ML20065K102
From kanterella
Jump to navigation
Jump to search
Letter Sequence Other | |
|---|---|
TAC:11158, (Approved, Closed) | |
Initiation
Questions
Results Other: ML20065J906, ML20065K102, ML20083D703, ML20084J700, ML20150F079, ML20207L458, ML20212J238 | |
MONTHYEARML20148A6741978-12-22022 December 1978
[Table View]Requests That Gap Remit Req Class 3 Fee of $4,000 for Review of 781201 Appl for Amend to Facil Oper Lic NPF-5 Re Tech Spec Changes to Establish & Rept Differential Settlement Valves for Class 1 Struc Listed on Table 3.7.8-1 of Specs Project stage: Approval ML20150F0791979-03-30030 March 1979 Requests Addl Info Re Tech Spec Changes for Settlement of Class I Structures,As Proposed in .Forwards Staff Position,Which Differs from That of Util.Requests Revision within 30 Days Project stage: Other ML20065K1021982-09-27027 September 1982 Tech Specs 3/4.7.7 Re Penetration Fire Barriers Project stage: Other ML20065K0911982-09-27027 September 1982 Application to Amend License NPF-5,deleting App a Tech Specs on Bldg Settlement & Withdrawing 781201,790814 & 1008 Submittals Re Differential & Total Settlement Values Based on Consolidation Settlement Project stage: Request ML20065J9061982-10-0101 October 1982 Forwards Remittance & Copies Omitted from Re Bldg Settlement Project stage: Other ML20083D7031983-12-0707 December 1983 Discusses Total Bldg Settlement of Control Bldg,Intake Structure & Unit 1 Reactor Bldg.Monitoring Process Will Be Continued Through Procedural Controls Rather than Tech Spec Limitations Project stage: Other ML20084J7001984-05-0404 May 1984 Advises of Inaccuracies Presented in 831207 Submittal Delineating Percentages of Total Allowable Bldg Settlement for Seismic Category 1 Structures.Changes Will Be Submitted Upon Completion of Engineering Analysis by 840525 Project stage: Other ML20138N7791985-12-18018 December 1985 Submits Info Re Total Settlement of Control Bldg,Intake Structure & Unit 1 Reactor Bldg,Replacing 831207 Submittal as Supplemented by .Tech Spec Settlement Values More Restrictive than FSAR Project stage: Supplement ML20155E9681986-04-0404 April 1986 Discusses 820927 Request for Elimination of Ref to Total & Differential Bldg Settlement from Tech Specs.Discussions W/ Project Manager & NRR Reviewer Established Acceptable Basis for Deletion of Tech Spec as Listed Project stage: Request ML20212J2381986-05-31031 May 1986 Rept on Settlement of Major Plant Structures Project stage: Other ML20207L4581986-11-30030 November 1986 Revised Rept on Settlement of Major Plant Structures Project stage: Other ML20207L4301987-01-0505 January 1987 Forwards Revised Rept on Settlement of Major Plant Structures, Clarifying Areas Discussed During 861021 Meeting Re Deletion of Refs to Bldg Settlement from Tech Specs Project stage: Meeting ML20212J1441987-01-21021 January 1987 Summary of 861021 Meeting W/Util in Bethesda,Md Re Util Request to Delete Bldg Settlement Monitoring Requirements from Tech Specs.Bechtel May 1986 Rept, Rept on Settlement of Major Plant Structures, Presented at Meeting,Encl Project stage: Meeting 1984-05-04 |
| ML20065K102 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 09/27/1982 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20065K094 | List: |
| References | |
| TAC-11158, NUDOCS 8210060278 | |
| Download: ML20065K102 (1) | |
Similar Documents at Hatch | |
|---|---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20212J2721999-10-0101 October 1999
[Table view]Proposed Tech Specs,Modifying DG Fuel Oil Storage Requirements ML20210G2971999-07-29029 July 1999 Proposed Tech Specs LCO 3.1.7 Re Standby Liquid Control Sys ML20203C5931999-02-0505 February 1999 Proposed Tech Specs Pages Revising TS to Implement Previously Approved Generic Changes ML20199J9081999-01-21021 January 1999 Proposed Tech Specs Increasing Allowable Values for Reactor Bldg & Refueling Floor Ventilation Exhaust Radiation Monitors ML20197H5171998-12-0404 December 1998 Proposed Tech Specs Section 2.1.1.2,deleting Footnote Which Specifies That SLMCPRs Are for Cycle 18 Only & TS Section 5.6.5.b.2 ML20236U2551998-07-22022 July 1998 Proposed Tech Specs Increasing Allowable Values for High Radiation Trip for Reactor Bldg & Refueling Floor Ventilation Exhaust Monitors ML20197K1861997-12-18018 December 1997 Marked-up Pages to Licenses DPR-57 & NPF-5,respectively. Proposed Changes Delete or Modify Existing License Conditions,Surveillance Requirements That Have Been Completed & Exemptions That Are No Longer in Effect ML20211J1861997-10-0101 October 1997 Corrected TS Pages Unit 1 & 2 Page 3.4-8,Unit 1 Page 3.5-6 & Unit 2 Page 3.5-5 Provided in Order for Util to Issue Amends 208 & 150 to Manual Holders ML20211A2301997-09-19019 September 1997 Proposed Tech Specs Page 2.0-1 & Corresponding mark-up Page Re SLMCPR ML20210J0491997-08-0808 August 1997 Proposed Tech Specs,Allowing Plant to Operate at Uprated Power Level of 2763 Mwt Which Represents Power Level Increase of 8% ML20141B8561997-05-0909 May 1997 Proposed Tech Specs,Revising Operability Requirements for Rod Block Monitor Sys ML20141B7591997-05-0909 May 1997 Proposed Tech Specs 2.1.1.2,revising Safety Limit Minimum Critical Power Ratio to Reflect Results of Cycle Specific Calculation Performed for Unit 1 Operating Cycle 18,expected to Commence in Nov 1997 HL-5376, Proposed Tech Specs 3.4.9 Re Reactor Coolant Sys Pressure & Temp Limits1997-04-29029 April 1997 Proposed Tech Specs 3.4.9 Re Reactor Coolant Sys Pressure & Temp Limits ML20133F3641997-01-0707 January 1997 Proposed Tech Specs Providing Alternate Method of Testing S/Rvs During Shutdown Conditions Rather than During Unit Startup as Is Currently Done ML20132G2261996-12-17017 December 1996 Proposed Tech Specs Re pressure-temp Limits ML20132E0161996-12-13013 December 1996 Proposed Tech Specs Re Physical Security & Contigency Plan & Guard Training & Qualification Plan ML20135D4881996-12-0303 December 1996 Proposed Tech Specs Revising SLMCPR Values Based Upon Unique plant-evaluations for Current Cycle 13 & Use of GE-13 Fuel in Next Cycle 14 ML20129H9181996-10-29029 October 1996 Proposed Tech Specs,Associating Changes W/Installation of Digital Power Range Neutron Monitoring Sys & Incorporation of long-term Stability Solution Hardware ML20128M8701996-10-0707 October 1996 Proposed Tech Specs to Licenses DPR-57 & NPF-5,increasing Nominal Mechanical Pressure Relief Setpoints for All SRVs & Allow Operation W/One SRV & Associated Functions Inoperable ML20113F5541996-09-19019 September 1996 Proposed Tech Specs,Clarifying Applicability of Certain Surveillances Addressing Rvp & Temp Limits & Replacing Vessel Pressure & Temp Limit Curves W/New Curves ML20117M2251996-09-11011 September 1996 Proposed Tech Specs,Authorizing Southern Nuclear to Become Licensed Operator & to Have Exclusive Responsibility & Control Over Physical Const,Operation & Maint of Plant ML20115J4861996-07-16016 July 1996 Proposed Tech Specs,Reflecting Changes Through June 1996, Satisfying Requirements of 10CFR50.71 ML20117H1391996-05-21021 May 1996 Proposed Tech Specs 3.5.2,ECCS - Shutdown & 3.5.2.2.b SR for Units 1 & 2 Revise to Change Unit 1 CST Water Level Requirement from 12 Feet to 13 Feet & Change Unit 2 CST Water Level Requirement from 12 Feet to 15 Feet ML20100H7431996-02-21021 February 1996 Proposed Tech Specs,Revising Changes of Drywell Air Temp LCO from 350 F to 150 F ML20094K3831995-11-10010 November 1995 Proposed Tech Specs,Reflecting Implementation of 10CFR50,App J,Option B ML20085K4011995-06-20020 June 1995 Proposed Tech Specs for Power Uprate ML20085A1661995-06-0606 June 1995 Proposed Tech Specs Re Secondary Containment Draw Down & Vacuum Surveillance Requirement Acceptance Criteria ML20082V3791995-05-0404 May 1995 Proposed Tech Specs,Minimizing Thermal Stratification Events ML20082L3331995-04-14014 April 1995 Proposed Tech Specs Re Elimination of Selected Response Time Testing Requirements from TS ML20081F3471995-03-14014 March 1995 Proposed Improved Ts,Permitting Drywell & Wetwell Purge Valves Isolated by Drywell Radiation Monitor Signal to Be Opened W/Inoperable Drywell Radiation Monitor ML20077S0331995-01-13013 January 1995 Proposed Tech Specs Allowing Plant to Operate at Uprated Power Level of 2558 Mwt ML20077D8921994-12-0202 December 1994 Proposed Deleted ETS ML20078G7161994-11-0101 November 1994 Proposed Tech Specs,Converting Current TSs to Improved TS Consistent w/NUREG-1433 ML20076L6911994-10-19019 October 1994 Proposed Improved Tech Specs,Rev F ML20149G3751994-10-13013 October 1994 Proposed Tech Specs,Lowering ATWS-RPT Setpoint by Approx 2 Ft 2 Inches Allowing Restarting Recirculation Pump Following RPT When Temp Differential Between Coolant at Reactor Bottom Head & Reactor Steam Dome Cannot Be Obtained ML20073G9631994-09-23023 September 1994 Proposed Improved Ts,Rev E ML20073D3231994-09-20020 September 1994 Proposed Tech Specs Change to Unit 1 TSs Re EDG Operability Requirements During Reactor Shut Down Conditions ML20072V3641994-08-31031 August 1994 Proposed Tech Specs Re Improved Standard Ts,Rev D ML20072H0571994-08-16016 August 1994 Proposed TS 3.9.C,allowing Shutdown Operations W/Only One of Two Required EDGs Aligned to Corresponding Core or Containment Cooling Sys ML20072E4021994-08-0808 August 1994 Proposed Tech Specs Re Rev Insertion Instructions Rev C ML20072B7541994-08-0404 August 1994 Proposed Tech Specs Re Traversing Incore Probe Operability Requirements ML20071H8381994-07-19019 July 1994 Proposed TS 3.3.6.6,allowing Less than Four Traversing in- Core Probe Machines to Be Operable ML20071H6851994-07-0808 July 1994 Proposed Tech Specs Re Improved Std Insertion Instructions, Consistent w/NUREG-1433 ML20069J3101994-06-0707 June 1994 Proposed Tech Specs Allowing Planned Testing at Plant to Demonstrate Capability to Operate Plant Up to Core Power Level of 2,558 Mwt ML20059E9231994-01-0606 January 1994 Revised Proposed TS Pages for Increase in Allowable MSIV Leakage Rate & Deletion of MSIV Leakage Control Sys ML20059L2051993-11-0909 November 1993 Proposed Tech Specs Changing Unit 1,Section 4.9 & Unit 2, Section 4.8 Re Diesel Generator Testing Under Hot Initial Conditions ML20058P8881993-10-19019 October 1993 Proposed Tech Specs Re Time Delay for RPS Electric Power Monitoring Sys Trips ML20046B6061993-07-30030 July 1993 Proposed Tech Specs for Implementation of New 10CFR20 Requirements ML20046B5561993-07-27027 July 1993 Proposed Tech Specs Showing Original & Unrelated Changes Re Removal of Main Steam Line Radiation Monitor Trips ML20045E7281993-06-28028 June 1993 Proposed TS 3.7.A.4 & 3.6.4.1 for Units 1 & 2,respectively, Allowing One or More Suppression chamber-drywell Vacuum Breakers to Open During Surveillance Testing 1999-07-29 Category:TECHNICAL SPECIFICATIONS & TEST REPORTS MONTHYEARML20212J2721999-10-0101 October 1999
[Table view]Proposed Tech Specs,Modifying DG Fuel Oil Storage Requirements ML20210G2971999-07-29029 July 1999 Proposed Tech Specs LCO 3.1.7 Re Standby Liquid Control Sys ML20210A4041999-07-15015 July 1999 Ei Hatch Nuclear Plant Unit 1,Extended Power Uprate Startup Test Rept for Cycle 19 ML20204J6031999-03-19019 March 1999 Ei Hatch Nuclear Plant Unit 2 Extended Power Uprate Startup Test Rept for Cycle 15 ML20203C5931999-02-0505 February 1999 Proposed Tech Specs Pages Revising TS to Implement Previously Approved Generic Changes ML20199J9081999-01-21021 January 1999 Proposed Tech Specs Increasing Allowable Values for Reactor Bldg & Refueling Floor Ventilation Exhaust Radiation Monitors ML20197H5171998-12-0404 December 1998 Proposed Tech Specs Section 2.1.1.2,deleting Footnote Which Specifies That SLMCPRs Are for Cycle 18 Only & TS Section 5.6.5.b.2 ML20236U2551998-07-22022 July 1998 Proposed Tech Specs Increasing Allowable Values for High Radiation Trip for Reactor Bldg & Refueling Floor Ventilation Exhaust Monitors ML20217A0861998-04-30030 April 1998 Ei Hatch Nuclear Plant,Units 1 & 2,Process for Implementing Technical Requirements of 10CFR54,License Renewal Rule HL-5558, Edwin I Hatch Nuclear Plant,Unit 1,Power Uprate Startup Test Rept for Cycle 181998-02-17017 February 1998 Edwin I Hatch Nuclear Plant,Unit 1,Power Uprate Startup Test Rept for Cycle 18 ML20197K1861997-12-18018 December 1997 Marked-up Pages to Licenses DPR-57 & NPF-5,respectively. Proposed Changes Delete or Modify Existing License Conditions,Surveillance Requirements That Have Been Completed & Exemptions That Are No Longer in Effect ML20211J1861997-10-0101 October 1997 Corrected TS Pages Unit 1 & 2 Page 3.4-8,Unit 1 Page 3.5-6 & Unit 2 Page 3.5-5 Provided in Order for Util to Issue Amends 208 & 150 to Manual Holders ML20211A2301997-09-19019 September 1997 Proposed Tech Specs Page 2.0-1 & Corresponding mark-up Page Re SLMCPR ML20210J0491997-08-0808 August 1997 Proposed Tech Specs,Allowing Plant to Operate at Uprated Power Level of 2763 Mwt Which Represents Power Level Increase of 8% HL-5438, Ei Hatch Nuclear Plant - Unit 2 Power Uprate Startup Test Rept for Cycle 141997-07-21021 July 1997 Ei Hatch Nuclear Plant - Unit 2 Power Uprate Startup Test Rept for Cycle 14 ML20141B7591997-05-0909 May 1997 Proposed Tech Specs 2.1.1.2,revising Safety Limit Minimum Critical Power Ratio to Reflect Results of Cycle Specific Calculation Performed for Unit 1 Operating Cycle 18,expected to Commence in Nov 1997 ML20141B8561997-05-0909 May 1997 Proposed Tech Specs,Revising Operability Requirements for Rod Block Monitor Sys HL-5376, Proposed Tech Specs 3.4.9 Re Reactor Coolant Sys Pressure & Temp Limits1997-04-29029 April 1997 Proposed Tech Specs 3.4.9 Re Reactor Coolant Sys Pressure & Temp Limits ML20133F3641997-01-0707 January 1997 Proposed Tech Specs Providing Alternate Method of Testing S/Rvs During Shutdown Conditions Rather than During Unit Startup as Is Currently Done ML20138G6271996-12-19019 December 1996 Rev 11 to ODCM for Ei Hatch Nuclear Plant ML20132G2261996-12-17017 December 1996 Proposed Tech Specs Re pressure-temp Limits ML20132E0161996-12-13013 December 1996 Proposed Tech Specs Re Physical Security & Contigency Plan & Guard Training & Qualification Plan ML20135D4881996-12-0303 December 1996 Proposed Tech Specs Revising SLMCPR Values Based Upon Unique plant-evaluations for Current Cycle 13 & Use of GE-13 Fuel in Next Cycle 14 ML20129H9181996-10-29029 October 1996 Proposed Tech Specs,Associating Changes W/Installation of Digital Power Range Neutron Monitoring Sys & Incorporation of long-term Stability Solution Hardware ML20128M8701996-10-0707 October 1996 Proposed Tech Specs to Licenses DPR-57 & NPF-5,increasing Nominal Mechanical Pressure Relief Setpoints for All SRVs & Allow Operation W/One SRV & Associated Functions Inoperable ML20113F5541996-09-19019 September 1996 Proposed Tech Specs,Clarifying Applicability of Certain Surveillances Addressing Rvp & Temp Limits & Replacing Vessel Pressure & Temp Limit Curves W/New Curves ML20117M2251996-09-11011 September 1996 Proposed Tech Specs,Authorizing Southern Nuclear to Become Licensed Operator & to Have Exclusive Responsibility & Control Over Physical Const,Operation & Maint of Plant HL-5192, Edwin I Hatch Nuclear Plant,Unit 1,Power Uprate Startup Test Rept for Cycle 171996-07-18018 July 1996 Edwin I Hatch Nuclear Plant,Unit 1,Power Uprate Startup Test Rept for Cycle 17 ML20115J4861996-07-16016 July 1996 Proposed Tech Specs,Reflecting Changes Through June 1996, Satisfying Requirements of 10CFR50.71 ML20212C1491996-05-31031 May 1996 Stability Monitor ML20117H1391996-05-21021 May 1996 Proposed Tech Specs 3.5.2,ECCS - Shutdown & 3.5.2.2.b SR for Units 1 & 2 Revise to Change Unit 1 CST Water Level Requirement from 12 Feet to 13 Feet & Change Unit 2 CST Water Level Requirement from 12 Feet to 15 Feet ML20100P1041996-03-0404 March 1996 Ei Hatch Nuclear Plant Unit 2 Power Uprate Startup Test Rept for Cycle 13 ML20100H7431996-02-21021 February 1996 Proposed Tech Specs,Revising Changes of Drywell Air Temp LCO from 350 F to 150 F ML20094K3831995-11-10010 November 1995 Proposed Tech Specs,Reflecting Implementation of 10CFR50,App J,Option B ML20093G9401995-10-0505 October 1995 Inservice Insp Program Third 10-Year Interval for Ei Hatch Nuclear Plant Units 1 & 2 ML20092H6461995-07-24024 July 1995 Ei Hatch Nuclear Plant Units 1 & 2 IST Program ML20085K4011995-06-20020 June 1995 Proposed Tech Specs for Power Uprate ML20086E8471995-06-19019 June 1995 Rev 0 to Field Disposition Instruction (Fdi) HT2-0121-12900. Fdi Documents Design Requirements & Matl Required to Install Stabilizers for Shroud Horizontal Welds ML20086E8311995-06-0909 June 1995 Rev 0 to Fabrication Spec 25A5719, Fabrication of Shroud Stabilizer ML20086E8141995-06-0606 June 1995 Rev 1 to Code Design Spec 25A5717, Shroud Stabilizers ML20085A1661995-06-0606 June 1995 Proposed Tech Specs Re Secondary Containment Draw Down & Vacuum Surveillance Requirement Acceptance Criteria ML20086E8121995-05-17017 May 1995 Rev 0 to Design Spec 25A5718, Shroud Repair Hardware ML20082V3791995-05-0404 May 1995 Proposed Tech Specs,Minimizing Thermal Stratification Events ML20082L3331995-04-14014 April 1995 Proposed Tech Specs Re Elimination of Selected Response Time Testing Requirements from TS ML20081F3471995-03-14014 March 1995 Proposed Improved Ts,Permitting Drywell & Wetwell Purge Valves Isolated by Drywell Radiation Monitor Signal to Be Opened W/Inoperable Drywell Radiation Monitor ML20077S0331995-01-13013 January 1995 Proposed Tech Specs Allowing Plant to Operate at Uprated Power Level of 2558 Mwt ML20077D8921994-12-0202 December 1994 Proposed Deleted ETS ML20078G7161994-11-0101 November 1994 Proposed Tech Specs,Converting Current TSs to Improved TS Consistent w/NUREG-1433 ML20076L6911994-10-19019 October 1994 Proposed Improved Tech Specs,Rev F ML20149G3751994-10-13013 October 1994 Proposed Tech Specs,Lowering ATWS-RPT Setpoint by Approx 2 Ft 2 Inches Allowing Restarting Recirculation Pump Following RPT When Temp Differential Between Coolant at Reactor Bottom Head & Reactor Steam Dome Cannot Be Obtained 1999-07-29 |
Text
, . - j PLANT SYSTEMS BASES 3/4.7.7 PENETRATION FIRE BARRIERS The functional integrity of the penetration fire barriers ensures that fires will be confined or adequately retarded from spreading to adjacent portions of the facility. This design feature minimizes the possibility of a single fire rapidly involving several areas of the facility prior to detection and extinguishment. The penetration fire barriers are a passive element in the facility fire protection program and are subject to periodic inspections.
During periods of time when the barriers are not functional, a continuous fire watch is required to be maintained in the vicinity of the affected barrier until the barrier is restored to functional status unless the OPERABILITY of the fire detection instruments, providing coverage of the fire detection zones on each side of the non-functional barriers, has been demonstrated.
HATCH - UNIT 2 B 3/4 7-4
~ iE10060278 820927
( -E 1 PDR ADOCK 05000366
.P_ PDR
_ _
Retrieved from "https://kanterella.com/w/index.php?title=ML20065K102&oldid=3548715"