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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
[Table view] |
Text
,; . Rev. O 11/1/79
,,,,./ ,
D - , , Q */ $ b., ,
MFOBQl'[ndAT PERFORMANCE TESTING PROCEDURE PT-109 FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 O
RC BLEED LINE LEAK RATE TEST REVIEWED BY: Plant Review Committec 8J). 977 a %ee Date / / h
!!eeting No. k-APPROVED.BY: Nuclear Plant !!anager As/AA/
g.n 2R 9h/2#
7911200 " 529
4 O 1.0 PURPOSE 1.1 The purpose of this test is to measure the actual leak rate of the reactor coolant (RC) bleed line between HUV-Il2 and the RC bleed tanks.
2.0 REFERENCES
AND ENCLOSURES
2.1 REFERENCES
2.1'.1 OP-407, Liquid Waste Disposal System 2.1.2 FPC Dwg. FD-302-681
- 2.1. 3 FPC Dwg. FD-302-661 2.1.4 MP-137, System Hydrostatic Pressure Testing 2.2 ENCLOS0RES Enclosure 1 Data Sheet I 3.0 TIME REQUIRED 3.1 Approximately 6 hrs. from start of test to completion ,
including:
- a. Assembly of Pressure Test Rig (PTR)
- b. System Testing
- c. Calculations
- d. Disassembly of PTR 4.0 MANPOWER 4.1 Plant Auxiliary Operator (1) 4.2 Level 11 Visual Inspector (1)
O 1371 2I3 Page 1 PT-109 Date 11/1/79 Rev. O
- 4. 3 Maintenance Mechanics (2) 4.4 Test Engineer (1) 5.0 SPECIAL TEST EQUIPt1ENT 5.1 lieans of timing leak collection (stcpwatch).
5.2 containers suitable for leakage collection.
. 5. 3 ?'iR similar to that described in flP-137, System Hydro-static Pressure Testing, Figure 1.
5.4 Jraduated container suitable for measuring total col-lected leakage.
4 6.0 LI!!ITS AND PRECAUTIONS 6.1 All work will be performed under a Radiation Work b Permit (RWP).
o.2 If leakage exists, the piping must be maintained under test pressure for a minimum of I hr. for leakage col-lection.
6.3 The PTR water supply shall be of RC makeup quality.
6.4 When the system is under pressure, the PTR must be manned at all times and pressure monitored.
6.5 If at any time the leak rate exceeds the acceptance criteria, the necessary repairs must be made and test redone.
6.6 If unanticipated bleed operations become necesstry during the performance of this test, terminate the l
test and restore the systems to normal operation.
I--2 t
Page 2 PT-109 Date 11/1/79 Rev. 0
\ 31 \ 2 \ 4'
() 6.7 There are no Technical Specifications applicable to this system.
7.0 REQUIRED PLANT STATUS AND PREREQUISITE CONDITIONS 7.1 Plant should be in Mode 3, 4, 5, or 6.
7.2 Bleed operations are not anticipated for the duration of the test.
- 7. 3 An appropriate RWP has been issued and approved.
8.0 TEST FETHOD Initials 3.1 Verify all required plant status and prerequisite con-ditions as set forth by Section 7.0 of this procedure have been completed.
flh 8.2 Verify normal system valve lineup per OP-407, Liquid Waste Disposal System.
8.3 Notify the Shift Supervisor that test is to begin.
8.4 Connect PTR to test connection (to be installed) between WDV-6 and WDV-18, 20, or 22.
8.5 Open WDV-6.
8.6 Position MUV-112 (three-way valve) for feed to makeup and purification filters 3A and/or 3B.
8.7 Verify that WDV-7 and WDV-8 are closed.
8.8 Verify that WDV-18, 20, and 22 are closed.
8.9 Pressurize PTR and assure zero leakage.
8.10 Notify Control Center that system is about to be ,
pressurized. __
O
\31\ 2\$
Page 3 PT-109 Date 11/1/79 Rev. O
() 8.11 Slowly open isolation valve on PTR. Verify that system pressure increases to test pressure value
~
(150 psig) +5%, -0%. __
8.12 Allow 15 min. for system stabilization.
8.13 Initiate inspection of piping and components for evidence of leakage.
8.14 If leakage is detected, collect for a period of not less than I hr. and record leakage on Data Sheet I of this procedure.
NOTE: If inspection of the piping and components dis-close no leakage, the test may be terminated and appropriate annotation made on Data Sheet I of this procedure.
fhh 8.15 Determine the system leak rate as required by Data Sheet I of this procedure.
8.16 Retu rn the system to normal as follows:
8.16.1 Stop the PTR pump.
8.16.2 Position MUV-ll2 for normal operation.
8.16.3 Close WDV-6.
8.16.4 Assure normal system lineup per OP-407, Liquid Waste Disposal System.
8.16.5 Close the PTR isolation valve vent and disconnect the PTR.
8.17 Notify Control Center and Shif t Supervisor that test is complete and of the results. .
O
\bl\ l\b Page 4 PT-109 Date 11/1/79 Rev. O
~
Q 9.0 DATA COLLECTION 9.1 Refer to Data Sheet I.
10.0 ACCEPTANCE CRITERIA 10.1 To be detemined; low as practical.
9 1371 2i.7 O
Page 5 PT-109 Date 11/1/79 Rev. O
h DATA Si!EET I ENCLOSURE I DELTA TitiE -
LEAK IDCATION TIME START TIME STOP (I HR/i!IN.) VOLUt!E LEAK RATE
9 O
TOTAL
- Leak Rate = Volume (gals.) = GPil Delta Time (hrs.)
O
\57\ 218 Page 6 PT-109 Date 11/1/79 Rev. O
