ML20030C370
| ML20030C370 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 07/10/1981 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Faulkenberry B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, ANPP-18381-BSK, NUDOCS 8108260033 | |
| Download: ML20030C370 (7) | |
Text
{{#Wiki_filter:l i 4 j' k * }[Reporb N 50.55 .?FFliQ d DocketaNof)L50-5,2_8f;529/530 NGid4 V 2 EilEsM / b b ~ PHOENIX. AR62ON A 85036 P. O. BOX 21666 Jaly 10, 1981 ANPP-18381-BSK b y U. S. Nuclear Regulatory Commission S C Region V v ~ .c \\ c'j! Q,3 ]S Walnut Creek Flaza - Suite 202 1990 North California Boulevard 'g f Walnut Creek, California 94596 jQ / Attention: Mr. b. H. Faulkenberry, Chief Reactor Construction and [, [' . / / : ih - Engineering Support Branch 'x2
Subject:
Final Report, Revision 1 A 50.55(e) Potentially Reportable Deficiency Relating to Safety-Related Sway Struts File: 81-019-026 D.4.33.2
Reference:
(1) Telephone Conversation between R. Dodds and B. S. Kaplan on May 28, 1980 (DER 80-6) (2) Final Report, /NPP-15723, dated June 25, 1980
Dear Sir:
Attached, is Revision 1 of the final written report of the potentially reportable deficiency, under 10CFR50.55(e). This revision provides additional information which supports changing the previous reportable disposition to Not Reportable. A Code interpretation by ASME indicates that the assemblies are in compliance with design requirements. Therefore, it is concluded that this would not have constituted a significant safety condition. Very truly yours, k "t A;_c dn LLL E. E. Van Brunt, Jr. APS Vice President Nuclear Projects ANPP Project Director EEVBJr/BSK:ske TE.>7 Attachment f lil 8108260033 810710 PDR ADOCK 05000528 S PDR gj_.j l g
r-k), 94,., i 's U. S. Nuclear Regulatory Commission Attention: Mr. B. H. Faulkenberry, Chief ANPP-18381-BSK/ JAR July 10, 1981 Page 2 cc: Victor Stello, Jr., Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 A. C. Gehr Snell & Wilmer J. A. a iedel R. L. Robb D. B. Fasnacht W. E. Ide J. M. Allen A. C. Rogers J. A. Brand W. H. Wilson W. G. Bingham W. J. Stubblefield R. L. Patterson R. W. Welcher D. R. Hawkinson Bruce Myerson, Esq. Arizona C.nter for Law in the Public Interest 112 North Fifth Avenue Phoenix, Arizona 85003 Ms. Patricia Lee Hourihan 6413 South 26th Street Phoenix, Arizona 85040 l i J J e I 1 I
.,z, li FINAL REPORT, REVISION 1 POTENTIAL REPORTABLE DEFICIENCY 50.55(e) ARIZONA PUBLIC SERVICE COMPANY (APS) PVNGS UNIT NO. 1 I. Description of Deficiency During a Bechtel Power Corporation audit of the ITT Grinnell Corporation, Warren, Ohio, twelve (12) Figure 211 Size 1 and 2 Sway Strut Assemblies (Linear Compo-nent Standard Supports) were found to have fillet welds of 1/4". ASME Section III, Division 1, Subsection NF-3292 and Table NF-3132.1(b)-1 were interpreted at the time to require these assemblies to have a minimum fillet weld of 5/16". On June 25, 1980, a 10CFR50.55(e) Final Report, Revision 0, was transmitted to the NRC dealing with this subject indicating that a reportable condition existed because delivery of sway struts with 1/4" fillet welds rather than 5/16" fillet welds was made to the jobsite. Subsequently, information trans-mitted to Bechtel by ITT Grinnell (attached) indicate that this original interpretation could be modified to accept the 1/4" minimum fillet weld sizes as meeting ASME III requirements. Code inquiries by Tennessee Valley Authority and Consumer Power Corporation (ASME File NI-77-406) have resulted in a ruling by ASME con-cerning the size of the fillet welds. Grinnel Figure 211 Size 1 and 2 Sway Strut Assemblies with 1/4" fillet welds are in compliance with this ruling of the Code. II. Analysis of Safety Implications The Code interpretation indicates that this condition is not considered safety significant and that the assem-blies are in compliance with design requirements. III. Corrective Action Stop Work Notice 80-SW-3 was issued to prevent further installation of the discrepant struts, but will be closed based on the Code inquiry interpretation. Nonconformance Report P-A-1245 will be revised to change the disposition of the subject products from Reject to Use-As-Is.
b i TLF 1 ITTGrinnellCorporation 621 Dana Avenue, N. E. Warren, Ohio 44481 Telephone (216)3997566 June 4, 1981 Bechtel Power Corporation M #12.Mf/g) P.O. Box 60860 / Terminal Annex s t. } } Los Angeles, California 90060 Q C ~ s..u.o p-Attention: W. G. Bingham - Project Manager f3.. I-s - t-Subj ect: Palo Verde Nuclear Generating Station J~_- ,. m -- >~ ~ _M of,- --- --7 '*-.. Purchase Order 10407-13-PM-209/210 7 Zdu - t-- t
Reference:
Letter B/ITT-E-28680 Dated 6/23/80 --if I---. ' I _~~M, '. * ' * .$- 1 E I Gentlemen: ~ ...._ j ,7. ..~, in regards to Bechtel's Deficiency Evaluation Report #80-6 con:efning weld i sizes used in the fabrication of our Figure 211 sway struts, we hah 'p'er,forr.e3 f .I testing for the purpose of load rating. The results of this testirM s ggibulated below: E o I n't.- w. :.:~.. Size Rated Load Fa j lure lo1d. j i ,t A 650# 15,0 DOT T*r ~ B 1,500# 30,000# (*) C 4,500# 43,300# 1 8,000# 69,000# 2 11,630# 90,500# 3 15,700# 125,000# (*) No failure occurred. Please not that in no case was the weld in question the failure mechanism (fail-ure defined as material fracture). Attached are the latest copies of the ASME Code interpretation regarding weld size selected by load rating. Executin Offices! Providence, Rhode Island yn n- ., - ~, n.
e ht4 Po er Corporation ( tPage Two Based on the above, it is recomendet that Deficiency Evaluation Report #80-6 be dispositioned as not reportable and that Bechtel NCR P-A-1245 be cancelled. If there are any coments or questions, please feel free to contact us. Very truly yours, ITT GRINNELL CORPORATION /S.f.)nr):jifi D. E. McMillin Project Manager /rv attacheent cc: P. Stanish - Providence R. Russell - Warren B. Kelly - Providence
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Att: W. R. Bird E. L. K E *.s'.i L E H 's..cy,.y Subj ect: -Section III, Division 1 o v.rist NutstG Tabic NF-3132.1(b)-1 and NF-3292 U.W.BACE Ref: Your letter of October 23, 1977 R o town
- n. J. sos *. A K ASE reply letter of December S,1977
- u. n. en EssL[n AS'-!E File # NI 77-406 V.W.BuiLER
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- o. A.CANorm o dentlemen:
R. J. CETLUCH L J. CHotKIE w o.coty Further consideration of your above referenced inquiry has resulted in the 8.G. EARNHtART folloVir.; revised interpretations : O.R. GALLUP "] Question 1: If Class 1 linear support are designed by " experimental str s. R analysis" or by " load rating," does NF-3292 apply?
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M ;* E..:. n u.u v J. ticor r 1: coly 1: NF-3292 is applicabl s'to linear supports designed by any of the J H Mack ^ procedures pelwit.ted by NF 121 1(a) for the selection of permissible tyi.e: ',(g",Qy of welded joints. When the we ds are sized by analysis, NF-3292.1 provides the allowabic stress limits. F. N. 8/OstHiM ii. E. N OilT* 4,l ' W. O. PAh K E A Question 2: When NF-3292 applies, if fillet welds only are selected for R. F. R E COY fabrication, do the minimum site requirements of XVII-2432.1 applv? If A.T sLATT
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be satisfactory, can it, be used? Peolv 2: The minimum size requirements of XVII-2452.1 apply when the cc ponent,. support is designed by analysis when only fillet welds are used to ncke t he /, joints. 'Ihese minimum welds size requirements cre independent ofcalcultions,f and do not permit smaller veld sizes to be used even if shown to be acceptahl j For welded joints in con:ponents desip,ned by experimental stress analyns or c{ ' load rating, the tests as defined in NF-3250.1nd NF-3260 shall verify the adequacy and acceptability of the uc1J size selected. y 4' A -- S '9'ul.~i W6f U
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1 The American Society of Mechanical Engineers 3,f g. d e, ? Lt. New Yorx. N.Y.10017 e 212 644-7722 e TWX.710-5815267 ur. ice Ervesccring Center e 345.E 4: (D September 26, 1980 Tsnnesse Valley Authority 3' 'l' 'i ~ i. ~ W10D190 [,g i 3,, .-:i. c. ~j 1 V ' ' '400 Co==erce Aventie ~ ,..._.c..,..., y,,;.? Knoxville, TN 37902,, r g,t 3,, t ;
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Subject:
Section III, Division 1 ~ Table NF-3132.1(b)-1 an.1 NF-3292 Raf: Your letter of June 19, 1980 ASME File # NI 80-95 Centlemen: Our un'derstanding of the questions in your inquiry, and our repIles reiterate these of ASME File 4 NI 77-406, dated September 24, 1980, which are as follows: If Class 1 linear supports are designed by " experimental stress analysis" Question 1: er by " load rating," does NF-3292 apply? .3i'2. NF-3292 is applicable to linear supports designed by any of the procedures Reolv 1: for the selection of permissible types of welded joints. permitted by NF-31g.1(a)When the welds are sized by analysis, NF-3292.1 provides th When NF-3292 applies, if fillet welds only are selected for fabrication, Question 2_: do the mini =um size requirements of XVII-2452.1 apply? If the support is designed by satisfactory, can it be used?- cnalysis, and a smaller veld size is shown to be Ihe minimum site requirements of XVII-2452.1 apply when the component sup- ....Repiv 2: Ihese port is designed by analysis when only fillet welds are used to make the joint. minimum welds size requirements are independent of calculations and do not permit For welded joints in smaller veld sizes to be used even if shown to be acceptable. the tests as de-components designed oy experimental stress analysis or load rating, fined in NF-3250 and NF-3260 shall verify the adequacy and acceptability of the wc]i size selected. n-r_- Yottrs truly, .:- t.&,, /:& .' & k John M111 man':.. I Assistant $ccretary (212) 644-3049 -tASME procedures provide for reconsideratiori of this interpretatio'.when or if additio Further, persons aggrievec ey this available wheCh the inQuarer tJi etes minnt affect the snierptCtatioo Interpretatiott m3y apo0Al10 th0 CGQnt2 ant ASMC commettee or subcommitteo. As stated in the f oreword of Code documents. ASMt ORS not " approve."' Certify,* *rste." or "onoorse ' any stom. Construction propractary l device or actmty. I 7 ~ ~ ~ " " ' _}}