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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20212E9031999-09-30030 September 1999 FPC Crystal River Unit 3 Plant Reference Simulator Four Year Simulator Certification Rept Sept 1995-Sept 1999 ML20211L1321999-08-31031 August 1999 EAL Basis Document ML20212C1501999-08-31031 August 1999 Non-proprietary Version of Rev 0 to Crystal River Unit 3 Enhanced Spent Fuel Storage Engineering Input to LAR Number 239 ML20209F5601999-07-31031 July 1999 EAL Basis Document, for Jul 1999 ML20155F4071998-10-31031 October 1998 Rev 2 to Pressure/Temp Limits Rept ML20236W6501998-07-31031 July 1998 Emergency Action Level Basis Document ML20236V8801998-07-30030 July 1998 Control Room Habitability Rept ML20217B1731998-04-16016 April 1998 FPC Crystal River,Unit 3,Tendon Surveillance Program Engineering Evaluation of Sixth Tendon Surveillance ML20203K1521998-02-28028 February 1998 Post-LOCA Boron Concentration Mgt for CR-3 ML20203K4991998-02-16016 February 1998 Boron Dilution by RCS Hot Leg Injection ML20202J4291998-02-13013 February 1998 Rev 2 to MPR-1887, Crystal River 3 Reactor Bldg Cooling Fan Logic Mod Failure Modes & Effects Analysis ML20198J8181998-01-10010 January 1998 Assessing Performance & Organizational Roles ML20198J8371998-01-10010 January 1998 Engineering ML20198J8621998-01-10010 January 1998 Maintenance ML20198J8821998-01-10010 January 1998 Licensing ML20198J7501998-01-10010 January 1998 Corrective Action Program Overview ML20198J7811998-01-10010 January 1998 Design & Licensing Basis ML20198J8041998-01-10010 January 1998 Integrated Verification Team Rept ML20198J7291998-01-10010 January 1998 Overall Restart Readiness ML20198J8571998-01-10010 January 1998 Operations ML20198J8881998-01-10010 January 1998 Training ML20198H5071997-12-31031 December 1997 Rev 5 to Justification for Continued Operation for CR Emergency Ventilation Sys & Control Complex Habitability Envelope ML20197B2911997-12-11011 December 1997 Generic Operability Evaluation for Large Bore Safety Related Piping at Crystal River-3 ML20198K4451997-11-30030 November 1997 Reactor Bldg Cooling Fan Logic Mod Failure Modes & Effects Analysis, Rev 0 ML20202D4161997-11-26026 November 1997 Mod Outage Integrated Verification Team Rept ML20199K4731997-11-24024 November 1997 Sys Readiness Review Summary Rept ML20212F4191997-10-31031 October 1997 Revised Boron Dilution by RCS Hot Leg Injection ML20199D5751997-10-30030 October 1997 Overview of Safety Related Large Bore Piping & Piping Support Design & Construction Currently Existing at Crystal River-3 Nuclear Power Plant, Rev 0 ML20198T1051997-10-25025 October 1997 Tracer Gas Air Inleakage Measurements within Crystal River Unit 3 Control Complex Habitability Envelope, Summary Rept ML20211N1771997-10-11011 October 1997 Rev 1 to Pressure/Temp Limits Rept ML20210T9421997-08-29029 August 1997 B Dilution by Hot Leg Injection ML20148K7961997-06-12012 June 1997 Safety Analysis Input to Startup Team Safety Assessment Rept ML20148J3821997-05-23023 May 1997 Rev 16 to PSA F Annunciator Response ML20141D9401997-04-16016 April 1997 Summary Document for Pressurizer NDE Development for FPC Crystal River Unit 3 ML20132F4861996-12-0303 December 1996 Restart Panel ML20133B2711996-10-31031 October 1996 Monthly Trend Rept for Oct 1996 ML20199D5431996-10-28028 October 1996 Evaluation of Piping & Support Documentation for Crystal River 3 ML20134K9581996-10-15015 October 1996 Independent Design Review Panel Rept on 961015 ML20117C6431996-07-25025 July 1996 FPC Crngp Unit 3 Graded Approach Methodology for Instrument Uncertainty ML20101F6081996-02-29029 February 1996 Iga & Wear Voltage Correlations & Uncertainty Analysis ML20100G4141996-02-29029 February 1996 Input to Items a & C of NRC Questions on Relief Request for Insp of Transition Piece to Bottom Head Weld at Crystal River Unit 3 ML20100G4281996-02-0101 February 1996 Flaw Acceptance Handbook for Crystal River Unit 3 RPV & Nozzle Weld Insps ML20095L1461996-01-0202 January 1996 Seismic Evaluation Rept for USI A-46, Rev 0 ML20098A4571995-09-19019 September 1995 Plant Ref Simulator Four Yr Simulator Certification Rept ML20101F6001995-06-30030 June 1995 Alternate Disposition Strategy for Low Vol OTSG Eddy Current Indications ML20092M2061995-06-27027 June 1995 Pyrolysis Gas Chromatography Analysis of 3 Thermo-Lag Fire Barrier Samples ML20084L6931995-05-31031 May 1995 Exam of Crystal River-3 Pulled SG Tubes Final Rept B51956, 8R/9R Bobbin Voltage (S/N) Growth Rate Calculations1995-05-31031 May 1995 8R/9R Bobbin Voltage (S/N) Growth Rate Calculations ML20092M2051995-05-11011 May 1995 Pyrolysis Gas Chromatography Analysis of 5 Thermo-Lag Fire Barrier Samples ML20080T4661995-02-27027 February 1995 Final Rept One & Three H Fire Endurance Tests & Hose Stream Tests Thermal Barrier Sys for Electrical Components 1999-09-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G0191999-10-15015 October 1999 Safety Evaluation Concluding That Licensee Followed Analytical Methods Provided in GL 90-05.Grants Relief Until Next Refueling Outage,Scheduled to Start on 991001.Temporary non-Code Repair Must Then Be Replaced with Code Repair 3F1099-19, Part 21 Rept Re Damage on safety-grade Cable Provided to FPC by Bicc Brand-Rex Co.Damage Was Created During Cabling Process While Combining Three Conducters.Corrective Action Program Precursor Card PC99-2868 Was Initiated1999-10-13013 October 1999 Part 21 Rept Re Damage on safety-grade Cable Provided to FPC by Bicc Brand-Rex Co.Damage Was Created During Cabling Process While Combining Three Conducters.Corrective Action Program Precursor Card PC99-2868 Was Initiated ML20217B0931999-10-0606 October 1999 Part 21 Rept Re Damaged Safety Grade Electrical Cabling Found in Supply on 990831.Damage Created During Cabling Process While Combining Three Conductors Just Prior to Closing.Vendor Notified of Reporting of Issue ML20212L0881999-10-0404 October 1999 SER Accepting Licensee Requests for Relief 98-012 to 98-018 Related to Implementation of Subsections IWE & Iwl of ASME Section XI for Containment Insp for Crystal River Unit 3 ML20212J8631999-10-0101 October 1999 Safety Evaluation Supporting Licensee Proposed Alternatives to Provide Reasonable Assurance of Structural Integrity of Subject Welds & Provide Acceptable Level of Quality & Safety.Relief Granted Per 10CFR50.55a(g)(6)(i) ML20212E9031999-09-30030 September 1999 FPC Crystal River Unit 3 Plant Reference Simulator Four Year Simulator Certification Rept Sept 1995-Sept 1999 3F1099-02, Monthly Operating Rept for Sept 1999 for Crystal River,Unit 3.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Crystal River,Unit 3.With ML20212E6911999-09-21021 September 1999 Safety Evaluation Supporting Proposed EALs Changes for Plant Unit 3.Changes Meet Requirements of 10CFR50.47(b)(4) & App E to 10CFR50 ML20211L1321999-08-31031 August 1999 EAL Basis Document 3F0999-02, Monthly Operating Rept for Aug 1999 for Crystal River,Unit 3.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Crystal River,Unit 3.With ML20212C1501999-08-31031 August 1999 Non-proprietary Version of Rev 0 to Crystal River Unit 3 Enhanced Spent Fuel Storage Engineering Input to LAR Number 239 ML20211B7291999-08-16016 August 1999 Rev 2 to Cycle 11 Colr ML20210P1111999-08-0505 August 1999 SER Accepting Evaluation of Third 10-year Interval Inservice Insp Program Requests for Relief for Plant,Unit 3 ML20210U5341999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Crystal River,Unit 3 ML20209F5601999-07-31031 July 1999 EAL Basis Document, for Jul 1999 3F0799-01, Monthly Operating Rept for June 1999 for Crystal River,Unit 3.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Crystal River,Unit 3.With ML20210U5411999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Crystal River,Unit 3 3F0699-07, Monthly Operating Rept for May 1999 for Crystal River,Unit 3.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Crystal River,Unit 3.With ML20210U5601999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Crystal River,Unit 3 ML20195C6271999-05-28028 May 1999 Non-proprietary Rev 0 to Addendum to Topical Rept BAW-2346P, CR-3 Plant Specific MSLB Leak Rates ML20196L2031999-05-19019 May 1999 Non-proprietary Rev 0 to BAW-2346NP, Alternate Repair Criteria for Tube End Cracking in Tube-to-Tubesheet Roll Joint of Once-Through Sgs 3F0599-04, Monthly Operating Rept for Apr 1999 for Crystal River Unit 3.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Crystal River Unit 3.With ML20210U5631999-04-30030 April 1999 Revised Monthly Operating Rept for Apr 1999 for Crystal River,Unit 3 3F0499-04, Monthly Operating Rept for Mar 1999 for Crystal River Unit 3.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Crystal River Unit 3.With ML20204D9661999-03-31031 March 1999 Non-proprietary Rev 1,Addendum a to BAW-2342, OTSG Repair Roll Qualification Rept 3F0399-04, Special Rept 99-01:on 990310,discovered Containment Tendons That Required Grease Addition in Excess of Prescribed Limits During Recent Insp Activites.Six Tendons Were Refilled with Appropriate Amount of Grease1999-03-10010 March 1999 Special Rept 99-01:on 990310,discovered Containment Tendons That Required Grease Addition in Excess of Prescribed Limits During Recent Insp Activites.Six Tendons Were Refilled with Appropriate Amount of Grease 3F0399-03, Monthly Operating Rept for Feb 1999 for Crystal River Unit 3.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Crystal River Unit 3.With ML20203A4381999-02-0303 February 1999 Safety Evaluation Supporting EAL Changes for License DPR-72, Per 10CFR50.47(b)(4) & App E to 10CFR50 ML20206E9891998-12-31031 December 1998 Kissimmee Utility Authority 1998 Annual Rept ML20206E9021998-12-31031 December 1998 Florida Progress Corp 1998 Annual Rept ML20206E9701998-12-31031 December 1998 Ouc 1998 Annual Rept. with Financial Statements from Seminole Electric Cooperative,Inc 3F0199-05, Monthly Operating Rept for Dec 1998 for Crystal River Unit 3.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Crystal River Unit 3.With ML20206E9261998-12-31031 December 1998 Gainesville Regional Utilities 1998 Annual Rept 3F1298-13, Monthly Operating Rept for Nov 1998 for Crystal River,Unit 3.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Crystal River,Unit 3.With 3F1198-05, Monthly Operating Rept for Oct 1998 for Crystal River,Unit 3.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Crystal River,Unit 3.With ML20155F4071998-10-31031 October 1998 Rev 2 to Pressure/Temp Limits Rept ML20155J2701998-10-28028 October 1998 Second Ten-Year Insp Interval Closeout Summary Rept 3F1098-06, Monthly Operating Rept for Sept 1998 for Crystal River Unit 3.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Crystal River Unit 3.With ML20206E9461998-09-30030 September 1998 Utilities Commission City of New Smyrna Beach,Fl Comprehensive Annual Financial Rept Sept 30,1998 & 1997 ML20206E9561998-09-30030 September 1998 City of Ocala Comprehensive Annual Financial Rept for Yr Ended 980930 ML20206E9101998-09-30030 September 1998 City of Bushnell Fl Comprehensive Annual Financial Rept for Fiscal Yr Ended 980930 ML20206E9811998-09-30030 September 1998 City of Tallahassee,Fl Comprehensive Annual Financial Rept for Yr Ended 980930 ML20195E3121998-09-30030 September 1998 Comprehensive Annual Financial Rept for City of Leesburg,Fl Fiscal Yr Ended 980930 3F0998-07, Monthly Operating Rept for Aug 1998 for Crystal River Unit 3.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Crystal River Unit 3.With ML20236W6501998-07-31031 July 1998 Emergency Action Level Basis Document 3F0898-02, Monthly Operating Rept for Jul 1998 for Crystal River,Unit 11998-07-31031 July 1998 Monthly Operating Rept for Jul 1998 for Crystal River,Unit 1 ML20236V8801998-07-30030 July 1998 Control Room Habitability Rept 3F0798-01, Monthly Operating Rept for June 1998 for Crystal River Unit 31998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Crystal River Unit 3 ML20236Q4611998-06-30030 June 1998 SER for Crystal River Power Station,Unit 3,individual Plant Exam (Ipe).Concludes That Plant IPE Complete Re Info Requested by GL 88-20 & IPE Results Reasonable Given Plant Design,Operation & History 3F0698-02, Monthly Operating Rept for May 1998 for Crystal River Unit 31998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Crystal River Unit 3 1999-09-30
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J s INTERIM RESP 0ilSE TO -
U OVERPRESSURIZATI0il AT SHUTOOWN C0ftDITIONS There have been a number of reactor vessel overpressurization occurrences in operating PWR plants in which the Technical Specification Limit for maximum RC System pressure has been exceeded. The majority of these occurrences have occurred when the RC System was in a " solid water" condition during cold shutdown.
For those occurrences which have the potential for causing the RC System pressure to increase, the increase will be significantly faster in a
" solid water" system than in a B&W Plant with a steam or gas space in the pressurizer. The Crystal River 3 Unit will always operate with a steam.or_ nitrogen gas bubble in the pressurizer; no operations will involve a " solid water" condition.
To provide additional assurance that no overpressurization event will occur on Crystal River #3, the following additional design controls are available:
- 1. Nitrogen Overpressure Protection - CR#3 utilizes nitrogen gas to maintain the gas bubble in the pressurizer whenever a steam bubble is not maintained. In accordance with plant operating procedures, nitrogen gas is added to the pressurizer when the RC System pressure is at 50 psig or less during plant cooldown. Nitrogen addition is controlled by a 50 psig regulator valve (HGV-85). Relief valve NGV-ll5 provides protection against RC System overpressurization in the event of regulator failure. In addition, plant operating procedures require that NGV-82 be normally locked closed to prevent erroneous addition of nitrogen to the pressurizer. These valves are shown on FSAR Figure 6-28.
- 2. Dual Setooint Pilot Actuated Relief Valve - A dual setpoint capability will be added for the pilot actuatad relief valve located on the pressurizer. The lower setpoint (550 psig) will be initiated by automatic actuation of a temperature switch closing at approximately 300 F RCS ternperature during plant cooldown prior to startup of the-Decay Heat Peraval System at 280 F RCS temperature. Use of the pilot-actuated relief valve with the lower setpoint will provide overpressure protection for CRi3 for any credible occurrence in the #
shutdown condition. This dual setpoint modification will require approximately 2 months for materials and installation. In the interim, we have available through present CR#3 design and administrative controls the capability for the operator to manually actuate from the Control Room the pilot-actuated relief valve. Upon indication .
of a RC System pressure of 550 psig, the operator would actuate the relief valve by turning the key switch located in the Non-nuclear Instrumentation Cabinets (NNI) from the automatic to the open position. Opening of the relief valve will be verified by position l indicator lights and is alarmed in the Control Room. Shutdown !
procedures will contain the provision for this action until the l design change is effected. j 6003180 7 7
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- 3. Alarms and/or Indications - The following alarms and/or indications are available to the operator to aid in detection of potential for and/or termination of an overpressure transient.-
A.. Pres'surizer high level alarm (s) '
-B. Higher than normal makeup line flow rate indication
- _ _ . , C. Lower than normal makeup pump discharge pressure D. Full open indicating. light for makeup valve E. High temperature alarm for relief valve discharge line F. Higher than nomal RCS pressure. indication G. Higher than normal pressurizer level indication H. Higher than normal . letdown flow rate indication to makeup tank I. The "on" indicating lights for all pressurizer heater banks J.. HPI actuation alarm K. HPI pump status indication L. CFT discharge valve (s) position indication and alarms -
u M. CFLlevel _ indication H. Pressurizer pilot actuated relief valve position indication and alam
- 0. Makeup tank level indication and high and low level alams P. DH pump (s) status indication
.Q. DH pump (s) discharge valve position indication R. DH pump s) low flow alarm (s)
S. flow rate indication T. DHpumps)'statusindication RC pump s)
U. RC drain tank level indication In addition to the design features outlined above, the fallowing administrative controls are included in the present plant operating procedures or will be added to reduce the potential for RC System overpressurization.
- 1. The cooldown, shutdown, startup and testing of CR#3 are performed ;
in accordance with approved plant operating procedures and technical l specifications. The operator must initial each step of an operating 1
- procedure until completed. Following completion of a procedursl !
section. the shift supervisor checks to see that all steps were perfomed and then signs off on the-procedure indicating his acceptance. Procedural steps requiring the removal of equipment from ~.
. operation.or the lcr. king out of pump and valve breakers, etc.
.must be' perfomed in accordance with Procedure CP-115 In-plant
' Equipment Clearance end Switching Orders. This procedure requires that the operator mutt obtain from the shift supervisor an 'In-plant Equipment Clea':ance Order prior to removing equipment from service or locking out breakers of pumps and valves. Once the Equipment )
Clearance Order has been executed by -the op'erator the equipr. -
will-be tagged in accordance with CP-ll5. For electrical purposes, red tags are.placed on all open switches or control handles when these switches are not to be closed. For mechanical
x purposes, a red tagged device shall not be operated or moved from its tagged position. Ir; the case of locking out breakers of pumps and: valves _ red tags.are placed'on buth the control
. room breaker switches and at the breaker location. Once this
- equipment has been placed under these administrative restrictions, the status of this equipment cannot be changed until the Shift -
Supervisor issues the appropriate Equipment _ Clearance Order allowing the change of status.
'2. The circuit breakers for the four normally closed HP injection motor-operated valves are " locked out" during plant cooldown when the RC System pressure is less than or. equal to 150 psig.
This.is accomplished by opening and tagging the selector switch in the Control' Room and locking out and tagging the breakers located at the Motor Control Center. The operator has indiciation that power has been removed as the status lights in ,
the Control Room will be off.
- 3. - No testing of the HPI pumps during shutdown, as requir_ed by CR#3 Technical Specifications, will be performed except when the Reactor Vessel head is physically removed from the vessel.
- 4. . At'700 psig or less, the CFT motor-operated block valves, CFV-5 & 6, will be closed and the' breakers placed in the " locked out" position and tagged n accordance with CP-ll5. The locking out of the breakers is accenplished at the breaker location
'outside the Control Room. W status of the position of the CFT block valves is indicated in V e Control Room by position indicator lights and is alarmed should the position change.
- 5. As part of our cooldown procedure, the pressurizer heater banks will be placed in the off position during cooldown to prevent erroneous energizing of the heaters. This function is performed by the operator from the Control Room. Position indicator lights in the Control Room provide the operator with continuous status of the heaters. I
- 6. Maintenance on the pilot-actuated relief valve located on the pressurizer will be performed only when the RC System is in Modes 5 or 6 and is _at steady state conditions. -~
The CRr3 Decay Heat System is. designed to include redundant, diverse,
. interlock and automatic closure of both DH high-pressure isolation valves tc prevent pos'sible overpressurization of_ the DH system from-the Reactor Coo? ant System. These features include the following: .
- a. 'ndependent and diverse interlocks on each valve to prevent
- gross-overpressurization of_ the DH system by preventing the opening of.these _ valves when RC System pressure exceeds 284 psig.
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- b. Instrumentation and controls to ensure automatic closure of
. the valves if these same conditions exist.
In addition, the DH System has the following installed relief capacity:
Approx Water Relief Capacity
'!al Je,: Pressure Relief Setpoint at 10%&25% Overpressure 9 70*F(gpm) 10% 25%
'DHV-37(F) 300'psig 17"- 7873 DHV-38(F) _ 300 psig 17 28.3 DHV-14(F) 300 prig 17 28.3 DHV-17(F) 450~psig 20.5 34.2 DHV-28(F ) . - 450 psig 20.5 34.2 -
Since- the 0H System is automatically isolated from the RC System when .the RC pressure exceeds 284 psig, no additional relief protection from the DH System is availabile to the RC System in the event of an overpressure transient.
Conclusion The.dosign controls presently. installed-and the administrative controls which -have been discussed herein, provide sufficient assurance that a Reactor Coolant System overpressurization event will not occur at Crystal River Unit #3.
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