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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20212C0961999-09-16016 September 1999 Proposed ITS & Bases Changes Strikeout & Shadowed Text & Revision Bar Format,Increasing Licensed Capacity for Spent Fuel Assembly Storage in SFP & Revising Configuration for Storage of Fresh Fuel ML20211L1011999-09-0202 September 1999 Proposed Tech Specs Re Once Though SG Tube Surveillance Program,Alternate Repair Criteria (ARC) for Axial Tube End Crack (Tec) Indications ML20209D2971999-07-0808 July 1999 Proposed Tech Specs,Changing ITS for CREVS & VFTP & Correcting Typo in ITS Section 5.6.2.12 ML20195B8091999-05-26026 May 1999 Proposed Tech Specs,Revising ITS Bases That Will Update NRC Copies of ITS ML20195B7081999-05-17017 May 1999 Proposed ITS Section 3.3.8, EDG Lops, SR 3.3.8.1,revising Note for Surveillance & Deleting Note for Frequency ML20206S7691999-05-12012 May 1999 Proposed Improved Tech Specs Pages 3.4-21 Through 3.4-21D ML20206N1401999-05-10010 May 1999 Proposed ITS Administrative Controls Section 5.8, High Radiation Area ML20206M0961999-05-0707 May 1999 Proposed Tech Specs,Revising Wording for SR 3.5.2.5 to Be More Consistent with NUREG-1430,Rev 1 & Clarifying Process of Valve Position Verification ML20206H6541999-05-0505 May 1999 Proposed Tech Specs,Proposing Alternate Repair Criteria for Axial Tube End crack-like Indications in Upper & Lower Tubesheets of CR-3 OTSGs ML20204D9211999-03-18018 March 1999 Proposed Tech Specs Re OTSG Tubes Surveillance Program,Tube Repair Roll Process ML20202E6551999-01-27027 January 1999 Proposed Tech Specs Re OTSG Tubes Surveillance Program,Insp Interval Extension ML20196D6761998-11-30030 November 1998 Proposed Tech Specs LCO 3.9.3,allowing Both Doors in Personnel Air Locks & Single Door in Oeh to Be Open During Refueling Operations ML20195K4551998-11-24024 November 1998 Proposed Tech Specs,Installing diesel-driven EFW Pump to Remove Interim ITS & Provide Resolution to EDG Capacity Limitations ML20195K0031998-11-23023 November 1998 Proposed Tech Specs Re LAR Number 241,rev 0 for High Pressure Injection Sys Mods ML20195H6581998-11-17017 November 1998 Proposed Improved Tech Specs (Its),Revising 5.7.2 by Changing Type of Structural Integrity Assessment Required from Probabilistic to Deterministic ML20155F4501998-10-30030 October 1998 Proposed Revised Improved Tech Specs (ITS) Deleting Note Re Number of Required Channels for Degrees of Subcooling Function & Subdividing Core Exit Temp Function Into Two New Functions in ITS Table 3.3.17-1 ML20155F4021998-10-30030 October 1998 Proposed Revised Improved Tech Specs (ITS) Section 5.6.2.19, ITS Section 3.4.11,Bases 3.4.11 & 3.4.3 Re PTLR & LTOP Limits ML20155F9551998-10-30030 October 1998 Proposed Tech Specs Pages to LAR 245,changing Methodology for Sf Pool B Criticality Analysis ML20154P3101998-10-16016 October 1998 Proposed Tech Specs Resolving USQ by Leaving Valves DHV-34 & DHV-35 Normally Closed ML20154C1581998-09-30030 September 1998 Proposed Tech Specs Pages Re LAR 238,to Correct RCS Leakage Detection Capability of RB Atmosphere Gaseous Radioactivity Monitor Described in ITS Bases & FSAR ML20238F4761998-08-31031 August 1998 Proposed Tech Specs,Proposing New Repair Process for Plant OTSGs ML20151X0431998-08-31031 August 1998 Proposed Tech Specs Adding Three Addl Reg Guide 1.97 Type a Category 1 Pami Variables & One Type B Category 1 Pami Variable to ITS Table 3.3.17-1, Pami ML20236V8831998-07-30030 July 1998 Proposed Tech Specs Pages Re CREVS & Ventilation Filter Test Program ML20236E9851998-06-30030 June 1998 Proposed Tech Specs Re Exigent License Amend Request 228,rev 1 for Once Through SG Tube Surveillance Program ML20249B2671998-06-18018 June 1998 Proposed Tech Specs Pages Re one-time Exigent License Amend to Allow Operation W/Number of Indications Previously Identified as Tube End Anomalies & Multiple Tube End Anomalies in OTSG Tubes ML20247P8931998-05-22022 May 1998 Proposed Improved Tech Specs 5.2.1 Re Onsite & Offsite Organizations ML20217P5181998-04-28028 April 1998 Proposed Tech Specs Re Reactor Coolant Pump Motor Flywheel Insp ML20217G0121998-04-23023 April 1998 Proposed Improved Tech Specs Section 5.7.2, Special Repts, Clarifying That Complete Results of OTSG Tube Inservice Insp Shall Be Submitted to NRC 90 Days After Startup (Breaker Closure) ML20217C6341998-03-20020 March 1998 Proposed Tech Specs Re Editorial Changes to Improved TS Saftey Limits & Administrative Controls to Replace Titles of Senior Vice President,Nuclear Operations & Vice President, Nuclear Production W/Position of Chief Nuclear Officer ML20217C4931998-03-20020 March 1998 Proposed Improved Tech Specs 5.6.2.8.c Re Reactor Coolant Pump Motor Flywheel Insp ML20203D1611998-02-20020 February 1998 Proposed Tech Specs,Providing Revs to CR-3 Improved TS Bases That Update NRC Copies of Improved TS ML20198S9151998-01-22022 January 1998 Proposed Tech Specs Consisting of Rev 1 to TS Change Request 210,correction of Typo & Addition of Footnotes ML20202G8511997-12-0505 December 1997 Proposed Tech Specs Establishing New Improved TSs (ITS) Surveillance Requirement for Performance of Periodic Integrated Leak Test of Cche Boundary & Revising ITS Bases 3.7.12 to Define Operability of Cche ML20202G7991997-12-0505 December 1997 Proposed Tech Specs Revising Description of Starting Logic for RB Recirculation Sys Fan Coolers to Ensure That Only One RB Fan Starts on Es RB Isolation & Cooling Signal ML20199G8461997-11-21021 November 1997 Proposed Tech Specs Pages Involving Additional Restrictions, Editorial Clarifications & Typos ML20212F2741997-10-31031 October 1997 Proposed Tech Specs Pages Re Decay Heat Removal Requirements in Mode 4 ML20212C9801997-10-25025 October 1997 Proposed Tech Specs Re Power Operated Relief Valve Lift Setpoint TS Limit That Has Been Revised for Instrument Uncertainty ML20217F5231997-10-0404 October 1997 Proposed Tech Specs Pages Addressing Revision to Description of Electrical Controls for Operating Reactor Building (RB) Recirculation Sys fan/cooler,AHF-IC,as Discussed in FSAR & Improved TS ML20217D2741997-10-0101 October 1997 Proposed Tech Specs Adding Methodology to Monitor first-span Intergranular Attack (Iga) Indications & Disposition Growth During Future B OTSG Eddy Current Exams ML20210T9771997-09-12012 September 1997 Proposed Tech Specs Replacement Pages Re New Improved TS 3.4.11 Re Low Temp Overpressure Protection Sys ML20216F8481997-09-0909 September 1997 Proposed Tech Specs Re Analysis Rev for Makeup Sys Letdown Line Failure Accident as Discussed in FSAR ML20217Q2121997-08-26026 August 1997 Proposed Tech Specs Changing Design Basis of EDG Air Handling Sys ML20217N2501997-08-20020 August 1997 Proposed Improved Tech Specs 5.6.2.10 Re Tube Surveillance ML20210K8921997-08-16016 August 1997 Proposed Tech Specs 3.8.1.3,requesting one-time Outage on Each EDG to Perform Necessary Mod & Maint ML20151L7541997-08-0404 August 1997 Proposed Tech Specs Extending Frequency of EDG Surveillances During Period of Time CR-3 EDGs Are Being Modified ML20196J1431997-07-29029 July 1997 Proposed Tech Specs Adding EDG Kilowatt Indication to post- Accident Monitoring Instrumentation to Support CR-3 Restart Issue of EDG Load Mgt ML20196H0281997-07-18018 July 1997 Proposed Tech Specs Changes Establishing Requirements for Low Temperature Overpressure Protection Sys ML20148K7811997-06-14014 June 1997 Proposed Tech Specs Re Efw,Hpi,Emergency Feedwater Initiation & Control Sys ML20138H8781997-05-0101 May 1997 Proposed Tech Specs Replacing Prescriptive Requirements of 10CFR50,App J,Option a w/performance-based Approach to Leakage Testing Contained in 10CFR50,App J,Option B ML20137X5361997-04-18018 April 1997 Proposed Tech Specs,Providing Revs to CR-3 Improved TS Bases That Update NRC Copies of Improved TS 1999-09-02
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20212C1121999-09-16016 September 1999 Criticality Safety Analysis of W Spent Fuel Storage Racks in Pool B of Crystal River Unit 3 ML20212C0961999-09-16016 September 1999 Proposed ITS & Bases Changes Strikeout & Shadowed Text & Revision Bar Format,Increasing Licensed Capacity for Spent Fuel Assembly Storage in SFP & Revising Configuration for Storage of Fresh Fuel ML20211L1011999-09-0202 September 1999 Proposed Tech Specs Re Once Though SG Tube Surveillance Program,Alternate Repair Criteria (ARC) for Axial Tube End Crack (Tec) Indications ML20212C0991999-08-31031 August 1999 Criticality Safety Analysis of Crystal River Unit 3 Pool a for Storage of 5% Enriched Mark B-11 Fuel in Checkerboard Arrangement with Water Holes ML20209D2971999-07-0808 July 1999 Proposed Tech Specs,Changing ITS for CREVS & VFTP & Correcting Typo in ITS Section 5.6.2.12 ML20195B8091999-05-26026 May 1999 Proposed Tech Specs,Revising ITS Bases That Will Update NRC Copies of ITS ML20195B7081999-05-17017 May 1999 Proposed ITS Section 3.3.8, EDG Lops, SR 3.3.8.1,revising Note for Surveillance & Deleting Note for Frequency ML20206S7691999-05-12012 May 1999 Proposed Improved Tech Specs Pages 3.4-21 Through 3.4-21D ML20206N1401999-05-10010 May 1999 Proposed ITS Administrative Controls Section 5.8, High Radiation Area ML20206M0961999-05-0707 May 1999 Proposed Tech Specs,Revising Wording for SR 3.5.2.5 to Be More Consistent with NUREG-1430,Rev 1 & Clarifying Process of Valve Position Verification ML20206H6541999-05-0505 May 1999 Proposed Tech Specs,Proposing Alternate Repair Criteria for Axial Tube End crack-like Indications in Upper & Lower Tubesheets of CR-3 OTSGs ML20204D9211999-03-18018 March 1999 Proposed Tech Specs Re OTSG Tubes Surveillance Program,Tube Repair Roll Process ML20205A7651999-03-18018 March 1999 Rev 29 to AR-305, Es E Annunciator Response ML20205A7961999-03-15015 March 1999 Rev 22 to AR-301, ESA Annunciator Response ML20205A8051999-03-15015 March 1999 Rev 33 to AR-303, ESC Annunciator Response ML20205A8211999-03-15015 March 1999 Rev 35 to AR-403, PSA H Annunciator Response ML20205A3441999-03-12012 March 1999 Rev 25 to AR-402, PSA G Annunciator Response ML20204D5781999-03-0909 March 1999 Rev 10 to AP-513, Toxic Gas ML20204D5821999-03-0808 March 1999 Rev 22 to AR-603, Tgf O Annunciator Response ML20207H7741999-03-0303 March 1999 Rev 15 to AR-602, Tgf N Annunciator Response ML20207J6591999-03-0202 March 1999 Rev 18 to AR-504, ICS L Annunciator Response ML20207J6461999-03-0202 March 1999 Rev 21 to AR-301, ESA Annunciator Response ML20206S7561999-02-28028 February 1999 Rev 2 to Pressure/Temp Limits Rept, Dtd Feb 1999 ML20203C7461999-02-0303 February 1999 Rev 2 to AR-801, FSA Annunciator Response ML20202E6551999-01-27027 January 1999 Proposed Tech Specs Re OTSG Tubes Surveillance Program,Insp Interval Extension ML20202B1411999-01-22022 January 1999 Rev 22 to AR-401, PSA F Annunciator Response ML20199G5201999-01-15015 January 1999 Rev 11 to AP-961, Earthquake ML20199G5581999-01-12012 January 1999 Rev 4 to AP-404, Loss of Decay Heat Removal ML20199G5691999-01-12012 January 1999 Rev 4 to AP-604, Waterbox Tube Failure ML20198T2411999-01-0606 January 1999 Rev 19 to AR-701, Ssf P Annunciator Response ML20196G6771998-12-0101 December 1998 Rev 17 to Annunciator Response AR-702, Ssf Q Annunciator Response ML20196D6761998-11-30030 November 1998 Proposed Tech Specs LCO 3.9.3,allowing Both Doors in Personnel Air Locks & Single Door in Oeh to Be Open During Refueling Operations ML20196G5851998-11-25025 November 1998 Rev 32 to AR-303, ESC Annunciator Response ML20196G3371998-11-25025 November 1998 Reissued Rev 15 to AR-702, Ssf Q Annunciator Response ML20195K4551998-11-24024 November 1998 Proposed Tech Specs,Installing diesel-driven EFW Pump to Remove Interim ITS & Provide Resolution to EDG Capacity Limitations ML20196F6691998-11-24024 November 1998 Rev 11 to AP-330, Loss of Nuclear Svc Cooling ML20195K0031998-11-23023 November 1998 Proposed Tech Specs Re LAR Number 241,rev 0 for High Pressure Injection Sys Mods ML20196F7721998-11-23023 November 1998 Rev 3 to EOP-12, Station Blackout ML20196F7031998-11-23023 November 1998 Rev 3 to AP-404, Loss of Decay Heat Removal ML20196F7541998-11-23023 November 1998 Rev 7 to EOP-08, LOCA Cooldown ML20196F7461998-11-23023 November 1998 Rev 6 to EOP-07, Inadequate Core Cooling ML20196F7241998-11-23023 November 1998 Rev 2 to AP-510, Rapid Power Reduction ML20196F7161998-11-23023 November 1998 Rev 9 to AP-470, Loss of Instrument Air ML20196F8711998-11-23023 November 1998 Rev 28 to AR-305, Es E Annunciator Response ML20196F9451998-11-19019 November 1998 Rev 7 to AP-1080, Refueling Canal Level Lowering ML20196F9381998-11-19019 November 1998 Rev 27 to AP-770, Emergency Diesel Generator Actuation ML20195H6581998-11-17017 November 1998 Proposed Improved Tech Specs (Its),Revising 5.7.2 by Changing Type of Structural Integrity Assessment Required from Probabilistic to Deterministic ML20196D8321998-11-13013 November 1998 Rev 1 to Crystal River Unit 3 ASME Section Xi,Isi Program Interval 3 & Ten Yr NDE Program ML20195H8761998-11-0505 November 1998 Rev 23 to AR-302, Esb Annunciator Response ML20155F4021998-10-30030 October 1998 Proposed Revised Improved Tech Specs (ITS) Section 5.6.2.19, ITS Section 3.4.11,Bases 3.4.11 & 3.4.3 Re PTLR & LTOP Limits 1999-09-02
[Table view] |
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APPLIQABILITY SURVEILLANCE RinEREME2HS l
4.0.1 Surveillance Requinsnents shall be applicable during the OPERATIONAL j M300S or other conditions specified for iniividtnl Limiting conditions for ~
Operation unless otherwise stated in an individual Surveillance Requirement.
4.0.2 Eacti Surveillance Requirement shall be performed within the specified j time interval with a maxinun allowable extensior, not to eM 25% of the '
surveillance interval, l
l l
4.0.3 Performance of a Surveillance Requirement within the specified time interval shall constitute ocmpliance with OPERABILITV requiruments for a Limiting Condition for Operation and associated Action statements unless otherwise required by the specification. Surveillance Requirements do not have to be perfoned on incperable equipnent.
4.0.4 Entry into an OPERATIONAL 100E or other specified applicability coniitions shall not be mMe unless the Surveillance Requirement (s) associated with the Limiting coniition for Operation has been performed within the stated surveillance interval or as otherwise specified.
4.0.5 Surveillance Requirements for inservloe inspection and testing of ASME code class 1,2, and 3 wigwnts shall be aplicable as follcus: i
- a. Ibr the time period frun issuanoe of the Facility Operating License to the start of facility comercial cperation, inservice testing of ASME Code Class 1,2, and 3 punps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel code 1974 Diition, and Adderda through Sumer 1975, except where speciffc written relief has been granted by the Ocanission.
- b. For the time period folicwing start of facility cannercial operation, inservice inspection of ASME code Class 1,2, and 3 wiWwnts and inservice testing of ASME Code Class 1,2, and 3 punps and valves shall be perfarmed in accordance with Section XI of the ASME Boiler and Pressne Vessel Code and applicable Addenia as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has been '
l granted by the rW=nimaion pursuant to 10 CFR 50, Section
! 50.55a(g) (6) (i) .
CRfSTAL RIVER - LNIT 3 3/4 0-2 Amentient No.
$T11130150 syju3; rDR ADOCK 05000302 P PDC
1 i
APPilCABIllTY l
BhSES '
i subsystaans, trains, cruponents and devices sqplied by the inoperable normal I pwar sources, both of the offsite cirulits, would also be inoperable. This !
sculd dictate invoking the agplicable AcrIm statanents for eat of the i applionble D:Ds. However, the prtwisions of Specification 3.0.5 permit the l time limits for centinand cperation to be consistent with the AcrIm statament ,
for the inoperable nonnal power sources instead, prtwided the other specified !
oorditions are satisfied. In this case, this would mean that for one division !
the asner9ency power scuros must be OPERABIZ (as must be the a.ir< wits supplied l by the amargency power source) ard all redundant systems, subsystems, trains, r
+-sis and devions in the other division must be OERABIE, or likewise !
satisfy Specification 3.0.5 (i.e., be capable of performing their design i functions and have an amargency power source ORRABIE). In other words, both i emergency power sources must be ORRABIE ard all redundant systans, subsystems, tra. ins, wi its and devices in both divisions must also be OPERABII. If ;
these corditions are not satisfied, shutdown is required in accordance with this specification.
i In ) ODES S or 6, Specification 3.0.5 is not applicable, and thus the individual I ACTIN statements for and applicable Limiting Cordition for Operation in thcao '
! )OWS nust be a&ered to. i I
l 4.0.1 'this specification prtwides that surveillance activities man to l insure the Limiting conditicms for operaticm are met and will be performed ;
t
' during OMRATImhL PONS or other ocrditions for whid the Limiting Conditions l for operaticm are applicable. Prtwisions for additicmal surveillance '
activities to be performed without regard to the applicable OPERATINAL PONS .
l or other conditicms are provided in the individual Surveillance Requirements. {
4.0.2 'Ihe prtwision of this specificatico establishes the limit for which i the specified time interval for Surveillarce Haquirunants may be extended. It :
permits an allowable extension of the normal surveillance interval to [
facilitate surveillance scheduling and ocmsiderstice of plant operating ,
conditions that may not be suitable for conducting the surveillance; e.g., i
, transient conditions or other ongoing surveillance or maintenance activities. ,
It also prtwides flexibility to arw-rdate the length of a fuel cycle for surveillances that are performed at and refueling cutage and are specified ;
with an 18-aanth surveillance interval. It is not intended that this prtwision be used repeatedly as a convenience to extend surveillance intervals beyond !
that specified for surveillances that are not performed during refueling i eutages. 'Ihm limitation of Specificatica 4.0.2 is based on angineering ,
judgement ard the w.windtion that the nost probable result of any particular surveillance being performed is the verification of conformance with the :
( Surveillance Requirements. 'this prtwision is sufficient to ensure that the i
reliability ensured through surveillance activities is not significantly ,
deg 3ed beyond that cbtained frtan the specified surveillance interval. ,
4.0.3 'Ihm prtwisicms of this specification set forth the criteria for determination of cxmpliance with the OEPABILITY requirunents of the Limiting Ccmditions for Operation. Under this critaria, equi;xnent, systems or cuur -its are assumed to be OPERABIE if the associated surveillance activities have been satisfactorily performed within the mYSML RIVER - WIT 3 B 3/4 0-3 Amerdment No.
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