|
---|
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 REPORT
MONTHYEARML20212C1121999-09-16016 September 1999 Criticality Safety Analysis of W Spent Fuel Storage Racks in Pool B of Crystal River Unit 3 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 ML20206S7561999-02-28028 February 1999 Rev 2 to Pressure/Temp Limits Rept, Dtd Feb 1999 ML20155F9771998-10-20020 October 1998 Rev 1 to Holtec Rept HI-982056, Reanalysis of Crystal River Pool B Spent Fuel Storage Racks with Boraflex Degradation ML20141F6821997-04-0808 April 1997 Hydraulic Evaluation by Ingersoll-Dresser Pump Co for Fl Power Corp Crystal River 3 Plant ML20135A8001996-08-19019 August 1996 Rept on Raceway Fire Barriers for Aluminum Cable Tray & Aluminum Wireway Sys 3F0796-25, Thermal-Lag & Mecatiss Ampacity Test Investigation of Raceway Fire Barriers for Conduit & Cable Tray Sys1996-05-0707 May 1996 Thermal-Lag & Mecatiss Ampacity Test Investigation of Raceway Fire Barriers for Conduit & Cable Tray Sys ML20117M9181996-02-28028 February 1996 Books 1-6 of Underwriters Labs Test Repts for FPC for Feb 1996 ML20211D1611994-09-13013 September 1994 Results of 2000 Hour Test at 385 Bhp/Cyl on 38TD8-1/8 OP Engine,Rept R-5.08-0236 ML20211D1521994-01-25025 January 1994 200 Hour Rating Qualification Test Rept ML20092C1771991-11-0707 November 1991 Reactor Containment Bldg Integrated Leakage Rate Test Rept 3F0990-07, Cycle 8 Startup Rept1990-09-30030 September 1990 Cycle 8 Startup Rept 3F0588-02, Cycle 7 Startup Rept1988-04-30030 April 1988 Cycle 7 Startup Rept ML20150E0701987-11-30030 November 1987 Reactor Containment Bldg Integrated Leak Rate Test ML20093N1611984-07-31031 July 1984 Once-Through Integral Sys Hot Leg High Point Vent Test 240100 ML20093N1681984-07-31031 July 1984 Once-Through Integral Sys Hot Leg High Point Vent Test 240200 ML20078H2301983-07-31031 July 1983 Reactor Containment Bldg Integrated Leak Rate Test, Jul 1983 ML20050K5431982-04-0808 April 1982 Local Leak Rate Test Rept, Pages 6,9 & 10 ML20041F5401982-03-31031 March 1982 Cycle 4 Startup Rept,Mar 1982 ML20049H7971982-02-19019 February 1982 Local Leak Rate Test Rept ML17268A1041981-05-31031 May 1981 B&W Post-Test Evaluation of Loft Test L3-1. ML20010A3351980-12-31031 December 1980 Exam & Test of Crystal River 3 Power-Operated Relief & Safety Valves ML19340B5291980-10-31031 October 1980 Cycle 3 Startup Rept ML19339B1311980-09-26026 September 1980 Local Leak Rate Test Rept. ML19339B1281980-09-0303 September 1980 Reactor Containment Bldg Integrated Leak Rate Test. ML19250B5921979-10-18018 October 1979 Cycle 2 Startup Rept. ML19253B3901979-09-20020 September 1979 Local Leak Rate Test Rept ML19317H0311979-05-10010 May 1979 Test Rept for Seismic Qualification Testing of Potential Transformer Model JVM4 & Current Transformer Model JCM4. ML19261B3591979-01-30030 January 1979 Cycle 1:Mid-Cycle Startup Rept. ML19308D6931977-07-27027 July 1977 Startup Rept ML19263C0731977-06-0909 June 1977 Fire Retardant Cable Test,June-Sept 1977,R&D Project. ML19308D7011976-12-0909 December 1976 Reactor Containment Bldg Preoperational Integrated Leak Rate Test. ML19308D6861976-12-0707 December 1976 Reactor Containment Bldg Structural Integrity Test. ML19326B2451976-11-0404 November 1976 Structural Integrity Test Preliminary Rept 1999-09-16
[Table view] |
Text
.___._...
F-28 Ou17, g,y, g R EA N A _YS S 0 7
- E C RYS A R V E R 300_ 3 S 3 Es" TU E _ S"0 RAG E RAC 5m "
0.9079 0.9055 0.9120 0.9082
"0 " oS5 0.9095 0.9071 0.9136 0.9098 w/is m os5 0.9115 0.9091 0.9156 0.9118
"'2 0* o "
0.9138 0.9114 0.9179 0.9141 KENO-CASMO correction includes temperature correction to 4'C, the KENO bias, and the reactivity facts for checkerboarding with 5% fuel.
Conservative values for fresh fuel used.
Holtec Report HI-982056 -
9 e
F-284017. Rev. O Table 6.4 REACTIYlTY SU3131ARY REGION 2 (Fully Loaded)
Enrichment 1.63 2.04 2.31 3.20 4.07 5.20 Temp-4*C 4C 4C 4*C 4*C 4*C sumup.
0 8
15 25 35 45 MWDA.gu Reference k.inf 0.9128 0.9114 0.8861 0.8977 0.8976 0.9095 KENO / CASMO 0.0049 0.0049 0.0049 0.0049 0.0049 0.0049 Corr.
y,n",";
0.0013 0.0013
- 0.0083 Tolerances Enrichment 0.0095 0.0074
& Dens Tol De I j a 0
0.0039 0.0069 0.0106 0.0135 0.0153 n
Totai uncert 0.0154 0.0141 0.0141
- 0.0165 0.0177 Reactivity 0.9177 0.9163 0.8910 0.9026 0.9025 0.9144
- 0.0154 0.0141 0.0141 0.0149
- 0.0165 0.0177 Muimum 0.9331 0.9304 0.9051 0.9175 0.9190 0.9321 Reactivity w/5% ion 0,9354 0.9327 0.9074 0.9198 0.9213 0.9344
"'IO% 3o5$
0.9367 0.9340 0.9087 0.9211 0.9226 0.9357 wrisn ioss o,9395 0.9278 0.9115 0.9239 0.9254 0.9385 w/20% io" 0.9410 0.9383 0.9130 0.9254 0.9269 0.9400 Holtec Report Hl 982056..
l l
l
\\
F ".84017. Rev. C
\\
Table 6.5 REACTIVITY
SUMMARY
REGION 2 (3 of 4 Loading) l
((i[*f,"t 1.63 2.04 2.31 3.20 4.07 5.20 y
T'mp-4*C 4'C 4C 4C 4"C 4*C B3,""g 0
8 15 25 35 45 C^suo4 cas' F2 ENR F2-B204 F2-B231 F2-B320 F2-B407 F2-B520 In'["ek-0.9128 0.9114 0.8861 0.8977 0.8976 0.9095
[Q0lg c,,,.
-0.0994
-0.0994
-0.0994
-0.0994
-0.0994
-0.0994
{"['";
i 0.0013 0.0013 i 0.0013 0.0013 0.0013
- 0.0007 0.0007 0.0007 0.0007
- 0.0007 Statistics Mechanical 0.0120 0.0113
- 0.0091 0.0083 Tolerances EQ;,"
i 0.0095 0.0074 0.0062 0.0036
- 0.0026 0.0029 De letion 0
0.0039 0.0069
- 0.0106 0.0135 0.0153 Total uncen 0.0154 0.0141 0.0141
- 0.0177 Reactivity 0.8134 0.8120 0.7867 0.7983 0.7982 0.8101 0.0154
- 0.0177 M*=m 0.8288 0.8261 0.8008 0.8132 0.8147 0.8278 Reactivity w/5% io" 0.8306 0.8279 0.8026 0.8150 0.8165 0.8296
- /10% 'o" 0.8327 0.8300 0.8047 0.8171 0.8186 0.8317
- 'l 5% 'on 0.8347 0.8320 0.8067 0.8191 0.8206 0.8337
"'E I"$
0.8367 0.8340 0.8087 0.S211 0.8226 0.8357 l
l Holtec Report HI-982056 -
O
F-9&4017, Rey, g.
Table 6.6 REACTIVITY EFFECTS OF ABNORMAI, AND ACCIDENT CONDITIONS Acciden:/ Abnormal Conditions Reactivity Effect Tempeiature increase Negative Void (Boiling)
Negative
~ Assembly dropped on top of rack Negligible Seismic movement Negligible Misplacement of a fuel assembly Worst Case Requires minimum 350 ppm soluble boron l
l i
Holtec Repon HI-982056 r e
p
--.m.-
r
F-08 OO17, Rey, c Table 6.7 EFFECT OF TEMPERATURE AND VOID ON CALCULATED REACTIVITY OF STORAGE RACK Case Incremental Reactivity Change, ak Region 1*
Region 2 4*C (39'F)
Reference 20*C (68'F)~ -
0.0011/-0.0014
-0.0011 40*C ( 104*F)
-0.0035/-0.0042
-0.0041 80*C ( 176*F) 0.0103/-0.0120
-0.0086 l
120*C (248'F)
-0.0192/-0.0226
-0.0151 120'C + 10% void 0.0442/-0.0504
-0.0342 Region 1 uses fuel of 5% enrichment burned to 30 MWD /KgU in a checkerboard arrangement with unburned fuel of 5% enrichment. The two values in this column are the temperature effects at 30 MWD /KgU and for unburned fuel, both of which show a negative coeffient of reactivity.
i Holtec Report HI 982056 21 -
et O
e
-me r--r a -.,
w s
yi--
r-5-
y-mer
--ww-re w -
F-98-0017. Rev. O
._..}._.-._______
7.50 i 0.063" BORAFLEX i
I IN 0.120" GAP i
i i
2 j
0.085 0.007" THK.0269 0.0039 gmB-10/cm I
t p - m - - - mmy
! 000000000000000l I
l O00000000000000 l
i l O00009000000000 l
i ona l
l 000000000009000i l
l O00000000000000 i
i i
! O00000000000000 1
l
! O00000000000000 i
- 000000090000000 l
l i
! O00000000000000 1
! 000000000000000 i
WATER GAP
! 000000000000000 l
'l
! 000000000000000 i
l O00000000000000 i
i
! =OOOC
?OOOO=!
i e.00010.088 80x i.0.
l l OOObuvvvvv00000 l.
l
h*******
N 0.060" SS 80X 10.600 0.088" g-.-.-
l
.VOT TO SC.41.E I
Fig. 4.1 REGION 1 FUEL STORAGE CELL
+
- P i
Appendix A to Chapter 5 of the Holtec Report, HI-98056
" Benchmark Calculations" Provided to FPC as PROPRIETARY.
Therefore not included; will be provided or can be viewed on-site upon request.