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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20206B9211999-04-23023 April 1999 Proposed Defueled Tech Specs Stating That Characterization of Revised Review & Audit Function Remain in Plant TS Rather than Be Transferred to Plant QA Plan ML20205N1821999-03-24024 March 1999 Proposed Tech Specs Deleting Condition 2.C(10) from Plant License ML20204E5701999-03-17017 March 1999 Proposed Tech Specs,Removing Section 6.7, Procedures & Programs & Section 6.9, Record Retention, from TS & Transferring to Yankee Decommissioning QA Program ML20204E5241999-03-17017 March 1999 Revised Tech Specs,Consolidating Mgt Positions & Transferring Review & Audit Functions to Yankee Decommissioning QA Program ML20204D9031999-03-17017 March 1999 Proposed Tech Specs Section 6.2.2,deleting Overtime Restrictions Currently Incorporated in Ynps TS ML20155A2561998-10-15015 October 1998 Proposed Defueled Tech Specs Re Required Frequency of Submittal of Radioactive Effluent Release Rept ML20237E3631998-08-20020 August 1998 Proposed Tech Specs,Removing Definition of Site Boundary from Subsection 1.10 of Definitions & Modifying Subsection 5.1 of Design Features ML20216E2101997-09-0505 September 1997 Proposed Tech Specs,Modifying Defueled TS 3.1.3 to Allow Util to Continue W/Implementation of Ynps Decommissioning Plan Which Has Been Incorporated Into Ynps FSAR ML20126E7601992-12-21021 December 1992 Permanently Defueled Tech Specs ML20055D4031990-06-25025 June 1990 Proposed Tech Specs Re Changes in Safety Injection Tank Min Water Inventory ML20247L3581989-09-14014 September 1989 Proposed Tech Specs Re Limiting Condition for Operation & Surveillance Requirements for Control Rod Insertion Limits, Boron Control,Peak LHGR & Xenon Redistribution Multiplier ML20246M0541989-08-31031 August 1989 Proposed Tech Specs,Modifying Pages 3/4 3-19,Table 3.3-4 & 3/4 3-21,Table 4.3-3,to Add Steam Line Monitors & Primary Vent Stack Noble Gas Monitor to Listing of Radiation Monitoring Instrumentation & Surveillance Requirements ML20247M6321989-07-24024 July 1989 Proposed Tech Specs Re Power Distribution Limits ML20246M0221989-07-12012 July 1989 Proposed Tech Spec Tables 3.3-4, Radiation Monitoring Instrumentation & 4.3-3, Radiation Monitoring Instrumentation Surveillance Requirements ML20244D3841989-04-14014 April 1989 Proposed Tech Specs Re Steam Generator Pressure/Temp Limits, Primary Pump Seal Water Sys,Control Room Emergency Air Cleaning Sys & Sealed Source Contamination ML20246P1401989-03-21021 March 1989 Proposed Tech Specs Adding Snubber DRH-SNB-1 to Table 3.7-4 ML20196B0771988-11-22022 November 1988 Tech Spec Page 3/4 3-2 Inadvertently Omitted from Util 881021 Proposed Change 222 to Tech Specs ML20205L1691988-10-21021 October 1988 Proposed Tech Specs,Removing Description of High Pressurizer Water Level & Modifying Description of Main Coolant Sys High Pressure ML20151Z1871988-08-11011 August 1988 Proposed Tech Spec Changes to Remove Ref to Specific Value of 2,200 Ppm & Provide Generalized Boron Concentration Value & Remove Requirement for Inverse Count Rate Multiplication Measurement After Insertion of Each Five Fuel Assemblies ML20150B0371988-06-27027 June 1988 Proposed Tech Specs,Allowing Installation of Two Piping Mods Necessary for Installation of Enhanced Water Cleanup Sys ML20196K7361988-06-27027 June 1988 Proposed Tech Spec Table 3.6.1, Containment Barriers, Deleting Valve VD-V-752 & Tech Spec 3.4.5.1, Main Coolant Leakage Detection Sys, Adding Operability,Action & Surveillance Requirements for Telltale Level Switch ML20196K1391988-06-27027 June 1988 Proposed Tech Specs Table 3.6-1 ML20196J2831988-06-27027 June 1988 Proposed Tech Specs 3.5.1.e,increasing Nitrogen Supply Pressure to Safety Injection Accumulator to 488 Pounds Per Square Inch Gauge ML20154J5991988-05-19019 May 1988 Proposed Tech Spec 4.9.7.2, Spent Fuel Pit ML20148Q8911988-04-0404 April 1988 Proposed Tech Specs Defining Incore Detection Sys as Combination Sys of Both Fixed & Movable Detectors & Associated Equipment ML20151D0671988-04-0404 April 1988 Proposed Tech Spec Page 3/4 8-10 Re Battery Chargers ML20150E2381988-03-25025 March 1988 Proposed Tech Specs Modifying Containment Isolation Barriers ML20148J2991988-03-25025 March 1988 Proposed Tech Spec Table 3.3-2, ESF Instrumentation & Table 4.3-2, ESF Instrumentation Surveillance Requirements, Reflecting Deleted Modes 5(1) & 5*, Respectively ML20148J2701988-03-23023 March 1988 Proposed Tech Spec 3.1.1.1.2,reflecting Change in Shutdown Margin Switching Temp from 490 to 470 F ML20150C0171988-03-11011 March 1988 Proposed Tech Specs Modifying Section 6.2 & Moving Organization Charts (Figures 6.2-1 & 6.2-2) to Section 501 of FSAR ML20148K1671988-01-15015 January 1988 Proposed Tech Specs,Adding Shipping Cask Liners,Vol Reduction Equipment,Shipping Casks Not for Spent Fuel & Spent Fuel Assembly Nondestructive Test Equipment to Tech Spec 3.9.7 ML20149E8871988-01-0505 January 1988 Proposed Tech Specs,Modifying Tables 3.3-2,3.3-3 & 4.3-2 to Require 18-month Functional Test of First Level Undervoltage Protection for Each of Three 480-volt Emergency Buses ML20149E7271988-01-0505 January 1988 Proposed Tech Spec Figure 6.2.2, Facility Organization, Reflecting Elevated Mgt Concerns Re Security ML20210A5041987-01-29029 January 1987 Proposed Tech Specs Re Extension of Cycle 18 in-core Instrumentation Sys to Cycle 19 ML20213A4431987-01-22022 January 1987 Proposed Tech Specs,Providing Flexibility in Areas Governing Integrity Testing of Steam Generator Tubes ML20215N6281986-10-22022 October 1986 Proposed Tech Spec 4.5.2.b.4,increasing Allowable Open Time for LPSI Min Recirculation Line Valve CS-MOV-532 to 120 Minutes Per Wk ML20197A7611986-10-20020 October 1986 Proposed Tech Specs,Allowing for Performance of 10CFR50.59 Reviews for Future Core Reloads ML20211E8091986-10-0909 October 1986 Proposed Tech Spec Table 4.3-1, Reactor Protective Sys Instrumentation Surveillance Requirements ML20204F7191986-07-31031 July 1986 Proposed Changes to Tech Specs 3.3.3.2,4.2.1.2,4.2.2.1, 4.2.2.2 & 4.2.3.2 Re Operation of in-core Instrumentation Sys ML20211K7501986-06-24024 June 1986 Proposed Changes to Tech Specs to Allow Performance of 10CFR50.59 Reviews for Future Core Reloads ML20151U5571986-02-0505 February 1986 Proposed Tech Specs,Per Generic Ltr 84-43, Reporting Requirements of 10CFR50... & Generic Ltr 85-19, Reporting Requirements on Primary Coolant Iodine Spikes & Supporting LER Sys Mods ML20136J3981986-01-0808 January 1986 Proposed Changes to Tech Spec Table 3.6-1,replacing Manual Containment Isolation Valve W/Blank Flange ML20141G3461986-01-0606 January 1986 Proposed Tech Spec Changes,Permitting Filing of Supplemental Dose & Meteorological Summary Rept within 150 Days of Jan 1 Each Yr ML20138N3131985-10-31031 October 1985 Proposed Tech Spec Changes Per NUREG-0737,Item II.F.1.6, Containment Hydrogen Monitors ML20133K5061985-10-16016 October 1985 Proposed Tech Spec Table 4.3-2, Engineered Sys Instrumentation Surveillance Requirements, Requiring Monthly Functional Test of New Second Level Degraded Grid Voltage Protection for Each 480-volt Emergency Bus ML20133K2041985-10-15015 October 1985 Proposed Tech Specs,Reflecting Mods to RCS Vent Sys Valve Power Supplies ML20133K4491985-10-15015 October 1985 Proposed Tech Spec Table 3.6-1,adding Two Containment Isolation Valves for Compliance W/Tech Spec 3/4.6.2 Which Requires Type C Tests for Valves ML20133J8001985-10-15015 October 1985 Proposed Tech Spec Changes,Revising Table 3.3-4, Radiation Monitoring Instrumentation, Table 4.3-3, Radiation Monitoring Instrumentation Surveillance Requirements & Tech Spec 3.3.3.2, Instrumentation-In-Core Detection Sys ML20133C5801985-09-30030 September 1985 Proposed Tech Specs Re Radiological Environ Monitoring ML20133C3211985-09-30030 September 1985 Proposed Changes to Tech Spec 2.2.1 & Tables 2.2-1,3.3.2 & 3.3-3,increasing Required Setpoint for Main Steam Line Isolation Trip from 200 Psig to 262.5 Psig 1999-04-23
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20206B9211999-04-23023 April 1999 Proposed Defueled Tech Specs Stating That Characterization of Revised Review & Audit Function Remain in Plant TS Rather than Be Transferred to Plant QA Plan ML20205N1821999-03-24024 March 1999 Proposed Tech Specs Deleting Condition 2.C(10) from Plant License ML20204D9031999-03-17017 March 1999 Proposed Tech Specs Section 6.2.2,deleting Overtime Restrictions Currently Incorporated in Ynps TS ML20204E5241999-03-17017 March 1999 Revised Tech Specs,Consolidating Mgt Positions & Transferring Review & Audit Functions to Yankee Decommissioning QA Program ML20204E5701999-03-17017 March 1999 Proposed Tech Specs,Removing Section 6.7, Procedures & Programs & Section 6.9, Record Retention, from TS & Transferring to Yankee Decommissioning QA Program ML20155A2561998-10-15015 October 1998 Proposed Defueled Tech Specs Re Required Frequency of Submittal of Radioactive Effluent Release Rept ML20237E3631998-08-20020 August 1998 Proposed Tech Specs,Removing Definition of Site Boundary from Subsection 1.10 of Definitions & Modifying Subsection 5.1 of Design Features ML20197D4341997-12-31031 December 1997 Rev 1 to Ynps License Termination Plan ML20216E2101997-09-0505 September 1997 Proposed Tech Specs,Modifying Defueled TS 3.1.3 to Allow Util to Continue W/Implementation of Ynps Decommissioning Plan Which Has Been Incorporated Into Ynps FSAR ML20141F6391997-05-15015 May 1997 License Termination Plan for Yankee Nuclear Power Station ML20198G6381997-02-0707 February 1997 Rev 12 to Ynps Off-Site Dose Calculation Manual ML20138Q5301996-10-31031 October 1996 Rev 11 to Off-Site Dose Calculation Manual ML20198S6131993-12-31031 December 1993 Partially Deleted Rev 9 to Edcr 93-303, Vessel Internals Segmentation Component Removal Program 1995 ML20198S5681993-08-0202 August 1993 Partially Deleted Rev 6 to Edcr 93-303, Reactor Vessel Internals Segmentation Component Removal Program 1993 ML20126E7601992-12-21021 December 1992 Permanently Defueled Tech Specs ML20058D8451990-10-29029 October 1990 Separate Rept Re Local Leak Rate Test Results from Core 19/20 Refueling Outage ML20058D8421990-06-30030 June 1990 June 1990 Reactor Containment Bldg Integrated Leak Rate Test & Periodic Local Leak Rate Tests ML20055D4031990-06-25025 June 1990 Proposed Tech Specs Re Changes in Safety Injection Tank Min Water Inventory ML20247L3581989-09-14014 September 1989 Proposed Tech Specs Re Limiting Condition for Operation & Surveillance Requirements for Control Rod Insertion Limits, Boron Control,Peak LHGR & Xenon Redistribution Multiplier ML20246M0541989-08-31031 August 1989 Proposed Tech Specs,Modifying Pages 3/4 3-19,Table 3.3-4 & 3/4 3-21,Table 4.3-3,to Add Steam Line Monitors & Primary Vent Stack Noble Gas Monitor to Listing of Radiation Monitoring Instrumentation & Surveillance Requirements ML20247M6321989-07-24024 July 1989 Proposed Tech Specs Re Power Distribution Limits ML20246M0221989-07-12012 July 1989 Proposed Tech Spec Tables 3.3-4, Radiation Monitoring Instrumentation & 4.3-3, Radiation Monitoring Instrumentation Surveillance Requirements ML20244D3841989-04-14014 April 1989 Proposed Tech Specs Re Steam Generator Pressure/Temp Limits, Primary Pump Seal Water Sys,Control Room Emergency Air Cleaning Sys & Sealed Source Contamination ML20244D3931989-04-11011 April 1989 Core 20 Startup Program for Yankee Nuclear Power Station ML20246P1401989-03-21021 March 1989 Proposed Tech Specs Adding Snubber DRH-SNB-1 to Table 3.7-4 ML20196B0771988-11-22022 November 1988 Tech Spec Page 3/4 3-2 Inadvertently Omitted from Util 881021 Proposed Change 222 to Tech Specs ML20205L1691988-10-21021 October 1988 Proposed Tech Specs,Removing Description of High Pressurizer Water Level & Modifying Description of Main Coolant Sys High Pressure ML20151Z1871988-08-11011 August 1988 Proposed Tech Spec Changes to Remove Ref to Specific Value of 2,200 Ppm & Provide Generalized Boron Concentration Value & Remove Requirement for Inverse Count Rate Multiplication Measurement After Insertion of Each Five Fuel Assemblies ML20196K1391988-06-27027 June 1988 Proposed Tech Specs Table 3.6-1 ML20150B0371988-06-27027 June 1988 Proposed Tech Specs,Allowing Installation of Two Piping Mods Necessary for Installation of Enhanced Water Cleanup Sys ML20196K7361988-06-27027 June 1988 Proposed Tech Spec Table 3.6.1, Containment Barriers, Deleting Valve VD-V-752 & Tech Spec 3.4.5.1, Main Coolant Leakage Detection Sys, Adding Operability,Action & Surveillance Requirements for Telltale Level Switch ML20196J2831988-06-27027 June 1988 Proposed Tech Specs 3.5.1.e,increasing Nitrogen Supply Pressure to Safety Injection Accumulator to 488 Pounds Per Square Inch Gauge ML20154J5991988-05-19019 May 1988 Proposed Tech Spec 4.9.7.2, Spent Fuel Pit ML20148Q8911988-04-0404 April 1988 Proposed Tech Specs Defining Incore Detection Sys as Combination Sys of Both Fixed & Movable Detectors & Associated Equipment ML20151D0671988-04-0404 April 1988 Proposed Tech Spec Page 3/4 8-10 Re Battery Chargers ML20148Q4681988-03-31031 March 1988 Rev 2 to Guidance for Development of Simulation Facility to Meet Requirements of 10CFR55.45 ML20150E2381988-03-25025 March 1988 Proposed Tech Specs Modifying Containment Isolation Barriers ML20148J2991988-03-25025 March 1988 Proposed Tech Spec Table 3.3-2, ESF Instrumentation & Table 4.3-2, ESF Instrumentation Surveillance Requirements, Reflecting Deleted Modes 5(1) & 5*, Respectively ML20148J2701988-03-23023 March 1988 Proposed Tech Spec 3.1.1.1.2,reflecting Change in Shutdown Margin Switching Temp from 490 to 470 F ML20150C0171988-03-11011 March 1988 Proposed Tech Specs Modifying Section 6.2 & Moving Organization Charts (Figures 6.2-1 & 6.2-2) to Section 501 of FSAR ML20154L9791988-03-0606 March 1988 Rev 6 to Yankee Nuclear Power Station Offsite Dose Calculation Manual ML20148K1671988-01-15015 January 1988 Proposed Tech Specs,Adding Shipping Cask Liners,Vol Reduction Equipment,Shipping Casks Not for Spent Fuel & Spent Fuel Assembly Nondestructive Test Equipment to Tech Spec 3.9.7 ML20149E8871988-01-0505 January 1988 Proposed Tech Specs,Modifying Tables 3.3-2,3.3-3 & 4.3-2 to Require 18-month Functional Test of First Level Undervoltage Protection for Each of Three 480-volt Emergency Buses ML20149E7271988-01-0505 January 1988 Proposed Tech Spec Figure 6.2.2, Facility Organization, Reflecting Elevated Mgt Concerns Re Security ML20235Q7771987-09-30030 September 1987 Core Xix Startup Program for Yankee Nuclear Power Station ML20237C7631987-06-30030 June 1987 Reactor Containment Bldg Integrated Leak Rate Test ML20237C7911987-05-31031 May 1987 Separate Accompanying Summary Rept of Type B & C Results.. ML20210B5551987-04-20020 April 1987 Rev 4 to Procedure DC-1, Seismic Reevaluation & Retrofit Criteria ML20206D3741987-03-31031 March 1987 Yankee Nuclear Power Station Graded Exercise,Exercise Manual ML20210A5041987-01-29029 January 1987 Proposed Tech Specs Re Extension of Cycle 18 in-core Instrumentation Sys to Cycle 19 1999-04-23
[Table view] |
Text
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ATTACHMENT A Revised Technical Soecifications Pages Annotated Version 1-2 3/4-6 6-17 6-22
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1.0 DEFINITIONS (Continued) 0FF-SITE DOSE CALCULATION MANUAL (00CM) 1.6 The OFF-SITE DOSE CALCULATION MANUAL (00CM) contains the methodology and parameters used in the calculation of off-site doses resulting l 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.
The ODCM also contains (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 61.8. and (2) descriptions of the information that should be l l
included in the Annual Radiological Environmental Operating and l l Sem4 annual Annual Radioactive Effluent Release Reports required by '
Specifications 6.8.2.a and 6.8.2.b.
OPERABLE - OPERABILITY 1.7 A system, subsystem, train, component 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 assumption that all necessary attendant instrumentation, controls, electric power. cooling or seal water, lubrication or other auxiliary 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 (PCP) i 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 to assure compliance with 10 CFR Parts 20. 61 and 71 state regulations, burial ground requirements.
and other requirements. governing the disposal of solid radioactive waste.
REPORTABLE EVENT 1.9 A REPORTABLE EVENT shall be any of those conditions specified in 10 CFR 50.73.
SITE BOUNDARY 1.10 The SITE BOUNDARY shall be that line beyond defining an area within which the land is not owned, leased, or otherwise controlled by the licensee. Any area within the SITE BOUNDARY used for residential i
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'3/4.4 LIQUID HOLD-UP TANKS LIMITING CONDITION FOR OPERATION 3.4 The quantity of radioactive material contained in any outside i tank that is not surrounded 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 l limited to less than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases.
APPLICABILITY: At all times.
1 ACTION:
With the quantity of radioactive mater 1.1 in any outside tank exceeding the above limit, without delay, take action to suspend all additions of radioactive material to the tasik. 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 io within the limit and describe l the events leading to this condition in the next Sem4 annual 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 analyzing 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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YAtlKEE-ROWE 3/4-6
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'6.0 ADMINISTRATIVE CONTR01S (Continued)
The dose assignment to various duty functions may be estimates based on pocket dosimeter. TLD. or film badge measurements.
Small exposures totalling less than 23% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the whole body dose received from external l sources shall be assigned to specific major work functions. l
- b. Any other unit-unique reports required on an annual basis. ,
6.8.2 Unique Reporting Requirements
- a. Environmental Radiological Monitoring The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year. The report shall include summaries, interpretations. and analysis of trends of the results of the Radiological Environmental Monitoring Progrdm for the reporting period. The material provided shall be consistent with the objectives outlined in (1) the ODCM.
and (2) Sections IV.B.2. IV.B.3. and IV.C of Appendix 1 to 10 CFR 50.
l b. Sem4 annual Annual Radioactive Effluent Release Report l The Sem4 annual Annual Radioactive Effluent Release Report covering the operation of the unit during the l previous s4x-months-of-eperat4en calendar year shall be j submitted w4th4n-60-days-after-January-1-and-July-1 l before May 1 of each year. The report shall include a summary of the quantitles of radioactive liquid and gaseous ef fluents and solid waste released f rom the unit. The material provided shall be (1) consistent ,
with the objectives outlined in the ODCM and PCP. and l (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I 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 activities identified below pursuant to the requirements of the applicable reference specification:
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(ANKEE-ROWE 6-17
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l 6.0 ADMINISTRATIVE CONTROLS (Continued) l 6.13 0FF-SITE DOSE CALCULATION MANUAL (0DCM) 6.13.1 Changes to the ODCH:
- a. Shall be documented and records of reviews performed 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 evaluation justifying the change (s), and
- 2) A determination that the change will maintain the level of the radioactive ef fluent control required by 10 CFR 20.106. 40 CFR 190. 10 CFR 50.36a and Appendix I to 10 CFR 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
- b. Shall become effective after review and acceptance by the PORC and the approval 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 l or concurrent with the Sem4 annual Annual Radioactive '
Ef fluent Release Report for the period of the report in which any change to the ODCH was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g.
month / year) the change was implemented.
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ATTACHMENT B Revised Technical SocciHeations Paces l
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l-2 3/4-6 i 6-17 6-22 i
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1 1.0 DEFINITIONS (Continued) 0FF-SITE DOSE CALCULATION MANUAL (ODCM) 1.6 The OFF-SITE DOSE CALCULATION MANUAL (ODCM) 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 ef fluent monitoring alarm / trip setpoints, and in the conduct of the Environmental Radiological Monitoring Program.
The 00CM also contains (1) the Radioactive Effluent Controls and l
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 Release Reports required by Specifications 6.8.7.a and 6.8.2.b.
OPERABLE - OPERABILITY 1.7 A system. subsystem train, component 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 assumption that all necessary attendant instrumentation, controls, electric power. cooling or seal water. lubrication or other auxiliary 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 (PCP) 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 to assure compliance with 10 CFR Parts 20. 61 and 71. state regulations, burial ground requirements, and other requirements, governing the disposal of solid radioactive waste.
REPORTABLE EVEN1 1.9 A REPORTABLE EVENT shall be any of those conditions specified in 10 CFR 50.73.
l SITE BOUNDARY 1.10 The SITE BOUNDARY shall be that line defining an area within which the land is owned. leased or otherwise controlled by the licensee.
Any area within the clTE BOUNDARY used for residential quarters or I
YANKEE-ROWE l-?
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3/4.4 LIQUID HOLD-UP TANKS LIMITING CONDITION FOR OPERATION 3.4 The quantity of radioactive material contained in any outside i tank that is not surrounded by liners, dikes or walls capable of l holding the tank contents. or that does not have a tank overflow l
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.
APPLICABILITY: At all times.
l 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 l 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 l l l the events leading to this condition in the next Annual Radioactive Effluent Release Report, pursuant to Specification 6.8.2.b.
i SURVEILLANCE REQUIREMENTS m_
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 analyzing 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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4 YANKEE-ROWE 3/4 6
6.0 ADMINISTRATIVE CONTROLS (Continued)
The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements.
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 l sources shall be assigned to specific major work functions. I
- b. Any other unit unique reports required on an annual basis.
6.8.2 Uniaue Reporting Reauirements
- a. Environmental Radiological Monitoring The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in (1) the ODCM, and (2) Sections IV.B.2, IV,B,3, and IV.C of Appendix I to 10 CFR 50.
I b. Annual Radioactive Ef fluent Release Report i The Annual Radioactive Effluent Release Report covering I the operation of the unit during the previous calendar l 1 year shall be submitted before May 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP, and (2) in conformance with 10 CFR 50.36a and Section IV.3.1 of Appendix I 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 activities identified below pursuant to the requirements of the applicable reference specification:
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6.0 ADMINISTRATIVE CONTROLS (Continued) 6.13 0FF-SITE DOSE CALCULATION MANUAL (ODCM) i 6.13.1 Changes to the ODCM:
- a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.9.2.0.
This documentation shall contain:
l
- 1) Sufficient information to support the change l together with the appropriate analyses or evaluation justifying the change (s), and
- 2) A determination that the change will maintain the ,
level of the radioactive effluent control required by 10 CFR 20.106, 40 CFR 190, 10 CFR 50.36a, and Appendix I to 10 CFR 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
- b. Shall become effective after review and acceptance by the PORC and the approval 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 I or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented, f
YANKEE-ROWE 6-22