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Category:OPERATING LICENSES & AMENDMENTS
MONTHYEARML20217C1131999-10-0808 October 1999 Amend 153 to License DPR-3,revising TS Section 6.0, Administrative Controls,By Deleting TS Section 6.2.2.f, Which Contains Limits on Working Hours of Plant Staff ML20211J2971999-08-27027 August 1999 Amend 152 to License DPR-3,deleting License Condition 2.C(10) Which States: Licensee Shall Maintain FFD Program IAW Requirements of 10CFR26 ML20207F9221999-03-0505 March 1999 Amend 151 to License DPR-3,revising Pol by Changing Submittal Interval for Radioactive Effluent Rept from Semiannual to Annual ML20203G2461999-02-12012 February 1999 Errata to Amend 150 Issued to License DPR-3.Index Page Corrected ML20202H5811999-02-0303 February 1999 Amend 150 to License DPR-3,revising Possession Only License Through Three Changes to TS ML20249A7891998-06-17017 June 1998 Amend 149 to License DPR-3,revising TS Sections Re Min Water Cover Over Spent Fuel,Crane Travel Over Spent Fuel & Related Bases ML20237F1591998-02-19019 February 1998 Amend 147 to License DPR-3,deleting Main Coolant Sys Water Chemistry Limits & Surveillance,Secondary Water Chemistry Monitoring Program & Requirements for Oxygen Monitoring of Waste Gas Holdup Sys ML20058C4011990-10-22022 October 1990 Amend 137 to License DPR-3,modifying Page 3/4 1-27, Surveillance Requirement 4.1.3.4.a,to Delete Ref to Control Rod Group a as Control Group ML20059M0561990-09-26026 September 1990 Corrected Pages to Amend 136 to License DPR-3 ML20059G2371990-09-0606 September 1990 Amend 135 to License DPR-3,modifying Tech Spec Surveillance Requirement 4.5.2a to Change ECCS Pump Surveillance Frequency from Monthly to Quarterly & to Remove Min Required Discharge Pressures from Tech Spec ML20058L6611990-08-0202 August 1990 Amend 134 to License DPR-3,incorporating NRC Guidance in Generic Ltr 88-17 Into Facility Tech Specs & Adding Three New Tech Specs Specifying Plant Conditions & Equipment Operability Requirements to Prevent Core Uncovery ML20058L0281990-08-0202 August 1990 Amend 133 to License DPR-3,incorporating Wording from Std Westinghouse Tech Specs Into Util Limiting Condition for Operation Specs 3.10.3 & 3.10.4 ML20055C8581990-06-18018 June 1990 Amend 132 to License DPR-3,changing Title of Technical Svc Supervisor,Establishing New Positions Entitled Maint Support Supervisor & Operations Support Supervisor & Increasing Number of Senior Reactor Operators on Shift to Two ML20247F1231989-09-0707 September 1989 Amend 124 to License DPR-3,moving Onsite & Facility Organizational Charts from Section 6.0 of Tech Specs to Section 401 of FSAR ML20247E6681989-08-31031 August 1989 Amend 123 to License DPR-3,removing Description of High Pressurizer Water Level in Section 2 Re Bases of Tech Specs on Page B2-4 ML20195D6651988-11-0101 November 1988 Amend 120 to License DPR-3,enabling Piping Mods Needed to Allow for Installation of Water Cleanup Sys ML20205G1661988-10-25025 October 1988 Amend 119 to License DPR-3,permitting Increase in Nitrogen Pressure in Safety Injection Accumulator Tech Spec ML20204G4641988-10-17017 October 1988 Amend 118 to License DPR-3,revising Tech Specs Re Specific Values of Boron Concentration ML20205C3961988-10-14014 October 1988 Amend 117 to License DPR-3,changing Tech Specs by Adding Four Isolation Valves,In Two Spare Penetrations,To Table 3.6-1, Containment Barriers ML20195C9941988-10-12012 October 1988 Corrected Page 2 to Amend 116 to License DPR-3 ML20207L6891988-10-12012 October 1988 Amend 116 to License DPR-3,permitting Mods to nonsafety-class Portions of Neutron Shield Tank Cavity Leakage Collection Piping ML20207E8101988-08-0505 August 1988 Amend 115 to License DPR-03 Re Changes in Physical Security Plan ML20151M4861988-07-29029 July 1988 Amend 114 to License DPR-3,making Battery Charger Surveillance Requirements in Tech Specs Same for All Three Battery Chargers ML20151K3691988-07-25025 July 1988 Amend 113 to License DPR-3,revising Tech Specs to Permit Loads Greater than 900 Lbs to Travel Over Plant Fuel Pit to Enable Removal of Control Rods from Spent Fuel Pit ML20151K8531988-07-19019 July 1988 Amend 112 to License DPR-3,revising Shutdown Margin Switching Temp to 470 F & Correcting Typo & Inadvertent Omission of Previously Approved Surveillance Requirement ML20196K2471988-06-28028 June 1988 Amend 111 to License DPR-3,removing Requirement for Plant Operations Manager to Maintain Senior Reactor Operator License from Tech Specs ML20195K1401988-06-17017 June 1988 Amend 110 to License DPR-3,revising Tech Specs Re Control Rod Position Indication & Correcting Minor Error in Tech Specs ML20195C5111988-06-13013 June 1988 Amend 109 to License DPR-3,deleting Refs to Mode 5 in Tech Spec Tables 3.3-2 & 4.3-2 ML20155K5071988-06-0909 June 1988 Amend 108 to License DPR-3,changing OL Expiration Date from 971104 to 000709 ML20154J7621988-05-18018 May 1988 Amend 107 to License DPR-3,adding Surveillance Requirements to Tech Specs Re 480-volt Emergency Buses ML20216J4031987-06-26026 June 1987 Amend 106 to License DPR-3,modifying Tech Spec Requirements on Min Number of Operable Neutron Detector Thimbles for Cycle 19 Operation ML20213G9111987-05-13013 May 1987 Amend 105 to License DPR-3,revising Tech Spec Requirements for Surveillance Testing of Power Range & Intermediate Power Range Neutron Flux Channels ML20213D9511987-05-0707 May 1987 Amend 104 to License DPR-3,revising Tech Specs Re Reporting Requirements on Reportable Events & on Primary Coolant Iodine Spiking ML20211L3561987-02-17017 February 1987 Amend 103 to License DPR-3,revising Tech Specs Re Max Nominal Enrichment of Reload Fuel ML20207N8741987-01-0707 January 1987 Amend 102 to License DPR-3,modifying Tech Specs Re RCS Vent Sys by Allowing Power to Be Removed from Valves During Normal Plant Operations ML20207N4161987-01-0606 January 1987 Amend 101 to License DPR-3,changing Tech Specs to Increase Time Period That Valve CS-MOV-532 May Be Open from 30 Minutes/Wk to 120 Minutes/Wk ML20214X3321986-12-0101 December 1986 Amend 100 to License DPR-3,revising Tech Spec Requirements Re Min Number of Operable in-core Neutron Detector Thimbles for Remainder of Cycle Xviii Operation ML20210S1741986-09-23023 September 1986 Amend 99 to License DPR-3,modifying Portions of Radiological Effluent Tech Specs for Consistency W/Current NRC Guidance on Environ Monitoring ML20212M8441986-08-20020 August 1986 Amend 98 to License DPR-3,modifying Tech Specs Re Required Date for Submittal of Supplemental Dose Assessment & Meteorological Summary Info ML20215E2831986-07-11011 July 1986 Corrected Page to Tech Spec 3/4 6-11 Re Containment Barriers ML20199K4801986-06-27027 June 1986 Errata to Amend 95 to License DPR-3,correcting Tech Spec Page 3/4 3-18 Re Radiation Monitoring Instrumentation ML20206M7181986-06-17017 June 1986 Amend 97 to License DPR-3,modifying Tech Specs to Add Containment Isolation Valves for Containment Breathing Air Sys ML20199L7521986-06-13013 June 1986 Corrected Tech Spec Pages to Amend 92 to License DPR-3 Re Main Coolant Sys,Eccs Subsystems & Vessel Fluence for Weld Metal ML20199D5341986-06-0909 June 1986 Amend 96 to License DPR-3,modifying Tech Specs to Replace Manual Containment Isolation Valve W/Blank Flange ML20211G6791986-06-0505 June 1986 Amend 95 to License DPR-3,modifying Tech Specs to Add Containment high-range Radiation,Pressure & Water Level Monitors & Core Exit & Reactor Vessel Head Thermocouples to Required Instrumentation List ML20198S6371986-05-28028 May 1986 Amend 94 to License DPR-3,changing Tech Specs by Adding Containment Isolation Valves for Containment Breathing Air Sys ML20198C3361986-05-14014 May 1986 Amend 92 to License DPR-3,changing Tech Specs Re Safety Injection Tank Solution Temp,Steam Generator Blowdown Monitors,Containment Isolation Boundary,Eccs Surveillance & Reactor Vessel Fluence ML20141K3191986-01-15015 January 1986 Amend 91 to License DPR-3,deleting Tech Spec Requirements for Insp of Control Rod Shroud Tube Assemblies & Pressurizer Internals ML20136B7971985-12-16016 December 1985 Amend 90 to License DPR-3, Modifying Tech Specs to Define Limiting Conditions for Operation & Surveillance Requirements to Limit ECCS Leakage to 50 Gallons Per Day ML20137Z6131985-11-30030 November 1985 Amend 89 to License DPR-3,revising Tech Spec Surveillance Interval for Second Level (Degraded Grid Voltage) Undervoltage Protection 1999-08-27
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20217C1131999-10-0808 October 1999 Amend 153 to License DPR-3,revising TS Section 6.0, Administrative Controls,By Deleting TS Section 6.2.2.f, Which Contains Limits on Working Hours of Plant Staff ML20211J2971999-08-27027 August 1999 Amend 152 to License DPR-3,deleting License Condition 2.C(10) Which States: Licensee Shall Maintain FFD Program IAW Requirements of 10CFR26 ML20206B9181999-04-23023 April 1999 Application for Amend to License DPR-3,requesting That Characterization of Revised Review & Audit Function Remain in Plant Defueled TS Rather than Being Transferred to Plant QA Plant ML20205M1391999-03-24024 March 1999 Application for Amend to License DPR-3,deleting Condition 2.C.(10) Re Ffd,From License.Condition No Longer Applies to Plant Since Plant Has Permanently Ceased Operation & Permanently Removed Fuel from Reactor Vessel ML20204D8681999-03-17017 March 1999 Application for Amend to License DPR-3,proposing Deletion of Overtime Restrictions Currently Incorporated in Ynps TSs ML20204E5511999-03-17017 March 1999 Application for Amend to License DPR-3,requesting Transfer of Adminstrative Requirements from Plant Defueled TS to Decommissioning QA Program ML20207F9221999-03-0505 March 1999 Amend 151 to License DPR-3,revising Pol by Changing Submittal Interval for Radioactive Effluent Rept from Semiannual to Annual ML20203G2461999-02-12012 February 1999 Errata to Amend 150 Issued to License DPR-3.Index Page Corrected ML20202H5811999-02-0303 February 1999 Amend 150 to License DPR-3,revising Possession Only License Through Three Changes to TS ML20155A2491998-10-15015 October 1998 Application for Amend to License DPR-3,changing Defueled TS 1.6,page 1-2 & 3/4.4,page 3/4-6 to Revise Title of Radioactive Effluent Release Rept from Semiannual to Annual ML20237E3571998-08-20020 August 1998 Application for Amend to License DPR-3,removing Definition of Site Boundary Contained in Subsection 1.10 of Definitions & Modifying Subsection 5.1 of Design Features ML20249A7891998-06-17017 June 1998 Amend 149 to License DPR-3,revising TS Sections Re Min Water Cover Over Spent Fuel,Crane Travel Over Spent Fuel & Related Bases ML20237F1591998-02-19019 February 1998 Amend 147 to License DPR-3,deleting Main Coolant Sys Water Chemistry Limits & Surveillance,Secondary Water Chemistry Monitoring Program & Requirements for Oxygen Monitoring of Waste Gas Holdup Sys ML20197B0831997-12-18018 December 1997 Application for Amend to License DPR-3,to Approve License Termination Plan to Modify License to Incorporate New License Condition 2.C.11 as Listed ML20216E1721997-09-0505 September 1997 Application for Amend to License DPR-3,modifying Defueled TS 3.1.3 to Allow Util to Continue W/Implementation of Ynps Decommissioning Plan Which Has Been Incorporated Into Ynps FSAR ML20059E4261993-10-28028 October 1993 Certificate of Compliance 9256,Rev 0,for Model Ynps SG Package ML20126E7461992-12-21021 December 1992 Application for Amend to License DPR-3,consisting of Proposed Change 259 to Modify Pages 3 & 4 of License & TS to Reflect Permanently Shutdown & Defueled Status.Page 3 of License Re Defueled Security Plan ML20058C4011990-10-22022 October 1990 Amend 137 to License DPR-3,modifying Page 3/4 1-27, Surveillance Requirement 4.1.3.4.a,to Delete Ref to Control Rod Group a as Control Group ML20059M0561990-09-26026 September 1990 Corrected Pages to Amend 136 to License DPR-3 ML20059G2371990-09-0606 September 1990 Amend 135 to License DPR-3,modifying Tech Spec Surveillance Requirement 4.5.2a to Change ECCS Pump Surveillance Frequency from Monthly to Quarterly & to Remove Min Required Discharge Pressures from Tech Spec ML20058L0281990-08-0202 August 1990 Amend 133 to License DPR-3,incorporating Wording from Std Westinghouse Tech Specs Into Util Limiting Condition for Operation Specs 3.10.3 & 3.10.4 ML20058L6611990-08-0202 August 1990 Amend 134 to License DPR-3,incorporating NRC Guidance in Generic Ltr 88-17 Into Facility Tech Specs & Adding Three New Tech Specs Specifying Plant Conditions & Equipment Operability Requirements to Prevent Core Uncovery ML20055D3991990-06-25025 June 1990 Application for Amend to License DPR-3,deleting Redundant Gallons Values for Safety Injection Tank (SIT) from Tech Specs & Revising Section 3/4.5.4 to Show That SIT Increased to 52,000 Gallons ML20055C8581990-06-18018 June 1990 Amend 132 to License DPR-3,changing Title of Technical Svc Supervisor,Establishing New Positions Entitled Maint Support Supervisor & Operations Support Supervisor & Increasing Number of Senior Reactor Operators on Shift to Two ML20247L3481989-09-14014 September 1989 Application for Amend to License DPR-3,eliminating cycle-specific Operating Limits from Tech Specs & Including Operating Limits in Core Operating Limits Rept,Per Generic Ltr 88-16 ML20247F1231989-09-0707 September 1989 Amend 124 to License DPR-3,moving Onsite & Facility Organizational Charts from Section 6.0 of Tech Specs to Section 401 of FSAR ML20247E6681989-08-31031 August 1989 Amend 123 to License DPR-3,removing Description of High Pressurizer Water Level in Section 2 Re Bases of Tech Specs on Page B2-4 ML20246M0261989-08-31031 August 1989 Application for Amend to License DPR-3,revising Tech Specs to Incorporate Main Steam Line Monitors & Primary Vent Stack Noble Gas Monitor,Per NUREG-0737,Item II.F.1-1. Proposed Change Synopsis Encl ML20247M5291989-07-24024 July 1989 Application for Amend to License DPR-3,modifying Tech Spec 3.2.4,Table 3.2-1 to Substitute Limit on Operating Loop Average Temp for Current Limit on Cold Leg Temp ML20246L9031989-07-12012 July 1989 Application for Amend to License DPR-3,modifying Tech Spec Page 3/4 3-19,Table 3.3-4 & Page 3/4 3-21,Table 4.3-3 to Incorporate Main Steam Line Monitors & Primary Vent Stack Noble Gas Monitor,Per NUREG-0737,Item II.F.1-1.Fee Paid ML20244D3801989-04-14014 April 1989 Application for Amend to License DPR-3,consisting of Proposed Change 209,changing Tech Specs Re Control Room Emergency Air Cleaning Sys.Change Proposed to Reflect Compliance W/Tmi Item III-D.3.4 ML20246P0721989-03-21021 March 1989 Application for Amend to License DPR-3,adding Snubber DRH-SNB-1 to Table 3.7-4 of Tech Spec 3.7.9 ML20195D6651988-11-0101 November 1988 Amend 120 to License DPR-3,enabling Piping Mods Needed to Allow for Installation of Water Cleanup Sys ML20205G1661988-10-25025 October 1988 Amend 119 to License DPR-3,permitting Increase in Nitrogen Pressure in Safety Injection Accumulator Tech Spec ML20205L1631988-10-21021 October 1988 Application for Amend to License DPR-3,removing High Pressurizer Water Level Trip Instrumentation from Tech Spec Tables 3.3-1,4.3-1 & Section 2 Bases & Modifying Description of Main Coolant Sys High Pressure.Fee Paid ML20204G4641988-10-17017 October 1988 Amend 118 to License DPR-3,revising Tech Specs Re Specific Values of Boron Concentration ML20205C3961988-10-14014 October 1988 Amend 117 to License DPR-3,changing Tech Specs by Adding Four Isolation Valves,In Two Spare Penetrations,To Table 3.6-1, Containment Barriers ML20195C9941988-10-12012 October 1988 Corrected Page 2 to Amend 116 to License DPR-3 ML20207L6891988-10-12012 October 1988 Amend 116 to License DPR-3,permitting Mods to nonsafety-class Portions of Neutron Shield Tank Cavity Leakage Collection Piping ML20151Z1751988-08-11011 August 1988 Application for Amend to License DPR-3,modifying Tech Specs to Remove Ref to Specific Value of 2,200 Ppm & Provide Generalized Boron Concentration Value & Remove Requirement for Inverse Count Rate Multiplication Measurement.Fee Paid ML20207E8101988-08-0505 August 1988 Amend 115 to License DPR-03 Re Changes in Physical Security Plan ML20151M4861988-07-29029 July 1988 Amend 114 to License DPR-3,making Battery Charger Surveillance Requirements in Tech Specs Same for All Three Battery Chargers ML20151K3691988-07-25025 July 1988 Amend 113 to License DPR-3,revising Tech Specs to Permit Loads Greater than 900 Lbs to Travel Over Plant Fuel Pit to Enable Removal of Control Rods from Spent Fuel Pit ML20151K8531988-07-19019 July 1988 Amend 112 to License DPR-3,revising Shutdown Margin Switching Temp to 470 F & Correcting Typo & Inadvertent Omission of Previously Approved Surveillance Requirement ML20196K2471988-06-28028 June 1988 Amend 111 to License DPR-3,removing Requirement for Plant Operations Manager to Maintain Senior Reactor Operator License from Tech Specs ML20196K7281988-06-27027 June 1988 Application for Amend to License DPR-3,modifying Tech Spec Table 3.6.1, Containment Barriers to Delete Valve VD-V-752 & Tech Spec 3.4.5.1, Main Coolant Leakage Detection Sys, to Add Requirements for Level Switch.Fee Paid ML20196K1041988-06-27027 June 1988 Application for Amend to License DPR-3,adding Tech Spec Section C.2 Re Check Valves to Table 3.6-1,containing Check Valve WC-V-622 & Manual Isolation Valves WC-V-621,VD-V-1170 & VD-V-1171 to Section B.1 of Table 3.6-1.Fee Paid ML20150B0311988-06-27027 June 1988 Application for Amend to License DPR-3,changing Tech Specs to Allow for Installation of Two Piping Mods Necessary for Installation of Enhanced Water Cleanup Sys.Fee Paid ML20196J2611988-06-27027 June 1988 Application for Amend to License DPR-3,increasing Nitrogen Supply Pressure to Safety Injection Accumulator from 473 to 488 Pounds Per Square Inch Gauge.Fee Paid ML20195K1401988-06-17017 June 1988 Amend 110 to License DPR-3,revising Tech Specs Re Control Rod Position Indication & Correcting Minor Error in Tech Specs 1999-08-27
[Table view] |
Text
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t UNITED STATES l 2
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20666 0001
- * * * * ,o YANKEE ATOMIC ELECTRIC COMPANY ,
1 DOCKET NO.50-029 YANKEE NUCLEAR POWER STATION .
I AMENDMENT TO POSSESSION ONLY LICENSE
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Amendment No.151 License No. DPR-3
- 1. The U. S. Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A. The application for amendment filed by Yankee Atomic Electric Company (the licensee) dated October 15,1998, 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; B. The facility will be maintained in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance: (i) 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 Commission's i regulations set forth in 10 CFR Chapter I; j l
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 tha Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment. Paragraph 2.C.(2) of Possession .
1 Only' License No. DPR-3 is hereby amended to read as follows:
(2) Technical Specificatio_n_s {
The Technical Specifications contained in Appendix A, as revised through l Amendment No.151, are hereby incorporated in the license. The licensee shall possess and maintain the facility in accordance with the Technical Specifications.
I 9903110356 990305 PDR ADOCK 05000029 :
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' 3. This license amendment will be effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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i Marvin M. Mendonca, Acting Director Non-Power Reactors and Decommissioning Project Directorate Division of Regulatory improvement Programs Office of Nuclear Reactor Regulation >
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Attachment:
Appendix A Technical Specification Changes Date of issuance: March 5, 1999
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l l ATTACHMENT TO LICENSE AMENDMENT NO.151 ,
POSSESSION ONLY LICENSE NO. DPR-3 l DOCKET NO. 50-29 i
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Replace the following pages of the Appendix A Technical Specifications with the attached '
revised pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change. 1 l
l Remove insert 1-2 1-2 3/4-6 3/4-6 6-17 6-17 i 6-22 6-22 1
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1.0 DEFINITIONS (Continued) 0FF-SITE 00SF CALCULATION MANUAL (0DCM)
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1.6 The 0FF-SITE DOSE CALCULATION MANUAL (00CM) contains the methodology and parameters used.in the calculation of off-site doses resulting ]
from radioactive gaseous and liquid effluents. in the calculation of' !
gaseous and liquid effluent monitoring alarm / trip setpoints, and in ,
the. conduct of the Environmental Radiological Monitoring Program. l The ODCM also contains (1) the Radioactive Effluent Controls and 1 Radiological Environmental Monitoring Programs required by Section 61.8. and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and l Annual Radioactive Effluent Re' ease Reports required by Specifications 6.8 2.a and 6.8.2.b.
OPERABLE OPERABILITY l
1.7 A system., subsystem. train, componen+ or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function (s). Implicit in this definition shall be the j assumption that all necessary attendant instrumentation, controls, electric power cooling or seal water, lubrication or other I auxillary equipment that are required for the system subsystem.
train. component or device to perform its safety function (s) are also capable of performing their necessary support function (s).
PROCESS CONTROL PROGRAM (PCF) 1.8 The PROCESS CONTROL PROGRAM contains the current formulas. sampling, analyses, test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as tu assure compliance with 10 CFR Parts 20. 61, and 71. state regulations, burial ground requirements.
and other requirements, governing tne disposal of solid radioactive waste.
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_EPORTABlf EVENT 1.9 A REPORTABLE EVENT shall be any of those conditions specified in 10 CFR 50.73.
l YANKEE-ROWE 1-2 Amendment No. 151 i
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3/4.4 L10VID HOLD-UP TANKS LIMITING CONDITION FOR OPERATION 3.4 The quantity of radioactive material contained in any outside tank that is not .urrounded by liners. dikes or walls capable of holding the tank contents. or that does not have a tank overflow connected to the liquid radwaste treatment system. shall be limited to less than or equal to 10 curies, excluding tritium and
' dissolved or entrained noble gases.
APPL lC AB il lT Y : At all times.
ACTION:
With the quantity of radioactive material in any outside tank exceeding the above limit. without delay, take action to suspend all additions of radioactive material to the tank. Within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit and describe j the events leading to this condition in the next Annual Radioactive Effluent Release Report. pursuant to Specification 6.8.2.b.
SURVEILLANCE REQUIREMENTS 4.4.1 The quantity of radioactive material contained in any outside tank that is not surrounded by liners.. dikes, or walls capable of holding the tank contents shall be determined to be within the above limit by analy21ng a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.
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YANKEE-ROWE 3/4-6 Amendment No. 151 l
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6.0 ADMINISTRATIVE CONTROLS (Continued)
? l The dose assignment to various duty functions may be estimates based on pocket dosimeter. TLD. or film badge measurements. l Small exposures totalling less than 20% of the individual '!
total dose need not be accounted for in the aggregate, at !
least 80% of the whole body dose received from external )
sources shall be assigned to specific major work functions.
- b. Any'other unit-unique reports required on an annual basis.
1 6.8.2 linique Report ing Roouirements
- a. Environmental Radiological Monitoring The Annual Radiological Environmental Operating Report j covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year. The report shall include sunaaries. l interpretations. and analysis of trends of the results l of the Radiological Environmental Monitoring Program for l the reporting period. The material provided shall be consistent with the objectives outlined in (1) the ODCM. q and (2) Sections IV B.2. IV.B.3. and IV.C of Appendix I I to 10 CFR 50.
j b Annual Radioactive Effluent Release Report l The Annual Radioactive Effluent Release Report covering l the operation of the unit during the previous calendar ,
l year shall be submitted before May 1 of each year. The I report shall include a summary of the quantities of radioactive 14 quid and gaseous effluents and solid waste released fram 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 1 to 10 CFR 50.
6.8.3 Special Reports Special reports shall be submitted pursuant to 10 CFR 50.4 within the time period specified for each report. These reports shall be submitted Covering the
- activitles identified below pursuant to the requirements of l the applicable reference specification
- j YANKEE-ROWE 6-17 Amendment No. 151 l
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6.0 ADMINISTRATIVE CONTROLS (Continued) ;
6 13 -0FF-SITE DOSE Ct.LCUlATION MANUAL (0DCM) !
6;13.1 Changes to the ODCM:
- a. Shall be documented a.1d records of reviews performed l shall be' retained as required by Specification 6.9.2.0.
This documentation shall contain:
- 1) Sufficient information to support the change together with the appropriate analyses or l evaluation justifying the change (s). and .l
- 2) A determination that the change will maintain the ;
level of the radioactive effluent control required I by 10 CFR 20.106. 40 CFR 190. 10 CFR 50.36a, and )
Appendix I to 10 CFR 50 and not adversely impact i the accuracy or reliability of effluent, dose, or j setpoint calculations. !
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!. b. Shall become effective after review and acceptance by the PORC~and the approvci of the Plant Superintendent.
- c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM 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 ODCM was made. Each change shall be identified by markings in the margin of the affected pages. clearly indicati.ig the area of the page that was changed. and shall indicate the date (e.g., month / year) l the change'was implemanted.
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I YANKEE.ROWE- 6-22 Amendsent No. 151