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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Delete or Modify Existing License Conditions,Surveillance Requirements That Have Been Completed & Exemptions That Are No Longer in Effect ML20211J1861997-10-0101 October 1997 Corrected TS Pages Unit 1 & 2 Page 3.4-8,Unit 1 Page 3.5-6 & Unit 2 Page 3.5-5 Provided in Order for Util to Issue Amends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 Edwin I. Hatch Nuclear Plant - Unit 2 Request to Revise Technical Specifications for Traversing Incore Probe (TIP) Operability Requirements Page Change Instructions Remove Page Insert Page 3/4 3-57 3/4 3-57 3/4 3-57b B 3/4 3-4 B 3/4 3-4 F
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INSTRUMENTATION TRAVERSING INCORE PROBE SYSTEM LIMITING CONDITION FOR OPERATION 3.3.6.6 The traversing incore probe system shall be OPERABLE with: ,
- a. Four movable detectors, drives, and readout equipment to map the l core, and
- b. Indexing equipment to allow all required detectors to be normalized in l a common location.
APPLICABILITY:
When the traversing incore probe is used for:
- a. Recalibration of the LPRM detectors and
- b. Monitoring the APLHGR, LHGR, or MCPR.
ACTION:
- a. With one or more TIP measurement locations inoperable, required measurements may be performed as described in 1 or 2 below.
- 1. TIP data for an inoperable measurement location may be replaced by data ,
obtained from that string's redundant (symmetric) counterpart if the substitute TIP data were obtained from an operable measurement location and the control rod pattern is octant symmetric, provided the total TIP uncertainty for the present cycle has been measured to be less than 8.7 percent.
- 2. TIP data for an inoperable measurement location may be replaced by data obtained from the on-line core monitoring system (process computer) normalized with available operating measurements, provided the total number of simulated channels (measurement locations) does not exceed eight,
- b. Otherwise, with the TIP system inoperable, suspend use of the system for the above applicable monitoring or calibration functions.
- c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
HATCH - UNIT 2 3/4 3-57 techsp\h\94-12u2. pro \l15 l
INSTRUMENTATION ;
TRAVERSING INCORE PROBE SYSTEM LIMITING CONDITION FOR OPERATION 1
1 SURVEILLANCE RE0VIREMENTS l 4.3.6.6 The traversing incore probe system shall be demonstrated OPERABLE by normalizing each of the above required detector outputs prior to or during use when required for the above applicable monitoring or calibration functions, if not performed within the previous 31 EFPD. .
b HATCH - UNIT 2 3/4 3-57a techsp\h\94-12u2. pro \115 l
1 (This page intentionally left blank.)
UMT2 3/4 3-57b techsp\h\94-12u2. pro \0 l
INSTRUMENTATION BASES MONITORING INSTRUMENTATION (Continued) 3/4.3.6.4 POST-ACCIDENT MONITORING INSTRUMENTATION l
The OPERABILITY of the post-accident monitoring instrumentation ensures that sufficient information is available on selected plant param-eters to monitor and assess important variable following an accident.
3/4.3.6.5 SOURCE RANGE MONITORS The source range monitors provide the operator with information on the status of the neutron level in the core at very low power levels during startup. At these power levels,- reactivity additions should not be made without this flux level information available to the operator. When the intermediate range monitors are on scale adequate information is available without the SRMs and they can be retracted.
3/4.3.6.6 TRAVERSING INCORE PROBE SYSTEM The OPERABILITY of the traversing incore probe system with the specified minimum complement of equipment ensures that the measurements obtained from use of this equipment accurately represent the spatial neutron flux distribution in the reactor core.
The specification allows use of substituted TIP data from symmetric channels, adjusted by the plant computer to remove machine and power level dependent biases, if the control rod pattern is symmetric. The source of substituted data may also be calculations performed by the on-line computer core monitoring system which are normalized to available real data. Symmetry is not required for substitution of calculated readings.
3/4.3.6.7 MCRECS ACTUATION INSTRUMENTATION The OPERABILITY of the MCRECS ensures the necessary protective actions will be automatically initiated to provide protection for control room personnel.
3/4.3.6.8 (Deleted)
HATCH - UNIT 2 B 3/4 3-4 techsp\h\94-12u2. pro \96 l
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INSTRUMENTATION
- TRAVERSINr,INCORE PROBE SYSTEM
-LIMITING CONDITION FOR OPERATION 3.3.6.6. The traversing incore probe system shall be OPERABLE with: i
- a. Four/movabledetectors,drivesandreadoutequipmenttomapthe l core, and
( b. Indexing equipment to allow all,fettr[ detectors to be normalized in a common location. g pg i l
APPLICABILITY:
When the traversing incore probe is used for:
- a. Recalibration of the LPRM detectors and
- b. Monitoring the APLHGR, LHGR, or MCPR l
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%7%e'"%c(lib'"! v' 'g*'L1 "c'y*"' ' 'T"f SURVEILLANCE RE0VIREMENTS 4.3.6.6. The traversing incore probe system shall be demonstrated OPERABLE by normalizing each of the above required detector outputs prior to or during use when required for the above applicable monitoring or calibration-functions, if not performed within the previous 31 EFPD.
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- 0perabi44ty-requirements-c:n bc ::st-with-three-movable-detecters-unt44-
{i -ths and of-Cycle 19r HATCH . UNIT 2 3/4 3-57 Amendment No. 43, 115
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- a. With one or more TIP measurement locations inoperable, required n;easurements may be performed as described in 1 or 2 below. I
- 1. TIP data for an ince trable measurement location may be replaced by data obtained from that string's redundant (symmetric) counterpart if the substitute TIP data were obtained from an operable measurement location and the control rod pattern is octant symmetric, provided the total TIP l uncertainty for the present cycle has been measured to be less than 8.7 percent.
- 2. TIP data for an inoperable measurement location may be replaced by data obtained from the on-line core monitoring system (process computer) normalized with available operating measurements, provided the total number of simulated channels (measurement locations) does not exceed eight. I
- b. Otherwise, with the TIP system inoperable, suspend use of the system for the above applicable monitoring or calibration functions. ;
- c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
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INSTRUMENTATION t
BASES MONITORING INSTRUMENTATION (Continued) 3/4.3.6.4 POST-ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the post-accident monitoring instrumentation ensures that sufficient information is available on selected plant param-eters to monitor and a ness important variable following an accident. ..
).t 3/4.3.6.5 SOURCE RANGE MONITORS The source range monitors provide the operator with information on the status of the neutron level in the core at very low power levels -
during startup. At these power levels, reactivity additions should not be made without this flux level information available to'the operator. When the intermediate range monitors are on scale adequate information is i available without the SRMs and they can be retracted. >
3/4.3.6.6 TRAVERSING INCORE PROBE SYSTEM G
N T . '^ OPERABIL Y of the y aversing ore probe system with the '
spe i ie niin mu om (eme { f e' quip nt nurgstpf t me remen s d obtpnedf/om 3e o this equ, 'ent\ cura y re y'es t. spa ial neytr n ux i tri ft re/c, torc e. ll tio se 0P fiAB > TY o his 'l s/ stem eonsprftd y irrf'dating 'eac dt tokt e us an h
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3/4.3.6.7 MCRECS ACTUATION INSTRUMENTATION l .
The OPERABILITY of the MCRECS ensures the necessary protective L actions will be automatically initiated to provide protection for control room personnel. S
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HATCH - UNIT 2 B 3/4 3-4 Amendment No. 79,,96 4 t
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The OPERABILITY of the traversing incore probe system with the I specified minimum complement of equipment ensures that the measurements obtained from use of this equipment accurately represent the spatial neutron flux distribution in the reactor core. i l The specification allows use of substituted TIP data from symmetric channels, I
adjusted by the plant computer to remove machine and power level dependent biases, j
if the control rod pattern is symmetric. The source of substituted data may also ;
be calculations performed by the on-line computer core monitoring system which are normalized to available real data. Symmetry is not required for substitution of calculated readings. ,
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