W3P83-0251, Forwards Documentation Re Progress &/Or Completion of All Confirmatory Items in Seismic Qualification Review Team audit.NSS-PE-25, Boric Acid Tank Circulating Valve, Only Remaining Confirmatory Item
| ML20083P585 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 01/21/1983 |
| From: | Maurin L LOUISIANA POWER & LIGHT CO. |
| To: | Novak T Office of Nuclear Reactor Regulation |
| References | |
| 3-A20.08, A-A1.01.04, W3P83-0251, W3P83-251, NUDOCS 8302030532 | |
| Download: ML20083P585 (206) | |
Text
{{#Wiki_filter:1 142 DELA90NDE STREET P O W E R & L I G H T! P O BOX 6908
- NEW ORLEANS. LOUISIANA 70174
* (504) 366-2345 UTILIT!LS SV STEM January 21, 1982 L V MAunin Voce President Nuclear Operaten?
W3P83-0251 A-A1.01.04 3-A20.08
' Mr. Thomas H. Novak Assistant Director for Licensing U. S Nuclear Regulatory Commission Washington, D. C. 20555
SUBJECT:
Waterford SES 3 Docket No. 50-382 Formal submittal of follow up items from SQRT audit
Dear Mr. Novak:
Please find enclosed documentation of the progress and/or completion of all confirmatory items identified in the Seismic Qualification Review Team audit for Waterford 3 SES. A review of these documents; as agreed upon in a January 18, 1983, telecon with Messrs. Jim Wilson, Jerry Jackson, and Jack Singh; should be sufficient to show that NSSS-PE-25, Boric Acid Tank Circulating Valve, is the only remaining confirmatory item. Resolution of Generic Issues is in progress. Reports / Analyses pertaining to these issues will be submitted as they are completed. If you have any questions, please advise. Sincerely. V L. V. Maurin W LVM/SMJ/jcb Attachments cc: Jim Wilson, Jerry .Tackson, Jack Singh (EG6G), E. L. Blake, W. M. Stevenson l 8302030532 8.0121
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PDR ADOCK 00000382 A PDR
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i bec: (w/o Attachments): R. P. Barkhurst, F. J. Drummond, D. B. Lester, T. F. Gerrets, G. B. Rogers, R. W. Prados, C. J. Decareaux, R. F. Bruski, P. V. Prasankumar, J. R. McGaha, S. A. Alleman, G. R. Peeler, T. K. Armington, K. R. Iyengar, M. I. Meyer, L. L. Bass, Richard Hymes, M. G. Williams, S. M. Jones, Kanti Gala, H. B. Mulliken (CE), John Hart - (Ebasco), John Tompeck (Ebasco), John Zudans (NUS), Central Records, Nuclear Records (3) L' ensing Library i, I I I 1
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Before the UNITED STATES NUCLEAR REGULATORY COMMISSION DOCKET NO. 50-382 In the Matter of LOUISIANA POWER & LIGHT COMPANY RESPONSE TO SQRT AIDIT Louisiana Power & Light Company, Applicant in the above captioned proceeding, hereby files a Response.to Seismic Qualification Review Team Audit. Respectfully submitted, LOUISIANA POWER & LIGHT COMPANY BY: 6un i
~ ' ' " '
L.V. Madrin Vice President Nuclear Operations i I l l
STATE OF LOUISIANA)'
) SS PARISH OF ORLEANS )
L. V. Maurin, being duly sworn, states that he is Vice President-Nuclear Operations of Louisiana Power & Light Company and that he is authorized on the part
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of said company to sign and file with the Nuclear Regulatory Commission this report.
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L.V.'Maurin SUBSCRIBED AND SWORN to befoge met e Notary Public, in and for the Parish and State abow named, this A' fA da of T AA//A ,
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1983. / l
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n JY -. h Notirty P6blic 4 MY COMMISSION EXPIRES:
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" LIST OF ENCLOSURES" ENCLOSURE ATTACHMENTS CURRENT AS OF 1 (1) Response to PE-31 9/17/82 (2) Response to BOP E-68 2 (1) Status of Confirmatory Items 10/4/82 (2) Seismic Qualification Completion Schedule 3 (1) Seismic Qualification Completion Schedule 10/15/82 4 (1) Status of PE Confirmatory Items 11/10/82 (2) Seismic Qualification Completion Schedule (3) Seismic Analyses of Muellor 3" Y-Type Strainer (4) ME-894 Certified Design Report of Horizontal Ptmp 5 (1) Status of PE Confirmatory Items 12/3/82 (2) Seismic Qualification Completion Schedule 6 (1) Documentation of Telephone Conversation 1/18/83
CONFIRMATORY ITEMS Item Description SQRT NO. Answered by
- 1. Control Components BOP-E-68 Enclosure 1
- 2. Pressure Switch NSSS-ICE-16 Enclosure 1 Low 011 Pressure Switch NSSS-PE-13
- 3. Boric Acid Make up Pump NSSS-PE-14 Enclosure 2
- 4. Boric Acid Tank Circulating Valve NSSS-PE-25 Response expected 1/24/8.3
- 5. Holdup Tank C NSSS-PE-33 Modification in pregress
- 6. Resister imput card NSSS-ICE-5a Enclosure 3
- 7. 1151 Indicator NSSS-ICE-8-1 Analysis in progress
- 8. CEDM Reed Switch Position NSSS-ICE-15 Enclosure 2 NOTE: Items 1, 2, 3, and 8 closed by above mentioned telecon.
Generic Issue 5 (neglected nozzle loads in stress analysis) closed by telecon and Enclosure 5. Dccumentation of Telephone Conversation, January 18, 1983 Enclosure 6 L
ENCLOSURE 1 SEISMIC QUALIFICATION REVIEW TEAM RE-AUDIT FOLLOW UP Attachment (1) LW3-1196-82 Attachment (2) LW3-1174-82 September 17, 1982
EB ASCO SERVICES INCORPORATED SUOT*.O EBoSCO Tac V. *.: base Ce~e? f.e4 Ycrm N Y 10048 September 14, 1982 LW3- 1174-82 File: 70-C-5 (1-S-1) 7-D-1 Mr G B Rogers, Site Director Louisiafna Power & Light Company P O Box B Killona, Louisiana 70066 RE: WATERFORD SES UNIT NO. 3 SQRT AUDIT FOLLOW-UP CONFIRMATORY ITEMS - BOP E-68 Ref: LP&L Seismic Qualification Audit - Summary sheet used at NRC exit interview on September 3, 1982
Dear Mr Rogers:
Please transmit the following information to Mr R Macek of EG&G with regards to BOP Item E-68: Via telephone conversation with Mr W W Schaff of Dayton T Brown Labs, Inc., Ebasco was advised that all control components tested did pass the seismic testing program. The anomolies noted were not malfuncti ons as all components were operable during and after the seismic testing and this determines whether or not the item is seismically qualified. If you have any questions, please contact A DeVito on (212) 839-3861. Very truly yours,
/
R K Stampley Project Manager AD:as - cc: Central Records'- W3 (2) RECENED Nuclear ?,ecords - GO (2) WCt.EAg RECOPDS D C Gibbs L V Maurin g 1q9-uA,..- g2-5/LL -
c.-c. <mmri. E8 ASCO SERVICES INCORPORATED EBASCO Two We'id Trace Cente . New York.N Y.10048 September 17, 1982 LW3- 119 6-82 File: 20-A-3C Mr G B Rogers, Site Director Louisiana Power & Light Company P O Box B Killona, Louisiana
SUBJECT:
WATERFORD SES UNIT NO. 3 SQRT AUDIT - RESPONSE TO CONFILMATORY ITEM PE-31 FROM ORIGINAL SEPTEMBER, 1981 AUDIT Ref: 1. C-CE-7358, dated 10-26-81
- 2. LW3-120-82, dated 2-2-82
- 3. C-CE-7541, dated 2-24-82
Dear Mr Rogers:
The NRC and their consultant EG&G decided during the audit he3d August 31-September 3, 1982 that the subject confirmatory ite.- would have to be reviewed by'EG&G's INEL group to close out this item. The information provided below should be forwarded to EG&G to assist them in that review. In Reference 1, it was proposed by CE to eliminate the charging pump lube oil switch from the protective circuit of that pump on account of their inability to establish seismic qualification for the pressure switch. In the same referenced letter, it was assumed that the pressure switch would develop a chatter in its contact during the seismic event that will respit in automatic tripping of the pump. Our detetiled review of the charging pump protect!'e circuit indicates that it is not necessary to expose the charging pump to the damage on loss of lube oil, through elimination of pressure switch, since # l the circuitry is of such a nature that the chattering contact, due . _; to the seismic event, will not be able to trip the charging pump. 4 Our reasoning in arriving to that conclusion is as outlined below: Please refer to the attached Control Wiring Diagram Dwg No. LOU 1564B-424, Sheet E365. RECEWED IVUCLEAR 39CotD3 SEP 28 Ik'2 l u h _ _ & g- --- g p w n - -- ~, ,.m
e September 17, 1982 Mr G B Rogers LW3-1196-82 The N.O. contact of lube oil pressure switch is closed when lube < oil pressure is normal and is keeping coil of relay PX continuously energized. On loss of lube oil pressure, the pressure switch contact will drop off the relay PX, and provided the charging pump is in operation, will energize the coil of time delay relay 2-2. A t'me delay of up to 15 seconds may be established on relay 2-2 before it will pick up and close 'a contact to trip the charging pump. This time delay of between 10 and 15 seconds will be a positive indication that the contact on lube oil pressure switch opened because of loss . in pressure rather than because of chatter. Furthermore, we have suggested that the wiring of the tripping contact 2-2 be modified to connect contact 2-2 in se, ries with N.O. of SIS relay, this will prevent 2-2 from tripping the charging pump during the emergency operation, at the same time we will not suspend the pro-tective function. of the lube oil pressure switch. The existing lube oil pressure low alarm remains active during normal and emergency operation of the charging pump. The above reasoning was reviewed and concurred to by CE in their Reference 3 letter. If you have any questions, please advise. Very truly yours,
/
h f$ R K Stampley
& Project Manager ! RKS:JKT:as cc: Central Records - W3 (.2 )
Nuclear Recordss - GO (2) D C Gibbs L V Maurin M Williams (LP&L) l l
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ENCLOSURE 2 SEISMIC QUAI'FICATION REVIEW TEAM RE-AUDIT FOLLOW UP Attachment (1) Status of Confirmatory Items Attachment (2) Seismic Qualification Completion Schedule October 4, 1982 l t i t l
Attachment.to LN3-1341-02
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l Pega ,'l of 10 !' SEISHIC QUALIFICATION l Revision 1 1' . s' I COMPLETION SCllEDULE 10/15/82 - HSSS-ICE I . I ,. P.O./ SPEC ' EQUIPHENT SQRT FILE Ho. QUALIFICATION INSTAT.LATION 1 (TAG HOS.) , SCilEDULE UllEDULE ' 9403341 (P.O.) .
- i See sttachment Al NSSS-ICE-5 Equipment has been qualified *
' Equipment installed .
9270-ICE-0005 according to vendor i Rev 01 NSSS-ICE-5a (Westinghouse). Proprietary , (Spec.) thru Sh reports will be released to l'. LP&L pending resolution of proprietary agreement between Westinghouse and L - i LP&L. ... II (See C-CE-798i of 10/4/82) .. NSSS-ICE-9-1 ' same P.O. and Original seismic test ,'t . Spec. as above See attachment A2 NSSS-ICE-9-2 (Westinr,boue i EL991) . Equipment installed. 8" not approved _ Westinghouse resubmitted with new test report (IEI.1348) C-E '
- technical review completed but adminsitrative work
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QTR-1010 and QTR-1008 N.. ,
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the applicable qualificatio n ; .. references,,for the Veri- ..'
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Retesting by Westi6ghouse ;
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(TAC N09.) SCilEDULE SCllEIMILE NY-403506 !
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246 ISI-V2510 (2) No File Established Yet Report has been reviewed with! l = 247 ISI-V1592 (6) " [ ^ comunents " I i 248 2Cil-V I 530 " "2
. I 249 2Cil-Vl542 . !
2xx-V500 (59) 250 - i thru V558 . 251 2XX-V559 " " F - Y E thru V583 " I 252 lxx-V900 (2)) { ' thru V926 -" " l ' HY-403522 ' f,e I.00-1564.103A . . 1: Io 219A 3 % V223 (2) No File.E,stablished Yet Seismic report received. 226A 3WM-V224
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21 RY-010A, B , C, D Later NSSS-ICE-23 22 Reactor Trip Switchgear Yes , NSSS-ICE-3 Cabinet l 23 ESFAS Auxiliary Relay Yes NS SS-ICE-4 Chbinet
~
24 Process Instrument Rack Yes NSSS-ICE-5 25 TY-il2CA-1/TY-112HA-1/ Yes NS S S-ICE-5a TY-122CA-1/TY-122HA-1/ PY-1013A-1/PY-1013A-2 / ,
^
PY-1023A-1/ PY-1023A-2/ LY-305A-1/PY-352A-1/ SPARES PT-101A-1/PY-101A-2 / ' PY-102A-1/PY-102A-2 / LY-1113A-1/LY-1113A-2/ . LY-1123A-1/LY-1123A-2 / , PY-351A-1/ SPARES .. TY-112 CB-1/TY-112EB-1/ - - TY-12 2CB-1/TY-122HB-1/ l PT-10135-1/PY-10133-2 / PY-1023B-1/PY-10235-2 / . PY-101B-1/PY-101B-2 / ' PY-1023-1/PY-1025-2 / . LY-1113 B-1/LY-11135-2/ . -- - LY-11233-1/LY-11235-2/ , PY-3 513-1/ SPARES TY-112 CC-1/TY-112HC-1/ TY-122t.,0-1/TY-122HC-1/ r
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[ EQUIPMENT ,
. AVAILABILITY TAG OR FOR INSPECTION SQ REPORT ITDd.
IDENTIFICATION IN FIELD FILE NO. ACCESSORIES 25 PY-101C-1/PY-101C-2/ Later (Cont'd) - PY-102C-1/PY-102C-2/ LY-305C-1/PY-352C-1/SPARIS PY-1013 C-1/ PY-1013 C-2 / PY-1023C-1/PY-1023C-2 / LY-lll3 C-1/LY-1113 C-2/ LY-1123C-1/LY-1123C-2 / PY-351C-1/ SPARES n-112 CD-1/2-112HD-1/ TY-122CD-1/TY-122HD-1/. , i PY-1013D-1/PY-1013D-2 / ' - 8 PY-1023D-1/PY-1023D-2 / LY-305D-1/PY-35 2D-1/ SPARES PY-101D-1/PY-101D-2/ PY-10 2D-1/PY-10 2D-2 / LY-1123D-1/LY-1123D-2 . PY-3 51D-1/ SPARES , 26 TY-3 03I, TY-3 03Y, TY-3 51% , Late: NS SS-ICE-Sb TY-352I, TY-351Y, TY-352Y (.
% 27 TY-112CA, TY-112CB , Later NSSS-ICE-Sc i TY-112CC, TY-112CD,
- TY-122CA, TY-122CB ,
i TY-122CC, TY-122CD, . TY-112HA, TY-112HB , TY-112HC, TY-ll2HD, , TY-122HA, TY-122HB, TY-122HC, TY-122HD, - PY-101A, PY-101B , PY-101C, PY-101D, PY-103, PY-104, PY-303I, PY-303Y, PY-102A, PY-102B , PY-102C, PY-102D, . LY-305A, LY-305B , LY-305C, - LY-305D, PY-1013A, PY-1013B, PY-1013 C, PY-1013D, PY-1023A , PY-1023B , PY-1023C, PY-1023D, - LY-1113A, LY-11133, LY-1113C. LY-1113C, LY-1123A, LY-11235, _ ,, ._ LY-1123C, LY-1123D, LY-110I, LY-110Y, PY-105, PY-10 6, . . PY-351A, B , C , D PY-352A, B. C, C - e
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- Plant Protection I.., EQUIPMENT . -
AVAILABILITY , TAG OR FOR INSPECTION SQ REPORT ITDi , IDENTIFICATION IN FIELD FILE NO. ACCESS 0 PIES 28 . JC-002A/JC-002A-1/ Later NSS S-ICE-5d PC-103 /PC-103-1/ SPARE / PS7A-A, JC-0023/JC-0023-1/ PC-104/PC-104-1/ SPARE /PSFA-B JC-002C/JC-002C-1/PC-105 / SPARE / SPARE /PSTA-C, JC-002D/ JC-00 2D-1/PC-106 / SPARE / SPARE / PSFA-D 29 JA-002A/JA-Ob2A-1 .. Later NSSS-ICE-5e JA-00 23/JA-002B-1 - JA-002C/JA-002C-1 JA-002D/JA-002D-1 30 PA-103/PA-103-1, PA-105 Later , NSSS-ICE-5f PA-104/PA-104-1, PA-106 31 TY-3 51X-1. TY-3 51Y-1, Later NSSS-ICE-5g TY-303X-1. TY-303Y-1 PY-1023A-3, PY-1023A-4 C. LY-110Y-1, LY-101Y-2 PY-10133-3, PY-1013B-4 TY-35 2Y-1. TY-352X-1, PY-102A-3, PY-102A-4 LY-1113A-3, LY-1113A-4 JY-001A, JY-001A-1 PY-1023-3, PY-1033-4 PY-1013A-3, PY-1013A-4 LY-1123B-3, LY-1123B-4 32 JY-001C, JY-001D Later NS SS-ICE-5h JY-002A, JY-002A-1 ,,
. LY-1123A-3, LY-1123A-4 '.
LY-110X-1, LY-110X-2 LY-1133-3, LY-113B-4 , PY-10233-3, PY-10233-4 ,
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(.: SEISMIC QUALIFICATION SI:MMARY , SYSTEM: Nelear Ins trumentation .
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, EQUIPMENT AVAILABILITY - TAC OR FOR INSPECTION SQ REPORT ITIM IDENTIFICATION IN FIELD FILE NO. ACCES SORIES 1 JI-RC-0003 A Tes NSSS-ICE-8-2 JI-RC-0004A JI-RC-0003B JI-RC-00043 JI-RC-0003 C , JI-RC-0004 C 8 JI-RC-0003D . '#- . JI-RC-0004D . JI-RC-0001A -' -l JI-RC-00 01B S JI-RC-00 01C ~ JI-RC-00 01D .-- . 2 JR-RC-0002A Yes NSSS-ICE-9-1 JR-RC-0002B
.F JR-RC-4002 C
(. JR-RC-000 2D 3 , JR-RC-0001 Yes NS SS-ICE-9-2 4 Nuclear Instrumene I.at er NSSS-ICE-13 - De tector , 5 Nuclear Instrument Later NS SS-ICE-14 - Preamplifier
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..e liATEPJORD SES UNIT NO. 3
(, , $ SEISMIC OUALITICATION
SUMMARY
SYS"EM: Reactor Coolant , IQUIPMENT AVAILABILITY TAG OR FOR INSPECTION SQ REPORT I TD'. IDENTITICATION IN TIELD TILE NO. ACC'ES SORIES 1 TT-il2CA, CB, CC, CD No NSSS-ICE-51 TT-122CA, 'CB , CC, CD TT-ll2HA, HB, HC, E TT-122HA, HB , BC, HD ~ PI-101 A, PI-101B , PI-101't ' 2 Yes NSSS-ICE-8-1 , PI-101D, LI-110X, LI-110Y 3 TI-1C 2HA, TI-102HB , Yes NS SS-ICE-8-2 TI-102HC, TI-102E TI-102CA, TI-102CB
- TI-102CC, TI-102CD PI-102A, PI-102B , PI-102C, PI-102D 4 IR-102HA, TR-102CA Yes NS S S-ICE-9-1, 5 LR-110X, PR-102A Yes N3SS-ICE-9-2 i 6 TE-ll1X, TE-121X Yes NSSS-ICE-10-1 TE-112 C A, CB , CC, CD TE-122CA, CB, CC, CD .
TE-112HA, HB , HC, E TE-122HA, BB , HC, E - 7 PT-100X, Y Tes NS SS-ICE-l i.-l PT-101A, B, C, D PT-102A, B , C D ** PT-103, 105
- 8 LT-110X, Y Tes NSSS-ICE-ll-2 9 PT-104, 106 Tes NSS S-ICE-11-6 o
10 PS-224X, Y, Z Tes ' NSSS-ICE-16
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NO.
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OF EQUIPtENT NO. REPORT NO. LW3 ACCEPTANCE NO. TAC NO. , A30 Flow Indicating Swit ch SQ-IC-4 Qualification LW3-1855-79 (Walver) FIS-AC-5004-S SQ-IC-4A Testing in Progress LW3-1345-81 Test Repo rt December 4,1981 R3-580-1 LW3-818-80 i R3-288A-1 August 12, 1980 I A31 " " " " FIS-AC-5006 S A32 " " " " FIS-AC-5010 3 A33 -" " " i FIS-AC-5011 S A34 FIS-AC-5012 S A3 5 '" + " " - " Fis-AC-5013 S A36 " " l' u u FIS-AC-5030 AS A3 7 " " " " FIS-AC-5030 BS A38 ," " " " FIS-AC-5010 cs CI " " " " FIS-AC-5040 AS C2 " " " " FIS-AC-5040 ns e
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-PURCilASE GdDER: NY 403485 P VENDOR: ITT BARTON PO lit.H CENERAL DESCRIPTION SQRT FILE VENIX)R SEISHIC [
NO. OF EQUIPIENT N O. REPORT NO. LW3 ACCEPTANCE NO. TAC HO. . A 39 Flow Inlicat ing Swit cl,i SQ-lC-4 Qualification LW3-1855-79 (Waiver) FIS-CC-5070 AS S Sy-IC-4A Testing in Progrens LW 3-13 i5-81 i Test Hepo rt December 74,1981 I R3-580-1 LW3-818-80 R3-288A-1 August !? 1980 r A4 0 " " " " FIS-CC-5070 BS A41 " " " " FIS-CC-5070 CS i A4 2 FIS-CC-5770 AS A4 3 " " " " FIS-CC-5770 Als A4 4 , .i FIS-CC-5770 A2S A45 " " " " FIS-CC-5770 BS A4 b FIS-CC-5770 B1S c, A4 7 " " " " FIS-CC-5770 B78 A4 8
- FIS-CC-5770 CS A4 " " " "
FIS-CC-5710 Cls
e, , e O SI'EC I FICATION: 1564.421 O O - SilEET 5 0F.10 , PilHCII ASE ORDER: NY 403485 . VENIX111: ITT BARTON PU 11 EH , CENERAL DESCRIPTION SQRT FILE VENDOR SEISHIC No. OF EQUIPMENT 14 0 . REPORT NO. LW3 ACCEPTANCE NO. TAC HO. .- A50 Flow Indicating Swit ch SQ-IC-4 Qualification LW3-1855-79 (Walver) FIS-CC-5770 C2S SQ-IC-4A Testing in Progress LW3-1345-81 Te st Repo rt Ditcember 24,1981 R3-580-1 LW3-818-80 R3-288A-1 Augu st 12, 1980 A51 FIS-CC-5770 DS A57 " " " " FIS-CC-5770 Dis Il e _ l' A5 3 " " " " FIS-CC-5770 D2S A80 Level Switch " " " LS-MS-03tl S A81 " " " " a LS-MS-03)2 AS A82 " " " " LS-HS-0312 BS A83 " " " " LS-HS-0313 AS A84 " " " 1 ." LS-MS-0313 BS l C3 Pressure Swit ch * " " PS-NC-0940 AS t C4 " " a a pg NC-0941 BS O . 9
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, SPEC I FICAT ION: 15(4.421 SilEET 6 0F'10 PURCllASE ORDER: NY 403485 -
VENIM)R: ITT BARTON . PO ITEN GF*'ERAL DESCRIPTION SQRT FILE VENDOR SEISHIC HO. OF EQU1PE NT N O. REPORT NO. LW3 ACCEPTANCE NO. TAC HO. C5 Pressure Swit ch SQ-IC-4 QtnIification LW3-1855-79 (Weiver) PS-NC-0942 AS SQ-IC-4A Testing in Progress LW3-1345-81 Te st Repo rt December 24,1981 R3-580-1 LW3-818-80 ' R3-288A-1 August 12, 1980 C6 " " " PS-NC-0943 BS C7 " " " " ps.3c-0944 As C8 " ' " " " PS-NC-0945 us . l C9 "
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E6 Pressure Swit ch SQ-I C-4 Quali f ication LW3-1355-79 (Waiver) PS-CC-3083 D S Q- IC-4 A Testing in Progress. LW3-1345-81 Test Repo rt Decemi,er 24,1981 R3-580-1 LW3-818-80 f H3-288A-1 August 12, 1980 E1 " " " "
, PS-CC-3034 A
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PS-CC-3084 n
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PS-CC-3084 C ElO " " " PS-CC-3084 D El1 " * " " " PS-CC-3086 E12 '- " " " P SI A-9 740 A E13 " " " " PSIA-9740 8 1 " " " Level Indicator *LI-r9-7123 AS
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- SQ-IC-4A Te st ing in Progress LW3-1345-81 Te st Re po rt December 24,1981 R3-580-1 LW3-818-80 R3-288A-1 August 12, 1980 A58 FIS-CC-7651 B3 ;
A59 " " " " FIS-CC-7750 AS i
" " l A60 " "
Fl.9-CC-7750 RS , Abt ) " ' FIS-CC-7850 AS A62 " " " "
.' FIS-CC-7850 ns A63 " " " "
FIS-CC-7850 CS ___.I A64 " " " " FIS-CD-2202 A A65 " " " " FIS-Ck)-2202B Pre ssure Switch " " PS-SI-3149 A , PS-St-3149 0 9
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'l R3-580-1 LW3-818-80 i R3-288A-1 August 12, 1980 s' " " "
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- PS-Cll-0234 Z i
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g SPEC I FI CAT IO N- 1564.4 02A SilEET t OF > - I PURCllASE ORDER: NY 403642 VENDOR: ITT tlARTON ! i PO ITEtt CENERAL DESCRilrr!ON SQRT FILE VENDOR SEISNIC in. OF EQUIPMENT NO. REPORT NO. IR3 ACCEPTANCE NO. TAC NO. _ A01 low Dif ferential Pressure Trans- SQ- 1C-4 9 Qualification Attachment to DPT-ilV-506 7 AS mitter Testing in Pro!ress Le tter 1M3-111-78 Seismic Qualif. Test Procedu re O de IND N05991 ,
. Document Number .
999.5002.2 A02 DPT-ilV-5067 BS A03 DPT-ilV-5068 AS A04 DPT-IIV-5068 ns A05 DPT-ilv-510 5 AS A06 DPT-ilV-5105 as I A09 DPT-ilV-5270 A10 DPT-ilV-52 71 AS Ali " " " " DPT-liv-5 2 71 n s A12 DPr-IIV-5272 AS 5e
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.; . DPT-ilV-5274 us Al8 DPT-ilV-5275 AS A19 DPT-ilV-5275 BS A20 DPT-IIV.-5276 AS A21 " " " "
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V E NI)OR : 1 IT llAR~ ION ' e j PO ITEH GENERAL DESCRIPTION SQRT FILZ VENDOR SEISHIC 4 N00 0F EQUIPHENT NO. REPORT No. LW3 ACCEPTANCE NO. TAC No. A23 Low Differential Pressure 'hrans- SQ-IC-48 Qualification At t achine nt to DPT-IIV-5277 BS I mitter Testing in Progress Letter LW3-111-78 l Seismic Qualif. Test Proced ure j' Co<l e IND N05991
- Neument Numbe r r 999.5002.2
- A2's " " "' "
FT-IIV-5065 AS A25 . " FT-ilV-5065 BS i l A26 " " "* " FT-ilV-5066 AS . A21 "
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FT-ilV-5066 BS ' 1 A28 " " " " FT-ilv-5294 S ; I e D e e e
ENCLOSURE 3 SEISMIC QUALIFICATION REVIEW TEAM RE-AUDIT FOLLOW UP Attachment (1) Seismic Qualification Completion Schedule October 15, 1982 i 1, I J
]
A rr/CHMEt) ? .g RESPONSE TO CE/ PLANT ENGINEERING CONFIRMATORY ITEMS FROM WATERFORD UNIT #3 SQRT RE-AUDIT ITEM COMMENTS / RESPONSE GENERIC Comment: It was noticed that during the review of NSSS-PE-10 (Deborating Ion Exchanger), NSSS-PE-15 (Purification Filter) and NSSS-PE-33 (Holdup Tank), nozzle loads were negelected in the stress analysis. This seems to be a c'neric pattern. , Response - Nozzle loads for this equipment (seismic category tanks, HXS, Filters and Ion Exchangers) were origd' ally simulated in the seismic analyses by .acreasing the sesimic acceleration loading imposed on these components. This imulation was considered to be conservative beca; < ~. the component supports were judged to be more highly loaded than they would be if the - appropriate seismic and nozzle loads were considered. In response to the SQRT audit c-qcern, a follow-on effort has been,,nitiated to confirm that the original approach was conservative. All of the design repor* , for the applicable CE equipment have been reviewed and nozzle loacs have been directly evaluated to determine their effect on component supports. In all cases, the original support loadings were more severe. l All components are also being evaluated to confirm that i nozzle-to-shell juncture stresses are within acceptable levels. This effort will r completed :hortly and tne results of the evaluatio. 4111 be forvarded.
' GENERIC Comment l' Status of equipment not yet seismically qualified and their qualification schedule should be provided to -
NRC. This status should be submitted monthly until completion of qualification of all safety related l equipment.
Response
Status is given on Attacnment (2) {
ITEM COMMENTS / RESPONSE
~
ITEM NO.NSSS-1 Ccmment SQRT NO. NSSS-PE-14 SA MAKEUP PUMP 1. Explain basis for load cases 4 & 5 and show that SPECIFIC ITEM: PUMP B they are conservative. Resoonse Load Case 4 is " nozzle plus impeller loads in the x-di recti on ". Load Case 5 is " nozzle plus irpeller loads in the z-di rection". CE has reviewed these loading cases in detail end confirms that these loadings encompass the most severedirection possible for the app-lication of nozzle loads Comment
- 2. Explain load combinations used .or computing bolting stress and show that they are conservative.
Response
The load combinations used for computing boit stresses include those loads from seismic accelerations in both - transverse directions (note that a vertical accele-ration would have no effect on the bolts), inpeller loads, and nozzfe loads in the most severe direction. CE has reviewed these loads and confirms that they are conservative. ITEM NO. NSSS 2 Comment , SQRT NO. NSSS-PE-25' BORIC ACID TANK CIRC. 1. Provide certification that the computer VALVE calculations based on Engineering Standard ES100 SPECFIC ITEM: Rev. B dated 4/8/75 have been verified. 3CH-F171B
Response
CE has contacted the vendor on this issue and is currently awaiting a reply. T54 s reply is exsected before 10/31/82. Comment l l 2. Confirm that deflections :alculated in Seismic l Analysis for Order 1-46610 dated April 3,1976 for l tag number CH-511 will not interfere witn valve ' Closure. l Resconse Same as Previous Response.
~ _. _.. -- --
ITEM COMMENTS / RESPONSE ITEM NO. NSSS 5 _ Comment SQRT No. NSSS-PE-52 FW CONTROL VALVE Verification of computer program ES100, Rev. S (?/8/75) SPECIFIED ITEM: is being performed for item NSSS-PE-25. Results teill 5FW-FM834 . also be applicable here.
Response
CE has contacted the vendor on this issue and is currently awaiting a reply. This reply is expected before 10/31/82. 9 0 m 4 0 y -- -- - c w a e ry+ w- +-, , . 3m+ w e5- y--- -g , ----7 +w w 9 - -+---y- r y--yy
RESPuNSE TO OUTSTANDING ISSUES DE7 ELOPED AT TriE LP&L SQRT AUDIT FOR NSSS I&C EQUIPMEN-ITEM COMMENTS / RESPONSE . ITEM NO. NSSS-7 Comment
" The test on the indicator shows a 5% variation between-hC R 1.
the reading before and after test. The spec rr r'i red SPECIFIC ITEM: PI-101B 1.5% variation. Why was the indicator operability variation accepted?
- Response As explained at the SQRT Audit, the specified 1 1/2% tecuired v Jacy is a purchase specification, but is not meant to account for earthquake - induced uncertainties. These uncertainties are reviewed for acceptability by an Instrument Uncertainty Analysis. This analysis is to be perfortned on all safety-related applications of the Sigma 1151 and 1251 indicators. This analysis will be perfonned using the 5%
uncertainty found in the current documentation. The Uncertainty Analysis will be completed for the Sigma ~ indicators by January 14, 1983. Coment ,
- 2. Provide i spectra at the location of the instrument in the panel.
Resoonse Closed - See Ebasco Let'ter LW3-1131-82 dated 8/31/82. ITEM NO. NSSS-6 Coment
- 1. Verify by means of test data that operability of resistor
^ 5S tPTC Input card was der:enstrated during the test.
SPECIFIED ITEM: Resoonse Letter, W. J. Ritter - Westinghouse, Industry Electronics Division, to T. A. MacNair - Combustion Engineering, I&CE Department; Subject - NCI Resistor Card Seumic Operability Doc.:'nentation, dated September 10,1982 (attached). Coment
- 2. Detennine if loose cables in cabinet will be tied dcwn at a later date (supply date). Indicate procedures to secure cables in cabinet.
Resoonse Closed. See Fishback & Moore procedure CP-307 page 5 cf 23. Also, Ebasco letter from Wills to DeBevin dated 9/2/82.
l ITEM COMMENTS / RESPONSE 1 TEM NO. NSSS-12 Comment j
- 1. The CEDM which houses the transmitter was tested biaxially, DM kD 'd TCH P0 ITION but only in one horizontal axis. This was based en the ZNDICATOR .
assumption that the CEDM is symmetrical about the vertical SPECIFIED ITEM: axis. While this may be true for the CEDM, it is not true for the transmitter, and there is no as.curance of seismic qualification. An investigation revealed that this oversight was caught and transmitter qualification for subsequent nuclear projects included testing in two arthogonal horizontal axes. These subsequent tests were performed at levels substantially higher than those required for Waterford 3. The r'eed switch design was the same as Waterford 3. This strongly suggests an adequate seismic design for the Waterford 3 transmitter. Receipt of a test report con-firming the above will close this issue.
Response
Combustion Engineering Nuclear Laboratories Seismic Test Report iTR-ESE-442 for ANPP 150" Reed Switch Position Transmitter. E 9 l -- - - - - - - --
I lesry Ele:n:ni:s civ:sion Westinghouse Industrial Control Electric Corporation Olvisions 200 sea onve September 10, 1982 o Ha a rc.csn:s Pinsourgn Fennsylvania 15238
'412)782 1730 ,
Combustion Engineering, Inc. Nuclear Division , ' 1000 Prospect Hill Rd. Windsor, CT. 06095 Attention: Mr. T. MacNair
Subject:
Louisiana Power & Light Waterford SES Unit No. 3 C.E. P.O. 9403341-9270 (W) IED W8000 Seismic Qualification Review Team Audit Item NSSS 6 NCI SORT No. NSSS ICE-5A Resistor Card
. Reviewer: R. W. Macek Audit Date: Sept. 1, 1982
Reference:
Westinghouse E12ctric Corp. Seismic Test Report - WCAP 8828 Seismic Operability Demmstration Testing of the Westinghouse IED 7300 Series Process Instrumentation Bistables Gen #:emen: The subject audit concluded with one action for Westinghouse Industry Electrorics Division (WIED) as follows:
" Verify by means of test data that operability of resistor input card was demonstrated during the test".
Mr. Macek noted that WCAP 8828 included the NCI card in its equipment listing, ) Table 2-1, demonstrating the cards inclusion in the test. He also noted there was no direct mention of, or data to show, the cards operability during the
. test.
Westinghouse stated that the evidence of NCI operability could be provided but it would be in the nature of raw data, i.e. block diagram sketches, schematic sketches, copies of strip chart recordings and explanations showing linkage bet-ween WCAP 8828, the NCI card, signal nar2s, sketches and recordings. ha
Combustion Engineering Page September 10, 1982 The followinng is a list of attachments to this letter which will serve to demonstrate oper;oility of the NCI card: Attachment A. B' nek diagram of circuit'y in Card Frame #1 Attachment B. Schematic of Card Frame #1 Wiring Attachment C. Strip Chart recording of NCI outputs Attachment A defines, in block diagram form, the circuitry of card frame #1. Attachment B defines the hardware and wiring which implements the block diagram. Attachment C shows strip chart recordings of signals described in Attachments A
& B.
The relationship of itc! card output, signal name and recorder / pen number are as follows: NCI Outout Signal Recorder No. Pen No. TD/411 A A TLL 2 3 TD/411E TC 2 4 TD/412A TAVG 2 5 TD/411B OPSP 2 6 . TD/411C OTSP 2 7 In Attachment C, the signal on Pen !2 was purposely changed in order to vary the input to bistables to demonstrate that they change state. The signals on recorder pens 3,4,5 & 6 are not functionally affected by the signal on Pen #2, and therefore, remain at a steady state value. The signal on Pen #7 is func-tionally affected and, therefore, moves as expected. The Attachment C recording - was run during the seismic test and showed no anomalies. Therefore, the operabi ity of the NCI card is demonstrated. If I can be of any further service, please advise. Very truly yours,
//7?? o /
7/Vt44MV ' W. J. Ri tter Projects Director WJR:msb cc: Mr. J. W. Veirs - Combustion Engineering Mr. L. Karl - (W) IED r
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E v.c fiOV 3 01531 ARIZONA NUCLEAR POWER PROJE^T 150" Reed Swi:ch Position ' Transmitter and Litton E ectrica Connector SE SM C QUAL 710A".0N 'IES" . ; Sine Sweep Testing ; est Report TR-ESE-642 NUCLEARLABORATORY' i s POWER i=, SYSTEMS l
C&fBUSTION ENGINEERD'G DEVEIDFMENT DEPARDE.T TEST REPORT SEISMIC QUALIFICATION TESTING SYSIDi 80 REEC SWITG POSITION TRANSMITTER AND LITION EIECTRICAL CONhTCIOR ARIZONA NUCLEAR POWER PROJECT - PAID VERDE NUCLEAR GENERATING STATIONS 1, 2, AND 3 777009 PREPARED BY: (2/v . (46 W REVIEWED BY: '
/ /b p K. H. iiaslinger g REVIDED BY: IWid6 o((/[4[,
Quality Assurartce DOCLET NO. : TR-ESE-442 DATE OF ISSUE: b(( m Test Request Nr. SF40 d l
TABLE OF CONIST3 SECTION TITLE PAGE NO.
~
1.0 Introduction 1 2.0 Sm mary , 1 2.1 Sine Sweep Testing i 2.2 Seismic Qualification Testing i 3.0 objectives 2 3.1 Sine Sweep Testing 2 3.2 Seismic Qualifi w c.. Testing . 2 4.0 Description of Reed Switch Position Transmitter 2 (RSFI) . 4.1 RSFI 2 . 4.2 Litton Electrical Connector 3 5.0 Test Description 3 5.1 Mechanical Test Set-UP 3-5.2 Instnenentation Set-Up 4 , 5.3 Sine Sweep Test Procedure 6 5.4 RSFI Electrical Perfonnance Monitoring 7
- 5. 5. RSPT Inspection Requirements 7 5.6 Simulation of Seismic Test Enviro:nent 8
~
5.7 Test Procedure, Test Matrix 9 6.0 Discussion and Results 10 l 6.1 Sine Sweep Testing 10 i 6.2 Seismic Qualification Testing 13 7.0 References 16 8.0 Appendices i E-ESE-M2
TABLE OF CDNTENIS (cont'd)
- PAGE NO.
APPENDIX A - Electrical And Functional Inspection Sheets _ A-1 APPE CIX B - log Sheets B-1 APPENDIX C
' Results: Static Ioad Deflection Tests and C-1 First Mode Dynamic Test e
6 e e l em l l 11 tr.-ESE-442
LIST OF FIGLEES DE CRIPTION PAGE NO. FIGURE NO. 1 Reed Switch Fosition Transmitter 18 2A, B ANPP RSFT Seismic Qualification Test 19 Instrunentation Iocations 3 Vibration Control and Data Acquisition System 21 Sine Sweep Testing
~ Typical Input Listing - Sine Sweep Test 22 4
5A, L , C Typical Sine Sweep Traces - Transfer Function 23 Test File RSSN02 - 0.02 g's Excitation Typical Sine Sweep Traces - Strain Frequency 26 6 Response Plots - 0.02 g's Excitation 7 Determination of Modal Damping Properties from 27 - Blown-Up Sine Sweep Traces , Comparison of Experimental and Analytical Mode 28 8 Shapes - First Mode 9 Ccmparison of Experinental and Analytical Mode -29 Shapes - Second Mode Ccrnparison of Experinental and Analytical Mode 30 10 Shapes - Third Mode OBE Recuired Response Spectra AhTP RSFr 31 11 Qualification Test - 2% Damping SSE Recuired Response Spectra ANPP RSFr 32 12 Qualification Test - 2% Damping
. 13 Vibration Control and Data Analysis Instrumentation - 33 Block Diagram Shock Response Spectrun Testing Block Diagram for Monitorin of RSFT Electric 34 14 Output During Seismic Qualigication
& Test l l l Typical Input Listing - Shock Response Spectrum 35 15 Test - ANPP SSE Event I
l l iii TF.-ESP.-442 J
( l LIST OF FIGURES (cont'd) FIG 1RE NO. DESGIFITON PAGE NO. 16 Position of Test Specimens During Test 36 Orientations 1-4/ Top View 17 Horizontal Table Time History Run 26, SSE Event 37 18 Strain and RSFI Time Histories, OBE Event Test 38 Orientation 3 19 Strain and RSPT Time Histories, SSE Event Test 39 Orientation 1 20A Horizontal and Vertical Test Response Spectra 40 OBE Event / Test Orientation 1 - Run Nos. 4 & 5 20B Horizontal and Vertical Test Response Spectra 41 OBE Event / Test Orientation 1 - Run Nos. 6 & 7 20C Horizontal and Vertical Test Response Spectra 42 OBE Event / Test Orientation 1 - Run No. 8, Test Orientation 2 - Run No.13 20D Horizontal and Vertical Test Response Spectra 43 OBE Event / Test Orientation 3 - Run No. 20, . Test Orientation 4 - Run No. 27 21A Horizontal and Vertical Test Response Specti 44 SSE Event / Test Orientation 1 - Run No. 9, Test Orientation 2 - Run No.11 21B Horizontal and Vertical Test Response Spectra ~45 SSE Event / Test Orientation 3 - Re.1 No. 26, Test Orientation 4 - Run No. 33
~
22 Horizontal and Vertical Table Time Histories 46 OBE and SSE Event / Test Orientation 1 , Response-Spectra at Different Shroud Elevations 47 23 OBE ivent/ Orientation 1, 2% Damping 24 Response Spectra at Different Shroud Elevations 48 SSE Event / Orientation 1, 2% Damping iv 3-ESE-02
LIST OF FIGURES (cont'd) FIGURE NO. DESCRIFITON PAGE NO. 25 Acceleration Time Histories at Different Shroud 49 Elevations OBE Event / Orientation 1 26 Acceleration Time Histories at Different Shroud 50 Elevations SSE Event / Orientation 1 LIST OF TABLES TABLE NO. DESCRIPTION PAGE NO. l 1 Sumary of Results .02g Excitation Sweeps 51 Test File RSSN02 2 Stumary of Results .05g Excitation Sweeps 52 l Test File RSSN05 1 3 Sumary of Modal T$ansfer Functions - Sine Sweep 53 Testing 4 Sumary of Modal Strain Iavels - Sine Sweep Testing 54 5 Modal Damping Properties - Sine Sweep Testing 55 6 Strain 14vels and RSFT Electrical Perfomance 56 l
- Seismic OBE and SSE Testing l List of Equipnent and Instru:nentation 57 7
l l . l l v ~7-ESE-c2 _i
1.0 Ih'TRODUCHON ne 150" Reed Switch Position Transmitter (RSFI) and the Litton connector are electrical devices which nust function in an environ-nent of high temeprature, radiation, humidity and vibration during normal plant operation. In addition, as a Class 1E electrical coc:- ponent, the instrunent must perform adequately during seismic environ-ments up to SSE intensities as transmitted up to its mounting location (namely, the CEEM shroud) in a plant. The subject report describes the procedures which were undertaken to demonstrate the RSFI's ability to withstand the seismic intensities stipulated for the ANPP reactor when it is ins'talled in a representative CEM. The test specimens had already undergcne temperature and radia-tion aging. 2.0 SLM4ARY 2.1 Sine Sween Testing .
~
Sine sweep tests confirmed the analytically predicted dynamic behavior (natural frequencies) of the ANPP type CEDM. Tnis fact gave assurance that the su'bsequently conducted qualification effort would address the worst seismic response condition for the ANPP reactor. . The large amount of frequency, damping and mode shape data reported in this document will serve for future correlation efforts with analytical models. 2.2 Seismic Qualification Testing The two RSFI samples as installed in a representative ANPP type CEM were exposed to a sufficient ntrnber of biaxial " random" multi-
~
frequency input motions of intensities greater than the required OBE and SSE response spectra. The RSPTs were tested in four orientatic% to allow for their asymnetric design. No adverse transients of failure modes in the electrical performance of the RSPTs were observed in any of the ntrnerous tests. Therefore, the conducted test is proof that the RSFT assembly meets the seismic requirements imposed by the References 2 and 10. 1 3 ,SE-l.42 J
3.0 03JECTIVES 3.1 Sine'Sweeo Testing
'Ihe objective of the sine sweep test was to identify the dynamic -
characteristics of the RSFT support structure; namely, of the ANFP type CEDM with the longest nozzle. Natural frequencies and associated mode shapes, as well as modal damping parameters were to be obtained prior to the qualification tests for correlation with analytical predictions. 3.2 Seismic Qualification Testing
'Ihe objective of this program was to seismically qualify the ANFP RSFT and the associated Litton electrical connector for commrcial service in accordance with the purchaser's requirements -
of References 3 and 4. Proof was to be established that the RSFT design would remain functienal when installed at its permanent location during or following a seismic event of an intensity up to SSE magnitudes. The RSFT was to be exposed to a minimum of five OBE events and one DEE event following the appropriate tem-perature and radiationaging test programs. 4.0 EQUIPMENT DESCRIPTION 4.1 RSFT
'Ihe production RSPT is a transducer device used to determine the position of the CEA within the reactor core. The instrument is housed in a stainless steel tube within the shroud which is pesi-tiened adjacent to' the extension shaft upper pressure housing of a CEDM.
2 3 -ESE-u.: a
he production RSPT is essentially a voltage divider network comprised of an array of magnetically actuated reed switches wired to a series chain of resistors. We reed switches, resis-
- tors, and wire are mounted on an extruded plastic strip at precise 1.5 inch intervals. A permanent magnet attached to the top of -
the extension shaft generates the magnetic flux necessary to actuate and deactuate the switches yielding voltage signals proporational to the CEA position. Bree additional separate circuits provide contact closures which indicate the Upper Elec-trical Limit, lower Electrical Limit, and Dropped CEA position. We RSFI is fabricated in compliance with the drawing of Ref-erence 8 and specifications of Reference 7. A 150" full length RSPT has been randomly selected from the. pro-duction line for qualification testing. This test specimen has
- already undergonethermal and radiation aging. .
l i 4.2~ Litten Electrical Connectors The ccrcponent is a bayonnet locking electrical connector providing the interface connection between the head area cabling and the RSPT. 'The cable penetrations are designed to seal against fluid entry into the connector. The head area cabling connector is the Litton CIR06-CE-20-33S straight plug. The mating box moun:ing receptacle which is attached to the RSPT is the Litton CIR02-CE-20-33P. 5.0 TEST DESCRIPTION . 5.1 Mechanical Test set-Up e A full-size 150-inch Control Rod Drive Mechanism (representative of the ANPP design), including the drive shaft, water, conduit and 3 ~T-ES E-!42
.2
2 RSFIs (Serial Nos. 597 and 604), were assembled onto the seismic simulation fixture. For this purpose, a special test nczzle had been designed and fabricated. The test set-up simulated the longest CEIM nozzle which, by analysis, had been shown to yield the highest CEM response characteristics. . For the sine sweep, as well as the seismic qualification tests, the hydraulic actuator of the seismic shaker system was set at a 45 angle, thus providing excitations of similar magnitudes to both~ axes. Although the CEIN itself is synmetric about its . vertical. axis, the RSPTs are not, thus,in accordance with the Guidelines of Reference 2, four test orientations were required. This was acccmplished by rotating the test nozzle plus CEI24 structure once by 90 and by switching the two RSPI samples in each of the two nozzle orientations. Figure 16 depicts the four test orientations. The two RSPT samples provided for the , test were inserted in the CEDi shroud and clamped into place. The actuating magnet was attached to the drive shaft and was located near the top position inside the upper pressure housing. f 5.2 Instru entation Set-Up . TW control accelerometers, mounted in a mutually perpendicular Arrangement to the base plate (which simulated the reactor head elevation) were used to monitor the excitation levels in the horizontal and vertical axes. Figure 1 indicates the strain gauge locations at the test nozzle which is the highest stressed ccmponent of the CEI24 design. The stress levels at this location, although not a criterion for the RSPT qualification, were used as an index for the intensity of the seismic event and to help avoid overtesting (failure) by correlating ceasured stress values to analytically predicted ones. 4 ~7.-ESE-u.2 1
The respcase accelerometers indicated in Figure I were used to monitor CEDM deflections during sine sweep testing. Accelerometer locations 9, 7, 5, and 3 were also recorded on magnetic tape . Muring the seismic qualification program to be later displayed in the form of time histories and/or response spectra. All strain gauges (1/4 Bridge Hook-itp) and accelerometers were connected over the replay panel to the patch panel of the Digital Vibration Control System. For signal conditioning of the strain gauges, the Unholtz Dickie, Type R, Charge / Voltage Amplifiers were used. Unholtz Dickie, Type H, Charge Amplifiers were used
- for the response accelerometers and the model 2216-X units for the tuo control accelerometers.
Selected CEDM nozzle strain gauges were monitored on the visi-corder during preliminary and actual test runs. The RSPT elec- . trical performance was monitored on the visicorder during all qualification phases. For the sine sweep testing, the "SN21T Versica - 04" software package of the digital vibration control system was used. This program allows the monitoring of 4 channels of data simultaneously. For synthesis and on-line analysis of the generated seismic envirements, the "SS20T, 3.0 Decade" software package of the digital vibration control system was used. During the tests, selected transducer signals were recorded on a.7-channel tape recorder. Test response spectra of the table input or CEDI can- . ponent motions were then developed off the tape by playback into analysis sof.tware portion of the "SS20T" package. 5 TR-ESE-C':
f Doct:nented strain measurements are accurate within 5%, and the acceleration measurements within 10% of indication. All accelero-meters had been calibrated within the last 12 months of testing. One non-critical response accelerometer, which showed erroneous indications, we.s replaced during the early phase of the test . program. . , 5.3 Sine Sweep Test Procedure The "SN21T Version - 04" software package of the digital vibration control system was employed for the tests. Figure 4 is a typical l listing of an input file. For interpretation of the various input parameters, Reference 12 is to be used. I i I The C-E sinusoidal vibration control system, in conjunction with . the MfS hydraulic actuator and control units (See Figure 3), is . a closed loop, digital system that provides four-channel, multi-strategy control for performing a variety of swept-sine vibration tests. The system accepts analog input from the seismic table, digitizes the analog data, and continuously controls the amplitude of the resulting control signal so.that it matches the amplitude of the specified reference spectrum. The control signal amplitude i ! is regulated by controlling the amplitude and frequency of a sinusoidal drive signal that is generated by a programrable frequency synthesizer. During the test program, the horizontal table motion was controlled using channel A of the D.V.C. system. The remaining channels B, C, and D monitored selected, calibrated transducer signals and l ' stored them on disc. In this fashion, while maintaining constant acceleration input amplitude over a frequency range as vide as 1 1 I to 33 Hertz, frequency response data was accumulated for all t 6 TE-ESE-c.2
monitoring locations in consecutive sweep cycles. De data was later retrieved frcm the disc and displayed in a suited manner as phase, response amplitude or transfer function versus fre-
'quency. At the ccr::pletion of the test program, all pertinent files were transferred to tape NL-014 and stored at the Bldg. 5 data center. We developed hard copies, along with the reduced data, are stored in the Nuclear laboratories, Bldg. 2, Records Room.
5.4 RSM Electrical Performance Monitoring With the magnet held in a fixed position (close to the full with-drawn position of CEA travel), the voltage output signal.c of both RSMs were recorded on a Visicorder oscillograph and also stored on tape during all seismic test phases of test orientations 3 and 4. Figure 14 renders a block diagram of the basic monitoring scheme. De resolution of the oscillograph recorder was sufficient to detect any transient ups$t conditions or voltage signal changes down to five millivolts. 5.5 RSPT Incoection Recuirements he operational specifications and the inspection requirements of the RSM position indication and the limit switch circuits are outlined in Sections 4.0 and 6.5 of Refe:ence 10, respectively. Prior to and following the seismic qualification test programs,
- the electrical and functional characteristics of the RSM assembly were inspected under laboratory ambient conditions in ccepliance '
- with Section 6.5 of the reference test procedure. The results of inspections gre recorded on the pertinent data sheets and are l
included in Appendix A of this report. l l l 7
~R-ESE-442 J
5.6 Simulation of Seismic Test Environment The test specimens were subjected to 32 seconds of simultaneous horizontal and vertical inputs of randem wavefom motion. This random waveform consisted of frequencies spaced - 1/6 octave apart.over the frequency range of 1 Hertz to 25 . Hertz as necessary, to envelope the Required Response Spectra of Figures 11 & 12. The technique used to synthesize the shock , spectrum was to generate a series of wavelets at discrete fre-quencies (spaced 1/6 octave apart within the desired frequency , range). . The occurrence of these wavelets at each frequency (within the available time frame of 32 seconds) was specified in an arbitrary (randcm) fashion and the amplitude in g's for each wavelet was controlled by the Required Response Spectrum 1 (RRS). At least 3 wavelets, spaced randomly throughout the event, were used at each sixth octave frequency close to the . CEDM natural frequencies. The Digital Vibration Control System was used to sum up all the wavelet parameters and to produce a cmposite wavefom that contained energy at all frequencies across the band. At a Icw test level, this wavefom was then converted into shaker table motion by the shaker control units. - Initial 11y, the program automatically approximated the amplitude of each wavelet assuming that the transfer function of the shaker system is flat. The shock response spectrum of the table response wavefom (in horizontal axis only) was then analyzed and compared with the specified RRS. The difference between the two spectra was then used to adjust autcmatically the wavelet amplitudes and to thereby compensate the drive wavefom. This process was repeated until acceptable agreement had been demonstrated. Next, the output level was increased to arrive at the OBE and the DBE test levels. Following each increase in test level, several steps of synthesis were normily required to arrive at a satis-
, factory drive si.gnal.
8 TR-ESF.-u.2 {
In addition to the on-line analysis of the horizontal table motions, both horizontal and vertical control accelerometer response signals were stored on tape and analyzed later over a
~
frequency range of 1-50 Hertz using the "SS20T, 3.0 Decade" software package. Figure 15 shows a listing of the input - file for the SSE event analysis. For interpretation of the various input parameters, Reference 14 is to be used. The software capabilities were verified in accordance with the Q.A. requirements as doctmented in Reference 15. Figure 17 depicts a horizontal table time history for Test Run 26 (SSE event). The duration of this event was 32-seconds. The maxinnu value of this acceleration time history (approxi- ' mately 0.7 g's) is representative of the actual Zero Period l Amplitude (ZPA) level reached during this event which easily exceeded the requirements of 0.4 g's (see Figure 12). The character of the wave font reflects the superposition of low, medium, and high frequency pulses which resulted in the gen-eration of a "randca" type, multifrequency waveform similar to those of actual earthquakes. The required low frequency excitations for the high ANP" response spectrum peak (at about 2 hertz) are noticeable even in this acceleration trace.
. 5.7 Test Procedure. Test Matrix
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For more detailed guidelines about the test performance, refer to the test procedure of Reference 10. A listing of all data runs is enclosec*as Appendix B to this test report. 9 ~E-ESE-!.C _.._. --_________J
( 6.0 DISCUSSION AND RESULTS 6.1 Sine' Sween Testing Tables 1 through 5, along with Figures 5 through 10, surarize - the results obtained from the sine sweep test. Appendix B renders the complete Test Matrix. Initial low lewl sine sweep testing verified the analytically predicted natural frequencies or interest. The experimental frequencies of 2.32, ~ 9.2, and ~ 11.6 Hertz compare favorably with the theoretical values of 2.39, 10.08 and 11 Hertz for vibration modes 1, 2, and 3, respectively. Slight variations in these experimental frequencies with test level were observed especially for the somewhat non-linearly responding vibration modes 2 and 3. Figure 5 exhibits a series of transfer function
- plots developed for all 9 accelerometer locations along the CEN height. The three resonance modes can clearly be discerned.
The transfer function amplitudes at these resonances were taken from all available frequency response graphs and are listed in Tables 1, 2, and 3, along with damping and strain level infor. ration. Figures 8, 9, and 10 render ccmparisons of experimental and analytical mode shapes. For the purpose of this illustration, "the deflections are shown with similar amplitudes. However, no attempt was made here to match the actual test levels analytically. Generally, the mode shapes agree quite well. But, it is also noted that the transfer function levels vary with test intensity, a fact which reflects the variation of damping with test level (especially modes two and threa), as well as a certain amount of scatter between repeat test runs. For these. reasons, one must view the entire range of test results, rather than using a single test run for possible input to model correlation efforts or
extrapolation of results 'to other plants or higher excitation levels. Figure 7 shows some blown-up plots of resonance peaks. These - graphs were used to determine the modal critical damping properties employing the half- power point technique. af c/cr = 2f x 100 n . where c/c r= Critical Damping Ratio in (%) of = Width (in Hertz) of Resonance Peak at 0.707 times Peak Amplitude Value f = Resonance Frequency in Gertz) , n l t For a variety of transducerclocations, modal damping properties l were obtained, averaged, and listed in Tables 1, 2, and t i
- 5. First m:>de damping values varied between 2.2 and 3.09 percent of critical. The two percent value assumed in the CEDM analyses appears semesat conservative, however, based on this data, three percent could not be justified.
Second mode damping ranged between 3.5 and almost 6 percene. Surprisingly, this variation showed up when results taken on different test days were compared. The damping values obtained for a vide range of excitation levels (.05 to .25 g's - Table 5), - on a single day, is quite consistent. Apparently, the CEDM l stnicture condition (e.g. looseness of coilstack and rotation) asaffected67testlevels,canchange. 11 TR-ESE-u.2
Third mode da= ping values ranged frcra 2.2 to 3.3 percent of critical. It is of interest to note here that the AFPP CFDM has no additional tie between the upper pressure housing and shroud. This tie, which exists for the TVA and WPSS plant,-has the effect of eliminating one mode and cochining the second and . third ANPP modes into one. . 1 Modal Strain levels are sunnarized in Tables 1, 2, and 4. For correlation with analytically predicted stress levels, one must
~
determine the associated deflections by converting transfer function levels into displacements. Considering test file RSSNO2 (Table 1), this is done as follows: ACC/9/ Horizontal Control Ace = 59.39 (g/g) - Acceleration level = Transfer Fet x Excitation
= 59.39 x 0.02 = 1.19 (g's) .
Deflection Amplitude = 9.8 x g = 9.8 x 1.19 = 2.16 (inches) 2
= f2 2.32 j
Ihe associated maximtra nozzle strain = 175 uc or 81 pc/ inch { deflection at CEDM Top Girst Mode). Following the seismic qualification program, static load deflec-l tion tests (incrementally deflect CEM top and monitor strain
' gang s 7. & 8), as well as simple dynamic tests (manually excite first mode), were conducted to verify the observed CFRf strain versus deflection ratio. The detailed results given in Appendix i
l , C confirm the shaker table data. I 1 8 l 1 12 ~R-ESE-u.2 1
i I 6.2 Seismic Qualification Testing he ANFP reactor design calls for 87 CEDMs with 16 different nozzle lengths. Earlier analyses has shown that the CEDM type with the longest nozzle would tend to respond in.the most - critical manner. Berefore, this nozzle condition was selected for testing. Be stipulated seismic intensities for the reactor head elevation are shown in Figures 11 and 12 for the OBE and the SSE event, respectively. It had been decided earlier to perform the tests with the hydraulic actuator set up at.a 45 angle with the horizontal plane, thereby providing equal input
- motions in the vertical axis and in the horizontal axis. During the tests, the horizontal control accelercrneter was used for the synthesis of the random type waveforms. He Required Response Spectra (RRS) used for the synthesis represented the envelope of the vertical RRS and. the horizontal RRS, whereby the latter was constructed frcxn two horizontal spectra (using the Root-Sum-
~
o f-the-Square technique). Figure 13 shows a diagram of the instrumentation hook-up and control logic. De RSPIs were placed inside the CEDM shroud and connected to recording equipment as shown in Figure 14. he RSPT locations during the four test orientations are iden-i tified on Figure 16. During the course of the test program, the RSPTs were exposed
- to at least 30 and 10 seismic disturbances, each intensity range equal to at least that of the OBE and the SSE type earth- '
quakes, respectively. Be official test log is enclosed as Appendix B, hich includes a minimum of 5 OBE and 1 SSE events in each test orientation. In all test cases, no transient upset f or anomalous conditions were found in the RSPT signal traces. 13 TR-ESE ':.2 (
r Tne sig.al loss observed during one test run was due to a mon-itoring cable break (cable was inadequately secured at pcrer supp1v). The inspections conducted prior to and following ' the seismic qualification tests revealed no changes in the functional characteristics of the two specimens as provided for testing (Appe'ndix A). Figure 17 shows the synthesized table acceleration time history for an SSE event. Since the Required Response Spectrum has a high spectrun peak at about 2 Hertz, the waveform clearly reflects' these large, low frequency ccxnponents superimposed by higher frequency contributions. Typical strain and ESPI time histories are shown for the OBE and the SSE events in Figures 18 and 19, respectively. With the exception of a small " ripple" (less than 3 milliseconds)* all RSPI monitoring traces are undisturbed. The strain gauges reflect the response characteristics of the CEat and reveal an overwhelming response (proportional to deflectiod) at its fundamental frequency. Peak CE21 component strain levels are listed in Table 6 for all test runs. The maxinun values (635 pc for OBE and 770 uc for . SSE events) are well within material allombles. Figure 20 renders OBE Test Response Spectra for all four test orientations. The analyses of the table motions was performed at 1/6th octave increnents over a frequency range of 1 to 50 Hertz. In all cases, the graphs demcastrate complete envelep-
- ment of the Required Re'sponse Spectra (vertical 1!nes show actual test intensity, spectrum curve reflects RRS). A seismic table resonance was responsible for the high spectrum peak i
l above 30 Hertz. 14 :-ES E-l.J.2
l
. I 1
Horizontal and Vertical Test Response Spectra are shown in Figure 21 for the SSE event. Again, complete envelopnent of the requirement is demonstrated. Additional table acceleration ~ time histories are given in Figure 22. In crder to captbre' the resulting seismic intensities at the - RSFT mounting locations (CEIN shroud), four response accelero-meters Nos. 3, 5, 7, and 9 were monitored and recorded on tape. Unfortunately, the tape channel recording the CEDM top motions was set up improperly which resulted in attenuation of higher frequency signal ccxnponents. Be test response spectra sh'cun in Figures 23 and 24 capture the true seismic intensities at all four shroud elevations, whereby the Acc 9 curve was extra-polated using data from the other 3 locations. Rese response spectra (2% damping) exemplify the large CEDM response at about 2.3 Hertz. Some contribution frca CEDM Mode 2 is apparent at i 10 Hertz. he response spectrum peaks above 30 Hertz are due
- to the table resonance mentioned earlier.
( l Figures 25 and 26 sunmarize the acceleration time histories as recorded at the four shroud elevations during OBE and SSE event simulations. Accelercmeter 3, 5, and 7 traces are basically unfiltered and some of the higher acceleration spikes may actually be caused by impacts (e.g. coilstack shifting at Acc 3 location) . However, this fact would not influence the response spectrum character across the frequency range of interest (1-
- 30 Hertz) which is shown in Figures 23 and 24.
Prior to seismic testing, RSPI Sample No. 604 was removed. frdm test loop 7A after 1730 hours of thermal aging at 375'? for a '
~
performance check and a visual inspection. h e visual inspection ' showed scme deterioration of the silgard encapsulant and the
- diallyl phthalate mounting strip. Based on this inspection, it t
I i l 15 'I?-ESE-L42 j
( - was decided to waive future visual inspections of both RSFI's until the entire qualification program had been completed. Therefore, details of the above visual inspection and the
- final visual inspection will be docunented in the final ' '
qualification report. l ! 7.0 RDEENCES
- 1. Im Standard Number 323, 1974,. General Guide for Qualifying Class 1 Electrical Equipnent for Nuclear Power Generating Stations.
- 2. IEEE Standard Number 344, 1975, Guide for Seismic Qualification of Class 1 Electrical Equipment for Nuclear Power Generating l Stations.
i l *
- 3. Specification Number SYS80-MD-0311, Revision 02, Design Specifi-cation for Control Element Drive c
Mechanism.
- 4. Specification Number 14273 ^O-0311, Revision 02, Project Design Specification for CEEH for Arizona Nuclear Power Project - Palo .
Verde Nuclear Generating Stations,1, 2, and 3.
- 5. Document Number QC-28-05 ER N?tH4 CEm/ PILED 4 Design Control Procedure, dated 9/19/74. g
- 6. Docunent Number 0000(HR.E-070, Revision 0, Procedure for Control of Measuring and Test Equipnent. .
- 7. Manufacturing Specification for the Class 1E Reed Switch Position Transmitter, Specification Nunber 00000-ESE-203, Revision 01.
l I l 8. Drawing CE}f-E-R1000, Revision 02, Reed Switch Assembly. [ i 16 3-ESE- '.2
r
- 9. Drawing D-STD-162-003, Revision 01, Magnet Assenbly and Details.
- 10. Test Procedure 00000-ESE-323, " Seismic Qualification Testing System 80 RSFT and Litton Electrical Connector - ANPP,"
K. H. Haslinger, July 31, 1981.
- 11. Test Report TR-ESE-285, "SCE CEDH-RSPT Seismic Qualification Test," K. H. Haslinger, May 15, 1979.
- 12. Operating Manual for Sinusoidal Vibration Control System," Time /
~
Data Division. Docunent 1923-5124, December,.1977.
- 13. Q.A. Verification of Time / Data Sinusoidal Vibration Control Code Version 04, C-E Analysis Report Nos. S669-100 and S669-101.
- 14. Operating Manual for Shock Spectrun Synthesis and Analysis System, Time /DataDivision,Documegt 1973-5127, July, 1977, TR-ESE-424.
- 15. J. P. 'fhanpson, "Q.A. Verification of 3.0 Decade WAE Synthesized SRS Analysis Program," S863-113, dated May 2, 1979. ,
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AFFENDIX C RESULTS: STATIC 10AD DEFECHON TESTS AND FIRST ? ODE DMAM. C 'IEST 9 e 5 4 C-1 TF-ESE-442
Static Deflection Tests Using a pull wire arrangement (connected to the CEM top), the CEEM was deflected incrementally up to 5 inch total displacement. H e deflection at the CEDM top was measured by an LM with 5 inch travel. He strain gauges (Nos. 7 and 8) were comected to a balance box and measured by a digital readout unit. ne results from the static load deflection te'sts are su::marized on page C-3. A linear deflection characteristic was observed with a strain to deflection ratio of about 111 pc/in, whereby the strain was measured 4 inches above the base plate and the deflection at the CEIH top. First Mode Dynamic Test Strain gauges 7 and 8 were connected over two dynamic signal conditioning uni.ts (same as described in main report) to the visicorder readout device. The 5" stroke L u was displayed on a third visio -der channel. ne CEEN was set into vibratory motion by exciting it manual;v above the coilstack. ne resulting CEEH top motions, as well as the nozzic strain levels were then recorded on calibrated visicorder traces and converted into engineering units. We figure on page C-4 shcus a typical visicorder trace and 'an averagnozzle strain of about 240 pc per 2.41 inch top deflection (or 100 pc/in.) is observed. his value is slightly higher than those recorded for strain gauges 1 through 4 of the shaker table tests. n e differences may be explained by the fact that these two tests were n:n with the CEDM - set-up in two different orientations and/or by some flexibility of the shaker table suspension system. List of Test Equipnent in addition to items listed in Table 7. LVITf Schaevitz Model M/N 5000 HPD, S/N 192, Calibrated 1/16/80. Dicital Voltmeter MM200, C-E EL-259, Chlibrated 2/10/81. Strain Read-Out Unit Vishay VE-20A, S/N 25026, Perfomance Check 9/81. 1 l l l C-2 E-ESE-22 i
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- . SEISHIC qllA101FICATION I COHPl.ETl0H SCllEDULE h HSSS-ICE I INSTAL.l.ATION i.0./ SPEC EQUIPHENT SQRT Fil.E HO. QUALIFICATION SCllEDUI.E SCllEI)Hl.E (TAG HOS.)
l 9 t.01141 (P.O.) See ,ttachment Al HSSS-ICE-5 Equipment has been qualified Equipment I nn t al l eil l 9210-ICE-0005 according to vendor Rev.01 HSSS-ICE-Sn ' (Westinghouse). Proprietary (Spec.) thru 3h reports will be released to LP&L pending resolution of proprietary agreement between Westinghouse and LP&L. ..'. (See C-CE-7987 of 10/4/82) HSSS-ICE-9-1 anme P.O. and OrigJnal seismic test Spec. as above See attachment A2 HSSS-ICE-9-2 (Westinghoue i EL991) . Equipment installed. not* approved Westinghouse
- recubraltted with new test
- report (fEL1348) C-E
; technical review completed
~
but adminsitrative work not completed.
- QTR-1010 and QTR-1008 N, should replace Ei.991 as th<
applicable qualification references for the Veri- -
.. Trak.Rccofd'ers. EL1348 is contained in QTR-1010.
Retesting by Westitighouse vp is required. Testing i$ N ,
.. completion.is. scheduled for ,
May 1, 198.3.. "EI 8, $
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i TABIE 1 SUtt%RY OF RESULTS .02g EXCITATION S'wiEPS TEST FIII: RSSN02 MODAL STRAIN AMI1UDES
! ODES 1 2 3 STRAIN GAUGE 2.3 Hz - 9 Hz -12 Hz (uc)
S.G. 10 93.51 10.11 48.09 36.55 S.G. 9 S.G. 6 141.7 S.G. 5 _ S.G. 4 186.07 9.16 18.89 S.G. 3 164.31 9.16 18.32 S.G. 2 171.76 10.31 18.32 i S.G. I 174.62 l 10.31 l 18.89 l FIRST MODE DA'! PING MODAL W.NSFER WCTIONS (g/g) (.g) l ACC 9 59.39 , 6.90 6.70 l 2.7 . ACC 8 50.0 4.58 9.06 ( ACC 7 l 39.79 2.19 12.40 2.6 ACC 6 33.87
.95 15.08 !
ACC 5 23.38 2.19 15.46 l 2.4 ACC 4 3.05 13.36 l l ' ACC 3 8.87 3.45 9.77 f 6.86 ACC 2 6.32 3.07 ACC 1 3.54 2.20 3.80 i l e i 4 51 TR-ESE-442
i . TABI2 2
SUMMARY
OF RESULTS .05g EXCITATION SWEEPS TEST FILE: RSSN05 . MO:KL TRANSFER RHCTION ATLI1UDES FODE l ACC 1 l ACC 2 l ACC 3 ACC 4 ACC 5 ACC 6 ACC 7 ACC 8 ' ACC 9 1 2.8 4.6 7.0 - 17.4 25.5 30.1 38.8 43.-3 2 2.9 4.9 5.3 - 4.8 .5 6.3 7.7 18.9 ! 3 2.3 3.9~ 5.4 - 9.2 9.1 8.8 7.5 6.7 MODAL DATING VALUFS MODE ACC 5 ACC 6 ACC 7 ACC 8 ACC 9 AVG. 1 2.54 2.69 2.54 2.65 2.61 2.61 , 2 3.86 - 2.76 4.04 3.39 3.51 3 1.95 l 2.11 2.51 - - 2.19 FODAL STRAIN A9LI'11? DES i FODE S.G.1lS.G.2 S.G. 3 S.G. 4 S.G. 6 S.G. 9 1 360 367 347 377 293 61 2 '37 43 37 40 - - 3 23 23 23 23 - 25 l 52 TR-ESE-442
TABIE 3 SlM4ARY OF HOML TRANScrn FLHCi10NS - SINE S'a:.:.y TESTING EXCITATION MODE IEVEL (g) ACC 1 ' ACC 2 ACC 3 ACC 4 ACC 5 ACC 6 ACC 7 ACC 8 ACC 9 s 1 .02 l 2.77 4.43 6.41 10.80 15.77 l 22.28 27.44 34.13 41.49
.04 l 2.42 3.90 5.93 9.56 14.72l 20.55 26.10 31.84 36.43
.06 2.95 5.11 7.40 13.58 20.08 27.15 35.85 45.22 60.61
.08 20.36 1 34.23 52.01
.10 19.60 , 33.27 46.18
.12 l 18.83 31.74 40.15 2 .05 2.87 4.33 5.0 l 4.04 2.31 l 1.25 3.81 8.10 11.35 l .10 3.44 5.48 6.53 l 5.69 3.72l .98l 3.97 9.31 13.3 1 l .15 l 3.50 ' 5.58 6.50 l 6.12 4.48 l .86 4.52 9.29 15.16 .
.20 l l 5.77 l l l 3.81 l12.88
.25 5.66 l l 3.37 l11.73 I .
I I I 3 .05 l 2.12 3.85 l5.75 l 7.87 8.94 8.35 6.71 4.52 2.69
.10 l1.79 l 3.13 4.61 l 6.19 7.16l 6.87l 6.03 4.32l 3.74 .
.15 2.29 3.88 5.77 7.60 8.33 8.87l 6.63 4.99l 5.09
.20 4.62 5.19 3.75 l
i .25 3.69 4.25 2.60 ( Note: The Transfer Ftmetions are defined by the Ratio of Acceleration levels of the monitored Accelercreter over the Horizontal Control Accelercceter. 53 3-ESE-442
i TASIE 4
. SL*t4ARY OF MODAL SEAIN IIVELS SINE Skur TESTING EXCITATION .
! ODE 12 VEL (2) S.G. 1 S.G. 2 S.G. 3 S.G. 5 S.G. 6 S.G. 10 1 .02 132 136.5 127 117 101.7 76
.04 236 241 228 212 183 149
.06 472 492 460 427 l 366 283
.08 643 660 600 560 480 350
.10 790 810 740 690 580 420
.12 910 920 860 790 660 480 2 .05' 47 47 43 28 19 26
.10 93 96 88 55 l 34 46 .
.15 138 144 131 79 41 64
.20 162 165 150 96 51 90
.25 207 210 192 120 60 110
.05 29 29 26 15 9 69 3
.10 42 44 40 27 15 121
.15 74 75 70 43 21 203
.20 87 90 81 48 27 240
.25 96 99 84 51 27 230 l
Note: Strain values are listed in microinch/ inch 54 E-ESE-442
r TABLE 5 MODAL DAMPING PROPERTIES - SINE S'nIEP TESTING EXCITATION MODE LEVEL ACC 1 ACC 2 ACC 3 ACC 4 ACC 5 ACC 6 ACC 7 ACC 8 ACC 9 AVERAGE (g) 1 .02 3.15 3.05 3.10 3.05 l 3.12 3.09
.04 2.93 2.80 2.94 2.73 2.72 2.77 2.82
- .06 2.32 2.32 2.38 2.14 2.07 1.97 2.20 l .08 2.43 2.41 , 2.34 2.39
.10 2.32 2.48 l2.74 2.51 l .12 l 2.52 2.48 l3.14 2.71
- I I I i 2l .05 8.32 6.63 5.17 5.48 4.48 5.04I l 5.85
.10 l 1 l l l l
.15 l 4.93 4.82 l 5.09 4.86 5.05 l l l 4.55 l .20 l 5.96 l l ! l 5.96
.25 l 5.65 l l l 5.65 l l l 1 l l 3.45 3.33 3.08 3.08 l 3.48 l 3.28 3l .05 l l l ,
j .10 l 3.14 l3.19 3.47 3.28 3.19 3.17 I l 3.2'4 l .15 3.19 2.54 2.61 3.10 3.20 3.58 l 3.04
.20 2.19 l l l
i 2.19
.25 l 3.12 l l 3.12 Divping values are listed in Percent of Critical 55 E-ESE-i.42 . __.~ __ _ __ _ _ _ . . _ _ _ . . . . _ _ _ _ . . _ _ . _ _
J
TABLE 6 STRAIN LEVE1S AND RSPT ELECIRICAL FERIDM%NCE SEISMIC OBE AND SSE TESTING ELECIRICAL MEASURED S'IRAIN DATA-VISICORDER PERWANCE
- TEST TEST TAPE RUN S.G. 1 S.G. 3 S.G. 5 S.G. 10 RS?T 1 PSFr 2 ORIEN. DESCRIFFION NO. pc pc pc pc S/N 604 S/N 596 1 i OBE 1 4 625 600 550 340 OK OK 1 i OBE 2 5 625 600 550 350 1 OK I OK 1 i OBE 3 6 625 605 550 '
340 i OK i OK 1 1 OBE 4 7 635 605 550 335 I OK i OK 1 i OBE 5 8 625 605 550 l 340 i OK t OK 1 1 SSE 1 9 775 745 675 ' 405 i OK i OK 2 i SSE 1 11 1 755 ' 745 680 405 i OK I OK 2 i SSE 2 12 775 745 675 400 1 OK i OK 2 I OBE 1 13 620 600 550 335 I OK I OK 2 t OBE 2 1 14 625 600 555 ' 335 i OK i OK 600 550 330 OK i OK 2- 1 OBE 3 1 15 625 t 2 i OBE 4 1 16 625 600 550 340 t OK i OK - 605 555 335 i OK i OK 3 I OBE 5 1 17 625 I S.G. 7 S.G. 8 uc ut 3 I OBE 1 20 600 615 i i OK i OK 3 i OBE 2 1 21 600 625 I i i II)CSE iG.3LE 3 I OBE 3 1 22 610 635 I i OK I OK 3 I OBE 4 l 23 620 630 I i OK l OK 3 I OBE 5 1 24 615 630 I i OK i OK 3 l OBE 6 1 25 615 63 0 I i OK i OK 3 i SSE I 26 755 740 ' I I OK I OK 4 i OBE 1 1 27 760 740 1 I OK I OK 4 i OBE 2 ' 28 760 750 I I OK i OK 765 760 i OK i OK 4 i OBE 3 1 29 I ! 4 i OBE 4 6 30 770 760 i i OK i OK 4 i OBE 5 1 31 770 750 i i OK ; OK i OK ' OK 4 i OBE 6 32 770 750 4 4 i SSE , 33 765 ' 750 1 I i OK i OK Note: OBE Events for Test Orientation 4 inadvertently were run at SSE Intensity. 56 W i2E~LL2
. TABIE 7 I
LIST OF EQU11tGWF AND INSTRlWNFATION t Instrinnent Manufacturer ikxici Ntnnber Serial Ninnber Calibration Requirencnts Seismic Shaker Table M/itad Ilydraulic Shaker HIS 204.63 299 Shaker Controller MIS 406.llB 1094 Shaker Control thit MIS 436.llAB 463 Digital Vibration . P/N 2931-973 Unit C-E QA Verification of sof tware used Control System Time Data Corp. 1DV-25P , Control Accelerometers Unholtz Dickie 100-PA 492/493 , Per Manufacturer Oicek Unholtz Dickie 75 D2/PA 156/104-117 Per Manufacturer calibrated within Response Accelerometers ast 12 months Response Accelerometers Endevco 7701-100 AA15, AA16 Per Manufacturer , Signal Conditioners Unholtz Dickie 2216x 145/146 Perfonnance Qieck Giarge Anplifiers Unholtz Dickie D-2211 Type 2024-2027 Perfonnance Qicck Otarge/ Voltage Amps Unholtz Dickie D-22 R Type 2048-2053 Perfonnance Qicck ; Oscilloscope Tektronix 5000 Series Bil7232 Perfonnance Qicck
~
Strain Gauges Micro Heasurement WK-06-125AD-350 - Visicorder lioneywell 1858-07906 170401177 Signal Calibration Power Supply ' Power Mate or equal QRD15-1 1L-113 Tape Recorder Racal Store 7D D7 690/S Signal Calibration W -IN- 2 . 57
APPa' DIX A . ELECmICAL AND RECTIMAL INSPECTION SHED3 e e 9 l i 3 l l 1 i A-1 g_gg_gy
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e, acsr unvc-T s.. *. Acse unve-T so. FIGiHE 25 ACCEIF.IIATION Tit!E IIIS'IORIES AT DIFFERITTT SIIROtID EIF.VATIONS, OllE EVTAT ORIFATATION 1 E~f8E-#2 49 A
l ENCLOSURE 4 l SEISMIC QUALIFICATION REVIEW TEAM RE-AUDIT FOLLOW UP Attachment (1) Status of PE Confirmatory Items Attachment (2) Seismic Qualification Completion Schedule Attachment (3) Seismic Analyses of Muellor 3" Y-Type Strainer Attachment (4) ME-894 Certified Design Report of Horizontal Pump' i November 10, 1982 i k i l t.
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. l Attachment 1 Page 1 of 3 RESPONSE TO CE/ PLANT ENGINEERING CONFIRMATORY ITEMS FROM WATERFORD UNIT #3 SQRT RE-AUDIT l
4 ITEM' CCiMENTS/ RESPONSE GENERIC Coment: It was noticed that during the review of NSS-PE-10 i (Deborating Ion Exchanger), NSSS-PE-15 (Purification f Filter) and NSSS-PE-33 (Holdup Tank), nozzle loaris were , negelected in the stress analysis. This seems to be a ' generic pattern.
Response
Nozzle loads for this equipment (seismic category tanks, HXS, Filters and Ion Exchangers) were originally simulated in the seismic analyses by increasing the I seismic acceleration loading imposed on these components. This simulation was considered to be conservative because the component supports were judged to be more highly loaded than they would be if the appropriate siesmic and nozzle loads were considered. In response to the SQRT audit concern, a follow-on effort has been initiated to confirm that the original approach was conservative.
- All of the design reports for the applicable CE equipment have been reviewed and nozzle loads have been directly evaluated to determine their effect on I component supports. In all cases, the original support loadings were more severe.
All nozzle-to-shell juncture stresses were also l evaluted and found to be within acceptable levels. l
. GENERIC Coments Status of equipment not yet seismically qualified and i
their qualification schedule should be provided to NRC. This status should be submitted monthly until i completion of qualification of all safety related j l equipment. i j Resoonse l Status is given on Attchment (2) l l
r~ ---
/
Attachment 1 Page 2 of 3 COMMENTS / RESPONSE ITEM ITEM NO.NSSS-1 COMMENT SQRT NO. NSSS-PE-14 BA MAKEUP PUMP 1. Explain basis for load cases 4 & 5 and show that-SPECIFIC ITEM: PUMP B they are conservative. Resoonse Load Case 4 is " nozzle plus impeller loads in the x-di rection". Load Case 5 is " nozzle plus impeller loads in the z-direction". CE has reviewed these loading cases in detail and confirms that these loadings encompass the most severe direction possible for the - application of nozzle loads. Comment
- 2. Explain load combinations used for computing boltir.g stress and show that they are conservative.
Response
The load combinations used for computing bolt stresses include those loads from seismic accelerations in both ' transverse directions (note that 'a vertical accele-f'* ration would have no effect on the bolts), impeller loads, and nozzle loads in the most severe direction. CE has reviewed these loads and confirms that they are conservative. Item No. NSSS-2 Comment SQRT NO. N533!FE-25 Provide certification that the computer calculation BORIC ACID TANK CIRC. 1. based on Engineering Standard ES100, Rev. B dated VALVE SPECIFIC ITEM: 4/8/75 have been verified. 3CH-F1718
Response
CE has contacted the vendor on this issue and is currently awaiting a reply. This reply is expected before 11/30/82. Comment i
- 2. Confirm that deflections calculated in Seismic Analysis for Order 1 46610 dated' April 3,1976 for tag number CH-511 will not interfere with valve .
cl osure. 1 Resoonse Same as Previous Response.
(, s Attacnment 1 Page 2 of 3 < CDP.MENTS/ RESPONSE IIEM ITEM NO.NSSS-1 COMMENT SORT NO. NSSS-PE-14 BA MAKEUP PUMP 1. Explain basis for load cases 4 & 5 and show that-SPECIFIC ITEM: PUMP B they are conservative.
Response
Load Case 4 is " nozzle plus impeller loads in the x-di rection". Load Case 5 is " nozzle plus impeller loads in the z-direction". CE has reviewed these loading cases in detail and confirms that these loadings encompass the most severe direction possible for the - application of nozzle loads. Comment
- 2. Explain load combinations used for computing bolting stress and show that they are conservative.
Resconse The load combinations used for computing bolt stresses include those loads from seismic accelerations in both
transverse directions (note that 'a vertical accele-ration would have no effect on the bolts), icoeller loads, and nozzle loads in the most severe direction.
CE has reviewed these loads and confirms that they are conservative. Item No. NSSS-2 Cornent SORT NO. NSSS-PE-25 Provide certification that the computer calculation BORIC ACID TANK CIRC. 1. based on Engineering Standard ES100, Rev. B dated VALVE SPECIFIC ITEM: 4/8/75 have been verified. 3CH-F171B
Response
CE has contacted the vendor on this issue and is currently awaiting a reply. This reply is expected before 11/30/82. Comment
- 2. Confirm that deflections calculated in Seismic Analysis for Order 1 '6610 dated April 3,1976 for tag number CH-511 will not interfere with valve closure.
Resconse Same as Previous Response. t
F Attachment 1 Page 3 of 3 ITEM COMMENTS / RESPONSE ITEM NO. NSSS-5 Comment SQRT NO. RSSS-PE-52 FW CONTROL VALVE Verification of computer program ES100, Rev. B SPECIFIC ITEM: (4/8/75) performed for Item NSSS-PE-25. Results will SFW-FNE34 also be applicable here.
Response
CE has contacted the vendor on this issue and is currently awaiting a reply. This reply is expected before 11/30/82. 4 G G S e l .
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CERTIFICATION STATEMENT This Crane-Deming Figure 4066 Size 8x8x12 pump has been analyzed in accordance with Combustion Engineering Specification No. S yY0-PE-404 Rev. #00; ASME Boiler and Pressure vessel Code, Section III, Class 3,1974 Edition including Winter '75 Addenda; and accepted good practice in seismic stress analysis. The analysis shows that the pump is structurally a'dequate to withstand the specified loads and will perform its intended function during Upset and Faulted loads. Please note the limitation on resultant nozzle loads given in Section 4.6 of the report. 1 y c Ir - C. K. Mcdonald, Ph.D. , P. E. Alabama Registration No. 9586 September 25, 1981 (k hf( f'y .b 8p .. ..' ., ., 4. 4 ,., , jf,. Oh . *7,'\
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.e TABLE OF CONTENTS 1
- 1. INTRODUCTION
- 2.
SUMMARY
OF RESULTS 3
- 3. FREQUE,NCY ANALYSIS 4 3.1 Dynamic Model 4 3.2 Cocputer Analysis 7
- 4. LOADING CRITERIA 12 4.1 Seismic Loading 12 4.2 Individual Nozzle Loads ~ 13 4.3 Internal Pressure Leading 13 4.4 Shaft Torsional Loading 13
_. 4.5 Other Pump Normal Loads 13 4.6 Resultant Nozzle Loads 13
- 5. STRUCTURAL INTEGRITY ANALYSIS 15 5.1 Motor Hold Down Bolts 15 5.2 Pump Housing Hold Down Bolts 16' 5.3 Anchor Bolt Stresses 16 Shaft Stresses 17 5.4 5.5 Stresses in Support Frame 17 18 5.6 Casing / Frame Flange Analysis 5.7 Nozzle Analysis 18 5.8 Nozzle Flange Analysis 20 5.9 Pump Foot Stress 20 Continued...
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( l TABLE OF CONTENTS (Cont.)
- 6. FL7CTIONAL CAPA3ILITY ANALYSIS 21 6.1 Pu=p Bearing Loads 21 6.2 Flexible Coupling Analysis 22 6.3 Impeller Key Analysis 23 6.4 Impeller Clearance -
23 6.5 Shaft Mechanical Seal 24 Appendix A - Computer Output for Stress Analysis Appendix B - Nomenclature and Formulas Appendix C - Co=puter Output for Frequencies and Mode Shapes l Appendix D - ND Bearing Allowable Loads Appendix E - Member Properties l l i l i i l l' .
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,9
- 1. INTRODUCTION This report covers the seismic, stress, and deflection analysis of Crane-De=ing Figure 4066 Size 8 x 8 x 12 Pump. The analysis is directed t; ward proving both the structural integrity and functional capability of the pump.
A dynamic model is developed and a computer frequency analysis is made to obtain the frequencies of the assembly, as required by the specification. The pump is shown to be rigid. The nozzle loads are imposed on the computer model of the assembly and the resulting stresses and deflections are calculated. The stresses are then compared to the allowables given in the ASHI Code. The deflections ] are compared to operating clearances or other limiting criteria. The nozzles are analyzed for the max. nozzle loads.
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- The loeds given in the specification were re,duced somewhat, see Section 4.2 of the report.
, This pump casing is of complex geometry and has been well verified for l normal operation by service experience and hydrostatic tests. The seismic and nozzle loads impose negligible stress in the casing except at nozzle penetrations and flanges which have been analyzed in this report. This pump has a cast iron frame that cannot withstand nozzle loads. Thus, although the casing will withstand the individual nozzle loads given in Section 4.2, the resultant nozzle loads resolved to the intersection of the discharge / suction centerlines must be zero. l l _m._. _ . , . .
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? '4 2. SUMHARY OF RESULTS Ihe A su==ary of the stresses, deflections, and loads are given here.
actual values are given and ce= pared to the allowable valtas. Coreonents Actual Adlevable Motor Hold' Down Bolts Stress, PSI - Shear 4,010 10,000
- Tensile 7,436 20,000 8,021 20,000 Pu=p Hold Down Bolt Stress, PSI - Tensile 10,000
- Shear 2,202 Anchor Bolt Strcss, PSI - Shear 3,530 10,000 Tensile 4,969 20,000 Shaft Stress, PSI 12,272 -26,250 Frame Stress, PSI - 11,344 21,600 Pu=p Toot Stress, PSI 8,'501 12,500
- Maximum Nozzle Stress, PSI - Discharge 8,030 19,800
- Suction 11,667 19,800 816 20,253 l Pump Bearing Loads, Lbs. - Inboard 27,000
- Outboard 5,435 Flexible Coupling Misalignment, Radians .001 .017 2,489 12,000 Impeller Key Stress , PSI - Shear
.0062 .0065 Impeller Clearance, ' Inches 75,648 123,212*
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- Faulted, allowables given here, see detailed calculations for Upset Case. All other allowables are Upset allowables and are compared to Faulted actual values.
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J 3. FREQUENCY ANALYSIS A dynamic model is prepared and a computer frequency analysis is made to determine the assembly frequencies as required by the specification. A detailed discussion of the dynamic model and computer analysis is given below. . 3.1 Dynamic Model , The dynamic model which was developed for the frequency analysis is , shown in Figure 2, page 5. The joint numbers (enclosed in circles) and - member numbers are included to facilitate the computer input. Several assumptions were made in developing the model. These assumptions were l i made such that the model would be more flexible than the actual assembly. Thus, the frequencies predicted by the model vill be lower than the actual frequencies. Some of these assumptions are:
- 1. The bedplate is assumed to be supported only at the foundation bolts. This is true for upward forces but for downward forces the bedplate channel flanges are continuously supported.
- 2. The motor could help restrain the pump in the
. direction parallel to the shaft centerline by transmitting forces through the coupling. -
This is not included in the model since the coupling connection is not positive in that direc-tion. This is also not desirable since this would l
- i= pose thrust Ioads on the pump and motor bearings.
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Masses are lumped at joints in accordance with good practice in . seismic analysis. Most of the mass of the pump is lu= ped at Joints 9A and 11. Joint 9A is the centerline of the nozzles, i.e. where the discharge and suction nozzle centerlines intersect. The pump and motor casings are modeled by equivalent hollow beam sections. Members 27 through 48 represent the motor casing and Members - 20 through 26 and 61, 62, 63, and 67 represent the pump casing. I e 6M O ,e ooeeemn m * *
- d4 3.2 Cocputer Analysic The ec=puter analysis for the frequencies is perfor=ed by use of the ICIS-STRUDL co=puter program operating on an IBM 370/158 ce=puter.
Users manuals on the STRUDL program can be obtained from the Massachusetts Institute of Technology. The code has been well verified for frequency, calculations. These verification checks will be made available upon request . The detailed input data sheets are given on pages 8 through 11. These are believed to be self-explanatory. The motor and pump shaf t vary in cross section and are input accordingly. The analysis is made for the three dimensional frame. Thus, the model is assigned 15 degrees of freedom. However, only the first two frequencies
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in seismic conditions. The computer output is shown below. The lowest frequency .is seen to be - 40 .C.P.S. - The mode . shapes for the two modes are given in Appendix C. JOB ID - ME-894 JOB TITLE - CRANE CEMING FIGURE 4066 PUMP ACTIVE UNITS - LENGTH FORCE ANGLE TEMPERATURE TIME INCH L8 RAD DEGF SEC ACTIVE STRUCTURE TYPE - SPACE FRAME ACTIVE CGCRdINATES AXES XYZ EIGENVALUES MCDE -- EIGENVALUE- FR EQ UEN CY- ---PE R I OD------R AD I AN S--/ 1 0.632167D 05 0.4001620 02 0.2498990-01 0.251429D 03 2 0.4455530 06 0.1062350 03 C.9413050-02 0.6674970 03 t __
- Notes for Dynamic Seismic Analysis Course, by C. K. Mcdonald University of Alaba=a in Bir=ingham
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- 4. LOADING CRITERIA 4.1 Seismic Loading The lowest natural frequency of the pump system, including bedplate is 40 cp s .. The following loads exceed those given by the specification.
OBE SSE Horizontal *, I and Z 1.0g 1.5g Vertical .7g 1.0g The loads were applied to the center of mass of each individual pump com-ponent. The loads for all three directions are applied, as required by the specification. The stresses are then combined directly for all three directions, which is more conservative than the square-root-of-the-sum-of-the-squares method. The SRSS method is used in some cases. A computer analysis for the loading condition is made. The computer input is shown on page 14. The analysis is made for the following load cases. 1 .1.5g Lateral I Seismic
- 2. 1.5g Lateral Z Seismic
- 3. Ig Vertical Seismic
- 4. Nozzle plus Impeller Loads Load case 3 is ratioed by the proper factor to obtain net upward or down-i vard loads, as appropriate.
The computer model shown in Figure 2, page 5, which was used for the i frequency analysis is also used for t.'4e static seismic and nozzle load an-alysis. The joint and member input data is the same as for the frequency. analysis and is not repeated. The computer output data is given in Appendix A. a. e
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o ' fJ' 4.2 Individual Nozzle Loads The nozzle loads for the individual no::les, suction and discharge, are given in Paragraph 4.2.8 of the specification. These loads are listed below. However, it should be noted here that the ce=bined resultant loads at the centerline of the suction / discharge intersection must be limited as shown in Section 4.6 below. 8" Suction 8" Discharge Resultant Force, F , lbs 2,520 2,520 R Resultant Moment, Ft-lbs 6,304 6,304 4.3 Internal Pressure Loading The internal pressure design conditions are 150 psig at 2000F. 4.4 Shaft Torsional Leading . The motor horsepower is 60 at 1800 R.P.M. Thus, the shaft torque is: T = 63000(60) 2,100 in-lbs 1800 4.5 Other Pump Normal Loads ( The pump impeller is subjec ed to a 300 lbs radial and a 1000 lbs axial load during norual operation. 4.6 Resultant Nozzle Loads ! The pump was analy=ed for a set of resultant nozzle loads, resolved to the no==le centerline at Joint 9A on the computer model. However, it was found that the pump foot would be overstressed with these loads. Thus, the resultant nozzle loads at Joint 9A must be zero. Note that the pump foot, Section 5.9, is fully stressed with no resultant no::le loads. G S.6 a G O
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