Similar Documents at Hatch |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20212J2721999-10-0101 October 1999 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Delete or Modify Existing License Conditions,Surveillance Requirements That Have Been Completed & Exemptions That Are No Longer in Effect ML20211J1861997-10-0101 October 1997 Corrected TS Pages Unit 1 & 2 Page 3.4-8,Unit 1 Page 3.5-6 & Unit 2 Page 3.5-5 Provided in Order for Util to Issue Amends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
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20212J2721999-10-0101 October 1999 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
[Table view] |
Text
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@ LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS p
'3.7.A.5. Oxygen Concentration 4.7.A.5 0xygen Concentration L a. After completion of the startup' The primary containment test program.and demonstration. Oxygen concentration shall
-~ o f plant electrical. output, the be measured and recorded' n .' primary containment ' atmosphere daily in the main control shall be reduced to less.than room.
4%Loxygen with nitrogen gas dur-ing~ reactor power operation with reactor coolant pressure above 100 psig, except as' stated in
- Specification 3.7.A.5.b.
- b. Within the 24-hour
- period sub- *A 72-hour period _is allowed sequent to placing the reactor .for the startup in progress in the Run Mode following a shut- on February 7,1982.
down, the containment atmosphere oxygen concentration shall be re-duced to less than 4% by volume and maintained in this condition. 'De-inerting may commence 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to a shutdown. ,
3i 6. Containment Atmosphere Dilution (CAD) 6. Containment- Atmosphere Dilution (CAD)
- a. Operability Requirements a. Functional Test
'After completion of the startup test The post-LOCA Containment program and demonstration of plant- Atmosphre Dilution (CAD) electrical output and thereafter System shall be' functionally whenever the reactor is in power .
tested once per operating operation, the post-LOCA containment cy cle.
Atmosphere Dilution (CAD) System -
must be operable and capable of supplying nitrogen to the' primary containment for. dilution if required by post-LOCA conditions. If this
' specification cannot be met, the system must; be restored to an operable condition within seven days or the reactor must be taken out of power operation.
- b. Seven-Dcy Nitrogen Supply Seven-Day Nitrogen S,upply After completion 07 the startup test The level in the liquid program and demonstration of plant nitrogen storage tanks !
electric output and thereafter shall be recorded twice ;
whenever the reactor is in power l operation, the CAD System shall con- i tain a minimum of 2000 gallons of , )
11guld nitrogen. If this specification cannot be met, the minimum volume will i be restored within seven days or the j reactor must be taken out of power ;
operation. !
8711050002 880228 3,7_9 PDR ADOCK 05000321 p PDR
- I
7_
[*G y.; h 3, .
f L
l' Whenever the reactor is in power - .
Instrumentation Surveillance'is L operation, there shall be at least. listed in Table 4.2-ll.-
one CAD System H2 and 02 analyzer 'l:
serving the primary containment. -
If one H2 and.02 analyzer is in-
[.: . operable, the reactor may remain-inperation o for.a period not to;
' exceed seven days.
1
- d. Post-LOCA Repressurization Limit The maximum. post-LOCA primary con-tainment repressurization limit !
-allowable usirg the CAD System l shall be 30 psig. Venting via the SGTS to the main stack must be initiated at 30 psig following the initial post-LOCA pressure peak.
-7. Drywell-Suppression Chamber 7. DIywell-Suppression' Chamber ,
Differential Pressure -Differential Pressure-
' Differential pressure between the The pressure differential drywell and suppression chamber shall between the drywell. and . ,~ l be maintained equal to or greater suppression chamber shall !
than 1.5 psid except as'specified in be recorded once each shift. 1 (1)'and (2) below: -If this specifica- l tion cannot be met, and the differential pressure cannot be restored within the ,
subsequent six (6) hour ' period, an orderly shutdown shall be initiated ,
and the reactor shall be in a Hot .l
' Shutdown condition in six (6) hours i and a Cold Shutdown condition in the following eighteen-(18) hours.
]
- 1) This differential pressure shall l be established within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> * *A 72-hour period is allowed after having placed the Mode for the start-up in progress .
Switch in the RUN moue. The dif- -on February 7,1982. i ferential pressure may be removed f within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />' prior to achiev- 1 ing a shutdown. !
- 2) This differential pressure may be decreased to less than 1.5 psid - 4 for a maximum of four h,gurs during required operability testing of the HPCI system pump, the RCIC system pump, and the drywell-pressure suppression chamber vacuum breakers.
3.7-10
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