Letter Sequence Other |
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MONTHYEARML20134L6861985-08-23023 August 1985 Proposed Tech Spec Changes to Tables 3.7-4 & 3.6.3-1 Re Primary Containment Isolation Valves to Reflect Drywell Pneumatic Sys Mods Project stage: Other ML20134L6611985-08-23023 August 1985 Application for Amends to Licenses DPR-57 & NPF-5,revising Tech Spec Tables 3.7.4 & 3.6.3-1 Re Primary Containment Isolation Valves to Reflect Drywell Pneumatic Sys Mods.Fee Paid Project stage: Request ML20141F1261985-12-26026 December 1985 Safety Evaluation Supporting Amends 120 & 59 to Licenses DPR-57 & NPF-5,respectively Project stage: Approval ML20141F1211985-12-26026 December 1985 Amends 120 & 59 to Licenses DPR-57 & NPF-5,respectively, Revising Tech Specs to Add & Delete Values Listed in Containment Isolation Value Tables to Reflect Drywell Pneumatic Sys Mods Project stage: Other ML20141F1121985-12-26026 December 1985 Forwards Amends 120 & 59 to Licenses DPR-57 & NPF-5, Respectively & Safety Evaluation.Amends Revise Tech Specs to Add & Delete Values Listed in Containment Isolation Value Tables to Reflect Drywell Pneumatic Sys Mods Project stage: Approval 1985-12-26
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Similar Documents at Hatch |
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Category:OPERATING LICENSES & AMENDMENTS
MONTHYEARML20211J9351997-10-0606 October 1997 Corrected TS Pps to Amends 208 & 150 for Licenses DPR-57 & NPF-5,respectively,consisting of Pps 3.4-8 & 3.5-6 for Unit 1 & Pps 3.4-8 & 3.5-5 for Unit 2 to Reflect Revised SRV Setpoints ML20137N1751997-04-0404 April 1997 Amends 206 & 147 to Licenses DPR-57 & NPF-5,respectively, Revising Surveillance Requirements Addressing Reactor Vessel Pressure & Temperature ML20059E6831993-10-21021 October 1993 Amends 190 & 129 to Licenses DPR-57 & NPF-5,respectively, Relocating Procedural Details Contained in Radiological Effluent Ts,Incorporating New Part 20 & Revising Frequency of Reporting Radiological Effluent Releases ML20153F9901988-05-0202 May 1988 Amend 153 to License DPR-57,revising Tech Specs to Require Full Stroke Testing of Msivs,Per ASME Code,Section XI ML20236E2561987-07-24024 July 1987 Corrected Tech Spec Pages from Amends 141 & 77 to Licenses DPR-57 & NPF-5,modified to Correct Typos &/Or Include Previously Issued Amends ML20141N0651986-02-21021 February 1986 Errata to Amend 122 to License DPR-57,providing Tech Spec Pages 3.2-10 & 3.2-33 Re Instrumentation Which Initiates or Controls Automatic Depressurization Sys ML20141F1211985-12-26026 December 1985 Amends 120 & 59 to Licenses DPR-57 & NPF-5,respectively, Revising Tech Specs to Add & Delete Values Listed in Containment Isolation Value Tables to Reflect Drywell Pneumatic Sys Mods ML20062A4691978-10-0404 October 1978 Amend 60 to Facil Oper Lic DPR-57 Revising Tech Specs Re Limiting Conditions for Oper & Surveillance Requirements for Exisiting Fire Protec Sys & Admin Controls of Subj Facil ML20207U1541978-06-16016 June 1978 Amend 56 to License DPR-57,modifying Tech Specs by Revising Limiting Conditions for Operation & Surveillance Requirements Associated W/Plant Svc Water Sys 1997-04-04
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARHL-5770, Application for Amends to Licenses DPR-57 & NPF-5,revising Acceptance Criteria for Diesel Fuel Oil Storage as Surveillance Requirement 3.8.1.3 Min Fuel Oil Level for DG Day Tanks Will Be Changed to Greater than 500 Gallons1999-10-0101 October 1999 Application for Amends to Licenses DPR-57 & NPF-5,revising Acceptance Criteria for Diesel Fuel Oil Storage as Surveillance Requirement 3.8.1.3 Min Fuel Oil Level for DG Day Tanks Will Be Changed to Greater than 500 Gallons HL-5811, Application for Amends to Licenses DPR-57 & NPF-5,revising Wording Contained in LCO 3.1.7 Re Standby Liquid Control Sys1999-07-29029 July 1999 Application for Amends to Licenses DPR-57 & NPF-5,revising Wording Contained in LCO 3.1.7 Re Standby Liquid Control Sys HL-5591, Application for Amends to Licenses DPR-57 & NPF-5, Respectively.Amends Would Implement Some of Generic Changes to ITSs Previously Approved by NRC1999-02-0505 February 1999 Application for Amends to Licenses DPR-57 & NPF-5, Respectively.Amends Would Implement Some of Generic Changes to ITSs Previously Approved by NRC HL-5694, Revised Application for Amends to Licenses DPR-57 & NPF-5, Revising TS for Increase in Allowable Values for Reactor Bldg & Refueling Floor Ventilation Exhaust Radiation Monitors1999-01-21021 January 1999 Revised Application for Amends to Licenses DPR-57 & NPF-5, Revising TS for Increase in Allowable Values for Reactor Bldg & Refueling Floor Ventilation Exhaust Radiation Monitors HL-5698, Application for Amends to Licenses DPR-57 & NPF-5,revising TS 2.1.1.2 by Deleting Footnote Which Specifies That SLMCPRs Are for Cycle 18 Only & Deleting TS 5.6.5.b.21998-12-0404 December 1998 Application for Amends to Licenses DPR-57 & NPF-5,revising TS 2.1.1.2 by Deleting Footnote Which Specifies That SLMCPRs Are for Cycle 18 Only & Deleting TS 5.6.5.b.2 HL-5658, Application for Amends to Licenses DPR-57 & NPF-5,increasing Allowable Values for High Radiation Trip for Reactor Bldg & Refueling Floor Ventilation Exhaust Monitors1998-07-22022 July 1998 Application for Amends to Licenses DPR-57 & NPF-5,increasing Allowable Values for High Radiation Trip for Reactor Bldg & Refueling Floor Ventilation Exhaust Monitors HL-5400, Application for Amends to Licenses DPR-57 & NPF-5, Respectively.Amends Remove/Modify Existing License Conditions,Surveillance Requirements That Have Been Completed & Exemptions That Are No Longer in Effect1997-12-18018 December 1997 Application for Amends to Licenses DPR-57 & NPF-5, Respectively.Amends Remove/Modify Existing License Conditions,Surveillance Requirements That Have Been Completed & Exemptions That Are No Longer in Effect ML20211J9351997-10-0606 October 1997 Corrected TS Pps to Amends 208 & 150 for Licenses DPR-57 & NPF-5,respectively,consisting of Pps 3.4-8 & 3.5-6 for Unit 1 & Pps 3.4-8 & 3.5-5 for Unit 2 to Reflect Revised SRV Setpoints HL-5413, Application for Amends to Licenses DPR-57 & NPF-5,allowing Plant to Operate at Uprated Power Level of 2763 Mwt Which Represents Power Level Increase of 8%.Proprietary TR NEDC-32749P Encl1997-08-0808 August 1997 Application for Amends to Licenses DPR-57 & NPF-5,allowing Plant to Operate at Uprated Power Level of 2763 Mwt Which Represents Power Level Increase of 8%.Proprietary TR NEDC-32749P Encl HL-5368, Application for Amend to License DPR-57,revising Safety Limit Minimum Critical Power Ratio in TS 2.1.1.2 to Reflect Results of Cycle Specific Calculation.Proprietary Basis for Change,Also Encl.Encl Withheld,Per 10CFR2.790(a)(4)1997-05-0909 May 1997 Application for Amend to License DPR-57,revising Safety Limit Minimum Critical Power Ratio in TS 2.1.1.2 to Reflect Results of Cycle Specific Calculation.Proprietary Basis for Change,Also Encl.Encl Withheld,Per 10CFR2.790(a)(4) HL-5362, Application for Amends to Licenses DPR-57 & NPF-5,revising Operability Requirements for Rod Block Monitor Sys1997-05-0909 May 1997 Application for Amends to Licenses DPR-57 & NPF-5,revising Operability Requirements for Rod Block Monitor Sys ML20138H4021997-04-29029 April 1997 Application for Amend to License DPR-57,revising TS 3.4.9 Re Reactor Coolant Sys Pressure & Temp Limits HL-5345, Application for Amend to License DPR-7,requesting Rev to TS 3.4.9 Re Reactor Coolant Sys Pressure & Temp Limits1997-04-14014 April 1997 Application for Amend to License DPR-7,requesting Rev to TS 3.4.9 Re Reactor Coolant Sys Pressure & Temp Limits ML20137N1751997-04-0404 April 1997 Amends 206 & 147 to Licenses DPR-57 & NPF-5,respectively, Revising Surveillance Requirements Addressing Reactor Vessel Pressure & Temperature HL-5276, Application for Amends to Licenses DPR-57 & NPF-5,which Provides an Alternate Method of Testing S/Rvs During Shutdown Conditions Rather than During Unit Startup as Is Currently Done1997-01-0707 January 1997 Application for Amends to Licenses DPR-57 & NPF-5,which Provides an Alternate Method of Testing S/Rvs During Shutdown Conditions Rather than During Unit Startup as Is Currently Done HL-5270, Application for Amend to License NPF-5,revising SLMCPR Values Based Upon Unique plant-evaluations for Current Cycle 13 & Use of GE Fuel in Next Cycle 141996-12-0303 December 1996 Application for Amend to License NPF-5,revising SLMCPR Values Based Upon Unique plant-evaluations for Current Cycle 13 & Use of GE Fuel in Next Cycle 14 HL-5054, Application for Amends to License DPR-57 & NPF-5, Respectively,Associating Changes W/Installation of Digital Power Range Neutron Monitoring Sys & Incorporation of long- Term Stability Solution Hardware1996-10-29029 October 1996 Application for Amends to License DPR-57 & NPF-5, Respectively,Associating Changes W/Installation of Digital Power Range Neutron Monitoring Sys & Incorporation of long- Term Stability Solution Hardware HL-5230, Application for Amends to Licenses DPR-57 & NPF-5,revising SRs 3.1.7.7 & 3.4.3.1 & LCOs 3.4.3,3.5.1 & 3.6.1.6 to Increase Nominal Mechanical Pressure Relief Setpoints for All SRVs & Allow Operation W/One SRV1996-10-0707 October 1996 Application for Amends to Licenses DPR-57 & NPF-5,revising SRs 3.1.7.7 & 3.4.3.1 & LCOs 3.4.3,3.5.1 & 3.6.1.6 to Increase Nominal Mechanical Pressure Relief Setpoints for All SRVs & Allow Operation W/One SRV HL-5213, Application for Amends to Licenses DPR-57 & NPF-5,clarifying Applicability of Certain Surveillances Addressing Rvp & Temp Limits & Replacing Vessel Pressure & Temp Limit Curves W/New Curves1996-09-19019 September 1996 Application for Amends to Licenses DPR-57 & NPF-5,clarifying Applicability of Certain Surveillances Addressing Rvp & Temp Limits & Replacing Vessel Pressure & Temp Limit Curves W/New Curves HL-5163, Application for Amends to Licenses DPR-57 & NPF-5,revising TSs Re CST Level Indication to Ensure Water Level Sufficient to Provide 50,000 Gallons of Water for Core Spray Makeup to Reactor Pressure Vessel1996-05-21021 May 1996 Application for Amends to Licenses DPR-57 & NPF-5,revising TSs Re CST Level Indication to Ensure Water Level Sufficient to Provide 50,000 Gallons of Water for Core Spray Makeup to Reactor Pressure Vessel HL-5004, Application for Amends to Licenses DPR-57 & NPF-5, Respectively,Revising Changes of Drywell Air Temp LCO from 135 F to 150 F1996-02-21021 February 1996 Application for Amends to Licenses DPR-57 & NPF-5, Respectively,Revising Changes of Drywell Air Temp LCO from 135 F to 150 F HL-5051, Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Reflect Implementation of 10CFR50,App J,Option B1995-11-10010 November 1995 Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Reflect Implementation of 10CFR50,App J,Option B HL-4861, Application for Amends to Licenses DPR-57 & NPF-5.Amends Would Revise Secondary Containment Draw Down & Maintain Vacuum Surveillance Requirement Acceptance Criteria1995-06-0606 June 1995 Application for Amends to Licenses DPR-57 & NPF-5.Amends Would Revise Secondary Containment Draw Down & Maintain Vacuum Surveillance Requirement Acceptance Criteria HL-4816, Application for Amend to Licenses DPR-57 & NPF-5,minimizing Thermal Stratification Events1995-05-0404 May 1995 Application for Amend to Licenses DPR-57 & NPF-5,minimizing Thermal Stratification Events HL-4789, Application for Amend to License NPF-5 Re Elimination of Selected Response Time Testing Requirements from TS1995-04-14014 April 1995 Application for Amend to License NPF-5 Re Elimination of Selected Response Time Testing Requirements from TS HL-4724, Application for Amends to Licenses DPR-57 & NFP-5,proposing Changes to Ts,To Allow Plant to Operate at Uprated Power Level of 2558 Mwt.Also,Forwards Proprietary Power Uprate SAR for E I Hatch Plant Units 1 & 21995-01-13013 January 1995 Application for Amends to Licenses DPR-57 & NFP-5,proposing Changes to Ts,To Allow Plant to Operate at Uprated Power Level of 2558 Mwt.Also,Forwards Proprietary Power Uprate SAR for E I Hatch Plant Units 1 & 2 HL-4723, Application for Amends to Licenses DPR-57 & NPF-5,replacing Environ TS W/Environ Protection Plan (Nonradiological) & Revising OLs to Reflect Changes1994-12-0202 December 1994 Application for Amends to Licenses DPR-57 & NPF-5,replacing Environ TS W/Environ Protection Plan (Nonradiological) & Revising OLs to Reflect Changes ML20078G7051994-11-0101 November 1994 Application for Amends to Licenses DPR-57 & NPF-5,converting TS to Improved TS Consistent w/NUREG-1433 HL-4587, Application for Amends to Licenses DPR-57 & NPF-5,lowering ATWS-RPT Setpoint & Allowing Restarting Recirculation Pump Following RPT When Temp Differential Between Coolant at Reactor Bottom Head & Reactor Steam Dome Cannot Be Obtained1994-10-13013 October 1994 Application for Amends to Licenses DPR-57 & NPF-5,lowering ATWS-RPT Setpoint & Allowing Restarting Recirculation Pump Following RPT When Temp Differential Between Coolant at Reactor Bottom Head & Reactor Steam Dome Cannot Be Obtained HL-4695, Application for Amend to License DPR-57,requesting Temporary Change to Unit 1 TSs Re Emergency Diesel Generator Operability Requirements During Reactor Shut Down Conditions1994-09-20020 September 1994 Application for Amend to License DPR-57,requesting Temporary Change to Unit 1 TSs Re Emergency Diesel Generator Operability Requirements During Reactor Shut Down Conditions HL-4648, Application for Amend to License DPR-57,proposing one-time Change to TS 3.9.C to Allow Shutdown Operations W/Only One of Two Required EDGs Aligned to Corresponding Core or Containment Cooling Sys1994-08-16016 August 1994 Application for Amend to License DPR-57,proposing one-time Change to TS 3.9.C to Allow Shutdown Operations W/Only One of Two Required EDGs Aligned to Corresponding Core or Containment Cooling Sys HL-4661, Application for Amends to Licenses DPR-51 & NPF-5,revising Result of Meetings & Includes Page Change Insertion Instructions,Per NUREG-14331994-08-0808 August 1994 Application for Amends to Licenses DPR-51 & NPF-5,revising Result of Meetings & Includes Page Change Insertion Instructions,Per NUREG-1433 ML20072B7441994-08-0404 August 1994 Application for Amend to License NPF-5,revising TSs for Traversing Incore Probe Operability Requirements HL-4651, Application for Amend to License NPF-5,revising TS 3.3.6.6 Requirements for All Traversing in-core Probe Machines to Be Operable,To Allow Less than Four Machines to Be Operable1994-07-19019 July 1994 Application for Amend to License NPF-5,revising TS 3.3.6.6 Requirements for All Traversing in-core Probe Machines to Be Operable,To Allow Less than Four Machines to Be Operable HL-4620, Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Improved Insertion Instructions,Consistent w/NUREG- 14331994-07-0808 July 1994 Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Improved Insertion Instructions,Consistent w/NUREG- 1433 HL-4561, Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Allow Testing Planned at Plant to Demonstrate Capability to Operate Plant Up to Core Power Level of 2,558 Mwt1994-06-0707 June 1994 Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Allow Testing Planned at Plant to Demonstrate Capability to Operate Plant Up to Core Power Level of 2,558 Mwt HL-4495, Application for Amends to Licenses DPR-57 & DPR-5 Revising Units 1 & 2 TS to Be Consistent w/NUREG-1433 Standard TS GE Plants,BWR/41994-02-25025 February 1994 Application for Amends to Licenses DPR-57 & DPR-5 Revising Units 1 & 2 TS to Be Consistent w/NUREG-1433 Standard TS GE Plants,BWR/4 HL-3433, Application for Amend to Licenses DPR-57 & NPF-5 Revising Unit 1 TS 4.9 & Unit 2 TS 4.8 Re Diesel Generator Testing Under Hot Initial Conditions1993-11-0909 November 1993 Application for Amend to Licenses DPR-57 & NPF-5 Revising Unit 1 TS 4.9 & Unit 2 TS 4.8 Re Diesel Generator Testing Under Hot Initial Conditions ML20059E6831993-10-21021 October 1993 Amends 190 & 129 to Licenses DPR-57 & NPF-5,respectively, Relocating Procedural Details Contained in Radiological Effluent Ts,Incorporating New Part 20 & Revising Frequency of Reporting Radiological Effluent Releases HL-3416, Application for Amends to Licenses DPR-57 & NPF-5,revising Unit 1 TS 3.9.D & Unit 2 TS 3/4.8.2 to Add Time Delays to RPS Electric Power Monitoring Trips1993-10-19019 October 1993 Application for Amends to Licenses DPR-57 & NPF-5,revising Unit 1 TS 3.9.D & Unit 2 TS 3/4.8.2 to Add Time Delays to RPS Electric Power Monitoring Trips ML20045E7261993-06-28028 June 1993 Application for Amends to Licenses DPR-57 & NPF-5,revising TS 3.7.A.4 & 3.6.4.1,respectively,to Allow One or More Suppression chamber-drywell Vacuum Breakers to Open During Surveillance Testing ML20044D0771993-05-0303 May 1993 Suppl to 920921 Application for Amends to Licenses DPR-57 & NPF-5,changing TS Administrative Controls Section Re Semiannual Radioactive Effluent Release Rept to Reflect New 10CFR50.36a,per GL 89-01 HL-3048, Application for Amend to License DPR-57,revising TS Re Removal of Primary Containment Isolation Valves E11-F022 & E11-F0231992-12-21021 December 1992 Application for Amend to License DPR-57,revising TS Re Removal of Primary Containment Isolation Valves E11-F022 & E11-F023 HL-2962, Application for Amend to License NPF-5,changing TS to Temporarily Revise Containment Sys Section to Allow Unit 1 Standby Gas Treatment Sys to Be Inoperable for Up to 7 Days During Unit 2 Operation,Per Generic Ltr 89-161992-11-10010 November 1992 Application for Amend to License NPF-5,changing TS to Temporarily Revise Containment Sys Section to Allow Unit 1 Standby Gas Treatment Sys to Be Inoperable for Up to 7 Days During Unit 2 Operation,Per Generic Ltr 89-16 HL-2006, Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Remove Main Steam Line Radiation Monitor Reactor Scram & Group Isolation Functions,Per BWROG Topical Rept NEDO-31400, SE for Eliminating BWR MSIV Closure..1992-10-19019 October 1992 Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Remove Main Steam Line Radiation Monitor Reactor Scram & Group Isolation Functions,Per BWROG Topical Rept NEDO-31400, SE for Eliminating BWR MSIV Closure.. HL-2409, Application for Amends to Licenses DPR-57 & NPF-5,revising Definition of Members of the Public & Unrestricted Area, in TS & Deleting Ref in ETS Footnote Re RM Instrumentation, in Response to New 10CFR20 Requirements,Per GL 89-011992-10-14014 October 1992 Application for Amends to Licenses DPR-57 & NPF-5,revising Definition of Members of the Public & Unrestricted Area, in TS & Deleting Ref in ETS Footnote Re RM Instrumentation, in Response to New 10CFR20 Requirements,Per GL 89-01 HL-2390, Application for Amends to Licenses DPR-57 & NPF-5, Incorporating Programmatic Controls for RETS Into Administrative Controls Section of TS & Relocating Procedural Details for RETS to ODCM & Pcp,Per GL 89-011992-09-21021 September 1992 Application for Amends to Licenses DPR-57 & NPF-5, Incorporating Programmatic Controls for RETS Into Administrative Controls Section of TS & Relocating Procedural Details for RETS to ODCM & Pcp,Per GL 89-01 ML20118A5761992-09-18018 September 1992 Application for Amends to Licenses DPR-57 & NPF-5,allowing Southern Nuclear Operating Co,Inc to Possess,Manage,Use, Operate & Maintain Facilities.Certificate of Concurrence from Southern Nuclear Operating Co,Inc Encl HL-2335, Application for Amends to Licenses DPR-57 & NPF-5,changing TS Figure 2.1-1 for Unit 1 & TS Figure 3/4 3-1 for Unit 2 to Reflect Correct Top of Active Fuel Reactor Pressure Vessel Water Level1992-09-0202 September 1992 Application for Amends to Licenses DPR-57 & NPF-5,changing TS Figure 2.1-1 for Unit 1 & TS Figure 3/4 3-1 for Unit 2 to Reflect Correct Top of Active Fuel Reactor Pressure Vessel Water Level HL-2355, Application for Amend to License DPR-57,changing TS to Revise Allowable Outage Times for EDG 1B to 14 Days to Perform Work on DG & Revising DG Surveillance Requirements 4.9.B.1 & 4.9.B.2 to Correct Adminstrative Error1992-07-30030 July 1992 Application for Amend to License DPR-57,changing TS to Revise Allowable Outage Times for EDG 1B to 14 Days to Perform Work on DG & Revising DG Surveillance Requirements 4.9.B.1 & 4.9.B.2 to Correct Adminstrative Error 1999-07-29
[Table view] |
Text
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UNITED STATES
- E o NUCLEAR REGULATORY COMMISSION s :y WASHWGJOP!, D. C. 20565 s.,...../
GEORGIA PDWER COMPANY
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OGLETHORPE'F0WER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DkTON, GEORGIA DOCKET NO. 50-321 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.120 License No. DPR-57
- 1. The Nuclear Regulatory Comission (the Comission) has found that:
A. The application for amendment by Georr;ia Power Company, et 'al.,
(the licensee) dated August 23, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; s i, ..
C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted withoJt endangering tiie 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 s E. The issuance of this' amendment is[in a::cordance with 10 CFR Part 51 of the Comission'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,
+' and psragraph 2.C.(2) of Facility Operating License No. DPR-57 is hereby amended to read as follows:
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i 8601080629 B51226 DR ADOCK O y1
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2-Technical Specifications
'd,
'f 41 The Technical Specifications contained in Appendices M- A and B, as revised through Amendment No.120, are
+ hereby incorporated in the license. The licensee shall operate the facility in accordance with the 4 ,
Technical Specifications.
p1: s' 3.- This license amendment is effective as of its date of issuance and shall i be implemented within 30 days of issuance.
>! OR THE NUCLEAR REGULATORY C0ml ION I,
l /d 77),, n
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s Daniel R. Muller, Director BWR Project Directorate #2 V Division of BWR Licensing
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(Lianges to the Technical Specifications
)
Date of Issuance: December 26, 1985
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i ATTACHMENT TO LICENSE AMENDMENT NO. 120 j FACILITY OPERATING LICENSE NO. DPR-57 DOCKET NO. 50-321 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by Amendment number and contains vertical lines indicating the area of change.
Remove Insert 3.7-24 3.7-24 f
4
. . o-9
Table 3.7-4 (Continued)
Primary Containment Testable Isolation Valves Penetration Number Valve Designation Notes X-21 P51-F513 & F514 (1) (2) (4) (5) (9)
X-22 P70-F004, F005 (1) (2) (4) (5) (10)
X-25 T48-F307, F308, F309, F103 & F324 (1) (2) (4) (5) (9)
X-25 T48-F113 & F114 (1) (2) (4) (5) (9)
X-25 T48-F321 & F322 X-25 T48-F104, F118A, F1188 (1) (2) (4) (5) (9)
X-26 T48-F319 & F320 (1) (2) (4) (5) (9)
X-26 T48-F334A & F335A X-26 T48-F334B & F335B X-26 T48-F340 & F341 X-26 P33-F002 & F010 X-27F P70-F066, F067 (1) (2) (4) (5) (10)
X-28 P33-F003 & F011 (1) (2) (4) (5) (9)
X-31 P33-F004 & F012 "
X-36 C11-F086 (1) (2) (4) (5) (10)
X-36 C11-F083 X-39A E11-F016A & F021A (1) (2) (4) (5) (9)
.X-39A E11-F016B & F0218
+ X-40 P70-F002 & F003 X-41 B21-F019 & F020
} X-42 C41-F006 (1) (2) (4) (5) (10)
X-42 C41-F007 X-46 P21-F353 & F406 (1) (2) (4) (5) (9)
X-203 E-51-F003 & F031
. X-204A E11.F065A'& F004A (1) (2) (5) (9) (12)
Amendment No. 57,120 3.7-24
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- % UNITED STATES
. ! t NUCLEAR REGULATORY COMMISSION
- ej WASHINGTON, D. r 20555
%,*****e' GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPALEldCTRICAUTHORITYOFGEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-366 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 59 License No. NPF-5
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Georgia Power Company, et'a1.,
(the licensee) dated August 23, 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; B. The facility will operate 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 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 31 of the 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 tae attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-5 is hereby amended to read as follows:
~
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 59 , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
$ 44 /
Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: December 26, 1985
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ATTACHMENT TO LICENSE AMENDMENT NO. 59 FACILITY OPERATING LICENSE NO. NPF-5 DOCKET NO. 50-366 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.
Remove Insert 3/4 6-24 3/4 6-24 3/4 6-25 3/4 6-25 3/4 6-26 3/4 6-26 3/4 6-27 3/4 6-27 * -
3/4 6-28 3/4 6-28 i
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v, .
31 TABLE 3.6.3-1 (Continued) I g PRIMARY CONTAIMENT ISOLATION VALVES
-e E ISOLATION TIME i VALVE FUNCTION AND NUMBER VALVE GROUP (a) (Seconds) ;
b A. Automatic Isolation Valves (Continued)
' 25. Traversing Incore Probe Isolation Valve .s; Ball Valves
- 26. Vacuum Relief Isolation Valves 2T48-F309 6 5 2T48-F324 6 5 g "I See Specification 3.3.2. Table 3.3.2-1, for isolation signals that operate each valve group. i
[ Closes upon withdrawal of TIP. TIP automatic withdrawal is actuated by either low reactor -
vessel water level or high drywell pressure.
4 w
?4 8
e O
f
~
4 TABIE 3.6.3-1(Oontirued)
- M PRDERY CDtfrAIMElfr ISO [ATION VALVES
~I i VALVE RJNCTION AND ID EER B. t!At0AL ISOIATION VALVES (e) l g .
- 1. Main steam isolation valves 2E32-F001B, F, K, P
- 2. IER return to recirottlation loop isolation valtes l 2 Ell-F015A, B i 3. LOCA H2 recombiner isolation valtes 2T49-F002 A, B 2r49-F004 A, B y 4. Chre spray isolation valves
, y 5. Service air isolation valtes 2P51-F651 2P51-F513 j I i
y 6. RBOCW sJpply and return isolation valtes
, g 2P42-F051
- ? 2P42-F052 ,
1 g e '
5
'*) Includes power operated valves which do not isolate aitomatically.
E 9
b .
. .g:
. .. r; rg,, .
.) , .
\ b-
< t I. TABLE 3.6.3-1 (Continued) j
' PRIMARY CONTAINMENT ISOLATION VALVES iE i
@ VALVE FUNCTION AND NUMBER e B. I
- MANUAL ISOLATION VALVES ') (Continued)
) l-E 7. .
i
" Drywell pressure instrumentation line isolation valves 2E11-F041A, B, C, D l 2T48-F363A, B 8.
-! ILRT verification flow isolation valves 2T23-F004 '
l.
I 2T23-F005 j 9. Traversing incore probe isolation valve Shear valve (explosive) [
- . I _ i
' " 10. N2 makeup inlet isolation valves
/ 2T48-F322 1.
L i
? 2T48-F325 C
IX 2T48-F327 1
- 11. Demineralized water isolation valves
[' 2P21-F032 ,
l 4i 2P21-F034 17 12. Chilled water supply and return isolation valves Y 2P64-F045 j
, a 2P64-F047
.i g 13. Chemical pump discharge isolation valves 2G11-F852 E 2G11-F853 l li E i >
e id.
\ u
),
.. I kr TABLE 3.6.3-1 (Continued)
PRIMARY CONTAINMENT ISOLATION VALVES VALVE FUNCTION AND NUMBER
^
E B. MANUAL ISOLATION VALVES (e) (Continued) 1 0 c- 14- Nitrogen vent isolation valves i'i l
- 16. RCIC pump suction isolation valves l 2E51-F003 2E51-F031 17- RHR pump suction isolation valves j g 2 Ell-F004A, B, C, D IS. Vacuum relief isolation valves l-
? 2T48-F310 9? 2T48-F311 19' Vacuum relief instrumentation line isolation valve 2T48-F364A, B l
- 20. Torus water l'e' vel instrumentation line isolation valves j-2T48-361 A, B 2T48-362 A, B
[ 21* HPCI pump suction isolation valve {
g 2E41-F051 5 22. Core spray pump suction isolation valves A 2E21-F001 A, B l I
- 23. Fire protection isolation valve 2T43-F160 l y- '
R .
I i
y
, ' 9
'~
TABLE 3.6.3-1 (Continued) lE PRIMARY CONTAINMENT ISOLATION VALVES M
x VALVE FUNCTION AND NUMBER
!! B. MANUAL ISOLATION VALVES I *I (Continued) h3 1' 24. FPM sample isolation valves I
2D11-F058 i 2011-F061
- , 25. Torus purification suction isolation valves l I- 2G51-F002 26't RHR relief valve discharge isolation valve
] 2E11-F103 A, B l I' ~
as 27. Nitrogen makeup isolation valves -(
3: 2T48-F115 2T48-F116 ai '
ns
[ 28. Core spray test line isolation valves [
,' 2E11-F007 A, B I .
N i a 8F i 2
- c
.EF
' mbt 2 3.6.3-1 (Contimed)
- PRDERY CONTADMENP ISCIATION VALVES
C. ODIER ISOUn' ION VALVES
~
M 1. Primary feedwater isolation valtes 2B21-F010 A, B 2B21-F077 A,(f) B(f)
- 2. Drywell pneumatic return isolation valves 2P70-F004
- 3. Recirculation line flow instmmentation line isolation valtes(9) w 2B31-F009 A, B, C, D 1 2B31-F010 A, B, C, D 2B31-F011 A, B, C, D 7
y 2B31-F012 A, B, C, D
- 4. Reciraalation pump seal pirge isolation valtes 2B31-F013 A, B 2B31-F017 A, B
- 5. Pecirculation line pressure instmmentation line isolation traltes(9) 2931-F057 A, B
- 6. Recirculation pure discharge pressure instmmentation line isolation va15es(9) 2B31-F040 A, D ,
I i
i-N
=
o.
Po (f) Air assist check valte
", (9) Excess flow check valte E I i
f . ,
O
_