ML20005E589

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Advises That Insp of Plant Conducted on 890717-27 W/Nrc Mobile Nondestructive Testing Lab,Per Request.Violations & Unresolved Items Noted.Suggests That Licensee Be Requested to Review Unit 2 Activities for Similar Violations
ML20005E589
Person / Time
Site: Comanche Peak Luminant icon.png
Issue date: 08/31/1989
From: Boger B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To: Charemagne Grimes
Office of Nuclear Reactor Regulation
Shared Package
ML20005E588 List:
References
FOIA-89-428 NUDOCS 9001090022
Download: ML20005E589 (11)
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Text

{{#Wiki_filter:F . ' ' weg*g I+" [' UNiito sTAf ts ' s[ f NUCLEAR REGULATORY COMMISSION RE0lON I hh g os ALLENDALE ROAD I mNo oF PRU$slA. PENNSYLVANIA 1940. {O' SEP - 5 m AUG 3119H MEMORANDUM FOR: Christopher I. Grimes, Director m t> d J Comanche Peak Project Division Office of Special Projects j l FROM: Bruce A. Boger, Acting Director Division of Reactor Safety RI i

SUBJECT:

NRC NOE INDEPENDENT MEASUREMENTS INSPECTION AT COMANCHE PEAK, UNIT 1 i Per your request, we conducted an inspection with the NRC mobile nonde l testing laboratory at Comanche P?ak Unit I during the period July !? throug i 27, 1989. This inspection focused on preservice inspection (PSI), licensee actions to disposition construction deficiencies and the licensee's erosion-j corrosion program. Our inspection report is enclosed. Based on the inspection, performance of the PSI in In addition, we want to highlight the licensee's inadequate corrective ment. actions taken with regard to two different problems dealing with containment i penetrations. These findings led to identification of three violations and three unresolved items. The notice report) are included for your use. s of violation (Appendix A to the enclosed to regtew Comanche Peak Unit 2 activities for similar types of violat unreso'Ived issues. deficiencies are important. Timely identification and resolution of these types of We hope this independent measurement inspection and documentation f needs. issues identified in the Comanche Peak inspection.Please contact We offer our services in the future and solicit any comments or recommen regarding improvement of the NDE mobile laboratory program to better serve N needs. Bruce Boger, Acting Ofrector Division of Reactor Safety, RI cc w/ attachments: C. Y. Cheng, NRR .TH"~ttveNeTg~commanchePeak) BYrMs7RIV ~^'~ ~ H. Kerch, RI J. Strosnider, RI 90010900D2 900104 PDR FOIA GARDE 89-428 PDR \\

~~".... APPENDIX A 2 C. 10 CFR 50, Appendix B, Criterion XVI requires that deficiencies are promptly identified and corrected. Contrary to the above, the licensee did not correct deficiencies identi-fied in the fabrication of fuel transfer tube penetration welds. Fuel transfer tube penetration welds lA, IB, 2A and 28 were radiographed and rejected on June 3,1989 because of welding defects not acceptable by the applicable construction codes and specifications. The nonconforming condi-tions were documented by the licensee in NCR 89-04023, dated April 4, 1989. On June 20, 1989, Site Engineer 11.g inappropriately dispositioned NCR 89-04023, Rev. I " accept-a s-is." The Itcensee's basis for acceptance of the welds reited on stress analyses that are not technically acceptable substitutes for the required ASME III nondestructive examinations. This is a Severity Level IV violation. (SupplementII) Pursuant to the provisions of 10 CFR 2.201, Texas Utilities, Comanche Peak Unit 1 is hereby required to submit to this office within thirty days of the date of the letter which transmitted this Notice, a written statement or explenation in reply, including: (1) the corrective steps which have been taken and the results achieved; (2) corrective steps which will be taken to avoid further violations; and (3) the date when full compilance will be achieved. Where good cause is shown, consideration will be given to extending this response time.

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$lkO9<89 23:53 tRC R1 IOCKET ROQrt NO.(96 P002 b B- [ T $311.T.315.t' stT rtoN V NON!*$TRUCr VE EX AMINATION esamination on senelcontact surfaces in the range of inclusive, with respect to the perpendicular to the survature from 0.9 to 1.5 times the basic calibration en(ry surface. block diameter. For example, an 8 in. diameter curved block rney be used in calibrate the ca. (c) Durance Anp/hude Correction-Compensatioit amination on venel contact surfaces in the range of for the distance traversed by the ultrasonic baam as it i curyaturc from 't.2 to 12 in. diameters.The curvatute papes through the materialis provided by the use of rnnge from 0.94 in. to 20in. diameter requires 6 block the curves shown by Fig. T.$3S(s) or electronica!!y. ! tu Determ/norton of (d) The basic calibration block for examination of plinide correction curves shal tDonstructed byCuws ewivatures n indicateJ in Fig.1 33)(b). f - longitudinal welds shall be of essentially the same utiljaing tesponses from the basic calibratiori hole 7e8 described in T.53).2. he first point on the curve is nominal diameter as the part to be examined, except obtfined by placing the search unit as near as %A that for diameters greater than 20in., flat blocks maypossible, but not taas than % ves-nath or 2 in., qUA be used. whkhever is leu, from the calibratioit hole and T.533.2 8alc Callbretion linic (a) The basic cahbration hole shown in Fig. T. b '8h k $3)(a) shall be drilled parallel to the contact surfa ce of the basic calibration block or the component, he 9/ /7 location, depth, and diameter of this hole shall be h--4. /N'%,@ Mh-g obtained from the able in Fig.T.533(a). ~ (6) llowever, other calibration reflectors may be Y used, provided equivalent responses to that from the ron Twienwasa i mcw osittas basic cabbration hole are demonstrated. N T 534 surface Preparation ~ - $$ M I D E !$c"ne Y j,, ' g sict Lars4 T.534.1 Contact surfacca, ne finished contact surfaces shall be free from we!d spatter and any ""* - p.,,

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,,,go roughnen that would interfere w1th free movement of the search unit or impair the transmission of ul-1)...,,**"* " ' "j **-.... trasonic vibrations. t n (es0NTMs Or a V((*ParN a e e is T 534.2 Weld Surfacen. De weld surface shall be finished so they cannot mask or be confused with ,,-{f*d a@ ,L reflections from defects, and should merge smoothly into the surfaces of the adjacent base materials. . g '., / T 534.3 Base Material. he volume of base material yy through which the sound will travelin angle beam examination shall be tornf etely scanned Mth a poa mcemeu odaii+ cn l straight beam nearch unit to,&IscITef,c2 tors which mig'hi'a*Tre~cGlerpreta tion of angle beam results. This is not intended as an acceptance. rejection ex- "" aa,e og,.ia lv,,a n.,tew ge su *t tsw c ch a mina tion. ',Ma$le Lty'.L \\,N T.535 Angle Beam Method $,,ce];A - T 535.1 Calibration of Equipment _j~'*"" l' ' ' 'J! * (o) I'repency ne nominal frequency shall be l 2.25 Milz unless variables such as production (cishtas or a vst-rern e a 6 1 material grain structure require the use of other frequencies to assure adequate penetration. F10. h436(a) TYPICAL DISTANCE AMPt.lTU i i (b/ Beum Angle-The beam angte in the prod-CORRtCTION CURVE (ANGl.E BEAM METH001 uction material shall be in the rangt of 40 to 75 de6 (Dirtinnoe in elehths of a voo. path, l'or example, 14 is ' */s of a vee path.) 22 l

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/ stt acttt e the basic calibration block and in the component and ~ ~ correctin for the difference' [ The te crenc4 reflectors may be Y notches (which I a must sub equently be removed), an angle beam ~ s / fa) search unit acting as a reflector,or anyothw reflector which will aid in accomplishing the tranetw. sec.cn e t.; (/) Vesseh.-ne transfer method shall be used t' T; Y M

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.i.u.,a.u v. as a minimum, once for each welded joint for pipe D. j s is....,a4 5.. ..... t. sites 10 in. In diameter and over, and once for each 5 F10. T 535(b) TYPICAL DOUBT.E SEARCH UNIT ifl of weld for pipe less than loin. in diameter. TECHNIQUE FOR DETECTING LACK OF PENETRATION IN DE8LE. WELDED JolNTS T.$35.1 bamlnation Procedwt positioning for maxirnum response.%e galn control (a) Cmrege-Where possible, butt welds shall be i is then ut m this response is 75 percent of full screen esamined from both sides of the weld, usually from only one surface, on the cathode ray tube (CRT). This is the primary (3) ger,3ftMty level-he reference level eensitivity reference response. Without changing the galn, the search unit should be placed similarly at other for monitoring diwontinuitica is the primary ref. positions covering the expected examination distance etenc4 response corrected for distance by the dis-sance. amplitude curve or electronically, and modified range, and the corresponding responses marked on by the transfer method if used. When possible, the CRT sereen. These points are joined by a smooth line w hose length should cover the eaam! nation range scanning shall be performed at a sais setting of 2 (see Fig.T 535(a)). timeJ (6d B) the teference level sensitivity. (c) Aeference f.cel-ne reference Imlfor mon. (2) Electronic Distance Amplitude Correctiontf an electronic distance amplitude correction device is Itoring discontinuitles is the primary reference re. sponse, corrected for distance by the distance am. used, the primary reference response shall be plitude curve or electronically, modified by the equalized at 50 percent of fullCRT screen height over transfer method. the distance ringe to be employed in the enamination. y (d) Transfer Afethod-Transfer methods are used (d) Detection of Discontinuhles torallello the Weld toheime se mpoERs from the basic calibration (1) scanning Motion-The search unit shall be block and from the component. Transfer is ac* placed on the contact surface with the beam aimed at complished by noting the difference between re-about 90 deg to the weld and manipulatedlaterally sponses recched from the same reference reflectorin and longhudinally so the ultranome beam passes through all of the weld metal in t approachesof thebeamtothereflector, p different l (2) 1% Search Unit Technique-Techniques r a y 3 Y using two search units shown in Fig.T $35(b)may be g l g u' sed to detect lack of penetration in double welded b - l i ur toas.,fg* buttjoints. o MNbNN b -:7 (e) Detection of Discontinuities Trans erse to the Y Weld-Two uarch units shall be placed on the O contact surfaces adjacent to the Weld, one on each ilde, forming an angle of 45 des or less with the aals of the weld as shown in Fig.T.535(c). As anahernate,if 3-Ihe weld surface has been made sufficiently smooth, Flo. T 53$1c) TYPICAt. TWO SEARCH UNIT TECH. One search unit rnay be p! aced on the centerline of the d NIQUE FOR DETECTING TRANSVERSE DISCON. weld with the beam directed along the weld to scan M TINUITIES IN WELDED JOINTS the entire depth and width of the weld. N l 4%!+i ~

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v" t:ynne- + m r t ,,c. % *,. - - 3 4 4 i U.$. NUCLEAR REGULATORY COMMISSION REGION I l Report Nos. 50-445/89-38 50-446/89-38 t t Docket Nos. 50-445 50-446 i License Nos. CPPR-126 CPPR-127 i Licensee: Texas Utilities Generating 2001 Bryon Tower Dallas Texas 75201 Facility Name: Comanche Peak Units 1 and 2 I Inspection At: glenRose._ Texas Inspection Conducte)!.hly 17 through 27,3 Inspectors-4 f/1//f W; Kerch, Senior Reactor Engineer g date f 4/t147 L.* is, NDE Technict.in cate t y/.Oliveri ND$ Technici,an ~ S////f4 date i Approved by: 8////47 R. Strosnider, Chief, Materials and date Processes Section, EP8, ORS, Region ! Inspection Summary and

Conclusions:

A routins unannounced inspection was conducted at Comanche Peak Nuclear Power Station on July 17 through July 27,1989, Report No. 50-445/89-38. Areas Inspected: This inspection focused on preservice inspection activities, licensee disposition of deftetencies reported, and the licensee's erosion / corrosion program. Summary and

Conclusion:

Three violations and three unresolved items were identified during this inspection. Necessary corrective actions for significant deficiencies were not promptly identified and resulted in inappropriate correc-tive action by site engineering. Preservice ultrasonic examination data of piping weldments are of poor quality and will rot be of benefit during Inservice Inspections. .g 9 9-l3-@4-74 'Y

n 1 1-p I 4 DETAILS i 1.0 Persons Contacted (30703) Texas Utilities Generatino (TUGCO) [ S. G. McBee, NRC Interface Susan Palmer, Stipulation Manager Fred W. Madden, Mechanical Engineer David L. Foken, Mechanical Engineer Xen Pointer, Licensing Engineer L J. T. Maxwell, Quality Control Manager j W. G. Guldemond, Manager Site Licensing S. L. Ellis, Test Manager J. W. Muf fett, Manager, Engineering W. J. Cahill, Jr., Executive Vice President Stone & Webster Engineering Corp. (SWER Roger Smith, Engineering M. P. ilo11and, Lead Structural Engineer T. W. Houston, Group Supervisor C4tizens Association for Sound Energy (CASE Dillie Gede, CASE Attorney O S. Nuclear Regulatory Corrmission. Comanche peak Division L4 Sc H. Livermo&,hesident Inspector Rasident Inspector re R. M. Latt P. F. McKee, Deputy Director CPPD J. S. Weike, Reactor Engineer R. F. Warnick, Reactor Engineer The above listed personnel were present at the exit meeting. The inspector also contacted other administrative and technical personnel during the inspection. 2.0 Independent Measurements - NRC Nondestructive Examination and Quality Records Review During the period of July 17 through July 27, 1989 inspection was conducted at Comanche Peak Huclear Pcwer Station.an onsite inde The inspection was conducted by NRC regional based inspectors. The objectives of this inspection were to assess the adequacy of the

, yquppyqnw, t 3 i licensee's preservice inspection program, welding quality control program, and erosion / corrosion program. The Itcensee's actions regarding verification i of the "As-Butit" configuration of pipe hanger / supports and the licensee's actions to disposition identified construction deficiencies were evaluated.- Examinations required of the licensee by regulations and codes were reper-l formed by the NRC inspectors. j h 2.1 Nondest*uctive Examinations (NDE) t Visual Examination of Pipe Welds (57050)(rris o) Forty-two safety related pipe weldments and adjacent base material (1/2 inch on either side of the weld) were visually examined in accordance with NRC procedure NDE-10 Rev. O Appendix A, and associated site QC documents isometrics and as-built drawings. Included in this inspection were ASME Class 1 and 2 pipe we'dments selected.from the Safety Injection-($1) and Chemical Volume Control (CS) Systems. This examination was performed specifically to identify any crack: or linear indications, gouges, leakage strikes with craters, or corrosion, which may infringe upon, the arc minimum pipe wall thickness. Results The welding and everall workmansh'p inspected were satisfactory. No-violations were identified. Visual inswetion of Hancers/ Supports (57050) I g During this inspection ff/ty-six safety related hanger / supports were visually inspected per NRC procedure NDE-10, Rev. O, Appendix i and B in conjunct %n with r,f te QC documents, isometric /drawinCs. Included in this inspection were hanger / supports selected from the Safety Injection (SI), Chemical Volume Control (CS), Reactor Coolant (RC) and Residual Heat Removal (RHR welds, the accessible surface area a)nd adjacent base metal for Systems. In the areas of distance of one-half inch on either side of the weld was examinated In the area of component integrity specific attributes looked for were proper installation, configuration or modification of supports, evidence of mechanical or structural damage, corrosion and bent, missing or broken members. Results Welding and surface conditions were satisfactory, no violations were identified. Liquid Penetrant Examination (57060) L Forty safety related pipe weldments and adjacent base material (1/2 inch on either side of the weld) were examined using the visible w W u-y -v y

~- ;, %.yo- - 3 l 4 i dye, solvent removable method per NRC procedure NDE-9, Rev. O, in-conjunction with the Itcensee's procedure QCl-3.12, Rev. 4. Included in this sample were ASME class 1 and 2 pipe weldments (CS). selected from the Safety Injection (51) and Chemical Volume Cont Results l Welding and surface conditions were satisfactory, no violations were identified. Ultrasonic Examination (57080) a Sonic Mark 1 ultrasonic flaw detector.Six safety related p[ These examinations were performed in accordance with NRC procedure i NDE-1, Rev. O and associated site drawings, procedures and ultrason test data reports. linearity) was performed per NRC procedure NDE-2, Rev. O i amplitude correctice. A distance calibration blocks, T8X-0 ar.d TBX-5. curve (OAC) was constructed using t ultrasonic examination, the instrument setting and search unitTo e (transducer) were matched as near as possible to those indicated b: the licenste's ultrasonic data reports. R_esults An ultrasonic examination of scid 7, T8X-2 2523; in the safety injecti system revealed an indication which was greater than 50% of the DAC. 1980 Edition, paragraph IWA 2232 bin accordance with the AS reflectors that produce a respon(se)g(c) for examination of welds, level shall be recorded. reater than 50% of the reference j NRC was confirmed by the utility as being over 50% of DAC.T l the PSI Ultrasonic data report did not show this reportable reflector

However, As discussed in Section 3.0, further investigation by the inspector revealed that this deficiency was the result of an improper procedure.

l Erosion / Corrosion Examination (57080) Seven grid locations were selected for independent erosion / corrosion examinations by the NRC inspectors. Included in this examination were piping from the Condensate (Co) and Feedwater (FW) systems (grid numbers C003, C010, C013 C014 0016,FV13,andFW29). A Nova 0-100 digital thickness gauge w,as use,d to acquire the data in accordance with NRC procedure NDE-11, Rev. O and the Comanche Peak " Corrosion Monitoring Plan." also reviewed during this inspection.The software for data storage and

-- y g g y ~, m a & T,L ~' ~ ^ 5 Results The NRC acquired data showed no discernible difference from the data 8 i taken by technicians from Comanche Peak. The grids were marked on components in a way to ensure repeatabla data collection. The data ing minimum wall violations and help establish eros rates in the future. Service Water Erosion / Corrosion Unit 1 (92701) The inspectors performed a follow-up inspection on the previously identified problem of sandblast coating removal, corroston and remote NRC inspection reportsvtsval inspection of the 10" piping of the Uni Engineering Report ER-ME-19, dated Septensber88-47, 88-48 and t 21, 1988 were reviewed. These reports documented the itcensee's corrective actions to assure that minimum wall thickness requirements were satisfied for the service water piping. spool pitees and additional inspections.These actions included repla Also, a: discussed below the procedures for removal cf coating arid visual examinations were, modified for Unit 2 to avoid the type of probless that occurred at o Unit 1. The inspector had no further concerns regarding this issue and considers the Scryice Water 10" piping issue closed for Unit 1. i Service W,ter Eros _ ton / Corrosion Unit 2(92701), During this inspection, the itcensee was performing removal of coatin r by sandbl6 sting and remote vf sal examinations of the Jrit 2 Service Water ;,1pi!.9 systa.. Several procedures dealing with these operations (included in Attech:nent 3) were reviewed by tht intpectors and found to be acceptable. 3.0 _ Review of See CE Procedures and Manuals (57050)(n ole >) The procedures ilsted in Attachment 3 were reviewed in the re during this inspection period for comp 1tance to the licensee'gional office s FSAR commit-ments and applicable codes, standards and specifications. Results Westinghouse procedure, Manual Ultrasonic Examination of Welds section 7 i reads in part that valid flaw indications which provide a response equal to or greater than 50% of primary DAC shall be considered a recordable indication. Section 6.0 of the procedure interprets valid indications to be reflectors cause by flaws, such as crac,ks, lack of penetration or fusion inclusions and porosity. This is not in accordance with ASME Code Section of 50% or greater shall be recorded.XI,1980 Edition which in part rea This procedural deficiency is a violation of 100FR 50, Appendix B, Criterion IX (50-445/89-38-04). indicated in Section 2.1 of this report, independent NRC inspection As identified a Code recordable indication that was not recorded beca this procedural deficiency.

-.y ow.m -+ :~n n ~w A ~me w wrr"rn!9f*N O"" i .~ j 6 r 4.0 Preservice Inspection (PSI) Program (73055) (73051) (73053)(nore) The Comanche Peak Unit 1 preservice inspection has been completed. Comanche Peak's program was prepared and implemented by Westinghouse The PSI program incorporates the requirements of the ASME Boiler and 1 Pressure Vessel Code, Section XI 1980 supplemented by additional i requirements of USNRC Reg. Guide 1.150. reitef from specific ASME Code re The licensee has requested which they feel are impractical. quirements appitcable to this program, Such requests with technical justification for relief have been submitted to the NRC for review and approva1. Reviews The inspector reviewed the following to ascertain compliance with applicable ASME code requirements, iteense commitments, and regulatory requirements. i The preservice inspection program Personnel certification records for qualification of PSI contractor personnel PSI examinatitm data reports NDC proceduret TSAR In addition, tho inspectors witnessed a liquid penetrant PSI examination operformed by the licensee. The NRC inspectors reperformed visual, Isiqvid peqctrant and ultrasonic examinations on a selected sample of velds. i Listed below me cencerns tiot vere identifico during these irtspectient,. l (he volume of weld t-xamined by the licenste was not adequately l documented (no plots existi.d to assure proper ultrascrite coverage, { only estimated per;entages were provided on final NDE reports). Examination limitations were not properly documented. L Ultrasonic examination reports of record did not have dispositions L as to the acceptability of examination results. i improper documentation of reflectors greater than 50% of OAC. Results l. Because of deficiencies in the documentation of preservice ultrasonic I examination data the licensee's PSI program has not provided a good baseline for future inservice inspections (ISI). documentation will compitcate the evaluation of 151 data.The lack of good The itcensee should ensure that data taken during ISI are adequate to provide a good baseline for future examination. action and NRC review (Unresolved ItemThis item is unresolved pending licensee 50-445/89-38-01). l e

y.,s..% 4 jz >^ l I L i PSI Calibration Blocks 1 i The licensee does not have as-built drawings of the site preservice inspection calibration blocks. There are approwfmately 44 calibration i blocks. i Because of the lack of as-built drawings it could not be verified that the blocks satisfy the 1980 ASME Section XI PS! requirements or the 1986 ASME Section XI requirements applicable to future inservice inspections, This item is considered unresolved pending licensee action to verify accept-i ability of the calibration blocks (Unresolved item 50-445/89-38-02). PSI Procedure OP$-NSD-101 Rev. 5 dated April 8, 1975 i . Forms used during the PS! examinations were different than the ones contained in the procedure and the emplanation in the procedure of what -information needs to be included on the forms was inadequate for the ultrasonic data taken during the PSI. licensee action and NRC review (Unresolved ItemThis issue is unresolved pendin 50-445/89-38-03). PSI Reactor Vessel Nozzle Inner Radius (73055} Ouring the review of DSI data two.:occtrns wre idensified regaraing the reactor tessel nozzle inner radiuf, preservice 1:1spections. 1. The insputer discussed the rationale for performing m6nual ultrasonic examinattens from the inner surfaces nf the reactor vessel nozzin, L when radiological conditions will prohibit manual exanination irring i % service. It was determined that during th DSI the autc94 tic equipmeM. was t,nable 1,0 perfor,s the naneuvers requ, ired to conohtely 1 examine the nozzle inner radius and manual exWsation wn needed e a supplement. Since that time the capabil'ty of the automatic equip-cent to provide the required examinatita coverage has been developed and a completely automated preservice exam has been completed. 2. There was no evidence of the required approvals for PSI procedure ISI-155, Manual Ultrasonic Examination of Nozzle Inner Radius, by the i authorized inspection agency nor the licensee. Documentation was found that indicated the procedure had received a review. To supplement this the licensee is resubattting ISI-155, Rev. O procedure to the authorized Nuclear Inservice Inspector and the licensee's NDE Level III for review in order to have evidence of proper reviews of acceptability. Result The inspector has no further concern and considers these subjects closed.

~ m.y i t 5.0 Electrical Penetrations (92706) The Itcensee identified by deficiency report OR-C-88-02376, dated October 25, 1988, that the electrical penetrations (full penetration weld-during the construction phase.ments) did not have the ASME code re 1 The containment structural integrity test had been performed and fuel load was scheduled in approximately 70 days a the time of this report. The Comanche Peaks Unit 1 FSAR' requires that the Section !!!, Olvision I, Subsection NE,1971 through 1973 Summer addenda for the full penetration Class 11 welds. In addition, Gibbs and Hill's Specification 2323-$5-14 Rev. 4 requires these electrical of NE-5120 of Section III of the ASME Boller and Pressu The inspector reviewed the actions taten by the licensee to resolve this nonconformance. The Itcensee stated that they had performed a stress analysis of the subject penetrations and that a change to the FSAR to eitminate the code required volumetric examinetton of the welds planned to be submitted to the NRC. The inspector performed a walkdown of the i electrical penetrations and concluded that radicgraphy was.not suitable at s this ti,me, however, the code required volumetric exantiistion of the penetra-tions could be met by performing ultrasonic exat.inationi Etrust analysis is not d substitute for the performahre of nondestrut;tive testing that is intended tu verify the u ceptable quality of fabricated components. It was evident that adequate engineering corrective action had not taken place and the dispositfon was inadequate. Tnis is a violation of NRC rgquirer.ents(50-445/89-28-06). At the conclugf0n of this inspection, the licensee was preparing to nerform ultratonic ?xam! nations of the electrical penetrations. 6.0 Fuel fransfer Tube Penctration Sleeve Veldments (92706)(fl o9 1 The licensee identified in deficiency report ORC-68-02376, dated October 25, 1988, that the fuel transfer tube penetration sleeve did not have the ASME Section !!! code required radiography examinations for the full penetration Class II weldments (1A,18, 2A and 28). DRC-88-02376 required the fuel transfer tube weldsents to be radiographed. Nonconfirmance report number 89-04023, Rev.1, dated April 4,1989, was initiated and defects in accordance with site radiographic procedure AQ L - NRC review of this deficiency revealed the following: DCA-6500 tssued March 19, 1980 did not incorporate on the OCA drawi + the required engineering design (weld symbol) for the required full penetration weldments. ments for 100% radiography for these weldments.This DCA also did The requirements for 4 , -,., ~ >~-a w -m~- -v-w

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c w v w :n, r.,,,,-,;.. .w.. full penetration welds and for 100% radiography were established in. FSAR Section 3.8.1.2.3, through reference to the ASME Boiler and Pressure Vessel Code, Section !!!, Olvision I, Subsection NE,1971 through and including the 1973 Summer Addenda. Gibbs and H111's site specification for containment Steel Liner 2323-$$-14, Section 10.2.3 also specified the requirement for full penetration welds and 1005 radiographic inspection. The control, verification and site quality regttrements for this Field Design change were not in accordance with site procedures CP-EP-4.6, CP-EP-4,5 and CP-EP-4.0. u These deviations were not promptly identified. The disposition of NCR-89-04023 Rev.1 accepted "as-is" the Class Ill weldments (IA,18/ 2A and 28) with rejectable radiographic indica-tions. This is not an appropriate in that an adequate corrective action is to repair the radiographic rejected areas in accordance with ASME Section 111 requirements and post repair magnetic particle exarainattens and radiography in 4::cordance with ASME Section III, @ 5120 and as required by site specificatten 2323-55-14. This is a violation of NRC requirementr (50-445/89 30-05). 7.0 Attachmer.ts Att4chment No.1 is a tabulation of specific pipe weldaents and compoe.unts esamin60. Attachment No. 2 it a tat:ulat. ion of specific hanger / supports

4xamined, Attachaent 3 is a list of the NDS Droc?dures reytewed.

8.0 Unresolved Items Unreselved items are matters about which more inforestion is required in order to ascertain whether they are acceptable items or violaticns. Three unresolved items appear in paragraph 4.0. 9.0 Management Meetinos (30703) Licensee management was informed of the scope and purpose of the inspection at the entrance interview on July 5, 1989. The findings of the inspection were discussed with the licensee representatives during the course of the inspection and presented to licensee management at the exit interview (see paragraph 1.0 for attendees). At no time during the inspection was written material provided to the licensee by the inspector. The licensee did not indicate that proprietary information was involved within the scope of this inspection. ~

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e c yq q.p w riT4F wna w M yyr" w &st"9??'! J. ATTACHMENT 3 Westinghouse Nuclear Services Division (N0!$) t Procedure Title P Number / Revision Westinghouse j Preservice and Inservice Examination Documentation Magnetic Particle Examination INT-ISI-101, Rev 0 t Liquid Penetrant Examination INT-ISI-70, Rev 0 i Visual Examination INT-151-ll, Rev 0 Manual Ultrasonte Examinatica INT-ISI-8, Rev 0 of Welds in Vessels Manual Ultrasonte Exa:ntnation INT-ISI-47 Rev 0 of Yelds Reactor Vessel Inspection Program INT *SI-206, Rev 0 Preparation and Documentation Freservice Inspecticn Renctor Vessel RV-ISI-01,.Rev 1 Manual VT Examination of Reactor ISI-154, Rev 1 i Wozzle Inner Radius Manual VT Examination of Full 151 155, Rev 0 Penetration Circumferential and Longitudinal Butt Welds Magnetic Particles ISI-205, Rev 2 151-70, Rev 2 Texas Utilities Generatino Company (TUGCO) Corroston Monitoring Program Ultrasonic Measurements i Visual Examination HQA 3.09-8.47, Rev 0 Radiography VE-1, Rev 1 Coating Removal of 10" Piping RT-ANSI-B31.1, Rev 0 l Quality Personnel for Abrasive QCP-2, Rev 0 j Blast Removal Remote Visual of 10" Piping DCA 88609, Rev 2 L I . After Plastic Removal Remote Visual of 10" Piping Prior 2 PPT-40.9 to Plastic Removal Design Vertf tcation 2 PPT-40.8 Field Design Change Control CP-EP-4.5 Procedure Design Central General CP-EP-4.6 CP-EP-4.0 1

y z; e y o w n p w ' w -vr. w t. M ' .-o-w ATTAC*ENT 3 2 Procedure Tttie Number / Revision Oliver B. Cannon Coating Removal by Abrastve Blasting CSPVL339 (QCP-1, Rev 2 Brown and Root Remote Visual Examination Radiographic Examination AQP-10,11 AQP-10,4 Stone and Webster Engineerino Qualtf tcation for Remote Spin Blast for 10" Piping Qualification for Handheld Blast for sp.TP-ME-03, Rev 1 24" and 30" Piping sw.TP-ME-02,'Rev 1 Gibbs a,nd Hill Design Specificetton for Containment Steel Liner 2323-55-14 \\ G I l l - - - - -, - -}}

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