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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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occument sceti,n , 9 N F O R is AT I O N O N L 'id ~
C. R. Nuclear PERFORMANCE TESTING PROCEDURE PT-108 FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 DECAY HEAT RD10 VAL AND REACTOR BUILDING SPRAY SYSTDi LEAK RATE TEST REVIEWED BY: Plant Review Cocu:littee M u e\l h ate }/ /
I Q
/
Meeting No. N APPROVED BY: Nuclear Plant !!anage r i N c5n 29 0.t. ' u/ug -
\ 70112oo
\ : R SI 2
1.0 PURPOSE 1.1 The purpose of this test is to determine the actual leak rate of the decay heat removal (DHR) and Reactor Building (RB) spray systems to assure compliance with the applicable Technical Specifications.
2.0 REFERENCES
AND ENCLOSURES
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2.1 REFERENCES
2.1.1 OP-404, Decay Heat Removal System 2.1.2 OP-405, Reactor Building Spray System 2.1.3 FPC Drawings 2.1. 3.1 IS-318-641, Decay Heat Removal 2.1.3.2 IS-318-621, Spent Fuel Cooling
- 2.1. 3. 3 IS-318-711, Reactor Building Spray 2.1.3.4 IS-318-661, Makeup and Purification 2.1.3.5 IS-318-651, Reactor Coolant 2.1.4 ttP-137, System Hydrostatic Pressure Testing 2.1. 5 Plant Technical Specifications 2.2 ENCLOSURES Enclosure 1 Data Sheet 1 3.0 TI!1E REQUIRED 3.1 Approximately 8 hrs. from start of test to completion, including:
- a. Assembly of Pressure Test Rig (PTR)
- b. System Testing (two trains) i 1371 203 Page 1 FI-108 Date 11/1/79 Rev. 0
- c. Calculations
- d. Disassembly of PTR 4.0 MANPOWER 4.1 Plant Auxiliary Operator (1) 4.2 Level II Visual Inspectors (2) 4.3 Nbintenance Ikchanics (2) 4.4 Test Engineer (1) 5.0 SPECIAL TEST EQUIP!1ENT 5.1 Method of timing leak collection (stopwatch) 5.2 Containers suitable for leakage collection.
5.3 PTR similar to that described in MP-137, System Hydro-static Pressure Testing, Figure 1.
5.4 Calibrated container suitable for measuring total collected leakage.
6.0 LIMITS AND PRECAUTIONS 6.1 Any leak found during the performance of this test must be measured for a period of no less than I hr.
b.2 The PTR sater supply boron concentration must be main-tained equal or greater than that required for cold shutdova.
o.3 One train of the DilR must be operable for low pressure injection (LPI) during !! odes 1, 2, 3, and 4.
Page 2 PT-108 Date 11/1/79 Rev. O {37} -
- 6. 4 One train of the RB spray must be operable during Modes 1, 2, 3, and 4.
6.5 When the system is under pressure, the PTR must be manned at all times and pressure monitored.
6.6 All work will be performed under a Radiation Work Permit (RWP).
6.7 If at any time the leak rate exceeds 6 gph in the DHR
.. or RB spray systems, refer to Technical Specification 3.5.1 or 3.6.1.
6.8 SYSTEM TEST PRESSURE 6.8.1 Technical Specifications require leak rate measurement pressures of above 190 psig. The combined system leak rate test shall be conducted at 200 psig +5 -0% to assure meeting all requirements. If specific sections of the system are to be tested, refer to Technical Specifications 4.5.1 and 4.6.1 for minimum acceptable test pressures.
7.0 REQUIRED PLAh"I STATUS AND PREREQUISITE CONDITIONS 7.1 The plant should be in tbde 1, 2, or 3.
7.2 The DER system is in the normal standby mode per OP-404, Decay Ikat Removal System.
7.3 The RB spray system is in the normal standby mode per OP-405, Reactor Building Spray System.
7.4 RWP(s) for the performance of the test have been issued and approved.
1371 205 Page 3 PT-108 Date 11/1/79 Rev. O
- 7. 5 System fluid and PTR fluid are at approximately the same temperature.
8.0 TEST METHOD Initials 8.1 Verify all required plant status and prerequisite conditions have been met.
8.2 Verify that the DHR system is aligned as required by Valve Check List III of OP-404, Decay Ikat Removal System.
- 6. 3 Verify that the RB spray system is aligned as required by Valve Check List I of OP-405, Reactor Building Spray System.
8.4 Notify the Shift Supervisor that test is to begin and of the nature of the test.
8.5 Connect PTR to DHR system as follows:
- a. Verify SFV-87 is closed.
- b. Connect PTR to DRV-89.
8.6 Perform leak rate test on "A" train as follows:
8.6.1 Open and tag out breakers for DHP-3A and RBSP-3A.
NOTE: Implement the " Action Statements" of Technical Specifications 3.5.1 and 3.6.1.
8.6.2 Verify RCV-53 is closed.
8.o.3 Align DHR system valves as follows:
- 8. 6. 3.1 Close the following:
- a. DHV-34F
- b. DilV-18
- c. DHV-1.i
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Page 4 PT-108 Date 11/1/79 Rev. 0 1371 206
8.6.3.2 Open the following:
- a. DHV-8
- b. DHV-39
- c. DIIV-91
- d. DHV-41
- e. DHV-48 8.6.4 Align RB spray system valves as follows:
- a. Open BSV-5.
- b. Open BSV-28.
8.6.5 Start PTR and pressurize to test pressure.
- d. 6. 6 Visually check PTR connection for leakage; assure zero leakage before continuing.
8.6.7 Pressurize the system as follows:
8.6.7.1 Notify the Control Center Operator that system pres-
~
sure test is now in progress.
8.6.7.2 Slowly open DHV-89.
8.6.7.3 Verify that system pressure increases to test pressure
(+5% -0%).
8.6.7.4 Allow 15 min. for system stabilization.
8.6.7.5 Initiate inspection of components and piping for evidence of leakage.
8.6.7.6 If leakage is detected, collect the leakage for a period of not less than I hr. and record on Data Sheet I.
8.6.7.7 Determine the system leak rate per Data Sheet I.
1371 207
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Page 5 PT-108 Date 11/1/79 Rev. O
8.7 Return the system to normal as follows:
8.7.1 Close DHV-89.
8.7.2 Stop the PTR pump.
8.7.3 Align DHR valves as follows:
8.7.3.1 Close the following:
- a. DHV-48
- b. DHV-8
- c. DHV-39
- d. DHV-41
- e. DHV-91 8.7.3.2 Open the following:
- a. DHV-34F
- b. DRV-13
- c. DHV-18 6.7.3.3 Remove the tag from DHP-3A.
8.7.4 Align RB spray system as follows:
8.7.4.1 Close the following:
- a. BSV-28
- b. BSV-5 8.7.4.2 Remove the tag f rom RBSP-3A.
8.8 Perform leak rate test on "B" train as follows:
8.8.1 Open and tag out the breaker for DHP-3B and RBSP-38.
NOTE: Implement the " Action Statements" of Technical Specifications 3.5.1 and 3.6.1.
8.8.2 Align the valves of the DHR as follows:
1 1371 208 Page 6 PT-108 Date 11/1/79 Rev. O
8.8.2.1 Close the following:
- a. DHV-35F
- b. DHV-24 8.8.2.2 Open the following:
- a. DHV-7
- b. Dl!V-48 8.8.3 Pressurize the PTR to test pressure.
8.8.4 Assure zero leakage of PTR before continuing.
8.8.5 Repeat Section 8.6.7 for the "B" train.
8.9 Return the systes to normal as follows:
8.9.1 Close DHV-89.
8.9.2 Stop the PTR pump.
- e. 9. 3 Align the DHR system as follows:
8.9.3.1 Close the following:
- a. DHV-48
- b. DHV-7
- 8. 9. 3. 2 Open the following:
- a. DHV-35F
- b. DHV-24 8.9.3.3 Remove the tag f rom DHP-33.
8.9.4 Align RB spray system as follows:
8.9.4.1 Remove the tag f rom RBSP-3B.
- 8. 10 Determine the total system leak rate for the DHR system per Data Sheet I.
8.11 Determine the total system leak rate for the RB spray system per Data Sheet I.
k 1371 209 Page 7 PI-108 Date 11/1/79 Rev. O
, 8.12 When the total systeu leak rate has been determined to be 'less than 6 gph each for both the DER and RB spray syscens, return the system to normal as follows:
8.12.1 Verify that the DRR system is aligned per Valve Check List III of OP-404, Decay Heat Removal System.
8.12.2 Verify that the FB spray systen is aligned per Valve Check List I of OP-405, Reactor Building Spray System.
8.12.3 Vent and remove the PTR.
9.0 DATA COLLECTION 9.1 Refer to Data Sheet I.
10.0 ACCEPTANCE CRITERIA 10.1 The leak rate of either the DER system or the RB spray system may not exceed 6 gph.
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Page 8 PT-108 Da te 11/1/79 Rev. O
DATA SilEET I ENCLOSURE 1 Decay lleat Removal System:
LOCATION TIME START TIME STOP DELTA TIME VOLUME LEAK RATE
- INITIALS TOTAT, Reactor Building Spray System:
TOTAL
- Leak Rate = Volume (gals.)
Time (hrs.)
L \57\ 2\\
Page 9 PT-108 Date 11/1/79 Rev. O