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Category:TECHNICAL SPECIFICATIONS
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[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Delete or Modify Existing License Conditions,Surveillance Requirements That Have Been Completed & Exemptions That Are No Longer in Effect ML20211J1861997-10-0101 October 1997 Corrected TS Pages Unit 1 & 2 Page 3.4-8,Unit 1 Page 3.5-6 & Unit 2 Page 3.5-5 Provided in Order for Util to Issue Amends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
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ENCLOSURE 3 i
PLANT HATCH - UNIT 1 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 REQUEST TO REVISE TECHNICAL SPEClflCATIONS: !
TEMPORARY EXTENSION OF DIESEL GENERATOR LC0 PAGE CHANGE INSTRUCTIONS
'The proposed change to the Plant Hatch Unit 1 Technical Specifications will be incorporated as follows:
Remove ELqa Insert Page 3.5-10 3.5-10 3.9-5 3.9-5 -
1
..HL-2355 003813 E3-1 9208050122 920730 PDR ADOCK 05000321.
P. PDR-
,' LIMITI% CDwDIT10ws F0E Orf tA110w 50Rv[1LLANCE 6[00lttMEw15
+-
3.$.S. Minimus Core and Con,11jj;!g.n.i 4.$.G. Surveillance of Core and Cnntain-Cooline Systees Availati ntv sent Cooline 5vstees During any period when one of When it is determined that one the stan6by diesel generators of the standby diesel generators )
is inoperable is inoperable, all of the compo-
- operationis\imitedtolcontinued r! actor l nents in the RHR system LPCI days unless operability of the mode and containment cooling diesel generator is restored node connected to the operable within this period. During suth diesel generators shall be veri- d 7" days all of the conoonents f fied to be operable. *?
in the RHR system LPCI node "
and containment cooling mode h
, p 4 mode shall be operable. If this reduirement cannot be met, an crderly shutdown shall be initi- .
ated and the reactor shall be in the Cold shutdown Conditica within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Specification 3.g. provides further guidance on )
electrical system availability.
Any combination of inoperable components in the tore and con-tainment tooling systems shall not defeat the capability of the remaining operable components to fulfill the core and contain-ment cooling functions.
When irradiated fuel is in the reactor vessel and the reactor is in the Cold Shutdevn Condi-tion, both C5 systems and the LPCI and containment cooling subsystems of the RHR system may be inoperable provided that g the shutdown cooling subsystem tf the 4tHR system is operable in accordance with Specification 3.5.8.1.b and that no work is being done which has the potential for draining the reactor vessel.
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HATCH - UNIT 1 3.5-10 Amenoment No. TI, f(7,110 Ocf cp -/.2
4 LIMITIhG CONDITIONS FOR OPERATION 5URVEILLANCE RE0VIREMENT5 3.9.8.1. One Startuo Avuiliary Transformer 4.9.8.1. pne Startuo Auriliary Transformer (IC or 10) Inoperable or Only One f1C or ID) Inoperable or Oniv One Of f site Power Source Available Qf f,Jit# Power Source Available (230 kV Transmission Line) f 230 kV transmission Line)
Reactor operation is permissible When it is established that one for seven days from the date that startup auxiliary transformer one startup auxiliary transformer (1C or 10) is inoperable or in-(1C or 10) is inoperable or in- coming power is available from
(. coming power is available from only one 230 kV offsite trans-only one 230 kV offsite trans- mission line, verify correct '
mission line provided the in- breaker alignments and indica-creased Surveillance Require- ted powe availability within ments as stated in Specification one hour and at least once per 4.9.8.1. are implemented. eight hours thereafter, and k perform Surveillance Require-
".;.i t.e within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
me n t/t. *t. A . 3. n . I
- 2. One DieLel_ genera tor (I A.18. 2. Qne Die'11 Generator (1 A.18.
or IC) : noperable or IC) Inoperable From and after the date that one When it is estab18thed that one of the diesel generators is made diesel generator () A,18, or IC) or found to be inoperable, continued is inoperable, verify correct reactor operation is permissible in breaker alignments and indicated accordance with Specification 3.5.G. power availability within one houri for a period not to exceed seven and at least once per eight hours j days *provided that two 230 kV off- thereaf ter, and perfom surveill i
- site transmission lines are avail- ante Requirement 4.0 ".0.e within 8 able, both remaining diesel gen- 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> I erators and associated emergency thereafter.
buses are operable, and the in- M. '7. A . 7. 4 . l creased Surveillance Requirements '
as stated in Specification 4.9.B.2.
are implemented.
- 3. One 125/250 Volt DC Power System 3. One 125/250 Volt DC Power System (Plant Batterv 1 A or IB) Inoper- (Plant Battery 1A or 18) InoDer-ikli d.11 From and after the date that one When it is established that one of of the two 125/250 volt plant bat- the 125/250 volt DC power systems teries is made or found to be in- (plant t,.ttery 1 A or 18) is n.ade operable, continued reactor oper- or found to be inoperable, the ation is pemissible during the pilot cell voltage and specific succeeding seven (7) days within gravity and the overall battery
{ Slectrical safety considerations, voltage of the operable plant bat-provided repair work is initiated tery shall be; tested daily and de-immediately to return the failed termined to be sattsfactory.
component to an operable state, Specification 3.5.G. is satisfied.
(
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( HATCH - UNIT I 3.9-5 A,ncndment No.147
N
, , .LIMlilN U OND1110NS FOR OPERATION $URVilltdL NfMENTS 3.6.G. Minimum Core and Containment 4.5.G. Surveillance of Core and Contain-Coolina Systems Availability ment Coolino Svittml ]
During any period when one of When it is detemined that one the standby diesel generators of the standby diesel generators !
is inoperable, continued reactor is inonerable, all of the compo- !
operation is limited to 7* l nents in the RHR system LPCI l days unless operability of the mode and containment cooling .
diesel generator is restored mode connected to the operable within this period. During such diesel generators shall be veri-7* days all of the components l fied to be operable. '
in the RHR system LPCI mode i.nd containment cooling mode W e shall be operable. If this strement cannot be met, an f>rly shutdown shall be initi-
.4ea and the reactor shall be in the Cold Shutdown Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Specification 3.9. provides further guidance on electrical system availability.
-Any combination of inoperable components in the core and con-tainment cooling systems shall not defeat the capability of the remaining operable components to fulfill the core and contain-ment cooling functions.
When irradiated fuel is in the reactor vessel and the reactor is in the Cold Shutdown Condi-tion, both C5 systems and the LPCI and containment cooling subsystems of the RHR system may be inoperable.provided that the shutdown cooling subsystem of the RHR system is operable in accordance with Specification 3.5.B.I.b and that no work is being done which has the potential for draining the reactor vessel.
o
- The IB diesel generator may be inoperable for up to 14 days during the Hatch Unit 2 tenth refueling
. outage to perform preventative maintenance and
' modification work.
HATCH - UNIT 1 3.5-10 techsp\h\92-12Bu1\l70 4
, ' , - .,4, ,. - :-- -
e
[' LIM 111% COO 1110NS f 0R OPERA 110N $15MittMl P10J151MLNTS 3.9.B.1 One startuo Auxiliary Transforver 4.9.B.l. 00t_111riuo Auxiliary Tran1{pnet UCorID) InoDerable or Only One 11CorID) InoDCrable or Only One Qfft11e Power Sourte Available Offsite Power Sourte Available (230 by 1ransmission Line) (230 kV Transmission Line)
Reactor operation is permissible When it is established that or.e for seven days from the date that startup auxiliary transforrer one startup auxiliary transfomer (IC or 10) is inoperable or in-(10orID)isinoperableorin. cmirg pwer is available from coming power is available frun only one 230 kV offsite trans-only one 230 kV offsite trans- mission line, verify correct mission line provided the in- breaker aligments and indica-creased Surveillance Re<pire- tedpoweravailabilitywithin cents as stated in Specification one hour and at least once per 4.9.B.I. are i@lemented. eight hours thereafter, and perfom surveillance Require-cent 4.9 A.2.a.1 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. l
- 2. Qnt,01111]_f>tattitor (IA. IB. 2. One Diesel Generator f1A. IB.
or IC) Inopgn klg or IC) InoggrAbig from and after the date that one When it is estabitsbed that one of the diesel generators is nude diesel generator (IA,18, or IC) or found to be ineperable, continued is inoperable, verify correct reactor operation is pemissible in breaker aligments and indicated accort:ance with Specification 3.5.G. pwer availability within one hour for a period not to exceed seven and at least once per eight hours days
- provided that two 230 kV off- l thereafter, and perfom Surve111-site transmission lines are avail- anceRequirtment4.9.A.2.a.1withinj able, both rtmaining diesel gen- 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> erators and associated m ergency thereafter, buses are operable, and the in-creased Surveillance Requirments as stated in Specification 4.9.B.2.
are iglmented.
- 3. DDe 12W250 Volt DC Power System 3. Ont_121/21Q_yolt DC Power.,ints g ant Batterv 1A or IB) Inocer- (Plant B111ery LA or IB) Inoner-Abit Ahlt Frun and after the date that ont When it is established that one of of the two 125/250 volt plant bat- the125/250voltDCpowersystems teries is cade or found to be in- (plant battery 1A or IB) is made operable, continued reactor oper- or found to be inoperable, the atton is pemissible during the pilot cell voltage and specific succeedingseven(7)dayswithin gravity and the overall battery electrical safety considerations, voltage of the operable plant bat-provided repair work is initiated tery shall be tested daily and de-inrediately to rvtum the failed termined to be satisfactory, co m onent to an operable state, Specification 3.5.G. is satisfied,
- The IB diesel generator may be inoperable for up to 14 days during the Hatch Unit 2 tenth refueling outage to perfom preventative maintenance and nodification work.
HAICH - INil 1 3.9-5 techsp\h\92-12Vl\l47 I