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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20210P5971999-08-11011 August 1999 Proposed Tech Specs SR 3.3.7.3,replacing Analytical Limits Currently Specified as Acceptance Criteria with Allowable Values,Per Calculation E4C-098,change Notice 25 ML20210P6301999-08-10010 August 1999 Corrected Proposed Tech Specs Re Diesel Generator Testing ML20210N5121999-08-0909 August 1999 Proposed Cycle 10 Update to TS Bases That Have Been Revised Between 980101-990630 ML20195E5171999-06-0808 June 1999 Proposed Tech Specs Pages Re Application for Amend to Licenses NPF-10 & NPF-15,to Revise TS 3.5.2,3.1.9,3.7.1 & 5.1.7.5 ML20207A3911999-05-24024 May 1999 Proposed Tech Specs 3.8,clarifying Bases for SRs 3.8.1.7, 3.8.1.12 & 3.8.1.15 ML20199D0391999-01-13013 January 1999 Proposed Tech Specs Conservatively Restricting Required Actions Completion Time to Close All Containment Penetrations Providing Direct Access from Containment Atmosphere to Outside Atmosphere ML20206R2801999-01-11011 January 1999 Proposed Tech Specs to Increase Min Required Vol of Water in Condensate Storage Tank T-120 from 280,000 to 360,000 Gallons ML20198L6211998-12-31031 December 1998 Proposed Tech Specs 3.3.5 Re ESFAS Instrumentation ML20198G4001998-12-22022 December 1998 Proposed Tech Specs,Allowing SG Tube Repair Using W Laser Welded Sleeving as Alternative SG Tube Repair to Either ABB-CE ML20196H9321998-12-0404 December 1998 Proposed Tech Specs Reducing RCS Temp & Revising Volumetric Min Flow Rate ML20195J9021998-11-23023 November 1998 Proposed Tech Specs Revising TS 3.3.1, RPS Instrumentation - Operating ML20195J9551998-11-23023 November 1998 Proposed Tech Specs Re Turbine Missile Protection ML20155B8741998-10-20020 October 1998 Proposed Tech Specs Adding SR to TS 3.3.9, CR Isolation Signal ML20154J2991998-10-0909 October 1998 Proposed Corrected Tech Specs Pages for 980511 Suppl 1 to Amend Application Re App J,Primary Containment Leakage Testing for water-cooled Power Reactors,Option B ML20153G7511998-09-22022 September 1998 Proposed TSs Revising TS 3.3.1, RPS Instrumentation - Operating, Re Rt Operating Bypass Removal Process Variable ML20151W6801998-09-10010 September 1998 Proposed Tech Specs Eliminating Requirements for Hydrogen Control Sys from Low Power Plant License Conditions 2.C(19)i & from TSs 3.3.11 & 3.6.7 ML20151T6561998-09-0404 September 1998 Proposed Tech Specs Section 3.4.10,increasing as-found Psv Setpoint Tolerances ML20236S6241998-07-22022 July 1998 Proposed Tech Specs Section 3.8.1,extending Offsite Circuit Completion Time from 72 H & 6 Days from Discovery of Failure to Meet LCO to 72 H & 17 Days from Discovery of Failure to Meet LCO ML20249B4291998-06-19019 June 1998 Proposed Tech Specs Changes Reducing Minimum Primary RCS Cold Leg Temp from 544 F to 535 F Between 70% & 100% Rated Thermal Power Levels ML20216B6201998-05-11011 May 1998 Proposed Tech Specs Re App J,Primary Reactor Containment Leakage Testing for water-cooled Power Reactors,Option B ML20216B4141998-05-0707 May 1998 Proposed Tech Specs Pages,Revising TS Section 1.1, Definitions, to Change Reference Used for Obtaining Dose Conversion Factors for Calculating Dose Equivalent I-131 ML20217P8471998-04-0606 April 1998 Proposed Tech Specs Revising Containment Isolation Valves Completion Times ML20216C0051998-03-0606 March 1998 Proposed Tech Specs,Eliminating Ref to Inverters in TS 3.4.12.1 ML20199K6451998-02-0303 February 1998 Proposed Tech Specs 3.5.1,extending Completion Time for Single Inoprable SIT from 1 H to 24 H & Adding New TS 5.5.2.14, Configuration Risk Mgt Program ML20198H8511998-01-0909 January 1998 Proposed Tech Specs 3.5.2 Re Extension of Completion Time for Low Pressure Safety Injection Train ML20198H6881998-01-0909 January 1998 Proposed Tech Specs 3.5.1 Re Extension of Completion Time for Safety Injection Tanks ML20198H7601998-01-0909 January 1998 Proposed Tech Specs 3.8.1 Re Extension of EDG Completion Time ML20198E6051998-01-0202 January 1998 Proposed Tech Specs Pages,Revising TS 3.7.5 & Bases to Indicate Turbine Driven AFW Pump Is Operable When Running in Manual Mode to Support Plant Startups,Shutdowns & Testing ML20197C7281997-12-19019 December 1997 Proposed Tech Specs Reducing Pressurizer Water Level Required for Operability ML20199C6391997-11-14014 November 1997 Proposed Tech Specs,Revising Ufsar,Section 3.5, Missile Protection to Allow Use of Probability of Damage to Critical Components in Evaluating tornado-generated Missile Protection Barriers ML20148R4051997-06-30030 June 1997 Proposed Tech Specs Deleting SONGS Unit 2 License Condition 2.C(19)b & Revising SONGS Unit 2 & 3 TS 3.3.1,3.3.2,3.3.5, 3.3.10,3.3.11,3.4.7,3.4.12.1,3.7.5,5.5.2.10 & 5.5.2.11 ML20141B4481997-06-18018 June 1997 Proposed Tech Specs Revising TS 3.8.1, AC Sources - Operating & Applicable Bases to More Clearly Reflect Safety Analysis & Testing Conditions ML20198R0281997-05-30030 May 1997 Proposed Tech Specs Re Revised Bases Pages for Songs,Units 2 & 3 ML20137V2501997-04-15015 April 1997 Proposed Tech Specs 3.8.1, AC Sources - Operating, Revising SR 3.8.1.8 & Applicable Bases Allowing Credit Overlap Testing ML20134P9941997-02-21021 February 1997 Proposed Tech Specs Clarifying Note Which Relays Will Not Be Response Time Tested Until Next Songs,Unit 3 Refueling Outage to Satisfy SR 3.3.5.6 of TS 3.3.5, ESFAS Instrumentation ML20138L1151997-02-18018 February 1997 Proposed Tech Specs Defering Implementation of SR 3.3.5.6 of TS 3.3.5, ESFAS Instrumentation, for 30 Subgroup Relays Until Next Refueling Outage on Songs,Unit 3 ML20134M0831997-02-16016 February 1997 Proposed Tech Specs Re Requirements of SR 3.3.5.6 of TS 3.3.5, ESFAS Instrumentation ML20134J6991997-02-0707 February 1997 Proposed Tech Specs SR 3.1.5.4, CEA Alignment ML20134G7911997-02-0606 February 1997 Proposed Tech Specs 3.1.5, CEA Alignment ML20134A9911997-01-24024 January 1997 Proposed Tech Specs Revising SR 3.8.1.9 to TS 3.8.1, AC Sources - Operating, Which More Accurately Reflects Safety Analysis Conditions ML20133G9101997-01-14014 January 1997 Proposed Tech Specs 3.8.1.14 & 3.8.1.15, AC Sources - Operating, Surveillance Requirements ML20133F7741997-01-13013 January 1997 Proposed Tech Specs Providing Followup to Request for Discretionary Enforcement from SR 3.0.3 Requirements Delaying Implementation of SR 3.8.1.14 & 3.8.1.15 of TS 3.8.1,until NRC Approves Revs ML20128P3631996-10-11011 October 1996 Proposed Tech Specs Reinstating Provisions of TS Revised as Part of Amends 127 & 116 ML20117K9931996-08-30030 August 1996 Proposed Tech Specs,Clarifying Figures 3.7.18-1 & 3.7.18-2 by Adding Line at 4.8 W/O Initial U-235 Enrichment to Explicity Show That Acceptable Zone of Operation Ends at Maximum of 4.8 W/O ML20116C6801996-07-29029 July 1996 Proposed Tech Specs,Consisting of Change Request 443, Permitting Increase in Licensed Storage Capacity of Spent Fuel Pools,By Allowing Spent Fuel to Be Consolidated After Min Required Time in SFPs ML20113C2561996-06-25025 June 1996 Proposed Tech Specs,Revising TS 3.3.11, Pami, & 5.5.2.13, Diesel Fuel Oil Testing Program ML20117L0611996-06-11011 June 1996 Revised Proposed Tech Specs Re LCO 3.3.11, Post Accident Monitoring Instrumentation (Pami) ML20112D4611996-06-0303 June 1996 Proposed Tech Specs,Reinstating Provisions of Current SONGS TS Revised as Part of NRC Amends 127 & 116 ML20117J8391996-05-30030 May 1996 Proposed Tech Specs,Consisting of Change Number 164, Requesting Changes to SR 3.6.1.1,SR 3.6.2.1 & SR 3.6.3.6 Which Allows Implementation of Option B to 10CFR50,App J ML20112D0351996-05-29029 May 1996 Approved Tech Specs,Amends 127 & 116 & Proposed TS for Units 2 & 3 1999-08-09
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211B2381999-08-31031 August 1999 Revised Interjurisdictional Policy for Songs ML20210P5971999-08-11011 August 1999 Proposed Tech Specs SR 3.3.7.3,replacing Analytical Limits Currently Specified as Acceptance Criteria with Allowable Values,Per Calculation E4C-098,change Notice 25 ML20210P6301999-08-10010 August 1999 Corrected Proposed Tech Specs Re Diesel Generator Testing ML20210N5121999-08-0909 August 1999 Proposed Cycle 10 Update to TS Bases That Have Been Revised Between 980101-990630 ML20196A9981999-06-17017 June 1999 Revised Pages to Risk-Informed IST Program for Sce ML20195E5171999-06-0808 June 1999 Proposed Tech Specs Pages Re Application for Amend to Licenses NPF-10 & NPF-15,to Revise TS 3.5.2,3.1.9,3.7.1 & 5.1.7.5 ML20207A3911999-05-24024 May 1999 Proposed Tech Specs 3.8,clarifying Bases for SRs 3.8.1.7, 3.8.1.12 & 3.8.1.15 ML20216D9741999-05-0707 May 1999 Rev 3 to Abnormal Operating Instruction SO23-13-14, Reactor Coolant Leak ML20199D0391999-01-13013 January 1999 Proposed Tech Specs Conservatively Restricting Required Actions Completion Time to Close All Containment Penetrations Providing Direct Access from Containment Atmosphere to Outside Atmosphere ML20206R2801999-01-11011 January 1999 Proposed Tech Specs to Increase Min Required Vol of Water in Condensate Storage Tank T-120 from 280,000 to 360,000 Gallons ML20198L6211998-12-31031 December 1998 Proposed Tech Specs 3.3.5 Re ESFAS Instrumentation ML20198L5111998-12-23023 December 1998 Rev 0 to SONGS Risk-Informed Inservice Testing Program, Engineering Analysis & Program Description ML20198G4001998-12-22022 December 1998 Proposed Tech Specs,Allowing SG Tube Repair Using W Laser Welded Sleeving as Alternative SG Tube Repair to Either ABB-CE ML20196H9321998-12-0404 December 1998 Proposed Tech Specs Reducing RCS Temp & Revising Volumetric Min Flow Rate ML20195J9021998-11-23023 November 1998 Proposed Tech Specs Revising TS 3.3.1, RPS Instrumentation - Operating ML20195J9551998-11-23023 November 1998 Proposed Tech Specs Re Turbine Missile Protection ML20155B8741998-10-20020 October 1998 Proposed Tech Specs Adding SR to TS 3.3.9, CR Isolation Signal ML20154J2991998-10-0909 October 1998 Proposed Corrected Tech Specs Pages for 980511 Suppl 1 to Amend Application Re App J,Primary Containment Leakage Testing for water-cooled Power Reactors,Option B ML20153G7511998-09-22022 September 1998 Proposed TSs Revising TS 3.3.1, RPS Instrumentation - Operating, Re Rt Operating Bypass Removal Process Variable ML20151W6801998-09-10010 September 1998 Proposed Tech Specs Eliminating Requirements for Hydrogen Control Sys from Low Power Plant License Conditions 2.C(19)i & from TSs 3.3.11 & 3.6.7 ML20151T6561998-09-0404 September 1998 Proposed Tech Specs Section 3.4.10,increasing as-found Psv Setpoint Tolerances ML20206N5381998-08-12012 August 1998 Rev 15 to Emergency Operating Instruction S023-12-7, Loss of Forced Circulation/Loss of Offsite Power, Pages 1,3,18, 39 & 122 ML20236S6241998-07-22022 July 1998 Proposed Tech Specs Section 3.8.1,extending Offsite Circuit Completion Time from 72 H & 6 Days from Discovery of Failure to Meet LCO to 72 H & 17 Days from Discovery of Failure to Meet LCO ML20249B4291998-06-19019 June 1998 Proposed Tech Specs Changes Reducing Minimum Primary RCS Cold Leg Temp from 544 F to 535 F Between 70% & 100% Rated Thermal Power Levels ML20216B6201998-05-11011 May 1998 Proposed Tech Specs Re App J,Primary Reactor Containment Leakage Testing for water-cooled Power Reactors,Option B ML20216B4141998-05-0707 May 1998 Proposed Tech Specs Pages,Revising TS Section 1.1, Definitions, to Change Reference Used for Obtaining Dose Conversion Factors for Calculating Dose Equivalent I-131 ML20217P8471998-04-0606 April 1998 Proposed Tech Specs Revising Containment Isolation Valves Completion Times ML20206N5231998-03-16016 March 1998 Rev 15 to Emergency Operating Instruction S023-12-1, Std Post Trip Actions ML20216C0051998-03-0606 March 1998 Proposed Tech Specs,Eliminating Ref to Inverters in TS 3.4.12.1 ML20206E6001998-02-27027 February 1998 Rev 31 to S023-ODCM, SONGS Units 2 & 3 Odcm ML20199K6451998-02-0303 February 1998 Proposed Tech Specs 3.5.1,extending Completion Time for Single Inoprable SIT from 1 H to 24 H & Adding New TS 5.5.2.14, Configuration Risk Mgt Program ML20206N5021998-01-30030 January 1998 Temporary Change Notice 2-1 to Rev 2 to Alarm Response Instruction S023-15-50.A1, Annunciator Panel,50A Pzr/Cea Windows 1-30, Pages 1,3,14,15 & 62-64 ML20198H8511998-01-0909 January 1998 Proposed Tech Specs 3.5.2 Re Extension of Completion Time for Low Pressure Safety Injection Train ML20198H7601998-01-0909 January 1998 Proposed Tech Specs 3.8.1 Re Extension of EDG Completion Time ML20198H6881998-01-0909 January 1998 Proposed Tech Specs 3.5.1 Re Extension of Completion Time for Safety Injection Tanks ML20198E6051998-01-0202 January 1998 Proposed Tech Specs Pages,Revising TS 3.7.5 & Bases to Indicate Turbine Driven AFW Pump Is Operable When Running in Manual Mode to Support Plant Startups,Shutdowns & Testing ML20197C7281997-12-19019 December 1997 Proposed Tech Specs Reducing Pressurizer Water Level Required for Operability ML20199C6391997-11-14014 November 1997 Proposed Tech Specs,Revising Ufsar,Section 3.5, Missile Protection to Allow Use of Probability of Damage to Critical Components in Evaluating tornado-generated Missile Protection Barriers ML20198P4011997-10-31031 October 1997 Rev 2 to Document 90022, Susceptibility of RCS Alloy 600 Nozzles to Primary Water Stress Corrosion Cracking & Replacement Program Plan ML20217K0081997-10-16016 October 1997 Rev 1 to Evaluation of SONGS Unit 3 SG Eggcrate Support Condition-Cycle 9 ML20203E1201997-09-11011 September 1997 Rev 1 to S-PENG-DR-003, Addendum to Piping Analytical Stress Rept for SCE San Onofre Units 2 & 3. W/Memo from C Chiu to Jt Reilly Re Corrective Action for Unit 3 Pressurizer Nozzle Failure in Mar 1986 ML20203D8421997-08-28028 August 1997 Rev 1 to S-PENG-DR-002, Addendum to Pressurizer Analytical Stress Rept for SCE San Onofre Units 2 & 3 ML20203D8981997-07-0303 July 1997 Rev 0 to TR-PENG-042, Test Rept for Mnsa Hydrostatic & Thermal Cycle Tests ML20203D8761997-07-0202 July 1997 Rev 0 to TR-PENG-033, Seismic Qualification of San Onofre, Units 2 & 3 Mnsa Clamps for Pressurizer Instrument Nozzles & RTD Hot Leg Nozzles ML20148R4051997-06-30030 June 1997 Proposed Tech Specs Deleting SONGS Unit 2 License Condition 2.C(19)b & Revising SONGS Unit 2 & 3 TS 3.3.1,3.3.2,3.3.5, 3.3.10,3.3.11,3.4.7,3.4.12.1,3.7.5,5.5.2.10 & 5.5.2.11 ML20141B4481997-06-18018 June 1997 Proposed Tech Specs Revising TS 3.8.1, AC Sources - Operating & Applicable Bases to More Clearly Reflect Safety Analysis & Testing Conditions ML20198R0281997-05-30030 May 1997 Proposed Tech Specs Re Revised Bases Pages for Songs,Units 2 & 3 ML20217P9981997-05-28028 May 1997 Rev 30 to SONGS Unit 2 & 3, Odcm ML20137V2501997-04-15015 April 1997 Proposed Tech Specs 3.8.1, AC Sources - Operating, Revising SR 3.8.1.8 & Applicable Bases Allowing Credit Overlap Testing ML20134P9941997-02-21021 February 1997 Proposed Tech Specs Clarifying Note Which Relays Will Not Be Response Time Tested Until Next Songs,Unit 3 Refueling Outage to Satisfy SR 3.3.5.6 of TS 3.3.5, ESFAS Instrumentation 1999-08-09
[Table view] |
Text
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1.1 Definitions CORE ALTERATION within the reactor vessel with the vessel head (continued) removed and fuel in the vessel. Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.
CORE OPERATING LIMITS The COLR is the unit specific document thdt REPORT (COLR) provides cycle specific 3arameter limits for the current reload cycle. T1ese cycle specific parameter limits shall be determined for each reload cycle in accordance with Specification i 5.7.1.5. Plant operation within these limits'1s addressed in individual Specifications, j 1
DOSE EQUIVALENT I-131 00SE EQUIVALENT I-131 shall be that concentration of I-131 (microcuries/ gram) that alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table E-7 of Regulatory Guide 1.109, Rev. 1, NRC, 1977.
E- AVERAGE E shall be the average (weighted in proportion DISINTEGRATION ENERGY to the concentration of each radionuclide in the reactor coolant at the time of sampling) of the 4 Sum of the average beta and gamma energies per l disintegration (in MeV) for isotopes, other than (
iodines, with half lives > 15 minutes, making up at least 95% of the total noniodine activity in the coolant.
ENGINEERED SAFETY The ESF RESPONSE TIME shall be that time interval FEATURE (ESF) RESPONSE from when the monitored parameter exceeds its ESF TIME actuation setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their
- required positions, pump discharge pressures reach l their required values, etc.). Times shall include diesel generator starting and sequence loading .
delays, where applicable. The response time may be measured by means of any series of sequential, overlapping, or total steps 50 that the entire response time is measured.
l (continued)
SAN ON0FRE--UNIT 2 1.1-3 Amendment No. 127 9805190065 990507 "
DR ADOCK 0 1
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- PCN 492 ,
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Attachment B (ExistingPage)
SONGS Unit 3 l
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L Definitions 1.1
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l CORE ALTERATION within'the reactor vessel with the vessel head I (continued)- removed and fuel in the vessel. Suspension of
- CORE ALTERATIONS shall not preclude completion of movement of a component.to'a safe. position.
l-
- i. CORE OPERATING LIMITS The COLR is the unit specific document that l~ ' REPORT (COLR) provides cycle specific )arameter limits for the current reload cycle. T1ese. cycle specific L parameter limf ts shall be determined for each. i
- l. reload cycle in accordance with Specification 5.7.1.5. Plant operation within these limits is j addressed in individual Specifications.
DOSE EQUIVALENT I-131 DOSE EQUIVALENT.I-131 shall be that concentration of I-131 (microcuries/ gram) that alone would produce the same thyroid dose as the quantity and-isotopic mixture of I-131, I-132, I-133, I-134, )
and I-135 actually present. The thyroid dose i conversion factors used for this calculation shall l be those listed in Table E-7 of Regulatory Guide l 1.109, Rev. 1, NRC, 1977. l E- AVERAGE l shall be the average (weighted in proportion -
DISINTEGRATION ENERGY ~to the concentration of each radionuclide in the reactor coolant at the time of sampling) of the i sum of the avera j disintegration (ge beta and gamma energies perin MeV) forj iodines, with half lives > 15 minutes, making 'up )
at least 95's of the total noniodine activity in the coolant.
ENGINEERED SAFETY The ESF RESPONSE TIME shall be that time interval FEATURE (ESF) RESPONSE from when the monitored parameter exceeds its ESF i TIME. actuation setpoint at the channel sensor until the j ESF equipment is capable of performing its. safety ;
function (i.e., the valves travel to their required positions, pump discharge pressures reach theirrequiredvalues,etc.). Times shall include ;
- diesel generator starting and sequence loading !
delays, where applicable. The response time may 4 l~ be measured by means of any series of sequential, I overlapping, or total steps so that the entire response time it measured.
l (continued)
SAN ON0FRE--UNIT'3 1.1-3 Amendment No. 116
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PCN 492 -
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Redline and Strikeout SONGS Unit 2 i
l I
- Definitions 1.1 1.1 Definitions CORE ALTERATION within the reactor vessel with the vessel head (continued) removed and fuel in the vessel. Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.
CORE OPERATING LIMITS The COLR is the unit specific document that REPORT (COLR) provides cycle specific parameter limits for the current reload cycle. These cycle specific parameter limits shall be determined for each reload cycle in accordance with Specification 5.7.1.5. Plant operation within these limits is addressed in individual Specifications.
I DOSE EQUIVALENT I-131 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcuries/ gram) that alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The thyroid dose conversion factors used.for this calculation shall ,
~
be_thoselistedinICRP;30JSup)ommi.ttedgDose.,.lementito"Parn 3agesi192-212F Tables :titledM:
Equivalent 41n 2 Tar i ofq uni t1Ac ti v if ty. getE-7 s 0rgansYor?T
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E- AVERAGE E shall be the average (weighted in prcportion DISINTEGRATION ENERGY to the concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of the avera disintegration (ge beta and gamma energies perin MeV) for iso iodines, with half lives > 15 minutes, mnking,up at least 95% of the total noniodine activity in the coolant.
ENGINEERED SAFETY The ESF RESPONSE TIME shall be that time interval FEATURE (ESF) RESPONSE from when the monitored parameter exceeds its ESF TIME actuation setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays, where applicable. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.
(continued)
SAN ON0FRE--UNIT 2 1.1-3 Amendment No. ttf
. PCN 492 l
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Redline and Strikeout SONGS Unit 3
t Definitions 1.1 1.1 Defini. tons CORE ALTERATION within the reactor vessel with the vessel head (continued) removed and fuel in the vessel. Suspension of j CORE ALTERATIONS shall not preclude completion of i movement of a component to a safe position.
CORE 0PERATING LIMITS The COLR is the unit specific document that REPORT (COLR) provides cycle specific parameter limits for the ,
current reload cycle. These cycle specific 1 parameter limits shall be determined for each j reload cycle in accordance with Specification 1 5.7.1.5. Plant operation within these limits is L addressed in individual Specifications.
DOSE EQUIVALENT I-131 00SE EQU! VALENT I-131 shall be that concentration .
of I-131 (microcuries/ gram) that alone would 1 l produce the same thyroid dose as the quantity and !
isotopic mixture of I-131, I-132, I-133, 1-134, i and I-135 actually present. The thyroid dose conversion factors used this calculation thoselistedin.ICRPF be_ss91921212pTablesstjt y:ommitted;. Dose' dhu rQ1 ilementito l
l p' 1l E 1ValentninGargett0r o ,untt!ActivityLiahE,ganstorkTiss 1.iv>, nev. i, nnu, is ,.
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E- AVERAGE E shall be the average (weighted in proportion DISINTEGRATION ENERGY to the concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of the avera disintegration (ge beta and gamma energies perin MeV) for 1so) iodines, with half lives > 15 minutes, making up ;
at least 95% of the total noniodine activity in '
the coolant.
ENGINEERED SAFETY 'The ESF RESPONSE TIME shall be that time interval FEATURE (ESF) RESPONSE from when the monitored parameter exceeds its.ESF TIME actuation setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include ,
diesel generator starting and sequence loading l delays, where applicable. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire 1 l
response time is measured.
(continued)
SAN ON0FRE--UNIT 3 1.1-3 . ndment No. ttfr
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Definitions 1.1 1.1 Definitions CORE ALTGb ION within the reactor vessel with the vessel head (continwc removed and fuel in the vessel. Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.
CORE OPERATING 'MITS The COLR is the unit specific document that REPORT (COLR) provides cycle specific parameter limits for the
, current reload cycle. These cycle specific parameter limits shall be determined for each reload cycle in accordance with Specification 5.7.1.5. Plant operation within these limits is ;
addressed in individual Specifications.
DOSE EQUIVALENT I-131 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcuries/ gram) that alone wou'Id produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in ICRP-30, Su p ges 192-212, Tables titled, gplement CommittedtoDose Part 1, E uivalent in Target Organs or Tissues per Intake o Unit Activity E- AVERAGE E shall be the average (weighted in proportion DISINTEGRATION ENERGY to the concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of the avera
, disintegration (ge beta and gamma energies perin MeV) for iso fodines, with half lives > 15 minutes, making up i at least 95% of the total noniodine activity in the coolant.
ENGINEERED SAFETY The ESF RESPONSE TIME shall be that time interval FEATURE (ESF) RESPONSE from when the monitored parameter exceeds its ESF TIME actuation setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the v31ves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays, where applicable. The response time may l be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.
(continued)
SAN ON0FRE--UNIT 2 1.1-3
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. PCN 492 4
l Attachment F (ProposedPage)
SONGS Unit 3 1
I I
v Definitions 1.1 1.1 Definitions CORE ALTERATION within the reactor vessel with the vessel head (continued) removed and fuel in the vessel. Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.
CORE 0PERATING LIMITS The COLR is the unit specific document that REPORT (COLR) provides cycle specific parameter limits for the current reload cycle. These cycle specific parameter limits shall be determined for each reload cycle in accordance with Specification 5.7.1.5. Plant operation within these limits is l addressed in individual Specifications.
DOSE EQUIVALENT I-131 DOSE EQUIVALENT I-131 shall be that concentration ofI-131(microcuries/ gram)thatalonewould l
produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, 1 and I-135 actually present. The thyroid dose -l conversion factors used for this calculation shall l l
Su be those 3 ages listed inTables 192-212, ICRP-30,d, title gplement CommittedtoDose Part 1, l uivalentinTargetOrgansorTissuesperIntake l 0 Unit Activity l
l E- AVERAGE E shall be the average (weighted in proportion I l DISINTEGRATION ENERGY to the concentration of each radionuclide in the
! reactor coolant at the time of sampling) of the l sum of the avera
- disintegration (ge beta and gamma energies perin MeV) for 1 iodines, with half lives > 15 minutes, making up at least 95% of the total noniodine activity in the coolant.
ENGINEERED SAFETY The ESF RESPONSE TIME shall be that time interval FEATURE (ESF) RESPONSE from when the monitored parameter exceeds its ESF TIME actuation setpoint at the char,ael sensor until the ESF equipment is capable of performing its safety the function (i.e. Ions,valvestraveltotheir required posit pum '
diesel generatoretc. . Times shall include starting an)d sequence lo
!. delays, where applicable. The response time may L be measured by means of any series.of sequential, L
overlapping, or total steps so that the entire response time is measured.
(continued)
. SAN ONGFRE--UNIT 3 1.1-3