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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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3 i FLORIDA POWER CORPORATION
-CRYSTAL RIVER UNIT 3 CONTAINMENT STRUCTURAL INTEGRITY i
DOME-SURVEILLANCE I
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. Prepared by: C11hert AssocIntes, Inc. !
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I- Date: 4'-26-77 !
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TABLE OF CONTEUTS Section Page .
Table of Contents . . . . . . . . . . . . . . . . . i 1.0 V SCOPE . .. . . . . . . . . . . . . . . . . . . . . 1
2.0 DESCRIPTION
. . . . . . . . . . . . . . . . . . . . 1 2.1 SURVEY OF DOME SURFACE ELEVATIONS . . . . . . . . . 1 2.1.1 Procedure . . . . . . .. . . . . . . . . . . . . .
1 2.1.2 Acceptance Criteria . . . . . . . . . . . . . . . . 2 2.1.2.1 Normal Operation / Shutdown . . . . . . . . . . . . . 2 2.1.2.2 First Periodic Containment Integrated Leak Race Test (ILRT) . . . . . . . . . . . . . . . . . . . . 3 2.2 CRACK INSPECTION . . . . . . . . . . . . . . . . . 3 3.0 .
SURVEILLANCE INTERVALS . . . . . . . . . . . . . . 3
4.0 REFERENCES
. . . . . . . . . . . . . . . . . . . . 4 FIGURE 1 . . . . . . . . . .. . . . . . . . . . . 5 FIGURE 2 . . . . . . . . . . . . . . . . . . . . . 6 Date: 4-26-77 Rev. 1 1
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FLORIDA POWER CORPORATION CRYSTAL RI'!ER UNIT 3 ^
CONTAINMENT STRUCTURAL INTEGRITY DOME SURVEILLANCE 1.0 SCOPE ,
The Crystal River' Unit 3 operating license requires a surveillance program for the purpose of detecting future delamination of the Reactor Containment Building dome.
The dome is a combined prestressed and conventiorally reinforced .
concrete structure. The capability of the dome to withstand postulated loads is demonstrated by References 1 and 2.
This report describes an enhanced inservice surveillance program (in addition to tendon surveillance) which is responsive to the USNRC requirements.
l
2.0 DESCRIPTION
The surveillance program described herein consists of periodic monitoring of relative vertical movements of the dome and in-s action of surface cracks.
2.1 SURVEY OF DOME SURFACE ELEVATIONS 2.1.1 Procedure Permanent benchmarks will be established at three (3) locations.
tm the ring girder to which survey mensiirements of the dome wi t L be referenced. Seven (7) permanent survey points will be located Page 1 Date: 4-26-77 Rev. 1 L
on the dome. A baseline survey will establish the clevation dif-ference between each of the seven. dome survey points and the three (3) benchmarks (see Figure 1).
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At the surveillance intervals specified in Section 3.0, the baseline survey procedure will be repeated. The elevation differences be-tween the survey points and the benchmarks will be computed and compared to baseline differences.
2.1.2 Acceptance criteria .
The measured changes in elevation differences will be compared to an acceptance criteria which is dependent upon the state of the structure at the time of the surveillonce. This state will be either normal operation / shutdown or pressurized for a contain-ment integrated leak rate test.
2.1.2.1 Normal Operation / Shutdown The vertical movement of the dome during normal operation / shutdown will be upward or downward from the baseline condition as a function of temperatures inside and outside the Reactor Contain-ment Building. The acceptance limit for this state of the strUc-ture is based on consideration of expected movement and survey ;
accuracy coupled with an acceptable strain level for the radial reinforcement. For example,,a change in elevation for the dome apex of 0.03 Ccet has been established as an acceptance limit.
- Changes of a greater magnitude may be indicative of delamination and would necessitate evaluation and resolution.
Page 2 Dato: 4-26-77 Rev. 1
2.1.2.2 Firs't Periodic Containment Integrated Leak Rate Test (ILRT)
This inspection will verify that the structure continues to perform as predicte'd under an internal pressure load. Acceptance criteria will be sinilar to that foe the Structural Integrity Test (SIT, Reference 2) applied to the change in dome elevations during the ILRT.
2.2 CRACK INSPECTION Crack inspection will be made at the surveillance intervals specified in Section 3.0.
In a designated area of the dome, (see Figure 2) crack widths will be measured and crack patterns plotted. The designated .
area shown is the identical portion of the dome inspected during the SIT (Reference 2). This area includes the circumferential -
joint between the new cap and the original structure.
Cracks wider than 0.010 inches will be measured and recorded.
Cracks greater enan 0.040 inches will require evaluation and resolution. ,
In addition, a general visual inspection of the entire dome surface area will be made.
3.0 SURVEILLMICE INTERVALS Dome surveillance subsequent to the SIT will be. performed at the following intervals:
(1) One (1) year after the SIT.
l Page 3 Date: 4-26-77
! Rev. 1 i
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- 6-(2) Eighteen (18) months after the SIT.
(3) Two (2) years after the SIT.
(4) Three (3) years after the SIT.
(5) Forty (40) months I ten (10) months after the SIT coincident ,
with the first periodic Integrated Containment Leak Rate Test.
(6) Five (5) years af ter the SIT.
The need for continuing the enhanced surveillance program beyond the five (5) years will be evaluated af ter the five (5) year .
inspection. , , , ,
4.0 REFERENCES
- 1. " Reactor Building Dome Delamination", Crystal River Unit 3 Nuclear Generating Plant, Final Report, December 10, 1976, Florida Power Corporation.
- 2. " Reactor Con;ainment Building Structural Integrity Test",
Crystal River Unit 3 Nuclear Generating Plant, Gilbert Associates, Inc. Report No. 1930, December 7, 1976, Florida Power Corporation.
I Page 4 Date: 4-26-77 Rev. 1
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Page 6 Date: 4-26-77 l Rev. 1