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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] |
Text
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FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 i
DOCKET NO. 50-302/ LICENSE NO. DPR-72 l
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ATTACIBIENT B l
EXIGENT LICENSE AMENDMENT REQUEST #228, REVISION 1 ONCE THROUGH STEAM GENERATOR TUBE SURVEILLANCE PROGRAM Proposed Technical Specification Change Page (Shaded) l l
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i 9007010322 980630 PDR ADOCK 05000302 P
PDR t
Procedures, Programs and Manuals 5.6 5.6 Procedures, Programs and Manuals 5.6.2.10 OTSG Tube Surveillance Program (continued) 8.
Plugging / Sleeving Limit means the extent of degradation beyond which the tube shall be restored to serviceability by the installation of a sleeve or removed from service because it may become unserviceable prior to the next inspection and is equal to 40% of the nominal tube or sleeve wall thickness.
No more than five thousand sleeves may be installed in each OTSG.
9.
Unserviceable describes the condition of a tube if it leaks or contains a defect large enough to affect its structural integrity in the event of an Operating Basis Earthquake, a loss-of-coolant accident, or a main steam line or feedwater line break, as specified in 5.6.2.10.3.c, above.
10.
Tube Inspection means an inspection of the entire OTSG tube as far as possible.
b.
The OTSG shall be determined OPERABLE after completing the corresponding actions exceeding the plugging /slee(plug or sleeve all tubes vin limit and all tubes containing through-wall cracks required by Table 5.6.2-2 (and Table 5.6.2-3 if he provisions of Specification 5.6.2.10.2.d are utilized).
Defective tubes may be repaired in accordance with the B&W process (or method) equivalent to the method described in report BAW-2120P.
l There7are aTnumberTof;0TSG4tubss thatiha elthe potentialf to exceed: thel tube; plugging /sleevingiliinit"as a resultLofstube end/ anomalies. DefectiveltubesJwill be repaired or. plugged during:the.next outage;of'.
sufficient' duration.s -An evaluation hasLbeen performed which! confirms that-operability of_the CR-310TSGs will not befimpacted with those tubes inservice.
c 5.6.2.11 Secondary Water Chemistry Program This program provides controls for monitoring secondary water chemistry to inhibit steam generator tube degradation and low pressure turbine disc stress corrosion cracking.
The program shall include:
a.
Identification of a sampling schedule for the critical variables and control points for these variables; b.
Identification of the procedures used to measure the values of the critical variables; (continued)
Crystal River Unit 3 5.0-17 Amendment No. MB l
l FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 l
DOCKET NO. 50-302/ LICENSE NO. DPR-72 l
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i ATTACHMENT C l
EXIGENT LICENSE AMENDMENT REQUEST #228, REVISION 1 l
ONCE THROUGH STEAM GENERATOR TUBE SURVEILLANCE PROGRAM Proposed Technical Specification Change Page (Revision Bar)
Procedures, Programs and Manuals 5.6 5.6 Procedures, Programs and Manuals 5.6.2.10 OTSG Tube Surveillance Program (continued) 8.
Plugging / Sleeving Limit means the extent of degradation beyond which the tube shall be restored to serviceability by the installation of a sleeve or removed from service because it may become unserviceable prior to the next inspection and is equal to 40% of the nominal tube or sleeve wall thickness.
No more than five thousand sleeves may be installed in each OTSG.
9.
Unserviceable describes the condition of a tube if it leaks or contains a defect large enough to affect its structural integrity in the event of an Operating Basis Earthquake a loss-of-coolant accident, or a main steam line or feedwater line break, as specified in 5.6.2.10.3.c, above.
10.
Tube Inspection means an inspection of the entire OTSG tube as far as possible.
b.
The OTSG shall be determined OPERABLE after completing the corresponding actions exceeding the plugging /slee(plug or sleeve all tubes vin limit and all tubes containing through-wall cracks required by Table Specifica(and Table 5.6.2-3 if 5.6.2-2 he provisions of tion 5.6.2.10.2.d are utilized).
Defective tubes may be repaired in accordance with the B&W process (or method) equivalent to the method described in report BAW-2120P.
There are a number of OTSG tubes that have the potential to exceed the tube plugging / sleeving limit as a result of tube end anomalies. Defective tubes will be repaired or plugged during the next outage of sufficient duration. An evaluation has been performed which confirms that operability of the CR-3 OTSGs will not be impacted with those tubes inservice.
)
5.6.2.11 Secondary Water Chemistry Program This program provides controls for monitoring secondary water chemistry to inhibit steam generator tube degradation and low pressure turbine disc stress corrosion cracking.
The program shall include:
a.
Identification of a sampling schedule for the critical variables and control points for these variables; b.
Identification of the roc of the critical variab$es;edures used to measure the values (continued)
Crystal River Unit 3 5.0-17 Amendment No.
e+
FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 DOCKET NO. 50-302/ LICENSE NO. DPR-72
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ATTACHMENT D EXIGENT LICENSE AMENDMENT REQUEST #228, REVISION 1 i
ONCE THROUGH STEAM GENERATOR TUBE SURVEILLANCE PROGRAM List of Regulatory Commitments
U.S. Nuclear Regulatory Commission Attachment D 3F0698-33 Page 1 of1 LIST OF COMMITMENTS The following table identifies those actions committed to by Florida Power Corporat%n in this document 'Any other actions discussed in the submittal represent intended or plannc i actions by Florida Power Corporation. They are described to the NRC for the NRC's information and are not regulatory commitments. Please notify the Manager, Nuclear Licensing of any questions regarding this document or any associated regulatory commitments.
I Commitment Due Date l.
There are a number of OTSG tubes that have the potential to During the next outage of l
exceed the tube plugging / sleeving limit as a result of tube end sufficient duration.
anomalies. Defective tubes will be repaired or plugged.
l-The results of a study originally requested by the B&W Owners The analytical work is Group will determine if any of the tubes with tube end anomalies scheduled to be performed (TEAS) or multiple end anomalies (MEAS) need to be reclassified this summer with as defective. The analytical work is scheduled to be performed this confirmatory laboratory summer with confirmatory laboratory testing to be conducted testing to be conducted L
through the remainder of 1998, through the remainder of l-1998.
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