ML20128E534

Proposed Tech Specs Deleting Section 5.9.4 Re Radioactive Effluent Release Rept.Draft Chemistry Manual Procedure Encl

ML20128E534
Person / Time
Site:	Fort Calhoun
Issue date:	02/08/1993
From:	OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20128E502	List: LIC-93-0012, Forwards Application for Amend to License DPR-40,revising TS to Implement GL 89-01 to Delete Section 5.9.4 Re Radioactive Effluent Release Rept,Per Guidance Contained in NUREG-0133 ML20128E526 ML20128E534
References
RTR-NUREG-0133, RTR-NUREG-133 NUDOCS 9302100503
Download: ML20128E534 (50)

Text

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• d0 AN1/NI37XAT/l/6 doAlTWoA,5 5.9.3 Special Reoorts Special reports shall be submitted to the Regional Administrator of the appropriate NRC Regional Of6cc within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification where appropriate:

a. In service inspection report, reference 3.3.

b. Tendon surveillance, reference 3.5.

c. Containment structural tests, reference 3.5.

d. Special maintenance reports.

c. Containment leak rate tests, reference 3.5.

f. Radioactive.cf0uent-releases,4eference 2,9. DELETED

g. Materials radiation surveillance specimens reports, reference 3.3.

h. Fire protection equipment outage, reference 2.19.

1. Post accident monitoring instrumentation, reference 2.21

j. Electrical systems, reference 2.7(2). l .

5.9.4 Unjque Reportlnc Reauirem.cn13 ATrnCHME^tT o Radioactive Effluent Rgkase Reoort A 4 rrfious six eport covering months shall the within be submitted operation of the 60 days after Fort January Calhoun 1 and July Station duri year pefte requirements of 10 CFR 50.36a.

The radioac uent release report shall include a summ of the quantities of radioactive liqui aseous efnuents and solid waste cased from the plant r.s outlined in Regulato % ide 1.21, Revision 1.

The radioactive efDuent releastgeport shal) include a summary of the meteorological conditions concurrent Wi th clease of gaseous efDuents during each quarter as outlined in Regulatory Gy 1.21, Revision 1.

' The radioactive efauent release re shall in assessment of radiation doses from the radioactive liq d and gaseous effl cleased from the unit during each calendar quarte outlined in Regulatory GuA1.21, Revision 1.

In addition, the unrestric area boundary maximum noble gab - ma air and beta air doses shall b usted. The meteorological conditions conc . ent with the l

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15 Amendment No. 9,24,38,46,86, i +10,4+3,443 . 147

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[7YAcAn12H7 23

a. Annual RadioacAve Effluent Release Report The Annual Radioactive Effluent Release Report covering the operation of the unit during the previous 12 months of operation shall be submitted each year.

The report shall include a summary of the quantities of mdioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be 1) consistent with the objectives outlined in the ODCM and PCP, and 2) in conformance with 10 CFR 50.36a. and Section IV.B.1 of Appendix I to 10 CFR 50.

b. Annual Radiological Environmental O PCrallDe Reoort The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year. The report shall include summaries, interpretations, and analysis 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 (1) the ODCM and (2)Section IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR 50.

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5.0 ADMINISTRAT.LVJ CONTROLS 5.16 Eadiologicifffhignts and Enyhenmental Monitorimt ProWm1 The following programs shall be established, implement,x!, and maintained.

5.16.1 Radioactive Effluent Controls Program A program shall be provided conforming with 10 1R 50.36a for the control of radioactive effluents and for maintaining the doses to individuals in unrestricted areas from radioactive effluents as low as reasonably achievable.

The program (1) shall be contained in the ODCM, (2) shall be itnplemented by operating procedures, and (3) shall include remedial actions to be taken

,' whenever the program limits are exceeded. The program shall include the following elements:  !

4 a. Limitations on the operability of radioactive liquid and gaseous radiation  ;

monitoring instrumentation including operability tests and setpoint determination in accordanco with the methodology in the ODCM. - )

b. Limitations on the concentration of radioactive material, other than l dissolved or entrained noble gases, released in liquid effluents to 4 unrestricted areas :onforming to 10 CFR Part 20, Appendix B, Table II, Column 2. For dissolved or entrained noble gases, the concentration shall be limited to 2.0 E-04 pCi/ml total activity.

c. Monitoring, sampling, and knalysis of radioactive liquid and ga.seous effluents in accordance with 10 CFR 20.106 and with the methodology and parameters in the ODCM.

d. Limitations on the annual and quarterly doses or dose commitment to individuals in unrestricted areas from radioactive materials in liquid

i. effluents released to unrestricted areas conforming to Appendix I to 10 CFR Part 50.

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c. Determination of cumulative doses from radioactive effluents for the

, current calendar quarter and current calend tr year in accordance with the l ODCM on a quarterly basis.

L f. Limitations on the opembility and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity in plant effluents, i

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5.0 ADMINISTRATIVE CONTROLS 5.16 Radiolocical Effluents and Environmental Monitorine Ptparams (continued) ,

g. Limitations on the concentration resulting from radioactive material released in gaseous effluents to unrestricted areas conforming to 10 CFR Part 20, Appendix B, Table II, Column 1.

h. Limitations on the annual and quanerly air doses resulting from noble gases released in gaseous effluents to unrestricted areas conforming to Appendix I to 10 CFR Part 50.

i. Limitations on the annual and quarterly doses to an individual beyond the site boundary from Iodine-131, tritium, and all radionuclides in particulate form with half lives greater than 8 days in gaseous effluents released to unrestricted areas conforming to Appendix I to 10 CFR Part 50.

j. Limitations on the annual dose or dose commitment to an individual beyond the site boundary due to releases of radioactivity and to radiation from utanium fuel cycle sources conforming to 40 CFR Part 190.

5.16.2 Radiological Environmental Monitoring Program A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) represcutative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

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

b. A Land Use Census to ensure that changes in the u e of areas at and beyond the site boundary are identified and that moo:fications to the monitoring program are made if required by the results ot'this census,

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

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5.0 ADMINISTR ATIVE CONTROLS i 5.17 Offsite Dose Calculation Manual (ODCM)

Changes to the ODCM:

! a. Shall be documented and records of reviews performed shall be retained as required by Specification 5.10.2.o. This documentation shall contain:

1. Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and

2. A determination that the change will maintain the level of radioactive efnuent control required by 10 CFR 20.106,40 CFR Part 190,10 CFR Part 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of efnuent, dose, or setpoint calculations,

b. Shall become effective after review and acceptance by the Plant Review Committee and the approval of the Manager Fort Calhoun Station,

c. Temporar,*, changes to the ODCM may be made in accordance with Technical Spwincation 5.8.3.

d. Shall be submitted to the Nuclear Regulatory Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Efauent Release Report for the period of the report in which any change to the ODCM was made. Each change shall be identined by markings in the margin of the affected pages, clearly indicating the area of L

the page that was changed and shall indicate the date (e.g., month / year) the change was implemented.

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t 5.0 ADMINISTRATIVII CONTROLS 5.18 Process control Program (Pcin Changes to the PCP:

a. Shall be documented and records of reviews performed shall be retained as required by Specification 5.10.2.0. This documentation shall contain:

1. Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and

2. A determination that the change will maintain the overall conformance of the solidified waste program to existing requirements of federal, state, or other applicable regulations.

b. Shall become effective after review and acceptance by the Plant Review Committee and the approval of the Manager - Fort Calhoun Station.

c. Temporary changes to the PCP may be made in accordance with Technical Specification 5.8.3.

d. Shall be submitted to the Nuclear Regulatory Commission in the form of a complete, legible copy of the entire PCP as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the PCP was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed and shall indicate the date (e.g., month / year) the change was implemented.

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5.0 ADMINISIEATIVE CONTROLS l 5.9.3 SluiaLRepsis

, Special reports shall be submitted to the Regional Administrator of the appropriate NRC Regional Office within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the j'

applicable reference specification where appropriate:

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a. In service inspection report, reference 3.3.

b. Tendon surveillance, reference 3.5.

c. Containment structural tests, reference 3.5. I

d. Special maintenance reports. l

c. Containment leak rate tests, reference 3.5.

f. DELETED l 1

g. Materia!s radiation surveillance :.pecimens reports, reference 3.3.  !

h. Fire protection equipment outage, reference 2.19. l

i. Post-accident monitoring instrumentation, reference 2.21 _

J. Electrical systems, reference 2.7(2). j 5.9.4 Unique Reoorting.RCQuiICIMais

a. ArumaLRadioactin.r:fflgnt Re!easLReput The Annual Radioactive Effluent Release Report covering the operation of the unit during the previous 12 months of operation shall be submitted each year.

The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste scleased from the unit. The material provided sball be 1) consistent with the cbjectives outlined in the ODCM ana PCP, end 2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix 1 to 10 CFR 50,

b. ADnual RadiologicaLEnvironmental Oper&1[pg Renort The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the repoiting period.- The material provided shall be consistent with the objectives outlined in (1) the ODCM and (2)Section IV.B.2, IV.P 1, and IV.C

of Appendix 1 to 10 CFR 50.

5-15 Amendment No. 9,34,38,46,86, 40,H3,433,447,

5.0 ADMINISTRATIVF CONTROLS 5.16 Radiologicauluhitn1 Land Environmental Monitoring Programs The following programs shall be established, implemented, and maintained.

5.16.1 Radioactive Effluent Controls Program A program shall be provided conforming with 10 CPR 50.36a for the control of radioactive effluents and for maintaining the doses to individuals in unrestricted areas from radioactive effluents as low as reasonably achievable.

The program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

a. Limitations on the operability of radioactive liquid and gaseous radiation monitoring instrumentation including operability tests and setpoint determination in accordance with the methodalogy in the ODCM.

b. Limitations on the concentration of radioactive material, other thar.

dissolved or entrained noble gases, released in liquid effluents to unrestricted areas conforming to 10 CFR Part 20,- Appendix D, Table 11, Column 2. For aissolved or entrained noble gases, the concentration shall be limited to 2.0 E-M pCi/ml total activity,

c. Monitoring, sampling, and analysis of radioactive liquid and gaseous i

effluents in accordance with 10 CFR 20.106 and with the methodology and parameters in the ODCM.

d. Limitations on the annual and quarterly doses or dose commitment to individuals in unrestricted areas from radioactive materials in liquid ef0uents released to unrestricted areas conforming to Appendix 1 to 10 CFR Part 50.

e. Determination of cumulative doses from radioactive effluents for the current calendar quarter and corrent calendar year in accordance with the ODCM on a quarterly basis,

f. Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity in plant effluents.

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i 5.0 ADMINISTRATIVE CONTROLS 5.16 Badiological Effluents and Environmental Monitoring Programs (continued)

Limitations on the concentration resulting from radioactive material g.

relcar,ed in gaseous effluents to unrestricted areas conforming to 10 CFR Part 20, Appendix B, Table II, Column 1.

h. Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents to unrestricted areas conforming to Appendix I to 10 CFR Part 50,

1. Limitations on the annual and quarterly doses to an individual beyond the site boundary from lodine-131, tritium, and all radionuclides in particulate form with half lives greater than 8 days in gaseous effluents released to

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unrestricted areas conforming to Appendia I to 10 CFR Part 50. 1 l

J. Limitations on the annual dose or dose commitment to an individual beyond the site boundary due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.

5.16.2 Radiological Environmental Monitoring Program A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. Tbc program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent menitoring program and modeling of environmental exposure pathways. The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

a. Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the enviromnent in accordance with the methodology and

, parameters in the ODCM.

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

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

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t 5.0 ADMINISTRATIVE CONTROLS 5.17 Offsite Dose Calculation Manual (ODChu Changes to the ODCM:

a. Shall be documented and records of reviews performed shall be retained as  ;

required by Specification 5.10.2.o. This documentation shall contain:  !

1. Sufficient information to suppon the change together with the appropriate analyses or evaluations justifying the change (s) and

2. A determination that the change will maintain the level of radioactive efnuent control required by 10 CPR 20.106,40 CFR Part 190,10 CFR l Part 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact l the accuracy or reliability of effluent, dose, or setpoint calculations. '

b. Shall become effective after review and acceptance by the Plant Review Committee and the approval of the Manager - Fort Calhoun Station,

c. Temporary changes to the ODCM rnay be made in accordance with Technical Speci6 cation 5.8.3.

d. Shall be submitted to the Nuclear Regulatory Commission in the form of a complete, legible copy of the entire ODCM as a prt of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly _ indicating the area of the page that was changed and shall indicate the date (e.g., month / year) the change we implemented.

5-24

5.0 ADMINISTRATIVE CONTROLS 5.18 Process Control Program (PCPJ Changes to the PCP:

a. Shall be documented and records of revices performed shall be retained as required by Specification 5.10.2.o. This dxumentation shall contain:

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1. Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and

2. A determination that the change will maintain the overall conformance of the solidified waste program to existing requirements of fedtral, state, or other applicable segulations,

b. Shall become effective after review and acceptince by the Plant Review Committee and the approval of the Manager - Fort Calhoun Station.

c. Temporary changes to the PCP may be made in accordance with Technical Specification 5.8.3.

d. Shall be submitted to the Nuclear Regulatory Commission in the form of a

, complete, legible copy of the entire PCP as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in

, which any change to the PCP was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicatinF the area of the page that was changed and shall indicate the date (e.g., month / year) the change was implemented.

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U.S. Nuclear Regulatory Comission LIC-93 0012 ATTACHMENT B

DISCUSSION, JUSTIFICATION, AND NO SIGNIFICANT HALARDS CONSIDERATIONS DISCUSSION AND JUSTIFICATION proposes to revise the Fort Calhoun The Omaha Station Public Unit No. Power District 1 Technical (OPPD)tions to implement Generic Letter 89 01 Specifica and to concerning the Radiological revise the requirements for theEffluent Technical Containment S9ecifications Radi'ation High Signal(RETS)llowing fo the guidance of NUREG 0133.

Eroposed chanags_to RETS As specified in Gtneric Letter 89 01 it is proposed to relocate RETS from the Technical Specifications to the Offslte Dose Calculation Manual (0DCM). The following is a description of the proposed changes:

1. The definitions for the ODCM and Process Control Program PCP) were revised to agree with the definitions ;n Generic Lett(er 89-

01. Definitions for purge purging and venting were moved to the 1

ODCH.

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2. Technical Specifications 2.9 under Limiting Condition for Operations Section, and 3.11 and 3.12 under Surveillance Requirements Section were relocated from the Technical Specifications and incorporated into the ODCH.

3. Tables 3-2, 3 3, and 3 4 were revised to ensure that LCO require.nents, which are currently controlled by Specification 3.12, were retained. The surveillance function and frequency for ,

Containment Radiation High Signal, Area and Post Accident Radiation Monitors,in Table 3.2 are updated for consistency.and Primary-to radiation monitors Sampling requirements for steam generator blowdown are being relocated from Table 3-11, which is being deleted, to Table 3-4.

Operating modes are baing added to the sampling of steam generator blowdown consistent with the actions required by Specification 2.20.

4. Tables 3-9 3 Specification-11, and s and 3-12 wereinto incorporated relocated from the Technical the ODCM.

S. S)ecifications 2.9 and 3.12 are proposed to retain requirements in tie Technical Specifications that are related to explosive gases.

This was a specific requirement of the Generic Letter. The grab sample provisions are in agreement with the present Specification 2.9.l(2)d. A 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Limiting Condition for Operation has been added for the time allowed for hydrogen and oxygen concentrations to be out of specification. This is consistent with the Standard RETS.

6. Reporting and records requirements were revised in Section S 9.4 and Sections 5.16, 5.17 and 5,18 under Administrative Controls wereaddedtotheTechnlcalSpecificationstodefine administrative details of the ODCM and PfP. Records retention for RETS will be covered under existing Technical Specification 5.10.2.

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7. Spe:ification 5.16.1.b excludes dissolved or entrained noble gases from conforming with 10 CFR Part.20 Appendix B, Table 11 Column 2 consistent with current Technical Specification 2.9.l(l? (i).

The allowed. concentration is stated in Specification 5.m .l.b.

8. Specification 5.16.1.e requires that doses will be determined quarterly in accordance with the current Technical Specification requirements contained in Specification 2.9.l(l)b and 2.9.l(2)b.

9. Specification 5.16.1.g contains limitations on concentrations in 1 accordance with the current Technical Specifications 2.9.1(1)b and  !

2.9.l(2)b.

10. S>ecification 5.16.1.1 does not state limitations on Iodine-133 w11ch is consistent with the current Technical Specification 2.9.1.B.(3).

11. No limitations on venting and purging Mark Il containments are being proposed as Fort Calhoun does. not have a Mark II containment.

12. It is proposed to allow temporary changes to the 00CM or the PCP consistent with Specification 5.8.3 which allows temporary changes for all other procedures, figposed Chanaes to the Containment Radiation Hiah Sianal Consistent with NUREG-0133, it is proposed to remove the Ventilation Isolation Actuation sampling theSignal (VIAS) Building Exhaust Stack and Containment.

Auxiliary The proposal functions of the particulate an would remove the VIAS functions of three effluent monitors. These are VIAS signals for Stack lodine (RM-060), Stack Particulate (RM 061) and Containment Particulate (RM-050).

The particulate and iodine monitors will continue to sample effluents, but W ll not initiate VIAS. NUREG-0133 recommends the use of gas monitors for VIAS initiation because it is considered tn be impractical- to apply instantaneous alarm / trip setpoints to integrating radiation. monitors sensitive to radiciodines or radioactive materials other than noble gases.

The gas monitors will continue to isolate releases so that 10 CFR Part 20

, instantaneous limits and 10 CFR Part. 50 annual limits _ will be complied with.

The following pages are being revised in the Technical Specifications to update the VIAS functions so that only gas monitors initiate VIAS; pages 2-37, 2-38, 2-61, 2-66a, 2-69, and 2-69a.

Chanaes to Continuous Samolina Reauireme ds Technical Specification 2.9.1(2)h and Table 3-12 currently require that continuous samples be taken during continuous releases, it is proposed to revise this requirement to provide 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to initiate the auxiliary sampling required during continuous releases. The problems associated with meeting the requirements to continuously sample weia reported to the NRC in LER's91-028, and 92-001. As described in Regulatory Guide 1.21 Appendix A, the intent of continuous sampling is to identify radionuclides being released and to predict their concentrations. Two hours is proposed as a reasonable amount of time which will allow investigation of trouble alarms .on equipment and to complete calibrations, . filter changes and testing requirements without significantly 2

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affecting the results of the sampling. Current requirements allow periodic 4 grab samples be taken when monitors are inoperable for releases which have a greater impact on the total effluents released from the plant.- These changes  ;

j liave been included in the draft ODCM. .

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Administrative changes

a. The Table of Contents is being revised to reflect proposed

. changes.

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b. Page 24 is being revised to-correct a reference that was changed as a resu't of the Generic Letter changes,

c. Page 2-38 is being revised to delete a reference to the specific procedure which implements the independent verification of fuel

. burnup which is required to move fuel directly to Region 2 of the ,

i ' spent - fuel pool . The requirements remain -only the name of the

, procedure is being deleted. Additionally wording which reflects theCEStandardTechnicalSpecificationsIsbeingaddedtoclarify movement of irradiated fuel.

d. Reference 2 on Page 2-63 is-being revised-to reflect a Section of the Updated Safety Analysis Report (USAR) which better describes the Containment Radiation High Signal, e.- Table 2-4, Item 3B on page 2-69 is being revised-to reflect the requirements of CE Standard Technical Specifications. As the described in USAR Containment Radiation High Section Signal (CRHS7.3.2.6isolates pressure relief, air sample, and purge system valves. As and the~S$ecification conta 2.8(2) currently' written, it could be implied that all valves which receive a VIAS are required to be closed in order to place the CRHS channels in bypass. This change clarifies the requirements that onl

' closed. yAthe containment description vent and of these purge valves valvesadded is being are required to be to the basis of Specification 2.15 on page 2 66a. A change is-also proposed for page 2-66a to revise the term FSAR to the present nomenclature for this document which is the USAR (Updated-Safety Analysis Report).

f. Page 3-Ob is being revised to delete an example of' a surveillance test table that will be relocated to the ODCM. - Additionally, a.

typographical error " Code of Federal Requirements," is being corrected to read " Code of Federal Regulations."

g. Page 3-63b is bein revised to include a statement on the bottom.

of the page indica ing that the next page will be-page 3-69.

, h. The. heading "5.0 ADMINISTRATIVE CONTROL

• is being added to.Page 5-15 to be consistent with other pages in Section 5.0.

1. I't is proposed to revise the requirements contained in Specification 5.9.4a for submitting the Radioactive Effluent Release Report from semi-annually to annually to reflect a recent rule change to 10 CFR 50.36a'as publ.ished in the Federal Register (57 FR 39353) August 31,~1992.

J. Page 5-19 is being revised to add records retention requirements for the 0DCM and PCP.

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U.S. Iluclear Regulatory Commission LIC-93-0012 ATTACHMENT C

FORT CALHOUN STATION ) ;f- PAGE 3 OF 13 CHEMISTRY MANUAL PROCEDURE ]L+i[\ ~

CMP-6 PART II-1.0 RADIOACTIVE EFFLUENTS RELEASE LIMITS . . . . .. . , . - . 2.

1.1 Liquid Effluants . . . . . . . - . . . . . . . . . . . -

2 11 . 2 Gaseous Effluents . . - . . .. . . . . . . . . .. 2  ;

1.3 EPA Release Limits . . .. . . . . . . . . . . . . 3 2.0 RADIOLOGICAL EFFLUENT RELEASE REQUIREMENTS . . . . . . . 4 2.1 Liquid Effluents Releases . . . . . .. . . . . . .- 4

, 2.1.1 Monitor Tanks =. . . .. . . . . . . - . .. . 4 l- 2.1.2 Steam Generator . . . . . . . . . . . . . . 6 2.2 Gaseous Effluent Releases . . . . . .. . . . . . . 7 2.2.1_ Gaseous Auxiliary Building: Exhaust Stack . 7

- 2.2. 2 ' Condenser Of fgas ...... . - . . . . .. 11 1 2.2.3 Laboratory and Radwaste Building Stack . - . - _ 11 3.0 RADIOLOGICAL EFFLUENT SAMPLING AND-ANALYSIS REQUIREMENTS 12 3.1 ' Liquid Effluents -. . . . . . .. . - . . . . . . . 12 3.2 Gaseous Effluents .- . . . . .. . - . . . . . . .. 13

'3.3 Lower Limit off Detection (LLD) . . . . - . . . . . . . 13 4.0 RADIOACTIVE LIQUID EFFLUENT REPORTING REQUIREMENTS , . . 15 4.1 Liquid Effluents ... . . . . . . . . .. . . . . . . 15 l 4.2- Gaseous Effluents . . - . . . . . . . _ . . . . . . . -

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4.3 Semi-Annual Report . . . . . . . . . . . . . . -. . .. 17 4.4 Annual. Report . . . . . . . . - . . . . .. . - . . . . 18 1 4.5 Non-Routine Report . . . . . .. ..: . - . _ . . . . . . 19 4.6 EPA 40 CFR 190 Reporting Requirements' -. . .. .. '19 i

r 5.0- RADIOLOGICAL ENVIRONMENTAL MONITORING REQUIREMENTS . . .-

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FC/ CMP /01 121392 w w ~ _g

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FORT CALHOUN STATION PAGE-1 OF 32 CHEMISTRY MANUAL PROCEDURE ' CMP >

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PART II i

RADIOLOGICAL EFFLUENT CONTROLS l.

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FORT CALHOUN STATION s PAGE 2 OF 32 CHEMISTRY MANUAL PROCEDURE CMP-6 1.0 RADIOACTIVE EFFLUENTS RELEASE LIMITS The limits.and conditions for the controlled release of-radioactive material in liquid and gaseous effluents stated in this Section are to ensure that these releases result-in concentrations of radioactive materials in liquid and gase-ous effluents released to unrestricted areas are within'the limits specified in 10 CFR 20 and.to ensure that the release of radioactive material to the environment be as low as reasonably achievable in conformance with 10 CFR 50.34a and 50.36a. To meet these criteria, the following requirements must be met for all radioactive liquid and gaseous effluents from FCS:

1.1 Lignid Effluents 1.1.1 The release rate of radioactive material in liquid effluents shall be controlled such that the instantaneous concentrations for radionuclides, other than dissolved or en-trained noble gases, do not exceed the values specified in.10 CFR 20 for liquid effluents in unrestricted areas. For dissolved or entrained noble gases, the concentration shall be limited to 2.0 E-04 pCi/ml, total activity.

1.1.2 The dose or dose commitment to an individual in unrestricted areas from radioactive materials in liquid effluents during any calendar year shall not exceed a millirems to the total body, 1.1.3 The dose or dose commitment to an individual in unrestricted areas from radioactive materials in liquid effluents during any calendar year shall not exceed 12 millirems to any oraan.

When the concentration of radioactive material released to unrestricted areas exceeds the.above

. limits, appropriate corrective actions shall be.taken immediately to restore concentrations within the above limits.

1.2 Gaseous Effluents 1.2.1 The release rate of radioactive material in gaseous effluents shall-be controlled such

.that the instantaneous concentrations for these radionuclides do not exceed the values specified in 10 CFR 20 for' gaseous effluents j in unrestricted areas at and beyond the site j boundary.  !

1

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FORT CALilOUN STATION '

PAGE 3 OF 32 CHEMISTRY MANUAL PROCEDURE CMP-6 1.2 Gascop EffingAtg (Continued) 1.2.2 The gamma air dose in unrestricted areas due to the release of noble gases in gaseous effluents shall not exceed 10 millirads during any calendar year; 1.2.3 The beta air dose in unrestricted areas due to the release of noble gases in gaseous effluents shall not exceed 20 millirada during any calendar year; and 1.2.4 The dose to an individual or dose commitment to any organ of an individual in unrestricted areas due to the release of I-131, Tritium, and radioactive materials in particulate form with half-lives greater than eight days (excluding noble gases) in gaseous effluents ehall not exceed 15 millirema from all exposure pathways during any calendar year.

When the concentration of radioactive material released to unrestricted areas exceeds the above limits, appropriate corrective actions shall be taken immedletely to restore concentrations within the above limits.

1.3 The dose to any real individual from uranium fuel cycle sources shall be limited to 1 25 mrem to the total body or any organ ( except the thyroid, which shall be limited to 5 75 mrem ) during each calendar year.

I-

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FORT CALHOUN STATION CHEMISTRY MANUAL PROCEDURE D AR >AoE 4 or 2a CMP-6 2.0 BADIOACTIVE EFFLUENT RELEASE REQUIREMENTS The requirements for'the release of radioactive liquid and gaseous effluents from FCS stated in this Section are to ensure that the limits of Section 1 will be net, as well as to allow for operational flexibility. When any of the requirements for release of radioactive effluents cannot be complied with, the release shall not be permitted to occur or it shall be immediately terminated, if it is in progress.

2.1 Liould Effluent Releases 2.1.1 Monitor Tanks During release of radioactive liquid efflu-ents, excluding releases from the steam generators, the following conditions shall be met:

2.1.1.1 There shall be sufficient dilution flow so that, at site discharge:

M

}:clapc,s1 2*1 i

where:

C, a concentration of the i*

radionuclide in the liquid effluent at site discharge, mpc, = 10 CFR 20, Appendix B, Table 2, Column 2 limits. ,

2.1.1.2 The overboard header effluent radiation monitor shall be set in accordance with Part III to alarm and automatically close the-discharge valve prior to exceeding 10 CFR 20 limits.

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l FORT CALHOUN STATION _ PAGE 5 OF-32 CHEMISTRY MANUAL PROCEDURE. f- -CMP-6 2.1 .Liould Effluent Releases (Continued) 2.1.1 Monitor Tanks (continued) '

2.1.1.3 The liquid effluent radioactivity shall be. continuously monitored during the release. If.the efflu-ent radiation monitor:is inoper-able,; effluent releases may con-tinue provided:that: _(prior to-initiating a release); ~

A. At least two_ independent samples are analyzed in accordance_with-applicable-chemistry procedures.

B. At least two shift qualified chemistry technicians indepen-

dently

verify the' release rate ,

calculaticns.

2.1.1.4 The' liquid effluent radioactivity shall be continuously' recorded ~dur-ing the~ release.- If the process-radiation monitorJchart recorder is not operational and radioactivity levels'cannot be recorded automa-tically, effluent releases may con-i tinue-provided-that the radioacti-1 vity level is recorded-manually?at l least onceLper fourihours.during

(

I actua11 release.

2.1.1.5~ The; liquid _ effluent flow rate-shall be continuouslyfmonitored'and

-recorded duringitheorelease. -If.

the flow rate recorder-is,inoper-

-able, effluent. releases may continue provided'the' flow rate-is

) determined at-least once per four-L hours during1 actual-release..

L l

l l

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FORT CALHOUN STATION PAGE 6 OF.32 CHEMISTRY MANUAL PROCEDURE . CMP-6 2.1 Liquid Effluent Rel. gases (Continued)-

2.1.2 Steam Geney h During the release of' steam _ generator blow-down to the discharge tunnel,-the following?

conditions shall be net:'

2.1.2.1 There-shall be1 sufficient dilution flow so-that, at site discharge:

n.

Cg{mpc3 $1 al where:

C, = concentration'of the i*

radionuclide in the- -

liquid ~ effluent.at'~ site

discharge.:

mpc, = 110 CFR'20, Appendix B, Table,2,Tcolumn11' limit.

2.1.2.2 The steam generatorfblowdown radia-tion monitors shall'_be-set in-accordance withMPart1III.to alarm andLautomatically close-the blowdown isolation valves _ prior:to exceeding 110!CFR~20 limits.

2.1.2.3 The radioactivity for each blowdown-line shall be_ continuously moni-tored:and recorded by the blowdown-radiation monitors.-

zi A. If one of theitwo-radiation-monitors is_ inoperable, the activitysfor both_ blowdown

--lines'shall-be. monitored byj

-the operable radiation monitor.

B.. IfLboth radiation monitors are1 inoperable,' steam-generator liquid releases may; continue provided: grab-samples.are-analyzed'for principal-gamma emitters'atta sensitivity'of 5.0E-07jpCi/ml and1 recorded 1at~-

least' daily when'the specific activity-of, Steam Generator;

. Blowdown {.is t less - than or; ~ equal'

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mew FORT CALHOUN STATION , fl PAGE 7 OF 32 CHEMISTRY MANUAL PROCEDURE CMP-6 2.1 L.iould Effluent Releases (Continued) 2.1.2 Steam Generator (Continued) 2.1.2.3 to 0.01 pCi/ gram dose equiva-lent I-131 and at least

. C. Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the specific activity of the secondary coolant la greater than 0.01 pCi/ gram dose equivalent I-111.

4 2.1.2.4 The radioactivity for each blowdown line shall be continuously re-corded. If the process radiation monitor chart recorder is not-oper-ational, Steam Generator releases may continue provided that the radioactivity level is recorded manually at least once per four hours during actual reJease.

2.2 Gasequs Effluent Ecleanga 2.2.1 Gaseous Auxiliarv Buildina Exhapst Stack 2.2.1.1 During release of gaseous radioac-tive effluents from containment pressure relief line to the Auxiliary Building Exhaust Stack, the following conditions shall be met:

A. The Auxiliary Building Exhaust Stack noble gas monitor, iodine sampler and particulate sampler shall be operational.

B. The Auxiliary Building Exhaust Stack 1 noble gas radiation mon-itor shall be set in accor-

' dance with Part III to alarm and automatically terminate the release prior to exceeding 10 CFR 20 limits at site boundary (see Part'III., Figure

' 1) .

C. At least one Auxiliary Build-ing exhaust fan shall be in operation.

l l

l

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FORT CALHOUN STATION PAGE 8 OF 32 CHEMISTRY MANUAL PROCEDURE CMP-6 2.2 Gaseous Effluent Relea22n (continued) 2.2.1 93seoyg_ Auxiliary Buildina Exhaust Stack (continued) 2.2.1.1 D. The Auxiliary Building Exhaust Stack gaseous radioactivity shall-be monitored and recorded during the release.

If the process radiation monitor chart recorder is not operational and gaseous radioactivity levels cannot be recorded automatically, releases from containment may continue provided that the gaseous radioactivity level is recorded manually at least once per four hours during the actual release.

E. The containment flow rate-shall be monitored and automatically recorded during the release. If_the' flow rate recorder is inoperable, releases from the containment may-continue provided the flow rate is determined at least once per:four hours during actual release.

2.2.1.2 During the release of gaseous '

radioactive effluento from the containment purge line:

A. The conditions set forth in Section 2.2.1.1 shall be met.-

B. A noble gas monitor shall monitor the containment. build-ing atmosphere. If the process radiation monitor chart recorder is not operational and-gaseous radioactivity levels cannot be recorded-automatically,. releases from containment may continue pro-vided that the gaseous radioactivity level is recorded manually at least once per four hours during the actual release.

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FORT CALHOUN STATION j (*. l PAGE 9 OF 32 CHEMISTRV MANUAL PROCEDURE CMP-6 2.2 Gaseous Effluent Releases (continued) 2.2.1 Gaseous Auxiliary Buildina Exhaust Stack (continued) 2.2.1.3 During the release of gaseous effluents from the gaseous waste discharge heador:

A. The Auxiliary Building Exhaust Stack noble gas radiation non-itor shall be set in accor-dance with Part III to alarm' and automatically terminate the release prior to exceeding 10 CFR 20 limits at site boundary (see Part III, Figure 1).

B. If the Auxiliary Building Exhaust' Stack radiation monitor is inoperable, efflu-ent releases may continue pro-vided that (prior to release):

1. At least two independent samples are analyzed in accordance with the applicable chemistry procedure.

11. At least two shift _quali-fled chemistry techni-cians independently.

verify.the release rate calculations.

C. At least one Auxiliary Build-ing exhaust fan shall be in operation.

D. The waste gas discharge header flow rate shall be monitored and automatically recorded' during releases. If the flow rate recorder is-inoperable, releases may continue provided the flow rate is determined at.

least once per four hours during actual' release.

2.2.1.4 The Auxiliary Building Exhaust Stack noble gas monitor,.particu-late. sampler, or iodine sampler may be inoperable provided that:

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FORT CALHOUN STATION- I PAGE 10 OF.32

-CHEMISTRY MANUAL PROCEDURE CMP-6 c-2.2 Gaseous' Effluent Releases (continued)  ;

2.2.1 Gaseous Auxiliary Building __ Exhaust Stac1 (continued) i 2.2.1.4 A. Whenever the Auxiliary Build-ing Exhaust-Stack noble-gas monitor is: inoperable,-

releases from the containment pressure relief line and the.

containment-purge line.are to be secured in.the'most.

expeditious manner. . .

Ventilation of the auxiliary building via the-Auxiliary Building Exhaust stack may continue provided grab-samples are taken and analyzed-once per eight-(8) hours-for principal gamma emitters.

B.- Whenever the_ Auxiliary

, -Building:-Exhaust. Stack iodine

-or particulate sampler (s) is/are inoperable, releases from the_ gaseous waste discharge header, containment pressure-relief line or the containment purge line are to be secured'in the most'

-expeditious manner. These

! releases may continue-provided samples are. collected using l auxiliary sample collection i equipment in accordance with-

[

Table.2; i

l C. Whenever the-Auxiliary l Building Exhaust Stack iodine or particulate sampler (s) is/are inoperable, ventilation of the-auxiliary building via the Auxiliary Building Exhaust-Stack may continue provided-sample collection using_

auxiliary sample collection.

equipment is initiated:within-

'2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of the~ discovery of.

the inoperability in

'accordance with' Table 2.

l FC/ CMP /01- '020393-r l

4 FORT CALHOUN STATION PAGE 11 OF 32 CHEMISTRY MANUAL PROCEDURE 1]s ,it[) F """)5 CMP-6 2.2.2 Condenser Offaas 2.2.2.1 During power operation, the con-denser air ejector discharge shall be monitored for gross radioacti-vity. If this monitor is inoper-able, grab samples shall be taken and analyzed daily for principal gamma emitters. (See Table 2) 2.2.3 Laboratory and Radioactive Waste Processina Agildina Stack 2.2.3.1 The Laboratory and Radioactive Waste Processing Building (LRWPB)

Stack noble gas monitor, particu-late sampler or iodine sampler may be inoperable and effluents via this pathway may continue provided:

A. If the noble gas monitor is inoperable, grab samples will be taken once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and analyzed for principal gamma emitters.

B. If the iodine or particulate sampler (s) is/are inoperable, ventilation of the LRWPB may-continue via the LRWPB Stack provided sample collection using auxiliary sample collecion equipment is initiated within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of the discovery of the inoperability in accordance with Table 2.

C. The LRWPB Stack flow rate shall be monitored and recorded during ventilation of the LRWPB. If the flow rate recorder is inoperable, ventilation may continue provided tne flow rate is determined.at least once per four hours.

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FORT CALHOUN STATION J

) )

d\

PAGE 12 OF 32 CHEMISTRY MANUAL PROCEDURE CMP-6 3.0 RADIOLOGICAL EFFLUENT SAMPLING AND ANALYSIS REOUIREMENTH The sampling and analysis requirements stated in this Sec-tion will provide reasonable assurance that radioactive materials present in the liquid and gaseous effluents will be properly identified and accurately quantified. This information will serve as the basis for determining doses to individuals as a result of radioactive effluents from FCS.

Records shall be maintained and reports of the sampling and results of analyses shall be submitted to the Nuclear Regu-latory commission in accordanca with Section 4 of these controls.

3.1 Liquid Ef fluents 3.1.1 Radioactive liquid waste sampling and activity analyses shall be performed in accordance with Table 1. The results of these analyses shall be used with the calculational methods in Part IV of this manual to assure that the concen-traticn at the point of release does not ex-ceed 10 CFR 20 limits for unrestricted areas.

3.1.2 Prior to release of each batch of liquid effluent, the batch shall be mixed, sampled, and analyzed for principal gamma emitters.

When operational or other limitations preclude specific gamma radionuclide analysis of each batch:

3.1.2.1 Gross radioactivity measurements shall be made to estimate the

! quantity and concentrations of L radioactive materials released in the batch.

(

3.1.2.2 A weekly sample composite from proportional aliquots from each batch released during.the week shall be analyzed for the principal gamma-emitting radionuclides.

3.1.3 Records shall be maintained of the radioactive concentrations and volume before dilution of each batch of liquid effluent released and of the average dilution flow and length of time over which each discharge occurred. Analyti-cal results shall be submitted to the Commis-sion in accordance with Section 4 of Part II..

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a FORT CALHOUN STATION CHEMISTRY MANUAL PROCEDURE f~74f Il e+j{Al*t3"['

t.

PAGE 13 OF 32 CMP-6 3.1 Ljgqvid Effluents (Continued) 3.1.4 The radiation monitors for liquid effluents shall have their operability verified in accordance with the requirements in Table 3, Iten A.

4 3.2 Qgagnyp_Jff1ueatu 3.2.1 Radioactive gaseous waste sampling and activity analyses shall be performed in accordance with Table 2. The results of these analyses shall bc uced with the calculational methods in Part IV of this manual to assure that the concentration of radioactive materials does not exceed 10 CFR 20 limits for unrestricted areas.

3.2.2 The radiation monitors for gaseous effluents shall have their operability verified in

. accordance with the requirements in Table 3, Item B.

3.3 L9 war _ Limit of Detsstion (LIA).

The lower limit of detection (LLD) for liquid and gaseous discharges, referenced in Tables 1 and 2 of the Radiological Effluent Controls (Part II), is defined as the smallest concentration of radioactive l material in a sample that will' yield a net count, above system background, that will be detected with 95 L

percent probability with_only 5 percent probability of falsely concluding that a blank observation represents a "real" signal.

l For a particular measurement system, which may include radiochemical separation:

l i

4.66-* s3 LLD=

E

• V

• D

• Y

• exp ( -la t)

Where:

LLD = the lower limit of detection as defined above, l in either picocuries or microcuries, per unit  !

l mass or volume as a function of the value of D Sb= the standard deviation of-the background l . counting rate or of the counting rate.of a l blank sample, as appropriate, as counts per l minute FC/ CMP /01 020393

4 FORT CALHOUN STATION CHEMISTRY MANUAL PROCEDURE l*1 -

PAGE 14 OF 32 CMP-6 3.3 L9Xer.,J,imit of Det.ection ( LLD.), -(Continued) i E= the counting efficiency, as counts per disintegration )

l V= the sample size in units of man' or volume D= 2.22E+06 of disintegrations per minute per microcurie or 2.22 disintegrations per minute per picocurie Y= the fractional radiochemical yield, when applicable A= the radioactive decay constant for'the particular radionuclide At = the elapsed time for the plant effluent between the midpoint of sample collection and time of counting Appropriate values of E, V, Y and at should be 'used in the calculation.

It should be recognized that the LLD is defined as an A Priori limit representing the capability of a mea-surement system and not as a limit for a particular measurement.

LLD verifications will be performed on a periodic basis. This determination is to ensure that the counting system is able to detect levels of radiation 4 at the LLD values for the specific type of analysis required by Tables 1 and 2. They will be performed with a blank (non-radioactive) sample in'the same counting geometry as the actual sample.

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FORT CALHOUN STATION .PAGE 15 OF 32 CHEMISTRY MANUAL PROCEDURE

}]+g n }kl*[M CMP-6 4.0 RADIOACTIVE LIOUID EFFLUENT REPORTING REQUIREMENTS The reporting requirements for radioactive effluents stated in this Section are to provide assurance that the limits set forth in Section 1 are complied with. These reports will l meet the requirements for documentation of radiosctive l

effluents contained in 10 CFR 50.36a; Reg. Guide 1.21, Rev.

1; Reg. Guide 4.8, Table 1; and Reg. Guide 1.109, Rev. 1.

t 4.1 leiauid Effluents _

4.1.1 The radiation dose contributions from radio-active materials in liquid effluents released l to unrestricted areas shall be determined, in l

accordance with Part IV, section 2.1, on'a quarterly basis. If the dose contribution, i due to the cumulative release of liquid l effluents averaged over a calendar quarter, l exceeds one-half of the annual design objectives, the following course of actions shall be taken:

A. Make an investigation to identify the l

causes for such releases.

B. Define and initiate a prcgram of action to reduce such releases to the design levels.

C. Submit a special report, pursuant to Tech-nical Specification 5.16, within 30 days i from the end of the quarter during which I the release (s) occurred, identifying the l causes and describing the proposed program of action.to reduce such-releases to the design levels.

4.1.2 The equipment or subsystem (s) of the liquid l radwaste treatment system as identified in the l

Part III, section 2.1, shall be operable. If the radioactive liquid wastes.were discharged without treatment by_one or more of.the pieces of equipment or subsystem (s) identified in that section and it-is confirmed that one-half of the annua 3 dose objective will be exceeded during the calendar quarter, a special report,.

pursuant to Technical Specification 5.16, shall be prepared and submitted-to the Nuclear Regulatory Commission within 30 days of the:

end of the quarter during which the equipment  !

or subsystem (s) were inoperable. This report shall include the following information:

A. Identification of equipment or sub-system (s) nct operable and reasons for inoperability.

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k PAGE 16 OF 32 CMP-6 4.1- Licuid EfflueDig (Continued)

B. Action (s) taken to restore the inoperable equipment to operable status.

C. Summary description of action (s) taken to prevent a recurrence, 4.2 Gaseous Effluents 4.2.1 The radiation dose contributions from radioac--

tive materials in gaseous effluents shall be determined, in accordance with the Part.IV, section 2.2, on a quarterly basis. If the dose contribution, due to the cumulative release of gaseous effluents averaged over a calendar quarter exceeds one-half of the annual design objectives, the following course of. actions shall be-taken:

A. Make an investigation to. identify the cause for such release rates.

B. Define and initiate a program of action to reduce such releases to design levels .

C. Submit a special report, pursuant to Technical Specification 5.16, within 30 days from the end of the quarter during which the release (s) occurred, identifying the causes and describing the proposed program of action to reduce dose contri -

butions.

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PAGE 17 OF 32 CHEMISTRY MANUAL PROCEDURE d*N CMP-6 4.2 Gasgous Effluents (continued) 4.2.2 The equipment or subsystem (s) of the gaseous radwaste treatment system as identified in Part III, section 2.2, shall be operable. If the radioactive gaseous wastes were discharged without treatment by one or more of the equipment or subsystems (s) identified in that section and it is confirmed that one-half of the annual dose objective will be exceeded during the calendar quarter, a special report, pursuant to Technical Specification 5.16, shall be prepared and submitted to the Nuclear Regulatory Commission within 30 days of the end of the quarter during which the equipment or subsystem (s) were inoperable. This report shall include the following information:

A. Identification of equipment or sub-system (s) not operable and reason for inoperability.

B. Action (s) taken to restore the inoperable equipment to operable status.

C. Summcry description of action (s) taken to prevent a recurrence.

4.3 Annual Radioactive Effluent Relegge Renort' 4

A report covering the operation of the Fort Calhoun Station during the previous calender year shall be submitted within 90 days after January 1 of each year per the requirements of 10CFR 50,36a.

Yhe radioactive effluent release report shall include a summary of the quantities of radioactive liquid'and gaseous effluents and solid waste released from the plant as outlined in Regulatory Guide 1.21, Revision 1.

The radioactive effluent release report shall include a summary of the meteorological conditions concurrent with the release of gaseous effluents during each quarter as outlined in Regulatory Guide 1.21, Revision 1.

The radioactive effluent release report shall include 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, Revision 1. The assessment of radiation doses shall be performed in accordance with calcula-tional methodology of the Regulatory Guide 1.109, Revision 1.

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FOPT CAIP. gun STATION PAGE 18 OF 32 d

CHEMISTRY MANUAL PROCEDURE CMP-6 4.3 ' Annual Radioactive Efflue.nt Release Report-(cont'd)

The radioactive effluent release report shall include any changes to the Process Control Program (PCP)-or to the Offsite Dose Calculation Manual (ODCM) made during the reporting period. These changes can be initiated either by the licensee (implementation: subject to review by the PRC) or by the Nuclear Regulatory Com-mission (implementation: subject to their applicabil-ity to the Fort Calhoun Station design, review by the PRC and followed by a revieA by the SARC). A level of detail commensurate to the significance of the change will be provided.

4.4 Annual. BAdip10_g.iqaLJnvironmental Operatiner Rep _gri The Annual Radiological Environmental Operating Report for-the previous one year of operation shall be sub-mitted prior to May 1 of each year. This report contains the data gathered from the radiological environmental monitoring program. The content of the report shall include:

4.4.1 Summarized and tabulated results of the radiological environmental sampling / analysis activities following the format of Regulatory Guide 4.8, Table 1. In the event'that some results are not available, 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.

4.4.2 Interpretations and statistical evaluation of the results, including an assessment of the observed impacts of the plant operation ~and environment.

4.4.3' The results of participation in a NRC approved Interlaboratory Comparison Program.

4.4.4 The results of land use survey required by Part II, Section'5.1.4.

4.4.5 The results of specific activity analysis in which the primary coolant exceeded the limits of Technical Specification 2.1.3._ The following information shall.be included:

4,4.5.1 Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in I which the limit was' exceeded; 1

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FORT CALHOUN STATION j. , PAGE 19-OF 32 CHEMISTRY MANUAL PROCEDURE '

CMP-6 4.4 Annual Radiolocigal Environmental ODeratina Report (Continued)

A. Results of the last isotopic analysis for radiciodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than the limit. Each result-should include date and time of_ sampling and the radiciodine concentrations; B. Purification system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; C. Graph of-the I-131 concentration and one other radiciodine iso-tope' concentration in micro-curies por gram as a function of time for the duration of the specific activity above the steady-state level; and D. The tire duration when the specific activity of the primary coolant exceeded the radiolodine limit.-

4.5 Mon-Routine Reoort If a confirmed measured radionuclide concentration in an environmental sampling medium averaged over any calendar quarter sampling period exceeds the reporting level referenced in Tabla 7, and if the radioactivity is attributable to plant operation, a written report shall be submitted to the Nuclear Regulatory Commis-sion within 30 days from the end of the quarter.

The report shall include an evaluation of any release conditions, environmental factors, or other aspects necessary to explain the anomalous result.

4.6 EPA 40 CFR 190 Reportina Reauirements With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the' limits of Part II, sections 1.1.2, 1.1.3, 1.2.2, 1.2.3, or 1.2.4, based on quarterly.and annual calculations, prepare and submit a special

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FORT CALHOUN STATION: ]D -g7 PAGEl20 OFJ32 CHEMISTRY MANUAL PROCEDURE 1 J#4% A;s- _ CMP-6 4.6 EPA-40 CFR-190 Reportina Reauirements-= (Continued) _

- report to the Commission within 30 days and1-limit-th'e subsequent' releases such'that the

dose totanygreal individual:from uranium; fuel = cycle sources?is limited- .j

to 1 25 mrem to the total-body orLany. organ'(except thyroid, which is

limited . to's 75-- mram)D over' the" calendar: year.- This.-special report shall-include an  !

analysis which demonstrates that radiation exposures

.ta) .any member.of.the public from; uranium fuel cycle  ;

sources-(including all effluent pathways-and: direct' radiation)Eare less than the 40 CFR'190 - standard.

otherwise, obtain a variance from the. commission .ta) .

permit' releases which_ exceed theR40 CFR'190Latandard.-  ?

The-submittalnof the-report 11s to.be considered;a ,

timely' request'and aLvariance ia granted pending;the

~

1 final action on the variance request from the JCommission.

1 u

F i

i' i:

i 4

S k

l r

4 1

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. .a.--._. _. . , _. . . . . , _ . - . -.

FORT CALHOUN STATION PAGE 21 OF 32 CHEMISTRY MANUAL PROCEDURE CMP-6 5.0 RADIOLOGICAL ENVIRONMENTAL MOtllTORING REOUIREMENTS The requirements set forth in this Section will provide reasonable assurance that radioactive liquid and gaseous effluent releases to the environment in and around Fort Calhoun Station are monitored and that any deviation of radiation levels above background will be identified.

5.0.1 The radiological environmental monitoring program shall be conducted according to Table 4. No' changes shall be made to the ODCM which might reduce the effectiveness of the program. Analytical results of this program and deviations from the sampling schedule shall be reported to the Nuclear Regulatory Commission in the Annual Radiological Environmental Operating Report (Part II, Section 4.4).

5.0.2 If the level of radioactivity, from calculated doses, in the Annual Radiological' Effluent Release Report leads to a higher exposure pathway to individuals, this pathway shall be added to the Radiological Environmental Monitoring Program.

5.0.3 If the level of radioactivity in an environmental sampling medium exceeds the reporting level specified in Table 7, a Non-routine Report shall be prepared and submitted to the Nuclear Regulatory. Commission (Part II, Section 4.5). *he detection capabilities of the equipment used fc- he analysis of Environmental Samples must meet the requirements of Table 6 for Lower Level of Detection (LLD).

5.0.4 A land use survey shall be. conducted once per 24 months between the dates of June 1 and October 1.

This survey shall identify the location of the nearest milk animal, nearest meat animal, nearest vegetable garden, and the nearest residence in each of the 16 cardinal sectors within a distance of five miles. The results of the land use survey shall be submitted to the Nuclear Regulatory Commission in the Annual Radiological Environmental Operating Report (Part II, Section 4.4). The survey shall be conducted under the following conditions:-

A. Within a one-mile radius from the plant site, enumeration by door-to-door or equivalent counting techniques.

B. Within a five-mile radius, enumeration by using referenced information from county agricultural agents or other reliable sources, i

FC/ CMP /01 020393

4 4

< FORT CALHOUN STATION PAGE.22 OF 32-CHEMISTRY MANUAL PROCEDURE

. CMP-G  ;

5.0 RADIOLOGICAL' ENVIRONMENTAL MONITORING REQUIREMENTA-(continued) y 5.0.4~ (Continued)

B. If it is' learned from_this survey that milk animals-are present at a location which yields ,

a calculated dose greater than from previously sampled location (s),.the new location (s) shall- ,

be added to the monitoring. program. .The. sam-pling location (s) having the lowest _ calculated.

dose may then be dropped from-the monitoring program'at_the end of the grazing and/or grow-ing season during which the survey'was conduc-ted and the new location is then added to the ,

monitoring program. Also, any location (s) from which milk can no longer be obtained may be dropped and replaced if practicable from the monitoring program and'the Nuclear Regula-

. tory Commission shall'be notified'in the

< Annual Radiological Environmental-Operating-Report (Part II, Section 4.4)..

C. Radiological Environmental Sampling locations and the media that is utilized for analysis are presented in Table.5.

5.0.5 Analyses shall be performed on radioactive' materials as part of an Interlaboratory Comparison Program that has been approved by the Nuclear Regulatory Commis-sion. The results of thesetanalyses shall L be included i in the Annual' Radiological Environmental Operating Report. ,

I 5.0.6 Deviations from the monitoring program,-presented in-l this section and detailed in Table 4,Jare permitted if

! specimens _are1 unobtainable due to hazardous =condi-tions, seasonal unavailability, malfunction of; equip-ment, or if a-person discontinues participation:in.the:

i' program and other legitimate reasons. If thezequip--

mont malfunctions, corrective actions will be complete as soon.as practicable. _If a person no. longer .

supplies samples, a replacement will be made. All-deviations from the. sampling schedule will be described in the Annual Radiological Environmental-Operating Report,. pursuant to Part.II, Section 4.4.

i I

l l

i.

FC/ CMP /01 020393 L

i

. FORT.CALHOUN STATION. PAGE 23lOF 32 r, - CHEMISTRY. MANUAL PROCEDURE CMP 5 TABLE 1

' Radioactive ' lould Waste Samotina and Anahgj,g a

4 1

- A. = leonitor & Notel Weste Tenks Releases I Lower Limit of of Actly ty Analysis DetectiongD)

T i

Senpling fre m y (scl/st). ,

E Each Satch' Principeh Emitters g 5.0 E 07 I 131(2) 1.0 E 06 i Monthly from- Dissol ed Noble one Batch r.asesLNJ (Ganne 1.0 E 05  ;

, Emitters)

Monthly caposite(I) H3- 1.0 E 05 ,

Gross a 1.0 E 07.

Quarterly Composite (7) tr 89, Sr 90 5.0 E 08-2 4

4 i - 3. Steam Generator Rtoudoem I - Lower Limit of Type of Detection (LLO)

! sanpting frequency' Activity Analysis (Act/st)93 -

Weekly Composite (I)- G Principel3)amme Emitters ( .

5.0 E 07.

~

I l I 131(5) . -1.0 E 06--

Monthly Dissolved Noble . .

Gases (Game -- 1.0 E 05

, Emitters)

Monthly Composite (7) H3'- -- 1.0 E 05 -

l Gross e 1.0 E 07-Quarterly Cenposite(7) Sr-89, sr 90 - 5.0 E-08 L

1 l -.

l .

I

~

l I

n l- . .-. .

l FC/ CMP /01-.020393 J

l l-j

o

^-

l

-a ..,- .

h. '% I 4 _.

FORT-CALHOUN STATION _ e ,

PAGE.24'OF 32-CHEMISTRY MANUAL PROCEDURE #l ll --

CMP-6

-TABLE 2-

]

Radioactive Caseous Waste Samotina and Analvsh A. Gas Decay Tank Reteeses Lower Limit of Type of .

$ampling Frequency Activity Analysis Detection .(SC1/mL) gD)

Prior to each Principeg48Qasuna -

release Emitters 1.0 E 04

s. Centalrument Purge Releases or Centelnuent Pressure Relief Line Releases Lower Limit of Type of Sanpling Frequency Activity Analysis Detection (ACl/mli gD)

Prior to each Principeg --- .

release Emitters 1.0 E 04..

Prior to each release H3 1.0 E 06 C. Condenser Air Ejector Reteeses Lower Limit of-Type of - Detection (jtD)

Sampling Frequency. Activity Analysis (acl/ml)L 3 Monthly (6) Trittun (H 3)- ~1.0 E 06 Mon'.h t t' - Principa}'Qansne Fmitters' ' - 1.0 E 04.-

D. Aistillary Buildits Enhaust Stack and .a Laboratory and Redmaste Building Enhaust Stack '

Lower Limit of-l Type of Detecti /J.LD)

Sanpting Frequency'* l Activity Analysl6 l- (#Cl/ml) '8

-l-Weekly- . _..

(Charcoal Sample) 1 131 . 1.0 E 12 Weekly-Principeg4gasuna (Particulates) Emitters ,.1 131 1.0 E 11-and Particulates-with half-Lives t than eight days.-

Monthly Composite - Gross a- 1.0 E 11 Quarterty Composite . .

(Particulates) $r 89, $r*90L '1.0 E 11 FC/ CMP /01 020393

-_-_ _ =__ -. - =

FORT CALilOUN STATION [* PAGE 25 OF 32 CHEMISTRY MANUAL PROCEDURE *bf[ "] '* CMP-6 1ABLtl 1 ard 2 (Continued)

Hott o (1) LLO la defined in Part it, lection 3.3.

(2) Grops Radioactivity is defined be the determination of radioactivity levels without regard to speelf te radionuclide identification and individual isotopic quantification.

'3) The principal genene emitters for which the LLO speelfication arplles emetusively are the following radionuctides Mn 54, Fe 59, Co 58, Co 60, In 65, Mo 99, Cs 134 Cs 137, Ce 141, and Ce 144 1

(4) the prinetpal panvna emitters for wh'ch the LLO specification ap.pties exclusively are the following radionuclid.64 Kr+87, Kr 88, Xe 133, xe 133m, ke 135, and re 138 for vaseous selssions and Mn 54, fe 59, co 58, co 60, In 65, ha 99, Ca 134, Co 137, Ce 141, Ce 144 for particulate emissions.

(5) A weekly grab sample ard analyses progran irttuding gener,a isotopic Idontification will be inttlated for the turbine inJitding swp ef fluent when the steam generato* blowdown water conposite analysta indicM is the I 131 concetstration la greater than 1.0 E 06 microcurle/mittititor.

(6) Renutred only when steam generator blowdown radioactivity for trititan (fable 1, item B) exceede hg,M microcurle/mltlltiter.

(7) to be representative of the average quantitles and concentrations of radioactive materlets in Liquid ef fluents, canples should be collected in proportion to the rate of flow of the ef fluent stream. Prior to analyses, all sanples taken for the composite should be mixed in order for the conposite sample to be representative of the average effluent release.

I (8) These senples are continuously collected during the release of radioactive ef fluents. However, releases are allowed to continue for periods of up to 30 days when the continuous senpler is not in service provided that sanptes are collected using auxiliary senpling equipnent.

FC/ CMP /01 020393

FORT CAL 110Uli STATIOli CilEMISTRY mal 1UAL PROCEDURE

")' [ PAGE 26 OF 32 CMP-6 1ABLE 3 Radiation and Envirorrental Monitors Doetability Reautrecents Daily Monthly Quarterly Source Check Cha sour Channel Refueling Prior Llcpid Mmitors Check {) Checkg) Func. Test (3) Callbretton(4) ReleasegI A.

RM 054 A/B XI9) M N X X

~

RM 055/55A .(9) . x x x Ostly Monthly Quarterly Source Check the lour Channel Refueling Prior 1 CheckgI Releasetg)

5. Gaseous Monitors Check {) Func. Test (3) Calibration (')

RM 043 x X X X RM 057 X X X X RM 062/51(6) x x x x x Monthly Annust Operatlgns Airflow C. Envirrantl. Monitors Check ') Calibration (3)

RM 035 - 039 x x i

l if0TC5:

(1) Documentation is provided by signof f on OP $f SHIFT 0001.

(2) Docunentation is provided ty signof f on IC $f RM 0050.

(3) Docunentation la provided by signof f on IC si-RM 0050.

(4) Docunentation la provided by conpletion of appropriate calibration procedure. Air or Llould flowrote cattbratione must be included for RM 054 A/B and RM 043, f.M 05T, and RM 062/51.

(5) Documentation is provided by signof f on applicable Release Permit Form l l

(6) RM 051 will be substituted for RM 062 when it is sanpling the Auxiliary sullding ventilation stack.

(7) Docunontation is provided by signof f nn IC ST RM 0100.

(8) Documentation is provided by complotton of calibration procedure (9) Visual f(owcheck dally l

l FC/ CMP /01 020393

e FORT CALilOUli STATI011 M !*'y >- p*i y PAGE 27 OF 32 CllEMISTRY MAliUAL PROCEDURE I/ A 'agg  ; CMP-6 TABL8 4 Radiologicet Envirorcental Monitoring Program Exposure Pathway and/or $artte Collection $lte(O fypes of Analysis (2) pregaency

1. Direct twflatim A. Ten TLD indicator stations, Gama dose Quart &rly one control station, total of 11.

B. An imer ring of 16 stations, Game dose during site Replaced one in each meteorological Area and General Emera Annually sector in the general stea of gencies only, the site boundary and within 2.5 miles.

C. An outer rtng of 16 stations, Game dose daring site Reptoced i in each meteorological Area and General Emer* Annually cector located outside of the pencies only.

(mer ring, but no are die-tant than approximately 5 miles.

2. Air Manitoring A. Ind b toe $tations Weekly 1)Filted)forGross sete

1. 3 stations in the general area of the $lte Bomdary. 2) Charcoal for I 131 Weekly

2. City of Blair 3) Filter for Gama Quarterly

. Isotopic cor p site of B. One background station Some se A. above

3. Water A. Missourt River at nearest Cama isotopic, N 3 Monthly com-downstream drinking water posite for intake. Game Isoto-plc Analysis B. Missourt River downstream Quarter.y near the mlaing tone, ccmposite for H 3 Analysis C. Missouri River upstream of plant intake (background).

4. Milk ('I A. Nearest faally cow when Cama Isotopic and 1 131 scalmonthly available or one dairy farm grating sea.

within 5 miles. aon (May to October)

8. One dairy farm between 5 miles and 18.75 miles.

(Background)

5. Fish A. Four fish samples within Coma Isotopic once per vicinity of plant discharge. season (May to October)

8. One background sanple up-stream of plant discharge.

6. Sedlemt One senple f rom downstream eren Cams Isotopic temiannually on the station side of the Missourl River.

l FC/ CMP /01 020393

. s, ,

e FORT CAL 110Ulf STATIO!1 ]' PAGE 28 0F 32 CllEMISTRY MAliUAL PROCEDURE W -

4 CMP-6 TA8tt 4 (Continued)

Radiological (nvirorenental Monitoring Program imposure Pathway ard/or lanple Cottection lite (1) Types of Analysis (2) Frequency T. Vegetables or A. One aanple outside of 5 Sanma Isotopic Once per fond Prockets miles. (Background) season (May to October)

p. One senple in the highest exposure pathway.

Notes (1) See Tabte 6 for required detection limits.

(2) The Lower Limit of Detection (LLD) for analysis is defined in the ODCM in accordance with the wording of HUREG 0472 ReV. 3, DrafI I.

(3) When 4 gross beta count Indicates redloactivity greater than it 12 SCl/ml or 1 pCl/m*, a ganma spectral analysis will be performed.

(6) When milk sanples are not evallable, a broad leaf vegetation or pasture grass sample shall be collected, when avaltable.

FC/ CMP /01 020393 l

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PAGE 31 or 32 s

. FORT CALMOUW ST4 Tion-DW-6 # ;:

-CMEMISTRY MANUAL PROCEDueE  !

TABLE 6 .

Detection capabilities for Erwirorisentet Sammte Analysis (1)(2)(3)

Lower tioit of Detection itLD)  !

Gross .

a 3

Sample ' tJnits . Seta O h 54 Fe-59 Co-58. 60. In-65 Zr-95 ab-95 t-131 Cs-134 v-137 sa-140 j

\,

Meter) Pci/L'- --i 2.0E+03 1.5E+C1' 3.0E+01 1.5E+01 3.0E+01 1.5E+01 1.5E+01 1.0E+00 1.5E41 1.8E+01 1.5E+01 [

. . Fish - - PcI/k9 * " ' -- 1.3E+02 2.6E+02 1.3E+02 2.6E+02 -- -- --

1.3E+02 1.5E+02 -

-(wet)

Milk ' Pci/L.

-- -- -- -- -- -- -- -- 1.0E+00 1.5E+01 1.8E+01 1.5E+01 i i

-- 7.0E-02 -- -- --  !

'AirJ . Pci/m3 1.0E-02 .. -- -- -- -- -- --

~I Particu ..

-late or j Geses

' Sediment Pel/kg -- -- -- -- -- -- -- -- -- 1.5E+02 1.8E+02 --

(dry)' )

Grass or Pcl/kg -- '-- -- -- -- -- -- --

6.0E+01 6.0E41 8.0E+01 -- ,

Broad Leaf (wet)_  ;

Vegetation /-

vegetootes: 19 _

Q '

L m Ai p%+

m e4 e (1)' ' This list does not mean that only these nuelldes are to be considered. Other peeks that are identifiable as plant effluents, together with those  ;

of the above nuclides, shalt also be analyzed and report.;d in the Arviunt Radiological Erwirorumental Surveittance Report pursuant to Part !!,

- Section 5.1.1.~~  ;

i

Required detection capabilities for.thermotuurinescent dosimeters used for erwirorunental measurements shall be in accordance with the ,m_../

4 ' (2)

- tions of Regulatory Guide 4.13. ,

'(3) The LLD is defined, for purposes of these specifications,'as the smettest concentration or radioactive meteriet in a sample that will yield a net ,

j- count, above system backgrourd, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a *reet* signet. .

For a porticular measurement system, editch may include radiochemical seperation:

['

i 1

4.66 sb - 1

(

_(LD a E+ ve 2.22E+06 * . Y % esp (-Mt) - ,

1, i k

4 FC/ CMP /01. 020393

__--b--.- ___c.._____.___m_. -

._w _ , , . , , , , , , ,. , _ _ , .

. - _._s , , . - . _ . m ~.-.--..-.-......----_.-----.m.m..- -_ ._..- -. .._ ~. -=. - _ _ ._,-m. - .- . . .

d

_ . . e PAGE 32 W 32

• i FORT' CALMOUN STt.TIOg N4 l'g f  !

CHE"1STRY suuduAL PROCEDURE '>

TABLE 7 .

'k Reportins tevels foe Radioactivity Concentrations in Envirarmental SamplesIII 4

Zn45 'Zr-95 6 95 Cs-134 Cs-137 se-140 sempte Units ' ' N-3 pav-54 Fe-59 Ct 51 Co-60 h]}]

5.0E+01 2.0E+02 mter-' L Pci/L .' 2.0E+04 1.0E+03 4.0E+02 1.0E+03 ' 3.0E+02 3.UE+02 4.0E+02 4.0E+02 2.0E+00 3.0E+01 3.0E+04'.1.0E+06 3.0E*06 1.0E+04 2.0E+06 -- -- -

1.0E+03 2.0E+03 -

Fish ' Pci/kg . ; --

i- (uet) i -- - -- -- -- - 3.0E*00 6.0E+01 7.0E+01 3.0E+02

.Mith ~ Pci/L - -- -

9.0E-01 -

Air . Pci/m31 -- -- --

Ferticulate or Gases 1.0E+02 1.0E+03 2.0E+03 -

h  : - - - - -

Grass or ' ;Pci/kg . - - -- -.

. Brood Leaf (wet)

< Vegetation /-

Vegetables 1,

30

===i I(1) ' A non-routine report shalt be sidseitted iAen more then one of the'rsdionuclides listed above are detected in the sampilns sedium and:

Concentration G + concentratie (2) + - - - - - 1 1.0 ,

Report bg Levet (1) neporting Levet (2) i When radionuctices 'other than those listed above are detected and are the result of plant effluents,"this report shett be Js isritted if the poten--

tial annual dose to a W of.the general pihtic is ept to er greater than the dose objectives of Part II, Section 1.1 and 1.2. This report i Lis not required if the measured towet of radioectivity ases not the result of plant, effluents; howver, in such an event, the corufition shall be reported and described in the Annual Radiological Emirorumentat operating Report.

.? .

N

, FC/ CMP /01~. 020393 4

_,,-..._,,.1

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