV-1 ODCM (Issue 1. Revision 1. Effective October. 1984) 8.2.2.1      A description of the changes that were implemented with this revision'are as follows:
8.2.2.1.1        Section 1.0: Table 1.3-1 was revised to include liquid dose factors for nuclides presently identified at BVPS and not included in the original table.'
8.2.2.1.2        Section 2.0: Equations 2.1-19 and 2.1-22 were revised as approved at RSC Meeting No. BVPS-RSC-1-84 on January 31, 1984. The equations were revised to clarify flow rate terminology.
              .8.2.2.1.3        Section 2.0: Section 2.2.2 was revised to delete the food and ground pathways for gaseous dose rate calculations of I-131, tritium, and' radionuclides in particulate form with half lives'greater than 8 days.
8.2.2.1.4        Section 2.0: Table 2.2-13 was revised to include 7 organs r'ather than only'.
the maximum organ. Also, the receptor was changed from infant to child, and addition/deletion of nuclides to be consistent with the Technical Specifications and nuclides identified at BV-1.                                              l
 
ProedureNumber Beaver Valley Power Station                                                  1/2-ODC--.o1
 
==Title:==
Unit:        Level Of Use:
1/2      General Skill Reference ODCM: Index, Matrix and History of ODCM Changes                                        Reision:    Page Number 8.2.3      'Change (3) of BV-1 ODCM (Issue' 1. Revision 2. Effective JulY. 1986) 8.2.3.1        A description of the changes that were implemented with this revision are as follows:
8.2;3.1.1        Section 1.0: Provide a flow based monitor setpoint adjustment factor in Section 1.1.2. This change makes Section1.1.2 consistent with Section 1.1.1 and current'procedures.
8.2.3.1.2        Section 1.0 and 2.0: Revise the 31-day dose projection limits and methodology in Sections 1.3.2, 2.3.1.2, and 2.3.2.2. This change corrected
: the 31-day'dose-projection limits ahd changed the dose projection methodology to be consistent with proposed software.
8.2.3.1.3        Section'2.0: Revise the Gaseous Effluent Monitor Setpoints in Sections
                              ' 2.1.1 and 2.1.2. They were revised due to pressure corrections determined I        'for the 'detectors, changes in isotopic literature,- and the addition of SPING' Channel 5 alternate monitor data. The calculations supporting this item are contained in Calculation Packages ERS-SFL-85-031 and ERS-ATL86-008.
8.2.4      Change (4) of BV-1 ODCM (Issue 2. Effective July 1987). and BV-2 ODCM (Issue 1.
Revision 1. Effective July. 1987) 8.2.4.1        With the start-up of BV-2 in the second half of 1987, the BV-1' ODCM required revision and the BV-2 ODCM required initial implementation. A description of the changes are as follows:'
8.2.4.1.1        Produce functionally-compatible BV-1 and BV-2 ODCMs which address site dose rate limits and meet regulatory requirements. Note that due to the scope of the revisions to the Unit 1 ODCM, it was re-issued as Issue 2.
Also, for clarity, 'the draft BV-2 ODCM previously submitted to the NRC was regarded as Issue 1-(historical) and operation of BV-2 began with Issue 1, Revision 1 of the BV-2 ODCM.                        -
              '-8.2.4.1.2        Section 1.0: A shared liquid radwaste system, permitting mixing of waste for processing, the sharing of dilution water, and the apportionment of dose according to NUREG-0133 was incorporated into both ODCMs.
            '8.2.4.1.3        'Section 2.0: A shared elevated gaseous radwaste system, permitting the mixinig of gaseous radwaste and the apportionment of dose, according to NUREG-0133 was'incorporated into both ODCMs.
8.2.4.1.4        Section 2.0: Separate ground level gaseous releases were maintained. The BV-1 ODCM was updated to'incorporate the BV-2 five year meteorology base. Gaseous source terms were revised to that calculated for BV-1 in the BV-2 FSAR, and terms were added for calculation of a turbine building release.
 
                                                                              -  Proedure Number~
Beaver Valley Power Station                                    l1/2-ODC-10.-
ritle.                                                                          Unit:        Lvel Of Use: -  -    ,
1/2      General Skill Reference ODCM: Index, Matrix and History of ODCM Changes                                  Revision:    ae        of 7er 8.2.4.1.5        Section 2.0: The gaseous effluent monitor alarm. setpoints of both ODCMs were revised as required by revisions to meteorology,' source terms, monitor efficiencies, and revised percentages of site dose rate limits.
8.2.4.1.6        Section 2.0: Formaljustification was provided for use of the "T" factor in Containment Purge Dose Rate calculations. Whereas, the dose rate for a Containment Purge may be averaged over. a time period not to exceed 960' minutes. Since the Containment air volume change time period is 60 minutes, then the maximum value for "T" is 16 (i.e., 960 minutes/60 minutes
                              -16).
8.2.5    Change (5) of BV-1 ODCM (Issue 2. Revision-I Effective December. 1987). and BV-2 ODCM (Issue 1. Revision 2. Effective December. 1987) 8.2.5.1      Section 2.0: Sections 2.1.3 and 2.1.4 of both ODCMs were changed to delete a note concerning noble gas nuclides as requested by a NRC letter dated July14, 1987 titled Beaver Valley Unit 2 - Offsite Dose Calculation Manual, ODCM (TAC 63996).
8.2.6    Change (6) of BV-1 ODCM (Issue 2. Revision 2 Effective June. 1989). and BV-2 ODCM (Issue l. Revision 3. Effective June. 1989)                      -
8.2.6.1      A description of the changes.that were implemented with this revision are as follows:
8.2.6.1.1        Section 1.0 and 2.0: Both ODCMs were revised for'addition of Sections 1.4' and 2.4. This addition gives a description of and includes flow diagrams of the Liquid RadWaste System and the Gaseous Radwaste System. (See
                              'justification 1) 8.2.6.1.2        Section 1.0: Corrected typos to BV-1 ODCM Equation 1.1-8 to show differentiation between the two fs, and add the division sign. (See Justification 1) 8.2.6.1.3        Section 1.0: Re-define Fk in equation 1.3-1 of both ODCMs, as allowed by" the NRC. (See Justification 1) '
8.2.6.1.4        Section 1.0 and 2.0: Typos were corrected to the following: (1) BV-1 ODCM equation 1.3-7; add a division sign between the brackets. (2) BV-I ODCM equation' 1.3-8; add a division sign between the brackets. (3)
Equation 2.1-20 of both ODCMs; change the HHSP to HSP multiplier from 0.70 to 0.33. (4) Equation 2.1-24 of both ODCMs, change the HHSP to HSP'multi'lier from 0.70 to 0.33. (See Justification 1)
 
Beaver Valley Power Station                                  Procedure1NUn 2-ODC-1.01
 
==Title:==
Unit:        Level Of Use:
1/2        General Skill Reference ODCM: Index, Matrix and History of ODCM Changes                            Revision:    Page Number:
4                20 of 72 8.2.6.1.5      Section 1.0 and 2.0: Typos were also corrected as follows: (1) Add the words "from each reactor unit" to five places (Sections 1.3.1, 1.3.2, 2.3.1.1, 2.3.1.2, and 2.3.2.2) of both ODCMs. This ensures compliance with the current requirements of the Technical Specifications. (2) Correct punctuation in Section 2.3.2.1 of the BV-1 ODCM. (3) Correct typos in Table 3.0-1 of both ODCMs. (4) Correct typos in Figure 3.0-3 of both ODCMs.
8.2.6.1.6      Section 2.0: Add a Reference to Section 2 of the BV-1 ODCM. (See Justification 3) 8.2.6.1.7      Section 2.0: Add the words "from the site" to Section 2.2.2 of both ODCMs.
This ensures compliance with the current requirements of the Technical Specifications. (See Justification 2) 8.2.6.1.8      Section 2.0: Revise BV-1 ODCM Table 2.2-2 to change the particulate and iodine radionuclide mix for the Unit 1 Ventilation Vent and to correct a typo for Xe-135m in the Containment Vacuum Pumps. (See Justification 3) 8.2.6.1.9      Section 2.0: Provide re-verified PiT values for the BeaverValley site in Table 2.2-13 of both ODCMs. (See Justification 1) 8.2.6.1.10      Section 2.0: Correct the definition for the tf value in the cow-meat pathway in Section 2.3.2.1 of both ODCMs. (See Justification 1) 8.2.6.1.11      Section 2.0: Provide re-verified R values for the Beaver Valley site in Tables 2.3-2 through 2.3-20 of both ODCMs. (See Justification 1) 8.2.6.1.12      Appendix B: Change the particulate and iodine release fractions in Appendix B of the BV-1 ODCM. (See Justification 3) 8.2.6.2      The justification used for Change (6) to the ODCMs are as follows:
8.2.6.2.1      A letter dated March 2, 1989 (from the NRC) was received by Duquesne Light regarding-acceptance of the Offsite Dose Calculation Manuals. The NRC acceptance of the BV-1 and BV-2 ODCMs was based on Technical Evaluation Reports (TER No. EGG-PHY-8194 and EGG-PHY-8217) provided by the Idaho National Engineering Laboratory.
As stated in the letter, minor concerns are delineated in Section 4 of the TER.
In general, these concerns are considered typos or additions and in one way impact any of the calculations currently being performed for dose contributions. However, one of these concerns is regarding the inability to reproduce the ODCM R values for the cow-meat, cow-milk and goat-milk pathways when using the ODCM/NUREG-0133 methodology. These R values (along with all other ODCM R values) were re-validated VIA Calculation Package No. ERS-ATL-89-014. The results of this package showed that the R
 
II
            *. Beaver Valley Powefr-Sati                      tto              ~~d~u
____  ______ ___ ___ ___ ___ ___ ____ ___ ___  ___  ___1/2-OD                  C-1.01
 
==Title:==
Unit:      Level Of Use:
1l/2  I General Skill Reference N ODCM: Index, Matrix and History of ODCM Changes                                          Revision:  Page Numbero values for the three aforementioned pathways were in error. Since the R values in error do not involve the controlling receptor'for gaseous release (i.e.; the controlling receptor is VIA the Inhalation, Ground, and Vegetation pathways, not the pathways subject to error) than these changes to the ODCM will not adversely impact the accuracy or reliability of effluent dose calculations.
8.2.6.2.2        As requested by DLC letters ND3NSM:3431, NDlNSM:3522, and NDINSM:3652, Technical Specifications were required to be verified in all plant implementing procedures. As part of this effort, wording errors/typos were identified in various sections of the ODCM. This revision corrects the anomalies identified during the verification effort.
8.2.6.2.3        As delineated in letter ND I SHP:776, dated February 12, 1988 (BVPS-1 ODCM Table 2.2-2, Appendix B) a series of apparent discrepancies were identified between ODCM Table 2.2-2 and similar tables of the BVPS-2 FSAR. Evaluation showed that apparent credit was given for continuous filtration of SLCRS releases which is invalid at Unit 1. However, the calculation package on which the BVPS-2 FSAR expected release tables are based,: is correct (i.e.; no credit was taken for routine filtration for Unit 1 releases). Except for revising the ODCM, no further corrective action is necessary because the particulates and iodines in the ODCM were not used for gaseous effluent alarm setpoint. Therefore, this change does not adversely impact the accuracy or reliability of setpoint calculations.
8.2.7    Change (7) of BV-I and 2 ODCM (Issue 3. Effective August. 1995) 8.2.7.1      The combined ODCM, as implemented by ISSUE 3, contains the following changes:
8.2.7.1.1        Prior to ISSUE 3, BV-1 and BV-2 had individual ODCMs that were generically equal. In an effort to simplify the implementing documents, the ODCMs have been combined. This merger of the individual ODCMs 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 Part
: 50. Also, this merger will not adversely impact the accuracy or reliability of effluent,'dose, or setpoint calculations.
8.2.7.1.2        Section 1.0: Revised Section 1.0 (Liquid Effluents) to show compliance with 10 CFR 20 Appendix B (20.1001 - 20.2401), Table 2, Col. 2 EC's. This includes the following: (1) Revising the alarm setpoints for monitors [RM-lLW-104, RM-lLW-1 16, and 2SGC-RQ100]. (2) Updating the BV-1 monitor detection efficiencies. (3) Updating discharge rate and dilution rate parameters for BV-1 and BV-2. (4) Adding the alarm setpoints for monitors
[RM-IRW-1 00, RM- IDA-I 00, 2SWS-RQ1 01, and 2SWS-RQ1 02].
 
Procedure Number Beaver Valley Power Station                                              1/2-ODC-1.01
 
==Title:==
Unit:        Level Of Use:
1/2      General Skill Reference ODCM: Index, Matrix and History of ODCM Changes                        Revision:    Page Number 8.2.7.1.3      Section 1.0: Revised Section 1.0 (Liquid Effluents) and Section 2.0 (Gaseous Effluents) to merge the BV-i alarm setpoint calculations with the BV-2 alarm setpoint calculations. For all practical purposes, when Tables, Figures, and Equations were transferred to the combined ODCM, the numbering was kept generically equal. The two exceptions to this are as follows: (1) If a table was contained in both ODCMs, but each had data specific to BV-1 or BV-2, then an a or b was added to the table. For example, Table 1.1-1 was previously included in the BV-1 ODCM and the BV-2 ODCM. These tables are now numbered 1.1-la and 1.1-lb denoting BV-1 and BV-2 respectively. A cross reference for ODCM tables is provided in the Table Of Contents. (2) If an equation was contained in both ODCMs, but each had data specific to BV-1 or BV-2, then a (1) or (2) was added to the equation. For example, Equation 1.1-1 was previously included in the BV-1 ODCM and the BV-2 ODCM. These equations are now
                      -numbered 1.1(1)-I and 1.1(2)-1, denoting BV-I and BV-2 respectively. A cross reference for ODCM equations is provided in the Table Of Contents.
8.2.7.1.4      Section 3.0: Revised Section 3.0 (Radiological Environmental Monitoring
                    .Program) to list the program requirements from the Radiological Assessment Branch Technical Position (Revision 1, 1979).
8.2.7.1.5      Section 4.0: Revised Section 4.0 (Information Related To 40 CFR 190) to provide clarified reporting requirements for the Special Report. The clarifications were taken from Generic Letter 89-01, Supplement No. 1 (NUREG-1301).
8.2.7.1.6      Appendix A: Revised Appendix A to transfer the Batch Release dispersion parameters from Appendix A (Tables A-2 through A-5) to Section 2.3 (Tables 2.3-35 through 2.3-38). This revision was done for clarification.
For example, all dispersion parameters are now included in one area of the ODCM.
8.2.7.1.7      Appendix C: This is a new Appendix to the ODCM. Procedural details for the Radiological Effluent Technical Specifications (RETS) were transferred from the Technical Specifications to Appendix C of the ODCM per Generic Letter 89-01 and Generic Letter 89-01, Supplement No. 1 (NUREG 1301).
This Appendix also includes selected Definitions and Tables as delineated in the Technical Specifications (Section 1) and selected Applicability and Surveillance Requirement statements as delineated in the Technical Specifications (Section 3/4). These were added to Appendix C for reference purposes, even though they are currently described in the Technical Specification.
8.2.7.1.8      Appendix D: This is a new Appendix to the ODCM.. The bases for ODCM Controls were transferred from the Bases Section of the Technical Specifications to Appendix D of the ODCM per Generic Letter 89-01.
 
I Beaver Valley Power-Station                                              /-OedureDNumbr
 
==Title:==
Unit:      Level Of Use:
                          .    .1/2                                                  General Skill Reference .l ODCM: Index, Matrix and History of ODCM Changes                          Revision:  Pa  N    t  fm7r 8.2.7.1.9      Appendix E: This is a new Appendix to the ODCM. The Annual Radioactive Effluent Release Report and the Annual Radiological Environmental Report reporting requirements are listed in this appendix to the ODCM.
8.2.7.1.10      There are three differences (i.e., non-editorial changes) in this ODCM revision when compared to the previous BV-1 and BV-2 Technical Specifications. These are the only changes that are identified by revision bars. These differences are as follows:
8.2.7.1.10.1      First Difference - LLD Definition Clarification is described as follows:
(1) There was a sentence removed in the LLD Standard Deviation Definitions delineated in Appendix C Tables 4.11-1 and 4.11-2. This sentence stated: ' "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 in milk samples)." (2) This sentence was removed by justification of NUREG-0472, Rev. 2 (i.e., this revision to the NUREG removed the sentence from Tables 4.11-1 and 4.11-2). At BV-1 and 2, there are no other radionuclides normally present in effluent samples.
However, there is applicability to environmental LLD calculations due to the existence of other radionuclides in environmental samples. This sentence, therefore, will not be removed from Appendix C, Table 4.12-
: 1. (3) Removal of the sentence from Appendix C, Tables 4.11-1 and' 4.11-2 does not adversely impact the accuracy or reliability of current or past effluent LLD calculations. This change maintains 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 Part 50, and does not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations. (4) This change brings ODCM Appendix C, Tables 4.11-1 and 4.11-2 in generic agreement with NRC guidance (i.e., NUREG-0472) and industry standard.
 
Beaver Valley Power Station                                  Procedure Nuer.ODC101
 
==Title:==
Unit:        Level Of Use:
1/2      General Skill Reference ODCM: Index, Matrix and History of ODCM Changes                        Revision:    Page Number.
i4                                                                            24 of 72 8.2.7.1.10.2      Second Difference - Change From Semi-Annual Report To Annual Report as follows: (1) The frequency of the Radioactive Effluent Release Report was changed from Semi-Annual to Annual. This change is justified by Federal Register, Rules And Regulations (Vol.
57, No. 169, Monday, August 31, 1992), where as; 10 CFR Part 50.36a(a)(2) states, in part. "Each licensee shall submit a report to the Commission annually that specifies the quantity of each of the principal radionuclides released to unrestricted areas in liquid and in gaseous effluents during the previous 12 months of operation...the time between submission of the reports must be no longer than 12 months..." (2) This change maintains the level of radioactive effluent control required by I0 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50, and does not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
8.2.7.1.10.3      Third Difference - Implementation Of New 10 CFR 20 is described as follows: (1) The definition for MEMBER(S) OF THE PUBLIC was revised to agree with the definition in 10 CFR 20.1003. (2) The definition for UNRESTRICTED AREA was modified from the definition that was in the Technical Specifications prior to transferring to the ODCM. This modification was necessary to ensure that the ODCM dose model for gaseous releases is not affected. The modification involved adding the following sentence: "For gaseous release dose calculations, the UNRESTRICTED AREA should exclude any public road, railway, or waterway adjacent to or crossing the site that is not occupied continuously by MEMBER(S) OF THE PUBLIC". (3) The limits for liquid effluent concentration were changed from 1 times 10 CFR 20 Appendix B (20.1 - 20.601), Table II, Col. 2 MPC's to 10 times 10 CFR 20.Appendix B (20.1001 -
20.2401), Table 2, Col. 2 EC's. This limit will now be referred to as the ODCM Effluent Concentration Limit (OEC). (4) For gaseous effluents, no changes were made to implement the New 10 CFR 20.
As justification, when the,utility adopted the RETS (1/1/84),
compliance to 10 CFR 20 shifted from the MPC concept to the Unrestricted Area Dose Rate concept. The Dose Rate concept is the preferred method of controlling gaseous effluent release rate, and will continue to be used in-lieu of the MPC or EC concept. (5) Changing to the OEC limit for liquid effluents accommodates needed operational flexibility to facilitate implementation of the New 10 CFR 20 requirements. (6) For information, the general intent of the New Part 20 is that radiation doses to members of the public not exceed 100 mrems per year, which is more restrictive than the 500 mrems per year limit in the Old Part 20, and that fuel cycle licensees also comply with 40 CFR 190. The New Part 20 does not include a requirement on
 
Beaver Valley Power Station                                        -
 
==Title:==
Unit:      Level Of Use:
1/2    General Skill Reference .
ODCM: Index, Matrix and History of ODCM Changes                72mer Revision:    Pg limiting radioactivity concentrations in effluents, which is less restrictive than the Old Part 20. (7) The basic requirements for RETS (i.e.; ODCM Appendix C Controls) are stated in 10 CFR 50.36a.
These requirements indicate that compliance with the RETS will keep average annual releases of radioactive material in effluents to small percentages of the limits specified in the 10 CFR 20.106 (10 CER 20.1302). These requirements also indicate that operational flexibility is allowed (with considerations for public health and safety) which may temporarily result in releases higher than such small percentages, but still within the MPC limits specified in the 10 CFR 20.106. The MPC's relate to an annual dose of 500 mrem. Also, 10 CFR 50.36a indicates that when using operational flexibility, best efforts shall be exerted to keep levels of radioactive materials in effluents to ALARA as set forth in 10 CFR 50 Appendix I. (8) As stated in the Introduction to Appendix B of the New 10 CFR 20, the liquid EC's are based on an annual dose of 50 mrem. -Since a release concentration corresponding to a limiting dose rate of 500 mrem/year has been acceptable as a RETS limit for liquid effluents, it should not be necessary to reduce this limit by a factor of ten. (9) BV-l and BV-2 has demonstrated that the use of the MPC's associated with the 10 CFR 20.106 has resulted in calculated maximum individual doses to a member of the public that are small percentages of the limits of 10 CFR 50 Appendix I. Thereforej the use of the OEC's, which correspond to an annual dose of 500 mrem (i.e.; 10 times the 10 CFR 20 EC's) should not have a negative impact on the ability to continue to operate within the limits of 10 CFR 50 Appendix I, and 40 CFR 190. (10) Operational flexibility is also necessary in establishing a basis for effluent monitor setpoint calculations. As previously discussed, the EC's stated in 10 CFR 20 relate to a dose of 50 mrem in a year. This is too restrictive to base effluent monitor setpoint calculations. For many liquid effluent release situations, the monitor background is high, which could result in a monitor setpoint that is approximately equal to the monitor background. (11) In summary, to accommodate operational flexibility needed for effluent releases, the limits associated with the liquid release concentration (i.e.; the OEC) are based on 10 times the EC's stated in the 10 CFR 20. The multiplier of 10 is used because the annual dose of 500 mrem (10 CFR 20 MPC bases) is a factor of 10 higher than the annual dose of 50 mrem (IO CFR 20 EC bases). Compliance with the 100 mrem dose limit of the 10 CFR 20.1302 will be demonstrated by operating within the dose limits of 10 CFR 50 Appendix I, and 40 CFR 190 (which are also ODCM Controls for liquid and gaseous effluents). Implementation of the 10 CFR 20 for liquid effluents maintains 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 Part 50, and does not f
l
 
. I Beaver Valley Power Station                                    reeU          ODClOI
 
==Title:==
Unit:      Level Of Use:
1/2    General Skill Reference ODCM: Index, Matrix and History of ODCM Changes                                  Revision:  PageNumber:
adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
8.2.7.2      In summary, Per Generic Letter 89-01, the transfer of RETS procedural details fulfills the goal of the USNRC Policy Statement for Technical Specification improvements. It is not the USNRC's (or DLC's) intent to reduce the level of radioactive effluent control. Rather, the intent is to provide programmatic controls for RETS (as delineated in Technical Specification 6.8.6) and allow for relocation of the procedural details of the RETS to the ODCM.
8.2.8    Change (8) of BV-l and 2 ODCM (Issue 3. Revision 1, Effective October. 1995) 8.2.8.1      A description of the changes that were implemented with this revision are as follows:
8.2.8.1.1        Index: Editorial changes were made for clarity. (See justification 1) 8.2.8.1.2        Section 1.0: Revised Nb-95 and Nb-97 dose factors in Table 1.3-1 due to changing the niobium bioaccumulation factor. (see justification 2) 8.2.8.1.3        Appendix A: A change was made to Table 1.1 so that the letter A would proceed the table number. (Seejustification 1) 8.2.8.1.4        Appendix B: A descriptive paragraph was added at the front of this Appendix. Also, changes were made to the tables so that the letter 13 would proceed the table numbers. (See justification 1) 8.2.8.1.5        Appendix C: Descriptive paragraphs were added at the front of the Appendix (See justification 1). Removed the process flow rate operability and surveillance requirements for gaseous effluent radiation monitors
[2RMQ-RQ301, 2RMQ-RQ303 and 2HVL-RQI12] from Tables 3.3-13 and 4.3-13 (See justification 3). Added alternate system effluent flow rate measuring devices for the three gaseous effluent pathways to Tables 3.3-13 and 4.3-13 (See justification 4). Revised Surveillance Requirements 4.11.1.1.3 and 4.11.1.1.4 and notes e andgofTable4.11-1 to clarify Turbine Building sump sampling requirements (See justification 5).
8.2.8.1.6        Appendix D: Descriptive paragraphs were added at the front of the Appendix. (Seejustification 1) 8.2.8.1.7        Appendix E: Descriptive paragraphs were added at the front of the Appendix. (Seejustification 1) 8.2.8.1.8        Appendix F: This is a new Appendix to the ODCM. It contains plant procedure references for Radiological Effluent Technical Specification (RETS) that were transferred from the Technical Specification Procedure Matrix. (See justification 1)
 
Beaver Valley Power Station -CedureNumber-
 
==Title:==
Unit:      Level Of Use:
1/2    General Skill Reference.-
ODCM: Index, Matrix and History of ODCM Changes                              Revision:  Page Number 8.2.8.2      The justification used for change (8) to the ODCM are as follows:
8.2.8.2.1      These changes are considered editorial in nature. Therefore, these editorial changes 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. Also the editorial changes will not adversely impact the accuracy or reliability of effluent dose or setpoint calculation.
8.2.8.2.2      This change resulted from revising the bioaccumulation factor (BF) for niobium from the value posted in Table A-1 of Regulatory Guide 1.109, Revision 1, 1977 (30,000 pCi/kg per pCi/l). Since this change in niobium BF (as documented and justified in Appendix A to Calculation Package No.
ERS-ATL-83-027) merely removes the conservatism associated with organism uptake, then 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. Also, removing the conservatism will not adversely impact the accuracy or reliability of effluent dose or setpoint calculation.
8.2.8.2.3      This change removes the process flow rate operability and surveillance requirements for BV-2 Gaseous Effluent Radiation Monitors [2RMQ-RQ301, 2RMQ-RQ303 and 2HVL-RQ1 12] from Appendix C Tables 3.3-13 and 4.3-13. These items were removed from the ODCM by justification provided in Calculation Package No. ERS-ATL-907021. A safety analysis and a no significant hazards-evaluation were prepared and approved prior to submitted it to the NRC via TSCR No. 2A-61 in 1992. However, it was withdrawn in 1993 in an effort to alleviate any further delays associated with approval of TSCR No. LA-175/2A-37 (Generic Letter 89-01 implementation). Removal of these requirements from the ODCM 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.
Also removal of these items will not adversely impact the accuracy or reliability of effluent dose or setpoint calculation. The following is a summary of the justification. (1) BVPS-1 and BVPS-2 is currently using, and will continue to use design (maximum) system flow rates in ODCM Dose & Dose Rate Calculations, rather than those flow rates observed during normal plant operation. (2) BVPS-2 UFSAR Section 11.3.3 indicates that the source term for these three pathways are not significant. These pathways are not included in UFSAR Tables 11.3-1 through 11.3-4 that list the expected and design releases for each potentially radioactive pathway. (3)
The DLC commitment to Regulatory Guide 1.97, Rev. 2 (Section 1.8-1 of the BVPS-2 UFSAR) is not affected. This RG applies to instrumentation used during and after postulated accident conditions. These three process flow rate instruments were not used in any accident analysis, nor are they used to assess plant conditions during and following an accident. (4) The DLC commitment to Regulatory Guide 1.21, Rev. 1 (Section 1.8-1 ofthe
 
Procedure Number.
Beaver Valley Power Station                                              1/2-ODC-1.01
 
==Title:==
Unit:        Level Of Use:
                                                                        .1/2            General Skill Reference ODCM: Index, Matrix and History of ODCM Changes                          Revision:    Pg Numer BVPS-2 UFSAR) is not affected. RG 1.21, Section C.2 (Location of Monitoring) states in part: "All major and potentially significant paths for release of radioactive material during normal reactor operation, including anticipated operational occurrences, should be monitored. Measurements of effluent volume, rates of release, and specific radionuclides should be made insofar as practical. . " As previously stated, the. three process flow rate instruments are located on effluent pathways that do not have a significant source term. (5) BVPS-2 UFSAR Sections 9.4.13 and 9.4.16 indicate that the building ventilation system for these three pathways are non-safety related and are not required to perform any safety-related function. (6)
There is no effect to the Noble Gas Monitors located on these three pathways. The Noble Gas Monitors are still capable of performing their intended functions as described in BVPS-2 UFSAR Section 11.5.2.4.
8.2.8.2.4    This change adds alternate system effluent flowrate measuring devices for the three BV-1 gaseous effluent pathways to Appendix C Tables 3.3-13 and 4.3-13. A 10 CFR 50.59 safety evaluation has concluded that no unreviewed safety question is involved by adding the alternate measuring devices to Appendix C Tables 3.3-13 and 4.3-13. This conclusion is based on the following: (1) There is no increase in the probability or consequences of accidents or malfunctions of equipment important to safety. (2) There is no creation of a possibility for an accident or malfunction of a different type than any evaluated previously. (3) There is no reduction in the margin of safety. (4) Also, since this change merely adds alternate measuring devices that meet the same surveillance requirements of the primary channel, then 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. Also, addition of the alternate flow rate measuring devices will not adversely impact the accuracy or reliability of effluent dose or setpoint calculations.
8.2.8.2.5    This change to the ODCM clarifies Turbine Building sump sampling requirements and clarifies effluent related actions associated with detection of radioactivity in the secondary system. These clarifications are documented and justified in Calculation Package No. ERS-ATL-95-006.
Also, since these clarifications were shown to meet the intent of NUREG-1301 (superseding NUREG-0472) and the BVPS-1 and 2 UFSAR's, then the clarification 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. Also, the clarifications will not adversely impact the accuracy or reliability of effluent dose or setpoint calculation. Also, a 10 CFR 50.59 safety evaluation has concluded that no unreviewed safety question is involved by clarifying these actions. This conclusion is based on the following: (1) There is no increase in the probability or consequences of accidents or malfunctions of equipment important to safety. (2) There is no creation of a possibility for an accident or malfunction of a different type
 
Beaver Valley Power Station                                    Pedu      /2re DCNm.01      -
 
==Title:==
Unit:      Level Of Use:
1/2      General Skill Reference . N ODCM: Index, Matrix and History of ODCM Changes                                  Revision:  Page Number:
than any evaluated previously. (3) There is no reduction in the margin of safety.
8.2.9    Change (9) of BV-1 and 2 ODCM (Issue 3. Revision 2. Effective May 1997) 8.2.9.1      A description of the changes that were implemented with this revision are as follows:
8.2.9.1.1      Index: Editorial changes were made for clarity. (See Justification 1) 8.2.9.1.2      Section 1.0: Clarifying statements were added to-Tables 1.2-la and 1.2-lb to show that the recirculation times listed. are based on historical recirculation rates. Figure 1.4-3 was added to show BV-1 and 2 liquid Effluent Release Points. (See Justification1) 8.2.9.1.3.      Section 3.0: Removed the option to perform broad leaf vegetation sampling at the site boundary in a sector with the highest DIQ. (See Justification 2) 8.2.9.1.4      Appendix C: Added plant specific Mark Numbers to Tables 3.3-12, 4.3-12, 3.3-13 and 4.3-13 (See Justification 1). Corrected typographical errors on Surveillance Requirement 4.11.4.1.1 (See Justification 1). Added clarifying statements from NUREG-1301 and the Radiological Assessment Branch Technical Position to Tables 3.12-2 and 4.12-1 (See Justification 1).
Removed the option to perform broad leaf vegetation sampling at the site boundary in a sector with the highest D/Q (See Justification 2).
8.2.9.1.5      Appendix E: Corrected typographical error on Table 6.9-1. (See Justification 1) 8.2.9.1.6      Appendix F: Added procedure details to Tables 11, 12 and 13. (See Justification 1) 8.2.9.2      The justification used for Change (9) to the ODCM are as follows:
8.2.9.2.1      These changes are considered editorial in nature. -The changes either correct typographical errors or add editorial details from previously approved station documents. Therefore, these changes 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. Also, the editorial changes will not adversely impact the accuracy or reliability of effluent dose or setpoint calculations.
                                                                                                                        -/
 
Procedure Number.
Beaver Valley Power StationPe                                            N      ODCl1l
 
==Title:==
Unit:        Level Of Use:
1/2        General Skill Reference ODCM; Index, Matrix and History of ODCM Changes                                  Revision:    Page Number:
8.2.9.2.2      This change removes the option to perform broad leaf vegetation sampling at the site boundary (in a sector with the highest D/Q) in lieu of the garden census. Per NUREG-1 301 and the Radiological Branch Technical Position, this option does not apply to plants with elevated releases. Since BV-1 and 2 have elevated releases, the option should not be exercised. A review of past garden census showed that the option was never exercised at BV-1 and 2.
Since this change removes an option that should not be exercised, then 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. Also, removal'of the option will not adversely impact the accuracy or reliability of effluent dose or setpoint calculations.
8.2.10    Change (1O0 of BV-l and 2 ODCM (Issue 3, Revision 3. Effective June 1997) 8.2.10.1      A description of the change that was implemented with this revision is as follows:
8.2.10.1.1      Section 2.0: A release point for the BV-2 Turbine Building Vent was added (for editorial purposes) to Figure 2.4-2.
8.2.10.2      The justification used for Change (10) to the ODCM is as follows:
8.2.10.2.1      This change is considered editorial in nature. The change adds an equivalent item that was previously located on BV-2 Technical Specification Figure 5.1-2. Since BV-2 Technical Specification Amendment 83 removed this figure, then the gaseous release point for the BV-2 Turbine Building Vent needed transferred to the ODCM. Therefore, since this change is considered editorial, 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. Also, the editorial change will not adversely impact the accuracy or reliability of effluent dose or setpoint calculations.
8.2.11    Change (11) of BV-1 and 2 ODCM (Issue 3, Revision 4, Effective March 1998 8.2.11.1    A description of the changes that were implemented with this revision are as follows:                                ,
8.2.11.1.1      Index: Editorial changes were made for clarity.
8.2.11.1.2      Section 3.0: The distances for the environmental monitoring sample points were revised to show a more accurate measurement from the center of the Unit I Containment Building. The actual sample locations and descriptions remain unchanged. Also, the 4 individual quadrant maps showing TLD locations were consolidated into 1 map. This is a Corrective Action to Condition Report CR 980353.
 
Beaver Valley Power Station                      -            edureNuD_
 
==Title:==
Unit:      Level Of Use: -
1/2    General Skill Reference ODCM: Index, Matrix and History of ODCM Changes                              Revision:  Page Number:
4      . 31 nf 72 8.2.11.1.3      Section 4.0: Added clarifying statements as to how doses due to radioactive effluents for MEMBERS OF THE PUBLIC conducting activities inside the site boundary are derived and reported. This is a Corrective Action to Condition Report CR 971578.
8.2.11.1.4      Appendix C: Added statements to Action 23 of Table 3.3-12 to clarify that.
batch liquid releases may also be initiated with the same Action needed for resuming the release. This is a recommendation from the 1997 RETS Self-'
Assessment. A note was also added to this table to clarify that independent signatures on the discharge permit satisfy the requirement for "two technically qualified members 'of the Facility Staff independently verify the release rate calculation..." Added Action 29 to RM-lGW-108B on Table 3.3-13. This addition ensures consistency with the other 7 continuous a
gaseous effluent pathway Actions for Noble Gas Monitor inoperability.
Added plant specific Mark Numbers for primary and alternate instrumentation to Tables 3.3-13 and 4.3-13 as follows: (1) For Noble Gas.
Activity Monitors, [RM-IVS-109 Channel 5] was added as an alternate to
[RM-1VS-1OB] and [RM-lVIS-110 Channel-5] was added as an alternate to [RM-lVS-107B]. [RM-IGW-109 Channel 5] was not added as an alternate to [RM-lGW-108B] at this time, because it does not perform on auto-isolation of gaseous waste decay tank release upon upper activity alarm.-        -/
(2) For Particulate Activity Monitors, [RM-IVS-109 Channel 1] was added as an alternate to [RM-IVS-lOlA], [RM-lVS-11 10 Channel 1] was added as an alternate to [RM-VS-1 107A], and [RM-lGW-109 Channel 1] was added as an alternate to RM-lGW-108A.
8.2.11.1.5      Appendix E:. Corrected typographical errors on Table E:6.9-1 8.2.11.1.6      Appendix F: Updated the procedure details for primary and alternate instrumentation included in Appendix C Tables 3.3-13 and 4.3-13. Reduced the amount of detail contained in reference to the Operating Manual L-5 logs so that the position of the surveillance on the logs can be changed without having a need to change'the Tables in this Appendix. This is a Corrective Action to Condition Report CR 980129.
8.2.11.2    The justification used for Change (11) to the ODCM is as follows:
8.2.11.2.1      These changes are considered editorial in nature. The changes either correct typographical errors or add editorial details from previously approved station documents. Therefore, these changes 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. Also, the editorial changes will not adversely impact the accuracy or reliability of effluent dose or alarm setpoint calculations.
 
Beaver Valley Power Station                                  Procedure NumberODCl1l
 
==Title:==
Unit:        Level Of Use:
1/2      General Skill Reference ODCM: Index, Matrix and History of ODCM Changes                                Revision:    Page Number:
8.2.12    Change (12) of BV-1 and 2 ODCM (Issue 3, Revision 5, Effective November 1998) 8.2.12.1      A description of the changes that were implemented with this revision are as follows.
8.2.12.1.1      Index: Editorial changes were made for clarity. (See Justification 1.)
8.2.12.1.2      Section 1.0: Added clarification for calculation of radionuclide concentration when the Post Dose Correction Factor is >1. (See Justification 1).
8.2.12.1.3      Section 3.0: Added an additional site location for the upstream environmental surface water sample. Added additional method after collecting and compositing this sample. (See Justification 2.)
8.2.12.1.4      Appendix C: Revised the definitions for MEMBER(S) OF THE PUBLIC and UNRESTRICTED AREA to ensure compliance with 10 CFR 20.1003.
(See Justification 1.) Added a definition for MEMBER(S) OF THE PUBLIC to ensure compliance with 40 CFR 190.02(k). (See Justification 1.)
Added plant specific Mark Numbers for primary and alternate instrumentation to Table 3.3-13 that were inadvertently omitted from change (11) to the ODCM. (See Justification 1.) Added clarification to Table 4.11-2 as to where and when H-3 samples of Waste Gas Storage Tanks are to be obtained. This is a Corrective Action to Condition Report CR 981489. (See Justification 1.) Added clarification to note "e" of Table 4.11-2 as to the appropriate ventilation release path. This is a Corrective Action to CR.
981490. (See Justification 1.). Corrected an obvious omission on Table 3.12-1 to ensure that 2 TLD's are used for determination of Direct Radiation.
(See Justification 1.) Incorporated the appropriate changes to Table 3.12-1 that are described above for Section 3.0. (See Justification 2.)
8.2.12.1.5      Appendix F: Added procedure details from the Chemistry Manual to Table
: 6. This is a Corrective Action to Condition Report CR 981488. (See Justification 1.)
8.2.12.2      The justifications used for Change (12) to the ODCM are as follows:
8.2.12.2.1      These changes are considered editorial in nature. The changes either correct typographical errors or add editorial details from previously approved station documents. Therefore, these changes 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. Also, the editorial changes will not adversely impact the accuracy or reliability of effluent dose or alarm setpoint calculations.
 
s  >                                .ProcedureNumberee    Of Use Beaver Valley Power Station                                    Po2ed          ODCrNl.mb
 
==Title:==
Unit:        Uevel. Of Use:
1/2      General Skill Reference, ODCM: Index, Matrix and History of ODCM Changes                                  Revision:    Page Number.
4                33 of 72 8.2.12.2.2      These changes involve the upstream environmental surface water sample method and sample site. Since these changes were shown to meet the intent of NUREG-1301, and BVPS-1 and 2 UFSAR's, then 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.
Also, the change will not adversely impact the accuracy or reliability of effluent dose or alarm setpoint calculations. Also, a 10 CFR 10.50 safety evaluation has concluded that no unreviewed safety question is involved by adding an additional sample site and sample method. This evaluation is based on the following: (1) There is no increase in the probability or consequences of accidents or malfunctions of equipment important to safety.
(2) There is no creation of a possibility for an accident or malfunction of a different type than any evaluated previously. (3) There is no reduction in the margin of safety.
8.2.13    Change (13) of BV-1 and 2 ODCM (Issue 3. Revision 6. Effective May 1999) 8.2.13.1      A description of the changes that were implemented with this revision is as follows:
8.2.13.1.1      Index: Editorial changes were made for clarity.
8.2.13.1.2      Section 3.0: Updated figure number and table reference. Removed a redundant upstream environmental surface water sampling location.
8.2.13.1.3      Appendix C: Made editorial changes for clarity. Added definitions for SHUTDOWN and STARTUP. Changed definition for ODCM to ensure agreement with definition provided in Unit 1/2 Technical Specification Amendments 220/97. Changed designations for primary and alternate instruments on Tables 3.3-12, 4.3-12, 3.3-13 and 4.3-13 from "P" and "A" to "Pri" and "Alt". Clarified use of the Flow Rate Measurement Devices for the Cooling Tower Blowdown Line on Tables 3.3-12 and 4.3-12 to show that the Unit 1/2 combined instrument [FT-ICW-l01-1] is the primary and both of the individual Unit I and Unit 2 instruments [FT-ICW-101] and [2CWS-FT101] are the alternates. Updated Actions 24, 25 and 26 of Table 3.3-12 to describe use of comparable alternate monitoring channels when the primary channels are INOPERABLE. Clarified Table 3.3-13 Action 28 applicability for Unit 2 gaseous effluent monitors. Clarified Table 3.3-13 Action 30 to show that applicability is for batch purges of the reactor containments.
Changed reference of Special Report compliance requirement from Technical Specification 6.9.2f to 10 CFR 20.2203 and 10 CFR 50.4 as permitted by Unit 1/2 Technical Specification Amendments 220/97.
Clarified note b of Table 4.11-2 regarding sampling and surveillances frequencies. ClarifiedControls3.12.1 and3.12.2to ensurecompliancewith NUREG-1301.
 
.            .                        ,                      .Procedure                    Number~
Beaver Valley Power Station                                      r      e    2-ODC-1.01
 
==Title:==
Unit:        Level Of Use:
1/2        General Skill Reference ODCM: Index, Matrix and History of ODCM Changes                                  Revision:    Page Number 8.2.13.1.4      Appendix E: Made editorial changes for clarity. Changed reference of Special Report compliance requirement from Technical Specification 6.9.2f to 10 CFR 20.2203 and 10 CFR 50.4 as permitted by Unit 1/2 Technical Specification Amendments 220/97. Changed submittal date of annual REMP report from May 1 to May 15 as permitted by Unit 1/2 Technical Specification Amendments 220/97. Changed column heading in Table E: 6.9-1 to ensure consistency with NUREG-1301.
8.2.13.2    The justification used for change (13) to the ODCM is as follows:
8.2.13.2.1      All changes are considered editorial in nature. The changes either clarify the intent of the original specification or add equivalent items form the standard guidance document (NUREG-1301) or recent Technical Specification Amendments. Therefore, since these changes are considered editorial, the changes 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. Also, the editorial changes will not adversely impacttheaccuracyor reliabilityofeffluentdoseorsetpoint calculations.
8.2.14    Change (14) of BV-1 and 2 ODCM (Revision 14. Effective March 2000) 8.2.14.1    Prior to this ODCM change, the change numbers did not match the Issue and Revision numbers. For example, the last implemented ODCM change was (13),
but carried an Issue 3, Revision 6 designation. Therefore, as of this ODCM change (14), consecutive Revision numbers will begin with Revision 14.
8.2.14.2      A description of the changes that were implemented with this revision is as follows:
8.2.14.2.1      Index: Editorial changes were made for clarity. References to condition reports CR 982097,: CR 992652 and CR 993021 were added.
8.2.14.2.2      Appendix C: Editorial changes were made for clarity. Corrected a typographical error on Table 3.3-12 in regards to FT-CW-101-1. Changed the grab sampling requirement from 8 hours to 12 hours for Table 3.3-12 Action 24 (NUREG-1301, Table 3.3-12, Action 36 and 37 allow this change). Enhanced the Channel Functional Test requirements on Table 4.3-12 from Q(6) to Q(l) for RM-lDA-100 (Corrective Action to Condition Report CR 993021). Add clarification to Table 3.3-13 and 4.3-13 to show the plant specific Mark Numbers for the primary and alternate BV-1 Sample Flow Rate Measuring Devices. Corrected a typographical error on Table 3.3-13 Action 27. Separated Action 28 of Table 3.3-13 into individual Action 28 requirements for System Effluent Flow Rate Measuring Devices/Process Flowrate Monitors and individual Action 28 requirements for Sample Flow Rate Measuring Devices/Sample Flowrate Monitors.
Added clarification to Table 3.3-13 to show that Action 29 and Action 32 are
 
B V eotndure Number O      l Beaver Valley Power Station                                              1/2-ODC-1.01
 
==Title:==
Unit:        Level Of Use:
1/2        General Skdll Reference ODCM: Index, Matrix and History of ODCM Changes                                Revision:    Page Number applicable for continuous releases. Added an alternate method in lieu of grab sample collection (ie., local monitor readings can be obtained when communication is lost to the Control Room) to show compliance to Table' 3.3-13 Action 29. Changed the grab sampling requirement from 8 hours to
                            '12 hours for Table 3.3-13 Action 29 and Action 32 (NUREG-1301, Table 3.3-013, Action 47 allows this change). Corrected typographical errors on Table 4.11-1 in regards to liquid composite analysis frequency and table notation.
8.2.14.2.3      Appendix F: Made editorial changes for clarity. Updated the procedure details for primary and alternate instrumentation included in Appendix C Tables 3.3-13 and 4.3-13. Added appropriate references to the HP Shift Logs (ie., HPM Appendix 1) when these logs are used satisfy ODCM Appendix C Surveillances and Actions (Corrective Action to Condition Report CR 992652).
8.2.14.3      The justification used for change (14) to the ODCM is as follows:
8.2.14.3.1      Most of these changes are considered editorial in nature. All changes were screened for I0CFR50.59 applicability. In summary, the BVPS-1 and 2 UFSAR's are not impacted, because'the changes either clarify the intent of the original specification, add plant specific Mark Numbers, or add equivalent items from the standard guidance document (NUREG-1301).
Therefore, these changes will maintain the'level of radioactive effluent control requried by 10CFR20.1302, 40CFR Part 190, 10 CFR50.36a, and Appendix I to 10CFR50. Also, these changes will not adversely impact the accuracy or reliablity of effluent dose or alarm setpoint calculations.
8.2.15    Change (15) of BV-I and 2 ODCM (Revision 15, Effective August 2000) 8.2.15.1      A description of the changes that were implemented with this revision is as follows:
8.2.15.1.1      Index: Editorial changes were made for clarity. Reference to Condition Report CR 001682 was added. Reference to NRC unresolved Item 83-30-05 was added.
 
Beaver Valley Power Station                                      oedureNumber
 
==Title:==
Unit:      Level Of Use:
1/2    General Skill Reference ODCM: Index, Matrix and History of ODCM Changes                              Revision:  Page Number-8.2.15.1.2      Appendix C: Editorial changes were made for clarity. Annotated Actions 28 of Table 3.3-13 into Action 28A and 28B to show differentiation between Action 28A requirements for system/process flow rate measurement and Action 28B requirements for sampler flow rate measurement. Added an alternate method in lieu of 4 hour flow rate estimations (ie; assume ODCM design values for system/process flow rate) to show compliance with Table 3.3-13 Action 28A when the system/process flow rate monitor is inoperable.
Annotated Actions 30 of Table 3.3-13 into Action 30A and 30B to show differentiation between Action 30A requirements for BV-I reactor containment purges and Action 30B requirements for BV-2 reactor containment purges.
8.2.15.2    The justification used for change (15) to the ODCM is as follows:
8.2.15.2.1      Some of these changes are considered editorial in nature. These changes were screened for 10CFR50.59 applicability and determined not to impact the BVPS-1 and 2 UFSAR's. Since the editorial changes clarify the intent of the original specification, then these changes will maintain the,level of radioactive effluent control required by 10CFR20.1302, 40CFR Part 190, IOCFR50.36a, and Appendix I to 10CFR50. Also, these changes will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation.
8.2.15.2.2      The change to allow use of design (maximum) system flow rates in lieu of 4 hour flow rate estimations (for five of the eight gaseous effluent release pathways) was screened for 10CFR50.59 applicability and determined not to impact the BVPS-1 and 2 UFSAR's. The 4 hour flow rate estimations for these effluent release pathways have never been used in ODCM Dose and Dose Rate Calculations. The method for use of process flow rates in ODCM Dose and Dose Rate Calculations remains unchanged. For example, BVPS-1 and BVPS-2 is currently using, and will continue to use design (maximum) system flow rates in ODCM Dose and Dose Rate Calculations for all eight gaseous effluent release pathways. This is necessary to ensure that DLC response to NRC Unresolved Item 50-334/83-30-05 is not compromised.
Also this change is considered similar and within the justification provided for ODCM change (8) that removed all of the process flow rate operability and surveillance requirements for the other three gaseous effluent release pathways. Based on the above, these changes will maintain the level of radioactive effluent control required by 10CFR20.1302, 40CFR Part 190, 10CFR50.36a, and Appendix I to 10CFR50. Also, these changes will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation.
 
Procedure Number.
Beaver Valley Power Station                                              1/2-ODC-1.01 t
 
==Title:==
Unit:          Level Of Use:
I/2        General Skill Reference Revision:      Page Number:
ODCM: Index, Matrix and History of ODCM Changes                                                                        I -,
A -    I          17nf79 8.2.16    Change (16) of BV-1 and 2 ODCM (Effective April 2002) 8.2.16.1      A description of the changes that were implemented with this revision are as follows:
8.2.16.1.1        The entire BV-1 and 2 ODCM was converted to the ODC format as delineated in 1/2-ADM-0100. As-part of this process, the ODCM was separated into eight procedures as follows:
8.2.16.1.1. 1        1/2-ODC-1.01, Rev 0; ODCM: Index, Matrix and History of ODCM Changes (formerly, ODCM Index and Appendix F) 8.2.16.1.1. 2        1/2-ODC-2.01. Rev 0; ODCM: Liquid Effluents (formerly, ODCM Section 1 and 5) 8.2.16.1.1. 3        1/2-ODC-2.02: Rev 0; ODCM: Gaseous Effluents (formerly, ODCM Section 2 and 5) 8.2.16. 1.1. 4      1/2-ODC-2.03. Rev 0; ODCM: Radiological Environmental Monitoring Program (formerly; ODCM Section 3) 8.2.16.1.1. 5.      1/2-ODC-2.04. Rev 0; ODCM: Information Related to 40CFR190 (formerly; ODCM Section 4) 8.2.16.1.1. 6        1/2-ODC-3.01. Rev 0; ODCM: Dispersion Calculational Procedure and Source Term Inputs (fornerly, ODCM Appendix A & B) 8.2.16.1.1. 7.      1/2-ODC-3.02. Rev 0; ODCM: Bases for ODCM Controls (formerly, ODCM Appendix D) 8.2.16.1.1. 8        1/2-ODC-3.03. Rev 0; ODCM: Controls for RETS and REMP Programs (formerly; ODCM Appendix C and E)
N
                                                                                                                      -V_
I .,  .  .1                  I  . .                - .    .              .- , I
 
Procedure Number~
Beaver Valley Power Station                                            l/2-ODC-l.01
 
==Title:==
Unit:          Level Of Use:
1/2        General Skill Reference ODCM: Index, Matrix and History of ODCM Changes                        Revision:      Page Number:
1 4      -          38 of 72 8.2.16.1.2    Procedure 1/2-ODC-3.02, Rev 0: Technical Specification Bases 3/4.3.3.1 was duplicated in the Bases for ODCM Controls as permitted by Unit 1/2 Technical Specification Amendments 1A-246/2A-124.(3268) 8.2.16.1.3    Procedure 1/2-ODC-3.03, Rev 0: Portions of Technical Specification LCO 3.3.3.1 (including portions of Tables 3.3-6 and 4.3-3) were transferred to the ODCM Controls as permitted by Unit 1/2 Technical Specification Amendments IA-246/2A-124. 32 6 8 ) Specifically, this includes the Mid and High Range Channels of Noble Gas Effluent Monitors [RM-lVS-109 (7 and 9), RM-1VS-1 10 (7 and 9), RM-IGW-109 (7 and 9), and 2HVS-RQ109C and 109D], the Atmospheric Steam Dump Valve/Code Safety Relief Valve Discharge Monitors [RM-lMS-1OOA, B and C] and Auxiliary Feedwater Pump Turbine Exhaust Monitor [RM-lMS-101]. The Preplanned Method of Monitoring (PMM) was also added for clarification of necessary actions when the primary instrument is inoperable. Addition of the PMM's are considered an editorial change because it merely specifies the asset number (or appropriate form number), which were included as PMM's in previously approved station documents.
8.2.16.1.4    Procedure 1/2-ODC-3.03. Rev 0: Added clarifications to ODCM Control 3.3.3.9 Table 3.3-13 to show that Action 30A and Action 3B are applicable to the initial batch purge of the reactor containment atmosphere. All other releases of reactor containment atmosphere (i.e.; after the initial batch purge) are considered continuous releases.
8.2.16.1.5    Procedure 1/2-ODC-3.03, Rev 0: Added specific plant asset numbers to ODCM Control 3.3.3.10 Table 3.3-13 and Table 4.3-13 to show that Sample Flow Rate Monitor flow transmitters [2HVS-FITl01-l, 2RMQ-FIT301-1, 2HVL-FITI 12-1 and 2RMQFIT303-1] maybe used as comparable alternates when the primary instruments [RM-l 1 Monitor Item 28 for 2HVS-RQ101, 2RMQ-RQ301, 2HVL-RQ1 12 and 2RMQ-RQ303], respectively, are INOPERABLE. This is considered an editorial change because the primary monitoring channel (i.e.; RM-1 1 Monitor Item 28) display already receives its input from these same flow transmitters.
8.2.16.1.6    Procedure 1/2-ODC-3.03. Rev 0: Added notation to ODCM Control 3.3.3.10 Table 3.3-13 and Table 4.3-13 to show that [RM-lGW-109 Channel 5] may be used as a comparable alternate to [RM-iGW-108B] for continuous releases. However, since [RM-IGW-109 Channel 5] cannot perform an automatic isolation of gaseous waste decay or storage tank releases, then notation was also added to prevent using this monitor as a comparable alternate for batch releases. This is considered an editorial change because it merely specifies the asset number of a redundant alternate monitoring channel that was included in previously approved station documents.
 
Beaver Valley Power Station                        -e                    12-ODC-1.01
 
==Title:==
Unit:      Level Of Use:
1/2      General Skill Reference ODCM: Index, Matrix and History of ODCM Changes                                  Revision:  Page Number:
4        39 f 72-8.2.16.1.7      Procedure-1/2-ODC-3.03. Rev 0: Replaced the requirements for "Particulate Activity Monitors" in ODCM Control 3.3.3.10 Tables 3.3-13 and Table 4.3-13 with requirements for "Particulate and Iodine Samplers". This is considered an editorial change because the NRC guidance document used for preparation of ODCM Controls (NUREG-1301) contains the clarification that the requirements listed in these Tables are for the "Particulate and Iodine Samplers", and not for the "Particulate Activity Monitors".
8.2.16.2    The justification used for change (16) to the ODCM is as follows:
8.2.16.2.1      The specific radiation monitoring channels transferred to the ODCM provide alarms and indications to alert plant personnel of high radiation conditions and to assist in evaluating and trending plant effluents. The Actions applicable if the monitors are inoperable require only that area surveys be performed on a daily basis, or that explanations of inoperability be provided in an annual effluent report. The Actions do not impact or reference the operability of other systems nor do the Actions require that plant operation be terminated at any time.
8.2.16.2.2      Some of the radiation monitoring effluent monitors transferred to the ODCM provide indications used to assess selected plant parameters following an accident consistent with the recommendations of NUREG-0737. However, the monitors do not provide indication for post accident variables that have been identified as Regulatory Guide 1.97 Type A or Category I.
8.2.16.2.3      The Safety Analysis performed for the License Amendments conclude that the radiating monitoring channels transferred to the ODCM do not reduce the effectiveness of the requirements being relocated. Rather, the transferfed results in. a change in the regulatory control required for future changes made to the requirements. The requirements will continue to be implemented by the appropriate plant procedures in the same manner as before. However, future changes to the transferred requirements will be controlled in accordance with 10 CFR 50.59 instead of requiring a license amendment per 10 CFR 50.90.
8.2.16.2.4      Based on the above, these changes 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. Also, these changes will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation.
8.2.17    Change (17) of BV-I and 2 OCDM (Effective August 2002) 8.2.17.1      A description of the changes that were implemented with this revision are as follows:
 
Procedure Number:
Beaver Valley-Power Station                                                1/2-ODC-1.01
 
==Title:==
Unit          Level Of Use:
1/2        General Skill Reference ODCM: Index, Matrix and History of ODCM Changes                                Revision:    Page Number:
8.2.17.1.1        Procedure 1/2-ODC-3.03, Rev 1: Technical Specification LCO 3.11.1.4 for Liquid Storage Tank Activity Limits, and LCO 3.11.2.5, for Gas Storage
            -              Tank Activity Limits were transferred to ODCM Controls 3.11.1.4 and 3.11.2.5 respectively as permitted by Unit 1/2 Technical Specification Amendments 1A- 250/2A-130.( 32-6 9 )
8.2.17.1.1.1        As part of the preparation work for transfer of the Liquid Storage Tank Activity Limits to the ODCM, the 10 Curie Limit for these tanks was re-verified and documented in Calculation Package ERS-ATL                                    007.(3239) The results of this calculation provide tank specific activity limits to ensure that the IOCFR20 Appendix B Table 2, Col. 2 EC Limits will be maintained should an accidental release of the tank(s) contents occur. Previously, LCO 3.11.1.4 used a generic limit of 10 Curies for each of the four tanks listed. However, formal documentation for derivation of the 10 Curie value could not be located in the records storage system.
              -8.2.17.1.1.2      In addition, individual tank Activity limits were developed for the Unit 1 and 2 Refueling Water Storage Tanks (RWST's), which were also added to this ODCM Control. The Surveillance Requirements for determination of RWST Activity will not be performed once per 7 days like the other Liquid Storage Tanks, because radioactive material is not added to the RWST's on a weekly basis. Therefore, the :
surveillance for determination of (RWST's) Activity will be performed within 7 days of returning reactor cavity water (radioactive material) back to the RWST (i.e.; during a refueling outage).
8.2.17.1.2        Procedure 1/2-ODC-3.03, Rev 1: Changed the due date of the Annual Radioactive Effluent Release Report from April 1 to May 1 as permitted by Unit 1/2 Technical Specification Amendments lA-250/2A-130.( 32 6 9 )
8.2.17.1.3        Procedure 1/2-ODC-3.03. Rev 1: Changed Table 3.3-12 of Control 3.3.3.9 to correct an obvious omission of Channel Operability and Action Statement Requirements for Flow Rate Measurement Device [FR-lLW-103] on the Liquid Waste Containment Drain Line. This obvious omission is detailed in CR 02-05533.(3.2.2.12) 8.2.17.1.4        Procedure 1/2-ODC-3.03. Rev l: Made editorial changes to correct the primary asset numbers of the BVPS-2 Sample Flowrate Monitors as shown on Tables 3.3-13 and 4.3-13 of Control 3.3.3.10. These changes clarify that the primary Sampler Flowrate Monitor is the device that is used for monitoring sample flowrate through the Particulate and Iodine Sampler Flowpath, not the Particulate and Iodine Monitoring Flowpath.
8.2.17.2      The justification used for change (17) of the ODCM is as follows:
 
I Beaver Valley Power Station                                    Pe2-ODCl1l I_..OD                -10
 
==Title:==
Unit:.      Level Of Use:
1/2    General Skill Reference i Revision:  Page Number:
ODCM: Index, Matrix and History of ODCM Changes 4              41 of 72      i 8.2.17.2.1      These changes merely transfers existing storage tank activity limits from the Technical Specification to the ODCM and changes the due date for the Annual Radioactive Effluent Release Report as permitted by Unit 1/2 Technical Specification Amendments lA-250/2A-130. As part of this change, the ODCM Control for Liquid Storage Tank Activity Limits was enhanced to add ODCM Controls and Surveillance Requirements for the Unit 1 and Unit 2 RWST's. Therefore, these changes (as delineated in the Technical Specification Amendments) 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. Also, these changes will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation.
8.2.18    Change (18) ofthe BV-l and 2 ODCM (Effective October 2002).
8.2.18.1    'A description of 'the changes that were implemented with this revision are as follows:
8.2.18.1.1      Procedure 1/2-ODC-3.03. Rev 2: Added requirement for applicable station groups notification of pending ODCM changes as described in CR 09-05711 (3.2.2.13) 8.2.18.2      The justification used for change (18) of the ODCM is as follows:
8.2.18.2.1      This change is considered editorial in nature, which exempts the change from Regulatory Applicability Determination. Therefore, this change will not impact the level of radioactive effluent control required by 10CFR20.1302, 40CFR Part 190, 10CFR50.36a, and Appendix I to 10CFR50. Also this change will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation.
8.2.19    Change (19) of BV-l and 2 ODCM (Effective November 2002) 8.2.19.1      A description of the' changes that were implemented with this revision are as follows:
8.2.19.1.1      Procedure 1/2-ODC-2.01, Rev 1: Changed Table 1.1-la and 1.1-lb to add Zn-65 to the respective BV-1 and 2 Liquid Source Term as described in CR 02-06174 (CA-01, CA-13 and CA-14). For information, zinc may be added to the reactor coolant system in an effort to reduce general corrosion of primary system materials and mitigation of stress corrosion cracking. Added benefits to zinc addition involve preferential release of nickel and cobalt which, in-turn, reduces plant dose rates. Development of the specific Zn-65 Annual Release Activity is delineated in Calculation Package No. ERS-ATL-83-027.(323.l) Addition of Zn-65 to the source terms also caused changes in the Liquid Effluent Monitor Alarm Setpoints, and appropriate monitor conversion factors.
 
Procedure Number~
Beaver Valley Power Station                        -/2-ODCl.01 Titde:                                                                          Unit:        Level Of Use:
1/2      General Skill Reference ODCM: Index, Matrix and History of ODCM Changes                                Revision:    Page Numb4r 8.2.19.1.2      Procedure 1/2-ODC-2.01, Rev 1: Table 1.1-la was changed to update the remainder of the source term with annual release values derived in Stone and Webster Calculation Package No. UR(B)-160.(32 310 )
8.2.19.1.3      Procedure 1/2-ODC-2.01. Rev 1: Editorial changes were made to this procedure for update of ODCM references and to add discussion of why Liquid Waste Evaporators are no longer used at BV-1 and 2 to process liquid waste.
8.2.19.2    The justification used for change (19) of the ODCM is as follows:
8.2.19.2.1      Addition of Zn-65 to the BV-1 and 2 Liquid Source Terms, along with update of the BV-1 and 2 Liquid Source Term is considered a procedure correction, and is enveloped by the Regulatory Applicability Determination performed for BV-1 ECP-02-0410. Based on the above, these changes 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.
Also, these changes will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation.
8.2.20    Change (20) of BV-1 and 2 ODCM (Effective October 2003) 8.2.20.1      A description of the changes that were implemented with this revision are as follows:
8.2.20.1.1      Procedure 1/2-ODC-2.01. Rev 2: Changed LW System diagrams (Attachment D) to indicate the flow path for cross connect of LW between Unit 1 and Unit 2.
8.2.20.1.2      Procedure 1/2-ODC-2.02. Rev 1: Changed Table 2.1-1 to revise the source term for the Unit I Containment Vacuum Pumps as described in CR03-04830 (CA-03).
8.2.20.1.3      Procedure 1/2-ODC-3.03. Rev 3: Changed the Preplanned Method of Monitoring (PMM) in Attachment D Table 3.3-6 and Table 4.3-3.
Specifically, the 2nd PMM for the Reactor Building/SLCRS Mid & High Range Noble Gas Monitors (RM-lVS-i 10 Ch 7 & Ch 9) was changed FROM "(RM-lVS-107B)" TO '(RMIlVS-107B, orRM-lVS-110 Ch 5)".
Also, the 2nd PMM for the Auxiliary Building Ventilation System Mid &
High Range Noble Gas Monitors (RM-lVS-109 Ch 7 & Ch 9) was changed FROM "(RM-lVS-IOlB)" TO "(RM-lVS-1O1B, or RM-lVS-109 Ch 5)".
Similarly, the 2nd PMM for the Gaseous Waste/ Process Vent System Mid &
High Range Noble Gas Monitors (RM-IGW-109 Ch 7 & Ch 9) was changed FROM "(RM-1GW-108B)" TO "(RM-lGW-108B, or RM-1GW-109 Ch 5)".
8.2.20.1.4      Procedure 1/2-ODC-3.03, Rev 3: Changed Attachment J Control 3.11.1.4 to update the activity limits for the liquid storage tanks to the values specified in Calculation Package No. ERS-ATL-95-007.
 
Procedure Number:
Beaver Valley Power Station                                                1/2-ODC-1.01
 
==Title:==
Unit:        Level Of Use:
1/2        General Skill Reference ODCM: Index, Matrix and History of ODCM Changes                              Revision:    Page Numberd.
4                43 of 72 8.2.:20.1.5    Procedure 1/2-ODC-3.03. Rev 3: Changed Attachment K Table 4.11-2 to add more specific guidance for sampling of Gaseous Effluent Pathways.
Specifically, this table is generic for Unit 1 & Unit 2 Gaseous Effluent Pathways, but sampling may only need required at some of the Gaseous Effluent Pathways rather than all of the Gaseous Effluent Pathways (as could be inferred from the wording in the Table Notation). Therefore to prevent unnecessary sampling, applicability statements were added to this table to delineate which ventilation systems are affected by the note(s). Also, note (f) includes a clarification of how compliance to this requirement is achieved per response to NRC Unresolved Item 50-334/83-30-05.
8.2.20.2    The justifications used for change (20) of the ODCM are as follows:
8.2.20 .2.1    Procedure 1/2-ODC-2.01. Rev 2: Changing the diagram to show the LW cross connect between Unit 1 and Unit 2 is not a change to plant configuration, and is considered a procedure correction. Specifically, this procedure of the ODCM already describes the shared radwaste treatments system. Also, the UFSAR's describe the cross connect. Based on the abovej this 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. Also, this change will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation.
8.2.20.2.2      Procedure 1/2-ODC-2.02, Rev 1: The original source-term calculation for the GW System was based on an operating flow rate of 5 scfm for the Unit 1 containment vacuum pumps. The flow rate for the new pumps is 70 scfin.
Consequently, the source-term was revised per Calculation Package ERS-HHM-87-014 and then transcribed to this procedure. Although the new pumps represent a factor of 15 increase in flow rate, the gaseous effluent monitor alarm setpoints are unchanged. Specifically, the previous setpoints were based on a percentage of Offsite Dose Rate Limits, and those values were actually above the range of the instruments, so an on-scale value was substituted. This is also true for the re-calculated setpoints, so the same on-scale values are used. In summary, changing the source term is considered a procedure correction, and is enveloped by the Regulatory Applicability Determination performed for BV-1 ECP-02-0079. Based on the above, this 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. Also, this change will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation. . This is a Corrective Action per CR03-04830-03.
 
I      ~-I-i Beaver Valley Power Station                                    Pcu      1/2-ODC-1.01
 
==Title:==
Unit:      Level Of Use:
1/2    General Skill Reference ODCM: Index, Matrix and History of ODCM Changes                                  Revision:  Page Number A
AA4of77) st      I -L 8.2.20.2.3      Procedure 1/2-ODC-3.03, Rev 3: Changing the Preplanned Method of Monitoring (PMM) will prevent unnecessary grab sampling (ie; the 3rd PMM) when the primary channel for the Mid or High Range Noble Gas Monitor is inoperable. Specifically, IF other Noble Gas Monitoring channels are available on that effluent pathway, THEN monitoring should be assumed with those channels as the 2nd PMM. In summary, the 3rd PMM (ie; obtaining grab gas samples. every 12 hours) should only be performed as.
a last resort to a complete lack of continuous noble gas monitoring channels being available on that effluent pathway. Based on the above, this 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.
Also, this change will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation. . This is a Corrective Action per CR03-06123-01.
8.2.20.2.4      Procedure 1/2-ODC-3.03. Rev 3: Changing the activity limits for liquid storage tanks does not affect original plant accident analyses. Specifically, the original analyses were performed in accordance with NUREG-0800 SRP 15.7.3 using the best available data at that time. The updated analyses were also performed in accordance the same NUREG, but current (more accurate) data was used to determine allowable activity content in each tank. Based on the above, this 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. Also, this change will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation. This is a Corrective Action per CR03-07487-05.
8.2.20.2.5      Procedure 1/2-ODC-3.03. Rev 3: Changing Attachment K Table 4.11-2 to add more specific guidance for sampling of Gaseous Effluent Pathways is considered a simple change. Specifically, this change merely prevents unnecessary sampling of unaffected ventilation pathways. Based on the above, this 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. Also, this change will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation. This is a Corrective Action per CR03-06281-01.
8.2.21    Change (21) of BV-1 and 2 ODCM (Effective November 2004)
(
8.2.21.1      A description of the changes that were implemented with this revision are as follows:
8.2.21.1.1      Procedure 1/2-ODC-2.01. Rev 3: Changed Attachment D to correct the volume Liquid Waste Drain Tanks (2LWS-TK21A/21B) from 7,500 gal/tank to 10,000 gal/tank.
 
B r Vn                  *Procedure                    Number:
                                    .Power Station                                    1/2-ODC-1.01 TItle:                                                                      Unit          Level Of Use:
1/2        General Skill Reference ODCM: Index, Matrix and History of ODCM Changes                            Revision:        eNumber 8.2.21.1.2    Procedure 1/2-ODC-3.03. Rev 4: Changed Attachment C to implement the increased flexibility in Mode restraints that is described in LAR IA-321/2A-193 and CR03-09288-19.
8.2.21.1.3    Procedure 1/2-ODC-3.03. Rev 4: Corrected a typographical error in Attachment 0, Control 3.11.2.5 per CR03-11726-01. Specifically, the final word in Action (a) was changed from "nad" to "and".
8.2.21.1.4    Procedure 1/2-ODC-3.03. Rev 4: Revised Attachment F, (Table 3.3-13 and 4.3-13) to correct a typographical error per CR04-01643-01. Specifically, the Asset Number for the Vacuum Gauge used for measurement of sample flow (from the Alternate Sampling Device) was changed from [PI-IGW-13]
to [PI-lGW-135].
8.2.21.1.5    Procedure 1/2-ODC-3.03, Rev 4: Revised Attachment F, (Table 3.3-13 and 4.3-13) per CR04-02275-01. Specifically, clarification was provided to indicate that the "Sampler Flow Rate Monitors are the devices used for "Particulate and Iodine Sampling".
8.2.21.1.6    Procedure 1/2-ODC-3.03. Rev 4: Revised Attachment J, Control 3.11.1.4, ACTION a, to add clarification that requires specific calculation of 10 CFR Part 20 EC's when the individual tank limits are exceeded.
8.2.21.2    The justifications used for change (21) of the ODCM are as follows:
8.2.21.2.1    Procedure 1/2-ODC-2.01. Rev 3: Changing the volume of the Unit 2 Liquid Waste Tank is considered a procedure correction. SINCE this was a typographical error on the Attachment, THEN it does not impact the actual tank volume that is used in effluent release calculations and offsite dose deterninations. Therefore, this 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. Also, this change will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation.
8.2.21.2.2    Procedure 1/2-ODC-3.03, Rev 4: Changing Attachment C to implement the increased flexibility in Mode restraints (described in LAR IA-321/2A-193) is considered a simple change. SINCE the change implements guidance provided in the Technical Specifications, THEN 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. Also, this change will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation. This is a Corrective Action per CR03-09288-19.
 
Procedure Number:
Beaver Valley Power Station                                              1/2-ODC-1.01
 
==Title:==
Unit:        Level Of Usc:
1/2        General Skill Reference ODCM: Index, Matrix and History of ODCM Changes                        Revision:    Page Numbero 8.2.21.2.3    Procedure 1/2-ODC-3.03. Rev 4: The typographical error in Attachment 0, Control 3.11.2.5 is considered a procedure correction. Therefore, this 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. Also, this change will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation. This is a Corrective Action per CR03-11726-01.
8.2.21.2.4    Procedure 1/2-ODC-3.03. Rev 4: Correcting the typographical error in Attachment F, (Table 3.3-13 and 4.3-13) is considered a procedure correction. SINCE this change merely corrects an obvious error, THEN this 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 Ito 10 CFR
: 50. Also, this change will not impact the accuracy or reliability of effluent dose or alarm setpoint calculation. This is a Corrective Action per CR04-01643-01.
8.2.21.2.5    Procedure 1/2-ODC-3.03. Rev 4:. Providing clarification for the Sampler Flow Rate Monitors is considered a simple change, because it was possible to misinterpret which filter paper sampler (e.g.; moving filter or fixed filter) the specification was referring to. SINCE'no changes were made to actual samplers used for effluent release calculations or offsite dose determinations, THEN this 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. Also, this change will not impact the accuracy or
                    -reliability of effluent dose or alarm setpoint calculation. This is a Corrective Action per CR04-02275-01.
8.2.21.2.6    Procedure 1/2-ODC-3.03. Rev 4: Providing clarification that requires calculation of 10 CFR Part 20 EC's (when the individual tank limits are exceeded) is considered a simple change. Specifically, the individual tank limits were derived from an assumed source-term and may not be representative of the actual source term at time of sample. This clarification also insures that a "Special Report" is submitted only when the limits (i.e.;
when calculated using actual sample analysis) are exceeded at the nearest surface water supply and the nearest potable water supply in the unrestricted area. Per Calculation Package No. ERS-ATL-95-007,( 32 39) the nearest surface water supply and the nearest potable water supply are considered to be the entrance to the Midland Water Treatment Facility. SINCE no changes were made to the bases for the tank activity limits, THEN this 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.
Also, this change will not impact the accuracy or reliability of effluent dose -
or alarm setpoint calculation.                                                            I
                                                - END -
 
Procedure Number:
Beaver Valley Power Station                                      1l/2-ODC-1.01
 
==Title:==
Unit:        j    Of Use:
1/2        General MO Reference ODCM: Index, Matrix and History of ODCM Changes                    Revision:    Pe          of 7?
ATTACHMENT A Page 1 of 6 LIST OF ODCM TABLES LIQUID EFFLUENTS Included in Procedure 1/2-ODC-2.01 1.1-la    BV-1 Liquid Source Term 1.1-lb    BV-2 Liquid Source Term 1.2-la    BV-1 Recirculation Times Required Before Sampling Of Liquid Discharge Tanks 1.2-lb    BV-2 Recirculation Times Required Before Sampling Of Liquid Discharge Tanks 1.3-1      Ai, Values For An Adult For The Beaver Valley Site GASEOUS EFFLUENTS Included in Procedure 1/2-ODC-2.02 2.1-la    BV-I Radionuclide Mix For Gaseous Effluents 2.1-lb    BV-2 Radionuclide Mix For Gaseous Effluents
      .-2a BV-1 Monitor Detector Efficiencies 2.1-2b    BV-2 Monitor Detector Efficiencies 2.2-1      Modes Of Gaseous Release From Beaver Valley Site Vents For Implementation Of 10 CFR 20 And 10 CFR 50 2.2-2a      BV-1 Radionuclide Mix For Gaseous Effluents 2.2-2b      BV-2 Radionuclide Mix For Gaseous Effluents 2.2-3      Distances Of Limiting Maximum Individual Receptors To Release Points For Annual %/Q Values ANNUAL AVERAGE XIQ Included in Procedure 1/2-ODC-2.02 2.2-4      BV-1 And 2 Containment Vents (Ground Release) 2.2-5      BV-1 And 2 Ventilation Vents (Ground Release) 2.2-6      BV-1 And 2 Process Vent (Elevated Release) 2.2-7      BV-1 And 2 Turbine Building Vents (Ground Release) 2.2-8      BV-2 Decontamination Building Vent (Ground Release)
 
Beaver Valley Power Station                              ProcedureNu2-ODC-1.01
 
==Title:==
Unit:      Level Of Use:
1/2  General Skill Reference ODCM: Index, Matrix and History of ODCM Changes                    Revision:  Page Number:
ATTACHMENT A Page 2 of 6 LIST OF ODCM TABLES 2.2-9    BV-2 Waste Gas Storage Vault Vent (Ground Release) 2.2-10  BV-2 Condensate Polishing Building (Ground Release)
NOBLE GAS DOSE FACTORS AND DOSE PARAMETERS Included in 1/2-ODC-2.02 2.2-11  Dose Factors For Noble Gases And Daughters 2.2-12  Dose Parameters For Finite Elevated Plumes, Beaver Valley Site P&I DOSE PARAMETERS Included in 1/2-ODC-2:02 2.2-13  Pir Values For A Child For The Beaver Valley Site MODES OF GASEOUS RELEASES Included in Procedure 1/2-ODC-2.02 2.3-1  Modes Of Gaseous Release Form The Beaver Valley Site Vents For Implementation Of 10 CFR 20 And 10 CFR 50 P&I ORGAN DOSE FACTORS Included in 1/2-ODC-2.02 2.3-2  R Values for Inhalation - Adult 2.3-3  R Values for Inhalation - Teen 2.3-4  R Values for Inhalation - Child 2.3-5  R Values for Inhalation - Infant 2.3-6  R Values for Ground 2.3-7  R Values for Vegetation - Adult 2.3-8  R Values for Vegetation - Teen 2.3-9  R Values for Vegetation - Child 2.3-10  R Values for Meat - Adult 2.3-11  R Values for Meat - Teen 2.3-12  R Values for Meat - Child 2.3-13  R Values for Cow Milk - Adult 2.3-14  R Values for Cow Milk - Teen
 
                                                                                                      ---  -IL ea                            .      -wt-. Procedure Numb<:r-B eaver Valley      Power Station                      I            1/2-ODC-1.01
 
==Title:==
Unit:        Level Of Use:
1/2        General Skill Reference ODCM: Index, Matrix and History of ODCM Changes.                    Revision:    Pg Nube ATTACHMENT A Page 3 of 6 LIST OF ODCM TABLES 2.3-15    R Values for Cow Milk - Child 2.3-16    R Values for Cow Milk - Infant 2.3-17    R Values for Goat Milk - Adult 2.3-8    R Values for Goat Milk - Teen 2.3-19    R Values for Goat Milk - Child 2.3-20    R Values for Goat Milk: Infant CONTINUOUS RELEASE DEPOSITION PARAMETERS (0-5 Miles)1rickxiedinPrcede 1/2-ODC-202 2.3-21    BV-l And 2 Process Vent (Elevated Release)-
2.3-22    BV-1 And 2 Containment Vents (Ground Release) 2.3-23    BV-1 And 2 Ventilation Vents (Ground Release) 2.3-24    BV-l And 2 Turbine Building Vents (Ground Release)'
2.3-25    BV-2 Condensate Polishing Building (Ground Release) 2.3-26  BV-2 Decontamination Building Vent (Ground Release) 2.3-27    BV-2 Waste Gas Storage Vault Vent (Ground Release)
CONTINUOUS RELEASE DEPOSITION PARAMETERS (SPECIAL DISTANCES) Included in Procedure 1/2-ODC-2.02 2.3-28  BV-1 And 2 Process Vent (Elevated Release) 2.3-29  BV-1 And 2 Containment Vents (Ground Release) 2.3-30  BV-1 And 2 Ventilation Vents (Ground Release) 2.3-31  BV-1 And 2 Turbine Building Vents (Ground Release) 2.3-32  BV-2 Condensate Polishing Building (Ground Release) 2.3-33  BV-2 Decontamination'Building Vent (Ground Release) 2.3-34  BV-2 Waste Gas Storage Vault Vent (Ground Release)
 
Beaver Valley Power Station                              Procedure Nub 2  ODC
 
==Title:==
Unit:        Level Of Use:
1/2      General Skill Reference ODCM: Index, Matrix and History of ODCM Changes                    Revision:    Page Number:
ATTACHMENT A Page 4 of 6 LIST OF ODCM TABLES BATCH RELEASE DISPERSION PARAMETERS (Special Distances) Included in Procedure 1/2-ODC-2.02 2.3-35    BV-1 And 2 Containment Vents (Ground Release) 2.3-36    BV-1 And 2 Ventilation Vents (Ground Release) 2.3-37    BV-I And 2 Process Vent (Elevated Release)
BATCH RELEASE DISPERSION PARAMETERS (0-5 Miles) Included in Procedure 1/2-ODC-2.02 2.3-38    BV-1 And 2 Process Vent (Elevated Release)
ENVIRONMENTAL MONITORING Included in Procedure 1/2-ODC-2.03 3.0-1    Radiological Environmental Monitoring Program DISPERSION CALCULATION Included in Procedure 1/2-ODC-3.01 A:1      BV-1 And 2 Release Conditions INPUTS TO COMPUTER CODES Included in Procedure 1/2-ODC-3.01 B:la      Inputs To GALE Code For Generation Of BV-1 Liquid Source Term Mixes B:lb      Inputs To SWEC LIQ1BB Code For Generation Of BV-2 Liquid Source Term Mixes B:2a      Inputs To SWEC GASIBB Code For Generation Of BY-i Gaseous Source TermMixes B:2b      Inputs To SWEC GAS 1BB Code For Generation of BV-2 Gaseous Source Term Mixes ODCM CONTROLS Included in Procedure 1/2-ODC-3.03 C: 1.1    Operational Modes C:1.2    Frequency Notation C:3.3-6  Radiation Monitoring Instrumentation C:4.3-3  Radiation Monitoring Instrumentation Surveillance Requirements C:3.3-12  Radioactive Liquid Effluent Monitoring Instrumentation C:4.3-12  Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements C:3.3-13 Radioactive Gaseous Effluent Monitoring Instrumentation
 
Beaver Valley Power Station                -          1 Pr2edureNuibODC
 
==Title:==
Unit:        Level Of Use:
1/2      General Skill Reference ODCM: Index, Matrix and History of ODCM Changes                      Revision:    Page Number ATTACHMENT A Page 5 of 6 LIST OF ODCM TABLES C:4.3-13  Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements C:4.11-1  Radioactive Liquid Waste Sampling And Analysis Program C:4.11-2  Radioactive Gaseous Waste Sampling And Analysis Program C:3.12-1  Radiological Environmental Monitoring Program C:3.12-2 Reporting Levels For Radioactivity Concentrations In Environmental Samples C:4.12-1 Maximum Values For The Lower Limits Of Detection (LLD)
FORMAT FOR ANNUAL REPORT Included in Procedure 1/2-ODC-3.03 E:6.9-1  Environmental Radiological Monitoring Program Summary ODCM CONTROLS PROCEDURE MATRIX Included in Procedure 1/2-ODC-1.01 F:la    BV-1 Radiation Monitoring Instrumentation Surveillance F:lb    BV-2 Radiation Monitoring Instrumentation Surveillance F:2a    BV-1 Liquid Effluent Monitor Surveillances F:2b    BV-2 Liquid Effluent Monitor Surveillances F:3a    BV-I Gaseous Effluent Monitor Surveillances F:3b    BV-2 Gaseous Effluent Monitor Surveillances F:4      BV-1 and 2 Liquid Effluent Concentration Surveillances F:5      BV-1 and 2 Liquid Effluent Dose Surveillances F:6      BV-1 and 2 Liquid Effluent Treatment Surveillances F:7      BV-I and 2 Liquid Storage Tank Activity Limit Surveillances F:8      BV-1 and 2 Gaseous Effluent Dose Surveillances F:9      BV-I and 2 Gaseous Effluent Air Dose Surveillances F:10    BV-I and 2 Gaseous Effluent Particulate and Iodine Dose Surveillances F:1      BV-1 and 2 Gaseous Effluent Treatment Surveillances
 
Beaver Valley Power Station                            Pcedure Nu      DC101
 
==Title:==
Unit:      Level Of Use:
1/2    General Skill Reference ODCM: Index, Matrix and History of ODCM Changes                  Revision:  Page Number:
ATTACHMENT A Page 6 of 6 LIST OF ODCM TABLES F: 12a  BV-I Gaseous Storage Tank Activity Limit Surveillances F:12a    BV-2 Gaseous Storage Tank ActivityLimit Surveillances F:13    BV-1 and 2 Total Dose Surveillances F:14    BV-1 and 2 REMP Surveillances F: 15    BV-1 and 2 Land Use Census Surveillances F:16    BV-1 and 2 Interlaboratory Comparison Program
 
Beaver Valley PoWer Station                            IPoedure ODC-1.0.Number.
: i. 1/.    ,D_    A._1
 
==Title:==
Unit:            Level Of Use:              .
1/2          General Skill Reference ..
Revision:        Page Number:
ODCM: Index, Matrix and History of ODCM Changes 4                  53 of 79*X ATTACHMENT B Page 1 of 1 LIST OF ODCM FIGURES LIOUID EFFLUENTS Included in Procedure 1/2-ODC-2.01 1.4-1  BV-1 Liquid Radwaste System 1.4-2  BV-2 Liquid Radwaste System 1.4-3  BV-I and 2 Liquid Effluent Release Points 5-1      Site Boundary For Liquid Effluents GASEOUS EFFLUENTS Included in Procedure 1/2-ODC-2.02 2.4-1    BV-1 and 2 Gaseous Radwaste System 2.4-2    BV-1 and 2. Gaseous Effluent Release Points 5-1      Site Boundary For Gaseous Effluents RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Included in Procedure 1/2-.
ODC-2.03 3.0-1    Air Sampling Locations 3.0-2    TLD Locations 3.0-3    Shoreline Sediment, Surface Water, And Drinking Water Sampling Locations 3.0-4    Milk Sampling Locations 3.0-5    Foodcrop Sampling Locations 3.0-6    Fish Sampling Locations 1-I  --1
 
Procedure Number:
Beaver Valley Power Station                                                    1/2-ODC-1.01
 
==Title:==
Unit:        Level Of.Use:
1/2      General Skill Reference ODCM: Index, Matrix and History of ODCM Changes                                    Revision:    Page Number ATTACHMENT C
                                                        - Page lofl9 ODCM CONTROLS PROCEDURE MATRIX BV-1 RADIATION MONITORING INSTRUMENTION SURVEILLANCES TABLE F:Ra ODCM Control 3.3.3.1: Radiation Monitoring Channels In 112-ODC-3.03, Table 3.3-6 OPERABLE APPLICABILITY: Modes    I  thru 4 ODCM SR                  DESCRIPTION                                      PROCEDURE 4.3.3.1      Test Monitors at Table 4.3-3 Frequency' 4.3.3.1.1    Noble Gas Effluent Monitors -          NOTE: Actions for INOPERABLE Monitors are documented SPINGS                                in the Operations Shift Logs, and the RP Shift Logs.
4.3.3.1.1.a  Supplementary Leak Collection and      1MSP-43.59-1: Channel Calibration Release System                          1OM-54.3 L5 Log Item 205: Channel Check (RM-1VS-1I10 CH7 & CH9)                IOST-43.07: Channel Functional Test 4.3.3.1.1.b  Auxiliary Building Ventilation System  IMSP-43.60-1: Channel Calibration (RM-1VS-109 CH7 & CH9)                  1OM-54.3 L5 Log Item 204: Channel Check 1OST-43.07: Channel Functional Test 4.3.3.1.1.c  Process Vent System (RM-1GW-109        IMSP-43.58-l: Channel Calibration CH7 & 9)                                IOM-54.3 L5 Log Item 206: Channel Check I OST-43.07: Channel Functional Test 4.3.3.1.2    Noble Gas Steam Effluent                NOTE: Actions for INOPERABLE Monitors are documented Monitors                              In the Operations Shift Logs, and the RP Shift Logs.
4.3.3.1.2.ci  Atmospheric Steam Dump Valve and        I MSP-43.62-1: RM-1 MS-1 O0A Channel Calibration v.1.2a        Code Safety Valve Discharge            1MSP-43.63-l: RM-1 MS-1 00B Channel Calibration (RM-1 MS-1 OOA, B, C)                  IMSP-43.64-1: RM-1 MS-1 00C Channel Calibration IOM-54.3 L5 Log Item 078: RM-1 MS-1 OOA Channel Check IOM-54.3 L5 Log tem 079: RM-1 MS-1 OOB Channel Check IOM-54.3 L5 Log Item 103: RM-1 MS-1 00C Channel Check 1OST-43.05: Channel Functional Test 4.3.3.1.2.b  Auxiliary Feedwater Pump Turbine        IMSP-43.65-l: Channel Calibration Exhaust (RM-1MS-101)                    IOM-54.3 L5 Log Item 104: Channel Check I OST-43.05: Channel Functional Test
 
Beaver Valley Power Station                                                    1/2edure 11 Nui-ODC-                      l
 
==Title:==
Unit:        Level Of Use:
1/2      General Skill Reference ODCM: Index, Matrix and History of ODCM Changes                                    Revision:    Page Number                -I
_  _  _  __ _of__                  _      _72                4__
ATTACHMENT C Page 2of 19 ODCM CONTROLS PROCEDURE MATRIX BV-2 RADIATION MONITORING INSTRUMENTION SURVEILLANCES TABLE F:Ib ODCM Control 3.3.3.1: Radiation Monitoring Channels In 1/2-ODC-3.03, Table 3.3-6 OPERABLE APPLICABILITY: Modes 1 thru 4 ODCM SR                DESCRIPTION                                        PROCEDURE 4.3.3.1    Test Monitors at Table 4.3-3 Frequency 4.3.3.1.1  Noble Gas Effluent Monitors            NOTE: Actions for INOPERABLE Monitors are documented in the Operations Shift Logs, and the RP Shift Logs.
4.3.3.1.2. Supplementary Leak Collection and      2MSP-43.33-l: Channel Calibration c.i.1.1.a  Release System (2HVS-RQ109C & D)        20M-54.3 Log L5 Log Item 133: Channel Check 20ST-43.08: Channel Functional Test K
* PN
 
Beaver Valley Power Station                                                Procedure Nub 2 er:ODC
 
==Title:==
Unit:        Level Of Use:
1/2      General Skill Reference ODCM: Index, Matrix and History of ODCM Changes                                            Revision:      Page Number:
4                56 of 72 ATTACHMENT C Page 3 of 19 ODCM CONTROLS PROCEDURE MATRIX BV-1 LIQUID EFFLUENT MONITOR SURVEILLANCES TABLE F:2a ODCM Control 3.3.3.9: Liquid Effluent Monitors In 1/2-ODC-3.03, Table 3.3-12 OPERABLE APPLICABILITY: During Releases Through The Flow Path ODCM SR                  DESCRIPTION                                              PROCEDURE 4.3.3.9      Test Monitors at Table 4.3-12 Frequency 4.3.3.9.1    Monitors Providing Alarm and              NOTE: Actions for INOPERABLE monitors are documented In the Automatic Termination                      Operations Shift Logs, and the RP Shift Logs.
4.3.3.9.1.a  Liquid Radwaste Effluent Line              lMSP-43.18-I: Channel Calibration (RM-1LW-104)                              IOM-54.3 L5 Log: Channel Check 1/20M-17.4A.D: Source Check 1OST-43.09: Channel Functional Test 112-ADM-1611.F03: Channel Check (Back-up) 4.3.3.9.1.b  Uquid Waste Contaminated Drain Une        'IMSP-43.23-l: Channel Calibration (RM-1 LW-1 16)                            IOM-54.3 L5 Log: Channel Check 1/20M-17.4A.D: Source Check IOST-43.09: Channel Functional Test 112-ADM-1611.F03: Channel Check (Back-up) 4.3.3.9.1.c  Auxiliary Feed Pump Bay Drain Monitor      IMSP-43.70-1: Channel Calibration (RM-1DA-100)                              10M-54.3 L5 Log: Channel Check 1OM-54.3 L5 Log: Source Check IOST-43.09: Channel Functional Test 112-ADM-161 1.F03: Channel Check (Back-up) 4.3.3.9.2    Monitors Providing Alarm, but Not          NOTE: Actions for INOPERABLE monitors are documented In the Prividing Auto Termination                Operations Shift Logs, and the RP Shift Logs.
4.3.3.9.2.a  Component Cooling - Recirculation          1MSP-43.1 0-l: Channel Calibration Spray Hx River Water-Monitor              IOM-54.3 L5 Log: Channel Check (RM-1RW-I00)                              1OST-43.09: Channel Functional Test IOST-43.09A: Source Check 112-ADM-1611.F03: Channel Check (Back-up) 4.3.3.9.3    Flow Rate Measurement Devices              NOTE: Actions for INOPERABLE monitors are documented in the Operations Shift Logs, 1/2-HPP-3.06.005, and the RP Shift Logs 4.3.3.9.3ab  Liquid Radwaste Effluent Lines            1MSP-17.05-1: Channel Calibration (3b) 3a: (FR-1LW-104 for RM-ILW-104)            IMSP-17.06-1: F-LW-104-1 Channel Calibration (3a) 3b: (FR-ILW-103 for RM-1LW-116)            IMSP-17.07-I: F-LW-104-2 Channel Calibration (3a) 1MSP-1 7.08-I: F-LW-1 04-1 Channel Functional Test (3a) lMSP-17.09-l: F-LW-104-2 Channel Functional Test (3a) 1(MSP-17.10-l: F-LW-I03 Channel Functional Test (3b) 10M-54.3 L5 Log: FR-LW-103 Channel Check (3b) 1OM-54.3 L5 Log: FR-LW-104-1 Channel Check (3a) 1OM-54.3 L5 Log: FR-LW-104-2 Channel Check (3a) 4.3.3.9.3.c  Cooling Tine Tower Blowdown                        1MSP-31.04-i: F-CW-1o01 Channel Calibration (FT-iCW-101) SIMSP-31.05-l:                                FL-W-101 Channel Functional Test (FT-lCW-101-1)fMSP-31.0-1:                                F-CW-101-1 Channel Calibration 1MSP-31.07-1: F-CW-101-1 Channel Functional Test 15M-54.3L5 L-og: FT-1Ch01 Channel Check 1OM-54.3 L5 Log: FT-CW-101-1 Channel Check 4.3.3.9.4    Tank Level Indicating Devices              NOTE: Actions for INOPERABLE monitors are documented In the Operations Shift Logss 4.3.3.9.4.a  Primary Water Storage Tank                  IMSP-8.01-l: L-PG115A Channel Functional Test (LI-1PG-115A for 1BR-TK-6A)                1MSP-8.03-1: L-PG115A Channel Calibration 1OM-54.3 L5 Log: Channel Check (When Adding to Tank) 4.3.3.9.4.b  Primary Water Storage Tank                  1MSP-8.02-1: L-PG-1 15B Channel Functional Test (Ll-1 PGA 15B for I BR-TK-6B)              IMSP-8.04-1: L-PG-1 15B Channel Calibration 1OM-54.3 L5 Log: Channel Check (When Adding to Tank) 4.3.3.9.4.c  Steam Generator Drain Tank                  I1MSP-17.01-l: L-LW110 Channel Functional Test (LI-1LW-110 for 1LW-TK-7A)                  IMSP-17.03-l: L-LW110 Channel Calibration 1OM-54.3 L5 Log: Channel Check (When Adding to Tank) 4.3.3.9.4.d  Steam Generator Drain Tank                  IMSP-17.02-l: L-LW111 Channel Functional Test (Ll-1 LWAI I for 1LW-TK-7B)                1MSP-1 7.04-1: L-LW1 11 Channel Calibration I1 OM-54.3 L5 Log: Channel Check (When Adding to Tank)
 
==Title:==
Beaver Valley Power Staton                                          'tProcedure Number 1/2-ODC-1.01    . . '
Unit:          Level I    Of Use:
I1/2        General Skill Reference .1 Revision:      Page Number:
ODCM: index, Matrix and History of ODCM Changes 4      1          57 of 72 ATTACHMENT C Page 4 of 19 ODCM CONTROLS PROCEDURE MATRIX BV-2 LIQUID EFFLUENT MONITOR SURVEILLANCES TABLE F:2b ODCM Control 3.3.3.9: Liquid Effluent Monitors In 1/2-ODC-3.03 Table 3.3-12 OPERABLE APPLICABILITY: During Releases Through The Flow Paths ODCM SR                DESCRIPTION                                            PROCEDURE 4.3.3.9      Test Monitors at Table 4.3-12 Frequency 4.3.3.9.1    Monitors Providing Alarm and            NOTE: Actions for INOPERABLE monitors are documented Automatic Termination                    In the Operations Shift Logs, and the RP Shift Logs.
4.3.3.9.1.a  Liquid Waste Process Effluent            1/2-ADM-1611.F04: Channel Check tBack-up)
Monitor :                                1/2-HPP-3.06.005.FO1: Source Check I                  (2SGC-RQ100)                            2MSP-43.39-l: Channel Calibration 1/20M-17.4A.C: Source Check 20M-54.3 L5 Log: Channel Check 20M-25.4.L: Source Check 20M-25.4.N: Source Check 20ST-43.03: Channel Functional Test 4.3.3.9.2    Flow Rate Measurement Devices            NOTE: Actions for INOPERABLE monitors are documented in the Operations Logs, 1/2-HPP-3.06.005, and the RP Shift Logs.
4.3.3.9.2.a  Liquid Radwaste Effluent                2MSP-25.01-l: 2SGC-P26A,B Ch Cal &Ch Functional Test (2SGC-FIS100)                        ;  2MSP-43.39-l: Channel Calibration 20M-54.3 L5 Log L5: Channel Check 4.3.3.9.2.b  Cooling Tower Blowdown Line              2MSP-31.04-l: Channel Calibration.
(2CWS-FT101)                            2MSP-31.05-I: Channel Functional Test 20M-54.3 L5 Log: Channel Check
 
Procedure Number:
yPower Station                                          1/2-ODC-1.01
 
==Title:==
Unit:        Level Of Use:
1/2      General Skill Reference ODCM: Index, Matrix and History of ODCM Changes                                          Resion:      Page Number:
ATTACHMENT C Page 5 of 19 ODCM CONTROLS PROCEDURE MATRIX BY-1 GASEOUS EFFLUENT MONITOR SURVEILLANCES TABLE F:3a ODCM Control 3.3.3.10: Gaseous Effluent Monitors In 112-ODC-3.03 Table 3.3-13 OPERABLE APPLICABILITY: During Releases Through The Flow Paths ODCM SR                  DESCRIPTION                                            PROCEDURE 4.3.3.10      Test Monitors at Table 4.3-13 Frequency 4.3.3.10.1    Gaseous Waste I Process Vent              NOTE: Actions for INOPERABLE monitors are documented System                                    In the Operations Shift Logs, 112-HPP-3.06.006, and the RP
        .        _          ._                          :Shift  Logs.
4.3.3.10.1.a  Noble Gas Activity Monitor                IMSP-43.22-l: Channel Calibration Pri: (RM-1GW-108B)                        IOM-19.4.E, H: Channel Check Alt (RM-1GW-109 Ch 5): for                1OM-19.4.E, H: Source Check continuous releases only, not      1/2-OM-19.4A.D: Source Check an alternate for batch releases    1/2-OM-19.4A.D: Channel Check I OM-54.3 L5 Log: RM-iGW-108B Channel Check I OM-54.3 L5 Log: RM-IGW-109 Channel Check I OST-43.09: Channel Functional Test 112-ADM-1611.F03: Channel Check (Back-up) 4.3.3.10.1.b  Particulate & Iodine Sampler              112-ADM-1611.F03: Channel Check Pri: Filter Paper and Charcoal Cartridge for (RM-1GW-1 09)
Alt: Filter Paper and Charcoal Cartidde for (RM-1 GW-1I10) 4.3.3.10.1.c  System Effluent Flow Rate                I MSP-1 9.05-I: Channel Functional Test Measuring Device                          I MSP-1 9.06-I: Channel Calibration Pri: (FR-IGW-108)                        1OM-54.3 L5 Log: Channel Check Alt: (RM-IGW-109 Ch 10)                  1/2-ADM-1611.F03: Channel Check (Back-up) 4.3.3.10.i.d  Sampler Flow Rate Measuring              1MSP-43.21-I: Channel Calibration Device                                    I MSP-43.71 -I: Channel Functional Test (Rotometer)
Pet: (RM-1GW-109 Ch 15)          -          OM 54.3 L5 Log L5: Channel Check Alt: (Rotometer FM-IGW-101 and            10ST-43.07: Channel Functional Test Vacuum Gauge: PI-1GW-135            I OST-43.11: Channel Functional Test
                      - for RM-1 GW-110)                    112-ADM-161 1.F03: Channel Check (Back-up) 4.3.3.10.2    Auxiliary Building Ventilation            NOTE: Actions for INOPERABLE monitors are documented System (Ventilation Vent)                In the Operations Shift Logs, 1/2-HPP-3.06.006, and RP Shift Logs.
4.3.3.10.2.a  Noble Gas Activity Monitor                IMSP-43.13-l: Channel Calibration Pri: (RM-1VS-101B)                        1OM-54.3 L5 Log: RM-1VS-101B Channel Check Alt: (RM-1VS-109 Ch 5)                    IOM-54.3 L5 Log: RM-IVS-109 Channel Check
                                                        .OST-43.07A:
I              RM-1 VS-1 09 Channel Functional Test IOST-43.09: Channel Functional Test I OST-43.09A: Source Check 1/2-ADM-1611.F03: Channel Check (Back-up) 4.3.3.10.2.b  Particulate & Iodine Sampler              1/2-ADM-1611.F03; Channel Check Pri: Filter Paper and Charcoal Cartridge for (RM-IVS-109)
Alt: Filter Paper and Charcoal Cartridge for (RM-IVS-1 I 1) 4.3.3.10.2.c  System Effluent Flow Rate                IMSP-44.07-l: Channel Functional Test Measuring Device                          1MSP44.08-l: Channel Calibration PA: (FR-iVS-101)                          IOM-54.3 L5 Log: Channel Check Alt: (RM-IVS-109 Ch 10)                  1/2-ADM-161 1.F03: Channel Check (Back-up)
 
                                                                                                                              -U-
                                    . _ . r ,        <a      .              .      Prcedure Numbw.
                .Beaver Valley          beave  Power Station              va.1/2-ODC-1.01 PoeueNiO~~
 
==Title:==
Unit:        Level Of Use:
1/2      General Skill Reference ODCM: Index, Matrix and History of ODCM Changes                                        Revision:    Page Number 4              59 of 72 ATTACHMENT C Page 6 of 19 ODCM CONTROLS PROCEDURE MATRIX BV-I GASEOUS EFFLUENT MONITOR SURVEILLANCES Continued TABLE F:3a ODCM Control 3.3.3.10: Gaseous Effluent Monitors In 1/2-ODC-3.03 Table 3.3-13 OPERABLE APPLICABILITY: During Releases Through The Flow Paths ODCM SR                  DESCRIPTION                                          PROCEDURE 4.3.3.10.2.d  'Sampler Flow Rate Measuring              1MSP-44.07-l: Channel Functional Test Device                  -              1MSP-44.08-l: Channel Calibration Pri: (RM-IVS-109 Ch 15)                  1OM 54.03 L5 Log: Channel Check Alt: (Rotometer FM-IVS-102 and          IOST-43.07: Channel Functional Test Vacuum Gauge: P1-iVS-659            IOST-43.11: Channel Functional Test for RM-I VS-1)                      1/2-ADM-161 1.F03: Channel Check (Back-up) 4.3.3.10.3      Rx Containment I SLCRS                  NOTE: Actions for INOPERABLE monitors are documented (Elevated Release)                      in the Operations Shift Logs, 112-HPP-3.06.006, and the RP Shift Logs.
4.3.3.10.3.a    Noble Gas Activity Monitor              IMSP-43.20-l: Channel Calibration Pri: (RM-IVS-107B)                      IOM-54.3 L5 Log: RM-1VS-107B Channel Check Alt: (RM-1VS-110 Ch 5)                  1OM-54.3 L5 Log: RM-IVS-1IO Channel Check IOST-43.07A: RM-1VS-110 Channel Functional Test 10ST-43.09: Channel Functional Test 1OST-43.09A: Source Check                                        I.
1/2-ADM-1611.F03: Channel Check (Back-up) 4.3.3.10.3.b    Particulate & Iodine Sampler            1/2-ADM-1611.F03: Channel Check Pri: Filter Paper and Charcoal Cartridge for (RM-1VS-1 10)
Alt: Filter Paper and Charcoal Cartridge for (RM-1VS-112) 4.3.3.10.3.c    System Effluent Flow Rate                1MSP-44.09-l: Channel Calibration Measuring Device                        I MSP-44.10-l: Channel Functional Test Pri: (FR-IVS-112)                        IOM-54.3 L5 Log: Channel Check Alt (RM-1VS-l10 Ch 10)                  1/2-ADM-1611.F03: Channel Check (Back-up) 4.3.3.10.3.d    Sampler Flow Rate Measuring            1MSP-43.19-l: Channel Calibration Device                                  1MSP-43.72-l: Channel Functional Test (Rotometer)
Pri: (RM-1VS-1l0 Ch 15)                lOM 54.3 L5 Log: Channel Check Alt: (Rotometer FM-iVS-103 and          10ST-43.07: Channel Functional Test Vacuum Gauge: P1-IVS-660          1OST-43.1 1: Channel Functional Test for RM-IVS-112)                    1/2-ADM-1611.F03: Channel Check (Back-up)
 
Beaver Valley Power Station                                                1/2-ODC-P.Or
 
==Title:==
Unit:        Level Of Use:
1/2      General Skill Reference ODCM: Index, Matrix and History of ODCM Changes                                    Revision:    Page Number:
ATTACHMENT C Page 7 of 19 ODCM CONTROLS PROCEDURE MATRIX BV-2 GASEOUS EFFLUENT MONITOR SURVEILLANCES Continued TABLE F:3b ODCM Control 3.3.3.10: Gaseous Effluent Monitors In 1/2-ODC-3.03 Table 3.3-13 OPERABLE APPLICABILITY: During Releases Through The Flow Paths ODCM SR                DESCRIPTION                                      PROCEDURE 4.3.3.10      Test Monitors at Table 4.3-13 Frequency 4.3.3.10.1    SLCRS Unfiltered Pathway            NOTE: Actions for INOPERABLE monitors are documented (Ventilation Vent)                  In the Operations Shift Logs, 1/2-HPP-3.06.006, and the RP
. .                                                      Shift Logs.
4.3.3.10.1.a  Noble Gas Activity Monitor          2MSP-43.36-l: Channel Calibration Pri: (2HVS-RQ101B)                  20M-54.3 L5 Log: Channel Check 20ST-43.09: Channel Functional Test 112-ADM-161 1.F04: Channel Check (Back-up) 2-HPP-4.02.018: Source Check (DRMS Auto Function) 4.3.3.10.1.b  Particulate & Iodine Sampler        1/2-ADM-1611.F04: Channel Check Pri: Filter Paper and Charcoal Cartridge for (2HVS-RQI01A) 4.3.3.10.1.c  Process Flow Rate Monitor          2MSP-43.36-l: Channel Calibration Pri: (Monitor Item 29 for 2HVS-    2MSP-43.36A-I: Channel Functional Test VP101)                              Work Request: Channel Calibration (Velocity Probe) 20M-54.3 L5 Log: Channel Check 1/2-ADM-1 611 .F04: Channel Check (Back-up) 4.3.3.10.1.d  Sampler Flow Rate Monitor          2MSP-43.36-1: Channel Calibration Pri: (2HVS-FIT101-1)              - 2MSP-43.36A-1: Channel Functional Test 20M-54.3 L5 Log: Channel Check 112-ADM-1 611.F04: Channel Check (Back-up) 4.3.3.10.2    SLCRS Filtered Pathway              NOTE: Actions for INOPERABLE monitors are documented (Elevated Release)                  in the Operations Shift Logs, 112-HPP-3.06.006, and the RP Shift Logs.
4.3.3.10.2.a  Noble Gas Activity Monitor          2MSP-43.32-1: 2HVS-RQ109A Channel Calibration Pri: (2HVS-RQ109B)                  2MSP43.33-l: 2HVS-RQ109BC,D Channel Calibration 20M-54.3 L5 Log: Channel Check 20ST43.08: Channel Functional Test 112-ADM-1 61 1.F04: Channel Check (Back-up) 2-HPP4.02.018: Source Check (DRMS Auto Function) 4.3.3.10.2.b  Particulate &Iodine Sampler        112-ADM-1611.F04: Channel Check Pri: Filter Paper and Charcoal Cartridge for (2HVS-RQ109A) 4.3.3.10.2.c  Process Flow Rate Monitor          2MSP43.32A-I: Channel Functional Test Pri: (Monitor Item 29 for 2HVS-    2MSP-43.33-I: 2HVS-RQ109BC,D, Channel Calibration FR22)                        20M-54.3 L5 Log: Channel Check 1'Ait (2HVS-FI22A and F122C)        1/2-ADM-1611.F04: Channel Check (Back-up) 2 nd At (2HVS-FI22B and F122D) 4.3.3.10.2.d  Sampler Flow Rate Monitor          2MSP-43.32-l: 2HVS-RQ109A Channel Calibration Pdi: (Monitor Items 28 & 72 for    2MSP43.32A-I: Channel Functional Test 2HVS-DAU109A)                2MSP-43.33-l: 2HVS-RQ1 09B,C,D, Channel Calibration 20M-54.3 L5 Log: Channel Check
                                              .          112-ADM-1611.F04: Channel Check (Back-up)
 
Beave          rValley Beaver VallHeyPower Station Power    Stat
                                                                            .-  7!~          1*CreNumber-12-'ODC-1.01 Level Of Use:
 
==Title:==
Unit:
1/2      General Skill Reference A Revision:    Page Number:
ODCM: Index, Matrix and History of ODCM Changes 4                61 of72 ATTACHMENT C Page 8 of 19 ODCM CONTROLS PROCEDURE MATRIX BV-2 GASEOUS EFFLUENT MONITOR SURVEILLANCES Continued TABLE F:3b ODCM Control 3.3.3.10: Gaseous Effluent Monitors In 112-ODC-3.03 Table 3.3-13 OPERABLE APPLICABILITY: During Releases Through The Flow Paths ODCM SR                  DESCRIPTION                      -PROCEDURE 4.3.3.10.3      Decontamination Building            NOTE: Actions for INOPERABLE monitors are documented Vent                                in the Operations Shift Logs, 112-HPP-3.06.006, and the RP Shift Logs.
4.3.3.10.3.a    Noble Gas Activity Monitor          2MSP-43.35-l: Channel Calibration Pri: (2RMQ-RQ301B)                  20M-54.3 L5 Log: Channel Check 20ST-43.09: Channel Functional Test 2-HPP-4.02.018: Source Check (DRMS Auto Function) 1/2-ADM-161 1.F04: Channel Check (Back-up) 4.3.3.10.3.b    Particulate & Iodine Sampler        1/2-ADM-1611.F04: Channel Check Pri: Filter.Paperand.Charcoal Cartridge for (2RMQ-RQ301A) 4.3.3.10.3.d    Sampler Flow Rate Monitor          2MSP-43.35-l: Channel Calibration Pri: (2RMQ-FIT301-1)                2MSP-43.35A-1: Channel Functional Test 20M-54.3 L5 Log: Channel Check 1/2-ADM-161 1.F04: Channel Check (Back-up) 4.3.3.10.4      Condensate Polishing                NOTE: Actions for INOPERABLE monitors are documented Building Vent                      In the Operations Shift Logs, 1/2-HPP-3.06.006, and the RP Shift Logs.
4.3.3.10.4.a    Noble Gas Activity Monitor          2MSP-43.38-l: Channel Calibration Pri: (2HVL-RQ1 12B)                20M-54.3 L5 Log: Channel Check 20ST 2.43.09: Channel Functional Test 1/2-ADM-1611.F04: Channel Check (Back-up) 2-HPP-4.02.018: Source Check (DRMS Auto Function) 4.3.3.10.4.b    Particulate & Iodine Sampler        1/2-ADM-1611.F04: Channel Check Pri: Filter Paper and Charcoal Cartridge for (2HVL-RQ 1I2A) 4.3.3.10.4.d    Sampler Flow Rate Monitor            2MSP-43.38-l: Channel Calibration Pri: (2HVL-FITI 12-1)              2MSP-43.38A-1: Channel Functional Test 20M-54.3 L5 Log: Channel Check 1/2-ADM-161 1.F04: Channel Check (Back-up) 4.3.3.10.5      Waste Gas Storage Vault Vent        NOTE: Actions for INOPERABLE monitors are documented In the Operations Shift Logs, 1/2-HPP-3.06.006, and the RP Shift Logs.
4.3.3.10.5.a    Noble Gas Activity Monitor          2MSP-43.37-l: Channel Calibration Pri: (2RMQ-RQ303B)                  20M-54.3 L5 Log: Channel Check 20ST-43.09: Channel Functional Test 1/2-ADM-161 1.F04: Channel Check (Back-up) 2-HPP-4.02.018: Source Check (DRMS Auto Function) 4.3.3.10.5.b    Particulate & Iodine Sampler        1/2-ADM-161 1.F04 Channel Check Pri: Filter Paper and Charcoal Cartridge for (2RMQ-RQ303A) 4.3.3.10.5.d    Sampler Flow Rate Monitor            2MSP-43.37-l: Channel Calibration Pri: (2RMQ-FIT303-1) .              2MSP-43.37A-1 Channel Functional Test 20M-54.3 L5 Log: Channel Check 1/2-ADM-161 1.F04: Channel Check (Back-up)                        -/
 
Beaver Valley Power Station_._____    Powe Staion1/2-ODC-1.01 Procedure Number:
 
==Title:==
Unit:        Level Of Use:
1/2        General Skill Reference ODCM: Index, Matrix and History of ODCM Changes                                    Revision:    Page Number:
4                62 of 72 ATTACHMENT C Page 9 of 19 ODCM CONTROLS PROCEDURE MATRIX BV-1 AND 2 LIQUID EFFLUENT CONCENTRATION SURVEILLANCES TABLE F:4 ODCM Control 3.11.1.1: Effluent Concentration Within 10 Times 10CFR20 EC's APPLICABILITY: At All Times ODCM SR                DESCRIPTION                                        PROCEDURE 4.11.1.1.1    Sample and Analyze Radioactive      1/2-ADM-1601: Liquid Radwaste Discharges Liquid Wastes per Table 4.1 1-1 4.11.1.1.1 A  Batch Waste Release Tanks            CHM CP 3: Sampling and Testing CHM CP 5: Radiochemical Procedures CHM CP 8: Logs and Forms (Analysis)
CHM CP 9: Conduct of Operation 1/2-ADM-1611.F03 & F04: LW Tank Sampling 1/2-HPP-3.06.001.FO1: LW Tank Sampling 1/2-HPP-4.02.002.F02: Rad Monitor Sampling 1/2-HPP-4.05.023: Gamma Spec Analysis Matrix 4.11.1.1.1.B1  Continuous Releases                  CHM CP 3: Sampling and Testing CHM CP 5: Radiochemical Procedures CHM CP 8: Logs and Forms (Analysis)
CHM CP 9: Conduct of Operation 1/2-ADM-1611.F03 & F04: LW Tank Sampling.
1/2-HPP-4.02.002.F02: Rad Monitor Sampling 1/2-HPP-4.05.023: Gamma Spec Analysis Matrix 4.11.1.1.2    Use ODCM Methodology to              112-HPP-3.06.005.FO1: RWDA-L Assure Compliance                    1/20M-17.4A.D: RWDA-L 4.11.1.1.3    Take Turbine Building Grab          CHM CP 3: Sampling and Testing Sample When BV-1 Primary to          CHM CP 5: Leak Rate Calculations Secondary Leakage Exceeds 0.1        CHM CP 8: Logs and Forms (Analysis) gpm (142 gpd)                        1/2-ADM-1611.F03 & F04: Sump Sampling 1/2-HPP-3.06.001.F01: LW Tank Sampling 112-HPP-3.06.005.F01: RWDA-L 1/2-HPP-4.02.002.F02: Rad Monitor Sampling 4.11.1.1.4    Take Turbine Building Grab          CHM CP 3: Sampling and Testing Sample When BV-2 Primary to          CHM CP 5: Leak Rate Calculations Secondary Leakage Exceeds 0.1        CHM CP 8: Logs and Forms (Analysis) gpm (142 gpd)                        1/2-ADM-161 1.F03 & F04: Sump Sampling 1/2-HPP-3.06.001.FO1: LW Tank Sampling 112-HPP-3.06.005.FO1: RWDA-L 1/2-HPP-4.02.002.F02: Rad Monitor Sampling 4.11.1.1.5    Take Grab Samples Prior to BV-2      112-ADM-1611.F03 & F04: Sump Sampling Recirculation Drain Pump            1/2-HPP-3,06.001.FO1: LW Tank Sampling Discharge to Catch Basin No. 16      20M-9.2: Rx Plant Vents and Drains (CB-16) 20M-9.4F: Drain RSS Pump Casing I Pit 20M 51: OM Clearance 51-86 (2DAS-P215A/B)
 
                                                                                                                      -l-a-Bea'ver Valle'yy Po'we'r      w    SPicedure St'ation                    I Number-1/2-ODC-1.01
 
==Title:==
Unit:        Level Of Use:
1/2        General Skill Reference Revision:    Page Number:
ODCM: Index, Matrix and History of ODCM Changes
                                                                                  -4                  63 of 72 ATTACHMENT C Page 10 of 19 ODCM CONTROLS PROCEDURE MATRIX BV-1 AND 2 LIQUID EFFLUENT DOSE SURVEILLANCES TABLE F:5 ODCM Control 3.11.1.2: Uquid Effluent Dose APPLICABILITY: At All limes ODCM SR              DESCRIPTION                                    -PROCEDURE 4.11.1.2.1  Using the ODCM - Determine          1/2-HPP-3.06.005.FO1: RWDA-L Cumulative Dose From Liquid        SHP Letter: Monthly Dose Projection Effluents Every 31 Days            1/20M-17.4A.D: RWDA-L
 
,,                .,^                                          .Procedure                    Number:
Beaver Valley Power Station                                                      1/2-ODC-1.01
 
==Title:==
Unit:        Level Of Use:
                                                                                    .1/2            General Skill Reference ODCM: Index, Matrix and History of ODCM Changes                                    Revision:    Page Number.
ATTACHMENT C Page 11 of 19 ODCM CONTROLS PROCEDURE MATRIX BV-1 AND 2 LIQUID EFFLUENT TREATMENT SURVEILLANCES TABLE F:6 ODCM Control 3.11.1.3: Liquid Effluent Treatment System APPLICABILITY: At All limes ODCM SR              DESCRIPTION                                          PROCEDURE 4.11.1.3.1  Using the ODCM - Project the Liquid    1/2-HPP-3.06.005.FO1: RWDA-L Release Dose Every 31 Da                SHP Letter Monthly Dose Projection
                                      .                ~1/20M-17A4A.D:    RWDA-L
 
Beave Valle Power StatoProceduro Number.                .1      ..
Beaver Valley Pow-er'Station-12OC.0
 
==Title:==
Unit:        Level Of Use:
1/2    I GeneralSkillReference*.]
Revision:    Page Number:
ODCM: Index, Matrix and History of ODCM Changes                                                                                  , /
4A-              65 of 72 ATTACHMENT C Page 12 of 19 ODCM CONTROLS PROCEDURE MATRIX BV-1 AND 2 LIQUID STORAGE TANK ACTWIVTY LIMIT SURVEILLANCES TABLE F:7 ODCM Control 3.11.1.4: <10 Curies in I BR-TK-6A&B, 1LW-TK-7A&B and Misc. Temp Liquid Tanks. Also, <4.2 Curies in 1QS-TK-1 and 2QSS-TK21.
APPLICABILITY: At All Times ODCM                    DESCRIPTION                                          PROCEDURE SR 4.11.1.4.1    Every 7 days Analyze a tank sample        1/2-HPP-3.06.001.F05: Activity Determination when radioactive material is added to      1/2-HPP-3.06.005.FO1: RWDA-L tanks except the RWSTs.                    1OM-8.4.Z: Recirculate Test Tanks Thru Ion Exchanger.
I1OM-17.4.AJ: LW Transfer to 1LW-TK-7A&B For RWSTs, analyze sample within          1OM-54.3 L5 Log Item 197:
7 days of reactor cavity drain down        1 OM-54.3 L5 Log Item 132:
back to the RWST.                          1OM-54.3 L5 Log Item 134:
IOM-54.3 L5 Log Item 200:
20M-17.4B: LW to SG Blowdown Tank
_______    1 ______________________                  .1.
 
Beaver Valley Power Station                                            Procedure NubODC
 
==Title:==
Unit:        Level Of Use:
1/2        General Skill Reference ODCM: Index, Matrix and History of ODCM Changes                                            Revision:    Page Number ATrACHMENT C Page 13 of 19 ODCM CONTROLS PROCEDURE MATRIX BV-1 AND 2 GASEOUS EFFLUENT DOSE SURVEILLANCES TABLE F:8 ODCM Control 3.11.2.1: Gaseous Effluent Dose Rates APPLICABILITY: At All Times ODCM SR                    DESCRIPTION                                          PROCEDURE 4.11.2.1.1          Using the ODCM - Determine the      1/2-HPP-3.06.006.FO1: RWDA-G Noble Gas Effluent Dose Rate        112-ENV-01.03.FO1: Continuous Release Permit 112-HPP-3.06.012.FO1: Abnormal Gaseous Releases IOM-19.4E, H: RWDA-G for Unit 1 GWOrs 1120M-19.4AkB: RWDA-G for Unit 2 GWSTs 4.11.2.1.2          Sample and Analyze per Table        1/2-ADM-1601: Gaseous Radwaste Discharges 4.11-2 to Determine Inhalation Pathway Dose 4.11.2.1.2.A        Waste Gas Storage Tank -            CHM CP 3: Sampling and Testing Grag Sample Each Tank              CHM CP 5: Radiochemical Procedures CHM CP 8: Logs and Forms (Analysis)
CHM CP 9: Conduct of Operation 1/2-ADM-161 1.F03 & F04: GW Tank Sampling 1-HPP-3.06.003.FO1: GW Tank Sampling 1/2-HPP-3.06.006.FO1: RWDA-G 112-HPP-4.02.002.FO1: Rad Monitor Sampling 4.11.2.1.2.B        Containment Purge -                CHM CP 3: Sampling and Testing Grag Sample Each Purge              CHM CP 5: Radiochemical Procedures CHM CP 8: Logs and Forms (Analysis)
CHM CP 9: Conduct of Operation 1/2-ADM-1611.F03 & F04: GW Tank Sampling 112-HPP-3.06.006.F01: RWDA-G 112-HPP-3.07.003.FO1: Air Sample Record
: _                                              1/2-HPP-4.02.002.FO1 Rad Monitor Sampling 4.11.2.1.2.C        Ventilation Systems 4.11.2.1.2.C.1      BV-1 Grab and Continuous Samples    CHM CP 3: Sampling and Testing thru                                                    CHM CP 5: Radiochemical Procedures 4.11.2.1.C.3                                            CHM CP 8: Logs and Forms (Analysis) and                                                      CHM CP 9: Conduct of Operation 4.11.2.1.2.D.1                                          112-ADM-1611.F03 & F04: GW Tank Sampling thru          ENV-01.03.F01:                                            Continuous Release Permit 4.11.2.1 .2.D.3                                          1/2-HPP-4.02.002.FOI: Rad Monitor Sampling 112-HPP-4.02.017.Fxx: RMS & DRMS Sample Flow Valve Line-Up 1-HPP-5.01.001: SA-9/10 Emergency Operation 1-HPP-5.01.002: SPING-4 Emergency Operation 4.11.2.1.2.C.4      BV-2 Grab and Continuous Samples    CHM CP 3: Sampling and Testing thru                                                    CHM CP 5: Radiochemical Procedures 4.11.2.1.2.C.8                                          CHM CP 8: Logs and Forms (Analysis) and                                                      CHM CP 0: Conduct of Operation 4.11.2.1.2.D.4                                          112-ADM-1611.F03 & F04: GW Tank Sampling thru                                                    112-ENV-01.03.FO1: Continuous Release Permit 4.11.2.1.2.D.8                                          112-HPP-4.02.002.FO1: Rad Monitor Sampling 2-HPP-5.04.001: Emergency Operation of WRGM Assembly
 
Procedure Number~
Beaver-Valley Power Station                                                    1/2-ODC-1.O1
 
==Title:==
Unit          Level Of Use:
1/2        General Skill Reference ODCM: Index, Matrix and History of ODCM Changes                                  Revision:          Number 4                67 of 72.
ATTACHMENT C Page 14 of 19 ODCM CONTROLS PROCEDURE MATRIX BV-1 AND 2 GASEOUS EFFLUENT AIR DOSE SURVEILLANCES TABLE F:9 ODCM Control 3.11.2.2: Gaseous Effluent Air Doses APPLICABILITY: At All Times ODCM            DESCRIPTION                                        PROCEDURE 4.11.2.2.1  Using the ODCM - Determine the      1/2-HPP-3.06.006.FO1: RWDA-G Noble Gas Cumulative Dose          1/2-ENV-01.03.FO1: Continuous Release Permit Contributions Every 31 Days        112-HPP-3.06.012.FOI: Abnormal Gaseous Releases 1/-HPP-4.02.002.FO1: Rad Monitor Sampling I OM-1 9.4E, H: RWDA-G for Unit 1 GWDTs 1120M-19.4A.B: RWDA-G for Unit 2 GWST's SHP Letter Monthly Dose Projection
 
Procedure Number:
Beaver Valley Power Station                                                    1/2-ODC-1.01
 
==Title:==
Unit:        Level Of Use:
1/2      General Skill Reference ODCM: Index, Matrix and History of ODCM Changes                                    Revision:    Pag Numb        2 ATTACHMENT C Page 15 of 19 ODCM CONTROLSPROCEDURE MATRIX
              - BV-1 AND 2 GASEOUS EFFLUENT PARTICULATE AND IODINE DOSE SURVEILLANCES TABLE F:10 ODCM Control 3.11.2.3: Gaseous Effluent Particulate And Iodine Doses APPLICABILITY: At All Times ODCM                DESCRIPTION                                        PROCEDURE SR 4.11.2.3.1  Using the ODCM - Determine the        1/2-HPP-3.06.006.FO1: RWDA-G Particulate & Radioiodine Cumulative  1/2-ENV-01.03.FD1: Continuous Release Permit Dose Contributions Every 31 Days      1/2-HPP-3.06.012.FO1: Abnormal Gaseous Releases 1/2-HPP4.02.002.FO1: Rad Monitor Sampling 1OM-1 9.4E, H: RWDA-G for Unit I GWDTs 1/20M-19.4A.B: RWDA-G for Unit 2 GWSTs SHP Letter Monthly Dose Projection
 
Valley      Peaver e r _ Station1/2-ODC-lO1 Balel ayPower I Procedure Number:
 
==Title:==
Unit:          Level Of Use:
1/2        General Skill Reference Revision:      Page Number:
ODCM: Index, Matrix and History of ODCM Changes 4                  69 of 72 ATTACHMENT C Page 16 of 19 ODCM CONTROLS PROCEDURE MATRIX BV-1 AND 2 GASEOUS EFFLUENT TREATMENT SURVEILLANCES TABLE F:11 ODCM Control 3.11.2.4: Gaseous Effluent Treatment System APPLICABILITY: At All Times ODCM                DESCRIPTION                                      PROCEDURE SR 4.11.2.4.1  Using the ODCM - Project the Gas      1/2-HPP-3.06.006.FO1: RWDA-G Release Dose from the Site Every 31  1/2-ENV-01.03.F01: Continuous Release Permit Days                                  1/2-HPP-3.06.012.FO1: Abnormal Gaseous Releases SHP Letter Monthly Dose Projection 1OM-1 9.4E. H: RWDA-G for Unit 1 GWDTs 1/20M-19.4A.B: RWDA-G for Unit 2 GWSTs
 
Beaver Valley Power Station                                  .2ProcedureNui'-ODC-1.01
 
==Title:==
Unit:        Level Of Use:
                                                                                            .112    General Skill Reference ODCM: Index, Matrix and Histoiy of ODCM Changes                                      Revision:    Page Number:
ATTACHMENT C Page 17 of 19 ODCM CONTROLS PROCEDURE MATRIX BV-1 GASEOUS STORAGE TANK ACTIVITY LIMIT SURVEILLANCES TABLE F:12a ODCM Control 3.11.2.5: Gas Storage Tank Activity Must be <52000 Curies Noble Gas (Considered Xe-133)
APPLICABILITY: At All Times ODCM                DESCRIPTION                                        PROCEDURE SR 4.11.2.5.1  Determnine Tank Gas Contents when    1/2-1-11P-3.06.003.F01: Activity Determinabion Adding Rad Material & (RCS Activity    IOM-19.4.G: GW Disposal System
                  >140nuCUml)
N\
BV-2 GASEOUS STORAGE TANK ACTIVITY LIMIT SURVEILLANCES TABLE F:12b ODCM Control 3.11.2.5: Connected Group of Gas Storage Tanks must be <19000 Curies Noble Gas (Considered Xe-1 33)
APPLICABILITY: At All Times ODCM SR              DESCRIPTION                                        PROCEDURE 4.11.2.5.1  Determine Gaseous Waste Tank          1/2-HPP-3.06.003.FO1: Activity Determination Rad Material When Adding Rad          20M-19.2: GW Precautions & Limitations Material to the Tank.                20M-19.4G: GW transfer from Unit 2 20M-54.3 L5 Log Item 133:
 
                                                                                                                                -UL-
                                                                                .. Procedure Number            .
Beaver Valley Power Station                                                      1/2-ODC-1.O1
 
==Title:==
Unit:        Level Of Use-1/2        General Skill Reference ODCM: Index, Matrix and History of ODCM Changes                                    Revision:    Page Number
                                                - ATTACHMENT C Page 18 of 19 ODCM CONTROL
 
==S. PROCEDURE==
MATRIX BV-1 AND 2 TOTAL DOSE SURVEILLANCES TABLE F:13 ODCM Control 3.11.4.1: Liquid And Gaseous Doses APPLICABILIIY: At All Times ODCM              DESCRIPTION                                          PROCEDURE SR 4.11.4.1.1  Using the ODCM - Determine            1/2-ENV-01.05.FO1: Annual RETS Report (40CFR190)
Cumulative Gas & Liquid Dose per      112-HPP-3.06.005.FO1: RWDA-L Control 3.11.1.2, 3.11.2.2, 3.11.2.3  1/2-HPP-3.06.006.F01: RWDA-G 1/2-ENV-01.03.F01: Continuous Release Permit 1/2-HPP-3.06.012.FOI: Abnormal Gaseous Releases 1/2-ENV-01.04: Effluent Data Logs (40CFRI90)
                                                                                                                          -IN\
N,
 
Procedure Number:
Beaver Valley Power Station                                                      1/2-ODC-1.01
 
==Title:==
Unit:          Level Of Use:
1/2      General Skill Reference ODCM: Index, Matrix and History of ODCM Changes                                    Revision:      Page Number:
4      -          72 of 72 ATTACHMENT C Page 19 of 19 ODCM CONTROLS PROCEDURE MATRIX BV-1 AND 2 REMP PROGRAM SURVEILLANCES TABLE F:14 ODCM Control 3.12.1: Radiological Environmental Monitoring Program (REMP)
APPLICABILITY: At All Times ODCM                DESCRIPTION                                          PROCEDURE SR 4.12.1.1  Using Locations in the ODCM -Collect    1/2-ENV-02.01: Description of overall REMP and Analyze Samples per Tables          112-ENV-03.01: Environmental Sampling 3.12-1, 3.12-2 & 4.12-1 TABLE F:15 ODCM Control 3.12.2: Land Use Census APPLICABILITY: At All Times ODCM                DESCRIPTION                                          PROCEDURE SR 4.12.2.1    Using the Best Available Method -      1/2-ENV-02.01: Description of overall REMP Conduct a Land Use Census Yearly      1/2-ENV-4.02: Compliance to ODCM Control 3.12.2 Action a Between 6/1 & 10/1                    and b TABLE F:16 OCM Control 3.12.3: Interlaboratory Comparison Program APPLICABILITY: At All Times ODCM                DESCRIPTION                                        PROCEDURE SR 4.12.3.1    Include Analysis Results of the      1/2-ENV-02.01: Description of overall REMP Interlaboratory Comparison Program in the Annual Radiological Environmental Report
 
RTL #A9.621B Beaver Valley- Power Station Unit 1/2 1/2-ODC-2.01 ODCM: LIQUID EFFLUENTS Document Owner Manager, Nuclear Environmental and Chemistry Revision Number                                      3 Level Of Use                              General Skill Reference Safety Related Procedure                            Yes
 
Beaver Valley Power Station                                        edureNumber
 
==Title:==
Unit:        Level Of Use:
1/2      General Skill Reference ODCM: LIQUID EFFLUENTS ODCM LIUIDEFFUENS                                        1 Revision:
3 Page Number 2of 39 TABLE OF CONTENTS 1.0  PURPOSE                                      ...........                                                  ;;3 2.0  SCOPE ...................................                                                                3
 
==3.0  REFERENCES==
AND COMMITMENTS                                                .3 3.1 References ...............                                                                            3 3.2 Commitments                                              ..                                          5 4.0 RECORDS AND FORMS                                                    .            .            .          5 4.1 Records                                                ..                                            5 4.2 Forms ..                                                                                              5...:;5 5.0 PRECAUTIONS AND LIMITATIONS                                              .          .              .      5 6.0 ACCEPTANCE CRITERIA ..........................                                                              6 7.0 PREREQUISITES...6 8.0 PROCEDURE .........................                                                                        7 8.1 Alarm Setpoints                                            ..                                        7 8.1.1        BV-1 Monitor Alarm Setpoint Determination                          .7 8.1.2        BV-2 Monitor Alarm Setpoint Determination .12 8.2 Compliance With 10 CFR 20 EC Limits (ODCM CONTROL 3.11.1.1) .                            .17 8.2.1        Batch Releases .17 8.2.2        Continuous Releases .19 8.3 Compliance With 10 CFR 50 Dose Limits (ODCM CONTROLS 3.11.1.2 And 3.11.1.3).19 8.3.1        Cumulation Of Doses (ODCM CONTROL 3.11.1.2) .......................................... 19 8.3.2        Projection Of Doses (ODCM CONTROL 3.11.1.3) .22 8.4 Liquid Radwaste System                              ..                                              22 8.4.1        BV-1 Liquid Radwaste System Components .23 8.4.2        BV-1 Laundry and Contaminated Shower Drain System Components .24 8.4.3        BV-2 Liquid Radwaste System Components                                                24 ATTACHMENT A LIQUID SOURCE TERMS                                ..                                            26 ATTACHMENT B RECIRCULATION TIMES .30 ATTACHMENT C INGESTION DOSE COMMITMENT FACTORS .32 ATTACHMENT D LIQUID RADWASTE SYSTEM .35 ATTACHMENT E SITE BOUNDARY FOR LIQUID EFFLUENTS .38
 
Beaver Valley Power Station                                            1/2-ODC-2.01
 
==Title:==
Unit:        Level Of Use:
1/2      General Skill Reference ODCM: LIQUID EFFLUENTS                                                        Revision:    Page Number:
                                                                                    -3              3of38      -
1.0        PURPOSE 1.1      This procedure provides the calculational methodology to be used for determination of the following release parameters as denoted in the Administrative Controls Section of the Unit 1/2 Technical Specifications.(3 ) l 1.1.1    Liquid effluent monitor alarm setpoints (Technical Specification 6.8.6.a, Item 1) 1.1.2      Liquid effluent release concentration calculations (Technical Specification 6.8.6.a, Item 2) 1.1.3      Liquid effluent dose projection and cumulative dose calculations (Technical Specification 6.8.6.a, Items 4 and 5) 1.2      This procedure also provides information related to the following:
1.2.1    Liquid Radwaste Treatment System (Technical Specification 6.8.6.a, Item 6) 1.2.2      Site Boundary used for liquid effluents 1.3      Prior to issuance of this procedure, these items were contained in Section 1 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    References For BV-I Liquid Effluent Monitor Setpoints 3.1.1.1      Beaver Valley Power Station, Appendix I Analysis - Docket No. 50-334 and 50-412; Table 2.1-3 3.1.1.2      Beaver Valley Power Station, Appendix I Analysis - Docket No. 50-334 and 50-412; Table 2.1-2 3.1.1.3      10 CFR 20, Appendix B, (20.1001-20.2402) Table 2, Column 2 EC's 3.1.1.4      Calculation Package No. ERS-SFL-92-039, Isotopic Efficiencies For Unit 1 Liquid Process Monitors 3.1.1.5      Calculation Package No. ERS-ATL-93-021, Process Alarm Setpoints For Liquid Effluent Monitors
 
xra                                                                          Procedure Nurnber                -
Beaver Valley Power Station
_/2-ODC-2.01
                                                                          -  edur  -        ODNumbet
 
==Title:==
Unit:          Level Of Use:
1/2        General Skill Reference ODCM: LIQUID EFFLUENTS                                                      Revision:    Page Number4 3.1.1.6      Stone and Webster Calculation Package No. UR(B)-160, BVPS Liquid Radwaste Releases and Concentrations - Expect and Design Cases (per Unit and Site) 3.1.2    References for BV-2 Liquid Effluent Monitor Setpoints 3.1.2.1      10 CFR 20, Appendix B, (20.1001-20.2402) Table 2, Column 2 EC's 3.1.2.2      Calculation Package No. ERS-SFL-86-026, Unit 2 DRMS Isotopic Efficiencies 3.1.2.3      Stone and Webster Computer Code LIQ1BB; "Normal Liquid Releases From A Pressurized Water Reactor" 3.1.2.4      Calculation Package No. ERS-JWW-87-015, Isotopic Efficiencies For 2SGC-RQ100 3.1.2.4.1      The Isotopic Efficiencies for 2SGC-RQ100 are superceded by the values presented in Calculation Package No. ERS-SFL-86-026.
3.1.2.5      Calculation Package No. ERS-WFW-87-021, Conversion Factor for 2SGC-RQ100 3.1.2.5.1      The Monitor Conversion Factor (CFI) for 2SGC-RQ100 is superceded by the value presented in Calculation Package No. ERS-ATL-93-021.
3.1.2.6      Calculation Package No. ERS-ATL-93-021, Process Alarm Setpoints For Liquid Effluent Monitors 3.1.2.7      Stone and Webster Calculation Package No. UR(B)-160, BVPS Liquid Radwaste Releases and Concentrations - Expect and Design-Cases (per Unit and Site) 3.1.3    References used for Other Portions of this procedure 3.1.3.1      NUREG-0133, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants 3.1.3.2      NUREG-1301, Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors (Generic Letter 89-01, Supplement No. 1) 3.1.3.3      NUREG-0017; Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from PWR's, Revision 0 3.1.3.4      Regulatory Guide 1.113; Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I, April 1977 3.1.3.5      Regulatory Guide 1.109; Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance to 10CFR Part 50, Appendix I
 
Beaver Valley Power Station                                  Procedure NubODC        2
 
==Title:==
Unit:        Level Of Use:
1/2      General Skill Reference ODCM: LIQUID EFFLUENTS                                                          Revision:    Page Number:
3              .5of38 3.1.3.6        Calculation Package No. ERS-ATL-83-027; Liquid Waste Dose Factor Calculation for HPM-RP 6.5, Issue 3 and Later 3.1.3.7        NUREG-0172; Age-Specific Radiation Dose Commitment Factors for a One-Year Chronic Intake 3.1.3.8        UCRL-50564; Concentration Factors of Chemical Elements in Edible Aquatic Organisms, Revision 1, 1972 3.1.3.9        1/2-ADM-1640, Control of the Offsite Dose Calculation Manual
        *3.1.3.10      1/2-ADM-0100, Procedure Writers Guide 3.1.3.11      NOP-SS-3001, Procedure Review and Approval 3.1.3.12      1/2-ODC-3.03, ODCM: Controls for RETS and REMP Programs 3.1.3.13      CR 02-06174, Tracking of Activities for Unit 1 RCS Zinc Addition Implementation. CA-014, Revise ODCM Procedure 1/2-ODC-2.01 (Tables 1.1-la and lb) to include the addition of Zn-65 to the ODCM liquid source term.
3.1.3.14      CR 03-02466, RFA-Radiation Protection Effluent Control Provide Recommendation on Processing when Performing Weekly Sample of [lLW-TK-7A17B]. CA-02, Revise ODCM Procedure 1/2-ODC-2.01, (Attachment D) to show the liquid waste flow path cross-connect between Unit 1 and Unit 2.
3.2      Commitments 3.2.1      Unit 1/2 Technical Specification 6.8.6.a 4.0      RECORDS AND FORMS 4.1      Records 4.1.1      Any calculation supporting ODCM changes shall be documented, as appropriate, by a retrievable document (e.g.; letter or calculation package) with an appropriate RTL number.
4.2      Forms 4.2.1      None 5.0      PRECAUTIONS AND LIMITATIONS 5.1      BV-1 and BV-2 utilize the concept of a shared liquid radioactive waste system according to NUREG 0133.(313 1) This permits the mixing of liquid radwaste for processing and allocating of dose due to release as defined in Section 8.4.
 
                                                                                  -Tmcd      Number:
Beaver Valley Power Station                                    I.          1ODC-2.01-
 
==Title:==
Unit:      Level Of Use:
1/2      General Skill Reference I.
ODCM: LIQUID EFFLUENTS                                                          -Revision:      Page Number:
                                                                                        .3                6 of 3s 5.1.1      In Section 8.1 of this procedure, effluent monitor setpoints for a conservative mix are based on the individual Units' specific parameters, but effluent monitor setpoints for analysis prior to release permit use of the total dilution flow available at the site.
5.2        There is a difference in alarm setpoint terminology presentations for the radiation monitoring systems of BV-I and BV-2.
5.2.1      Where HIGH and HIGH-HIGH terminology are used for BV-I monitors, Alert and High terminology is used for BV-2 monitors.
5.2.2      BV-2 setpoints are presented in uCi/ml rather than cpm as in BV-1. This.difference is due to BV-2 software which applies a conversion factor to the raw data (cpm). Note that the uCi/ml presentation is technically correct only for the specific isotopic mix used in the determination of the conversion factors. Therefore, BV-2 setpoints determined on analysis prior to release will be correct for properly controlling dose rate, but the indicated uCi/ml value may differ from the actual value.
5.3        This procedure also contains information that was previously contained in Section 5 of the previous BV-1 and 2 Offsite Dose Calculation Manual.
5.3.1      In regards to this, the site boundary for liquid effluents was included in this procedure.
5.3.2      The Site Boundary for Liquid Effluents is shown in ATTACHMENT E Figure 5-1.
6.0        ACCEPTANCE CRITERIA 6.1        All changes to this procedure shall contain sufficient justification that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR 50, and not adversely impact the accuracy or reliability of effluent dose or alarm setpoint calculation.( 3 32 )
6.1.1      All changes to this procedure shall be prepared in accordance with 1/2-ADM-0100( 3 l3 10 )
and 1/2-ADM-1640.( 3 'l39 6.1.2      All changes to this procedure shall be reviewed and approved in accordance with NOP-SS-3001(3 1.3.11) and 1/2-ADM-1 640.(3 39)    .
7.0        PREREOUISITES 7.1        The user of this procedure shall be familiar with ODCM structure and format.
 
Beaver Valley Power Station                                  ProcedureNumber:
 
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ODC:LQUD  EFLENT-3                                                            7of 39 8.0        PROCEDURE 8.1        Alarm Setpoints 8.1.1    BV-1 Monitor Alarm Setpoint Determination This procedure determines the monitor HIGH-HIGH Alarm Setpoint that indicates if the concentration of radionuclides in the liquid effluent released from the site to unrestricted areas exceeds 10 times the EC's specified in 10 CFR 20, Appendix B (20.1001-20.2402),
Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases or exceeds a concentration of 2E-4 uCi/ml for dissolved or entrained noble gases. (311-5)
The methodology described in Section 8.1.1.2 is an alternative method to be used to determine the (RM-lLW-104 or RM-lLW-1 16) monitor HIGH-HIGH Alarm Setpoint (HHSP). The methodology in Section 8.1.1.2 may be used for any batch release and shall be used when the respective total gamrna activity concentration of the liquid effluent prior to dilution exceeds 3.14E-3 uCi/ml and 7.33E-3 uCi/ml. This concentration is equivalent to the respective HHSP's derived in Section 8.1.1.1 and allows for respective tritium concentrations up to 4.26E+0 uCi/ml and 9.94E+0 uCi/ml.( 31 15 )
8.1.1.1      BV-1 Setpoint Determination Based On A Conservative Mix The Alarm Setpoints for the liquid monitors shall be set at the values listed in the following table:
BV-1 LIQUID MONITOR SETPOINTS Icpm              Above Background
                                                -      Monitor          CR          HHSP          HSP Liquid Waste Effluent Monitor RM-lLW-104 3.53E+5                  3.53E+5 2.47E+5 Laundry And Contaminated          RM-lLW-116 8.24E+5              8.24E+5 5.77E+5 Shower Drains Monitor Component Cooling/                RM-lRW-100 2.57E+4              2.57E+4      1.80E+4.
Recirculation Spray Hx River Water Monitor Component Cooling Hx River        RM-IRW-101 9.02E+3              9.02E+3      6.32E+3 Water Monitor Aux Feed Pump BayDrain            RM-lDA-100 1.22E+4              1.22E+4      8.55E+3 Monitor                                              .
The setpoints for RM-lLW-104 and RM-1LW-1 16 are based on the following conditions.
The setpoint bases for RM-IRW-100 and RM-lDA-100, can be found in Calculation Package ERS-ATL-93-021. (3.1.1.5)
 
Beaver Valley Power Station                                                                    I
 
==Title:==
ODCM: LIQUID EFFLUENTS
* Source terms given in ATTACHMENT A Table 1.1-la. These source terms (without Zn-65) have been generated from the GALE Computer Code, as described in NUREG-0017.( 3 l33 ) The inputs to GALE are given in 1/2-ODC-3.01 Appendix B.
The Zn-65 source term was generated via Calculation Package No. ERS-ATL                  021 (3.1.1.5,3.1.3.13)
* Dilution water flow rate of 22,800 gpm        (15,000 gpm BV-I + 7,800 gpm BV-2).
* Discharge flow rate prior to dilution of 35 gpm for the Liquid Waste Effluent Monitor (RM-lLW-104).
* Discharge flow rate prior to dilution of 15 gpm for the Laundry and Contaminated Shower Drains Monitor (RM-ILW-116).
The above setpoints for (RM-ILW-104 and RM-1LW-1 16) can be varied based on actual operating conditions resulting in changes in the discharge and dilution flow rates as follows:
HEBSp=542F                                                                        1(1]
f where:
HHSP      Monitor HIGH-HIGH Alarm Setpoint above background (ncpm).
542    = Most restrictive proportionality constant based on nominal flow conditions:
542    = 3.53E+5 ncpm x 35 gpm -22,800 gpm (RM-ILW-104) 542    = 8.24E+5 ncpm x 15 gpm &#xf7;22,800 gprn (RM-lLW-1 16)
F      =  Dilution water flow rate (gpm), BV-1 plus BV-2 Cooling Tower Blowdown Rate (not including release through the Emergency Outfall Structure).
f      =  Discharge flow rate prior to dilution (gpm).
8.1.1.1.1        BV-1 Mix Radionuclides The "mix" (radionuclides and composition) of the liquid effluent was determined as follows:
* The liquid source terms that are representative of the "mix" of the liquid effluent were determined. Liquid source terms are the radioactivity levels of the radionuclides in the effluent from ATTACMENT A Table 1.1-la.
* The fraction of the total radioactivity in the liquid effluent comprised by radionuclide "i" (Si) for each individual radionuclide in the liquid effluent was determined as follows:        !
 
Beaver Valley Power Station                                  Procdure Nuer.              01
 
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                              .i where:
Ai= Annual release of radionuclide "i" (Ci/yr) in the liquid effluent from ATTACHMENT A Table 1.1-la.
8.1.1.1.2  BV-1 Maximum Acceptable Concentration (All Radionuclides)
The maximum acceptable total radioactivity concentration (uCi/ml) of all radionuclides in the liquid effluent prior to dilution (Ct) was determined by:
      -Ct=                F                                                                  [1-1(1)-3]
fZ,Si i OECi where:
F            Dilution water flow rate (gpm), BV-1 plus BV-2 Cooling Tower Blowdown Rate (not including release through the Emergency Outfall Structure).
22,800 gpm = (15,000 gpm BV-1      +  7,800 gpm BV-2) f            Maximum acceptable discharge flow rate prior to dilution (gpm).
                            =35 gpm for-Liquid Waste Effluent Monitor (RM-ILW-104).
15 gpm for Laundry and Contaminated Shower Drains Monitor (RM-lLW-116).
OEC= The ODCM liquid effluent concentration limit for radionuclide "i" (uCi/ml) from ATTACHMENT A Table 1.1-la. The OEC is set at 10 times the new 10 CFR 20, Appendix B (20.1001-20.2402) Table 2, Col.
2 EC values.
Si        =The fraction of total radioactivity attributed to radionuclide "i", from Equation [1.l(l)-2].
8.1.1.1.3  BY-1 Maximum Acceptable Concentration (Individual Radionuclide)
The maximum acceptable radioactivity concentration (uCi/ml) of radionuclide
                  'i" in the liquid effluent prior to dilution (Ci) was determined by:
Ci = Si C,                                                                  [1.1(1)-4]
 
Beaver Valley Power Station
____________________I________                                l f          -  1,C 1/2-ODC-2.01
 
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ODCM: LIQUID EFFLUENTS                                                        Revision:      Page Number:
3 -0              I(Of3 8.1.1.1.4        BV-I Monitor Count Rate The calculated monitor count rate (ncpm) above background attributed to the radionuclides; (CR) was determined by:
CR= E C; E;                                                                11()5 where:
E; = Detection efficiency of the monitor for radionuclide "i" (cpm/uCi/ml) from ATTACHMENT A Table 1.1-1 a. If not listed there, from Calculation Package ERS-SFL-92-039.      (3.1.1.4) 8.1.1.1.5        BV-1 Monitor HHSP The monitor HIGH-HIGH Alarm Setpoint above background (ncpm) should be set at the CR value. Since only one tank can be released at a time, adjustment of this value is not necessary to compensate for release from more than one source.
8.1.1.2      BV-1 Setpoint Determination Based On Analysis Prior To Release The following method applies to liquid releases when determining the setpoint for the maximum acceptable discharge flow rate prior to dilution and the associated HIGH-HIGH Alarm Setpoint based on this flow rate for the Liquid Waste Effluent Monitor (RM-ILW-104) and the Laundry and Contaminated Shower Drains Monitor (RM-ILW-1 16) during all operational conditions.
* The monitor alarm setpoint is set slightly above (a factor of 1.25) the count rate that results from the concentration of gamma emitting radionuclides in order to avoid spurious alarms. To compensate for this increase in the monitor alarm setpoint, the allowable discharge flow rate is reduced by the same factor.
When the discharge flow rate is limited by the radwaste discharge pump rate capacity or by administrative selection rather than the allowable flow rate determined form activity concentration, the alarm setpoint will be proportionally adjusted based upon the excess dilution factor provided.
8.1.1.2.1        BV-I Maximum Acceptable Discharge Flow Rate The maximum acceptable discharge flow rate (f) prior to dilution (gpm) is determined by:                                                                            -
f      F                                                                  [1-1(1)-6]
1.25 Z Ci i GECi
 
Procedure Numnber~
Beaver Valley Power Station                                              1/2-ODC-2.P1
 
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1/2        General Skill Reference ODCM: LIQUID EFFLUENTS                                                  Revision:      Page Number:
                                                  . -3                                          1 1 of 3,8 where:
F    =    Dilution water flow rate, BV-1 plus BV-2 Cooling Tower Blowdown (gpm).
The dilution water flow rate may include the combined cooling tower blowdown flow from both units exiting the discharge
* structure (but excluding emergency outfall structure flow) when simultaneous liquid discharges are administratively prohibited.
C;  =    Radioactivity concentration of radionuclide "i" in the liquid effluent prior to dilution (uCi/ml) from analysis of the liquid effluent to be released.
1.25  =  A factor to prevent spurious alarms caused by deviations in the mixture of radionuclides which affect the monitor response.
OEC= The ODCM liquid effluent concentration limit for radionuclide "i" (uCi/ml) from ATTACHMENT A Table 1.1-la. The OEC is set at 10 times the new 10 CFR 20, Appendix B (20.1001-20.2402)
Table 2, Col. 2 EC values.
8.1.1.2.2  BV-1 Monitor Count Rate The calculated monitor count rate (ncpm) above background attributed to the radionuclides, (CR) is determined by:
CR= 1.25 Z C; E;                                                              [1.1(1)-7]
                            -i where:
E;      =  The detection efficiency of the monitor for radionuclide "1" (cpm/uCi/ml) from ATTACHMENT A Table 1.1-la. If not listed there, from Calculation Package ERS-SFL-92-039.( 31'l.4) 1.25  =  A factor to prevent spurious alarms caused by deviations in the mixture of radionuclides which affect the monitor response.
8.1.1.2.3  BV-1 Monitor HHSP The liquid effluent monitor HIGH-HIGH Alarm Setpoint above background (ncpm) should be set at the CR value adjusted by any excess dilution factor provided as defined in the following equation:
HHSP = CR f                                                                  [1.1(1)-8] -
 
                                                                                                                      -It-
 
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Beaver Valley Power Station                                  I          -
oedureNuDC 2 .
Unit:      Level Of Use:
1/2    General Skill Reference ODCM: LIQUID EFFLUENTS                                                          Revision:  Page Number:
                                                  .                                    3              17 of 38-where:
HSP='Monitor HIGH-HIGH Alarm Setpoint above background.
CR    Calculated monitor count rate (ncpm) from equation [1.1(1)-7].
f      Maximum acceptable discharge flow rate prior to dilution determined by equation [1.1(1)-6].
Actual maximum discharge flow rate to be maintained for the discharge. The reduced value of f may be due to pump limitations or administrative selection.
8.1.2    BV-2 Monitor Alarm Setpoint Determination This procedure determines the monitor HIGH Alarm Setpoint that indicates if the concentration of radionuclides in the liquid effluent released from the site to unrestricted areas exceeds 10 times the EC's specified in 10 CFR 20, Appendix B (20.1001-20.2402),
Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases or exceeds a concentration of 2E-4 uCi/ml for dissolved or entrained noble gases.( 3 " 6 )
The methodology described in Section 8.1.2.2 is an alternative method to be used to determine the (2SGC-RQ100) monitor HIGH Alarm Setpoint (HSP). The methodology in Section 8.1.2.2 may be used for any batch release and shall be used when the total gamma radioactivity concentration of the liquid effluent prior to dilution exceeds 1.14E-3 uCi/ml.
This concentration is equivalent to-a monitor response and HIGH Alarm Setpoint derived in Section 8.1.2.1 and allows for a tritium concentration of up to 2.16E+0 uCi/ml. The setpoint was obtained by use of a conversion factor of 5.61E-9 uCilmllcpm determined for 1
the nuclide mix.    .6 8.1.2.1      BV-2 Setpoint Determination Based On A Conservative Mix The HIGH Alarm Setpoint for the liquid monitors shall be set at the values listed in the following Table:
BV-2 LIQUID MONITOR SETPOINTS
__Ci/ml Above Background Monitor            DV          HSP          ASP Liquid Waste Effluent Monitor 2SGC-RQ100                1.14E-3      1.14E-3      7.99E-4 Service Water Monitor              2SWS-RQ101        4.28E-5      4.28E-5      2.99E-5 Service Water Monitor                2SWS-RQ102        4.30E-5      4.30E-5      3.01E-5 The setpoint for 2SGC-RQ100 is based on the following conditions, however, the                  I setpoint bases for 2SWS-RQ101 and 2SWS-RQ102 can be found in Calculation Package ERS-ATL-93-021. (3.1.2.6)
 
Procedure Number.
Beaver Valley Power Station                                                  1/2-ODC-2.01
 
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1/2        General Skill Reference ODCM: LIQUID EFFLUENT S
-                                                                          Revision:    Page Number.
* Source terms given in ATTACHMENT A Table 1.1-lb. These source terms (without Zn-65) have been generated by using models and input similar to NUIREG-0017. The inputs are given in 1/2-ODC-3.01. The Zn-65 source term was generated via Calculation Package No. ERS-ATL-93-021.(3 .2.6,313-13)
* Dilution water flow rate of 22,800 gpm = (15,000 gpm BV-1 + 7,800 gpm BV-2).
* Discharge flow rate prior to dilution of 80 gpm for the Liquid Waste Effluent Monitor (2SGC-RQI00).
* A software conversion factor of 5.61E-9 uCi/mllcpm associated with Liquid Waste Effluent Monitor (2SGC-RQ100).(3 .26)
The above setpoint for (2SGC-RQ 100) can be varied based on actual operating conditions resulting in the discharge and dilution flow rates as follows:
HSP  = 4.OOE-6 F                                                                    [1.1(2)-l]
f where:
HSP          Monitor HIGH Alarm Setpoint (uCi/ml) above background.
4.OOE-6    = Proportionality constant based on nominal flow conditions:
4.OOE-6 = 1.14E-3 net uCi/ml x 80 gpm 22,800 gpm F          = Dilution water flow rate, BV-1 plus BV-2 Cooling Tower Blowdown Rate (gpm).
f          = Discharge flow rate prior to dilution (gpm).
8.1.2.1.1        BV-2 Mix Radionuclides The "mix" (radionuclides and composition) of the liquid effluent was determined as follows:
* The liquid source terms that are representative of the "mix" of the liquid effluent were determined. Liquid source terms are the radioactivity levels of the radionuclides in the effluent from ATTACHMENT A Table 1.1-lb.
                        . The fraction of the total radioactivity in the liquid effluent comprised by radionuclide "i" (Si) for each individual radionuclide in the liquid effluent was determined as follows:
Si= Ai                                                              [1.1(2)-2]
Z Ai i
 
I          -I-9
                                                  --    .              Procedure Number. -              -
Beaver Valley Power Station                      -r-r                    1r2-ODC-2.01
 
==Title:==
Unit:        Level Of Use:
I1/2      General Skill Reference_
ODCM: LIQUID EFFLUENTS                                                  Revision:    Page Number:
where:
Ai =Annual release of radionuclide "i" (Ci/yr) in the liquid effluent from ATTACHMENT A Table 1.1-lb.
8.1.2.1.2  BV-2 Maximum Acceptable Concentration (All Radionuclides)
The maximum acceptable total radioactivity concentration (uCi/ml) of all radionuclides in the liquid effluent prior to dilution (Ct) was determined by:
Ct=    F                                      -[1-1(2)-3]-
OECi where:
F      = Dilution  water flow rate (gpm), BV-I plus BV-2 Cooling Tower Blowdown Rate (not including release out through the Emergency Outfall Structure).
22,800 gpm    (15,000 gpm BV-1      +  7,800 gpm BV-2).
f        Maximum acceptable discharge flow rate prior to dilution (gpm).
80 gpm for Liquid Waste Process Effluent Monitor (2SGC-RQ100).
OECi      The ODCM liquid effluent concentration limit for radionuclide "i" (uCi/ml) from ATTACHMENT A Table 1.1-lb. The OEC is set at 10 times the new 10 CFR 20, Appendix B (20.1001-20.2402) Table 2, Col.
2 EC values.
Si      = The  fraction of total radioactivity attributed to radionuclide "i", from' Equation [1.1(2)-2].
8.1.2.1.3  BV-2 Maximum Acceptable Concentration (Individual Radionuclide)
The maximum acceptable radioactivity concentration (uCi/ml) of radionuclide "i" in the liquid effluent prior to dilution (Ci) was determined by:
vCi =Si Ct                                                            --    [1.1(2)-4i 8.1.2.1.4  BV-2 Monitor Display Value The calculated monitor Display Value (uCi/ml) above background attributed to.
the radionuclides; (DV), was determined by:
DV =5.61E-9 Z: C; E;                                                        [1.1(2)-51
 
Beaver Valley Power Station                                              1/2-ODC-2.01
 
==Title:==
Unit:      Level Of Use:
1/2      General Skill Reference ODCM: LIQUID EFFLUENTS                                                      Revision:  Page umbert 1              15 of 39 where:
5.61E-9  = Conversion factor (uCi/ml/cpm), an average determined for the source term mix.
E        = Detection efficiency of the monitor for radionuclide "i" (cpm/uCi/ml) from ATTACHMENT A Table 1.1-lb. If not listed there, from Calculation Package ERS-SFL                                              026 (.1v) 8.1.2.1.5        BV-2 Monitor HSP The monitor HIGH Alarm Setpoint above background (uCi/ml) should be set at the DV value.
8.1.2.2      BV-2 Setpoint Determination Based On Analysis Prior To Release The following method applies to liquid releases when determining the setpoint for the maximum acceptable discharge flow rate prior to dilution and the associated HIGH Alarm Setpoint based on this flow rate for the Liquid Waste Effluent Monitor (2SGC-RQ100) during all operational conditions.
The monitor alarm setpoint is set slightly above (a factor of 1.25) the concentration reading that results from the concentration of gamma emitting radionuclides in order to avoid spurious alarms. To compensate for this increase in the monitor alarm setpoint, the allowable discharge flow rate is reduced by the same factor.
When the discharge flow rate is limited by the radwaste discharge pump rate capacity or by administrative selection rather than the allowable flow rate determined form activity concentration, the alarm setpoint will be proportionally adjusted based upon the excess dilution factor provided.
8.1.2.2.1        BV-2 Maximum Acceptable Discharge Flow Rate The maximum acceptable discharge flow rate (f) prior to dilution (gpm) is determined by:
f=    F                                                                [1.1(2)-6]
1.25  SC; OEC1 where:
F  =  Dilution water flow rate, BV-1 plus BV-2 Cooling Tower Blowdown (gpm).
 
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==Title:==
Beaver Valley Power Station.-
J Pr Unit:
dure Number. S t l/OC.20 I-Level Of Use:
                                                                      .1/2            General Skill Reference  L ODCM: LIQUID EFFLUENTS ODM IUDEFUNS-3                                        Revision:    Page Number 16(of 38 The dilution water flow rate may include the combined cooling tower blowdown flow from both units exiting the discharge structure (but excluding emergency outfall structure flow) when simultaneous liquid discharges from both plants are administratively prohibited.
C=        Radioactivity concentration of radionuclide "i" in the liquid effluent prior to dilution (uCi/ml) from analysis of the liquid effluent to be released.
1.25 =  A factor to prevent spurious alarms caused by deviations in the mixture of radionuclides which affect the monitor response.
OECi    =  The ODCM liquid effluent concentration limit for radionuclide "i" (uCi/ml) from Table 1.I-1b. The OEC is set at 10 times the new 10 CFR 20, Appendix B (20.1001-20.2402)
ATTACHMENT A Table 2, Col. 2 EC values.
8.1.2.2.2    BV-2 Monitor Display Value The calculated monitor Display Value (uCi/ml) above background attributed to the radionuclides; (DV) is determined by:
DV = (1.25) (5.61E-9) Z; C; E;                                            [1.1(2)-7]
where:
E=          The detection efficiency of the monitor for radionuclide "i" (cpml/uCi/ml) from ATTACHMENT A Table '.1-lb. If not listed there, from Calculation Package ERS-SFL                                        .-26.31.22)
                                    . 26.
1.25 =      A factor to prevent spurious alarms caused by deviations in the mixture of radionuclides which affect the monitor response.
5.61E-9    = Conversion factor (uCi/mllcpm), an average determined for the source term mix.
8.1.2.2.3    BV-2 Monitor HSP The liquid effluent monitor HIGH Alarm Setpoint above background (uCi/ml) should be set at the DV value adjusted by any excess dilution factor provided as defined in the following equation:                                                      -
HSP = DV f                                                                  [1-1(2)-8]
 
Procedure Number Beaver Valley Power Station                                    P        N/2-ODC 2 Ol
 
==Title:==
Unit:        Level Of Use:
1/2      General Skill Reference ODCM: LIQUID EFFLUENTSODM IUDEFUNS.I                                            Revision:
                                                                                      -      Page Number:
17 of 38 where:
HSP    = Monitor    HIGH Alarm Setpoint above background.
DV      Calculated monitor concentration reading (uCi/ml) from equation
[1.1(2)-7].
f    = Maximum acceptable discharge flow rate prior to dilution determined by equation [1.1(2)-6].
                            '  =  Actual maximum discharge flow rate to be maintained for the discharge.
The reduced value of may be due to pump limitations or administrative selection.
8.2        Compliance With 10 CFR 20 EC Limits (ODCM CONTROL 3.11.1.1) 8.2.1    Batch Releases 8.2.1.1    Pre-Release The radioactivity content of each batch release will be determined prior to release in accordance with 1/2-ODC-3.03, Table 4.1 1-1. In order to assure representative samples, at least two tank volumes of entrained fluid from each tank to be discharged shall be recirculated through the mixing eductors. This will be accomplished by recirculating the tank contents for at least the time periods indicated in ATTACHMENT B Table 1.2-la and 1.2-lb. BV-1 and BV-2 will show compliance with ODCM Control 3.11.1.1 in the following manner:
The activity of the various radionuclides in the batch release, determined in accordance with 1/2-ODC-3.03, Table 4.11-1, is divided by the minimum dilution flow to obtain the concentration at the unrestricted area. This calculation is shown in the following equation:
Conci    C; R                                                                    [1.2-1]
MDF where:
Conci  =  Concentration of radionuclide "i" at the unrestricted area (uCi/ml).
Ci    =  Concentration of radionuclide "i" in tfte-potential batch release (uCi/ml).
R      =  Release rate of the batch (gpm).
MDF    =  Minimum dilution flow (gpm). (May be combined BV-1/BV-2 flow when simultaneous liquid discharges are administratively prohibited).
 
                                                                                                                  -II-Beaver Valley Power Station                              ~            N/2 OD5 2 Ol
 
==Title:==
Unit      Level Of Use:
1/2    General Skill Reference ODCM: LIQUID EFFLUENSRevision:                                                          Page Number The projected concentrations in the unrestricted area are compared to the OEC's.
Before a release is authorized, Equation [1.2-2] must be satisfied.
Ti (Conci/OECi) < I                                                              [1.2-2]
where:
OECi = The ODCM effluent concentration limit of radionuclide "i" (uCi/ml) from ATTACHMENTATable l.1-laand 1.1-lb. TheOECissetat 10timesthe new 10 CFR 20, Appendix B, (20..1001-20.2402) Table 2, Col. 2 EC vauS(3.1.1.3, 3.1.2.1).
8.2.1.2  Post-Release Following release from the batch tank, the Post Dose Correction Factor will be calculated in the following manner:
PDCF = (VAt)/(DFA)                                                              [1.2-3]
(VIt)/(DFI                                              --
where:
PCDF -            Post Dose Correction Factor.
VAt      =        Actual Volume of tank released (gal).
DFA      =        Actual Dilution Flow during release (gpm).
VIt    -          Initial Volume authorized for release (gal).
DFI      =        Initial Dilution Flow authorized for release (gpm).
The concentration of each radionuclide following release from the batch tank will be calculated in the unrestricted area in the following manner when the Post Dose Correction Factor shown in equation [1.2-3] is >1:
The average activity of radionuclide "i' during the time period of release is divided by the actual dilution flow during the period of release to obtain the concentration in the unrestricted area. This calculation is shown in the following equation:
Concik = Cik Vtk                                                                [1.2-4]
ADFk where:
Concik    =        The concentration of radionuclide "i" (uCi/ml) at the unrestricted
                                -        area, 'during the release period of time k.
 
Procedure Number:
valley Peaver Power Station                                    1/2-ODC-2.o1
 
==Title:==
Unit:        Level Of Use:
1/2        General Skill Reference ODCM: LIQUID EFFLUENTS                                                        Revision:    Page Number.
3                19 of 3-8 NOTE:            Since discharge is from an isolated well-mixed tank at essentially a uniform rate, the difference between average and peak concentration within any discharge period is minimal.
Cik        =      Concentration of radionuclide "i" (uCi/ml) in batch release during time period k.
Vtk        =      Volume of Tank released during time period k (gal).
ADFk      =      Actual volume of Dilution Flow during the time period of release k (gal).
To show compliance with ODCM CONTROL 3.11.1.1, the following relationship must be satisfied:
Ei(Concik/OECQ) < 1                                                            [1.2-5]
8.2.2    Continuous Releases Continuous releases of liquid effluents do not normally occur at BV-I or BV-2. When they do occur, the concentration of various radionuclides in the unrestricted area would be calculated using Equation [1.2-1] with Cik, the concentration of isotope i in the continuous release. To show compliance with ODCM CONTROL 3.11.1.1, Equation [1.2-5] must again be satisfied.
8.3        Compliance With 10 CFR 50 Dose Limits (ODCM CONTROLS 3.11.1.2 And 3.11.1.3)
BV-1 and 2 utilize the concept of a shared liquid radioactive waste system according to NUREG 0133.(3-1.3 ') This permits mixing of the liquid radwaste for processing. Since the resulting effluent release cannot accurately be ascribed to a specific reactor unit, the treated effluent releases are allocated as defined below.
8.3.1    Cumulation Of Doses (ODCM CONTROL 3.11.1.2)
The dose contribution from the release of liquid effluents will be calculated monthly for each batch release during the month and a cumulative summation of the total body and organ doses will be maintained for each calendar month, current calendar quarter, and the calendar year to date. The dose contribution will be calculated using the following equation:
D= UAF Z Ai'r Z m Atk Cik Fk                                                        [1.3-1]
i k=l where:
D= The cumulative dose commitment to the total body or any organ, r, from the liquid effluents for the total time period
 
                                                                                                              -U-Beaver Valley Power Station                                          Procedre  N2jODC-2.01
 
==Title:==
Unit:        Level Of Use:
ODCM: LIQUID EFFLUENTS                                                          Revision:    Page Number.
E Atk (mrem) k--
Atk      The length of the kth release over which Cik and Fk are averaged for all liquid releases (hours).
Cik =The        average concentration of radionuclide, "i"h(uCi/ml), in undiluted liquid effluent during time period Atk from-any liquid release.
Ai      The site related ingestion dose comrmitment factor to the total body or any 'organ
                      'r for each identified principal gamma and beta emitter (mrem-ml per hr-uCi) from ATTACHM4ENT C Table 1.3- 1.
m    =Numnber          of releases contributing to the cumulative dose, Dt.
UAF    =Unit      allocati-on factor. Provides apportionment of dose between BV- I and BV-
: 2. Normally set at 0.5 for each unit. (Must total to <1.0).
Fk  =The        near field average dilution factor for Cik during any liquid effluent release.
Defined as the ratio of the average undiluted liquid waste flow to the product of the average flow from the site discharge structure during the report period to unrestricted receiving waters, times 3. (3 is the site specific applicable factor for the mixing effect of the BV-lI and BV-2 discharge structure).
                          -Waste      Flow (3)(Dilution Water Flow)
The site specific applicable factor of 3 results in a conservative estimate of the near field dilution factor based upon Regulatory Guide 1.1 l.3(L.4 methodology and is a factor of 10 below the limit specified in NUREG-0133, Section 4*3(1.3.)
The dose factor Ai was calculated for an adult for each isotope using the following equation from NUREG-0133.~ 3 3 ~
AiT  =  1.14E5 (730fD + 21BFi)DFi,                                                          [1.3-2]
where:
730      =            Adult water consumption rate (liters/yr).
D  -            Far field dilution factor fromn the near field area within 1/4 mile of the-release point to the potable water intake for adult water consumption.
 
Procedure Number.
Beaver Valley Power Stationi/2-ODC-2.01
 
==Title:==
Unit:        Level Of Use:
1/2        General Skill Reference ODCM: LIQUID EFFLUENTS                                                  Revision:    Page Number 3      -        21 off 38 21    =        Adult fish consumption (kg/yr).
BFi    =        Bioaccumulation factor for radionuclide Fiji in fish from Table A-1 of Regulatory Guide 1.109(3 135) (pCi/kg per pCi/l). However, if data was not available from that reference, it was obtained from Table 6 of UCRL-50564,,3 l 3 )
The bioaccumulation factor for niobium (300 pCi/kg per pCi/l) was not obtained from either of the above references noted. It was otained from IAEA Safety Series No. 57. Justification for use of this value is documented in Appendix A to Calculation Package No. ERS-ATL                              027.(1)
DFi    =        Dose conversion factor for radionuclide "i" for adults for a particular organ T(mremlpCi) from Table E-11 of Regulatory Guide 1.109,( 3 '3 5 )or NUREG-Ol72.( 3 l 3 -7)
A table of Aj, values for an adult at BV-1 and BV-2 are presented in ATTACHMENT C Table 1.3-1.
The far field dilution factor (Dw) for BV-1 and BV-2 is 200. This value is based on a total dilution factor of 600 applicable to the Midland water intake located 1.3 miles downstream and on the opposite bank from BV-I and BV-2 (i.e., 200 = 600 &#xf7; 3). The total dilution factor of 600 represents a conservative fully mixed annual average condition. Since the Midland intake is located on the opposite bank and is below the water surface, essentially fully mixed conditions would have to exist for the radioactive effluent to be transported to the intake.
The cumulative doses (from each reactor unit) for a calendar quarter and a calendar year are compared to ODCM CONTROL 3.11.1.2 as follows:
For the calendar quarter, D, < 1.5 mrem total body                                                          [1.3-3]
D, < 5 mrem any organ                                                              [1.3-4]
For the calendar year, D, < 3 mrem total body                                                              [1.3-5]
D, < 10 mrem any organ                                                              [1.3-6]
If any of the limits in Equation [1.3-3] through [1.3-6] are exceeded, a Special Report pursuant to ODCM Control 3.11.1.2 of 1/2-ODC-3.03 is requried.( 3 l3 2 )
 
I Procedure Number:
Beaver Valley Power Station                                  I            1/2-ODC-2.0i
 
==Title:==
Unit:        Level Of Use:
1/2        General Skill Reference ODCM: LIQUID EFFLUENTS                                                          Revision:    Page Number:
3                2? of 38a 8.3.2      Projection Of Doses (ODCM CONTROL 3.11.1.3)
Doses due to liquid releases shall be projected at least once per 31 days in accordance with ODCM CONTROL 3.11.1.3 and this section. 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 each reactor unit, when averaged over 31 days would exceed 0.06 mrem to the total body or 0.2 mrem to any organ. Doses used in the projection are obtained according to equation [1.3-1]. The 31-day dose projection shall be performed according to the following equations:
When including pre-release data, D 3 1 =[A+B]      31+C                                                                [137 When not including pre-release data, D3'          31+C                                                                    [13-8]
where:
D3= Projected 31 day dose (mrem).
A      Cumulative dose for quarter (nirem).
B      Projected dose from this release (mrem).
T      Current days into quarter.
C = Value which may be used to anticipate plant trends (mrem).
8.4        Liquid Radwaste System The liquid radwaste system has the capability to control, collect, process, store, recycle, and dispose of liquid radioactive waste generated as a result of plant operations, including anticipated operational occurrences. This system also uses some of the components of the steam generator blowdown system for processing.
Simplified flow diagrams of the liquid radwaste systems for BV-1 and BV-2 are provided as ATTACHMENT D Figures 1.4-1 and 1.4-2 respectively. A diagram showing the liquid effluent release points is provided as ATTACHMENT D Figure 1.4-3. A diagram of the site boundary for liquid effluents is provided as ATTACHMENT E Figure 5-1.
Since the concept of a shared liquid radwaste system is used, then any liquid waste generated can be stored, processed and discharged from either BV-1 or BV-2.
 
Beaver Valley Power Station                                  P/2-ODC-2.0l
 
==Title:==
Unit:        Level Of Use:
1/2      General Skill Reference ODCM: LIQUID EFFLUENTS                                                          Revision:    Page Number:
3              23 of 39 8.4.1    BV-1 Liquid Radwaste System Components 8.4.1.1      lLW-TK-2A/2B: High Level Waste Drain Tanks There are two of these tanks, each tank has a capacity of 5,000 gallons. They are located on the northwest wall of the Auxiliary Building (elevation 735'). They receive liquid wastes from the vent and drain system.
8.4.1.2      lLW-TK-3A/3B: Low Level Waste Drain Tanks There are two of these tanks, each tank has a capacity of 2,000 gallons. They are located in the northwest corner of the Auxiliary Building (elevation 735'). They also receive liquid wastes from the vent and drain system.
8.4.1.3        lLW-I-2: Liquid Waste Pre-Conditioning Filter & Demineralizer.
The main purpose of the pre-conditioning filter & demineralizer is to clean liquid waste water of particulate and dissolved radioactive contaminants that is stored in ILW-TK-2A/2B and lLW-TK-3A/3B. There are four resin beds and a pre-conditioning filter associated with this system. The pre-conditioning filter can be customized with varying grades of activated charcoal intended for removal of radionuclides in a colloidal state. Each of the demineralizer beds can be customized with different resins for effective removal of chemical contaminants along with radioactive contaminants. Generally, beds I and 2 contain a Cation Resin and beds 3 and 4 contain a Mixed Bed Resin. This system is located in the Decontamination Building (elevation 735').
8.4.1.3.1        An evaporator (6 gpm) was originally used to process liquid waste at Unit 1.
However, this evaporator was retired prior to initial issue of the ODCM, because of concerns for creating a mixed-waste.
8.4.1.4        lLW-TK-7A/7B: Steam Generator Drain Tanks There are two of these tanks, each tank has a capacity of 34,500 gallons. They are located in the Fuel Pool Leakage Monitoring Room (elevation 735'). They normally receive liquid waste that has been processed through the liquid waste demineralizer.
These tanks can also receive liquid waste from Unit 2. Upon completion of filling operation, the tank is placed on recirculation through the demineralizer until the radioactivity concentration is acceptable for discharge. A minimum of two tank volumes must be recirculated prior to sampling for discharge permit preparation..
8.4.1.5      RM-lLW-104: Liquid Waste Discharge Radiation Monitor This off-line gamma scintillator radiation monitor continuously analyzes liquid waste as it is being discharged. The upper activity alarm on this radiation monitor has a setpoint that would indicate we are approaching OEC limits for radioactive water
 
Beaver Valley Power Station                                .
IProcedure Number:
                                                                                          - 1/2-ODC-2.01I
 
==Title:==
Unit:        Level Of Use:
1/2    l  General Skill Reference .L_
ODCM: LIQUID EFFLUENTS                                                          Revision:      Page Number.
3    I          24of 38        -
leaving the site. If an upper activity alarm on this radiation monitor is received, it automatically terminates the discharge by closing the discharge line isolation valve.
8.4.2      BV-1 Laundry and Contaminated Shower Drain System Components 8.4.2.1    -LW-TK-6A/6B:        Laundry and Contaminated Shower Drain Tanks There are two of these tanks, each has a capacity of 1200 gallons. They are located in the northwest corner of the Auxiliary Building (elevation 722'). They receive laundry and contaminated shower drains waste from the Service Building. These tanks can also receive mop water waste from Unit 2. The waste in these tanks is not sent to the liquid waste demineralizer for cleanup because this waste may contain organic compounds that will deplete a resin bed. Upon completion of filling operation, the tank must be recirculated a minimum of two tank volumes prior to sampling for discharge permit preparation.
8.4.2.2      RM-ILW-1 16: Laundry and Contaminated Shower Drains Tank Discharge Radiation Monitor This off-line gamma scintillator radiation monitor continuously analyzes laundry and contaminated shower drains waste as it is being discharged. The upper activity alarm on this radiation monitor has a setpoint that would indicate we are approaching OEC limits for radioactive water leaving the site. If an upper activity alarm on this radiation monitor is received, it automatically terminates the discharge by closing the discharge line isolation valve.
8.4.3      BV-2 Liquid Radwaste System Components 8.4.3.1      2LWS-TK21A/21B: Waste Drain Tanks There are two of these tanks, each tank has a capacity of 10,000 gallons. They are located in the northeast corner of the Auxiliary Building (elevation 710'). They receive liquid wastes from the vent and drain system. These tanks can also receive liquid wastes from Unit 1. IF further. processing is not necessary, THEN it may be placed on recirculation. A minimum of two tank volumes must be recirculated prior to sampling for discharge permit preparation.
8.4.3.2      2SGC-IOE21A/21B: Steam Generator Blowdown Cleanup Ion Exchangers The main purpose of the ion exchangers is to clean liquid waste water of particulate and dissolved radioactive contaminants through an ion exchange process. There is a resin bed, outlets strainer, and cleanup filter associated with each of these ion exchangers. They are located in the Waste Handling Building (elevation 722').
8.4.3.2.1        Two evaporators (20 gpm each) were orignially used to process liquid waste at Unit 2. However, this evaporator, was retired prior to initial issue of the ODCM, because of concerns for creating a mixed-waste.
 
Beaver Valley Power Station                                  edurNu2-ODC-2.01
 
==Title:==
Unit:      Level Of Use:
1/2      General Skill Reference ODCM: LIQUID EFFLUENTS                                                    Revision:  Page Number:
3              25 of 38 8.4.3.3    2SGC-TK23A/23B: Steam Generator Blowdown Test Tanks There are two of these tanks' each has a capacity of 18,000 gallons. They are located in the Auxiliary Building (elevation 755'). They receive liquid waste that has been processed through the cleanup ion exchangers. Upon completion of filling operation, the tank is placed on recirculation through the demineralizer until the radioactivity concentration is acceptable for discharge. A minimum of two tank volumes must be recirculated prior to sampling for discharge permit preparation.
4 8..4.3.4  2SGC-TK21AI21B: Steam Generator Blowdown Hold Tanks There are two of these tanks, each has a capacity of 50,000 gallons. They are located ia theWaste Handling Building (elevation 722'). These tanks are used to store liquid waste when the radioactive concentration of the steam generator blowdown test tank is not acceptable for discharge.. These tanks can also receive liquid wastes from Unit 1. The contents of this tank may be drained or processed through the Unit 1 or Unit 2 Liquid Radwaste Treatment System until the radioactivity concentration is acceptable for discharge. A minimum of two tank volumes must be recirculated prior to sampling for discharge permit preparation.
8.4.3.5    2SGC-RQ100: Liquid Waste Effluent Monitor This off-line gamma scintillator radiation monitor continuously analyzes liquid waste as it is being discharged. The upper activity alarm on this radiation monitor has a setpoint that would indicate we are approaching OEC limits for radioactive water leaving the site. If an upper activity alarm is received, it automatically terminates the discharge by closing the discharge line isolation valves.
                                                          - END -
 
                                                                                                    - LK-Procedure Number.
Beaver Valley Power Station                              ODC-2.01
 
==Title:==
Uni          Level Of Use:
                                                                .1/2      General Skill Reference ODCM: LIQUID EFFLUENTS                                      Revision:    PageNumber.
ATTACHMENT A Page 1 of 4 LIQUID SOURCE TERMS TABLE 1.1-la BV-1 LIQUID SOURCE TERM E;
(3)
DEIECI1N ANNUALRELEASE          OEC;              EFFEIR4CY NUCLIDE Cr-51              13E-3              5E&3                    1.18E+7 Mn-54              3.1E4              3E-4                    8.59E+7 FE-55              1.6E-3              1E-3                      (5)
Fe-59              83E-4              1E-4                  9.17E+7 Co-58              1.4E-2            2E-4                    1.16E+8 Co-60              2.0E-3            3E-5                    1.73E+8
            .r,465(3.1.3.13)    2.69E-2            5E-5                    4.67E+7 Np-239              1.4E-4            2E4                    &49E+7 Br-83              251-S              9E-3                    1.36E+6 Br-84              25135              4133                    9.75E+7 Br-85              2.7E-6              (5)                  6.19E+6            -I Rb-86              7.5-5              7E-5                        (5)
Sr-89            29134              8E-5                      (5)
Sr-90            1.1E-5              5E-6                      (5)
Y-90              9.4E-6              7E-5                      (5)
Y-91m              8.7E-6              2E-2                  8.98E+7 Y-91              5.7E-5              8E-5                  2.60E+5 Y-93              7.4E-7              2E4                        (5)
Zr-95            5.11E-5            2E-4                  8.60E+7 Nb-95              5.2E-5              3E4                  8.64E+7 Sr-91            1.3E-5              2E4                  6.97E+7 Mo-99              l.lE-2              2E-4                  2.84E+7 Tc-99m              1.1E-2              1E-2                  8.96E+7 Ru-103              3.4E-5              3E4                    9.5E+7 Ru-106              1.0E-5              3E-5                      (5)
Rh-103m              3.4E-5              6E-2                      (5)
Rh-106              1.0E-5              (5)                      (5)
Te-125m              2.5E-75            2E4                  1.83E+5 Te-127m              2.6E4              9E-5                  4.09E+4 Te-127              2.7E-4              1E-3                  1.38E+6 Te-129m              l.1E-3              7E-5                  4.02E+6 Te-129              6.7E4              4E-3                  1.12E+7 I-130            1.2E-4              2E-4                  3.08E+8 Te-131m              1.6E-4              8E-5                  1.8213+8 Te-131                3E-5              8E-4                  1.2013+8 I-131              1.6E-1            1E-5                  1.11E+8 Te-132              4.3E-3              9E-5                  1.17E+8 I-132            4.9E-3              1E-3                  2.66E+8 1-133            4.0E-2              7E-5                  9.90E+7
 
w      .E                            ,,.                              .Procedure                Number:
Beaver Valley Power Station                                  -              1/2-ODC-2 .
 
==Title:==
Unit:        Level Of Use:
1/12      General Skill Reference ODCM: LIQUID EFFLUENTS                                                                Revision:    PageNumber ATTACHMENT A Page 2 of 4 LIQUID SOURCE TERMS I-134                    8.OE-5                      4E-3                    2.70E+8 Cs-134                  4.6E-2                        9E-6                    1.99E+8 1-135                  4.3E-3                        3E-4                    1.19E+8 Cs-136                    8.9E-3                      6E-5                    2.80E+8
                    'Cs-137                    3.3E-2                      1E-5                    8.01E+7 Ba-137m                    3.1E-2                    .lE-5'                    8.01E+7 Ba-140                    l.lE-4                      8E-5                    4.37E+7 La-140                    l.lE-4                      9E-5                    2.OOE+8 Ce-141                    5.1E-5                      3E-4                    5.07E+7 Ce-143                    2.8E-6                      2E-4                    7.27E+7 Ce-144                    3.2E-5                      '3E-5                    1.06E+7 Pr-143                    2.7E-5                      2E-4                    1.04E+O Pr-144                    3.2E-5                      6E-3                    2.25E+6 H-3                  5.50E+2                        1E-2                        (5)
TOTAL"-                          4.05E-1
(')    Excluding Tritium and Entrained Noble Gases (2)    Source Term for (RM-1LW-104 and RM-lLW-1 16) from Stone and Webster Calculation Package -UR(B)-160 (3'Lt6)
(3)    ODCM Effluent Concentration Limit = 10 times the EC values of 10 CFR 20 ('')
(4)    Detection Efficiency for (RM-lLW-104 and RM-lLW-1 16) from Calculation Package ERS-SFL-92-039        0 14)
  ,      Insignificant
 
                                                                                                          -I-UL Procedure Number.
Beaver Valley Power Station                                    1/2.ODC-2..1
 
==Title:==
Unit:        Level Of Use:
1/2        General Skill Reference ODCM: LIQUID EFFLUENTS                                        Revision:    Page Number:
3        28 of            I ATTACHMENT A Page 3 of 4 LIQUID SOURCE TERMS TABLE 1.1-lb BV-2 LIQUID SOURCE TERM (2)                                            (4)
(3)
DETECTION ANNUAL RELEASE          OEQ                    EFFICENCY NUCLIDE                  La-Cr-51                1.00E-4              5E-3                      2.01E+7 Mn-54                250E-5              3E-4                      127E+8 Fe-55                130E-4              1E-3                          (5)
Fe-59                650E-5              1E-4                      126E+8 Co-58                1.10E-3              2E34                      1.82E+8 Cof60                1.60E4              31-5                      2.38E+8 (3.1.3. 13) 5.10E-2              5E-5                      6.50E+7 Np-239                3.20E-5              2E14                      1.65E+8 Br-83                290E-5              9E-3                      2.42E+6 Br-84                5.90E-9              4E-3                      138E+8 Rb-86                3.70E-5              71-5                      1.04E+7 Sr-89              2.20E-5              8E-5                      1.83E+4            I Sr-90              850E-7              51-6                          (5)
Sr-91              5.30E-6              2E-4                      1.04E+8 MO-99                2.30E-3              2134                      4.47E+7 Tc-99m                2.10E-3              1E-2                      1.4OE+8 Te-125m                1.90E-6              2E-4                      3.94E+5 To-127m                2.10E-5              9E-5                      126E+5 Te-127                2.50E-5              1E-3                    2.43E+6 Te-129n                8.20E-5              7E15                      653E+6 Te-129                5.30E-5              4E-3                      196E+7 1-130              230E-4              2E-4.                    5.18E+8 Te-131m                5.2E-5                8E-5                    2.85E+8 Te-131                9.40E-6              8E-4                      1.88E+8
              - I131              1.00E-1              lE-5                      1.96E+8 To-132              7.80E-4              913-5                    1.76E+8 I-132              230E-3                1E-3                    422E+8 I-133              6.50E-2              7E-5                      1.73E+8 1-134              4.60E-6              4E-3                      4.06E+8 Cs-134              3.OOE-2              9E-6                      32 5E+8 1-135              9.20E-3              3E-4                      1.71E+8 Cs-136              3.90E-3              6E-5                      4.28E+8 Cs-137              2.20E-2              1E.-5                    1.28E+8 Ba-137m                2.10E-2              11E-5                    133E+8 Ba-140              930E-6                8E-5                      750E+7 La-140                8.40E-6              9,-5                      3.08E+8
 
                                                                  -  ~Procedure Number:
Beaver Valley Power Station                                          1dureDumber:
12-ODC-2.01
 
==Title:==
Unit:            Level Of Use:
1/2          General Skill Reference' ODCM: LIQUID EFFLUENTS                                                  Revision:        Page Number:
                                                                              -3                  29 of 38 ATTACHMENT A Page 4 of 4 LIQUID SOURCE TERMS TABLE 1.1-lb (continued)
BV-2 LIQUID SOURCE TERM (2)                                      (4)
Ai                                      Ei (3)
ANNUAL                              DETECTION RELEASE                OECQ        EFFICENCY NUCLIDE              .(,Ci)  -        (uCi/mI          (cpmluCilml)
Y-90              6.OOE-7              7E-5 Y-91m              3.60E-6              2E-2              1.59E+8 Y-91              4.40E-6              8E-5            -3.55E+5 Y-93              3.00E-7              2E-4              2.03E+7 Zr-95            4.OOE-6              2E-4              1.35E+8 Nb-95              4.OOE-6              3E-4              1.33E+8 Ru-103            2.70E-6              3E-4              1.71E+8 Ru-106            8.20E-7              3E-5                  (5)
Rh-103m            2.70E-6              6E                (5)
Rh-106            8.20E-7                                  5.65E+7 Ce-141            4.OOE-6              3E-4              7.75E+7 Ce-143            8.60E-7              2E-4              1.20E+8 Ce-144            2.60E-6              3E-5              1.87E+7 Pr-143            2.30E-6              2E4                1.63E+0 Pr-144            2.60E-6              6E-3              3.40E+6 H            5.50E+2              1E-2                  (5)
TOTAL(')            2.40E-1 (I)  Excluding Tritium and Entrained Noble Gases (2)
Source Term for (2SGC-RQ100) from Computer Code LIQ1BB (3.1.23)
(3)  ODCM Effluent Concentration Limit = 10 times the EC values of 10 CFR 20 (3-1-2-1)
(4)
Detection Efficiency for (2SGC-RQ 100) from Calculation Package ERS-SFL-86-026              (3.1.2.2)
(5)
Insignificant
 
                                                                                                                                                  - U--
Beaver Valley Power Station
_ _ _  I uwNuu!  1 /2 -O D C -2 .0 1
 
==Title:==
Unit:      I Level Of Use:
1/2      _
General Skill Reference Revision:    Page Number.
ODCM: LIQUID EFFLUENTS
                                                                                                          .I              0 of 39 ATTACHMENT B Page 1 of 2 RECIRCULATION TIMES TABLE 1.2-la BV-I RECIRCULATION TIMES REQUIRED BEFORE SAMPLING OF LIQUID DISCHARGE TANKS APPROXIMATE RECIRCULATION TIME(')
TANK DESCRIPTION                              ASSET NO.                (Based on Historical Recirculation Rates)
Laundry And Contaminated                        ILW-TK-6A/6B          2.5 hrs - (1200 gal) (2) (16 gpm)
Shower Dain Tanks Low Level Waste Drain Tanks                    lLW-TK-3A/3B          1.5 hrs = (2000 gal) (2) / (45 gpm)
High Level Waste Drain Tanks                    ILW-TK-2A/2B          3.4 hrs = (5000 gal) (2) / (50 gpm)
Respirator Test Tanks                          ILW-TK-5A/5B          1.4 hrs = (3000 gal) (2) / (73 gpm)
Steam Generator Drain Tanks                    lLW-TK-7A/7B          17.2 hrs -(35000 gal) (2)/(68 gpm)
                                                                                                                                            ,, wN Boron Recovery Test Tanks                      IBR-TK-2A/2B          9.7 hrs =(13,000. gal) (2)/(45 gpm)
(l)  The times listed are those approximated for two recirculations of a full tank with one recirculation pump in operation (using historical recirculation rates). Recirculation times for a partially full tank are directly proportional to the fraction of the tank. capacity-occupied by the entrained liquid waste (after isolation). Actual recirculation times are determined prior to sampling using actual tank volumes and actual recirculation rates available in the BV-1 Control Room.
 
Beaver Valley Power Station                                    ProcedureNui2-DC      2 Ol
 
==Title:==
Unit:      Level Of Use:
1/2    General Skill Reference ODCM: LIQUID EFFLUENTS                                                          Revision:  PageNumber.
3              31 of 38 ATTACHMENT B Page 2 of 2 RECIRCULATION TIMES TABLE 1.2-lb BV-2 RECIRCULATION TIMES REQUIRED BEFORE SAMPLING OF LIQUID DISCHARGE TANKS APPROXIMATE RECIRCULATION TIME(')
TANK DESCRIPTION                ASSET NO.              (Based on Historical Recirculation Rates)
Liquid Waste Tanks              2LWS-TK21A/21B          11.5 hrs = (10,000 gal) (2)/(29 gpm)
Steam Generator Blowdown        2SGC-TK21A/21B          25.8 hrs = (51,000 gal) (2)/(66 gpm)
Hold Tanks Steam Generator Blowdown        2SGC-TK23A/23B          9.1 hrs = (18,000 gal) (2)/(66 gpm)
Test Tanks (I?  The times listed are those approximated for two recirculations of a full tank with one recirculation pump in operation (using historical recirculation rates). Recirculation times for a partially full tank are directly proportional to the fraction of the tank capacity occupied by the entrained liquid waste (after isolation). Actual recirculation times are determined prior to sampling using actual tank volumes and actual recirculation rates available in the BV-2 Control Room.
 
        -IProcedur                                                      I          eNumber:            .
Beaver Valley Power Station                                Poeue12OC2O
 
==Title:==
Unit:            Level Of Use:
1J2        1General Skill Reference .
ODCM: LIQUID EFFLUENTS                                                    Revision:        Page NumberJ ATTACHMENT C Page 1 of 3 INGESTION DOSE COMMITMENT FACTORS TABLE 1.3-1 Ait VALUES FOR THE ADULT FOR THE BEAVER VALLEY SITE (mrem/hr per uCi/ml)
NUCIUDE      BONE      LIVER    T-BODY          THYROID  KIDNEY              LUNG              GqlU H-3        0.002-01  270601    2702-01        2702-01  2702-01            2.70E-01        270201 C-14        3.13E04    626E03    626203        626E03    626203            626E03          626E03 Na-24      4.0802:    4.08E02    4.08E02        4.08E02  4.08E02            4.08E02Q        4.08E02 P-32        4.62E07    287E06    1.79E06      - 0.0001    O.OOE;01          0.00EO01        5.19E06 Cr-51      0.00E201  0.0001    127200        7.62E-01  281E01              1.69E00        321E02 Mn-54      0.0001    438E03    835E02        0.OOE-01  130E03            O.OOE01          134E04 Mn-56      0.00E-01  1.10E02    195EOI        O.OOE-01  1.40E02            O.OOE-01        352E03 Fe-55      6.59E02    456E02    1.06E02        O.OOE01  0.00E01            254E02          261EO2 FE-59        1.04E03  245E03    938E02        0.002-01  0.002-01          6.83E02          &15E03 Co-57      O.OOE-01  2IOE01    350E01        0.OO2)01  O.OD1301          0.002-01        533EO2 Co-58      O.O01      8.95EO1    2OE102        O.OOE0O1  O.OO-01            O.OO-01            1S2E03 Co60        0.OOEO1    25?E02    5.67E02        O.OOW00 1 O.00E201          0.001301        4.83E03 N-63        3.12E04    2.16E03    1.05E03        O.OO;0O1  O.OO-01            0.002-01        451E02 Ni65        1.27E02  1.65E01    751EOO        O.OO-01  O.OO-01            M.OOE-OI        417E02 Qi-64      QO.O201    1.0E01    4.70E00        O.OOE0-1  252E01            O.ODE-01        &53E02 Zh65        232E04    737E04    333E04        0.02-01  493E04            O.OOE-01        4.64E04 Zh-69      4-93E01    9.43E01    656EOO        0.002-01  6.13E01            0.00601          1.42E01 Br-83      0.00201    0.0001    4.04E01'      0.0E}0    0.00E0I            0.002-01        5.82E01 Br-84      0.00201    0.00-01    524EO1        O.OOEO1'. 0.002-01          0.00-01          4.11E-04 Br-85      O.OOEO01  0.0E-01    215EOO        0.00E3 01 O.OOEOI            0.00601          O.OO-01 Rb-86      0.002-01  l.01E05    4.71E04        O.OOE0O1  O.OOEOI            O.OOE-01        199E04 Rb88        0.00-01    29OE02    154E02        0.00-01  O.OOE-01          0.00FLO1        4.00E-09 Rb-89      0.00E-01  1.92EO2    135E02        0.00-01  00M01              0.00-01          1.122-11 Sr-89      222E04    O.OOE-01  639E02        O.OOE-01  0.0001            0.001301        357E03 Sr-90      5.48E05    0.02-01    134E05        0.002-01  O.OOE-01          O.OOE-01        158E04 Sr-91      4.10E02    O.OOE-01  1.65EO1        O.OOE001  0.00)01            O.OE-01          195E03 Sr-92        155E02    0.00601    6.72E00        0.00201  0.00201            0.0OE-01        3.08E03 Y-90        5.802-01  0.002-01  155E-02      -0.00-01    O.O0E01            0.002-01        6.15E03 Y-91m      5.48E-03  O.OO-01    212E204  -O.OOE-01      0.0001            0.00-01          1.61E-02 Y-91        850E00    0.00E 2Z7201        O.OOE-01  0.00-01            0.00-01          4.68E03 Y-92        5.09E-02  O.OOE0-1  1.49E-03      O.OOE-01  0.00-01            0.002-01        892E02 Y-93        1.62S01  0.00-01    4.46E-03      0.00E01  O.00201            0.0Q-01          5.12E03 Zr-95      253E-01    811E-02    5.49E-02      0.00F201  1272.01            0.00E-01        257EO2 Zr-97        1.40602  282E-03    129E-03        0.00201  426203            O.OOE0-1        &73EO2 Nb-95      4.47E00    249E00    134EOO        O.O0OE01  246E00            0.002-01        151E04 Nb-97      3.75EO2    9.49E-03  3.462-03      O.OOE1    1.11E-02          0.00-01          350EO1
 
Beaver Valley Power Station                                                              Po2u              1      DC-2.01
 
==Title:==
Unit:                Level Of Use:
1/2              General Skill Reference K> ODCM: LIQUID EFFLUENTS                                                                                  Revision:            Page Number:
1 3                          33 of 38 ATTACHMENT C Page 2 of 3 INGESTION DOSE COMMITMENT FACTORS TABLE 1.3-1 Ait VALUES FOR THE ADULT FOR THE BEAVER VALLEY SITE (mremthr per uCi/ml)
NUMCDE      BONE            IVER                    T-BODY          THYROID          KIDNEY                    LUNG              GI-LI Mo-99    O.OOE0-1      1.05E102                  200E01            O.OOE--01        2.38E02                0.OOE-01            2.43E02 Tc-9in    8971303      254E-02                    3231-01          O.OOE-01          3.8513-01              124E-02            150E01 Tc-101    923E-03      133E-02                    130E01          O.OOE01          239E-01                6.791-03            4.00E-14 Ru-103    451EOO        0.00E-O1                '94ECO0              0.O0EO1          1.72E01            '0.COE-01              526E012 R-l105    3.75E-01      O.OOE00      1            1.48E01          O.OOE00 1        4.85EOO                O.OOE0-1            229E02 Ru-106    6.70E01      O.OOE0-1                  &48E00            0.001301          1.29E02                0.00E01            434E03 Ag-1Orn  9.48E301      8.771301                  521E-01          0.001-01          1.72EOO                O.OOE0-1            358E02 Sb-124    7.87E 00      1.49E-01                  3.12EOO          191E-02          O.OOE00    1          6.13E00            223E02 Sb-125    5.03EOO1 5.62E-02                        120E00          5.11E103          O.OOE0-1              3.88E00            554EO1 Te-125m  257E03        930E02                    3.44E102          7.72E02          1.04E04                O.OOE00    1        1.03E04 Te.127m  6.49E03      232E03                    790E02            1.66E03          263E04                O.OOE00    1        217E04 Te-127    1.05E02    .3.78E01                    2.28E01          7.81E01          4.29E02                0.00-01            832E03 Te-129m  1.10E04      4.11E03                    1.74E03          3.78E03          4.60E04                    O.ME1          555E04 Te-129    3.01E01      1.13E01                    733E00            231E01            1266E02                O.OOE0-1            227EO1 Te-131m  1.66E03      8.10E02                    6.75E02          128E03            821E03                O.OOE-01            8.05E04 Te-131    1.89E01      7.88E00                    596E00            155E01            827EOI                O.OOE0-1            2.67EOO Te-132    2.41E03      1561303                    1.47E03          1.72E03          150E04                O.OOE-01            739E04 Te-134    3.10E01      2.03EO1                    1255E01          2.71E01          196E02                O.OO301            3.44E-02 1-129    1.19E02      1.02E102                  335E02            263E105          219E102.              0.00-01            1.61E01 I-130    2.75E01      8.10E01                    320EO1            6.87E03          126E02                0.0013.01          697EOI I-131    1511E02      2.16E02                    124E02          7.081304          3.71E02                0.00E01            5.70E01 M132      737E00        197E01                    6.90E100          6.90E02          3.14E01                  0O.OOE-01        3.71EO1 1-133    5.16E01      897EO13                    2.74E01          132E04            1.57E02                O.OOE0-1            8.06E01 1-134    3.85E00      1.05E01                    3.74E00          1.81E02          1.66E01                O.OOE00    1        9.12E103 M135      1.61E01      421E01                      1;55E01          278E03            6.76E01                0.OOE-01            4.76E01 Cs-134    2.98E05      7.09E05                    5.79E105          O.O-011          229E05                7.61E04            124E04 Cs.136    3.12E04        1233E05                    8.86E04          0.001301          6.85E04                939E03              1.40E04 Cs-137    3.82E05      522E05                    3.42E05          0.001-01          1.77E105              5.89E04            1.01E04 Cs-138    264E02        522E02                    2.59E02          O.OOE0-1          3.84E02                3.79E01            2231303 Ba-139    9.691301      690E-04                    284E-02          0.0013O01        6.45E-04              392E-04            1.72EOO Ba-140    203E02        255E-01                    133EO1          0.0013O01        8.66E-02                1.46E-01          4.18E02 Ba-141    4.711301      356E104                      159102          O.OOE0-1          331E-04                2.02E-04            2221-10 Ba-142    213E101-      219E104                      134E102        O.OOE-01          18E304                124E-04            3.001-19 La-140    1511301      759E-02                    2011E302        O.OOE-01          O.OOE0-1              O.OO0131            557E03 La-142    7.711-03      351E-03                    &74E04- - 0.00O-01                O.OOO13                0.001E01            256EOI Ce-141    263E-02        1.78E-02                  2021303          O.OOE-101        826303                0.001-01            6.80E01
 
                                                                                                                -II-Procedure Number Beaver Valley Power Station                                      1/2-ODC-2.01 t
 
==Title:==
Unit:            Level Of Use:
1/2        General Skill Reference Revision:        Page Number.
ODCM: LIQUID EFFLUENTS I          34 of 38 ATTACHMENT C Page 3 of 3 INGESTION DOSE COMMITMENT FACTORS TABLE 1.3-1 Ait VALUES FOR THE ADULT FOR THE BEAVER VALLEY SITE (mremlhr per uCi/ml)
NUCLIDE    BONE        LIVER  T-BODY    THYROID  KIDNEY            LUNG            GI-IJI Ce-143    4.64E03    3.43E100  3.79E04    0.001E-01 151E-03          0.OOE-01        1288E02 CO-144    137E00    5.73E-01  736E-02    0.00E101  3.40E-01        0.0013-01        4.64E02 Pr-143    554E-01    2221E01  275E-02    0.00E-01  128E-01          0.00E-01        243E03 Pr-144    1.81E03    753304    922E05    0.00E-01  425304          0.00E-01        261E-10 Nd-147    3.79301    438E01    2.62E02    0.00E-01  256E301          0.001-01        2.10E03 W-187    296E02    2.47E102  8.65E01    0.0013-01 0.00E-01        0.0013-01        8.10E04 Np-239    2.90E-02  2.8513-03 15713.03  0.00E-01  8.8913-03        0.00E-01        5.85E02
                                                                                                          .,_/
 
Beaver Valley PProcedure                                                      Number.
yPower Station                                                1/2-ODC-2.01
 
==Title:==
Unit:          Level Of Use:
1/2        General Skill Reference ODCM: LIQUID EFFLUENTS                                                              Revision:      Page Number
                                                                                          -3                '35 of 19 ATTACHMENT D Page 1 of 3 LIQUID RADWASTE SYSTEM STREAM                    UNIT 1: COLLECTION, TREATMENT, & DISCHARGE Containment Sump        Waste Drains Tanks                                      Effluent Radiation        BVPS-2 Liquid Waste Ion Exchanger Pre-filter              Monitor              Cooling Aux Bldg Sumps          I LW-TK-2A/2B                and Resin Beds                                      Tower 5,000 gal/tank                                          RM-ILW-104              Blowdown Laboratory Drains                                ILW-[-2-1, ILW--2-2,.              35 gpm              7,800 gpm I LW-TK-3A/3B            I LW-l-2-3, ILW-1-2-4 F.
Reactor Plant Samples    2,000 gal/tank                                                                          BVPS-l.
Cooling .
Miscellaneous Sources    Steam Generator                                                                r    I  Tower Blowdown Tanks                                                                          Blowdown 15,000 gpm 1LW-TK-7Af7B 34,500 gal/tank Steam Gen. Pre-filter Backwash From Unit 2:
2LWS-TK21A/21B 2SGC-TK23A/23B See Attachment D page 2 of 3 I                        VI To Unit 2 GO TO Attachment D page 2 of 3 F
Effluent Radiation Laundry and                - Laundry                                                                      BVPS I&2 Monitor Contaminated              Drains Tanks                                                                    Combined Shower Drains                                                            RM-ILW-l 16                    Cooling Tower ILW-TK-6A/6B                                                                    Discharge Point 1200 gal/tank                                      15 gpm 22,800 gpm LIQUID WASTE DISCHARGES TO BVPS-1 COOLING TOWER BLOWDOWN AND ENVIRONMENT
 
Beaver Valley Power Station -                                                          II Procedure Number 1/2-ODC-2.01
 
==Title:==
Unit:            Level Of Use:    e  n 1/2 I
General Skill ReferenceI ODCM: LIQUID EFFLUENTS                                                                                          Revision:        Page Number.
___________________________________________________                                                            A        1    1          16 nf3R ATTACHMENT D Page 2 of 3 LIQUID RADWASTE SYSTEM STREAM                                            UNIT 2: COLLECTION, TREATMENT, & DISCHARGE.
To Unit 1 GO TO Attachment D Page 1of 3
                                                                      *R
                                                                                                          .I
(
                                                      .        -
* Steam Generator Containment Sump                                  LiquidWaste                                                                          BVPS-l Liquid Waste Ion                    Condensate              Cooling Drains Tanks                Exchanger                        Test Tanks Aux Bldg Sumps                                                                                                                          Tower Pre-filter and Resin Beds 2LWS-TK21A/21B                                                                            Blowdown 4-    2SGC-TK23A/23B Miscellaneous Sources                            10,000 gal/tank        2SGC-IOE21A/21B                                              15,000 gpm 18,000 gal/tank Reactor Plant Samples                                                                                                                        BVPS-2 Cooling Steam Generator Laboratory Drains                                Condensate                                                                                  Tower I,                      Blowdown Hold Tanks Condensate                                                                                                                                    7,800 gpm Effluent Radiation Demineralizer                                2SGC-TK2 1A/2 I B                                                    Monitor Rinse Water                                    50,000 gal/tank 2SGC-RQ I00 80 gpm From Unit 1:
lLW-TK-7A/7B                            I          Sump          I See Attachment D page I of 3 BVPS 1&2 Combined Cooling Tower Discharge Point 22,800 gpm LIQUID WASTE DISCHARGES TO BVPS-2 COOLING TOWER BLOWDOWN AND ENVIRONMENT
 
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RTL #A9.621B Beaver Valley Power Station Unit 1/2 1/2-ODC-2.02 ODCM: GASEOUS EFFLUENTS Document Owner Manager, Radiation Protection Revision Number                                          1 Level Of Use                                    In-Field Reference Safety Related Procedure                                Yes
 
Procedure Number Beaver Valley Power Station                                                                    1/2-ODC-2.02
 
==Title:==
Unit:        Level Of Use:
1/2          In-Field Reference ODCM: GASEOUS EFFLUENTS                                                                        Revision:    Page Numbec I 1                    2of 129 TABLE OF CONTENTS 1.0  PURPOSE ..................................                                                                                            4 2.0  SCOPE ..................................                                                                                              4
 
==3.0  REFERENCES==
AND COMMITMENTS ................................                                                                            4 3.1 References .................................                                                                                      4 3.2 Commitments ...                        ..............................                                                              6 4.0 RECORDS AND FORMS ................................................................................................................. 6 4.1 Records ...............................                                                          .6 4.2 Forms .................................                                                                                            6 5.0 PRECAUTIONS AND LIMITATIONS ................................                                                                            6 6.0 ACCEPTANCE CRITERIA .................................                                                                                    7 7.0 PREREQUISITES .................................                                                                                          8 8.0 PROCEDURE .................................                                                                                              8 8.1  Alarm Setpoints ...............................................                                                                  8 8.1.1          BV-1 Monitor Alarm Setpoint Determination ...............................................                          8 8.1.2          BV-2 Monitor Alarm Setpoint Determination ..............................................                          17 8.1.3          BV-1/2 Monitor Alarm Setpoint Determination .............................................. 27 8.2  C c With 10 CR20DoseRateLimits (ODCM CONITROL3.112.1) .                                            .....................................
34 8.2.1          Dose Rate Due To Noble Gases .............................................. 34 8.2.2          Dose Rate Due To Radioiodines And Particulates .............................................. 41 8.3 Compliance With 10 CFR 50 Dose Limits (ODCM CONTROLS 3.11.2.2 And 3.11.2.3)
(Gaseous) .45 8.3.1          Dose Due To Noble Gases ..............                                                                          45 8.3.2          Dose Due To Radioiodines And Particulates ..............                                                        52 8.4 Gaseous Radwaste System ..............                                                                                          67 8.4.1          BV-1 Gaseous Radwaste System Components ..............                                                          67 8.4.2          BV-2 Gaseous Radwaste System Components ..............                                                          68 ATTACHMENT A GASEOUS SOURCE TERM ..............                                                                                            70 ATTACHMENT B GASEOUS EFFLUENT MONITOR DETECTION EFFICIENCIES .............. 72 ATTACHMENT C MODES OF GASEOUS RELEASE ..............                                                                                      74 ATTACHMENT D RADIONUCLIDE MIX ..............                                                                                              75 ATTACHMENT E            DISTANCES            TO  RELEASE          POINTS    ..............                                            77 ATTACHMENT F 0-5 MILE DISPERSION PARAMETERS ..............                                                                                78 ATTACHMENT G NOBLE GAS DOSE FACTORS AND DOSE PARAMETERS ..............                                                                    85 ATTACHMENT H ORGAN DOSE PARAMETERS ..............                                                                                          87 ATTACHMENT I            MODES OF GASEOUS RELEASE ..............                                                                          88 ATTACHMENT J P&I ORGAN DOSE FACTORS ..............                                                                                        89 ATTACHMENT K CONTINUOUS RELEASE DEPOSITION PARAMETERS (0-5 MILES) ...... 108 ATTACHMENT L CONTINUOUS RELEASE DEPOSITION PARAMETERS (SPECIAL DISTANCES) 115 ATTACHMENT M BATCH RELEASE DISPERSION PARAMETERS (SPECIAL DISTANCES) 122 ATTACHMENT N BATCH RELEASE DISPERSION PARAMETERS (0 - 5 MILES) .............. 125 ATTACHMENT 0 GASEOUS RADWASTE SYSTEM ..............                                                                                      126
 
Procedur Numnber.
Beaver Valley Power Station,                        12-ODC-2.02 Unit:          Level Of Use:
1/2              In-Field Reference ODCM: GASEOUS EFFLUENTS                          Revision:      Page Number:
I1                        of 128 TABLE OF CONTENTS ATTACHMENT P BV-1 AND BV-2 GASEOUS EFFLUENT RELEASE POINTS ...................              127 ATTACHMENT Q SITE BOUNDARY FOR GASEOUS EFFLUENTS........................................... 128 I : . ;
 
                                                                                                  - -    I            UI-Beaver Valley Power Station I . Procedure- Number 1/2.-ODC-2.02
 
==Title:==
unit          Level Of Use:
1    1/2            In-Field Reference ODCM: GASEOUS EFFLUENTS                                                          Rcvisiou:      P    Numbec 1.0      PURPOSE 1.1      This procedure provides the calculational methodology to be used for determination of the following release parameters.
1.1.1      Gaseous effluent monitor alarm setpoints 1.1.2      Gaseous effluent dose rate calculations 1.1.3      Gaseous effluent dose calculations 1.2      This procedure also provides information related to the following:
1.2.1      Gaseous Radwaste Treatment System.
1.2.2      Site Boundary used for gaseous effluents.
1.3        Prior to issuance of this procedure, these items were located in Section 2 and Section 5 of the old ODCM.
2.0      SCOPE 2.1        This procedure is applicable to all station personnel (including subcontractors) that are qualified to perform activities as described and referenced in this procedure.
 
==3.0        REFERENCES==
AND COMMITMENTS 3.1        References 3.1.1      References for BV-1 Gaseous Effluent Monitor Setpoints 3.1.1.1      Beaver Valley Power Station, Appendix I Analysis - Docket No. 50-334 and 50-412; Table 2.1-3 3.1.1.2      Beaver Valley Power Station, Unit 2 FSAR; Table 11.3-1 3.1.1.3      BVPS Specification No. BVS 414, Table V Nuclide Data,; Table 1 and Figure 1, Table 3, and Figure 2, May 30, 1974 3.1.1.4      Calculation Package No.ERS-SFL-85-031, Unit 1 Gaseous Effluent Monitor Efficiency Data 3.1.1.5      Calculation Package No. ERS-HHM-87-014, Unit 1/Unit 2 ODCM Gaseous Alarm Setpoint Determinations 3.1.1.6      Calculation Package No.ERS-ATL-87-026,BVPS-1 and BVPS-2 ODCM T Factor Justification
 
Procedur Numiber.
Beaver Valley Power Station                                          1/2-ODC 202 Ilde                                                                      Uite:        Uevel of Use:
1/2          In-Field Reference ODCM: GASEOUS EFFLUENTS                                                    Revision:    Page Number:
3.1.1.7      Letter ND1SHP:776, dated February 12, 1988, BVPS-1 ODCM Table 2.2-2, Appendix B 3.1.1.8      Stone and Webster Calculation No. UR(B)-262, Gaseous Releases From Containment Vacuum Pumps 3.1.2    References for BV-2 Gaseous Effluent Monitor Setpoints 3.12.1        Calculation Package No.ERS-SFL-86-026, Unit 2 DRMS Isotopic Efficiencies 3.1.2.2      Calculation Package No. ERS-HHM-87-014, Unit 1/Unit 2 ODCM Gaseous Alarm Setpoint Determinations 3.1.2.3      Beaver Valley Power Station, Unit 2 FSAR; Table 11.3-2 3.1.2.4      Calculation Package No. ERS-ATL-87-026, BVPS-1 and BVPS-2 ODCM T Factor Justification 3.1.2.5      Stone and Webster Calculation No. UR(B)-262, Gaseous Releases From Containment Vacuum Pumps 3.1.3      References Used for other portions of this procedure 3.1.3.1      NUREG-0133, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants 3.1.3.2      NUREG-1301, Offsite Dose Calculation Manual Guidance; Standard Radiological Effluent Controls for Pressurized Water Reactors (Generic Letter 89-0 1, Supplement No. 1) 3.1.3.3      NUREG-0324; XOQDOQ Program for the Meteorological Evaluation of Routine Releases at Nuclear Power Stations, September 1977 -
3.1.3.4      NUREG-0017; Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents form PWR's Revision 0.
3.1.3.5      Regulatory Guide 1.109, Calculation of Annual Dose to Man from Routine Releases of Reactor Effluents for the Purpose of Implementing Appendix I, April 1977 3.1.3.6      NUREG-0172, Age - Specific Radiation Dose Commitment Factors for a one-year Chronic Intake 3.1.3.7      1/2-ADM-1640, Control of the Offsite Dose Calculation Manual 3.1.3.8      1/2-ADM-0100, Procedure Writers Guide 3.1.3.9      NOP-SS-3001, Procedure Review and Approval
 
                                            ,      ,    .                    Pwocedur Number.
Beaver Valley Power StationI                                  P        Nu1/2-ODC-2.02 Tide:                                                                          Unit:        Level Of Use:
1/2      In-Field Reference ODCM- GASEOUS EFFLUENTS                                                        Revision:    Page Number 1              6 of 198 3.1.3.10      CR03-04830, Containment Vacuum Pump Replacement Increases ODCM Source Term. CA-03, Revise Unit 1 Containment Vacuum Pump Source-Term in ODCM procedure 1/2-ODC-2.02, Attachment A, Table 2.1-la.
3.2      Commitments 3.2.1      None 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'calkulation package) with an appropriate RTL number.
4.2      Forms 4.2.1      None 5.0        PRECAUTIONS AND LIMITATIONS 5.1      ODCM CONTROLS applicable to dose rate apply to the site. The site dose rate is due to the summation of releases from both units.
5.2      ODCM CONTROLS applicable to accumulated dose apply individually to each unit.
5.3      Releases at the Beaver Valley site may be ground level or elevated in nature.
5.3.1      All ground level releases are identified with a specific unit in the determination of site dose rate and dose attributed to that unit.
5.3.2      Elevated releases from both units are consideredto originate from a shared radwaste system and are discharged from a common release point, the Process Vent, at the top of the BV-1 cooling tower.
5.4      At BV-1 and BV-2, the dose from continuous and batch (Gas Waste Storage Tanks) releases via the shared radwaste system (Process Vent) are normally apportioned equally to the units.
Other continuous and batch releases via non-shared radwaste systems shall be attributed to a specific unit. The only exception is a containment purge via the Process Vent which shall be attributed to a specific unit.
5.5      There is a difference in setpoint terminology presentations of the radiation monitoring systems of BV-1 and BV-2.
5.5.1      Where HIGH and HIGH-HIGH terminology are used for the BV-I Victoreen monitors, ALERT and HIGH terminology are used for the BV-1 Eberline SPING monitors and the BV-2 monitors.
 
Procedure N~umber Beaver Valley Power Station
 
==Title:==
Unit:                                                                                    Level Of Use:
1/2            In-Field Reference ODCM: GASEOUS EFFLUENTS                                                        Revision:      Page Number 1                7 of 128 5.5.2      Also, BV-2 setpoints are presented in uCi/cc rather than cpm as in BV-1. This difference is due to BV-2 software which applies a conversion factor to the BV-2 raw data (cpm). The user is cautioned that the uCi/cc presentation is technically correct only for the specific isotopic mix used in the determination of the conversion factor. In practice, setpoints determined for a calculated mix are correct for that mix. Setpoints determined on analysis prior to release will be correct for properly controlling dose rate, but the indicated uCi/cc value may differ from the actual value.
5.5.3      All BV-1 and BV-2 effluent monitors specified herein have Upper Alarm Setpoints established at 60 percent of the site limit, and Lower Alarm Setpoints established at 30 percent of the site limit.
5.6      A release may be batch or continuous in nature. Batch refers to releases that are intermittent in radionuclide concentrations or flow, such as releases from gas storage tanks, containment purges and ventings of systems or components with infrequent use.
5.6.1      Batch releases may be due to operational variations which result in radioactive releases greater than 50% of the releases normally considered as continuous. Batch releases from these sources during normal operation, including anticipated operational occurrences, are defined as those which occur for a total of 500 hours or less in a calendar year, but not more than 150 hours in any quarter.
5.6.2      The batch relative concentration value has been calculated in accordance with the guidelines provided in NUREG-0324(3.133 1for short-term release.
5.6.3      IF simultaneous batch and continuous release out of one vent occurs, THEN use the lowest setpoint obtained according to Sections 8.1.1.1 through 8.1.3.2.
5.7      This procedure also contains information that was previously contained in Section 5 of the previous BV-1 and BV-2 Offsite Dose Calculation Manual.
5.7.1      In regards to this, the site boundary for gaseous effluents was included in this procedure.
5.7.2      The Site Boundary for Gaseous Effluents is shown in ATTACHMENT P Figure 5-1.
6.0        ACCEPTANCE CRITERIA 6.1        All changes to this procedure shall contain sufficient justification that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302,40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR 50, and not adversely impact the accuracy of effluent dose or alarm setpoint calculation. (3.1.3.2) 6.1.1      All changes to this procedure shall be prepared in accordance with 1/2-ADM-0100(3.1. 3 .8) and 1/2-ADM-1640. (3.1.3.7) 6.1.2      All changes to this procedure shall be reviewed and approved in accordance with NOP-SS-3001(3 13.9) and 1/2-ADM-1640. (3.1.3.7)
 
_ML_
Beaver Vay PNumber I.Beaver        Valley Power Station                                          12OC20
'itle:                                                                          unit:        Lvel Of Usl 1/2          In-Field Reference I ODCM: GASEOUS EFFLUENTS                                                        Revision:    Page Number:
1          89 of 128v 7.0      PREREOUISITES 7.1      The user of this procedure shall be familiar with ODCM structure and content.
8.0      PROCEDURE 8.1      Alarm Setpoints.
8.1.1    BV-1 Monitor Alarm Setpoint Determination ODCM CONTROL 3.11.2.1 require that the dose rate in unrestricted areas due to noble gas radionuclides in the gaseous effluent released from the site shall be limited to < 500 mrem/yr to the total body and to < 3000 mrem/yr to the skin.
This section describes the methodology used to maintain the release of noble gas radionuclides within ODCM CONTROL 3.11.2.1 for the site, and determines monitor setpoints for BV-1.
The methodologies described in Section 8.1.1.2, 8.1.2.2, and 8.1.3.2 provide an alternate means of determining monitor alarm setpoints that may be used when an analysis is performed prior to release.
Control of the site dose rate limit due to noble gases is shown in the following Table. Dose rate control is exercised through a total of 8 effluent stream monitors, of which 3 are located at BV-1 (alternates exists for these monitors), and 5 are located at BV-2. As previously noted, BV-1 and BV-2 elevated releases are via the PV-1/2 Process Vent.
                                                                                                    . 1
 
Beaver Valley Power Station                                          eNuj/7      D 0 c 2 02
 
==Title:==
Unit          Level Of Use.
                                                                              .1/2    IIn-Field Reference ODCM: GASEOUS EFFLUENTS                                                    Revision      Page Number:
                                                                                    'l9            of 128 Monitor Setpoint Specifications Based On Fraction Of Site Limit UNIT RELEASE POINT                        FRACTION OF SITE LIMiTING DOSE RATE MONITOR NO.                                Upper Alarm              Lower Alarm (VV-1) Unit 1, Auxiliary Building Vent PA.: RM-1VS-101B or                        60% (HIGH-HIGH)          30% (HIGH)
Alt.: 'RM-IVS-109 (5)                      60% (HIGH)                30% (ALERT)
(CV-l) Unit 1, RX Containment/SLCRS Vent Pri.: RM-lVS-107B or                      60% (HIGH-HIGH)          30% (HIGH)
Alt.: RM-1VS-110 (5)                      .60% (HIGH)                30% (ALERT)
(PV-1/2), Unit 1/2; Gaseous Waste/Process Vent Pri.: RM-lGW-108B or                      60% (HIGH-HIGH)          30% (HIGH)
Alt.: RM-IGW-109 (5)                      60% (HIGH)                30% (ALERT)
(CV-2), Unit 2, SLCRS Filtered Pathway 2HVS-RQ109E                                60% (HIGH)                30% (ALERT)
(VV-2), Unit 2, SLCRS Unfiltered Pathway 2HVS-RQl01B                                60% (HIGH)                30.(ALERT)
(WV-2), Unit 2, Waste Gas Storage Vault Vent, 2RMQ-RQ303B                                60% (HIGH)                30% (ALERT)
(DV-2), Unit 2, Decontamination Building Vent 2RMQ-RQ301B                                60% (HIGH)                30% (ALERT)
(CB-2), Condensate Polishing Building Vent 2HVL-RQI 12B                              60% (HIGH)                30% (ALERT)
With the monitor setpoints based on fractions of the site limit as defined above, the following criteria may be applied to determine that the dose rate due to noble gas released from the site complies with ODCM CONTROL 3.11.2.1:
* The site dose rate is 30% of the site dose rate limit when any monitor is indicating a Lower Alarm.
* The site dose rate is 60% of the site dose rate limit when any two monitors are indicating Lower Alarms.
* The site dose rate is 60% of the site dose rate limit when any monitor is indicating an Upper Alarm.
* The site dose rate is 90% of the site dose rate limit when any monitor is indicating an Upper Alarm and any other monitor is indicating a Lower Alarm.
 
                                                                        ' : IProcede Numb=:
Beaver Valley Power Station                                          -    1/2-ODC-2.02
'fit.e                                                                        Uni:cvel            Of Use: .fl 1/2          In-Field Reference ODCM: GASEOUS EFFLUENTS                                                    -  Revision:      Page Numbec I .. I                  llo of 1f9 -
8.1.1.1      BV-1 Setpoint Determination Based On A Calculated Mix For W-1 and CV-1 Ground Releases The table below gives the calculated monitor count rate above background (CR), in ncpm, and provides the equivalent monitor indication associated with the most limiting site dose rate limit (i.e.; 500 mrem/yr Total Border or 3000 mrem/yr skin).
The monitor HIGH-HIGH alarm setpoint above background (HHSP), and the monitor HIGH alarm setpoint above background (HSP) for each vent and operational condition shall be as follows:
BV-1 ALARM SETPOINTS FOR GROUND RELEASES cpm ABOVE BACKGROUND 309o (f)PRRAARY* '                  I SIHE            Sf1 MONILOR (A) ALTERNATE                      UPPER UPPER MONITOR              C R      ALARM      ALARM
* Continuous Release Via The BV- I (P)RM-1VS-1O1B.                  3000          1800        900 Auxilary Building Vent (VV-i)            (A)RM-IVS-109(5)        1470          879        440
* Batch Release Of Containment              (P)RM-lVS-1OlB.        1200        718          359    I' Purge Via The BV-1 Auxiliary              (A)RM-lVS-109(5)        1430        860          430 Building Vent (VV-1)
* Continuous Release Via The BV-1          (P)RM-IVS-107B          6440        3870          1930 Rx Containment/SLCRS Vent                (A)RM-IVS-110(5)        3380        2030          1010 (CV-1)
* Batch Release Of Containment -- (P)RM-lVS-107B                    12,700      7630        3810 Purge Via The BV-I Rx                    (A)RM-IVS-1 10(5)        6660      4000        2000 ContainmentlSLCRS Vent (CV-1)
              *IF the primary monitor is out of service, THEN ODCM CONTROL 3.3.3.10 is met for the respective alternate monitor. The alternate setpoints shall be utilized.
The setpoints were determined using the following conditions and information:
* Source terms given in ATTACHMENT A Table 2.1-la. The gaseous source terms were derived from Stone & Webster computer code GAS 1BB (similar to NUREG-0017),(3 34) and computer code DRAGON 4 (for the containment vacuum pump sources). ATTACHMENT A Table 2.1-la does not include particulates and iodines, which are not used in site noble gas dose rate calculations.
* Onsite meteorological data for the period January 1, 1976 through December 31, 1980.
0  Discharge flow rate of 62,000 cfm for a VV-1 Continuous Release.
 
Procedure Number.
Beaver Valley Power Station                                                *1/2-ODC-2.02 Unit:        Level Of Use:
hi,
:    1/2      J    In-Field Reference ODCM: GASEOUS EFFLUENTS                                                  Revision:    Page Number
                                  -                                      .  . l                  ofn128 Dischargetflow rate of 92,000 cfm for a VV-1 Batch Release of Containment Purge.
This is comprised of 30,000 cfm from the containment purge plus 62,000 cfm for VV-1.
* Discharge flow rate of 49,300 cfm for a CV-1 Continuous Release.
Discharge flow rate of 56,800 cfm fora CV-1 Batch Release of Containment Purge.
This is comprised of 7,500 cfm from the containment purge plus 49,300 cfm for CV-1.
* Informnation listed under References for BV-1 Gaseous Effluent Monitor Setpoints.
The calculation method given in Sections 8.1.1.1.1 through 8.1.1.1.7 was used to derive the monitor setpoints for the following operational conditions:
* Continuous release via'-VV.'
            . Continuous release via CV-l.
Batch release of BV-1 Containment Purge via VV-1.
            '  Batch release of BV-1 Containment Purge via CV-2.
8.1.1.1.1      BV-1 Mix Radionuclides.
The "mix" (noble gas radionuclides and composition) of the gaseous effluent was determined as follows:
                          . The gaseous source terms that are representative of the "mix" of the gaseous effluent were selected. Gaseous source terms are the radioactivity of the noble gas radionuclides in the effluent. Gaseous source terms can be obtained from ATTACHMENT A Table 2.1-la.
The fraction of the total radioactivity in the gaseous effluent comprised of noble gas radionuclide "i" (Si) for each individual noble gas radionuclide in the gaseous effluent was determined by:
:  Al Si        i where:
Ai = The total radioactivity or radioactivity concentration of noble gas
                            -:    radionuclide "i" in the gaseous effluent from ATTACHMENT A Table 2.1-la.
 
                                                                                                              - II-Beaver Valley Power Station -                          i;        1/2  ODC-2.02 ritle.                                                                    Unit:        Level Of Use:
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      -8.1.1.1.2        BV-1 Maximum Acceptable Release Rate (Whole Body Exposure)
The maximum acceptable total release rate (uCi/sec) of all noble gas radionuclides in the gaseous effluent (Qt) based upon the whole body exposure limit was calculated by:
                                -  500
[2.1(1)-2]
Qt= (X/Q)XKi Si I .
where:
(X/QXVv      =The      highest calculated annual average relative concentration of effluents released via VV-I for any area at or beyond the unrestricted area boundary for all sectors (sec/m 3 ) from ATTACHMENT F Table 2.2-5.
1.03E4 sec/m 3 for continuous releases.
( X/q X%    =    The highest calculated short term relative concentration of effluents released via VV-1 for any area at or beyond the unrestricted area boundary for all sectors (sec/m3 ) from*
ATTACHMENT M Table 2.3-36.
3.32E-4 sec/m3 for batch release of containment purge.
(X/Q)6v    =-  The highest calculated annual average relative concentration of effluents released via CV-1 for any area at or beyond the unrestricted area boundary for all sectors (sec/rn3 ) from ATTACHMENT F Table 2.2-4.
                                    =    9.24E-5 sec/m 3 for continuous releases.
(X/q)cv          The highest calculated short term relative concentration of effluents released via CV-1 for any area at or beyond the unrestricted area boundary for any sectors (sec/m 3 ) from ATTACHMENT M Table 2.3-35.
3.08E-4 sec/m 3 for batch release of containment purge.
The total whole body dose factor due to gamma emissions from noble gas radionuclide "i", (mrem/year/uCi/m 3 ) from ATTACHMENT G Table 2.2-11.
Si        =    From equation [2.1(1)-I] above.
 
Procedure Numberc Beaver Valley Power Station                                            1/2-ODC-2.02
'Title:                                                                Unit          Level Of Use:
1/2          In-Field Reference ODCM: GASEOUS EFFLUENTS                                              Revision:    Page Number 1      -- 13 of 129 8.1.1.1.3 ; BV-1 Maximum Acceptable Release Rate (Skin Exposure)
Qt was also determined based upon the skin exposure limit by:
3000, Qt -
(XlQ) Z (Li + 1.1M,) Si where:
1,          =    The skin dose factor due to beta emissions from noble gas
                                    -radionuclide "i"(mremlyear/uCi/rn 3 ) from ATIACBMENT G Table 2.2-11.
Mi          =    The air dose factor due to gamma emissions from noble gas radionuclide "i"(mrad/year/uCi/m 3 ) from ATTACHMENT G Table 2.2-1 1.
1.1        =    The ratio of the tissue to air absorption coefficients over the energy range of the photons of interest, (mrem/mrad).
(XJQ)      =    Same as in Section 8.1.1.1.2.
8.1.1.1.4  BV-1 Maximum Acceptable Release Rate (Individual Radionuclide)
The maximum acceptable release rate (uCi/sec) of noble gas radionuclide "i" in the gaseous effluent (Qi) for each individual noble gas radionuclide in the gaseous effluent was determined by:
Q= Si Qt                                                                  [2.1(1)-4]
NOTE: Use the lower of the Q, values obtained in Section 8.1.1.1.2 and 8.1.1.1.3.
 
Beaver valey Power Stafion                    B  Valley  P r S o    Number.
112
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_  Unit        Level Of Use:
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The maximum acceptable radioactivity concentration (uCi/cc) of noble gas radionuclide "i' in the gaseous effluent (C;) for each individual noble gas radionuclide "i" in the gaseous effluent was determined by:
2.12E-3 Qj Ci =                                                      [2.1(1)-5]
F where:
F            _ The maximum acceptable effluent flow rate at the point of release (cfm) as listed in Section 8.1.1.1.
2.12E-3    =    Unit conversion factor (60 sec/min x 3.53E-5 ft3 /cc).
8.1.1.1.6  BV-1 Monitor Count Rate' The calculated monitor countkrate (ncpm) above background attributed to the noble gas radionuclide. CRvwas determined by:
CR = Z CiEi          -[21)6]
where:
Ei = The detection efficiency of the monitor for noble gas radionuclide "i" (cpm/uCi/cc) from ATTACHMENT B Table 2.1-2a.
8.1.1.1.7    BV-1 Monitor Setpoints The monitor alarm setpoints above background were determined as follows:
                    . The monitor HIGH-HIGH Alarm Setpoint above background (ncpm) was determined by:
HHSP = 0.60 x CR                                                        [2.1(1)-7]
* The monitor HIGH Alarm Setpoint above background (ncpm) was determined by:
HSP = 0.30 x CR                                                          [2.1(1)-81 NOTE:    The values 0.60 for the HHSP and 0.30 for the HSP are fractions of the total radioactivity concentration that may be released via the monitored pathway to ensure that the site boundary limit is not exceeded due to simultaneous releases from both units.
 
Procedue Number.
Beaver Valley Power Station                                                1/2-ODC-2.02 ride                                                                        Unit:    b    evel Of Use:
1/2        In-Field Reference ODCM: GASEOUS EFFLUENTS                                                      Revision    Page Number.
l          1IS of 129 8.1.1.2      BV-1 Setpoint Determination Based On Analysis Prior To Release For W-1 and CV-1 Ground Releases When the setpoints established using "the calculated mix" for ground releases do not provide adequate flexibility for operational needs, the method described below may be used in lieu of that set forth in Step 8.1.1.1. In this case, the results of sample analysis are used to determine the source term "mix." This calculational method applies to gaseous releases via VV-1 and CV-1 when determining the setpoint for the maximum acceptable discharge flow rate and the associated HIGH-HIGH Alarm Setpoint based on this flow rate-during the following operational conditions:
Batch release of Containment Purge via YV- I.
* Batch release of Containment Purge via CV-1.
8.1.1.2.1      BV-1 Maximum Acceptable Release Rate The maximum acceptable discharge flow rate from VV-1 and CV-1 during purging is determined as :follows::
The maximum acceptable gaseous discharge flow rate (f) from VV-1 and CV-1 (cfm) during purging based upon the whole body exposure limit is calculated by: ;-
1.06 S T                                                        [2.1(1)-17]
f = (X/q)    K. Ci where:
1.06      = 50mrem/yr x 2.12E-3 500 mrem/yr = dose rate limit 2.12E-3          = unit conversion factor
                                                        = (60 sec/mn x 3.53E-5 ft3 /cc)
S        =  Percent of site dose rate released via this pathway. Up to 60% of the site dose rate is permissible for one release point under the alarm set point rules of Section 8.1.1.
T          =  Maximum valve for T is 16 based on the limiting restriction in ODCM CONTROL 3.11.2.1 where the dose rate for a containment purge may be averaged over a time period not to exceed 960 minutes. (As containment air volume change time period is 60 minutes; T = 960/60 = 16).(3ll6)
 
_  _  -    ALl-Beaver Valley Power Station                                  Prt          1;.1 O
                                                                              '4umbDC-2.02 litie:                                                              Unit:          Level Of Use:
1/2            In-Field Reference ODCM: GASEOUS EFFLUENTS                                              Reion:          Pagc                        A -i (Xtq)w      = The highest calculated short term relative concentration of effluents released via VV-I for any area at or beyond the unrestricted area boundary for all sectors (sec/m 3 ) from AATTACHMENT M Table 2.3-36.
I I
                            = 3.32E-4 sec/rn3 '
(X/q)cv    =  The highest calculated short term relative concentration of effluents released via CV-1 for areas at or beyond the unrestricted area boundary for all sectors (sec/m 3 ) from ATITACHMENT M Table 2.3-37.
                              -  3.08E-4 sec/m 3 K;          =  The total whole body dose factor due to gamma emissions from noble gas radionuclide ''i" (mrem/year/uCi/m 3 ) from ATTACHMENT G Table 2.2-11.
C;          =  The undiluted radioactivity concentration of noble gas radionuclide "i" in the gaseous source (uCi/cc) as determined by analysis of the gas to be released.
The flow rate (f) is also determined based upon the skin exposure limit as follows:
6.36S T
[2.1(1)-18]
f =(Xlq) I (Li- + l. lM; ) Ci where:
6.36 i    3000 mrem/yr x 2.12E-3 3000 mrem/yr      =  dose rate limit
: 2. 12E-3          =  unit conversion factor (60 sec/min x 3.53E-5 ft3 /cc)
L;    =  The skin dose factor due to beta emissions from noble gas radionuclide "i" (mrem/year/uCilm 3 ) from ATTACHMENT G Table 2.2-11.
M;= The air dose factor due to gamma emissions from noble gas radionuclide "i" (mrad/year/uCilm 3 ) from ATTACHMENT G Table 2.2-11.
(X/q) = Same as above.
 
Procedue Number Beaver Valley Power Station                                              1/2-ODC-2.02 Tidle:                                                                        Unit:        Level Of Use:
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* The flow rate (f) is determined by selecting the smaller of the calculated (f) values based on the whole body exposure limit, or the skin exposure limit shown above. The actual purge flow rate (cfm) must be maintained at or below this calculated (f) value or the discharge cannot be made from the vent.
8.1.1.2.2      BV-1 Monitor Setpoints The monitor alarm setpoints above background are determined as follows:
* The calculated monitor HIGH-HIGH Alarm Setpoint above background (ncpm) attributed to noble gas radionuclides is determined by:
f Z Cj E; HHSP[2.1(1)9]
where:
f      =  The maximum acceptable gaseous discharge flow rate (cfm) determined in Section 8.1.1.2.1.
F'    =  The maximum actual or design effluent flow rate (cfm) at the point of release.
                                  =  92,000 cfm for VV-1
                                  =  56,800 cfm for CV-1 Ci    =  The undiluted radioactivity concentration of noble gas radionuclide "i" in the gaseous source (uCi/kc) as determined by analysis of the gas to be released.
E,    =  The detection efficiency of the monitor for noble gas radionuclide "i" (cpm/uCi/cc) from ATTACHMENT B Table 2.1-2a.
* When a HIGH-HIGH set point has been calculated according to this section, the monitor HIGH Alarm Setpoint above background (ncpm) is determined as follows:
HSP = UHSP x 0.5                                                    [2.1(1)-20]
8.1.2    BV-2 Monitor Alarm Setpoint Determination See Section 8.1.1 for a description of Monitor Alarm Setpoint Determinations.
8.1.2.1      BV-2 Setooint Determination Based On A Calculated Mix For W-2, CV-2, DV-2, WV-2 and CB-2 Ground Releases.
 
Beaver Valley Powe rBeave          SlPImcedreN Vally Station        P r                            c 12-D-.2_
 
==Title:==
unit:        Level Of Use:
1/2        In-Field Reference ODCM: GASEOUS EFFLUENTS                                                      Revision:    PageNumbcr I              l X of 128 The table below gives the calculated monitor count rate above background (CR) in ncpm, and provides the equivalent monitor indication (DV) in net uCi/cc associated with the most limiting site dose rate limit (i.e., 500 mremlyr Total Body or 3000 mrem/yr Skin). The HIGH alarm setpoint (HSP) in uCi/cc above background, and the ALERT alarm setpoint (ASP) in uCilcc above background for each vent and operational condition shall be as follows:
BV2 ALARM SETPOINTS FOR GROUND RELEASES uC~i/cc ABOVE BACKGROUND (unless otherwise specified) 60%          30%
SITE          SITE LIMIT LUAU CR                UPPER LOWER MONITOR            ncpm          DV    ALARM ALARM
* Continuous Release Via The BV-2      2HVS-RQIOlB          8260    3.01E-4    1.81E-4 9.04E-5 SLCRS Unfiltered Pathway (VV-2)
* Batch Release Of Containment        2HVS-RQlOlB          2020      7.39E-5  4.43E-5 2.22E-5 Purge Via The BV-2 SLCRS Unfiltered Pathway (VV-2)
* Continuous Release Via The BV-2      2HVS-RQ109E          43          2940      1770          883 SLCRS Filtered Pathway (CV-2)                                        ItCi/sec  ItCi/sec      ItCi/sec
* Batch Release Of Containment        2HVS-RQ109E          16,400      1130      676          338 Purge Via The BV-2 SLCRS                                            giCi/sec  ItCi/sec      jICi/sec Filtered Pathway (CV-2)
* Continuous Release Via The BV-2      2HVL-RQ I12B        28,900    1.611E-3  9.63E-4 4.82E-4 Condensate Polishing Building Vent (CB-2)
* Continuous Release Via The BV-2      2RMQ-RQ301B          56,600    3.15E-3  1.89E-3 9.44E-4 Decontamination Building Vent (DV-2)
* Continuous Release Via The BV-2      2RMQ-RQ303B        912,000 2.58E-2      1.55E-2      7.74E-3 Waste Gas Storage Vault Vent (WV-2)
 
                    .B  . Valey owerStaionProcedure                        Number BeyPower Station                              2-ODC-2.02 Title                                                              Unit:      Level Of Use:
1/2        In-Field Reference ODCM: GASEOUS EFFLUENTS                                                        Page Number 1            19 of 12.S The setpoints were determined using the following conditions and information:
* Source terms given in ATTACHMENT A Table 2.1-lb. These gaseous source terms were derived from Stone & Webster computer code GAS 1BB (similar to NUREG-0017)( 3 "3 43 and computer code DRAGON 4 (for the containment vacuum pump sources). ATTACHMENT A Table 2.1-lb does not include particulates and iodines, which are not used in site noble gas dose rate calculations.
* The Containment Building Purge radionuclide mix was utilized for the purposes of determining an alarm setpoint for the SLCRS Unfiltered Pathway on the basis of the proximity of the contiguous areas.
* The Decontamination Building and Condensate Polishing Building ventilation exhaust are not expected to be radioactive. However, for purposes of determining an alarm setpoint, it is conservatively assumed that Xe-133 is in the ventilation exhaust at concentrations that would result in the appropriate dose rate limits.
* The Waste Gas Storage Vault ventilation exhaust is also not normally radioactive. However, the monitor alarm setpoint is based on the assumption that the ventilation exhaust radionuclide spectrum is similar to the gaseous inventory in the system housed by the waste gas storage vault. This spectrum is listed in ATTACHMENT A Table 2.1-lb under Gaseous Waste System.
* Onsite meteorological data for the period January 1, 1976 through December 31, 1980.
* Discharge flow rate of 23,700 cfm for a VV-2 Continuous Release.
* Discharge flow rate of 53,700 cfm for a VV-2 Batch Release of Containment Purge. This is comprised of 30,000 cfm from the containment purge plus 23,700 cfm from the CV-2.
* Discharge flow rate of 59,000 cfrn for a CV-2 Continuous Release.
* Discharge flow rate of 59,000 cfm for a CV-2 Batch Release of Containment Purge. This is comprised of 7,500 cfm from the containment purge plus 51,500 cfm from CV-2.
* Discharge flow rate of 30,556 cfm for a CB-2 Continuous Release.
* Discharge flow rate of 12,400 cfm for DV-2 Continuous Release.
* Discharge flow rate of 2,000 cfm for WV-2 Continuous Release.
 
_ Procedurt Number. t Beaver Valley Power Station                        I                        1I2LoDC-2.o2
'ntle-                                                                      Unit:          Level Of Use:
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* Information listed under References for BV-2 Gaseous Effluent Monitor Setpoints.
The calculation method given in Sections 8.1.2.1.1 through 8.1.2.1.7 was used to derive the alarm setpoints for the following operational conditions:
* Continuous release via W-2.
* Continuous release via CV-2.
                -Batch    release of BV-2 Containment Purge via V-2.
* Batch release of BV-2 Containment Purge via CV-2.
* Continuous release via CB-2.
* Continuous release via DV-2.
* Continuous release via WV-2.
8.1.2.1.1        BV-2 Mix Radionuclides The "mix" (noble'gas radionuclides and composition) of the gaseous effluent was determined as follows:
* The gaseous source terms that are representative of the "mix" of the gaseous effluent were selected based on the relative stream composition and volumetric flowrate. Gaseous source terms are the radioactivity of the noble gas radionuclides in the effluent. Gaseous source terms can be obtained from ATTACHMENT A Table 2.1-lb.
* The fraction of the total radioactivity in' the gaseous effluent comprised of noble gas radionuclide "i" (Si) for each individual noble gas radionuclide in the gaseous effluent was determined by:
SA;                                                                [2.1(2)-1I where:
                      --A-' = The radioactivity concentration of noble gas radionuclide "i" in the.
gaseous effluent (for VV-2, CV-2 and WV-2) is from ATTACHMENT A Table 2.1-lb. However, SINCE releases via CB-2 and DV-2 do not v have a valid source term mix, THEN the noble gas radioactivity concentration is assumed to be Xe-133.
 
Procedure Number:
Beaver Valley Power Station                              ODC-2.02
* k                                                                  Unit:        Level Of Use:
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1              21 of I29 8.1.2.1.2  BV-2 Maximum Acceptable Release Rate (Whole Body Exposure)
The maximum acceptable total release rate (uCilsec) of all noble gas radionuclides in the gaseous effluent (Qt) based upon the whole body exposure limit was calculated by:
500
[2.1(2)-21 I -    (X/Q) XK. S where:                    -- - -        -
(X/Q)X    =    The highest calculated annual average relative concentration of eeffluentsreleased via VV-2 for any area at or beyond the unrestricted area boundary for all sectors (sec/m 3 ) from ATTACHMENT F Table 2.2-5.
1.03E-4 secirn 3 for continuous releases.
(XUq)vv  = The short term relative concentration of effluents released via VV-2 for any area at or beyond the unrestricted area boundary for all sectors (sec/m 3 ) from ATTACHMENT M Table 2.3-36.
                            = 3.32E-4 sec/m 3 for batch release of containment purge.
(X/Q)CV  =    The highest calculated annual average relative concentration of effluents released via CV-2 for any area at or beyond the unrestricted area boundary for all sectors (sec/m 3 ) from ATTACHMENT F Table 2.2-4.
                            = 9.24E-5 sec/m3 for continuous releases.
(X/q)cv  = The short term relative concentration of effluents released via CV-2 for any area at or beyond the unrestricted area boundary for all sectors (sec/m 3 ) from ATTACHMENT M Table 2.3-35.
                            = 3.08E-4 sec/r      3 for batch release of containment purge.
(X/Q)4- = The highest calculated annual average relative concentration of effluents released via CB-2 for any area at or beyond the unrestricted area boundary for all sectors (sec/rn3 ) from ATIACHMENT F Table 2.2-10.
                            -    7.35E-5 sec/m 3 for continuous releases.
 
                            . _'-      o  ..        ,    .ProcedureNumba:                                      e Beaver Valley Power StationProdreNme
___    ____  ___      ____  ___  __1/2-ODC-2.02I Unit    Utve Of Use-1/2    In-Field Reference ODCM: GASEOUS EFFLUENTS                                                              Revisio: P Numf    r2 1      22 f 128 (X/Q)d,        = The highest calculated annual average relative concentration of effluents released via DV-2 for any area at or beyond the unrestricted area boundary for all sectors (sec/m 3 ) from ATTACHMENT F Table 2.2-8.
                                      = 9.24E-5 sec/m3 for continuous releases.
(X/Q)W          =    The highest calculated annual average relative concentration of effluents released via WV-2 for any area at or beyond the unrestricted area boundary for all sectors (sec/m 3 ) from ATTACHMENT F Table 2.2-9.
                                      -    9.24E-5 sec/mr      for continuous releases.
K1      i      =    The total whole body dose factor due to gamma emissions from noble gas radionuclide "i" (mrem/yearluCi/m 3 )from ATTACHMENT G Table 2.2-11.
Si              = From equation [2.1(2)-i].
8.1.2.1.3      BV-2 Maximum Acceptable Release Rate (Skin Exposure)
T' Qt was also determined based upon the skin exposure limit by:
3000 Qt =                                                                              [2. 1(2)-3]
(X/Q) I (Li + 1.1M;) Si where:
Lj            = The skin dose factor due to beta emissions from noble gas radionuclide "i"(mremlyear/uCi/m 3 ) from ATTACHMENT G Table 2.2-1 1.
                                      = The air dose factor due to gamma emissions from noble gas radionuclide "i"(mrad/year/uCi/m 3 ) from ATTACHMENT G Table 2.2-1 1.
1.1            -    The ratio of the tissue to air absorption coefficients over the energy range of the photons of interest, (mrem/mrad).
(X/Q)          = Same as in Section 8.1.2.1.2.
8.1.2.1.4      BV-2 Maximum Acceptable Release Rate (Individual Radionuclide)                                  I The maximum acceptable release rate (uCi/sec) of noble gas radionuclide "i" in the gaseous effluent (Qj) for each noble gas radionuclide in the gaseous effluent was determined by:
 
Beaver Valley Power Station                                -u N            mbe          2        :
                                                                        . 1/2    I    In-Field Reference ODCM: GASEOUS EFFLUENTS                                                    Revisioa:    Page Number.
l l        23 of 128 Qi = Si Qt                                                                  [2.1(2)4]
NOTE: Use the lower of the Q, values obtained in Section 8.1.2.1.2 and 8.1.2.1.3.
: 8. 1.2. 1.5  BV-2 Maximum Acceptable Concentrations (Individual Radionuclide)
The maximum acceptable radioactivity concentration (uCilcc) of noble gas radionuclide "i" in the gaseous effluent (Ci) for each individual noble gas radionuclide in the gaseous effluent was determined by:
                  'Ci=      m      a        ,        ,.                                        2.1(2)-5],
      , .1.. 1.
where:
F                The maximum acceptable effluent flow rate at the point of release (cfm) as listed in Section 8.1.2.1.
2.12E-3 = Unit conversion factor (60 sec/min x 3.53E-5 ft 3 /cc).
BV-2 Monitor Count Rate The calculated monitor count rate (ncpm) above background attributed to the noble gas radionuclide (CR) was determined by:
CR = YCi E 1                                      -                          [2.1(2)-6)]
where:
Ei      =  The detection efficiency of the monitor for noble gas radionuclide "i" (cpm/uCi/cc) from ATTACHMENT B Table 2.1-2b.
8.1.2.1.7    BV-2 Monitor Setpoints The monitor alarm setpoints above background were determined as follows:
* The monitor HIGH Alarm Setpoint above background (uCi/cc) was determined by:
0.60 x CR HSP- 06            CR                                                        [2.1(2)-7]
El ave where; E; ave    = The CR of equation [2.1(2)-6] divided by the sum of the C; for the respective mix.
 
Be      e  V                                                      Procedure Number.*-
-Beaver                    Valley          Power Stationi                ~        -          1/2-'ODC-2.02 Mitle:                                                                            Unit          Level Of Use:          4
                    ..    ..                                                        1/2          In-Field Reference  .
ODCM: GASEOUS EFFLUENTS                                                          1112
                            ...                                                        1I              24of 128S
* The monitor ALERT Alarm Setpoint above background (uCi/cc) was determined by:
0.30 x CR ASP =                                                                          [.()8 Eiave 8.1.2.2      BV-2 Setpoint Deternination Based On Analysis Prior To Release for VV-2 and CV-2 Ground Releases When the setpoints established using "the calculated mix" do not provide adequate flexibility for operational needs, the method described below may be used in lieu of that set forth in Section 8.1.2.1. In this casej the results of sample analysis are used to determine the appropriate nuclide mix. This calculational method applies when determining the setpoint for the maximum acceptable discharge flow rate and the associated HIGH Alarm Setpoint based on respective vent flow rate during the following operational conditions:
* Batch release of Containment Purge via VV-2.
                    . Batch release of Containment Purge via CV-2.
8.1.2.2.1        BV-2 Maximum Acceptable Release Rate The maximum acceptable discharge flow rate from VV-2 or CV-2 during purging is determined as follows:
* The maximum acceptable gaseous discharge flow rate (f) from VV-2 or CV-2 (cfm) during purging based upon the whole body exposure limit is calculated by:
f            06 S                                                        [2.1(2)-171
                                  -(X1q)      YKi C, where:
1.06        =    500 mrem/yr x 2.12E-3 500 mrem/yr      = dose rate limit, whole body exposure 2.12E-3          = unit conversion factor
                                                                = (60 sec/min x 3.53E-5 ft3/cc)
S            =    Percent of site dose rate released via this pathway. Up to 60% of the site dose rate is permissible for one release point under the alarm setpoint rules of Section 8.1.2.
 
Procedure Number:.
Beaver Valley Power Statiol                                              112-ODC-2.02 Tik
-Ide                                                                Uait:            vel Of Use.
E                                                                  1/2            In-Field Reference ODCM: GASEOUS EFFLUENTS
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9'5 of 128--
T              Maximum value for T is 16 based on the limiting restriction in ODCM CONTROL 3.11.2.1 where the dose rate for a containment purge may be averaged over a time period not to exceed 960 minutes. (As containment air volume change time period is 60 minutes; T = 960160= 16).
(Xfq)      = The highest calculated short term relative concentration of effluents released via VV-2 for any area at or beyond the unrestricted area boundary for all sectors (sec/rn3 ) from ATTACHMENT M Table 2.3-36.
                            = 3.32E-4 sec/m3 Q(/q)V= The highest calculated short term relative concentration of effluents released via CV-2 for any area at or beyond the unrestricted area boundary for all sectors (seclm 3 ) from AT[ACHMENT M Table 2.3-37.
                            = 3.08E-4 sec/m3 Ki          =  The total whole body dose factor due to gamma emissions from noble gas radionuclide "i" (mrem/year/uCi/m 3 ) from ATTACHMENT G Table 2.2-11.
Ci          =  The undiluted radioactivity concentration of noble gas radionuclide "i" in the gaseous source (uCi/cc) as determined by analysis of the gas to be released.
* The flow rate (t) is also determined based upon the-skin exposure limit as follows:
6.36 S T f=(X/q) Y, (Li + IAM;j) Ci[21)-8 where:
6.36 = 3000 mrenilyr x 2.12E-3 3000 mremfyr      = dose rate limit, skin exposure 2.12E-3            = unit conversion factor
                                                = (60 sec/min x 3.53E-5 ft3 /cc)
I,    = The skin dose factor due to beta emissions from noble gas radionuclide "i" (mremlyear/uCi/m 3 ) from ATTACHMIENT G Table 2.2-11.
 
Procedure Number                      1 Beaver Valley Power Station                                          1/2-ODC-2.02 -
Tie:                                                              Unit:        Level Of Use:
In-Field Reference ODCM: GASEOUS EFFPELUENTS                                          ReN          giur:
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                - M;= The air dose factor due to gamma emissions from noble gas radionuclide "i" (mrad/yearluCim 3 ) from AITACHMENT G Table 2.2-11.
(X/q) = Same as above.
                . The flow rate (f) is determined by selecting the smaller of the calculated (f) values based on the whole body exposure limit, or the skin exposure limit shown above. The actual purge flow rate (cfm) must be maintained at or below this calculated (f) value or the discharge cannot be made from the vent.
8.1.2.2.2  BV-2 Monitor Setpoints The monitor alarm setpoints above background are determined as follows:
* The calculated monitor HIGH Alarm Setpoint above background (net uCilcc) attributed to the noble gas radionuclides is determined by:
f E C; E; HSP = Ft                                                                  [2.1(2)-19]  -
F'iE ave where:
f          =  The maximum acceptable containment purge flow rate (cfm) determined in Section 8.1.2.2.1.
F'        =  The maximum actual or design effluent flow rate (cfm) at the point of release.
                                  =  53,700 cfm for VV-2
                                  =  59,000 cfm for CV-2 C;        =  The undiluted radioactivity concentration of noble gas radionuclide "i" in the gaseous source (uCilcc) as detennined by analysis of the gas to be released.
Ej        =  The detection efficiency of the monitor for noble gas radionuclide "i" (cpmluCi/cc) from ATTACHMENT B Table 2.1-2b.
E, ave    =  The CR of equation [2.1(2)-6] divided by the sum of the Ci for the respective mix.
 
Beaver Valley Power-Station'                          '                  112-ODCNme 1/-OC-2.02 ilde:.                                                                        Unit:        Level Of Use:
1C2        In-FPeld Reference ODCM: GASEOUS EFFLUENTS                                                        Revision:    Page Number.
1              27 of 129 NOTE:    To enable maintaining a constant conversion factor from cpm to uCi/ce in the Digital Radiation Monitoring System software, the "calculated mix" is used rather than the analysis mix to calculate E; ave above. This does not cause any change in the function of the monitor setpoint to properly control dose rate. However, the monitor indicated uCi/cc value may differ from the actual value.
When.a HIGH Alarm Setpoint has been calculated according to this
                              ; section, the monitor ALERT Alarm Setpoint above background (net uCi/cc) is determined as follows:
ASP =HSP x 0.5                                                      [2.1(2)-20]
8.1.3    BV-1/2 Monitor Alarm Setpoint Determination See Section 8.1.1 for a description of Monitor Alarm Setpoint Determination.
8.13.1    BV-1/2 Setpoint Determination Based On A Calculated Mix For PV-1/2 Elevated Releases The calculated monitor count rate'above background (CR), in ncpm, the monitor HIGH-HIGH alarm setpoint above background (HHSP), and the monitor HIGH alarm setpoint above background (HSP) for each operational condition are shown in the following Table:
BV-1/2 ALARM SETPOINTS FOR ELEVATED RELEASES cpm ABOVE BACKGROUND 60%            30%
(P)PRIMARY*                        SITE            SITE MONITOR                          LIMIT          LIMIT (A)ALTERNATE                      UPPER LOWER MONITOR              CR      ALARM ALARM
                      -    Continuous Release        (P)RM-IGW-108B          3.49E7      3.60E5          1.20E5 (A)RM-IGW-109(5)        2.61E7      3.60E5          1.20E5
                      . Batch Release Of          (P)RM-LGW-108B          3.93E5      2.36E5          1.18E5
              . -        BV-1 Decay Tanks or      (A)RM-lGW-109(5)        7.87E6      3.60E5          1.20E5 BV-2 Storage Tanks
                      *IF the primary monitor is out of service, THEN ODCM CONTROL 3.3.3.10 is met for the respective alternate monitor. The alternate setpoints shall be utilized:
The setpoints were determined using a calculated mix from the FSAR and discharge flow rate of 1450 cfm for PV-1/2.
 
Beaver Valley Power Station:                              C      P1/2C-                      . l TheUnit:                                                                                Level Of Use.
1/2        In-Field Reference ODCM: GASEOUS EFFLUENTS                                                      Revision:  Page Numbe.
1 -      2Xofl?12l The calculational method below was used to derive the monitor setpoints for the following operational'conditions:
* Continuous release via PV-112.
* Batch release of BV-I or BV-2 Waste Gas Decay Tank via PV-1/2.
* Batch release of BV-1 or BV-2 Containment Purge via PV-1/2 is not shown in the above table: However, if it is necessary to perform a BV-1 or BV-2 Containment Purge via this release point, the alarm setpoint shall be calculated in accordance with Section 8.1.3.2.
8.1.3.1.1      BV-1/2 Mix Radionuclides The "mix" (noble gas radionuclides and composition) of the gaseous effluent was determined as follows:
* The gaseous source terms that are representative of the "mix" of the gaseous effluent were evaluated. Gaseous source terms are the radioactivity of the noble gas radionuclides in the effluent. The gaseous source terms can be obtained from ATTACHMENT A Tables 2.1-la. and 2.1-lb.
* The fraction of the total radioactivity in the gaseotis effluent comprised by noble gas radionuclide "i" (Si) for each individual noble gas radionuclide in the gaseous effluent was calculated by:
Si    A                                                              [2.1-9]
          -                        i A, :
where:
A;    =    The total radioactivity or radioactivity concentration of noble gas radionuclide "i" in the gaseous effluent from ATTACHMENT A Table 2.1-la and 2.1.1b.
8.1.3.1.2        BV-1/2 Maximum Acceptable Release Rate (Whole Body Exposure)
The maximum acceptable total release rate (uCi/sec) of all noble gas radionuclides in the gaseous effluent (Qt) based upon the whole body exposure limit was determined by:
Qt~-      js                                                            [2.1.10]  -
where: -                                  .  .                            .
 
Beaver Valley Power Station-                              Prfocedure Numlbei Tid.I
                                          ~1/2-ODC-2.02
                                          .                        Unt:e          Lz:ve Of Use:
1/2            In-Field Reference ODCM: GASEOUS EFFLUENTS                                            Revision        Page Number l                29 of128 V1 = The constant for noble gas radionuclide "i" accounting for the gamma radiation from the elevated finite plume (mremlyear/uCi/sec) from ATTACHMENT G Table 2.2-12.
Si= From equation {2.1-9]
8.1.3.1.3  BV-1/2 Maximum Acceptable Release Rate (Skin Exposure)
Qt was also determined based upon the skin exposure limit as follows:
3000
                    =t            30                                                        [2.1-11]
Q1    [Li(XQ)p, + .lBi]Si where:
L.,        = The skin dose factor due to beta emissions from noble gas radionuclide "i"(mrem/year/uCi/m 3 ) from A'ITACHMENT G Table 2.2-11.
(X/Q)p,    = The highest calculated annual average relative concentration of effluents releases via PV-1/2 for any area at or beyond the unrestricted area boundary for all sectors (sec/i 3 ) from ATTACHMENT F Table 2.2-6.
                            = 2.3 1E-6 sec/m 3 (0.5 - 1.0 miles)
(Xtq)p,    = The highest calculated short term relative concentration of effluents released via PV-1/2 for any area at or beyond the unrestricted area boundary for all sectors (sec/m 3 ) from ATTACHMENT N Table 2.3-38.
                            = 1.07E-5 sec/m3 (0.5 - 1.0 miles)
BD        = The constant for long term releases (greater than 500 hrs/year) for noble gas radionuclide "i" accounting for the gamma radiation dose from the elevated finite plume (mradlyear/uCilsec) from ATTACHMENT G Table 2.2-12.
8.1.3.1.4 BV-1/2 Maximum Acceptable Release Rate (Individual Radionuclide)
The maximum acceptable release rate (uCi/sec) of noble gas radionuclide "i" in the gaseous effluent (Qi) for each individual noble gas radionuclide in the gaseous effluent was determined by:
Qi=Si Qt                                                                    [2.1-12]
 
Beaver Valley Power"Station                              IProcedure Numnber0
                                                                                .1/1-ODC-2.02 Tide:                                                              Unit          Lvel Of Use.
                                                                        -1/2          In-Field Reference ODCM: GASEOUS EFFLUENTS                                            ReYiOf        PageNuniber 1                301 of 129 NOTE:    Use the lower of the Qt values obtained in Section 8.1.3.1.2 and 8.1.3.1.3.
8.1.3.1.5 BV-1/2 Maximum Acceptable Concentrations (Individual Radionuclide)
The maximum acceptable radioactivity concentration (uCi/cc) of noble gas radionuclide "i" in the gaseous effluent (C;) for each individual noble gas radionuclide in the gaseous effluent was determined by:
2.12E-3 Qj Fi    -[2.1-13]
where:
2.12E-3 = Unit conversion factor (60 sec/min x 3.53E-5 ft 3 /cc).
F        = The maximum acceptable effluent flow rate at the point of release (cfm) as listed in Section 8.1.3.1.
8.1.3.1.6  BV-1J2 Monitor Count Rate The calculated monitor count rate (ncpm) above background attributed to the noble gas radionuclide. (CR) was determined by:
CR = 1. C; E,                                                              [2.1-141 where:
E;    = The detection efficiency of the monitor for noble gas radionuclide "i" (cpm/uCi/cc) from ATTACHMENT B Table 2.1-2a and 2.1-2b.
8.1.3.1.7  BV-1/2 Monitor Setpoints The monitor alarm setpoints above background were determined as follows:
* The monitor HIGH-HIGH Alarm Setpoint above background (ncpm) was determined by:
HHSP = 0.60 x CR                                                        [2.1-151
* The monitor HIGH Alarm Setpoint above background (ncpm) was determined by:
HSP = 0.30 x CR                                                          [2.1-161    "
 
Procedure Number:
valley Peaver Power Station                                      1/2-ODC-2.02
 
==Title:==
Unit:        Level Of Use:
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I              '31 of 128 8.1.3.2      BV-1/2 Setpoint Determination Based On Analysis Prior To Release For PV-1/2 Elevated Releases The following calculation method applies to gaseous releases via the PV-1/2 Gaseous Waste/Process Vent when the "calculated mix" does not provide adequate operational flexibility. This method is used to determine the setpoint for the maximum acceptable discharge flow rate and the associated HIGH-HIGH Alarm Setpoint based on this flow rate for the BV-1/2 Gaseous Waste Gas Monitor (RM-GW-108B) or alternate (RM-lGW-109 CH 5) during the following operational conditions:
* Continuous release via PV-112.
* Batch release of BV-1 or BV-2 Waste Gas Decay Tank via PV-112.
* Batch release of BV-i or BV-2 Containment Purge via PV-1/2.
8.1.3.2.1      BV-1/2 Maximum Acceptable Release Rate Determine the maximum acceptable discharge flow rate for the release from the Process Vent for the analyzed mix.
* The maximum acceptable gaseous discharge flow rate (f) from the Process Vent (cfm) based upon the whole body exposure limit is determined by:
1.06 S                                                            [2.1-21]
                                -_ Vi Ci where:
1.06    =  500 mrem/yr x 2.12E-3 500 mrem/yr        = dose rate limit, whole body exposure 2.12E-3            = unit conversion factor
                                                          = (60 sec/min x 3.53E-5 ft3 /cc)
S            Percent of site dose rate released via this pathway. Up to 60% of the site dose rate is permissible for one release point under the alarm setpoint rules of Section 8.1.3.
Vi        =  The constant for noble gas radionuclide "i" accounting for the gamma radiation from the elevated plume (mremlyear/uCilsec) from ATTACIMENT G Table 2.2-12.
 
Beaver Valley Power Station                                  I          N mb/2eDCr2.0
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1~-          32 of 129 Ci            The undiluted radioactivity concentration of noble gas radionuclide "i" in the gaseous source (uCi/cc) as determined by analysis of the gas to be released.
* Based upon the skin exposure limit, (f) is calculated by:
f.6        6.36 S                                                      [2.1-221
                        ~[Li (X/Q)p,, + 1.lBi]C*                                                21-2 where:
6.36            3000 mrem/yrx2.12E-3 3000 mrem/yr            = dose rate limit, skin exposure 2.12E-3            = unit conversion factor
                                                  = (60 sec/min x 3.53E-5      ft3 /cc)
                          =    The skin dose factor due to beta emissions from noble gas radionuclide "i" (mremlyearluCi/m 3 ) from ATTACHMENT G Table 2.2-11.
(X/Q)p    =    The highest calculated annual average relative concentration of effluents released via PV-1/2 for any area at or beyond the unrestricted area boundary for all sectors (sec/m 3 ) from ATTACHMENT F Table 2.2-6.
                          =    2.31E-6 sec/m3 (X/q)p,    =    The highest calculated short term relative concentration of effluents released via PV-1/2 for any area at or beyond the unrestricted area boundary for all sectors (sec/m 3 ) from ATTACHMENT N Table 2.3-38.
                          =    1.07E-5 sec/m3 Bi        =    The constant for long-term releases (greater than 500 hrs/year) for noble gas radionuclide "i" accounting for the gamma radiation from the elevated finite plume (mradlyear/uCi/sec) from ATTACHMENT G Table 2.2-12.
* Select the smaller of the calculated f values based on the whole body exposure limit and based on the skin exposure limit shown above. The actual discharge flow rate (cfm) must be maintained at or below this (f) value.
 
                                                                      ~~~Ptxocedure Namber 9...-......
Beaver Valley Power Station            ,. . .. ..
 
==Title:==
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                                                                                -    1:--                of l28 8.1.3.2.2      BV-1/2 Monitor Setpoints The monitor alarm setpoints above background are determined as follows:
The calculated monitor HIGH-HIGH Alarm Setpoint above background (ncpm) attributed to the noble gas radionuclides is determined by:
f    C, E; HHSP          ;[2.1-23]
F'w where:
f        The maximum acceptable gaseous discharge flow rate (cfm) determined in Section 8.1.3.2.1.
F'    =  The maximum actual or design effluent flow rate (cfm) at the point of release.
                            =  1450 cfm for PV-1/2 C;    =  The undiluted radioactivity of noble gas radionuclide "i" in the gaseous source (uCi/cc) as determined by analysis of the gas to be released.
F,=      The detection efficiency of the respective monitor (RM-lGW-108B) or (RM-lGW-109 CH 5) for noble gas radionuclide "i" (cpm/uCi/cc) from ATTACHMENT B Table 2.1-2a and 2.1-2b.
When a HIGH-HIGH Alarm Setpoint has been calculated according to this section the monitor HIGH Alarm setpoint above background (ncpm) is determined by:
HSP = HHSP x 0.5                                                                [2.1-24]
 
          'Beaver Valley Power Station                          '    '      Nl      -Dc202                -
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1.
I-      . -14 of,18 82      Compliance With 10 CFR 20 Dose Rate Limits (ODCM CONTROL 3.1121) 8.2.1  Dose Rate Due To Noble Gases The dose rate in unrestricted areas resulting from noble gas effluents from the site is limited to 500 mremn/yr to the total body and 3,000 mrem/yr to the skin. Site gaseous effluents are the total of BV-1 and BV-2 specific ground releases and a shared elevated release, the PV-1/2 Gaseous Waste/Process Vent. Based upon NUREG-0133 (3.13.1) the following equations are used to show compliance with ODCM CONTROL 3.11.2. .a.
((ViQi + Ki (X/Q)v Qj,  I< 500 mrem/yr                                            [2.2-11 L(X/Q), + 1.1B, I Qj, + [L1 + 1.1M ](XIQ), Q.]<3000imrem/yr                        [2.2-2]
where:
K;      =    The total body dose factor due to gamma emissions for each identified noble gas radionuclide "i", mremlyear/uCi/m 3 .
Lj      =    The skin' dose factor due'to beta emissions for each identified noble gas radionuclide "i", mirem/year/uCi/m 3 .
M        -    The air dose factor due to gamma emissions for each identified noble gas radionuclide "i", mradlyear/uCi/m 3 .
Vi      =    The constant for each identified noble gas radionuclide "i" accounting for the gamma radiation from the elevated finite plume, mrem/year/uCi/sec.
Bi      =    The constant for long-term releases (greater than 500 hrs/year) for each identified noble gas radionuclide "i" accounting for the gamma radiation from the elevated finite plume, mrad/year/uCi/sec.
1.1      =    The ratio of the tissue to air absorption coefficients over the energy range of the photon of interest, mrem/mrad.
Qs      =    The release rate of noble gas radionuclide "i' in gaseous effluents from free-standing stack, uCi/sec.
Qi        =  The release rate of noble gas radionuclide "i" in gaseous effluents from all vent releases, uCilsec.
(XIQ ), = The highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary for elevated releases (sec/m 3 ).              4 (XI Q )V= The highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary for elevated releases (sec/m 3).
 
f . . ........................    . ..  .......  .Proced=rNumber:
Beaver Valley Power Station                                    " -    '    2UODC 202 litle:                                        .Unit:                                    Lzvel Of Use:
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1-        ~35 of 9 At the Beaver Valley site gaseous releases may occur from the following Release Points (RP's) as shown in ATTACHMENT P Figure 2.4.2:
RP 1 & 4. The BV-1 Auxiliary Building Vent and the BV-2 SLCRS Unfiltered Pathway atop the Auxiliary Buildings'(VV-1 and VV-2)
RP 2 & 5. The BV-1 Rx ContainmentlSLCRS Vent and the BV-2 SLCRS Filtered Pathway atop the Containment Domes (CV-1 and CV-2)
RP 3.        The BV-1/2 Gaseous Waste/Process Vent atop the BV-1 Cooling Tower (PV-1/2)
RP 6.        The BV-2 Condensate Polishing Building Vent (CB-2)-
RP 7.        The BV-2 Waste Gas Storage Vault Vent (WV-2)
RP 8.        The BV-2 Decontamination Building Vent (DV-2)
RP 9.        The'BV-2 Turbine Building Vent (TV-2)
* The effluents from Release Point 1 & 4 are ground level in nature. At BV-1 the sources of these releases are Containment Purges and normal Auxiliary Building Ventilation. 'At BV-2 the sources of these releases are Containment Purges and Contiguous Area ventilation.
* Effluent from the Release Point 2 & 5 are assumed ground level in nature. At BV-1 the source of these releases is the Supplementary Leak Collection and Release System (SLCRS). At BV-2 the source of these releases is normal Auxiliary Building Ventilation. It is also possible to release Containment Purges from these vents.
* Release Points 6, 7, 8 and 9 are not normally radioactive release points.
* The effluent from Release Point 3 are elevated, and the sources of these releases are the Main Condenser Air Ejectors, the Waste Gas Decay Tanks and the Containment Vacuum Pumps.
Noble gas releases may normally occur from Release Points 1 through 5 above. To show compliance with the site limits of ODCM CONTROL 3.11.2.1.a, Equations [2.2-1] and [2.2-2] are expressed in terms of the actual release points for the site. Note that the expressions for release points 6, 7, 8 and 9 are included for use if radioactive releases via these release points are identified in the future.
 
Pfocedurc Nubc
          ,Beaver Valley Power Station --                                              -
                                    .Unit                                                                  Level Of Us :
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1              36 of 12&
8.2.1.1        Total Body Dose Rate (All Release Points)
IXVQ.
Ii
                            +X.K. [(XQ)
I1              Cv Q.      +(X/Q) vv Q.      +(X/Q) cvi.
Q.    +(X/Q) vv Q.        +(X/Q) K              Q  +(XIQ)      Q        + (XQ) Q.              +((XQ)        +(Q        )v V      tV2 +        cb    i              dv i                    WV    i 2                  -cb2                                              dv2                      wv2
            < 500 mrem/yr                                                                                                  [2.2-31 8.2.1.2        Skin Dose Rate (AU Release Points).
                  ,[Li(XZQ),v +lAB;]Qi                                +lli[ Izk QCvi                    Q+(        vv      i
                                                          .          .          .cv2 (XIQ)
Cv Q.
1
                                                + (XQ)
VV Q.
1
                                                                      + (X/Q)
                                                                            -tv Q.
1
                                                                                            + (XIQ)        Q.
cb 9i
                                                                                                                    +  (XIQ) dv cv2                  vV2                    tv2                    cb2 i
dv2
                                + (XQ)w Qi vv2 I <3000 mremlyr                                            [2.24]
where:
Qi              = Release rate of radionuclide "i" from the PV-1/2, uCilsec.
pv
                            -      Release rate of radionuclide .Tfrom CV-1, uCi/sec.
QiCVI Release rate of radionuclide "i" from CV-2, uCi/sec.
  -..          cv2 QiVI            = Release rate of radionuclide "i" from VV-1 Auxiliary Building, uCi/sec.
wvl
                                -Release        rate of radionuclide "i" from, VV-2, uCilsec.,
Qi 1 I._ -          vv2 Qi              = Release rate of radionuclide "i" from TV-2, uCi/sec.
tv2
            .QQi              -    Release rate of radionuclide .T' from CB-2, uCi.sec.
cb Qi              = Release rate of radionuclide "i" from DV-2, uCi/sec.
dv2
 
_ toredv    Numbe
        ;Beaver Valley Power Station                          -ro:edue12-ODC-2.02
'itde:                                                                  Unit:            Level Of Use:
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1 vv2 (X/Q )p      =  Highest calculated annual average relative concentration for releases from the PV-1/2, sec/m 3 .
(X/Q )CV    =  Highest calculated annual average relative concentration for releases from CV-1 and CV-2, sec/m3 .
(X/Q)W      =  Highest calculated annual average relative concentration forreleases from
                          -W-1and VV-2, seclmo.
(XIQ )tv    =  Highest calculated annual average relative concentration for releases for TV-2, sec/rn3 .
(X/Q    )cb =  Highest calculated annual average relative concentration for releases for CB-2, sec/m 3 .
(X/Q )dv    =  Highest calculated annual average relative concentration for releases for DV-2, sec/m 3 .
(X/Q )W = Highest calculated annual average relative concentration for releases for WV-2, sec/rn3 .
The release rate for a containment purge is based on an averaged release rate in uCi/sec for the entire purge (not to exceed 960 min in accordance with ODCM CONTROL 3.11.2.1).
All other terms remain the same as those defined previously.
For the site, 4 potential modes of release are possible. The release modes identify the various combinations of sources of radioactivity and their release points which are used to determine the controlling locations. They are presented in ATTACHMENT C Table 2.2-1.
For Release Modes 1, 2, and 3, the controlling location for implementation of ODCM CONTROL 3.11.2.1.a is 0.35 miles NW. Inserting the appropriate X/Q's from ATTACHMENT F Tables 2.24 through 2.2-10 for this location, Equations [2.2-3] and
[2.24] become:
 
Title Beaver Valley Power Station                                                    I Pr-cdur Unit:
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J e 1        1          X nf 19R 8.2.1.3        Total Body Dose Rate (at 0.35 Miles NW)
ZV.Q.        +ZK. [9.24E-5Qi                      +1.03E-4 Q.              +9.24E-5Q.                +
pv    i                          cv1                                                1 2 ii                            cv 1.03E - 4 Q.          + 7.35E-5 Q                  +9.24E-5Qi              + 9.24E - 5 Q1              +
wV    ,                    tv                      dv                          W`V 7.35E-5 Q-            ] < 500mremlyr                                                                      [2.2-5]
cb 8.2.1.4        Skin Dose Rate (at 0.35 Miles NW)
I [7.E-10LI +l.1BIQ                        i [Li +l.lM.]+9.24E-5Q.                          + 1.03E-4 pv    1                .*                      cvi Q        + 9.24E - 5 Qi          +1.03E-4Q .              +7.35E-5Q                  + 9.24E -5Q                +
1          vv          cv122 cv                                                  t 2                        dv 2 dv 9.24E - 5 Q.            + 7.35E - 5 Q              ] < 3000 mrem/yr                                            [2.2-6]
wv2                        cb2 For Release Mode 4, the controlling location is 0.75 miles N. Inserting the appropriate XIQ's from ATTACHMENT F Tables 2.24 through 2.2-10 for this location, Equations
[2.2-3 and 2.2-4] become:
8.2.1.5        Total Body Dose Rate (at 0.75 Miles N)
I V. Q        + X K [3.95E- 6 Qi                  +4.99E-6Qi              +3.95E-6Qi                + 4.99E -
i  I    Ppv      i                  I    cv                      VVw 6Q i2      + 4.26E - 6 Qi            + 3.95E - 6 Qi            + 3.95E - 6 Qi              +4.26E-6Qi                  I wV                          2 tv                        dv2                          WV                          cb 2
                < 500 mrem/yr                                                                                          . .. L2.2-7]
8.2.1.6        Skin Dose Rate (at 0.75 Miles N)
Z[2.31E-6Li +1.LB.jQ.                    +Z[Li +1.lMi][3.95E-6Q                            +4.99E-6Qi                  +
i                                  pV        1                                      cv                        vv 3.95E - 6 Qi cv 2
                                    + 4.99E-6Qi wV 2
                                                                  + 4.26E-6Qi tv 2
                                                                                            + 3.95E-6Qi dv
                                                                                                                      + 3.95E-          I.
6Q.i      + 4.26E - 6 Qi          ] < 3000 mrem/yr                                                          [2.2-81 wv                    cb
 
                .eve. Valley        Poe-SaihProcedure
                                    - - BePoweStatio                                Number.
112-ODC-2.02
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1 -        q9 of 1IN '
8.2.1.7  Determination of Controlling Location The determination of controlling location for implementation of ODCM CONTROL 3.11.2.l.a for noble gases is a function of the following parameters:
          -      . Radionuclide mix and their isotopic release rate
                  . Release Mode
* Meteorology The incorporation of these 3 parameters into Equations [2.2-3] and [2.24] resulted in the equations for the controlling locations as presented in Equations [2.2-5 through 2.2-8 ] .
The radionuclide mix used to determine controlling locations was based on source terms calculated with the Stone and Webster Engineering Corporation computer code GAS IBB (similar to NUREG-0017.(3-.          Inputs were based on operating modes of the respective plants. The code inputs utilized are presented in 1/2-ODC-3.01. The source term is presented in ATTACHMENT D Tables 2.2-2a and 2.2-2b as a function of release type and Release Point.
The X/Q values utilized in the equations for implementation of ODCM CONTROL 3.11.2.1.a are based upon the maximum long-term annual average X/Q in the unrestricted area. ATTACHMENT E Table 2.2-3 presents the distances from the Release Points to the nearest unrestricted area for each of the 16 sectors as well as to the nearest vegetable garden, cow, goat, and beef animal. ATTACHMENT F Tables 2.24 through 2.2-10 present the long-term annual average (X/Q) values for all Release Points to the special locations presented in ATTACHMENT E Table 2.2-3.
A description of their derivation is provided in 1/2-ODC-3.01.
For Release Modes 1, 2, and 3, dose calculations were performed using the highest calculated site boundary X/Q values applicable to the release points involved and the projected radionuclide mix applicable to the release source. In that a simultaneous, continuous elevated release could contribute to the dose at a given location, the selection of the two highest sector X/Q values at the site boundary considered this contribution. From these results, the distance and sector associated with the highest calculated site boundary dose were selected as the'controlling location.
For Release Modes 1, 2, and 3 the controlling location is 0.35 miles NW. In Release Mode 1, the dominant release is via VV-I and CV-2. In Release Modes 2 and 3, the dominant release is a Containment Purge from the VV-l or VV-2.
 
        -Beaver Valley Power Station II Procedure Number,
                                                                            --      1/2-ODC-2.02          :
ltlc ..                                                                  Unit:        Level Of Us:
                                                                      .112            . In-Field Reference ODCM: GASEOUS EFFLUENTS                                                  Rension:      PageNumber For Release Mode 4, a similar evaluation was performed. Long-term annual average XIQ values were calculated at thermid-point of the 10 standard distances listed in ATTACHMENT F Table 2.24 through 2.2-10. In that a simultaneous, ground level release could contribute to the dose at a given location, the selection of the two highest XIQ values at the controlling distance considered this contribution. Since the two maximum XIQ values occurred in the 0.5 - 1.0 mile radial band, the controlling distance was selected at 0.75 miles. From the calculated dose results, the controlling sector was shown to be North. In this Release Mode, the dominant release is a Containment Purge via the PV-1/2 Gaseous Waste/Process Vent. Neither of the controlling receptor locations are presently inhabited.
Values for Kj, L, and Mi, which were used in the determination of the controlling receptor location and which are to be used in Equations [2.2-5] through [2.2-8] to show compliance with ODCM CONTROL 3.11.2.1.2, are presented in Table 2.2-11.
Values taken from Table B-i of NRC Regulatory Guide 1.109, Revision 1,(3.1.35) were multiplied by 1E6 to convert picocuries to microcuries for use in ATTACHMENT G Table 2.2-11.
Values for V; and Bi for the finite plume model can be expressed as shown in Equation [2.2-9] and [2.2-10]. Values were calculated using the NRC code RABFdN at the site boundary location which would receive the highest total dose from all Release Points. These values are presented in ATTACHMENT G Table 2.2-12 and calculated from the following equation:
K          f.Anu EI
                    -z    z      Aii Ua ElI229]
B.[2.2-9 E.          rd jk IUj                      .
where:
I    = The results of numerical integration over the plume spatial distribution of the airborne activity as defined by the meteorological condition of wind speed
                        .(UP)and atmospheric stability class "k" for a particular wind direction.
K    =    A numerical constant representing unit conversions.
(260 mrad)(radians) (m3 ) (transformation)  r16 sectors (sec)(MevXCi)                  L27r    radians
[        CiE r        seca]
2.1E4 mrad (m3) (transforrnation)/yr(Mev)(uCi).l rd  = The distance from the release point to the receptor location, meters.
 
Procedure Number.
Beaver Valley Power Station_:_-___    Powe Staion1/2-6DC-2.02 Tide:                                                                        Unit:          Level Of Use:
                                                                                  . .1/2    IIn-Field Reference ODCM: GASEOUS EFFLUENTS                                                                      Page Number
                                                                                      -  1          41 of 128 uj    = The mean wind speed assigned to the "j" th wind speed class, meters/sec.
fik  = The joint frequency of occurrence of the "j" th wind speed class and kth stability class (dimensionless).
Ali= The number of photons of energy corresponding to the "l"th energy group emitted per transformation of the "i" th radionuclide, number/transformation.
El    = The energy assigned to the "1"th energy group, Mev.
ua = The energy absorption coefficient in air for photon energy Hi, meters The V; factor is computed with conversion from air dose to tissue depth dose, thus:
f  A u E I -:UT T V=    1.1      iK ij                uia e2.2-10]
s    dr j k I                U.
where:
UT  =    The tissue energy absorption coefficient for photons of energy El, cm 2/gm.
Td    = The tissue density thickness taken to represent the total body dose (5gm/cm2 ).
1.1 = The ratio of the tissue to air absorption coefficients over the energy range of photons of interest, mrem/mrad.
8.2.2 Dose Rate Due To Radioiodines And Particulates The dose rate in unrestricted areas resulting from the of inhalation of I-131, tritium, and all radionuclides in particulate form (excluding C-14) with half lives greater than 8 days released in gaseous effluents from the site shall be limited to 1,500 mrem/yr to any organ.
Based upon NUREG-0133,( 3              the following basic equation is used to show compliance with ODCM CONTROL 3.11.2.1.b:
XPS pX/Q)s Qi        +  (X/Q)v Q1i, < 1,500 mrem/yr                                        [2.2-11]
where:
PT        =  Dose parameter for any organ    t for each identified radionuclide "i",
mrem/yr per uCi/m3.
Qi        = The release rate of radionuclide "i", in gaseous effluents from elevated releases, uCi/sec.
 
                                                                        - Beaver Vly-Nmber..
IBeaver Valley Power Station                                            1/-ODC-2.02 Tdle. *:.; .                                                                Unit:        Level Of Use:          I 1/2        In-Field Reference Revision:    Page Number ODCM: GASEOUS EFFLUENTS I        42 of 12 Qiv        = The release rate of radionuclide "i", in gaseous effluents from ground level releases, uCilsec.
(X/Q)s = The highest calculated annual average relative concentration at the unrestricted area boundary for elevated releases, sec/m3 .
(XIQ)V = The highest calculated annual average relative concentration at the unrestricted area boundary for ground level releases, sec/m3 .
NOTE:        The dispersion pararneters specified in Section 8.2.2 are limited to the site boundary as defined above.
Releases may occur from any Release Point in the Release Modes listed in ATTACHMENT C Table 2.2-1. To show compliance with ODCM CONTROL 3.11.2.1 .b, Equation [2.2-11] is now expressed in terms of the actual Release Points for the site.
2 +
Z P. [(X/Q)      Q.                                                                            i
                                        + (X/Q)cv Qi I +(XIQ) VQ      vV I + (X/Q)cv Qi IT        pv    1 pv cv                                        cv
                                                                                                                  )
(X/Q)tv Qi.      + ((X/Q)cb Qi        + (XIQ)dv Qi 2 +(X/Q)WV w        Qi        1*< 1500 mre/j tv2              cbI cb 2 WV'2 dv
[2.2-121 where:
(X/Q)pv = Highest calculated annual average relative concentration for releases from PV-1/2, sec/m 3 .
(X/Q)CV = Highest calculated annual average relative concentration for releases from CV-1 and CV-2, sec/m 3 .
(X/Q),, = Highest calculated annual average relative concentration for releases from VV-1 and VV-2, sec/m 3 .
(X/Q)tv = Highest calculated annual average relative concentration for releases from TV-2, sec/m3 .
(X/Q)Cb = Highest calculated annual average relative concentration for releases from CB-2, sec/m3 .
 
Beaver Valley Power Station                                    Procedu Number-.
Tide:                                                                  Unit:      Lvel Of Use:
112
                                                                          ...          In-Field Reference ODCM: GASEOUS EFFLUENTS                                                    I      Page Numbe4 (X/Q)d,    = Highest calculated annual average relative concentration for releases from DV-2, sec/m 3 .
(X/Q),, = Highest calculated annual average relative concentration for release from WV-2, sec/m3 .
Q.        = Long-term release rate of radionuclide "i" from PV-1/2, uCi/sec.
1 pv Q.        = Long-term release rate of radionuclide "i" from CV-1, uCilsec.
1cvl Q.      - = Long-term release rate of radionuclide "i" from CV-2, uCi/sec.
cv2 Q.        = Long-term release rate of radionuclide "i" from VV-1, uCi/sec.
1 vvl Q.        = Long-term release rate of radionuclide "i" from VV-2, uCi/sec.
vv2 Q.        = Long-term release rate of radionuclide "i" from TV-2, uCi/sec.
tv2 Q.        = Long-term release rate of radionuclide !'i" from CB-2, uCi/sec.
cb2 Q.        = Long-term release rate of radionuclide "i" from DV-2, uCi/sec.
1dv2 Q.        = Long-term release rate of radionuclide "i" from WV-2, uCi/sec.
                'wv2 All other terms are the same as those defined previously.
TV-2, CB-2, DV-2 and WV-2 are not normal radioactive Release Points. These Release Points are included only for use if radioactive releases via these vents are identified in the future. In the calculation to show compliance with ODCM CONTROL 3.11.2. .b only the inhalation pathway is considered.
Values of the organ dose parameters, Pi,, were calculated using methodology given in NUREG-0133.(3-          For the child age group, the following equation was used for all nuclides. The Pi,, values are presented in ATTACHMENT H Table 2.2-13.
            = 3.79E9 DFAIT                                                                    [2.2-13]
 
                                                                .-      .  . Procedur Numberc Beaver Valley Power Station                                                  I 1/2-ODC-2.02 The:            .Unit:                                                                      Lvel Of Use:
                      .  -  ..                                                  112          In-Field Reference ODCM: GASEOUS EFFLUENTS                                                        Revision:      age Num1ber where:
3.7E9 =      Breathing rate of child (3,700 m3 /yr) x unit conversion factor (1E6 pCi/uCi).
DFAi, =      The organ inhalation dose factor for a child from Table 6 of NUREG-0172,(3-'    for organ T, nuclide "i", in units of mrem/pCi.
For Release Modes 1 through 4, the controlling location is the site boundary, 0.35 miles NW.
Equation [2.2-12] becomes:
zP. [7.OOE-10Q.              +9.24E-5Q.          +1.03E-4Q.            +7.35E-SQ.            +
i                      pv                cv1                  vv1                      tvl 9.24E-5 Q            + 1.03E.-4 Q.        + 7.35E-5 Q-        +7.35E-5Q.              + 9.24E-cv2                  vv2                  tv2                    cb2 5Q.          + 9.24E-5Q.          I < 1500 mrem/yr                                        [2.2-141 dv2                    wv2 8.2.2.1      Determination of Controlling Location The determination of the controlling location for implementation of ODCM CONTROL 3.11.2.1.b for radioiodines and particulates is a function of the same 3 parameters as for noble gases plus a fourth, the actual receptor pathways. The incorporation of these parameters into Equation [2.2-12] results in the respective equations for each Release Mode at the site boundary controlling locations. The radionuclide mix was again based upon the source terms presented in ATTACHMENT D Tables 2.2-2a and 2.2-2b as a function of release type and Release Point.
In the determination of the controlling site boundary for each Release Mode, the highest 2 site boundary XIQ values for each Release Point were utilized in conjunction with the radionuclide mix and the release rate for each Release Point to determine the controlling location.
The Pi, values are presented in ATTACHMENT H Table 2.2-13.
The X/Q values in Equation [2.2-14] were obtained from ATTACHMENT F Tables 2.24 through 2.2-10.
A description of the derivation of the X/Q values is provided in 1/2-ODC-3.01.
 
Beaver Valley Power Station                                                    1120DC-2.02 Mtk          -      :                                                            Unit:          Lcvel Of USG
[                    In-Field e.1/2        Reference ODCM: GASEOUS EFFLUENTS                                                            Revision:      Page Number:
1-          4-5 of 128 8.3      Compliance With 10 CFR 50 Dose Limits (ODCM CONTROLS 3.11.2.2 And 3.11.2.3)
(Gaseous)
At the Beaver Valley site all elevated gaseous releases are considered to originate from a shared radwaste system. The effluent from both units are mixed and discharged from a common Release Point, the PV-1/2 Gaseous Waste/Process Vent, at the top of the Unit 1 Cooling Tower.
The resulting dose for the purpose of implementing 10 CFR 50 is normally apportioned equally to each unit. The only exception would be a Containment Purge via the Process Vent. The resulting dose shall be attributed to the contributing reactor unit. Since this operation is expected to be rare, equations are shown throughout this section with the apportionment set at 0.5.
8.3.1      Dose Due To Noble Gases 8.3.1.1        Cumulation Of Doses Section 11.1.1 of Appendix I of 10 CFR 50 (ODCM CONTROL 3.11.2.2) limits the releases of gaseous effluents from each reactor such that the estimated annual gamma air dose is limited to 10 millirad and the beta air dose is limited to 20 millirad. In addition, ODCM CONTROL 3.11.2.4 requires use of radwaste system if air doses when averaged over31 days exceed 0.2 mrad for gamma and 0.4 mrad for beta.
Based upon NUREG-0133,(P '3'l) the air dose limits in the unrestricted area due to' noble gases released in gaseous effluents are defined by the following equations:
8.3.1.1.1          Gamma Radiation Ouarter Limit 3.17E-8 I        i [M(X/Q)vQiv  + (X/q)vqiv +    [B Q.    +  biq.s  D      5 mrad          [2.3-1]
i                                          is 8.3.1.1.2          Beta Radiation Ouarter Limit 3.17E-    8 1      XQ)NQ        +(Xq) qiv + (XIQ)        Q . +(Xlq) qisJ* 10mrad                [2.3-2]
8.3.1.1.3          Gamma Radiation Year Limit 3.17E8 1          [M[(X/Q)v      i                +[BiQjs +biqis)) _ l0mrad 8.3.1.1.4          Beta Radiation Year Limit
                .,3.17E-8 z    Ni  k(X/rnQv    + (X/q) qiv + (X/Q)s Q. + (X/q)s]                              d
[2.34]
 
Beaver Valley Power Station) -                                --          1/2-ODC-2.02          -
TidC:                                                                    Unit        jlvet Of  Us:          -
                                    .1/2                                                  In-Field Reference ODCM: GASEOUS EFFLUENTS                                                  Revision:    Page Number 1              46S of 1298 8.3.1.1.5      Gamma Radiation Projection Averazed Over 31 Days 3.17E-81[M.      kX-/Q) Q~ +(Xtq) qqI+BQ., + b.q.5I                    .2rd.235 i i        v  iv      qv iv      t14  i +i.1l < 0.2 mrad                [2.3-5]
8.3.1.1.6  -  Beta Radiation Proiection Averaged Over 31 Days 3.17E-8Z N        1(X/Q)v      +d(Xtq) qV + (X/Q) Q      5 +(X3q)qisJO.4mrad                [2.3-6]
where:
Mi      = The air dose factor due to gamma emissions for each identified noble gas radionuclide "i" (mrad/yr per uCi/m 3 ).
Ni      = The air dose factor due to beta emissions for each identified noble gas radionuclide "i" (mrad/yr per uCi/m 3 ).
  -        (XIQ),  =  The annual average relative concentration for areas at or beyond the unrestricted area boundary for long-term vent releases greater than 500 hrs/year (sec/m 3 ).
(Xtq)    = The relative concentration for areas at or beyond the unrestricted area boundary for short-term vent releases equal to or less than 500 hrs/year (sec/M 3).
(X/Q)5  =  The annual average relative concentration for areas at or beyond the unrestricted area boundary for long-term free standing stack releases greater than 500 hrs/year (sec/r 3 ).
(Xtq)5  =  The relative concentration for areas at or beyond the unrestricted area boundary for short-term free standing stack releases equal to or less than 500 hrs/year (sec/m 3 ).
qis      =    Release of noble gas radionuclide "i" in gaseous effluents for short-term stack releases equal to or less than 500 hrs/year (uCi).
qiv      =    Release of noble gas radionuclide "i" in gaseous effluents for short-term vent releases equal to or less than 500 hrs/year (uCi).
Qis      = Release of noble gas radionuclide "i" in gaseous effluents for long-term free ,
standing stack releases greater than 500 hrs/year (uCi).
Qiv      = Release of noble gas radionuclide "i" in gaseous effluents for long-term vent releases greater than 500 hrs/year (uCi).
 
Procedure Numb=
:eaver Valley Power Station                                                112-ODC-2.02
 
==Title:==
Unit          Level Of Us 1/          In-Fteld Reference ODCM: GASEOUS EFFLUENTS                                                  Revisio:      Page Numbe-.
                                  -                                          1              47 of l128 Bi        =The constant for long-term releases (greater than 500 hrs/year) for each identified noble gas radionuclide "i" accounting for the gamma radiation from the elevated finite plume (mrad/yr per uCi/sec).
bi        =The constant for short-term releases (equal to or less than 500 hrs/year) for each identified noble gas radionuclide "i" accounting for the gamma radiation from the elevated finite plume (mrad/yr per uCilsec).
3;17E-8 = The inverse of the number of seconds in a year.
NUREG 0133(3- ' permits eliminating the short-term release term and short-term meteorological terms in the determination of doses when short-term releases are sufficiently random in both time of day and duration to be represented by annual average dispersion conditions. This special consideration is applied in Equations [2.3-1] through
[2.3-61, however, a summary of the "real time'. meteorological data coupled with the corresponding releases shall be included in the Annual Radioactive Effluent Release Report.
Short-term releases are also evaluated annually in computer codes technically consistent with XOQDOQ and GASPAR for inclusion in the Annual Radiological Environmental Report.
The incorporation of this option and the Release Modes of ATTACHMENT I Table 2.3-1 results in the following equations to show compliance with 10 CFR 50 for the calendar quarter or year.
8.3.1.1.7        Gamma Radiation Dose Equation 3.17E - 8[M [(X/Q) cvi        Qi    +(X/Q) VV Q-i - + (X/Q) cb Qi      +(X/Q) dvQi        +
cv              w                  cb                  dv (XIQ)      Q.    ]+0.5B.Q. I                                          [2.3-7]
wv1 WV        1  P
              < 0.2 mrad (per 31 days), or
              < 5.0 mrad (per quarter), or
              < 10.0 mrad (per year)
 
U-I.Beav'er_            Valley                Poe Stto Powe__Statio__________.
IProcedure Numbea 1/2-ODC-2.02 1
itle:                                                                          Unit            vel Of UReeec
.M    GASOU
          .S              EL,                                                        1/2        In-Field Reference Revision . Page Numb=r ODCM: GASEOUS EFF7LUENTS                                                                                                    --'
a      I              48 of 1298 8.3.1.1.8              Beta Radiation Dose Equation 3.17E- 8            Ni [(X/Q)cvQi        + (X/Q)vQi      + (XIQ)cbQi      +(X/Q)dvQi              +
I                    cv                wV              cb                      dv (X/Q) WV Q.I      + 0.5 (XQ) V Q.1 pV 1p                                  [2.3-8]
                                              -WV
                    < 0.4 mrad (per 31 days), or
                    < 10.0 mrad (per quarter), or
                    <20.0 mrad (per year) where:
(X/Q)CV = Annual average relative concentration for releases from CV-1 and CV-2 (sec/m 3 ).
(X/Q)v = Annual average relative concentration for releases from VV-1 and VV-2 (sec/m3 ).
(X/Q)P, = Annual average relative concentration for releases from PV-1/2 (sec/m 3 ).
(X/Q).v =        Annual average relative concentration for releases from TV-2 (sec/m 3 ).
Qi          = Release of radionuclide "i" from CV-1 and CV-2 (uCi).
cv Qi          = Release or radionuclide "i" from VV-1 and VV-2 (uCi).
Qi          = Release of radionuclide "i" from PV-1/2 (uCi).
pv Qi                Release of radionuclide "i" from TV-2 (uCi).
tv          R          of                    '
Qi      = Release of radionuclide "i" from the CB-2 (uCi).
cb Qi              Release of radionuclide "i" from DV-2 (uCi).
dv Qi    =    Release of radionuclide "i" from WV-2 (uCi).
WV
 
tatProcedure                    Number.
Beaver Valley Power Station                                                    1/2-oDC-20 fllde:                                                                      Unit            Level Of UseR
                      -M GS2                                                                  In-Feld Reference ODCM: GASEOUS EFFLUENTS                                                    Revision:      Page Number:
1          49 of 129 For Release Modes 1, 2, 3, and 4 the controlling location is 0.35 miles NW. Substitution of the appropriate XIQ values into Equations [2.3-7] and [2.3-8] results in the following:
8.3.1.1.9      Gamma Radiation Dose Determination 3.17E-8      [M.[9.24E - 5 Q.      + 1.03E -4 Q.        +7.35E-5Q            + 7.35E-5 Q              +
ICY                              1                    1 tv                  '    cb 9.24E-5Q.        + 9.24E - 5 Q.    ]+0.5BQ                                    [2.3-9]
                                  - -dv                wv        -    pv  -
          < 0.2 mrad (per 31 days), or
          < 5.0 mrad (per quarter), or
          <10.0 mrad (per year) 8.3.1.1.10      Beta Radiation Dose Determination 3.17E-8      Ni[9.24E-5 Qi        + 1.03E-4 Qi        + 7.35E-5 Qi          + 7.35E-5 Q.            +
1    .              cv                v                                              cb 9.24E -5 Qi.    +9.24E-SQi          + (0.5) 7.OE - 10Q.          1        [2.3-10]
dv                wv                            pv
          <  0.4 mrad (per 31 days), or
          < 10.0 mrad (per quarter), or
          < 20.0 mrad (per year) 8.3.1.1.11      Determination of Controllin2 Location The determination of the controlling locations for implementation of 10 CFR 50 is a function of the following parameters:
* Radionuclide mix and their isotopic release
* Release Mode
* Meteorology The incorporation of these parameters into Equations [2.3-7] and [2.3-8]
resulted in the equations for the controlling locations as presented in Equations
[2.3-9] and [2.3-10]. The radionuclide mix was based upon source terms calculated using the NRC GALE Code (see 1/2-ODC-3.01 for inputs) and are shown in ATTACHMENT D Tables 2.2-2a and 2.2-2b as a function of release type and Release Point.
 
TIlde:
Beaver Valley Power' Station' Unit 1/2-ODC-2.02 UCeI Of Use1 1
1/2      In-Field Reference ODCM: GASEOUS EFFLUENTSReisian:                                                Pag Nfmbet
              - _    _ _ _ _ _ _ _ _ _ _ _0_of_              _128 As in Section 8.2.1, for each Release Mode, the two highest boundary XIQ values for each release point and release duration were utilized in conjunction with the radionuclide mix and release for each release point to determine the controlling site boundary location. Since elevated releases occur from the BVPS site and their maximum X/Q values may not decrease with distance (i.e.,
the site boundary may not have highest X/Q values), the two highest X/Q values for those distances, greater than the site boundary, were also considered in conjunction with the radionuclide mix to determine the controlling location.
These values of XIQ were obtained for the midpoint of the 10 standard distance intervals previously presented in ATTACHMENT F Tables 2.24 through 2'.2-10.
For each Release Mode, a particular combination of Release Point mix and meteorology dominates in the determination of the controlling location. For Release Modes 1, 2 3, and 4 the controlling release is VV-1 and VV-2. For Release Mode 3, the controlling release is CV-1 and CV-2.
Values for Mi and Ni, which were used in the determination of the controlling location and which are to be used by BV-1 and BV-2 in Equations [2.3-9] and
[2.3-10]'to show compliance with 10 CFR 50 were presented in ATTACHMENT G Table 2.2-11. Values taken from Table B-I of Regulatory Guide 1.109, Revision 1(3.l.35) were multiplied by 1E6 to convert from picocuries to microcuries for use in ATTACHMENT G Table 2.2-11.
In determination of the controlling location for Release Modes 1, 2, 3, and 4, ATTACHMENT F Tables 2.2-4 through 2.2-7 are utilized for X/Q values. The Bi values to be utilized are'the same values which were presented in ATTACHMENT G Table 2.2-12. A description of the derivation of the various X/Q values is presented in 1/2-ODC-3.0 1.
The following relationship must hold for BV-I or BV-2 to show compliance with ODCM CONTROL 3.11.2.2-'
For The Calendar Quarter Dy* 5.0 mrad                                                            [2.3-11]
Dp < 10 mrad                                                            [2.3-12]
For The Calendar Year Dy <10 mrad                                                              [2.3-13]  C Dpi < 20 mrad                                                          [2.3-14]
 
Beaver Valley Power Station                          Nun'2-ODC..2o'
 
==Title:==
Unit:      Level Of Use:
1/2        In-Field Reference ODCM: GASEOUS EFFLUENTS                                                    Revision:  Page Number.
1        Sl1 of 128 where:
Dy=    The air dose from gamma radiation (mrad).
Dp = The air dose from beta radiation (mrad).
The quarterly limits given above represent one-half th' annual design'objective of Section L.B. 1 of Appendix I of 10 CFR 50. If any of the limits of Equations
[2.3-11] through [2.3-14] are exceeded, a special report pursuant to both Section IV.A of Appendix I of 10 CFR 50 and ODCM CONTROL 3.11 .2.2.a must be filed with the'NRC at the identified locations.
In addition, ODCM CONTROL 3.1.2.4 requiries that the gaseous radwaste system must be used to reduce radioactive materials in that waste when projected doses from each reactor unit when averaged over 31 days exceed any of the following:
Dy < 0.2 mrad                                                            [2.3-15]
Dp < 0.4 mrad                                                            [2.3-16]
8.3.1.2      Projection Of Doses (Noble Gas)
Doses due to gaseous releases from BV-1 and BV-2 shall be projected at least once per 31 days in accordance with ODCM CONTROL 4.11.2.4 and this section. (Also see Section 8.3.2.2 Projection Of Doses for additional specifications). 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 in accordance with ODCM CONTROL 3.11.2.4 when the projected gaseous effluent air dose due to gaseous effluent releases from each reactor unit, when averaged over 31 days, would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation.
(Also see Section 8.3.2.2 Projection Of Doses for additional specifications). The doses used in the 3 1-day dose projection will be calculated using Equations [2.3-9]
and [2.3-10] as appropriate.iThe 31-day dose projection shall be perfonned according to the following equations:
8.3.1.2.1        When Includine Pre-Release Data, D3 t=  [A      (3 i) + C                                                [2.3-17]
 
                                                                                    ~~~~~~~~~~~~~R                                      PNumber:
Beaver Valley Power Station
___    *1/2-ODC-2.02 1,'2-ODCNumb&
dve raass    .....................
 
==Title:==
Unit            Lvel Of Use-112            In-Field Reference ODCM:- GASEOUS EFFLUENTS                                                                Revision:        Page Numbec                        :
                                      . .                .                                  1                          2 of 128 8.3.1.2.2          When Not Including Pre-Release Data, D31 =[](        3 1 )+C                                                                        [2.3-18]
where:
D31      -      Projected 31 day dose (mrad).
A        =      Cumulative dose for quarter (mrad).
B        -      Projected dose from this release (mrad).
T        =      Current days into quarter.
C        =      Value which may be used to anticipate plant trends (mrad).
8.3.2    Dose Due To Radioiodines And Particulates 8.3.2.1      Cumulation Of Doses Section ll.C of Appendix I of 10 CFR 50 (ODCM CONTROLS 3.11.2.3 and 3.11.2.4) limits the release of radioiodines and radioactive material in particulate form from each reactor unit such that estimated dose or dose comnitment to an individual in an unrestricted area from all pathways of exposure is not in excess of 15
                        -mremto any organ. In addition, ODCM CONTROL 3.11.2.4 requires the use of
:gaseous radwaste treatment system when the projected dose due to gaseous effluent releases from each reactor unit;,when averaged over 31 days, would exceed 0.3 mrem to any organ. Based upon NUREG-0133,(3 3.1) the dose to an organ of an individual from radioiodines and particulates, and radionuclides other than noble gases with
            '          half-lives greater than 8 days in gaseous effluents released to unrestricted areas, can be determined by the following equation:
8.3.2.1.1          Radioiodines and Particulates Month, Ouarter, and Year Limits 3.17E-8      E  Ri. [WsQis + Wsqis + WvQiv + w vq.v
                                < 0.3 mrem (per 31 days), or                                                                    [2.3-191
                                < 7.5 mrem (per quarter), or
                                < 15.0 mrem (per calendar year)
 
Procedure Number:
Beaver Valley Power Station ./2-ODC-2.02
 
==Title:==
Unit:        Level Of Use:
1/2          In-Field Reference ODCM: GASEOUS EFFLUENTS                                    Revision:    Page Number.
                                                                    . 1          53 of 12is where:
                        =  Release of radionuclide "i" for long-term free standing stack releases greater than 500 hrs/yr (uCi).
Qiv =  Release of radionuclide "i" for long-term vent releases greater than 500 hrs/yr (uCi).
qis =  Release of radionuclide "i" for short-term free standing stack releases equal to or less than 500 hrs/yr (uCi).
qiv = Release of radionuclide "i" for short-term vent releases equal to or less than 500 hrs/yr (uCi).
wS  = Dispersion parameter for estimating dose to an individual at the controlling location for long-term free standing stack releases greater than 500 hrs/yr.
sec/m 3 for the inhalation pathway, (W/Q)s.
                        = meters-2 for the food and ground plane pathway, (D/Q )s.
WV = The dispersion parameter for estimating the dose to an individual at the controlling location for long-term vent releases greater than 500 hrs/yr;
                        = sec/rn3 for the inhalation pathway, (X/Q ),.
                        =  meters,2 for the food and ground plane pathway, (D/Q ).
wS =Dispersion parameter for estimating the dose to an individual at the controlling location for short-term stack releases equal to or less than 500 hrs/yr.
sec/rn3 for the inhalation pathway, (W/q )s.
meters 2 for the food and ground plane pathway, (D/q )s.
WV =The dispersion parameter for estimating the dose to an individual at the controlling location for short-term vent releases equal to or less than 500 hrs/yr.
                        =  sec/m 3 for the inhalation pathway, (X/q )v.
                        = meters-2 for the food and ground plane pathway, (D/q)v.
 
J U-Beaver Valley Power Station PduNume-r
__1/2-ODIC-2.02 TlUenit                                                                                              Level Of UseI 1/I2~ Ihn-Field Reference ODCM: GASEOUS EFFLUENTS                                                                  Revision:    Page Number:
                        -                                                          -            1            54 of 128 3.17E-8 = The inverse of the number of seconds in a year.
Reh            = The dose factor for each identified radionuclide "i" for the
                                                                                                              -2 organ "X"of interest (mrem/yr per uCi/sec per m or mrem/yr per uCi/m 3 ).
Radionuclides and particulates may be released from any of the BV-1 and BV-2 Release Points in the Release Modes identified in ATTACHMENT I Table 2.3-1. As described previously in Section 8.3.1.1, NUREG 0133(3.l 3.l) permits use of long-term annual average dispersion calculations (which with the release modes of Table 2.3-1 results in the following equations) to show compliance.
with ODCM CONTROLS 3.11.2.3 and 3.11.2.4. For a particular organ, Equation [2.3-19] becomes:
8.3.2.1.2          Radioiodines and Particulates Dose Equation 3.17E-8IR.i [0.5W-Q.                        +    WcVQi  +WVvQi          +WtQi          +WcbQi          +
p                cv                          tvcvvt        b      cb WdvQi            +W          QW i ]                                                [2.3-20]    >
dv                wv                                                          "F
                          < 0.3 mrem (per 31 days), or
                          < 7.5 mrem (per quarter), or
                          < 15.0 mrem (per calendar year) where:
0.5 Wpv            = Dispersion parameter for releases from PV-1/2. The value of 0.5 represents the portion of dose assigned to each Unit due to this being a shared Release Point WcV            = Dispersion parameter for releases from CV-1 and CV-2.
                                                = Dispersion parameter for releases from VV-1 and VV-2.
WIVv zAs5 wtv            =    Dispersion parameter for releases from TV-2.
Wcb            = Dispersion parameter for releases from CB-2.
Wdv            = Dispersion parameter for releases from DV-2.
Wwv            = Dispersion parameter for releases from WV-2.
Q.1            = Release of radionuclide "i" from PV-1/2 (uCi).
P.V
 
Pwocedute Number:
Beaver Valley Power Station                                              -1/2-ODC-2.02
'ride: .Unit:                                                                          Level Of Use:
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1            55 of 12R Qi      =    Release of radionuclide "i" from CV-1 and CV-2 (uCi).
cv Q.1      =    Release of radionuclide "i" from VV-1 and VV-2 (uCi).
Q.1      =    Release of radionuclide "i" from TV-2 (uCi).
tv Q.      =    Release of radionuclide "i" from CB-2 (uCi).
cb Q.      =    Release of radionuclide "i" from DV-2 (uCi).
dv Qi      =    Release of radionuclide "i" from WV-2 (uCi).
1 WV TV-2, CB-2, DV-2 and WV-2 are not normally radioactive Release Points.
These are included only for use if a radioactive release is identified in the future.
In determining the dose at a particular location, dispersion parameter W is a function of the pathway. For the food and ground plane pathway, W is in terms of D/Q. If the inhalation pathway is considered, W is in terms of X/Q.
Incorporation of the various pathways into Equation [2.3-20] results in the following equation for a particular organ:
8.3.2.1.2.1        Radioiodines aind Particulates Dose Determination 3.17E-8Z((R.          +R.      +R.    +R.    ][0.5W      Q.    +W        Q.    +
i    ITG      ITM      1V    IB            PV  iPV        CV    ICV W      Q.    +W      Q.  +W      Q.  +W Q.1 +W Q. I VV  1VV      tv Itv    cb Icb          dv dv            WV 1 WV
                                  + Rit [0.5 (X/Q) pv Q.i P    + (XQ) cv Q.iC + (X/Q) vv Q.i V +
1 (XtQ)      Qi    + (XIQ)  Q      + (XIQ)d Q.            +          w(XQ) tv              cb                    dv Q. ]                                                              [2.3-211 iWV
                      < 0.3 mrem (per 31 days), or
                      < 7.5 mrem (per quarter), or
                      < 15.0 mrem (per year)
 
Beaver Valley Power Station ODC-2.02
                                                                      . J, I Procedure Numbea
_/2 _O      Use:
 
==Title:==
Unit:            vel Of URefrn 1/21          In-Field Reference ODCM: GASEOUS EFFLUENTS J
Rcvisiow 1
Page Number 56 of 12 lv-where:
R.      = Dose factor for an organ "T"for radionuclide "i" for the ground plane exposure pathway (mrem/yr per uCi/sec per m72).
R.      = Dose factor for an organ "Xr" for radionuclide "i" for either the cow milk or goat milk pathway (mrem/yr per uCi/sec per rn 2).
Ri      = Dose factor for an organ "r" for radionuclide "i" for the vegetable pathway (mrem/yr per uCi/sec per Ri      = Dose factor for an organ "T"for radionuclide "i" for the meat pathway (mrem/yr per uCi/sec per rn 2).
R.      = Dose factor for an organ "T" for radionuclide "i" for the IT                  '
inhalation pathway (mrem/yr per uCi/m 3 ).
It should be noted that Wpv, WCV2 Ww, Wtv, Wcp, Wdv, and W,,,v in Equation
[2.3-21] are in terms of D/Q(m72 ).                                                          r Values of the dose factor, Rji, were calculated using the methodology of NUREG-0133.13 .'-3-1) The following equations were used for all nuclides except tritium:
8.3.2.1.2.2        Dose Factors For Inhalation Pathway R;        K'(BR)a(DFAiT)a
                          = mrem/yr per uCi/m3                                                        [2.3-22]
where:
K'            A constant of unit conversion (1E6 pCi/uCi).
(BR)a          The breathing rate of the receptor of age group "a" (m3 1yr).
(DFAij)a      Each organ inhalation dose factor for the receptor of age group "a" for the "i" th radionuclide (mrem/pCi). Inhalation dose factors (DFAit) by organ for the various age groups are given in Table E-7 through E-10 of Regulatory Guide 1.109, Rev. 1(3.1.3.5) or Tables 5 through 8 of NUREG-012(3.1.3.6)
 
              .        -      .      ...            ..      .      .Procoduft        Number:-
Beaver Valley Power Station                                  -                  /2ODC.      2 Ttcunit                                                                      Level Of Use.
e1/2          In-Feld Reference ODCM: GASEOUS EFFLUENTS                                                      - Revision:    Page Number.
The breathing rates (BR)a used for the various age groups are tabulated below, as given in Table E-5 of the Regulatory Guide 1.109.(3 Age Group(a)        Breathing Rate (m3 /vr)
Infant                  1400 Child                  3700 Teen                  8000 Adult                  8000
:.,-      ..1..
8.3.2.1.2.3            Dose Factors For Ground Plane Pathway R.      = K'K' (SF)DFGiz[(l '-      )/X;]
2                                                                  [2.3-23]
                                -= i  -mrem/yr per uCi/sec where:                    .      .
K'          =  A constant of unit conversion (1E6 pCi/uCi).
K'          =  A constant of unit conversion (8760 hr/year).
Xi          =  The decay constant for the "i" th radionuclide (sec'1).
t            =  The exposure time (4.73E8 sec or 15 years).
DFGj,        =  The groundplane dose conversion factor for organ "T"for the "i" th radionuclide (mrem/hr per pCi/m2 ). A tabulation of DFGL? values is presented in Table E-6 of Regulatory Guide 1.109.(3.-135)
SF          =  The shielding factor (dimensionless). A shielding factor of 0.7 as suggested in Table E-15 of Regulatory Guide 1.109 is rusedP(3135 8.3.2.1.2 .4            Dose Factors For Cow Milk or Goat Milk Pathway RM    =K'    F    ap_(r)(DFL)
F                    +(i mXrJW1atayP                    Ys
                                      = m2 -mrem/yr per uCi/sec                                          [2.3-24]
where:
 
Beaver Valley Power Station                            I__        1/2-ODC-2.02 2 Td.uitl:                                                                      Untvel Of use:
1/2        In-Field Reference .
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                  .                                                    1              .58 of 129 K'            A constant of unit conversion (IE6 pCiluCi).
QF        = The animal's consumption rate, wet weight (kg/day).
Uap        = The receptor's milk consumption rate, for age "a" (liters/yr).
Yp        = The agricultural productivity by unit area of pasture feed grass (kg/m2).
Ys        =  The agricultural productivity by unit area of stored feed (kglm2).
Fm        =  The stable element transfer coefficients (days/liter).
r          =  Fraction of deposited activity retained on animals feed grass.
(DFLir)a  =  The maximum organ ingestion dose factor for the "i" th radionuclide for the receptor in age group "a" (mrem/pCi).
Ingestion dose factors (DFL jr)a for the various age groups are given in Table E-1 1 through E-14 of Regulatory Guide 1.1091' "l5) or Tables 1 through 4 of NUREG-0172.( 3 ' 3 6
                                =  The decay constant for the "i" th radionuclide (sec-i).
Xw=          The decay constant for removal of activity on leaf and plant surfaces by weathering 5.73E-7 sec 1 (corresponding to a 14 day half-life).
tf        = The transport time from pasture, to animal, to milk, to receptor (sec).
th        =  The transport time from pasture, to harvest, to animal, to milk, to receptor (sec).
fp=          Fraction of the year that the animal is on pasture (dimensionless).
f        =  Fraction of the animal feed that is pasture grass while the animal is on pasture (dimensionless).
Tabulated below are the parameter values used for cow's milk and their reference to Regulatory Guide 1.o0.1.3.5) i
 
Si                        P-ocedure Numbec              -
      . B eaver Vall ey Power                1 tat owron
                                          ~ LL~lon1/2'.ODC-2.02      -12OC.0 Titk:        ;                                                          Unit          Level Of Use:
1/2          In-Field Reference ODCM: GASEOUS EFFLUENTS                                                  Revision:    Page Number Parameter                          Value                  RG. 1.109 Table r (dimensionless)                1.0 for radioiodine          E-15 0.2 for particulates        E-15 Fm (days/liter)                  each stable element          E-1 (cow milk)
E-2 (goat milk)
Uap (literslyr) - infaint        330                          E-5 chil d        330                          E-5 teer          400                          E-5 adult          310                          E-5 (DLFi,)a (mrem/pC i)      V;. each radionuclide            E-11 to E-14 Yp (kg/rm)                      0.7                          E-15
                        /2)
Ys (kglm)                        2.0                          E-15 tf(seconds)                      1.73E5 (2 days)              E-15 th (seconds)                    7.78E6 (90 days)              E-15 QF (kg/day)                      50                            E-3 fP                              0.5 fs                              1.0 For goat's milk, all values remain the same except for QF, which is 6 kg/day.
8.3.2.1.2.5        Dose Factors For Meat Pathway QFU Xitf RiT    = K-      +Ff        (r)(DFLiT )
B          1 -W
                            =  M2  -mrem/yr per uCi/sec                                              [2.3-25]
where:
Ff    = The stable element transfer coefficients (days/kg).
Uap    = The receptor's meat consumption rate for age "a" (kglyr).
 
                                                                      - BevedaleNuPdbc.,
IBeaver        Valley Power Station                                          110C.20 Unit:        Level Of Use:
1/2        In-Field Reference Revision:    Page Number. '
ODCM: GASEOUS EFFLUENTS
                                                                          . I . I -f            129R tf    =  The average time from slaughter of meat animal to consumption (sec).
th    = The transport time from crop field to receptor (sec).
All parameter values are the same as the milk pathway parameter values except Ff which is obtained from Table E-1. Parameter tf is obtained from Table E-15, and U.,is obtained from Table E-5. These values, as obtained from Regulatory Guide 1.109,(3.1 35) are as follows:
Parameter                    Value                    RG-1.109 Table Ff (days/kg)                  each stable element          E-1 tf (seconds)                  1.73E6 (20 days)              E-15 Uap (kglyr) - infant            0                          E-5 Child          41                          E-5 Teen          65                          E-5 Adult        110                          E-5 Man is considered to consume 2 types of vegetation (fresh and stored) that differ only in the time period between harvest and consumption; therefore:
8.3.2.1.2.6          Dose Factors For Vegetation Pathway R. v        1      j(DFL.          fLe L)[U    kiL+ USf e          Pithl
                              =    -mrem/yr per uCi/sec                                            [2.3-26]
where:
K'    =  A constant of unit conversion (1E6 pCi/uCi).
U La = The consumption rate of fresh leafy vegetation by the receptor in age group "a" (kg/yr).
us= The consumption rate of stored vegetation by the receptor in age group "a" (kglyr).
fL    = The fraction of the annual intake of fresh leafy vegetation grown locally.                                                                  '1 fg    =  The fraction of the annual intake of stored vegetation grown locally.
 
        -Beaver Valley Power Station                                -ceueNUIflbC-Tide:                                                                        Unit:        Lvel Of Use:
                                                                            . .. .1/2        In-Field Reference ODCM: GASEOUS EFFLUENTS                                                      Revision    PageNumber
_1          61 of 128 tL    =  The average time between harvest of leafy vegetation and its consumption (seconds).
th    =  The average time between harvest of stored vegetation and its consumption (seconds).
Y      =  The vegetation area density (kgf/m 2 ).
all other factors are defined previously.
Tabulated below are the appropriate parameter values and their reference to Regulatory Guide 1.109.(3.1l35) 7.'. .  : . : .:    . .
Parameter                          Value                      RG-1.109 Table r (dimensionless)                  1.0 for radioiodines          E-15 0.2 for particulates          E-15 (DFLjR)a (mrern/pCi)              each stable element          E-11 to E-14 Uab (kg/yr)-infant                0                            E-5 Child            26                            E-5 teen              42                            E-5 adult            64                            E-5 US (kg/yr) - infant              0                              E-5 child            520                            E-5 teen              630                            E-5 adult            520                            E-5 fL (dimensionless)                1.0                          E-15 Fg (dimensionless)                0.76                          E-15 tL (seconds)                      8.6E4 (1 day)                  E-15 th (seconds)                    5.18E6 (60 days)              E-15 Yv (kg/m )                        2.0                          E-15 As discussed in Section 8.2.2 for tritium, the parameter W for the food pathway is based upon XIQ. The ground plane pathway is not appropriate for tritium. Therefore, the left-hand portion of Equation [2.3-20] may be expressed for purposes of implementation of 40 CFR 190, discussed in 1/2-ODC-2.04, as follows:
 
                            ~eav~
Power vaiey  SttionI.                            l NBear l12-ODC-2.02            irmwCNumb
 
==Title:==
Unit          L:velfUse*.
1/2          IIn-FField Reference ODCM: GASEOUS EFFLUENTS                                                  Revisin:0 , Page Nunbw.-..
1IsIoi          6: onf 128 8.3.2.1.2.7        Tritium Dose Equation 3 .17 E  8 (RT    + RT      + RT      + RT)      [0.5 (XIQ)  QTPV + (XIQ)CV QT              +
T'rM T~      Tr, Trv                v    TPVcv                  T (X/Q)vvQT        +(X/Q) tvQT        +(XQ) cbQ            ( Q)dvQ T          (Q)wv9              ]I' vv            A. tv            .  -cb                  dv                      WV
[23-27]
where:        ;;
RTXM = Dose factor for organ "X"for tritium for the milk pathway (mrem/yr per uCi/m 3 ).
RTtv = Dose factor for organ "T"for tritium for the vegetable pathway (mremlyr per uCi/m3 ).
RTTB    =  Dose factor for organ "T"for tritium for the beef pathway (mrem/yr per uCi/m 3 ).
RT&#xb6;r    = Dose factor for organ "T" for tritium for the inhalation pathway (mrem/yr per uCi/m 3 ).
                                                                                                                'I Equation [2.3-271 is used to show compliance with 40 CFR 190, as discussed in 1/2-ODC-2.04.
The concentration of tritium in milk is based on the airborne concentration rather than the deposition. Therefore, the RTprM is based on [XiA):
8.3.2.1.2.8        Tritium Dose Factors For Milk Pathway RTTM = KK' FmQFUap(DLFii)a[0.7 5 (0.5/H)]
                  - mrem/yr per uCi/m 3                                                            [2.3-28]
where:
K"      = A constant of unit conversion (1000 gm/kg).
H        = Absolute humidity of the atmosphere (8 gm/m3 ).
0.75    = The fraction of total feed that is water.
                                                                                                                  .I 0.5      -  The ratio of the specific activity of the feed grass water to the atmospheric water.
 
W SttiProcedure                  Nunlber Beaver Valley Power Station                                                1nbU
                                                                                    ~1/2-ODC-2.02  .
OTit                                                                    Unit          Level Of Use:
1/2          In-Field Reference ODCM: GASEOUS EFFLUENTS                                                  Revision:      Page Number and other parameters and values are the same as for RirM.
The concentration of tritium in vegetation is based on the airborne concentration rather than the deposition. Therefore, the Rtr, is based on [XIQ]:
8.3.2.1.2.9          Tritium Dose Factors For Vegetation Pathway R        K      UL +Uf ](D i [0.75(0.51I)]
                      =
                          '+IU  a f L UfLa 'gJ( 1r'-)a mremlyr per uCi/h 3                                                          [2.3-29]
where all terms have been defined above.-
The concentration of tritium in meat is based on its airborne concentration rather than the deposition. Therefore, the RT&#xb6;B is based onIX/PM:
8.3.2.1.2.10        Tritium Dose Factors For Beef Pathway RT    =KXKTFfQ U          (DFLi)  [0.75(0.5/1)]
                    = mrem/yr per uCi/m3                                                            [2.3-30]
where all terms have been defined above.
To show compliance with ODCM CONTROLS 3.11.2.3 and 3.11.2.4, Equation [2.3-21] is evaluated at the controlling pathway location. For Release Modes 1 through 4, the controlling location is a residence 0.89 miles in the NW sector. Inserting appropriate X/Q values from ATTACHMENT F Tables 2.2-4 to 2.2-10 and D/Q values from A1TACHMENT L Tables 2.3-28 to 2.3-34, Equation 12.3-21] becomes:
8.3.2.1.3        Radioiodines and Particulates Dose Determination 3.17E- 8 i ((RiT. +R.          ][(0.5)4.22E-10Qi.      +l. 5 6 E-8Qcv +1.56E-8 Q.    + 1.55E-81    Q    +1.55E-8Qi 1    + 1.56E-8Qi1        +1.56E-8 v              cb                  dv Q.    ]+R.      [(0.5)7.30E-9Qi      +2.00E-5Qj          +2.71E-5Qi
* WV      l?[                                                              Wiy'v'I
                        +  2.22E-5Qi        +2.22E-5Qi      +2.OOE-5Qi.        +2.OOE-5Qiw
                                          !v              cb                dv                      V
 
e    ALey P            S                        : ftoceclue.2.e                    L I l                                                            Unit        Level Of Use:
                                                                  -    1/2          In-Field Reference  .
ODCM: GASEOUS EFFLUENTS                                              Revision    PageNumbc          .  '
I            -6f4 of 128f
                  < 0.3 mrem (per 31 days), or                                                [2.3-31]
                  < 7.5 mrem (per quarter), or
                  <15.0 mrem (per year)
For tritium, for purposes of implementation of 40 CFR 190, as discussed in 1/2-ODC-2.04, Equation [2.3-28] reduces to:
3.17E-8[RTv + RTrI ][(0.5)7.30E-9 Qi              + 2.00E-5Q.          + 2.71E-5Qi    + 2.22E-5Qi      +2.22E-5Qi 1          +2.OOE-5Qi1        +
Vtvcb                                            dv 2.OOE-5Q.      -                                              [2.3-32]
8.3.2.1.4  Determination of Controlline Location The determination of a controlling locating for implementation of ODCM CONTROLS 3.11.2.3 and 3.11.2.4 for radioiodines and particulates is a function of:
* Radionuclide mix and their isotopic release
                  . Release Mode
* Meteorology
* Exposure pathway
* Receptor's age The incorporation of these parameters into Equation [2.3-19] results in the -
respective equations for each Release Mode at the controlling location.
In determination of the controlling location for each Release Mode, the radionuclide mix of radioiodines and particulates was based upon the source terms calculated using the GALE code. This mix was presented in ATTACHMENT D Tables 2.2-2a and 2.2-2b as a function of Release Mode and Release Point. For the ground plane exposure pathway, all radionculides (excluding H-3 and C-14) were considered in determination of the controlling location. For the inhalation and food pathways H-3 and C-14 were also considered in determination of the controlling location.
In determination of the controlling location for each Release Mode, all of the exposure pathways, as presented inATTACHMENT E Table 2.2-3, were evaluated. These include cow milk, goat milk, beef and vegetable ingestion and inhalation and ground plane exposure. An infant was assumed to be present at all milk pathway locations. A child was assumed to be present at all vegetable garden and beef animal locations. The ground plane and inhalation exposure pathways were considered to be present at all locations.
 
Procedure Number.
Beaver Valley Power Station                                          1i21ODC-2.O2 ride.Unit:                                                                                Level Of Use:
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1          ~65(tof 128 For determination of the controlling location, the highest D/Q and X/Q values for each Release Point and Release Mode for the vegetable garden, cow milk, and goat milk pathways were selected. The organ dose was calculated at each of these locations using the radionuclide mix and Release Points of ATTACHMENT D Tables 2.2-2a and 2.2-2b Based upon these calculations, it was determined that the controlling location for Release Modes 1 through 4 is the residence (vegetable garden)/child pathway.
For Release Modes 1 through 4, the controlling Release Point and mix is VV-1 and VV-2.
E '- ij  . 1 ATTACHMENT J Tables 2.3-2 through 2.3-20 present Ri values for the total II-~
          -  V body, GI-LLI, bone, liver, kidney, thyroid, and lung organs for the ground plane, inhalation, cow milk, goat milk, vegetable, and meat ingestion pathways for the infant, child, teen, and adult age groups as appropriate to the pathways.
These values were calculated using the methodology described in NUREG-0133(3-1l3.1) using a grazing period of 6 months.
In determination of the controlling location for Release Modes 1-4, ATTACHMENT F Tables 2.2-4 through 2.2-10 are utilized for X/Q's, and ATTACHMENT L Tables 2.3-28 through 2.3-34 are utilized for long term D/Q values. A description of the derivation of the various X/Q and D/Q values is presented in 1/2-ODC-3.01.
Long-term D/Q values for PV-1/2, CV-1, CV-2, VV-1, VV-2, TV-2, CB-2, DV-2 AND WV-2 are provided for the midpoints of the following distances:
0.0-0.5 mi., 0.5-1.0 mi., 1.0-1.5 mi., 1.5-2.0 mi., 2.0-2.5 mi.,
2.5-3.0 mi., 3.0-3.5 mi., 3.54.0 mni., 4.0-4.5 mi., 4.5-5.0 mi.
The values appear in ATTACHMENT K Tables 2.3-21 through 2.3-27. These values may be utilized if an additional special location arises different from those presented in the special locations of ATTACHMENT E Table 2.2-3.
The following relationship must hold for BV-I or BV-2 to show compliance with ODCM CONTROL 3.11.2.3.
For The Calendar Quarter:
Dr < 7.5 mrem to any organ                                                  [2.3-33]
Fh l        Ye For The Calendar Year:
Di < 15 mrem to any organ                                                    [2.3-34]
where:
 
I Procedue Number; Beaver Valley Power Station -/2-ODC-2.02
  'ride:                                                                      Unit:        Lvel Of Use:
112        In-Field Reference s ODCM: GASEOUS EFFLUENTS                                                    Revision:    Page Numbet.
1              66 of 128 D= The dose to any organ from radioiodines and particulates (mrem).
The quarterly limits given above represent one-half the annual design objective of Section ILC of Appendix I of 10 CFR 50. If any of the limits of Equations
[2.3-33] and [2.3-34] are exceeded, a Special Report pursuant to both Section MV.A of Appendix I of 10 CFR 50 and ODCM CONTROL 3.11.2.3.a must be filed with the NRC at the identified locations.
8.3.2.2      Proiection Of Doses (Radioiodines And Particulates)
Doses due to gaseous releases from BV-1 or BV-2 shall be projected at least once per 31 days in accordance with ODCM CONTROL 4.11.2.4 and this section. (Also see Section 8.3.1.2, Projection Of Doses for additional specifications). The appropriate portions of the Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in gaseous waste prior to their discharge in accordance with ODCM CONTROL 3.11.2.4 when the projected doses due to gaseous effluent releases from each reactor unit, when averaged over 31 days, would exceed 0.3 mrem to any organ. (Also see Section 8.3.1.2, Projection Of Doses for additional specifications). Doses resulting from the gaseous effluent release of radioiodines and particulates will be calculated for use in the 31-day dose projection using Equation
[2.3-31]. The 31-day dose projection shall be performed according to the following equations:
8.3.2.2.1        When Including Pre-Release Data, FA+B1 D              I (31)+C                                                  [2.3-35]
LTJ 8.3.2.2.2        When Not Including Pre-Release Data, D31 =[T] (31) + C                                                          [2.3-36]
where:
D31= Projected 31 day dose (mrem).
A    =  Cumulative dose for quarter (mrem).
B    =  Projected dose for this release (mrem).
T    =  Current days into quarter.
C    =  Value which may be used to anticipate plant trends (mrem).
 
Procedure Number.
Beaver Valley Power Station                                              1/2-ODC-2.02 tle:                                                                        Unit:        Level Of Use:
1/2          In-Field Reference ODCM: GASEOUS EFFLUENTS                                                      Revision:    Page Number 1              67 of 128 8.4      Gaseous Radwaste System The gaseous radwaste system has the capability to control, collect, process, store, recycle, and dispose of gaseous radioactive waste generated as a result of plant operations, including anticipated operational occurrences.
A simplified flow diagram of the gaseous radwaste system for BV-1 and BV-2 is provided as ATTACHMENT N Figure 2.4-1. A diagram showing the gaseous effluent Release Points is provided as ATTACHMENT P'Figure 2.4-2. Since the concept of a shared gaseous radwaste system is used, then gaseous waste generated can be stored, processed, and discharged from either BV-1 or BV-2.
8.4.1    BV-1 Gaseous Radwaste System Components 8.4.1.1      BR-IEV-2A12B: Degasifters There'are two Degasifiers. They are designed to continuously process reactor coolant letdown for reducing entrained noble gases in the liquid.
8.4.1.2    GW-iE-1A/1B: Waste Gas Chillers There are two Chillers. Non-condensable gases from the degasifiers are directed by system pressure to the Waste Gas Chillers.
8.4.1.3    GW-lTK-3A thru 3D: Gaseous Waste Charcoal Delay Beds There are four Charcoal Beds. The dry effluent from the Chillers is directed to the Waste Gas Charcoal Delay Beds for holdup of xenon and krypton and adsorption of radioiodines. When four beds -areoperated in series, they provide a holdup of xenon isotopes for about 30 days.
8.4.1.4      GW-1FL-SA/5B: Overhead Gas Compressor Prefilters There are two Prefilters. The gaseous effluent (primarily hydrogen) is directed from the Gaseous Waste Charcoal Delay Beds to one of the Overhead Gas Compressor Prefilters. The filters remove carbon solids from the gas stream.
8.4.1.5      GW-1C-1A/1B: Gas Compressors There are two Compressors. The waste gas enters one of the compressors after passing through 'the Prefilters.
8.4.1.6      GW-ITK-2: Gaseous Waste Surge Tank There is one Surge Tank. It has a capacity of 52 cuft. After compression to about 65 psig, the waste gas is sent to the Surge Tank. This can be done automatically or manually.
 
Beaver Valley Power Station                                NIumber P
Ttle:                          :Unit:                                                    Level Of Use:
                                                                                .    .1/2 IIn-Field Reference ODCM: GASEOUS EFFLUENTS                                                    Revision      PageNumbe:
                            .                                                    1                69 of 1198 8.4.1.7    GW-lTK-IA thru 1C: Waste Gas Decay Tanks There are three Decay Tanks. Each has a capacity of 132 cuft. The contents of the Surge Tank is transferred to the Decay Tanks for storage and decay. After 30 days of storage, all xenon and iodine should have decayed, and the resulting predominant nuclide should be krypton 85.
8.4.1.8    RM-IGW-108 And RM-IGW-109: Gaseous Effluent Radiation Monitors There are redundant Radiation Monitors on the combined PV-1/2 Gaseous Waste/Process Vent release path. These Radiation Monitors continuously analyze, gaseous waste as it is being discharged. Gaseous Monitor RM-lGW-108B is an off-line gamma scintillator, while RM-IGW-109 Channel 5 is an off-line beta scintillator. The upper activity alarm on the gaseous Channels of these Radiation Monitors have setpoints that would indicate we are approaching the Total Body Dose Rate or Skin Dose Rate limits for radioactive gas leaving the site. If an upper activity alarm on RM-lGW-108B is received, it automatically terminates the discharge by closing an isolation valve downstream of the Decay Tanks.
8.4.2    BV-2 Gaseous Radwaste System Components 8.4.2.1    2BRS-EV21AI21B: Degasifiers There are four Degasifiers (two at Unit 1 and two at Unit 2). They are designed to continuously process reactor coolant letdown for reducing entrained noble gases in the liquid.
8.4.2.2    2GWS-E21AI21B: Waste Gas Chillers There are four Chillers (two at Unit 1 and two at Unit 2). Non-condensable gases from the degasifiers are directed by system pressure to the Waste Gas Chillers.
8.4.2.3    2GWS-TK22A thru 22D: Waste Gas Charcoal Delay Beds There are four Charcoal Beds (four at Unit 1 and four at Unit 2). The dry effluent from the Chillers is directed to the Waste Gas Charcoal Delay Beds for holdup of xenon and krypton and adsorption of radioiodines. When four beds are operated in series, they provide a holdup of xenon isotopes for about 30 days.
8.4.2.4    2GWS-FLT24A/24B: Overhead Gas Compressor Prefilters There are two Prefilters. The gaseous effluent (primarily hydrogen) is directed from the Waste Gas Charcoal Delay Beds to one of the Overhead Gas Compressor Prefilters. The filters remove carbon solids from the gas stream.                      r
 
Beaver Valley Power Station                            ; Procedure Numb=r~
1/2LODC-Z02
 
==Title:==
Unit:          Leva Of Use:
1/2          In-Field Reference ODCM: GASEOUS EFFLUENTS                                                                PageNumber.
8.4.2.5  2GWS-C21AJ21B: Gas Compressors There are two Compressors. 'The waste gas enters one of the compressors after passing through the Prefilters.
8.4.2.6  2GWS-TK21: Gaseous Waste Suree Tank There is one Surge Tank. It has a capacity of 52 cuft. After compression to about 65 psig, the waste gas is sent to the Surge Tank. This can be done automatically or manually.
8.4.2.7  2GWS-TK25A thru 25G: Gaseous Waste Storage Tanks There are seven Storage Tanks. Each has a capacity of 132 cuft. The contents of the Surge Tank is transferred to the Storage Tanks for storage and decay. After 30 days of storage, all xenon and iodine should have decayed, and the resulting predominant nuclide should be krypton 85.
8.4.2.8  RM-1GW-108 And RM-IGW-109: Gaseous Effluent Radiation Monitors Previously described in Section 8.4.1.
                                                          - END-5
 
Baver-Va'lley Power Station -i                                  'I- PFC.bf        Numb.SC2 1ILODC-2.02          z Un.it:            Lzvel Of Use:
:C-
      .,    ;G          U 1/2            In-Field Reference 4.
Revision:        Page Numbec.
ODCM: GASEOUS EFFPLUENTS                                                                                                              I ,,
1-          . 70Onfl2R ATIACHMENT A Page 1-of 2        -
                                                . GASEOUS SOURCE TERM TABLE 2.1-la BV-I RADIONUCLIDE MIX FOR GASEOUS EFFLUENTS (Ci/yr)
RX        AUXILIARY CONTAINMENT/          BUILDING                GSOS
                                                                                .  . I; A-    Ei  ,VE    C SLCRS VENT          VENT              GASEOUS WASTEIPROCESS VENT Long Term, And
                                                    ; AUXILIARY            MAIN      CONTAINMENT                  GASEOUS
                  -~      - CONTAINMENT              BUILDING        CONDENSERI        - VACUUM                  WASTE NUCLIDE(2)          BUILDING"      VENTILATION        AIR EJECTOR        - PUMPS(3)              SYSTEM Short Term      Long Term        Long Term          Long Term              Short Term s,
Kr-83m                2.2E-02          4.2E-01          2.7E-01            5.2E-03                0.0 Kr-85m                1.5E-01          1.9E+00          1.2E+00            5.5E-02                7.3E-02 Kr-85                  6.1E+01          2.5E+00          1.6E1+00            1.OE+01                2.3E+02 Kr-87                5.4E-02          1.3E+00          8.2E-01            1. 1E-02              0.0 Kr-88                2.4E-01          3.8E+00          2.4E+00            7.OE-02                0.0 Kr-89                  4.7E-04          1.2E-01          7.7E-02            4.3E-05                0.0 Xe-131m                7.4E-01          1.3E-01          8.0E-02            1.8E-01                1.3E+00 Xe-133m                8.9E-01          8.9E-01          5.6E-01            3.1E-01                0.0 Xe-133                8.9E+01          3.6E+01          2.3E+01            2.7E+01                2.3E+01 Xe-135m                4.5E-03          3.2E-01          2.0E-01            6.2E-04                0.0 Xe-135                7.OE-01          4.5E+00          2.8E+00            2.7E-01                0.0 Xe-137                L0E-03          2.E-01          1.3E-01            8.8E-05                0.0 Xe-138                1.5E-02          1.IE+00          6.6E-01            1.7E-03                0.0 Ar-41                  2.5E+01          0.0              0.0                0.0                    0.0
()    Containment can be purged via VV-1 (Auxiliary Building Vent), CV-1 (Rx Containment/SLCRS Vent), or PV-1/2 (Gaseous Waste/Process Vent)
(2)    Source Term from BVPS-2 UFSAR Table 11.3.1(3.1 1.2)
(3)    Original Source Term from Calculation No. UR(B)-262 was adjusted for a factor of 14 increase in pump flowrate due to installation of high capacity pumps during lR15. This change in Source Term is documented in Condition Report CR03-04830 and Calculation No. ERS-HHM          014.(3.1.1.5) (3.1.1.8) (3.1.3. 10)
IJ
 
Beaver Valley Power Station P          1/2-ODC-2.02
                                                                                                            /2-OD C-2.02 Titde:                                                                                        Unit          Level Of Use:
1/2          In-Field Reference ODCM: GASEOUS EFFLUENTS                                                                        Revision:      Page Number:
__1                                  71 of 128 ATTACHMENT A Page 2 of 2 GASEOUS SOURCE TERM TABLE 2.1-lb BV-2 RADIONUCLIDE MIX FOR GASEOUS EFFLUENTS (Ci/yr)
SLCRS                  SLCRS              TURBINE UNFILTERED              FILTERED            BUILDING PATHWAY                PATHWAY                - VENT                    GASEOUS WASTE/PROCESS VENT
        -    Long Terni, And
.              -I. -~.
AUXILIARY            TURBINE                  MAIN          CONTAINMENT            GASEOUS CONTAINMENT                BUILDING          BUILDING            CONDENSER/            VACUUM              WASTE NUCLIDE121    BUILDING("            VENTILATION. VENTILATION                  AIR EJECTOR            Pumps")            SYSTEM Short Tern              Long Term          Long Term            Long Term            Long Term          Short Term Kr-83m          4.0E-05                  4.2E-01            3.9E-05              2.7E-01            3.7E-04            0.0 Kr-85m          1.4E-02                  1.9E+00            1.7E-04              1.2E+00            3.9E-03              1.2E-02 Kr-85          6.1E+01                  2.5E+00            2.3E-04            , 1.6E+00            7.2E-01            2.3E+02 Kr-87          5.3E-06                  1.3E+00            1.lE-04              8.2E3-01          7.8E-04            0.0 Kr-88          4. 1E-03                3.8E+00            3.5E-04              2.4E+00            5.0E-03            0.0 Kr-89          0.0                      1.2E-01            l.lE-05              7.7E-02            3.1E-06            0.0 Xe-131m        7.2E-01                  1.3E-01            1.2E-05              8.0E-02            1.3E-02            8.3E-01 Xe-133m        7.6E-01                  8.9E-01            8.1E-05              5.6E-01            2.2E-02            0.0 Xe-133          8.4E+01                  3.6E+01            3.4E-03              2.3E+01            1.9E-00            8.2E+00 Xe-135m        0.0                      3.2E-01            2.9E-05              2.OE-01            4.4E-05            0.0:
Xe-135          2.4E-01                  4.5E+00            4.2E-04              2.8E+00            1.9E-02            0.0 Xe-137          0.0                      2.1E-01            2.11E-05              1.3E-01            6.3E-06            0.0 Xe-138          0.0                      1.lE+00            9.7E-05              6.6E-01            1.2E-04            0.0 Ar-41          2.5E+01                  0.0                0.0                . 0.0                0.0                0.0
() Containment can be purged via VV-2 (SLCRS Unfiltered Pathway), CV-2 (SLCRS Filtered Pathway), or PV-1/2 (Gaseous Waste/Process Vent)
(2) Source Term from BVPS-2 UFSAR Table 11.3.2(3.1.2.3) 12 (3) Source Term from Calculation No. UR(B)-262(3 . 5)
 
IL.
                            -BeaverValleyPower Station
 
==Title:==
ODCM: GASEOUS EFFLUENTS ATTACHMENT B
: Page 1 of 2 GASEOUS EFFLUENT MONITOR DETECTION EFFICIENCIES TABLE 2.1-2a BV-1 MONITOR DEFECTOR EFFICIENCIES (cpm/uCi/cc) f  GASEOUS WASTE/              I Rx CONTAINMENT/
NUCLIDE      AUXILIARY BUILDING VENT                  PROCESS VENT          -  ------ sqr
                                                                                          !=o r'i
                                                                                              \  vumhrr PRIMARY      ALTERNATE          PRIMARY      ALTERNATE        PRIMARY          ALTERNATE MONITOR(')      MONlTORl)        MONITOR(')      MONITOR (2)  MONITOR(')          MONITOR(2)
RM-VS-1OlB      RM-VS-109      RM-GW-108B      RM-GW-109    RM-VS-107B          RM-.VS-110 Channel 5                      Channel 5                        Channel 5 Kr-83m Kr-85m          9.80 E7        2.39 E7        9.00 E7        2.43 E7        5.16E7            2.57 E7 Kr-85            3.88 E5        2.47 E7        3.56 E5        2.51 E7        5.04 E7            2.67 E7 Kr-87          -7.38 E7        2.95 E7        6.78 E7        3.00 E7      9.60 E7            3.19E7 Kr-88            1.14E8          2.11 E7        1.05 E8        2.14E7          5.16E7            2.28 E7 Kr-89            1.39 E8        2.93 E7          1.28 E8        2.98 E7        9.59 E7          3. 16 E7 Kr-90            1.34 E8        3.05 E7          1.23 E8        3.10E7        9.87-E7          3.29 E7  \-el Xe-131rm        2.25 E6        i.56 E7        2.07 E6        1.59 E7        2.94 E7          -1.68 E7 Xe-133m          1.26E7          1.94 E7          1.16E7        1.97 E7      4.17 E7            2.09 E7 Xe-133          1.01E7          1.24 E7        9.24 E6        1.26 E7        2.28 E7            1.33 E7 Xe-135m          7.15 E7        5.70 E6        6.58 E7        5.80 E6        1.51 E7          6.15E6 Xe-135          1.12E8          2.91 E7          1.03 E8        2.96 E7        6.42 E7          3.14E7 Xe-137          3.16 E7        2.96 E7        2.91 E7        3.01 E7        1.05 E8          3. 19 E7 Xe-138          1.15 E8        2.66 E7          1.06 E8        2.70 E7        7.35 E7          2.87 E7 Ar-41            7.17E7          3.00 E7        6.59 E7        3.05 E7        7.19E7            3.23 E7
    ') The listed detector efficiencies for the respective primary monitors (Victoreen) are corrected for the reduced pressures observed and documented during operation.
(2) The alternate monitors (Eberline SPING Channel 5) efficiencies are corrected for detector unique installation factors. (Pressure corrections are not required for the SPING Monitors.) See Calculation Package ERS-SFL-85-03 1 for additional information.( 3 .1.1.4)
 
Procedure Numbec.
Beaver Valley Power Station                        ODC-2.02 Title  .:                                                                    Unit:        Levd Of Use:
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1              '73 of 128 ATITACHMENT B
                                              . Page 2 of 2 GASEOUS EFFLUENT MONITOR DETECTION EFFICIENCIES TABLE 2.1-2b BV-2 MONITOR DETECTOR EFFICIENCIES (cpm/uCi/cc)              l SLCRS          SLCRS          WASTE GAS                                CONDENSATE UNFILTERED      FILTERED          STORAGE              DECON              POLISHING NUCLIDE(')        PATHWAY        PATHWAY          VAULT VENT        BU1LDING VENT BUILDING VENT 2HVS-RQ1OlB      2HVS-RQ109B      2RMQ-RQ303B        2RMQ-RQ301B          2HVL-RQ112B Kr-83m                                                                4,.
Kr-85m                  3.20E7        5.83E7              3.20E7            3.20E7                3.20E7 Kr-85                    3.60E7        7.19E7-            3.60E7            3.60E7                3.60E7 Kr-87                  .3.73E7.        8.85E7              3.73E7            3.73E7                3.73E7 Kr-88                    3.05E7        6.80E7              3.05E7            3.05E7                3.05E7 Kr-89                    3.72E7        8.73E7              3.72E7            3.72E7                3.72E7
.Kr-90                    3.86E7        8.80E7              3.86E7            3.86E7                3.86E7 Xe-131m                  2.44E7        4.61E4              2.44E7;            2.44E7                2.44E7 Xe-133m                  2.86E7        6.06E4              2.86E7.-          2.86E7                2.86E7 Xe-133                  1.80E7        2.94E7              1.80E7              1.80E7                1.80E7 Xe-135m                  7.22E6        1.55E4              7.22E6            7.22E6                7.22E6 Xe-135                  3.86E7        7.48E7              3.86E7            3.86E7                3.86E7 Xe-137                  3.78E7        9.07E7              3.78E7            3.78E7                3.78E7 Xe-138                  3.52E7        7.74E7              3.52E7            3.52E7                3.52E7 Ar-41                    3.79E7        7.90E7              3.79Ei            3.79E7                3.79E7 Efficiencies from Calculation Package ERS-SFL-86-026.(3 L2 l)
 
Beaver Valley Power Station:                                              112-DC2.02 U    it  lI    Lvel Of Use:
flue    ...
O DC . .M    GS    E O. E r FE  N 1/2        1 - In-Field Reference  )
Revision        Page Number  : .
ODCM[- GASEOUS EFFLUENTS                                                                      I      I AAf II VQ      -JD ATTACHMENT C
                                                    . Page 1; of 1 MODES      OF GASEOUS RELEASE Table 2.2-1 MODES OF GASEOUS RELEASE FROM BEAVER VALLEY SITE VENTS FOR IIMPLEMENTATION OF 10 CFR 20 AND 10 CFR 50 RELEASE              RELEASE          RELEASE                  RELEASE RELEASE POINT                  MODE I                MODE 2            MODE 3                    MODE 4 RP 1; VV-1, Auxiliary              Aux. Bldg.            Containment      Same As Mode 1            Same As Mode 1 Building Vent(l)                  Ventilation          Purge(3 )
RP 2; CV-1, Rx                    Leakage Collection Same As Mode 1      Same As Mode 1            Same As Mode 1 Containment/SLCRS Vent(')          Exhaust                                and Containment Purge( )
RP 3; PV-1/2, Gaseous              Main Cond. Air        Same As Mode 1    Same As Mode 1            Same As ModelI Waste/Process Vent(2)              Ejector, Waste Gas,                                              and Containment Containment                                                      Purge Vacuum RP 4; VV-2 SLCRS Unfiltered Pathway(l)
Contiguous Areas      Containment Purge(3)
Same As Mode 1            Same As Mode 1  )
RP 5; CV-2, SLCRS Filtered        Aux. Bldg.            Same As Mode 1    Same As Mode 1            Same As Mode 1 Pathway Vent(')                    Ventilation                            and Containment Purge(3 )
                                            .(4)                  (4)              (4)                    (4)
RP 6; CB-2, Condensate Polishing Bldg Vent(l)
(4)                  (4)                (4)                    (4)
RP 7; WV-2, Waste Gas Storage Vault Ventol)
(4)
RP 8; DV-2,                                                      (4)                (4)
Decontamination Bldg Vent(l)
(4)
RP 9; TV-2, Turbine Bldg                    (4)                  (4)                (4)
Vent(')
NOTE: For the purpose of implementing 10 CFR 50, batch discharges may use continuous meteorology since short term meteorology is used at the time of the annual report.
(1) Continuous ground level meteorology is applicable (2) Continuous elevated meteorology is applicable (3) Mode established by purge from one unit, all other release points remain same as Mode 1 (4) Not normally a radioactive release point i
 
                                                        ,    *            .Procedure    Namber.-
Beaver ValleyPower -Station                                                1/2-ODC-202 Unit:          Leve[ Of Use
                                                                                    .1/2          In-Field Reference ODCM: GASEOUS EFFLUENTS                                                        Revision:      Page Number AITACHMENT D Page 1 of 2 RADIONUCLIDE M:IX TABLE 2.2-2a BV-1 RADIONUCLIDE MIX FOR GASEOUS EFFLUENTS (Ci/yr)
RX
:-  CONTAINMENTt        AUXILIARY SLCRS VENT      BUILDING VENT                    GASEOUS WASTE/PROCESS VENT Long Term, And AUXILIARY?'              MAIN          CONTAINMENT CONTAINMENT        BUILDING' -        CONDENSER/          VACUUMM            ,    4'GASEOUS NUCLIDE13)        BUILDING(')    VENTILATION          AIR EJECTOR          PUMPS&deg;)            WASTE SYSTEM Short Term      Long Term            Long Term          Long Term              Short Term Kr-83m              2.2E-02          4.213-01              2.7E-01            5.213-03                0.0 -
Kr-85m              1.5E-01        1.913+00              1.2E+00            5.513-02                1.2E-02 Kr-85              6.1E+01-2        2.5E+00                1.6E+00            1.013+01                2.313+02 Kr-87              5.4E-02          1.3E+00                8.213-01            1.1E-02                0.0 Kr-88              2.4E-01          3.813+00              2.4E+00            7.0E-02                0.0 Kr-89              4.7E-04          1.2E-01.  -            7.7E-02            4.3E-05                0.0 Xe-131m            7.4E-01          1.3E-01                8.0E-02            1.813-01                8.313-01 Xe-133m            8.91E-01        8.913-01              5.6E1-01            3.11E-01                0.0 Xe-133              8.9E+01        3.6E+01                2.313+01            2.7E+01                8.2E+00 Xe-135m            4.5E-03          3.213-01              2.013-01            6.2E-04                0.0 Xe-135            7.013-01        4.5E+00                2.8E+00            2.7E-01                0.0..
Xe-137              1.0E-03        2.1E-01                1.3E-01            8.813-05                0.0 Xe-138              l.513-02        1.1E+00                6.613-01            1.713-03                0.0 I-131              1.2E-03        4.6E-02                2.1E-02            6.613-03                0.0 1-132                0.0            0.0                    0.0                3.5E-05                  0.0 I-133              2.0E-04        6.713-02              3.0E-02,            1.213-03                0.0
'.I-134                0.0            0.0                    0.0                6.6E-06                  0.0 135                0.0            0.0                    0.0                2.013-04                0.0 Co-58              7.5E-04        6.013-02              0.0                2.213-04                0.0 Co-60              3.4E-04        2.7E-02                0.0                  1.013-04                0.0 Mn-54              2.2E-04          1.8E-02              0.0                6.9E-05                  0.0 Fe-59              7.5E-05        6.OE-03                0.0                2.2E-05                  0.0 Sr-89              1.7E-05          1.3E-03              0.0                5.213-06                0.0 Sr-90              3.0E-06        2.0E-04                0.0                  9.2E-07                0.0
  ,Cs-134              2.2E-04          1.813-02              0.0                  6.913-05'              0.0 Cs-137              3.8E-04        3.OE-02                0.0                .1.2E-04                0.0 C-14                1.0E+00        0.0                    0.0                  0.0                    7.0E+00 Ar-4              2.5E+01        0.0                    0.0                  0.0                    0.0 Containment can be purged via VV-1 (Auxiliary Building Vent),'CV-1 (Rx Containment/SLCRS Vent), or PV-1/2 (Gaseous Waste/Process Vent)
(2)  Source Term from BVPS-2UFSAR Table        11.3-1(3 .1.I2)
(3)  See Note (3) from ATTACHMENT A Table 2.1-la (3.1.1.5) (3.1.1.8) (3.1.3.10)
 
Beaver Valley Power Station -Ni - .                          Nuln-O2 Tilde:-                                                                    Unit:        Level Of Use:
1/2        In-Field Reference Revision: -  Page Number.
ODCM: GASEOUS EFFLUENTS I              7i af 15R        '
ATTACHMENT D Page 2 of 2 RADIONUCLIDE MIX TABLE 2.2-2b BV-2 RADIONUCLIDE MIX FOR GASEOUS EFFLUENTS (Ci/yr) '
SLCRS            SLCRS UNFILTERED        FILTERED          TURBINE PATHWAY          PATHWAY        BUILDING VENT    GASEOUS WASTE/PROCESS VENT
          - -- - Long Term, And AUXILIARY          TURBINE        MAIN          CONTAINMENT GASEOUS CONTAINMENT        BUILDING          BUILDING. CONDENSER/          VACUUM            WASTE NUCLIDE(2)      BUILDING(')    VENTILATION      VENTILATION  AIR EJECTOR          PUMPS&deg;3 )        SYSTEM Short Term        Long Term        Long Term    Long Term.        Long Term      Short Term Kr-83m            4.0E-05          4.2E-01            3.9E-05    2.7E-01            3.72-04          0.0' Kr-85m            1.4E-02            1.92+00          1.7E-04      1.22+00            3.9E-03          1.2E-02 Kr-85            6.IE+01          2.5E+00            2.3E-04      1.6E+00            7.2E-01        .2.3E+02 Kr-87            5.3E-06            1.3E+00          1.1E-04    8.22-01.            7.8E-04          0.01 Kr-88            4.1E-03          3.8E+00            3.5E-04    2.4E+00            5.0E-03          '0.0 Kr-89            0.0                1:2E-01          1.1E-05    7.7E-02            3.1E-06          0.0 Xe-131m          7.2E-01            1.3E          1.2E-05      8.0E-02            1.32-02          8.32-01 Xe-133m          7.6E-01            8.9E-01          8.1E-05    5.6E-01            2.22-02          0.0 Xe-133            8.4E+01            3.6E+01          3.4E-03    2.3E+01            1.92-00          8.22+00 Xe-135m          0.0                3.2E-01          2.9E-05      2.0E-01'          4.4E-05          0.0 Xe-135            2.4E-01          4.52+00            4.2E-04      2.8E+00            1.92-02          0.0 Xe-137            0.0                2.1E-01          2. 1E-05    1.3E-01            6.3E-06          0.0 Xe-138            0.0                I.IE+00          9.7E-05      6.6E-01            1.2E-04          0.0 1-13i            2.7E-05            4.6E-03          6.5E-04      2.1E-02            4.7E-04          0.0 1-132            0.0  -            0.0              0.0          0.0                2.52-06          0.0 I-133            2.6E-06            6.7E-03          8.7E-04      3.0E-02            8.42-05          0.0 1-134            0.0                0.0              0.0:        0.0                4.7E-07          0.0 1-135            0.0                0.0              0.0          0.0                1.4E-05          0.0 Co-58            7.5E-02            6.0E-04          0.0          0.0                1.62-05          0.0 Co-60            3.4E-02            2.7E-04          0.0          0.0                7.42-06          0.0 Mn-54            2.2E-02            1.8E-04          0.0          0.0                4.9E-06          0.0 Fe-59            7.5E-03            6.0E-05          0.0          0.0                1.6E-06      -  0.0 Sr-89            1.7E-03            1.3E-05          0.0          0.0                3.7E-07          0.0 Sr-90            3.0E-04            2.OE-06          0.0          0.0                6.6E-08          0.0 Cs-134          2.2E-02            1.82-04          0.0          0.0                4.9E-06          0.0 Cs-137          3.8E-02            3.OE-04          0.0          0.0                8.4E-06          '0.0 C-14              1.0E+00          0.0              0.0          0.0                0.0              7.02+00 Ar-41            2.5E+01            0.0              0.0          0.0                0.0              0.0 Containment can be purged via VV-2 (SLCRS Unfiltered Pathway), CV-2 (SLCRS Filtered Pathway), or PV-1/2 (Gaseous Waste/Process Vent)
(2) Source Term from BVPS-2UFSAR Table 11.3-2l3 1 t3)-
(3) See Section 8.1.1.1
 
(                        (                                              C' TABLE 2.2-3 C
DISTANCES OF LIMITING MAXIMUM INDIVIDUAL RECEPTORS TO RELEASE POINTS FOR ANNUAL X/Q VALUES (meters)
VEGETABLE D      SITE  BOUNDARY*        GARDEN            MILK COW          MILK GOAT        MEAT ANIMAL            RESIDENT DOWNWIND          S.T BONDRY SECTOR          GROUND      ELEV GROUND ELEV GROUND ELEV GROUND ELEV GROUND ELEV GROUND ELEV (1)    (2) 670    579      413  2,623    2,423      ---      ... 4,651      4,418    4,152    3,919    2,527      2,295 N
535    792      632  2,740    2,461      ---      ---    6,276      6,033  2,848  2,605      2,639      2,461 NNE NE                    490    442      327    724      901  7,741    7,526  20,760    20,545    7,741  7,526        708        790 490    448      394  1,674    1,658      ---      ---    6,824      6,671    ---    ---          708    1,562 ENE 545    546      551  1,979    1,922 7,065        6,998    4,265      4,200  4,265    4,200        756    1,922      >
E 575    607      672  1,577    1,619      ---      ---    2,865      2,899  1,577    1,619      1,577    1,650 ESE 575  701      815  1,835    1,961 5,729        5,848    5,729      5,848  3,299    3,420      1,835    1,961      >
SE SSE                    655  762    '912  1,738    1,933 5,053        5,244    9,977    10,166    1,770    1,964      1,432    1,628 S                      850  887    1,054  3,138    3,372  3,347      3,539      ---      ---    2,253    2,487    2,189      2,423  ; >-
SSW                    975 1,064    1,226  2,317    2,560 3,347        3,590    5,616      5,859  2,317  '2,560    1,223      1,466 1,435 1,439    1,574  2,221    2,439      ---      ---    2,993      3,210  2,414    2,632    2,221'    2,439 SW 595  561      660  2,301    2,463  5,182      5,341      -.-      ---    2,446    2,608    2,301      2,463    0 WSW W                      685  640      681  3,556    3,635 5,118        5,195      ---      ---    4,088    4,166    3,556      3,635 WNW                    810  701      676  3,605    3,590 4,538        4,521  22,529    22,507    3,605    3,590    3,605      3,590 1,464    1,415      ---      ---  10,944    10,832  4,570    4,461      1,432      1,383          M NW                    655  567      482 1,464    1,285      ---      ---  15,450    15,262  3,959    3,774      1,143      1,253        _g NNW                    645  558      420
*Distances for ground releases are measured from the center point between the BV- 1 and BV-2 Containment Buildings. Distances for elevated release are measured from the BV-1 Cooling Tower. Elevated release is applicable to PV-1/2. Ground release is applicable to n
all other release points.
(1) TV-2 and CB-2 (2) VV-1, CV-1, VV-2, CV-2, DV-2, WV-2
 
I'0    i TABLE 2.2-4 CV- 1 AND CV-2 ANNUAL AVERAGE, GROUND LEVEL, X/Q VALUES FOR CONTINUOUS RELEASES, SPECIAL DISTANCES                                                              0 (IDENTIFIED IN ATTACHMENT E, TABLE 2.2-3), AND SELECTED CONTROL LOCATIONS 3
(1E3-7 sec/rn) 0' ,''
INDIVIDUAL RECEPTORS                                DISTANCES TO THE CONTROL LOCATION, IN MILES DOWN-    SITE  VEGE-                                                I0.5-
                                                                                      '1.5-  2.0-  2.5-  3.0-  3.5-  4.0-  4.5-'
WIND SECTOR BOUND- TABLE MILK MILK MEAT ARY GARDEN COW GOAT ANIMAL DENCE RESI-      0-0.5 1.0    1.0-1.5    2.0    2.5  3.0    3.5    4.0  4.5    5.0            ASP...
0 N        125.0    12.80  --      5.360    6.21    13.S0    233.0  39.5    18.70  11.80    7.68  5.82  4.240  3.480 2.660  2.280 tin NNE      50.2    6.92  --      2.040    6.42    7.16    148.0  26.8    10.80    6.62  4.60  3.44  2.690  2.190  1.830 1.560 NE      102.0    47.40    1.200  0.265    1.20    49.10    120.0  21.6    11.60    6.99  4.81  3.55  2.370  1.910  1.450 1.230 ENE-      85.8    12.50  --      0.124            42.20    .103.0  18.4      9.55    5.70  4.14  3.04  2.340  1.880  1.260 1.060 I--  >
E        54.5    6.16  0.807  1.910    1.91    32.60      89.5  15.7      6.08    3.65  2.49  1.83  1.300 1.040  0.859  0.726 ESE      31.1    6.92  --      3.010    6.92    6.92      59.1  10.5      5.16    3.10  1.95  1.43  1.020, 0.815 0.612  0.517  An  to SE        27.8    6.70  0.994  0.994    2.74    6.70      65.9  12.0      5.89    3.54  2.41  1.77  1.160 0.931  0.768 0.649 SSE      24.1    6.68    1.030  0.372    6.50    9.01      67.2  12.0      5.46    3.30  1.91  1.41  .0.997 0.803  0.665  0.563    "  o AV -_ 4 S        27.5    3.40  3.090  --      5.57    5.81      99.9  17.5      6.77    4.11' 2.84  2.10  1.490  1.200 0.999. 0.848 SSW      23.8    6.31    3.700  1.740    6.31    19.30    110.0  19.9      7.83    4.80 3.33    2.48  1.940 3.430 1.580 2.790 1.190 1.020 2.110 1.800 It SW        22.3    13.90  --      9.050  12.30    13.90    160.0  29.2    16.10    9.94 5.85    4.37 WSW      163.0    19.30  5.720  --      17.70    19.30    283.0  49.8    23.50  14.60 10.30    7.72  5.690  4.650 3.620 3.090 W        278.0    15.70 9.540 --          13.00    15.70    615.0 103.0    . 49.00  31.00  15.40 11.70  9.320 7.660 6.460 5.550 WNW      487.0    40.70 30.100 1.810      40.70    40.70    1290.0 203.0      92.10  59.20  40.60 31.20 25.000 20.700'14.200 12.200 NW      924.0  194.00 : --      8.660  40.50 . 200.00    1710.0 262.0      123.00 79.80  55.00 42.30 34.000 28.200 19.400 16.700 NNW      302.0    63.00 --        1.720  15.40    92.30    547.0 86.4      40.80  26.20  17.60 13.50- 10.100 8.350 6.560 5.660 i
1 J,
 
(  )                                                                  (    .)                                                              i- .
r --
TABLE 2.2-5                                                                  0 VV-1 AND VV-2 ANNUAL AVERAGE, GROUND LEVEL, X/Q VALUES FOR CONTINUOUS RELEASES, SPECIAL DISTANCES (IDENTIFIED IN ATTACHMENT E, TABLE 2.2-3), AND SELECTED CONTROL LOCATIONS 3
(11E-7 sec/r)
INDIVIDUAL RECEPTORS                            - DISTANCES TO THE CONTROL LOCATION, IN MILES DOWN-    SITE  VEGE-WIND  BOUND- TABLE MILK MILK MEAT                RESI-    0-          0.5-  1.0-      1.5-  2.0-  2.5-  3.0-  3.5-  4.0-  4.5-SECTOR  ARY GARDEN COW GOAT ANIMAL DENCE                  0.5          1.0  1.5      2.0    2.5  3.0    3.5  4.0    4.5    5.0 0
N        152.0  15.00  --      5.980    7.06  15.90  276.0      49.9 22.70      13.70  8.75  6.52  4.69  3.810  2.900  2.470 NNE        62.3  7.66  --      2.150    7.08    7.95  189.0      32.0 12.20      7.31  4.99  3.69  2.87  2.320  1.920 1.630 NE        132.0  57.90  1.240    0.269    1.24  60.20  156.0      24.8 12.70      7.51  5.09  3.73  2.47  1.980  1.500 1.270 ENE      110.0  13.60  --        1.270          50.40  135.0      20.6 10.20      6.01  4.31  3.14  2.41  1.930  1.290 1.080 E          67.8  6.66  0.828    1.990    1.99  38.80  116.0      17.7  6.57      3.86  2.61  1.90  1.34  1.070 0.883  0.774 ESE        38.0  7.64  -.        3.200    7.64    7.64    76.7      11.9  5.59      3.29  2.05  1.49 ;O.5    0.842 '0.630  0.531 SE        33.3  7.27  1.030    1.030    2.88    7.27    86.2      13.5  6.37      3.75  2.53  1.84  1.20  0.960 0.790  0.666    Z&deg; I SSE        29.1  7.41  1.080    0.382    7.19  10.10    87.0      13.7  5.98      3.53  2.02  1.48  1.04  0.833 0.688  0.531
                                                                                                                                    .0_  4 S          32.8  3.65  3.300    --      6.10    6.38  127.0      20.3 7.56        4.48  3.04  2.23  1.57  1.260  1.050 0.885 SSW        28.7  7.08  4.040    1.850    7.08  22.90  140.0      23.6 8.87        5.28  3.60  2.66  2.07  1.670  1.260 1.070 SW        26.2  15.70  --        9.980  13.80  15.70  204.0      34.8 18.40      11.40  6.38  4.71  3.66  2.960  2.230  1.900 WSW      201.0  22.40  6.230    --      20.40  22.40  347.0      61.3 27.70      16.60  11.40  8.49  6.19  5.020  3.880  3.300 PO W        345.0  18.00  10.600--        14.70  18.00  715.0      132.0  60.30    36.50  17.70 13.20  10.40  8.440 7.060 6.040 WNW      598.0  48.60  35.000 1.920      48.60  48.60  1410.0      269.0  120.00    73.00  48.50 36.40  28.70 23.400 15.900 13.600 NW      1030.0 262.00    --. 9.520  47.80  271.00  1820.0      350.0  164.00    100.00 66.60 50.10  39.50 32.300 21.900 18.800 NNW      345.0  83.40  --        1.840  18.10  121.00  601.0      114.0  52.80    32.20  21.00 15.80  11.60 9.460 7.360 6.310
 
TABLE 2.2-6                                                                        0'S      '.
PV-1/2 ANNUAL AVERAGE, ELEVATED LEVEL, X/Q VALUES FOR CONTINUOUS RELEASES, SPECIAL DISTANCES (IDENTIFIED IN ATTACHMENT E, TABLE 2.2-3), AND SELECTED CONTROL LOCATIONS                                                      Qcon 3
(1E3-7 sec/rn) trr INDIVIDUAL RECEPTORS                                    DISTANCES TO THE CONTROL LOCATION, IN MILES
:Cd DOWN-        SITE    VEGE.                                                                                                                        Itj '
WIND      BOUND- TABLE MILK MILK MEAT                  RESI-      0-          0.5-  1.0-  1.5-  2.0- 2.5-  3.0-  3.5-  4.0. 4.5-0.5          1.0  1.5    2.0  2.5  3.0  3.5    4.0    4.5    5.0            9          '
SECTOR      ARY GARDEN COW GOAT ANIMAL DENCE 0
1i            ct N          0.0082    6.720              1.910  2.27    6.790  0.0289  23.1000 8.2700    5.32  2.56  1.91 1.480  1.200  0.996  0.846 NNE        0.0280    6.690              1.430  6.14    6.890  0.0175  14.5000 6.9800    5.47  3.27  2.69 1.770  1.430  1.290  1.100 NE          0.0110    .074      1.610  0.350  1.61    0.055  0.0069    0.1160 .2300      7.10  5.38  3.68 2.880  2.090  1.880  1.570                          0 ENE        0.0110    9.090              1.770          0.525  0.0135    0.3310 7.2800    6.02  4.75  3.22 2.620  2.030  1.710  1.100 E          0.0360    8.300      1.240  2.870  2.87    8.300  0.0124  17.1000    7.8600  6.20  3.67  2.83 2.190  1.730  1.280  1.200 ESE        0.0420  11.600              4.570  11.60  11.200  0.0208  12.7000    8.1400  4.78  3.00  2.20 1.360  1.160  0.830  0.737 7.4000    7.5700  4.45  2.79  2.05 1.460  1.180  0.811  0.686  N n SE        0.0750    7.890      1.230  1.230  3.05    7.890  0.4770 0.2060    7.390      1.160  0.357  7.20    9.770  0.3030    9.4400  6.9300  4.06  2.58  1.89 1.170  0.937  0.646  0.546                          0' SSE                                                                                                                                        ZI
                                                                                                                                          > -1 I
S          5.740    3.760    3.490            6.06    6.310  0.7960    8.5100 8.4900    4.98  3.37  2.47 1.380, 1.110 0.774  0.655 SSW        7.640    3.610    2.140    0.872  3.61    5.820  26.1000 9.1000 4.0300      3.11  2.11  1.56 1.030  0.834 0.807  0.684    3Z SW        6.500    3.900              2.560  3.47    3.900  36.1000 15.9000 4.9300      3.12  1.77  1.57 1.201  1.060 1.150  0.977 WSW        0.126    4.350      1.420          .3.98    4.350  0.3870 17.8000 4.9000      3.53  2.36  1.64 1.460  1.210 0.920  0.781
:5.        :,,,
W          0.029    2.490      0.764          2.02    2.490  0.0147    8.7200  6.2300  3.68  2.50  1.84 0.741  1.120. 0.851  0.795 WNW        0.033    2.530      1.780  0.163  2.53    2.530  0.0202    0.0549  0.0809  3.07  2.50  1.84 1.110  0.686  0.791  0.731                        :.,
NW        0.007    0.074    --      0.305  1.67    0.073  0.0084    0.0650    0.1170  3.66  2.30  1.69 1.210  0.903  0.804  0.683 NNW        0.008    6.460    --      0.224  1.81    6.590  0.0135    6.7800  5.0200  2.96  1.93  1.49 1.050  0.849  0.705  0.599                        :0 0-4A C'
*Elevated release X/Q value at site boundary location where ground level release X/Qs maximize.
                                                                                                                                                          -R
:v.
Q.
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I        I K)
['Li
 
(I                                                                  (    - /
(.2 TABLE 2.2-7 TV-2 ANNUAL AVERAGE, GROUND LEVEL, X/Q VALUES FOR CONTINUOUS RELEASES, SPECIAL DISTANCES (IDENTIFIED IN ATTACHMENT E, TABLE 2.2-3), AND SELECTED CONTROL LOCATIONS 3
(1E-7 sec/r)
INDIVIDUAL RECEPTORS                            DISTANCES TO THE CONTROL LOCATION, IN MILES DOWN-    SITE  VEGE-RESI-    0-        0.5-  1.0-      1.5-  2.0-  2.5-  3.0-  3.5-  4.0-  4.5-WIND    BOUND- TABLE MILK MILK MEAT 0.5        1.0    1.5      2.0  2.5  3.0    3.5    4.0    4.5    5.0 SECTOR    ARY GARDEN COW GOAT ANIMAL DENCE 14.00            5.740    6.74  14.80  244.0      42.6  20.50      12.70  8.18  6.15  4.45  3.640  2.770  2.380 N        105.0            --
7.37            2.130    6.83  7.64  161.0      28.8  11.40      6.94  4.79  3.56  2.78  2.250  1.870  1.590 NNE      102.0            --
1.250 51.90    1.230  0.268    1.23  53.80  132.0      23.0  12.10      7.24  4.95  3.64  2.42:  1.950  1.480 NE        96.6 13.20            1.280  --    46.30  115.0      19.4    9.89      5.85  4.23  3.09  2.38  1.900  1.270  1.070 ENE        84.1          --
5      >
6.49      .829  1.980  1.98  35.70  99.2      16.6    6.32      3.75  2.55  1.87  1.32  1.060  0.871  0.735 E          60.7 7.25  .-      3.100  7.25  7.25  65.8      11.1    5.36      3.19  2.00  1.46  1.03,  0.829  0.621  0.524 ESE        37.1 SE        41.8    7.06    1.020  1.020  2.85  7.06  73.5      12.6    6.12      3.64  2.47  1.81  1.18  0.945  0.779  0.658    I! 4 7.16    1.070  0.384    6.96  9.69  74.2      12.7    5.71      3.41  1.97  1.45  1.02  0.818  0.676  0.572 SSE        34.0 0.866 coQ 3.64    3.310  --      6.00  6.27  109.0      18.6    7.13      4.29  2.94  2.17  1.53  1.230  1.020 S          32.7 6.73    3.890  1.800  6.73  20.90  120.0      21.3    8.31      5.03  3.46  2.57  2.00  1.620  1.230  1.040 SSW        29.7 1.850 14.80            9.550 13.10  14.80  174.0      31.2  17.20    10.40  6.10  4.54  3.54  2.870  2.170 SW        24.1          --
6.010  --    19.10  20.80  301.0      53.6  25.30      15.60 10.80  8.09  5.93  4.830  3.750  3.200 WSW      159.0  20.80 16.90  10.100          13.90  16.90  636.0    111.0  53.90      33.50 16.50 12.40  9.82  8.040 6.760 5.790 W        264.0                    --
44.50  32.500    1.870 44.50  44.50  1310.0  218.0    104.00    65.40 44.20 33.60 26.70  22.000 15.000 12.900 WNW      404.0 216.00            9.100 43.90  222.00  1720.0  279.0    140.00    88.80 60.30 45.90 36.60  30.100 20.600 17.700 NW      735.0            --
71.00            1.820 17.00  99.40  557.0    924.0  45.90      28.90 19.20 14.60 10.80  8.880 6.950 5.980 NNW      247.0            --
 
I  . Beaver Valley Power Station - - -._ - i
_ _I 1/2IODC-2 1/-'O C-.
02 TitIk:Unit                                                                  Of Use: -
c]:YI 1/2      In-Field Referen ODCM: GASEOUS EFFLUENTS                                    Revasion  PageNumber:
ATTACHMENT F Page 5 of 7 0-5 MILE DISPERSION PARAMETERS TABLE 2.2-8 DV-2 ANNUAL AVERAGE, GROUND LEVEL, X/Q VALUES FOR CONTINUOUS RELEASES, SPECIAL DISTANCES (EDENTIFIED IN ATTACHMENT E, TABLE 2.2-3), AND SELECTED CONTROL LOCATIONS (LE-7 sec/m 3 )
Same as Table 2.2-4
 
ii Powr Beaver          ~*                    PocwdurNumber~
Aey              tation        --              1/2-ODC-2.02 Xe    .-                                                    Unit -      evel Of Use  .
1/2        In-Field Reference ODCM: GASEOUS EFFLUENTS                                      Revision:  Page Number.
                                                                . 1              SX of -128
                                *AITACHMENT F            --
Page 6 of 7 0-5 MILE DISPERSION PARAMETERS TABLE 2.2-9
              - WV-2 ANNUAL AVERAGE, GROUND LEVEL, X/Q VALUES FOR CONTINUOUS RELEASES, SPECIAL DISTANCES
~(IDENTJLEDl IN ALTIACHMENT E; TABLE 2.2-3), AND SELECrED CONTROL LOCATIONS (SE-7 sec/rn2)
Same a's Table 2.2-4
 
Beaver Valley Power  aeyStation-4            odu N 1/2-ODC-2.02 Ttl::                                                    nevel        Of Use:
1/2      In-Field Reference Revisiou: Page Number.
ODCM: GASEOUS EFFLUENTS I.        84 of 128 A'ITACHMENT F Page 7 of 7 0-5 MILE DISPERSION PARAMETERS TABLE 2.2-10 CB-2 ANNUAL AVERAGE, GROUND LEVEL, XIQ VALUES FOR CONTINUOUS RELEASES, SPECIAL DISTANCES (IDENTIFIED IN ATTACHMENT E, TABLE 2.2-3), AND SELECTED CONTROL LOCATIONS Same as Table 2.2-7
 
Beaver Valley      . BevsPower nI StationJPoedeNun7DC b
* ER E -- 112-ODC-2.02.                    2
 
==Title:==
Unit:      Level Of Use:
1/2
                                                                                  -.-        In-Field Reference ODCM: GASEOUS EFFLUENTS                                                      Revision:  Page Number.
                      -                                                            1  ,    5 of 128 IATTACHMENT G Page 1 of 2
                    - NOBLE GAS DOSE FACTORS AND DOSE PARAMETERS TABLE 2.2-11 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS K;
                                                  *,.. Li                                              N; TOTAL BODY          -; SKIN DOSE          GAMMA AIR            BETA AIR DOSE NUCLLDE(1 )      DOSE FACTOR              FACTOR          DOSE FACTOR                  FACTOR
                          .    -mrem/yr
                                . e              mrem/yr              -mradlyr                mrad/yr Per                - iPer                Per                      Per uCi/m 3              uCi/m3              ' uCilm3                  uCi/m 3 ''
Kr-83m            *7.56E-02                                -  1.93E+01              , 2.88E+02 Kr-85m              *1.17E-I03            *1.46E+03            .1.2313+03              1.97E+03 Kr-85                1.61E+O1            1.34E+03              1.72E+01                1.95E+03 Kr-87                5.92E-i03            9.73E+03              6.17E+03                1.03E+04 Kr-88                1.47E+04            2.37E+03            -1.52E+04                2.93E+03 Kr-89              .1.66E-e04            1.01E+04              1.73E+04                1.06E+04 Kr-90                1.56E+04            7.29E+03              1.63E+04                7.83E+03 Xe-131m              9.15E+01            *4.76E+02              1.56E+02                1.1 1E+03 Xe-133m              2.51E+02            9.94E+02              3.27E+02                1.48E+03 Xe-133                                    3.06E+02              3.53E+02                1.05E+03 Xe-135m              3.12E+03            <7.11E+02              3.36E+03                7.39E+02 Xe-135
* 1.81E+03              1.86E+03              1.92E+03                2,46E+03 Xe-137              -1.42E+03            1.22E+04              1.51E+03                1.27E+04 Xe-138              8.83E-i03            4.13E+03              9.21E+03                4.75E+03
* 8.84E+03              2.69E+03              9.30E+03                3.28E+03 (1) The listed dose factors are for radionuclides that may be detected in gaseous effluents.
 
Beaver Valley Power Station                                  Pl-Od c    2Numbc.
m~l:Unit                                                            Level Of Use:
1/2    In-Field Reference ODCM: GASEOUS EFFLUENTS                                                    Revision:  Page Number=
1          Sd6f12R'
                                        --  ATTACHMENT G Page 2 of 2 NOBLE    GAS  DOSE  FACTORS      AND DOSE PARAMETERS TABLE 2.2-12 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES Bi(1),(2)              M  i(3)
TOTAL BODY          GAMiA AIR          TOTAL BODY              GAMMA AIR NUCLIDE(4 )        DOSE FACTOR        DOSE FACTOR        . DOSEFACTOR            DOSE FACTOR mremi/yr              mrad/yr            'mrem/yr                  mrad/yr
                        ''    'Per                  Per          -  -  Per                      Per uCi/sec              uCi/sec          - uCi/sec                  uCi/sec 1 Kr-83m              3.19E-10              1.75E-8              4.58E-8                  3.96E-5, Kr-85m              7.8 lE-5              1.16E-4              4.70E-4                -7.06E4, Kr-85              1.55E-6              -2.35E-6              5.54E-6              - g 8.40E-6; Kr-87              5.13E-4              7.i4E-4              1.45E-3              - 2.19E-3 Kr-88              1.39E-3              2.09E-3              4.09E-3                  6.16E-3 .
Kr-89              7.99E-4              1.20E-3              1.25E-3                  1.88E        Xe-131m            1.64E-5              2.47E-5              1.67E4                    3.09E        Xe-133m            1.38E-5              2.1 1E-5              1.32E-4                  2.61E-4' Xe-133              1.05E-5              1.56E-4              1.54E-4                  2.76E4 Xe-135m            2.41E-4              3.66E4                6.21E-4                  9.50E-4 Xe-135              1.41E4                2.12E4                6.96E-4                  1.05E-3, Xe-137              6.OOE-5              9.05E-5              9.66E-5                  1.46E-4 Xe-138        ' i  8.11E-4              1.22E-3              2.22E-3                  3.34E-3 Arl41              1.02E-3              1.53E-3              2.68E-3                  4.02E-3 (1)
V, and Bi values used to implement Modes 1, 2, and 3 of Section 2.2.1 (10CFR20)
(2)
Bi values used to implement Modes 1, 2, 3, and 4 of Section 2.3.1 (10CFR50)
M3
' ' Vi and B. values to implement Mode 4 of Section 2.2.1 (10CFR20) and to implement monitor setpoint determinations of Section 2.1.2 and 2.1.4 (4) The listed dose parameters are for radionuclides that may be detected in gaseous effluents.
I'-
A
 
Beaver Valley Power Station                                                      !'
Procedure Number-
                                                                                                          -t2..D-2.02 Unit:                  Level Of Use:
1/2                        In-Field Reference ODCM: GASEOUS EFFLUENTS                                                                        Revisio4:              Page Number l                  ~87 of 128.
ATTACHMENT H Page 1 of 1 ORGAN DOSE PARAMETERS I                                                                                                                  I hilI 2.2-13
                                            -(utar per Ci/cufte        I I  .- : t . ;. 1    S- '
Wcild        lao. Ur        T. kd    Tkyrold      Ilduej        Lug      01-LLI
                  .11-3      C.0OMO1  1.121+03    1.11+03 1.125+03 1.13+0        1.121+03    1.121+43 2 P-32      2.601+08  I.1 1+05 9.11+04        6.001+00 0.001+00    0.001+00    4.221+04 3 cc-5l    0.001+00  o.60100 1.541+02        5.551+01 2.431+01    1.701+04    1.081+03 Sh-54      0.001+00  4.2s1+4o 9.511+03      0.001+00  1.001l4  1.581+06 2.2m104 2.071+04  3.341+04      .11+04 0.00+00      0.001+00t1.271+06    7.071+04 8 C-57      0.001+00  9.031+02      1.071+03  0.001+00 3.001+00 5.071+05        1.321+04 7 Co-S8 Ice-ST      0.00140    1.771+03  3.161+03    0.001+00 6.001+00 .i11+06        3.441+04 t t-65      0.001+40  1.31t+4    2.2U+04    0.001+00 0.001+00 7.071+6        3.U21+04 9 h-li5    4.251044  1.133+05    7.631+04  0.001+00 7.14i+04 9.951405        1.531+04 10lblrU      0.001+00  1.381+05    I.41+05    0.001+00 0.001+00 0.001+00        7.191+03 12Sr-SO      5.99145  0.001+00    1.721+04 0.001+00    0.001+00  2.161+08    1.671+05 l.OOtM    0.001+00    6.44U+t60.001+00      0.601+00  1.451+07    3.43145 13 7-91      9.141+05    .oo1+00 2.441+04 0.001+0        0.00t+00  2.631+06      1.84+05 142r-9S      1.901+05 4.181+04 3.701+04 0.001+0          5.961+04  2.231+06    6.111+04 15 1lb-I    2.351+04 9.151+03 6.551t03        6.001+00  8.621+03  6.14105    3.701+04 16lb-ST      4.291-01  7.701-02    3.601-02 0.001+00      8.551-02 3.121+03- 2.711+04 17 Io-19    0.601+00  1.721+02    4.261+01 0.001+00    3.921+02 1.25145 1.211t05 UStc-99u    1.751-03  3.4-3        6.771-02 0.001+00      5.01142 1.511+02 4.811+3 19 h-103    2.719103  0.001+00      1.0e713 6.00140      7.M31+03 6.62+05 4.45+04 2l lee-I      1.3XtO5  0.001o0o    1.691+04  6.001+0    1.64O+05  1.411+07    4.291+05 21 4g-llhn    1.691+4    1.141+04 9.141+03      0.001+00  2.121+04 5.4IU+0      1.001+05 22 Sb-12      5.741+04  7.401MU22.601044        1.261+02  0.001+00 3.241+06      1.84+05 9.6414    7.551+02    2.071+04  9.101+01  0.001+00 2.321+06      4.031+04 t3Sbt-125    2.491+04  3.551+03 3.021+03      6.071+03  6.M3U+04  1.41+06      7.141+04 1.921*04  6.651+03 3.041+03      6.331+03  5.031+04 1.761+06      1.521+05 2t61-131      4.511+4  4.811+04    2.731+04  1.621+07  7.UI+04  0.0010      2.841+03 27 1-13      1.61+04  2.43104      7.705+03  3M1S+06    3.381+04  0.001+0      5.481+03 2t Cr-134    6.511+05  1.611+06    2.251+05  6.001+00  3.301+05  1.211+05    3.851+03 29 C.-138    6.511+04  1.711+a5    1.161+05    3.001+00  9.s51+04 1.451*04    4.IU+03 30 Ce-slT    9.071tO5  8.251+05    1.2U1t5 0.001+00      2.821+05  t.641+05    3.621+03 31 h-105      1.401t04  6.41+ol      4.835+03  0.001+00  2.111+01  1.74146      1.02145 32 a-110s    6.441+02  2.251+02    7.551+t    0.001+00  0.001+00  1.831+05    2.2614t5 33 C.-124    3.621+04  1.951+04    2.961+43  0.001+00  8.551+01  5.441+45      M.6UM+I 34 Ce-127    6.11+06  2.121+06    3.611+05    6.001+00  L.17+0    1.201+07    3.891+05 CQlclatad per OOM slutlos 2.2-13
 
Procedu    Number.
Beaver Valley Power Station                                I.
1-i/2- ODC-2.02 A..._
Unit          Levet Of Use:
IL      : GASOU        E                                                                      In-Field Reference Revision:      Page Numbern ODCM:- GASEOUS EFFLUENTS I                RR nf 19R ATTACHMENT I Page 1 of 1 MODES OF GASEOUS RELEASE TABLE 2.3-1 MODES OF GASEOUS RELEASE FROM BEAVER VALLEY SITE VENTS FOR IMPLEMENTATION OF 10 CFR 20 AND 10 CFR 50 RELEASE-..        . RELEASE            RELEASE                  RELEASE RELEASE POINT                  MODE I            MODE 2              MODE 3                    MODE 4 i
RP 1; VV-1, Auxiliary            Aux. Bldg.          Containment      Same As Mode 1            Same As Mode I Building Vent(')                Ventilation        Purge(3 )
RP 2; CV-1, Rx                  Leakage Collection Same As Mode 1 -Same As Mode 1              Same As Mode 1 Containment/SLCRS Vent"l)        Exhaust                              and Containment Purge(3 )
RP 3; PV-1/2, Gaseous            Main Cond. Air      Same As Mode 1  Same As Mode 1            Same As Mode 1 Waste/Process Vent( 2 )          Ejector, Waste Gas,                                            and Containment N
Containment                                                    Purge Vacuum RP 4; VV-2 SLCRS                Contiguous Areas    Containment      Same As Mode 1            Same As Mode 1 Unfiltered Pathway~l)                              Purge( )
RP 5; CV-2, SLCRS Filtered      Aux. Bldg.          Same'As Mode 1  Same As Mode 1            Same As Mode 1 Pathway(l)                      Ventilation                          and Containment Purge(
(4)                (4)                (4)                    (4)
RP 6; CB-2, Condensate Polishing Bldg Vent '?
(4)              (4)                    (4)_
RP 7; WV-2, Waste Gas                    (4)
Storage Vault Vent l    .
DPS-  nu-                  I.,          (4)                  (4)              (4)                    (4)
      -s -, v v- ,
Decontamination Bldg Vent(')
(4)                  (4)                (4)                    (4)
RP 9; TV-2, Turbine Bldg Vent(')
NOTE: For the purpose of implementing 10 CFR 50, batch discharges may use continuous meteorology since short term meteorology is used at the time of the annual report.
(1) Continuous ground level meteorology is applicable (2) Continuous elevated meteorology is applicable (3) Mode established by purge from one unit, all other release points remain same as Mode 1 (4) Not normally a radioactive release point I
 
Procedure Nwber.
valley Power      Peaver Station                                                      - -1i2-ODC-2.02 Title                                                                                        Unit:        Level Of Use:
1/2          In-Field Reference ODCM: GASEOUS EFFLUENTS                                                                      Revision: -    Page Number 1        89 of 128 ATTACHMENT J Page 1 of 19 P&I ORGAN DOSE FACTORS
                                                      ?Oa1l2.3-2 usIS M 31m VALL slE (aJn/yr pievCt/cu oeter)
Pathway: laaltlote, 4o greop : Iilt liaclIde        hee      LInr    I. bd    Tkrid      MIdey      Luj      GI-ULI 1-1-3        0.001+00 1.26t+03      1.261*03  1.281+03  1.2u13    1.2814t3    1.261+03 2 P-32        1.3213+6 7.7044        5.0114    0.
COMO0    0.001+00  0.001tO0    I.64141 3 Cr-51      0.001*00 0.00100      1.001t42  S.V51+01  2.2Ut11  1.441*4    3.321*3 4 h-54        0.001*00 3.H14*04      4.301*0  0.001*00  1.641+03  1.401*0    7.74104 51t-SI        1.16159 M        2.781+04    L.61*04  0.001+00  0.001*00  1.021+06    1.88105 OCo-5T        0.001*00 4.121*2      6.711*02  0.001+00  0.601*00 3.701*05    3.113*04 7 Co-SO      0.001+00 1.58103    -2.01n03    0.001*00  0.001*00 1.281+05    1.081*05
                  &#xa3;Co-4        0.001+00 1.151*04      1.t4LO  4 0.001*00  0.001+00 5.911*06    2.851*05 91es-I        3.2+104 I-1.031*0      4.68 4    0.t001*00 6.901*04 8.641*05    5.3U104 1o lb-as      0.001+00 1.3*05        5.901+04  0.001*00  0.0OMM0  0.001*00    1.88104 11 Sr-ss      3.041+05  0.001*00    0.72103  0.031*00  0.003*00  1.4010W    3.501*05 12 sr-9o      1.921*+0  0.001+00 6.10106 0.001+00      0.001+00  9.601+06    7.221+05 1-11        4.621+05  0.001+00 1.241*04 0.001*00      0.00100  1.701*06    3.651*05 14 r-9S        1.1T1*05  3.441*0 2.33*4 0.001*00        5.421*04  1.771*0t    1.501*05 15 lb-95      1.411*04  7.621+03 4.211*03 0.001*00      7.741*03  5.051*05    1.041*05 16t -97        2.22141    5.621-2    2.001-02 0.00100,  4.541-02 2.403+03    2.421*02 17o-9"        0.001*00  *.211*02    2.301*01 0.601*00  2.911+02 9.121044    2.MtO*S 18 Ic-s..      1.03e-43  2.9113-0    3.701-02 0.01+00    4.421-02 7.641+02    4.1.6103 19h-163        1.53143    0.001+00    6.S58102 0.601+00  5.631*03L50*          1OMS.11+
20 h-108      6.s11*04  0.001*00    6.21*03 0.001*00    1.341*05 1.31*04      9.121+05 21 4g-110      1.081*04 1.01+04      5.141+03  0.001*00  1.171+ 4 4.033t+o 3.021ut5 22 Sb-124      3.121+04 5.601+02      1.21*04  7.551*01  0.001*00 2.416 4.081+05 23 Sb-125      5.341*04 5.151+02      1.28304  5.401*01  6.603+00 1.741*6 1.01*05 24'Te-11n 1.2U6+04 5.7nt3            1:5s1*03  3.291*03  4.581*04 1.601*05 1.501*05 25        9e-12h 9.761*03 4.671*3      1.5818+3  3.441+03  3.681*04    .16*06 3.631+45 26 1-131      2.521*4t  3.581*84 .2.051*4f 1.1910t1      6.131*04 0.001*00    8.28300 27 1-133      6.64+03    1.43*044    4.51*03  2.15106 2.5U104      .001*00    3.6u8+03 28 Cd-134      I3.t9405  L.481W      7.21+05 :0,01*00 '2.67+05    1.761+04    1.041+04 29 C-136 -:3.101*04      1.4+05      1.101+05 0.601*00 6.581+04    1.20144    1.111+0(
30 Ca-137      4U1J+05  6..211*01    4.2105 0.001*00 2.223+05      7.52304    8.401*03 31 h-140 --3.901+01      4.901+01    2.571*03 0.001*00  1.671+01  1.m*06      2.161+05 32 L 3.44302        1.741+0      4.583*61 0.001*00  0.001*00  1.363+05    4.51*05 33 C-141        1.991+04  1.351*04    1.51+03  0.001+00  6.241+03  3.62*05    1.201+05 34 Ce-144      3.431+06    1.431*06    1.841tO5 0.003+00  6.481*0  7.7M 565.161*+0 Calculated per ODHa gaeticn 2.3-22
 
r                                                                              S              .I. Pwcedur Number I Beaver Valley Power Station                                                      -/                    li.ODC-2.02
 
==Title:==
Unit              Level Of Use:
1/2            In-Field Reference ODCM: GASEOUS EFFLUENTS                                                                          Revision:        Page Number I        I        sn  of 12I AITACHMENT J Page 2 of 19 P&I ORGAN DOSE FACTORS la'ole 2.3-3 1 TimK FORW1m2 ViAUl          ginI (oneljt per VCi/ri inter)
MWAYus    lihalAtlca ISO Group    TMe hellie            lee      Liver    T. lody    TIrold        lTlsey      Lua        91-U' 1 1-3        0.001400  1.2T7103    1.271*03  1.27103 I.M103        1.271*03    1.271+03 2 P-32        I.O91tC    1.101+05    7.161+04  0.001+00 6.001+00      0.001+00    1.281+4l 3 &-51        0.001.0* 0.001+o  0    1.351*02  7.501+01 -. 0`1+01    2.101+4t    3.001+03 4 1-54        O.001+00  5.1114      5.401+03  0.001+0 1.m2+04        1.961+06    6.61+04 s r.-ss      *1.53+04 3.701+04      1.431+4    0.001+00 6.001+00      1.531+06    1.781+05 Co-57      0.001Q00  9.W442 9.201+02 0.001+t0            0.001+00 5.861+05    3.141+04 7 Co-sa      0.001.00  2.071+03    2.781*03  0eO.+00      0.001*00 '1.343+06    9.521+04 8 Co-1o      0.001*00  1.511*04    1.181*0    0.001+00    0.001*00 6.121+06    2.591+05                          :-:
9 la-6S      3.81+04    1.341+05    6.211+*0  0.001+00    3.64+04  1.211+06    4.661+04 1 16        6.001+00  1.901*05      .401*01  0.001fa6    0.001*00  0.001+00    1.7744 11 Sr-19      4.341*05  0.001*00    1.251+04  0.001+00    0.001*00  2.421+6    3.711+05 12 sr-9O        1.08+01  0.001+00    6.681+01  0.001*00    0.00gM    1.651*07    7.651+05 13 t-91        6.U1105    0.001+00    I.1+04    0.001+00    0.001*+0  2.941+06    4.091*05 14 Sr-95        1M4ato0    4.581+04    3.151+04  0.001+00    6.741+04  2.891+06    1.491+05 15 15          1.88104  1.031+04N    SU1+03    0.001*0      1.001*04  7.511+05    9."11+01 1615-97        3.14-01    7.7U-02      2.841-02  0.00KM0      SA1-02    3.931+03    2.1T7+03 17 N-S9        0.001*00  L.891+02 3.2214+1      0.001+00    4.111*02  1.541+05    2.691+05 is IC-so        1.381-03  9:t61-03 4.191-02      0.001+00    5.761-02  1.151+03    6.131+03 is l1-103      2.101403  o.001+00 8.98UtO2      0.001+00    T.431*3  7.439+05    1.091+05 20 h-B16        .841+04  0.001+00    1.241+04  0.e1+00      1.901+05  1.611+07    9.801+05 21  1g-110      1.31+04    1.311*04    7.99103 0.001+00        2.501+04  6.751+06    2.731+05 22  Sb-124      4.301*04  7.941+02    1.681+04 M.7U+M        4..0010  3.341+06    3.9B1+05 23    b-S25    1.381+04  6.081*02    1.721+04 .7.04+0        0.001+00  2.74+06      9.921+04 24  To-l27o    1.e01+4    8.161+03    2.181*03 4.381+03      6.541+04  1.61+06    1.5s1+05 25  Te-129      1.391a04  6.583+3    2.251*0O34A+3          5.111*04  1.981+01    4.051+05 26 1-131        3.54104    4.911+04    2.641+04    1.461+07    1.401+04  0.001+00    6.491+03 271-133        1.223+04 2.051+04      6.221+03    2.12106o    3.59104  0.001+00    1.031+04 21 Cs-134      5.0215*0 1.131+06      5.411*05  0,00I*0. 3.151+05 11.461+05    9.781+03 21Ca-136        5.151tU0  1.941+05    1.371+05  0.001+00    1.101*05  1.711+04    1.091+04 30 CJ-137      6.701*05  6.481+05    3.111+05  0.001 eo    3.04105    1.211+05    8.461+03 31  1a-140      5.4AT04    6.101*01  3.521+03    0.001t+0    2.281+01 2.031+08      2.291+05 32  L-140      4.791102  2.361+02    6.281+01  0.001+00    0.001+00t 2.141+05    4.8t1+05 33  C-1I1      2.841+04  1.901+04    2.171+03    0.00100      8.881+03 6.141105    1.261*05 34  C-144      4.891+01  2.021*06    2.621+05  0.001+00    1.211+06 1.341+07    5.141+05 Calculated per OD    equatios 2.3-22
 
Procedur Numtbe:
Beaver Valley Power Station                                                                              1/2-ODC-2.02 Unit            Level Of Use:
112          In-Field Reference ODCM: GASEOUS EFFLUENTS                                                                          Revision:        Page Number:
I      1:            41 of 128 ATTACHMENT J Page 3 -of 19 P&I ORGAN DOSE FACTORS Sble 2.3-4 I WIS vim          31t1mm hILU    s11 (amle_ r per1:....
                                              .m ..
vei/es mter) patilva= Ilshaltlon 4p Group Child luclide          Sow      Mmver T. lody            Thyroid    Kliney                61-LI I 1-3          6.001+0  1.2t1+03      1.2+03      1.121+03  1.121+03  1.121+03    1.121+03 2 P-32        2.M0UM06  1.141+05    9.31+04        .601+00            0.001+00    4.221+04 3 Cr-SI        0.00100 0.00t+00        1.541+02    8.551+01  2.431+01  1.703+04 4 .-SO        o.eoioo  4.291+04    9.511*03      o.eooWoo  1.001+04  1.581+oo    2.291+04 S to-SS        2.071+04  3.341+04      1.M71+04    O.eo+0oo  0.001too 6 CO-57        0.001+00  3.31+02      1.0?1+43    0.001+00  0.001too  5.011*05    1.321+44 7 CS          0.001+00  1.m7+03        .16105    0.001+00  0.601+00  l~li+Os 1.111+06    3.441+0 BCo-60        0.00100  1.311+04      2.2n+04      0.601*00  0.001+00 1.071+06    9.621+04 S    -I65    4.25104    1.131tOS    7.031+04    0.001+00  1.141+0  9.351+05    1.631+04 10tlob-          .001+00  1.381+05    1.141+05    0.001+00  0.001+00 0.001+00      7.991+03 11 sr-s        5.991*05  0.001+00      1.731+04    0.001+00  0.001too  2.161+06    1.671*0 12Sr-9O        1.011+08  0.001+00      6.441+0      0.001+00  0.001+00  1.481+01    3.431+5 13 1-9L        9.1414+5  0.001+0      2.41+04      0.001+00  0.001+00  2.631+06    1.341*05 14 ZIr-S        1.901+05  4.181+04      3.701+04    0.001*00  5.961+04  2.231+06    8.311+04 15 lb-9S        2.351t4  9.181+03      6.551+03    0.001400  3.62103              3.701+04 16 b-9T        4.291-01  1.701-62 .3.6102 0.001tOO            8.558-02  3.421+03    2.781+04 17la-I      . 0.001+00  1.12+02 1.2131+01 0.601+00          3.921+02  1.351+05    1.271+05 18Ic-I9a        1.76143  3.411-03 5.7 71-02 0.001+00          5.011-02  9.511+02    4.811+03 19 h-103        t.l91*03  6.001+O  0 1.0N1+030.601400          7.031+03  6.621MO      4.483+04 20 h-l6 -      1.381+0  0.001+00 11.31+04 0.001+00            1.641+5  1131+07      4.291+05 21 1g-1101      1.691tU4  1.141+04    9.141+03      0.001+00  2.12104  5.481+06 22 Sb-124      5.741#04 7.4012        2.64 1+04 . 1.261+02    0.001+00  3.241+04    1.841+05 23 5b:125      9.841+04 1.591+02      2.0 71+04 9.101+01      8.001+00  2.321*06    4.031+04 24 1e-127.      2.4MU+0M.551+03        3.0;21+03 3.071+03      6.36104  1.481+06    7.141+04 25 le-129a      1.921+04 6.851+03      3.0eu+03 6.331+03        5.031+04  1.181+06    1.821+01 26 1-131        4.811*4    4.811+04    2.7M31041.621+07        7.88104  0.001+00    2.841*03 2?  1-133      1.68104t  2.631+44 1.701+03          3.811+06  3.31*04  0.001*00    5.481+03 21  Cs-134      6.511+05  [.011+08 -2.251+05        01&deg;1+00    3.301+05  1.211tO5    3.85+03 29  C1-136      6.511+04  1.711+05 1.161+05          0.401+00  9.551+04  1.451+44    4.161+03 30  CS-137    9.015      85+          1.231+05      0.601+00  2.321+05  1.041+05    3.621+03 31 b-140        7.401+04  8.451+01    4.331+03 0.e01+00        2.111+01  1.741U06    1.2U405 32 h4-140        6.411+02  2.251+02    1.5 511+010.601*f00      0.00+o0o  1;331+05    2.261+05 33 Ce-ll        3.9+1t04  1.951+04    2.901+03 0.601+00        8.551+03  5.440105    S.6u1+04 34 Ce-144        6.771+0  2.121+0H    3.6 M0M 0.601+00        1.171+06  1.201+0    3.891+05 Calculated per CDCIepatlot 2.3-22
 
      . Beaver Valley Power-Station                                                          1I Bee Pure        1NubeC 1/2-ODC-2.02 Wte:                                                                                            Unit              LcvelOfuse:
                                                                                              ; : 1/2            I    In-Field Reference ODCM: GASEOUS EFFLUENTS                                                                        Revision:          Page Numbee
                .                                                                                    1                  42 of 129 ATTACHMENT J Page 4 of 19 P&I ORGAN DOSE FACTORS Taile 2.3-5 I        70132 1TTIM "lIUIS      LL SIT1 (area/yr per nCi/e meter) fatbuy Inhlatla.
Ag group: Isfut helild          lom      Liver    T. Body  7tyroid        lldney      Lu        61-UI 111-3        0.001*00    .4102      6.m1+02 6.471+02 6.471+02 6.471+02          6.47102 2 1-32        2.031+06  1.121+05    7.741+U 4 0.003t+0 M.OM1+0.001+00            1.611+01 3 Cr-SI      0.001+06  0.001+00    8.951+01 5.751+0L 1.323+01 1.28+04          3.511+02 4 Nu-54      0.001+00  2.531+04    4.901+03 0.001+00 .4. .03        1.001+06    7.061+03 5 te-SI        1.36ilt  2.351+04    9.4U1+03 0.00100 0.001+00 1.011+06          2.481+04
                  &#xa3; C-57        0.001400  6.511+02    6.411+02  0.001+00    C.OM+0O  3.791+05    4.861+03 7 Co-5t      0.001+00  1.22t+03    1.e21tO3  0.001+00    0.001+00  7.M71+05    1.111404 I Co-6        0.001+00      M.e21+03  I.11U+04  0.001*00    0.001+00  4.511+06    3.191+0t 9 m-5          1.931+04  6.281t+4 3.111+04      0.001+00    3.251+04  6.471+05    5.141+04 10 lB-88        0.001+00  1.901+05 8.821+04      0.001+00    0.001+00  0.001+00    3.04103 11 Sr-"        3.90t+05  0.001+00    1.1t4+04  0.001+00    6.001+00  2.031+06    6.401+04 12 Sr-90        4.091+07  0.001+00    2.591+06  0.001+00    0.001+00  1.121+01    1.311+05 13 1-91        5.881+05  0.001+00    1.571+04  0.00100      0.001+00  2.451+06    7.031+04 14 If-95        1.153+65  2.791+04    2.63104  0.001+00    3.111+04  1.751+06    2.171+04 15 lb-95        1.571+04  6.431+03    3.781+03  0.001+00    4.721+03  4.791+06    1.271+04 16 1-917        3.4I-01  7.291-02    2.831-02  0.0014+0    5.701-02  3.321+03    2.891+04 17 5g-9I        0.001+00  1.651t02    3.231+0I  0.001+00    2.851+02  1.351+05    4.871+04 1t c-gS.        1.401-03  2.881-03      3.721-02  0.001+00    3.111-02  6.111+02    2.031+03 19 h-l13        2.621+03  0.001+0      8.791+02  0.001+0O    4.241+3  5.521+45    1.611+0 20 l-106        8.88A+0    0.001+00    1.091+04  0.001+00    1.071+05 1.161+07    1.641+05 21  Ag-110a    9.981+0    7.221+03    5.001+03  6.001+00    1.091+04 3.671+06    3.301+04 22  S5-124    3.791+04  5.541+02    1.201+04  1.011+02    0.001+00 M.651U06    5.911St 23    5b-125    5.171t+04  4.M102      1.0.1+04  6.231+01    0.001+00 1.641+06    1.471+04 24  Te-127u    1.671+04  8.901+03    2.071+03  4.871+03    3.751+4 1.311+06      2.731+04 25  Te-129    1.411+04  6.091+03    2.231+03  4.211t+03    3.181+04 1.681+0      6.901+04 261-131        3.791+4    4.441+04    1.96+04  1.481+07  -  5.181+04  0.001408    1.081+03 2n 1-133      1.321+04  1.921+04    5.601tO3  i.581+06    2.2U4t4  0.001+00    2.101+03 28 Ca-134      3.9M1+OS  7.031+05    7.451+04  0.001+00    1.901+05 7.971+04    1.331+03 29 Cs-136      4.t31+04  1.351+05    5.291+04  0.001+00    5.64+04  1.181+04    1.431+03 30 CJ 137      S.4A11MS  6.121+05    4.551+04  0.00100      1.721405  t.l11+04    1.331+03 31  h-140      5.801+44 5.601t01      2.901tO3  0.001+00    1.341+01  1.80106    3.061+04 32  TA-140      5.051+02 2.001+02      5.151+Ot  0.0010      0.001400  1.U81+05    8.481+04 33  Ce-141    2.771+4 1.671+04        1.991+03  0.001+00    5.251+03  5.171+05    2.161404 34  Ce-144    3.191+06 1.211+06      1.763+05  0.001+00    5.389+05  9.141+06    1.481+05 Calcalated per OM eutiot 2.3-22
 
        -Beaver Valley Power Station                                                                `-Number'  l2 1dtle: '                                                                                        Unite              Level Of Use:
1/2            In-Field Reference ODCM: GASEOUS EFFLUENTS                                                                        Revision          PageNumba
                --                                                                                    19-3              9of    128 ATTACHMENT J Page 5 of 19 P&I ORGAN DOSE FACTORS 7*41. 2.3-5 I llUS a            1m LM siI
                                      -      (    meter-ci/jr ler SeCI/ee)
PathWa    Ground INclIe          lone      Mimer    T. Myd SI id            lidner      LU        61-ULI 1 1-3,        0.001tW    0.001*00      C.0OMMoo    0.001+0  0.00100    .003l00    0.001*00 2 F-32        0.001+00  0.001*00      6.00140 o0.001.00    0.01040 0.001+00        0.001*00 3 Cr      4.661+06  4.661*06 4.681*06 4.561*01          4.66146 4.681406        4.681+06 4 -5          1.Ka5  o 391+09  1.391      -        1.3191+9 1.391    1.31O 9 1.391*09        1.391*09 5 l-59        2.731+08  2.131*06 2.131+05 2.131+08          2.131+08 2.731*08      2.731*08 I Ca-St      0.001*00  *.00100      0.001o00 0.001+00o:6.001*00    0.001*00      0.001*00 1 Co-55      3.191*0    3.111*08 3
* 3.79+08 3.71406    3.MUM8 3.79+106 Co-60      2.151+10  2.151+10 2.151+10 2.151+10 2.151+10          2.151+10 2.151+10
                  - -9  45      MU 7.41*0      1.410 -. l.47106 1.471*08 1.471*0        7.4t11 7.471+08 10 31-86      8.991*08  C.99106                6.991*06 8.991    6.mto6 8    .991d+88.991+06 11  Sr-89      2.161t0 2.161*04 2.161+04 2.161*04 2.181*04            2.161*04      2.161+04 12  Sr-SO      6.001+00e  o0.0"0100-. 0too  1      0.001*0 0.001+00    001*00        0.001+00 13  T791        1.01+06 1.071+t6 1.01+06 1.07110              1.071*0    '1.071+06    1.071+06 14  Zr-95      2.451*08 2.45108 2.451*0 2.1SOW                2.451*08  2.451+08      2.451*08 15  1b-95      1.37108 1.371*0          1.371108 1.371+0e 1.371*08      1.371*0      1.371+06 6Ilb-Si      0.001*00  0.001+00    0.001+00    0.001*00  0.001+00 O .001*00 0.001+00 17Ho-99        4.001+0    C.001M0      i4.001+06  4.001*08  4.001+06 4.001+6        4.001+08
                  -, I-CS 18            1.641105  1.641*5      1.6405 e    1.641*5  1.841*05 1.84105 1.841+05 19 h-103      1.081*08  1.081*08      1.081+08  1.081+08  1.081*08 1.0t08 1.0e1u0a 20 h-106        4.221*8 4.221*08        4.221*08  4.2210    4.221*08 4.221*08 4.221+08 21 1.-110. '3.441+09      3.441+09      3.41*09,  3.441+09  3.441+U 3.4409          3.441+09 2 s-124                  0.00.00100 0.001+00                              0.001+00      0.001e00 23 Sh-125      0.001+00 OM.00 0.00100              0.00100    0.001*00  0.001*00      0.001*00 24 0-12        9. 9.17104  4 9.171          +0s' 4    .1+14  9.171*04  9.171 04 9.171+04 25 7.-l2t      1.981+07 1.981+*0        1.181+01 1.981+07    1.981+07  1.981+7      1.911+07 26 1-131        1.121*071.72U1*1.Mo721*.1.121+0'              1.21*07    1.721+07    1.721*07 27 1-133      2.451*06 2.451U0 2.451+6 *2.Ult06  25        2.45*06'  2.451+06      2.451+08 28 Co-134      6.8t1a0    4.88*09 6.861+05 8.68109 6.681409            6.681*09 6.161+09 29 Ca-13      1.511+09    1.511t*8    1.511*08    1.511+08  1.511*08  1.511*08 1.511*08 30 C-137      1.031+101.03110          1.0310      1.031+10  1.031U10  1.031*10      1.031*10 31  1a-0IO    2.051t07 2.051+07        2.051+07 2.051307    2.051+07  2.051+07      2.051*07 32  La-140      1.921+07  1.921t7      1.921*071:-1.921+47  1.921+07  1.92107      1.921+07 33  Ce-1l1      1.371*07  I.3 01      1.371*1 1.371+07      1.37T107  1.371*07      1.371+07 34  Ce-144    6.981*07 6.S9+07          U.9to*7 6.861+07    6.961+07  6.961*07      6.961+07 Calculatei perODY  ejuttios 2.3-23
 
Beaver Valley Power Station- -N                                                                        /ODC-.2O2 Titk.                                                                                          Unit:            Level Of Use 1/2              In-Field Referen e ODCM: GASEOUS EFFLUENTS                                                                                          P Nubefeec
                    -                                                                                1                ~94 of 9_
ATTACHMENT J Page 6 of 19 P&I ORGAN DOSE FACTORS Table 2.3-7 I IIlKS        B1MuILLIT SIT!
(.t seter-ares/ir per CI/wec)
Fathea    Vegetatlos Ageamp: Idlt dide          hue        LUnr    T. lodr    Ityroid      lidme1      tU        61-LUI 13-3          C.0OMO    2M            .26143 MUM          2.261403  2.t26+03    2.26143 2 V-32        1.4010    6.7?+41      5.431t47 0.001+00      6.001400  0.00 4      1.581+08 3 Cr-SI      0.001+00  6.001+0      4.641+04 2.781404      1021+44  6.161*04    1.171+07 4 K-54        0.001+00  3.1314M 5.g7 7 0.001*00            9.311417  0.0014      9.590148 kt-S9      1.261408  2.9a1+0eI.IU+08 0.001+00            0.0010    8.211+01    9.881+06
                  &#xa3; Co-S7      0.001*00  1.1T7107    1.951+07 9.001+00 0.001+00      0.001*00    2.971+05 7 Co-SI      0.001+00  3.01140      6.881+07 0.001+00 0.001+0        0.00100      6.231'08 1 Ce-6        0.001+40  1.61+08      3.81+06s 6.001+00 o.00140t      0.001+00    3.14U409 OZa-IS        3.17T108              4.56108 0.001+00 6.751+06 4I.00                            0.001400    6.361+08 10lb-H          6.001+0  2.110        1.021tJ+080.001+06 o.001+00    0.001+00    4.331+07 11 sr-t9        9.m+9    0.001+00      2.661408  0.00140    0.001+0  0.001400    1.60149 12 St-90        6.051+11  0.001*00      1.411i1  0.001+00    0.001o00  0.001+00      1.751*10 137-91        '5.1t1+06  0.01M00      1.371+05  0.0014      0.60034  0.001+0      2.611+09 14 2r-IS        1.171+06 .3.71+05      2.551+05  0.0014      5.911+05  0.001+00,    1.191+09 IS lb-S5        L421+05 . 7.921+04      4.261+04  0.001*00    7.831+04  0.001O        4.811+08 16 lb-9T        2.161-06  5.461-07    1.001-07  0.0014t    6.3t-07  0.0014O      2.021-03 17 o-"S        0.001+06  6.151+0        .1T1+06 0.0014t    1.3914?    0.001+00    1.431+07 i te-Os.        3.1010 . 6.771t        1.121+02  0.00140    1.331+02  4.301+00    5.191+03 19 h-103          .71+06  6.001+00    2.0+06    0.0O1+00  1.621+07  0.0014o    5.57T148 20 h-10        1.13148    6.001+00    2.441+07  0.001+00    3.721+05  0.001+00    1.251+10 21 11-lI0      1.051+07  9.751t0t    5.791+06  0o001+00 1.921tO7    0.00140    3.906109 22 Sb-124      I. 0418    1.961+06    4.111+07  2.511+05 6.001+00    8.071+07    2.941+09 23 Sb-125      1.371+08 1.531+06 3.251+07        1.391+05 6.001+00    1.051+08    1.501409 24 ?e-U7m      3.401+06U  1.251t8O4.261+0t7        .921+0'7 I.14+09    0.0014      1.17149 25 Ta-120      2.511i06 1.381+01 3.01+07          8.641+7 1.051+09      0.001+00    1.271+0 261-131        8.081+07    .161+6    1.621+07  3.791+10    1.91+08  0.0010      3.051+07 2T 1-133        2.091+06  3.61+06      1.111+06  5.33148    6.331+06  0.001400    3.261+06 28CA-134        4.671+09  1.111+10    1.081*09  0.0014O    3.591+09  1.101+9      1.41+08 29 Cs-16        4.271+07  1.691+08    1.211+08    0.001+00    1.381+07  1.291*07    1.011+07 30 C-137i 6.36109          t:701+98' 5.701+09      0.001+      2.951409  1.811+08    1.6814+8 31 h-140        1.29010t  I1.611+05  8.421+0    0.001S4      M01+0    9.24104      2.651+08 32 La-140      1.9861+3  9.07142      2.631+02  0.001tO 0.001+00      o0.0014      7.321+07 33 Ce-141      1.971+05  1.331+05    1.511+04  0.001+00. .6.191+04    .001+04    S.101408 34 Ce-144  '3.M2+07        1.381+07    1.771+06  0.001+00    8.161+06  0.0014e      1.111+10 All aUcildes (except 1-31 calculated per 0DCH    qutlos 2.3-26 1-3 calcalated per ODCI    ejuatlos 2.3-29
 
Procedure Numbec
        -Beaver Valley Power Station;
___      ___      ____          ___      ___    ___    __                      /2-'O DC-2.02 Titic                                                                                                      Unit:            Level Of Use:
:1/2            In-Field Reference ODCM. GASEOUS EFFLUENTS                                                                                    Revisio          PageNumber.
f .128 ATTACHMENT J Page 7 of 19 P&I ORGAN DOSE FACTORS Tail$ 2.3-I l flos r mm Tuim sm (sq eter-ur/yr per sci/sec)
Pethva: yegetatios 4se Group ieea
                                          'Nclode lone        liver    7. lIo        ti4mld - luep            Lug      61-UI 11-3          0.001+00 2.591+00        2.5ilO03 2.591+03 '2.591+03          2.591+03    2.591+03 2 P-32        1.611+09 9.11t+07        f.241+07 0.001+00 4.001+00          0.001+00    1.351+98 3 Cr-51      0.001+00 0.001+00          .11TR+04    3.431044 1.351+04    8.613+04    1.043+0T 4 h-54        0.001+00 4.541+05        11.011+0 0.001+00 1.38148            0.003+00    3.321+5 5 Fe-S9        1.751+08 -4.191+08        1.62+08 0.001+0 0o.001+00            1.321+08    9.90+08 OCo-SI        0:001.00      .791+0i1. 3.001+07      0.001+0    0.001+00  0.001+0      3.331+8 1 cos58      0.001+00    1.361+07 1.001+08          0.001+00  001+00    0.001+0      8.011+08 5 Co-6        0.001+00    2.491+08 5.601+08          0.001+00  0.001+00    0.001+00    3.21+09 s Z-os        4.21+08    1.471+09 6.81+T0            0.001+00  9.421+08  6.001+00    6.231+08 to              0.001+00    2.141+8 -1.2t+08            0.001+00  0.001+00    0.001+00    4.051+07 ISr-9          1.51110    0.001+00oo  4.34+0        0.001+00'  0.001+00  0.003+00    1.801+09 12 Sr-O        7.511011 A B        .003+00 1.851*11          0.001+00  0.001+00  0.003+00    2.111+10 13 1-91        7.141+06    6.001+00 2.161+05          0.001+00  0.001+00    0.003+00    3.211+09 14 Zr-95        1.721+06    5.431+05 -3.741+05          0.001+00  7.983+05  0.001+00    1.251+09 15 nb-95        1.921+05    1.071+05 5.871+04          O.001+0  -1.033+05    0.001+00    4.561+08 16 f-97        2.001-08 4.971-0          1.811-07      0.001+00  5.811-07    0.003+00    1.191-02 17 Io-99        0.001+00 S'.851+06 1.08+086            0.001+00  1.291+07    0.003+00    1.011+07 It Tc-I9s      2.74+00 7.1641+00 -. 903+01            0.001+00  1.143+02    4.2U+00    5.021+03 191l-103        8.321 080.001+0: 2.921306              0.001+0    2.U11+07    0.001400    5.701+08 20 a-106-        2.3810 0.001i0 -3.901+07N              0.001+00  5.971*08    0.001+00    1.481+10 21 4-llb        1.52 7 -I;U43+07 t.72E+06.              0.001+00  2.741+07    0.001t00    4.031t09 22 5S-124      1.541+08 12.(11+06 - 6.2107-            -3.501+05  0.001+00    1.351+08  3.111+09 23 S-125        2.141408 2.341+08' s.0U17              -2.051+05  0.001+00    1.688+08  1.6o39 24 Te-127z      5.521+0t 1.983+08 6.581+07              1.311+08  2.241+9    0.001+00    1.371+09 25 Te-129a      3.621+08 1.341+08 5.731+0?              1.171+08  1.511+09    0.001+00    1.361+09 2681-131 - 7.891407- IMIt8 .5.783.0? 3.141+10 1.81+O8                          0.001+00    2.131+07 27 1-133        1.941+08 3.291t0 1,1.001+06 -;L91+08 5.771+06                  0.001+00    2.491+08 2S Cn-134      .7.1019 -. 61+10 7.7s51+0                0.001+00 5.311+09    2.031+09    2.081+0 29 C-l3t -4.361+07          1.72E1+8 -1.161+08 0.001+00 9.3M+07              1.(1+07    1.391+07 30 Cs-137      1.011+10 1.351+10 4.691+09 0.001.00 4.591t+9                    1.781t+9  1.921+08 31 a-140    . 1.381tO8    1.69+05      6.901+0t      0.001+00  5.141+04    1.141+05  2.133+08 32 La-140      1.811103    J.W+02        2.361+02      0.001+00  0.001+00    0.003+00  5.101+07 33 Ce-lU        2.83+01      1.891+05    2.1T+04        0.001+00  6.901+04  0.001+00    5.411+08 34 Ce144        5.271+07 . 2.181+7    -2.83Ul06      O.O01O+O0  I.301+07    0.001+00    1.331+10 All saelides (ewept 1-3) calculated per DC equatlon 2.3-26 9-3 calenlated per ODIC    iqutlon 2.3-29
 
        -BeavNer Valley Power Station-                                                  .
Tule  -                                                                                            Unit:            Level Of Use:
1/2        I    In-Field Reference ODCM: GASEOUS EFFLUENTS                                                                            Revision:        Page Numbe.;
              .
* _                              1          -      96of 12R ATTACHMENT J Page 8 of 19
                                      -P&I ORGAN DOSE FACTORS Tible 2.3-9 I VAL0S "1 Bum U1,19LSIT!
fit  aeter-ta/yr pewrC11sec) athw-ay VegetatWoR 4ie 6roup Child fElide          ; 6OC        Liver    7. D*      Tkyld        [Idaer        Lug      C-I-W 1 1-3          0.001+00  4.011+03    4.0113      4.01103    4.011+03  4.011+03    4.011+03 2 1-32        -3.371+09    1.58108- 1.301X0        6.00100o    0.001+00  0.001C00    1.321407 3 Cr-St        0.001400 0A.001+00 1.171+O          6.501+04 1.718104      1.191+05    6.211406 4 KA-54        0.001+00 -. 651+06 1.m710        .6.001+oo -1.861t08      0.01+00    5.581+08 5 1-59          3.961+08 6.431+08, 3.201*d0        6.001+00    0.001+00  1.7108      8.70101 6 Ca-ST        0.001+00  2.991+0      .041+07    0.001+00    0.001400  0.001+00    2.MU1+05 7 Co-58        0.00+00    6.41+O7-    1.91t08    0.001+0M    0.001+00  0.001+06    3.71+0S I Co-60        0.001+00' 3.111+1      1.121O+0. 0.001+00      0.001+00  0.001+00    2.101+09 9 5 -65        8.131+01  2.171+09    1.351+09    0.001+00    1.361+09  0.00140    3.601+08 O b-9S6        0.001+00  0.521+05    2.1t1+06    0.001+00    0.001+00  0.001+00    2.911+07 11 Sz-BS      .M3.601,10    0.001+00    1.031+09    0.00&deg;+00&deg;0.001+00      0.00+00    1.391+09 12 Sr-9O        1.2U1t2    0.001+00    3.151+11    0.001+00 -0.001+0      0.001+00    1.71+10 13 T-91          1.661+07  0.001+00    4.991+05    0.001+00 0.001+00      0.001+00    2.411+09 14 Ir-95        3.861+06  5.411+05    7.551+05    0.001+00 1.211+06      0.001+0    5.8151+08 1531-95          4.111+05  1.601+05    1.11+05    0.001+00. 1.501+05    0.001+00    2.961+08 16 1-97          3.651-06  1.59147      3.081-07    0.OM1+00 7.311-01 0.001+00 2.031-01 7No-99          0.001+00  7.711+06    1.911+06    0.001+00 1.651+0M0.0t010 6.381+06 IS Ye-S9        4.711+00  9.2u4100    1.531+02    0.001+O  O 1-.3U402 4.691+00 5.261+03 19 h-103        1.53t+07-  0.001+0      5.901+06    0.001+00 3.613+07 0.001+OO3.971+06 20 h-:106        7.45108+/--- 0.001+to    9.t301+7    0.001tOO .1.011+09 O.01+00 1.161+10 21 h-11h        3.211+07  2.171+07 1.731+07 0.001+00 4.041+07            0.001+00 2.561+09 22 S-124    -    3.521+06  4.511+06 1.231+08 1.77105, 0.001+0              1.951+08 2.201+O9 23 Sl-125        4.911+06  3.851+06 1.051+08 4.631+05 0.001+00            2.1+1 M.        1.191+09 24 to-127a'      1.321+09'    .561+08 -. 571+06 3.1+08 M.171t9                .OO      1.071+09 25 1e-129z      8.411+06  2.351+0 - 1.311+08 .2.7i1+08.-2.471+"L          6.001+00 1.031+09 261-131          1.431+08  l.U41OWI    6.1t7+07 4.761+10 2.361+08        0.001+00    1.281+07 2 1-133          3.531+01    4.371+06    .1:651+06 't.121+08 7.281+06      0.001+00    1.781+06 28 Cs-131        1.61+10'  2.631+10    5.551+09 O.001+00 8.151+09        2.131+01    1.421+08 29 Cs-136      .8.241+07  2.m2+06      I.4T1+01 0.00+00 -1.211+08        1.801+07    7.9e1+06 30 Co-13T        2.391+10  2.291+10    3.381+09-'t.001+00 7.461+09        2.681+09    1.431+08 31 k-140        2.171+06  2.4n+07 I.'1.2+7        0.001+00 7.891+04    - 1.451+05    1.401+01 32 U-140        3.251+03    1.131+03 3.831+02      0.001+00 O.It1+00      0.001+00    3.161+07 33 l -4 6.561+05            3.271+05 -4.86+05        0.001+00 1.433+05      0.001+00    4.081+00 34 Ce-111        1.271+08: 3.981+0M 6.781+06        0.001+00    2.211t07  0.001O      1.041+10 I11 suolides (except 1-3) 'ieaclated per OD equatio 2.3-26 1-3 calculated per OD0equatioa 2.3-29 L
 
      .      Beaver Valley Power Station                                                  -        -          e!un7 iODC-2.02 Unit:            Level Of Use: Reeec
  . . -> : -      .                                                                                          1/2            InField Reference ODCM: GASEOUS EFFLUENTS                                                                                  Revision:        Page Number.
                  . .. . -                                                                                    197                    of 198 ATIACHMENT J
                                                    .. Page-9 of 19 P&l ORGAN DOSE FACTORS Table 2.3-10 1 tAM'1ISF      UA WMIDWLLE      SIR!
og weter-uJeyr per vCI/sec)
Pathway    Neat Ae group: Adult Euclide            Boat        Liver          A.      thirold      lideuy      lang        l-lul 1 1-          .O.001o00      3.251+02      3.251*02    3.251*02    3.251+02  3.251*02    3.251+02 2 P32          3.151*01      2.461+08      1.133+06    0.001*0V 6.001+00      6.001*00    4.441+08 3 Cr-SI    r-0.00100        0.001*00      5.681+03    3.501*03 . 1.291*03    7.781*03    1.471+06 4:  -h54 o0.001*00,. 0.491*              1.241*8    6.001+00    1.931406  0.001+00    1.991+07 Se-59      ' 2.i4+08 5.041+08            1.+1*08    0.001*00    0.001+00  1.411+01    1.681+09
                      - Ce-57        0.001+00    - 4.011+6      t666S56    0.001*00oe.001*00      0.001*00    1.021+08 7 Co-So        0.001*00 .1.421+07          3.18+017  '0.001*00      .001+00  0.00140    2.81*8 8 Co-a        .0.00100      S.121+07 1.3I+08. 0.001+00            1.00t+00  8.001+00    9.411+08 911-85        2.541*08      M.UM1+08    3.U.08- 0.001+00        5.411+      .001*00  5.101*08 1a              0.001+00      4.111+08      1.921*0    0.001+00    0.001*00  0.001*00    U.11+07 11 Sr-U9        2.411+08      0.0010        6.921+06    0.00100    0.001+00  0.001+00    3.071+0?
12 Sr-90      .1.411*09      0.001+00      2.081*0    0.001+00    0.0010oo  0.001*oo    2.431*08 13 T-91        8.9405        0.001*00    .2.39104    0.001+00    0.001*00  0.001*00    4.921*08 14 Ir-95        1.471*+0    4.711+05      3.131+05 .0.00140      7.391+05  0.001+00    1.491+09 15 lb-s5        1.891+06    1.051+06      5.W41+05    0.01+0      1.04*06  O.001+00    6.371+09 16 lb-97      ttt$tt$t$t$*St        Stt***Ui*        0.001*00              o.00100tsStststts 1l Ho-99        0.1+00        8.511+04 1.121+04        0.001*00    1.931+05 .0.001.00 1.971+05 16 Tc-99a - 3.631-21          1.OBI-20 .1.361-19        0.001*00    1.641-19 5.301-21 6.401-18 1i h-103 -8.571+01            0.001+00      3.093+07    0.001+00    3.271+08  0.001+00    1.00110 20 h-106        1.911*09        o 0.001+00      2.491+08    0.001+00    3.801+09  0.00t+00    1.271*11 21 g-li      *. 4.771+06      4.411t0t      2.0621t0l  C.0OMO1  . 8.671N06 0.001+00      1.801+09 22 Sb-12        0.001+00 .0.001+00.        0.001*00  0.001+00 0.001*00 .0.001+00        0.01+00 23 Sb-125, 0.001*            0.001+00      0.001+00  0.001+00    0.001*00  0.601+OO    0.001+00 24 ,1-127ls 6.381+68 3.001+08                1.021+08  2.141+08    3.401+09  0.001+00    2.11*09 25 Te-129& 9.331+08 3.41UM                    M1.UM06  3.2M1+06    3.891+09  0.001400    4.701*09 26 1-131 , 9.131+06            1.311*07      7.481+06    4.281+09, .2.241+07    0.001+00  3.451+00 2.1.133      -3.121-01        5.421U-1      1.051-01    7:961+61 9,481-01. 0.001*00    4.871-01 28JC-134        4.531+08      1.401*09    .3.51106    0.001+00    3.4t1n06  1.161*08    I.891+07 29 Ca-13        -1.021+01 4.041+0? ,2.911+07 - 0.00OMO0 .2.251+0? , 3.081+06 4.591+06 30 C-137          5.i01*08    8.041+8    '5.281t*0    0.001+00    2.741+08  9.101*07    1.581to7 31  h-140        2.44+07 '3.0U414t          1.6016      0.001+00    1.041*04  1.751+04    5.021+07 32  La-10      -3.161-02 1.151-12          4.211-03    0.001*00    0.001*00  0.001+00    1.171+03 33  Ce-141        1.161*04 .;f7.831s3        8.681+02    0.001*00    3.1+03    0.001+00    2.91*07 34  Ce-144        1.031+06 4.321+05          5.551l44    0.001*00    2.5610+05  0.001i0    3.501+08 All nuclides (aex Ft i-31 calculated per OD4H          equatior 2.3-25.
1-3 calculated per OD1 equation 2.3-30
 
I                Numbe
        -Beaver-Valley
 
==Title:==
Power Station                                                Pcedure Uo~~It c
I&2ODC-2.02 ce fUe 2
Tiltle.:                                                                                            Unit:            Level Of Use:
                                                                                                        .1/2            In-Field Reference ODCM:. GASEOUS EFFLUENTS                                                                            Revision:        Page Number-ATTACHMENT J Page 10 of 19 P&l ORGAN DOSE FACTORS Table 2.3-11 IALIS m 101 BUi          ul nLIT SITE (aj mter-arus/yr per sCI/sec)
Patkbay Neat 4g Groep = Teel s1cide          etoe    Liver    t. Body    Tioid        Kidney      kg        GI-LI t 1-3          C.OM1M      .141.02    1.9U+02    1.941+02    1.141*02  1.MUM12      1.941+2 2 1-32        3.34109;    2.01*08    1.291+08    0.00100    0.001o00  0.001o00    2.51#0O 3 Cr-sI      0.001+00    0.001*00    4.691+03    2.t01*03    1.031*03  6.691+03    7.I+05 4 -54        0.001+00e  4.951+06    3.t11+05    0.001*00    1.481m+    0.001+00    1.611+07 5 J*.59        1.11*08    4.001+08    I.541+08  0.001+00        0tOO  1.261+08    9.451+06 6 CO-S        6.001+00. 3.221+06    5.401+06    0O.01+0O    O.001+00  0.001+00    6.011+07 7 Co-56        0.001+00  1.091+07    2.521+07    0.001+00    0.001+00  0.001+00    1.511+08 I8co-O        06014+0 '  3.7+07      8.951+01    0.001+00    0.001+00  0.001400    5. 171+08 9 h-Os        17.T1+0    6.211+08    2.901+0h    0.00100    3.971+08  0.001+0      2.o631+0 10 b-D6          0.001+00  3.431+08    1.611+08  0.001+00      .001+00  0.001400    5.081+07 1  Sr-H        2.031+8    0.001+0      5.831t+0  0.001+0    0.0010    0.001+00    2.421t*O 12  Sr-so      5.441+9    0.001+00    1.341+9    0.001+00    6.001+00  0.001+00    1.531+48 13  7-91        7.531+05-  0.01+00    2.021+04    0.001+00    0.0010    0.001+00    3.031+08 14  Zr-9S      1.181+06  3.711+05    2.551+05    0.001*00    5.4515    0.001*00    8.561+08 15  lb-S        1.471+06  6.1715      4.501+05  0.001+00    7.921tO5  0.001+00    3.491+09 16 lb-97      *sttttttsstteet          tte+++  ttt 0.001 0 $Oestis.s0.00100 stsesmsssts 17Ho-9l        0.001+00 7.033+04 1.3d414 0.001+00 1.611+05 0.001+00 1.261+05 18 Tc-99a      3.041-21  8.481-21    1.101-19    0.00+00    1.261-19  4.711-21      5.573-18 19 b-103        8.9e107      .001+00    2.181+07    0.001+00    2.481+08  0.00100      5.83109 iOLi-l06        1.281+O'  0.0C1+00o    2.091+08    0.001+00    3.191+09  0.001+00      7.9d+10 21  ig-llk      3.611+06    3.421+086  2.08t06    0.001+00    6.521+0  0.001+00      9.601+*6 22  Sb-124      0.001+0    0.001+00      0.001+00  0.001+00    0.001+00  0.001+00      0.001+00 23  Sb-2      .0.001+00  02001.00    O.00100    0.001+00    0.001+00  0.001+00      0.001+00 24  te-1271    7.071+08  2.511+06    t.411+07    1.681+08    2.871+09  0.001+00      1.78*09 25  Te-129u    7.821+08  2.901+08      1.241+08  2.521+08    3.271*09  0.001+00      2.931+09 26 1-131        7.591+06    1.061+07    5.711+06  3.101+09 1.831+07      0.001+00    2.101+06 27 1-133        2.611-01    4.421-01    1.351-01  6.17T+01 7.751-01      0.001*O0    3.341-01 28 Co-134      3.601+08    1.48148      3.931tO8  *.001+00 2.691+08      1.031+08    1.051+0t 29 Cs-136      '7.98106    3.141+0T      2.1INT    0.001*00 A1.711+07    2.691+06    2.531+06 30 Ce-137        4.901+08  6.511+08    2.271+08  0.001+00 2.221+08      0.611+07    9.271+06 31 h-140        2.021+07  2.47104      1.301t06  0.0010      6.381+03  1.661+04    3.111+0o 32 LA-140        2.601-02  1.281-02    3.401-03  0.001+00    0.001+00  0.001o+0    1.331+02 33 Ce-l41        9.721+03  6.491+03    7.461+02  0.001+00    3.041+03  0.001+00    1.861+7 34 CU-144        0.721+05  3.e11+05    4.61+04    0.001+00    2.151+05  0.001*00    2.191+08 111 auclides (except 1-3) calculated per ODCM    equation 2.3-25 3-3 calculated per ODCH  egatlom 2.3-30
                                                                                                                                            '-1"
 
Pmocedure Number.
Beaver Valley Power Station                                                                    Unit          1I/2-ODC-2.02
.T-I.                                                                                                    Unit:            lZvdI Of Use.
1/2            In-Field Reference ODCM: GASEOUS EFFLUENTS                                                                                Revision:        Page Number:
t.,      : .                                                                                  199                    o~f 1?R A1ITACHMENT J Page l of 19 P&I ORGAN DOSE FACTORS liSle 2.3-12 It      sluS1fulniu=      AL sin (Sq iettr-are/ylr per vC11/ec Fatbsy: Heat 4t Group CSild luclide          lose        iver      T. od      Thyirold      Klidty      Uast      Cl-LLI 1 1-3        0.00100      2.3u412+0    2.341+02      2.341s02 12.341*2      2.341+02    2.341+02 2 ?-32        6.291*09    2.9,1*08 2.431+0          0.001*0 0.001+00      0.001+00    1.141+0
                    .3C-SI        ' o.001+0      o.001+00 1.311 3          4.0861o03 -1.11+03    7.411+3      3.881*05 4          0.001+0 ME-SM      5.s681+0 .1.511+08        0.001+o0.o 1          0.001+00    4.751+08 5 fe-S        3.041*08 -4.911*08          2.451+M    0.001-00    0.00100    1.U21+08    5.121+0 6 CO-sT        0.010      4.211+06      6.521s06 A.001+00        0.001+00  0.001+00    3.451+07 7 Co-        0.001*00    1.281s07      3.911+07 '0.001*00      0.001+00  0.001+00    7.451+07 8Co-60        0.01+00    4.721+07      1.391+08 0.00100        0.001+00  0.001+00    2.611+08 S Zn-s        2.881+0    7.151#48  '  4.441+08 0.001+00      4.501+01  0.001+00    1.251+08 1o 38          0.001+00    4.81+06      2.991+08 0.001+00      0.001+00  0.001+00    3.131+07 11 3:49        '.5108 .0.001+00o-1.101+07              0.001fo0    0.001+00  0.001+00    1.491+07 12 Sr-S0        7.031+09s '.0010          1.181*09    0.001+00    6.001*00  0.001*00    '.47107 13 -91          1.421+06 0.001400 "3.811+04            0.001+00    0.001+00    0.001400    1.901*08 14 Zr-9S        2.091+06 4.551+05 4.091*05:            0.001+0    6.51t+05    0.001+00    4.791+08 15 lb-9S        2.541*06 0.101*05 7.071+05            0.001*00    1.301+05    0.001*00    1.131+09 I6 ib-97        * .;**outss.*;q              iss      0.001*0t ts$t**8aS:    0.001*00 ttmtut**2*
17l-99          0.001*00    9.7s91+04    2.4UM1*0.001+00 2.091+05            0.0010oo 8.091*04 1 Ic-99S        5.331-21    1.051-20      1.13-19 0.001*00        1.521-19  5.311-21 5.951-18 19 h-103        1.281+08    0.01+00      4.851+017, 'O.001*00    3.151+08  0.001+00 3.281+09 20 h-lo6        3.111+09    O.001*00      3.891*08 0.001+00    o  4.211+9    0.001*00 4.6351*10 21 4-110i      5.991+06    4.041*08      3.231+06    0.001+00    7.531+04  0.001+00    4.811*+
22 b-124        0.001e00    e6.001+00    0.001+00    0.0o00+0    0.001+00  0.001+00 0      .001+00 23 9b-125      0.001w00 0.001*00          0.001*00 '0.001*00      0.001*00 0.00*+00      0.001+00 24 Te-1217    '1.331+09 i3.591*08          1.581+0-    3.191+0t    3.801+09 -0.001*0      1.001+09 25 Tt-129a      1.471*09 4.111+08          2.238      4.7510        331e09 0.001*00      1.801+09 24  1-131        1.411*07    1.2OW 8.0,106 4.091+0                  2.321+07 0.001*00      1.281+08 27  1-133    :4.841-01      S.99-01 2.241 1.111+02                9.98141 - 0.001+00      2.41141 28  Cs-134    -6.351+08      L.04*09 2.201+03 9.001+00              3.231+08 1.181+08      5.821+06 29  Ce-136      1.381*07    3.781+07e,2.451+07 -0.001+00          2.011+07 3.001+06      1.331+06 30  Ce-137      9.02108    6.6 0os I.m2 08 0.001*00              2.811+08 1.911+08      5.401+06 31 h-l(O        3.721+07 3.261*06 '2.171*T06 0.001+00              1.081+04    1.341*04    I.891O7 32 L-14O        4.761-02 1.661-02 5.611- 0 0.001+00                0.ole00    0.001+00    4.631*02 33 ct-141        1.131*04 9.131W03 1.3681+4 0.001+00                4.001+03    0.001+00    1.141*07 34 Ce-144        1.641+08 5.151*05 '3I.M7+4 0.001+00                2.851K5    0.00M+0      1.3U438 Il uncldms (eeept 1-31 calcuhlted per ODCtf          eqoatloe 2.3-25 1-3 ca1lated per COCK      equtiot 2.3-30
 
UL-
        ;Beaver    Valley Power Station -/                                                              Il Procedure Number:
                                                                                                - .2-ODC-2.02
            ./-DC20
 
==Title:==
uni              I Level Of Use:
I/                In-Field Reference Rcvis~ion          PagecNumber.. -
ODCM: GASEOUS EFFLUENTS                                                                                                                                  ,..)
A        I          I        1OO of  12R AITACHM!ENT J Page 12 of 19 P&I ORGAN DOSE FACTORS Table 2.3-13
                                                  ;I YALUI 11 4111m      fLL1 Siltl (ag mter-ara/r per UCI/nC athway- Cow ilt A4 roup -dult Iodide    . Eow          Liver .,T. Body      Thyroid        1Idey            L          61-11 1 1-3        0.001+00      7.631*02    1.631+02    7.631+02    7.631+02    7.630+02        .31+02 2 1-32        1.45    0.,"9.011*0        5.601Cum    0.001+00    0.001+00    0.001+00      1.631+09 3 Cr-51      0.00100 '0.001+00t        2i.381+04    1.421+04    5.24+03      3.151+04      5.961+06 4h-54        0.o1+0        5.951+06    1.131+06. 0.00100        1.m11+06                    1.621*07 5 1e-59      2.401+07      5.631+07    2.1651+07, o.0ot+oo      0.001+00 1.511+07          1.661+06 6 Co-s7      0.001+00      9.101*05      I1J+06    0.OM+        0.001*00 0.001+00          2.311+07 7 Co-58      0.001+00      3.6106,5      8.221+06  0.00100      0.001*00 0.001t00          7.431+07 a CO-60      0.001+00        1.121+07 . 2.461t01    0.001*00    6.001+00 0.001+00          2.101+08 9 Z-65      1.601+08      3.121+09      1.411+09  0.001+00    2.091+09 0.001+00              .96o09 10olb-6        0.001+00      2.191*01      I.021tO9. .0.001+00    0.00100 0.001+00            4.321*08 lI It-1g        1.181+09      0.001+00      3.331+07  0.001*00    0.00+0      0.001+00      1.6810 12 Sr-90        3.161+10      0.00i+00      M.61+9    0.00100      0.001+00    0.001*00      9.141+06 13 !-91        6.781+03      e0.001+00    11.11+02    0.001+00    0.001+00    0.001*00      3.721+06 14 r-95        7.tO+02.      2.371+42      1.611+02  0.001+00    3.721+02    0.001+00      7. 521+05 15 Ib-95      8.771+04      3.771+04    2.031+04    0.001+00    3.721+04    0.001+00      2.29Mto+
16 lb-91    -  2.811-12    . 7.111-13      2.601-13  0.001+0      8.301-13    0.001*00      2.621-09 17 Io-99      e0.00104      2.1117        4.011+06  0.001+00      .771*07    0.001*00      4.631+07
              -      I Tc-99.      2.631+00      7.991t00      1.021+02  Q.001+00    1.211+02    3.9100        4.731+03 13 6-103        6.291+02      0.001+00      3.571t02  0.001+00    3.161+03 0.001foo          9.681+04 20 h-lN6        1.431+04      0.MONOl 1.511t03        0.001+00    2.T71+04 0.001+00          9.271+05 21 Ag-110      4.161t+        3.641+07 2.281*07 0.001+00 7.565+07              O.001+00      1.571*10 22 lb-124      0.00100      0.001+00 0.0ONOlO0.001+00 '.001+00.                0.001+00      0.001+00 23 Sb-25        0.001+00      0.001+00. 0.001+00 0.001+00 0.001+00              0.001tOO      0.001+00 24 ho-127l      3.1.4,17 1.231+0T          4.191*06 6.791+06 1.401+08 : 0.001+00                1.151+0 25 Te-129      4.951+07      1.851+07      M.U1M06 1.701+017 2.0T1+06 0.001400                2.491*06 2u1-131        2.521+06      3.601t6t    2.061+08  1.161*11 6.171+06        0.001+00      9.501+07 a
271-133        3.291+06      5.72m16      1.751+0    6.411+0      9.991+06    0.001+00      5.141+06 28 Co-134      3.891+9        9.271+09    7.58109    0.001N00 3.001t09        9.981*08        1.621+08 2SC-136        2.231+08      B.621*0M    6.351*06  0.001*00 4.911+06        6.731+07        1.0010+6 30 C.-137      4.991*09      6.621+09    4.471*09    0.001*00 2.321+09        7.701+0        1.321*06 N
31 B-140        2.281+07      2.871+04 . 1.491+06    0.001+00      9.741+03    1.641+04      4.10107 32 La-l4O      3.641*00      1.9330o I 5.1114-1 0.001+00          0.001+0    0.001+00        1.421U05 33 Cc-ll        3.991+03      2.701+03 :3.061+02. 0.001+00          1.251+03    0.00+00        1.031t07 34 CO-144      2.541+05      1.061+05 1.3614 O.      0.00*00      6.291+04    0.001+00        o.51o07 Ill uciides (except 1-3) calculated per ODCI          equutlon 2.3-24 0-3 ealeulated per ODCI      equatios 2.3-28 +                                                                              . d
 
Beaver Valley Power Station                                                                                          5:-2um it,
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I            I                1()1 of 12%
ATTACIRMENT J Page 13 of 19 P&I ORGAN DOSE FACTORS I    ble 2.3-14 I 11335 101 1111 ALLIT SITI (a meteir-reall PrwtC ec)
Weatha Cow    Milk VeGroup Te=e oldide          lOe      LiLer      T. loy      Tb1rold                                    C1-LU Il-3          0.001+00  S.141+2      I.4*02      5.941+02    1.34t02      3.94+02        9.141+2 2 P-32        2.671+10  1.81+*09 '0I.41+09        0.001+00 ' O.0100        0.001*00        2.251+09 3 Ct-SI        0.003+00  0.001+00 4.151+04        2.311*04 1.101+03        5.331*4t        8.171S0 0.001+00  9.9106 1.961+06          0.001+00 2.151+04        0.001*00        2.031*01 5 fe-59        4.181+07  s.751a7 3.M771            0.001+00 O.Ot1+00        3.011+07        2.311+08
                  &Co-57        0.001+00  1.l01l06    2.681+06    0.001+00    0.et+00      6.0010oo        2.981+07 ICo-58        0.001+00  6.171+06    1.421+07    0.001+00    0.001+00      0.e01*00        5.511*07 8 C-tO        0.001+00  l.691*07    4.261+07    0.001+00    0.001t0o      0.001*00        2.461*08 9h-tS        1.511+09  5.231+09    2.441+09    0.001+00    341U*09      0.001o00        2.211*09 10 Rb-96        0.001+00 '3.991+09      I.87109    0o.001+00  0.001*00      0.001+00o      5.911+08 I lt-S9        2.141+09 0.001+00      6.121t07    0.001+00    0.001+00      0.001*00        2.551*08 12 St-N0        4.411+10 0.001tO0      1.101+10    0.001+oo    0.001+00      6.101*00        1.251*09 IJ 1-91        t.251+04 0.00*0O        3.351+02    0.001+00    0.001+00      0.0o1+00        5.111*06 14 Ir-S9        1.291+03 4.081+02    . 2.811+02    0.001+00    6.001402    0.001+00        9.421+05 S15-95        1.161+05 6.41134        3.531+04      .001+00  6.211+04      0.601+00        2.ut+08 16 lb-91        5.131-12 1.271-12        4.051-13 0.001+00 1.491-12 0.002+00                  3.041-0 17 10-t9      0.001*00 3.601*07      7.251+06 0.OOtOO 8.101+07 1.001+00                    6.811+07 18Ic-991      4.101+00 1.371*01          .171+02 0.001+00 2.041+02 7.591+00                  8.181+03 19 lau-10      1.471*3 0.001*00        6.301*02 0.0010          5.201*03 : 0.001e00          1.231*05 20 u-l10O      2.031*04 0.001*00        3.321+03 0.001*0 5.01+04 0.001+00                      1.261+O6 21 4g-110      6.871#07 6.501*07        3.951+07    0.001+00    1.241*06      0.001+00        1.831+10 22 Sb-124      0.00t00 .0.001*00        0.001+00    0.001+00    0.001fOO 0.001*00            0.001*00 23 S-125        0.001+00 0.001+00        0.001*00    0.001+00    0.001+00 0.001+00            6.001*00 24 Te-127e -5.341+07 2.251t*7              .641+06    1.511+07    2.5n+08 .0.001+00            1.561+0B 25 le-129a 9.061+01 3.361+0              1.431+07    2.921+07    3.731+09  . 0.001*00          3.401+08 26  1-131      4.511+08  6.391+08    3.431*08    1.11+11    1.101+09      0.001+00        1.2f1+08
                '27  1-133      6.011*08  1.21*07      3.111+06    1.421+09    1.791*07      0.001*00        7.711+06 26  CA-134    -6.761*09  1.591+10    7.38109      0.;00+00    5.061+09      1.131+09        L.981*08 2g  Ce-136      3.801*08        1.501 0 1                  O 0.001+00      .151408      .261*08      1.201t08 30  Cs-S37      1.051+09  1.201+10 4.191+09        0.001*00    4.101*09      1.581*09        1.711408 31 ib-140      4.121*07, 5.1S1*04      2.651+06    0.001+00    1.711+04      3.391+04        6.351+07 32 L140        6.891*00  3.391+00 9.611-01        0.001+00 0.001+00        0.001+00        I.S41*05 33 Ce-141      7.321+03  4.691*03 .5.621+02        0.001+00 2.301+03        0.001+00        1.401tOt 34 Ce-144      4.071+05  1.931+05 2.511+04        0.001+00 1.151+05        0.001*00        1.171408 111taveldes (except 1-3) calculated per ODC0        equatiou 2.3-24 1-3 calculated per 0008 equation 2.3-28
 
Beaver Valley Power Station                                                            I              Num br 0 Titk:                                                                                            Unit            Level Of Use 1/2            In-Field Reference  .
ODCM: GASEOUS EFFLUENTS                                                                          Revisiao:        Page Numb=c
                                                                                                .      1                102lofl12R AITACHMENT J Page 14 of 19 P&I ORGAN DOSE FACTORS Table 2.3-15 I T*i Sol 701        VILLIT SITU (q Meter-trii/yr per ud/seo) tatbny- Co 111k 4geCroup C1ild
                    - eilde            We      Liver    7. Body    Timoid        1idoey      Lu        Cl-LLI 13-3            0.001*00  1.57i*03    1.571t43 1.5sn o3 1.5s1n03        1.571O3      1.57t1*3 2 7-32          6.5911+0  3.011*09    2.541*0 70.00103        .00140  6.0010      1.Z1*09 3 Cr-Si        ,0.00*00  0.001e00    8.46144 MUM0104        1.2104    6.5811*4    4.4S106 411-54          0.001*0  1.481*07    3.151*06    0.001*06 4.161*0      0.00tM      1.2407 5 IL-59        M.7O0T171.51*08      7.121*4    O;001*0t0.001*00 4.551*07          1.631*08 lc-si          0.001*00  2,731*+0    5.521*08    0.001 oo          66001e00 0.001*06    2.21*07 Co-53        0.00100    .431*06  2.891*07    0.001*00    e.00100  0.001*06 5.501*07 I Co-60        0.001*00  2.s41*07    S.P1*07    0.001*00    0.001*00 0.00100 1.631*0                                Y, 'I 9 ze-6s        2.95109  7.6t1U09    4.891*00    0.001*00    4961*09 0.001*00 1.381e09 e0w s6          0.001*00  7.401*09    4.551*09    0.001*00    0.001*00 0. 1OO*04.761*0 1 gr-9          5.291*09  0.001*00    i.s5108    0.001*00    0.001+00  0.001*0      2.051*08 12 Sr-9O        7.551U10  0.01+*00    1.911+10  0.001*00    0.001*00  0.001*0      1.021*9 13 T-1          3.081+*0  0.001+00    8.241+02 0.001*00      6.00100 0.00Koe        4.113+04 14 Ir-95        3.001*03  6.601*02    5.88*02 0.001*00        9.45102 0.001*00      6.691*0S 15 lb-95        2.611*05  1.021+05  7.26104K 0.0000        1.54104 0.001*00      1.881 It 397          1.251-11  2.251-12    1.051-12  I.0o00o0    2.501-12  0.00Kt      0.941-07 11 KO-I99        e.oel+00  8.92tt07    1.711#0    e4.elGo    1.4Ut#t  0.001*0      5.721+07 18tc-99o          1.121+01  2.201+01    3.151*02  0.001o00 3.20102      1.121*01    1.291*04 19 h-103          3.491*03  0.00100    1.341+03  0.001*00 e      .781*03 0.001*00    9. 01104 20 h        6.49104    0.001O0    8.10143    0.001*00 1.768104    0.001+00    1.011+6 21    4-k1.      1.491*08  1.011*0t 8.051*07      0.001*00 1.87108      0.001+00    1.2Nl10 22  &124        0.001*00  0.00o 0 0.0010        0.00KMtoo 0.001+00    0.0o1t00    0.001*00 23  5b125        0.001*00  0.00KtO    0.001*00  0.00KM0C o0.001*00    0.001*00    0.001*00 24  To-12i% 1.561*08        4.211*07    1.861+07  3.741+07    4.461*+8  0.001*00 1.271*08 25  T-129s        2.231+08  6.241U07    3.471*07  1.201t0    6.581*08  0.001*00 2.721*06 21.1-131          1.11109  1.11109. 8.331+08  3.881*11    1.831*09 0.00tM      9.321*07 27 1-133          1.4U+*07  1.811*+    6.91+*06  3.361t0    S.011107  0.00KM0o    7.281+06 23 C-134          1.56110  2.561*10    5.401*09  0.001*00    7.931*09  2.651*09    1.381*06 29 Ca-136        8.581*06  2.361*09    1.531*09  0.001*00    1.281*09  1.71*0      8.291*07 30 Cb-13t        2.161+10  2.091*10    3.081*09  1.001+00    6.601909  2.451*09    1.311*06 31  h-140      .9.941*07    t.7*OS    5.60lf    0.001*06    2.641*04  5.19104    5.041*07 32  La-140        1.651tO1  5.771*00    1.941+00  0.001+06    0.001*00  0.06KM      1.611*05 33  Ce-141        1.601+04  0.991*03    1.341*04    0.001*00  3.94su03  0.001*00    1.121t07 34  Ce-i44        1.151+06  3.611*05    6.151*04    0.00Ko    2.001+05  0.001o00    9.411*07 All  ouclides (eocept 1-3) calculated per ODCI  equatiou 2.3-24 8-3 calculated per ODM equation 2.3-28
 
                                                                                                  .Proicedure      Number~
Beaver Valley Power Station.                                                  .                            1/2-ODC-O20
  'File:  -.                                                                                        Unit              Level OfUse 1/2              In-Field Reference ODCM: GASEOUS EFFLUENTS                                                                            Revision:        Page Number
                        . .        -..                                                                . 1            -      103Of 12.%
ATTACHMENT J Page 15 of 19 P&I ORGAN DOSE FACTORS Table 2.3-It I IALOIS 1 Da VIWALLET        SIm (st meter-area/r per 4CI/gc)
                      ?atbayi Cow      Nilt Ag4OrouP Sdfuat halidce          Ioon      Liver      1. Boh    Throid          i~der      Lag 6 I-UI 1-3          8.001*00 2.381*03        2.381*03  2.391tO3. 2.381t03    2.381t03    2.381*03 21-32          1.381+11: 7.299149      5.m27109    0.601*00 0.00o*t0      0.001+00    1.t4109 3 Cr-Sl        0.001*00 0.00100          1.141*05  8.151*04 1.911t04      1.701t05    3.911*06 4 II-N        .0.001*00 2.76*07          6.251*06  04.60000 8.1t1*08      0.001400    1.011*01 5 1.-H          1.811*08 3.l Inea        I.tl1*O8  0.101*00 0.001400      9.351*07    1.511+08 Co-s7        0.001*00  .6.36106      1.031*01  0.801*00    0.002*00  0.001040    2.171+0T 7 Co-SO        0.001*00    1.89107 4.701+07        0.001*00 0.001*00      0.001+00    4.71*+07 a Co-sO        0.001*00      .003*07 1.421*08      .0.W0100 -. 001*00      0.001*00    1.431*08 9 la-S          3.M109      1.361*10 6.21+*09        0.001*00 6.t01*09      0.001*00    1.151*10 10 slB        0.001*00    1.83+10 5.2109          O.0*0oo 0-          0.001*00  0.001*00    4.511*05 It Sr-I          1.011*10    0.001ot0 2.591018        0.001*00    0.001*00  0.001+00    2.01+*08 12 Sr-90        8.221+10    0.001*00: 2.091*10      0.001*00    0.001*00  0.00+*00    1.031+09 13 T-91          5.191*04    0.001*00      1.541*03  0.001*00    0.001*00 0.001*00      4.151*06 14 Zr-95        5.331*03    1.301*03    9.221*02    0.001*00    1.40103 .0.001*0      6.4710+5 15 Ib-95        4.871*05    2.011+05      1.181+05  0.601+00    1.441*05 -0.001+00    1.691+*0 16 lb-97      - 2.111-11 -5.82-12        2.031-12    0.001*00    4.391-12  0.001+00    1.771-06 17 Uo-99        0.001*00 A.MA*0          3;451*07    4.01*00      2.641+08  0.0014*0    5.31+07 18 c-9S          2.341*O01 4.621*01      6.211*02    0.801+00    5.191+02  2.521+01    1.401*04 19 h-103        7.01+803    0.001*00      2.361303  0.001*00    1.4714    0.003*00    1.591*04 201i-106        1.341+05 f0,001*00      .1.71+04 0.001*00        1.581+05  0.001+00    1.011*06 21 li-1O.        2,751*08    2.011+6    :1.331*00    0.001*00    2.881+*0  0.001+00    1.041*10 22 Sb-124        0.001*00    0.o01*00    0.001*00    6.001*00    0.001*00  0.001*00    0.001*00 23 5b-125        0.001*00    0.001+0        .001*00  0.001*00    .0.001+00  0.001*00    0.001+00 24 Te-127.      3.181*08    1.051*01    3.831*07    9.141+07    7.791t08  0.001+00    1.281+08 25 le-129e    A4.58104 -1.571+0          1.061+*7    1.761+*0    1.1510+9  0.001*0    2.70410 26  1-131        2.311*9    2.n2*0        1.201+09 6.951+11      3.183*9  0.801+00    9.21*07 2  1-133        3.0810T7    4.491*07      1.311+07 5.171*09      5.281+07  0.001*00    7.601*06 25  Co-134      2.511*10    4.591*10 4.731+*0        0.801*00    1.211*10  4,951+09    1.271+06 29  C,13        1.681*09    4.931*49 1.841*09 A.01*00            1.971*09  4.021+*0    7.491+07 30  Ce-137      3.48110    4.71*10 -2.691*09 0.001*00            1.091+10  4.431*09    1.271*08 31  A-140      2.051*06 . 2.051*05      1.051+17  0.001*00    4.85144  1.261*05    5.021*07 32  WH-O40      3.45141:    1.X1441      3.501OW0  0.001*00    0.001*00  0.001*00    1.600105 33  Ce-141      3.57*04    2.181*04      2.571*03  0.1OMO      6.721*03  0.001*00    1.131+*7 34  Ce-144      1.651*06    6.751+05    9.253*04. 0.001*0      2.731*05  0.001*00    9.471*0t 111 sucilidee (except 1-3) calculated per ODCH      equation 2.3-24 1-3 clculated per ODOC      equatior 2.3-28
-U
 
      . .... Beaver Valley Power Station
              ..                                                                                  Pe              -nODC    2.02 Irlde:                                                                                              Unit:          Lzvel Of Use:
1/2          I n-Field Reference .
ODCM: GASEOUS EFFLUENTS                                                                            Rcvision:      Page Number.
1                104 ofl w8 ATTACHMENT J Page 16 of 19 P&I ORGAN DOSE FACTORS table 2.3-I7 I lAIs IU M          V1ILLIT 8IT (sq mter/-re/r per iCi/aec)
Pathwy goat Milk Ag. Crc: Adult hll.e            Boose liror        2. hd      Treld y          ldity      bog      Gl-ELI IlS 0.001+00 1.561+03          1.50+03.    .1+3    1510        .6+3      1510 1 F1eno                    .1-o        .i~3    i.Wto0    1.5811+3  1.S01#03    1.561,ea3 2 1-32        1.741U10, 1.081+01      6.1+08    0.001+00 6.003+00    0.001+00    1.961+09 3 Cr-SI        0.0o1+00o 0.009+O00    2.6+3      1.101+03e6.261+02    3.761+03    7.171e5 4 h-54        0.001+00 7.141+05      1.36+05    0.001+00 2.121+05    0.001+00    2.191+46 5 1s.-s        3.1n+05 T.321+05        2.611+05  0.001+00 1.001+00    2.051+05    2.441+06 6 Co-57        0.001+00    1.091+05    1.621+05  o.001+OO  6.001+00  0.001+00    2.7n+08 7 Co-sI        0.001+00 4.401+05      1.611+05  0.001+00  0.003+00  0.001+00    8.911+06 6 Co-GO        0.001+00    1.31+06    2.961+06  0.001+00  0.001+00  0.003+06    2.521+07 9 ha-lS        1.161+08    3.741+08    1.691+08  6.001+00  2.501+08  0.001+00    2.360+06 1o 1-8      ' 0.001+00      2.631+08    1.221+08  0.001+00  0.01+00    0.001+00    5.181+07 11 Sr-O9        2.431+09    0.001+00    6.991+07  0.001+00  0.001+00  0.001+00    3.911+08
                    *2 Sr-so        6.641+10    0.001+00    1.631+10  6.001+00 0.001+00    0.00+00    1.921+09 131-1l          8.141U+2'  0.001+00    2.161+01  0.001+00 0.001400    0.0Nl+0    4.48105 14 Zr-IS        6.M+01      2.851+01    1.931+01  0.001o0 4.411+1      0.001+00    9.02104 Is -ss          8.131+03    4.521+03    2.431+03  0.00t+00 4.471+03    0.001+00    2.741+0?
16 lb-9l        3.381-13    8.54-14    3.121-14  0.001+00 9.90-14      0.001+00    3.151-10 17 1a-9S        0.001+00    2.531+0      4.811+05  0.00100 5.723O6      0.001+00    5.861406 It Tr-9s.      3.391-0t'  1.591-01    1.221+01  o.o01+O01.461+01      4.701-01    5.61+02 19 h-103      :9.951+01    0.001+00    4.211+01  0.001+00. 3.601+02  0.001+00    1.161+0i 20 hlO-1        1.721+03    0.001+00    2.111+02  0.001+00  3.321+03  0.001+00    1.111+05 21 g-1tC        4.991+6  - 4.611+06    2.741+06  o.o01+0o  L.OS+0    6.001+00    1.68+09 22 Sb-12        0.00140    0.001+00 0.00t1O+ 0.0010to        0.001+00  0.001+00    0.001+00 23 55-125      6.001+00    6.003+00- 6.001+00 0.001+00        0.061+00  0.001+00    0.001+00 24 Ts-12.      4.131+06    1.41+06    5.031+05  1.051+0t  1.681+01  0.001+00    1.381+07 25 Te-29.      5.941+06    2.221+06    9.411+05  2.041+06:  2.481+07  0.001+00    2.191+07 26 1-131        3.621+08  1.323+08    2.481+8    1.421*1 17.401+08 .0.001+00      1.141+08 27 1-133        3.951+08  6.871+O6    2.091+06  1.011+09 - 1.26+07 0.001+00      6.171+06 28 Co-134      4.671+06    1.111+0    1.091+08  0.001+00 3.601+08 1.191+08        1.951+07 29 C-136'      6.701+08  2.651+09    1.901+09  o0.001+00 1.4T+09 2.021+08        3.011+08 30 Cs-137 -    1.50110    2.051+10    1.31.10    0.001+00 6.951+01 2.311+09        3.961+06 31 la-140      2.741+6    3.441+03    1.791+0    0.001+00  1.173+03  1.971+03    5.641+06 32 h-140        4.60101    2.321-01    6.131-02  0.001+00  0.001+00  0.001+00    1.701+04 33 Ce-141      4.193+02    3.241+02    3.081+01  0.001N00    l.511+02  0.001+00    1.241+06 34 C-144        3.051+04    1.271041    1.641+3    0.001+00  1.551+03  0.001+00    1.031+07 All muclldes (iapt 1-3) calculated per CDCouatlon 2.3-24 1-3 calctlated per OWN eqvatioa 2.3-26
 
Y                                                                      Number:
Beaver Valley Power i
                                      -      -.o Station,
                                                                                                                  .Procedure
___112-~ODC-2.02 Unit llntle:          Level Of Use:
1/2
                                                                                                                          ...              In-Field Reference ODCM: GASEOUS EFFLUENTS                                                                                            Rcvision:        PageNumber.
1              105 of 12.S ATTACHMENT J Page 17 of 19 P&I ORGAN DOSE FACTORS
                                                                    . hae; 2:,3-18 1 IvntS lot 11Am bLLIM SI171 (equteiiisreg/r"pe'ruia/ftcl Pathway =Goat BilkIi_
ice Swap = een Iolide                  logo          Liver. 1. lod      Thyroid        lidoee          Lug        01-tL O.001+00        2.031es3 'i.031*03          .i031*03 2.031+03          2.0i1t03      2.031*03 29-32              3.211*10        IM91*          1.241+9 '"0.001#00 1.00100              0.001+00      2.7019M 3 Cr-51            0.001*00      0.0ooi00      4.131+03    2.771*03    1.091+03      7.111*0        1.371+05
* 4 h-54            0.001+00        .1.11*06 -2.31*05          0.001*00 A3.551*05          0.001*00      2.441*06 5 Fe-S5            5.441it5        1.+216 4.901*1            o.00100 0.001400            4.001*05      3.001+06 6 Co-SI            e0.001o00        l.9210t      3.211*05, 0.001+00        .001*00      0.001*00 3.57T1*
7 Co-SB            0.001+0        7.40105 1.711t06 0.001*00. C.901*O                    0.001+00 1.021+07 8 Co-BC            0.001*00        2.271*6, . s5.1106      -0.001*00 3.001*00            0.001*00 2.9U+07 9 la-65            1.811+06      6.271*0'      2.931+08    0._001*00,-. 4.011+08      O.001*00 2.86U+08 10 b-86            0.001#*0        4.71*08        2.251*08    0.001*00    0.001400      0.001*00 7.0961*7 11Sr-49          ,4.49109 0.001*00 1.291*08 o0.001+00              o      .001*0      0.00100        5.351+06 12 Sr-90            9.391*10 0.001*00 2.321+10 '0.001D00                    0.001*00      0.001+00 2.641+09 13 7-91              1.501403 0.001+0 :4.011+01 0.001+00                    1.00100        0.001*00 8.141*05 It Zr-95        -1.551*02 4.901*01 3.371+01 0.001400                        7.11*01        0.001*00 1.131+05 I                  Is 11-95            1.391+4 7.6tA 3 4.231+03 0.0010                        7.451+03      0.001*00 3.291*07 16 1197              6.151-13 1.53-13                .511-14 4.001*00 1.791-13 0.001+O03.851-09
:0.001+00 4.51*06 :56.701*05 0.00140. 1.041+01 0.001*00 8.171+06 i 1 ic-99            5.881-01 '1.641U+0 '2.1312        MU 0.001+00 2.451+01 .9.111-01 1.0o1*03 19 h-103            1.771+02 0.001*00 7.51*01 0.001+00 7.241*02 0.001400 1.481*04 20 h-lOB            2.441+03 0.001*00 3.981+02 0.001+00 6.101*03 0.00100 1.521*05 21 g-I10.          J:241*8        7.801*08 1.751tO6          0.001+00      1.491*07 0.001*00 2.191+0M 22 G1-124          0.001*00        6.001C00 -0.00t+00        0.001+00    0.001400 .:0.001O0 0.001*00 23 Sb-125            0.001+00      0.01+00        0.001+00o0.00300        0.001+00o 0.001*00 0.001+0 24 Te-l21            7.B11+06 '2.701*08            9.051*05 . 1111+06      3.081*07 0.001+0 1.101*07 25 le-129i          1.091+07 4.031*8              1.721*6 3.511*06          4.551*07 0.001+00 4.08+07 26 1-131            5.481+06 7.671+0              4.121+08 2M2M1IIl 1.310t9              0.001too      1.521*06 27 I-133            7.211*06 1.221+07 3.1H+06 :1.711+09 2.151+07                          0.001*00      9.281+06 28 CU-34              8.111:e        1.911409 8.881*08 0.001*0 8.071*8                    2.3211        2.381*07 29 Ce-136            I ld09 4.491+09 -3.021*09: 0.001*0 '2.441+09                          3.851+06      3.611*08 30 C-137            2.711+10 3.611+10 1.261+10 0.001*00 1.231+10                          4.171+09      5.141+08 4.941*06. 6.061*3            3.181t0s    0.001+00    2.051+03      4.071o03 7.621*04 32 La-140            8.271-01 4.0u-01              1.081-01  0.001*00    0.901*00      0.001*00 2.331+04 33 Ce-141            8.791+02' 5.71+02'            6.741+01    o0.00100    2.761+02      0.001+00 1.681+06 34 Ce-144            5.601+04        2.321+04      3.01+03    0.001+00      1.39104      0.001+00 1.411+07 111 euclldee (except 3-3) calculated per 000 equation 2.3-24 1-3 calculated per 0D0a equtlon 2.3-28
 
_ ,,,Procd      Number Beaver Valley Power Station                                                      -112-ODC-2.02 Tide<:                                                                                        Untit:            Level Of Us=
1/2              n-Field Reference L ODCM: GASEOUS EFFLUENTS                                                                        Revision:        PageNumber
                      -:                                                                              1              ~106 of 12    - 1 AITACHMENT J Page 18 of 19 P&I ORGAN DOSE FACTORS
:Table 2.3-19 1 IWS 101 BuMl IIl            SITI (0t seter-sres/yr per ivC/sec)
Pathay - Goat Bilk A4e Group: Mild helids            ose    Llver        . ady    Tkyrold      Kidney      L          61-LUI 1 1-3        0.001fo0 3.201+03 3.2010            3.201+03  3.201,03  3.201+03    3.201+03 2 F-32        7.911+10 3.TO+09 3.MU+M9            0.001+00  0.001+00  0.001+00    2.191*09 3 Cr-5I      O.001+00 .0.00100 1.021+04          s.61+03    1.54+03  1.031*04    5.311+05 4 18-sd      0.001e00 1.781*06 (.74105          0.001+00  4.091+*0  0.00100      1.491,06
                  - Ye-S9      1.261*60  2.041*0 -1.02106          0t001*00  0.001*00  5.911*05    2.12106 6 Co-57      0.001*00  3.27mto0      6.631+5 0.001+00      0.01*0    0.001400    2.681MM I oS          6.001+00  1.131*06    3.461046 0.001*00      0.001fo0  0.001+00    6.601t04 8 CoS60      0.001*00  3.531*06      1.041+07 0.001o0      0.001+00  9.001+00    1.951+07 9 Z45        3.541+08  9.441*08      5.871*06 0.001*00      5.951+08  0.001*00    1.661#05 10 lb-6        0.001*00  I.8 08        5.461+08o .0.001+00    0.001+00  0.001+00    5.711*07 11 Sr49        1.111+10  0.001o00 3.171*08        0.001ew0  0.00100  0.001t      4.301*08 12 Sr-so      1.591+11  0.00100 -4.621+10        0.001+00  0.001+00  0.001+00 2.141+09 13 T-91        3.701+03  0.001+00 -. 69101        0.00100    0.001oo00 0.001+00o4.131CM 14 Z.-IS      3.601+02  7.921+01 7.051+01        6.001+00  1.131+02  0.001*00e 8.2104 15  lb-95    - 3.131UM    1.221*04 6.711*03        0.001+00  1.141+40  0.001+00 2.251*07 16 lb-97      1.491-12  2.101-13    1.261-13    0.001+00  2.051-13  0.001+00    5.331-08 17n-99
                    -          0.00100    8.301046    2.051+06    0.001*00  1.771+0  0.001+00. 6.71 6+06 18 Tc-OSI      1.351*00  2.651*00    4.391+01    0.001*00  3.64101  1.34*00      1.511+03 19 h-103      4.181+02  0.001*00      1.6t1+02    0.001*00  1.051*03  0.00100      1.081+04 20 h-106      7.791*03  0.001*00    9.721+02    0.001+00  1.051+04  0.001*00    1.211+05 21 Ag-lih      1.791+01  1.211+07    9.651+06    0.0010    2.251*07  0.001+0      1.441*09 22 gb-124      0.001+00  0.001*00    0.001#00*  0.001+00  0.001*00  0.001+00    0.001*00 23 gb-125      0.001+00  0.O1MM0      0.001*00    0.001+00. 0.001*foo 0.400100    0.001*00 24 te-12n      1.881*07  5.051+046    2.231+06    4.4u1*04  5.351+07  0.00100      1.521*07 25 Te-129s    2.681M+7  1.481+06    4.161*06    8.641+06  7.61+07  0.001*00    3.271+07 26  1-131      1.331+03  1.341*09    7.601+08    4.421+11  2.191+09  0.001+00    1.191+06 27  1-133      1.751*07  2.171+07    8.201+06    4.031+09  3.811+07  0.001+00    8.731+06 26 Ce-134      1X.109:  3.071+09    6.481*08    0.OM*O0    1.521+08  3421+08      1.661+07 29 Cs-136      2.581*09  7.081+0      4.581*09    0.001+00  3.771*09  5.623*08    2.491+08 30 C-13U7      8.5410. 6.261*tO    9.241u09    0.001+00  2.04U110  2.31*09      3.921+06 31  ga-140      1.191*07  1.051*06    6.981+05    0.00100    3.401*03  8.231+03    6.041*06 32  LA-140      1.981+00  6.92-01      2.331-01    0.001*00  0.001*00  0.001+00      1.931+04 33  C-141      2.161+03  1.001+03      1.601+03  0.001+00    4.731+02 0.001+00      1.351+06 34  Ce-144      1.381*05  4.331*04    7.371+03    0.001+00  2.401+04  0.001*oo      1.131+07 Ill c clidee (ezceit 1-3) calculated per eDa epaitie 2.3-24 1-3 calculated per eDaH  equiatie 2.3-28
 
xBeaver  Valley Power Station -I-                                                                  -      12.l/2ODC-2.02
 
==Title:==
-  .                                                                        -                  Unit:            Level Of Use:
        -  ,-                                                                                            1/2              In-Field Reference ODCM:' GASEOUS EFFLUENTS                                                                                Revision:        Page Number
                                                                                                        ,. ~          ~        l~nl8-0 of 12
                                                *A&#xb6;ITACEIMENT J Page 19 of 19 P&I ORGAN DOSE FACTORS .
Talse 2.3-20 1 ihIDI    0 7 Al      11117 SI!
(sq a4eter-sru/yr per aCtllnc)
Psthayl Cout milk Its group        lert n:
cilide        Iobe      LiUer      .lady  'Tyrold      Ilidiey        laag      GI-UI1 11-3          0.001+00    4.38303    4.861t+3    42841+03 4.61103 4.8113            4.1861103 2 1-32        1.631+11    9.591+09    6.321+09    0.001+00 0.001+00 0.01100          2.211+09 3 Cr-SI      0.001144    0.001*5      1.611+04    1.01+04 2.291t03 2.041+04          4.691+05 4 b-54        0.501+00    3.311+04    7.501+05    0.001+00 7.331*05 0.001+0          1.211+06 5 Iq-59      2.351+06    4.111t06    1.621+06    0.001+00 0.001+03 1.211+04          19AMM08 6 CO-57      D.AU1+00    T.41+05      1.241u06    C.oMo    0.001100    0.001+00    2.601+08 7 Ce-Sl      0.001+00    2.261+06    5.64+08    0.001+00  0.501100    0.e01+00    5.641*06 9 Co4O        0.001+00    7.m0tm6      1.701107    0.001100  0.501100      0.001100    1.711*07 Sa-45        4.761+06    1.631+09    7.53q1t0    0.001100  7.s21s08  -. 001+00    1.381+09 10 l-as        0.001o00    2.251tO9    1.111+09    0.001+00  0.001300    0.001+00    5.771+07 11 Sr-89      2.111MUM    0.001*00    6.06110    0.001100  0.003100    0.001+00    4.341+08 12 Sr-90        1.731+11 O.00100        4.391*10    6.001+00  0.001t00    0.501+00    2.141+09 13 T-91        6.941+03 6.001+00        1.851+02    -02001100 0.001+00    0.001+00    4.681+05 14 I-S5        6.401+02 -1.541t2        1.111102    0.003100  1.68+02      0.001+00    7.771+04 15 gb-5        5.841+04 2.411+44        1.3S1+04    0.001400  1.721+04    0.00150o    2.031+07 16 Ib-91      3.111-12    .74-13      2.431-13    0.001+00  5.271-13    0.001+00    2.131-07 17 NO-99      0.503+00    2.121tO7    4.141+06    0.01+00  3.171+07    0.001+00    6."91+08 li Tc-99R      2.811+00    5.7010      7.461+01    00401100  6.23+01      3.0s31+00    1.681+03 19 I-103      8.471+02    6.001+00    2.431+42.    .001o00  1.761+03    C.OM1M0      1.031+04 20 I-IO6      1.801+O4    0.001+00    2.ento03    0.001100  1.901534    0.501+00    1.221*05 2.601*07    0.001+00 21 4g-llQ0    3.301*07    2.411M07                          3.45107      0.001+00 1.251tO9 22 Sb-124      C.O01+00    0.01+00                            0.001+00      0.01+00 -0.00t+00 23 WM-25      0.0OM10O    0.o00100 0.601100        0.001100 0.001+50    0.001+00 0.001+00 24 Te-127      3.81+47    1.261+07 4.591+40        1.101+07  9.351+07    0.501*00    1.531+07 25 le-129h    5:501+07    1.t91*01 8.471*06        2.11N4    1.331+06    0.001*00    3.281107 261-131        2.171tO9    3.TIn09                            3.821MU  9 0.001+00      1.111+08 271 -133      3.7M*ON7    5.391t07    1.5411+07 1.601109    1.34        C7 0.1UN0      9.121+06 28 Ca-134      3.021+9    5.621+09    5.681+0t O.00+o00    1.031+09      5.331+04    1.531+07 29 Ce-13t      5.031109    I1481+10    5.521+49 0.003*00    .5.90109      1.211+09    2.251+08 30 Ce-131      1.043+11    1.221+11    1.481*09 0.40l1+0    3.2t1+10      1.331+10    3.821+08 31 Ba-14O      2.451*07    2.451041    1.261t10    0.001*OO5.831+03        1.511+04    6.031106 32 La-140      4.141100    1.631+00    4.111-01    0.001+00 0.001100      0.001+00    1.921+04 33 Ce-lUl      4.291413    2.621503    3.481+02    0.001+00 8.071+02      0.001+00    1.351+06 34 Ce-144      I 1.981+05      .111+04    1.111+04    0.001*0N 3.281+04      0.001*0      1.141107 il lsuclides (exeapt 1-31 calculated per coa evetion 2.3-24 1-3 calculated per OD egatiom 2.3-28
 
                                                                                                                                  -              V-0 TABLE 2.3-21 PV- 1/2 DEPOSITION PARAMETERS (D/Q) FOR
                                                                                                                                          .  .l CONTINUOUS RELEASES >500 HRS/YR OR >150 HRS/QTR                                                            o.'
                                                            -2 (meters )
CD cd,
                                  - DISTANCES TO THE CONTROL LOCATIONS, IN MILES                                                                    CD 3.5-4.0 a."
SECTOR  0.0-0.5  0.5-1.0    1.0- 1.5    1.5 -2.0 ' 2.0-2.5    2.5-3.0,. 3.0'-3.5                4.0 - 4.5  4.5 - 5.0                            <:w-0-..
cn N      6.OOE- 10 8.60E-09    3.14E-09    1.76E-09    8.12E-10 5.70E-10    4.24E-10    3.29E-10 '.2.63E-10  2.15E-10 NNE    6.66E-10  5.64E-09    1.98E-09    2.55E-'09  1.33E-09, :1.07E-09  6.*E-10'    5.23E-10 4.56E-10    3.74E-10 NE    1.03E-09  1.57E-09    1.32E-09    3.62E-09    2.63E-09  1.64E-09  1.23E-09    6.13E-10 7.85E-10    6.42E-10                              CD tlI ENE    1.13E-09  1.55E-09    3.69E-09 '  3.27E-09,  2.31E-09'  1.29E-09  1.21E-09    6.78E-10  6.72E-10  3.89E-10  t_ w E      1.35E-09  1.28E-08    4.09E-09,    3.12E-09    1.91E-09  1.36E-09  1.01E-09    7.83E-10  4.15E-10  5.10E-10    W  '                      -t C.t2 ESE    9.82E-10  7.85E-09    4.40E-09,    2.46E-09    1.47E-09. 1.03E-09  5.65E-10  '5.OSE-10  3.25E-10  3.OOE-10  c4                        .w tzl 1                    z-I Pz SE    2.76E-09  6.41E-09    3.52E-09    1.97E-09    1.18E-09 8.27E-10 5.68E-10, 4.40E-10        2.93E-10  2.43E-10 SSE    2.22E-09  4.66E-09    3.01E-09    1.68E-09    1.02E-09 7.14E-10" .4.25E-10' '3.29E-10      2.19E-10  1.80E-10 1.36E-09 9.52E- 10 5.12E-10 3.96E-10        2.68E-10  2.20E-10  It o S      3.OOE-09  4.8 1E-09  3.76E-09    2. 1OE-09 SSW    1.44E-08  2.89E-09    7.83,E-10    8.84E-10    5.70E-10 4.OOE-10 , 2.55E-10 1.98E-10        1.84E-10  1.51E-10 SW    1.89E-08  5.55E-09    1.55E-09    8.71E-10    2.61E-10 :3.94E-10' 1.57E-10 2.50E-10        2.54E-10  2.08E-10 Z
w WSW    1.57E-09  6.63E-09    1.36E-09    1.04E-09    5.44E-10  2.39E-10  3.84E-10    2.98E-10  2.17E-10  1.78E-10  2~
W      3.78E-10' 2.95E-09    1.84E-09    1.03E-09    6.63E-10  4.66E-10  1.37E-10.. *2.68E-10  1.12E-10  1.75E-10 I.I.
                                                                                                                                  -      i~
WNW    4.54E- 10 4.13E-10    3.09E-10    4.71E-10    7.35E-10  5.16E-10  1.93E-10    1.10E-10  1.12E-10  1.80E-10  rtA NW    4.52E-10  4.09E-10    2.86E-10    1.18E-09    7.04E-10  4.94E-10  3.37E-10    2.10E-10  2.09E-10  1.71E-10 NNW    3.40E-10  2.05E-09    1.63E-09    9.12E-10    5.86E-10  4.13E-10  2.79E-10    2.16E-10  1.73E-10  1.42E-10 0'
z  7 !Rn DO
                                                                                                                                  -I.,
0
_    i Q. w tJ xO        91 I
                                                                        ./                                                              K
 
1 I (    I        .  - -      -    s.. ... . -    ,
I -1                                                            (VI Y
TABLE 2.3-22 CV- I AND CV-2 DEPOSITION PARAMETERS (D/Q) FOR CONTINUOUS RELEASES >500 HRS/YR OR >150 HRS/QTR
                                                                .2 (meters )
DISTANCES TO THE CONTROL LOCATIONS, IN MILES n
SECTOR  0.0 - 0.5  0.5- 1.0  1.0 - 1.5 , 1.5 - 2.0    2.0 - 2.5  2.5 - 3.0  3.0 - 3.5    3.5 - 4.0    4.0 - 4.5      4.5 - 5.0 N      4.46E-08  7.73E-09  3.24E-09    1.8 1E-09  1.08E-09    7.57E-10    5.16E-10    4.OOE-10      2.91E-10      2.38E-10 NNE    5.42E-08  9.39E-09  3.37E-09    1.89E-09    1.22E-09    8.54E-10    6.35E-10    4.92E-10      3.94E-10      3.22E-10  0#
NE      7.32E-08  1.27E-08  6.21E-09    3.47E-09    2.24E-09    1.57E-09    1.OOE-09    7.77E- 10    5.69E-10      4.66E-10 w-C ENE    7.77E-08  1.35E-08  6.51E-09    3.64E-09    2.50E-09    1.76E-09    1.3 1E-09    1.01E-09    6.58E-10      5.39E-10 E      6.08E-08  1.05E-08  3.79E-09    2.12E-09    1.37E-09    9.59E-10    6.54E-10    5.06E-10      4.05E-10      3.32E-10 ESE    3.23E-08  5.60E-09  2.54E-09    1.42E-09    8.46E-10    5.94E-10    4.05E-10    3.14E-10      2.28E-10      1.87E-10  rA M:
SE SSE S
SSW 3.29E-08 2,84E-08 3.67E-08 2.61E-08 5.70E-09 4.92E-09 6.37E-09 4.52E-09 2.59E-09 2.06E-09 2.26E-09 1.60E-09 1.45E-09 1.15E-09 1.26E-09 8.97E-10 9.32E-10 6.29E- 10 8.14E-10 5.78E-10 6.55E-10 4.42E-10 5.71E-10 4.06E-10 4.12E-10 2.99E-10 3.86E-10 3.02E-10 3.19E-10 2.32E-10 2.99E-10 2.34E-10 2,55E-10 1.85E-10 2.39E-10 1.70E-10 2.09E-10 1.52E-10 1.96E-10 1.39E-10 tv  I~
SW      3.06E-08  5.30E-09  2.62E-09    1.47E-09    8.OIE-10    5.62E-10    4.18E-10    3.24E-10      2.35E-10      1.93E-10 WSW    4.60E-08  7.97E-09  3.34E-09    1.87E-09    1.20E-09    8.45E-10    5.87E-10    4.55E-10      3.38E-10      2.77E-10 W      6.49E-08  1.13E-08  4.72E-09    2.64E-09    1.19E-09    8.36E-10    6.22E- 10  4.82E-10      3.85E-10      3.ISE-10  z-4 WNW    9.25E-08  1.60E-08  6.43E-09    3.60E-09    2.21E-09    1.55E-09    1.16E-09    8.96E-10      5.79E-10      4.75E-10 NW      1.19E-07  2.07E-08  8.68E-09    4.86E-09    2.99E-09    2.10E-09    1.56E-09    1.21E-09    7.83E-10      6.41E-10 NNW    5.22E-08  9.04E-09  3.79E-09    2.12E-09    1.28E-09    9.OOE-10    6.25E- 10  4.84E-10      3.59E-10      2.94E-10
 
II-
            ,BaeValyPower Valley          Station        ,11-OC-.0 Procedure Sn.
rtheDM                                                  Unit:        Level Of Use:
GA  U E 112          In-Field Reference Revision:. Page Numb.    ;
ODCM: GASEOUS EFFLUENTS I-    I        i1 0nf 1I2 ATTACHMENT K
                                -Page 3 of 7 CONTINUOUS RELEASE DEPOSITION PARAMETERS (0-5 MILES)
TABLE 2.3-23 VV- IAND VV-2 DEPOSITION PARAMETERS (D/Q) FOR CONTINUOUS RELEASES >500 HRS/YR OR >150 HRS/QTR (meters 2 )
Same as Table 2.3-22 N
 
Beeaver Valley Power Station
                                                                                          ;_ _ _ _1I2 Pocedr    Number O D C -2 .0 2 itie  -Unit:                                                                                                      Level Of Use:
1/2          In-Field Reference ODCM: GASEOUS EFFLUENTS                                                                              Revision:    PageNumber.
1I          11 6f 129 i ATrACHMENT K Page 4 of 7 CONTINUOUS RELEASE DEPOSMTIONTPARAMETERS (0-5 MILES)
TABLE 2.3-24 TV-2 DEPOSITION PARAMETERS (D/Q) FOR
              ;CONTINUOUS RELEASES >500 HRS/YR OR >150 HRS/QTR (meters-2 )
: Same as Table 2.3-22
 
                                                                                        .  -              a-
          >' i-,:-  ,  .
Beaver Valley Power Station Proc
                                                      ;    -Idure ro IelO drNumbec..
                                                                    -A Nu'
                                                                        ...      fU :
                                                                                      -      .t I
DtlC:                                                    Unit:            LvedOAUs 112          . In-Field Reference ODCM: GASEOUS EFFLUENTS                                  Revision:      Page Number.          -r' I                                              .    ,      I. I    1 1o nf  I R
                                - ATTACHMENT K
                                    - - Page5 of 7 CONTINUOUS RELEASE DEPOSITION PARAMETERS (0-5 MILES)
                                      'TABLE 2.3-25
                  -  CB-2 DEPOSiTION PARAMETERS (D/Q) FOR
              '' CONTINUOUS RELEASES >500 HRSIYR OR >150 HRS/QTR (meters-2 )
: Same as Table 2.3-22
:-xX--
 
:.Kc  <  -  Or: *Proped=r sr1                Number,
        -  Beaver Valley Power taton12-ODC-2.02
 
==Title:==
Unit:        Level Of Use:
1/2          In-Field Reference ODCM- GASEOUS EFFLUENTS                              Revision:    Page Number
                ,.
* 1      -113          of 129 ATTACHMENT K Page 6 of 7 CONTINUOUS RELEASE DEPOSITION PARAMETERS (0-5 MILES)
TABLE 2.3-26 DV-2 DEPOSITION PARAMETERS. (D/Q) FOR CONTINUOUS RELEASES >500 HRSJYR OR >150 HRS/QTR (meters 2 )
Same as Table 2.3-22
 
BePwIN Stin      umbe 1r.:.
Be~a'ver"'alley Power Station                  II            '1/2:'ODC2..02___
lvtcunit:                                                      Level Of Use: ,
                    ..                                  j                    In-Field Reference T
ODCM: GASEOUS EFFLUENTS                                  j      t1/2 Revision:
                                                                  .1 Page Number:
114'of 129.
AITACHIMENT K Page 7 of 7 CONTINUOUS RELEASE DEPOSiTION PARAMETERS (0-5 MILES)
TABLE 2.3-27 WV-2 DEPOSITION PARAMETERS (D/Q) FOR CONTINUOUS RELEASES >500 HRS/YR OR >150 HRS/QTR
                                -    .(meters')
Same as Table 2.3-22
 
s  r    . n    *.          .Procedure          Number.
Beaver Valley PowerStation                      -- -                    e/2@DC 2 O2 Unit          Level Of Use:
1/2          In-Field Reference ODCM: GASEOUS EFFLUENTS                                                  Rvisionf      Page Number AITACHMENT L Page 1 of 7 CONTINUOUS RELEASE DEPOSlTION PARAMETERS (SPECIAL DISTANCES)
TABLE 2.3-28 PV-1/2 DEPOSTION PARAMETERS (D/Q) FOR CONTINUOUS RELEASES
                >500 HRS/YR OR >150 HRS/QTR FOR SPECIAL DISTANCES (lDENTIFIED IN ATTACHMENT E TABLE 2.2-3)
(lE-9 meters 2 )
INDIVIDUAL RECEPTORS DOWNWIND          SITE      VEGETABLE            MILK          M      -      MEAT SECTOR    BOUNDARY          GARDEN            COW          GOAT          ANIMAL          RESIDENCE N              .600          2.340                          .572-          .707              *2.510 NNE            .673          3.220                          .524          2.920              .3.220 NE            .766          1.280            .660          .111            .660              -1.200 ENE          1.010          5.080                          .702                              1.760 E            1.370          4.420            .401          1.290          1.290              4.420 ESE            .984          6.390                          2.340          6.390              6.180 SE          11.000'          3.680            .466          .466          1.300              3.680 SSE          7.060          3.220            .423            .105          3.140              4.320 S            5.780          1.540          1.410                          2.610              2.730 SSW          2.040          1.040            .578            .208          1.040              1.460
-iSW              1.610          1.120                            .693            .979              1.120 WSW          1.710          1.310            .370                          1.190                1.310 W              .377            .659          .138,                          .518                .659 WNW            .424            .746          .497            .029            .746                .7461
    - NW              .447            .425                          .070 -          .488                .422 NNW            .340          1.840                          .043            .545              1.92
 
U-_
Beaver Valley      Powe        S r/2-ODC-2.02 PowrSatin____`________                      Nube  1
 
==Title:==
Unit:              Level Of Use:
ODM    . :G      O                                                      1/2              In-Field Reference ODCM: GASEOUS EFFLUENTS                                              Revision:          Page Number:
I          I        1 1A nf 19R ATITACHMENT L Page 2 of 7 CONTINUOUS RELEASE DEPOSITION PARAMETERS (SPECIAL DISTANCES)
TABLE 2.3-29 CV-1 AND CV-2 DEPOSTION PARAMETERS (D/Q) FOR CONTINUOUS RELEASES
                    >500 RS/YR OR >150 HRS/QTR FOR SPECIAL DISTANCES (IDENTIFIED IN ATTACHMENT E TABLE 2.2-3)
(lE-9 meters 2 )
INDIVIDUAL RECEPTORS DOWNWIND              SITE      VEGETABLE          MILK    MILK            MEAT SECTOR      BOUNDARY        GARDEN            COW    GOAT          ANIMAL.r RESIDENCE  '
TM INN An    -      2                -      A1                QA7
                                                                                .(U. I
                                                                                                  -19  t. 1.>
NNE          18.80          2.02                    .459            1.850                    2.11 NE            63.40          29.30            .455    .078              .455                30.40 ENE          65.90          8.92                    .661                                  32.20 E            38.00          3.90            .382  1.020            1.020                  22.70    -I..
ESE          17.10          3.56                  1.380            3.560                    3.56 SE          13.80          3.03            .350    .350            1.100                    3.03  4-,
SSE          10.50          2.65            .317    .094            2.570                    3.68 S            10.60          1.05            .934                    1.860                    1.95 SSW          5.59          1.26            .663    .266            1.260                    4.42 SW            3.94          2.21                  1.320            1.920                    2.21 WSW          27.50          2.65            .596                    2.380                    2.65 W            31.60            1.23          .645                      .960                  1.23 WNW          39.10          2.23          1.490    .045          2.230                    2.23 NW          70.60          15.00                    ;276          1.990                  15.60 NNW          31.50          6.52                    .068          1.090                    9.91
 
Be'aver'Valley PowerStation Lower          Procedre 112-ODC--2.02 T..e.                                                  Unit:      Level Of Use:
1/2      In-Field Reference ODCM: GASEOUS EFFLUENTS                                RcvisLo  . Page Number
                                                          . I            117 of 128 ATTACHMENT L Page 3 of 7
      - CONTINUOUS RELEASE DEPOSITION PARAMETERS (SPECIAL DISTANCES)
: TABLE 2.3-30 VV-1 AND VV-2 DEPOSTION PARAMETERS (D/Q) FOR CONTINUOUS RELEASES
              >500 HRS/YR OR >150 HRS/QTR FOR SPECIAL DISTANCES
                  -(IDENTIFIED IN ATTACHMENT E TABLE 2.2-3)
({IE-9 meters 2 )
Same as Table 2.3-29
 
BeaverValley Power Station                    -        Ieaer1/2-ODC-2.02 P eureu ThIC                                                                Unit:          Leved Of Use 1/2            In-Field Reference ODCM: GASEOUS EFFLUENTS                                            Revision:      Page Number, ATTACHMENT L Page 4 of 7 CONTINUOUS RELEASE DEPOSITION PARAMETERS (SPECIAL DISTANCES)
TABLE 2.3-31 TV-2 DEPOSTION PARAMETERS (D/Q) FOR CONTINUOUS RELEASES
                >500 HRS/YR OR i150 HRS/QTR FOR SPECI[AL DISTANCES (IDENTIFIED IN ATTACHMENT E TABLE 2.2-3)
(lE-9 meters 2 )
INDIVIDUAL RECEPTORS DOWNWIND          SITE      VEGETABLE          MILK      MILK              MEAT SECTOR    BOUNDARY        GARDEN            COW      GOAT          ANIMAL            RESIDENCE N            20.20          2.05              -      .693              .847              2.190.
NNE          34.90          2.02              --      .459            1.850              2.110 NE          54.20          29.30          .455      .078              .455              30.400 ENE          57.50          8.92              --      .661                --              32.200 E            38.10          3.90          .382      1.020            1.020              22.700 ESE          18.60          3.56              --    1.380            3.560              3.560 SE          19.00          3.03          .351      .351            1.100              3.030 SSE          13.30          2.65          .318      .094            2.570              3.690 S            11.30          10.40          .934          --            1.860              1.950 SSW          6.44          1.26          .664      .266            1.260              4.430 SW            3.95          2.21              -      1.320            1.920              2.210 WSW          25.10          2.65          .597          --            2.380              2.650 W            28.40            1.23          .646          --            .961              1.230 WNW          30.90          2.23          1.490        .045            2.230              2.230 NW          56.10          14.90              -        .276            1.980              15.500 NNW          25.10          6.53              --      .068            1.100              9.920
                                                                                                          ,.- .NE
 
IProcedure Number:
Beaver Valley Power.Station                  -                112-ODC-2.02 Titl-tk-      :.                                            Unit:          Level Of Use:
                                                          .      1/2          In-Field Reference ODCM: GASEOUS EFFLUENTS                                      Revision:      Page Number:
                          - 4                                      1    -11          9 (if  8 ATTACHMENT L Page 5:of 7 CONTINUOUS RELEASE DEPOSITION PARAMETERS (SPECIAL DISTANCES)
TABLE 2.3-32 CB-2 DEPOSTION PARAMETERS (D/Q) FOR CONTINUOUS RELEASES
                  >500 HRS/YR OR->150 HRS/QTR FOR SPECIAL DISTANCES (IDENTIFIED IN ATTACHMENT E TABLE 2.2-3)
(1E-9 meters-2 )
Same as Table 2.3-31
 
Procedur Number~
Bea~ver Valley Power Station,                            1/2:DC-2.02
  .i .Unit:                                                            Leved Of Use:-
1/2        'n-Fteld Reference ODCM: . ASEOUS DC:Revision:
EFFLUENTScion  aeNmd                                Page Numbei i            120) of 128 ATTACHMENT L Page 6 of 7 CONTINUOUS RELEASE DEPOSITION PARAMETERS (SPECIAL DISTANCES)
TABLE 2.3-33 DV-2 DEPOSTION PARAMETERS (D/Q) FOR CONTINUOUS RELEASES
                >500 HRS/YR OR >150H RS/QTR FOR SPECIAL DISTANCES (IDENTIFIED IN ATTACHMENT E TABLE 2.2-3)
                                                      -2 (1E-9 meters-)
Same as Table 2.3-29
 
Beaver Valley Power Station ^i ^P1o2deN-C--. -
Tride:    ;-  ;,..                                              ... Unit:  1Level Of Use:-
in-Field                                      1/2                Reference ODCM:  O~M -GASEOUS      EFFLUENTSRevision:
AEU-E;F..UENT.S                                            Page Number:
                                                                                  -121 of 128 ATTACHMENT L Page 7 of 7 CONTINUOUS RELEASE DEPOSITION PARAMETERS (SPECIAL DISTANCES)
TABLE 2.3-34 WV-2 DEPOSTION PARAMETERS (DIQ) FOR CONTINUOUS RELEASES.
                        >500 HRS/YR OR >150 HRSIQTR FOR SPECIAL DISTANCES (IDENTIFIED IN ATTACL1MENT E TABLE 2.2-3)
(11E-9 meters-)
Same as Table 2.3-29
 
                                -    .      ,,        :      -.  *Procedure        Number.'
Beaver Valley        Power        Station              ;-:            kj2ODC 2O 2
'ride:                                                                      Unit:        Level Of Use:
          -..                                                                      2          In-Field Reference ODCM: GASEOUS EFFLUENTS                                                    Revision:    PageNumber:
                                                                                  -1              122 of 12R ATTACHMENT M Page 1 of 3 BATCH RELEASE DISPERSION PARAMETERS (SPECIAL DISTANCES)
TABLE 2.3-35 CV-1 AND CV-2 DISPERSION PARAMETERS (X/Q) FOR BATCH RELEASES
                      >500 HRS/YR OR &#x17d;150 HRS/QTR FOR SPECIAL DISTANCES (IDENTIIEED IN ATTACHMENT E TABLE 2.2-3)
(sec/m3)
INDIVIDUAL RECEPTORS DOWNWIND                SITE      VEGETABLE            MILK    MILK              MEAT SECTOR*        BOUNDARY          GARDEN            COW    GOAT            ANIMAL          RESIDENCE N              8.21E-5          8.38E-6                    3.72E-6          4.34E-6            8.82E-6 NNE            3.04E-5          4.71E-6                    1.40E-6          4.38E-6            4.87E-6 NE            4.59E-5          2.21E-5          6.05E-7  1.38E-7          6.05E-7            2.28E-5 ENE            3.72E-5          5.25E-6                    5.66E-7                              1.88E-5 E          . 2.93E-5          3.79E-6          5.15E-7  1. 17E-6          1.17E-6            1.78E-5 ESE            2.47E-5          5.61E-6                  2.34E-6          5.61E-6            5.61E-6 SE            2.14E-5          5.00E-6        8.13E-7  8.13E-7          2.03E-6            5.OOE-6 SSE            2.21E-5          6.3 1E-6        1.11E-6  3.92E-7          6.13E-6            8.49E-6 S              2.15E-5          3.03E-6        2.76E-6                    4.93E-6            5.14E-6 SSW            2.18E-5          6.58E-6        3.81E-6  1.82E-6          6.58E-6            1.78E-5 SW              1.82E-5          1.03E-5                  6.67E-6          9.12E-6            1.03E-5 WSW            1.09E-4          1.29E-5        4.10E-6                    1.19E-5            1.29E-5 W              1.49E-4          1.05E-5        6.55E-6      --            8.77E-6            1.05E-5 WNW            l.91E4          1.72E-5          1.28E-5  1.23E-6          1.72E-5            1.72E-5 NW              3.08E4          6.13E-5            --    3.80E-6          1.36E-5            6.366E-5 NNW            1.80E-4          3.54E-5            --    1.35E-6          9.27E-6            5.29E-5
  *Measured relevant to center point between BV-I and BV-2 Containment Buildings Period of Record: 1976 - 1980
 
Procedure Numbei yPower Station                                      1/2-ODC-2.02 ritle:                                                                  Unit            Lcvel Of Usc.
1/2            In-FReld Reference ODCM: GASEOUS EFFLUENTS                                                  Revision:        Page Numb=C 1                123 of 1'2fs ATTACHMEN1T M Page 2 of 3 BATCH RELEASE DISPERSION PARAMETERS (SPECIAL DISTANCES)
TABLE 2.3-36 VV-1 AND VV-2 DISPERSION PARAMETERS (XIQ) FOR BATCH RELEASES
                    >500 HRS/YR OR &#x17d;150 HRS/QTR FOR SPECIAL DISTANCES (IDENTIFIED IN ATTACHMENT E TABLE 2.2-3)
(seclm3 )
INDIVIDUAL RECEPTORS DOWNWIND              SlTEu      VEGETABLE          MILK-- - MILK
                                                                    -              MEAT.
SECTOR*      BOUNDARY          GARDEN            COW      GOAT            ANIMAL            RESIDENCE
        -N            9.75E-5          1.0013-5                  4.21E-6        '4.95E-6                1.0613-5 NNE        - 3.78E-5          5.11E-6                  1.43E-6          4.72E-6              5.30E-6 NE          6.131E-5        2.70E-5        6.20E,-7  1.40E-7      - 6.2013-7              2.81E-5 ENE          4.83E-5          5.58E-6                  5.71E-7              --              2.24E-5 151E3        3.66E-5          3.99E-6        5.25E-7  1.19E-6          1.191E-6              2.10E-5 ESE          2.991E-5        6.13E-6                  2.43E-6          6.13E-6              6.13E-6 SE          2.55E-5          5.29E-6        8.2413-7  8.24E-7          2.13E-6                5.2913-6 SSE          2.65E-5          6.72E-6        1.12E-6  3.95E-7          6.53E-6                9.22E-6 S            2.52E-5          3.14E-6        2.83E-6                    5.291E-6              5.53E-6 SSW          2.601E-5        7.34E-6        4.1513-6  1.9213-6        7.34E-6                2.09E-5
      'SW            2.1313-5        1.18E-5                  7.41E-6          1.0413-5              1.18E-5 WSW          1.34E4          1.51E-5        4.46E-6                    1.38E-5              1.51E-5 W      -      1.77E-4          1.25E-5        7.40E-6        --          1.0213-5              1.2513-5 WNW          2.331E-4        2.07E-5          1.49E-5  1.3013-6        2.07E-5                2.07E-5 NW            3.32E-4        8.57E-5              --    4.24E-6          1.64E-5              -8.85E-5 NNW          1.9013-4        4.691E-5            --    1.4513-6        1.09E-5          -- 6.75E-5
  *Measured relevant to center point between BV-1 and BV-2 Containment Buildings Period of Record: 1976 - 1980
 
V                                                                        V Procedure Number:
Beaver Valley Power Station                    -      L 1/2-'ODC-2.02    ______
TWtle:                                                                    Unit:          Level Of Use 1                n-Field Reference ODCM: GASEOUS EFFLUENTS                                                  Revision:    . Page Number.      .    .
I                124 nf t28 ATTACHMENT M Page 3 of 3
                ' BATCH RELEASE DISPERSION PARAMETERS (SPECIAL DISTANCES)
TABLE 2.3-37 PV-1/2 DISPERSION PARAMETERS (XIQ) FOR BATCH RELEASES
                      &#x17d;500 HRSIYR OR &#x17d;150 HRS/QTR FOR SPECIAL DISTANCES (IDENTF'IED IN ATTACHMENT E TABLE 2.2-3)
(sec/rn3 )
INDIVIDUAL RECEPTORS DOWNWIND              SITE ' VEGETABLE                MILK    MILK,            MEAT, SECTOR* -.'BOUNDARY-"          GARDEN            'COW      GOAT            ANIMAL          'RESIDENCE
        - N              3.09E-9; -    3.30E-6                    1.13E 1.34E-6                    3.36E-6 NNE        2.85E-9 '      2.68E-6                    6.52E :2.47E-6                - 2.68E-6 NE        -2.02E-1O'      7.42E-9          5.44E-7    1.24E-7-; 5.44E-7                  - 5.51E-9 ENE        1.02E-9 ' >    3.21E-6                    6.29E-7'-            --            ' 1.67E-9 E          2.15E-9  -    2.91E-6          4.96E-7    1.14E-6        1.14E-6              2.91E-6
      - ESE            6.90E-9        4.97E-6                    1.95E-6 '-' 4.97E-6                  4.81E-6 SE          2.91E-6        3.52E-6          6.02E-7    6.02E-7        1.43E-6              3.52E-6 SSE        4.91E-6        3.56E-6          6.53E-7    2.18E-7        3.47E-6              4.71E-6
        '.S            2.41E-6        1.78E-6          1.65E-6      -        I 2.84E-6                2.96E-6 SSW        4.83E-6        2.52E-6          1.50E-6  6.60E-7'        2.52E-6              3.96E-6 SW          4.82E-6        2.75E-6                    1.78E-6        2.44E-6              2.75E-6
          - WSW          5.77E-7        2.81E-6        8.79E-7      --          2.57E-6              2.81E-6
        ' W              2.88E-9        1.68E-6        4.89E-7                    1.37E-6              1.68E-6 WNW        3.40E-9        1.61E-6          1.13E-6  1.101E-7        1.61E-6              1.61E-6
          -NW            1.34E-9        3.3 1E-8                  2.03E-7          1.07E-6            - 3. 10E-8 NNW          1.52E-9        3.73E-6                    1.73E-7          1.3 1E-6            3.81E-6
    *Measured relevant to BV-1 natural draft cooling tower Period of Record: 1976 - 1980
 
C,  .      I I(i ..
TABLE 2.3-38                                                                      C)  z PV-1/2 DISPERSION PARAMETERS (D/Q) FOR                                                              cjt CONTINUOUS RELEASES 2500 HRS/YR OR 2150 HRS/QTR I..      (sec/mr3)                                                                      V:
tz DISTANCES TO THE CONTROL LOCATIONSIN MILES SECTOR    0.0- 0.5  0.5 - 1.0    1.0- 1.5    1.5 - 2.0    2.0 - 2.5  2.5 - 3.0    3.0 - 3.5,  3.5 - 4.0  4.0 - 4.5  4.5 - 5.0 N      2.75E-15    1.07E-5      4.1OE-6    2.61E-6      1.5 1E-6  1.13E-6      8.84E-7    7.13E-7    5.93E-7
* 5.06E-7 NNE    5.90E- 17  5.39E-6      2.83E-6    2.19E-6      1.36E-6    1.13E-6      8.05E-7    6.51E-7    5.64E-7    4.81E-7 NE    4.453-16    1.67E-8      7.3 9E-8    2.28E-6      1.72E-6    1.19E-6      9.28E-7    6.76E-7    7.34E-7    5.32E-7    C/)
I9.25E                                      t"d ENE    1.92E3-15  8.87E-8    I2.60E-6    2.21E-6      1.66E-6    1.13E-6                  7.23E-7    6.06E-7    3.82E-7 ti E      .1.8413-15  5.10E-6    2.77E-6      2.23E-6      1.44E-6    1.12E-6      8.74E-7    6.92E-7    5.11E-7:  4.82E-7        'v I 1.34E-6    9.93E-7      6.70E-7'    5.76E-7    4.37E-7    3.83E-7        to >
ESE    2.96E-13    5.26E-6      3.48E-6    2.04E-6                                                                                  OQ 0 SE    ~9.1 6E8    3.13E-6      3.38E-6    1.99E-6      1.3 1E-6  9.58E-7      7.14E-7    5.74E-7    4.32E-7    3.68E-7 z
SSE    3.50OE-8    4.86E-6      3.33E-6    1.95E-6      1.29E-6    9.42E-7      6.55E-7    5.24E-7.,  3.95E-7    3.32E-7 S      1.2213-7  4.12E-6      3.97E-6    2.34E-6      1.59E-6    1.17E-6      7.75E-7    6.24E-7 . 4.74E-7    4.OOE-7 SSW    .1.758-5    6.22E-6    2.84E-6      2.18E-6      1.48E-6    1.08E-6      7.83E-7    6.31E-7    5.62E-7    4.77E-7 SW    2.08E-5    9.1IE-6    3.47E-6:    2.19E-6      1.25E-6    l.11E-6      8.19E-7    7.17E-7    6.89E-7    5.85E-7 WSW    8.5613-8  9.35E-6      3.16E-6    2.29E-6      1.46E-6    1.O1E-6      9.06E-7    7.52E-7    5.99E-7    5.07E-7 la W      5.44FE-17  4.52E-6      4.21E-6    2.49E-6      1.69E-6    1.25E-6      4.86E-7    7.68E-7    5.80E-7    5.48E-7 WNW    9.2513-18  1.44E-8      5.66E-8    1.92E-6      1.59E-6    1.17E-6      7.75E-7    4.61E-7    5.28E-7    4.89E-7 NW    2.61E-16    1.98E-8      8.37E-8    2.24E-6      1.46E-6    1.08E-6      8.09E-7    6.12E-7    5.42E-7    4.60E-7 NNW    1.9 lE-iS  3.91E-6      3.66E-6    2.15E-6      1.40E-6    1.08E-6      8.03E-7    6.48E-7    5.37E-7    4.56E-7
 
B vl V    y -Procedurc o      r        i.                    [          Number: .
Beaver valley Power Station -                                                          /-ODC-2.02
 
==Title:==
Unit          Level Of Use:
1/2          In-Field Reference Revisio.      Page Number.
ODCM:. GASEOUS EFFLUENTS L      I.I .            )A o II ATTACHMENT 0 Page 1 of 1 GASEOUS RADWASTE SYSTEM FIGURE 2.4-1 BV-1 AND 2 GASEOUS RADVASTE SYSTEM Lt
                                                                                                                                      'N
 
Beaver Valley Power Station                                                                    NricrdDC2 O2
'rile:                                                                                        Unit:      Lvel Of Use:
1/2        In-Field Reference ODCM: GASEOUS EFFLUENTS                                                                      Revision    PageNumbe        .-
1          127 of 128 ATITACHMENT P Page 1 of 1 BV-1 AND BV-2 GASEOUS EFFLUENT RELEASE POINTS FIGURE 2.4-2 ct*et. Potat
* Descripton                        E eytloan
: 1. Utnit  I:    Ventfletfan Vent                    7V feet
* 24  meter
: 2. unit    I:    Contarmnt / SLaCt Vent            154 feet  * *?  meters
: 3. thit    i12:  Process Vent                      475 feet
* 145 moters
: 4. unit  2:    Ventitation Vent                    S5 fet
* 26  _t\er
: 5. Unit    2:    Conteint I SLCtt Vent              154 fet  *t 47 mters
: 6. iit    2:    Condesate Nttshfrq Suitdiq Vent il et        - 24  mters T. bhit    2:      et* CmeStorap Veutt lent          O feet
* 24  meters S  Unit    2:    Secontamlintion Suitding Vent      i0 feet  - 24  =ter*
: 9. Unit    2:    Turbine WtIoding Vent.              09 feet  - 33  mters ote: Te h Wels. Point shownfor the Unit 2 Turbine fuiltdit Vent is a rep sntstive a-ht      tuolnt fer TMw1C roof 09s      outlets.
 
o      (z .
I        Md      Iand            .......
t-I 4'0
_                    ll ll    ^>*                      ~~Shippingport for This Site Boundary Liquid Effluents does notr include the areas over the *ay Ohio With this River.        i    exception k
the site Boundaries are identical.
                                  /              ,.-..
__SIte  Boundary-Elluent          ME            1 Dralnage-LlquIds      j[g        l  t
                                                        + ^ G~Drecilonof
              . L                    lt
                                                                                                    .. .      E
 
A9.621B Beaver Valley Power Station Unit 1/2 1/2-ODC-2.03 ODCM: Radiological Environmental Monitoring Program Document Owner Manager, Health Physics Revision Number                                        0 Level Of Use                                General Skill Reference Safety Related Procedure                              Yes
 
                                                                                                                                                        -        W p
I Beaverr VValley              e P  Power  e StationI S                                          Procedure Number 1/2-ODC-2.03
 
==Title:==
Unit:            Level Of Use:
ODCM: Radiological Environmental Monitoring Program                                                          1/2            General Skili Reference Revision:        Page Number:
0                      2 of 19 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 ....................                                                                                                              3....3 4.1 Records .......................                                                                                                                3 4.2 Form s.....................................................................................................................................4 5.0 PRECAUTIONS AND LIMITATIONS ................................                                        ;            ...                                  4 6.0 ACCEPTANCE CR ITERIA ................................                                                                                              4 7.0 PREREQUISITES.............................................................................................................................4 8.0 PROCEDURE ................................                                                                                                          4 8.1 REMP Overview ..                                                                                                                                4 8.2 Sampling and Analysis Program                                                                  .4 8.3 Crosscheck Program                                                                  .5 8.4 Land Use Census Program                                                                  .6 8.5 Direct Radiation Monitoring Program ..........................                                                                              ;77 ATTACHMENT A EXPOSURE PATHWAY AND SAMPLING REQUIREMENTS...                                                                                                8 ATTACHMENT B LOCATION OF SAMPLING SITES                                                                            .          .          .          12
 
Beavr      V      e    P      r SProcedure                          Number.
Beaver V alley Power Station                                            1/2-ODC-2.03
'Ttle:                                                                          Unit:        Level Of Use:
ODCM: Radiological Environmental Monitoring Program                                1/2      General Skill Reference Revision:    Page Number:
0                3 of 18 1.0        PURPOSE 1.1      This procedure provides the Radiological Environmental Monitoring Program (REMP) requirements from the Radiological Branch Technical Position.(3 '1
  -I  1.1.1    Prior to issuance -of this procedure, these items were located in Section 3 of the old ODCM.
2.0        SCOPE 2.1      This procedure is applicable to all station personnel that are qualified to perform activities as described and referenced in this procedure.
 
==3.0        REFERENCES==
AND COMMITMENTS 3.1      References 3.1.1    Radiological Branch Technical Position, Revision 1, 1979.
3.1.2    Regulatory Guide 1.109, Calculation of Annual Dose to Man From Routine Releases of Reactor Effluents For the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Revision 1, 1977.
3.1.3    NUREG-1301, Offsite Dose Calculation Manual Guidance; Standard Radiological Effluent Controls for Pressurized Water Reactors (Generic Letter 89-01, Supplement No.
1).
3.1.4    Regulatory Guide 1.111, 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      1/2-ADM-0100, Procedure Writers Guide 3.1.7      1/2-ADM-0101, Review and Approval of Documents 3.2        Commitments 3.2.1      10 CFR 50 Appendix I 4.0        RECORDS AND FORMS 4.1        Records 4.1.1    Any calculation supporting ODCM changes shall be documented, as appropriate, by a retrievable document (e.g., letter or calculation package) with an appropriate RTL number.
 
I          WU Procedure Number:
Beaver Valley Power Station                                                1/2-ODC-2.03
 
==Title:==
Unit:        Level Of Use:
ODCM: Radiological Environmental Monitoring Program                                  1/2      General Skill Reference Revision:    Page Number:
0                4 of 1 4.2        Forms 4.2.1    None.
5.0        PRECAUTIONS AND LIMITATIONS 5.1      The specified detection capabilities are state-of-the-art for routine environmental measurements in industrial laboratories.
6.0      ACCEPTANCE CRITERIA 6.1      Any change to this procedure shall contain sufficient justification that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a and Appendix I to 10 CFR 50, and not adversely impact the accuracy or reliability of effluent dose or setpoint calculation.
6.1.1    All changes to this procedure shall be prepared in accordance with 1/2-ADM-0100( 3            16 )
and 1/2-ADM-1640t 3 l 5 ).
6.1.2    All changes to this procedure shall be reviewed and approved in accordance with 1/2-ADM-0 10 i 7)and 1/2-ADM-164 7.0      PREREQUISITES 7.1      The user of this procedure shall be familiar with ODCM structure and format.
8.0      PROCEDURE 8.1      REMP Overview 8.1.1    Attachment A, Table 3.0-1 contains the site number, sector, distance, sample point description, sampling and collection frequency, analysis, and analysis frequency for various exposure pathways in the vicinity of the Beaver Valley Power Station for the REMP. Attachment B, Figures 3.0-1 through 3.0-6 show the location of the various sampling points.
8.2      Samplin! and Analysis Program 8.2.1    Environmental samples shall be collected and analyzed according to Attachment A, Table 3.0-1. Analytical techniques used shall be such that the detection capabilities in 1/2-ODC-3.03, Table 4.12-1 are achieved.
8.2.2    The results of the radiological environmental monitoring are intended to supplement the results of the radiological effluent monitoring by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways.
 
Beaver Valley Power Station                                    Pm edurc Number          03
 
==Title:==
Unit:        Level Of Use:
ODCM: Radiological Environmental Monitoring Program                                  1/2      General Skill Reference Revision:    Page Number:
0                5 of Is 8.2.2.1      The specified environmental monitoring program provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of individuals resulting from the station operation.
8.2.2.2      The initial radiological environmental monitoring program should be conducted for the first 3 years of commercial operation (or other period corresponding to a maximum burnup in the initial core cycle). Following this period, program changes may be proposed based on operational experience.
8.2.3    Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons.
8.2.3.1      IF specimens are unobtainable due to sampling equipment malfunction, THEN every effort shall be made to complete corrective action prior to the end of the next sampling period.
8.2.3.2      All deviations from the sampling schedule shall be documented in the annual REMP report.
8.3      Crosscheck Program 8.3.1    The laboratories of the licensee and licensee's contractors which perform analyses shall participate in the Environmental Protection Agency's (EPA's) Environmental Radioactivity Laboratory Intercomparisons Studies (Crosscheck) Program or equivalent program.
8.3.1.1      This participation shall include all of the determinations (sample medium-radionuclide combination) that are offered by EPA and that also are included in the monitoring program.
8.3.1.2      The results of analysis of these crosscheck samples shall be included in the annual REMP report. The participants in the crosscheck program may provide their program code so that the NRC can review the participant data directly in lieu of submission in the annual REMP report.
8.3.1.3      IF the results of a determination in the crosscheck program are outside the specified control limits, THEN the laboratory shall investigate the cause of the problem and take steps to correct it. The results of this investigation and corrective action shall be included in the annual REMP report.
8.3.2    The requirement for the participation in the crosscheck program, is based on the need for independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices as part of the quality assurance program tor environmental monitoring in order to demonstrate the results are reasonably valid.
 
U-_
Procedure Number:
Beaver Valley Power Station                                                1/2-ODC-2.03 Tile:                                                                            Unit:        Level Of Use:
ODCM: Radiological Environmental Monitoring Program                                  1/2      General Skill Reference Revision:    PNge Number
                                                                                  .                    6Sof 18 8.4      Land Use Census Program 8.4.1    A census shall be conducted annually during the growing season to determine the location of the nearest milk animal, and nearest garden greater than 50 square meters (500 sq. ft.) producing broad leaf vegetation in each of the 16 meteorological sectors within a distance of 8 km (5 miles).
8.4.1.1      For elevated releases as defined in Regulatory Guide 1.11 1 the census shall also identify the locations of all milk animals, and gardens greater than 50 square meters producing broad leaf vegetation out to a distance of 5 km (3 miles) for each radial sector.
8.4.1.2      IF it is learned from this census that the milk animals or gardens are present at a location which yields a calculated thyroid dose greater than those previously sampled, or if the census results in changes in the location used in ODCM dose calculations, THEN a written report shall be submitted to the Director of Operating Reactors, NRR (with a copy to the Director of the NRC Regional Office) within 30 days identifying the new location (distance and direction).
8.4.1.2.1        Milk animal or garden locations resulting in higher calculated doses shall be added to the surveillance program-as soon as practicable.
8.4.1.3      The sampling location (excluding the control sample location) having the lowest calculated dose may then be dropped from the surveillance program at the end of the grazing or growing season during which the census was conducted. Any location from which milk can no longer be obtained may be dropped from the surveillance program after notifying the NRC in writing that they are no longer obtainable at that location.
8.4.1.4      The results of the land-use census shall be reported in the annual REMP report.
8.4.1.5      The census of milk animals and gardens producing broad leaf vegetation is based on the requirement in Appendix I of 10 CFR Part 50(3.2-1) 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.
8.4.1.5.1        IF the census reveals milk animals are not present or are unavailable for sampling, THEN vegetation must be sampled.
8.4.1.6      The 50 square meter garden, considering 20% used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and a vegetation yield of 2 kg/mi, will produce the 26 kg/yr assumed in Regulatory Guide 1.109(3 2), for child consumption of leafy vegetation.
 
                                                              ...            Procedurfe Number~
Beaver Valley Power Station                                                1/2-ODC-2.03
 
==Title:==
Unit:          Level Of Use:
ODCM: Radiological Environmental Monitoring Program                                1/2        General Skill Reference Revision:      Page Number n            ~7 of 18 8.5        Direct Radiation Monitoring Program 8.5.1    The increase in the number of direct radiation stations is to better characterize the individual exposure (mrem) and population exposure (man-rem) in accordance with Criterion 64 - monitoring radioactivity releases, of 10 CFR Part 50, Appendix A. The NRC will place a similar amount of stations in the area between the two rings designated in 1/2-ODC-3.03, Table 3.12-1.
                                                    -END-
 
TABLE 3.0-1 PROGRAM DETAILS EXPOSURE                                                          SAMPLING AND PATHWAY AND/OR  SITE              SAMPLE POINT                  COLLECTION          TYPE AND FREOUENCY SAMPLE          NO. SECTOR' MILES2 DESCRIPTION 3                  FREOUENCY          OF ANALYSES                                  0
                                                                                                                                          'W CD
: 1. AIRBORNE          13    11    1.4  Meyer's Fame                  Continuous sampler Radioiodine Cartridge:
Radioiodine and  30    4    0.5  Shippingport (S.S.)            operation with      1-131 analysis weekly.            M              CD Particulates                                                      collection at least                                    0 32    15    0.8  Midland (S.S.)
weekly              Particulate Sampler: Gro! 3s      C        Oi 46.1  3    2.3  Industry, Midway Dr.
beta analysis following fil ter                  ct Pd 48    10    16.3  Weirton, W. Va., Weirton change 5 ; Gamma isotopic Water Tower, Collier Way4                                                                            0 analysis on composite (by location) quarterly.
I
                                                                                                                                            ,t 0
: 2. DIRECT RADIATION  10    3    1.0  Shippingport Boro              Continuous          Gamma dose quarterly.                            0 13    ll    1.4  Meyer's Farm                  measurement with 14    ll    2.5  Hookstown                      quartcrly                                                            C/)
15    14    3.7  Georgetown Post Office        collection.
0 o~v 27    7    6.1  Brunton's                                                                            En 28    1    8.6  Sherman's Farm 29B    3    8.0  Beaver Valley Geriatric Center 30    4    0.5  Shippingport (S.S.)
32    15    0.8  Midland (S.S.)                                                                        t>o      c-t
                                                                                                                                            =.W 45    5    2.2  Rt. 18 & Anderson Street                                                                            0>0 45.1  6    1.9  Raccoon Twp., Kennedy's Corner 46    3    2.5  Industry, Midway Drive                                                                      30 46.1 47 3
14 2.3 4.9 Industry, Rt. 86 - Garage East Liverpool, OH Water IW        CA
_e Treatment Plant 48    10    16.3  Weirton, W. Va., Weirton                                                                              r-3 Water Tower, Collier Way z
51    5    8.0  Aliquippa (S.S.)                                                                                    O. r 59    6    1.0  236 Green Hill Rd.
60    13    2.5  444 Hill Road 70      1    3.4  N. of Western. Beaver School-Engle Rd.
71    2    6.0  Brighton Twp., First Western                                                                    (b n'
Bank                                                                                              n
( J2                                                    ()                                                                (' )
I
 
(,.2                                                      I!
Y 0 i TABLE 3.0-1                                                                            _C) to!
PROGRAM DETAILS EXPOSURE                                                            SAMPLING AND                                                _R.
PATHWAY AND/OR  SITE                SAMPLE POINT                    COLLECTION      TYPE AND FREOUENCY SAMPLE          NO. SECTOR' MILES 2 DESCRIPTION 3                  FREOUENCY        OF ANALYSES                                        a 0T0      CD
: 2. DIRECT RADIATION  72    3    3.3  Industry, Logan Park            Continuous      Gamma dose quarterly.
(continued)      73    4    2.5  618 Squirrel Run Road          measurement with                                                    q 74    4    7.0  CCBC, 137 Poplar Avenue        quarterly                              .0 75    5    4.1  117 Holt Road                  collection.                              En
                                                                                                                                    ~1      CD 76    6    3.8  Raccoon Elementary School                                                                  &deg;),
77    6    5.6  3614 Green Garden Road                                                  5                  _.
78    7    2.7  Raccoon Municipal Building eQ.
79    8    4.4  Rt. 151 & Pross Ln.                                                      -OQ              tej      -t 80    9    8.2  Raccoon Park Office, Rt. 18                                              co                        0 81    9    3.6  Millcreek United Presb. Church                                          ,>.                :3 82    9    6.9  Hanover Municipal Building                                                                          C/)
83    10    4.2  735 Mill Creek Road                                                                                  A)-1 84    11    8.3  Hancock Parks & Recreation                                                                          ft+
Complex              --
85    12    5.7  Rts. 8 and 30 Intersection                                                                          0 86    13    6.2  East Liverpool, Oh., 1090 Ohio Avenue 87    14    7.0  Calcutta, Oh.- Calcutta Smith's Ferry Rd & Valley Drive                                                  I0 88    15    2.8  Midland Heights, 110 Summit                                                                        0Q Road                                                                      DtoH 89    15    4.8  Ohioville, 488 Smith's Ferry 90    16    5.2 Road Opposite Fairview School 1: c.
UJ a
91    2    3.9  Pine Grove & Doyle Roads                                                Am                              z 92    12    2.8  Georgetown Road (S.S.)                                                - i3            B.
93    16    1.1  Midland - Sunrise Hills                                                                                ta 94    8    2.2  McCleary Road & Pole Cat                                                                        )Or 6
:3  n Hollow Road                                                                          CO
                                                                                                                                          'I) 95    10    2.3  832 McCleary Road                                                                      0
                                                                                                                              !4    _x C  0 a0 x
                                                                                                                                      ~p 3
0 I-.-.-
 
I-TABLE 3.0-1 (continued)
PROGRAM DETAILS 0.
EXPOSURE                                                                  SAMPLING AND PATHWAY AND/OR          SITE                SAMPLE POINT                  COLLECTION          TYPE AND FREQUENCY                          0 SAMPLE                  NO. SECTOR' MILES 2 DESCRIPTION'                  FREOUENCY            OF ANALYSES                                          W
: 3. WATERBORNE              49    3    5.0  Upstream side of Montgomery    Composite sample    Gamma isotopic analysis a) Surface (River)                          Dam 4                          with sample          monthly; tritium analysis on tTj            CD        CD.
collection at least  composite (by location)      0 2.1 14    1.5  Downstream, Midland -J&L      monthly 6 .          quarterly.                    Cn                      P 0        x--
CD b) Drinking Water          4  15    1.3    Midland Water Treatmcnt Plant Composite sample    1-131 analysis bi-weekly;                eq.        0 R
5  14    4.9    East Liverpool, Oh.,          with sample          gamma isotopic analysis on                  0 Water Trcatment Plant        collection at Icast  composite (by location)                    e-bi-weckly 6.        monthly; tritium analysis on composite (by location)                              (D quarterly.
c) Ground Water                              None required 7                                                                            o pa CWLJ Gamma isotopic analysis
                                                                                                                                    >e O:s-d) Shoreline Sediment      2A  13    0.2    BVPS Outfall Discharge        Semi-annually.
semi-annually.
I' 4,0      =
: 4. INGESTION                25    10    2.1    Searight's Farm              At least bi-weekly  Gamma isotopic and I-131              ao(D
                            *8                                              when animals are    analysis on each sample.
a) Milk                        __
                            *8    _                                                                                                          00 on pasture; at least
                            *8                                              monthly at other 96    10    10.4    Windsheimer's Farm4          times.                                              M.
B..
b) Fish                    2A  13    0.2    BVPS Outfall Discharge        Semi-annually        Gamma isotopic analysis.                                z one sample of        On edible portion.
gn available species.                                                      63 49      3    5.0    Upstream side of Montgomery Dam                                                                                                    k) a t:
0 c) Foc d Products                    --    Three (3) locations within 5  Annually at harvest Gamma isotopic and 1-131 (Leeafy Vegetables)              --    miles of BVPS (Shippingport,  time.                analysis on edible portion.
                                        --    Industry, and Georgetown) 9 One (1) control location                                                                        0 (Weirton, W. Va. area) 9 I  T ~
(9)                                                            (I
 
(-9.                                                            _(
TABLE 3.0-1 (continued)
PROGRAM DETAILS EXPOSURE                      SITE SECTORt MILES 2 SAMPLE POINT                                SAMPLING AND TYPE AND FREOUENCY PATHWAY AND/OR                NO.                          DESCRIPTION 3                      COLLECTION          OF ANALYSES SAMPLE                                                                                          FREOUENCY                                                o        d 0*      CD l Sector numbers l-16 correspond to the 16 compass direction sectors N        - NNW.                                                                    3
                                                                                                                                                  '0 2
Distance (in miles) is as measured from BVPS Unit I Containment Building.
3-3 All Sample Points, unless otherwise noted, are in the Commonwealth of Pennsylvania. Maps showing the approximate locations of the Sample Points are provided as Attachment B. Figures 3.0-1 through 3.0-6.
4                                                                                                                                                        0 This is a Control Station and is presumed to be outside the influence of BVPS effluents.
sAgamma isotopic analysis is to be performed on each sample when the gross beta activity is found to be greater than l times the mean                    M of the Control Station sample.                                                                                                                  >      Z' 6                                                                                                                                                                C)
Composite samples are obtained by collecting an aliquot at intervals not exceeding 2 hours. For the upstream surface water location site        CC2 49, a weekly grab sample, composited each month based on river flow at time of sampling 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 s6urces in the area. .
3 These Sample Points will vary and are chosen based upon calculated annual deposition factors (highest).
9Exact location may vary due to availability of food products.                                                                                              C 0
                                                      .  ,,                                                    ,                                        n        .%
Cb
 
                                                                                                                              ~-ffi_
Ir                                  -                    -
Procedure Number:
Beaver Valley Power Station                                                      l/2-ODC-2.03
 
==Title:==
Unit:          Level Of Use:
ODCM: Radiological Environmental Monitoring Program                                1/2        General Skill Reference Revision:      Page Number              to' 0                I? of Is ATTACHMENT B Page 1 of 7 LOCATION OF SAMPLING SITES FIGURE 3.0-2 AIR SAMPLING LOCATIONS 1,<-I Sector - Site #  Distance (miles)  Location 11      13              1.4        Meyer's Farm 4      30              0.5        Shippingport (S. S.)
15      32              0.8        Midland (S.S.)
3      46.1            2.3        Industry, Rt. 68 Garage 10      48    1        16.4        Weirton, W. Va.,-Weirton Water Tower, Collier Way
 
Beaver Valley Power Station                      Procedure Num        C2    0 3 rTitle:                                                  Unit:        Level Of Use:
ODCM: Radiological Environmental Monitoring Program            1/2      General Skill Reference Revision:    Page Number.
0                13 of 18 ATTACHMENT B Page 2 of 7                                            I LOCATION OF SAMPLING SITES FIGURE 3.0-2 (continued)
ThIDLOCATIONS
 
                                                                                                                                    ~-1,-
Beaver Valley Power Station                                                            1/2-ODC-2.03
 
==Title:==
Unit:        Level Of Use:
ODCM: Radiological Environmental Monitoring Program                                                1/2      General Skill Reference Revision:    Page Number n                14 of 18 ATTACHMENT B Page 3 of 7 LOCATION OF SAMPLING SITES FIGURE 3.0-2 (continued)
TLD LOCATIONS Southeast Sector Site # Distance                      Location            _ Sector Site # Distance                      Location (miles)    __                                                    (miles) 7        27      6.1    Brunton's Farm                    ^'      7    78        2.7    Raccoon Municipal Bldg.
6        45.1      1.9    Raccoon Twp., Kennedy Corners Y            8    79        4.4    Rt. 151 & Pross Ln.
5        51      8.0    Aliquippa (S.S.)                  &#xa3;i      9    80      8.2    Raccoon Park Office-Rt. 18 6        59        1.0    236 Green Hill Road                        9    82      6.9    Hanover Municipal Building 6        76      3.8    Raecoon Elementary School                  8    94        2.2    McCleary Road &
                                                                ,--'                            Pole Cat Hollow Road 6        77      5.6      3614 Green Garden Road            _                _
Northwest Sector Site # Distance                      Location                  Sector Site # Distance                  Location (miles)    .                                            ____    (miles) 14        15      3.7    Georgetown Post Office                    14    87      7.0    Calcutta, Oh. - Calcutta Smith's
                                                                . __                        Ferry Rd & Valley Drive 15        32      0.8    Midland (S.S.)                            15    88      2.8    Midland Heights - 110 Summit Rd 14        47      4.9      E. Liverpool, Oh.                        15    89      4.8    Ohioville - 488 Smith's Ferry Road (Water Company)                        _        _
13        60      2.5      Haney's Farm                              16    90      5.2      Opposite Fairview School 13        86      6.2    E. Liverpool. Oh., 1090 Ohio              16    93        1.1    Midland - Sunrise Hills Avenue                                  _
Northeast Sector Site        Distance                Location                  Sector Site #Distance                    Location
_        (miles)                                                    ___    (miles) l__
4        10        1.0    Shippingport Boro                          1    70        3.4    North of Western Beaver School -
I__    0              Engle Road 1        28      8.6    Sherman's Farm                            2    71        6.0    Brighton Twp., First Western Bank 3        29B      8.0    Beaver Valley Geriatric Ctr.              3    72        3.3    Industry, Logan Park 4  . 30      0.5      Shippingport (S.S.)                        4    73      2.5      618 Squirrel Run Road 5        45      2.2      Rt. 18 & Anderson Street          i        4    74      7.0      CCBC - 137 Poplar Avenue 3        46      2.5      Industry, Midway Drive                    5    75      4.1      117 Holt Road 3        46.1    2.3      Industry, Rt. 68 - Garage          '      2    91        3.9. Pine Grove Rd. & Doyle Rd.
Southwest Sector Site #Distance                      Location                  Sector Site #Distance                    Location (miles) l                                                ___    (miles) ll 11        13        1.4    Meyer's Farm                              11    84        8.3    Hancock Co. Parks & Recreation Complex 11        14      2.5    lHookstown                                12    85      5.7    IRts. 8 & 30 Intersection 10        48    16.3      Weirton, W. Va., - Weirton                12    92      2.8      Georgetown Road
_    _    __    _        _ lWater Tower, Collier Way                _        _      _
9        81      3.6    Millcreek United Presb. Church            10    95        2.3    832 McCleary Road 10        83      4.2      735 Mill Creek Road            l
 
Procedure Number Beaver Valley Power Station                                              1/2-ODC-2.03 Title.                                                                    Unit:          Level Of Use:
ODCM: Radiological Environmental Monitoring Program                          1/2      I General Skill Reference Revision:    Page Number:
0                a5  of 18 ATTACHMENT B Page 4 of 7 LOCATION OF SAMPLING SITES FKIURE3.0-3 SHORELINF. SEDIMENT SURFACEWATER, AN DRINKING WAhR SAMPLING LOCATIONS
.N Water/Shoreline Sediment Sampling Locations Sample Type - Sector  Site #  Distance (miles)                Location Surface Water    14      2.1    -    1.5      Downstream, Midland - J&L Surface Water    3    49            5.0      Upstream side of Montgomery Dam
  )          Sediment        13      2A          0.2      BVPS Outfall Discharge Drinking Water  15      4            1.3      Midland Water Treatment Plant Drinking Water  14      5 -      -  4.9      E. Liverpool, Oh. Water Treatment Plant
 
                                                      -~~~~~~~~~~~~~~                                                        U - dd Beaver Valley Power Station                                              Procedure Number:
 
==Title:==
Unit:        Level Of Use:
ODCM: Radiological Environmental Monitoring Program                                    1/2        General Skill Reference Revision:    Page Number 0                16 of I 8 ATTACHMENT B Page 5 of 7 LOCATION OF SAMPLING SITES FIGURE 3.0-4 MILK SAMPLING LOCAT1ONS 7'_
Milk Sampling Locations Sector  Site #      Distance (miles)                Location 10      25*              2.1                Searight's Farm 10      96              10.4                  Windsheimer Farm
                                                *I
                          *Three dairies based on highest deposition factors.
 
Prbocedure Number Beaver Valley Power Station                                    e/-DC20
 
==Title:==
Unit:          Level Of Use:
ODCM: Radiological Environmental Monitoring Program                        1/2        General Skill Reference Revision:      Page Number:
(0                17 Of 18 ATTACHMENT B Page 6 of 7 LOCATION OF SAMPLING SITES FIGURE 3.0-5 FOODCROP SAMPLING LOCATIONS Food Sampling Locations Site #            Description 10      Shippingport Boro-15      Georgetown Post Office 46      Industry, Midway Dr.    -
                                - 48      Weirton, W. Va., - Weirton -
I Water Tower, Collier Way
 
U-_
Beaver Valley Power Station Tiale:
ODCM: Radiological Environmental Monitoring Program
 
A9.621B Beaver Valley Power Station Unit 1/2 112-ODC-2.04 ODCM: Information Related to 40 CFR 190 Document Owner Manager, Health Physics Revision Number                                        0 Level Of Use                                General Skill Reference Safety Related Procedure                              Yes
 
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B            e    V        l        Pwer  Statn                Procedure Number:
Beaver V alley Power Station1/2-ODC-2.04
 
==Title:==
Unit            Level Of Use:
1/2        General Skill Reference ODCM: Infornation Related to 40 CFR 190                                      Revision:      Page Number 0                  2of6 TABLE OF CONTENTS 1.0  PURPOSE ..................................                                                                  3 2.0  SCOPE ...................................                                                                  3
 
==3.0  REFERENCES==
AND COMMITMENTS ...............................              ..                                3 4.0  RECORDS AND FORMS ....................................                  ...                                3 5.0  PRECAUTIONS AND LIMITATIONS ...................................                                            4 6.0  ACCEPTANCE CRITERIA ...................................                                                    4 7.0  PREREQUISITES ...................................                                                          4 8.0  PROCEDURE ...................................                                                              4 8.1 Information Related To 40 CFR 190 ...............................            ;.4 8.2 Inside The Site Boundary Radiation Doses                                    .5
 
Procedure Number:
Beaver Valley Power Station                                              1/2-ODC-2.04
 
==Title:==
Unit:        Level Of Use:
1/2      General Skill Reference ODCM: Information Related to 40 CFR 190                                        Re.ision:    PageNumber
____________________I___________3__                                                of6 1.0        PURPOSE 1.1      This procedure provides the steps to be taken when the Total Dose of ODCM Control 4.11.4.1 exceeds twice the limit of any of the ODCM Controls specifying an Offsite Dose
      -      Limit.(3.1.2) 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    112-ODC-3.03, ODCM: Controls for RETS and REMP Programs 3.1.3    1/2-ADM-1640, Control of the Offsite Dose Calculation Manual 3.1.4    1/2-ADM-0100, Procedure Writer's Guide 3.1.5    1/2-ADM-0101, Review and Approval of Documents l
3.2        Commitments 3.2.1    Technical Specification 6.9.2f, Special Reports 3.2.2    NUREG-1301, Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors (Generic Letter 89-01, Supplement No.
1) 4.0      RECORDS AND FORMS 4.1        Records 4.1.1    Any calculation supporting ODCM changes shall be documented, as appropriate, by a retrievable document (e.g.; letter or calculation package) with an appropriate RTL number.
4.2      Forms 4.2.1    None
 
M-I Procedure Number~
Beaver Valley Power Station                                              1/20DC2.04
 
==Title:==
Unit:        Level Of Use:
1/2        General Skill Reference ODCM: Information Related to 40 CFR 190                                        Revision:    Page Number:
0                41f4 5.0        PRECAUTIONS AND LIMITATIONS 5.1        The Offsite Dose Limits used to show compliance to this procedure are as follows:
5.1.1    ODCM Control 3.11.2.a; Liquid Effluents: < 1.5 mrem/quarter Total Body or < 5 mremlquarter 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 mradlquarter Gamma, or < 10 mradlquarter Beta 5.1.4    ODCM Control 3.11.2.2.b; Gas Effluents-Noble Gas: < 10 mrad/year Gamma < 20 mradlyear Beta 5.1.5    ODCM Control 3.11.2.3.a; Gas Effluents-Particulates & Iodines: < 7.5 mremlquarter any organ 5.1.6    ODCM Control 3.11.2.3.b; Gas Effluents-Particulates & Iodines: < 15 mrem/year any organ                                                                                                [-N 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 < 75 mrem/year 6.0        ACCEPTANCE CRITERIA 6.1        Any changes to this procedure shall contain sufficientjustification that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR 50, and not adversely impact the accuracy or reliability of effluent dose or setpoint calculation.(3. 2 2 6.1.1    All changes to this procedure shall be prepared in accordance with 1/2-ADM-010013 14 )
and 1/2-ADM-1640.( 3 l3 )
6.1.2    All changes to this procedure shall be reviewed and approved in accordance with 1/2-ADM-0 101(31 and 1/2-ADM- 1640.(3 1.3) 7.0        PREREQUISITES 7.1        The user of this procedure shall be familiar with ODCM structure and content.
8.0        PROCEDURE 8.1        Information Related To 40 CFR 190 8.1.1    CONTROL 3.11.4.1 requires that when the calculated doses associated with the effluent releases exceed twice the limits of ODCM CONTROL 3.11.1.2.a, 3.11.1.2.b, 3.11.2.2.a, 3.11.2.2.b, 3.11.2.3.a, or 3.11.2.3.b, the following shall be performed:
 
Beaver Valley Power Station                                      ProcedureNumbe
 
==Title:==
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1/2      General Skill Reference ODCM: Information Related to 40 CFR 190                                            Revision:    Page Number:
I_0        ____of6 8.1.1.1        Calculations shall be made including direct radiation contributions from the units (including outside storage tanks, etc.) to determine whether the dose or dose commitment to any MEMBER OF THE PUBLIC from all facility releases of radioactivity and to radiation from uranium fuel cycle sources exceeds the limits of
                        < 25 mrem to the total body or any organ, except the thyroid, which is limited to <
75 mrem for a calendar year.
8.1.1.1.1      If any of these limits are exceeded, prepare and submit to the Commission within 30 days a Special Report pursuant to Technical Specification 6.9.2f.13-2 1 The following shall be included in the Special Report:
8.1.1.1.1.1        Define the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the limits of ODCM CONTROL 3.11.4.1.
Include the schedule for achieving conformance within the limits of ODCM CONTROL 3.11.4. 1.
8.1.1.1.1.5        Include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar 8.1.1.1.1.3 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.
8.1.1.1.1.5        If the estimated dose(s) exceeds the limits of ODCM CONTROL 3.11.4.1, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, include a request for a
  '                                  variance in accordance with the provisions of 40 CFR Part 190.
Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.
8.2        Inside The Site Boundary Radiation Doses 8.2.1    In regards to assessment of radiation doses (from Radioactive Effluents) to MEMBERS OF THE PUBLIC due to their activities inside the site boundary, the following is provided:
8.2.1.1      A separate assessment of radiation doses from radioactive effluents to MEMBERS OF THE PUBLIC due to their activities inside the site boundary is generally not necessary because the exposure time for individuals not occupationally associated with the plant site is minimal in comparison to the exposure time considered for the dose calculation at or beyond the site boundary.
 
M-Beaver Valley Power Station                                          PDC-2.04    1/2O
 
==Title:==
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ODCM: Information Related to 40 CFR 190                                            Revision:      Page Number:
0                  6_f6 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 forDose                X/Q Where an Assumed                      X/Q References Calculation              MEMBEROFTHEPUBI1C                                  fiom Would Most Likely Have the Maximum                  b2-ODC-202 Excpc zuimeh SiteBoundaiy          Inside the Site          Inside the Site      See Attachrent F 0352 milesNW              Bounday                  Boundary 0-05 niles N          0-05 miles NNW 924E-5 soclhr          233E-5 sechin            5.47E-5 secW              Table 2.24 1.03E4 se&ch    n      2.76E-5 sechm            6.01I5 sec/i  3          Table 22-5 735E-5 sechr 3          244E-5 sec/i    3        5.57E-5 secn  3          Table 22-7 924E-5 sech&            2.33E-5 sechn3            5.47E-5 scm&              Table 2.2-924E-5 sen    3        23313E5sech    3        5.47E-5sw? 3              Table 2.2-9 735E-5 sec/ 3          2.44E-5 sechr 3          557E-5 se&h            Table 2.2-10
                                                        - END -
 
A9.621B Beaver Valley Power Station Unit 1/2 1/2-ODC-3.01 ODCM: Dispersion Calculational Procedure and Source Term Inputs
. A Document Owner Manager, Health Physics Revision Number                                        0 Level Of Use                                General Skill Reference Safety Related Procedure                              Yes
 
r                                                                                                          berg
 
==Title:==
1/2          General Skill Reference Iputs Revision:        Page Number:
ODCM: Dispersion Calculational Procedure and Source Term Inp                                                      2 of 12 TABLE OF CONTENTS 1.0  PURPOSE .................................................                                                                3 2.0  SCOPE ...............................................                                                                    3 3.0  REFEFERENCES AND COMMITMENTS ................................................                                            3 3.1  References .................................................                                                        3 3.2 Commitments .................................................                                                        4 4.0 RECORDS AND FORMS ................................................                                                        4 4.1  Records ................................................                                                            4 4.2 Forms ................................................                                                              4 5.0 PRECAUTIONS AND LIMITATIONS .................................................                          ;.                4 6.0 ACCEPTANCE CRITERIA ................................................                                                      4 7.0 PREREQUISITES ................................................                                                            4 8.0 PROCEDURE .................................................                                                                5 8.1  Summary of Dispersion and Deposition Methodology ................................................                  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..
                                                                                                        ..                        9 ATTACHMENT C GASEOUS SOURCE TERM INPUTS                                                .        .          .11
 
Beaver Valley Power Station                                  Procedu0reNumber
 
==Title:==
Unit:        Level Of Use:,
1/2      General Skill Reference ODCM: Dispersion Calculational Procedure and Source Term Inputs                Revision:    Page Number:
I_- 0____                  of 12 1.0        PURPOSE 1.1      This procedure contains the basic methodology that was used for calculating dispersion (X/Q) and deposition (DIQ).
1.1.1    Prior to issuance of this procedure, these items were located in Appendix A of the old ODCM.
1.2      This procedure also contains the input parameters to the various computer codes used by the
  .        Licensee and its subcontractors for determination of the liquid and gaseous source term mixes.
1.2.1    Prior to issuance of this procedure, these items were located in Appendix B of the old ODCM.
2.0        SCOPE 2.1        This procedure is applicable to all station personnel (including subcontractors) that are qualified to perform activities as described and referenced in this procedure.
3.0        REFEFERENCES AND COMMITMENTS 3.1        References 3.1.1    NUS-2173,Development Of Terrain Adjustment Factors For Use At the Beaver Valley 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 1.1 11, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents In Routine Releases From Light-Water-Coded Reactors, Revision 1, July 1977 3.1.5    NRC Gale Code, 3.1.6    SWEC LIQ1BB Code, 3.1.7    SWEC GAS1BB 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) 3.1.9      1/2-ADM-1640, Control of the Offsite Dose Calculation Manual
 
l-
: 1. .i !
Procedure Number:                            i
                --Beaver Valley Power Station                                              -1/2-ODC-3.Ol                    I I
litle:                                                                          Unit:          Level Of Use:
1/2      General Skill Reference ODCM: Dispersion Calculational Procedure and Source Term Inputs                Revision:      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 of Documents 3.2        Commitments 3.2.1    None 4.0        RECORDS AND FORMS 4.1        Records 4.1.1    Any calculation supporting generation of dispersion, deposition, or source term mixes shall be documented, as appropriate, by a retrievable document (e.g.; letter or calculation package) with an appropriate RTL number.
4.2      Forms 4.2.1    None 5.0        PRECAUTIONS AND LIMITATIONS 5.1      This procedure contains the information that was previously contained in Appendix A and Appendix B of the previous BV-1 and 2 Offsite Dose Calculation Manual.
5.1.1    In regards to this, the Tables that were transferred from Appendix A and Appendix B to the appropriate 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 will maintain the level of radioactive effluent control required by 10 CFR 20.1302,40 CFR Part 190, 10 CFR 50.36a and Appendix I to 10 CFR 50, and not adversely impact the accuracy or reliability of effluent dose or setpoint calculation.
6.1.1    All changes to this procedure shall be prepared in accordance with 1/2-ADM-0100( 3 ''0 &
and 1/2-ADM-1640.t 3'l 9 )
6.1.2    All changes to this procedure shall be reviewed and approved in accordance with 1/2-ADM-010 10 3 '' ') and 1/2-ADM-1640 .(31.9) 7.0      PREREQUISITES 7.1      The user of this procedure shall be familiar with ODCM structure and content.
 
            - Beaver Valley Power Station                                          edureNum2-ODC-3.
 
==Title:==
.                                                                  Unit:      Level Of Use:
1/2    General Skill Reference ODCM: Dispersion Calculational Procedure and Source Term Inputs                  Revision:  Pae Num      f 12 8.0        PROCEDURE 8.1        Summary of Dispersion and Deposition Methodology 8.1.1    Annual average and grazing season average values of relative concentration (X/Q) and deposition (D/Q) were calculated for continuous and intermittent gaseous releases of activity from the site according to the straight-line airflow (Gaussian) model described in RG-1. I Il 1 8.1.1.1      Undecayed and undepleted sector average XIQ and D/Q values were obtained for each of sixteen 22.5-degree sectors at the site boundary and maximum individual receptors.
8.1.1.2      For an elevated release, (i.e.; occurring at a height that is twice the height or more of a nearby structure) credit was taken for the effective release height which is comprised of the physical release height plus momentum plume rise minus the terrain height at a given receptor.
8.1.1.3      A building wake correction factor was used to adjust calculations for ground-level releases.
8.1.1.4      Airflow reversals were also accounted for by applying site-specific terrain recirculation factors for both ground and elevated releases at the site. t3 ''
8.1.1.5      The methodology employed in the calculation of intermittent release X/Q and D/Q values is that described in NUREG/CR-2919.(3.l 2) 8.1.2    The site continuous gaseous release points that have been evaluated include the following:
8.1.2.1      PV-1/2: The Unit 1/2 Gaseous Waste/Process Vent attached to the Unit 1 natural draft cooling tower 8.1.2.2      CV-1 and CV-2: The Unit 1 Rx Containment/SLCRS Vented the Unit 2 SLCRS Filtered Pathway 8.1.2.3      VV-1 and VV-2: The Unit 1 Ventilation Vent and the Unit 2 SLCRS Unfiltered Pathway 8.1.2.4      TV-2: The Unit 2 Turbine Building Vent 8.1.2.5      CB-2: The Unit 2 Condensate Polishing Building Vent 8.1.2.6      DV-2: The Unit 2 Decontamination Building Vent 8.1.2.7      WV-2: The Unit 2 Gaseous Waste Storage Tank Vault Vent 8.1.3    The intermittent releases are from PV-1/2, VV-1, VV-2, CV-1 and CV-2.
 
                                                                                                                    'I-Beaver Valley Power Station                                    edureNu2-ODC-3.0
 
==Title:==
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_ _  _  _ _  _Inputs__    _ _  _  _ _  _ _  _    _6                            of 12 8.1.4    Only PV-1/2 was considered to be an elevated release with all other release points being treated as ground level releases. A summary of the release characteristics and their locations is given in ATTACHMENT A.
8.1.5    Onsite meteorological data for the period January 1, 1976 through December 31, 1980 were used as input for the annual-average calculations.
8.1.5.1      The grazing season was represented by a six-month period from May I through October 31 for each year of the 5-year meteorological data base. This grazing season corresponds reasonably well with the growing season.
8.1.5.2      The data were collected according to guidance in NRC RG-1.23      3 .13 2  as described in Section 2.3 of the BVPS-2 FSAR.
8.1.5.3      The parameters used in the XIQ 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 XIQ and D/Q values for the continuous and intermittent radioactive releases were calculated at the site boundary, nearest resident, nearest vegetable garden, nearest milk cow, nearest milk goat, and nearest meat animal.
8.1.6.1      In the case of the Process Vent releases, several of each receptor type were evaluated in each downwind sector to determine the maximum X/Q and DIQ values.
8.1.6.2      The distances of the limiting maximum individual receptors from the radioactive release points are given in ATTACHMENT E (Table 2.2-3) of 1/2-ODC-2.02.
8.1.6.3      The continuous release annual average X/Q values at the special locations for the Containment Vents, Ventilation Vents, Process Vent, Turbine Building Vents, Decontamination Building Vent, Waste Gas Storage Vault Vent, and Condensate Polishing Building Vent are given in ATTACHMENT F (Tables 2.2-4 through 2.2-10) of 1/2-ODC-2.02. Continuous release annual average X/Q's for these same release points are also given at ten incremental downwind distances of 0-5 miles.
8.1.6.4      Continuous release D/Q values for these same release points are given in ATTACHMENT K (Tables 2.3-21 through 2.3-27) of 1/2-ODC-2.02 for the same 0-5 mile incremental distances, and in ATTACHMENT L (Tables 2.3-28 through 2.3-34) of 1/2-ODC-2.02 for the special locations.
8.1.6.5      Due to their location adjacent to the Containment Building, the Decontamination Building and Gaseous Waste Storage Tank Vault X/Q's and D/Q's are the same as the Containment Vent X/Q's and D/Q's.
 
Procedure Number:
Beaver Valley Power Station                                  edu-eDC-ber
 
==Title:==
Unit          Level Of Use:
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_ __ __ _ __ __ _ _ _ _ _ _  _  _  _  _  _  _  _  _                            7o f 12 8.1.6.6      Likewise, the Turbine Building Vent %/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 1/2-ODC-2.02 contain short term
                %/Q 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 hours per year of Containment and Ventilation Vent purges and 74 hours per year of Process Vent purges.
8.2      Summary of Source Term Inputs 8.2.1    Liquid Source Term Inputs 8.2.1.1      Inputs to the NRC Gale Code used for generation of BV-1 Liquid Source Term Mixes are shown in ATTACHMENT B (Table B:la).
8.2.1.2      Inputs to the SWEC LIQIBB Code used for generation of BV-2 Liquid Source Term Mixes are shown in ATTACHMENT B (Table B:lb) 8.2.2    Gaseous Source Term Inputs 8.2.2.1      Inputs to the SWEC GAS 1BB Code for generation of BV-1 Gaseous Source Term Mixes are shown in ATTACHMENT C (Table B:2a) 8.2.2.2      Inputs to the SWEC GAS 1BB Code for generation of BV-2 Gaseous Source Term Mixes are shown in ATTACHMENT C (Table B:2b)
 
                                                                                                              -I--
Beaver Valley Power Station                  -          edurcNun  r.0 DC  3 0 1
 
==Title:==
Unit      Level Of Use:
1/2    General Skill Reference ,-
ODCM: Dispersion Calculational Procedure and Source Term Inputs        Revision:  Page Number ATTACHMENT A Page 1 of 1 BV-1 AND 2 RELEASE CONDITIONS TABLEAA 1 VV-1                CV-I RX          PV-1/2 GASEOUS        TV-2 TURBINE VENTILATION          CONTAINMENTI      WASTE/PROCESS        BUILDING VENT VENT (PAB            SLCRS VENT        VENT EXHAUST)
VV-2 SLCRS          CV-2 RX UNFILTERED          CONTAINMENT/
PATHWAY              SLCRS FILTERED PATHWAY TYPE OF RELEASE        GROUND LEVEL        GROUND LEVEL        ELEVATED            GROUND LEVEL LongTerm And        IixgTerm And      LongTerl And          LongTerm And ShortTerm          ShortTerm.      ShortTerm              ShortTerm ReleasePointHeight                26                  47              155                      33 (m)
AdjaeilBuilding                  19                  44              155                      33 Height (m)
RelafiveLocationTo      ESideOfPfimay        Top CenterOf      AtopCoolingTower      TubineBuildng AcdjentStaxies          AuxiliaryBldg        Con i ntDome ExDtVdlocivinsec)                NA                  NA                9.4                      NA IntemalStack                    NA                  NA              025                      NA Diameter (m)
BuildingCis-                    1600                1600            NA                        NA Secdional Area (in)
PurWEequeny                      32                  32              74-                      NA Pul Durafion                      8                    8              NA                        NA (hlease)
*Applied to ShoitTeim calculation only
 
Beaver Valley Power Station                                                        1/2e DC-3.01 TiLle:                                                                              Unit:            Level Of Use:
1/2          General Skill Reference ODCM: Dispersion Calculational Procedure and Source Term Inputs                      Revision        Page Number
__  _ _ __ _ _ _ __  __  _ _  _  _  _ _ _  _  _ _ _    _  _0                            9  f 12 ATTACHMENT B Page I of 1 LIQUID SOURCE TERM INPUTS TABLE B:la INPUTS TO GALE CODE FOR GENERATION OF BV-1 LIQUID SOURCE TERM MIXES BV-I PWR INPUTS                                              -VALUE Thermal Power Level (megawatts)                                                              2766.000 Plant Capacity Factor                                                                              .800 Mass Of Primary Coolant (thousand ibs)                                                        345.000 Percent Fuel With Cladding Defects                                                                .120 Primary System Letdown Rate (gpm)                                                              60.000 Letdown Cation Demnineralizer Flow                                                                6.000 Number Of Steam Generators                                                                        3.000 Total Steam Flow (million lbs/hr)                                                                11.620 Mass Of Steam In Each Steam Generator (thousand Ibs)                                              6.772 Mass Of Liquid In Each Steam Generator (thousand lbs)                                          97.000 Total Mass Of Secondary Coolant (thousand Ibs)                                              1296.000 Mass Of Water In Steam Generator (thousand ibs)                                              291.000 Blowdown Rate (thousand lbslhr)                                                                33.900 Primary To Secondary Leak Rate (lbs/day)                                                      100.000 Fission Product Carry-Over Fraction                                                                .001 Halogen Carry-Over Fraction                                                                    - .010 Condensate Demineralizer Flow Fraction                                                            0.000 Radwaste Dilution Flow (thousand gpm)                                                          22.500 BV-I LIQUID WASTE INPUTS COLLECTION DELAY          DECONTAMINATION FLOWRATE FRACTION FRACTION                        TIME        TIME              FACTORS STREAM      (gal/day)          OF PCA DISCHARGE            (days)    .(days)          I        Cs OTHERS Shim Bleed    1.32E4            1.000        0.000        11.260      7.220        1E7      1E7      1E7 Rate Equipment    6.00E2            1.000        0.000        11.260      7.220        1E7      1E7        1E7 Drains Clean Waste  7.50E1            1.000        1.000        0.071        0.648        lE5      2E4        IE5 Input Dirty Waste    1.35E3            0.035          1.000        0.071        0.648        lE5    2E4        IE5 Input Blowdown      9.75E4                          1.000        0.071        0.648        lE5    2E4        IE5 Untreated      0.0 Blowdown
 
Beaver Valley Power Station                                  oedureNumber:
 
==Title:==
Unit:        Level Of Use:
1/2      General Skill Reference ODCM: Dispersion Calculational Procedure and Source Term Inputs            Revision:    Page Number:
__Inputs        0                10 of 12 ATTACHMENT B Page 2 of 2 LIQUID SOURCE TERM INPUTS TABLE B:lb INPUTS TO SWEC LIQIBB CODE FOR GENERATION OF BV-2 LIQUID SOURCE TERM MIXES BV-2 PWR INPUTS                                          VALUE Thermal Power Level (megawatts)                                                    2766.000 Plant Capacity Factor                                                                    .800 Mass Of Primary Coolant (thousand Ibs)                                              385.000 Percent Fuel With Cladding Defects                                                      .120 Primary System Letdown Rate (gpm)                                                    57.000 Letdown Cation Demineralizer Flow                                                      5.700 Number Of Steam Generators                                                              3.000 Total Steam Flow (million lbs/hr)                                                    11.600 Mass Of Steam In Each Steam Generator (thousand Ibs)                                    8.700 Mass Of Liquid In Each Steam Generator (thousand ibs)                                100.000 Total Mass Of Secondary Coolant (thousand Ibs)                                    2000.000 Mass Of Water In Steam Generator (thousand Ibs)                                      298.000 Blowdown Rate (thousand lbs/hr)                                                      22.300 Primary To Secondary Leak Rate (lbs/day)                                            100.000 Fission Product Carry-Over Fraction                                                      .001 Halogen Carry-Over Fraction                                                              .010 Condensate Demineralizer Flow Fraction                                                  .700 Radwaste Dilution Flow (thousand gpm)                                                  7.800 BV-2 LIQUID WASTE INPUTS -
COLLECTION DELAY        DECONTAMINATION FLOW RATE FRACTION FRACTION              TIME    TIME            FACTORS STREAM            (gal/day) OF PCA        DISCHARGE      (hrs)      (hrs)    I    CsRb      OTHERS Containment            40        1.000        1.0        35.5      6.2  IE3        1E4        1E4 Sump Auxiliary            200      0.100          1.0        35.5
* 6.2    1E3        1E4        IE4 Building Sump Miscellaneous        700      0.010          1.0        35.5      6.2  IE3        IE4        IE4 Sources Rx Plant              35        1.000        1.0        35.5      6.2  IE3        IE4        IE4 Samples Lab Drains            400      0.002          1.0        35.5      6.2  1E3        1E4        IE4 Cond. Demin.        2685      1.1 E-4        1.0        35.5      6.2  1E3        1E4        IE4 Rinse Water CVCS                  60                      1.0        1300      173  1E4      4E3          IE5 Turbine              7200                      1.0 Bldg.Drains
 
Beaver Valley Power'Station                                            eNu2-ODd 3 Ol
 
==Title:==
Unit:      Level Of Use:
1/2    General Skill Reference ODCM: Dispersion Calculational Procedure and Source Term Inputs                Revision:      e Numbe1
_  __ _  __  __  _ _ _ _  _  _  _  _    _ _ _  _ _ _0                      11 of 12 ATTACHMENT C Page 1 of 1 GASEOUS SOURCE TERM INPUTS
.                                                        TABLE B:2a                    .
  -    INPUTS TO SWEC GAS 1BB CODE FOR GENERATION OF BV-1 GASEOUS SOURCE TERM MIXES BV-1 PWR INPUTS                                      VALUE Thermal Power Level (megawatts)                                                          2766.000 Plant Capacity Factor                                                                            .800 Mass Of Primary Coolant (thousand Ibs)                                                      385.000 Percent Fuel With Cladding Defects                                                                .120 Primary System Letdown Rate (gpm)                                                            57.000 Letdown Cation Demineralizer Flow                                                              5.700 Number Of Steam Generators                                                                    -3.000 Total Steam Flow (million lbslhr)                                                            11.600 Mass Of Steam In Each Steam Generator (thousand Ibs)                                            8.700 Mass Of Liquid In Each Steam Generator (thousand Ibs)                                      100.000 Total Mass Of Secondary Coolant (thousand Ibs)                                            2000.000 Mass Of Water In Steam Generator (thousand Ibs)                                            298.000 Blowdown Rate (thousand lbslhr)                                                              52.000 Primary To Secondary Leak Rate (lbs/day)                                                    100.000 Fission Product Carry-Over Fraction                                                              .001 Halogen Carry-Over Fraction                                                                      .010 Condensate Demineralizer Flow Fraction                                                      . 0.000 Radwaste Dilution Flow (thousand gpm)                                                        15.000 BV-I GASEOUS WASTE INPUTS                                      VALUE There Is Not Continuous Stripping Of Full Letdown Flow Hold Up Time For Xenon (days)                                                                  39.000 Hold Up Time For Krypton (days)                                                                  2.000 Primary Coolant Leak To Auxiliary Building (lb/day)                                            160.000 Auxiliary Building Leak Iodine Partition Factor                                                  7.5E-3 Gas Waste System Particulate Release Fraction                                                    0.000 Auxiliary Building Charcoiodine Release Fraction                                                  1.000 Auxiliary Building Particulate Release Fraction                                                  1.000 Containment Volume (million cu-ft)                                                                1.800 Frequency Of Primary Coolant Degassing (times/yr)                                                2.000 Primary To Secondary Leak Rate (lb/day)                                                        100.000 There Is A Kidney Filter Containment Atmosphere Cleanup Rate (thousand cfm)                                                2.000 Purge Time Of Containment (hours)                                                                8.000 There Is Not A Condensate Demineralizer Iodine Partition Factor (gaslliq) In Steam Generator                                              0.010 Frequency Of Containment Building High Vol Purge (times/yr)*                                      4.000 Containment Volume Purge Iodine Release Fraction                                                  1.000 Containment Volume Purge Particulate Release Fraction                                            1.000, Steam Leak To Turbine Building (lbslhr)                                                      1700.000 Fraction Iodine Released From Blowdown Tank Vent                                                  0.000 Fraction Iodine Released From Main Condensate Air Ejector                                        0.440 There Is Not A Crvogenic Off Gas System
        *2 cold and 2 hot purges
 
Beaver, I Procedure NumberS Beaver Valley Power Station                                                    12OC30
 
==Title:==
Unit:        Level Of Use:
1/2      General Skill Reference ODCM: Dispersion Calculational Procedure and Source Term Inputs 1
Revision:    Page Number 12 o12 ATTACHMENT C Page2 of 2 GASEOUS SOURCE TERM INPUTS TABLE B:2b INPUTS TO SWEC GAS IBB CODE FOR GENERATION OF BV-2 GASEOUS SOURCE TERM MIXES BV-2 PWR INPUTS                                            VALUE Thermal Power Level (megawatts)                                                                2766.000 Plant Capacity Factor                                                                                .800 Mass Of Primary Coolant (thousand Ibs)                                                          385.000 Percent Fuel With Cladding Defects                                                                    .120 Primary System Letdown Rate (gpm)                                                                57.000 Letdown Cation Demineralizer Flow                                                                  5.700 Number Of Steam Generators                                                                          3.000 Total Steam Flow (million lbs/hr)                                                                  11.600 Mass Of Steam In Each Steam Generator (thousand Ibs)                                                8.700 Mass Of Liquid In Each Steam Generator (thousand Ibs)                                            100.000 Total Mass Of Secondary Coolant (thousand lbs)                                                  2000.000 Mass Of Water In Steam Generator (thousand Ibs)                                                  298.000 Blowdown Rate (thousand lbslhr)                                                                  22.300 Primary To Secondary Leak Rate (lbs/day)                                                        100.000 Fission Product Carry-Over Fraction                                                                  .001 Halogen Carry-Over Fraction                                                                          .010 Condensate Demineralizer Flow Fraction                                                                .700 Radwaste Dilution Flow (thousand gpm)                                                              7.800 BV-2 GASEOUS WASTE INPUTS                                            VALUE There Is Not Continuous Stripping Of Full Letdown Flow Hold Up Time For Xenon (days)                                                                      45.800 Hold Up Time For Krypton (days)                                                                        2.570 Primary Coolant Leak To Auxiliary Building (lb/day)                                                160.000 Auxiliary Building Leak Iodine Partition Factor                                                      7.5E-3 Gas Waste System Particulate Release Fraction                                                          0.000 Auxiliary Building Charcoiodine Release Fraction                                                      0.100 Auxiliary Building Particulate Release Fraction                                                        0.010 Containment Volume (million cu-ft)                                                                    1.800 Frequency Of Primary Coolant Degassing (times/yr)                                                      2.000 Primary To Secondary Leak Rate (lb/day)                                                            100.000 There Is A Kidney Filter Containment Atmosphere Cleanup Rate (thousand cfm)                                                  20.000 Purge Time Of Containment (hours)                                                                      8.000 There Is Not A Condensate Demineralizer Iodine Partition Factor (gas/liq) In Steam Generator                                                  0.010 Frequency Of Containment Building High Vol Purge (times/yr)*                                          4.000 Containment Volume Purge Iodine Release Fraction                                                      1.000 Containment Volume Purge Particulate Release Fraction                                                  1.000 Steam Leak To Turbine Building (lbs/hr)                                                          1700.000 Fraction Iodine Released From Blowdown Tank Vent                                                      0.000 Fraction Iodine Released From Main Condensate Air Ejector                                              0.270 There Is Not A Cryogenic Off Gas System
        *2 cold and 2 hot purges
 
A9.621B Beaver Valley Power Station Unit 1/2 1/2-ODC-3.02 ODCM: Bases For ODCM Controls Document Owner Manager, Radiation Protection Revision Number                                        I Level Of Use                                  General Skill Reference Safety Related Procedure                              Yes
 
                                                                                                            -  ]    -      - u Beaver Valley Power Station II PBcediuS  Number.
1/2-ODC-3.02 ritak                                                                          Unit:            Level Of Usc:
ODCM: Bases For ODCM Controls                                                        1/2          General Skill Reference Revision:        Page Number 1                        )2.ofl 13 TABLE OF CONTENTS 1.0 PURPOSE  .........                                                                                                3 2.0 SCOPE                                                      .....                                                    :3 3.0    REFERE        NCES 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 LIMlTATIONS ................................            .                                          5 6.0 ACCEPTANCE CRITERIA ................................                                          .5 7.0 PREREQUISITES ...................................                                                                  5 8.0 PROCEDURE .................................                                                                        5 ATTACHMENT A BASES FOR ODCM CONTROLS: INSTRUMENTATION ................................                                  6 ATIACHMENT B BASES FOR ODCM CONTROLS: LIQUID EFFLUENTS ................................                                7 AITACHMIENT C BASES FOR ODCM CONTROLS: GASEOUS EFFLUENTS ...........................                                    9 ATTACHMENT D BASES FOR ODCM CONTROLS: TOTAL DOSE                                                      ...            12 ATTACHMENT E BASES FOR ODCM CONTROLS: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) ..........................................................................              13
 
Procedure Number:
Beaver Valley Power Station                                              1'2-ODC-3.02
'lrde:                                                                          Unit:          evel Of Use:
ODCM: Bases For ODCM Controls                                                      1/2        General Skill Reference Revision:    Page Number 1                -3of13 1.0      PURPOSE 1.1      This procedure contains the Bases for the ODCM Controls that were transferred from the Bases Section of the Technical Specification per Unit 1/2 Amendments lA-18812A-70, and in accordance with Generic Letter 89-01 and NUREG-1301 (Generic Letter 89-01, Supplement No. 1). (315 3.2.10) 1.1.1      Prior to issuance of this procedure, these items were located in Appendix D of the old ODCM.
1.2      This procedure also contains the Bases for the ODCM Controls (for Radiation Monitoring Instrumentation) that were duplicated from the Bases Section of the Technical Specification per Unit 1/2 Amendments 1A-246/2A-124, and in accordance with NUREG-1431.( 3 "6 '3-"-
1.3      This procedure also contains the Bases for the ODCM Controls (for Liquid Holdup Tank Activity Limits and for Gas Decay/Storage Tank Activity Limits) that were transferred from the Bases Section of the Technical Specification per Unit 1/2 Amendments lA-250/2A-130, and in accordance with NUREG-1431 .(31.7 3-2 -l1) 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      112-ODC-2.01, ODCM: Liquid Effluents 3.1.2      1/2-ODC-2.02, ODCM: Gaseous Effluents 3.1.3      1/2-ODC-3.03, ODCM: Controls for RETS and REMP Programs 3.1.4      1/2-ADM-1640, Control of the Offsite Dose Calculation Manual 3.1.5      Unit 1/2 Technical Specification 6.8.6, including Amendments IA-188/2A-70 (LAR 1A-17512A-37), Implemented August 7, 1995 3.1.6      Unit 1/2 Technical Specification 3.3.3.1, including Amendments IA-246/2A-124 (LAR IA-287/2A-159), Implemented April 11, 2002 3.1.7      Unit 1/2 Technical Specifications 3.11.1.4, 3.11.2.5 and 6.8.6, including Amendments LA-250/2A-130 (LAR IA-291/2A-163), Implemented August 7,2002 3.1.8      1/2-ADM-0100, Procedure Writer's Guide 3..1.9      1/2-ADM-0101, Review and Approval of Documents
 
Beaver Valley Power Station I
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==Title:==
Unit:        Level Of Use:
ODCM: Bases For ODCM Controls                                                        1/2      General Skill Reference Revision:    Page Numbe=
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 of TMI Action Plan Requirements, October, 1980 3.2.10    NUREG-1301, Offsite Dose Calculation Manual Guidance. Standard Radiological Effluent Controls For Pressurized Water Reactors (Generic Letter 89-0 1, 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.
4.2        Forms 4.2.1      None
 
                                          ~T11                                Pocedlure Number.
Beaver Valley Power Station                                              12O-.
Tide:                                                                        Unit          Level Of Use:
ODCM: Bases For ODCM Controls                                                      1/2      General Skill Reference Revision:    Page Number.
15              of 13 5.0        PRECAUTIONS AND LITMITATIONS 5.1      The numbering of each specific ODCM Bases contained in this procedure does not appear to be sequential. This is intentional, as all ODCM Bases numbers remained the same when they were transferred from the Technical Specifications. This was done in an effort to minimize the amount of plant procedure changes and to eliminate any confusion associated with numbering changes.
6.0      ACCEPTANCE CRITERIA 6.1      Any change to this procedure shall contain sufficient justification that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appenidx I to 10 CFR 50, and not adversely impact'the accuracy or reliability of effluent dose or setpoint calculation.(3.2 .10 )
6.1.1    All changes to this procedure shall be prepared in accordance with 1/2-ADM-0100'3 and 1/2-ADM-1640.( 3 ' 4A 6.1.2    All changes to this procedure shall'be reviewed and approved in accordance with 1/2-ADM-0101(3--9' and' 1/2-ADM_1640.( 3 l. 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 with Instrumentation.
8.2      See ATTACHIMENT B for a complete description of Bases for ODCM Controls associated with Liquid Effluents.
8.3      See ATTACHMENT C for a complete description of Bases for ODCM Controls associated with-Gaseous Effluents.
8.4      See ATTACHMENT D for a complete description of Bases for ODCM Controls associated with Total Dose.
8.5      See ATTACHMENT E for a complete description of Bases for ODCM Controls associated with the Radiological Environmental Monitoring Program (REMP).
 
I-t I        Procedure Numberc Beaver Valley Power Station                                  Pr-    r    1120DC3.02 rthi:                                                                    Unit          Lcvel Of Use:
ODCM: Bases For ODCM Controls                                                      -    General G12 Skill Reference Revision:      Page Number.        ,
l  ~        6ofl-1 ATTACHMENT A Page 1 of i BASES FOR ODCM CONTROLS: INSTRUMENTATION 314.3.3.1  RADIATION MONIT0IG lNSMRUMEWATION The OPERABILITY of the radiation monitoring channels ensures that: 1) the radiation levels are continually measured in the areas served by the individual channels; 2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded; and 3) sufficient information is available on selected plant parameters to monitor and assess these variables following an accident. This capability is consistent with the recommendations of NUREG-0737 .t. 9 )
3/4.3.3.9  RADIOACTIVE LIOUID 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.(321.322) 3/4.3.3.10  RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm/trip setpoints for these instruments shall be calculated in accordance with Section 2 of this manual to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. This instrumentation also includes provisions for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the waste gas holdup system.
The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.(321l 322)
 
Procedure Number-Beaver Valley Power Station                                                l/2-ODC-3.O2 Tide:                                                                        Unit          Level Of Use:
ODCM: Bases For ODCM Controls                                                      112      General Skill Reference Revision:      Page Number:
77of l3 ATTACHMENT B Page 1 of 2 BASES FOR ODCM CONTROLS: LIQUID EFFLUENTS 3/4.11.1.1    LIQUID EFFLUENT CONCENTRATION i  I. .
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 specifieain 10 CFR Part 20, Appendix B (20.1001-20-2401), Table 2,
                'Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposure within (1) the Section ll.A design objectives of Appendix 1, 10 CFR Part 50, to an individual and (2) the limits of 10 CFR Part 20.1302 to the population. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on
.    .          Radiological Protection (ICRP) Publication 2.(32.1.3.2.2) 3/4.11.1.2      LIQUID EFFLUENT DOSE This CONTROL is provided to implement the requirements of Sections ll.A, 1I.A, and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation                            I 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 releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable." Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141. The dose calculations in the procedure 1/2-ODC-2.01 implement the requirements in Section 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 of radioactive 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 1.1 1 3 .(3Ll.322323-325-327 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.
 
                                                                        -  : re      Numbew    -.
Beaver Valley Power Station -                                            1/2-ODC-3.02 l
tle:                                                                    Unit          Level Of Use:
ODCM: Bases For ODCM Controls                                                1/2        General Skill Reference Revision:    Page Number              :
I                R of    _3 ATTACHMENT B Page 2 of 2 BASES FOR ODCM CONTROLS: LIQUID EFFLUENTS 314.11.1.3    UIQUID WASTE TREATMENT SYSTEM The CONTROL that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and design objective given in Section ll.D of Appendix [to 10 CFR Part
: 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section ILA of Appendix I, 10 CFR Part 50, for liquid effluents. This specification applies to Beaver Valley Power Station, Unit No. 1 or Unit No. 2.(3 3/4:11. 1.4  -LIUID HOLDUP TANKS 1              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.                                                                                to
 
Beaver Valley Power Station                                    Pcedure  Number imde:                                                                      Unit          lzvel Of Use.
ODCM: Bases For ODCM Controls                                                  1/2        General Skill Reference Revision:    Page Number l                99of 13 ATTACHMENT C Page 1 of 3 BASES FOR ODCM CONTROLS: GASEOUS EFFLUENTS 3/4.11.2.1  GASEOUS EFFLUENT DOSE RATE This CONTROL is provided to ensure that the dose at anytime at the site boundary from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an unrestricted area, either within or outside the site boundary, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)). For individuals who may at times be within the site boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the site boundary. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the site boundary to < 500 mrem/year to the total body or to
            < 3,000 mremlyear 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. (32 1 3/4.11.2.2  DOSE, NOBLE GASES This CONTROL is provided to implement the requirements of Sections ll.B, M.A, and IV.A of Appendix 1, 10 CFR Part 50. The CONTROL implements the guides set forth in Section ll.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 M.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated. The dose calculations established in procedure 1/2-ODC-2.02 for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide -
1.109, and Regulatory Guide 1.1 11. The equations in procedure 1/2-ODC-2.02 are provided for determining the air doses at the exclusion area boundary, and are based upon the historical average atmospheric conditions. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111. This specifications applies to the release of gaseous effluents from Beaver Valley Power Station, Unit No. 1 or Unit No. 2.(312. 3.2.2.3.2.3.2., 3.2.5)
 
I1L BaeValyPower Station' -                                IeProcedure l          Numbr 1/2-ODC-3.02 S
Thid                                                                    Unit          Level Of Usc ODCM: Bases For ODCM Controls                                              l/2        General Skill Reference Revision:    Page Number.
1~    ~      1 nof 13          N' ATTACHMENT C Page 2 of 3 BASES FOR ODCM CONTROLS: GASEOUS EFFLUENTS 3/4.11.2.3  DOSE. RADIOIODINES. RADIOACTIVE MATERIAL IN PARTICULATE FORM AND RADIONUCLIDES OTHER THAN NOBLE GASES This CONTROL is provided to implement the requirements of Sections II.C, lII.A, and IV.A of Appendix I, 10 CFR Part 50. The CONTROLS are the guides set forth in Section U.C of Appendix L(32.2)
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 of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." The calculational methods specified in the surveillance requirements implement the requirements in Section II.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 appropriate pathways is unlikely to be substantially underestimated.. The calculational methods in procedure 1/2-ODC-2.02.are for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, and Regulatory Guide 1.1 11. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for radioiodines, radioactive material in particulate form, and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathways which are examined in the development of these calculations are: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man. This CONTROL applies to radioactive material in particulate form and radionuclides other than noble' gases released from Beaver Valley Power Station, Unit No. I or Unit No.2.( 3 l 3 2 2 3.2.6.3.2.7)
 
v  T  . ,    -. .Paocde                      Numuber Beaver Valley Power Station''U                                                  ODC. 3O2 TeUnit:                                                                                  Level Of Use:
ODCM: Bases For ODCM Controls                                                1/2        General Skill Reference Revision:      Page Number-I                1 Ioff 13 ATTACHMENT C Page 3 of 3 BASES FOR ODCM CONTROLS: GASEOUS EFFLUENTS 3/4.11.2.4  GASEOUS RADWASTE TREATMENT SYSTEM The CONTROL that the appropriate portions of these systems be used when specified provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFRIPart 50, and design objective Section ll.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections 11.B and ll.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. (1-2, 3.2.2) 3/4.11.2.5  BV-I GASEOUS WASTE STORAGE TANKS Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting total body exposure to an individual located at the nearest exclusion area boundary for two hours immediately following the onset of the release will not exceed 0.5 rem. The specified limit restricting the quantity of radioactivity contained in each gas storage tank was specified to ensure that the total body exposure resulting from the postulated release remained a suitable fraction of the reference value set forth in 10 CFR 100.11 (a)(1).
3/4.11.2.5  BV-2 GASEOUS WASTE STORAGE TANKS Restricting the quantity of radioactivity contained in any connected group of gaseous waste storage tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting total body exposure to an individual located at the nearest exclusion area boundary for two hours immediately following the onset of the release will not exceed 0.5 rem. The specified limit restricting the quantity of radioactivity contained in any connected group of gaseous waste storage tanks was specified to ensure that the total body exposure resulting from the postulated release remained a suitable fraction of the reference value set forth in 10 CFR 100.11(a)(1). The curie content limit is applied individually to each gaseous waste storage tank and collectively to the number of unisolated gaseous waste storage tanks.
 
IL BPedureNumbec e
Beaver Valley Power Station                                  I          l/2-ODC-3.02
 
==Title:==
Unit:      Lvel Of UsC:
ODCM: Bases For ODCM Controls                                                1/2    General Skill Reference.
Revision:    Page Number l            12 of 13 ATTACHMENT D Page 1 of I BASES FOR ODCM CONTROLS: TOTAL DOSE 3/4.11.4  TOTAL DOSE This CONTROL is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525. The CONTROL requires the preparation and submittil of a Special Report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. For sites containing up to 4 reactors, it is highly unlikley that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the units (including outside storages tanks, etc.) are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from
* other nuclear fuel cycle facilities at the same site or within a radius of 5 miles must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.405c, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only. relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in ODCM CONTROL 3.1 1.i. 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 ' 3 ' 321, 3.2.2,3.2.4)
 
Procedure Number Beaver Valley Power Station                                                  1/2-ODC-3.02
 
==Title:==
Unit:        Level Of Use:
ODCM: Bases For ODCM Controls                                                    1/2        General Skill Reference Revision:    Page Number.
                                                                    -    __    -  l                13 of 13 ATTACHMENT E Page I of 1 BASES FOR ODCM CONTROLS: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 3/4.12.1      MONITORING PROGRAM The radiological monitoring program required by this CONTROL provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclidesWhich 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.(3.1-3 3.2.3) 3/4.12.2      LAND USE CENSUS ODCM CONTROL 3.12.2 is provided to ensure that changes in the use of unrestricted areas are identified and that modifications to the monitoring programs are made if required by the results of this census. The best survey information from the door-to-door survey, aerial survey, or by consulting with local agriculture authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix Ito 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.(3.1 3 3.2.2) 3/4.12.3      INTERLABORATORY COMPARISON PROGRAM The ODCM CONTROL 3.12.3 for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of a quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.( 3 l 3 )
 
RTL #A9.621B
-I-N Beaver Valley Power Station Unit 1/2 1/2-ODC-3.03 ODCM: Controls for RETS and REMP Programs Document Owner Manager, Nuclear Environmental and Chemistry Revision Number                                    4 Level Of Use                              General Skill Reference Safety Related Procedure                  I -    Yes
 
x        r        ro      n,-        .Procedure                              Number:
Beaver Valley Power Station                                                                      o                      /2-ODC-3.03
 
==Title:==
Unit:                          Level Of Use:
1/2              l General Skill Reference ODCM: Controls for RETS and REMP Programs                                                              Revision:                      Page Number:
                                      -                                                                              4              1          2 of 78 TABLE OF CONTENTS 1.0  PURPOSE ...........................................                                                                                                    3 2.0  SCOPE ...........................................                                                                                                      3
 
==3.0  REFERENCES==
AND COMMITMENTS ................................                                                                        ..                .3 3.1  References ................................                                                                                              '.3 3.2 Commitments ...................................                                                                                                    5 4.0 RECORDS AND FORMS .................................                                                                                                      6 4.1  Records .........                                                                                                                                6 4.2 -Forms ...............................                                                                                                            6.:
6 5.0 PRECAUTIONS AND LIMITATIONS ...............................                                                                                              6 6.0 ACCEPTANCE CRITERIA ................................                                                                                                    7 7.0 PREREQUISITES ................................                                                                                                          7 8.0 PROCEDURE .............................................                                                                                                  7 ATTACHMENT A ODCM CONTROLS: OPERATIONAL MODES AND FREQUENCY NOTATION                ............................................                                                                                  8 ATTACHMENT B ODCM CONTROLS: DEFINITIONS .                                                ..........................................                        10 ATTACHMENT C ODCM CONTROLS: APPLICABILITY AND SURVEILLANCE REQUIREMENTS..........................................................................................................................1. 3 ATTACHMENT D ODCM CONTROLS: RADIATION MONITORING INSTRUMENTATION. 16 ATTACHMENT E ODCM CONTROLS: RETS INSTRUMENTATION FOR LIQUID EFFLUENTS                                                                ..                                                                        24 ATTACHMENT F ODCM CONTROLS: RETS INSTRUMENT FOR GASEOUS RELEASES ... 34 ATTACHMENT G ODCM CONTROLS: LIQUID EFFLUENT CONCENTRATION .47 ATTACHMENT H ODCM CONTROLS: LIQUID EFFLUENT DOSE .52 ATTACHMENT I              ODCM CONTROLS: LIQUID RADWASTE TREATMENT SYSTEM .                                                                                53 ATTACHMENT J ODCM CONTROLS: LIQUID HOLDUP TANKS .54 ATTACHMENT K ODCM CONTROLS: GASEOUS EFFLUENT DOSE RATE .55 ATTACHMENT L ODCM CONTROLS: DOSE- NOBLE GASES .60 ATTACHMENT M ODCM CONTROLS: DOSE - RADIOIODINES AND PARTICULATES .61 ATTACHMENT N ODCM CONTROLS: GASEOUS RADWASTE TREATMENT SYSTEM .62 ATTACHMENT 0 ODCM CONTROLS: GAS STORAGE TANKS .63 ATTACHMENT P ODCM CONTROLS: TOTAL DOSE .64 ATTACHMENT Q ODCM CONTROLS: REMP-PROGRAM REQUIREMENTS .65 ATTACHMENT R ODCM CONTROLS: REMP - LAND USE CENSUS                                                                                        ..              73 ATTACHMENT S ODCM CONTROLS: REMP - INTERLABORATORY COMPARISON PROGRAM                                                                .74 ATTACHMENT T ODCM CONTROLS: ANNUAL REMN REPORT .75 ATTACHMENT U ODCM CONTROLS: ANNUAL RETS REPORTS .77
 
Beaver Valley Power Station                            :          ee    1/2NODC-3.03
 
==Title:==
Unit:        Level Of Use:
                                                                              . 1/2      General Skill Reference ODCM: Controls for RETS and REMP Programs                                      Revision:    Page Number 4                3 of 78 1.0        PURPOSE 1.1      This procedure includes selected Definitions and Tables as delineated in Section 1 of the Technical Specifications and selected Applicability and Surveillance Requirement statements as delineated in Section 3/4 of the Technical Specifications.
1.1.1    Prior to issuance of this procedure, these items were located in Appendix C of the old ODCM, and were added to this procedure for reference purposes, even though they are currently described in the Technical Specifications.
1.2      This procedure contains the controls for the Radiological Effluent Technical Specification (RETS) that were transferred from the Technical Specifications per Unit 1/2 Amendments IA-188/2A-70, and in accordance with Generic Letter 89-01 and NUREG-130i.( 32 0l )
1.2.1    Prior to issuance of this procedure, these items were located in Appendix C of the old ODCM.
1.3-      This procedure contains the reporting requirements for the Annual Radioactive Effluent Release Report and the Annual Radiological Environmental Report that were transferred from the Technical Specifications per Unit 1/2 Amendments IA-188/2A-70 and in accordance with Generic Letter 89-01 and NUREG-1301. (3.2.10) 1.3.1    Prior to issuance of this procedure, these items were located in Appendix E of the old ODCM.
1.4      This procedure contains the controls for Radiation Monitoring Instrumentation that were transferred from the Technical Specification per Unit 1/2 Amendments 246/124, and in accordance with NIJREG-1431. 332 .11) 1.5      This procedure contains the controls for Liquid Holdup Tank Activity Limits and for Gas Decay/Storage Tank Activity Limits that were transferred from the Technical Specification per Unit 1/2 Amendment 250/130, and in accordance with NUREG-143 1.(3.1.6 3-2-11) 2.0        SCOPE 2.1        This procedure is applicable to all station personnel that are qualified to perform activities as described and referenced in this procedure.
 
==3.0        REFERENCES==
AND COMMITMENTS 3.1        References 3.1.1    1/2-ODC-2.01, ODCM: Liquid Effluents 3.1.2    1/2-ODC-2.02, ODCM: Gaseous Effluents 3.1.3      1/2-ODC-3.02, ODCM: Bases for ODCM Controls
 
                                                                                                                    'I-Beaver Valley Power Station                          .    [ProcedureNumber Iw          1/2-ODC-3.03
 
==Title:==
Unit        Level Of Use:
1/2      General Skill Reference -
ODCM: Controls for RETS and REMP Programs                                  Revision:    Page Number.
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 246/142 (LAR 1A-287/2A-159) Implemented April 1l, 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 lA-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-IDA-100 trip function as required by ODCM.
No ODCM changes are required for this CR.
3.1.13 CR 001682, ODCM Action 28 Guidance. CA-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 CR02-0571 1, TS and ODCM changes not reflected in 1OM.54.3.L5 Surveillance Log.
CA-01, Revise 1/2-ODC-3.03' to add a requirement for applicable station groups notification of pending ODCM changes.
3.1.15 CR03-06123, Enhance Table 3.3-6 of 1/2-ODC-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 I Mid or High Range Noble Gas EfMfluent Monitors are Inoperable.
3.1.16 CR03-06281, Gaseous Tritium Sampling Required by ODCM (1/2-ODC-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.
 
Procedure Number:
Beaver Valley Power Station                                              1/2-ODC-3.03
 
==Title:==
Unit:        Level Of Use:
1/2        General Skill Reference ODCM: Controls for RETS and REMP Programs                                  Revision:    Page Number:
4                5of 78 3.1.17  CR03-07487, Results of NQA 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-ODC3.03 Control 3.11.1.4 to update the activity limits for the outside storage tanks.
3.1.18  CR03-07668, Benchmark Effluent & Environmental Programs VS Papers Presented at 13tth 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. CR03-09288, LAR IA-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  CR03-09959, RFA-Rad Protection Provide Clarification to ODCM 1/Day Air Tritium Sample. CA-01, Revise ODCM procedure 1/2-ODC-3.03 Attachment K (Table 4.11-2 note c & note e) to allow sampling of the appropriate building atmosphere.
3.1.21  CR03-11726, Typographical Error Found in ODCM 3.11.2.5. CA-01, Revise ODCM procedure 1/2-ODC-3.03, Attachment 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  CR04-01643, Procedure Correction - Typographical Error in the ODCM. CA-01, Revise ODCM procedure 1/2-ODC-3.03, Attachment F, (Table 3.3-13 and 4.3-13) to correct a typo-graphical error. Specifically, the Asset Number for the Vacuum Gauge used for measurement of sample flow (from the Alternate Sampling Device) needs changed from [PI-lGW-13] to [PI-lGW-135].
3.1.23  CR04-02275, Discrepancies in Table 3.3-13 of the ODCM. CA-01, Revise ODCM procedure 1/2-ODC-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".
3.2        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.
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
 
H -
Valley Power Station Beaver _________________________________________________    Id1/2uODC-3.03 1/--.0
 
==Title:==
Unit:      Level of Use:
                                                                                    .1/2    General Skill Reference TitRee:sin:t                                                        Level Ofuse:
ODCM: Controls for RETS and REMP Programs                                      Revision:  Page Number:
                                                            .4                                      6 of 78 3.2.6    Regulatory Guide 1.111, Methods For Estimating Atmospheric Transport And Dispersion Of Gaseous Efifuents In Routine Releases From Light-Water-Cooled Reactors, Revision 1, July 1977 3.2.7      Regulatory Guide 1.113, Estimating Aquatic Dispersion Of Effluents From Accidental And Routine Reactor Releases For The Purpose Of Implementing Appendix I, April 1977 3.2.8    NUREG-0133, Preparation of Radiological Effluent Technical Specifications for' Nuclear Power Plants, October 1978 3.2.9    NUREG-0737, Clarification of TMI Action Plan Requirements, October 1980 3.2.10    NUREG-1301, Offsite Dose Calculation Manual Guidance; Standard Radiological Effluent Controls For Pressurized Water Reactors (Generic Letter 89-01, Supplement No. 1) 3.2.11    NUREG-143 1, Standard Technical Specifications - Westinghouse Plants Specifications 3.2.12    NUREG-0800, Standard Review Plan, Postulated RadioactiveReleases 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 correction factors to determine particulate activity in samples obtained from the effluent release pathways.
4.0        RECORDS AND FORMS 4.1      Records 4.1.1      Any calculation supporting ODCM changes shall be documented, as appropriate, by a retrievable document (e.g.; letter or calculation package) with an appropriate RTL number.
4.2      Forms 4.2.1      None 5.0        PRECAUTIONS AND LIMITATIONS 5.1      The numbering of each specific ODCM Control, ODCM Surveillance Requirement and ODCM Table contained in this procedure does not appear to be sequential. This is intentional, as all ODCM Control, ODCM Surveillance Requirement and ODCM Table numbers remained the same when they were transferred from the Technical Specifications.
This was done in an effort to minimize the amount of plant procedure changes and to eliminate any confusion associated with numbering changes.
 
Procedure Number:
Beaver Valley Power Station                                              1/2-ODC-3.03
 
==Title:==
Unit:        Level Of Use:
1/2        General Skill Reference ODCM: Controls for RETS and REMP Programs                                      Revision:    Page Number:
4          -    7 of 7R 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 charge will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40-CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR 50, and not adversely impact the accuracy or reliability of effluent dose or setpoint calculation.( 3 2 ' 0 )
    ,6.1.1      All changes to this procedure shall be prepared in accordance with 1/2-ADM-0100(3.'18) and 1/2-ADM-1640.(3' 7 )
6.1.2    Pending changes to this procedure shall be provided to applicable station groups. For example, IF Control 3.11.1.1 is being changed, THEN the proposed changes shall be provided to the applicable station groups (i.e.; owner of the procedures), identified in the MATRIX of ODCM procedure 1/2-ODC-1.01. This will allow the station groups to revise any affected procedures concurrent with the ODCM change.(3' 1 4 )
6.1.3    All changes to this procedure shall be reviewed and approved in accordance with NOP-SS-3001    (3.1.9) and 1/2-ADM-1640.(31.7) 7.0        PREREQUISITES 7.1        The user of this procedure shall be familiar with ODCM structure and content.
8.0      PROCEDURE 8.1      See ATTACHMENT A for a Table of Operational Modes and a Table of Frequency Notation.
8.2      See ATTACHMENT B for a list of defined terms used throughout the ODCM.
8.3      See ATTACHMENT C thru ATTACHMENT S for a complete description of all ODCM Controls.
8.4      See 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 -
 
Procedure Number:
Beaver Valley Power Station                                            1/2-ODC-3.03
                                                                                                    -l l
 
==Title:==
Unit:          Level Of Use:  e 1/2      lGeneral Skill Referencel N ODCM: Controls for RETS and REMP Programs                                Revision:      Page Number.
_  __    _  _of__                  _  _78                A__                        ~      I ATTACHMENT A Page 1 of 2 ODCM CONTROLS: OPERATIONAL MODES AND FREQUENCY NOTATION TABLE 1.1 OPERATIONAL MODES REACTIVITY            % RATED                    AVERAGE COOLANT .
MODE              CONDITION, Keff      THERMAL POWER(l)                    TEMPERATURE
: 1. Power Operation            20.99                >5%                              &#x17d;3500 F
: 2. Startup                    I0.99              <5%                              &#x17d;3500 F
: 3. Hot Standby                <0.99                  0                              &#x17d;350`F
: 4. Hot Shutdown              <0.99                .0                                3500 F >T.ivg
                                                                                      >2000 F 1--1/
: 5. Cold Shutdown              <0.99                  0                                *2000 F
: 6. Refuieling(2)              <0.95                  0                                <1400 F (1)    Excluding decay heat.
(2)    Reactor vessel head unbolted or removed and fuel in the vessel.
7
 
Beaver Valley Power Station                                    lN2-ODC-3.03
 
==Title:==
Unit:      Level Of Use:
1/2    General Skill Reference ODCM: Controls for RETS and REMP Programs                      Revision:  Page Number ATTACHMENT A Page 2 of 2 ODCM CONTROLS: OPERATIONAL MODES AND FREQUENCY NOTATION TABLE 1.2 FREQUENCY NOTATION NOTATION            FREQUENCY S          At least once per 12 hours D          At least once per 24 hours 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 S/U        Prior to each reactor startup P          Completed prior to each release N.A.      Not applicable
 
Beaver Valley Power Station 'NUi-ODC.                                              3 O3      -
Tide:                                                                      Unit:      Level Of Use: -
1/2      General Skill Reference ODCM: Controls for RETS and REMP Programs                                  Revision:  PageNumb        -
4              ljof78 ATTACHMENT B Page 1 of 3 ODCM CONTROLS: DEFINITIONS The defined terms of this section appear in capitalized type and are applicable throughout these CONTROLS.
ACTION shall be those additional requirements specified as corollary statements to each principal CONTROL and shall be part of the CONTROLS.
CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated.
CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.                                                                                  -y 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.
FREOUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.2.
GASEOUS RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.
MEMBER(S) OF THE PUBLIC (10 CFR 20 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.
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.
 
Procedure Number~
Beaver Valley Power Station                                              1/2-ODC-3.03
 
==Title:==
Unit:        Level Of Use:
112        General Skill Reference ODCM: Controls for RETS and REMP Programs                                  Revision:    Page Number:
                                          - ATTACHMENT B Page 2 of 3 ODCM CONTROLS: DEFINITIONS OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring AlarmlTrip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Technical              !
Specification (TS) Section 6.8.6 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports that are also required by the Administrative Controls Section of the TS 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).
OPERATIONAL MODE shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in ATTACHMENT A Table 1.1.
PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating conditions, in such a manner that replacement air or gas is required to purify the confinement.
RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 2689 MWt.
REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.
SHUTDOWN means reactor power change to 0% power.
SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee. The Figure for Liquid Effluent Site Boundary is contained in 1/2-ODC-2.01.
The Figure for Gaseous Effluent Site Boundary is contained in 1/2-ODC-2.02.
STARTUP means reactor power change from 0% power.
SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.
THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
UNRESTRICTED AREA means any area access to which is neither limited nor controlled by the licensee.
 
II-Procedure Number Beaver Valley Power Station___    Power tation1/2-ODC-3.03j                        ___
 
==Title:==
Unit:        Level Of Use:
                                                                              .1/2      General Skill Reference ODCM: Controls for RETS and REMP Programs                                  Revision:    Page Number.
412 of 78 ATTACHMENT B Page 3 of 3 ODCM CONTROLS: DEFINiTIONS VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal absorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents). Engineered Safety Feature (ESF) atmospheric.
cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM.
components. -
VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating conditions, in, such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process.
 
Procedure Number.
Beaver Valley Power Station                                              1/2-ODC-3.03
 
==Title:==
Unit:          Level Of Use:
1/2        General Skill Reference ODCM: Controls for RETS and REMP Programs                                  Revision:    Page Number.
4                13 of 78 ATTACHMENT C Page 1 of 3 ODCM CONTROLS: APPLICABILITY AND SURVEILLANCE REQUIREMENTS CONTROLS: APPLICABILITY 3.0.1 Compliance with the ODCM CONTROLS in the succeeding ODCM CONTROLS is required during the OPERATIONAL MODES or other conditions specified therein; except that upon failure to meet the ODCM CONTROL, the associated ODCM ACTION requirements shall be met, except as provided in ODCM CONTROL 3.0.6.
3.02  Non-compliance with a ODCM CONTROL shall exist-when the requirements of the ODCM CONTROL and associated ODCM ACTION requirements are not met within the specified time intervals. -If the ODCM CONTROL is restored prior to expiration of the specified time intervals, completion of the ODCM ACTION requirements is not required.
3.03  When a ODCM CONTROL is not met (except as provided in the associated ODCM ACTION requirements) within one hour, action shall be initiated to place the unit in a MODE in which the ODCM CONTROL does not apply by placing it, as applicable, in:
: 1.      At least HOT STANDBY within the next 6 hours,
: 2.      At least HOT SHUTDOWN within the following 6 hours, and
: 3.      At least COLD SHUTDOWN within the subsequent 24 hours.
Where corrective measures are completed that permit operation under the ODCM ACTION requirements, the ODCM ACTION may be taken in accordance with the specified time limits as measured from the time of failure to meet the ODCM CONTROL. Exceptions to these requirements are stated in the individual ODCM CONTROLS.
3.0.4 When an ODCM CONTROL is not met, entry into an OPERATIONAL MODE or specified condition in the Applicability shall only be made:
: a. When the associated ODCM ACTIONS to be entered permit continued operation in the OPERATIONAL 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 OPERATIONAL MODE or other specified condition in the Applicability, and establishment of risk 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.
 
II-Procedure Number:
Reaver Valley Power Station                                            1/2 ODC-3 03
 
==Title:==
Unit:        Level Of Use:
1/2        General Skill Reference ODCM: Controls for RETS and REMP Programs                                Revision:    Page Number:
4                14 of 79 ATTACHMENT C Page 2 of 3 ODCM CONTROLS: APPLICABILITY AND SURVEILLANCE REQUIREMENTS This ODCM CONTROL shall not prevent changes in OPERATIONAL 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.
3.0.5 When a system, subsystem, train, component or device is determined to be inoperable solely because its emergency power source is inoperable, or solely because its norma. power source is-inoperable, it may be considered OPERABLE for the purpose of satisfying the requirements' of its applicable ODCM Control for Operation, provided; (1) its corresponding normal or emergency power source is OPERABLE; and (2) all of its redundant system(s), subsystem(s),
train(s), component(s) and device(s) are OPERABLE, or likewise satisfy the requirements of this specification. Unless both conditions (1) and (2) are satisfied within 2 hours, action shall be initiated to place the unit in a MODE in which the applicable ODCM CONTROL does not apply, by placing it, as applicable, in:
: 1.      At least HOT STANDBY within the next 6 hours,
: 2.      At least HOT SHUTDOWN within the following 6 hours, and
: 3.      At least COLD SHUTDOWN within the subsequent 24 hours This ODCM CONTROL is not applicable in MODES 5 or 6.
3.0.6 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.
 
Procedure Number.
Beaver Valley Power Station                                            1/2-ODC-3.03
 
==Title:==
Unit:        Level Of Use:
1/2        General Skill Reference ODCM: Controls for RETS and REMP Programs                                  Revision:    Page Number:
4                15 of 78 ATTACHMENT C Page 3 of 3 ODCM CONTROLS: APPLICABILITY AND SURVEILLANCE REQUIREMENTS CONTROLS: SURVEILLANCE REQUIREMENTS 4.0.1- Surveillance Requirements shall be met during the OPERATIONAL MODES or other conditions specified for individual ODCM CONTROLS unless otherwise stated in an individual ODCM Surveillance Requirement. Failure to meet a 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 allowed surveillance interval, defined by ODCM Surveillance Requirement 4.0.2, 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.
4.02  Each ODCM Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the ODCM surveillance interval.
4.0.3  If it is discovered that a ODCM Surveillance was not performed within its allowed ODCM surveillance interval (defined by ODCM Surveillance Requirement 4.0.2), then compliance with the requirement to declare the ODCM CONTROL not met may be delayed, from the time of discovery, up to 24 hours 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 hours 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 a 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.
4.0.4  Entry into an OPERATIONAL MODE or other specified condition in the Applicablity 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 a ODCM CONTROL is not met due to Surveillances not having been met, entry into an OPERATIONAL 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 OPERATIONAL 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.
 
I                _LL_
Beaver Vnlhev IA_-
Pnwe-r
_ i- "-
Station
 
==Title:==
ODCM: Controls for RETS and REMP Programs A --
T"I A 1rTmTl  TT.TVI' Th
                                                -i I I `kfl  I fi N1 1)                  -
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 hours 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 riot applicable.,
SURVEILLANCE REQUIREMENTS.
4.3.3            Each radiation monitoring instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the modes and at the frequencies shown in ODCM Control 3.3.3.1, Table 4.3-3.
                                                                                                            )
 
Beaver Valley Power Station                                            P1/2-ODC-3.03
 
==Title:==
Unit:            Level Of Use:
1/2          General Skill Reference ODCM: Controls for RETS and REMP Programs                                                Revision:        Page Number:
                                      -            .                                        ~          ~417of7 ATTACHMENT D Page 2 of 8 ODCM CONTROLS: RADIATION MONITORING INSTRUMENTATION TABLE 3.3-6 BV-i RADIATION MONITORING INSTRUMENTATION Pri = Primary Instruments, PMM - Preplanned Method of Monitoring(a)
MINIMUM                                                    NOMINAL CHANNELS APPLICABLE                                    MEASUREMENT INS.TRUMENT                OPERABLE          MODES          SETPOINT<')                RANGE            ACTION
*1. Noble Gas Effluent Monitors - SPINGS(4)
: a. Reactor Building/SLCRS (CV-1; Also called Elevated Release)
                                                                                                . 10-3_103 U Mid Ranne Noble Gas                    (1)      1, 2.3.- & 4        .:5798 cpm                        ci/cc(2)    35 Pri: (RM-lVS-1 10 Ch 7) 1st PMM: (RM-lVS-112 SA-IO) 2nd PMM: (RM-lVS-107B, or 110 Ch 5) 3rd PMM: Grab Sampling every 12 hours Hieh Ranee Noble Gas                    (1)    1, 2,3,&4                N/A                                        35 Pri: (RM-lVS-ll0Ch9)
IstPMM: (RM-IVS-112SA-9 2nd PMM: (RM-lVS-107B, or 110 Ch 5)                                                        lo-,-lo, uCi/cc~2 )
3rd PMM: Grab Sampling every 12 hours b.Auxiliary Building Ventilation System (VV-1; Also called Ventilation Vent)
Mid Range Noble Gas                  (1)        1, 2, 3, & 4    <669 cpm                                            35 Pri: (RM-IVS-109Ch7) 1stPMM: (RM-IVS-111 SA-10) 2nd PMM: (RM-IVS-1O1B, or 109 Ch 5) 3rd PMM: Grab.Sarnpling every 12 hours High Range Noble Gas                    (1)    1, 2, 3, & 4            N/A              ItT-i_1& UCi/CC(2)        35 Pri: (RM-1VS-109 Ch 9)
Ist PMM: (RM-lVS-lI I SA-9) -
2nd PMM: (RM-IVS-IO1B, or 109 Ch 5) 3rd PMM: Grab Sampling every 12 hours
: c. Gaseous Waste/Process Vent System (PV-1/2)
Mid Range Noble Gas                      (1)    1, 2, 3, & 4            N/A                                        35 Pri: (RM-IGW-109Ch7) lstPMM: (RM-IGW-I1OSA-10) 2nd PMM: (RM-lGW-108B, or 109 Ch 5) 3rd PMM: Grab Sampling every 12 hours High Ranee Noble Gas                    (1)    1, 2,3, & 4        < 1.83E 5 cpm          10'-i-0 5 uCi/cc~l      35 Pri: (RM-IGW-109Ch9) 1st PMM: (RM-IGW-110 SA-9) 2nd PMM: (RM-IGW-108B, or 109 Ch5) 3rd PMM: Grab Sampling every 12 hours (a) Instruments or action's 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.
 
Beave r Valley Power-Beavere          Station Sain-12OC30.                    edureNumber-
 
==Title:==
Unit          Level Of Use:
1/2        General Skill Reference ,
ODCM: Controls for RETS and REMP Programs                                            Revision:      Page Number:
4                  18 of78 ATTACHMENT D -
Page 3 of 8 ODCM CONTROLS: RADIATION MONITORING INSTRUMENTATION TABLE 3.3-6 (Continued)
BV-I RADIATION MONITORING INSTRUMENTATION
                  - Pri = Primary Instruments, - PMM = Preplanned Method of Monitoring~a)
MINIMUM        -                                        NOMINAL CHANNELS APPLICABLE                                  MEASUREMENT INSTRUMENT              - OPERABLE          MODES          SETPOThW1            - RANGE            IACTION
: 2. Noble Gas Effluent Steam Monitors
: a. Atmospheric Steam Dump Valve and Code Safety Relief Valve Discharge Pri: (RM-IMS-1OOA)                      (1)    1, 2, 3, & 4          <50 cpm                                    35 PMM: (Form 1/2-HPP-4.02.009.FO1)                                                        *I01-l03 UCi/~Cc Pri: (RM-lMS-1OOB)                      (1)    1, 2, 3, & 4          < 50 cpm                                  35 PMM: (Form 1/2-HPP-4.02.009.FO1)
Pri: (RM-IMS-IOOC)                      (1)    1,2,.3,&4            <SOcpm              lo -lo~ uCifcc        35 PMM: (Form 1/2-HPP-4.02.009.FOI) b.Auxiliary Feedwater Pump Turbine Exhaust Pri: (RM-lMS-101)                        (1)  1, 2,3, & 4          < 650 cpm                                  35 PMM: (Form 1/2-HPP4.02.009.FOI)
(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.
 
w sr                        oAce,,                                            .Procedure            Number:
Beaver Valley Power Station                                          P            1/2eODC3O 3
 
==Title:==
Unit:          Level Of Use:
1/2        General Skill Reference ODCM: Controls for RETS and REMP Programs                                                Revision:      P    Nuofe78 ATTACHMENT D Page4of8 ODCM CONTROLS: RADIATION MONITORING INSTRUMENTATION TABLE 3.3-6 (Continued)
BV-2 RADIATION MONITORING INSTRUMENTATION Pri = Primary Instruments,          PMM = Preplanned Method of Monitoring(a)
MINIMUM                                                    NOMINAL CHANNELS      APPLICABLE                              MEASUREMENT INSTRUMENT                  OPERABLE      - MODES              SETPOrNT<'1            RANGE            ACTION
.,    1. Noble Gas Effluent Monitors
: a. SLCRS Filtered Pathway (CV-2; Also called Elevated Release)
Midranee Noble Gas (Xe-133)
Pr: (2HVS-RQ109C)                    (1)        1, 2, 3, & 4            N.A.            10-102 fiCi/cc        35 IstPMM: (2HVS-RQ109D) 2nd PMM: (2HVS-RQ109B) 3rd PMM: Grab Sampling every 12 hours High Range Noble Gas (Xe-133)
Pri: (2HVS-RQ109D)                    (1)      1, 2,3, & 4              N.A.            10-1,105 [tCi/cc      35 1st PMM: (2HVS-RQ109C) 2nd PMM: (2HVS-RQI09B) 3rd PMM: Grab Sampling every 12 hours
(')    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..
 
ritle:
Beaver Valley Power Station                        -I    ledueNUT2-ODC- 3 Unit:      Level Of Use:
3 Il 1/2    General Skill Reference .
ODCM: Controls for RETS and REMP Programs                                  Revision:  Page Number:              Ih
                                                                        &      4  I          20of78 ATTACHMENT D Page 5 of 8 ODCM CONTROLS: RADIATION MONITORING INSTRUMENTATION TABLE 3.3-6 (Continued)
TABLE NOTATIONS
(')    Above background (2)    Nominal range for Cl 7 and Ch 9. The Alarm in set on Cl 7.
(3)    Nominal range for Ch 7 and Ch 9. The Alarm in set on Ch 9.
(3Noia      ag    o    h7a.C      9    h    lr    nsto    h9 (4)    Other SPING4 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 hours, or:
a)      Initiate the preplanned alternate method of monitoring the appropriate.
parameter(s), and b)    Return the channel to OPERABLE status within 30 days, or, explain in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.
I
 
Procedure Number Beaver Valley Power Station                                                            1/2-ODC-3.03
 
==Title:==
Unit          Level Of Use:
1/2        General Skill Reference ODCM: Controls for RETS and REMP Programs                                                      Revision:      Page Number:
ATTACHMENT D Page 6 of 8 ODCM CONTROLS: RADIATION MONITORING INSTRUMENTATION TABLE 4.3-3 (Continued)
BV-1 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REOUIREMENTS Pri - Primary Instruments,          PMM = Preplanned Method of Monitoring(3)
CHANNEL            MODES IN WHICH CHANNEL            CHANNEL            FUNCTIONAL            SURVEILLANCE INSTRUMENT                          CHECK        CALIBRATION                TEST                REQUIRED
: 1. Noble Gas Effluent Monitors - SPINGS
: a. Reactor Building/SLCRS (CV-1; Also called Elevated Release)
Mid Range Noble Gas                                    S              R                    M                1,2,3, & 4 Pri: (RM-IVS-llOCh7)
Ist PMM: (RM-IVS-112 SA-10) 2nd PMM: (RM-IVS-107B, or VS-I 10 Ch 5) 3rd PMM: Grab Sampling every 12 hours High Ranee Noble Gas                                                R                    M                  1,2,3,&4 Pri: (RM-IVS-I 1O Ch9) lstPMM: (RM-IVS-112SA-9) 2nd PMM: (RM-lVS-107B, or VS-I 10 Ch 5) 3rd PMM: Grab Sampling every 12 hours
: b. Auxiliary Building Ventilation System (VV-1; Also called Ventilation Vent)
Mid Ranne Noble Gas                                S              R                    M                  1, 2,3,&4 Pri: (RM-IVS-109Ch7) lstPMM: (RM-lVS-Ill SA-lO) 2nd PMM: (RM-lVS-1OB, or VS-109 Ch 5) 3rd PMM: Grab Sampling every 12 hours Hieh Ranie Noble Gas                                S              R                    M                  1,2, 3,&4 Pri: (RM-lVS-109 Ch9) lst PMM: (RM-lVS-i II SA-9) 2nd PMM: (RM-IVS-1OlB, or VS-109 Ch 5) 3rd PMM: Grab Sampling every 12 hours
: c. Gaseous Waste Process Vent System (PV-1,2)
Mid Ranae Noble Gas                                  S            R                    M                  1,2,3, &4 Pri: (RM-IGW-109Ch7)
Ist PMM: (RM-IGW-1 0 SA-10) 2nd PMM: (RM-IGW-108B, or GW-109 Ch 5) 3rd PMM: Grab Sampling every 12 hours Hieh Range Noble Gas                                  S            R                    M                  1,2,3,&4 Pri: RM-IGW-109Chl9) 1st PMM: (RM-lGW-1 10 SA-9) 2nd PMM: (RM-IGW-108B, or GW-109 ChS) 3rd PMM: Grab Sampling every 12 hours (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 alternatemonitoring 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.
 
Procedure Number Beaver Valley Power Station                                    -    I          .
2-ODC-3.03
                                                                                                    ./2.O.C-...
 
==Title:==
Unit:          Level Of Use:          -
1/2        General Skill Reference                1 ODCM: Controls for RETS and REMP Programs                                              Revision:      Page Number                  .
: 4.                  22 of T>            -r'I ATTACHMENT D 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)
CHANNEL            MOE )ES IN WHICH CHANNEL          CHANNEL          FUNCTIONAL              Sul BVEILLANCE INSTRUMENT                          CHECK        CALIBRATION              TEST                    I LEQUIRED Io
: 2. Noble Gas Effluent Steam Monitors
: a. Atmospheric Steam Dump Valve and Code Safety Relief Valve Discharge Pri: (RM-IMS-IOOA)                              S                R              -    Ml                : 1,2,3, &4
                                                                                                                    .. I PMM: (Form 1/2-HPP-4.02.009.FO1)
Pri: (RM-IMS-IOOB)                              S                R                    M                        1, 2, 3,&4 PMM: (Form 1/2-HPP-4.02.009.FO I)                                                                .      .    ..          f Pri: (RM-lMS-100C)                              S                R                -M                          1,2,3,&4 PMM: (Form 1/2-HPP4.02.009.FO1)
: b. Auxiliary Feedwater Pump Turbine Exhaust Pri: (RM-IMS-101)                              S                R                    M                      1,2,3, &4              N PMM: (Form 1/2-HPP4.02.009.FO1)
()    Instrunents or actions shown as PMM are the preplanned methods to be used when the primary instrument is inoperable. SINCE the PMM instruments shown are not considered comparable alternate monitoring channels, THEN the ODCM Surveillance Requirements do not apply to the PMM. Therefore, the reporting requirement of Action 35b would still apply when inoperability of the primary instrument exceeds 30 days.
I'
 
Procedure Number:
Beaver Va                Pley ower Station                                          1/2-ODC-3.03
 
==Title:==
Unit:          Level Of Use:
1/2        General Skill Reference ODCM: Controls for RETS and REMP Programs                                                Revision:      Page Number.
4    -            23 of 78 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)
CHANNEL          MODES IN WHICH CHANNEL              CHANNEL          FUNCTIONAL            SURVEILLANCE INSTRUMENT                          CHECK          CALIBRATION              TEST                REQUIRED
: 1. Noble Gas Effluent Monitors
: a. SLCRS Unfiltered Pathway (CV-2; Also called Elevated Release)
Mid Ranie Noble Gas                          S                  R                    M                  1,2,3, &4 Pri: (2HVS-RQ109C) lstPMM: (2HVS-RQ109D) 2nd PMM: (2HVS-RQI09B) 3rd PMM: Grab Sampling every 12 hours Hieh Ranee Noble Gas                        S                  R                    M                  1, 2,3, &4 Pri: (2HVS-RQ109D) lstPMM: (2HVS-RQ109C) 2nd PMM: (2HVS-RQ109B) 3rd PMM: Grab Sampling every 12 hours (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.
 
Procedure Number-Tie    Beaver Valley Power Station l                        -                  1/2-ODC-3.03
 
==Title:==
-  .Unit:.                                                                        Level Of Usv.
1/2      General Skill Reference ODCM: Controls for RETS and REMP Programs                                    Revision:    Page Number:
ATTACHMENT E Page loflO ODCM CONTROLS: RETS INSTRUMENTATION FOR LIQUID EFFLUENTS CONTROLS: RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 3.3.3.9          In accordance with BV-1 and BV-2 Technical Specification 6.8.6a, Item 1, the radioactive liquid effluent monitoring instrumentation channels shown in ODCM Control 3.3.3.9, Table 3.3-12 shall be OPERABLE with their alarmltrip 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 1/2-ODC-2.01.
Applicability: During releases through the flow path.
Action:
: a.      With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or correct the 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, explain in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.
: c.      The provisions of ODCM CONTROL 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.9            Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated operable by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in ODCM Control 3.3.3.9, Table 4.3-12.
 
Procedure Number:
Beaver Valley Power Station                                          -1/2-ODC-3.03
 
==Title:==
Unit:        Level Of Use:
1/2      General Skill Reference ODCM: Controls for RETS and REMP Programs                                Revision:          Number.
ATTACHMENT E Page 2 of 10 ODCM CONTROLS: RETS INSTRUMENTATION FOR LIQUID EFFLUENTS TABLE33-12 BV-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Pri = Primary Instruments,  Alt = Alternate Instruments MINIMUM CHANNELS INSTRUMENT                                      OPERABLE                    ACTION
: 1. Gross Activity Monitors Providing Automatic Termination Of Release
: a. Liquid Waste Effluents Monitor                                      (1)              23 Pri: (RM-lLW-104)
: b. Liquid Waste Contaminated Drain Monitor                              (1)              23 Pri: (RM-1LW-116)
: c. Auxiliary Feed Pump BayDrain Monitor                                (1)              94 Pri: (RM-IDA-100)
: 2. Gross Activity Monitors Not Providing Termination Of Release
: a. Component Cooling-Recirculation Spray Heat                          (1)              2' t Exchangers River Water Monitor Pri: (RM-lRW-100)
: 3. Flow Rate Measurement Devices a Liquid RadwasteEffluentline                                          (1)              25 Pit (FR-lLW-104) for (RM-lLW-104)
: b. Liquid Waste Contaminated Drain Line                                (1)              25 Pri: (FR-ILW-103) for (RM-ILW-116)
: c. Cooling Tower Blowdown Line                                          (1)              25 Pri: (FT-ICW-101-1) or Alt: (FT-lCW-101) and (2CWS-FT101)
: 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-lPG-115B) for (1BR-TK-6B)
: c. Steam Generator Drain Tank                                          (1)              26 Pri: (LI-ILW-1 10) for (ILW-TK-7A)
: d. Steam Generator Drain Tank                                          (1)              26 Pri: (LI-1LW-1 11) for (LLW-TK-7B)
 
Beaver Valley Power Station                                          1 Num        C  3            .03
 
==Title:==
Unit:          Level Of Use:
1/2      General Skill Reference-.
ODCM: Controls for RETS and REMP Programs ATTACHMENT E
                                                                      ;_4 Revision:
                                                                                  -_26 Page Number.
of 79      I Page 3 of 10 ODCM CONTROLS: RETS INSTRUMENTATION FOR LIQUID EFFLUENTS TABLE 3.3-12 (continued)
BV-2 RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION Pri  Primary Instruments, Alt = Alternate Instruments MINHMUM CHANNELS INSTRUMENT                                      OPERABLE                    ACTION'
: 1. Gross Radioactivity Monitor Providing Alarm And Automatic Termination Of Release
: a. Liquid Waste Process Effluent Monitor                              (1)                23 -
Pri: (2SGC-RQIOO)
: 2. Gross Radioactivity Monitors Providing Alarm But Not Providing Termination Of Release
: a. None Required
: 3. Flow Rate Measurement Devices
: a. Liquid Radwaste Effluent                                            (1)                25.
Pri: (2SGC-FS100)
: b. Cooling Tower Blowdown Line                                        (1)                25 Pri: (FT-ICW-101-1) or Alt: (FT-lCW-101) and (2CWS-FT101)
: 4. Tank Level Indicating Devices (for tanks outside plant buildings)
: a. None Required
 
Procedure Number Beaver Valley Power Station-                                              /l2-ODC-3.03
 
==Title:==
Unit:          Level Of Use:
1/2        General Skill Reference ODCM: Controls for RETS and REMP Programs                                    Revision:      Page Number:
4      -          27 of 78 ATTACHMENT E Page 4 of 10 ODCM CONTROLS: RETS INSTRUMENTATION FOR LIQUID EFFLUENTS TABLE 3.3-12 (continued)
ACTION STATEMENTS Action 23        With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may be initiated (or resumed) provided that prior to release:
: 1.      At least two independent samples are analyzed in accordance with ODCM SURVEILLANCE REQUIREMENT 4.1 1.1.1.1, and at least two technically qualified members of the Facility Staff independently verify the release rate calculations(t) and discharge valving, or
: 2.      Initiate monitoring with the comparable alternate monitoring channel. ODCM Surveillance requirements applicable to the inoperable channel shall apply to the comparable alternate monitoring channel when used to satisfy this ODCM CONTROL requirement.
Otherwise, suspend release of radioactive effluents via this pathway.
Action 24        With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided:
: 1.      That at least once per 12 hours grab samples are analyzed for gross-radioactivity (beta or gamma) at a Lower Limit of Detection (LLD) of at least 1E-7 uCi/ml, or
: 2.      Initiate monitoring with the comparable alternate monitoring channel. ODCM Surveillance requirements applicable to the inoperable channel shall apply to the comparable alternate monitoring channel when used to satisfy this ODCM CONTROL requirement.
(') 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..."
 
BeavrValley vrn              Power Statio                        I Procedure Number:
1/2..ODC-~3.03 LeelOfUs:
 
==Title:==
--          -      Unit:          Level Of Use: -.
Tie              -.                                                      1/2      General Skill Reference ODCM: Controls for RETS and REMP Programs                                Revision:    Page Number.
* 4                2of78:' XXl ATTACHMENT E Page 5 Of10 ODCM CONTROLS: RETS INSTRUMENTATION FOR LIQUID EFFLUENTS Table 3.3-12 (continued)
ACTION STATEMENTS Action 25    With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided:.
: 1. The flow rate is estimated at least once per 4 hours 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 ihe inoperable channel shall apply to the comparable alternate monitoring channel when used to satisfy this ODCM CONTROL requirement.
Action 26    With the number of channels-OPERABLE less than required by the Minimum Channels OPERABLE requirement, liquid additions to this tank may continue provided: :
: 1. The tank liquid level is estimated during all liquid additions to the tank, or
: 2. Initiate monitoring with the comparable alternate monitoring channel; ODCM Surveillance requirements applicable to the inoperable channel shall apply to the comparable alternate monitoring channel when used to satisfy this ODCM CONTROL requirement.
 
Procedure Number:
Beaver Valley Power Station                                              1/2-ODC-3.03
 
==Title:==
Unit:          Leel Of Use:
1/2        General Skill Reference ODCM: Controls for RETS and REMP Programs                                    Revision:      PageNumbcr 4                29 of 78 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 CHANNEL CHANNEL        SOURCE          CHANNEL          FUNCTIONAL INSTRUMENT                      CHECK          CHECK        CALIBRATION              TEST 1.Gross Beta or Gamma Radioactivity Monitors Providing Alarm And Automatic Termination Of Release
: a. Liquid Radwaste Effluent Line                D              PQ) -R(3)                  -lQ)
Pri: (RM-ILW-104)
: b. Liquid Waste Contaminated                  D              p(5)              R(3)                Q(
Drain Line Pri: (RM-ILW-116)
: c. Auxiliary Feed Pump Bay                    D              D                                    Qt1)
Drain Monitor Pri: (RM-IDA-100)
: 2. Gross Beta Or Gamma Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination Of Release
: a. Component Cooling - Recirculation            D              M(5)              R(3)                Q(2)
Spray Heat Exchangers River Water Monitor Pri: (RM-IRW-100) 3.Flow Rate Monitors
: a. Liquid Radwaste Effluent Lines            D(4)            NA                  R                  Q Pri: (FR-ILW-104) for (RM-lLW-104)
: b. Liquid Waste Contaminated Drain Line      D(4)            NA                  R                  Q Pri: (FR-ILW-103) for (RM-ILW-1 16)
: c. Cooling Tower Blowdown Line                D(4)            NA                  R                  Q Pri: (FT-lCW-I I-1) or Alt: (FT-ICW-101) and (2CWS-FT101)
 
PrcedureNumber-                  -    I Beaver' Valley Power Station -                                                1/2-ODC-3.03                I
 
==Title:==
Unie          Level Of Use:      -
1/2        General Skill Reference 1 ODCM:. Controls for RETS and REMP Programs                                          Revision:    Page Number          ;
_ _4              3of78 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 Iristruments CHANNEL CHANNEL            SOURCE          CHANNEL          FUNCTIONAL INSTRUMENT                        - CHECK            CHECK      CALIBRATION                TEST
: 4. Tank Level Indicating Devices (for tanks outside plant buildings)
: a. Primaxy Water Storage Tank-                      D*            -    NA                R Pri: (LI-IPG-1 15A) for (IBR-TK-6A)                                                  R                -- Q
: b. Primary Water Storage Tank                                          NA Pri: (LI -IPG-1 15B) for (1BR-TK-6B)                                                R                    Q
: c. Steam Generator Drain Tank                                        NA Pri: (LI-ILW-110) for (lLW-TK-7A)
: d. Steam Generator Drain Tank                                        NA                R                    Q Pri: (LI-lLW-I 11) for (ILW-TK-7B)
  *Duinng liquid additions to the tank.
                                                                                                            .i
 
.      ..                        ,              .                  .Procedure                Nurnber:
Beaver Valley Power Station                                                    1/2-ODC-3.03
 
==Title:==
Unit              Level Of Use:
112            General Skill Reference ODCM: Controls for RETS and REMP Programs                                          Revision:          Page Number:
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 REOUIREMENTS Pri = Primary Instruments,        Alt    Alternate Instruments CHANNEL CHANNEL              SOURCE          CHANNEL              FUNCTIONAL INSTRUMENT                        CHECK              CHECK:      CALIBRATION                    TEST
: 1. Gross Radioactivity Monitor Providing Alarm And Automatic Termination Of Release
: a. Liquid Waste Process Effluent                  D                  p( 5 )          R( 8 X3 )                Q( 7)
Pri: (2SGC-RQlOO)
: 2. Flow Rate Measurement Devices
: a. Liquid Radwaste Effluent                      D(4)                NA                R                      Q Pri: (2SGC-FSI100)
: b. Cooling Tower Blowdown Line                  D(4)                NA                R                      Q Pri: (FT-ICW-l0l-l) or Alt: (FT-ICW-ll) and (2CWS-FTl0l)
: 3. Tank Level Indicating Devices (for tanks outside plant buildings)
: a. None Required
 
                                                                                                            -IL-Beaver Valley Power Station                                              1/2-ODC-3 03
 
==Title:==
Unit:        Level Of Use:
                                                                              .-. 112 General Skl Reference GDCM: Controls for RETS and REMP Programs                                  Revision:    Pg Numer ATTACHMENT E Page 9 of 10 ODCM CONTROLS: RETS INSTRUMENTATION FOR LIQUID EFFLUENTS TABLE 4.3-12 (continued)
TABLE NOTATION The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and Control Room Alarm Annunciation occurs if any of the following conditions exist:
: 1.      Instrument indicates measured levels above the alarmltrip setpoint.
      .2.      Downscale failure.
: 3.      Instrument controls not set in operate mode.
(2)  The CHANNEL FUNCTIONAL TEST shall also demonstrate that Control Room Alarm Annunciation occurs if any of the following conditions exist:
: 1.      Instrument indicates measured levels above the alarm/trip setpoint.
: 2.      Downscale failure.
: 3.      Instrument controls are not set in operate mode.                          -
(3)    The initial CHANNEL CALIBRATION for radioactivity measurement instrumentation shall be performed using one or more of the reference standards certified by the National Bureau of (Standards/NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS/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).
(4). -CHANNEL      CHECK shall consist of verifying indication of flow during periods of release.
CHANNEL CHECK shall be made at least once daily on any day on which continuous, periodic, or batch releases are made.
A SOURCE CHECK may be performed utilizing the installed means or flashing the detector with a portable source to obtain an upscale increase in the existing count rate to verify channel response.
 
Procedure Number.
Beaver Valley Power Station                          _/2-ODC-3.03
 
==Title:==
Unit:        Level Of Use:
1/2        General Skill Reference ODCM: Controls for RETS and REMP Programs                            Revion:        ageNumber:
ATTACHMENT E Page 10 of 10 ODCM CONTROLS: RETS INSTRUMENTATION FOR LIQUID EFFLUENTS TABLE 4.3-12 (continued)
TABLE NOTATION 6    -- The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and Control Room Alarm Annunciation occurs when the instrument indicates measured levels above the Alarm/Trip Setpoint.
The CHANNEL FUNCTIONAL TEST shall also demonstrate that Control Alarm Annunciation occurs if any of the following conditions exists:
: 1.      Downscale failure.
: 2.      Instrument controls are not set in operate mode.
The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and Control Room Alarm Annunciation occurs if the instrument indicates measured levels above the alarm/trip setpoint.
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.
 
UL-Procedure Number1 Beaver Valley Power Station_:____*  Power tation1/2-ODC-3.03j
 
==Title:==
Unit:        Level Of Use:
1/2      General Skill Reference .
ODCM: Controls for RETS and REMP Programs                                  Revision:    Page Number:
4        34 of 7 ATTACHMENT F Page lofl3 ODCM CONTROLS: RETS INSTRUMENT FOR GASEOUS RELEASES CONTROLS: RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 3.3.3.10      In accordance with BV-1 and BV-2 Technical Specification 6.8.6a, Item 1, the radioactive gaseous effluent monitoring instrumentation channels shown in ODCM Control 3.3.3.10, Table 3.3 13 shall be operable with their alarm/trip setpoints set to ensure that the limits of ODCM CONTROL 3.11.2.1 are not exceeded. The alarm/trip setpoints of the radiation monitoring channels shall be determined in accordance with 1/2-ODC-2.02.
Applicability: During releases through the flow path.
Action:
: a. With a radioactive gaseous process or effluent monitoring instrumentation channel alarm/trip setpoint less conservative than a value which will ensure that the limits of ODCM CONTROL' 3.11.2.1 are met, immediately suspend the release of radioactive gaseous effluents monitored by            '~'
the affected channel or correct the alarm/trip setpoint.
: b. With one or more radioactive gaseous effluent monitoring instrumentation channels inoperable, take the ACTION shown in ODCM Control 3.3.3.10, Table 3.3-13 or conservatively reduce the alarm setpoint. Exert a best effort to return the channel to operable status within 30 days, and if unsuccessful, explain in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.
: c.      The provisions of ODCM CONTROL 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.10      Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated operable by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in ODCM Control 3.3.3.10, Table 4.3-13.
 
s I
of Beaver Valley Power Station                                          I          1r2-ODC-3.03
 
==Title:==
ODCM: Controls for RETS and REMP Programs
                                              -    ATTACHMENT F Page 2 of 13
                  .ODCM CONTROLS: RETS INSTRUMENT FOR GASEOUS RELEASES TABLE 3.3-13 BV-I RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Pri = Primary Instruments, Alt = Alternate Instruments MNI~MUM CHANNELS NgS  UMMENT                            OPERABLE            APPLICABILITY        ACTION l.Gaseous Waste/Process Vent System (PV-1,2)
: a. Noble Gas Activity Monitor                                      (1)
* 27,29,30A,30B Pri: (RM-IGW-108B) or Alt For Continuous Release: (RM-lGW-109 Ch 5) This channel may only be used as the comparable alternate monitoring channel for continuous releases via this pathway.
Alt For Batch Releases: (See Action 27) RM-lGW-109 Ch 5 SHALL NOT be used as the comparable alternate monitoring channel for batch releases of the BV-I GWDT's 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- I GWDTs or the BV-2 GWSrs via this pathway.
: b. Particulate and Iodine Sampler                                  (1)
* 32 Pri: (Filter Paper & Charcoal Cartridge for RM-lGW-109) or 1st Alt: (Filter Paper & Charcoal Cartridge for RM-lGW-l 10) or 2nd Alt: (Continuous collection via RASP Pump) or 3rd Alt: (Grab samples every 12 hours)
: c. System Effluent Flow Rate Measuring Device                      (1)
* 28A Pri: (FR-IGW-108) or Alt: (RM-lGW-109 Ch 10)
: d. Sampler Flow Rate Measuring Device Used for                    (1)
* 28B Particulate and Iodine Sample Collection (see L.b)
Pri: (RM-IGW-109 Ch 15) or Alt: (Rotometer: FM-lGW-101, and Vacuum Gauge: PI-lGW-135)
: 2. Auxiliary BuildingVentilation System (VV-1; Also called Ventilation Vent)
: a. Noble Gas Activity Monitor                                      (1)
* 29,30A Pri: (RM-IVS-1O1B) or Alt: (RM-IVS-109 Ch 5)
: b. Particulate and Iodine Sampler                                  (1)
* 32 Pri: (Filter Paper & Charcoal Cartridge for RM-IVS-109) or 1st Alt: (Filter Paper & Charcoal Cartridge for RM-IVS-1 11) or 2nd Alt: (Continuous collection via RASP Pump) or 3rd Alt: (Grab samples every 12 hours)
: c. System Effluent Flow Rate Measuring Device                      (1)
* 28A Pri: (FR-IVS-101) or Alt: (RM-IVS-109 Ch 10)
: d. Sampler Flow Rate Measuring Device Used for                    (1)
* 28B Particulate and Iodine Sample Collection (see 2.b)
Pri: (kiM-IVS-109 Ch 15) or Alt: (Rotometer: FM-I VS-102, and Vacuum Gauge: PI-lVS-659)
  *During Releases via this pathway.
 
II-Beaver Valley Power Station                                      Pred      1/2-ODC-3.03
 
==Title:==
Unit:      Level Of Use:f.rence, 1/2      General Sldll Reference -N~
ODCM: Controls for RETS and REMP Programs                                          Revision:  Page Number:
4              16 of 78 ATTACHMENT F Page 3 of 13 ODCM CONTROLS: RETS INSTRUMENT FOR GASEOUS RELEASES TABLE 3.3-13 (continued)
BV-I RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Pri = Primary Instruments,      Alt = Alternate Instruments NIMOM
                                                                  .;ANN-aS NSIRUMF                      ~OPERABLE                  APPLKABIUTY            - ACON 3.Reactor Building/SLCRS (CV-1; Also called Elevated Release)
: a. Noble Gas Activity Monitor                                    (1)                                  29,30A Pri: (RM-IVS-107B) or Alt: (RM-IVS-1 10 Ch 5)
: b. Particulate and Iodine Sampler                                (1)                                    - 32 Pri: (Filter Paper & Charcoal Cartridge for RM-IVS-l 10) or 1st Alt: (Filter Paper & Charcoal Cartridge for RM-IVS-1 12) or 2nd Alt (Continuous collection via RASP Pump) or 3rd Alt: (Grab samples every 12 hours)
: c. System Effluent Flow Rate Measuring Device                    (1)
* 28A Pri: (FR-IVS-l 12) or Alt (RM-lVS-l 10 Ch 10)
: d. Sampler Flow Rate Measuring Device Used for                  (1)                                    28B Particulate and Iodine Sample Collection (see 3.b)
Pri: (RM-IVS-I 10 Ch 15) or Alt-. (Rotometer FM-lVS-103, and Vacuum Gauge: PI-lVS-660)
  *During Releases via this pathway.
 
Procedure Number:
Beaver Valley Power Station                                                  1/2-ODC-3.03
 
==Title:==
Unit:        Level Of Use:
1/2        General Skill Reference ODCM: Controls for RETS and REMP Programs                                          Revision:    Page Number:
                                                  - ATTACHMENT F Page 4 of 13 ODCM CONTROLS: RETS INSTRUMENT FOR GASEOUS RELEASES TABLE 3.3-13 (continued!
BV-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Pri = Primary Instruments, -Alt      = Alternate Instruments MINIMUM CHA-N'ES
                          -NSTRUMEN--                            OPERABLE          APPLICABILIIY                ACMiON 1.SLCRS Unfiltered Pathway (VV-2; Also called Ventilation Vent)
: a. Noble Gas Activity Monitor                                    (1)                                      29, 30B Pri: (2HVS-RQIOlB)                                                              .
: b. Particulate and Iodine Sampler                                (1)                                          32 Pri: (Filter Paper & Charcoal Cartridge for 2HVS-RQ101) or 1st Alt: (Continuous collection via RASP Pump) or 2nd Alt: (Grab samples every 12 hours)
: c. Process Flow Rate Monitor                                    (1)                                        28A Pri: (Monitor Item 29 for 2HVS-VPId1)
: d. Sampler Flow Rate Monitor Used for Particulate                (1)
* 28B and Iodine Sample Collection (see 1.b)
Pri: (2HVS-FITIOI)
: 2. SLCRS Filtered Pathway (CV-2; Also called Elevated Release)
: a. Noble Gas Activity Monitor                                    (1)                                    - 29, 30B Pri: (2HVS-RQ109B)
: b. Particulate and Iodine Sampler                                (1)                                          32 Pri: (Filter Paper & Charcoal Cartridge for 2HVS-RQ 109 High Flow Path) or 1st Alt: (Continuous collection via RASP Pump) or
* 2nd Alt: (Grab samples every 12 hours)
: c. Process Flow Rate Monitor                                    (1)                                        28A 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                (1)                                        28B and Iodine Sample Collection (see 2.b)
Pri: (Monitor Items 28 and 72 for 2HVS-DAU109B) 3.Decontamination Building Vent (DV-2)                                                    *
: a. Noble Gas Activity Monitor                                  (1)                                          29 Pri: (2RMQ-RQ301B)
: b. Particulate and Iodine Sampler                              (1)                                          32 Pri: (Filter Paper & Charcoal Cartridge for 2RMQ-RQ301) or                        Non 1st Alt: (Continuous collection via RASP Pump)
* 2nd Alt: (Grab samples every 12 hours)
: c. Process Flow Rate Monitor                                  None                                        None
: d. Sampler Flow Rate Monitor Used for Particulate              (1)                                        28B and Iodine Sample Collection (see 3.b)
Pri: (2RMQ-FIT301)
  *During Releases via this pathway.
 
                                                                                                                        -Iti-
* Beaver Valley Power Station                            -      Procedure NumI      . -7.cjI
 
==Title:==
Unit:      Level Of Use:      :
1/2    General Skill Reference, Revision:  Page Number        .  '
ODCM: Controls for RETS and REMP Programs                                                                            -V a                  7R R onf'R ATTACHMENT F Page 5 of 13 ODCM CONTROLS: RETS INSTRUMENT FOR GASEOUS RELEASES TABLE 3.3-13 (continued)
BV-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Pri = Primary Instruments,      Alt = Alternate Instruments MNUNMMUM.
CGANNEB OPERABLE      :APPUCABILfY              ACTION
: 4. Condensate Polishing Building Vent (CB-2)
: a. Noble Gas Activity Monitor                                  (1)                                      29 Pri: (2HVL-RQI 1213)
: b. Particulate and Iodine Sampler                              (1)                                      32 Pri: (Filter Paper & Charcoal Cartridge for 2HVL-RQ112):
1st Alt: (Continuous collection via RASP Pump) 2nd Alt: (Grab samples every 12 hours)
C. Process Flow Rate Monitor                                *None                None              None
: d. Sampler Flow Rate Monitor Used for Particulate and Iodine Sample Collection (see 4.b)
Pri: (2HVL-FIT1 12)
: 5. Waste Gas Storage Vault Vent (WV-2)
(1)                                    28B I.
: a. Noble Gas Activity Monitor                                  (1)                                      29 Pri: (2RMQ-RQ303B)
: b. Particulate and Iodine Sampler                              (1)                                      32 Pri: (Filter Paper & Charcoal Cartridge for 2RMQ-RQ303) 1st Alt: (Continuous collection via RASP Pump) 2nd Alt: (Grab samples every 12 hours)
: c. Process Flow Rate Monitor                                  None                None              None
: d. Sampler Flow Rate Monitor Used for Particulate              (1)                                    28B and Iodine Sample Collection (see 5.b)
Pri: (2RMQ-FIT303)
*Dulring Releases via this pathway.
I.
 
Procedure Number:
Beaver Valley Power Station                                              1/2-ODC-3.03
 
==Title:==
Unit:        Level Of Use:
1/2        General Skill Reference ODCM: Controls for RETS and REMP Programs                                  Revision:    Page Number:
4                39 of 78
                                      -    ATTACHMENT F Page 6 of 13 ODCM CONTROLS: RETS INSTRUMENT FOR GASEOUS RELEASES I TABLE 3.3-13 (continued)
ACTION STATEMENTS Action 27      APPLICABLE FOR BATCH RELEASES OF BV-I GASEOUS WASTE DECAY TANKS OR BV-2 GASEOUS WASTE STORAGE TANKS With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the Unit I 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 independentlyverify the release rate calculations and discharge valve lineup, or
: 2.      Initiate continuous monitoring with the comparable alternate monitoring channel.
ODCM Surveillance requirements applicable to the inoperable channel shall apply.
to the comparable alternate monitoring channel when used to satisfy this ODCM Control requirement.
Otherwise, suspend releases of radioactive effluents via this pathway.
Action 28A    APPLICABLE FOR BV-1 SYSTEM EFFLUENT FLOW RATE MEASURING DEVICES OR BV-2 PROCESS FLOWRATE MONITORS With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided:
: 1.      The system/process flow rate is estimated at least once per 4 hours (or assumed to be at the ODCM design value(')), or
: 2.      Initiate continuous monitoring with the comparable alternate monitoring channel.
ODCM Surveillance requirements applicable to the inoperable channel shall apply to the comparable alternate monitoring channel when used to satisfy this ODCM Control requirement.
(')  In lieu of estimating the system/process flow rate at least once per 4 hours, the system/process flow rate can be assumed to be at the following ODCM design values:
1,450 cfin = BV-1 Gaseous Waste/Process Vent System (PV-1,2) 62,000 cfrn = BV-1 Auxiliary Building Ventilation System (VV-1) 49,300 cfm = BV-I 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)
 
a-Beaver Valey Power Station -                            -
I Procedure NumberI 1/2-ODC-3.03.
 
==Title:==
Unit:        Level Of Use:
1    1/2        General Skill Reference c, ODCM: Controls for RETS and REMP Programs                                j Revision:    Page Number:
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 RATE MEASURING DEVICES OR BV-2 SAMPLER FLOWRATE MONITORS With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided:
: 1.      The sampler flow rate is estimated at least once per 4 hours, 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.
Action 29      APPLICABLE FOR CONTINUOUS RELEASES With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided:
: 1.      Grab samples (or local monitor readings)(l) are taken at least once per 12 hours. If grab samples are taken, these samples are to be analyzed for gross activity within
                      *24hours, 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.
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 hours in-lieu of obtaining grab samples at least once per 12 hours.
 
Procedure Number:
Beaver Valley Power Station                                            1/2-ODC-3.03
 
==Title:==
Unit:          Level Of Use:
1/2      General Skill Reference ODCM: Controls for RETS and REMP Programs                              Revision:    Page Number:
4                41 of 78 ATTACHMENT F Page 8 ofl3 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-IVS-104A and B are not OPERABLE with the purge/exhaust system in service. The following should also be noted:
: 1.      As stated, this Action is applicable for INOPERABLE monitors only when performing the initial batch purge of the reactor containment atmosphere (i.e.;
immediately after reactor containment atmosphere equalization).
: 2.      Since all other releases of reactor containment atmosphere (i.e.; after the initial batch purge) are considered continuous releases, then this Action is not applicable. Therefore, Action 29 is applicable for INOPERABLE monitors when performing a continuous release of the reactor containment atmosphere.
Action 30B  APPLICABLE FOR THE INITIAL BATCH PURGE OF THE BV-2 REACTOR CONTAINMENT With the number of channels OPERABLE less than required by Minimum Channels OPERABLE requirement, immediately suspend PURGING of Reactor Containment via this pathway if both 2HVR-RQI04A and 104B are not OPERABLE with the purge/exhaust system in service. The following should also be noted:
: 1. As stated, this Action is applicable for INOPERABLE monitors only when performing the initial batch purge of the reactor containment atmosphere (i.e.;
immediately after reactor containment atmosphere equalization).
: 2.      Since all other releases of reactor containment atmosphere (i.e.; after the initial batch purge) are considered continuous releases, then this Action is not applicable. Therefore, Action 29 is applicable for INOPERABLE monitors when performing a continuous release of the reactor containment atmosphere.
Action 32  APPLICABLE FOR CONTINUOUS RELEASES With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided samples are continuously collected with auxiliary sampling equipment as required in ODCM Control 3.11.2.1, Table 4.11-2, or sampled and analyzed once every 12 hours.
 
Bevr Beaver Valy valley        Power Station_
_  Procedure Number        a- -
                                                                                                          /2-ODC-3.03
 
==Title:==
Unit:          Level Of Use:
1  1/2        General Skill Reference ODCM: Controls for RETS and REMP Programs                                                  Revision:      Page Numbero ATTACHMENT F Page 9 of 13 ODCM CONTROLS: RETS INSTRUMENT FOR GASEOUS RELEASES TABLE 4.3-13 BV-I RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Pri = Primary Instruments, Alt = Alternate Instruments CHANNEL CHANNEL        SOURCE            CHANNEL          FUNCTIONAL INSTRUMENT                              CHECK        CHECK        CALIBRATION                TEST
: 1. Gaseous Waste/Process Vent System (PV-1,2)
: a. Noble Gas Activity Monitor                              '      p            p' 4              R'(3                  Q(1)
Pri: (RM-IGW-108B)
Alt For Continuous Release: (RM-IGW-109 Ch 5) This channel may only be used as the comparable alternate monitoring channel for continuous releases via this pathway.
Alt For Batch Releases: (See Action 27): RM-I GW-l 09 Ch'5 SHALL NOT be used as the comparable alternate monitoring channel for batch releases of the BV-I 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-I 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-IGW-109) or Ist Alt: (Filter Paper & Charcoal Cartridge for RM-IGW-I 10) or 2nd Alt: (Continuous collection via RASP Pump) or 3rd Alt: (Grab samples every 12 hours)
: c. System Effluent Flow Rate Measuring Device                  P            NA                R                    Q Pri: (FR- IGW- 108) or Alt: (RM-IGW-109 Ch 10)
: d. Sampler Flow Rate Measuring Device Used for                  D*            NA                R                    Q Particulate and Iodine Sample Collection (see I.b)
Pri: (RM-IGW-109 Ch 15) or Alt: (Rotometer FM-IGW-101, and Vacuum Gauge: PI-IGW-135)
: 2. Auxiliary Building Ventilation System (VV-I; Also called Ventilation Vent)
: a. Noble Gas Activity Monitor                                    D            M(4)              R(3)                  Q(2)
Pri: (RM-IVS-IOIB) or                                                    p(4)**
Alt: (RM-IVS-109 Ch 5)
: b. Particulate and Iodine Samplerj                                W            NA                NA                    NA Pri: (Filter Paper & Charcoal Cartridge for RM-IVS-109) or Ist Alt: (Filter Paper & Charcoal Cartridge for RM-1VS- 1I1) or 2nd Alt: (Continuous collection via RASP Pump) or 3rd Alt: (Grab samples every 12 hours)
: c. System Effluent Flow Rate Measurement Device                    D          NA                R                    Q Pri: (FR-IVS-101) or Alt: (RM-IVS-109 Ch 10)
: d. Sampler Flow Rate Measuring Device Used for                    D            NA                R                      Q Particulate and Iodine Sample Collection (see 2.b)
Pri: (RM-IVS-109 Ch 15) or Alt: (Rotometer FM-IVS-102, and Vacuum Gauge: PI-IVS-659)
* During Releases via this pathway.
  *** During purging of Reactor Containment via this pathway.
 
Beaver Valley Power Station                                          Procedu1Num          DC 3    3
 
==Title:==
Unit:          Level Of Use:
1/2        General Skill Reference ODCM: Controls for RETS and REMP Programs                                            Revision:      Page Number:
4                43 of 78 ATTACHMENT F Page 10 of 13 ODCM CONTROLS: RETS INSTRUMENT FOR GASEOUS RELEASES
                                              -  :    TABLE 4.3-13 BV-I RADIOACTIVE GASEOUS EFFLUENT MONITORING
                        - INSTRUMENTATION SURVEILLANCE REQUIREMENTS Pri = Primary Instruments, Alt = Alternate Instruments CHANNEL CHAI OTT
                                                                        .NNEL SOURCE        CHANNEL          FUNCTIONAL TXTC!T'TT TX&7 T 1IN.i1 KUIVrN I              -            fli]tECK  CHECK CALIBRATION                  TEST
: 3. Reactor Building/SLCRS (CV-1; Also called Elevated Release)
: a. Noble Gas Activity Monitor                                    ID)(4)                  R 3)                Q(2).
p(4)***
Pri: (RM-IVS-107B)or Alt: (RM-IVS-1 10 Ch 5)
: b. Particulate and Iodine Sampler                                W          NA            NA                  NA Pri: (Filter Paper & Charcoal Cartridge for RM-lVS-1 10) or 1st Alt: (Filter Paper & Charcoal Cartridge for RM-IVS-1 12) or 2nd Alt: (Continuous collection via RASP Pump) or 3rd Alt: (Grab samples every 12 hours)
: c. System Effluent Flow Rate                                      D          NA            R                    Q Measuring Device Pri: (FR-IVS-i 12) or Alt: (RM-IVS-1 10 Ch 10)
: d. Sampler Flow Rate Measuring Device Used for                    D          NA            R                    Q Particulate and Iodine Sample Collection (see 3.b)
Pri: (RM-lVS-1 10 Ch 15) or Alt: (Rotometer: FM-IVS-103, and Vacuum Gauge: PI-1VS-660)
  *During releases via this pathway.
  ***During purging of Reactor Containment via this pathway.
 
Beaver Valley Power Station                                                  1d/NU i2-ODC-3.03          -
 
==Title:==
Unit:        - Level Of Use:      . .ee-c-1O2          General SkislRererence:
ODCM: Controls for RETS and REMP Programs                                        Rvso:            Pg    ubr                  .I 4                  44 of 78 ATTACHMENT F
                                                  . Page 11 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 CHANNEL    SOURCE      CHANNEL            FUNCTIONAL INSTRUMENT                            CHECK    CHECK      CALIBRATION              TEST I.SLCRS Unfiltered Pathway (VV-2; Also called Ventilation Vent)
: a. Noble Gas Activity Monitor                              D        AV),  -      R N A(3X              Q(5).
Pri: (2HVS-RQ1OIB)                                                p(4)***
                                                                                          .NA
: b. Particulate and Iodine Sampler                          W          NA                                  NA Pri: (Filter Paper & Charcoal Cartridge for 2HVS-RQ1IO) or 1st Alt: (Continuous collection via RASP Pump) or 2nd Alt: (Grab samples every 12 hours)
: c. Process Flow Rate Monitor                                D          NA              R                    Q Pri: (Monitor Item 29 for 2HVS-VP101)
: d. Sampler Flow Rate Monitor Used for Particulate          D          NA              R                    Q and Iodine Sample Collection (see 1.b)
Pri: (2HVS-FITIOI) 2.SLCRS Filtered Pathway (CV-2; Also called Elevated Release)
: a. Noble Gas Activity Monitor                              D        M(4),        R( 3 X6                Q(5)
Pri: (2HVS-RQ109B)                                                p(4)***
: b. Particulate and Iodine Sampler                          W          NA            NA                  NA Pri: (Filter Paper & Charcoal Cartridge for 2HVS-RQ109 High Flow Path) or 1st Alt: (Continuous collection via RASP Pump) or                                                            Q_
2nd Alt: (Grab samples every 12 hours)
: c. Process Flow Rate Monitor                                D        NA            R                      Q Pri: (Monitor Item 29 for 2HVS-FR22) or 1st Alt: (2HVS-FI22A and F122C) 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-DAUI09B)
: 3. Decontamination Building Vent (DV-2)
: a. Noble Gas Activity Monitor                              D                                              Q(5)
Pri: (2RMQ-RQ301B)
NA                    NA
: b. Particulate and Iodine Sampler                          W        NA Pri: (Filter Paper & Charcoal Cartridge for 2RMQ-RQ301)  or 1st Alt: (Continuous collection via RASP Pump) or 2nd Alt: (Grab samples every 12 hours)
: c. Process Flow Rate Monitor                                NA        NA            NA                    NA
: d. Sampler Flow Rate Monitor Used for Particulate            D        NA            R                      Q and Iodine Sample Collection (see 3.b)
Pri: (2RMQ-FIT301)
 
Procedure Number.
                -Beaver Valley Power Station                                                  1/2-ODC-3.03
 
==Title:==
.        .Unit:                                                Level Of Use:
1/2          General Skill Reference ODCM: Controls for RETS and REMP Programs                                        Revision:      Page Number 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 CHANNEL.      SOURCE          CHANNEL          FUNCnIONAL INSTRUMENT                            CHECK        CHECK      CALIBRATION              TEST
: 4. Condensate Polishing Building Vent (CB-2):
: a. Noble Gas Activity Monitor                                D                          R(3 X6 Pri: (2HVL-RQI12B)
: b. Particulate and Iodine Sampler                            W          NA              NA                NA Pri: (Filter Paper & Charcoal Cartridge for 2HVL-RQ1 12) or Ist Alt: (Continuous collection via RASP Pump) or 2nd Alt: (Grab samples every 12 hours)
: c. Process Flow Rate Monitor                                NA          NA              NA                NA
: d. Sampler Flow Rate Monitor Used for Particulate          D            NA                R                  Q and Iodine Sample Collection (see 4.b)
Pri: (2HVL-FlTl 12) -
: 5. Waste Gas Storage Vault Vent (WV-2) 3
: a. Noble Gas Activity Monitor                                D                          R( X)              Q(5)
Pri: (2RMQ-RQ303B)
: b. Particulate and Iodine Samples                            W          NA              NA                NA Pri: (Filter Paper & Charcoal Cartridge for 2RMQ-RQ303) or 1st Alt: (Continuous collection via RASP Pump) or 2nd Alt: (Grab samples every 12 hours)
: c. Process Flow Rate Monitor                                NA          NA              NA                NA
: d. Sampler Flow Rate Monitor Used for Particulate          D            NA                R                  Q and Iodine Sample Collection (see 5.b)
Pri: (2RMQ-FIT303)
 
II-Procedure Number Beaver Valley Power Station                                              1/2-ODC-3.03
 
==Title:==
Unit:        Level Of Use
                    ..                                                        1/2        General Skill Reference ,
ODCM: Controls for RETS and REMP Programs                                  Revision:    Page Number              -I 4o ATTACHMENT F Page 13 of 13 ODCM CONTROLS: RETS INSTRUMENT FOR GASEOUS RELEASES TABLE 4.3-13 (continued)
                                      - TABLE        NOTATION (1)    The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and Control Room Alarm Annunciation occurs if any of the following conditions exist:
: a.      Instrument indicates measured levels above the alarm/trip setpoint.
      .b.      Downscale failure.
: c.      Instrument controls not set in operate mode.
(2)    The CHANNEL FUNCTIONAL TEST shall also demonstrate that Control Room Alarm Annunciation occurs if any of the following conditions exist:
: a.      Instrument indicates measured levels above the alarm/trip setpoint.
: b.      Downscale failure.
: c.      Instrument controls not set in operate mode.
(3)    The initial CHANNEL CALIBRATION for radioactivity measurement instrumentation shall ber' performed using one or more of the reference standards certified be National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards should permit calibrating the system over its intended range of energy and rate capabilities. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration should be used, at intervals of at least once per 18 months. This can normally be accomplished during refueling outages.
(4)    A SOURCE CHECK may be performed utilizing the installed means or flashing the detector with a portable source to obtain an upscale increase in the existing count rate to verify channel response.
(5)    The CHANNEL FUNCTIONAL TEST shall also demonstrate that Control Room Alarm Annunciation occurs if the instrument indicates measured levels above the 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 NurDC          3  3
 
==Title:==
Unit:          Level Of Use:
1/2      General Skill Reference ODCM: Controls for RETS and REMP Programs                                  Revision:    PageNumber ATTACHMENT G Page 1 of 5 ODCM CONTROLS: LIQUID EFFLUENT CONCENTRATION CONTROLS: LIQUID EFFLUENT CONCENTRATION 3.11.1.1        In accordance with BV-I and BV-2 Technical Specification 6.8.6a, Items 2 and 3, the concentration of radioactive material released at any time from the site (see 1/2-ODC-2.01, Figure 5-1) shall be limited to 10 times the EC's specified in 10 CFR Part 20, Appendix B (20.1001-20.2401), Table 2, Colunm 2 for radionuclides other than dissolved orfentrained 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/mI total activity.
Applicability:      At all times.
Action:
: a.  ' With the concentration of radioactive material released from the site to unrestricted areas exceeding the above limits; immediately restore the concentration within the above limits, and
: b.      Submit a Special Report to the Commission within 30 days in accordance with 10 CFR 20.2203(a)(2)(v) and 10 CFR 50.4(b)(1).
: c.      The provisions of ODCM CONTROL 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.1.1.1    Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of ODCM Control 3.11.1.1, Table 4.11-1*.
4.11.1.1.2    The results of radioactive analysis shall be used in accordance with 1/2-ODC-2.01 to assure that the concentration at the point of release are maintained within the limits of ODCM CONTROL 3.11.1.1.
4.11.1.1.3    When BV-1 primary to secondary leakage exceeds 0.1 gpm (142 gpd), samples of the Turbine Building Sump shall be obtained every 8 hours 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.
 
Beaver Valley Power Station                                        I Procedure Number 1/2-ODC-3'03 I  -
 
==Title:==
Unit:        Level Of Use:
1/2      General Skill Reference ODCM: Controls for RETS and REMP Programs                                  -Revision:                Page Number:
4                49 of 78' ATTACHMENT G Page 2 of 5 ODCM CONTROLS: LIQUID EFFLUENT CONCENTRATION SURVEILLANCE REQUIREMENTS (continued) 4.11.1.1.4          When BV-2 primary to secondary leakage exceeds 0.1 gpm (142 gpd), samples of the Turbine Building Sump shall be obtained every 8 hours to ensure that the Turbine Building Sump concentration does not exceed 1 OEC. Once it is determined that an OEC is reached, the Turbine Building Sump shall be routed to Steam Ge'nerator blowdown hold tank (2SGC-TK21A or 2SGC-TK21B).
4.11.1.1.5*        Pror to the BV-2 Recirculation Drain Pump(s) (2DAS-P215AIB) discharging to catch basin 16, a grap sample will be-taken. The samples will be analyzed for gross activity at a sensitivity of at least 1E-7 uCi/ml. Water volume discharged shall be estimated from the number of pump operations unless alternate flow or volume instrumentation is provided.
* Radioactive liquid discharges are normnally via batch modes. BV-1 and BV-2 Turbine Building Drains shall be monitored as specified in ODCM SURVEILLANCE REQUIREMENT 4.11.1.1.3 and 4.11.1.1.4. The BV-2 Recirculation drain pump discharge shall be monitored as specified in ODCM SURVEILLANCE REQUIREMENT 4.11.1.1.5, respectively.
 
Procedure Number~
Beaver Valley Power Station                                                P/2-ODC-303
 
==Title:==
Unit:          Level Of Use:
1/2          General Skill Reference ODCM: Controls for RETS and REMP Programs                                                Revision:      Page Number.
4                  49 of 78 ATTACHMENT G Page 3 of 5 ODCM CONTROLS: LIQUID EFFLUENT CONCENTRATION
                                                    . TABLE 4.1 1-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LOWER MINIMUM                TYPE OF                LIMIT OF LIQUID            SAMPLING ANALYSIS                          ACTIVITY              DETECTION RELEASE TYPE        FREQUENCY FREQUENCY                          ANALYSIS                    (LLD)
_ _ _ _ _  _ _ _ _ _ _  _  _ _ _ _ _ _ _ _  _  _ _  _ _ _ _ _ _ _  _    ( C i/m l)(a)
A. Batch Waste              P                    P            Principal Gamma                  5E17 Release Tanks(d) Each Batch(h)        Each.Batch()                Emitters(')
I-131                            1E-6 P                  M              Dissolved And                  1E-5 One                                  Entrained Gases Batch/M(h)                            (Gamma Emitters)
P                  M            H-3                              IE-5 Each Batch(E)        Composite(b)            Gross Alpha                  lE-7 P                                Sr-89, Sr-90                      5E-8 Each Batch(h) Composite(b)              Fe-55                            IE-6 B. Continuous        Grab Sample g)              W            Principal Gamma                  5E-7 Releases(e~)                            Composite(C)              Emitters~f?        .
                                                  -                  I-131 1                                1E-6 Grab Sample(g)              M              Dissolved And                  1E-5 Entrained Gases
____                    (Gamma Emitters)
Grab Sample          :      M.          H-3 .                            lE-5 Composite(C)            Gross Alpha                  IE-7 Grab Sample~g)              Q          Sr-89, Sr-90                      5E-8 Composite(c)        Fe-55                            11E-6
 
_-      .1-Procedure Number.
Beaver Valley Power Station______- Powe Staion1/2                          1ODC-3.03
 
==Title:==
Unit :        Level Of Use: - ec C                                              C      1/2                              N, GeneralfodgPReferenceNm ODCM: Controls for RETS- and REMP Programns                                Reiin I                            IaeNubr ATTACHMENT G Page 4 of 5 ODCM CONTROLS: LIQUID EFFLUENT CONCENTRATION TABLE 4.11-1 (continued)
TABLE NOTATION (a)
The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation):
LLD =          4.66 Sb (E)(V)(2.22)(Y) exp(-XAT)
N where:
LLD is the lower limit of detection as defined above (as pCi per unit mass or volume);
Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute);
E is the counting efficiency (as counts per transformation);
V is the sample size (in units of mass or volume);
2.22 is the number of transformations per minute per picocurie; Y is the fractional radiochemical yield (when applicable);
X is the radioactive decay constant for the particular radionuclide; AT is the elapsed time between sample collection (or end of the sample collection period) and time of counting (for environmental samples, not plant effluent samples).
The value of Sb used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. Typical values of E, V, Y and AT should be used in the calculations.
The LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as a posteriori (after the fact) limit for a particular measurement.
                                                                                                                ?
 
Beaver Valley Power Station                                  ProcedureNu2-ODC-3.03
 
==Title:==
Unit:      Level Of Use:
1/2    General Skill Reference ODCM: Controls for RETS and REMP Programs                                  Revision:  Page Nunber 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.
(c)    To be representative of the quantities and concentrations of radioactive materials in liquid' effluents, samples shall be collected continuously in proportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.
(d)    A batch release exists when the discharge of liquid wastes is from a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampling.
(e)    A continuous release exists when the discharge of liquid wastes is from a non-discrete volume; e.g., from a volume of a system having an input flow during the continuous release. Releases from the Turbine Building Drains and the AFW Pump Bay Drain System and Chemical Waste Sump are considered continuous when the primary to secondary leak rate exceeds 0.1 gpm (142 gpd).
The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be detected and reported.
Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the 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 Annual Radioactive Effluent Release Report.
(g)    When radioactivity is identified in the secondary system, a RWDA-L should be prepared on a monthly basis to account for the radioactivity that will eventually be discharged to the Ohio River.
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 hours during pump operation.
 
Beaver Valley Power Station                                      edureNum          C      -
 
==Title:==
Unit:      Level Of Use: .
1/2  l  General Skill Reference ODCM: Controls for RETS and REMP Programs                                      Revision:  Page Number.
4        52 of 7 ATTACHMENT Hi Page 1 of 1 ODCM CONTROLS: LIQUID EFFLUENT DOSE CONTROLS: LIQUID EFFLUENT DOSE 3.11.1.2          In accordance with BV-1 and BV-2 Technical Specification 6.8.6a, Items 4 and 5, the
.                  dose or dose commitment to MJEMBER(S) OF THE PUBLIC from radioactive materials in liquid effluents released from the reactor unit (see 1/2-ODC-2.01 Figure 5-1) shall be.
limited:
: a.      During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and
: b.      During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.
Applicability:        At all times.
Action:
: a.      With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to 10 CFR 20.2203(a)(2)(v) and 10 CFR 50.4(b)(1), a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce the releases, and
                                                                                                                      .F 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 shall be determined in accordance with 1/2-ODC-2.01 at least once per 31 days.
* Applicable only if drinking water supply is taken from the receiving water body within three miles of          -
the plant discharge (three miles downstream only).                            ,-
 
Procedure Number:
Beaver Valley Power Station                                              1/2-ODC-3.03
 
==Title:==
Unit:        Level Of Use:
1/2        General Skill Reference ODCM: Controls for RETS and REMP Programs                                  Revision:    Pg            ofm78 ATTACHMENT I Page 1 of 1 ODCM CONTROLS: LIQUID RADWASTE TREATMENT SYSTEM CONTROLS: LIQUID RADWASTE TREATMENT SYSTEM 3.11.1.3      In accordance with BV-1 and BV-2 Technical Specification 6.8.6a, Item 6, the Liquid Radwaste Treatment System shall be used to reduce the radioactive materials in each liquid waste batch prior to its discharge when the projected doses due to liquid effluent releases from the reactor unit (see 1/2-ODC-2.01 Figure 5-1) when averaged over 31 days would exceed 0.06 mrem to the total body or 0.2 mrem to any organ.
Applicability:      At all times.
Action:
: a.      With liquid waste being discharged without treatment and exceeding the limits specified, prepare and submit to the Commission within 30 days pursuant to 10 CFR 20.2203(a)(2)(v) and 10 CFR 50.4(b)(1) a Special Report which includes the following information:
: 1.  - Identification of the inoperable equipment or subsystems and the reason for inoperability.
: 2. Action(s) taken to restore the inoperable equipment to operational status, and
: 3.      Summary description of action(s) taken to prevent a recurrence.
: b.      The provisions of ODCM CONTROL 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.1.3.1      Doses due to liquid releases shall be projected at least once per 31 days, in accordance with 1/2-ODC-2.01.
 
                                                                                                                                      'I-Beaver Valley Power Station .edureNum
_______ ______ ___ ___ ____ ____ ___  ___  ____  ___ ___ __1/2-OD                    C-3.03 lTtle:                                                                                      Unit:        Level Of Use:    -
                                                                                                . 112 General Skil Reference ODCM: Controls for RETS and REMP Programs                                                    Revision:    Page Number:
4                54 of 8 ---
ATTACHMENT J Page I of I ODCM CONTROLS: LIQUID HOLDUP TANKS CONTROLS: LIQUID HOLDUP TANKS
.3.11.1.4              In accordance with BV-1 and BV-2 Technical Specification 6.8.6c, the quantity of radioactive material contained in each of the following tanks shall be limited to the values listed below, excluding tritium and dissolved or entrained noble gases.
: a.  <21 Curies: IBR-TK-6A (Unit I Primary Water Storage Tank)
: b.  < 21 Curies: lBR-lTK-6B (Unit I Primary Water Storage Tank)
: c.  < 7 Curies: ILW-TK-7A (Unit 1 Steam Generator Drain Tank)
: d.  < 7 Curies: ILW-TK-7B (Unit 1 Steam Generator Drain Tank)
: e.  < 5 Curies: 1QS-TK-l (Unit I Refueling Water Storage Tank-RWST)
: f.  < 139 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 ariea (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 hours 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          The quantity of radioactive material contained in each of the above listed tanks (except the Unit 1 and 2 RWST's) shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.
4.11.1.4.2          SINCE additions of radioactive material to the Unit I and 2 RWSTs are normally made at the end of a refueling outage (i.e.; drain down of the reactor cavity back to the RWST), THEN comnliance to this limit shall he nerformed as follows:                                                    .IH The quantity of radioactive material contained in the Unit 1 and 2 RWST's shall be determined to7 -
be within the above limit by analyzing a representative sample of the tank's contents within 7 days after transfer of reactor cavity water to the respective Unit's RWST.
 
Procedure Number.
Beaver Valley Power Station                                              1/2-ODC-3.03
 
==Title:==
Unit:        Level Of Use:
1/2      General Skill Reference ODCM: Controls for RETS and REMP Programs                                  Revision:    Page Number:
4                55 of 78 ATTACHMENT K Page 1 of 5 ODCM CONTROLS: GASEOUS EFFLUENT DOSE RATE CONTROLS: GASEOUS EFFLUENT DOSE RATE 3.11.2.1        In accordance with BV-1 and BV-2 Technical Specification 6.8.6a, Items 3 and 7, the dose rate in the unrestricted areas (see 1/2-ODC-2.02 Figure 5-1) due to radioactive materials released in gaseous effluents from the site shall be limited to the following values:
: a. The dose rate limit for noble gases shall be < 500 mrem/yr to the total body and <
3000 mrem/yr to the skin*, and
: b. The dose rate limit, inhalation pathway only, for I-131, tritium and all radionuclides in particulate form (excluding C-14) with half-lives greater than eight days shall be < 1500 mrem/yr to any organ.
Applicability:      At all times.
Action:
: a. With the dose rate(s) exceeding the above limits, immediately decrease the release rate to comply with the above limits(s), and
: b. Submit a Special Report to the Commission within 30 days pursuant to 10 CFR 20.2203(a)(2)(v) and 10 CFR 50.4(b)(1).
: c. The provisions of ODCM CONTROL 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.1.1      The dose rate due to noble gaseous effluents shall be determined to be within the above limits in accordance with 1/2-ODC-2.02.
4.11.2.1.2      The dose rate, inhalation pathway only, for 1-13-1, tritium and all radionuclides in particulate form (excluding C-14) with half-lives greater than eight days in gaseous effluents, shall be determined to be within the above limits in accordance with the methods and procedures of the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in ODCM Control 3.11.2.1, Table 4.11-2.
  *During containment purge the dose rate may be averaged over 960 minutes.
 
Procedure Number:
Beaver Valley Power Station                                              1/2-ODC-3.03 TIer                                                                          Unit:        j Level Of Use:
  .DM1/2                                                                                      General Skill RefeErencei--
ODCM: Controls for RETS and REMP Programs                                      Reiin            ae ubr ATTACHMENT K Page 2 of 5 ODCM CONTROLS: GASEOUS EFFLUENT DOSE RATE TABLE 4.11-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM MINHIMUM              TYPE              LOWER LIMIT OF GASEOUS                SAMPLING      ANALYSIS                OF                  DETECTION RELEASE              FREQUENCY FREQUENCY                ACTIVITY                      (LLD)
TYPE                    -                -          ANALYSIS                  (uCi/ml)(a)
A. Waste Gas Storage                  P            P            Principal                    1E-4 Tank                        Each Tank    Each Tank            Gamma Grab Sample        .Emitters(g)
Each Tank*    Each Tank* H-3*                                  1E-6 Grab Sample B. Containment Purge                  P              P        Principal Gamma                  1E-4 Each Purge(b) Each Purge(b)        Emitters(g)
Grab Sample                  H-3                              1E-6 C. Ventilation                  i(D                          Principal Gamma                  1E-4 Systems h)                Grab Sample                        Emittersg)
VV-I (Ul PABNentilation Vent)                                H-31E6 CV-1 (UlI Rx ContlSLCRS Vent)
PV-1/2 (Ul/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)
* The H-3 concentration shall be estimated prior to release and followed up with an H-3 grab sample from the Ventilation System during release.
 
Procedure Number.
Beaver Valley Power Station                                                1/2-ODC-3. 0 3
 
==Title:==
Unit:        Level Of Use:
1/2        General Skill Reference ODCM: Controls for RETS and REMP Programs                                      Revision:    Page Number ATTACHMENT K Page 3 of 5 ODCM CONTROLS: GASEOUS EFFLUENT DOSE RATE TABLE 4.11-2 (continued)
RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM MIN.IUM              TYPE              LOWER LIMIT OF GASEOUS            SAMPLING ANALYSIS                      OF                  DETECTION RELEASE          FREQUENCY              QUENC        ACTIVITY                    (LLD)
TYPE                                              ANALYSIS                  (uCi/ml)(3)
D. All Ventilation    Continuoust    -7              1-131                            I.E-12 Systems Listed                      Charcoal        1-133                          lE-10 Above (in C.)                      Sample Which Produce      _      _      ._.
Continuous        Continuous          7W'          Principal Gamma                IE-1 1 Release                            Particulate        - Emitters(g)
Sample          (I-131, Others)
Continuousif            M        GrossAlpha                      lE-1l Composite Particulate Sample      . _  . _. _..
                            .inuousWt            . Q        Sr-89, Sr-90                    lE-l1 Composite
                                          . Particulate
                            .Sample
                          . Continuous(f    Noble Gas      Noble Gases                      lE-6 Monitor        Gross Beta And
                                            ._ ._ . -        Gamma
 
Beaver Valley Power Station                                          -
Procedure Number:
l/2-ODC-3.03                  J
 
==Title:==
Unit:          LevelfOfUse:
M                                                              1/2        PaGeneral Skill Reference,:
ODCM: . Controls for RETS and REMP Programs                                                4                5eison of UaeNuner ATTACEMENT K Page 4 of 5.
ODCM CONTROLS: GASEOUS EFFLUENT DOSE RATE TABLE 4.11-2 (continued)
TABLE NOTATION (a)  The Lower Limit of Detection (LLD) is defined in Table Notation (a) of ODCM Control 3.1 1.1.1, Table 4.11-I for ODCM Surveillance Requirement 4.11.1.1.,
(b)  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 hour period. This requirement does not apply if (1) analysis shows that the Dose Equivalent 1-131 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 hours of reaching the intended steady state power level, and analyzed within 48 hours 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 lI*)
(c)  Tritium grab samples shall be taken at least once per 24 hours (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. (3.1l1) (3.119)
(d)  Part 1: Samples (continuous particulate & iodine) shall be changed at least once per 7 days and analyses shall be completed within 48 hours after changing, or after removal from sampler.
Applicability for Part 1: Unit I 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 hours for at least 7 days following each SHUTDOWN, STARTUP, or THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1 hour period and analyses shall be completed within 48 hours of changing.
When samples collected for 24 hours 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 hours of reaching the intended steady state power level, and analyzed within 48 hours of reaching the intended steady state power level.
Applicability for Part 2: Unit I 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)
 
Procedure Number Beaver Valley Power Station                                                      1/2-ODC-3.03
 
==Title:==
Unit:        Level Of Use:
1/2        General Skill Reference ODCM: Controls for RETS and REMP Programs                                          Revision:    Page Number ATTACHMENT K
                                              - Page 5 of 5 ODCM CONTROLS: GASEOUS EFFLUENT DOSE RATE (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 I 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 ' 9 )
(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 N13.1. 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 of 2 provides adequate compensation for any negative bias in particulate sample collection. (3.2.13)
Applicability: Unit I Ventilation Systems (VV-I, 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 I and Unit 2 Ventilation Systems (VV-1, CV-1, PV-1/2, VV-2, CV-2, DV-2, WV-2 &
CB-2).
 
Bae
_..                                                    .Prcedure      Number.        S      Ren Te:
Beaver      Valley Power Station                          -                      Of Use:
 
==Title:==
Unit:        /2-ODC-3 1/ Level Of Use:.03  -
:1/2                                                        General Skill Reference ODCM: Controls for RETS and REMP Programs                                    Revision:      Page Number 4        60 of 7 ATTACHMENT L Page Iof 1 ODCM CONTROLS: DOSE- NOBLE GASES.
CONTROLS: DOSE-NOBLE GASES 3.11.2.2        In accordance with BV-1 and BV-2 Technical Specification 6.8.6a, Items 5 and 8, the air dose from the reactor unit in unrestricted areas (see 1/2-ODC-2.02 Figure 5-1) due to noble gases released in gaseous effluents shall be limited to the following:
: a. During any calendar quarter, to < 5 mrad for gamma radiation and < 10 mrad for beta radiation.
: b. During any calendar year, to
* 10 mrad for gamma radiation and < 20 mrad for beta radiation.
Annlicabilitv-      At all times.
Actic in:                                                  --                        :.
: a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the6 above limits, prepare and submit to the Commission with in 30 days, pursuant to 10 CFR 20.2203(a)(2)(v) and 10 CFR 50.4(b)(1), a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions taken to reduce the releases and the proposed corrective actions to be taken to assure the subsequent releases will be within the above limits.
: b. The provisions of ODCM CONTROL 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.2.1      Dose Calculations. Cumulative dose contributions shall be determined in accordance with 1/2-ODC-2.02 at least once every 31 days.
 
Procedure Number:
Beaver Valley Power Station                                                1/2-ODC-3.03
 
==Title:==
.Unit:                                                                              Level Of Use:
N e                                                                            1U2      General Skill Reference ODCM: Controls for RETS and REMP Programs                                      Revision:    Page Number 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 BV-1 and BV-2 Technical Specification 6;8.6a, Items 5 and 9, the dose to MEMBER(S) OF THE PUBLIC from radioiodines and radioactive materials in particular form (excluding C-14), and radionuclides (other than noble gases) with half-lives greater than eight days in gaseous effluents releases from the reactor unit (see 1/2-ODC-2.02 Figure 5-1) shall be limited to the following:
: a.      During any calendar quarter to < 7.5 mrem to any organ, and
: b.      During any calendar year to < 15 mrehm to any organ.
Applicability:        At all times.
Action:
: a.        With the calculated dose from the release of radioiodines, radioactive materials in particulate form, (excluding C-14), and radionuclides (other than noble gases) with half-lives greater than eight days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to 10 CFR 20.2203(a)(2)(v) and 10 CFR 50.4(b)(1), a Special Report, which identifies the cause(s) for exceeding the limit and defines the corrective actions taken to reduce the releases and the proposed corrective actions to be taken to assure the
            -subsequent releases will be within the above limits.
: b.        The provisions of ODCM CONTROL 3.03 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.3.1        Dose Calculations. Cumulative dose contributions shall be determined in accordance with 1/2-ODC-2.02 at least once every 31 days.
 
BPecaue    Number        I -33  ' .
Beaver Valley Power Station                                              12OC30
 
==Title:==
Unit:        Lcvel Of Use:    --e-
                      .    ..                                                  1/2      General Skill ReferenceK ODCM: Controls for RETS and REMP Programs                                  Revision:    Page Number X--4                          62 of 79 ATTACHMENT N Page 1 of 1 ODCM CONTROLS: GASEOUS RADWASTE TREATMENT SYSTEM CONTROLS: GASEOUS RADWASTE TREATMENT SYSTEM 3.11.2.4        In accordance with BV-I and BV-2 Technical Specification 6.8.6a, Item 6, the Gaseous Radwaste Treatment System and the Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases from the reactor unit (see 1/2-ODC-2.02 Figure 5-1), when averaged over 31 days, would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation. The appropriate portions of the Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases from the reactor unit (see 1/2-ODC-2.02 Figure 5-1) when averaged over 31 days would exceed 0.3 mrem to any organ.
Applicability:      At all times.
Action:
: a.      With gaseous waste being discharged without treatment and in excess of the above lirmits, prepare and submit to the Commission within 30 days, pursuant to.10 CFR 20.2203(a)(2)(v) and 10 CFR 50.4(b)(1), a Special Report which includes the following information.
: 1.    'Identification of the inoperable equipment or subsystems and the reason for inoperability,
: 2.      Action(s) taken to restore the inoperable equipment to operational status, and
: 3.      Summary description of action(s) taken to prevent a recurrence.
: b.      The provisions of ODCM CONTROL 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS' 4.11.2.4.1      Doses due to gaseous releases from the site shall be projected at least once per 31 days, in accordance with 1/2-ODC-2.02.
 
Beaver Valley Power Station                                Procedure1NueDC- 3        . 3
 
==Title:==
Unit:        Level Of Use:
1/2    General Skill Reference ODCM: Controls for RETS and REMP Programs                                Revision:  Page Number:
4              63X of 78 ATTACHMENT 0 Page 1 of 1 ODCM CONTROLS: GAS STORAGE TANKS CONTROLS: GAS STORAGE TANKS 3.11.2.5    In accordance with BV-1 and BV-2 Technical Specification 6.8.6c, the quantity of radioactivity contained in the following gas storage tanks(s) shall be limited to the noble gas values listed below (considered as Xe-133).
: a.  <52,000 Curies: Each BV-1 Waste Gas Decay Tank (lGW-TK-1A, or IGW-TK-lB, or IGW-TK-1C)
: b.  <19,000 Curies: Any connected group of BV-2 Gaseous Waste Storage Tanks (2GWS-TK25A thru 2GWS-TK25G)
APPLICABILITY:      At all times.
ACTION:
: a. With the quantity of radioactive material in any gas storage tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours reduce the tank contents to within the limit, and
: b. Submit a Special Report in accordance with 10 CFR 50.4 (b)(1) within 30 days and include a schedule and a 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-I Waste Gas Decay Tanks: The quantity of radioactive material contained in each BV-1 Waste Gas Decay Tank shall'be determined to be within the above limit at least once per 24 hours when radioactive materials are being added to the tank.
Performance of this surveillance is required when the gross concentration of the primary coolant is greater than 100 uCi/ml.
For BV-2 Gaseous Waste Storage Tanks: The quantity of radioactive material contained in any connected group of BV-2 Gaseous Waste Storage Tanks shall be determined to be within the above limit at least once per 24 hours when radioactive materials are being added to the tanks.
 
                                                                                                                      -U-Beaver Valley' Power Sainl2OC30                            B vProcedure Number:        P    - -.
 
==Title:==
ODCM: Controls for RETS and REMP Programs Unit:
1/2 Revision:
1General L  l Of Use:
Skill Reference Page Number.
ATTACHMENT P Page 1 of 1 ODCM CONTROLS: TOTAL DOSE CONTROLS: TOTAL DOSE 3.11.4.1        In accordance with BV-1 and BV-2 Technical Specification 6.8.6a, Item 10, the annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to < 25 mrems to the whole body or any organ, except the thyroid, which shall be limited
          -      to < 75 mrems.
Applicability:        At all times.
Action:
: a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of ODCM CONTROL 3.11.1.2a, 3.11.1.2b, 3.11.2.2a, 3.11.2.2b, 3.11.2.3a, or 3.11.2.3b, calculations shall be made including direct radiation contributions from the units (including outside storage tanks, etc.) to determine whether the above limits of ODCM CONTROL 3.11.4.1 have been exceeded. If such is the case, prepare and submit to the Commission within 30 days, pursuant to 10 CFR 20.2203(a)(2)(v) and 10 CFR 50.4(b)(1), a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR 20.405(c), shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose(s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.
: b.        The provisions of ODCM CONTROL 3.0.3 are -not applicable.                -
SURVEILLANCE REQUIREMENTS 4.11.4.1.1      Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with ODCM SURVEILLANCE REQUIREMENTS 4.11.1.2.1, 4.11.2.2.1, and 4.11.2.3.1.
4.11.4.1.2      Cumulative dose contributions from direct radiation from the units (including outside storage tanks, etc.) shall be determined in accordance with 1/2-ODC-2.04. This requirement is applicable only under conditions set forth in Action a. of ODCM CONTROL 3.11.4. 1.
 
Procedure Number Beaver Valley Power Station                                    &deg;        1/2-ODC-3.03
 
==Title:==
Unit:        Level Of Use:
1/2        General Skill Reference ODCM: Controls for RETS and REMP Programs                                  Revision:    Page Number.
                                                                                -4                65i of 79 ATTACHMENT Q
                                                -Page 1 of8 ODCM CONTROLS: REMP-PROGRAM REQUIREMENTS CONTROLS: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 3.12.1 In accordance with BV-1 and BV-2 Technical Specification 6.8.6b, Item 1, the radiological environmental monitoring program shall be conducted as specified in ODCM Control 3.12.1, Table 3.12-1.
Applicability: At all times.
Action:
: a.      With the radiological environmental monitoring program not being conducted as specified in ODCM Control 3.12.1, Table 3.12-1, prepare and submit to the Commission, in the Annual Radiological Environmental Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period.
: b.      With the level of radioactivity in an environmental sampling medium at one or more of the locations specified in ODCM Control 3.12.1, Table 3.12.1 exceeding the limits of ODCM Control 3.12.1, Table 3.12-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days from the end of affected calendar quarter a Special Report pursuant to 10 CFR 20.2203(a)(2)(v) and 10 CFR 50.4(b)(1) which includes an evaluation of any release conditions, environmental factors or other aspects which caused the limits of ODCM Control 3.12.1, Table 3.12-2 to be exceeded. This report is not required if the measured level of radioactive was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Report.
When more than one of the radionuclides in ODCM Control 3.12.1, Table 3.12-2 are detected in the sampling medium, this report shall be submitted if:
Concentration (1)      Concentration (2)
Limit Level (1) + Limit Level (2)          +    > 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:
 
o              --            x                  Procedure Nurnber        -. -
BeaVer B          Valley Power Station
____________________________________I_
                                                                      -                  - 1/2-ODC-3.03
 
==Title:==
Unit          Level Of Use:
1/2        General Skill Reference, Revision:    Page Number:
ODCM: Controls for RETS and REMP Programs 4 -              66 of 78        "
ATTACHMENT Q
                                                    - -Page2 of 8
                      - ODCM CONTROLS: REMP-PROGRAM REQUIREMENTS TABLE 3.12-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE                NUMBER OF                SAMPLING AND            TYPE AND FREQUENCY(a)
PATHWAY ANDIOR SAMPLES AND                        COLLECTION              OF ANALYSIS SAMPLE                  LOCATIONS                FREQUENCY
: 1. AIRBORNE
: a. Radioiodine      5 locations              Continuous operation Each radioiodine canister.
And Particulates                      -    of sampler with sample
: 1. One sample from a      collection at least      Analyze for I-13 1; control location      weekly.
10-20 miles distant                            Particulate sampler.
and in the least                                Analyze for gross prevalent wind                                  beta weekly direction Perform gamma,isotopic
: 2. One sample from                                analysis on composite (by vicinity of                                    location) sample at least                  \
community having                                quarterly.
the highest calculated annual average ground
                          . level D/Q.
: 2. DIRECT              40 locations              Continuous              Gamma dose, quarterly.
RADIATION '                                  measurement with 2 2 TLDs or a pres-      collection at least surized ion              quarterly.
chamber at each location.
(a)Analysis frequency same as sampling frequency unless otherwise specified.
(b)Particulate samples are not counted for 2 24 hours after filter change. Perform gamma isotopic analysis on each sample when gross beta is >10 times the yearly mean of control samples.
  **Sample locations are given on figures and tables in 1/2-ODC-2.03.
1
 
Procedure Number Beaver Valley Power Station                                                    1/2-ODC-3.03
 
==Title:==
Unit:        Level Of Use:
1/2        General Skill Reference ODCM: Controls for RETS and REMP Programs                                            Revision:    Page Number
                                                                                        -4                6S7of 7 ATTACHMENT Q Page 3 of 8 ODCM CONTROLS: REMP-PROGRAM REQUIREMENTS TABLE 3.12-1 (continued)
                    -RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE                  NUMBER OF                  SAMPLiNG AND            TYPE AND FREQUENCY(a)
PATHWAY AND/OR SAMPLES AND                            COLLECTION              OF ANALYSIS SAMPLE                    LOCATIONS**                FREQUENCY
: 3. WATERBORNE
: a. Surface            2 locations.                Composite* sample      Gamma isotopic analysis of
: 1. One sample              collected over a period composite sample by location upstream.p-            not to exceed 1 month. monthly;
: 2. One sample                                      Tritium analysis of downstream.                                    composite sample at least quarterly.
: b. Drinking              2 locations.                Composite* sample      I-131 analysis of each collected over a period composite sample; not to exceed 2 weeks.
Gamma isotopic analysis of composite sample (by location) monthly; Tritium analysis of composite sample quarterly.
: c. Groundwater            N/A - No wells in lower elevations between plant and river
: d. Sediment From          1 location.                Semi-annually.          Gamma isotopic analysis Shoreline                                                                semi-annually.
(a) Analysis frequency. same as sampling frequency unless otherwise specified.
    *Composite samples shall be collected by collecting an aliquot at intervals not exceeding two hours. For the upstream surface water location, a weekly grab sample, composited each month based on river flow at time of sampling, is also acceptable.
  **Sample locations are given on figures and tables in 1/2-ODC-2.03.
 
                              ~~
Beaver-- Valley          Power VStation~ ~
                                                          --.        :Poedure    -              Numnber:-
1/2IODCcN3.03
 
==Title:==
ODCM: Controls for RETS and REMP Programs Unit:
1/2 Revision:
I Level Of Use:.. _-
General Skill Reference .
Page Number:
I          AR of 7R ATTACHMENT Q Page 4 of 8 ODCM CONTROLS: REMP-PROGRAM REQUIREMENTS TABLE 3.12-1 (continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE                NUMBER OF                  SAMPLING AND              TYPE AND FREQUENCY(a)
PATHWAY AND/OR SAMPLES AND                          COLLECTION                OF ANALYSIS SAMPLE                  LOCATIONS**                FREQUENCY -
: 4. INGESTION
: a. Milk              4 locations.&deg;              Atleast bi-weeklywhen      Gamrma isotopic and I-13 1 animals are on pasture; analysis of each sample.
: 1. Three samples          at least monthly at selected on basis of  other times.
highest potential thyroid dose using milch census data.
: 2. One local large dairy.                                                                                      . N
: b. Fish              2 locations.              Semi-annual. One          Gamma isotopic analysis on sample of available        edible portions.
species.
: c. Food Products    4 locations.              Annually at time of        Gamma isotopic analysis and (Leafy                                      harvest.                  I-131 analysis on edible Vegetables)        1. Three locations                                  portion.
within 5 miles.
: 2. One control location.
(a)Analysis frequency same as sampling frequency unless otherwise specified.
(b)  Other dairies may be included as control station or for historical continuity. These would not be modified on basis of milch animal census.
  **Sample locations are given on figures and tables in 1/2-ODC-2.03.
                                                                                                                              - 11 i
I- 1
 
Beaver Valley Power Station
___  ____    ___  ___  ____    ___  ___ ___1/2-O ProcedureNumber. D C -3 .03
 
==Title:==
Unit:        Level Of Use:
1/2      General Sldll Reference ODCM: Controls for RETS and REMP Programs                                                Revision:    Page Number:
4              69 of 78 ATTACHMENT Q
:'Page 5 of 8 ODCM CONTROLS: REMP-PROGRAM REQUIREMENTS TABLE 3.12-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES REPORTING LEVELS AIRBORNE                                            BROAD LEAF WATER          PARTICULATE OR                  FISH          MILK      VEGETABLES ANALYSIS (pCi/1)                GASES (pCi/rn )3        (pCi/kg, WET) (pCi/l            (pCi/kg, WET)
H-3          2E+4(a)
Mn-54        11E+3                                            3E+4 Fe-59        4E+2          -E+4 Co-58        1E+3                                            3E+4 Co-60        3E+2                                            1E+4 Zn-65        3E+2                                            2E+4 Zr/Nb-95      4E+2 1-13i        2 (b)                  0.9                                        3            1E+2 Cs-134        30                      10                -      E+3              60            IE+3 Cs-137        50                      20          -2E+3                        70            2E+3 Ba/La-140    2E+2                                                            3E+2 (a) For drnking water samples. This is a 40 CFR Part 141 yalue. If no drinking water pathway exists, a value of 3E+4 pCi/l may be used.
(b)  If no drinking water pathway exists, a value of 20 pCi/l may be used.
 
Peav&Wley kower    Station
                                                                .D TL    I Valley Procedure Number:
1/2-ODC-3.03
 
==Title:==
Unit:          Level Of Use: .    - .
1/2        GCeneral Skill Reference-ODCM: Controls for RETS and REMP Programs                                  Revision:      Page Number:
A4    1          71)nf 7f' ATTACHMENT Q                  7 Page 6 of 8 ODCM CONTROLS: REMP-PROGRAM REQUIREMENTS TABLE 4.12-1 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)(a)(e)
AIRBORNE PARTICULATE                                  FOOD ANALYSIS WATER            OR GAS          FISH    MILK        PRODUCTS            SEDIMENT S (pC)          (pCi/rn) -(pCi/kg,  WET) (pCi/l)  .(pCi/kg, WET)        (pCi/kg, DRY)
Gross Beta        4          IE-2 H-3          2 0 0 0 (d)
Mn-54            15                          130 Fe-59            30                          260 Co-58,60          15                        130 N
Zn-65            30                          260 Zr-95          30(c)
Nb-95          15(c)
I-131            1(b)        7E-2                        1              60 Cs-134            15        5E-2            130        15              60                  150 Cs-137            18        6E-2            150        18              80                  180 Ba-140          60(c)                                  60 La-140          15(c)                                  15
 
                                                                              *Pincedure Number Beaver Valley Power Station                                              1/2-ODC-3.03
 
==Title:==
Unit:        Level Of Use:
1/2      General Skill Reference ODCM: Controls for RETS and REMP Programs                                      Revision:    Page Number 4 -71                of 79 ATTACHMENT Q Page 7of8 ODCM CONTROLS: REMP-PROGRAM REQUIREMENTS TABLE 4.12-1 (continued)
TABLE NOTATION (a)    The LLD is the smallest concentration of radioactive material in a sample that will be detected with-95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.
      -For a particular measurement system (which may include radiochemical separation):
LLD=            4.66 Sb (E)(V)(2.22)(Y) exp (-XAT) where:
LLD is the lower limit of detection as defined above (as pCi per unit mass or volume);
Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute);
E is the counting efficiency (as counts per transformation);
V is the sample size (in units of mass or volume);
2.22 is the number of transformations per minute per picocurie; Y is the fractional radiochemical yield (when applicable);
X is the radioactive decay constant for the particular radionuclide; AT is the elapsed time between sample collection (or end of the sample collection period) and time of counting (for environmental samples, not plant effluent samples).
The value of Sb used in-the calculation of the 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 of E, V, Y and AT should be used in the calculations.
 
Beaver Valley Power Station                                        l Procedure Number:
___________1/2-OD                    C-3.03-03
                                                                                                            -o
 
==Title:==
Unit:  -    Level Of Use:
1/2        General Skill Reference ODCM: Controls for RETS and REMP Programs                                          Revision:          N  72 fmber ATTACHMENT Q Page 8 of 8 ODCM CONTROLS: REMP-PROGRAM REQUIREMENTS TABLE 4.12-l(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.
(C)  If parent and daughter are totaled, the most restrictive LLD should be applied.
(d)  If no drinking water pathway exists, a value of 3000 pCi/1 may be used.
(e)  This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall be identified in the Annual Radiological Environmental Report.
 
Beaver Valley Power Station                                    ProcedureNuibe        C
 
==Title:==
Unit        Level Of Use:
1/2      General Skill Reference ODCM: Controls for RETS and REMP Programs                                    Revision:  Page Number.
ATTACH1MENT R PagelofI ODCM CONTROLS: REMP - LAND USE CENSUS CONTROLS: RADIOLOGICAL ENVIRONMENTAL MONITORING - LAND USE CENSUS 3.12.2          In accordance with BV-1 and BV-2 Technical Specification 6.8.6b, Item 2, a land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 square feet producing broad leaf vegetation in each of the 16 meteorological sectors within a distance of five miles.
For elevated releases as defined in Regulatory Guide 1.111, (Rev. 1), July, 1977, the land use census shall also identify the locations of all milk animals and all gardens of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of three miles.
Applicability: At all times.
Action:
: a. With a land use census identifying a location(s) which yields a calculated dose or dose commitment greater than the values currently being calculated in ODCM SURVEILLANCE 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)(1), 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)(1),;a Special Report, which identifies the new location. The new location shall be added to the radiological environmental monitoring program within 30 days, if possible. The milk sampling program shall include samples from the three active milk animal locations, having the highest calculated dose or dose commitment. -Any replaced location may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted.
: c. The provisions of ODCM CONTROL 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.12.2.1        The land use census shall be conducted at least once per 12 months between the dates of June 1 and October 1 using that information which will provide the best results, such as by a door-to-door survey*, aerial survey, or by consulting local agriculture authorities.
* Confirmation by telephone is equivalent to door-to-door.
 
Beaver Valley Power Station                                l          u /2-ODC-3.03
 
==Title:==
-                                        Unit:      L[vel Of Us  e:f-r-nc
                        ..                                                      1/2      General MOdl Referene2.1 GODCM: Controls for RETS and REMP Programs                                  Revision:  Page Number ATTACHMENT S Page 1 of 1 ODCM CONTROLS: REMP - INTERLABORATORY COMPARISON PROGRAM CONTROLS: RADIOLOGICAL ENVIRONMENTAL MONITORING - INTERLABORATORY COMPARISON PROGRAM 3.12.3          In accordance with 13V-1 and BV-2 Technical Specification 6.8.6b, Item 3, analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program.
Applicability:
At all times.
Action:
: a. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Report.
a-1,
: b. The provisions of ODCM CONTROL 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.12.3.1        The results of analyses performed as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Report.
                                                                                                            '1
 
A-  .
Procedure Number~
                ~Beaver.Valley            Power -Station'12OC30
 
==Title:==
Unit:        Level Of Use:
1/2        General Skill Reference ODCM: Controls for RETS and REMP Programs                                        Revision:    Page Number 4              75 of 78-ATTACHMENT T Page 1 of 2 ODCM CONTROLS: ANNUAL REMP REPORT CONTROLS: ANNUAL REMP REPORT ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT                                      (3) 6.9.2            The Annual Radiological Environmental Operating Report covering the operation of the (old TS 6.9.1.10) unit during the previous calendar year shall be submitted before May15 of each year.
The report shall include summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM) and in 10 CFR Part 50 Appendix I Sections IV.B.2, IV.B.3, and IV.C.
The annual radiological environmental reports shall include:
* Summaries, interpretations, and statistical evaluation of the results of the radiological
                    ' environmental surveillance activities for the report period, including a comparison with pre-operational studies, operational controls (as appropriate), and previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment.
                  . The results of the land use censuses'required by ODCM CONTROL 3.12.2.
* If harmful effects or evidence of irreversible damage are detected by the monitoring,
                        -the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.
* Summarized and tabulated results in the format of ODCM Control 6.9.1.10, Table 6.9-1 of all radiological environmental samples' taken during the report period.
In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.
* A summary description of the radiological environmental monitoring program.
* A map of all sampling locations keyed to a table giving distances and directions from one reactor.
* The results of licensee participation in the\Interlaboratory Comparison Program required by ODCM CONTROL 3.12.3.
(3)    A single submittal may be made for a multiple unit site. The submittal should combine those sections that
      - are common to all units at the station.
 
11 TABLEE:6.9-1 ENVIROMENTAL RADIOLOGICAL MONITORING PROGRAM
 
==SUMMARY==
 
Name Of Facility                                            _      Docket No. _
0 Location Of Facility                                              Reporting Period (County, State)
MEDIUM OF            TYPE AND          LOWER                ALL              LOCATIONS WITH HlIHEST                CONTROL          NONROUTINE PATHlWAY SAPED TOTAL NUMBER                  LIMITS OF        INDICATOR                    ANNUAL MEAN                  LOCATIONS            REPORTED (UNIT OF          OF ANALYSES        DETECTION'        LOCATIONS                ~                ENF"MEASUREMENTS MEASRMENT)              PERFORMED            (ll)                              NAME DISTANCT IO          ANGE"    b            RANGE" C1]
                                                                                                                                                          . to g  3 Nominal Lower limils of Detction (LD)as defined in Table Notation 'of Table 4.12-1 of ODCM CONTROL 3.11.1.1.
bMean  and range based upon detectable msurcment only. Fraction of detcable measwrement at pcfiedlocations is indicated in parenthesis (f).
I
                                                                                              /I
 
                                                                                          ~Procedure Number~
Beaver Valley Power Station                        -
1/2-ODC-3.03
 
==Title:==
Unit:        Level Of Use:
I I , ...7.....
:1/2            General Skill Reference ODCM: Controls for RETS and REMP Programs                                    Revision:    Page Number:
4              --77 of 78 ATTACHMENT U Page I of 2 ODCM CONTROLS: ANNUAL RETS REPORTS CONTROLS: ANNUAL RETS REPORT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT                          (4) 6.9.3            The Annual Radioactive Effluent Release Report (ARERR) covering the operation of the (old TS 6.9.1.11) unit during the previous year shall be submitted prior to May I of each year in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive; liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM and Process Control Program (PCP) and in conformance with 10 CFR 50.36a and 10 CFR Part 50, Appendix I Section IV.B.1.
This report is prepared and submitted in accordance with 1/2-ENV-01.05, and at a minimum, shall contain the following:
* A summary of the quantities of radioactive liquid and gaseous effluent and solid waste released from the unit as outlined in Regulatory Guide 1;21, Revision 1, June, 1974, "Measuring, Evaluating, And Reporting Radioactivity In Solid Wastes And Releases Of Radioactive Materials In Liquid And Gaseous Effluents From Light-Water-Cooled Nuclear Power Plants," with data summarized on a quarterly basis following the format of Appendix B thereof.
* An assessment of radiation doses from the radioactive liquid and gaseous effluents released from the unit during each calendar quarter as outlined in Regulatory Guide 1.21. In addition, the unrestricted area boundary maximum noble gas gamma air and beta air doses shall be evaluated.- The assessment of radiation doses shall be performed in accordance with this manual.
                                -  Any licensee initiated changes to the ODCM made during the 12 month period.
* Any radioactive liquid or gaseous effluent monitoring instrumentation channels not returned to OPERABLE status within 30 days, and why the inoperability was not corrected in a timely manner. This applies to the liquid or gaseous effluent monitoring instrumentation channels required to be OPERABLE per ODCM CONTROLS 3.3.3.9 and 3.3.3.10.
* Any ODCM SURVEILLANCE 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 3.1 1.1.l, 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 Beve ValleyalyPower'Station ___                        IPrncedure Number 1/2..ODC.3.03    0
 
==Title:==
I                                                              Unii        I Level Of Use:    .e  n    I ODCM  ..                                                                1/2      General SkiEP  Reference ODCM: Controls for RETS and REMP Programsiso:Pg                                    Nubr                                J_,V
                                              -    -                            4                78 of 78          I ATTACHMENT.U Page 2 of 2 ODCM CONTROLS: ANNUAL RETS REPORTS CONTROLS: ANNUAL RETS REPORT (continued)
* The following information for each type of solid waste shipped offsite during the report period:
                    - container volume
                    - total curie quantity (determined by measurement or estimate)
                    - principal radionuclides (determined by measurement or estimate)
                    - type of waste (e.g., spent resin, compacted dry waste, evaporator bottoms)
                    - 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 ofjoint frequency distributions of wind speed, wind direction, and atmospheric stability.
                . An assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year;
* An assessment of the radiation doses from radioactive effluents to MEMBER(S) OF THE PUBLIC due to their activities inside the site boundary see 1/2-ODC-2.01 Figure 5.1 and 1/2-ODC-2.02 Figure 5-1 during the report period. All assumptions used in making these assessments (e.g., specific activity, exposure time, and location) shall be included in these reports. The assessment of radiation doses shall be performed in accordance with 1/2-ODC-2.04.
                -  An assessment of radiation doses to the likely most exposed real individual from reactor releases for the previous calendar year to show conformance with 40 CFR 190, Environmental Radiation Protection Standards For Nuclear Power Operation.
Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Revision 1. The 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.}}

Latest revision as of 18:40, 15 January 2025

Attachment 2, Beaver Valley Power Station - Units 1 & 2, Annual Radioactive Effluent Release Report 2004, Offsite Dose Calculation Manual Changes
ML051400269
Person / Time
Site: Beaver Valley
Issue date: 04/27/2005
From: Pearce L
FirstEnergy Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
L-05-072, RTL #A9.621B
Download: ML051400269 (366)
v • d • e


Text

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