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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
_
R*.v. 3 3/23/7s k* .
/
Document Section NFORM ATION ONL N C. R. Nuclear .
SURVEILLANCE PROCEDURE SP-670 FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3
( REACTOR BUILDING FUEL HANDLING BRIDGES (FHCR-1 & 2) LOAD TEST
{c'et5" M kh ,,
a- / N .. r.~,
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- -s/ts/77 i
REVIEWED BY: Pla Rev e
~
h/ J Committ, Date )
Meeting No. ['/
APPROVED BY: Nuclear Plant Manager i
f 9AfS S&e4* U 8 0 0313 o (Q> Date 9, / i r, / 7 r
1.0 SURVEILI.ANCE REQUIREMENTS The reactor building (RB) fuel handling bridges shall be demon-strated OPERABLE by performing-load capacity and load in'terlock l
tests. The demonstrations shall be performed during the modes !
I
-and at the frequencies indicated below. ;
l 1.1 TECHNICAL SPECI!! CATIONS REFERENCE Technical Surv. Req'd. Mode Surv. Freq.
Specification During Modes Notes Freo. Notes
.- 4.9.6 .
6 R 18 MODE NOTES: None SURVEILLANCE FREQUENCY:
R - Refueling (18 nonths)
FREQUENCY NOTES:
18 - Within 100 hrs. prior to movement of control rods or
(
fuel assemblies within the reactor pressure vessel.
2.0 ACCEPTANCE CRITERIA ,
2.1 ' Each R3 fuel handling bridge shall be OPERABLE with:
2.1.1 A hoist minimum capacity of 3,000 lbs., including weight of grapple tube, and 2.1.2 An automatic hoist overload cut-off limit of 2750 lbs. (wet)
~
or 2880 lbs. (dry), including weight of grapple tube.
NOTEi If the above acceptance criteria cannot be met, refer immediately to the " Action Statement" of Technical Specification (TS) 3.9.6.
3.0 REFERENCES
NEEDED TO DO PROCEDURE 3.1 Data Sheet I (Enclosure 1) 3.2 FP-601, Fuel Ha ' ling Equipment Operations Page 1 SP-670 Date 3/23/78 Rev. 3
i 4.0 SPECIAL CONDITIONS OR REQUIREMENTS I 4.1 During lifts to =4n4=n= loads or overload settings, do not exceed the expected load values by more than approximately 100 lbs; if automatic overload actuations do not occur do not
. proceed with Surveillance Procedure. Notify the Shift Supervisor.
5.0 EQUIPMENT REQUIRED None 6.0 PROCEDURE -
6.1 Demonstrate the OPERABILITY of the Mais Fuel Handling Bridge (FHCR-1) by performing the following steps:
6.1.1 Startup FHCR-1 in accordance with the startup procedure in FP-601, Fuel Handling Equipment Operation.
6.1.2 Place the main fuel hoist Dillon load cell range switch in position "A" (0 to 3000 lbs.) .
6.1.3 Position the main fuel handling grapple over the load testing fixture.. To position the auxiliary fuel handling grapple over the test fixture, the bridge left and trolly interlock bypass must be actuated.
6.1.4 Lower the main fuel handling grapple and engage the mating fitting on the test fixture. Visually check for proper engage-ment of grapple with test fixture.
l 6.1.5 . Slowly raise the main fuel handling grapple, using the "Jeg" button, until the hoist stops and the red " Overload" indicator light comes on. Record the fuel Dillon readout on Data Sheet I.
l- CAUTION: The overload cut-of f should actuate at or before reaching 2750 lbs. Do not exceed 2800 lbs.
Page 2 SP-670 _ _ _ _ _
Date 12/9/76 _
6.1.6 Slowly-lower the main fuel handling grapple until the fuel Dillon readout indicated approximately 2000 lbs.
6.1.7 Place the main fuel hoist Dillon load cell range switch in position "B" (3,000 to 6,000 lbs.).
6.1.8 Place the main fuel hoist' overload bypass switch in the "On" position.
6.1.9 Slowly raise the main fuel handling grapple, using the "J0G" button or manual handwheel, until the fuel Dillon readout indi-cates a load of 3050 t'o 3100 lbs.
Record the reading on Data Sheet I.
6.1.10 Lower the main fuel handling grapple to less than 3000 lbs. using the manual handwheel (grapple will not lower with jog button due to low load interlock being actuated by range switch in "B" position) then use jog button and disengage the test fixture visually verifying the disengagement.
6.1.11 Raise the main fuel handling grapple. Return the fuel hoist overload bypass switch to the "Off" position. Return the fuel hoist Dillon load cell range switch to the "A" (0 to 3,000 lbs.) position.
l i .
6.1.12 Complete the applicable section of the reactor building bridges log shttt attached to the bridge consoles.
Page 3 SP-670 Date 12/9/76 Rev. 2 ._
6.2 Demonstrate the OPERABILI1T of the Auxiliary Fuel Handling Bridge FHCR-2 by performing the following steps:
6.2.1 Startup FHCR-2 in accordance with the startup procedure in FP-601, Fuel Handling Equipment Operation.
6.2.2 Repeat Steps 6.1.2 through 6.1.11 except for the auxiliary fuel handling hoist, recording appropriate data on Data Sheet I.
6.2.3 Complete the applicable section of the reactor building bridges log sheet attached to the bridge consoles.
6.3 Return both FHCR-1 and FHt'2-2 bridges to their normal park locations and then, if applicable, shut'down both bridges in accordance with FP-601, Fuel Handling Equipment Operation.
6.4 No restoration is required.
- 6. 5 Notify the Shif t Supervisor of the completion and results of this Surveillance Procedure.
Page 4 SP-670 Date 5/21/76 Rev. 1 v --
T
ENCLOSURE 1
' ' 5. . SP-670 DATA SHEET I
\
l l
REACTOR BUILDING FUEL RANDLING BRIDGES (FCHR-1 & 2)
LOAD TEST TEST EQUIPMENT NO.
NONE ACTUAL ITEM REQUIRED FHCR-1 FHCR-2 Dillon Fuel load cell range switch placea in position "A" Fuel load cell reading at overload actuation, lbs. < 2750
- Dillon Fuel load cell range switch placed in position "B" Fuel hoist overload bypass switch placed in position. "On" Fusi load cell reading at =inimum lift capacity, lbs. 2,3000 el hoist overload bypass switch placed in position "Off" Dillon Fuel load cell range switch placed in position "A" Rod load cell reading with du=my rod lifted clear C010ETIS:
PERFORMED BY: DATE:
0When handling control rods or fuel assemblies with 3,23 feet of water over the top of fuel assemblies seated in the reactor core; otherwise the hoist overload cutoff shall be set at 2880 lbs, including the weight of grapple tube.
Page 5 '
-SP-670 Date 12/9/76 Rev. 2
