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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] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20205A7651999-03-18018 March 1999 Rev 29 to AR-305, Es E Annunciator Response ML20205A8051999-03-15015 March 1999 Rev 33 to AR-303, ESC Annunciator Response ML20205A7961999-03-15015 March 1999 Rev 22 to AR-301, ESA 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 ML20203C7461999-02-0303 February 1999 Rev 2 to AR-801, FSA Annunciator Response 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 ML20196G3371998-11-25025 November 1998 Reissued Rev 15 to AR-702, Ssf Q Annunciator Response ML20196G5851998-11-25025 November 1998 Rev 32 to AR-303, ESC Annunciator Response ML20196F6691998-11-24024 November 1998 Rev 11 to AP-330, Loss of Nuclear Svc Cooling ML20196F7161998-11-23023 November 1998 Rev 9 to AP-470, Loss of Instrument Air ML20196F7031998-11-23023 November 1998 Rev 3 to AP-404, Loss of Decay Heat Removal ML20196F8711998-11-23023 November 1998 Rev 28 to AR-305, Es E Annunciator Response ML20196F7541998-11-23023 November 1998 Rev 7 to EOP-08, LOCA Cooldown ML20196F7241998-11-23023 November 1998 Rev 2 to AP-510, Rapid Power Reduction ML20196F7461998-11-23023 November 1998 Rev 6 to EOP-07, Inadequate Core Cooling ML20196F7721998-11-23023 November 1998 Rev 3 to EOP-12, Station Blackout 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 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 ML20154E5161998-10-0101 October 1998 Rev 10 to AP-961, Earthquake ML20154C2691998-09-29029 September 1998 Rev 19 to AR-304, ESD Annunciator Response ML20154C2751998-09-29029 September 1998 Rev 18 to AR-701, Ssf P Annunciator Response ML20154E5361998-09-28028 September 1998 Rev 34 to AR-403, PSA H Annunciator Response ML20154F0841998-09-28028 September 1998 Rev 21 to AR-503, ICS K Annunciator Response ML20154E5271998-09-28028 September 1998 Rev 20 to AR-301, ESA Annunciator Response ML20154Q0061998-09-24024 September 1998 Rev 8-0 to Crystal River Unit 3 Security Training & Qualification Plan ML20237B4431998-08-10010 August 1998 Rev 14 to AR-703, Ssf R Annunciator Response ML20236W9711998-07-30030 July 1998 Rev 24 to AR-402, PSA G Annunciator Response ML20236P9891998-07-13013 July 1998 Rev 22 to AR-501, ICS I Annunciator Response ML20249C1531998-06-20020 June 1998 Rev 4 to EOP-14, Emergency Operating Procedure Enclosures ML20249A3341998-06-0505 June 1998 Rev 10 to AP-330, Loss of Nuclear Service Cooling ML20247E6861998-05-0606 May 1998 Rev 20 to AR-603, Tgf O Annunciator Response ML20217Q4621998-04-30030 April 1998 Rev 15 to Crystal River Unit 3 ASME Section XI Pump & Valve Program Inservice Testing Program ML20247E6621998-04-30030 April 1998 Rev 10 to AP-250, Radiation Monitor Actuation ML20216A9981998-04-24024 April 1998 Rev 30 to AR-303, ESC Annunciator Response ML20217E1481998-04-20020 April 1998 Rev 21 to AR-302, Esb Annunciator Response ML20217C1441998-04-17017 April 1998 Rev 20 to ICS K Annunciator Response ML20217C2631998-04-17017 April 1998 Rev 13 to AR-703, Ssf R Annunciator Response 1999-03-09
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'Wu SURVEILLANCE PROCEDURE SP-412 FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 ECCS AND CONTAINMENT SPRAY SYSTEM LEAK RATE TEST REVIEWED BY: Plant Review Comittee f th hb N Date i
!/[ !
h Meeting No.
APPROVED BY: Nuclear Plant Manager 12
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3yn 185 Date
' e/xo45 7911200 [h
N 1.0 SURVEILLANCE REQUIREMENTS The Emergency Core Cooling and Containment Spray System piping and components shall be inspected while pressurized to ensure that any leakage is within acceptable limits. This inspection, and leakage measurement if necessary, shall be performed during the modes and at the frequencies indicated below.
1.1 Technical Specification Reference Technical Surv. Req'd Modes Sury. Freq.
Specification During Modes Notes Freq. Notes 4.5.2.e.5 3 R 30 l 4.6.2.1.c 3 R 30 Surveillance Frequency Designation:
R-Refueling (18 Months)
Modes Notes:
None Frequency Notes:
30-Prior to Shutdown for Refueling 2.0 ACCEPTANCE CRITERIA 2.1 The following Recirculation Phase piping and components shall exhibit a combined total leak rate j:,6 gallons per hour when pressurized as indicated:
2.1.1 The piping and components from the containment emergency sump isolation valves (DHV-42, 43) to the suction valves of the Decay Heat Removal Pumps and the suction valves of the Reactor Building Spray Pumps at pressure 3,55 psig.
2.1.1.1 The Decay Heat System piping and components from the pump suction valves downstream to the Reactor Coolant System at pressure 3,
( 150 psig, g Page 1 SP-412 Date 2/15/79 Rev. 2
v 2.1.1.'2 The Containment Spray System piping and components from the Reactor Building Spray Pumps suction valves downstream to the Reactor Building Isolation Valves (BSV-3, 4) at pressure ,,
> 190 psig.
NOTE: If the Acceptance Criteria of 2.1 cannot be met refer immediately to the " Action Statements of 3.5.2 and 3.6.2.1, as applicable, of the Technical Specifications.
3.0 REFERENCES
NEEDED TO DO PROCEDURE 3.1 Data Sheet I (ENCLOSURE I) 4.0 SPECIAL CONDITIONS OR REQUIREMENTS ,
4.1 The Building Spray System is filled (to the RB Spray Header -
Inlet Iso. valves, BSV-3 and 4) and vented.
4.2 Reactor plant cooldown is in progress per OP-209, Plant Cooldown, with a hold in effect at RC temperature between 280 F0and 3000 F and RC pressure at approximately 200 psig to place the Decay Heat Removal System in service in accordance with OP-404, Decay Heat Removal System.
4.3 The total leakage, if any, from the piping defined in Step 2.1 is to be measured with all the piping at the RCS pressure, namely between 190 and 200 psig. This pressure will satisfy the pressurization requirements of each of the individual sections defined in Step 2.1. If leakage exists, the piping sections must be kept pressurized during the entire 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> leakage ,
collection period.
O 1371 187 Page 2 SP-412 Date 2/7/76 Rev. 1
5.0 EQUIPMENT REQUIRED s
5.1 A watch to measure the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period of leakage collection, if applicable.
5.2 Suitable containers to collect leakage, if applicable.
5.3 A suitable container calibrated to 6 gallons for determining total leakage, if applicable.
6.0 PROCEDURE 6.1 After placing the Decay Heat Removal System in service but prior to decreasing RC temperature and pressure below 280 07 and 190 psig respectively, read and record the pressures specified in Data Sheet I.
NOTE: Pressure indicators DH-005-PI 1 and 2 display pressure of piping defined in Step 2.1.1.1; BS-002-PI 1 and 2 the piping defined in Step 2.1.1.2; and RCS pressure the piping defined in Step 2.1.1.
6.2 Inspect the piping and components for, leakage. If any leakage is detected, collect the fluid from each leak for one hour, determine the total leakage flow rate, and record this value and another set of pressure readings on Data Sheet I.
6.3 No r'e-roration is required.
6.4 Notift the Shift Supervisor of the completion and results of this Surveillance Procedure.
i371 188 Page 3 SP-412 Date 2/7/76 Rev. 1
- ENCLOSURE 1 DATA SHEET I O
ECCS AND CONTAINMENT SPRAY SYSTEM LEAK RATES PRESSURE PRESSURE PIPING SECTION LEAKAGE ACTUAL REQUIRED INDICATION INITIAL FINAL Common piping from the contain-RCS ment sump isolation valves to gph. psig psig 1 55 psig DHP'and BSP suctions DH-005-PI I DHS piping from pump suctions gph psig psig 1 150 psig
. DH-005-PI 2 to RCS gph psig psig 3 150 psig BS-002-PI 1 BS piping from pump suctions gph psig psig 1 190 psig .
BS-002-PI 2 to spray isolation valves gph psig psig 1 190 psig TOTAL ACTUAL LEAKAGE ghp TOTAL ALLOWABLE LEAKAGE <6 ghp COMMENTS:
PERFORMED BY:
O, 1371 189 Page 4 SP-412 Date 2/7/76 Rev. 1