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| 1 United States Nuclear Regulatory Commission March 24,1999 Attention: Mr. Morton B. Fairtile Page 3 Regarding your request for an exemption from certain requirements of Part 26, you do not need an exemption because, as noted above, Part 26 is no longer applicable to your facility." | | 1 United States Nuclear Regulatory Commission March 24,1999 Attention: Mr. Morton B. Fairtile Page 3 Regarding your request for an exemption from certain requirements of Part 26, you do not need an exemption because, as noted above, Part 26 is no longer applicable to your facility." |
| By letter dated February 27,1992 (Reference (d)), YAEC notified the NRC of the permanent cessation of power operation of YNPS. In Reference (e) YAEC proposed modifications to the YNPS operating license to refL-ct this permanent cessation of power operations and the permanent removal of fuel from the YNPS reactor vessel. Thi se changes were approved and incorporated in the YNPS POL which was issued August 5,1992 (Reference (f)). Based on the definition of the scope of applicability of 10 CFR Part 26 in the rule itself, and the confirmation in the NRC correspondence with Maine Yankee of the non-applicability of this rule to plants which have permanently ceased operation and permanently removed fuel from the reactor vessel, YNPS should have no ongoing regulatory requirement to continue its Fitness for Duty Program. | | By {{letter dated|date=February 27, 1992|text=letter dated February 27,1992}} (Reference (d)), YAEC notified the NRC of the permanent cessation of power operation of YNPS. In Reference (e) YAEC proposed modifications to the YNPS operating license to refL-ct this permanent cessation of power operations and the permanent removal of fuel from the YNPS reactor vessel. Thi se changes were approved and incorporated in the YNPS POL which was issued August 5,1992 (Reference (f)). Based on the definition of the scope of applicability of 10 CFR Part 26 in the rule itself, and the confirmation in the NRC correspondence with Maine Yankee of the non-applicability of this rule to plants which have permanently ceased operation and permanently removed fuel from the reactor vessel, YNPS should have no ongoing regulatory requirement to continue its Fitness for Duty Program. |
| SAFETY CONSIDERATIONS The proposed change is administrative in nature in that it removes a requirement that does not apply to a plant which has permanently ceased power operations and permanently removed fuel from its reactor vessel. | | SAFETY CONSIDERATIONS The proposed change is administrative in nature in that it removes a requirement that does not apply to a plant which has permanently ceased power operations and permanently removed fuel from its reactor vessel. |
| Since the permanent cessation of electric power generation at YNPS on February 26,1992, the majority of systems and components not required to support fuel storage have been dismantled and disposed of off-site. The entire decommissioning task is estimated to be more than 80% | | Since the permanent cessation of electric power generation at YNPS on February 26,1992, the majority of systems and components not required to support fuel storage have been dismantled and disposed of off-site. The entire decommissioning task is estimated to be more than 80% |
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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20206B9181999-04-23023 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 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 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 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 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 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 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 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 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 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 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 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 ML20154J5931988-05-19019 May 1988 Application for Amend to License DPR-3,revising Tech Spec 4.9.7.2 Re Spent Fuel Pit.Fee Paid ML20151D0581988-04-0404 April 1988 Application for Amend to License DPR-3,changing Tech Spec Page 3/4 8-10 Re Battery Chargers to Reflect That Charger for New Battery Upgraded to Be Identical W/Existing Battery Chargers 1 & 2.Fee Paid ML20150E2331988-03-25025 March 1988 Application for Amend to License DPR-3,consisting of Proposed Change 214,revising Tech Specs Re Containment Isolation Barriers.Fee Paid ML20148J2881988-03-25025 March 1988 Application for Amend to License DPR-3,deleting Mode 5(1) from Applicable Modes of Table 3.3-2 & Mode 5* from Modes in Which Surveillance Required of Table 4.3-2 for Listed Items.Fee Paid ML20148J2561988-03-23023 March 1988 Application for Amend to License DPR-3,revising Tech Spec 3.1.1.1.2 to Change Shutdown Margin Switching Temp from 490 to 470 F.Fee Paid ML20150C0021988-03-11011 March 1988 Application for Amend to License DPR-3,modifying Tech Spec Section 6.2 & Moving Organization Charts (Figures 6.2-1 & 6.2-2) to Section 501 of FSAR ML20148H9711988-01-18018 January 1988 Correction to 871223 Application for Amend to License DPR-3, Proposed Change 211,changing Typo in Paragraph 2 of Safety Evaluation Section ML20148G7511988-01-15015 January 1988 Application for Amend to License DPR-3,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.Fee Paid ML20149E2311988-01-0505 January 1988 Application for Amend to License DPR-3,consisting of Suppl 1 to Proposed Change 203,revising Facility Organization Chart to Reflect Improved Security Organization & Elevated Concern for Security by Plant Mgt.Fee Paid ML20149E8771988-01-0505 January 1988 Application for Amend to License DPR-3,modifying Tech Spec 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.Fee Paid ML20238F8111987-09-15015 September 1987 Application for Amend to License DPR-3,extending Expiration Date to 200709.Assessment of Benefits & Potential Impacts of Proposed Change to Expiration Date of OL Encl.Fee Paid ML20210A4261987-01-29029 January 1987 Application to Amend License DPR-3,extending Present in-core Instrumentation Sys Tech Specs Applicable for Cycle 18 to Include Cycle 19 as Listed.Mods Would Only Be Utilized If Further Neutron Detector Thimble Failures Occur.Fee Paid ML20213A4281987-01-22022 January 1987 Application for Amend to License DPR-3,modifying Tech Specs Governing Integrity Testing of Steam Generator Tubes.Fee Paid ML20215N6231986-10-22022 October 1986 Application for Amend to License DPR-3,modifying Tech Spec 4.5.2.b.4 to Increase Allowable Open Time for LPSI Min Recirculation Line Valve to 120 Minutes Per Wk.Fee Paid ML20197A7351986-10-20020 October 1986 Application for Amend to License DPR-3,revising Tech Specs to Allow for Performance of 10CFR50.59 Reviews for Future Core Reloads.Fee Paid ML20211E7261986-10-0909 October 1986 Application for Amend to License DPR-3,changing Tech Spec to Clarify Table 4.3-1 Re Reactor Protective Sys Instrumentation Surveillance Requirements.Fee Paid ML20215C1091986-10-0303 October 1986 Requests Exemption from Requirements of 10CFR50.44(c)(3) Allowing Main Coolant Sys Vents to Be Remotely Operated from Control Room & Leaving Power Supply Breakers to motor-operated Vent Valves Open.Fee Paid ML20204F6991986-07-31031 July 1986 Application for Amend to License DPR-3,changing 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.Fee Paid ML20211K7321986-06-24024 June 1986 Application for Amend to License DPR-3,changing Tech Specs to Allow Performance of 10CFR50.59 Reviews for Future Core Reloads.Fee Paid ML20151U5371986-02-0505 February 1986 Application for Amend to License DPR-3,authorizing Listed Tech Spec Changes,Per Generic Ltr 84-43, Reporting Requirements of 10CFR50... & Generic Ltr 85-19, Reporting Requirements on Primary Coolant Iodine Spikes. Fee Paid ML20136J3781986-01-0808 January 1986 Application for Amend to License DPR-3,consisting of Proposed Change 198,revising Tech Spec Table 3.6-1 to Replace Manual Containment Isolation Valve W/Blank Flange. Fee Paid ML20141G3361986-01-0606 January 1986 Application for Amend to License DPR-3,consisting of Proposed Change 196,revising Tech Spec to Permit Filing of Supplemental Dose & Meteorological Summary Rept within 150 Days of Jan 1 Each Yr.Fee Paid ML20138N2941985-10-31031 October 1985 Application for Amend to License DPR-3,changing Tech Specs Per NUREG-0737,Item II.F.1.6, Containment Hydrogen Monitor. Fee Paid ML20133K5011985-10-16016 October 1985 Application for Amend to License DPR-3,modifying Tech Spec Table 4.3-2, Engineered Sys Instrumentation Surveillance Requirements, to Require Monthly Test of New Second Level Degraded Grid Voltage Protection for Each Bus.Fee Paid ML20133K4451985-10-15015 October 1985 Application for Amend to License DPR-3,adding Two Containment Isolation Valves to Table 3.6-1 for Compliance W/Tech Spec 3/4.6.2 Which Requires Type C Tests for Valves. Fee Paid ML20133K2001985-10-15015 October 1985 Application for Amend to License DPR-3,revising Tech Specs to Accommodate Mods to RCS Vent Sys Valve Power Supplies.Fee Paid ML20133J7911985-10-15015 October 1985 Application for Amend to License DPR-3,changing Tech Specs Re Containment Pressure Monitor,Containment Water Level Monitor & Instrumentation for Detection of Inadequate Core Cooling (Ref NUREG-0737,Items II.F.1 & II.F.2).Fee Paid ML20133C5691985-09-30030 September 1985 Application for Amend to License DPR-3,revising Tech Specs Re Radiological Environ Monitoring.Fee Paid 1999-04-23
[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 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 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 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 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 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 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 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 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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e Telephom(508) 568-2233 Facsimile (508)668-3703 YANKEEATOMICELECTRIC COMPANY "" ~~~
~.
h YANKEiE 580 Main Street, Bolton, Massachusetts 01740-1398 D N K. DAVIS March 24,1999 ce$$$EE CEr BYR 98-064 P.C. No. 263 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attention: Mr. Morton B. Fairtile Senior Project Manager Non-Power Reactors and Decommissioning Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation
Reference:
(a) License No. DPR-3 (Docket No. 50-29)
(b) Letter, M. J. Meisner, Maine Yankee Atomic Power Company (MYAPC) to USNRC,10 CFR 26, Fitness for Duty Programs, MN-97-125, dated November 6,1997 (Docket No. 50-309)
(c) Letter, M. K. Webb, USNRC, to M. B. Sellman, MYAPC, dated January 12,1998 (d) Letter, A. Kadak, Yankee Atomic Energy Company (YAEC), to T. Murley, USNRC, dated Febmary 27,1992 (e) Letter, J. K. Thayer, YAEC to T. Murley, USNRC, dated March 27,1992 (f) Letter, M. B. Fairtile, USNRC, to J. M. Grant, YAEC, dated August 5, 1992
/
Subject:
Request to Eliminate Fitness-for-Duty Requirement from Yankee Nuclear Power Station's (YNPS) License ,
Dear Mr. Fairtile:
Pursuant to Section 50.90 of the Commission's Rules and Regulations, Yankee Atomic Electric Company (YAEC) proposes the following modification to the YNPS License (Reference (a)).
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9904150126 PDR 990324~ /
W ADOCK 05000029 pg 400M
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United States' Nuclear Regulatory Commission . March 24,1999
- Attention: Mr. Morton B. Fairtile Page 2 :
' PROPOSED CHANGE YAEC proposes to delete condition 2.C.(10) fro i the YNPS License No. DPR-3. This condition currently reads as follows:
2.C.(10) 'The licensee shall maintain a Fitness for Duty Program in accordance with the .
requirements of10 CFR Part 26.
REASON FOR CHANGE The proposed change would delete a license condition which no longer applies to a plant such as
- YNPS which has pernianently ceased operations and permanently removed fuel from the reactor vessel. This deletion is viewed as an appropriate administrative action to update the present
' YNPS License.
BASIS FOR CHANGE The scope of 10 CFR Part 26 is stated in the NRC's regulations, in part, as follows:
"The regulations in this part apply to licensees authorized to operate a nuclear power reactor, to possess or use formula quantities of SSNM, or to transport formula -
quantities of SSNM...".
Because YNPS is no longer authorized to operate a nuclear power reactor and is not authorized to possess, use, or transport formula quantities of strategic special nuclear material (SSNM), the requirements of 10 CFR 26 no longer apply. 4 In a letter to the NRC dated November 6,1997 (Reference (b)), Maine Yankee Atomic Power Company indicated that having certified permanent cessation of power operation and ocemanent removal of fuel from the Maine Yankee reactor, it was believed that Maine Yankee was no longer required to comply with 10 CFR Part 26. Further, the subject letter stated that if the NRC did not agree with this interpretation of the rules, Maine Yankee was requesting an exemption from the requirements of 10 CFR Part 26. Pe NRC responded by letter dated Je luary 12,1998 (Reference (c)) as follows:
"The staff acknowledges that, due to the certifications that you provided under 10 CFR -
50.82(a)(1) regarding permanent cessation of operations and permanent removal of fuel from the reactor vessel, the Maine Yankee 10 CFR Part 50 license no longer authorizes operation of the reactor or emplacement of fuel into the reactor vessel. Therefore,' the staff concurs' with your conclusion that 10 CFR Part 26 no longer applies to Maine Yankee .
because 10 CFR Part 26 pertains to licensees authorized to operate a nuclear reactor, y
F 1
}
/ .
1 United States Nuclear Regulatory Commission March 24,1999 Attention: Mr. Morton B. Fairtile Page 3 Regarding your request for an exemption from certain requirements of Part 26, you do not need an exemption because, as noted above, Part 26 is no longer applicable to your facility."
By letter dated February 27,1992 (Reference (d)), YAEC notified the NRC of the permanent cessation of power operation of YNPS. In Reference (e) YAEC proposed modifications to the YNPS operating license to refL-ct this permanent cessation of power operations and the permanent removal of fuel from the YNPS reactor vessel. Thi se changes were approved and incorporated in the YNPS POL which was issued August 5,1992 (Reference (f)). Based on the definition of the scope of applicability of 10 CFR Part 26 in the rule itself, and the confirmation in the NRC correspondence with Maine Yankee of the non-applicability of this rule to plants which have permanently ceased operation and permanently removed fuel from the reactor vessel, YNPS should have no ongoing regulatory requirement to continue its Fitness for Duty Program.
SAFETY CONSIDERATIONS The proposed change is administrative in nature in that it removes a requirement that does not apply to a plant which has permanently ceased power operations and permanently removed fuel from its reactor vessel.
Since the permanent cessation of electric power generation at YNPS on February 26,1992, the majority of systems and components not required to support fuel storage have been dismantled and disposed of off-site. The entire decommissioning task is estimated to be more than 80%
complete. To support the decommissioning efforts and to eliminate potential problems which could arise from system interactions, those systems necessary for continued operation of the YNPS Spent Fuel Pit (SFP) have been reconfigured to provide approprice isolation from the balance of the plant. A significant result of this reconfiguration is that the remaining systems which require monitoring by Operations have been markedly reduced in number and complexity.
Concerning the operation of the YNPS SFP, there is very little or no epportunity for personnel to have a detrimental effect on the reactivity, heat content, or structural integrity of the fuel. The YNPS FSAR notes that with the level of decay heat in the SFP as of January 1994, more than four weeks would have to elapse without re-establishing cooling or adding make-up water before the water remaining in the SFP would not be sufficient to provide shielding adequate for operator response in the SFP. The accident analyses in the YNPS FSAR include the following spent fuel storage events: a fuel handling event, loss of spent fuel cooling capability, and interactions between spent fuel storage and decommissioning activities. For each of the postulated events, the scuario projected a maximum release of activity and no prompt mitigation actions. None of the analyzed scenarios resulted in a situation which could significantly effect the public health and safety. Any future fuel handling evolutions will require the combined efforts of several trained personnel. No one individual will have the capability to perform an evolution,
ynited States Nuclear Regulatory Commission March 24,1999 Attention: Mr. Morton B. Fairtile Page 4 intentionally or inadvertently, which will compromise the public health and safety in a time too short to avoid detection and corrective action.
l l Upon approval, YAEC intends to continue those elements ofits current fitness-for-( tty program which it believes have been most effective during the decommissioning of YNPS but anly as a practical matter and not as a matter of regulatory compliance or commitment. YAEC plans to continue a fitness-for-duty program in its entirety. At its own discretion, YAEC may elect to -
modify one or all of the elements of the fitnen 'or-duty program in the future.
l i
SIGNIFICANT HAZARDS CONSIDERATION The proposed change is administrative in nature in that it removes a reference in the YNPS Part j 50 License to a regulatory requirement no longer applicable to a plant which has permanently ceased power operations and permanently removed fuel from its reactor vessel. This will permit more cost beneficial use of available resources with no diminution in the YNPS staffs ability to maintain the safe operation of the YNPS SFP. The change will not:
- 1. Involve a significant increase in the probability or consequences of an accident previously evaluated. Each potential accident evaluated in the YNPS FSAR projects a maximum r-lease of activity and no prompt mitigation actions. None of the analyzed scenarios resulted in a situation which could significantly effect the public health and safety.
Removal of a regulatory requirement which does not apply to a plant which has permanently ceased power operations and permanently removed fuel from its reactor vessel cannot be deemed to involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Create the possibility of a new er different accident from any previously evaluated. The proposed change will not modify any plant systems or components and therefore will not create the possibility of a new or different accident from any previously evaluated.
- 3. Involve n significant reduction in the margin of safety. Removal of a regulatory requirement which does not apply to a plant which has permanently ceased power operations and which has permanently remove fuel from its reactor vessel cannot be deemed to involve a significant reduction in the margin of safety.
Based on the considerations contained herein, it is concluded that there is reasonable assurance that the proposed change will not endanger the health and safety of the public.
This proposed change has been revkwed by PORC and the Nuclear Safety Audit and Review Committee.
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- e U.nited States Nuclear Regulatory Commissinn .- March 24,1999 .
Attedtion: Mr. Morton B. Fairtile Page5 SCHEDULE OF CH4NGE The proposed change'will be implemented upon approval by the Commission.
Very truly yours, .
YANKEE ATOMIC ELECTRIC COMPANY h
Don K. Davis, Chairman President and CEO Attachments c: USNRC, Region I COMMONWEALTH OF MASSACHUSETTS WORCESTER COUNTY Ther personally appeared before me, Don K. Davis, who, being duly sworn, did rtate that lie is Chairman, President, and Chief Executive Officer of Yankee Atomic Electric Company, that he .
is duly authorized to execute and file the foregoing doctunent in the name and on the behalf of '
Yankee Atomic Electric Company and that the statements therein are true to the best of his knowledge and belief.
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Kathhn Gatef Notary Public My Commission Expires January 1,2004 P '