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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
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Technical Specification Change Recuest No. 25 (Appendix A)
Replace page 3/4 7-11, 7-12, B3/4 7-3 with the attached revised pages 3/4 7-11, 7-12, B 3/4 7-3.
Proposed Change Revise the Basis for the Secondary Water Chemistry Specification per the attached, revised pages.
Reason for Change A test program was conducted at Crystal River Unit 3 during approximately the first 6 months followirg initial criticality. This program was an extension of the preoperational program and it encompassed the program presently described in the Basis for the Secondary Water Chemistry Specification.
Toward the end of the test period, it was becoming apparent to the industry that steam turbine disc cracking as well as steam generator tube failures were a result of unknown mechanisms between the discs / tubes and the secondary water.
In order to correlate secondary water chemistry to these failures, the Electric Power Research Institute (EPRI) is backing Nuclear Water & Waste Technology (NWT) in a study of the secondary cycle chemistry of pressurized water reactors having once-through steam generators (Study No. PR-704-1).
A description of this study as well as a milestone chart is attached. The benefits of this program will be:
- 1) Operational comparison of four Babcock & Wilcox reactors, having important design and control differences in their secondary cycles.
- 2) Independent review of CR-3 sampling and analytical capabilities.
- 3) Correlation of operational chemistry control data to condenser leakage, polisher performance, chemical treatment dosage, and steam generator / turbine corrosion / deposition rates.
- 4) Availability of operational experience to interested electric utilities and EPRI via quarterly recorts.
Considering the history of steam generator tube failures, recent turbine disc cracking and the probability of improving present control strategies, it is proposed that this study replace the study in the Tech Specs as the l basis for the Secondary Water Chemistry Specification. I As can be seen on the milestone chart, the program is scheduled to run till the end of 1979, at which time, the results will be submitted to the Comission. In the meantime, Secondary Water Chemistry will be maintained within B&W specified limits (See Attached table). ;
Safety Analysis Justifying Procosed Change l None of the requirements applicable to the Safety Analysis are diminished by the proposed changes and no unreviewed safety question is involved.
R 0 0 3 0 5f9 N I
. . ~
While the original test program identified chemical constituents and concentration phenomena at various points in the secondary cycle, the lack of correlation to actual plant operations was detrimental in attempting to specifylimits on parameters and frequencies for monitoring.
The continuation of.the use of vendor specified limits on parameters and
-frequencies of monitoring is sufficient to ensure the integrity of the 4 secondary system until the proposed study is completed and the result can be instituted.
9 4
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n . TABLE 3.7-2 -
3' Yi . .
j!" . SECONDARY-WATER CHEMISTRY LIMITS- ,
2 9.
~ Water Sample-
! s Loca tion Parameters
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- Sample. locations, parameters and . limits to be established based upon test program described in b'ases.
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w-- TABLE 4.7-3
.5'
$ SEC0llDARY' WATER CilEMISTRY SURVEILLANCE REQUIREMENTS
.:o -
q Water sample
.g Location Parameters
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1 M
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- Sample locations, parameters and frequencies to be established based upon test pro 9 ram described in bases.
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ti , AP
, PLANTSYSTEMS BASES positive reactivity effects of the Reactor Coolant System cooldown associated with the blowdown, and 2) limit the pressure rise within containment in the event the steam line rupture occurs within contain-ment. The OPERABILITY of the main steam isolation valves within the closure times of the surveillance requirements are consistent with the assumptions used in the safety analyses.
3/4.7.1.6 SECONDARY WATER CHEMISTRY A test program will be conducted during 1978 and 1979 to establish the appropriate limits on the secondary water chemistry parameters and to determine the appropriate frequencies for monitoring these parameters.
The results of this test program will be submitted to the Comission for review. The Commission will then issue a revision to this specification specifying the limits on the parameters and the frequencies for monitoring these parameters.
The test program will include an analysis of normal plant chemistry in-cluding background chemistry, present chemistry follow, and corrosion product hardness follow. Inleakage chemistry will be looked at by chloride follow, sodium follow, sulfate silica follow, modeling, resin throw, and turbine sampling. The chloride follow 'or example will consist of four intensive two-week studies and two extended four month.
studies. The intensive studies will sample the secondary water, low and high pressure steam, moisture separator drains, and demineralizer inlets and outlets. The extended studies will compare three groups of samplings for six weeks each. The sampling groups are: (1) secordary water, low and high pressure steam, and moisture separator drains; (2) secondary water, demineralizer inlets and outlets and low pressure steam; and (3) low pressure steam, low pressure turbine drains A and B, and condensate.
3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION The limitation on steam generator pressure and temperature ensures that the pressure induced stresses in the steam generators do not exceed the maximum allowable fracture toughness stress limits. The limitations of 110'F and 237 psig are based on a steam generator RT NDT f 40*F and are sufficient to prevent brittle fracture.
3/4.7.3 CLOSED CYCLE COOLING WATER SYSTEMS The OPERABILITY of the closed cycle cooling water system ensures that sufficient cooling capacity is available for continued operation of safety related equipment during normal and accident conditions. The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the safety analyses.
CRYSTAL RIVER - Unit # 3 B 3/4 7-3