RBG-47876, Response to License Amendment Request (LAR) for Review and Approval of Relocation of the Reactor Core Isolation Cooling (RCIC) Injection Point NRC Request for Additional Information (RAI)
| ML18172A142 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 06/21/2018 |
| From: | Maguire W Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RBG-47876 | |
| Download: ML18172A142 (136) | |
Text
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1,'1 ;)" 1/11 11/1 William F. Maguire d VII;' I', '.'1ld"111
'1:1 B'lld I.ltl.l RBG-47876 June 21, 2018 Attn : Document Control Desk U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852-2738
SUBJECT:
Response to License Amendment Request (LAR) for Review and Approval Of Relocation Of The Reactor Core Isolation Cooling (RCIC) Injection Point NRC Request for Additional Information (RAI) River Bend Station , Unit 1 Docket No. 50-458 License No. NPF-47 RBF1-18-0136 References : 1) Entergy Letter: License Amendment Request (LAR) (RBG-47823 dated January 29, 2018) (ADAMS Accession No. ML18029A187)
- 2) NRC email: River Bend Station, Unit 1, Request for Additional Information dated May 24,2018 (ADAMS Accession No. ML18149A288)
Dear Sir or Madam :
In Reference 1, Entergy Operations, Inc (Entergy) submitted a request for the review and approval of relocation of the Reactor Core Isolation Cooling (RCIC) Injection Point from the Reactor Vessel Head Spray Nozzle to the 'A' Feedwater Line via the 'A' Residual Heat Removal (RHR) Shutdown Cooling Return Line . In an email dated May 24, 2018, (Reference 2) the NRC staff made a request for additional information (RAI). needed to complete the license amendment request. Enclosure 1 provides the responses to the RAls. Enclosure 2 contains the pipe stress calculation updates AX-002H, AX-071AG, AX-076A , and AX-076B. This letter does not contain any new commitments . If you require additional information , please contact Mr. Tim Schenk at (225)-381-4177 or tschenk @entergy.com . In accordance with 10 CFR 50 .91(b)(1) , Entergy is notifying the State of Louisiana and the State of Texas by transmitting a copy of this letter to the deSignated State Official.
RBG-47876 Page 2 of 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on June 21,2018. Sincerely, -- l WFM/BAJ : Responses to Request for Additional Information : Pipe stress calculation updates AX-002H, AX -071 AG, AX-076A, and AX-076B cc: U.S. Nuclear Regulatory Commission Region IV 1600 E. Lamar Blvd. Arlington , TX 76011-4511 U.S. Nuclear Regulatory Commission Attn : Ms. Lisa M. Regner, Project Manager 09-0-14 One White Flint North 11555 Rockville Pike Rockville, MO 20852 NRC Senior Resident Inspector Attn : Mr. Jeff Sowa 5485 U.S . Highway 61, Ste . NRC St. Francisville , LA 70775 Department of Environmental Quality Office of Environmental Compliance Radiological Emergency Planning and Response Section Ji Young Wil ey P.O. Box 4312 Baton Rouge, LA 70821-4312 Public Utility Commission of Texas Attn : PUC Filing Clerk 1701 N. Congress Avenue P. O. Box 13326 Austin, TX 78711 -3326
RBG-47876 Page 1 of 3 RBG-47876 Enclosure 1 Responses to Request for Additional Information
RBG-47876 Page 2 of 3 REQUEST FOR ADDITIONAL INFORMATION RELOCATION OF THE REACTOR CORE ISOLATION COOLING (RCIC) INJECTION POINT RIVER BEND STATION, UNIT 1 DOCKET NO.: 50-458
Background
By letter dated January 29, 2018, Entergy submitted a license amendment application . The licensee stated that the 6-inch Reactor Core Isolation Cooling (RCIC) system injection line is routed to the 20-inch Feedwater A Loop by tapping into the 10-inch Reactor Heat Removal system shutdown cooling mode return line to feedwater inside the main steam tunnel just south of the jet impingement wall. The staff noted that the piping system has to be qualified in accordance with ASME Code Section III requirements and meet 10 CFR 50.55(a) and relevant GOCs. The staff requests the licensee to address the following items related to the piping analysis: Question a Piping analysis model: The staff noted that this change affects 3 different systems. Figure 3A.24-1 of USAR provides RCIC piping system used in analysis of water hammer loads. The staff noted that the piping model does not appear to address the RHR piping . Please explain . Also, describe the piping model used for other load cases. Response to Question a PX-1037 was updated with the modification and contains the water hammer analysis of the RCIC Piping ; PX-1 000 was updated and contains the water hammer analysis for the feedwater piping. Both analyses were updated to show injection into Residual Heat Removal (RHR) piping RHS-010-065 that connects to the Feedwater Mixing Tee and Feedwater Line FWS-020-047. Line RHS-01 0-065 is the only portion of the RHR system piping that is impacted by the RCIC reroute modification as it is protected from backflow by check valve E12-VF050A and the normally closed isolation valve E12-MOVF053A (ref. PIO-27-07A). . Standard Load Cases for the requested RCIC and RHR system piping are provided in the response to Question b below. Additional analyses performed as a result of MR96-0069 can be provided on request. Question b Please provide the piping stress summary for RCIC and RHR systems. Response to Question b Pipe stress calculation updates to the affected RCIC and RHR piping as a result of MR96-0069 are provided in Enclosure 2: AX-002H , AX-071 AG , AX-076A, and AX-076B.
RSG-47876 Page 3 of 3 Question c Please discuss any thermal mode or transient changes and loading condition changes since the Cumulative Usage Factors (CUFs) and stresses are shown to lessen from previous values as specified below:
- 1. Table 3.6A-9a of the USAR lists the CUFs and the stresses for the feedwater system inside containment. The NRC staff noted that there is no routing change inside containment. Please explain what causes the reduction in stresses and CUFs.
- 2. Table 3.6A-10a of the USAR lists the stresses for the feedwater system outside of containment. The NRC staff noted that there is no routing change for the feedwater system outside of the containment. Please explain what causes the reduction in stresses.
Response to Question c Part 1 Stress and CUF were calculated in AX-017D revision 3K as part of the RCIC Reroute modification MR96-0069 . The fluid transient load case used in this calculation update is based on RSS calculation PX-1000 Rev. 2 (also revised with MR96-0069) curves which are smaller than the design loads of PX-1000 Rev. 1 used in the previous analysis. The transient loads have reduced as a result of installing a nozzle check valve FWS-V3052 into the Feedwater system with MR96-0069. This nozzle check valve has a faster closing time compared to the previously modeled swing check valves. The reverse flow when the nozzle check valve closes would be lower producing smaller fluid transient loads. Smaller transient loads result in lower stress and fatigue values. This revision also incorporated and superseded 6 additional addenda and markups of calculation AX-017D that were unrelated to the RCIC Reroute modification. The changes included a temperature change , piping schedule changes, a change in valve weight, and a change in damping curves that are unrelated to the changes made by modification MR96-0069; these incorporated changes may also have impacted the stress and CUF results. Response to Question c Part 2 See the response to Part 1 above. Note: The break points shown in current USAR Table 3.6A-1Oa have since been updated and no longer reflect the values changed by the subject RCIC modification MR96-0069 .
RBG-47876 Page 1 of 131 RBG-47876 Enclosure 2 Pipe stress calculation updates AX-002H , AX-071 AG , AX-076A, and AX-076B
CALCULATION COVER PAGE
----- ENGINEERING DEPARTMENT ENTERGY. RIVER BEND STATION TITLE: SUPERSEDES: N/A Stress Analysis for Main Steam Vent Line per MR 96-0069. . .......... . ...... .... ............................ ~~ . . .'..... .......... . . . . ................... ".... .
SUPPLEMENTS: AX-2H Rev. 3 CALCULATION STATUS: o APPROVED
- PENDING o CANCELED SYSTEM NO.: 209 MARK NO.:
CLASSIFICATION:
- SAFETY RELATED NON-SAFETY RELATED: 0 QAPA o NON-QAPA U.n.Jc'U'",,! SCOPE I OBJECTIVE:
To document the cbanges implemented by MR 96-0069. This MR re-routes tbe RCIC injection from the reactor vessel bead to the feedwater nozzle. As a result of this change~ line ICS-006-6-1 (previously qualified in AX-76A) is removed from the vent and spray assembly. CONCLUSION: The changes implemented by MR 96-0069 do not affect the piping qualified in AX-2H. The vent and spray assembly is now solely qualified by AX-2H. RPV nozzle numbe~7 and the vent and spray assembly remain qualified since the removal of line ICS-006* 6-1 reduces the loads acting on the vent and spray assembly. RECEIVED JUN 0 9 1998 ARE USED FOR ONO SDDF#: N/A Manufacturer: Name
- YersionlRelease No.
CONFIRMATIONS REQUIRED: 0 YES
- NO CONFIRMATION COMPLETE: 0 YES 0 NO 0 N/A KEYWORDS:
RPV Vent Line, MR 96-0069, RCIC, RPV nozzle REVIEW & APPROVAL 0~ ~< b-21-91 t~dWL 6-)3-97 (SignaturelDate) (SignaturelDate) Preparer o Reviewer (Non-Safety) Supervisor Camilo Cuadra, KCN 0969 . GrDesign Verification Reviewer (Printed Name, KCN, or SSN) WtSk G'vfTA
- 1051 Lothar Kuhn, KCN 1105 J
RBG-47876 Page 3 of 131 CALC. NO. - REV. ADDENDIJM CALCULATION AX-2H Rev. 3C
=-----
==~ ENGINEERING DEPARTMENT ATTACHMENT NO.:
ENTERGY RIVER BEND STATION JBINO.* PAGE 2 OF Stress Analysis fOT Main Steam Vent Line per MR 96-0069 TABLE OF CONTENTS SECTION DESCRIPTION PAGE NO. N/A REVISION mSTORY 3 N/A APPLICABLE DOCUMENTS 4 1.0 ISOME1RICS 5 3.0 CALCULATION CHECKLIST 6 N/A DESIGN VERlFICA TION CHECKLIST 7 Total Pages: 7
RBG-47876 Page4-r~==~ ____' -__________________________________' -______________________-T CALCULATION ENGINEERING DEPARTMENT ENTERGY
- RIVER BEND STATION Stress Analysis for Main Steam Vent Line per MR 96-0069 REVISION mSTORY Description of Change 3C All To document the changes implemented by rvlR 96-0069. This MR re-routes the RCIC injection from the reactor vessel head to the feedwater nozzle. As a result of this change, line ICS-006 I (previously qualified in AX-76A) is removed from the vent and spray assembly.
RBG-47876 Page 5 of 131 CALCULATION CALC. NO. - REV. ADDENDUM . AX-2H Rev.3C
=~ ENGINEERING DEPARTMENT ATTACHMENT NO.:
-ENTERGY
-~---
RIVER BEND STATION JBINO.: PAGE 4 OF Stress Analysi.s for Main Steam Vent Line per MR 96-0069 APPLICABLE DOCUMENTS L APPLICABLE CODES, STANDARDS, & REFERENCES (NON-RBS):
- 1. ASME Boiler ~ Pressure Vessel Code, Section m, Division 1, 1974 Edition IL RBS
REFERENCES:
- 1. MR 96-0069
- 2. AX-76A Rev. 3E llL AFFECTED DOCUMENTS:
DOC. NO. REV. DOCUMENT TITLE AFFECT CHANGE NO. (Superseded, Revised, Initiated, etc.) DOC.
RBG-47876 Page 6 ~.~--:;::C-:-:A-;-L-::C;;:UL;;-:A-::::T:::IO::::::N:;::W;:-:O;:::RK::::-::S:::HE;:::::E=
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ENGINEERING DEPARTMENT ENTERGY RIVER BEND STATION V'\
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RBG-47876 e Page 7 of 131 CALCULATION CALC. NO. - REV. ADDENDUM AX-2H Rev.3C
--_...... ENGINEERING DEPARTMENT ATIACHMENT NO.:
--- ENTERGY RIVER BEND STATION JBINO.:
PAGE 6 OF CALCULATION.CHECKLIST .. EDP-AA-20 YES NO N/A FORMAT SECI10N
)( Cover Page completed. 6.4.1 X Table of Contents completed (as required). 6.4.2 X Revision History Sheet completed (as required). 6.4.3 X Revisions are identified with revision lines in right margin. 6.4.3 X Applicable Documents Page completed. 6.4.4 X Definitions established (as required). 6.4.5 X Calculation/revision/addendwnlpage numbers are identified correctly. 6.4.10 CONTENTS X" Previous calculation for the required analysis exists. 6.3
'" )(' Calculation is appropriately titled for the intended scope. 6.4.1-2
- x Purpose and scope are clearly and adequately established. 6.4.1-7,7.1
)( Safety classification is correct for the identified scope. 6.4.1-6
>c Topics/documents/equipment for cross-reference/retrieval are identified. 6.4.1-11 X Calculation is clear and comprehensible. 6.1 X Applicable codes, standards, etc. are identified. 6.4.4-1 X RBS references are identified. 6.4.4-2 X Affected documents are identified 6.4.4-3 X Inputs and sources are identified, appropriate, and correct. 7.2.2-1 X Assumptions are identified and appropriate. 7.2.2-2 X Inputs derived from field walkdown have been witnessed/verified 7.22-5 X Engineeringjudgments are identified and appropriate. 7.2.2-6 X Calculation methodology is identified and supported by technical bases. 7.2.3 X Conclusion is appropriate and is justified by calculation. 7.3 X Confirmations are identified and indicated as required on Cover Page. 7.5.7 X Directions for Confirmations are included. 7.5.7-3 X Calculation data is appropriately included, attached, or referenced. 7.4
)( Programs and software are identified and have been verified and validated. 8.0 X Methods/calculations use to check results are identified and included.
_'X Results are accurate and in accordance with the established methodology. X* Certification by Professional Engineer is required. 11.7 VENDOR CALCULATIONS Calculation is performed in accordance with EDP-AA-25. 102 Calculation content and format are acceptable. 10.2 Vendor, preparer, reviewer, and approver are clearly identified. 10.3 X Design verification review has been completed (as applicable).
- ~arer (SignaturelKCN or SSNlDate):
, .r. J. 1';.~d. oL..... (0 qb q ) ~-2J~9'1
'Reviewer (SignaturelKCN or SSNlDate):
RBG-47876 CI-ItST) Page 1:~t111 ATTACHMENT I ES-P-002-00 -
~ENTERGY Page 1 of 2 Typical Design Verification Record Page '7 of 7 Document Number AX-2f-1 Revision 3C METHOD Verification methods to be used:
- X ,' Design Review Qualification .Testing Alternate Calculations DOCUMENT(S) REVIEWED: (Attach Additional Sheet(s), ifneeded)
Document Title e* fa::MSh-es ~ Co..l.c..u'Ye,."f-Document Number Revision A"X-2H .. 3 {o..{*o n
~v--- (,.i. !l S~M L."~~
SUMMARY
OF REVIEW: (Attach Additional S~eet(s), if needed) Design Verification Completed By , ~~ pa~e: (;-23-97 Comment Resolutions ACce~, Date: Engineering Supervisor . ( >h CupQ Date: /J-{~-17 ES-P-002, Form No.1, Rev. 6
RBG-478~ Enclosur~ E~TERGY Page 9 of 1~"'- ( Record Revision Notice ENGMSYS AY..- OOc2H _ ADDL Department Document No. Page 1 of ~ JBIX No. RevisionlDate FileNet Location Revision Description Change calculation / addendum status from pending to approved. Reason For Revision MR 96-0069 has been installed. RECE!VED
.JUN 2 5 i999 SA TIC Approvals:
Originator Date Section Supervisor
. I
RBG-47876 ~ALCULATION COVER PAGE Page 10 of I---::-:;:iiiil: ENGINEERING: D~PARTl\1ENT
---ENTERGY. RIVER BEND STATION TITLE:
SUPERSEDES: NlA Stress Analysis for Main Steam Vent Line per MR 96-0069. SUPPLEMENTS: AX-2H Rev. 3 CALCULATION STATUS: )(.APPROVED o CANCELED SYSTEM NO.: 209 CLASSlFICATION:
- SAFETY RELATED NON-SAFETY RELATED: 0 QAPA PURPOSE / SCOPE I OBJECI'IVE:
To doeoment the changes implemented by MR 96-0069. This MR re-rootes the RCIC injection from the reactor vessel bead to tbe feedwater nozzle. As a result oHbis change, line ICS"(}06-6-1 (previously qualified in AX-76A) is removed from the vent and spray assembly. REC EIVED
,JUN 2 5 i999 CONCLUSION: SA. T1 The changes implemented by MR 96-tJ069 do not affect the piping qualified in AX-2H. The vent and spray assembly is now solely qualified by AX-2H. RPV nozzle numbe~7 and tbe vent and spray ~ssembJy remain qualified since the removal of line ICS-006--6-1 reduces the loads acting on the vent and spray assembly.
RECE~VEO jUN 091998 Manufacturer: Name ' VersionlRelease No. CON:FIRMATIONSREQumED: DYES .NO CONFIRMATION COMPLETE: D YES DNO O N/A KEYWORDS: . RPV Vent Line, MR 96-0069, RClC, RPV nozzle
& APPROVAL
~ ~< {'-Z1-91 iczth9t,y ~ 6-21>--97 (SlgnaturelDate) (Signature/Date)
Preparer , 0 Reviewer (Non-Safety) Supervisor camilo Cuadra, KCN 0969 ~ign VerificatiOD Reviewer (Printed Name. KCN. or SSN)
/UuSk G;vprA'J 1051 Lothar Kuhn, KCN 1 IOS
~~;~:~~_ F.NT~~GY Page 11 of131 Record Revision Notice ENGMSYS AX- o1/Ab, Department Document No. Page lof ;z. JBIX No. 4-Revision/Date F1t50l/t) FileNet Location
+
Revision Description Change calculation / addendum status from pending to approved. Reason For Revision MR 96-0069 has been installed. RECEIVED
.J UN 2 5 1999 SA TIC Approvals:
Originator Date Section Supervisor Date Page 12 of 131
==:::8
- ENTERGY CALCULATION COVER PAGE ENGINEERING DEPARTMENT RIVER BEND STATION CALC. NO. - REV. ADDENDUM AX-71AG, Rev. 4-ATTACHMENT NO.:
/ ~/ao7
_ . .'\,. .m
. . . .- . . . . & ... ~ 'b~
TITLE: Pipe stress Analysis for ICS function added through FWS system per SUPERSEDES: AX*71AG Rev. 3
.- - . . ., ......... ...... --I'."..,. . ---- .. ..... ...
MR 96-0069 ., . . . " . . . .
\ -~ . ." ,. ' - ., . ~
., . ~ --~ ~
SUPPLEMENTS: CALCULATION STATUS: ;vu.PROVED Y1ffj';~l~~qq o CANCELED SYSTEM NO.: 204, 209 I MARK NO.: CLASsmCA nON: t&.sAFETY RELATED i NON-SAF.ETY RELATED: DQAPA IRI NON-QAPA I PURPOSE / SCOPE / OBJECfIVE: . -.... . ~. ,', .. ' .. .. .,
- T"'" ...* ft ....
See page 17 IU' 11-;2."7 RECEIVED
.JUN 2 5 1999 t
SATle RECEIVED JUN 0 9 1998 SOC ' CONCLUSION: .. .. . . .. This piping analysis demonstrates the acceptability of the piping system within acceptable design limits of ASME Section III Code for MR 96-0069* . .- . --.. ..... ... .. .. . ~ .,. - . ._- SOFI'WARE USED FOR CALCULATION: IXI YES DNO SDDF#: 6%%9.400-100-o01A Manufacturer: Bechtd . _.. ~lJ!le MEIGl '"':"C'- Venioll!Release No. ,N4 CONFIRMATIONSREQ~1): OY.ES.... .ml.NQ.1CONFIRMATION COMPLETE: DYES DNO IX) N/A KEYWORDS: pipe. stress calculation, MR 96-0069 REVIEW & APPROVAL r-..
..cr:::..~- *.@!6"fd'~ ~~ 6/i&/97 1~!~h~~~I'I-~..~n
"' U<Signature.IDate)
Prepare:r (SignatureIDate) o Reviewer (Non-Safety) *s. IItWnate) upetV150T. (Printed Name. KCN. or SSN) ~esign Verification Reviewer lUjesh Gupta(KCN) I~ Rajni R. Patel (0861) Lothar Kubn(llOS) Page 13 of 131
=-----==~
ENTERGY CALCULATION COVER PAGE ENGINEERING DEPARTMENT RIVER BEND STATION CALC. NO. - REV. ADDENDUM AX-71AG. Rev. 4 ATTACHMENT NO.: I rrfl;)07
& VA' ~\.P]/;7)(
TITLE: Pipe Stress Analysis for les function added through FWS system per SUPERSEDES: AX*71AG Rev. 3 MR96-0069 . ~- . . . .. ., - - .
--" ., Y.'-.-' ~
SUPPLEMENTS:
- . . . . . . ..... # * .,. * .,., ..... .--...... ~ .. . . 9 _ ..... .....,..,~~ r ** ~ ** *
- CALCULATION STATUS: o APPROVED iii PENDING o CANCELED SYSTEM NO.: 204, 209 I MARKNO.:
CLASSIFICATION: l&.sAFETY RELATED : I NON-SAFETY RELATED: DQAPA IX! NON-QAPA PURPOSE I SCOPE I OBJECTIVE: _ .. - . -. - . ... . -- .... .., ... fU'
~.
See page;7 1t-'h " 7 RECEIVED JUN 0 9 1998 SOC ' CONCLUSION: _. .. .. nus piping analysis demonstrates the acceptability of the piping system withln acceptable design limits of ASME Section III Code for MR 96-0069 . . .- . --- .. -........ - .... - .. _- SOFTWARE USED FOR CALCULATION: iii YES ONO SDDF#: 6229.400-100-00tA Manufacturer. Bechtel . Natpe
- -..... MEtOl ~*.V~ionIRelease No. N4 ..
CONFIRMATIONS REQUIRED.: 0 YES. . JXl. NQ.ICONFIRMATION COMPLETE: 0 YES ONO IX! N/A KEYWORDS: pipe. stress calculation. MR 96-0069 REVIEW & APPROVAL Idt< ~I; Guph"/11- "k-'7 L"'\. I~*;.
', G?!B[j'?
. IE A-. '. ~~ 6/1&/97 U(SignatureIDate)
Preparer (SignatureIDate) o Reviewer (Non*Safety) 's . J.S:.MIn."ture/Date) uperYlSor (Printed Name, KCN, or SSN) "ttDesign Verification Reviewer ~jesh Gupta(KCN) Jnrj Rajni R Patel (0861) Lothar Kuhn(l105)
RBG-47876 Page14ofr1=3~1~~ ____~__________________________________- .__________________~ CALCULATION CALC. NO. -REV. ADDENDUM AX-7IAG. Rev."
===~
ENTERGY ENGINEERING DEPARTMENT RIVER BEND STATION ATfACHMENT NO.: PAGE 2 OF TABLE OF CONTENTS SECTION PAGE
- 1. Title Page .. ... .................................................................................................................... 1
- 2. Table of Contents ... .. ............................................................................................ .. .......... 2-3
- 3. Revision History ............................................................................................................... 4
- 4. Applicable Documents ......................................................................................................5-6 Calculation Summary
- 5. Objective .. ............................................................... .................................. .......................7
- 6. Method of Analysis ........... .......................................................... ... ...................................8-9
- 7. Conclusion ................. .... .. ................................................................................................ 10
- 8. Notes........................ ...................................... ................................................................. 11
- 9. Assumptions .................................................................................................................... 12 Design Input
- 10. Isometric Sketch ............................................................................................................ 13-21
- 11. Basic Analytical Oata ......... .... ........................................................................................ 22-23
- 12. Valve Oata ..................................................................................................................... 24-27
- 13. Concentrated Weight Data .............................................................................................28
- 14. Relative Thennal Anchor Movements ......... .......... .......................................................... 29
- 15. Relative Seismic Anchor Movements ............................................................................. 30*32
- 16. Thermal Modes .............................................................................................................. 33
- 17. Fluid Transient Oata ....................................................................................................... 34
- 16. Dynamic Loads ........... ................................................................................................... 35 Summary of Results
- 17. Maximum Stress Levels .............................................................. ...................................36
- 18. Functional Capability Evaiuation .............................................................. ................ .......37
- 19. HELB I MELC Evaluation ................................................................. .............................. 38
- 20. Valve Accelerations ..................................................... ................................................... 39-45 21 . Flange Qualiflcatlon ............................................................................................ ............ 46-55
- 22. Vent & Drain Line Qualification .. ..... ................................................................................56
- 23. Sleeve Clearance Evaluation .............. ............................................................................57-69
RBG-47876 Page15vr~~ ____- .________________________________. -________________ ~ CALCULATION CALC. NO. - REV. DDENDUM AX-71AG, Rev. -' ENGINEERING DEPARTMENT ATIACHMENT NO.: ENTERGY RIVER BEND STATION PAGE J OF TABLE OF CONTENTS SECTION PAGE Checklists
- 24. Calculation Checklist. ..... ........ .......... ...................... ................................................ 70
- 25. Reviewers Checklist. ...... ....................................................................................... 71
- 26. Design Verification Record .... .... ............................................................................. 72 Attachments Attachment A........ ..................................................................................................... 1-14 Attachment B............................................................................................................. 1-1221 TOTAL:..... .... 1307
RBG-47876 Page16orf_13_1~~ ____. -________________________________- r______________________~ A CALCULATION CALC. NO. - REV. ADDENDUM AX-7tAG, Rev. "
=!:!::~ ENGINEERING DEPARTMENT ATTACHMENT NO.:
ENTERGY RIVER BEND STATION PAGE 4 OF REVISION HISTORY Revision Paragraph Description of Change No. No. 4 All Per MR 96-0069 the RCIC injection function was added to feedwater system by routing the renumbered RCIC injection line ICS-006-101 -2 via RHR line RHS-01 0 2 into the West loop feed water line. This revision incorporates all of former stress calc AX-76B into AX-71 AG, except the portion of former line ICS-006-7-' which was cut near node 78 and abandoned in place from node 86 to the penetration Z19.
RBG-47876 Page 17 of 131 CALC.NO.-RE~ADDENDUM CALCULATION AX-71AG, Rev. 4
--.....-- ENGINEERING DEPARTMENT ATTACHMENT NO.:
ENTERGY RIVER BEND STATION PAGE 7 OF APPLICABLE DOCUMENTS I. APPLICABLE CODES, STANDARDS, & REFERENCES (NON-RBS):
- 1. ASME Boiler and Pressure Vessel Code, Section III, 1974 edition
- 2. ME101 Version N4 Pipe Stress AnalYSis Computer Program
- 3. Piping Design and Engineering by ITT Grinnell Industrial Piping, Inc. Fifth Edition
- 4. Bergen-Paterson Pipe Supports, Catalog No. 82 II. RBS
REFERENCES:
- 1. Pipe stress analysis summary, Calculation No . AX-76B Including Addenda
- 2. EDS-ME-014, *Pipe stress Analysis and Pipe Support Design standard"
- 3. Specification No. 228.000, Rev. 2 *Piping Engineering and Design"
- 4. CHOC-EMTR-601 , "Design and Installation of Seismic Small Bore Piping, Instrumentation Tubing &
Supports for River Bend", dated Sept. 1980 "5'. EMTR 605-0, "Procedure for Qualification of Flanged Joints for ASME Ill, Class 1, 2, and 3 Piping Systems"
-6. CHOC-EMDM 82-BO , *Stress Intensification Factors and Stresses for Reduced Outlet Branch Connections,'
- 7. CHOC-EMDM-80-4, Use of Pipe Support Stiffness Values in Pipe Stress analysis
- 8. CHOC-EMDM-81 -8, *Valve Modelling Procedure"
. 9. LEM-34, "Frequencies and Acceptable Accelerations for Valve Qualification"
- 10. Calculation RBI-EQ-352, "Acceptable Acceleration for Manual Valves*
-11 . Calculation RBI-EQ-~16 , "Valve Modelling and Acceptable Accelerations"
- 12. Environmental Design Criteria No. 215.150, Rev. 2
- 13. Design Criteria No. 228',010 , "Pipe Stress and Pipe Support Design Criteria-
- 14. Design Criteria No : 220.950/960, -High Energy Line Break Evaluation"
- 15. Design Criteria No: 220.940, "Moderate Energy Line Crack Evaluation-
- 16. Une Designation Table Change Notice - LOTCN No.: 97-ICS-01
~
- 17. PICL Change No: AP*71-02
- 18. PICl Change No: AP-76-01
- 19. PICl Change No: AP-17-01 l
.20. Calculation G13.18.1 .S*08, Rev. 1, *Peak Spread ARS for Seismic Events Including Curves with N-411-1 Damping-
- 21. Calculation G13 .1B.1.S"09, Rev. 1. *Peak Spread ARS for SRV. Chugging, CO and Pool Swell events Including Curves with N-411-1 Damping"
RBG-47876 Enclosure 2 Page 18 of 131 CALC. NO. - REV. ADDENDUM CALCULATION AX-71AG, Rev. 4 ATTACHMENT NO.:
----.. ENGINEERING DEPARTMENT ENTERGY RIVER BEND STATION PAGE ~ OF APPLICABLE DOCUMENTS II. RBS
REFERENCES:
..22. Calculation PX-334, Rev. 2, "1/2 SSE Structural Seismic Displacements Data and Input Procedure for Piping. Analysis"
'23. Calculation PX-SB-316, *Pipe Stress Calc. for Vent, Drain & Instrument Connections'
- 24. Calculation PX-SB-304, *Pipe Stress Calc for Vent/Drain Connections'
- 25. Calculation AX-17D, "Pipe Stress Calc. For F.W. PPG. in Reactor & Aux. Bldg"
- 26. Calculation PX-873, "LPCI Pump Discharge Lines Water Hammer Analysis with Trapped air"
- 27. Calculation PX-1 037, "Water Hammer Analysis on Reactor Core Isolation Cooling Piping Due to Pump Trip'
- 28. Calculation PX-897, "RCIC Pump Discharge Lines Water Hammer Analysis with Trapped Air"
- 29. Calculation PX-1 015, "Fluid Transient on RHS Piping Associated with Check Valve Slam Following a Pump Trip"
. 30. Calculation PX-1024, "Fluid Transient on RHS Piping Associated with Suppression Pool Cleaning Mode with Trapped Air" I . 31. Calculation PX-888, "LPCI Pump Discharge Line Water Hammer Analysis with Trapped Air for Mode 8"
- 32. Calculation PX-1005, "Water Hammer Analysis on RHR PIping Une During Shutdown Cooling" In. AFFECTED DOCUMENTS:
DOC. NO. REV. DOCUMENT TITLE AFFECT CHANGE NO. (Superseded, Revued, Initiated, DOC. etc.) 013.18.10,3*221 o . Pipe Support Initiated MR 96-0069 Z-76-2073A OA Pipe Support . Supplements MR 96-0069 AX-76B 2 Pipe Sress Revised MR 96-0069
RBG-47876 Page 19 of 131 r-~=-----'--------------------------------'------------------~ CALCULATION CALC. NO. - REV. ENGINEERING DEPARTMENT AX-71AG, Rev." ENTERGY RIVER BEND STATION PAGE 7 OF PURPOSE I SCOPE I OBJECTIVE MR 96-0069 reroutes the RCIC Injection Line from its original connection to the RPV Head to the FWS system through a short portion of the RHS piping covered by this AX. The objective of Revision 4 is to evaluate the subject piping for the new function of ICS injection in addition to the existing function of the RHS piping . A new run of6" piping with a new check valve connecting line RHS-010-65-2 to the existing ICS piping is to be added. Since some of the originallCS piping beyond the diversion point is left in place and was downgraded to ASME Class 2. the active ICS line was renumbered from ICS-006-7-1 to ICS-006-101-2. The design pressure in the lines RHS-010-65-2 and WCS-004-22-2 upto the first check valve were reduced from 1885 to 1525 psig. The piping is to be evaluated for thermal. fluid transient. dynamic, and hydrodynamic events associated with both the RHS and ICS system operation . As a consequence, the piping of stress problem 1V<.-71 AG is now being extended top cover the ICS (RCIC) piping back to its nearest anchors. The added piping comprises all of the existing stress problem AX-76B. except the portion beyond the diversion point of which the first 6 ft is remained and the remainder abandoned in place is evaluated in calcualtion AX-76B. There are no support configuration changes; the rerouted ICS runs unsupported from its last existing support to the new check valve at the new junction to the RHS line.
RBG-47876 A Page200fr13~1~-=~ ____r-____________________________________- .____~~____________--, CALCULATION CALC.NO.~REV. o::==~ ENGINEERING DEPARTMENT AX*71AG, Rev." EtlTERGV RIVER BEND STATION PAGE <2 OF METHOD OF ANALYSIS The ICS piping was originally analyzed for hydrodynamic loads (SRV etc.) because it was connected to the containment penetration Z-19. Now it is connected to the reactor building via the feedwater line and therefore at least some of it has to be analyzed for the ARS transmitted from that end. The fluid transient due to ICS injection is also changed. There is no other physical or operational change to this stress problem. The ICS piping in this stress problem includes eNS piping and tie back into RHS line ofAX*71AG which previously in AX*76B had been modeled as a fictitious anchor. The thermal operating conditions of the incorporated piping from the AX*768 model have to be incorporated into those of the existing AX-71AG model. ME101 The piping was analyzed using ME101 , Version N4. The input files have been annotated with comments describing the changes made from the existing ME101 input file . Such changes cover incorporation into the coding of various notes made in previous revisions as well as the changes/additions due to this Revision. Fluid Transient Input The piping experiences a fluid transient due to RHR injection into the feedwater line and another FT due to les injection into the feedwater line via the RHR line. In order to simplify the analysis by executing it in a single ME101 run, the second fluid transient is appended after the end of the first fluid transient, so that the piping response from the first transient has ceased and then responds to the second transient. The maximum loads of this load case correspond to the envelope of the Individual fluid transient loads. The RCle transient input tile is derived from PX-1037 and run from t=o to *t=0.6 sec; the RHR transient Input file is derived from PX*1015 and is delayed 0.6 sec. To implement this, the time histories of the segments affected by the RHR transient are delayed. The fluid transient model of PX*1 037 uses a preliminary routing of the RCIC line. The final routing breaks up the long north*south segment into a short segment running at 45 deg to this segment and the remainder. It also corrects the length of the west-east segment at EI. 119'*9" from 9 ft to 3 ft. Addendum A to the PX calculation reconciles these differences by recommending an adjustment in the application. This Is implemented by using conservative multipliers for the existing curves as follows: LENGTH ADJUSTMENT SEGMENT PRELIMINARY FINAL FT MODEL CURVE APPLIED CURVE LENGTH (FT) LENGTH (Ff) PIPE NO AX MULTIPLIER SEGMENT NODE X75-X78 9 3 6*6 36 X75 1.0 X79-X80 - 2.2 N/A 38 X79 0.5 X80-X82 12 9.8 7*2 38 X80 1.0
RBG-47876 Page 21 of 131 r-~~----'--------------------------------.------------------~ CALC. NO. - REV. CALCULATION
----.. ENGINEERING DEPARTMENT AX-71AG, Rev. "
ENTERGY RIVER BEND STATION PAGE 9 OF METHOD OF ANALYSIS (cont.) Response Spectra Input The ARS input differs from Revision 3 mainly in that N-411 Code case spectra are now replacing 1% 2% spectra; but in addition , the Shield Building spectra are now also included, and no change to the piping mass points Is needed to separate regions affected by Reactor Building spectra from those wh ich experience only Auxiliary Building spectra . The Reactor Building spectra that are picked up from the feedwater line connection have been input as follows: The FWS penetration for AX*170 is at elevation 121 '-6" and is rigidly connected to the drywell wall and the Shield Building wall at that elevation. The drywell wall is a rigid 6 way anchor (AX-170 node 200), while the Shield Building support is a 2 way guide (AX-170 node 183). The Jet Impingement wall also provides 2 way guide support to the Feedwater line at the Auxiliary Building (AX-170 node 280). The Feedwater line runs In the plant global X direction. OBSA analysis uses the alternate Auxiliary Building displacement curves. High energy Line Break has been addressed in the calculation no: 228.850-CBC-2024 Rev. O. Since the flooding has been addressed in the HELB calculation, Moderate Energy Line Crack need not to be considered for this calculation .
RBG-47876 Page 22 of 131 _ CALCULATION
~~~~.----------~----~
CALC. NO.-REV.
====e
..---.. ENGINEERING DEPARTJ\'IENT AX-7lAG. Rev. 4 ENTERGY RIVER BEND STATION PAGE IOOF CONCLUSION The completed analysis shows that the stresses and reactions on the subject piping are within acceptable limits in accordance with the requirements of the ASME Section III Code.
Valve accelerations are within acceptable limits. Functional capability has been assured. Stresses on vents, drains, and test connections are within acceptable limits. Sleeve clearances are adequate.
RBG-47876 Page 23 of 131 r-~~---r----------------------------.---------------~ CALCULATION CALC. NO. - REV.
----- ENGINEERING DEPARTlVlENT AX-1tAG. Rev. oJ ENTERGY RIVER BEND STATION PAGE I j OF NOTES
- 1. The Coordinate system for all data expressed in the global system is defined as follows :
(-X) Is plant *called north per piping drawing W (y) Is vertical *up* (Z) According to right hand rule The local system is defined as follows for straight piping members : (X) Is along the axis of the pipe, positive in the direction of coding. (y) In the plane of the local X-Axis and the global +Y-Axis unless the local X-Axis is aligned with the global Y-Axis ; then the local Y-Axis will be parallel to the global X-Axis. (Z) According to right hand rule.
- 2. Forces and moments on restraints, supports, and equipment are those imposed by the piping systems O.e., actions, not reactions) .
- 3. Unless otherwise noted, forces and moments reported at an inline anchor represent the total forces and moments acting upon that anchor considering contributions from piping on all sides of that anchor. Reactions reported on terminal anchors are due to piping shown in this report only. For total reactions, values must be combined with those from continuation summaries shown on isometrics .
- 4. Unless otherwise indicated , stresses at intersections have assumed an unreinforced branch connection.
- 5. Piping support loads may be found in pipe support summary In Attachment B.
- 6. For lines requiring seismic analysis, the reactions reported are cyclic in character, and reactions must be considered as acting in either the positive or negative direction.
- 7. On systems requiring time-history dynamic analysis for flow-induced transients, reactions and deflections reported are the maximum values in magnitude. Reactions and deflections that may occur in opposite directions are not reported in this summary, but are available if required.
- 8. Abbreviations RH----------Rod Hanger SH---------Spring Hanger V.C.----Vertical Restraint RX-- X-Restraint RZ-- Z-Restraint RSKew----Skewed Restraint SX X-Snubber SY-- --V-Snubber SZ Z-Snubber SSKew-----Skewed Snubber EI----EJevation Rdcr-----Reducer S.R. Elb---Short Radius Elbow
- 9. The magnitude of the forces from flow transient PX-1 015 are much larger than those from flow transient PX-888, PX-873, PX-100S and PX*1024. Therefore, flow transient PX-1 015 is enveloping the other transient cases and Is the only one to be considered. in the analysis.
- 10. ME101 model and isometric has a small dimensional discrepancy between nodes 330 and 805 which is insignificant.
RBG-47876 Page 24 of 131
~a~~----------~~--~ CALCULATION CALC. NO. - REV.
~
----- ENGINEERING DEPARTMENT AX-71AG. Rev. 4 ENTERGY RIVER BEND STATION PAGE IZ OF ASSUMPTIONS The weight of the new 6" check valve is assumed to be 430 lbs.
..-----e---.-------r--------,
RBG-47876 Page 25 of 131 CALCULATION CALC. NO. - REV. ENGINEERING DEPARTMENT AX-71AG, Rev. 4
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~
CALCULAT ION IDENTIFICATION NUMBER J.O. OR W.O. NO. 12210 DIVISION & GROUP E.M.jPlpe stress CALCULA nON NO. 8X- 71 AGf OPTIONAL TASK CODE PAGE_ R.,",.4 2 3 4
!I VALVE C, G . (Ref. )
6 T CD Mev F 013 (NODE.)(1S) 8 9
/I I YAlYf... ONlY:- - - - - - - - - - ,(:10*14 *845 10
- =
II 12 13 OPE RA TOR ONLY : 14 1/ / X = 15 2*9 ::: ,242. 16
* ,f y
It (5,2 + 30* 437) - 10*14-IT
- =
18 /I I 19 :::: 25'4-'37 :; 2*125 3*7 I' 20 2I 22 r "" - -308
/
23 ao4 25 26 2T MOV F023 (NOnE. 345) 28 I 29 VALVE. ONLY Y=~~~ . :: '..5 1~ 30 31 OPE.RAtOR ONL'( 32 II r/ I 33
. ~ X = -3,4 = -. Z~3 II-r-0 ~~ ____ MOToR 34 r .
35
\.9 '( := ('.0+ \8.5~'2.) -, ~~'
36 37 IL lCc"
,\..'./.J X = IS*375
'1
= 1*531 I
eli ~ I, t 38 39 I 40 Flow '2 = - Il :: - '158, 41 42 C 43 44 45 46
RBG-47876 Page 40 0 f " CALCULATION CALC. NO. - REV.
- =s
_--'4-. ENGINEERING DEPARTMENT AX.7IAG, Rev.-"
- ENTERGY RIVER BEND STATION PAGE 21S0F CONCENTRA TED WEIGHTS ITEM COMPONENT DESCRIPTION WEIGHT (lBS) NODE POINT 1 VALVE BODY, 1E51 "MOVF013 690 X20 -
2 VALve OPERATOR , lE51-MOVFOI3 420 X22 3 VALVE,IE51'VF034 10 610 8 VALVE,lE12'VFOI9 145 320 9 VALVE, lE12 " VF061 10 815 10 VALVE l E12"VF062 10 835 11 VALVE BODY, lE12'MOVF023 280 350 12 VALVE OPERATOR , 1E12 'MOVF023 255 352 13 SUPPORT COMPONENT WT . 10 382 14 SUPPORT COMPONENT WT . 410 66 15 FLANGE WEIGHT 30 415 16 FLANGE WEIGHT 30 417 17 VALVE,IE12'VF086 350 520 18 1EI2*FEV014A(A*) 450 128 19 Valv& Operator 1El2 'MOVF053A 1100 82 20 Va(v& Weight 1E12 "MOVF053A 1900 80 21 lE12"VF050A 1850 182 22 Check Valva 430 X98 23 lE12"VF063A 350 304
RBG-47876 Page 41 0 fB1 CALC. NO ** REV. CALCULATION
- ---.. ENGINEERING DEPARTMENT AX-71AG, Rev."
ENTERGY RIVER BEND STATION PAGE2~OF RELA TIVE THERMAL ANCHOR DISPLACEMENTS ItJPP01T . lorPOlT it. SUPPOlt p.-HER ATIACBK!trr lI'O. TYPE LOCATION MODE nEVATION (ftJ_ ~X(in) .6T (in .6Z (in)
, If 215 ACisuH£~
ANC.HO~ AtJ X. 6 LOc,..
,*8 lZl- ,~ I* & '31
- 10 () . ogt
- 2. -.1'0 '009 - -007
f". RBG-47876 Page 42 0 CALC. NO. - REV. CALCULATION ENGINEERING DEPARTMENT AX-7lAG. Rev.'-
-ENTERGY
---~
- RIVER BEND STATION PAGE30 0F AELA TIVE SEISMIC ANCHOR DISPLACEMENTS IUPPOIT SUPPOlT n; SUProlT ATTACHMENT 110. TYP! LOCATION ELEVATION (ft) .61 (in) .6t (in ~ %(in)
A lJ~
- 5' AI'JC: HOR. '6 LOG-. loG -
I 9 '" - 27 .124 -240
-53 ~ R)( ,~z S 9'. S"
*t~ - .23 116
'* vc., Rc I OJ.' - Jl~,
, .. - -114 *2,"35 14'
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- * 'l l30 oil ANC~O~ ~~'.. "l1t *2.\
- 11.35 . 20!"
310 .; A~CHoR ,r 106- ~
*27 . 'IZ4 *21.1-0 REF: f>K-3.34
** Reference for the seismic anchor movements: Absolute/displacements of the Auxiliary Building.
All restraints have Auxiliary Building displacement except the fictitious anchor for the feedwater line (node 21 5) which has Reactor Building and orbital motion relative to Auxiliary Building restraints.
RBG-47876 STONE & WEBSTER ENGINEERING CORPORATION Page 43 of 131 CALCULA TION SHEET CALCULATION IDENTIFICATION NUMBER :;/ JO. OR WOo NO. 12210 DIVISION & GROUP NP(C) CALCULATION NO. A'I.-7l~ Rs..J,4 OPTIONAL TASK CODE PAGE REF. -- DESIGN INPUT (CONT'D) RELATIVE SEISMIC ANCHOR AND/OR SUPPORT DISPLACEMENTS
~
- 6i:ii ~JI:.GijLMlI9~t ~m ;Ht; P9LL9ltH!i6 PMiIH&~ ~.,,~ I .)
SUPPORT DISPLACEMENTS
- NODE SUPT. BUILDING A'I"l'ACHMENT (IN) REMARKS NO. TYPE ( STRUCTURE) ELEVATION (FT) OX OY DZ
>(1 ~ A tIX. /3L..D6t, q/,719 0.2550 0.1800 0.2370
)(9 ~~ Q7-'25 0.2750 ------ ------
)(47 IRskEW /04.75 ------ 0.1810 0.2680
)(48 ~KeW 104,75 0.3070 ------ 0.2680
)( 52 ~i! 104,75 ------ . ------ 0.2680
><. 61 R.e IO~.O ------ ------ 0.2720 X71 r-;skew IIB.lto7 0.3620 ------ 0.3030 X. 76 Vc. /1~75 ------ 0.1810 ------
p- /~ . 7.c:.
~ r-..-
~
/~~,6Z(P 100 0.3800 0.1810 --~
--.......... ~~(,
121 ~ ------ -~ 0.3130
'/c::. /1Z~t6'Z-z-. ~
~
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, 'J~
-- ~o 141 ~,~ 0.3130 220 ~,~
I~o_.~ /"2'2,w
- ---- 0.4110
~
~ ...... ~&:Nr. jll;Z, 1~ 0.9870 0.4390 0.8690 ~
RBG-47876 Enclosure 2 STONE 8& WEBSTER ENGINEERING CORPORATION Page 44 of 131 CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER
~2 JO. OR WOo NO. DIVISION 8& GROUP CALCULATION NO. OPTIONAL TASK CODE PAGE_
i . 12210 NP(C} Ay..-7l~ ~.4 REF. DESIGN INPUT (CONT'D) RELATIVE SEISMIC ANCHOR AND/OR SUPPORT DISPLACEMENTS (
- SEE CitbCtfbMi9N Oll 'fllfl POb hOWH'S E\\6B (5) ~
"I i .)
SUPPORT DISPLACEMENTS
- NODE SUPT. BUILDING ATTACHMENT (IN) REMARKS NO. TYPE (STRUCTURE) ELEVATION (FT) DX DY DZ o<ouv jf, ,I,J1 T'JI2V IAlJ: I I /~~,/7
.... ... . ,- .~
338 ~>\f. At/X, &..o<!,. '18.76 0.2800 0.1800 ------ 375 Rc IQ?385 ------ ------ 0.2570 380 Rx /oB,v;7 0.3020 ------ ------ 382 $1-/ 104,7e ------ 0.1810 ------ 410 Vc /tXtJ.75 ------ 0.1810 ------ us A.
..... lo~,75 0.3150 0.1810 0.2740 537 Vc;& 98.31 ------ 0.1800 0.2520
~. rM 103,QICJ, 575 r .... 0.3000 0.1800 0.2640
RBG-47876 e Page 45 of 131 CALCULATION CALC. NO. - REV. ENGINEERING DEPARTMENT AX-7lAG, Rev." ENTERGY RIVER BEND STATION PAGE~~OF Basic Analytical Data Thermal Modes: ICS and RHS is injecting - or not injecting - while FWS is hot or old, i.e, while feedwater connection node 215 has either the static displacement, for feedwater hot or cold. Injection at 122 deg F bounds "no injection" at 120 deg F. Modes 1-9 represent the different flow conditions . Modes 6-9 were not analyzed. They can be considered bounded by modes 1-5. Region Mode (Tempereture of) 1 2 3 4 5 6 7 8 9 Pipino Une No. 1 122 40 40 298 185 122 40 122 122 RHS-014-74-2 2 122 40 40 298 40 122 40 122 122 RHS-*Olo.66* 2 3 122 40 40 298 40 122 40 122 122 RHS-Olo.65* 2 4 426 40 425 298 425 122 40 170 170 RHS-Olo.65*2 (AFTER CK) 5 425 40 425 298 425 122 40 170 170 ICS-OOa*1 01 *2 (AFTER CK) 6 122 40 40 122 40 122 40 170 170 ICS-006-1 01 17-2. RH5-004-9o.2 7 122 40 40 122 40 122 40 170 170 IC5-006-8*2 8 122 40 40 122 40 122 122 122 122 RH5-004-113-2. CN5-004-52*2 9 122 40 40 100 40 122 laO 100 122 CN5-004-415-3 10 122 40 40 298 185 122 40 122 122 RH5-014-75*2 11 122 40 40 29B 40 122 40 122 122 CNS-004-58*2 12 122 40 40 100 185 122 40 122 122 CN5-004-5 7-3 425 40 425 425 425 425 425 425 70 Feedwator Uno Temp
RBG-47876 Page 46 of 131 CALCULATION CALC. NO. - REV.
=-----
==~ ENGINEERING DEPARTMENT AX-71AG. Rev."
- RIVER BEND STATION PAGE~40F ENTERGY DYNAMIC LOADS FLUID TRANSIENT FILE NAMES:
FROM TO FILENAME
/home3Iywu90/px1037Ifrcic.29 678
- 1178 1180 1680 /home3Iywu90/px1037Ifrcic.30 1682 2182 /home3/ywu90/px1037Ifrcic.31 2184 2684 /home3Iywu90/px1037Ifrcic.32 2686 3186 /home3Iywu90/px1037/frcic.33 3188 3688 /home3/ywu90/px1037/frcic.34 3690 4190 /home3Iywu90/px1037Ifrcic.35 4192 4692 /home3/ywu90/px1 037/frcic.36 4694 5194 /home3lywu90/px1 037/frcic.37 5196 5696 /home3lywu90/px1037Ifrcic.38 5698 6198 /home3lywu90/px1037Ifrcic.39 6200 6700 /home3/ywu90/px1037Ifrcic.40 6702 7202 /home3/ywu90/px1037Ifrcic.41 7204 7704 /home3/ywu90/px1037Ifrcic.42 7706 8206 /home3/ywu90/px1037/frcic.43 8222 8721 /home3/riverbend/ftlpx1 015/p1 015104.017 8723 9222 /home3/riverbend/ftlpx1 015/p1 015104.018 9224 9723 /home3/riverbend/ftlpx1 015/p1 015104 .019 9725 10224 lhome3/riverbend/ftlpx1 015/p1 015104.020 10226 10725 /home3/riverbend/ftlpx1 01Sfp1 015104 .021 10727 11226 lhome3/riverbend/ftlpx1 015/p1 015104 .022 11228 11727 lhome3Jriverbend/ftlpx1 015/p1 015104.023
RBG-47876 Page 47 0 f 131 CALCULATION CALC. NO. - REV.
- 8
...---- ENGINEERING DEPARTMENT AX-71AG. Rev.",
ENTERGY RIVER BEND STATION PAGE.37 0F DYNAMIC LOADS FILE NAMES Unifonn ARS method is used. All supports except the fictitious anchor at node 215 are in the Auxiliary Building; therefore, the seismic ARS for the elevation range from highest to the lowest Auxiliary Building attachments are input. Node 215 transmits the Reactor Building ARS of Drywell and Shield Building to the piping model. The feedwater penetration Z-3A is attached to these structures at EL. 121 .85'. For the seismic ARS, a structural point above and below have to be input; for the hydrodynamic ARS, the structural model has a node at the penetratlon elevatlon. TABLE 1 Structural Attachment Elevation (FT) Curve Number aBE SSE Auxiliary Building 70 auxbon01 .ace auxbsn02.ace Auxiliary Buildina 95 auxbon03.ace auxbsn04. ace Auxiliary Building 114 auxbon05.ace auxbsn06.ace Auxiliary Building 141 auxbon07.ace auxbsn08.ace Drywell 114 rbdwon41.ace rbdwsn42.ace Drywall 133 rbdwon43.ace rbdwsn44.ace Shield Building 112.67 rbsbon03 .ace rbsbsn04.ace Shield Building 133 rbsbon05 .ace rbsbsn06 .ace TABLE 2 Structural Elevation Curve Number Attachment (ft) SAV1V SAV16V CHCO PS Drywell Shield Build ina 121 121
- rbsbtn03.ace rbdwan43.ace rbsban03.ace rbdwcn43.ace rbsbcn03.ace rbdwpn43 .ace rbsbpn03.ace
~ 80Ul-JbE-.b ey S'RY\I CAsl!5'
RBG-47876 Page 48 of 131 CALCULATION CALC. NO. - REV.
----- ENGINEERING DEPARTl\'IENT AX-71AG, Rev. 4 ENTERGY RIVER BEND STATION PAGE3~OF MAXIMUM STRESS LEVELS ASHE SECT. III, CLASSES 2 , 3 LOCATION MAXIMUM ALLOWABLE COMPUTED OESIGN or MAXIMUM COMPUTED STRESS ---------
CONDITION LEVEL ENO ELEMENT STRESS I PSI} ( PSI} ALLOWABLE SUSTAINED SH LOADS X25 X27 7166 .478 EQN. 8 X25 15000 OCCASIONAL 1.2 SH LOADS s X35 X35 15674 .971 EQN. 9 290 18000 OCCASIONAL 1.8 SH LOADS C 303 302 20692 .766 EQN . 9 303 27000 OCCASIONAL 2. 4 SH LOADS D 303 302 21011 .584 EON. 9 303 36000 THER.'IIIL SA EXPANSION 505 21$ M 22098 .982 EQN. 10 505 22500 Based on industry practice the regions which are isolated from the Reactor Building by at least 3 equivalent dynamic restraints in each direction can be considered unaffected by the Reactor Building response spectra. These regions experience only OBE and SSE ARS, and not hydrodynamic ARS. The boundaries of the RB affected region are beyond nodes (or exclude boundary nodes) 116, X" and X338. Therefore, the stresses in these regions can be corrected to exclude the hydrodynamic loading. The maximum stresses for level C and 0 were not corrected, since they are within the aJlowables.
RBG-47876 Page 49 CALC. NO. - REV. CALCULATION ENGINEERING DEPARTMENT AX-71AG, Rev... ENTERGY RIVER BEND STATION PAGE 370F FUNCTIONAL CAPABIUlY EVALUA nON: The maximum stress level for Equation 9 emergency condition and Equation 9 faulted condition are below the Equation 9 Normal/Upset allowable, and OD/t is less than 50 for piping associated with this calculation. Therefore, the piping system ensures the functional capability. No further detail evaluation is required.
RBG-47876 Page50ur~~=-----Ir-------------------------------------r----~~~~--______~ CALCULATION CALC. NO. - REV.
----- ENGINEERING DEPARTMENT AX-71AG, Rev."
ENTERGV RIVER BEND STATION PAGE~SOF PIPE BREAK LOCATIONS The only applicable region is from the feedwater connection at node 215 upstream to the first check valve in the RHR line, the RCIC line and the RWCU line (not modelled) i. e., nodes 185-215 and X93-X98.
Conclusion:
Besides the mandatory new break at node X93 (the interface of High Energy and Moderate Energy piping - see calculation no: 228.850-CBC-2024 REV.O), no new High Energy breaks need be postulated . The stresses in the High Energy region are well below the allowbles.
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..... C - . j VALVE IDENTIFICAnON NUMBER: 1E12i1 MOVF053A \~Ia.r~~
Loading IAcceleration in Global Coordinate System Acceleration in Global Coordinate System Acceptable Acceleration (g) ~ Case at C.G. of operator (g) at C.G of Valve Body (g) NP82 NP81 l"Jj Ax A'I Ax Ay Az Ax Ay Az Az 2! as 9 oaEI 0.162 0.131 0.238 0.094 0.13 0.237 2 2 2 SSEI 0.323 0.259 0.475 0.187 0.259 0.486J 2 2 2 SRV1V 1.137 0.783 1.277 0.617 0.781 0.347 3.5 3.5 3.5 ;;j~tj SRV16V 1.563 1.112 1.759 0.858 1.11 0.545 4 4 4 :=l"Jj> CHUGICO 0.411 0.153 0.224 0.196 0.151 0.307 =~~ t'ljZtj PS 0.115 0.086 0.103 0.058 0.086 0.034 4 4 4 2 ~. ~ FT 0.093 0.083 0.151 0.094 0.083 0.087 4 4 4 OOt""4 r;,)t'!j>
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~
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~~Z FAULTED 1 3.835602951 1.122648651 3.366866671 3.837759111 1.218494971 3.668198061 7.211102551 7.211102551 7.21110255 O~
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~
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3.5 2 3.5 2 3.5 ~~(") SRV16V 2.262 1.28 1.73 1.149 1.361 1.041 4 4 4 ~~~ CHUG/CO 0.351 0.37 0.691 0.765 0.406 0.307 =zn PS 0.168 0.105 0.149 0 .096 0.114 0.08 4 4 4 ~~~ 1.456 0.705 1.259 0.908 4 4 4
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NP352 NP350 Ax Ay Az Ax Ay Az Ax Ay Az rt1 2: OBEI 0.367 0.179 0.306 0.128 0.154 0.126 2 2 2 SSEI 0.726 0.356 0.607 0.254 0.306 0.249 2 2 2
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VALVE IDENTIFICATION NUMBER: 1E12*VF086 i':~I,~~m Loading IAcceleration in Global Coordinate System Acceleration in Global Coordinate System Acceptable Acceleration (g) -< Case at C.G. of operator (g) at C.G of Valve Body (g) NP NP 520 t!!fJ
~ ~ ~ ~ ~ ~ Ax Ay ~ ~
OBEI 0.228 0.148 0.131 2 2 2 ~C'l SSEI SRV1V 0.451 0.963 0.294 0.927 0.261 1.07 2 3.5 2 3.5 2 3.5 ~~n SRV16V 1.308 1.436 1.581 4 4 4 ~;~ CHUG/CO 0.528 0.72 0.797 ~~n PS 0.086 0.115 0.155 4 4 4 2!C'ld FT 0.489 0.572 0.918 4 4 4 ~~~ CJ)~~
~~~
~>o UPSET o o 01 1.414909541 1.552798761 1.832879161 61 61 6 ..... ~~
FAULTED o o 01 1.55954161 1.730351411 2.011371421 7.211102551 7.211102551 7.21110255
~~
Valve Spec No: 228.211
~
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'c C')
(lIS
~
-..n
..,0
-~ B~
~
N y. . ' ;<
=
2 1-y
"' ~BG:47876 Enclosure 2 Page 58 of CALCULATION CALC. NO** REV. ENGINEERING DEPARTMENT AX-71AG, Rev. 4 ENTERGY RIVER BEND STATION PAGE4-('OF FLANGE QUAUFICA nON LIllI ]f0. 1-21-15 -OI4-7Z-2
SUBJECT:
QUALIFICATION OF J'LAliGID JOINTS (TABLE A)
.ned On: IH'I'R-605-0 . (R£r# ?)
Node Point No. l'lS ASHE III CIa ** 2 and 3 FlANGE TYPE: J? r. wElC>INGo N£,I< SIZE: 14" FUNCI MATERIAL: SA-\oS BOtTING KATERIAL: sA - 193 Gt.!S7 NO. OF BOLTS: 2..0 S
- 25000 psi ~20,OOO psi S, * '3' '2.00 psi C
- 20.15" io.
'\ * .7(3X2Q;IS.Uin. 2 Df * ". ?S in.
- Syl 36000 a _*~8~b__7,--____ S 1. 0 Fs
- _..:..\7.:.;.*..:5~6~.;.&,"t.lII.Iot S: Mioimum allowable value of Itr*** for boltinl material It lOOO! from hble 1-7.3, lubsection NA, ASHE III (psi)
Sy: Yield Itrenlth of flanae material .t the delilo t.mperltur~ from tlble 1-2.2, 1-7.1 lublection NA, ASHE III (pli) C: Diameter of bolt circl ** (in.) 2
~: Tot.l croll-Iectional Ir** of tb. boltl at the root of the tbreads. (iry o
Df : Outlide dia** ter of r.i,ed face of fllDle. (io.) ACCEPTABLE 0 UNACCEPTABLE rt"r"----"'T""'------=--:-:-==-=:---------I--~;-;;--:;;::-:==;--....., Page 59 of 1 CALCULATION CALC. NO. - REV. AX-71AG. Rev. 4 ENGINEERING DEPARTMENT ENTERGY RIVER BEND STATION PAGE 470F FLANGE QUAUFICAnON LM NO. R 1-1 S - 014 - 7 S - 2 hJp : 128 S1lJJECT: QUALIFICATION or FlANGED JOINTS (TABU B) laaed 00: EHTR-60S-0 ( RiF.:jf 7)
** Desiln, Normal and Upset Conditions
.-1 Deadweisht and Thermal
~LOADS Hx (ft-lb) tty (ft-lb) Hz (ft-lb)
DEADWEIGHT - Co 57 -lO99 3~O3 I 15 ~ , I c:; ~
-4'1, THERMAL H- 2.~g9 STEADY STATE * - -
TOTAL (A) * -+ (099 * ? S 92
- 1. Bcndinl moment. /(M )2 + (H )2 Y Z ft lb
- 2. Torsional .oment =Hx ft lb
- 3. Allowable moment z
---rr- *c 3125. F . ~
-1) ft lb "fa: The aaxi.WI of 1 or 2 * '7 ~ 3 3. ~+.
Total CA) i. the .. xiaua of the (deadwei,ht + It.ady Itate) or I. (deadwei,ht + th.~l + Iteady .tate) allebraic combination *
..... KaximWi COVY'foVle...,fs. -f'ro/"'Y') <i:1 fI 7h~n-y,ltl C6l-"S I;'r()~ .
RBG-47876 .---=:::----r-----------------r---:;::;:-;;:-:::-::-::---=~:----, Page60of1~~ CALCULATION CALC. NO.-REV.
;e;!i
..-....-.. ENGINEERING DEPARTMENT AX-1IAG, lUv.4
---ENTERGY RIVER BEND STATION FLANGE QUALIFICATlON LINE NO. R-1---4 So - 014 :.2. NP ~ 12 &
S'UBJECT: QUALIFICATION or FlANGED JOINTS (TABLE C) lued On: EMTR-60S-0 ( ~f r~ 5")
.-2 De.dweilht, Thermal and Dynlmic LOld.
~I-l Moments Mx (ft-lb) My (ft-lb)
LOADS ~ TOTAL (A) ~ 495 (,99 ? 892 N+U Dynlmi c *It ~ ~7 ~IJ 1100 OBEA 2~1 44'7. 2~7 TOTAL (B)
- 17 ~ 5.
- 4. Bendin& Moment
- 7439 ft-lb S. Torsional .o.ent
- Hx .
- I 093 ft-lb
- 6. Allowable .o.ent
- 6250 r ,t ~
1"2 I kfd S 6250 12 (Sy) C 36000 t\' Hid: the ani.WI of 4 or S.
- 74 39 (.'1- La
- Ab.olute ~o.bin.tion of At N+U dyoaaic and OlEA
** n.xi.ua value of all dynlmic lo.d combination. for norm.l .nd up.et condition (i .*. t OlE. SRV. fluid Tran.ient. etc)
/-JoTE: .s"y) I=T !:>OS t..JOT A~P!..'1' I SINe..;;
f$OL.AT&D F-J2.C>/Yf 'R..e.
~B(j-4787o Enclosure 2 """'"'---==---'"I"----------------'""'T'--=-:-:------...., Page 61 of 1 CALCULATION CALC. NO. - REV. ENGINEERING DEPARTMENT AX-71AG, Rev. 4 ENTERGY RIVER BEND STATION PAGE 490F FLANGE QUALIFICATlON LINE NO. R~'5.-
, 014-/5-2 NP:
SUBJECT:
QUALIFICATION OF FlANGED JOINTS (TABU D) lased On: IMTR-605-0 (~f' ~ 2)
- b. Ellulency Condition b-1 Deadweilht. Tbermal and Dynamic Load.
~LOADS Mx (ft-lb) My (ft"lb) Mz (ft-lb)
TOTAL (A) 495 &, 99 5 i 92 EMERGENCY DYNAHIC ** "331 (, ( I r I OO~ TOTAL (C)
- g?>2 I ~ 10 I (.,992
- 7. Bendin, moment ./(M )2 + (M )2 V y z
- J< I ~ 10)2 + <<(,~~~2 IS 7 I J,4 ft-lb
- 8. Tor.ionll Moment
- Mx = g 32 ft"'lb
- 9. Operatin. prellure
- Po * 'SQOfS; ~ l.SP. 1.5'XSoO =7r Q p5.i
- 10. Allowable aoment * (11250 ~ - 1:2 16 D2f P) e FIC /12
* (11'150)(1'.2' _~"I,.25aJCotoO)1(\1:lJ: 11328'1 1'2. I=-T. Le Po: Kaxi.tIII operatinl prellure durin. e.erlenC)' condition (psi). 500 f!>;
P: Deli,n pre .. ure (psi)
- S"oo r S,
'I: laer,ency condition pre .. ure concurrent with Mfd (pli) * ~()c) pSt
!tfcS: The .axi.... of 7 or a
- 7 I \ 4 fL ,..
- Ablolute co.biDation of A and emerlen~ dyn..1c ,
** Maxi.... value of all dyna.ic IOld combinations for .mer,en~ conditioD
- '*~rm*.:tt7S;O-Enclosure 2 Page 62 of 1 CALC. NO. - REV. CALCULATION ENGINEERING DEPARTMENT AX-7lAG, Rev. 4 ENTERGY RIVER BEND STATION PAGE ,~OP FLANGE QUALIFICAT10N tINE )l0. RH ~ - 014 - 7 ; - 2 ~P ~
SUBJECT:
QUAlIFICATION OT rtANGED JOINTS (TABLE E) aued On: EMTR-605-0 ( ~e. F't 2)
- c. Faulted ConditioD c-1 Deadweilht. Thlr.al and Dynamic Loads
~"
LOADS "x (ft-lb "y (ft-lb) Hz (ft-lb) TOTAl (A) 4 ~S; Co~9 S"g 9-.1 FAULTED DYNAMIC '*'* &;~~ I I 9 I. 2102-TOTAL (D) '* /157 J8<to 79~4
- 11. BlndiD, .oment * /(",)2 + (Mz)2
* /(/890)2 + (79)4)2
- go 2 14 ft-Ib 12 . Torsional Ha.ent * "x
- I I 77 f~-lb
- 13. Operatinl preslure
- Po. ~o~ psi ~2:0 p ~ '2 ~ $0-0 :.10"'a'0 fS;
- 14. Allowable .oment . ' (11250 '\ ... ti' DI Pf) F~cJ12
* (II*UO",!. 2'-4f"I,.~St,l(500)'J(!1.:.!.f ... 21121'1.
t~ ~r"LJ I"fd{(11250 ~ ... ~) DI Pf > -& (~(kJ ' @ Po: Kaxi.u. operatiD, pre ** ure durin, faulted cODdition (pli) * ~ou p~ ; P: Delip pres.ure (pai) * '$"00 psi
'f: Faulted condition pressure concurrent with Kfd (pai) * ~ 00 r' ~
Mfd : The axia.. of 11 or 12
- g.2 14 r~. La,
'* Ablolute eo.bination of A and faulted dynl.ic
** Maxi. . . .,lu. of all dynaaic. lOld co.bin.tioDI for faulted condition
RSG-47876 -- .. r--~=-----r----___ -------------r---::;-:-:-::-:::-::---------. Page 63 of 3 l i A , CALCULATION CALC. NO** Rn'.
;a;e!i ENTERGY ENGINEERING DEPARTMENT RIVER BEND STATION AX-7IAG, .......
PAGE] I 011' FLANGE QUALIFICATlON tUll NO.
'UlJECr: QUAlIfICATION Of rtANGtD JOINTS (TASLE A)
...... 011: EMn-60S-0 MA-)l,oP-Nodt Point No. ~/S~/7 AS~ III Class 2 and 3 nANG!: TYPE: . V1E.t..btl" N£C.J::.. SIZE: 4 #
FlANGE MA1'!RIAl: ~A- -10'5 IOlTING KATERIAl: ~-lqS,G,R.~7 NO. 0' JOLTS: S ~ :3;;d.'7::>h4-. 5 a 2~~ pli ~20,OOO pli 0 5,
- e~ooo pli C
- 7 *8£3 ie.
a ~ . 4/~ iD.2
~
Df
- U> . I 9 in .
'. a S I 36000
- Y
- rI .C a /*68
;.0 IN .
~ 1.0 @
riC: 5: HiDim~ allow.bl. v.lu. of Itrlll for boltin, a.t.rial .t 100*' fro~ table 1-7.3, lub,.etion KA, ASHE III (psi) Iy: Yi.ld Itr.n,th of 11.n,. ..t.ri.l at tb. d'lilft tlmp.ratur. fro. t.bl. 1-2.2, J-7.1 lubslctioD ~A. ASME III (pli) C: Dia.. t.r of 'olt circl ** (ie.)
~: Tot.1 ~ro ** - ** etioDil .r.a of the bolta at the root of lb. thr ** dl. (in)!
nf : o OUtlide di *** tlr 01 rail.d f.cl 01 Il.D,*. (iD.) ACanAiU - UNACanAiLE
F<BG-4787o ** -'" - - ~.......,=----r-----------------r----;.-:-:-::-::::-==~---, Page 64 of 1 CALCULATION CALC. NO. - REV. ENTERGV ENGINEERING DEPARTMENT RIVER BEND STATION AX-7tAG. PAGE,20¥ Rev." FLANGE QUALIFICA nON LIli'E NO. R ~ S - 004 - 113 - 2 i-..J P : 4/'7/411 I
SUBJECT:
gUALITICATION or ruNG£D JOINTS (TABLE B)
....d CD: EMTR .. 60S .. 0 ( R.f.F4- z)
- e. Desian, Normal and Upset Conditions
.-1 De.dwei,ht and Thermal
~
LOADS "x (ft-Ib) tty (ft-Ib) Mz (ft-Ib) DEADW'E I CHT - 47 '5 2~
** - 9I 50 I?t; THERHAL STEADY STATE ** - -
TOTAL (A) * - j 3g 55 1~4
- 1. Bendin, moment s JeHy )2 + (Hz )2
- J( t;?)2 + (184)2. 1'12.' ft Ib
- 2. Torlional moment
- Mx ft Ib
- 3. Allowable .oment
- 3125. F "1'2 Ie 0 ~
-0 ft Ib Mfa.: The axaWl of 1 or 2. (9.2,* ft. \ \a
- Totll (A) 11 the .,xiau. of the (deadweiaht + It.a41 Itate) or (deadweiabt + the~l + Iteldy Itate) .laebrlic combiDation.
*" M.xiau. comr0l'l~n+S +ron'"> c:il/l Th~rl"Y)~J c."'J:.~~ il"lf'o.d-..
- ~B(9-47e16 Enclosure 2'-t"Pt~=-_ _- . - - - - - - -_ _ _ _ _ _ _ _ _ _--r_ _::-:--::-:-_ _ _ _ _-r Page 65 of CALCULATION CALC. NO. - REV. AX-71AG. Rev." EN11:ROV ENGINEERING DEPARTMENT RIVER BEND STATION PAGE $] or FLANGE QUAllFICATlON LINE NO. /:2 4-l c:. - ood - I I 3 - 2 415/417 I
SUBJECT:
QUALIFICATION OF FtANGED JOINTS (TABLE C) Jaud On: EMTR-605-0 ( ~f 1="41 Z)
.-2 Deadveilht. Thereat and Dynamic Load.
~LOADS
!1 x (ft-lb) My (ft"'lb) Hz (ft-lb)
TOTAL CA) - 13 S ;S Ig4 N+U_Dytl,mic ** ~U> 210 I C; ;J OBIA 7 -2 510 I 7 ::2 TOTAL (B)
- 2:e:1J~~ 3:2t SO '7
- 4. Bendin& Moment
- J(~y)2 + (H )2 z
- JC-~2. I )2 + ('O~)2 * &> Q 2 ft-lb S. Tor.ional .o.ent ."x . * ~4~ ft-lb
- 6. Allowable moment
- 6250 FIC ~
12
* ~.
1'1
\7. s, X IS.t' .,395"5 ft-lb
- Absolut. c,OIIb1nation of A. N+U dyna.1~ and OBIA
** }faxtau. value of all dynamic load co.binationl for normal and Up.,t condition (i .*. , ORE. SRV. Fluid Transient ** tc)
--rtBG!47876 Enclosure 2 page66cl1~~~~~~~~~~-C~~-L~C-~-~~-T-I-~-~~~~~~~-C=~~~"N-O-.--~~"~~ ENTERGY ENGINEERING DEPARTMENT RIVER BEND STATION AX-71AG, ~"4 PAGE5~OF FLANGE QUALIFICAnON tINE NO. 12 1-4 S - 004 - I 1:3 - 2 NP: 415/4/7 I 1
SUBJECT:
QUALIFICATION OF FLANGED JOINTS (TABLE D) Baud On: £MTR-60S-0 (~r:'~ 30)"
- b. Emerlency Condition b-l Dead~eilht. Thermal and Dynamic LOlds Moments
~
ocal Mx (ft-lb) My (ft-lb) Mz (ft-lb) LOADS TOTAL (A) I .3 s t; 5 Ig~. (o8~rJoc.a) EMERGENCY DYNAMIC ** '3 (, 210 I r; 3 TOTAL (e)
- 174 2~7 I 337 7" Bendina lIoment
- J(My }2 + (Hz)~
- J( 2t..'7)2 + (3.~~)a
- 429 ft-lb
- 8. Torsional HOllent
- Mx :II 174 ft-lb
- 9. Opentin, prellure - Po :II '50o~S; < l.~P :II 1.5)(500 .: 7S';' ,~;
Po: Haxillua operatina pre.lure durinl ..eraeney CODditioD (p.i)- soc f~j P: Desiln prellure (psi) * ,00 PS l PI: luraeney condition pUllure concurrent with Hfd (psi) * 'fot) FSt Hfd : The lIaxi_WI of 7 or. - I 7 4 fk ,.,
- Absolute combinatiOD of A aad emeraeney dyaa.ic .
** Maxi.us value of .11 dyal.ic 10ld combination. for **erleney condition
RBG ~47876*- . 'iM-_____=---.,------=-:-:--==::---------r--~~_:;::~==_::__-...., Page 67 of 1 '~ CALCULATION CALC. NO. - REV.
;e;ee
---EHTERGY ENGINEERING DEPARTMENT RIVER BEND STATION AX-71AG, Rev. 4 FLANGE QUALIFICA nON tINE HO. RH$-004.119.-2 ~p~ 415/417 I
SUBJECT:
QUALIFICATION or FLANGED JOINTS (TABLE £) laud Ora: EMTR-60S-0 ( RE. F". )
- c. Faulted ConditioD c-l Deldwei,ht. Thermll and Dynamic Loadl OCIl MOllents
~
LOADS Hx (ft-lb TOTAL (A) ( 3 ~ FAULTED DYNAMIC ** 174. TOTAL (D) * ( ~ 2. 3 8 r 42D
- 11. BendiDI.oment * /(Hy )2 + (H z)2
- I( ~lf)2 + (420)2
- S~7 ft-lb
- 12. Torsional HomeDt
- Hx 19:2. ft-lb
- 13. Operltina pres.ure
- Po. ~o~ psi
- 14. Allowable 1I0aent * (11250 ~ - ti) DJ Pt) F~c/12
* (II'tS 0 )C 15.2, - if" 1'.2S t J( 500) ".!ill ... 211212-
- 11. I:r.LJJ I"fdSO 1250 ~ - fi) D~ Pf) -& (~fkJ ' @
Po: Haxi~ operatina pressure durinl faulted condition (psi) * ~~ Pi ; P: DedlD prellure (pit) * 'S oc) psi P,: FaultecJ condition pre .. ure concurrent with Htd (psi) * '500 rs, Hfcl : The uxi. . of 11 or 12 * . S fs:, 7- r~- Lit
- Ab.olute co.binatioD of A and faulted dynaa1c
** Haxia~ v.lue of .11 dynaaic load combination. for faultecl condition
- RBG-4787o"* Enclosure 2 Page 68 of 131 CALCULATION CALC. NO. - REV.
---- ENGINEERING DEPARTMENT AX-7tAG, Rev. 4 ENTERGY RIVER BEND STATION PAGE ,"OF VENT & DRAIN QUAUFICATION:
The following Vents & Drains are qualified generically by Calculation PX-S8-316: Valve No: R/-iS*V1229 RHS*V112 and V113 RHS*V51 RHS&V52 ICS*VF084 & VF085 ICS*VF061 & VF062 ICS*VF073 ICS*VF074 The following Vents & Drains are qualified with tie-back support: Valve No: ICS*VF034 1E12"VF058A & VF059A RHS*V112 & V113
RBG-47876 Page 69 of 131 r-~~---r----------------------------II--~~~------~ CALCULATION CALC. NO. - REV. ENTERGY ENGINEERING DEPARTMENT RIVER BEND STATION AX-71AG, Rev. 4 PAGE S70F SLEEVE CLEARANCES Piping displacements due to reanalysis of Rev. 4 have not changed significantly; either they have decreased at certain locations or Increased Insignificantly at some locations. The thermal load cases and Seismic Anchor Movement load case movements are not altered. and this analysis has used N411 damping values, which reduces the dynamic displacements. The onglnal values from previous revisions are still applicable.
-' RBG-47876 Encrosure ~ . STONE e. WI::BSTER ENGINE E RING CORPORA TlO N Page! 70 of 1'31 CALCUL.ATION SHEET
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CALCULATION IDENTIFICATION NUMBER c;A
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** 0'" 'i!~ N'"." P...... I TO e.a C/)M~"ltaD ~'nf --'IB~~"~£ e.L.A~c.s *
- A -- - - - - --- - ---- -. -- -------------
== RBG-47876 Enclosure 2 Page 71 of" p1 Sf ONE & WEBSTER ENGINEEkINC; COR"OR~flON CALCULATION SHEET a" CALCULATION IDENTIFICATION NlJMBE.R S~
- .1 .0 . OR W. O. NO.
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. RBG-47876 Enclosure. 2 0# . STONE ~ WEBSTER (NGINE£RING CORPORATION t' Page 12 of 131' CAl.CUl.ATION SHEET I CALCULATION IOENTI'ICATlON NUMa£1t ~O
., J. O. OR W.O. NO, WJ,ISION "'jGROUP CALCUl.ATION NO, 10PT'ONAL TASK CODE PAGE_
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!)8El IZ i! i .011 i
.011
" 'SS6Z I 11 '( ~ .021
+/- .ou.
-t .dD I'
It c l' .021 J).Y##1II11!. It Y ;t '0 "
~
t:14 (J, CI
'0 JO 20 ~ :t *0 It *otV n
D.::INA-U/G
<!JUg 2\
y :t.a,e.
.... '01'
~ i-ol9 -t
-0 { '
u ilY1JA#f14 'Y ;t .ot4 'ot ,. 14 CX:Cp 27 1! +/- .OlS - '"-" ,o2S I"'" U S. +
!rOT"" UL"TI1I6 I. - C!'u.u / ()eGJ) -
flYIJAIA/~
= DWT% 9U)G" t 09[1-I.
11 ~O"'M~ur$. !J.~'t.:r ~'TTU;MIIlt U DR. ::/ Ow, 1 'IlleR 1. "rt\(IACWT 81.0", + ~~-- + D:lNI.IA,Ie..
.0
- - , (OGGP)
.,** NOTe'!'t J.
* /NSI(,AJIF'"ANT (~Et P.f?
TH£ ~tQ.N D,. 'rHt 'lOTAL (&'t\TI~ ....ov(MeWTtt U.W.T er -rM-& .1~1f 0' T"," "'-'J""'\6M eo".,NAr,"'" 0 .. DW1.,.) 'tM£ftM .... AtJO SLD.,
., CO~ TrL' Me", T.
- 2. ~H(' M4'( 1..1JN OF "e.'T"~a. f! "cJ~T~ ~~ __ N ~"1 ,~
fl.6'ccueo tJU ?M. HCllT' PtA"r 't'O 68 c.oMPI'ltaD wIn. 11IC ~y£ ~L.M~e.a *
*6
-"RBG-47876 Enclosure 2 Page 73 of 1~ STONE & WEISTER tN(;INE£ HINri C(JRt-ORA riOH
~
CALCULATION SHEET 10" CALCULATION IDEN1IF'ICATIONNUM8ER &>1
-' .1.0 . OR W.O. NO. CALCULATION NO. OPTIONAL TASK COOf 12210 X- 71 A~.R.~* t-J/Ja
- AX ~ J.lO" 'BET"'(f'" '" OC~ .... 0. Ito" I" 1 1
!::>LEEVE CLEA~A.~c,e LOO~l~(O ~02.r"
!rOTA \.. JlC ~,,""
4
'M()'I~ '" et,&,TS.
*, = 'l.9'l75" )
z.. 2'"
- 'Z 1:: ..; * 'So f." =- A* A'J7~" '> ...,.
- l'5 ,
* ,j:z .of,,' = <4.1175" ,. .... '0'7
* -~ = 3~ == 1 . 1?S") .o6~
.0 t) .':. S"L~EV~ c .LeAi.AN(.eS 14 A ~ A (,(. E P 1'A S\."
'S
.1 n
0, 10 IS := 14
\
l .~ II
.I."
11' N/A
'0
, I n
H U Sl II S9 40 41 44 4S 41
RBG-47876 Enclosure 2 STONE
- weSTER eNGINEERING CORPORA nON Page 74 of 131 CALClLATION SI-EET
~~
JO. OR we. NO. DIVI&ON
- GROUP CALCULATION NO. OPTIONAL TASK cooe PAGE_
12210 IfP(C) AX- 7' AG( 2ev.4 REF. SLEEVE CLEARANCE EVALUATION NOce .5 NUPIPE Output MUPIPE Input Lo.d c. ** ca.e Pip. O.flection Pen.trat10n Sum of Relativ. D.scription )(0. Mov.ment Mov.ments x .005 -005 Dudw.iaht 81 ~ -.0/2 -.0 / 2..
)C: -.00,2 0 -.00:3 Thermal (N+U)
')< -.007 0 -.007 Thermal (Max.) 2& .c -.013 0 -.0/3 Thermal (Min.)
aulldin9 Settl...nt 1 Buildin9 Settlement 2 OBn 87
.02Lo
.009 ,00'1 OBE1 40 .0£4
.0/7 .0/7 SSEI 4/
.07'2 OVnamic OCCU 45 - ./-zG,
.074- - .074-55 ./~ * /'ZG
.075 .07'5 nvnamfc OCCP . / '3/
Total Relative Movement. *I + DW'l' -
+ 8uildin9 The. - Settlement I +
- OBEA -
+ 1)yanIa1c (OCCU/oca)
*I Or Wf -
+ + Bui1din9 The. - Settl..-nt I +
- SSIA -
+ 1)yanIa1c (occr)
Not ** I 1. Th**iCJn of the total relative movements .u.t be the I1CJn of the 1lUa... c:aab1natJ.on of Oudwa19ht, Thermal and Building S.ttl..ant.
- 2. The ... t.J- of either equation .hown above 11 recorded.
on the nut page to be compared. with the 11HYe clearance.
't-:: /.~5 -.001 ~O/~ .oZy~ .075 ~ .105" J; -: /-.01'2. -.0'3 ~ol" .024 ~ ./31 ~ .180"
- RBG-47876 Enclosure 2 STONE
- WESSTER ENGINEERING CORPORATION Page 75 of 131 CALCULATION SH:ET CALCIAA TION 100NTIFICATION NUMBER (,3 JOo OR WOo NO. DIVISION
- GROUP CAlCUlATlnN NO. OPTIONAl. TASK COOl PAG!_
12210 HP(C) AX- 7' A<i;f rzeY.4 REP, SLEEVE CLEARANCE EVALUATIOK i Sleeve Clearance Lookini Korth I y Total Relative Movcentl
-z * * -
z -z z y * * -
-y
-y Sheve Clearance Lookini Ea.t y
-x * * -
* -x y * * -
-y * * -
-y Sleeve Clearance Looking Up racini Korth NOPe 5 x
N1(A/, I,
-z I'IZ * /,5 " .180 Ire." ,leo*
* /.S"-
.. 01<,
z e3;8' z -z x
- * ~a75- ,/o5~
-x
- 2~~" -'2,375-" , /05 "
Conclusion z ... of<
- RB'G-47876 Enclosure 2 Page 76 of 131 STONE
- WEBSTER eNCiINEERING CORPORATION CALcu.ATION SI-&T CA£.CULATION ICENTlflCATlON ~ER J(). OR We. NO. DIVISION. GROUP CAlCUlATION NO. OPTIONAl. TASK COO!
12210 JfP(C) AX- 7' ~ 12eI.~ REF. SLEEVE CLEAlWIC!! EVALUATION NOC 71 WPIPI Output IWPIP! Input Load ea.e ca.e Pi~ OeUection Penetration Sum of Relative Cescription Mo. Oir. MoVement Mov_ent Movements o Deadweight o Thermal (H+U) o .76.7 Thermal (Mu.) Thermal (Min.) - .ooz. Buildin9 Settlement 1 Buildinq Settlement 2
.008 oaEA .~
. (joEi
. COS OBEI 40 . 005 .c~
.00<0 SSEI 41 .010 .010
, 058 .o~8 Dvnalllic accu 45 ./OE ./~
.86 *IO~ .108
.o:s!!:J DvnaDlic acc, ./0 .IQ'1 Total RelatiVe Movement.
Or
- I +
tINT -
+ Build1n9
'l'her. - Settl.-.nt I +
- oln -
+ Dyanmic (OCCU/OCCI)
- I DWf -
+ + Buildin9 Ther. - Sett1-.nt I +
- SSD -
+ nyan.1c (occr)
Mote': 1. The sign of the total relative 1DOV8IINantJ IlUlt be the lign of the . . . S*
- ccabin&tion of Deac1wai'iht, Theral and lul1tllnV Settl8Mllt.
- 2. The axial. of either equation .hown above i . recorded on the nut ,PAve to be compared with the Il.."e clearance.
"Jt.=/ a ~ .7(07.;0 .01<1/ + .OItJ, .;. .05~ * * &0"
~ = /-.OOZ<l-.'Zo7-.00/ /.;.. oC(3 + ./0'9 = .3'2/'"
RBG-47876 Page 77 of 131 STOM: , WEBSTER ENGiNEeRING COAPORATlON CALcu.ATION SI-EET CAl.CULATION IOeN11FICATlON NUMBeR JO. OR WOo NO. ClVISION. GROll' CAlCULATION NO. OPTIONAL TASK CODE 12210 WP(C) AX- 7 ( AGf lUV.4. FIEF, SLEEVE CL!ARANCE EVALUATIOH Sle.ve Clearance Looking North y Total aelative Mov_entl
-z * * - i z * * -
z -z y * *
-y - * -
-y Sle.ve Clearance Looking !&It y
-x *
- x *
- x -x y * *
-y *
- Sleeve Clearance Looking Up Facing North NODe 7/
,4/111, ~ ~1tGIf
- z:, I RfJQ1tJA/.
-z * ~~Ie" * ~.S7.S-" .av
- z
- 2~i "
*2 , ~75- " 3'2./ t z -z x
- I"l/i * /,B7~: .8G;O"
-x * /76" * /1875: *86,0" conclulion I
** DI<
RBG-47876 STCN;
- WEBSTER ENGINEERING CORPORAnON Page 78 of 131 CALCLl.ATION SteT CALCULAnON 100NTIFtCAnON NUMBER !.J;v JO. OR 12210 wo. NO. DMSION
- GROUP nee)
CA1.ClJLATION NO. AX-r I Ac::, ~.4-OPTIONAL TASK. COOE PAGE REF. SLEEVE CLEARANCE EVALUATION NODe Joe> HOPIPI Output HUPIPI Input Lo.! Ca.e Ca.e Pipe Deflection Penetration SwIl of Relative Description No. Dir. Movement Movement MOvement. y - .014- -.014 Deadweiqht E/ ~ .~ - -,Cb~ eo y *C>S4 0 .a£4. Thermal (N+U) . t .003 0 .003 y . //8 0 ./18 Thermal (Max.) '2~ i! .~~ 0 .~~ y .Ol? 0 .015 Thermal {Min.} ~3 1!- .002 0 ,ooz. Building I'l-c~ y .CJ04. c .00.1-Setthment 1 Z Ift.N i!: .0 0 0 Building z,.~ Y -.'Z72 -.2.70 -.aoz. Settlement 2 ;Z Rl/N e- O C 0 y ./9S. ./81 .0/4-08EA 87 i: .BI4- .e/~ .00/ y .028 SSEA _(2-08£.\) C .0<)'2.. Y .004. .0a4 40 - OBEl i!- .007 .007 Y 4-1
.Cl08
.008 SSEI -a .013 .0/3 y
- c:ASo .O~O oceo 4.15 -c .075 OVnamic . 67.5 y .050 Dynamic gS -Co
.o~
*075 .075 OCCI
'I .05/
8CD
.~~/
f'IuTI.",IC 0CC1' i!:
- 07~ . o7~
Total Relative Mov.mentl Or
- I DWr -
+ + Building Ther. - Settlement I +
- OBO -
+ Dyanmic (OCCU/OCCI)
- I +
DN"%' -
+ Building Ther. - Settlement I +
- SSIA -
+ DyanlDJ.c coca)
NotelJ 1. The lign of the total relative mov-.nt. IIlUlt be the lign of the . . .t.wa combination of Deadweight, Ther.al and Building Settl-.nt.
- 2. The mu1a.lJl of either equation shown above il recorded on the nut PAge to be cOIIIpU'ed wi tb the Ileeve clearance.
~
I.f =/-.C>l4 +-.//8 +.004/+ .0'2.8 + .o~/ = ./87 i5 .=. /~ oo~ ~ .oo~ of- 0/+ . ooz. +- .07G, . . . 071 II
RBG-47876 Page 79 of 131 STONE
- weBSTER ENGINEERING CORPORATION CAlClLATION SH:ET CAl.CULA TION toeNTFICAnON NUMBER
- ~7 JO, OR WOo NO. DIVISION
- GROUP CA1.CUI.AnON NO. OPTIONAL TASK COOl PAQI-12210 IfP(C) AX- 71 A~ ~.4 REF.
SLEEVE CLEARANCE EVALUA~IOK Sleeve Clearance Looking Korth NODE. /CX) y Total Relative MIN. Movement.
-z * /~6' ./.tI,2S "-
- CJ7~4' !
Z
- 1~8' * ;'~t'5:' .079*
z -z 01< y * / I~~' *;'8/~ "- - lei'
-y * / 1?f~1
* /*8/~*'- . 187"
-y Sleeve Clearance Lookinv Ealt y
-x * * -
x -x x * * - y * * -
-y * * -
-y Sleeve Clearance Look1ng Up Pacinv Korth x
-z * * -
z * * - z -z x *
- COnclusion :
- 01::-
RBG-47876 STOM!
- WEBSTER ENGINEeRING COAPOAA TION Page 80 of 131 CALCLLATION SI-EET CALCULATION 100001FlCATlON NUMBER J().
12210 OR woo No. DMSION
- GROUP DeC)
CAlCULATION NO. U-7t AGt 2RI.4 OPTI()NAL. TASK COCE PAGE REF. SLEEVE CLEARANCE EVALUATIOK NUPIPE Output WPIPE Input Load CA ** CA ** PiP41 Det lect10n Pen.tration Sua ot Relative O.scription No. Oir. Movemant MoVement Movement. Oea4w.ioht
~/
')<.
Y
.0/0
.0::31
- .010
.078
-,03/
Thermal (N+U)
. '2/'2.
Thermal (Mu.) .~ Thermal (Min.) Buildin9 Settlement 1 Building Settlement 2 o
~COI OBEA 81
,ozo .czo OBE1 40 .o~z
.0..33 . o~
SSEI 41 y
.II'Z .IIZ rhrn.mf C OCCU* y * -2/(,
- ./1'2, rhrn* ... c cx:::c:E y
./15 -
- lIS Dynamic OCCP y * '212.'1 Total R.lativ.
MOvement. *I DWr -
+ + Build1n9 Ther. - Settlement I +
- OHA -
+ Dyanm1c
{OCCU/OCC!}
*I +
DWl' -
+ Bu1ldin9 Ther. - S.ttlement I +
- SSu. -
+ Dyanmic (OCCJ')
)lot.,: 1. Th* *1911 of the total ~.lativ. lIOV..ant. IlUlt be the 1191\
of the . . .1IIuII cOllbination of DMdwe19ht, Theral and aUildin9 Settl.-.nt.
- 2. '!'h. lllUialJI ot either equation lhown above il recorded on the nut P&9. to be caapared. with the Ileev. clearanc**
1+ .002 f'
~;. / .alO +.21'2. +- 0 r.llo *
- QP/1 Y J:. / -. 031 +-,082>"" oj + .oo"Z. +.'Z'Z1 =' * '2~"
RBG-47876 STONE. WEBSTER ENGINEERING CORPORATION Page 81 of 131 CALCULATION SHEET CAL.Cll.ATION lCENTIFlCA TlON NUMBER JO. OR WOo NO. OIVISION
- GROUP CALCUl.ATION NO. OPTIONAL TASK COOE 12210 HP(C) AX-7 (AGr ~.4 REF.
SLEEVE CLEARANCE EVALUATION Sleeve Clearance Looking North y Total Relative Movement I
-z *
- z *
- z -z y * *
-y * *
-y Sleeve Clearance Looking Ealt /<h{;). 295 y
MIA/,
-x
- 3U(." .3 I,
- 3391(
- IZS-X
- B~* * .3 . 'Z~ :' . 3'3'1' x -x y * :3" * .$,0 " - . '288"
-y
- a" * ~ . D" - .'268"
-y Sleeve Clearance Looking Up Pacing North
-z *
- z *
- z -z x * *
-x * *
-a Conclulion I
- =RBG=478 Enclosure 2 Page 82 of 131 e--- EtflCRGY CALCULATION ENGINEERING DEPARTMENT RIVER BEND STATION CALC. NO. - REV. ADDENDUM AX-71AG, Rev. ATTACHMENT NO.: PAGE 70 OF CALCULATION CHECKLIST N/A EDP-AA-20 YES NO FORMAT SECTION x Cover Page completed. 6.4.1 x Table of Contents completed (as required). 6.4.2 x Revision History Sheet completed (as required). 6.4.3 x Revisions are identified with revision lines in right margin. 6.4.3 x Applicable Documents Page completed. 6.4.4 x Definitions established (as required). 6.4.5 x Calcu1ation!revision/addendumlpage numbers are identified correctly. 6.4.10 CONTENTS x Previous calculation for the required analysis exists. 6.3 x Calculation is appropriately titled for the intended scope. 6.4.1*2 x Purpose and scope are clearly and adequately established. 6.4.1-7,7.1 x Safety classification is correct for the identified sc::ope. 6.4.1-6 x Topics/documents/equipment for cross-reference/retrieval are identified. 6.4.1-11 x Calculation is clear and comprehensible. 6.1 x Applicable codes, standards, etc. are idc:ntified. 6.4A-l x RBS references are idc:ntified 6.4.4-2 x Affected documents are identified 6.4.4-3 x inputs and sources are identified, appropriate, and correct. 7.2.2-1 x Assumptions are identified and appropriate. 7.2.2-2 x [nputs derived from field walkdown have been witnessedlverified 7.2.2-5 x Engineeringjudgments are identified and appropriate. 7.2.2-6 x Calculation methodology is identified and supported by technical bases. 7.2.3 x Conclusion is appropriate and is justified by calculation. 7.3 x Confirmations are identified and indicated as required on Cover Page. 7.5.7 x Directions for Confinnations are included. 7.5.7-3 x Calculation data is appropriately included, attached, or referenced. 7.4 x Programs and software are identified and have been verified and validated. 8.0 x Methods/calculations use to check results are identified and included. x Results are accurate and in accordance with the established methodology. x Certification by Professional Engineer is required. 11.7 VENDOR CALCULATIONS x Calculation is perfonned in accordance with EDP-AA-2S. 10.2 x Calculation content and format are acceptable. 10.2 x Vendor, prepan:r, reviewer, and approver are clearly identified. 10.3 x Design verification review has been completed (as applicable).
~/I~ / '77 Preparer (Signature/KCN or SSNlDate): (~~ ..I... _
, - -"7T
' .~ ~~J)
~~(H05)
Reviewer (Signature/KCN or SSNlDate): 6/18/97
RBG-47876 Page 83 of 131 CALCULATION CALC. NO. - REV. A nn~NDUM AX-71AG~ Rev. B ENGINEERING DEPARTMENT ATTACUMENTNO:': ENTERGY RIVER BEND STATION PAGE iT OF REVIEWER'S CHECKLIST ( .~.tn Item Calc - ~ Page C'nm-mt'ntl: nUVlu.~By ('j .ResolVedBY R,
- t,~~ (~W5) 6/18/97 Revie?ler KeN Date -KCN Date R~"';;w<a KCN -Date
* "Y'
~BG-47S76 e--- Page 84 of 131 CALC. NO. - REV. ADDENDUM CALCULATION AX-7IAG, Rev. 4 _-.-.-'w ENGINEERING DEPARTMENT ATfACHMENTNO.: ENTERGY RIVER BEND STATION PAGE 72.0F Design Verification Record Document No. AX-7lAG, Rev. 4 METHOD Verification methods to be used: X Design Review Qualification Testing Alternate Calculations DOCUMENT(S) REVIEWED: (Attach Additional Sheet(s), if needed) Document No. Revision Doc:ument Title
~~
AX*7lAG 4
~71-.-1~ 9'-'-00 ~ .
SUMMARY
OF REVIEW: (Attach Additional Sheet(s), ifneeded) Acceptable as is. Design Verification Completed By ~~ (.1105) Date vjlg/97 Co~RcsolutionA_ted Q Date Engineering Supervisor ~l )1) Cj)V, Date 11~2.()-17
RBG-47876 Page 85 of 131 ( CALC. NO. - REV. ADDENDUM CALCULATION COVER PAGE AX-71AG, Rev.4A
=-----
==~ ENGINEERING DEPARTl\'1ENT ATTACHMENT NO.: (as required)
-- JBI NO.: G13 .10.2.2 ENTERGY RIVER BEND STATION PAGE 1 OF 6
Title:
Pipe Stress Analysis For ICS FWlction Added Through FWS System Per rvtR96-0069 CALCULATION o APPROVED
- PENDING ON IMPLEMENT ATlO OF MR 96-0069 o CANCELED STAT liS:
I o PENDING O N COl\']iIRl\<L\TIONS SYSTEM NO.: lO7fFWS MA..RKNO.: R~S-OIO'Ob5'-2 CLASSIFICATION:
- SAFETY RELATED NON-8AFETY RELATED: OQAPA D NON-QAPA PURPOSE I SCOPE I OBJECTIVE:
To qualify the welding tee due to a reduction in the wall thickness which was required for final fit up during construction. CONCLUSION: The piping remains within the code allowables. SOFTWARE USED FOR CALCULATION: DYES .NO SDDF#: Manufacturer: Name VersionlRclease No. KEYWORDS: Licensing/Design Basis Impact
- Addressed in DCA No. rvtR 96-0069 FWS,ICS D Licensing/Design Basis Impact Checklist included o None - Reason:
REVIEW & APPROVAL t~~ VA 4-15-Q' ~~ 6:c.!u. s.13/tt~ f1t<J,<;~t/i l n-t1 Brian Lanka, KCN 1311 (SignatureIDate) ( ignature/Date) Preparer C1 Reviewer (Non-Safety) Supervisor gj Design Verification Reviewer (printed Name, KeN, or SSN) (Printed Name, KeN, or SSN) RAJ£'Sk GVP'l7\ I (os<1 RECE\VED MAY 041999 SA Tie
RBG-47876 Page 86 of 131
=-----
==~
ENTERGY CALCULATION ENGINEERING DEPARTlVlENT RIVER BEND STATION CALC. NO. - REV. ADDENDUM AX-71AG, Rev.4A ATTACHMENT NO.: (as required) JBI NO.: GI3 .10.2.2 PAGE 2 REVISION HISTORY Revision Paragraph Description of Change No. No. 4A To qualify the welding tee due to a reduction in the wall thickness during frnal fit up during construction.
RBG-47876 Page 87 of 131
-ENTERGY CALCULATION ENGINEERING DEPARTME'N T RIVER BEND STATION CALC. NO.-REV.ADDENDUM AX-71AG, Rey. 4A ATTACHMENT NO.: (as required)
JBI NO.: Gl3 .10.2.2 PAGE 3 REFERENCE DOCUMENTATION L Control Document Cross References (Page four of NORMS) : Other Calculations, Procedures, Drawings, etc. Identify how documents are affected. EFFECT (Check One) DOC. NO.(Control Xrefs) REV. NO. TYPE Supplemented Superseded Voided Reference Only
- 1. AX-71AG 4- CALCSW X ll. Record Cross References (page five of NOIU.ttS): RBS change documents, ERs, :MRs, Calculation Addenda, etc. Identify how documents are affected.
EFFECT (Check One) RECORD NO. CRee Xref) REV NO TYPE Supplemented Supaseded Voided Reference Only
- 1. MR.96-0069 0 :MR X
- m. Miscellaneous References (Misc Ref): Applicable codes, standards, & references (non-RBS):
- l. ASME B &PV Code, 1974 Edition.
- 2. NAVCO Piping Datalog, lOUl Edition.
RBG-47876 Page 88 of 131
===~
ENTERGY CALCULATION \VORK SHEET ENGINEERING DEPARTMENT RIVER BEND STATION CALC. NO. - REV. ADDENDUM AX-71AG, Re\,. 4A A'ITACHMENT NO.: (as required) JBI NO.: G13,10.2 .2 PAGE 4 Calculation: During installation of the 10" welding tee (sch 160) at node point X98, the ends had to be machined to schedule 120 to allow proper fit up to pipe line RHS-OI0-065-2 (Sch 120). This tee was modeled and designed as a sch. 160 tee. The ME I 0 1 analysis (Ref. 1.1) considered the tee to be schedule 160. For the tee to be welded to the pipe, the ends had to be machined to sch 120. This calculation will qualify the tee stress as if it was schedule 120, which is conservative. Since only the thickness of the end of the tee is reduced, the change in weight will be negligible. Design Input: Properties are per Ref. II1.2. Pipe Size Schedule TIrickness r - mean radius 10" 120 0.843" 4.9535" 10" 160 1.125" 4.8125" PiI!e Stress The reduction in wall thickness affects mechanical stress and pressure stress. Pressure stress is calculated by P D I 4 t and mechanical stress is calculated by i M I z By. changing the thickness from 1.125" to 0.843" the pressure stress will increase 1.125 10.843 or 33%. The mechanical stress is calculated by i M I Z. Per NC-3652.4, Z ::: 1t r t. Where r is the mean radius. Thus Z 120 = 1t (4.9535)2 (0.843) "" 65.0 in) Z 160 =1t (4.8125)2 (1.125) = 81.9 in) Thus, the section modulus will change by 81.9 165 or 26%. The change in thickness will also affect the SIF for a welding tee. Per Ref. ill.l , SIF == 0.9! (4.4 t/r}667 Thus SIF 120 =0.9 I (4.4'" 0.S43 14.9535)*667 == 1.09 SIF 160 =0.9 I (4.4 ... 1.125/4.8125) 667 = 0.88 = 1.00 Since the SIF can not be less than 1.00. Thus the mechanical stress will increase by 1.09 ... 1.26 = 1.37. This value envelops the pressure stress term and will conservatively be used to increase the equation stresses. Existing stresses per Ref. 1.1. Equation Node Existing Stress New Stress (1.37 ... Allowable Margin (Psi) Existing Stress) Equation 8 X99-X97 4209 5766 15000 0.39 Equation 9B X99-X97 6185 8473 18000 D.lf7 Equation 9C X99-X97 6196 8489 27000 0*.31 Equation 9D X99-X97 6241 8550 36000 0.24 Equation 10 X99-X97 5269 7219 22500 0.32 High Energy Not Applicable per Ref. 1.1 Eq 9B + 10
- . Pipe stresses are within their allowables.
RBG-47876 Page 89 of 131
- !!!=
ENTERGY CALCULATION ENGINEERING DEPARTMENT RIVER BEND STATION CALC. NO. - REV. ADDENDUM AX-71AG, Re\'. 4A ATIACHMENT NO.: (as required) JBI NO.: G13 .10.2.2 PAGE 5 CALCULATION CHECKLIST EDP-AA-20 YES NO N/A FORMAT SECTION X Cover Page completed. 6.4.1 X Table of Contents completed (as required). 6A .2 X Revision History Sheet completed (as required). 6.4.3 X Revisions are identified with revision lines in right margin. 6.4.3 X Applicable Documents Page completed. 6.4.4 X DefInitions established (as required). 6.4.5 X Calculationlrevision/addendum/page numbers are identified correctly. 6.4. 10 CONTENTS X Previous calculation for the required analysis exists. 6.3 X Calculation is appropriately titled for the intended scope. 6.4 .1-2 X Purpose and scope are clearly and adequately established. 6.4.1-7, 7.1 X Safety classification is correct for the identified scope. 6.4.1-6 X Topics/documents/equipment for cross-reference/retrieval are identified. 6.4.1-11 X Calculation is clear and comprehensible. 6.1 X Applicable codes, standards, etc. are identified. 6.4.4-1 X RES references are identified. 604 .4-2 X Affected documents are identifIed , 6.4.4-3 X Inputs and sources are identified, appropriate, and correcL 7.2.2-1 X Assumptions are identified and appropriate. 7.2.2-2 X Inputs derived from field walkdown have been witnessedlverified 7.2.2-5 X Engineering judgments are identified and appropriate. 7.2.2-6 X Calculation methodology is identified and supported by technical bases. 7.2.3 X Conclusion is appropriate and is justified by calculation. 7.3 X Confirmations are identified and indicated as required on Cover Page. 7.5.7 X Directions for Confmnations are included. 7.5.7-3 X Calculation data is appropriately included, attached, or referenced. 7.4 X Programs and software are identified and have been verified and validated. 8.0 X Methods/calculations use to check results are identified and included. X Results are accurate and in accordance with the established methodology. X Certification by Professional Engineer is required. 11.7 VENDOR CALCULATIONS X Calculation is perfonned in accordance with EDP-AA-20. 10 .2 X Calculation content and format are acceptable. 10.2 X Vendor, preparer, reviewer, and approver are clearly identified. 10.2 Design verification review!l~heen completed (as applicable). Iii.. - -1A X Preparer (SignaturelKCN or SSNIDate): " -1)-'1 9 //3/1\ Reviewer (SignaturelKCN or SSNIDate): r;:-~ ~ ~df1 J_ ~~A'1 I... (qr69 )
RBG-47876 Page 90 of 131 (
~
CALC. NO. - REV. ADDENDUM CALCULATION AX-71AG, Rev. ~A
;, -= --
ENGINEERING DEPARTMENT ATTACHMENT NO.: (as required) JBINO.: G13 .10.2.2 ENTERGY RIVER BEND -STATION PAGE 6 Design Verification Record Document No. AX-71AG, Rel'. "A METHOD Verification methods to be used: X Design Review Qua1ificatioo Testing Alternate Calculations DOCUMENT(S) REVIEWED: (Attach Additional Sheet(s), ifneeded) Document No. Revision Document Title AX-71AG. 4A
SUMMARY
OF REVIEW: (Attach Additional Sheet(s), if needed) Acceptable as is. Design Verification Completed By ~ c..~ CoQ{5.) Date ~/3/f1, Comments Resolution Accepted By Date Engineering Supervisor fk,)~ Go;£R / 5-3-11 /kw 1054 r- {- Date S-3~~J
~! £~TERGY Record Revision Notice IJ X - 7/
UiqrJ}'Yp Department DE Document No. Page I of2 6.n-04i1 1{sqr-of}!., 6 (ASG IB[XNo.
. . J'J~1 Revlsloru te rJ FileNet Location Batch/Transmittal - Item No.
Revision Description Change the status of the calculation from Pending to Approved. Reason For Revision MR96-0069 was implemented during RF-OS. RECEIVED JUN 2 3 1999 BATIC Approvals: Originato Section Supervisor Date 6;£,z;ff
RBG-47876 Page 92 of 131 (
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ENTERGY CALCULATION COVER PAGE ENGINEERING DEPARTMENT RIVER BEND STATION CALC. NO. - REV. ADDENDUM AX-71AG, Rev.4A ATTACHMENT NO.: (as required) JBI NO.: 013.10.2.2 PAGE I OF 6
Title:
Pipe Stress Analysis For leS Function Added Through FWS System Per ~1R.96-o069
'\.
CALCULATIO~)~~ STATUS:
- PEi'iBHI6 e~1 JMP!.El'ttENTATION OF MR 96-0069 tq'APPROVED a PENDING ON CONFIRMATIONS QCANCELED SYSTEM NO.: lO7IFWS , MA.RKNO.: Rl45 -01() ,0"5"-2 CLASSIFICATION:
- SAFETY RELATED NON-5AFETY RELATED: ClQAPA Q NON-QAPA PURPOSE / SCOPE I OBJECTIVE:
To qualify the welding tee due to a reduction in the wall thickness which was required for final fit up during construction. CONCLUSION: The piping remains 'within the code allowables. SOFfWARE USED FOR CALCULATION: aYES .NO SDDF#: Manufacturer: Name VersioD/Rdease No. KEYWORDS: Liceasing/Design Basis Impact
- Addressed in DCA No. MR.96"{)069 FWS~ICS Cl LicensingfDesign Basis Impact Cbecldist included a None - keasoo:
Ij;~VA REVIEW & APPROVAL
't-I 5-9 , ~I~c;;,~,
Brian Lanka, KCN 1311 (SignatureJDate) 5h/r..f ~'Jh~ LS*3-'J'j ( ignaturelDate) Preparer a R~iewer (Non-Safety) Supervisor m Design Verification Reviewer (Printed Name. KeN, or SSN) (Printed Name, KCN. or SSN) RAJ£5k GuPTA I (oSOJ RECEiVEO RECEIVED MAY 041999 JUN 2 3 1999 . SA TIC
RBG-47876 Page 93 r.f 1 ':l.1 CALC.NO.~ CALCULATION COVER PAGE AX-76A Rev.3E
'.'!tQ:~ ENGINEERING DEPARTMENT ATTACHMENT NO.:
~----
ENTERGY RIVER BEND STATION . JBI NO.: G13.10.2.2 PAGE 1 OF' ~ TITLE: SUPERSEDES: N/A '
~ """ '" ~
St~ess Analysis for ICS Piping in the Reactor Building per MR 96~0069 ._
- ___ * * *
- 0 ..... ... . .... . . . '. ................. .'! ***.* o ...... . . ; .
SUPPLEMENTS: AX~76A Rev. 3 CALCULATION STATUS: D APPROVED
- PENDING DCANCELED SYSTEM NO.: 209 , lMARKNO.:
CLASsmICATION:
- SAFETY RELATED I NON~SAFETY RELATED: D QAPA DNON-QAPA I
P~OSE I SCOPE IOBJECfIVE: To document the cbanges implemented by MR 96-0069. This MR re:.routes the RCIC injection from the reactor vessel head to the feedwater nozzle. As a result of this changes, line.ICS-006-6~1 is removed and ICS-006-S7-1 is downgraded to ASME class 2 and abandoned in plac,e. CONCLUSION: The changes implemented by MR 96-0069 are acceptable. The removal of line ICS-006-6-1 reduces the loads on the RPV head nozzle and the Drywell Bellows Penetration DRB*Z130. Likewise, the abandonment of ICS-006~S7-2 gre~tly reduces the stress acting on the piping and the support loads acting on penetration DRB*Z130, penetration KJB*Z19, and pipe supports. Therefore, the piping systems analyzed by thjs calculation remain within the allowables of the ASME Section ill Code. SOFTWARE USED FOR CALCULATION: D YES D NO SDDF#: N/A Manufacturer: , Name Version!Release No. CONFIRMATIONS REQUIRED: DYES .NO Iq>NFIRMATION COMPLETE: D YES ONO DN/A KEYwORDS: ICS, ~ 96-0069, RCIC I REVIEW & APPROV~ /'""'\
~ ~ '-1("-91 \ ~"' .-... ~'~h~
~ 'CI [, ~7 k{[~>hQuJ)4.-' II-I"-~n fl>
(SignaturelDate) "", P.~Signature7Date) I I ~aturelDate) Preparer D viewer (Non-Safety) Supervisor Camilo Cuadra, KCN 0969 ~esign Verification Reviewer (Printed ~ame, KeN, or SS1'9 (Printed Name, KCN, or SSN)
, f2AJ&>H ,GvPTA I loSj
RBG-47876 Page 94 of 131 CALCULATION CALC.NO.-REV.ADDEND~
=-----
-==-
AX-76A Rev.3E
~- ENGINEERING DEPARTMENT ATIACHMENT NO.:
ENTERGY RIVER BEND STATION JBIND,' PAGE 2 OF Pipe Stress Analysis for (CS in the Reactor Building per MR 96-0069 TABLE OF CONTENTS SECTION DESCRIPTION PAGE NO. N/A REVISION mSTORY 3 N/A APPLICABLf: DOCUMENTS 4 1.0 ISOMETRICS 5 2.0 CALCULATION DETAILS 7 3.0 . CALCULATION CHECKLIST 8 N/A DESIGN VERIFICATION CHECKLIST 9
~
Total Pages: 9
RBG-47876 Page95ro~f~13~1~ ____ ~ ______________________ ~ __________ ~ ______________________--, _ . CALCULATION CALC. NO. - REV. ADDENDUM AX-76A Rev.3E *
- ==~
ENTERGY ENGINEERING DEPARTMENT RIVER BEND STATION ATTACHMENT NO.: (as requ.ired) JBI NO.: Pipe Stress An~lysis for ICS in the Reactor Building per MR 96-0069 REVISION mSTORY Revision No. Paragraph Description of Change No. 3A All Per MR 96-0069, the piping' is rerouted through the RHR system. As a result of this cbange, the piping in this calculation is either removed or abandoned in place.
RBG-47876 Page 96 of 131 CALCPLATION CALC.NO.-REY.ADDEND~ AX-76A Rev.3E
~
----- ENGINEERING DEPARTMENT ATTACHMENT NO.:
ENTERGY I RIVER BEND STATION JBINO.: PAliE ..4 OF Pipe Stress Analysis for ICS in tbe Rea'?tor Building per MR 96-0069 I APPLICABLE DOCUMENTS L APPLICABLE CODES, STANDARDS. & REFERENCES (NON-RBS): I . ASME Boiler & Pressure Vessel Code, Section III, Division I, 1974 Edition D. RBS
REFERENCES:
- 1. MR 96-0069 ill. AFFECfED DOCUMENTS:
DOC-NO. REV. DOCUMENT TITLE AFFECf CHANGE NO. (Superseded, Revised. Initiated, etc.) DOC. Z-76-3009A 0 Pipe Support Calculation VOID MR.96-0069 Z-76-3009A . OA Pipe Support Calculation VOID MR.96-0069 1Z-76-3012A 0 Pipe Support Calculation VOID MR.96-0069 Z-76-3012A OA Pipe Support Calculation VOID MR.96-0069 Z-76-3023A 0 . Pipe Support Calculation VOID MR.96-0069 Z-76-3023A
- OA Pipe Support Calculation VOID MR96-0069 1221O-N-SR-140
- lA Support Stress Report REVISED MR96-0069 122 1O-N-SR-l 43 IA Support Stress Report REVISED MR. 96-0069 12*210-N-SR-153 IA Support Stress Report REVISED MR96-0069 12210-N-$R-144 lA Support Stress Report REVISED MR96~OO69 12210-N-SR-145 lA Support Stress Report REVISED MR96-0069 12210-N-SR-146 lA Support Stress Report REVISED MR.96-0069 12210-N-SR-147 lA Support Stress Report REVISED MR96-0069 122tO-N-SR-148 lA Support Stress Rep*ort REVISED MR96-0069 11210-N-SR-149 lA Support Stress Report REVISED MR96-0069 12210-N-SR-150 lA Support Stress Report REVISED MR96-0069 12210-N-SR-151 lA Support Stress Report REVISED MR96-0069 1221O-N-SR-155 lA Support Stress Report REVISED MR96-0069 AX-002H 3C Pipe Stress Calculation GENERATED . MR96-0069
RBG-47876 Enclosur 2~ . CALCULATION WORK SHEET CALC.NO.-REV.ADDEND~ Page97 f. . . . AX-76A Rev.JE
~
ENGINEERING DEPARTMENT AITACHMENT NO.: JBINO.: ENTERGY RIVER BEND STATION PAGE; OF
RBG-47876 CALCULATION WORK SHEET ENGINEERING DEPARTMENT
--- RIVER BEND STATION ENTERGY
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RBG-47876 Page~~~~------------~--------------------------r-~--------~----------~ CALCULATION WORK SHEET ENGINEERING DEPARTMENT ENTERGY RIVER BEND STATION CALCULATION DETAILS MR 96-0069 re-outes the RGIC Injection Point from the Reactor Head Spray connection to the A Loop of Feedwater via RHR. piping. As a result of this cbange, pipe line ICS-006-6-1 (Z-) is removed from the RPV vent and head spray aSsembly to the cIrywell bellows penetration DRB*Z130.
- The flange at the RPV assembly is replaced by a blind flange, and the flange at DRB*Z130 replaced by plug as shown in the isometrics. Pipe supports associated with this pipe are removed. See isometrics. The remaining line ICS-006-57-2 (Z-) from DRB*Z130 to penetration lKJB*Z19 is abandoned in place. .
The abandoned pipe, ICS-006-57-1(Z-), will be empty and capped at both ends which results in a considerable reduction in dead weight and nullification of the thermal and fluid transient loads. Therefore, the structural integrities of the piping, the pipe supports, and the penetrations are assured. The pipe supports associated with this line are downgraded to Class 2. Removal of ICS*006*6-1 (Z-) eliminates the loads on one side of the RPV vent and head spray assembly. Line MSS-002-72-1(Z-) connected to the other side of the assembly is not affected by MR 96*Q069. Thus, RPV nozzle N7 is now solely qualified in AX-2H. Since the total load acting on the nozzle is reduced, the nozzle remains qualified. The following table lists the pipe supports affected by this MR.: Support No. Cbange ICS*PSSH-3009-Al Removed ICS*PSSH-3023-Al Removed ICS*PSSP-30 12-A 1 Removed ICS-PSR-3013-A2 Downgraded to class 2 ICS-PSR-3014-A2 Downgraded to class 2 ICS-PSSH-30 17-A2 Downgraded to class 2 ICS-PSSP-3018-A2 Downgraded to class 2 ICS-PSST-3,016-A2 Downgraded to class 2 ICS-PSST-3019-A2 Downgraded to class 2 lCS-PSST-3020*A2 Downgraded to class 2 ICS-PSST-3021-A2 Downgraded to class 2 ICS-PSST-3027-A2 Downgraded to class 2
RBG-47876 Page 100 of 131 CALCULATION CALC. NO. - REV. ADDENDUM AX-76A Rev.3E
=~ ENGINEERING DEPARTMENT ATTACHMENT NO.:
---~
ENTERGY RIVER BEND STATION JBINO.:
'P AGE g OF CALCULATION CHECKLIST EDP-AA-20 YES NO N/A FORMAT SECTION X_ Cover Page completed. 6.4.1
>< Table of Contents completed (as required). 6.4.2 X Revision History Sheet completed (as required). 6.4.3 X Revisions are identified with revision lines in right margin. 6.4.3 X Applicable Documents Page completed. 6.4.4 X Defmitions established (as required). 6.4.5
)( Calculationlrevisionladdendumlpage numbers are identified correctly. 6.4.10 CONTENTS '.
X Previous calculation for the required analysis exists. 6.3 X Calculation'is appropriately titled for the intended scope. 6.4.1-2 X Purpose and scope are clearly and adequately established. 6.4.1-7,7.1 X' Safety classification is correct for the identified scope. 6.4.1-6
- x Topics/documeots/equipmeot for cross-reference/retrieval are identified. 6.4.1-11 X calculation is clear and comprehensible. 6.1 l( Applicable codes, standards, etc. are identified. 6.4.4-1
.'0. RBS references are identified. 6.4.4-2 X Affected documents are identified 6.4.4-3 X Inputs and sources are identified, appropriate, 'and correct. 72.2-1
,X:. Assumptions are identified and appropriate. 72.2-2 X Inputs derived from field walkdown have been witnessed/verified 7.2.2-5 X Engineering judgments are identified and appropriate. 7.22-6 X Calculation methodology is identified and supported by technical bases. 7.2.3 X Conclusion is appropriate and is justified by calculation. 7.3 X Confirmations are, identified and indicated as required on Cover Page. 7.5.7
)( Directions for Confumations are included. 7.5.7-3 X Calculation data is appropriately included. attached. or referenced. 7.4 X Programs and software are identified and have been verified and validated. 8.0 X Methods/calculations use to check results are identified and included.
X Results are accurate and in accordance with the established methodology. Certification by Professional Engineer is required. 11.7 VENDOR CALCULATIONS Calculation is perfonned in accordance with EDP-AA-25. 10.2 Calculation content and fonnat are acceptable. 10.2 Vendor, preparer. reviewer, and approver are dearly identified. 10.3 X Design verification review has been completed (as applicable). Preparer (SignaturelKCN or SSNlDate):
--e~ ~A J" , (0969) (;-(2-'1 '7 ReVieWe~%maturelK~1"~e): to. ')
~~". ~ , O~4:>1 - 1:2. ... 9-7
~
U
RBG-47876 Enclosure 2 (LA5r-) ,Page 10 r or 1_,:1'1 ATIACHMENTI ES-P-002-00 eENTERGY Page 1 of 2 Typical Design Verification Record Page S of y Document Number Ax - 76A Revision :36 METHOD f,. , - . Verification methods to' be used:
~ Design Review Qualification Testing Alternate Calculations DOCUMENT(S) REVIEWED: (Attach Additional' S~e~t(s), if needed)
Document Number Revision Docwnent Title A x-7c:'A 3£ ~.~ !2..ft-e.~s b\ rl C4l¥. SiS' ~c
, . IC:S ,)) -#t c.: Res::..c iv,- B!~-
, lC2~C:::
M ({ '16. --006'1 '
SUMMARY
OF REVIEW: (Attach Additional S~eet(s), ~ needed) Design Verifi;"tion Completed B~~ ~ ~V Date: C::./t 7 / {g/92 Comment Resolutions Accep~ D~te: Engineering SUpeMsor _)6 ~a CloS1 ) Date: 11- (,)-'It ES-P-002, Fonn No.1, Rev. 0
RBG-478~ ' . Enclosure~ E~TERGY Page 102 off31 ( Record Revision Notice ENGMSYS AX-D7f.t;A _ ADoE: Department Document No. Page I of ~
~ J~. 10.~. 'd--
JBIX No. ReyisionlDate FileNet Location Revision Description Change calculation I addendum status from pending to approved. Reason For Revision MR 96-0069 has been installed. RECEIVED
.jU N 2 5 i999 SA. TIC Approvals:
I
~~,~ / ;)'/U 1P/;;-S/9Q Originator Date Section Supervisor ~~ci£ {
06S"r Date 6;iJ/?7
RBG-47876 Page 1030 f1e ------ ENTERGY CALCULATION COVER PAGE ENGINEERING DEPARTMENT RIVER BEND STATION CALC. NO.- ATTACHMENT NO.: JBI NO.: G13.10.2.2 AX-76A Rev.3E PAGE 1 OF* q
. TITLE: SUPERSEDES: N/A .
stress Analysis for IC~ Piping in the Reactor Building per MR 96-0069
- o. .... . o. . . . . . . o. of. o. .......... .... .. ~ ... I . ' * .... . \, o. . ...... . ..... o.o. .. ": ..... . o. . . .. .. ... . .
SUPPLEMENTS; AX-76A Rev. 3 CALCU'LATION STATUS: ~APPROVED
~~~/qq DCANCELED SYSTEM NO.: 209 .tMARK NO.:
CLASSIlflCAll0N:
- SAFETY RELATED I NON-SAFETY RELATED: O QAPA o NON-QAPA I
Pu,u'OSE I SCOPE I OBJECl1VE: : To document the cbanges imple~ented by MR 96-0069. This MR re:.rontes the RCIC injection from the reactor vesSel bead to the feedwater nozzle. As a result of this changes. ]jn~ ICS-006-6-1 is removed and ICS-006-S7-1 is downgraded to ASME class 2 and abandoned in pIae;e. CONCLUSION: The changes implemented by Mll96-0069 are ac~ptable. The remova l or line IC8-006-0-1 reduces the loads on the RPV head nozzle and the Drywell Bellows Penetration DRB*ZlJO. Likewise, the abandonment of ICS-006-S7-2 g~tly reduces the stress acting on the piping and the support loads acting on penetration DRB.... Zl30. penetration KJB*Z19, and pipe supports. Tberefore, the piping sYstems analyzed by this calculation remain within the REC EP.JED allowables of the ASME Section III Code.
. .JUN 2 5 1999 SA T{C SOFTWARE USED FOR CALCULATION: D YES D NO SDDF#: N/A Manufacturer: Name yersionJRelease No.
CONFIRMATIONS REQUIRED: 0 YES .NO ICONFIRMATION COMPLETE: 0 YES DNO ON/A KEYwORDS: ICS, ~ 96-0009, RcrC
, REVIEW & APPROVAL . /"""".
~ tPr-~6 '-/r-qt. \ ~h.' \~~~i~. elf i ~~>hQ,nL" 11_/~-O;7 (Signature/Date) .... r~~SignaturelDare) I I ~ture1Date)
Preparer D viewer (Non-Safety) Supervisor Caroilo Cuadra, KCN 0969 ~ign Verification ReViewer (Printed lfame, KCN, or SSN) (Printed Name, KCN, or SSN)
, f2AJt;~1-I . GuPTA, (oS?
RBG-47876 e Page 104 of 131 CALCULATION COVER PAGE
- CALC. NO. - REV. ADDENDUM AX-76B. Rev.1H.
----- ENGINEERING DEPARTMENT ATTACHMENT NO.:
ENTERGY RNER BEND STATION .:f47 PAGE 1 OF~
.' . ~~~~~~:~~:'~~.~~~~.t~....
TITLE: Pipe Stress Analysis for ICS-006-7-2 (abandoned inplace) in the Auxiliary Building per MR 96-0069 SUPPLEMENTS: lP/tat1g JW CALCULATION STATUS: . o APPROVED ~PENDING o CANCELED SYSTEM NO.: 204, 209 IMARKNO.: CLASSIF1CATION: lisAFETYRELATED I NON-SAFE:rY RELATED: OQAPA (gJ NON-QAPA I PURPOSE I SCOPE I OBJECTIVE: MR 96-0069 reroutes the RCIC Injection line from its original connection to the RPV Head to the FWS system through a short portion of the RHS piping RHS-010-65-2. The objective of this revision is to evaluate the abandoned pipe ICS-006-7-2 (downgraded from Class 1 to 2) in place. This piping has no function and it is not removed due to ALARA purpose. The piping is cut near an elbow as shown on isometric. The piping is to be evaluated for the applicable dynamic load cases only to meet Class 2 requirements. The supports, penetration, valves, and other piping components do not need evaluation because they are qualified with thermal, fluid transients, and all dynamic load cases in the previous revisions. RECEIVED JUN 1 2 1998 SD.C CONCLUSION: This analysis demonstrates that*the piping system is within acceptable design limits of AS ME Section III Code for changes implemented by MR 96-0069 . SOFTWARE USED FOR CALCULATION: (gJ YES DNO SDDF#: 6229.400-100-00lA Manufacturer: Bechtel .. N~e MEIOI VersionlRelease No. N4 . CONFIRMATIONS ~QlJIRED: 0 YES .~ NO I CONFIRMATION COMPLETE: D YES DNO ~N/A KEYWORDS: pipe, stress calculation, MR 96-0069 REVIEW & APPROVAL left'1.5/) CrAP t\/t/~/'-lI r". (Q5~94R~o/" (SignatureIDate)
~
""t. (SignaturelDateY
~~ 6. !U./fJ. i Ie:.; ate)
~
Preparer D . ~eviewer (Non-Safety) Supervisor (Printed Name, KCN, or SSN) ~sign Verification Reviewer RajeshGupta ( 10>'1 ) Rajni R. Patel (0861) Camilo Cuadra (0969)
R8G-47876 Page 105 of 13.1
~ - ~
. ~~----------------~------~
CALCULATION CALC. NO. REV. ADDENDUM _ . AX-76B, Rev. 1ft
~::e ENGINEERING DEPARTMENT
----- ATIACBMENTNO.:
ENTERGY RIVER BEND STATION PAGE 2. OF TABLE OF CONTENTS SECTION PAGE
- 1. Title Page ......................................... .............. .. ........................................ ......................... 1 2 . Table of Contents ..............................................................................................................2
- 3. Revision History ............................... .......... c... . ............. . ....... .. .. . ..... . ..................... ............. 3
- 4. Applicable Documents ..................... .... .. ... ............................. .... ........ .. .............................. 4. 5 Calculation Summary
- 5. Objective ......................:: .. ................. .. .......................................................... .................. .. 6 6 . Method ..................................................... .. .......... .. ...........................................................7
- 7. Conclusion ................................................................................................. .......................8
- 8. Notes ...................................................................................... .. .... .............. ...................... 9
- 9. Assumptions .................................................. .. ............................................ ..................... 10
. Design Input
- 10. Isometric Sketch ........... .. ........................ .. ........ ............................................................ .. 11
- 11. Basic Analytical Data ............................................................................................. .. .......12
- 12. Valve Data ........ .............. :........... ... ..................... ............ ......................... ............ .... .. ...... 13
- 13. Concentrated Weight Data ........... .... .. .................................:........ ........... .._.....................14
- 14. Rel~tive Seismic Anchor Movements .... ............ ,.... .. ...................................... .................15. 16
- 15. Dynamic Loads ... ..: ..................................................................... _...... :.............................. 17 Summary of Results
- 16. Maximum Stress Levels .................................................. .......~ .................... .................... 18
- 17. Functional Capability Evaluation ................................................ _......................................19
- 18. Valve Accelerations ...................... .............. ..................................... ............ ..... :..............20. 21
- 19. Vent & Drain Line Qualification ...... ..................... .................................................. .. .. ....... 22
- 20. Sleeve Clearance Evaluation ...................................................................... _................... 23 to 25 Checklists 21 . Reviewer's checklist. ........ ........................ .............................................. :.........................26
- 22. Calculation Checklist .......... ... ................... .. .... .. ................ ............... ,.... ................. :.........27
- 23. Design Verification Record .. .....: .. ................. :........................ ............... .... ........ ................ 28 Attachments Attachment A ...................................... ........ .................................................... .... ............ _.....A 1 to A6 Attachment B ..... :..... ..... .. ...... ...... .. .. .... .... .. ...................... ........ .......... .............. .. ........ ...........81 to 8306 TOTAL PAGES: .. ............ .340
RBG-47876 e--- Page 106 of 131 CALCULATION CALC. NO. - REV. ADDENDUM AX-76B, Rev.IR
----- ENGINEERING DEPARTMENT AITACHMENT NO.:
ENTERGY RIVER BEND STATION . r8..\7.1!. j U.I." REVISION HISTORY Revision Paragraph Description of Change No. No. 2 All ICS function is added to FWS System through RHR per MR 96-0069. Rev 2 of this calculation qualifies the abandoned pipe ICS-006-7-2 from penetration Z-19 to NP 87-88 (downgraded from Class 1 to Class 2). All design input and results are documented in their appropriate section .
RBG-47876 Page 107 of 131
~ - ~------~--------~~------~ CALCULATION CALC. NO. - REV. ADDENDUM AX-76B, Rev.lH ENTERGY PAGE 4 OF APPLICABLE DOCUMENTS I. APPLICABLE CODES, STANDARDS, & REFERENCES (NON-RB~):
- 1. ASME Boiler and Pressure Vessel Code, Section III, 1974 edition with addenda through Summer 1974.
- 2. ME101 Version N4 Pipe Stress Analysis Computer Program.
- 3. Piping Design and Engineering by ITT Grinnellndustrial Piping, Inc. Fifth Edition.
II. RBS
REFERENCES:
- 1. EDS-ME-014, *Pipe Stress Analysis and Pipe Support Design Standard".
- 2. Specification No. 228 .000, Rev. 1H "Piping Engineering and Design" .
- 3. Design Criteria No. 228.010, *Pipe Stress and Pipe Support Design Criteria" dated 6-25-84.
- 4. CHOC-EMTR 605-0, "Prpcedure for Qualification of Flanged Joints for ASME til ,
Class 1, 2, and 3 Piping' Systems"
- 5. Environmental Design Criteria S&W Document No. 215.150, Rev. 1H, Dated July 6, 1986.
B. Calculation G13.18.1 .S*08, Rev. 1, "Peak Spread ARS fOf Seismic Events Including , Curves with N-411-1 Damping", 7, CHOC-EMDM-81-08, *Valve Modeling Procedure" dated December 11,9181
- 8. . LEM-34, "Frequencies and Acceptable Accelerations for Valve Qualification"
- 9. Calculation RBI-EQ-416, "Valve Mo.deling and Accepta.ble Accelerations"
- 10. Line Designation Table Change Notice - LDTCN No.: 97-ICS-01
- 11. PICL Change No.: AP-76-01
- 12. CHOC-EMTR-B01, "Design and Installation of Seismic Small Bore Piping, Instrumentation Tubing & Supports for River Bend", dated Sept. 1980
- 13. Calculation 12210 NP(C)-PX-SB-316.0, *Pipe Stress Calc. for Vent, Drain & Instrument Connections*, .
dated 1fi/83.
- 15. Calculation PX-334, Rev. 1H, "1/2 SSE Structural Seismic Displacements Data and Input Procedure for Piping Analysis" dated July 18, 1984,
- 16. Calculation PX-462, Rev. 0, "Structural Displacements Due to Thermal Expansion" dated April 9, 1976,
- 17. DEM-1900, *Stress Analysis of Large Bqre Piping and Pipe Supports for Jet Impingement Loads",
dated 12-17-84
- 18. CHOG-EMDM-82-20, "Stress Intensification Factors for Reduced Outlet Branch Connections", dated 11-12-82. ._ ..
RBG-47876 Page 108 of 131
~-~----------~------~~------~ CALCULATION CALC. NO. - REV. ADDENDUM AX-76B, Rev. IH
~==~ ENGINEERING DEPARTMENT . AITACHMENTNO.:
ENTERGY RIVER BEND STATION PAGE 17 OF APPLICABLE DOCUMENTS II. RBS
REFERENCES:
- 19. DEM-P-4335, IOC from G. MartinoJK. Basu to D. ChristodoulouJD. Bhargava, "Model of Valve 1E51*AOVF065,' dated 11-19-84.
- 20. AX-76B including aU addendums ID. AFFECTED DOCUMENTS:
DOC. NO. REV. DOCUMENT TITLE AF,FECT CHANGE NO. (Superseded, Revised, Initiated, DOC. etc.) SR122 OA Pipe Support Stress Report Revised :MR 96-0069 SR126 OA Pipe Support Stress Report Revised :MR 96-0069 SR127 OA Pipe Support Stress Report Revised :MR96-0069 SR128 OA Pipe Support Stress Report Revised :MR 96-0069 SR132 OA Pipe Support Stress Report Revised :MR96*0069
RBG-47876 Page 109 of 131
~~~--~--------------~--------~
... CALCULATION CALC.NO.-REV.
==~
----. ENGINEERING DEPARTMENT AX-7GB, Rev.lB ENTERGY RIVER BEND STATION PAGE ~ OF OBJECTIVE MR 96-0069 reroutes the RCIC Injection Line from its original connection to the RPV Head to the FWS system through a short portion of the RHS piping RHS-010-65-2. Since some of the original ICS-006-7-1 piping beyond the diversion point is left in pl.ace and has been downgraded to ASME Class 2 . The objective of Revision 2 of this calculation is to evaluate the abandoned piping ICS-006-7-2 from containment penetration Z-19*to the capped near elbow after the horizontal restraint PSST-2071A1 (BZ-7SAN) at NP 90 as shown on*isometric.
The ICS piping was originally analyzed for thermal, fluid transients , dynamic and hydrodynamic load cases because it was connected to the containment penetration Z-19. The 'abandoned pipe in place is not functional; therefore , there is no water weight, and fluid transients associated with this piping. Only dynamic and hydrodynamic load cases are applicable to demonst~ate the structural integrity of piping is maintained for this piping . There are no support configuration change. Supports are qualified while the piping is operational. Since the piping is not going t~ experience any thermal, fluid tra.nsient loads, the original support design is adequate and no further analysis is required .
RBG-47876 Page 110 of 131 r-~~-----'-------------------------------------'r-------------------~ CALCULATION CALC. NO. - REV.
----- ENGINEERING DEPARTMENT AX-76B, Rev.IH ENTERGY RIVER BEND STATION PAGE 7 OF METHOD OF ANALYSIS ME101 The abandoned piping in place is unsupported at free end; however, the support configuration is adequate to provide supports to maintain the structural integrity of piping during seismic and LOCA events. To demonstrate the piping system is within the ASME code requirements, the piping was analyzed by ME1 01, Version N4 using only the dynamic and hydrodynamic load cases.
RBG-47876 Page 111 of 131
~ ~ ~~--------~----~
.... CALCULATION CALC.NO.-REV.
===~
----- ENGINEERING DEPARTMENT AX-76B. Rev.IR ENTERGY RIVER BEND STATION PAGE 2. OF CONCLUSION The completed analysis shows that the stresses and reactions on the sUbject piping are within acceptable limits in accordance with the requirements of the AsME Section III Code.
Functional capability evaluation is not performed because the piping is abandoned in place and is not functional. Stresses on vents, drains, and test connections are within acceptable limits per calculation PX-SB-316. Sleeve clearances are adequate. Penetration Z-19 loads are reduced due to deletion ofthennal and fluid transients load cases. Therefore, the previous revision loads are still valid and are acceptable. New analysis is not required.
RBG-47876 Page 112 of 131 r~~~---r-------C-A-L--C~
- U-L- A -T-I-O-N--------~c~ ~~c~.N-O- .--U-V-.--~
===~
----- ENGINEERING DEPARTMENT AX-76B, Rev. In ENTERGY RIVER BEND STATION PAGE 9 OF NOTES
- 1. The Coordinate system for all data expressed in the global system is defined as follows:
(-X) Is plant "called north" per piping drawing (y) Is vertical "up" (Z) According to right hand rule The local system for straight piping members is defined as follows: (X) Is along the axis of the pipe, positive in the direction of coding . (Y) In the plane of the local X-Axis and the global +Y-Axis unless the local X-Axis is aligned with the global V-Axis; then the local Y-Axis will be parallel to the global X-Axis. (Z) According to right hand rule.
- 2. Forces and moments on restraints , supports, and equipment are those imposed by the' piping systems 0.e., actions, not reactions) .
- 3. Unless otherwise noted, forces and moments reported at an inline anchor represent the total forces and moments acting upon that anchor considering contributions from piping on all sides of that anchor. Reactions reported on terminal anchors are due to piping shown in this report only. For total reactions, values must be combined with those from continuation summaries.
- 4. Unless otherwise indicated, stresses at intersections have assumed an unreinforced branch Connection .
- 5. Intersection reimorcement requirements indicated in this AX are based on mechanical loads only. No pressure reinforcement has been calculated or considerep. The' piping 'fabricator' sh,all perform these calculations, as well as area reinforce'ment requirements, and shall utilize the larger of the indicated pressure or mechanical reinforcement for fabrication .
- 6. Piping support loads may be found in Attachment B pipe support summary.
- 7. For lines requiring seismic analysis, the reactions reported are cyclic in character, and reactions must be considered as acting in either the positive or negative direction.
- 8. The valve 1E51*AOVF065 operator weight reduction of 40 Ib per Rev. 1B was neglected in this revision.
- 9. Abbreviations R.H---------Rod Hanger S.H--------Spring Hanger V. C.--------Vertical Restraint RX---~-------X-Restraint RZ---------~-Z-Restraint RSKew---~- Skewed Restraint SX---'-------X-Snubber SY---------Y-Snubber SZ---------Z-Snubber SSKew----Skewed Snubber EI------- ------Elevation Rdcr--- ----Reducer S.R. Elb-------Short Radius Elbow
RBG-47876 Enclosure 2 Page 113 of 131 I' " CALCULATION CALC. NO. - REV. I I
=-----
==~ ENGINEERING DEPARTMENT AX-76B. Rev. IH ENTERGY RIVER BEND STATION . PAGE {OOF ASSUM:PTIONS None
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RBG-47876 e Page 117of131 CALCULATION CALC. NO. - REV.
------ ENGINEERING DEPARTMENT AX-76B, Rev. IR ENTERGY RIVER BEND STATION PAGE 140F CONCENTRATED WEIGHTS:
Component Description Weight in Ib Node No Valve Body 1E51*AOVF065 307. B50 Valve Operator 1E51*AOVF065 123. 870 Small Bore Support Weight .40. 188
RBG-47876 STONE & WEBSTeR ENGINEERING CORPORATION Page 118 of 131 CALCULATION SHEET CALCULA TlON IDENTIFICATION NUMBER I~ JO. OR WOo NO. 12210 DIVISION & GROUP NP(C) CALCULATION NO. AX-76B ~E-I/. 1~ OPTIONAL TASK CODE PAGE REF. DESIGN INPUT (CONT'D) RELATIVE SEISMIC ANCHOR AND/OR SUPPORT DISPLACEMENTS E ;a; saa EiI&9filNUeU 91f !pua F9&lIsm:ii6 P/i6SE5~ ~*"I .~ SUPPORT DISPLACEMENTS ". NODE SUPT. BUILDING , ATTACHMENT (IN) REMARKS NO. TYPE (STRUCTURE ) ELEVATION (FT) DX DY DZ
""r A.v')'£)
r-::. "- At/X, &...eq, C//,719 0.2550 0.1800 V
~
9 R";: t'....... q7,;ZS 0.2750 ---~ ------ 47 f&kw ~ /04.75 -----~ VO.1810 0.2680 48 ISsKeW I~ ~3070 ------ 0.2680 ~/A 52 :5:e /~ ~-- ------ 0.2680 V 10-'" ............... 61 R~ /0(0 .0 ------ . ~---- 0.2720 71 $.;k~ V (/8./07 0.3620 ---~ I'-. . 0.3030
~ ~c. /1~75 ------ .0.1810 ~
90 K'~ /~,75 ------ ------ 0.3100 100 ~kEW 1-2~,5Z(P 0.3800 0.1810 ------ 121 R-c 1~,5~~ ------ ------ 0.3130 122 Vc /ee,6'2~ ------ 0.1810 ------ 141 ~,~ , /Z'2,5zt. ------ 0.1810 0.3130 220 ~,~ SIIEr:J:> &.r:x5" /'2~,(;o ------ 0.4110 0.8530 285 - ...... ~CcNr: /;Z,z, 1..1. /,,~ 7~ 0.9870 0.4390 0.8690
RBG-47876 STONE &. WEBSTER ENGINEeRING CORPORATION Page 119 of 131 CALCULA TION SHEET CALCULATION IDENTIFICATION NUMBER 16?
. JO. OR WOo NO.
12210 DIVISION &. GROUP NP(C) CALCULA TlON NO. AX-76B RE;V. {1.4 OPTIONAL TASK CODe PAGE REF. DESIGN INPUT (CONT'D) RELATIVE SEISMIC ANCHOR AND/OR SUPPORT DISPLACEMENTS (
- i i i CAi.grb,1'z'Uon eu ':PiH; Fer.r.OWnfe P-A<iE(S)
&6 GI .)
SUPPORT DISPLACEMENTS
- NODE SUPT. BUILDING ATTACHMENT (IN) REMARKS NO. TYPE (STRUCTURE ) ELEVATION (FT) DX DY DZ 260 Mc.HCI<, Z;fZYwe~L. 1'28,17 1.0460 0.4780 0.9310
~ ~~ AUx, &I::e,. <98.75 0.2800 0.1800 ---./-'
V R~ 1Q?,S85 ------ ---~~ 375 380 Rx "" ~ /65,(;71 0.30ze. ~--- 0.2570 382 $1-1 /~ ~- 0.1810 ------ 0'A 410 Vc /~ ~-- 0.1810 ------ V 4"45 .4v~ /o(P,75 0.3150 ~O. *1810 0.2740 537 ~)~ V' 98.51 ------ o~
"" ~
0.2520
~ t4t~ /o3.0/(P 0.3000 0.1800
RBG-47876 Page 120 of 131
==~
ENTERGY CALCULA.TION ENGINEERING DEPARTMENT RIVER BEND STATION
~ALC. NO. - REV.
AX-76B, Rev. PAGE 170F iH Dynamic Loads File Names TABLE 1 Structural Attachment Elevation (FT) Curve Number OBe SSE Auxiliary Building 114 auxbon05 .ace auxbsn06.ace Auxiliary Building 141 auxbon07.ace auxbsn08 .ace Drywell 114 rbdwon43 .ace rbdwsn44.ace Drywell 133 rbdwon45.ace rbdwsn46.ace Shield Building 112.67 rbsbon03.ace rbsbsn04.ace
, 133 rbsbon05.ace rbsbsn06.ace Shield Building TABLE 2 .
Structural Elevation Curve Number Attachment (ft) SRV1V SRV16V CHCO PS Drywell 121 rbdwtn43.ace rbdwan43.ace . rbdwcn43.ace rbdwpn43.ace Drywell 128 rbdwtn45.ace rbdwan45.ace rbdwcn45.ace rbdwpn45.ace Shield Building 121 rbsbtn03.ace rbsban03.ace rbsbcn03.ace rbsbpn03 .ace Shield Building 128 rbsbtn05.ace rbsban05.ace rbsbcn05.ace rbsbpn05.ace
RBG-47876 Page 121 of 131 CALCULATION CALC. NO. - REV.
= =~
----- ENGINEERING DEPARTMENT AX-76B, Rev. 1ft ENTEAGY RIVER BEND STATION PAGE f80F MAXIMUM STRESS. LEVELS PUWG ST~SS S1.1Ml1ARX CHECK AND COVER SHEET RB/562367 (B~043) 06/11/97 BG1043 ASHE SECT. III, CLASSES 2
- 3
?ROJECT JOB NO. 22497 PLANT DESIGN GROUP
?crc SYST£M PA!I.T NO'!' !N OP.:RATION
!UVER BEND SYSTEM CALC NO .~-76B ISO ' NO ~'? NO * .
- LOCATION MAX~~ ALLOWABLE COMPUTED DESIGN or }!rtXlMUM COt~UTED STRE.SS ------ ---
CONDITION LE VEL END ELEMENT STRZSS ( PSI) ( PSI) ALLal1ABLE SUSTAINED SH LO,\llS 134 132 776 .052 EQN. 8 lH 15000 CCCASZONAL 1.2 SH LOADS B 134 132 3511 .195 EQN. 9 131 18000 OCCASIONAL 1.B SH LaMS C 134 132 3793 .140 EQN. 9 134 27000 OCCASIONAL . 2.4 SH LOADS o ,1,3.4 132
- 3830 .106 EQN. S 134 36000 THER!~ SA EXPANSION 200 192 10114 EQl'l. 10 200 .; 22500
RBG-47876 Page 122 of 131 CALCULATION CALC. NO. - REV.
----., ENGINEERING DEPARTMENT AX-76B, Rev.lH ENTERGY RIVER BEND STATION PAGEf9 OF FUNCTIONAL CAPABILITY EVALUATION:
This abandoned pipe ICS-006-7-2 is not performing any function per MR 96-0069;.therefore, functional capability evaluation is not required .
RBG-47876 Page 123 of 131 r-~~-----'-------------------------------------'---------------------' CALCULATION CALC. NO. - REV.
----. ENGINEERING DEPARTMENT AX-76B, Rev. 18 ENTERGY RIVER BEND STATION PAGEZO OF VALVE ACCELERATIONS Valve 1E51*AOV065.is abandoned in place and Is not perfonning any function; therefore, it is not active. Valve accelerations from this analysis are reduced due to the use of N411 damping values for all dynamic and hydrodynamic load cases. Furthermore, the fluid transients are not applicable to this piping anymore. The valve accelerations from the previous revision are provided for infonnation only.
f' -um:;:o Dl::::lOJ (C(')G)
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...... cn,j:>.
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§ VJ Ref: Valve Identification No. /£5/-£-AoVF~5 AX Node Pt. 1350/1970 ~
o ill I ..... 0 Valve Spec. No. --Z~.'2/8 N " NO
..... :0 o~
Acceleration in Global Acceleration in Ulobal Acceptable ? Coordinate System at z Coordinate System at 'C.G.' Acceleration (g)
'C.G.' of Operator (g) of Valve Body/a' ~8.~ifte~ .. n.~ _0 /1."2 oA /7J ?
~~F}':;!!J~ ,~~ ~.aI!U -
Loading Case f-lO £>.e ) B&'o ~ 7l~7G} (g 0 ax . ay az ax 8y az ax ay 8Z l2~ 08EI .4112 .. (p/O * .45Z .. /87 .. 32:3 ~ .24-1 -2,0 2,0 -2,0 z-g
~ o d
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80:u B,o J'1 SSEI .715 / . /75 .671 ,3rao
- C't> '20 .4(03 6,0 3,0 0 r
0 C s.-
>",~
c r O 3 ,777 G,G38 4,08 -2,455 3 ,570 "U SRVmax (SYMA1E77<IC -/(,v) '2,{P13 3 ,6 E,S' :3,5 >>
-I rill Chugg /(50 -2 ,44/ 4-/572- ;tz ,47~ / .174 2 , 35/ /,732- 8,0 B,o 8,0 NO N>>
0 Z o ~ c", r:::V
..... r ,..,0 >""
pool ?we. l ! .315 .532 *::47 1:3c
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~
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tOTAL CcJA/&Np -Ur5er 4,~~ 8.1(P5 5.62/ 4,QQl 4,472. 8>.'507 5,0 -5,0 5,0 )\
0 6.&18 5,37Co o,a8o :3.95/
~ 0
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£1i411f3.' ~ -0 l>>
.4 !i.~ rt;.'=61}J'~~e.B . &e",-'~6t/,~f./J" ~ i,E.12J/)RE:JJ. e.(~i1JJ.t.ri.6 dPP&ClIC~L Q£. Itlll JL£ GHil1l 1LlC./J. TtI1IJ.l Ge.aae. C>
~ v ,Ir r~ p
- tv
--- -------~ - - ~ -- - ---- - ~ . ~
RBG-47876 Page 125 of 131 CALC. NO. - REV.
CALCULATION
=-----
==~ 'ENGINEERING DEPARTMENT AX-76B, Rev. IH
, ENTERGY RIVER BEND STATION PAGE2l0F VENT & DRAIN QUALIFICATION:
The following Vent & Drain is qualified with generic calculation PX*SB-316.
Valve No:
ICS*VF302 ICS*VF100
RBG-47876 Page 126 of 131
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----- ENGINEERING DEPARTMENT AX-76B, Rev.IR ENTERGY RIVER BEND STATION PAGE 230F SLEEVE CLEARANCES Piping displacements due to reanalysis of Revision 2 have not changed significantly, most of them have decreased due to the deletion of thermal and fluid transients load cases, which are not applicable anymore. The Seismic Anchor Movement load case movements are not altered, and this analysis has used N411 damping values, which r~duces the dynamic displacements.
RBG-47876 STONE & WEBSTER ENGINEERING CORPORATION Page 127 of 131 CALCULATtON SHEET i'lY CALCULATION IOENTIFICATION NUMBER rl-'~;.R~4 JO. OR WOo NO. DIVISION & GROUP CALCULATION NO. OPTIONAL TASK COCE PAGe'i205 NP(C) ,
12210 AX-76B R/JI-i REF.
SLEEVE CLEARANCE EVALUATION
)
NDDE. 100 NUPIPE Output NUPIPE Input Load Case Case Pipe Deflection Penetration Sum of Relative Description No. Dir. Movement Movement Movements Deadweight 3/ ~
y - ,014-
-.C02
- . 014
-,~~
y . 054 0 . OS/-
Thermal ( N+U) 120 ~ .003 ' ,
6 .003 Thermal (Max.) ~~
Y
-T:
. 1 18
*cx:l3 °0 . I IB
.003 y _ 01"5 Thermal (Min.l 28 :c .00'2. °0 ~0/5
,CIOZ,.
Building 1'I-cUfSS y
- Cx::J4.. 0 -0()4..
Settlement 1 2. /?liN .:e: ' .0 C> 0 Building ~~ y - .,z72 -.~70 -,aDZ..
Settlement 2 ~RtJN e 0 0 0 y ./ 9.,5 ./8/ .014-OBEA S7 .e .014- .~/O . 00/
Y _028 SSEA (2*OBEA) '-e .00'2.
y .0°4 ' -0C4-OBEl 40 -e .007 - .007 41 Y .008 - . 008 SSEI -i!
y
. 01.:3
.0,50
- ' , ~§o
.0/3 Oyna!pic OCCU , 46 .c- . 076 .075 Dynamic OCCE 35 ~
y . OQO
.01'S
-- .050
. (')75 y .0-51 - .051 Dynamic OCCF 8(0 ~
- 07~ - .OIG-:.
Total Relative
~ovements
- I DWT -
+ + Building TIler. - Settlement I +
' - OBEA -
+ Dyanmic (OCCU/OCCE )
Or
- I DWT
+
~
+ Building Ther. - Settlealent I- +
SSEA -
+ Dyanmic (OCCI')
Notes: 1. The sign ot the total relative movements 'must be the 5i~
of the maximum combination or. Deadweight, Thermal and Building Settlement.
- 2. The maximum of either equation shown above is recorded on the next page to be compared wi th the lIleeve clearance.
1/
C( = /-.614 +./18 +. 004/+ ,0"2.8 +- .O-5! = ./67 iE ~ / -. ooe + .005 + 0/ +
- 002..;- . C>7<:C =-
- 07'7 "
RBG-47876 Page 128 of 131 STONE & WEBSTER ENGINEERiNG CORPORATiON CALCULATION SHEET
/t' I ';~;.If' '2.5 CALCULA nON IDENTIFICATION *NUMBER.
JO. OR WOo NO, 12210
. DIVISiON NP(C) at GROUP CALCULATION AX-76B R ,H OPTIONAl. TASK coce PAGe~
REF.
SLEEVE CLEARANCE EVALUATION Sleeve Clearance Looking North ;.loDE. lex::;)
y Total Relative MI/J. Movements
-z -/ / ~8'
~8'
- 1,~:Z5
* ;.~~S:.
- .07 ~ 'I
.CJ79 ~
z
- z -z of:::..
y I'~~' -!8(~ "- . 187 "
-y * /1%;" * /,8/e '~ . 187 ft
-y
*Sleeve Clearance Looking East y
-x a
- 0= -
X ::0 .
K -x Y = as
-y * * -
-y Sleeve Clearance Looking up Pacing North x
-z * * -
Z z -z til IE X
-x :: s -
-x Conclusion . *
*0 of::-
RBG-47876 Page 129 of 131 CALCULATION CALC. NO. - REV. ADDENDUM AX-76B. Rev. IH
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==~ ENGINEERING DEPARTMENT ATIACHMENT NO.:
ENTERGY RIVER BEND STATION PAGE 2~OF REVIEWER'S CHECKLIST Item Calc Comments ResponseIResolntion Page AJOr1~
Conunents Provided By Conunents Resolved By Resolution Accepted I~ t.~~ 61~T t. /11 /'f'1 Reviewer KCN Date Preparer KeN Date Reviewer KCN Date
RBG-47876 Page 130 of 131 CALCULATION CALC.NO.*REV.ADDEND~
AX-76B, Rev. IH
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==~ ENGINEERING DEPARTMENT ATTACHMENT NO.:
- RIVER BEND STATION ENTERGY PAGE 2.7 OF CALCULATION CHECKLIST YES NO N/A EDP-AA-20 FORMAT SECTION x Cover Page completed. 6.4.1 x Table of Contents completed (as required). 6.4.2 x Revision History Sheet completed (as required). 6.4.3 '
x Revisions are identified with revision lines in right margin. 6.4.3 x Applicable Documents Page' completed. 6.4.4 x Definitions established (as required). 6.4.5 x Calculation/revision/addendumlpage numbers are identified correctly. 6,4.10 CONTENTS x Previous calculation for the required analysis exists. 6.3 x Calculation is appropriately titled for the intended scope. 6.4.1-2 x Purpose and scope are clearly and adeqUately established. 6.4.1-7, 7.1 x Safety classification is correct for the identified scope. 6.4.1-6 x Topics/documents/equipment for cross-reference/retrieval are identified. 6.4.1-11 x Calculation is clear and comprehensible. 6.1 x Applicable codes, standards, etc. are i,dentified. 6.4.4-1 x RES references are identified. 6.4.4-2 x Affected documents are identified 6.4.4-3 x Inputs and sources are identified, appropriate, and correct. , 7.2.2-1 x Assumptions are identified and appropriate. 7.22-2 x Inputs derived from field walkdown have been witnessedlverified 7.2.2-5 x Engineering judgments are identified and appropriate. 7.2.2-6 x Calculation methodology is identified and supported by technical bases. 7.2.3 x Conclusion is appropriate and is justified by calculation. 7.3 x Confirmations are identified and indicated as required on Cover Page. 7.5.7 x Directions for Confinnations are included. 7.5.7-3 x Calculation data is appropriately included, attached, or referenc~. 7.4 x Programs and software are identified and have been verified and validated. 8.0 x Methods/calculations use to check results are identified and included.
x Results are accurate and in accordance with the established methodology.
x Certification by Professional Engineer is required. 11.7 VENDOR CALCULATIONS x Calculation is perfonned in accordance with EDP-AA-25. 10.2 x Calculation content and fonnat are acceptable. 10.2 x Vendor, preparer, reviewer, and approver are clearly identified. 10.3 x Design verification review has been completed (as applicable).
Preparer (SignatureIKCN or SSNlDat~ "
-:;;~
/1-
~GlM! ~~'"I) (,11g./~7 Reviewer (SignatureIKCN or SSNlDate)~ ~
~ (0901') ,6/tf/97
RBG-47876 Page 131 rnrr':I:C::-----r----C-A-L-C-U-LA-T-I-O-N-----r--::-~-:-:---------,
----- ENGINEERING DEPARTMENT ENTERGY RIVER BEND STATION Design Verification Record Document No. AX-76B, Rev. IH METHOD Verification methods t9 be used:
X Design R~view
_ _ _ _ _ Qualification Testing
- - - - - Alternate Calculations DOCUMENT(S)
Document No. Revision Document Title AX-76B IH Pipe Stress Analysis for ICS-006-7-2
"',,. " " ... . . ~---"-"------
SUl\1MARY OF REVIEW:
Acceptable as is.
Design Verification Compl~ted By ~ c: ¢.du c Comments Resolution Accepted By _.....:.tJ--</,
c.. A! --I-_ _ _ _ _ __ _ Date
&gmoering Sup"';,., @ll-, C-ry:!? Date ll_/~-CH TABLE 1}}