ML20137A039
| ML20137A039 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 12/31/1985 |
| From: | Thadani A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20136G035 | List: |
| References | |
| NUDOCS 8601140127 | |
| Download: ML20137A039 (54) | |
Text
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'[, ' , ,g , NUCLEAR REGULATORY COMMISSION G E WASHINGTO N, D. C. 20555 %...../:
MAINE YANKEE ATOMIC POWER COMPANY DOCKET NO. 50-309 MAINE YANKEE ATOMIC POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.86 License No. DPR-36
- 1. The Nuclear Regulatory Comission (the Comission) has found that:
A. The application for amendment by Maine Yankee Atomic Power Company, (the licensee) dated May 8,1985 as supplemented May 29, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I;
- 8. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C. There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2 9601140127 85123139 PDR ADOCK O P l l l _ E ._
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. 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(6)(b) of Facility Operating License No. DPR-36 is hereby amended to read as follows: (b) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 86 , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendnent is effective July 1,1986.
FOR THE UCLEAR REGULATORY COMMISSION A Ashok C. Thadani, Director PWR oject Directorate #8 Division of PWR Licensing-B
Attachment:
Changes to the Technical
. Specifications Date of Issuance: December 31, 1985
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e t ATTACHMENT TO LICENSE AMENDMENT NO. 86 FACILITY OPERATING LICENSE NO. DPR-36 DOCKET NO. 50-309 Revise Appendix A as follows: Remove Pages Insert Pages Tableofcontents(2pgs) Table of contents (2 pgs) 3 3 6 6 7 7 3.0-1 3.0-1 3.16-1 through 3.16-7 3.16-1 through 3.16-4 3.17-1 through 3.17-8 3.17-1 through 3.17-7
- 3.28-1 through 3.28-6 4.1-10 4.1-10 4.2-3 4.2-3 4.2-3a 4.2-4 4.2-4 4.2-5 4.2-5 4.2-6
- 4.2-7 4.8-1 through 4.8-4 4.8-1 through 4.8-10
- 4.13-1 through 4.13-6 5.5-3 5.5-3 5.5-7 5.5-7 5.9-2 through 5.9-5 5.9-2 through 5.9-4 5.10-2 5.10-2 e
i 2 1
TABLE OF CONTENTS PAGE Definitions 1
- 1.1 Fuel Storage 1.1-1
- 1.2 Site Description 1.2-1 1.3 Reactor 1.3-1
! 1.4 Containment 1.4-1 i
! 2.0 Safety Limit Violation 2.0-1 l 2.1 Limiting Safety System Settings - Reactor Protection System 2.1-1 2.2 Safety Limits - Reactor Core 2.2-1 2.3 Safety Limits - Reactor Coolant System Pressure 2.3-1 l 3.0 Limiting Conditions for Operation 3.0-1
- 3.1 Reactor Core Instrumentation 3.1-1 3.2 Reactor Coolant System Activity 3.2-1 1 3.3 Reactor Coolant System Operational Components 3.3-1 1 3.4 Combined Heatup, Cooldown and Pressure-Temperature Limitations 3.4-1 3.5 Chemical and Volume Control System 3.5-1 1 3.6 Emergency Core Cooling and Containment Spray Systems 3.6-1
{ 3.7 Boron and Sodium Hydroxide Available for Containment Spray System 3.7-1 i 3.8 Reactor Core Energy Removal 3.8-1 Operational Safety Instrumentation, Control Systems
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3.9 and Accident Monitoring Instrumentation 3.9-1
. 3.10 CEA Group, Power Distribution, Moderator Temperature Coefficient Limits and Coolant Conditions 3.10-1 3.11 Containment 3.11-1 3.12 Station Service Power 3.12-1 3.13 Refueling and Fuel Consolidation Operations 3.13-1 , 3.14 Primary System Leakage 3.14-1 3.15 Reactivity Anomalies 3.15-1 , 3.16 Release of Liquid Radioactive Effluents 3.16-1 l 3.17 Release ofGaseous Radioactive. Waste 3.17-1 3.18 Reactor Coolant System Oxygen and Chloride / Fluoride Concentration 3.18-1
{ 3.19 Safety Injection System 3.19-1
- 3.20 Shock Suppressors (Snubbers) 3.20-1 3.21 Deleted
- 3.22 Feedwater Trip System 3.22-1 3.23 Fire Protection Systems 3.23-1 3.24 Secondary Coolant Activity 3.24-1
- 3.25 Installed Ventilation and Filter Systems 3.25-1 3.26 Reserved 3.27 Reserved .
i 3.28 Radioactive Effluent Monitoring Systems .; 3.28-1 i l Amendment No. 60,62,63,65,75,77, 86 i a
TECHNICAL $PECIFICATIONS Table of Contents (Continued) Page 4.0 Surveillance Requirements 4.0-1 4.1 Instrumentation and Control 4.1-1 4.2 Equipment and Sampling Tests 4.2-1 4.3 Reactor Coolant System Leak Tests 4.3-1 4.4 Containment Testing 4.4-1 4.5 Emergency Power System Periodic Testing 4.5-1 4.6 Periodic Testing 4.6-1 4.7 Inservice Inspection and Testing of Safety Class Components 4.7-1 4.8 Radiological Environmental Surveillance Program 4.8-1 4.9 Shock Suppressor (Snubber) Surveillance 4.9-1 4.10 Steam Generator Tube Surveillance 4.10-1 4.11 Ventilation Filter System Surveillance Testing 4.11-1 4.12 Fire Protection Systems Surveillance Testing 4.12-1 4.13 Radioactive Effluent Monitoring 4.13-1 i 5.0 Administrative Controls 5.1-1 I 5.1 Responsibility 5.1-1 5.2 Organization 5.2-1 5.3 Facility Staff Qualifications 5.3-1 5.4 Training 5.4 1 5.5 Review and Audit 5.5-1 5.6 Reportable Event Action 5.6-1 l 5.7 Safety Limit Violation Report 5.7-1 5.8 Procedures 5.8-1 5.9 Reporting Requirements 5.9-1 5.10 Record Retention 5.10-1 5.11 Radiation Protection Program 5.11-1 5.12 High Radiation Area 5.12-1 5.13 Deleted
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Amendment No. 34,50,63,55,7J,77,86 _ - _ - , _ _ = _ _ . _ _ _ _ _ _ _ _ _ _
i 4 9 1 i REACTOR PROTECTIVE SYSTEM . t Instrument Channels t One of four independent measurement channels, complete with the
; sensors, sensor power supply units, amplifiers, and trip modules ,
provided for each safety parameter. l Reactor Trip The de-energizing of the magnetic jack holding coils which releases ' j the shutdown and regulating control elements (CEA's) and allows them 4 to drop into the core. 4 i Trip Module A bistable unit in each of the instrument channels which is tripped j when the parameter signal exceeds a specified limit. The relay 4 contact outputs of the trip modules form the reactor protective system logic. ! ENGINEEREO SAFEQJARDS SYSTEMS I Subsystem i One of two or more redundant grouping of sensors, logic, and circuitry
- able to bring about automatic or manual initiation of an engineered -
{ safeguard.
- Degree of Redundancy !
l - The difference between the number of operable channels and the number j
- of channels which when tripped will cause an automatic system trip.
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5 i . t ! Amendment no. n, m,86 .
MISCELLANEOUS DEFINITIONS (Continued) , Minimum Pressurization Temperature (MPT) The lowest temperature at which a system or component may be pressurized to its design limit. Off-Site Dose Calculation Manual (0DCM) A manual containing the current methodology and parameters to be used for calcu-lating the off-site doses due to radioactivity in effluents. ~ Memt:er(s) of the Public Member (s) of the public include all persons who are not occupationally associated with the plant. This category does not include employees, contractors, vendors, delivery persons, service persons, or employees of government agencies. This category does include persons who use portions of the site for recreational, occupational, or other transient purposes not associated with the production of electricity. Site Boundary The site boundary shall be that line beyond which the land is not owned, leased, or otherwise controlled by the licensee. Any area within the site boundary used for residential or recreational purposes is considered to be beyond the site boundary for purposes of meeting gaseous effluent dose specifications. (Realistic occupancy factors, for visitors and others, shall be applied at these locations for the purposes of dose calculation.) The site boundary is shown in the ODCM. Gaseous Radwaste Treatment System A Gaseous Radwaste Treatment System is any system designed and installed to
. redcce radioactive gaseous effluents by collecting Primary Coolant System off-gases and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.
Process Control Program (PCP) The PCP contains the current sampling and analysis methods to be used to ensure that radioactive waste from liquid systems are properly prepared for shipment to disposal facilities in accordance with applicable Federal and State regulations. Dry active waste (DAW) such as compacted trash and contaminated components are not included in the scope of the PCP. Ventilation Exhaust Treatment System The Ventilation Exhaust Treatment System includes all systems designed and installed to reduce gaseous radiciodine or radioactive material in particulate form in efflu-i ents 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 release to the environment. Such systems are 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 Systems components. 5 Unrestricted Area
- An Unrestricted Area shall be any area at or beywd tR Site Boundary access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the Site Boundary used for residential, industrial, commercial, institutional, or recreational purpose.
Amendment No. 83,86
% 4 TABLE 0.1 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 if the plant is in the cold shutdown condition SA At least once per 184 days l
A At least once per year R At least once per 18 months P Prior to each reactor startup l PR Completed prior to each release l N.A. Not applicable 7 Amendment No. 26,65,83,86 . . __ _ - -
o 3.0 LIMITING COWITIONS FOR OPERATIONS Applicability: Applies to section 3 of these Technical Specifications. Objective: To specify general regulatory requirements for compliance with these specifications and appropriate remedial actions when compliance cannot be attained. Specification: A. Nonconformance with a L'imiting Condition for Operation: If a Limiting Condition for Operation (LCO) in Section 3 of the Technical Specifications is not met, the following sequential remedial actions must be taken until conformance with the specification is achieved.
- 1. perform any remedial action permitted by the applied specification l *See Note in Basis
- 2. commence a reactor shutdown within one hour and place the plant in a Hot Shutdown Condition within 6 hours after the discovery of the noncomforming condition or after any time period permitted by (1) above.
- 3. commence a reactor cooldown and place the plant in a Cold Shutdoen Condition within 30 hours after the discovery of the nonconforming condition or after any time period permitted by (1) above.
Exception: The provisions of A2 and A3 do not apply to Specifications 3.16, 3.17, and 3.28. B. Entry into a Higher Operating Condition: Entry into a Higher Operating Condition shall not be made whenever the following exists:
- 1. The provisions of A.2 or A.3 above apply.
- 2. Any of the following specific LCOs is not met for the existing or higher condition without reliance upon the provisions contained in the remedial action statements:
3.5-C; 3.6-A; 3.6-8; 3.9-A; 3.14-C C. Operability of safety-related components with emergency power sources:
- 1. When the plant is in a condition 4 or higher operating condition, two power sources, normal and-emergency, are required to determine operability. -
Amendment No. EJ,65.70, 86 3.0-1
3.16 RELEASE OF LIQUID RADIOACTIVE EFFLUENTS Applicability: Applies at all times to the release of all liquid waste discharged from the plant which may contain radioactive materials. Objective: To establish conditions for the release of liquid waste containing radioactive materials and to assure that all such releases are within the concentration limits specified in 10 CFR Part 20, and also assure that the releases from the site of radioactive materials in liquid wastes (above background) are kept "as low as is reasonably achievable" in accordance with 10 CFR Part 50, Appendix I. gecification: A. Liquid Effluents: Concentration
- 1. The concentration of radioactive material in liquid effluents released from the site to unrestricted areas shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than noble gases and 2 x 10 4 microcuries/ml total activity concentration for all dissolved or entrained noble gases.
Remedial Action: With the concentration of radioactive material released from the site to unrestricted areas exceeding the above limits, without delay take action to restore the concentration to within the above limits. B. Liquid Effluents: Dose
- 1. The dose or dose commitment to a member of the public from radioactive materials in liquid effluents released from the site to unrestricted areas 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 less than or equal to 10 mrem to any organ.
Remedial Action: With the calculated dose frem the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission a report within 30 days from the end of the quarter. The report shall identify the cause(s) for exceeding the limit (s) and define the corrective actions to be taken to ! reduce the releases and the corrective actions to be taken to assure thtt subsequent releases will be in compliance with the above limits. .- 5 Amendment No. 19,65,19, 86 3.16-1 l
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Remedial Action: With the calculated dose from the release of radioactive materials in liquid effluents exceeding twice the above limits, , calculations should be made including direct i radiation contributions from significant plant ! sources to determine whether the limits of 40 CFR 190 , have been exceeded. ' i If such is the case, prepare and submit to the Commission within 30 days pursuant to Specification 5.9, a Special Report. The report shall define the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the limits and include the schedule for achieving confernance with the limits. 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. C. Liquid Radwaste Treatment,
- 1. The Liquid Radwaste Treatment System shall be used in its designed modes of operation to reduce the radioactive 1.iterials in the liquid waste prior to its discharge when the estimated doses due to the liquid effluent from the site, when averaged with all other liquid releases over the last 31 days, would exceed 0.06 mrem to the total body, or 0.2 mrem to any organ.
Remedial' Action: With radioactive liquid waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission a report with the next Semi-Annual Effluent Release Report which includes the following information:
- a. Explanation of why liquid waste was being discharged without treatment and in excess of the above limits, identification of any inoperable liquid waste equipment which prevented treatment prior to discharge, and the reason for the inoperability;
- b. Actions taken to restore the inoperable equipment back to operable status; and ,
- c. Summary description of action (s) taken to $revent a recurrence. -
t Amendment No. 65,86 3.16-2 4
- - _ _ . - - _ _ . _ _ _ _ _ _ - . . _ _ _ ___.,,,..__,__._______e_ - - . _ _ _ _ _ - _ _ _ _ _ . , _ _ . . . - .
l l l o l Basis: A. Liquid Effluents: Corbentration l This specification is provided to ensure that the : concentration of radioactive materials released in liquid ! waste effluents from the site to unrestricted areas (at the l point of discharge into Back River; discharge from the i submerged multiport diffuser) will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposures within (1) Section II.A design objectives of Appendix I,10 CFR Part 50 to a member of the public, and (2) the limits of 10 CFR Park 20.106(e) to the population. The concentration limit for noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its WC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICR3) Publication 2. B. Liquid Effluents: Dose This specification is provided to implement the guidance of Sections II.A, III.A, and IV.A of Appendix I,10 CFR Part 50. The specification provides the required operating flexibility and at the same time assures that the releases of radioactive material in liquid ef fluents will be kept "as low as is reasonably achievable" as set forth in Section IV.A of Appendix I. In addition, since the facility is located on a salt water estuary, the release of radioactive waste in liquids will not result in radionuclide concentrations in finished drinking water which would be in excess of the requirements of 40 CFR Part 190. The dose calculations performed in accordance with the methods and parameters in the 00CM implement the guidance in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a member of the public through appropriate pathways is unlikely to be substantially underestimated. The remedial action requiring calculations when releases exceeds two times the design objectives is included to assure that appropriate reports and requests for variance are made should effluents 3xceed the limits settforth in 40 CFR 190. 5 Amendment No. 65,86 3.16-3
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. . l C. Liquid Radwaste Treatment The requirement that the appropriate portions of the liquid radwaste system (as indicated in the ODCM) 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 10CFR Part 50.36(a) and the design objective guidance given in Section II.D of Appendix I to 10 CFR Part 50.
The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I,10CFR Part 50, for liquid effluents. 4 i Amendment No. 65,86 3.16-4
3.17 RELEASE OF GASEOUS RADI0 ACTIVE WASTE Applicability: Applies at all times to the releases of all gaseous w radioactive materials. To establish conditions in which gaseous waste containing Objective:_ radioactive materials may be released and to assure that all such releases are within the dose limits specified in 10 CFR Part 20, and also assure that the releases of radioactive materials in gaseous wacte (above background) from the site are kept "as low as is reasonably abnievable" in accordance with 10 CFR 50, ,_ Appendix I. Specification A. Gaseous Effluents: Dose Rate i
- 1. The dose rate (when averaged over 1 hour) due to radioactive materials released in gaseous effluents %
from the site to areas at and beyond the site boundary shall be limited to the following. - For noble gasec: less than or equal to 500 mrem /yr p a. to the total body, and less than or equal to 3000 mrem /yr to the skin, and
- b. For Iodine-131, Iodine-133, tritium, and radioactive materials in particulate form with half-lives greater than 8 days: less than or equal to 1500 mrem /yr to any organ.
With the dose rates averaged over a period
- Remedial Action:
of 1 hour exceeding the above limits, without de B. Gaseous Effluents: Dose from Noble Gases
- 1. The air dose due to noble gases released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to the following:
less than or equal to
- a. During any calendar quarter:
5 mrad for gamma radiation, and less than or equal to 10 mrad for beta radiation, and less than or equal to 10
- b. During any calendar year:
mrad for gamma radiation, and less than or equal to 20 mrad for beta radiation. Remedial Action: With the calculated air dose from radioactive noble gases in gaseous effit.ents _ exceeding any of the above limits, prepare and submit to lhe Commission, a report in 30 days from the end .of.jthe quarter. 3.17-1 Amendment No. 63,19, 86 J
j . . j . , l . i i The report shall identify the cause(s) for exceeding i l limit (s) and define the corrective actions to be taken to ! reduce the releases of radinactive noble gases in gaseous i effluents and the proposed corrective actions to be taken j to assure that subsequent releases will be in compliance with the above limits. C. Gaseous Effluents: Dose from Iodine-131 Iodine-133. Tritium, and Radioactive Material in Particulate Form
- l. The dose to a member of the public from Iodine-131, l
Iodine-133 tritium and radioactive materials in particulate form wib1 half-lives greater than 8 days, in gaseous effluents released to areas at and beyond the site boundary shall be limited to the following:
- a. During any calendar quarter: less than or equal
- to 7.5 mrem to any organ, and j
- b. During any calendar year: less than or equal to 15 mrem to any organ.
a
- c. Less than 0.1% of the limits specified in 3.17.C.1.a and b as a result of burning contaminated oil.
j r Remedial Action: With the calculated dose from the release of Iodine-131, Iodine-133, tritium, and radioactive materials ! in particulate form with half-lives greater than 8 days in gaseous effluents exceeding any of the above limits, prepare j and submit to the Commission a report within 30 days from j the end of the quarter. { The report shall identify the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the releases and the proposed corrective r actions to be taken to assure that subsequent releases will j be in compliance with the above limits. Remedial Action: With the calculated dose from the release i - of radioactive materials in gaseous effluents exceeding twice i the limits of Specifications 3.17 8 or C, calculations should i be made including direct radiation contributions from significant plant sources to determine whether the limits of 40 CFR 190 have been exceeded. I {- If such is the case, prepare and submit to the Commission . within 30 days pursuant to Specification 5.9,,a;Special Report. - The report shall define the corrective actiori-i to be taken to reduce subsequent releases to prevent rc :urtence of exceding the limits and includes the schedule for achieving conformance with the limits. l Amendment No. 6,86 3.17-2 l } I . . __ . _ _ _ _ _ _ _. . _ _ __ _ _ _ _ ._. _ . _ ___. _ _ _ _ _ _ . .
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.
i. , Submittal of the report is considered a timely request, and a variance is granted until staff action on the . I request is complete. l D. Gaseous Radwaste Treatment System i i 1. 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 estimated gaseous effluent air doses due to gaseous effluent releases from the site to areas at and beyond the site boundary would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation over 31 i days. The Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the estimated doses due to gaseous effluent releases from the site to areas at and beyond t the site boundary would exceed 0.3 mrem to any organ over
- 31 days.
Remedial Action: With gaseous waste beincj discharged without processing through appropriate treatment systems as defined in the 00CM and in excess of the above limits, prepare and
. submit to the Commission a report with the next Semi-Annual l Effluent Release Report that includes the following information:
i
- a. Explanation of why gaseous radwaste was being discharged without treatment, identification of any l . inoperable equipment or subsystems, and the reasons
- . for the inoperability, -
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- b. Action (s) taken to restore any inoperable equipment to operable status, and
- c. Summary description of action (s) taken to prevent a 4
recurrence. 4 E. Gas Storace Drums i 1. The quantity of radioactivity contained in a waste gas ' 4 storage drums shall be limited to less than or equal [ to 9.0E44 curies noble gases (considered as Xe-133). j Remedial Action: With the quantity of radioactive material
! in a waste gas storage drum exceeding the above limit, without !, delay:
! Amendment No. 19,51,H ,86 3.17-3 b {
- a. Take action t$ suspend all additions of radioactive
; material to the drum and
- b. within 48 hours either reduce the drum contents to within the limit or if unsuccessful,
- c. provide notification to the Commission within the next 30 days. The written report shall include a description of activities planned and/or taken to reduce the drum contents to within the above limit.
F. Explosive Gas Mixture
- 1. The concentration of oxygen in the waste gas holdup system, determined in accordanca with Specification 4.2, shall be limited to less than or equal to 4% by volume l
whenever the hydrogen concentration exceeds 2% by volume. Remedial Action: With the concentration of oxygen in the waste gas holdup system greater than 4% by volume and hydrogen concentration greater than 2% by volume, take actions to:
- a. suspend all additions of waste gases to the system and
- b. reduce the concentration of oxygen to less than or equal to 4% by volume without delay.
Basis: A. Gaseous Effluents: Dose Rate This specification is provided to ensure that the dose rate at anytime at the site area boundary and beyond from gaseous effluents will be within the annual dose limits of 10 CFR Part 20. 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 a member of the public in an unrestricted area, 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 members of the public who may at times be within the site boundary area, the occupancy time will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that at the site boundary. I i Amendment No. 65, 86 3.17-4 i i _ _ . . . , _ - _ _ _ _ _ . . _ _ _ _ . _ _ _ . . . . _ _ _ _. . . . . . , _ - , . _ _ _ _ , _ _ . _ . _ _ _ _ . _ _ _ . . . _ _ _ . _ _ _ . . _ _ ,- _ _ . . . . _ - . _ _ _ . . - . . ~ _
o . 3 e . The specified release rate limits restrict, at all times, j the corresponding gamma and beta dose rates above background i to an individual at or beyond the site area boundary to less l than or equal to 500 mrem / year to the total body, or to less than or equal to 3000 mrem / year to the skin. These release rate limits also restrict, at all times, the corresponding i thyroid dose rate above background to an infant via the milk-infant pathway to less than or equal to 1500 mrem / year for the nearest real milk animal to the plant. I B. Gaseous Effluents: Dose fr'm o Ncble Gases This specification is provided to implement the guidance of Sections II.B, III.A, and IV.A of Apoendix I,10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.B of Appendix I. The specification provides the required operating flexibility I and at the same time assures that the releases of radioactive material in gaseous effluents will be kept "as low as is 4 reasonably achievable". Sampling and analysis requirements of Specification 4.13 implement tne guidance in Section III.A of Appendix I, i.e., that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a member of the public through the appropriate pathways is unlikely to be substantially underestimated. The appropriate dose , equaticra aIs specified in the 00CM equations for determining the air doses at the site area boundary and beyond, and are based upon tne historical average atmospheric conditions. l C. Dose: Iodine-131, Iodine-133. Tritium, and Radioactive Material in Particulate Form This specification is provided to implement the guidance of Sections II.C, III.A, .and IV.A of Appendix I to 10 CFR Part 50. The Limiting Conditions for Operation are the guides set forth in Section II.C of Appendix I. The specification provides the required operating flexibility and at the same time assures that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable". The 00CM calculational methods implement the guidance in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a member of the public through appropriate pathways is unlikely to be
- substantially underestimated. These equations also provide i for determining the actual doses based upon the historical average atmospheric conditions. The release. rate
- specifications for Iodine-131, Iodine-133, trittium, and radioactive material in particulate form with half-lives greater than 8 days are dependent on the existing radionuclide pathways to man, in arens at and beyond the site boundary.
Amendment No. H ,86 3.17-5
I 1
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l 1 (l i The pathways which are examined in the development of these calculations are: c
- 1. individual inhalation of airborne radionuclides i
- 2. deposition of radionuclides onto green leafy vegetation with subsequent consunption by man
;i
- 3. deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the j milk and meat by man, and l
- 4. deposition on the ground with subsequent exdosure of man.
The remedial action requiring calculations if releases exceed two times the design objectives is included to assure that j' appropriate reports and requests for variance are made j should effluents exceed the limits set forth in 40 CFR 190. l D. Gaseous Radwaste Treatment System b
- The requirement that the appropriate portions of the Gaseous Radwaste Treatment System and Ventilation Exhaust Treatment System be used when specified provides reasonable assurance
; that the releases of radioactive materials in gaseous i effluents will be kept "as low as is reasonably achievable". ; This specification implements the requirements of 10 CFR l Part 50.36(a), General Design Criterion 50 of Appendix A to 10 CFR Part 50, and the design objectives of Appendix I to 10 CFR Part 50. The action levels governing the use of appropriate portions of the Gaseous Radwaste Treatment System were specified as a suitable fraction of the guides i set forth in Sections II.B and II.C of Appendix I, 10 CFR l
Part 50, for gareous effluents. i E. Gas Storaae Drum l Restricting the quantity of radioactivity (considered Xe-133) ! contained in a waste gas storage drum provides assurance that ! In the event of an uncontrolled release of the drum's i contents, the resulting total body exposure to a member of the public at the nearest exclusion area boundary will not exceed 0.5 rem. This is consistent with Branch Technical Position ETS8 11-5 in NUREG-0800, July 1981. The total body I ganna dose (0.5 rem) is calculated using an exclusion boundary i dispersion coefficient (x/Q) value of 5.93 x 10-4 see m-3 l l and a Xe-133 total body gamma dose conversion factor of i' 2.94 x 10-4 (mrem-m3)/(pCi-yr) . .. e i [ l i i Amendment No. H , 86 3.17-6 1
F. Explosive Gas Mixture This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the waste holdup system is maintained below the flammability limits for hydrogen and oxygen. Maintaining the concentration of oxygen below its flammability limits provides assurance that the release of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50. An EPRI study (EPRI W-3476, May 1984) demonstrates that oxygen concentrations less than or equal to 4% by volume in waste gas system provide an adequate margin of safety, with little or nothing to be gained by reducing the oxygen limits to a lower value. Sanpling and analysis as required by Specification 4.1 assures conformance with this Specification. i Amendment No. M ,86 3.17-7
. - - - _ - _ . _ - . -- _ _ _ _ . _- . - - - - - _ - . ~ _-.
3.28 RADI0 ACTIVE EFTLUENT MONITORING SYSTEMS Applicability: Applies at all times to Radioactive Effluent Monitoring Systems which perform a surveillance, protective, or controlling function on the release of radioactive effluents from the plant. Objective: To assure the operability of the Radioactive Effluent Monitoring Systems to perform their design functions. Specification: A. Radioactive Liquid Effluent Instrumentation
- 1. The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.28-1 shall be operable with their alarm / trip setpoints set to ensure that the limits of Specification 3.16.A.1 are not exceeded during periods of release of radioactive material through the pathway ;
monitored. The alarm / trip setpoints of these channels shall be determined in accordance with the methodology in the ODCM. Remedial Action: With a radioactive liquid effluent monitoring instrumentation chamel alarm / trip setpoint less conservative than a value which will ensure that the limits of 3.16.A.1 are met, without delay:
- a. take action to suspend the release of radioactive liquid effluents monitored by the affected channel or
- b. declare the channel inoperable, or char.ge the setpoint so it is acceptably conservative.
Remedial Action: With less than the minimum number of radioetive'eTfluent fronitoring instrumentation channels operable, take action shown in Table 3.28-1. Exert reasonable efforts to;
- a. return the instrument (s) to operable status within 30 days and,
- b. If unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report the reason for the delay in correcting the inoperability.
B. Radioactive Gaseous Effluent Instrumentation
- 1. The radioactive gaseous process and effluent monitoring instrumentation channels shown in Table 3 28-2 shall be operable with their alarm / trip selpoints . set to ensure that the limits of Specification 3.17.A.1 are not exceeded during release of radioactive material via'this pathway.
Amendment No. 86 3.28-1
The alarm / trip selpoints of these channels shall be determined in accordance with the methodology in the ODCM. Remedial Action: With a radioactive gaseous process effluent monitoring instrnwnt9 tion channel cler / trip setpoint less conservative than a value which will ensure that the limits of 3.17.A.1 are met, without delay, take action to:
- a. suspend the release of radioactive gasenus effluents monitored by the affected channel,
- b. or declare the channel inoperable, or change the setpoint so it is acceptably conservative.
Remedial Action: With less than the minimum number of radioactive effluent monitoring instrumentation channels operable, take action shown in Table 3.28-2. Exert reasonable efforts to: -
- a. return the instrument (s) to operable status within 30 days and,
- b. if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report the reason for the delay in correcting the inoperability.
Basis: A. Radioactive Liquid Effluent 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 are 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.
- 8. Radioactive Gaseous Effluent 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 are 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. Amendment No. 86 3.28-2
j . . l TABLE 3.d8-1 RADIOACTIVE LIQUID EFFLtENT MONITORING INSTRUENTATION MINIMUM l CHANELS REEDIAL
; INSTRtMENT CPERAELE ACTION
- 1. Gross Radioactivity Monitors i
Providing Alarm and Autornatic Termination of Release
- a. Liquid Radwaste Effluent Line (1) 1-(Test Tanks)
- 2. Gross Radioactivity Monitors Providing
, Alarm but Not Providing Automatic l Termination of Release
- a. Service Water System Effluent Line (1) 3 l
- b. Steam Generator Blowdown Line (1)* 2
- 3. Flow Rate Mer.surement Devices
- a. Liquid Radwaste Effluent Line (1) 4 4
l i
- Not required during steam generator blowdown recycle.
1 .- 1 Amer.dment No. 86 3.28-3
- - - _ , , . . . _ - . . _ _ - - - , . - . - . - _ , _ - . . - . - , - . - .--,_e-_--., . _ , , . - - - - - - _ . - -
TABLE 3.28-1 (Continued) TADLC NOTATION ACTION 1 With the number of channels operable less than required by the minimum channels operable requirement, effluent releases may continue provided that prior to initiating or continuing a release:
- 1. At least two independent samples are analyzed in accordance with Specification 4.13, Table 4.13-1.
< 2. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge valving.
Otherwise, suspend release of radioactive effluents via this pathway. ACTION 2 With the number of channels operable less than required by the minimum channels operable requirement, effluent releases via this pathway may continue provided grab samples are analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 10-6 uti/ml:
- 1. At least once per 12 hours when the specific activity of the secondary coolant is greater than 0.01 uCi/ gram dose equivalent I-131.
- 2. At least once per 24 hours when the specific activity of the secondary coolant is less than or equal to 0.01 uCi/ gram dose
. equivalent I-131.
ACTION 3 With the number of channels operable less than required by the minimum channels operable requirement, effluent releases via this pathway may continue provided that at least once per 24 hours grab samples are collected and analyzed for gross radioactivity (beta or gamma) at a lower limit of detection of at least 10-6 uC1/ml. ACTION 4 With the number of channels operable'less than required by the minimum channels operable requirements, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 8 hours during actual release. Pump performance curves generated in situ may be used to estimate flow. i Amendment No. 86 3.28-4
TABLE 3.28-2 RADI0 ACTIVE GASEOUS EFFLLENT MONITORING INSTRUENTATION MINIMUM CHANELS INSTRUMENT OPERABLE ACTION
- 1. Waste Gas Holdup System (a)
- a. Noble Gas Activity Monitor (a) (1) 5
- b. Effluent System Flow Rate (1) 6,
- 2. Condenser Air Ejector
- a. Noble Gas Activity Monitor * (1) 7
- 3. Plant. Stack (Vent Header System)
- a. Noble Gas. Activity Monitor (1) 7
- b. Iodine Sampler Cartridge ** (1) 8
- c. Particulate Sampler Filter ++ (1) 8
- d. Effluent System Flow Rate (1) 6 Measuring Device
- e. Sampler Flow Rate Measuring (1) 6 Device (a) Monitor provides alarm and automatic isolation function.
- During power operations (operating condition 7)
** Normal shutdown for filter change out does not constitute inoperability.
.a 7
Amendment No. 86 3.28-5 l
. . o TABLE 3.28-2 (Continued)
TABLE NOTATION ACTION 5 With the number of channels operable less than required by the minimum channels operable requirement, the contents of the drum (s) may be released to the environment provided that prior to initiating or continuing the release:
- 1. At least two independent samples of the drum's contents are analyzed, and
- 2. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge valve lineup.
Otherwise, suspend release of radioactive effluents via this pathway. ACTION 6 With the number of channels operable less than required by the minimum channels operable requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 8 hours. ACTION 7 With the number of channels operable less than required by the minimum channels operable requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 24 hours and these samples are analyzed for gross activity within 24 hours.
. ACTION 8 With the number of channels operable less than required by the minimum channels operable requirement, releases via this pathway may continue provided samples are collected with auxiliary equipment.
*2 Amendment No. 86 3.28-6
~
- Table 4.1-3 .
l Minimum Frequencies For Checks, Calibrations and l Testing of Miscellaneous Instrumentation and Controls a . Surveillance - Channel Description Function Frequency. Surveillance Method , Reed Switch Rod Position . 1. Check S Compare rod position indication from Indication System the Reed Switch Position Indication j System with that of the Pulse Count-j ing Position Indication System when-j ever the reactor is critical and the l plant computer is available. I 2. Pulse Counting Rod Position Check S Compare rod position indication from Indication System the Pulse Counting Position Indication
- System with that of the Reed Switch Position Indication System whenever
[ o the reactor is critical and the plant computer is available.
- 3. Area, Process and Effluent a. Test D(6) a. Internal test signals used to i Monitors verify instrument operation.
4 ) b. Calibrate R b. Exposure to known external radia-
- tion source.
A N e 4. Emergency Plant Radiation Calibrate R Exposure to known radiation source. i j, y (Containment High Range) m l 5 5. Environmental Monitors a. Check M a. Operational check. , i 2 ! l P b. Calibrate A b. Verify airflow indicator.
, '. 4 ..
l - 6. Pressurizer Level a. Check S(3) a. Comparison of independent level I g readings. 4
- b. Calibrate R b. Known differential pressure applied to sensor.
- l l
4
I Table 4.2-1 (Continued) Test Freauency
- 4. Concentrated Boric Acid Baron Concentration Weekly (e)
- 5. Safety Injection Tanks Boron Concentration Bi-monthly (d)
- 6. Spent Fuel Pool Boron Concentration Monthly
- 7. Secondary Coolant Gross Activity Determination At least once per 72 hours Isotopic Analysis for DOSE EQUIVALENT I-131 concentra-tion. One per 31 da/s, whenever the gross activity determination indicates iodine concentratons greater then 10% of the allowable limit.
One per 6 months, whenever the gross activity determination indicates iodine concentrations below 10% of the allowable limit.
- 8. Liquid Radwaste Radioactivity Analysis Prior to release from test tank.
- 9. Radioactive Gas Decay Radioactivity Analysis 1. Prior to release from gas decay drum l i
- 2. At least once per 24 hours when radioactive material is being added to the drum if the noble gas activity l of the primary coolant exceeds 25 uC1/g.
- 10. Spray Chemical Addition
' Tank NaCH Concentration Semi-Annual (e)
- 11. Sealed Sources Leakage Semi-Annual (f) i I Amendment No. 38,86 4.2-3
l
- 12. Oxygen Content in Gas 02 Concentration Daily during plailt Decay Drum Samples operating conditions that may result in production or entrainment of oxygen in the primary coolant. Such conditions include FCS venting and r
purging and plant heatup.
- 13. Incinerated Oil Principle Gama Grab sample of oil in liquid frem prior to incineration (h),
(a) Sample to be taken after a minimum of 2 effective full power days and 20 days of power operation have elapsed since reactor was last subcritical for 48 hours or longer. Definition of E given in specification 3.2. (b) When continuous monitors are inoperable, sampling of monitored parameter shall be done daily. (d) Not required when the plant is in the cold shutdown condition. (e) Not required when the vessel is empty. (f) Radioactive sealed sources shall be leak tested for contamination. Tests for leakage and/or contamination shall be performed by the licensee or by other persons specifically authorized by the Commission or an agreement State as follows: A. Each sealed source except startup sources subject to core flux, containing radioactive materials, other than hydrogen 3, with a half-life greater than thirty days and in any form other than gas shall be tested for leakage and/or contamination at intervals not to exceed six months.
- 8. The periodic leak test required does not apply to sealed sources that are stored and are not being used. The sources exenoted from this test shall be tested for leakage prior to any use or transfer to another user unless they have been leak tested within six months prior to the date of use or transfer. In the absence of a certificate from a transferer indicating that a leak test has been made within six months
- prior to the transfer, sealed sources shall not be put into use until tested. .
g i ; L , Amendment No. 38, 86 4.2-4 I it vp----n - - . - - - <-wy- ,,,,,--so,._ -- ---- - ,-w7 q -, e m -. - , pp,m - - . .-,m%p ,,y 9mq, -.,m_me -_ _ , ,---- . . -,.--g. -
n Table 4.2-1 (Continued) I C. Startup sources shall be leak tested prior to and following any repair or maintenance and before being subjected to core fix. I The leakage test shall be capable of detecting the presence of 0.005 micro-curie of radioactive material on the test sample. If the test reveals the presence of 0.005 microcurie or more of removable contamination, it shall immediately be withdrawn from use, decontaminated, and repaired, or be disposed of in accordance with Commission regulations. Notwithstanding the periodic leak tests required by this Technical Specification, any licensed sealed source is exempt from such leak test when the source contalris 100 mic rocuries or less of beta and/or gama emitting material or 10 microcuries or less of alpha emitting material. (g) Perform the calculation in item B of Specification 3.7 whenever the refueling water storage tank boron concentration is terted. (h) Incinerated oil may be discharged via points other than the primary vent stack (e.g., auxiliary boilers). The release of radioactive material shall be accounted for based on the pre-release grab sample data. The grab sample shall be representative of the contaminated oil and analyzed with a LLD of 5 x 10-7 uC1/ml. i Amendment No. J8, 86 4.2-5
Table.4.2-2 Minimum Frequencies for Equipment Tests Test Frequency
- 1. Control Element Assemblies Drop Times of all full-lenth Each refueling (CEAs) CEAs interval
- 2. Control Element Assemblics Partial Movement of all CEAs Every two weeks when (minimum of 6") the reactor is critical
- 3. Pressurizer Safety Valves Set Point One valve each refueling interval
- 4. Main Steam Safety Valves Set Point 2 valves per steam generator, each refueling interval
- 5. Refueling System Interlocks Functioning Prior to refueling operations
- 6. Primary System Leakage Evaluate Daily **
- 7. Diesel Fuel Supply Fuel Inventory Weekly
- 8. Deleted
- 9. Turbine stop governor, Functioning Monthly when the Reheater and Intercept turbine is operating Valves
- 10. L.P. Turbine Rotor Visual, Magnetic Particle One Rotor each 4 Inspection or Liquid Penetrant years
- 11. Post-accident containment vent system a) Hydrogen detector Calibrate Upon installing and within one month of startup from each refueling shutdown 4.2-6 Amendment No. 3 , gh,86 l
n - - - - ,- ,- , , - -
.._-.u.
I l 1 . l l '
. i Table 4.2-2 (Cont'd) '
t
- Test Frequency i
4 b) System valves Verify operability Upon installation and within one month of startup from each j refueling shutdown. , c) Flowpath Verify system flow Upon installation and j capability by within one month of
; observing flow startup from each 3 indication on the refueling shutdown.
system flowmeter
- 12. PORV and PORV Block Valve operability test i a) Block Valves Verify operability At least once per 92 by operating the days.
I valve (s) through
- one complete cycle
] of full travel
; b) PORVs Verify operability At least once per 18 by manual actuation months. , of the control circuitry
- 13. Pressurizer Veri fy Level *** At least once por 12 hours.
- Filters for containment and fuel storage building purging
**Whenever the reactor coolant system l Is at or above operating pressure t
***0nly required when reactor coolant system T is greater than 500gy, F.
i l r i ' 4.2-7 Amendment Nc. 62/, 86 l
1 4.8 RADIOLOGICAL ENVIR0tNENTAL SURVEILLAbCE PRCGRAM Applicability: This section applies at all times to radiological environmental surveillance and land use census. Objective: To verify that plant operations have no significant radiological effect on the environment and that continued operation will not result in radiological effects detrimental to the environment. The program also shall verify that any measurable concentrations of radioactive materials related to plant operations are not significantly higher than expected based on effluent measurements f and modeling of the environmental exposure pathways. 4. Specification: A. Radiological Environmental Monitoring
- 1. The Radiological Environmental Monitoring Program chall be conducted as epecified in Table 4.8-1 with lower limits of detection (LLDs) as specified in Table 4.8-2.
- 2. With the Radiological Environmental Monitoring Program not being conducted as specified in Table 4.8-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.
~. With the level of radioactivity in an environmental i
sampling medium at a location specified in Table 4.8-1
- exceeding a reporting level of Table 4.8-3 when averaged over any calendar quarter, prepare and submit to the Commission with the next Semi-Annual Effluent Release Report following receipt of the Laboratory Analyses, a report which includes an evaluation of any release conditions, environmental factors or other aspects which caused the limits of Table 4.8-3 to be exceeded.
When more than one of the radionuclides in Table 4.8-3 are dtttected in the sampling medium, this report shall be submitted if: concentration (1) + concentration (2) +... >1.0 reporting level (1) reporting level (2) Exception: When radionuclides other than those in Table 4.8-3 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to an individual is equal to or greater than the calendar year limits of Specifications 3.16.8.1, 3.17.8.1, and 3.17.C.1. This report is not required if the measured level of radioactivity was not the result ~of' plant effluents; however, in such an event, the condition shall be reported and described in the~ Annual Radiological Environmental Operating Report. Amendment No. 21. 86 4,8-1
- 4. With milk samples no longer available from one or more of the sample locations required by Table 4.8-1, identify new location (s) if available, for obtaining replacement samples and add them to the Radiological Environmental Monitoring Program within 30 days. The specific location (s) from which samples were no longer available may then be deleted from the Monitoring Program. Identify the cause of the samples no longer being available and identify the new location (s) for obtaining available replacement samples in the next Annual Radiological Environmental Monitoring Report.
- 8. Land Use Census
- 1. An ennual land use census within the distance of five miles shall be conducted to identify the location of the nearest milk animal, nearest garden of SDn2,the nearest residence, and the In lieu of a garden census, broad leaf vegetation of at least three different kinds may be sampled at or near the site boundary in two different sections.
- 2. With a land use census identifying a location (s) which yields a calculated dose commitment (via the sa'me exposure pathway) at least twice than at a location from which samples are currently being obtained in accordance with Specification 4.8.A.1, identify the new locations ir.
the next Annual Radiological Environmental Operating
, Report.
If permission from the owner to collect samples can be obtained and sufficient sample volume is available, then this new location shall be added to the radiological environmental monitoring program within 30 days. The sanpling location having the lowest calculated dose or dose commitment (via the same exposure pathway) may be deleted at this time.
- 3. The land use census shall be conducted at least once per 12 months between the dates of Ane 1 and October 1.
The results of the land use census shall be included in the Annual Radiological Environmental Operating Report. C. Interlaboratory Co m arlson Program Analyses shall be performed on applicable radioactive environmental samples supplied as part of an inter-laboratory comparison program which has been approved by NRC, if such a program existr. ' If analyses are not performed as required above, a report shall be made in the next Annual Radiological Environmental Operating Report. Amendment No. 86 4.8-2 i
4 Basis: A. Radiological Environmental Monitorina The radiological environmental monitoring required by this specification provides measurements of radiation and of j 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. This monitoring program thereby supplements the radiological effluent monitoring program by verifying that l the measurable concentrations or 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. Program changes may be initiated based on operational experience.
A two-zone sample collection network has been established for . environmental surveillance. Samples are collected in Zone I l at locations in the vicinity of the plant where concentrations of plant effluents may be detectable. These samples are compared to samples which have been collected simultaneously at locations in Zone II where the concentration of plant effluents is expected to be negligible. The Zone II samples provide a running background which will make it possible to distinguish significant radioactivity i introduced into the environment by the operation of the plant from that introduced by weapons testing or other sources. The detection capabilities required by Table 4.8-2 are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an a priori (before the fact) limit ! representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement. This does not preclude the calculation of an a posteriori LLD for a particular measurement based upon the actual parameters for the sample in question. B. Land Use Census This specification is provided 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. The addition of new sampling locations to Specification 4.8.A.1 based on the land use census is limited to those locations l which yield a dose commitment at least twice the calculated dose commitment at any location currently being sampled. This eliminates the unnecessary changing of the-envircnmental
-5 Amendment No. 86 4,g_3 I
radiation monitoring program for new locations which, within the accuracy of the calculation, contribute essentially the same to the dose or dose commitment as the location already sampled. The substitution of a new sampling point for one already sampled when the calculated difference in dose is less than a factor of 2 would not be expected to result in a significant increase in the ability to detect plant effluent related nuclides. Changes in the location of monitoring locations is not to be done lightly since frequent changes disrupt time series and may make integretation of data more difficult. C. Participation in an NRC approved Interlaboratory Comparison program (if one exists) provides quality assurance for the environmental laboratory, similar to programs in place for other environmental monitoring efforts such as that for water quality. r i Amendment No. 86 4.8-4
)
k TABLE 4.8-1 - y . e RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE PROGRAM (1)(2)(3) Exposure Pathway Number of Sampling and Type and Frequency f and/or Sample Sample Locations Collection Frequency of Analysis (4) '
$ 1. /.IRBORNE ,
I h a. Radioiodine and 5 Continuous operation of Radioiodine canister. oo Particulates sampler with sample Analyze at least once collection as required per week for I-131. by dust loading but at least once per week. Particulate sampler. Analyze for gross beta radioactivity at least 24 hours following filter
, change. Perform gamma , isotopic analysis on com-f, posite (by location) sample at least once per quarter.
- 2. DIRECT RADIATION 38 Quarterly Gamma dose quarterly.
- 3. WATERBORNE
- a. Surface (Estuary) 2 Composite
- sample Gamma isotopic analysis of collected over a each monthly sample, period of 1 month. Tritium analysis of com-posite sample at least once per quarter.
- b. Ground ** 2 At least once per Gamma isotopic and tritium
;, quarter, analyses of each sampLo
- c. Sediment from Shoreline 2 At least once per Gamma isotopic analysi-6 months. of each sample.
- Composite samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours. Control station samples may be grab samples rather than composite.
** Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where hydraulic gradient or recharge properties are suitable for contamination.
TABLE 4.8-1 (Continued) . I ' g RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE PROGRAM (Continued) s g Exposure Pathway Number of Sampling and Type and Frequency - n and/or Sample Sample Locations Collection Frequency of Analysis - 2:
- 4. INGESTION
,. t
- a. Milk
- 3 At least once per month. Gamma isotopic and I-131
't analysis of each sample. @! b. Fish and Invertebrates 2 One sample in season, or Gamma isotopic analysis semiannually if not seasonal, on edible portions. of each of at least 2 commer-cially or recreationally important species.
- c. Food Products consisting 3 Monthly when available Gamma Isotopic and I-131 ~
f- of at least 3 types of
?
broad leaf vegetation. Performed only if milk , sampling is not done. (1) Specific sample locations for all media are specified in the Off-Site Dose Calculation Manual and reported in the Annual Radiological Environmental Operating Report. (2) See Table 4.8-2 for maximum values for the Lower Limits of Detection. ! (3) Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability or to malfunction of sampling equipment. If the latter occurs, every effort'shall be made to complete corrective action prior to the end of the next sampling period.
- n. '1 *-
(4) Gamma isotopic analysis means the identification and quantification of gamma-emmitting radionuclides that may be attributable to effluents from the plant.
- Food products (4.c) may be substituted for milk samples.
l TABLE 4.8-2 - E. DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS (a)(b)(d) H . o
" Lower Limits of Detection -
5 ' Airborne Particulate Food " M Water Fish & Invertebrates Milk Sediment Products or Gag
*) Analysis (* (pCi/1) (pCi/m ) (pCi/kg/ wet) (pCi/1) (pCi/kg, dry) (pCi/kg, wet) w t Gross Beta 4 .01 -
! 3 H 2000* 54 Mn 15 130 597 , 30 260 58, 60 15 130 Co en 4 657 , 30 260 , 15 c 95 Zr - Nb 131 7 1** .07 1 60 l 134 15 .05 130 15 150 60 Cs 137 18 .06 150 18 180 80 Cs 140 Ba-La 15 15"'
- c. t e.
- If no drinking water pathway exists, a v:tlue of 3000 pCi/1 may be used.
** If no drinking water exists a value of 15 pC1/1 may be used.
e 4 TABLE 4.8-2 (Continued) TABLE NOTATION
- a. The LLD is the smallest concentration of radioactive materiP1 in a sample that will yield a net count, above system background, that will be detected with 95% probability and that only a 5% probability exists of falsely !,b concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical
- separation):
4.66
- Sb LLD =
- E
- V
- 2.22
- Y
- Exp (-A
- at) where LLD is the "a priori" Lower Limit of Detection as defined above (as picoeuries per unit mass or volume) 4.66 is a constant derived from the K81Pha and g eta values for the 95%
confi,dence level. So 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 disintegration) V is the sample size (in units of mass or volume) 2.22 is the number of disintegration per minute per picocurie Y is the fractional radiochemical yield (when applicable) A is the radioactive decay constant for the particular radionuclide at is the elapsed time between sample collection and analysis. Typical values of E, V, Y, and at can be used in the calculation. This equation results in an LLD in terms of picocuries. For the purposes of Specification 4.12, where the required LLD is set forth in microcuries, the terms 2.22 in the denominator should be replaced by 2.22E6 which is the number of disintegrations per minute per microcurie. In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the background shall include the typical contribulions of other radionuclides normally present in the samples (e.g., Potassiumi40 in milk samples). Amendment No. 86 - 4.8-8
4
- TABLE 4.8-2 (Continued)
TABLE NOTATION The analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally, background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unavailable. In such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Repo t.
- b. It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measuremt3t sy: tem and not as an a, posteriori (after the fact) limit for a particular measurement. This does not preclude the calculation of an a posteriori LLD for a particular measurement based upon the actual parameters for the sample in question and appropriate decay correction parameters such as decay while sampling and during analysis,
- c. Parent only.
- d. If the measured concentration minus the 3 standard deviation uncertainty is found to exceed the specified LLD, the sanple does not have to be analyzed to meet the specified LLD.
j e. This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable together with those of the listed nuclides, shall also be analyzed and reported in the Annu?1 Radiological Environmental Operating Report pursuant to Specification 5.9.1.5.
- f. The Ba-140 LLD and concentration can be determined by the analysis of its short-lived daughter product La-140 subsequent to an 8-day period following collection. The calculation shall be predicated on the normal ingrowth equations for a parent-daughter situation and the assumption thst any unsupported La-140 in the sample would have decayed to an insignificant amount (at least 3.6% of its original value). The ingrowth equations will assume that the supported La-140 activity at the time of collection is zero.
i Amendment No.86 4.8-9
TABLE 4.8'-3 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Airborne Particulate Fish and Food Water orGasgs Invertebrater Milk Products Analysis ( (pC1/1) (pCi/m ) (pCi/kg/ wet) (pCi/1) (pCi/1) H-3 20,000* Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400** I-131 2*** 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200** 300
- For drinking water samples. If no drinking water pathway exists, a value of 30,000 pCi/1 may be used.
** Parent only.
*** If no drinking water exists, a value of 20 pCi/1 may be used.
r
- i Amendment No. 27,/42, 86 4.8-10
4.13 Radioactive Effluent Monitoring - Applicability: Applies to monitoring radioactive effluents both liquid and gaseous. Objective: To specify the nature and frequency of radioactive effluent monitoring requirements. Specification: A. Liquid Effluents: Sampling and Analysis
- 1. Liquid radioactive waste sampling and activity analysis shall be performed in accordance with Table 4.13-1.
- 2. The results of the radioactivity analyses shall be used in accordance with the methodology and parameters in the ODCM to assure that the concentrations at the point of release are maintained within the limits of Specification 3.16.A.l.
- 3. DJmulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall bc determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.
B. Liquid Effluents: Instrumentation Discharge of liquid radioactive effluents shall be continuously monitored with the alarm / trip setpoints of the monitor set in accordance with the methods outlined in the ODCM such that the requirements of Section 3.16.A are met. C. Gaseous Effluents: Sampling and Analysis
- 1. Gaseous radioactive waste sampling and activity analysis shall be performed in accordance with Table 4.13-2.
- 2. The cumulative doses due to gaseous effluents for the current calendar quarter and calendar year shall be determined to be within the limits of Specification 3.17.A, B, and C in accordance with the methodology and parameters of the ODCM at least once per 31 days.
- 3. Doses due to gasects releases from the site to areas at or beyond the site boundary shall be compared with the limits of Specification 3.17.D.1 in accordance with the methodology and parameters in the ODCM at least once per 31 days. If all gaseous releases for the. period have been procassed via a design mode of the Gaseous-Radwaste Treatment System, dose estimates for compliance with Specification 3.17.0.1 are not required. ,
i 1 i Amendment No. 86. 4.13-1
9 D. Gaseous Effluents: Instrumentation Radioactive gaseous effluents shall be continuously monitored with the alarm / trip setpoints of the monitors set in accordance with the methods outlined in the ODCM such that the requirements of Section 3.17.A will be met. Basis: The Sampling Analysis and Instrumentation requirements set forth in this specification provide reasonable assurance that all significant radioactive releases will be monitored and that the effluents will not result in exceeding the requirements of 10 CFR 20. j r i l Amendment No. 86 4.13 2
, 3 . TABLE 4.13-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Minimum Lower Limit of Sampling Analysis Type of Activity Detection (LLD) Liquid Release Type Frequency Frequency Analysis (uCi/ml)a
-7 A. Batch Waste PR PR Principal Gamma 5 x 10 Release Tanks d Each Batch Each Batch Emittersf
-6 I-131 1 x 10 PR M Dissolved and 1 x 10-5 One Batch /M Entrained Gases (Gamma Emitters)
PR M H-3 1 x 10 5 Each Batch Composite _7
-0 PR Q SR-89 Sr-90 5 x 10 Each Batch Composite b Fe-55 b 1 x 10
-6 e
B. Plant Continuous D W Principal Gamma 5 x 10-7 Releasese Grab Sample
- Compositeb Emittersf
- Turbine Building W8 I-131 1 x 10-6 Sump Grab Sample **
-5
** Steam Generator M M Dissolved and 1 x 10 Blowdown only Grab Sample Entrained Gases W8 M H-3 1 x 10-5 Grab Sample ** Composite D Gross Alpha 1 x 10-7 W8 Q SR-89, Sr-90 5 x 10-8 b
Grab Sample ** Composite 5 Amendment No. 86 4.13-3 l l l
e TABLE 4.13-1 (Continued) TABLE NOTATION
- a. The Lower Limit of Detection (LLD) is defined in Table Notation a. of Table 4.8-2 of Specification 4.8.
- b. 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 representativc of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected during release and composited 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 is the discharge of liquid wastes of 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 is the discharge of liquid wastes of a non-discrete volume; e.g., from a volume of system that has an input flow during the continuous release.
. f. 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-1g7, and Ce-141. Ce-144 shall also be measured but with an LLD of 5 x 10, . This list does not mean that only these nuclides are to be considered. Other gamma peaks which are identifiable, together with the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report. Nuclides which are below the LLD for the analyses should not be reported as being present at j the LLD level.
- g. Weekly grab samples from the steam generator blowdown only during periods when blowdown is being discharged overboard, and not when blowdown is recycled to the main condenser.
- h. Fe-55 shall be analyzed on quarterly composite samples commencing with I
July 1, 1986. If, after a period of 2 years, the results indicate j that FE-55 is likely to contribute 1% or less of the total dose attributable to this pathway, the licensee may discontinue the analysis. 7 i i Amendment No.86 4.13-4
TABLE 4.13-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Minimum Lower Limit of Sampling Analysis Type of Activity D:tt'J, ton (LLD) Liquid Reinase Type Frequency Frequency Analysis (uCi/c1)a A. Waste Gas Storage PR .PR Principal Gamma 1 x 10-Tank Each Tank Each Tank Emitterse Grab Sample
-0 B. Containment Purge PR PR Principal Gaseous 1 x 10 Each Purge b Each Purgeb Gamma Emitterse Grab Sample H-3 1 x 10-6 b gb -0 C. Plant Vent Stack M Principal Gamma 1 x 10 Grab Emitterse Continuous d gc I-131 1 x 10-12 Charcoal Sample Continuous d gc Principal Gamma 1 x 10-11 Emitterse Particulate (I-131, Others)
Sample d Continuous M Gross Alpha 1 x 10-11 Composite Particulate Sample d Continuous Q SR-89, Sr-90 1 x 10 -11 Composite Particulate Sample d -0 Continuous Noble Gas Noble Gases 1 x 10
. Monitor Gross Beta or Gamma r
i Amendment No. 86 4.13-5
( . l ,
- TABLE 4.13-2 (Continued)
TABLE NOTATION i
- a. The Lower Limit of Detection (LLD) is defined in Table Notation a. of Table 4.8-2 of Specification 4.8.
- b. Sampling and analyses shall also be performed within 24 hours following shutdown, startup, or a thermal power change exceeding 15% of the rated thermal power in one hour unless: (1) analysis shows that the dose equivalent I-131 concentration in primary coolant has not increased more thana{actorof3andtheresultantconcentrationisatleast 1 x 10- uCiAl; and (2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of 3.
- c. Sag ling shall also be performed at least once per 24 h'ours for at least 7 days following each shutdown, startup, or a thermal power change exceeding 15E of rated thermal power in one hour, and analysis shall be co@leted within 48 hours of changing the samples. This requirement to sample at least once per 24 hours for 7 days applies only if: (1) cnalysis shows that the dose equivalent I-131 concentration in the primary coolant has increased more than a 1 x 10-{ actor of 3 and the resultant concentration is at leastuti/ml; and (2) the no activity has increased more than a factor of 3. When samples collected for 24 hours are analyzed, the corresponding LLDs may be increased by a factor of 10.
- d. The ratio of the sample flow rate to the sampled stream flor rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Specifications 3.17.A, 3.17.B and 3.17.C.
- e. The principal gamma emitters for which the LLD specification applies exclusively are 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 emissionr.
This list does not mean that only these nuclides are to be detected and reported in the Semiannual Radioactive Effluent Release Report. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported in the Semiannual Radioactive Effluent Relesse Report. Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level for that nuclide but as "not 4 detected". When unusual circumstances result in LLDs higher than required, the reasons shall be documented in the Semiannual Radioactive Effluent Release Report. 7 4 Amendment No. 86 4 . 13 - 6
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- e. Review of Technical Specification violations, and for:
- 1. Approving reports evaluating such violations and providing recomendations to prevent recurrence.
- 2. Ensuring that those reports are forwarded to the Manager of Operations and to the Chairman of the Nuclear Safety Audit and Review Comittee.
- f. Review of all reportable events.
- g. Review of facility operations to detect potential nuclear safety hazards.
- h. Performance of special reviews, investigations of anal-yses and reports thereon as requested by the Chainnan of the Nuclear Safety Audit and Review Comittee.
- 1. Approval of the review of the Plant Security Plan and implementing procedures and ensuring that recomended changes are submitted to the Security Supervisor and Chainnan of the Nuclear Safety Audit and Review Comittee.
- j. Approval of the review of the Emergency Plan and imple-menting procedures and ensuring that recommended changes are submitted to the Plant Manager.
- k. Approval of the review of the Offsite Dose Calculation Manual and its implementing procedures and ensuring that recomended changes are submitted to the Plant Manager.
- 1. Approval of the review of the Process Control Program and its implementing procedures and ensuring that recomended changes are submitted to the Plant Manager.
- 8. AUTHORITV The Plant Operation Review Comittee shall:
- a. Recomend to the Plant Manager in writing, approval or dis-approval of items considered under 7(a) through (d) above.
- b. Render determinations in writing with regard to whether or not each item considered under 7(a) through (e) above constitutes an unreviewed safety question.
- c. Provide written notification within 24 hours to the Manager of Operations of disagreement between the PORC and the Plant Manager; however, the Plant Manager shall have respon-sibility for resolution of such disagreements pursuant to 5.1.1.above. 5 s
Amendment No. 34,39,50,77,79, 86 5.5-3
.. - . - .. . - . . . _ - =--
=
4
- e. The Facility Emergency Plan and implementing procedures at least once per 12 months.
- f. The Facility Security Plan and implementing procedures at least once per 12 months.
- g. The Facility Fire Protection Program and implementing 4 procedures at least once per 24 months.
- h. An independent fire protection and loss prevention
- inspection and audit shall be performed at least once per 12 months utilizing either qualified offsite licensee personnel or an outside fire protection firm.
s
- 1. An inspection and audit of ,the fire protection and loss prevention program shall be performed by an
< outside qualified fire consultant at intervals no greater than 3 years.
J. The Offsite Dose Calculation Manual and its implementing procedures at least once per 24 months.
- k. The Process Control Program and its implementing procedures at least once per 24 months.
- 1. Any other area of facility operation considered I appropriate by the NSAR Committee or the Vice President (YNSD).
- 10. AUTHORITY The NSAR Committee shall report to and advise the Vice President (YNSD) on those areas of responsibility specified in Section 5.B.8 and 5.B.9.
- 11. RECORDS Records of NSAR activities shall be prepared, approved and distributed as indicated below:
! a. Minutes of each NSAR meeting shall be prepared, and 4 forwarded to the Vice President (YNSD) within 20 working days following such a meeting,
- b. Reports of reviews encompassed by Section 5.B.8 above,'
shall be prepared, and forwarded to the Vice President (YNSD) within 20 working days following completion of the review.
- c. Audit reports encompassed by Section 5.5.d above, shall be forwarded to the management positions responsible for the areas audited within 30 working days after completion of the audit.
Amendment No. 3d,50,77, 86 5.5-7
- _ - - _ - - _._. .. _, _ ._ _..-__ _ - m. _ _ _- -- . _ _ - _ - - _ _ _ _ - _ _ . . - . _ . . ~ . _ - - - - -
routine maintenance, special maintenance (describe maintenance), waste processing, and refueling. The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements. Small exposures totaling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 804 of the total whole body dose received from external sources shall be assigned to specific major work functions. MONTH.Y (PERATING REP (RT 5.9.1.4 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Management Information Branch of tne Office of Resource Management, U. S. Nuclear Regulatory Commission, , Washington, D. C. 20555, with a copy tc the Regional Office, to arrive no later than the fifteenth of each month following the calendar month covered by the report. 1 UNIQLE REPORTING REQUIREENTS 5.9.1,5 Annual Radiological Environmental Operating Report l Routine Radiological Environmental Operating Repcrts covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year. The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, and an assessment of the environmental impact of plant operation, if any. The reports shall also include the results of the land use censuses required by Specification 4.8.8. The Annual Radiological Environmental Operating Reports shall include summarized and tabulated results of radiological environmental samples taken during the report period pursuant to the tables and figures in the OTM. 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. The reports shall also include the following: a summary description of the radiological environmental monitoring program including a map of all sampling locations keyed to a table giving distances and directions from the reactor; and a discussion of all analyses in which the LLD required by Table 4.8-2 was not achievable. 5.9.1.6 Semiannual Radioactive Effluent Release Report Tb Routine Radioactive Effluent Release Reports covering the operating of the unit during the previous 6 months of operation shall be submitted within 60 uays a Aer Canuary 1 and JJ1y 1 of each year. Amendment No. H,M,77,79, 86 5.9-2
l . 1 The Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid j waste released from the unit with data sumarized on a quarterly basis. In addition, the Radioactive Effluent Release Report to be submitted 60 days after January 1 of each year shall include 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 on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability.* The Radioactive Effluent Release Report to be submitted 60 days after January 1 of each year shall also include an estimate of the maximum potential radiation doses to the member (s) of the public from reactor releases for the previous calendar year. The assessment of radiation doses shall be performed in accordance with the Off-Site Dose Calculation Manual (00CM). The Radioactive Effluent Release Reports shall include the following information for each class of solid waste (as defined by 10 CFR Part 61) shipped off-site during the report period:
- a. Container volume.
- b. Total curie quantity (specify whether determined by measurement or estimate).
- c. Principal radionuclides (specify whether determined by measurement t , or estimate).
- d. Source waste and processing employed (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms).
- e. Type of container (e.g., LSA, Type A, Type B, Large Quantity).
i f. Solidification agent or absorbent (e.g., cement, asphalt, "Dow"). The Radioactive Effluent Release Reports shall include a list and i description of unplanned releases from the site-to-site boundary of radioactive materials in gaseous and liquid effluents made during the reporting period. The Radioactive Effluent Release Reports shall include a listing of new locations for dose calculations and/or environmental monitoring - identified by the land use census pursuant to Specification 4.8.B. 1 The Radioactive Effluent Release Reports shall include changes to the ODCM for information. -4 r
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- In lieu of submission with the first half year Radioactive Effluent Release Report, tne Licensee has the options of retaining this summary of required meteorological data in a file that shall be provided to the NRC upon request.
Amendment No M ,59,77,79, 86 5.9-3
SPECIAL REPORTS 5.9.1.7 Special reports shall be submitted to the Regional Administrator of the Regional Office of the NRC within the time period specified for each report. These reports shall be submitted concerning the activities identified below pursuant to the requirements of the applicable specification or rule,
- a. Reactivity anomalies, Specification 3.15.
- b. Excessive radioactive release, Specifications 3.16A2 and 3.17A2.
- c. Plans for restoration of 115 kV service, Specification 3.12.
- d. Containment Type A test failure, Specification 4.4IC2.
- e. Integrated leakage rate test report, Specifica-tion 4.4.III.
- f. Reactor Coolant System Activity, Specification 3.2.
- g. Total Dose, Specification 3.16 and 3.17.
i n Amendment No. 34,56,77,79, 86 5.9-4
- 1. Records of in-service inspections performed pursuant to these Technical Specifications.
J. Records of Quality Assurance activities required by the QA Manual.
- k. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10CFR50.59.
- 1. Records of meetings of the P(R and the NSAR Committees.
- m. Records of analysis required by the Radiological Environmental -
Monitoring Program. l
- 5 Amendment No. 34,5@,77,. 86 5 10-2
. . - - - _, __ -.}}