IR 05000482/1981005
| ML20137S780 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 04/21/1981 |
| From: | Crossman W, Gilbert L, Randy Hall, Martin L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20137S748 | List: |
| References | |
| 50-482-81-05, 50-482-81-5, NUDOCS 8509300504 | |
| Download: ML20137S780 (9) | |
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l U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
Report No. STN 50-482/81-05 Docket No. STN 50-482 Category h2
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Licensee: Kansas Gas and Electric Company P. O. Box 208 Wichita, Kansas 67201 Facility Name: Wolf Creek, Unit No,'1 Inspection at: Wolf Creek Site, Coffey County, Burlington, Kansas
. Inspection conducted: March 23-27, 1981 I
4 Inspectors:- 22_
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A. E, Martin, Reactor Inspector, Project Section 3 ~ Date*
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, (Paragraphs 1,.2, 3, 7, 8 and 9)
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P , f L. D. Gilbert, Reactor Inspector, Engineering and yl'.2//B/ Date Materials Section (Paragraphs 4, 5 and 6)
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. Approved by: --
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W. A. Crossman.. Chief, Project Section 3
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R. E. Hall, Acting Chief, Engineering and Materials ' ' Date Section Inspection Summary - Insoettion on March 23'27, 1981 (Report No. STN 50-482/81-05) Areas 7nsoected: Licensee action on previous inspection findings; site tour; observation of work and review of records for welding of Reactor: Coolant Pressure Boundary and other safety-related piping; review of records and installation of electrical equipment. The inspection involved 66 ' inspector-hours on site by two NRC inspector .
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Results: One deviation was identified in the area of review of records and
. _ installation of electrical equipment (Deviation - 4160 Volt Switchgear Specifi-cation Color Code Identification - Paragraph 7.b)
8509300504 850926 PDR ADOCK 05000482 H PDR _ - _ _ _ _ _ _ _ _ _ - _ _ - _ _ _ _ _ _ _ - _ _ _ - _ _ _ _ - _ - _ - - - - _ _ - _ - _ _ _ - _
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, DETAILS
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Principal Licensee Personnel
*D. W. Prigel, QA Manager, Site
*G. W. Reeves, QA Engineer
*J. L. Stokes, Construction Project Support Supervisor
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*N. L. Hill, Startup Manager R. G. Haines, QA Engineer Daniel International Personnel
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*L. F. Warrick, Project Manager
.. _* N. J. Criss, Audit / Procedure Coordinator T R. Schofield, Project Welding Engineer -
r B. Newton., Welding Engineer . g 'Q. Dennison, QC Manager ; C. Hopkins, Traveler Supervisor F J. T. Goodwin, Asst. Project Electrical Engineer Other Personnel D. E. Kent, Senior Welding Engineer, Westinghouse Electric
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Corporation
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F- - 'The NRC inspectors also . interviewed other contractor person 6el during -
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' Licensee Action on Previous Insoection Findings , _
(0 pen) Infraction (50-482/80-11): Failure to specify appropriate
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acceptance criteria. .The NRC inspector reviewed Welding Procedure i Techniques N-1-1-BA-1 Revision 6, N-1-1-BA-5 Revision 4, and N-1-8-BA-24 l Revision 1 and found the acceptance criteria for weld reinforcement to j now be consistent with that specified in paragraph NE-4426 of ASME B&PV l Code, Section III.1974 Edition through Summer 1975 Addenda. The welding
- procedure techniques for fabricating component supports are being review-ed by Daniel International for appr,opriate weld reinforcement requirements to preclude a similar problem when inspecting component supports to para- ~
graph NF-4426 of the above Cod ' This item will remain open pending completion of the review.and corrective i actio i m *
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. (0 pen) Unresolved Item (50-482/80-20): Qualification of procedures for ^
welding P Number 8 base material to A Number 8 weld material used as base material. The NRC inspector reviewed the revision issued by the Daniel International Corporate Office to Welding Procedure CWP 507, Revision 26, '
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which clarifies that the procedure is consistently qualified with ASME Code Case 212 for Welding P Number 8 base material to A Number 8 weld material used as base materia Since the corporate revision to the procedure had not been incorporated into the site procedure, this item will remain coen pending revision of site Procedure CWP 50 (0 pen) Unresolved Item (50-482/80-05): Concrete expansion anchors. During this inspection the NRC inspector called Mr. Mel Johnson of KG&E Engineering to determine the status of the qualification of the repair procedure for
. (T concrete expansion anchor Mr. Johnson said that Bechtel has advised him . _
that the necessary information is in typing and should be available soo T This item will remain open pending review of the Bechtel data substantiating that the yepair methods meet the requirements for loading, plus safety factor
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E .. . P (Closed) Infraction (50-482/80-15): Failure to provide appropriate pro-cedures for II/I Cable Raceway. The NRC inspector reviewed the list of II/I cable trays and the status of the inspection of this tray. The list of II/I tray was compared to drawing EOR 1321, Revision 14; EOR 1323, Rev-ision 5; and EOR 3511, Revision 12 to determine the accuracy of the lis The NRC inspector also reviewed inspection reports for 15 randomly selected II/I Raceways. The requirements for the installation and inspection of II/I are app'ropriately addressed in Procedures WP-X-300, WP-X-302 and.QCP-X-300,
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as documented in NRC. Inspection Report STN 50-482/80-24, and ~ the procedures
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F ~ have been implemented. -This item is considered close , t h 3.- Follow Un on Licensee Identified Problems
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Auxiliarv Panels and Main Control Board Weldino - 50.55(e), , l i-- .- l
- SNUPPS Construction Deficiency l
, The NRC inspector discussed the status of this item with the licensee l representative and examined several areas of concern in Auxiliary ! Panels and Main Control Board.- This deficiency is generic to Wolf Creek and Callaway. The Panel Fabricator, Comsip Customline Corpora-tion has built and seismically tested a prototype panel that will be utilized as a comparative standard for the panel welding at both
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Wolf Creek and Callawa Bechtel letter BLSE 9034 of December 24, 1980, indicates that the seismic testing of the panel has been accomplished by Action Laboratory, but the final test report is not.availabl Comsip is. now at Callaway doing the comparative evaluatio The final response for this item is now scheduled for July 1, .198 This item will remain ope .. l _ _ .. .- . .
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4 G.E. HFA Relay-GE Part 21, SNUPPS 50.55(e), NRC IE Information Notice 81-01
. Daniel has identified 48 suspect HFA relays used in Class IE applica-tions in equipment that is on site. Bechtel is still in the process of reviewing the design to identify any other HFA relays used i'n other equipment. The licensee has committed to replacing This all GE HFA relays item will remain both in Class IE and Non-Class IE application open pending completion of the Bechtel revie Damaced Motor Control Center (MCC) - Potential 50-55(e)
MCC IN603 The NRC inspector reviewed Deficiency Report (DR) ISD 5356 was damaged while movin A possible cause was identified with the 3 The fork lift was subsequently s__ - hydraulic repaired. system on the fork lift.The MCC was returned to the manuf ac
' 1980 for repair. The licensee letter of January 30, 1981 stated that #-- .-
this was not considered reportable under the requirements of 50.55(e). -
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Thig item is considered close r- . -
~ NEMA'3 Size Starters - Gould Part 21, NRC IE Circular 79-23 E--
f-The NRC inspector reviewed Nonconformance Reports (NCR) 15N1274E, 15N1275E, 1NN1373ER, and 1NN1426E The NCRs identified 70 size Gould subsequently 3 starters that might require replacemen Gould letter of identified three more starters for a total of 7 March 10, 1980 to Bechtel stated that a total of 74 starter contact This item
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carrier replacement kits had been installed at Wolf Cree 'h
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will remain open until the licensee can determine exactly how mar)y g_,,
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_ - kits were replace ,
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p . Internal Color Codino (G.E. SWGR) - Potential 50.55(e) .
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The NRC inspector discussed the status of this item with the licensee ~ representative. The licensee letter of June 6,1980 stated that'this item was not considered. reportable under the requirements of 50.55(e).
The reportabili-ty of this item is considered closed; however, the review of the specification (Specification No. 10466-E-009) has indicated an
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apparent Deviation as discussed in paragraph 7.b of this report.
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- Site Tour The NRC inspectors inspected the Reactor Building, Auxiliary Building and Control Building to observe construction activities in progress and house-keeping practice *
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No violations or deviations were identified.
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5 Reactor Coolant Pressure Boundary Piping The NRC inspector observed the welding of a field weld in the Loop 4 cross-over pipe identified as weld F408 on $rawing I-Loop 4 (Q) irt the Reactor Coolant Pressure Boundary piping system. The weld was being machine welded using the gas tungsten-are welding process in accordance with welding l Technique NM-8-8-B-1, Revision ! In the areas inspected, no discrepancies were noted concerning traveler i documentation, welder qualification, procedure compliance and material contro ~ No violations of deviations were identified
; Other Safety-Related Piping
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The NRC inspector observed welding activities on the following five field g - welds: Weld F005R-1 on Drawing I-M03BM01(Q) in the Steam Generator Blow-
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down piping system; Weld F038 on Drawing I-M03AE04(Q) in the Feedwater e piping system; Weld F026A on Drawing I-M03EM01(Q) in the High Pressure *!
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_ Coolant Injection piping system; and Welds F040 and F051 on Drawing ,
b I-M33EJ02(Q) in the Residual Heat Removal piping system. In the areas inspected, no discrepancies were noted concerning traveler documentation, welder qualification, procedure compliance and material contro The NRC inspector reviewed the supporting procedure qualification test reports, PQT 149 and 324, for Welding Technique N-1-3-BA-22, Revision 3, which was used for welding Welds F005R-1 and F038 abov The procedure
* qualification, in the areas reviewed, was consistent with requirements gf < ., Bechtel Specification 10466-M-204(Q) and ASME B&PV Code, Section'III NCs g,_ ,and Section IX 1974 Edition through Summer 1975 Addend *
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. .No violations or . deviations were identifie E ~ Electrical Ecuipment and Comoonents i ;
> l The NRC inspector reviewed the initial charging procedures and charge l records for the Class' IE Batteries NK-11, NK-12, NK-13 and NK-14. The , initial charge was accomplished by KG&E personne i i The NRC inspector reviewed the following documents: I
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Calibration Data Sheets For Battery Charges NK-21, NK-22, NK-23,
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and NK-24 l I Procedure 5U8-003, "Special Electrical Procedure .6 month j , Initial Storage Charge Performed To Maintain Battery Warranty" ;
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Pre-charge and Post-charge Data Sheets For Batteries NK-11, l NK-12, NK-13 and NK-14 l
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The NRC inspector inspected the battery rooms and the general installa-tion and condition of batteries NK-11, NK-12, NK-13 and NK-14. During the inspection the NRC inspector observed that there were ne. cell spacers installed between the cells on any of the four {1 ass IE Batter-ies. The NRC inspector found that the manufacturers Installation Drawings E-050-0006-02 and E-050-0009-02 show the cell spacers hs Bill of Material Mark Number 14. However, the Gould Instruction book for battery installation does not reference the cell spacers and the cell ! spacers were not received on sit These cell spacers are generally l utilized as a rethod of providing a degree of seismic restrain IEEE l 484, 1975, requires seismic restraint of the individual cells. Daniel's i Assistant Project Electrical Engineer initiated a Request for Clarifi-cation of Information, RCI No. 7158, for Bechtel to determine if the cell spacers are required or the method of restraint to be utilized
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is in lieu of the cell spacer This is an unresolved ite ,
#_ . The NRC inspector reviewed Bechtel Specification 10466-E-009 for the T Class IE .4160 Switchgear during closeout of potential 50.55(e) itefn in paragraph 3.e of this report. The NRC inspector found that ~ t . . Appendix A of this specification specifies a different color coding , =- ~
fer redundant separation groups than that specified in the Final
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The Wolf Creek FSAR section 7.1.2.B identifies the color coding for the separation groups as follows: Separation Group 1: Red Separation Group 2: White
' Separation Group 3: Blue N{ '
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: Black
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' Nonsafety h.~ e Section 7.1.2.3 further states, "Within the control panel, where mere than one separation group is present, wiring is identified by separa- - i" tion group. . . ." Section 8.3.1.3 states, "Within control panels where more than one separatica group is present, wiring is identified by separation group designati on. . . ." , Section E. 3.1.3 further states, "In cases where the majority. . . is ' i primarily one separation' group, standard color wire and/or sleeves for the majority separation group is used. The remaining wiring is L t
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identified, using the appropriate color."
Bechtel Specification 10466-E-009 Appendix 7 Revision *E, paragraph - 5.2.2 states, " Wiring of the various separation groups'.within the
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switchgear shall be identified (color-coded) in accordance with the following: '
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Separation Group 1: Red
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Separation Group 2: White Separation Group 3: Blue
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Separation Group 4: Green This is an apparent deviation to the FSAR commitment ' Unresolved Items > Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncompliance, e or deviations. One unresolved item disclosed during the inspection i *-- discussed in paragraph 7 $ ' Exit Interview - t-The. NRC i'nspectors met with licensee representatives (denoted in paraghtph 1)
g' - and the NRC Resident Reactor Inspector, T. E. Vandel, on March 26, 1981, and gi summarized the scope and findings of the inspection. No additional findings resulted from inspection activities continued on March 27, 198 % .
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REGIONAL OssiCE tET ER OR REPORT TR AnsuiTTAL DATE pop =sPECTioM om investigation SGI OR LETTER ISSUED TO UCEN3EE REPORT SENT TO NOS POR ACTION eMMEDIATI ACTION LETTER to eATE g5
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M M O 3 y y M M o0 y y SUBJECT QF GNVESTIGATION $CMECat OreE 802 QNLyt GH7 MIS to CFR 70 a03 TYPEa to CFR 20 405 Tv*E A 25C EQUIP FA1 LURE t t C (NT. 0VER EXPOSQR E IS Q CRITICAuTY 01 C INTE Ret AL OVE8lEXPCSURE OE C 18 O LOSS. THEFT 22C ALLEGAftON/ 12 C EXT. OVER EXPC5URE COMPLAINT 02 C IXTE RNAL Ovf REXPOSURE 07 C 13 C EXCES$ RAD. LEVELS 17 C MUF 5 03C RELEASE TO UNRE5T, AMEA 08 C 230 Pusuc1NTEREST t4 C EXCESS CONC LEVELS 18 C TR ANSPORTAT10N 08 C LDS$ OF FACsuTY 00 C 24C SAe0TAGE te C CONTAM/ LEAKING 06 C PROPERTY DAMAGE
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. ENCLOSURE 1 . UNITE D ST AT ES -
j= ric o NUCLE AR REGULATORY COMMISSION
/ 'o, y REGION IV
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[^ ,,y j 611 RY AN PLAZA DRIVE. SUITE 1000
, !' / g ARLINGTON, TEX AS 76011 n 1 f -
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' In Reply Refer To: ;
RIV Docket No. STN 50-482/Rpt. 78-01 a
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Kansas. Gas and Electric Company i -ATTN: Mr. G. L. Koester
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Vice President Operations
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4 e Post Office Box 208
' '-- Wichita, Kansas 67201 . ' - ~ Gentlemen:
This refers to the inspection conducted 4-6, 1978, of byactivities Mr. C.authomzed R. Oberg and
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of the NRC. staff during the period Januaryby NRC Constructio
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h discussion of our findings with Mr. J. O. Arterburn and other members of your j-staff at the conclusion of the inspection.
l' Areas examined during the inspection and our findings are disc ~ enclosed inspection report.
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selective examination of procedures and representative records, interviews :
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_ with personnel, and observations by the inspecto '
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E ~ ~ During ~ the inspection, it was
. appear to be in noncompliance with Appendix B to 10 CFR The items of found that certain 50 of the NRC activities Regu- unde -
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lations, " Quality Assurance Criteria for Nuclear Powe ' l ! t the enclosed Notice of Violatio _ I
! (-- One new unresolved item is identified in paragraph 9 of the enclosed reporl l
I This notice is sent t6 you pursuant to the provisions of Section 2.201 of t , NRC's " Rules of Practice," Part 2, Title 10, Code of Federal Regulations. l Section 2.201 requires you to submit -to this office, within 30 days of your; receipt of this notice, a written statement or explanation in reply includ l (1) corrective steps which have been taken by yj (3) the date when full compliance will be achieve i
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Kansas Gas and Electric Company - -2- January 24, 1978
. - In accordance with Section 2.790 of the NRC's Rules of Practice," Part 2, Title 10, Code of Federal Regulations,- a copy of this letter and the enclosed inspection report will be placed in the NRC's Public Document Room. If this report contains any information that you believe to be proprietary, it is necessary that you submit a written. application to this office, within 20 days of the date of this letter, requesting that such information be withheld from public disclosure. The application must include a full statement of the
' reasons why it is claimed that the information is proprietary. The application should be prepared so that any proprietary information identified is contained in an enclosure to the application, since the application without the enclosure will also be placed in the Public Document Roo If we do not hear from you in
; this regard within the specified period, the report will be placed in the Public 4_,_ Document Roo ., [-. . -
Should.you have any questions concerning this inspection, we will be pleaped to discuss them with yo '
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Sincerely,
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..[. yaw W. C. Seisile, Chief Reactor @nstruction and Engineering Support Branch
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Enclosure:
- Appendix A. Notice of Violation ,
E .. . . - IE Inspection Report No. STN 50-482/78-01 . F ~
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_ STN 50-482/78-01 Appendix A
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NOTICE OF VIOLATION . Based on the results of the NRC inspection conducted on January'4-6,1978, it appears that certain of your activities were not conducted in full compliance with conditions of your NRC Construction Permit No. CPPR-147 as indicated below: CFR Part 50, Appendix B, Criterion V requires that activities affecting quality shall be prescribed by documented instructions, procedures, or drawings of a type appropriate to the circumstances and shall be a
REGION LETTE R & HOS FOR NiTION
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43 61 52 59 60 DATE 65
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lalM alwr % ff I I I I l' I I IIIIII I , t.: ~ D 'O 'Y Y fJ f4 D D Y Y u fJ D D Y Y T_ SU5JICT OF INVEST 4 GAT 10N (CHECK ONE BOX ONLYl6667
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t *, C F R 20 4'53 * TYPE A TYPE B 13 CFR 23 4C5 ptS Ot O INTERNAL CVE PE x*01uR E C6 C 110lNT Ov!REXPO509E 15 0 CRITtC ALITY 210 EOtslP. F AILURE C2 C EXTERN AL CVEPEp.305URE 07 2 12O EFT QVERExPOSURE 16 0 LO55 7HE F T 22C ALLEGATION R C3 " RELEast TO I.,*.* EST ARE A 13 0 13C Ex0E55 R AD lev!LS 17 0 MUF - CO'.IPL AIN T C4:LO55OF7AtruTY ca: . 14 : Ex:ESS CONC,LEviLS 18 D TR AN5*0RTATION 230 PUSL6C 137E6aiST 35 3 PROPERTY D AY A0! 13 2 190 CONTA%1 LE AKING 240 SABOTAGE
,' SOURCE 25C ABNOPMAL OCCUR 23 O ENVIRONVENT AL l EVENT 26C OTHER HE ADO ; AS.TER$ E*.TRlis
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: uADE IN BLOCK 5 5 7
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USNRC . INSPECTION ft ENTOTICEMEST CTATISTICA1. D.iTA Wolf Creek STN 50-482/78-01 .
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f NOTE: STATU", CODING; I f N010 MODULC ntovinlNG 3 i
INOTE: *% COMPLETE AND STATUS: DLANK . TO REMAIN OPIN r bNLY WilCN MODULC l LE AVE OL ANK FOR Mc 07,93 5 94
- C CLc:;to ( IN7tcTto c 97 701 )
kritOCIDunfS AND 30 /07,30 703 & /,;LllilitOPf 0P[N & trAVC N litl*; OPCN in ANT.ACTITIN 30 300 : .)NI,Y i
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. v' D3tLF TitACKING INI0ftMATION ~
'Y MODULC NO. INSP,
'~ M L[~~ ~~ N/C N/C N/C N/C N/C 88,L ,' f J J
J . IIiuni *CO vi i S S S S *,
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M AN itit" plt TE > * 1*> - J 'a C00C C CODE r CODC L w *4 . .4
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__ LINC COLUMN NUMDCn $HOWN IN DOTTOM UN O coy,,wves ov et;estoura.e :~rre
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OCT CD ER 1977
(*>CC3351 LIMTED STAT &l huCLE AR EECULATORY Ciuws$ os INSPECTION & ENFORCEMENT-STATISTICAL DATA SUPPLEMENT
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. CENE R AL INSTRUCTIONS: BLOCK A MUST BE CHECKED TO SHOW TYPE OF INFORMATt04 CONT AINED ON THE f ORM ONE FORM IS TO BE COVPLETED FOR E ACH (A) ITEM OF NONCOMPLI ANCE CITE .
(8) ITEM OF NONCOMPLIANCE NOT CITED, AN (C) DEVIATsON CITED IN ENFORCEMENT CORRESPONDENCE DOC <ET huMsE R STN 50-482 OR LICENSE NuMsER REPORT Nuv8tR 78-01 A-TYPE 08 FINDINGS B-SPECIFIC N/C CODE ,gy ,,osat (CHECK ONE 804 ONLY) OR OEvl ATION cAust Pmoct ovat savameTv AREA 3 7 g 8 10 il 12 S
A 3 NONCOvPoiAsCE lEl FlBl l l P B 2 lll 1 2 8 LICENSE E IDE NTIFIE D ITEMS C-MODULE NUYSER 33 gg C DEVIATION l2 l4 l 7l0l5 l5 l Bl E-CONSE OL'E NCE S 0-HOWITEM OENTIFIED (CHECK ONE box ONLYI (CVECK ONE BOX ONLY) 7 L 0 tiCENSEE A O CAUSE OR CONSTITUTED ACTUAL OCCURRENCE tJ 20 1 INSPECTOR 21 P HAD FOTENTIAL TO RESULT IN ACTUAL OCCURREf4CE D 0 OTHEa N D DID NOT HAVE POTENTIAL TO RESULT IN ACTUAL W OCCURRENCE f *
.* F -E XEMPT INFORV ATION " i G-ADDITION AL UNtTS (E NTER *M"
' IN FIRST BOX FOLLOWED BY OTHER 23 25
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' 22 5 b CHECK 80X IF EXE*.'PT INFORMATION
,~ IS INCLUDE D IN TEXT BE LOW, PE R
* ' IDUN2MU H-NONCO*.**LI ANCE REPETITivf 0CCURRFNCE 27 (IF FIRST OCCURRENCE ENTER "I** )
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I-TEXT (ENTER UP TO 2400 CHARACTERS FOR EACH ITEM. IF THE TEXT OF THE NONCOMPLIANCE OR DEvlATtON EXCEEDS THIS
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NUMBER. lT WILL EE NECESSARY TO PAR APHR ASE) 1 rA
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Contrary to 10 CFR 50, Appendix B Criterion VI and SNUPPS QA rnanual, __
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Section 17.B.1.6, as-built drawings for the location of Cadweld splices
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were not reviewed for accuracy of informatio ~
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O'TO'IR1977
l'.*C 0535) units o sT ATi s Nucitan as cuLattav cumissio% INSPECTION & ENFORCEMENT-STATISTICAL DATA SUPPLEMENT
.
GE NE R AL INSTRUCTIONS:, BLOCK A PAUST BE CHECKED TO SHOW TYPE OF INFORM ATION CONTAINED ON THE FORM ONE FORM 15 TO BE COMPLETED FOR [ ACH (A) IT EPA OF NONCOMPLI ANCE CITE (S) ITEPA OF NONCOMPLIANCE NOT C1TED, A'NP, (C) DEVI ATION CITED IN ENFORCEMENT CORRESPONDj NCE E DE OR tiCENSE NuMsER REPORT NuvBE R i8-01 DOCKET t.uMaeR A-TYPE OR Fired.NCS B-SPECeFIC N/C CODE . pWtiom (CHECK ONE BOX ONLY) OR DEVtATION C4uSE PAOCEDumt SEVEmity AREA 3 7 g g A h NONCOMPLIANCE lE lE I BI I l P B 2 1 2 B LICENSEE IDENTIFIED ITEMS C-t.*ODULE NUveER 13 19 C DEVIATION l21417l0l5l5lBl E-CONSEQUE NCES D-HOW eTEM IDENTIFIED (CHECK ONE BOX ONLY) (CHECK ONE box ONLY) L LICENSEE A CAUSE OR CONSTITUTED ACTUALOCCURRENCE s 20 t b sNSPECTOR 21 P HAD POTENTIAL TO RESULT IN ACTUAL OCCURRIf4CE N E oiD NOT HAvE ,OTENTIAt TO RESutT i~ ACTuAt
$_ - , 0 0 OTHEa OCCURRENCE r* " '
F -EXEMDT INFORY& TION G-AODITION AL UNITS (E NTER "Al" /
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22 $ O C eCK sox iF ExEMPTiNFOa=ATiOs f.j-- IS e!.CLUDE D IN TE XT B E LO'.*t. PE R P- 10 CF R 2.790 H-NONCOMPLt ANCE REPET4TevE OC*NRRENCE ??
(IF FIRST OCCURRENCE ENTER ~l** 4 I-TEXT (ENTER UP TO 200 CH ARACTI RS FOR EACH ITE!.t. IF THE TEXT OF THE NONCOT.*PLIANCE OR DEVIATION EXCEEDS THIS NUMBER,IT '.*;tLL BE NECESSARY TO PARAPHRASEI
50
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Contrary to 10 CFR 50, Appendix B, Criterion V and specification (2p-toi 10466-C115. the freauency for testina of production Cadwelds was noti
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* . 'c, UNITED ST ATES [ g e, ,f j NUCLE AR REGULATORY COMMISSION - r REGION IV i '
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February 26, 1980 In Reply Refer To: .
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RIV . Docket No. STN 50-482/Rpt. 80-03 - Kansas Gas and Electric Company ATTN: Mr. G. L. Koester Vice President Operations Post Office Box 208 Wichita, Kansas 67201 T' - Gentlemen: Q-
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-- This refers to the inspection conducted by Messrs. L. E. Martin and L. lC Gilbert of'our staff during the period February 11-14, 1980, of activities y
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T authorized by NRC-Construction Permit No. CPPR-147 for Wolf Creek, Unit
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No.-1,andtothe'discussionofourfindingswithMr.M.E.Clarkandother( . i_ .. members of your staff at the conclusion of the inspectio i
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yO Areas examined during the inspection and our findings are discussed in the
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enclosed inspection report. Within these areas, the inspection consisted of selective ====4 nation of procedures and representative records, inter-views with personnel, and observations by the inspectors.
> - Within the scope of the inspection, no items of noncompliance were identi-
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! We have also awa=ined actions you have taken with regard to a previously *
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- ~ Identified inspection finding. The status of this item is identified in
' . paragraph 2 of the enclosed repor (, -
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In accordance with Section 2.790 of the NRC's " Rules of Practice," Part 2, .
{s-- Title 10, Code of Federal Regulations, a copy of this letter and the enclosed" i
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inspection report will be placed in the NRC's Public Document Room. If the report contains any information that you believe to be proprietary, it is necessary that you submit 'a written application to this office, witbin 20 days of the date of this letter, requesting that such information be withheld from public disclosure. The, application must include a full statement of the reasons why it is claimed that the information is proprietary. The application should be prepared so that any proprietary information identified is contained in an j enclosure to the application, since the, application without the enclosure will also be placed in the Public Document Room. If we do not haar from you in this regard within the specified period, the report will be placed in'the ** Public Document Roo , . . , :-
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Kansas Gas and Electric Company -2- February 26,1980
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Should you have any questions concerning this inspection, we will ,'be pleased to discuss them with yo '
Sincerely, .
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, w W. C. Seidl< Chief Reactor Cons uction and Engineering Support Branch
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Enclosure:
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IE Inspection Report No. STN 50-482/80-03 e -
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_ _ _ _ _ _ . _____ _ __________________________________ - __ .
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT ., . REdIONIV j
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Report No. STN 50-482/80-03 Docket No. STN 50-482 Category A2 Licensee: Kansas Gas and Electric Company l P. O. Box 208
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Wichita, Kansas 67201 Facility Name: Wolf Creek, Unit No. 1 3 Inspection at: Wolf Creek Site, Coffey County, Burlington, Kansas
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Inspection conducted: February 11-14, 1980
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I . Inspe'etors : ;; * r 2! 80
. E. Martin, Reactor Inspector, Projects Section Este (Paragraphs 1, 2, 3, 5 & 6)
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L. D. Gilliert, Reactor Inspector, Engineering Support Sr/s o Date' .-*' . Section (Paragraph 4) .
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- , Reviewed: *:: - 80 f C. R. Oberg, Reactor Inspector, Projects Section Date'
t a . Approved: [ en- - ~ 2- 8d W. A. Crossman, Chief, Projects Section Date L5" O R. E. Hall, Chief, Engineering Support Section batd
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Inspection Summary:
' Inspection on February 11-14, 1980 (Report No. STN 50-482/80-03)'
Areas Inspected: Licensee action on a previously identified item of noncompliance; ' safety-related piping; review of records and observation of work for safety-related steel supports; and site tour. The inspection involved forty-eight inspector-hours
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on site by two NRC inspector Results: No items of noncompliance or deviations were identifie .
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DETAILS
.. . Persons Contacted *
Principal Licensee Personnel }
* E. Clark, Manager, Quality Assurance, Site * Prigel, . Assistant Manager, Quality Assurance, Site *S. J. Walmsley, QA Technician *G. L. Fouts, Construction Manager, Site Daniel International *W. E. Hitt, Troject Manager t *R. D. Scott, Construction Manager .. *V. J. Turner, Project . Quality Assurance Manager (,_ *D. L. Jones, Quality Control Manager , - *D. J. Dennison, Assistant QC Manager s-_ . B. G. Bullard, Project Welding Engineer '
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"D~ *T. R. Barber., Assistant Welding Engineer P. C. Schaffer, Supervisor-Mechanical Welding QC ~(
r_ '. G. Martin, General Foreman, Welder Qualification -
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D. C. Bondurant, Mechanical Engineer p,'?... D. J. Harris, Area Civil Engineer F f Others
*R. D. Brown, Site Representative, SNUPPS
* R. Seiple, Resident Geotech, Dames & Moore
.,,, *E. Glasbergen, Site Manager, Westinghouse
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The IE inspectors also interviewed other licensee and contractor persongel
-. - including members of the.QA/QC and engineering staff e
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{,- * Denotes those, attending the exit intervie .
-- Licensee Action on Previous luspection Finding '.
(Closed) ltem of Noncompliance (STN 50-482/79-17): Failure to Follow Procedures for Blasting Operation The IE inspector reviewed the Dames & Moore records for the blasting performed on September 15, 1979, and the subsequent Daniel approved qualifications of Mr. R. D. Blake. Clarkson Blasting Procedure (B-1),
Revision 2 now includes the Daniel approved blasting specialist's qualifications as an enclosure and requires the blasting specialist's name to appear on the cover sheet of the blasting pla . This item is considered close .
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; Site Tour r l
The IE inspectors made a tour of the Reactor Building, Auxiliary Building, 7 and other general plant areas to observe construction activities in progress i and to inspect housekeepin f
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The IE inspectors advised the licensee representative of two areas (one inside containment around the base of the a
REGION LETTER & NO$ FOR ACTION
, z:. * - INSPECTION"NVESTIG ATION 8sNDiNGS tCMECK ONE sox ONLvt g** sg JI
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1 7 CLEAR 2 C NONCOMPLt ANCE 3 C DEVtAflON 4 C NONCOMPLtANCE & DEVIATION L lENFORCEMENT CONFERENCE MELO.1 C 30
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M NUMSER OF NONCOMPLIANCE ITEMS IN LETTER TO LICENSEE: moTg. cmAnos uus7 es sueurTTao ! om iss e s=gven easviowLv-e :3.o :Tsu os moncompuanca , N NUMSER OF DEVIATION ITEM $ 1N LETTER TO LICENSEE: 80 ICIALLv DELETBo FRoM Two'n' econ . O NUMSER OF LICENSEE EVENTS ,1 .,
~ ; , p 48 INSPECTION FEE 1 O NON. ROUTINE / VENDOR (No Feel 2 C ROUTINE INo Feel 3 0 ROUtsNE (Feel 4 C ROUTINE (Fee Remussel j .
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.- REGIONAL OFFICE LETTER OR REPORT TRANSMITTAL QATE FOR INSPECTION OR INVESTIGAT ON
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lesME04 ATE ACTION LETTER E DATE M !, en' 4A M E4
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$USJECT OF INVESTsGATION ICMECK ONE SQx ONLY6 6667 TYPE A 10 CFR 20 403 TYPE 8 10 CFR 20.405 MIS OS C 11 C INT. OVEREXPOSURE 150 CRITICALITY 21C EQUIP. FAILURE 01 C INTE RN AL OVER E XPOSURE
, 12 C EXT. OVEREXPOSURE 1e C LOS$/ THEFT 220 ALLEGATION / i C2 C EXTERNAL OVEREXPOSURE 07 C' COMPLAINT 5 03 C RELEASE TO UNREST. AREA 00 0 13C EXCESS RAD. LEVELS . 17 C MUF 00 C 14 C EXCESS CONC. LEVELS le C TR ANSPORTATION 23C PUSLtc INTEREST 04 C LOS$ OF F ACILITY 10C IS C CONTAM/ LEAKING 24C SA80TAGE 05 C PROPERTY DAMAGE . SOURCE 25C ASNORMAL OCCUR.
I 20 C ENVIRONMENT AL EVENT 200 OTHER
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NOTE: SLOCKS K TO N MUST SE U DATE MOS ENFORCEMENT LETTER. NOTICE. ORDER ISSUE l l l l l l l 9ERIFIED SY IE:MOS M M 0 0 Y Y . mutNEVER ENTRIES ARE $
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ANCV V CIVIL PE N ALT.Y,fS5UE D
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1IIII 75 W CATE 766 ENTERED NTO COMPUTER FILE IMO/vRI: y u y y ,
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FOftM NRC 704 - S80E 3 4 USNRC INSPECTION Er ENFORCEMENT STATISTICAL DATA
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Wolf Creek, Unit NO. 1 f NOTE: STATUS CODING; I f NOTE: MODULE REQUIRING j FOLL I eLANK TO REMAIN OPEN E ONLY WHEN MODULE f' LE NOTE:% AVE BLANK COMPLETE FOR MC 92,93 &ANDSTATUS; 94 I - C. CLOSED I 4' INSPECTE D IS 92 7018' i
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4 PROCEDURES AND 30 702. 30 703 &L L REOPEN & LE AVE OPEN 30ano l' P REOPEN.THIS TRANSACTION ' l
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. DN STN 50-482/80-03 t NONCOMPLIANCE M MODOLE TRACKING INFORMATION MODULE NO, INSP, ET . -
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,- .. _ .- . ' . ENCLOSURE 3 ,
UNITED STATES
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Emcg#o NUCLEAR REGULATORY COMMISSION
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REGION IV
S11 RYAN PLAZA DRIVE,SulTE 1000 ARLINGTON, TEXAS 76012 s .9 . b , , , . *# June 17, 1980 In Reply Refer To: BIV Docket No. SIN 50-482/Rpt. 80-11 Kansas Gas and Electric Company ATTN: Mr. Glenn L. Koester Vice President-Operations Post office Box 208
.. Wichita, Kansas 67201 'L - -
Gentlemen: iC '-
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r This refers to the inspection conducted by Messrs. L. E. Martin and L. D. Gilbert of .our stiff during the period May 27-30,' 1980, of activities authorized by NRC c- Construction Permit No. CPPR-147 for Wolf Creek, Unit No.1, and to the discussion
%- ~ of our findings with Mr. M. E. Clark and other members of your staff at the E conclusion of the inspectio Areas awa=4nad during the inspection and.our findings are discussed in the enclosed inspection report. Within these areas, the inspection consisted of selective ====4== tion of procedures and representative records, interviews with ,
personnel, and observations by the inspectors.
. , During the inspection, it was found that certain activities under your licenIe appear to be in noncompliance with Appendix B to 10 CFB.50 of the NRC Regulaf. ions,
' "" Quality Assurance Criteria for Nuclear Power Plants." .The item of noncompliance ' - ,and references to the pertinent requirements are identified in the enclosed ,
f Notice of Violatio t a i" We have also ====4==d actions you have taken with regard to previously ident1'fied inspection findings. The status of these items is identified in paragraph 2 of the enclosed repor l , This notice is sent to you pursuant to the provisions of the Section 2.201 of ' the NRC's " Rules of Practice," Part 2 Title 10, code of Pederal ' Regulation Section 2.201 requires'you to submit to this office, within 30 days of your i receipt of this notice, a written statement or explanation in reply includin ,
(1) corrective steps which will be taken by you, and the results achieved; I (2) corrective steps which will be taken to avoid further noncoup,11ance; and - -
(3) the date when full compliance will be mehiave *
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Kansas Gas and Electric Company 2 June 17, 1980 In accordance with Section 2.790 of' the NRC's " Rules of Practice," Part 2, 'I Title 10, Code of Federal Regulations, a copy of this letter and the enclosed inspection report will be placed in the NRC's Public Document Room. If the report contains any information that you believe to be proprietary, it is necessary that you submit a written application to this office, within 20 days of the date of this letter, requesting that such information be withheld from public disclosure. The application must include a full statement of the reasons why it is claimed that the information is proprietary. The application should be prepared so that any proprietary information identified is contained in an enclosure to the application, since the application without the enclosure will also be placed in the Public Document Roo If we do not hear from you in this regard within the specified period, the report will be placed in the Public Doctanent Roo s T Should you have any questions concerning this inspection, we will be pleased - _ to discuss them with yo ' T C
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Sincerel g
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e fi~ f W. C. S
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le, Chief s - Reactor truction and Engineering Support Branch
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Enclosures:
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, Appendix A, Notice of Violation ; ,,- . IE Inspection Report No. SDI 50-482/80-11 - . ,
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STN 50-482/80-11
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ppendix A
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NOTICE OF VIOLATION . ' Based on the results of the NRC inspection conducted on May 27-30, 1980, it appears that certain of your activities were not conducted in full compliance
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with the conditions of your NRC Construction Permit No. CPPR-147 as indicated below: i Failure to Specify Appropriate A
REGION IV==
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Report No. STN 50-482/80-11 . Docket No. STN 50-482 Category A2 Licensee: Kansas Gas and Electric Company ! P. O. Box 208 l l . Wichita, Kansas 67201 l Facility Name: Wolf Creek, Unit No. 1 i Inspection at: Wolf Creek Site, Coffey County, Burlington, Kansas
' --- Inspection conducted: May 27-30, 1980 . 'C .- -
Inspectors: [ =;r.-- /3
' , - L. E. Martin, Reactor Inspector, Projects Section Date . (Paragraphs 1, 2, 3, 6, 7 & 8)
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M . D. Gilbert,~ Beactof Inspector, Engineering 'Date
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R ai~wed: e re 8 j . C. R. Obets, Reactor Inspector, Projects Section 'Date ,
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'Da'te R. E. Halli Chief, Engineering Support Section
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Inspection Suasnary: Inspection on May 27-30, 1980, (Report No. STN 50-482/80-11) Areas Inspected: Licensee action on previous inspection findings; safety-related pipe welding; containment penetration welding; electrical raceway and equipment installation; and IE follow up on licensee identified deficiencies'. The inspection involved forty-eight inspector-hours by two NRC inspector * Results: Of the five areas inspected, one item of noncompliance was identified in one area (infraction - failure to specify appropriate acceptance criteria - paragraph 5).
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DETAILS l
. Pe-sons Contacted .
Principal Licensee Personnel -
*M. E. Clark, QA Manager Site *
D. W. Prigel, QA Engineer G. W. Reeves, QA Engineer
*D. G. Plasce, QA Technical Auditor *J. L. Stokes, Assistant Construction Manager
' Daniel International (Daniel) Personnel l
*T. Damashek, QC Engineer, Civil
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*C. E. Backney, QA Engineer, Welding M. Dugan, Electrical QC Inspector
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j D. C. McBee, Welding General Foreman C '
' C. Light, Pipe Department General Foreman c
, N. G. Wigginsi Pipefitter Foreman -
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-B. G. Bullard, Project Welding Engineer ! -
I ' . W. J. Dennison, Assistant QC Manager
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SNUPPS l R. D. Brown, Site Representative Yan=== Electric Power Cooperative
. A. Mee, Engineer .
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' ~ * Denotes those present at the exit interview - - The II inspectors also interviewed other licensee and contractor personnel ~
f., during the course of the inspectio , t (~ Licensee Action on Previous Inspection Findings .-
(Closed) Infraction (50-482/80-05): Failure to Provide Appropriate and Prompt Corrective Action. The reactor vessel internals have been relocated to in-place storage inside containment and the reactor head has been relocated to a new sheet metal storage building'in an area that is not susceptible to '
flooding. These actiions should preclude water ingress into the storage areas for these component . This item is considered close :
(0 pen) Unresolved Item (50-482/80-05): Concrete Expansion Anchors. Daniel had initiated a Request for Clarification of Information (RCI,No. 7153) to determine if there were criteria for the minimum distance that a replacement anchor can be located from an abandoned anchor. The response on the RCI from Bechtel Site Liasion Engineer stated that there were no criteri .,
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The IE inspector asked the responsible individual if this statement meant that there was not a requirement for criteria or if he could not find the criteria. The individual stated that he was not able to identify or locate any criteria for the minimum spacing from abandoned anchors.
- This ites will remain open until Bechtel can furnish data substantiating that tha repair and installation methods that have been used for concrete expansion anchors meet the requirements for loading plus safety factor of the original desig (0 pen) Unresolved Item (50-482/79-07)
- II/I Problem with Electrical Pro-cedure Interim Change (ICP) No. 156 to QCP-X-302 now includes within its scope II/I and indicates that the inspection requirements are the same as Class IE. The craft procedures are now undergoing revision to include the II/I requirement ,
3 This item will remain open pending revision of all pertinent procedure .
~ Site Tour 4- ' '
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The IE inspectors walked through the Reactor Building, Auxiliary Building, Control Building, and various outside storage areas to observe constructibn
' attivities in progress and housekeeping practice ' .
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No items of noncompliance or deviations were identifie . Safety-Related Piping ' The IE inspector observed welding of safety-related piping in the
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- mv-h Baron Refuelina Water Steam (Drawina I-M-03BN01(Q)) .
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F 014 Fill Welding ; F 016R-2 , Final Visual Inspection
' Chemical and Volume Control System (Drawina I-M-03BG01(Q))- ,
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F 025 FitUpInspection,Roo}tandFillWelding .
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F 022 Final Visual Inspectiqu ; i
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In the areas inspected, no discrepancies from the requirements of welding procedure CWP-507 and visual inspection procedure QCP-VII-200 were note Welding filler materials were. observed to be controlled and traceable to certified material test reports as required by the procedure.for Control of Welding Consumables (CWP-503). The Material Receiving Reports (MRR) for the following filler material heat numbers were inspected: Heat Number MRR Number 7D21B Mix 12 3435 411J4141 41727
, 462571 30669
__ No items of noncompliance or deviations were identifie .
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5. - Penetration Assemblies c
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using the. Gas Tungsten-Arc Welding process and welding procedure technigde f .. sheet N-1-1-BA-1, Revision 4. W 537 is identified on sheet D-2 of Drawing Ej C-OL-2916(Q)01 as a Class MC butt welding in penetration E-283 with Bechtel Specification 10466-M-204 as the control document. Specification 10466-M-204, paragraph 5.6.1 specifies requirements for asaking penetration welds in accordance with NE-4000, Class MC. In addition to technique sheet N-1-1-BA-1; technique sheet N-1-8-BA-24, Revision 0, a procedure specifically issued for welding carbon steel to stainless steel for NE-4000 applications; and '
.,..- QCP-VII-200, Revision 5, the visual inspection procedures were selectively
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! with ME-4000, in that the limits for maximum reinforcement of butt welds 1 (~ ~ -
specified in N-1-1-BA-1, N-1-8-BA-24 and QCP-VII-200 are less restrictive *
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f than required in NE-4000, paragraph NE-4426 of ASME Code, Section III,1974 g-- Edition through Summer 1975 Addenda. For example, NE-4426 limits maximum ~
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reinforcement to 3/32 inch for a material thickness of one inch, whereas, the welding technique sheets and Quality Control procedure permit a maximum reinforcement of 3/16 inch for a material thickness of one inch. For all nominal material thicknesses greater than 1/8 inch, the procedural allowance is greater than'the allowance permitted by NE-442 ~ This is an apparent item of noncompliance with Criterion V of 10 CFR 50, Appendix B, in that these procedures,did not specify appropriate acceptance criteri :
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. - _ . -- .- . . - . - . . . Electrical Systems and Components The IE inspector observed the partial installation of one 480 volt motor control center (NG02A) and one cable tray support (331-08). Neither installation was complete, but the IE inspector inspected the partial installation for compliance with the following engineering and construction documents:
480 Volt MCC NG021 Manufacturer's I.B. 10466-E-018-0190-06 Bechtel Specification 10466-E-018 Daniel Work Assignment WA-EI-331-03
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Design Change Notice DCN C-003-Rev. 8
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Cable Tray Support 331-08 Bechtel Drawing EOR-3311, Rev. 14
'w- J Bechtel Drawing C-0401(Q), Rev. 8 . ' ..
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' t Bechtel Drawing C-0404(Q), Rev. 9 - .. Daniel Field Sketch FSK-E-331, Rev. 11 Daniel Work Assignment WA-EI-331-01 QC Raceway Support Checklistis Dated April .9, April 5, March 1, and March 8,1979 for support 0331-08 The IE inspector also reviewed the c'ertification records for tec I.evel II and one Level I Electrical QC inspectors for compliance with ANSI-N45. ,
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No items of noncompliance or deviations were identifie .
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. .. Follow Up on Licensee Identified Deficiencies l
The IE inspector discussed the potential 50.55(e) item concerning Rockbestos l cable jacket extrusion defects reported to NRC on April 3, 1980, and KG&E's l letter of May 8, 1980, informing the NRC, that based on testing by Rockbestos, that the jacket defects do not constitute a 10 CFR 50.55(e) deficiency. The Rockbestos testing, according to KG&E, shows that the cable still meets the specification requirements and the original IEEE-323 test requirement The test documentation was not available on site, but KG&E advised the IE inspector that it would be on site for review during a subsequent inspectio The IE inspector observed the termination problems with Bunker-Ramo electrical penetrations. The licensee had identified improper crimps on lugs, undersized lugs, and improper insulation strippin Bunker-Ramo representatives were on site to determine corrective actions. This problem was reported to NRC
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on May 19, 1980, and was KG&E's response to investigating a SNUPPS 50.55(e) L of March 14, 1980, at Callawa . _
.r These items will remain open until the licensee submits his report as ,
t required by 10 CFR 50.55(e). " l
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- " Exit Interview .
F? The IE inspectors met with licensee representatives (denoted in para-graph 1) at the conclusion of the inspection on May 30, 1980. The IE inspector summarized the scope and findings of the inspection. The item of noncompliance was acknowledged by the licensee representative . i _
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ENCLOSURE 4
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c,#* *% UNITED STATES
'. : .i,ed NUCLEAR REGULATORY COMMISSION ; S ; j REGION IV t * s11 RYAN PLAZA DRIVE, sulTE 1000 ..
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% ,[[' * ARUNGTON.. TEXAS 79011 _
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October 23, 1980 ~. In Reply Refer To: RIV
Docket No. STN 50-482/Rpt. 80-20 Kansas Gas and Electric Company Attn: Mr. Glenn L. Koester Vice President-Nuclear Post Office Box 208 Wichita, Kansas 67201 Gentlemen: , u W 1This refers to the inspection conducted by Mr. L. D. Gilbert of our staff c
- ~ - during the period. October 7-10, 1980, of activities authorized by NRC Constr$1c- .
tion Permit No. CPPR-147 for Wolf Creek, Unit No. 1, and to the discussio'in { g 1 . of our findings with Mr. D. W. Prigel and other members of your staff at the-
' r conclusion of the inspectio Areas m eined during the inspection and our findings are discussed in the enclosed inspection report. Within these areas, the inspection consisted of selective av -4 m tion of procedures and representative records, interviews with . personnel, and observations by the inspecto . .Within the scope of the inspection, no items of noncompliance were identifie ; ,, .
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,,-gns, new unresolved item is identified in paragraph 3.a of the enclosed repor' ; p~~ In accordance with Section 2.790 of the NRC's " Rules of Practice," Part 2, .
g Title 10, Code of Pederal Regulations, a copy of this letter and the enclosard p.- inspection report will be placed in the NRC's Public Document Room. If the;
-- report contains any information that you believe to be proprietary, it is necessary that you submit a written application to this office, within 20 days , ; of the date of this letter, requesting that such information be withheld from l
- public disclosure. The application mst include a full statement of the reasons
' why it is claimed that the information is proprietary. The application should j be prepared so that any proprietary information identified is contained in an I enclosure to the application, since the application without the enclosure vill
also be placed in the Public Document Room. If we do not hear from you in this i regard within the specified period, the report will be placed in the Public
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Document Roo !
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Kansas Gas and Electric Company 2 October 23, 1980
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Shouldyouhaveanyquestionsconcerningthisinspection,wevilkbepleased to discuss them with yo
Sincerely, .
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/ 0 W.C.Seihe, Chief Reactor Construction and Engineering Support Branch
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Enclosure:
- IE Inspection R. sport No. STN 50-482/80-20 y .- -
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION'AND ENFORCEMENT
REGION IV
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Report No. STN 50-482/80-20 Docket No. STN 50-482 Category A2 Licensee: Kansas Gas'and Electric Company P. O. Bor 208 Wichita, Kansas 67201-Facility Name: Wolf Creek, Unit No. I
;. Inspection at: Wolf Creek Site, Coffey County, Burlington, Kansas u '
Inspection conducted: October 7-10, 1980
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Approved: ,_ M /e" g W. A. Crossma:1, Chief, Projdcts Section
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Inspection on October 7-10, 1980 (Report No. STN 50-482/80-20) Areas Inspected: Routine, unannounced inspection of construction activities including site tour and observation of work and review of records for welding of Reactor Coolant Pressure Boundary piping. The inspection involved seven-teen inspector-hours by one NRC inspector. - Results: No items of noncompliance or deviations were identifie .
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DETAILS l Persons Contacted Principal Licensee Personnel [
*D. W. Prigel, Assistant QA Manager *G. W. Reeves, QA Engineer *C. A. Snyder, Construction *J. Stokes, Construction
Daniel International (Daniel) Personnel
*C. Phillips, Engineering Manager
*R. Schofield, Welding Engineer
*W. E. Hitt, Project Manager
*R. Scott, Construction Manager
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,__ . *N. Criss,. Audit Response Coordinator ,
J *t- *M. D. Pfeifer, QC Engineer '-
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D. Dennison, Assistant QC Manager
> =. 'C.. Chavis, QC Senior Receiving Inspector . ~
V .. . p! * Denotes those present at the exit intervie The IE inspector also interviewed other contractor personnel during the course of the inspectio . . Site Tour
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- Reactor Coolant Pressure Boundary Piping 2 '
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i" Review of Procedures The IE inspector reviewed the Daniel Procedure for welding stainless steel, Procedure CWP.507, Revision 10, which included the Welding ' Technique Sheet (WTS) being used for machine welding the Reactor Coolant Loop piping, WTS NM-8-8-B-1, Revision 4 and its supporting procedure qualification tests, PQT-111 and PQT-18 . In the areas reviewed, no discrepancies with the requirements of the ASME Code Section III-NB or Section IX 1974 edition including Summer 1975 addenda were note ,
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During the inspection, it was noted that CWP 507 and WTS NM-8-8-B-1 were being used'for welding base material specification SA 351 Grade CF8A (P No. 8) to base material consisting of Type 308L filler metal (A No. 8) buttered onto base material specification SA 2,16 Grade WCC (P No. 1), when neither material is listed in Table I of CWP 507 for ~
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determining the type of filler metal to be used for welding the combination, e.g., field weld F 304 on Drawing I-Loop 3(Q). Since the ASME Code is not clear concerning the qualification of procedures for welding P No. 8 material to A No. 8 material, this item shall be considered unresolved pending a revision of the procedure as supported by a code clarificatio Observation of Welding Activities The IE inspector observed activities associated with fit up, welding and inspection of six field welds in the Reactor Coolant Loop pipin i
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The field welds and the activities observed were as follows: .
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Field Welds Drawing Activity
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b F 304 I-Loop 3 (Q) Welding F 404 I-Loop 4 (Q) Welding F 201 I-Loop 2 (Q) Repair Welding
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v F 402 I-Loop 4 (Q) ISI Weld Prepi (E: -
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REGION IV
.- -% - ARL N TON T X 760 2 q ^/a -
June 16, 1981
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.In Reply Refer To:
RIV Docket STN 50-482/Rpt. 81-11 Kansas Gas and Electric Company AT1N: Mr. Glenn L. Koester Vice President - Nuclear Post Office Box 208 Wichita, Kansas 67201-( .
[_ Gentlemen: - ,
e This refers to the' inspection conducted by Mr. L. D. Gilbert of our staff ~ l e_ during the period June 1-5, 1981, of activities authorized by NRC Constructiot) Permit CPPR-147 for Wolf Creek, Unit 1, and to the discussion of our findings-F with Mr. D. W. Prigel and other members of your staff at the conclusion of the inspectio Areas examined during the inspection and our findings are discussed in the enclosed inspection report. Within these areas, the inspection consisted of selective examination of procedures and representative records, interviews
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with personnel, and observations by the inspecto ~
- Within the. scope of the inspection, no violations or deviations were identi .=.. fie :
E- -Two new unresolved items are identified in paragraphs 4 and 5 of the enclose '
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We have also examined actions you have taken with regard to previously identified inspection findings. The status of these items is ide-tified in paragraph 2 of the enclosed repor In accordance with 10 CFR 2.790 of the Comission's regulations, a copy of this letter and the enclosed inspection report will be placed in the NRC's Public Document Room. * If this report contains any information that you believe to be exempt from disclosure under 10 CFR 9.5(a)(4), it is necessary that you (a) notify this office by telephone within 10 days from the date of this letter of your intention to file a request for withholding; and (b) sub-mit within 25 days from the date of this letter a written application to this office to withhold such information. If your receipt of this letter has been i r delayed such that less than seven days are available for your review, please notify this office promptly so that a new due date may be establishe ; ! l 7 I MNd 2 C . f n yD e
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Kansas Gas and Electric Company -2- June 16, 1981 Consistent with Section 2.790(b)(1), any such application must be accompanied by an affidavit executed by the owner of the infomation which identifies the document or part sought to be withheld, and which contains a full statement of the reasons on the basis which it is claimed that the infomation should be withheld from public disclosure. This section further requins the statement to address with specificity the considerations listed in 10 CFR 2.790(b)(4).
The infomation sought to be withheld shall be incorporated as far as possible into a separate part of the effidavi If we do not hear from you in this regard within the specified periods noted above, the report will be placed in the Public Document Roo Should you have any questions concerning this inspection, we will be pleased to discuss them with yo *
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Enclosure:
IE Inspection Report STN 50-482/81-11 w .
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U.S. NUCLEAR REGULATORY C0 MISSION OFFICE OF INSPECTION AND ENFORCEMENT
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' Report: STN 50-482/81-11 l Docket: STN 50-482 Category A2
Licensee: Kansas Gas and Electric Company
Post Office Box 208 Wichita, Kansas 67201 Facility Name: Wolf Crtek, Unit 1
) . Inspection at: Wolf Creek Site, Coffey County, Burlington, Kansas ,
u - Inspection Conducted: June 1-5, 1981
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=- Inspe'ctor: ' ~ // %- /A.. D. Gilbert, Reactor Inspector, Engineering and Materials
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,,b I Section Approved: 4 ( / , ,
R. E. Hall, Acting Chief. Engineering and Materials Section Date
- Inspection Suninary:
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F- Inspe'e tion During June 1-5, 1981 (Report STN 50-482/81-11)
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- . Areas Inspected: Licensee action on previous inspection findings; site tour; ,
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f and observation of work and review of records for welding of Reactor Coolant Pressure Boundary and other safety-related piping. The inspection involved e .
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r- 29 inspector-hours on site by one NRC inspector.
- Results
- In the areas inspected, no violations or deviations were identifie i .
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DETAILS Persons Contacted , Principal Licensee Personnel
. *D. W. Prigel, QA Manager, Site *P. Burck, QA Engineer *C. Snyder, Construction Supervisor Daniel Internati ns! Personnel *L. Bryant, Project Quality Manager *D. Dennison, Project Quality Inspection Manager *R. Schofield, Project Welding Engineer J. Doebler, Pipe Superintendent Automatic Welding , . R. Rigdon, QC Training Superviser . ~
The NRC inspector also interviewed other contracter personnel during i gi-
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? Denotes those present at the exit intervie *
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Licensee Action on Previous Inspection Findings
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(Cicsed) Infraction (STN 50-482/80-11): Failure to Specify Approcriate A
REGION IV sig nv AN PLAZA DRIVE SulTE 1000
, , .f AR LINGTON, TE X A5 76011 *****
April 29,1982
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Docket: STN 50-482/82-06 Kansas Gas and Electric Company ATTN: Mr. Glenn L. Koester Vice President - Nuclear P. O. Box 208 Wichita, Kansas 67201 Gentlemen: This refers to the inspection conducted by Mr. L. D. Gilbert of our staff
. during the period March 29 - April 2,1982, of activities authorized by T NRC Construction Permit CPPR-147 for Wolf Creek, Unit 1, and to the dis- <
cussion of our findings with Mr. D. W. Prigel and other members of your - , e staff, at the conclusion of the inspectio } f' Areas examined during the inspection ano our findings are discussed in the enclosed inspection report. Within these areas, the inspection consisted of selective examination of procedures and representative records, interviews with personnel, and observations by the inspecto Within the scope of the inspection, no violations or deviations were identi-fie . One new unresolved item is identified in paragraph 3.a of the enclosed report. { F in accordance with 10 CFR 2.790(a), a copy of this letter and the enclosure will be placed in the NRC Public Document Room unless you notify this office,
- -
P- ty telephone, within 10 days of the date of this letter and submit written *
; application to withhold infonnation contained therein within 30 days of the ' !-- '
date of this letter. Such application must be consistent with the require- - rentsof2.790(b)(1).
Should you have any questions concerning this inspection, we will be pleased to discuss them with yo ,
Sincerely, ,
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W. C. Seidle, Chief
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Reactor Project Branch 2 .
Enclosure:
- Appendix - NRC Inspection Report STN 50-482/82-06
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APPENDIX U. S. NUCLEAR' REGULATORY COMMISSION
REGION IV
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This Report Contains Results of an Investigation Report: STN 50-482/82-06 Docket: STN 50-482 Category A2 Licensee: Kansas Gas and Electric Company P. O. Box 208 Wichita, Kansas 67201
\_ Facility Name: Wolf Creek, Unit 1
. Inspection at: Wolf Creek Site, Coffey County, Burlington, Kansas 4 ^ "
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Inspection Conducted: March 29 - April 2, 1982 & 9 .
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E,- e Inspector: 4/' 9W83 L. D. Gilbert, Reactor Inspector, Engineering Section 'Datt - Reviewed:
# 7b - R. E. Hall, Chief, Reactor Project Section C Daty , - .
e . Approved: 29 M
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m& f/-? 7/81 I" D. M. Hunnicutt, Chief, Engineering Section Date'
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Q t" Inspection Sunwary - Inspection durina March 29 - April 2, 1982 (Report STN 50-482/82-06) Areas Inspected: Routine, unannounced inspection of construction activities incluoing an allegation item and observation of work and review of records for welding and nondestructive examination (NDE) of Reactor Coolant Pressure Boundary piping. The, inspection involved 30 inspector-hours onsite by one NRC inspecto Results: No violations or deviations were identified. The allegation dis-cusseo in paragraph 2 was not substantiated, t
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DETAILS
, Persons Contacted
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Principal Licensee Personnel
*0. W. Prigel, Manager QA, Site *G. W. Reeves, Assistant Manager QA, Site *0. L. Thero, Supervisor, QA Surveillance *C. E. Parry, Supervisor, QA Systems *D. A. Colwell, QA Technologist "J. L. Stokes, Project Support Supervisor Other Personnel -
J. Johnson, Project Piping Engineer, Daniel International Corporation ,
'
h- (Daniel) - J. Linsome, Mechanical Superintendent, Daniel '
#. . '
G. Robertson, NOE Level III, GEO Construction Testing <
. TheNRCinspectoralsointerviewedotherlicenseeandcontractoremplo'eek y
- during the course of the inspectio .
{_
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b * Denotes those attending the exit intervie . A11ecation Regarding Improper Weldina Techniques
! An allegation regarding improper welding techniques, received by the NRC l Resident Reactor Inspector on March 4, 1982, was reviewed by the NRC l l% inspector during the inspection. A welder claimed that while taking a i ' g" . .
test on Performance Test No. N-8-8-B-3 he was told to run the root pass , !
W,
. - and " wash" the remainder which he believed to be contrary to the procedur l 5* .. .- He refused to complete the weld by " washing" and was fired. The welder .
i also stated that he believed this practice was common onsite for weld-out <
[-- - of small bore extra strong pipe, but that it is not in a
REGION IV -
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Report: STN 50-482/82-15 Docket: STN 50-482 Category A2 Licensee: Kansas Gas and Electric Company P. O. Box 208
. Wichita, Kansas 67201 Facility Name: Wolf Creek, Unit 1 --- Inspection at: Wolf Creek Site, Coffey County, Burlington, Kansas -
p Inspection tonducted: October 4-8, 1982
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_ Inspector:
" ^ ~
L. D. Gilbert, Reactor Inspectnr, Engineering Section h/6L Date f/-- Reviewed: ue /Y1 'I #2_ Date QW/ D.(J@nson, Chief, Reactor Project Section C "
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Approved: h D. M. Hunnicutt, Chief, Engineering Section / 81-
, Dat'e}
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In'spection Summary h
' . Inspection durino October 4-8, 1982 (Report STN 50-482/82-15)
C i" Areas Inspected: Routine, unannounced inspection of licensee action on I-previous inspection findings; site tour; observation of work and review of records for welding and nondestructive examination (NDE) of safety-related piping. The inspection involved 30 inspector-hours onsite by one NRC inspector.
Results: In the areas, inspected,'no violations or deviations were identifie .
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DETAILS
. Persons Contacted Principal Licensee Personnel *D. W. Prigel, Manager, QA Site *D. L. Doncooe, QA Technologist *0. L. Thero, Supervisor, QA Surveillance *C. E. Parry, Supervisor, QA Systems * A. Colwell, QA Technologist 3 * W. Holloway, Project Construction Supervisor %7 *J. Fletcher, Quality Control $ Other Personnel ' - < . .
-* C. Grill, Project Piping Engineer, Daniel * - . - International Corporation (DIC) *
ffs- C. D. Mauldin, Project Quality Engineer, DIC
"~ G. Robertson, NDE Level III, GEO Construction Testing '
The NRC inspector also interviewed other licensee and contractor employees during the course of the inspectio ,
" Denotes those attending the exit intervie ,s
'
,2~. Licensee Action on Previous Inspection Findings lh[
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'(C1'osed) Unresolved Item '(8111-01): Grounding of welding machine to steam
, r , generator support base plat , I . t The NRC inspector reviewed the actions taken to resolve Deficiency Report F- No. ISD 7059M, which was issued to assess the potential damage resulting - from grounding a welding machine to a steam generator support base plate while welding on the Reactor Coolant Loop piping. The deficiency report was upgraded to Nonconformance Report No. ISN 3302 MW and work instructions were issued'to remove and inspect the steam generator support column for damage to the upper and lower pins and bearing surfaces. The visual inspection was performed and reported as acceptabl This item is considered resolve ,
* Site Tour
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! The NRC inspector toured the reactor building and auxiliary huilding to l observe construction in progress and to inspect housekeeping.
l No violat' ions or deviations were identifie j
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, Safety-Related Pipe Welding and Nondestructive Examination .
- Observation of Welding Activities \
The NRC inspector observed the welding and quality control ) activities associated with fabricating the following safety-related j piping weld ' Weld Control Drawing System Class i F-004 IM13BB04(Q) Reactor Coolant 1 1 FW-310 IM038G09(Q) Chemical & Volume Control 2 FW-320A IM03BG03(Q) Chenical & Vofume Control 2
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FW-313 IM03BG02(Q) Chemical & Volume Control 2 4_ F-002 IM038G16(Q) Chemical & Volume Control 3
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F-013 IM03BG16(Q) Chemical & Yolume Control 3
- FW-315 .
IM03BG16(Q) Chemical & Volume Control 3 , T FW-521 IM03BG16(Q) Chemical & Volume Control 3 , F-034A IM038G03(Q) Chemical & Volume Control 2 ;
=- FW-59 .IM03EM03(Q) High Pressure Core Injection 2 .
E .. FW-654 IM03EM03(Q) High Pressure Core Injection 2 P F-002 IM03EJ05(Q) Residual Heat Removal 2 F-001 IM03EG01(Q) Component Cooling Water 3 In the areas inspected, the entries on the weld control record were consistent with the status of the welds, the filler materials were traceable to certified material test reports, and the welders were
, qualified to ASME B&PV Code Section I ~ - Observation Of Nondestructive Examination Activities - .- -
_ The NRC inspector observed the liquid penetrant examination of the
,P- _ -
following completed welds: * 3-- Weld Control Drawing System Class 5-M96 IM03EM03(Q) High Pressure Core Injection 2 FW-654 IM03EM03(Q) High Pressure Core Injection 2 FW-306 IM03BM18(Q) Steam Generator Blowdown 2 FW-301 IM03BM20(Q) Steam Generator Blowdown 2 FW-301 IM03BM17(Q) Steam Generator Blowdown 2 The examinati'ons were performed consistent with requirements of GEO Procedure IPPT-340, Revision 1701-0 for liquid penetrant examination techniques, materials, and acceptance criteri :
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. _ Observation of Completed Welds The NRC inspector observed the weld surface condition of the following completed weld Weld Control Drawing System Class N1 IM13AE04(Q) Feedwater 2 FW-302 IM03EP01(Q) Safety Injection 1 F-001 IM03BB05(Q) Reactor Coolant 1 F-009 IM03EN03(Q) Containment Spray 2 F-001A IM13BB02(Q) Reactor Coolant 1 F-005A IM13BB02(Q) Reactor Coolant 1 , F-008 IM13BB02(Q) Reactor Coolant 1 FW-900 IM13BB02(Q) Reactor Coolant 1 -
F-004 IM13BB04(Q) Reactor Coolant 1 c FW-503 - IM13BB04(Q) Reactor Coolant 2
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FW-904 IM03EG24(Q) Component Cooling Water 3 FW-905 IM03EG24(Q) Component Cooling Water 1 3 FW-906- .IM03EG24(Q) Component Cooling Water 3 gg - FW-907 IM03EG24(Q) Component Cooling Water 3 P- F-003 IM03EJ05(Q) Residual Heat Removal 2 F-004 IM03EM03(Q) High Pressure Core Injection 2
.
In the areas inspected, no discrepancies with the requirements of ASME B&PV Code, Section III for completed welds were note Review of Nonconformance Reports
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The NRC inspector selected for review Nonconformance Report No. ISN5394 E- - - -
' ' on improper radiographic examination by GEO and determined that the .- recomunended disposition had been completed, cause of nonconformance *
had been established, and action to prevent recurrence had been
~ [~
e take ,
. ,__ ' Review of Records The NRC inspector reviewed the weld history and nondestructive examination documentation related to the fabrication of the following 14 completed weld '
Weld Control Drawing System Class
- N1 IM03BB05(Q) '
Reactor Coolant 1 l F-009 IM03EN03(Q) Containment Spray 2 ' F-001A IM13BB02(Q) Reactor Coolant -
F-005A IM13BB02(Q) Reactor Coolant ,
l F-008 IM13BB02(Q) Reactor Coolant -
FW-900 FW-503 IM13B802(Q) Reactor Coolant Reactor Coolant
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IM13BB04(Q) I l l
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FW-500 IM13BB04(Q) Reactor Coolant 2 FW-506 IM13BB04(Q) Reactor Coolant -
FW-509 IM13BB04(Q) Reactor Coolant 2 FW-904 IM03EG24(Q) Component Cooling Water 3 FW-905 IM03EG24(Q) Component Cooling Water 3 FW-906 IM03EG24(Q) Component Cooling Water 3 FW-907 IM03EG24(Q) Component Cooling Water 3 In the areas reviewed, the records indicated that specified inspections were completed; the records reflected adequate weld quality; and weld history records were adequat No violations or deviations were identifie u -
. Exit Interview TheNRCinspectormetwithlicenseerepresentatives(denotedinparagrapp1) *
.and T. E. Vandel (NRC Senior Resident Reactor Inspector) on October 8, f 1982, and summarized the scope and findings of the inspectio r ..
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ENCLOSURE 9
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In Reply Refer To: Docket: STN 50-482/83-12 26 g
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Kansas Gas and Electric Company ATTH: Glenn L. Koester Vice President - Nuclear km P.O. Box 208 Wichita, Kansas 67201 Gentlemen: This refers to the independent measurements inspection June 6-17, conducted by M Kerch and other members of the NRC, Region I office during the period
'1983, of activities authorized by NRC Construction Permit i CPPR-147, for th 4 - .
T Wolf Creek Generating Station and to the discussion o
' c t inspectio l -_
Areas examined during the inspection included safety-related piping,Within
*
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;
r.. structural, consisted and support weldment of selective examination of procedures andThese representative findings records p interviews with personnel, and observations by the inspector Ere documented in the enclosed inspection repor During this inspection, it was found that certain of your activities . t violation of NRC requirement ' these violations, in writing, in accordance with the provisions of
, - Section 2.201 of the NRC's " Rules of Practice," Part 2, Title 1 "
_,-(FederalRegulations.in Jhe Notice of Violation enclosed with this lette S .
.
F - In accordance with 10 CFR 2.790(a), a copy of this letter andffice, the enclosures ,
*
- will be placed in the NRC Public Document Room unless you notify this o ,
!.. by telephone, within 10 days of the date of this letter, and submit written
, ,
application to withhold information contained therein within 30 date of this lette i of 2.790(b)(1).
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RPB2
, 'v RPS-C O
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ES .I ES REHall WDJohnson WC5eidie LOGilbert: gb 8/?4/83 8/4 /83 8h 5 /83 ,
. 8/.- /83 ~
m Pk
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Kansas Gas and Electric -2-Company
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The response directed by this letter and the accompanying Notice is not subject to the clearance procedures of the Office of Management and Budget as
;
required by the Paperwork Reduction Act of 1980, PL 96-51 Should you have any questions concerning this inspection, we will be pleased to discuss them with yo
Sincerely, Urignal Oi ced By
,
W. C L;::a
'
4r W. C. Seidle, Chief
,__ ,
Reactor Project Branch 2 a-
,
c
Enclosures:
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1. - Appendix A - Notice of Violation *
- A'ppendix B - NRC Inspection Report pi" 50-482/83-12 bec to DMB (IE01)
bec distrib. by RIV: RPB1 Resident Inspector
. . RPB2 Section Chief (RPS-C)
TPB . J. Gagliardo, DRRP&EP .
" ~"b l. ~ . J. Collins, RA L. Gilbert *
jgs , C. Wisner', PA0 T. Morton, DDE&TP, RI MIS SYSTEM T. Westerman r_ .RIV File . E Myron Karman, ELD, MNBB (2) t KANSAS STATE DEPT. HEALTH -
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NOTICEdFVIOLATION Kansas Gas and Electric Docket No. 50-482/83-12 License No. CPPR-147 As a result of the' inspection conducted during the weeks of June 6 through June 17, 1983, and in a
REGION I==
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Report N /83-12 i Docket N License No. CPpR-147 Priority - Category C Licensee: Kansas Gas and Electric P.O. Box 208 5--- Vichita, Kansas 67201- $ Facility Name: Wolf Creek
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e
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Inspection At: Burlington, Kansas inspectionConducted: June 6 - 17, 1983 Inspectors: _omk 4 1 dat'e signed
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Hac W. Khrch '
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r' _ ar- SY
'date igned
$ ds Y D g- Rand / /dge signed -
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Approved by: -
<>/A A Pz ept- <;- M / R ':f -
acquf Durr
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Mat (signed
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Inspection Summary: Inspection on June 6 - 17,1983 (Report No. 50-482/83-12) Areas Inspected: A routine, announced NRC independent measurements inspection was concutted at the ut,ilities construction site using the NRC Mobile Nondestruc-tive Examination (NDE) laboratory. Selected safety related piping, structural and support weldments fabricated to ASME Code, Section III, Classes 1, 2 and 3 and American Welding Society (AWS) Code D1.1 requirements were inspected. Three regional base inspection personnel assisted by two sub-contracted NDE personnel were utilized during this inspection. The inspection involved 437.onsite hours and 196 offsite hour .'
,
Results: One violation was identified, radiographic penetrameter's were stationed across the weld area possibly masking indications on the radiograph (482/83-12-01) and one violation was identified concerning an unacceptable linear indication
' (482/83-12-02). -
r,n m I- ca f cy f
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D'e tails 1.0 Persons Contacted - Kansas Gas and Electric
* G. W. Reeves, Assistant Manager, QA
* C. E. Parry, QA Systems Supervisor
* E. W. Creel, Corporate QA Manager
* W. M. Lindsey, QA Supervisor
* T. Meyer, QC
* H. K. Helwig, Supervisor, Project Field Engineers
* J. G. Nelson, Project Quality Supervisor
- * J. Fletcher, LWQCE
'-- * W. M. Kemp, QA Auditor
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:
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* D. A. Colwell, QA Technician : - , ' '
Westinchouse - . R. Hopkins, Engineer -
[g~ * E. Glasbergen, Site Manager Daniels Int. Construction * E. G. Stuart, Senior QA Engineer J. R. Cook, Project QA'
Keith Hollingsworth, Project Welding Engineer
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'h, G. '
~ '* G.' P. Robertson
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I ~ ^ USNRC .
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: -~ * W. Roberds, SRI .- * L. Gilbert, Inspector
* Denotes attendance at Exit Meeting on June 16, 1983 !
2.0 Independent Measuraments - NRC Nondestructive Examination and Quality Records Review of Safety Relatec Systems During the period of May 23 through June 3,1983, quality records received from Wolf Creek Nuclear Power Plant'were reviewed in the regional office
;
for completeness and compliance to the licensee's FSAR commitment to appli-cable codes, standards and specification . Subsequently, anon-siteindependentverificationinspectior,hasconducted l during the weeks of June 6 through June 17, 1983 using the IRC Mobile Non-destructive Examination (NDE) laboratory. This inspectier. was conducted l , by regional cased personnel in conjunction with NRC sub-c:r.ract personne , l
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The purpose of this examination was to verify the adequacy of the licensee's welding quality control program. This was accomplished by duplicating 1. hose examinations required of the licensee by the regulations and
! valuating the results. In addition to the required examinations, several additional confirmatory examinations designed to verify conformance with ,
material specifications were performed and compared to quality assurance [ record An NRC inspector made a random selection of welds. These were intended to provide a representative sample of piping systems, components, pipe size, materials, shop and field welds to AWS and ASME Class 1,.2 and 3 Codes. The items selected were previously accepteo by the licensee based on vendor snop or onsite NDE record ' 2.1 Material Traceability
~ - .
T Thirty-three document packages containing the following documents !
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i were reviewed: g
,-
! rI,,
* - ' -- Material Certification, including weld wire l p --
NDE results
-- FaDrication record - shop and field --
Drawings (Isometric) l
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Physical properties t
-- Quality Procedures These documents were verified to satisfy NRC requirements and licensee i ,
commitments to industry codes and standard , ji, ..
- Results: All areas examined were acceptable per applicable criteria? . 2.2 Nondestructive Examination , ; Examinations were performed using NRC procedures with addenda written
' * specifically for compliance to the Licensee's PSAR commitment to the ~ i ASME B&PV Code, for onsite fabrication. The intent was to duplicate to the extent practicable the techniques and methods of the original examination ' The following examinations were p'erformed:
- Radiographic Examination - twenty-six welds were examined by radio-
- graphy using an Iridium 192 source per NRC Independent Measurements Procedure, NDE-5, Revision 0, addenda WC-1.5-1. Welds examined were *
ASME Class 1, 2, and 3 carbon and stainless stee ,
'
Results: One violation was identified 482/83-12-02 (see . para. 3.0) .
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--irrve,- - - -----r,- - - , - , --,~,r,m .--g-e=vm--- *"e- - ~-- i w m W1---- -r----ev re -ee m r
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Magnetic Particle Examination - two safety related pipe weldments and
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structural supports were examined per NRC procedure NDE-6, Revision 0, 1- and addendum WC-1-6- Samples included ASME and AWS Codie weld ' Results: All areas examined were found acceptable per applicable procedures and acceptance criteri ' Liouid Penetrant Examination - eighteen safety related pipe weldments were examined per NRC procedure NDE-9, Revision 0, and addendum WC-1-9-1. Samples examined included ASME Class 1, 2, and 3 weld Results: All areas inspected were acceptabl L Visual Examination - thirty-one weldments and adjacent base material Y were visually inspected for weld reinforcement, overall workmanship '
- and surface condition per NRC procedure NDE 14, Revision ~
Results: 'All areas inspected were acceptabl ?
~ Ultrasonic Examination - twenty-four Hilti anchor bolts were inspected I ultrasonically, for length only per NRC procedure NDE-18, Revision Results: All bolts examined were found acceptable per applicable criteri Thickness Measurement - six welds and adjacent pipe material were-y examinec per NRC procedure NDE-11, Revision 0, using a NORTEC NDT thickness gauge. Minimum wall thickness was determined by using ;.
W,
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A,STM standard pipe sizes and nominal thickness char ,
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Results: All areas examined were within tolerance requirement ; p - .
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- Ferrite Measurements - eight pipe welds were checked for delta
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;.. ferrite content using a Type II Ferrite Indicator (Severn Gauge). '
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Results: All Measurements were within acceptable limit Hardness Measurements - seven welds were checked for hardness (base material adjacent to welds) using.the Equo-tip haraness tester per NRC procedure NDE-12, Revision Hardness numbers were converted to Brinnell values and the approximate tensile strengths were deter-mined by use of conversion table ' Results: All areas examined were within acceptable limit, Alloy Analyzer - six pipe welds and adjacent base metals *were examined , using a Texas Nuclear Alloy Analyzer. A qualitative cherriical analysis was made on four stainless steel 304 type and two stainless steel 316 type materia Results: Areas examined were withir. 22*e of chemical analysis ! indicated on corresponding certified mill test report . .-. . _ - _ _ _____ ~_ _ _ . _ . _ _ _ _ _ _ _ . - - . _ _ _ _ - - -
__ _- - - _ _ - .-
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Windsor probe Test - three areas of concrete were tested to determine compressise strength using the Windsor probe test ki , Results: All area tests were within acceptable limit
Attachment:
Attachment No. 1 is a tabulation of the specific items examined and results of test .0 Review of Licensee's Radiographs A random selection of the licensee's safety relateo radiographs was reviewed to verify the adequacy of the radiographic program. Twenty-three radiographs that were previously a
REGION IV . NRC Inspection Report: 50-482/83-15 Docket: 50-482 Category A2 Licensee: Kansas Gas and Electric Company P. O. Box 208 Wichita, Kansas 67201
$__ Facility Name: Wolf Creek, Unit 1 Inspection. At: Wolf Creek Site, Coffey County, Burlington, Kansas , .
Inspection Conducted: June 6-9 and 14-16, 1983 _. ?
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Inspector: d/' # 7[8 3 L. 1. Gilbert fReactor Inspector, Engineering Date< Section
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Approved:
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_ W. D. Johnson, Chief, Reactcyr Project Section C
[[I7!/3-Date ,
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t ' *~ b9xLL& D. M. Hunn'icutt, Chief Engineering Section t/a,/e s Oate ~' l l Inspection Summary
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Inspection Conducted June 6-9 and 14-16, 1983 (Report 50-482/83-15) Areas Inspected: Routine unannounced inspection of activities including: l observation of work and review of records for installation of safety-related ' piping and coordination of the NRC independent verification inspection progra The inspection involved 39 inspector-hours onsite by one NRC inspecto ' Results: Within the areas inspected, no violations or deviations *were
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OETAILS
. Persons Contacted Principal Licensee Personnel *E. W. Creel, Corporate QA Manager *C. E. Parry, QA Systems Supervisor *G..W. Reeves, Assistant Manager QA " M. Lindsay, QA Surveillance Supervisor *H. K. Helwig, Supervisor Project Field Engineering *J. V. Palermo, Assistant Construction Manager ; *J. G. Nelson, Project Quality Supervisor , --- * M. Kemp, QA Auditor ,__ , "D. A. Calwell, QA Technologist =t- *J. Fletcher, Lead Welding QC Engineer f *T. Meyer, Qua'lity Control - ;
_
~
j{, - Other Personnel
"E. Glasbergen, Site Manager, Westinghouse "R. Hopkins, Engineer, Westinghouse *G. P. Robertson, Project Manager, GEO *B. G. Stenett, Senior QA Engineer, Daniel International Corp. (DIC)
K. Hollingsworth, Project Welding Engineer (DIC)
~*
The NRC. inspector also interviewed other licensee and contractor . employees during the course of the inspectio .
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* Denotes those attending.the exit intervie . Safety-Related-Pipe Welding t <
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The NRC inspector observed the welding and quality control activities associated with fabricating the following safety-related piping weld Weld Control Drawina System Class FW-308 IM03BB15(Q) Reactor Coolant 1
'FW-506A IM03EP02(Q) Safety Injection 1 F-023A IM03EJ04(Q) Residual Heat Removal 1 F-024 IM03EJ04(Q) Residual Heat Removal 1 FW-571 IM03EM05(Q) , High Pressure Core Injection 2 FW-500 X-M06-EJ04-R009/232(Q) Residual Heat Removal 2 i FW-501 X-M06-EJ04-R009/232(Q) Residual Heat Removal 2 l
FW-502 X-M06-EJ04-R009/232(Q) Residual Heat Remova FW-503 X-M06-EJ04-R009/232(Q) Residual Heat Removal 2 FW-504 X-M06-EJ04-R009/232(Q) Residual Heat Removal 2 FW-505 X-M06-EJ04-R009/232(Q) Residual Heat Removal 2 FW-506 X-M06-EJ04-R009/232(Q) Residual Heat Removal 2
.. FW-507 X-M06-EJ04-R009/232(Q) Residual Heat Removal 2 FW-500 M088G21-R501/242(Q) Chemical & Volume Control 2 FW-029A M13AE05(Q)-02 Feedwater 2 l
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In the areas inspected, the entries on the weld control records were consistent with the status of the welds, the welding procedures were being followed, the welding filler materials were traceable to certified material test reports, and the welders were listed as qualified to ASME B&PV Code Section I No violations or deviations were identifie . NRC Independent Verification Inspection Program The NRC inspector coordinated the activities of the NRC, Region I, NDE inspection team on arrival at the site and provided additional
;. information on the welds previously selected for the NRC independent (__ verification inspection program. The results and findings of the NRC -
independent verification inspection program will be documented in
- - NRC Inspection Report 50-482/83-1 ,g-- r
_. , Exit Interview
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F...
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The NRC inspector met with licensee representatives (denoted in paragraph 1) E7 and H. W. Roberds, NRC Senior Resident Reactor Inspector, on June 16, 1983, and summarized the scope and findings of the inspectio v .
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' ENCLOSURE 11
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1EB 25 885 In Reply Refer To: , Docket: STN 50-482/84-23
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Kansas Gas and Electric Company ATTN: Glenn L. Koester Vice President - Nuclear P. O. Box 208 Wichita, Kansas 67201 '
< ( -
Gentlemen: This refers to the inspection conducted by Mr. R. G. Taylor
'
14,and other 1984, ofmembers activitiesT
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T of our staff during the period September 10 . December
'
authorized by NRC Construction Pennit CPPR-147 for Wolf Creek Generating Station, and to the discussion of our findings with Mr. R. M. Grant and other;
. ' -_ ,
members of your staff at the conclusion of the inspectio ; g, j Areas examined during the inspection included review of procedures and records I
'
for installation of reactor coolant and other safety-related piping, review of quality records for installation of reactor vessel internals, comparison of
,
at-built plant to FSAR description, followup on allegations, safety-related pipe supports / restraints, as-built piping systems and structures, onsite design activities, followup on construction deficiency reports, and licensee actions concerning NRC Vendor Program Branch inspection findings at Colt Industrie ' Within these areas, the inspection consisted of selective examination of
-
W-
- .
5:-- procedures'and representative records, interviews with personnel, I andThe observations by the inspector.' . r-
-
inspection report. - . ' . i :-- During this inspection, it was found that certain of your activities were in , violation of NRC requirements. Consequently, you are required to respond to - these violations, in writing, in accordance with the provisions of j Section 2.201 of the NRC's " Rules of Practice," Part 2, Title 10, Code of ' Federal Regulation Your response should be based on the specifics contained
,% in, the Notice of Violation enclosed with this lette During this inspection ~,'it was' found that certain of your activities appeared to deviate from accepted industry standards. This item and referenceYou are requestedto the l
l standards is identified in the enclosed Aotice of Deviation.Your response should be is to respond to this deviation in writin specifics contained in the Notice of Deviation enclosed with this" letter.
l D:W RPB1/ RPB1/A YB1/A/ kB1 EKJohnson C:W LEMartin RPDenise
IBarnes JPJaudon j p'.RGTa/yor/jj 2 //,/85 /V85 /V /85 J//f //85 4 g /85 2 // 85 gp '
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Kansas Gas and Electric Company -2-
/
We have also examined actions you have taken with regard to previously identified inspection findings. The status of these items is identified in * paragraph 2 of the enclosed repor The responses directed by this letter and the accompanying Notices are not subject to the clearance procedures of the Office of Management and Budget as required by the Paperwork Reduction Act of 1980, PL 96-51 Should you have any questions concerning this inspection, we will be pleased to discuss them with yo
Sincerely, 3 -
*--- Orignal Signcd By:
Richard P. Denise t -
- -
R. P. Denise, Director r-
.
_, ?
. Wolf Creek Task Force
_ ' F'
Enclosures:
1. Appendix A - Notice of Violation 2. Appendix B - Notice of Deviation 3. Appendix C - NRC Inspection Report 50-482/84-23
.,
REGION IV==
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Construction Perinit: CPPR-147 NRC Inspection Report: 50-482/84-23 Docket: 50-482 Licensee: Kansas Gas and Electric Company (KG&E) P. O. Box 208 Wichita, Kansas 67201 L Facility Name: WolfCreekGeneratingStation(WCGS) Inspection ,At: WCGS Site Coffey County, Burlington, Kansas Inspection Conduct'ed: September 10 - December 14, 1984 ..
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Inspectors: IY4sIf) R. G. Tayf or, (Team Leader) Dith Wolf Creek Task Force
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16nad A7 6 -
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Da'te '
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L'. E. E11ershaw, Reactor Inspector - 5:-- - Wolf Creek Task Force
*
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//fff, R. P. Mullikin, Reactor Inspector Date -
Wolf Creek Task Force
. b. $%) 3/4/$5
. E. Bess, Reactor Inspector Date pWolfCreekTaskForce
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.O & N d... / . .=/?/S r
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; Date L. D. Gilbert, Reactor Inspector
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Wolf Creek Task Force
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Date i l. Barnes, Reactor Inspector i Wolf Creek Task Force
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I /> Y WZ//S J. K. Boardmah, actor Inspector Mtpr l
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Wolf Creek Tas Force l thfI < Vhye W. R. $nnett, Reactor Inspector Wolf Creek Task Force
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Approved: .
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E. 1. Martin, C ef, Wolf Creek Task Force Jat y ; ! j _ - ,
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y-inspection Sumary i Inspection Conducted Septent>er 10 - December 14, 1984 (Report 50-482/84-23) i
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Areas Inspected: Routine, announced inspection including licensee action on i previous inspection findings, review of procedures for installaticn of reactor [
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r, coolant and other safety-related piping, review of records for installation of ' h reactor coolant and other safety-related piping, review of quality records for ! ,
' s,. . ~ installation of reactor vessel internals, comparison of as-butit plant to FS4R description, followup of allegations, safety-related pipe supports / restraints, l
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.as-built piping systems and structures, onsite design activities, followup on l
, F- 10 CFR Part 50.55(e) construction deficiency reports, and licensee actions
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:.. concerning NRC Vendor Program Branch inspection findings at Colt Industrie *
l i The inspection involved 677 inspector-hours by nine NRC inspector .y
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Results: Within the 11 areas inspected, two violations and one deviation were , identified in the review of safety-related pipe supports /rtstraints and l , one violation was identified in followup on 10 CFR part 50.55(e) construction l deficiency report l
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DETAILS
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, Persons Contacted Principal Licensee Employees *R. M. Grant, Director-Quality i *P. Dyson, Field Engineering Supervisor *M. Johnson, Manager-Nuclear Plant Engineering
- *H. K. Chernoff, Licensing
*K. Peterson, Licensing
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*W. M. Lindsay, Supervisor-Quality Systems b Bechtel Power Corporation
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*C. M. Herbst, Assistant Project Engineer
.*Z. Botros, Senior Supervisor
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The NRC inspectors also interviewed other licensee, Daniel Internationai
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~~ (DIC) and Bechtel personne * Denotes those attending the exit interview . Licensee Action on Previous Inspection Findings (Closed)UnresolvedItem(STN 50-482/8412-02): The acceptance criteria for welded connections in the II/I cable tray supports has been revised.by
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b[ the engineer's approval of nonconformance report (NCR) ISN20073E In jfi, "
essence, the engineer accepted revision allow welds to be 1/3 undersizeIor -
;_ underlength. The combined percentage for welds exhibiting both 1 - .
deficiencies shall not exceed 331/3%. The NRC inspector has compared the t .. revised criteria to a known worst case in a statistical sample and had no '
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further question . ! ' This item is considered closed.
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(Closed)UnresolvedItem(STN same condition reported by the licensee 50-482/8219-02):
as a 10 CFR 50.55(e)This item item addressed the identified as TE 53564-K88 which was reviewed and closed in Inspection Report No. 50-482/84-12, paragraph This item is considered close (Closed) Open Item (STN 50-482/83-31): This item involved ,the need for a follow-up inspection to assure that the flexible conduit running to
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t This item is considered closed, Projections in fuel storage (Closed) Unresolved Item (STN 50-482/82-12): Documentation indicates that a joint envelopes in the spent fuel rack inspection by Westinghouse, SNUPPS and KG&E personnel determined that the projections satisfy the intent MRC of specifications; i.e., not damage fuel Inspection Report Mc. 50-482/83-21 also during movement of the fue j documents a final postinstallation inspection of the racks which found them to be acceptabl This item is considered closed.
' L (Closed) Unresolved Item (STN 50-482/8408-05): This item dealt wit change of category assignments on the turnover exception list without
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Thethe startup engineer initialing that he made and approved the chang c -
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turnover coordinator perfonned a general reviewIn ofaddition, all turnover all exception star. tup : lists to determine proper item categorizatio ~
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=- engineers and supervisors were instructed to ensure that their final .
j ~ Yeview checked for specific correct categorization of each ite '
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r This item is considered close ; NCR 19197H has been fully (Closed) Unresolved Item (STN 50-482/8412-01): ! dispositioned by DIC, Bechtel and KG&E. In sumary, it appears that the involved three-part memo did provide instructions at variance with the ! engineering criteria. The memo had, however, very limited distribution and other inspectors involved in inspection of components to which the
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memo.was applicable have certified that they do not have a copy of the ' Based on many NRC inspections of the comparable components, there
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8 -- - mem l
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is no evidence that would appear to contradict the rationale provided in '
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the NC .
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!-- This item is considered close "
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(Closed)OpenItem(STN 50-482/79-07): NRC Inspection Report No. STN 50-482/79-07' identified an open item concerning the establishment ;
of procedures for the maintenance of General Electric 4160 volt circuit ' breakers (type 1200 and 2000 ampere with MC-13 mechanism magne-blast). I Procedure No. MPE-E009-02, Revision 2, dated March 14, 1984, " Inspection and Testing of 13.8KV and 4.16KV Circuit Breakers," was written This and item is t approved. This procedure appears to resolve the concer l considered close ,
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(Closed)OpenItem(STN 50-482/84-22, paragraph 5): Additfonal inspections of as-built Electrical Raceway: This item is considered closed based on inspection activities documented in NRC Inspection
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Report No. 50-482/84-51.
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The NRC inspector reviewed licensee actions in accordance with licensee letter
' dated March 30, 1984, in response to NRC inspection report No. 50-482/83-36 and Notice of Violation dated February 14, 1984. The following paragraph numbers correspond to paragraph numbers in the KG&E letter:
Licensee response accepted. The revised FSAR was reviewed by the NRC inspecto Licensee response was acceptable. The NRC inspector reviewed revised Procedure WP-IV-111. " Structural Steel and Pipe Whip Restraints," Revision 11, dated April 5, 1984, and QCP-IV-111, Revision 16, dated , . May 7, 1984, " Erection of Structural Steel and Pipe Whip Restraints."
,i_ 4 Licensee response accepted. The NRC inspector reviewed procedure ,
',gt- - AP-VII-02, Revision 12, dated April 5, 1984, and found it to be ..
acceptabl .
' The NRC inspector reviewed documentation on the use of unplated Load E7 Indicating Washers (LIW's) with galvanized fasteners and found it to be acceptabl '
The NRC inspector reviewed licensee controls on reuse of LIW's and found them acceptabl , -. 7 Licensee response accepted relative to use of Load Indicating Washers under black (uncoated) bolt heads in bolted joints where the bolt is the - l[.;
-e . - turned elemen .
51. . .
- 8 Licensee response accepted relative to prohibitions on reuse of A325
, T- - bolt * >
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I- 9 Licensee response accepted relative to installation procedures to assume, . reuse of correct Load Indicating Washer Licensee response accepted. As stated in 2. above, Procedures WP-IV-Ill, Revision 11, and QCP-IV-111, Revision 16 were reviewe . O e
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, (0 pen)UnresolvedItem(8336-06): Apparent lack of procedures for
, ' revision control of manufacturers instructions. The licensee presented These the NRC inspector with existing procedures for revision contro procedures appear adequate. The concern is with those procedures This item will that , l were in effect during the entire construction phas ! remain open pending further review by the NRC inspecto l i l Review of Procedures for Installation of Reactor Coolant and Other
5afety Related Piping i The NRC inspector reviewed the quality control and work procedures listed l below pertaining to the range of installation activities for reactor
- a coolant and other safety-related piping within the scope of the ASME This review, which is one of a b Section III Code and FSAR connitment '
l series of such reviews, was undertaken at or near the end of all such
' construction activities to assure that the procedures, as revised duringr
}$! construction, continue to describe an acceptable progra ~
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i ' QCP-I-01, Revision 19, " Receiving, Storage and Preservation of * l [7
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Quality Related Materials and Items."
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' WP-VII-201, Revision 5. " Fabrication and Installation of l Piping."
l 1 QCP-VII-200, Revision 20. " Inspection of Weld Process."
l QCP-VII-201, Revision 14. "Inspction & Documentation of ASME , 'r - Piping Valves and Component . l K. ~ - ~ !
~ WP-VII-203, " Revision 9. " Cleaning and Sealing Pipe."
~ . No violations or deviations were identifie ~
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i *~.. ' Review of Records for Installation of Reactor Coolant and Other Safety-Related Piping , The NRC inspector reviewed four licensee audit reports pertaining to the subject activity area. Each report package contained a well defined
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statement of the objective of the audit which was further supported by a [ series of checklist type questions developed by the audit team leadersEac
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prior to the performance of the audit : defined audit findings, corrective action statements and final l resolution ,
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I t Covered pipe cutting and traceability transfer, ) (a) TE 57061-K69: bending, inspection of welding, verification of post-weld heat * l i treatment, and welder identification. t , i
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Drawing control in piping activities; control of Field (b) TE 57061-K75: Change Requests. NCRs and Design Change Notices; and accuracy of ~ installation traveler record dat (c) TE 57061-K77: General practices for installation of piping 2" and ove Special process control (weld procedure and welder (d) TE 57061-K112: qualification., The NRC inspector also reviewed the below listed NCRs pertaining to the subject activity area for legibility, adequacy of the definition of the e nonconformance, appropriateness of the disposition of the nonconforming ' b item (s) by engineering and reportability under 10 CFR 50.55(e). , 4Y ISN 5962 PW ' _
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b c ) ISN 5965-PW ISN 5975 PW
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dh' ISN 4057 P
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p e f 1SN 4074 P ISN 4516 P ISN 4574 P g) h ISN 4649 P i l 1SN 4623 P ' j ') ISN 5027 PW
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No violations or deviations were identifie g, ' Si . Review of Quality Records for Installation of Reactor vessel Internals .
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The NRC inspector reviewed the following traveler type records covering the installation, modification and repair of the reactor vessel internal core support structures. The travelers are detailed line-by-line
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instructions for both accomplishing the activity and for inspectionThe '. thereof based upon vendor drawings and generalized instruction travelers were prepared by the vendor (Westinghouse) engineering personnel and the inspections were perfonned by Westinghouse QC personne Supplementing the travelers were detailed records of welds performed and the inspections thereo (1) Traveler package G-SAP-WE-006, Revision 0 through 4, pertaining to the assembly and installation of the lower core support in accordance with Drawing 81214E5 (2) Traveler package G-SAP-WC-008 and Supplements B&E. pertaining to assembly and installation of the upper support in.accordance with Drawing 6121E72. Included within the review'were
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, 9 subpackages designated with a suffix "Q" which related to certain modification and repair activitie .
No violations or deviations were ioantifie . Comparison of As-Built Plant to FSAR Description The NRC inspectors reviewed four safety injection system drawings in order to:
* Verify that the latest revisions of the system field drawings are in agreement with FSAR piping and instrumentation diagrams (P& ids).
L * Verify by field observation that the component installations,
- including control and logic instrumentation, are as described in the ,FSA Comparison of Field Drawings to FSAR P& ids
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The following Bechtel P& ids were compared against corresponding FSAR
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' e- drawings:
* Drawing M-02EP01 (Q), Revision 13, dated February 15, 1985,
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" Accumulator Safety Injection."
- Drawing M-12BB01 (Q), Revision 0, dated September 19, 1984,
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" Reactor Coolant System."
" e * Drawing M-12BN01 (Q), Revision 0, dated October 31, 1983,
"8 crated Refueling Water Storage System."
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Drawing M-02EM01 (Q), Revision 8, dated June 2, 1983,."High h a
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Pressure Coolant Injection System."
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The NRC inspectors discovered no major discrepancies between field , and FSAR drawings. However, several hand operated valves were shown The as " locked closed" in the FSAR but not in the field drawing valves noted with this discrepancy are: V030 . V109 V058 V114 V061 V157
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V062 V158 V065 V173 * V066 V208 *
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V100 V209 ; V101 V212 ,
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V102 V213 V103 V214 V104 V216
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? In addition, valve V029 on Accumulator Tank C was not identified by
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number in the FSAR.
. The above discrepancies, although numerous, do not appear to raise However, it is reconnended that the licensee any cause for concern. determine whether the valves in question are designed closed" and that the as-built installation reflects the desig There were no violations or deviations identified in this are Comparison of Field Drawir.as to the As-Built Plant The NRC inspectors performed a walkdown of at least one safety train L for each drawing listed in paragraph 6.a. The drawings were compared
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against the physical installation to assure that: 1)pipingwas
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installedasdesigned;2)valveswereidentifiedandinstalledint)ie _ T correct position; and 3) instrumentation transmitters and indicators?
=- were identified and installed per desig ; ' -
15. . During the inspection of piping and associated hardware for all F four accumulator tanks the NRC inspectors noted that the nitrogen supply isolation valve (8875A) for tank A was installed in the opposite direction. The valve was identified to the licensee and it was removed and. reinstalled in the correct position. An evaluation of the significance of this finding was perfomed by the NRC staff and it was detemined that there would have been no impact on any
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safety function with the subject valve installed incorrectly. Thus, *
-r . ,with this detemination and the fact that no other hardware A - - discrepancies were . identified, this finding is considered an isolated* .
case with no safety significanc .
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i There were no violations or deviations identified in this are ,
..- .. Followup on Allegations A-84-A-58 (Closed): 'A person who identified himself as a former employee of the licensee contacted the NRC Region IV office relative to a concern that Code (ASME Section !!!) pressure boundary was being opened by CWPs (Construction Work Pemits) without QC involvement and that he, theThe NRC alleger, had been' discharged because of his findings in the are inspector found that the licensee had conducted a QA audit of "Startup" activities that identified the samp problem. The audit was performed during the period of April and May 1984. The licensee QA organization issued a Quality Program Violation on June 1,1984, on the ihatter. As a result of the violation, an administrative procedure was revised to
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-11-require the review, concurrence and observation by the appropriate QC unit in the activity. QA has verified that the change has been implemented as of July 16, 1984 The allegation has thus been substantiated. The NRC
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inspector would note that three licensee personnel were directly involved in the audit. The audit was concluded, documented and the Quality Program Violation issued by an employee still employed within the licensee's QA organization. It would appear that the alleger was not terminated by reason of involvement in the audit. The licensee informed the NRC l inspector that one of the persons involved in the audit had been tenninated because he had made an offer to provide illegal drugs to a licensee employee. The NRC inspector interviewed the latter employee who confirmed that the offer had been made and subsequently reported to the
- employee's supervision. The licensee management apparently believed the h- employee and discharged the allege ,
l@ ' (0 pen) 4-84-A-102: Allegations were made to the NRC by two individuals <in October 1984 concerning perfonnance of the structural steel weld reinspection program at WCGS. NRC personnel were informed that welding , _ inspectors had been instructed to visually inspect welds through paint in * ' {H violation of the AWS 01.1.-1975 Structural Welding Code. Written
" procedures were stated to have not been provided but welding inspectors were being required to mark inspection sheets as accept or reject. It was I
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' additionally identified that unacceptable and missing welds had been found by the reinspection program and one individual claimed to have been .
intimidated to produce results that would show welds were acceptabl * NRC Region IV staff were cognizant of structural steel weld discrepancies r- and reinspection of painted weld surfaces prior to receipt of the , l '$~ ' . allegations, as a risult of the NRC inspection activities in this areaFollowu,p ' i!.. , which are documented in NRC Inspection Report N /84-2 . of these allegations was performed by MRC . inspectors during October 16-19, . 1 1984. One welding engineer and each welding inspector involved in the structural steel weld reinspection program were interviewed and a review E.* was made of the reinspection records that had been generated prior to the NRC followup. It was ascertained from the interviews that the welding . ' inspectors, who were all AWS Certified Welding Inspectors, were concerned about being able to fully evaluate painted weld 01.1-1975 surfaces to theWelding Structural visual inspection quality requirements of the AWS Code. Initial activities, which comenced in late September 1984, were , established to have been perfonned under oral D!C Welding Engineering direction and without a written procedure. Document review showed that DIC had prepared written guidance on October 1,1984, and XG8E had Both ,
' subsequently issued an inspection procedure dated October 6,198 i of these documents identified that engineering evaluation of the l
inspection results would be made with the knowledge of paint and other foreign matter being present on most of the inspected welds. None of the l welding inspectors indicated during interviews that they had ever been l directed to improperly accept discrepant welds and review 'of the -
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reinspection records confirmed that discrepant conditions were being appropriately documented. The alleged intimidation was ascertained by interviews to relate to a disagreement concerning the need for and type of documentation to be made when conditions were judged to exist which affected perfomance of visual inspection of weld The Chief of the Wolf Creek Task Force and an NRC inspector interviewed
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the two individuals on October 3,1984, and subsequently interviewed the associated supervisor and manager on October 4, 1984. Based on these discussions and review of the inspection records performed by the individuals, the allegations concerning intimidation or harassment were not substantiate The NRC inspectors determined that the only technical issue requiring additional review is the adequacy of data generated from inspection of
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T painted weld surfaces. This subject will be addressed in a future inspection report after completion of review of the KG&E response to NRC "
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Inspection Report No. 50-482/84-2 p' Safety Related Pipe Supports / Restraints Inspection of Pipe Supports / Restraints The NRC inspectors selected the 21 pipe supports / restraints listedThe below for inspection of the installed support / restraint syste supports or restraints were randomly selected from three piping systems; i.e., the residual heat removal (RHR) system, the high 1* 5, ,- . pressure coolant injection (HPCI) system, and the accumulator safety , .. injection (ASI) syste Support / Restraint System
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Drawing
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R006 RHR M-15EJ01(Q) H006 RHR ',
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M-15EJ01(Q) RHR R019 M-15EJ01(Q) RHR M-15EJ01(Q) R016 H001 RHR M-15EJ01(Q) RHR CO21 M-15EJ04(Q) RHR M-05EJ03(Q) R015 R020 HPCI M-15EM03(Q)- HPCI C033 M-15EM03(Q) HPCI , C034 ' M-15EM03(Q) HPCI M 15EM03(Q) 'R022
- R023 HPCI i M-15EM03(Q) HPCI C039 M-15EM01(Q) NPCI R032 M-15EM01(Q) HPCI R011 M 15EM01(Q) '
*HPCI C012 M 15EM01(Q) HPCI C019 M 15EM01(Q) HPCI
- R010
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M-15EM05(Q) ASI H007 M-15EP01(Q) ASI H008 M 15EP01(Q) ASI C007 M-15EP01(Q) _ _ _ _ _ _ - - _ _ _ _ _ _ - . _. .__- . . _ _ _ _ - . - - _ _ _
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In the areas inspected, a limited number of anomalies were noted with , respect to compliance of pipe supports restraints Examples with theconditions of observed design drawing / specification requirement were a discrepant dimension on the EJ01/H006 restraint, excessive pin to pin dimension on the EJ01/R019Each restraint, of theand incomplete conditions welds noted by on the base of the EJ01/H001 suppor the hrC inspectors were ascertained to have been detected during Bechtel IE Bulletin 79-14 walkdown activities As a resultandofhad thebeen subjectato foregoing, evaluation by Bechtel engineerin review was performed of the SNUPPS IE Bulletin 79-14 Walkdown Procedure, Revision 7, and the SNUPPS Wolf CreekAGenerating sample of Station IE Bulletin 79-14 Evaluation Procedure, Revision walkdown findings was reviewed for various 8echtel categorizations of
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L required actions and verifications made that required actions
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appeared to be appropriate and had been accomplished in accordance-with procedure requirement 'y Within t'his area of inspection, no violations or deviations wer ?
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identifie * ,
. 'E Review of Pipe Support / Restraint Installation Records The NRC inspectors selected the six pipe support / restraint systems listed below for review of the installation record Support / Restraint System !
Drawing ASI C003
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h-g' M-15EP02(Q)
.M-15EM03(Q)
C034 R022 HPCI HPCI
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M-15EM03(Q) HPCI R020 M-15EM03(Q) HPCI
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M-15EM03(Q) RHR CO21
* M-15EJ04(Q) ,,
In the areas reviewed, the welding documentation was available for The welders each weld identified on the support / restraint drawin were established to have been qualified for the procedures used and , ' the welding saterial certification records were found to conform with welding procedure specification requirements for each of the welds reviewe During documentation review,,it was noted that the SNUPPS design specification for Bergen Paterson ASME Section !!! Code pipe supports,10466-M-218A(Q) Revision 6, permitted us Review.of vendor in the Appendices to the ASME Section III Cod Code Data Reports for Type 2540 mechanical snubber assemblies confirmed that the vendor had utilized Code Case 1644-7 for I
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1, Code Case 1644-7 is conditionally l manufacture of the assemblie accepted by Regulatory Guide 1.85, to which the SNUPPS F,$AR comits , to meet. The conditions established by the NRC staff for acceptance
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relate to the seasured ultimate tensile strength (UTS) of an l
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alternate component support material. Regulatory Guide 1.85 requires : d that either (1) the maximum measured UTS of the material be l restricted to a maximum of 170 Ksi, or (2) impact tests should be ! required by the design specification for applicationsThe where it is
$NUPPS l desired to utilize material with up to 190 Ksi UT ;
i design specification did not include the conditions of acceptance l stipulated by Regulatory Guide 1.8 l l
L Thisisaviolation(482/8423-01). '
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\ Certificates of Compliance had been furnished by Sergen Paterson for i -. _ the snubber assemblies reviewed by the NRC inspectors, which lT precluded identification of the Code Material Case 1644-7 materials test data obtaised?by that had ' i ) =. been utilized in snubber manufactur ,
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KGSE from Bergen Paterson, in response to a NRC request, showed th4t
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r... - - ASME SA 564 material from Code Case 1644-7 had been utilized for pins
i F' in the EJ04/C021 Type 2540 assembly reviewed. The material UTS for I Review
the specific pins reviewed was reported to be below 170 Ks ,
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of lower load capacity Bergen-Paterson snubber assemblies showed This that ! l ASTM A 574 capscrews had been utilized from Code Case 1644- ; l The sizes of ! specification has a minimum material UTS of 170 Ks i capscrews used were, however, below the minimum for Thewhich adequacythe ASME of l ! Section !!! Code specifies impact test requirement : ! use of capscrews with greater than 170 Ks1 measured UTS is considered
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- 'anopenitempendingadditionalNRCreview(482/8423-06).
i 3 -- -- f f- - Examination of documentation for the addition 411y showed that the snubber field weld (i.e., We EJ04-C021 snubber had- assemb
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The Sergen Paterson Lopd !
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only been inspected by visual examinatio l
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Capacity Data Sheet for the Type 2540 snubber stipulates that this - The Dit fabrication drawing for this i l weld be a full fillet wel assembly requirvd that welds be examined in accordance with the l provisions of paragraph NF-5212 in Section III, Subsection NF of the ASME Code. Paragraph NF-5212 requires that full fillet welds be
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examined by either the magnetic particle or liquid penetrant j l examinatiori method .
Thisisaviolation(482/8423-02) i ! i Review of GE0 Procedure No. 21.A.1, Revision 6 dated October 14, f l 1983, " Magnetic Particle Examination Dry Method," showed a The yoke l i method pole spacing requirement of between 3 and 8 inchit ! j procedure indicated that it'was in compliance with Sec' tion V of the I i ASME Code,1974 Edition through the Sumer 1975 Addend I l r
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Paragraph T-734.2 in Section V of the ASME Code (1974 Edition through the Sumer 1975 Addenda) specifies, however, that a pole ' spacing of 3 to 6 inches be used for the yoke method of magnetic particle examinatio This is a deviation (482/8423-04). As-Built Piping Systems and Structures Piping Systems The NRC inspectors selected portions of the seven Class 1 and Class 2
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piping systems listed below to verify that the as-built design and u - construction drawings or specifications correctly reflected the
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as-built condition of the plan p -
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(1) Accumulator Safety Injection System, Class 2 Piping ..
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, , ' r Piping Drawing C-M-13CP02(Q)Line 04-ECB-10" from Accumu - - Line 05-BCB-10" from Weld F002 to Weld FW 305 l
Support
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/ Restraint Supports / Restraints Drawing M-15EP02(Q)C003, R006, R005, H00
(2) Chemical and Volume Control System, Class 2 Piping
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Piping Drawing C-M-038G02(Q), Class 2 PipingLine 149-B ! E- - -
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F063 Line 158-BCB-3" from Weld F063 to Weld F060A f-
- - e * s y , ~ .- Support / Restraint Drawing M-15B(42(Q) .
Supports / Restraints, R020, R019. R018. H010 H009, R001 ,
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(3) Containment Spray System, Class 2 Piping PipingDrawingC-M-03EN01(Q)Line 01-HCB-14" from Weld F
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- Line 03-GCB-10" from Containment Spray Pump A to Weld FW 319
- Line 04-GCB-3" frog Line 03-GCB-10" to Weld FW 343 l - Line 58-GCB-3" from Line 04-GCB-3" to Weld F026 r
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Support /RestraintDrawingM-15EN01(Q)
- Supports / Restraints R010. H005, R012, H004, C001, H003 -
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(4) High Pressure Coolant Injection, Class 2 Piping
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Piping Drawing I-M-03EM01(Q)
- Line 6-CCB-4" from Safety Injection Pump A to Weld F001 -
Line 47-CCB-4" from Line 6-CCB-4" to Weld F010 Support / Restraint Drawing M-15EM01(Q)
- Supports / Restraints R013 C031, C030, R018, C013, CO29, R017, P028, C041 ; (5) High Pressure Coolant Injection, Class 1 Piping Piping Drawing C-M-03EM03(Q) , 't-- - Line BB-26-BCA-6" from Reactor Coolant Loop 2 Hot Leg '
to Weld F009
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Lir.e 10-BCA-6" from Weld F009 to Weld EJ04-F014 e
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Line 09-BCA-2" from Line 10-BCA-6" to Weld FW 531 ..
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Supports / Restraints H003, R004, R005, C057, C017, R009, * f,--
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P' C016 (6) Accumulator Safety Injection, Class 1 Piping Piping Drawing C-M-03EP02(Q)
- Line BB-22-BCA-10" from Reactor Coolant Loop 2 Cold Leg to
> ~ ' Weld F006
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Line 06-BCA-10" from Weld F006 to Weld F004 ,
,
*
* Support / Restraint Drawing M-15EP02(Q)
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- Supports / Restraints R010, R009. H005, H004, R007
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* (7) Reactor Coolant System, Class 1 Piping * ... '
Piping Drawing PSI-M-03BB01(Q)
- Line BB-69-BCA-14" from Reactor Coolant Loop 4 Hot Leg to Pressurizer i
Support / Restraint Drawing M-15BB01(Q)
- Sppports/ Restraints R001, H002, R002, H001, R003, R004 In the areas inspected, the as-built conditions of the piping and supports / restraints were consistent with the as-built drawings and specification .
.
,- Structures
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. .. -17-e '
The NRC inspector selected 20 structural steel assemblies from bolte seismic Category I structures located in the auxiliary building and the control building for verification of actual These particularinstallation assembliesagainst the latest approved design drawing were selected because they were at the opposite ends of welded i
connections No. 50-482/84-22, which had been identified in NRC Inspection defects; i.e., missing welds, cracked welds, undersized welds, and - missing beam seat The inspected connections are identtfied as follows: Control Building h Beam Identity Joint No * Orawino N r
-
C36 9585 --
,
C-121-1484-05 C52 * 9982 C-121-1484-05 C53
? ~ -
C-121-1484-05
'
9982 C54
*
6,-- 9983 P' C-121-1484-05 CSS 9984 C-121-1484-05 Ct0 9985 C-121-1484-05 C42 9986 C-121-1484-05 C37 99B10 C-121-1484-05 C13 4184 C-121-1411-02 C14 4184 w C-121-1411-02
,
E* g Auxiliary Building Joint No ,
*
Beam Identity Drawing N ,
, ,
A98 .
* 708B1 C-121-0617-03 A55 30784 <
C-121-1549-05 A10 '
.- -
C-121-0971-03 15689 A40 436B5 C-121-0627-05 A41 436B6 C-121-0627-05 A58 43686 C-121-0627-05 A39 43687 C-121-0627-05 A60
; 24283 C-121-0976-03 A61 l 24383 C-121-0976-03 A114 84983 C-121-1561-01 The above connections were in'spected to assure conformance wit
! identified drawings and the following applicable construction and ,
,
inspection procedures:
*
DIC Procedure No. WP-IV-!!!, Revipion ll, " Strut:tural Steel and Pipe Whip Restraint Erection"
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, _ - _ . _ _ _ _ . , . . _ , _ _ _ _ - - . . _ _ . _ . _ . _ . . _ , _ _ . . -. ._ __
_ _ _ - _ . - - - -, . . .-
, ,...
-18-(
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* DIC Procedure No. QCP-IV-III, Revision 11. " Structural Steel and Pipe Whip Restraint Inspection" '
* Bechtel Specification No. 10466-C122(Q), " Specification for Erection of Structural Steel (SNUPPS)" '
* Bechtel S;ecification No. 10466-C132(Q), " Specification for Erecting Miscellaneous Metal ($NUPPS)"
x
* AISC Specification for the " Design, Fabrication and Erection of Structural Steel for Buildings" * AISC Specification for " Structural Joints Using ASTM A325 or s A490 Bolts," approved May 8, 1974 . 't .-. * Orawing Nos. C-121-6003-04 and C-121-6004-03, which delineate .C- * .-
Joint assemblies showing the use of A325 and A490 bolts and -.
<
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placement of hardened load indicator washers l _ '
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While the specified gap between the load indicator washers and bolt; F
' heads could not be readily ascertained due to the remnants of concrete and flame retarding materials that had to be removed for ,
.
,
j this inspection, the number, spacing, and placement of all bolts were
' '
It was as required by the appitcable drawings and specification !
! further observed that bolt identity was stamped on all bolt head .
i
! .
No, violations or deviations were identifie . t l -
"
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-' ~ .A concurrent NRC inspection has been performed at Bechtel's i -- ~
Gaithersburg, Maryland, engineering office to . assure, with respect to *
-
~ the previously identified discrepant weld conditions, that !t I that as-6uilt changes on the design / construction drawings correctI9
.
t e reflect the as-built conditions. The esults of this inspection
,
.- ,
;
offort will be addressed in a NRC followup inspection repor !
,!
10. Onsite Desian Activities I
,
The NRC inspector reviewed 17 documentation packages (travelers)
~
pertaining to pipe supports to assure that onsite design activity, including controls for engineering and construction initiated field changes, was conducted in compliance with the technical and quality assurance requirements stipulated ,in the applicable procedure ,
.
The reviewed procedures included: ' !
; DIC Procedure No. WP-VII-209, " Preparation ' and Process;ing of :
.
Travelers" l
! **
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. .. . _ _ - _ - _ _ . - _ - . - - _ . . - . - - _ _ - - - - _ _ _ -
_ __ . _ . __ __
, ' ..
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-19-
, DIC Procedure No. AP-III-04, " Field Change Request (FCR),
ConstructionVarianceRequest(CVR),(MiddleThirdDeviationNotic -
(MTDN), and Middle Deviation Notice MDN)" ' KG&E Procedure No. KI-1030.2, " Controlling and Releasing Design Document Change Notice" DIC Procedure No. AP-IX-03, " Document Control" i DIC Procedure No. AP-III-05, " Field Prepared Drawings" DIC Procedure No. AP-III-06, " Field Prepared Specifications" ' -- Bechtel Procedure No. EDPI 4.46-01, " Project Engineering Drawir.gs" ' The procedures were reviewed to assure that control of the following , .$ elements was addressed: y a' . Design input - [f'
7; Drawings Interface between cognizant design organizations Design review, approval, and verification Specifications Nonconformances and corrective actions Field change (FCRs) As-built drawings
'r Quality assurance Engineeringchangenotice(ECN)
E*- Design change notice (DCN) { , E, . The travelers pertained to the following pipe supports: ' l
? ..
EM05-P004/231; AB05-H002/442; t
* AE01-H015/422; EJ01-H006; EP01-C007; EP01-R009; EP01-R017; EP01-H007;
' EJ01-H006; EJ01-R006; EJ01-R016; EM02-H007; EM03-R020; EM03-C034; EM03-R023; EM03-R022; EP02-C003; and included the traveler index, bill of material, installation drawing, weld control record (if applicable), quality inspection checklist, and a NCR(ifapplicable). , The traveler indexes were compared against the referenced drawings and specifications, and then compared against the Document Record and Status l ' Cards, use to verify that the latest applicable revisions had a had been incorporated; and if not, that they were included in the t _ -. - . _ ,. . _ - - . __. _ _ _ _ _ _ _ _ _
-
.
.
-20-
.
Verification was made by reviewing the Master File DCN/ECN-FCR l traveler Status Card Identified NCRs were reviewed to assure that they had been reviewed, dispositioned, approved, and that the dispositions had been implemented and verifie An attempt was made to assure that NCRs with a disposition of "use-as-is" However, it was had been correctly incorporated into as-built drawing established that Bechtel has until 90 days after fuel load to review the drawings and NCRs to assure reconciliation with actual as-built conditions. The specific as-built drawing criteria are included 19, in 198 Attachment 2 to Bechtel's letter No. BLSE 13166 dated January b
~
There were no violations or deviations identifie e
'
However, due to the 90 days after fuel load comitment with respect to reconciliation of design drawings and actual as-built conditions, this <* item shall remain ope _
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(482/8423-05). ,
r Followup on 10 CFR Part 50.55(e) Construction Deficiency Reports (CDRs) 1 ' On December 12, 1984 KG&E notified NRC Region IV of a potential CDR pertaining to pipe supports which, af ter final inspection had been tampered with by insulation contractors during insulation installation. The NRC inspector reviewed the available, pertinent It was detennined that DIC generated approximately
' 'r - documentatio NCRs, the first one being dated June 1,1984, dealing with pip '
E- ~ . supports which had been partially disassembled to facilitate the , l _ installation of insulation. However, the first 6 NCRs, dated through
".- .
July 27, 1984, caused KG&E to issue Corrective Action Request (CAR) .
! No. 14 on July 31, 198 * '" '.
' Four of the NCRs were silent and two were checked off "No" with respect to identifying that a potential 10 CFR Part 50.55(e) condition existe CAR 14, with respect to reportability to NRC, stated, "Under Evaluation 7/30/84." The evaluation was to be based on a DIC reinspection of the pipe supports which were within the insulation contractors' scope of work. DIC was directed to identify all rejectable conditions on NCRs. As a result of the reinspection
~
effort, another 25 NCRs were generated, of which 16 dated between September 4 and September 20, 1984, identified that a potential
.
10CFRPart50.55(e)conditionexiste .- KG&E closed out CAR No. 14 on December:11, 1984, based on verification that DIC had perfonned and documented the required ! _ _ . - - _ . ,
. - . - .-- _, - --
- _- - _ _ _ _ _ _ _ _ .. . . .
k-21- . .'
4 reinspections, closed out all applicable NCRs, and that the , insulation contractors had revised their installation procedures and retrained their personne . 10 CFR Part 50.55(e) requires the holder of a construction permit DIC to notify the NRC of each reportable deficiency within 24 hours.
, Procedure AP-VI-02 requires, upon detennination that a potentially , a reportable condition exists, innediate notification to KG&E by hand carrying-a copy of the.NCR to the KG&E deficiency coordinato Formal notification to KG&E by DIC of a significant deficiency occurred on December 11, 1984, when DIC completed the Wolf Creek Generating Station Request for Reportability Evaluation fonn.
. ..4 Therefore, KG&E could not have made the required notification within T !. . 24 hours of the significant deficiency first being identifie ,
. .
This is a failure to execute the required reporting of a signifJ. cant ! i
; =. . deficiency and is a violation of Criterion V of Appendix B to .
l CFR Part 5 (482/8423-03)
! F? (Closed) TE 53564-K68 - Potentially compromised Level II welding !
inspector examinations: It was discovered in July 1982 that a
. ' Level II welding inspector examination could potentially have been in inspecturs' possession since March 30, 1981. A new examination was innediately developed and given to the welding inspectors at WCGS.
t Three of the inspectors failed the new examination. Two of these three were given retraining and subsequently met the recertification
,{. *
requirements. The remaining individual terminated employment prior to being recertified. Fourteen other welding inspectors, who had - ,
., -
S;-- - - ! . been certified in the time period in question, were no longer r-
- employed at WCGS at the time of discovery of the potentially *
! ~ compromised examination. A sampling program was initiated to l reinspect work previously accepted by the 14 former employees and the l :-- ~ J 3 who had failed the new examination. The results of the ' reinspections indicated that all but one of the individuals had i perfonned acceptable inspections. Administrative actions were taken to identify during. document review those inspections performed by >
this individual, in order that the work could be reinspected for j acceptabili,t j ! This item is considered close * . l
,
12. Licensee Actions Concerning NRC Vendor Program Branch Inspection l Findings at Colt Industries , l TheNRCinspectorreviewedKG&Eactionstakenas.aresulto[QA i deficiencies identified by the NRC Vendor Program Branch during an l i f
-
!
;
r i _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _
** .
l
.
i -22-( inspection on March 26-30, 1984', at the Fairbanks Morse Engine Division of Colt Industrie Certain of the deficiencies were written in regard to QA records and documentation pertaining to diesel generators furnished by this vendor to WCG An audit was performed by Bechtel persdnnel on October 30-31, 1984, at the Fairbanks Morse Engine Division of Colt Industries, which addressed the vendor actions and response to the NRC inspection findings. The NRC inspector concluded from review of the audit report that KG&E had verified that appropriate actions had been taken by the vendor to resolve the NRC inspection finding No violations or deviations were identifie . Management Interview
., % _-
The NRC personnel met with the licensee and Bechtel personnel noted in paragraph 1 on November 30 and again on December 14, 1984 to provide -
' sunmary information on the overall scope of the inspection and the
_
, =C -
findings resulting therefrom. The licensee and engineering personnel' ? acknowledged their understanding of the finding .
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