ML20095F969
| ML20095F969 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 04/30/1992 |
| From: | ABB IMPELL CORP. (FORMERLY IMPELL CORP.) |
| To: | |
| Shared Package | |
| ML20095F968 | List: |
| References | |
| NUDOCS 9204280350 | |
| Download: ML20095F969 (9) | |
Text
{{#Wiki_filter:.... q PIPE RUPTURE ANALYSIS CRITERIA. OUTSIDE THE CEACTOR BUILDING CRYSTAL RIVER UNIT-3 Prepared for: Florida Power Corporation ..-3201 Thirty-Fourth St. South P. 0. Box 14042 St. Petersburg, FL.33733 J Prepared by: ImpelliCorporation 333'Research Court Technology Park / Atlanta Norcross, GA 30092 -Job Number: 0920-125 Impell Report: '03-0920-1186 Revision 2 i April 1992 - .9204280350 920421 .PDR ADOCK.-05000302 'P: PDR 'wwevr* u
REPORT APPROVAL COVER SHEET FLORIDA POWER CORPORATION C1 JEST: CR-3 HELB Outside Containment PROJECT: 0920-125 JOB NUMBER (F): REPORT TTTLE: Pine Ruoture Analysis criteria Outside thn unactnr Building - Crystal River, Unit 3 REPORT NLMBER: 03-0920-1186 REVISION RECORD RIV. PREPARID VERDTED REVIEWED APPROVED DATE O DW Peltola Jeffry R Dargis Amar Saini KN Kassam March 27, 1989 1 MA Likly DW Peltola Amar Saini KN Kassam December 7, 1989 'hD 9, hg f N Ap 1, 2
RfJISIONSTAlp.S 11GE.NO BE PAGE NO. E PAGE N0 RE1,, 4 i 2 16 1 32 0 il 2 17 0 33 0 l t iii 1 18 0 34 0 1 0 19 0 35 0 2 1 20 1 36 0 3 1 20A 2 37 0 4 0 21 1 38 0 5 0 21A 39 0 1 2? 1 40 0 v 7 0 23 0 41 0 8 0 24 0 42 0 9 1 25 1 43 1 10 0 26 0 44 1 11 0 27 1 45 1 12 0 28 0 46 0 13 1 29 0 47 1 14 0 30 0 47A 1 15 0 31 0 48 1 i l-Report Number: 03-0920-1186 Revision 2 l
1 i APPENDIX A Af_t PAGES REMAIN AT REVISION LEVEL 0 APPENDIX B PAGE NO. E PAGE NO, E PAGE NO, REL. B-1 0 B-3 2 B-5 0 B-2 0 B-4 0 B-6 0 b2ELUQLLC ffAILNO. E PAGE NO, E PAGE NO, E C-1 0 C-9 1 C-17 1 C-2 1 C-10 1 C-18 1 C-3 1 C-11 1 C-19 1 C-4 2 C-12 1 C-20 1 C-5 2 C-13 2 C-21 1 0-6 1 C-14 1 C-7 1 C-15 1 C-8 1 C-16 1 APPENDIX 0 ALL PAGES REHAIN AT REVISION LEVEL 0 l APPENDIX E l ALL PAGES REMAIN AT REVISION LEVEL 0 APPENDIX f PAGE NO, FJ.L. _PfA.GLi(Q.,. E PAGE NO. EfL F-1 1 F-2 1 F-3 1 ii Report N9mber: 03-0920-1186 Revision 2
4 combination is equivalent in the later ASME Codes to developing faulted loadings and comparing them to upset allowables, e very conservative approach. The stresses from each loading component identified above were calculated separately, and the stress results absolutely sumed. Due to the absolute suming process used, this is equivalent to absolutely suming the moment components, deteinining the resultant bending moment, and applying the component dependent SIF to produce the required local stress value used to determine pipe stress acceptability. This process meets the requirements of Reference 12. The break stress development for this Criteria included only the OBE seismic stresses (not tht: SSE stresses), and the resultant stresses were compared to the Giambusse break stress thresh:1d values. Cracks were assumed at one-half the break stress threshold. A review of the SIF values used at CR-3 was performed per Refer-ence 11 G and the results show justifiable and 6ppropriate individual Sif values were used for components, based on the piping code methods at the time of CR-3 piping design. Breaks, in accordance with Section 4.1.6, shall be postulated to accur at the following locations of B31.1 (N2 and N3) piping. All piping outside containment is analyzed t" and rupture locations Break locations for postulated on the recuirements of this section. the systems evaluatec to this criteria are identified in Appendix C, 1he terninal ends of the run. The section properties of the a) terminal end components will be considered to assure that the teminal end break is selected at the loct. tion having the highest potential for failure. b) At intermediate locations selected by either one of the following methods: 1) At each intermediate weld location of potentini high stress or fatigue; or Report Number: 03-0920-1186 Revision 2 Page 20A of 48
Table B-1 CR-3 Hiah Enerav Lines Outside Lontainment* (for Protection per the intent of the SRPs) Normal Operatina Line Nom. Pipe Press System flow Qescription Sire fin.) Temp (oF) (PSIG) Diaoram No. Remarks 1 Main Steam:
- a. Steam 24 590 925 D-302-011 Generator SH 1/4 (R/B in-terface) thru MS1V's to T/B Wall
- b. Thru MSV-55 6
590 925 D-302-011 Actual TE Break -56 to EFP SH 1/4; at 3" End of Turbine D-302-051 6 x 3 Reducer Inlet isol. SH 1/1 vivs ASV-5, -23, ASV-204 (ASV-5 bypass)
- c. to MSDT-1, 1 1/2 590 925 D-302-011 also Chem.
SH 1/4 D-302-114 Cleaning Lines
- d. to Atmos.
6 590 925 D-302-011 Relief SH 1/4 Valves
- e. to MS 6
590 925 D-302-011 SH 1/4 Safety Valves
- f. RB Pen.No 3
535 925 D-302-011 Operating temp. 427 & 428 to SH 2/4 and pressure from B&W reducing tee document 1.0. on blowdown 51 1153540-L'1, line HELB Analysis t'or OTSG Blowdown Piping
- g. Reducing tee 4
535 925 D-302-011 Same as 1-f. on blowdown SH 2/4 line to Turbine Bldg. Wall Includes " nuclear island" only (i.e.; intermediate, auxiliary, fuel handling, control, and diesel generator buildings). Excludes Reactor & Turbine Buildings. Report Nueher: 03-0920-1186 Revision 2 Page B-3
Table C-2 Crack Summary lyits Calculation Node Numbers FW CR-25 110, 620, 65, 615 CR-23 569 MS CR-3 72, 81, 90, 62, 92 CR-4 53, 54, 63, 72, 73, 82 CR-5 103, 112, 121, 122, 131, CR-6 88, 97, 106, 107, 116 MS(OTSG) CR-187 599, 601-602, 634-636 639 641, 660, 5, 24, 25, 611 I CC* 0920-125-C004A 10, 15.-148, 152, 155, 160 0920-125-C0048 10, 15, 148, 152, 155, 160 MSDT** 0920-125-C007 20, 25, 32, 48, 52, 58, 62 AS CR-4A 100, 103 Ref. 11.0 and G Ref. 11.0 and G t Report Number: 03-0920-1186 Revision 2 Page C-4
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