IR 05000346/1975021
| ML19319B418 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 12/09/1975 |
| From: | Hayes D, Key W, Sutton J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19319B371 | List: |
| References | |
| 50-346-75-21, NUDOCS 8001150990 | |
| Download: ML19319B418 (8) | |
Text
{{#Wiki_filter:__ . _ _.. _- - -. _ _ _ _.
._ _ _ ___ _ _ ___ _____ _ _ @ UtlITED STATES I'UCI. EAR REG 111.ATORY CO"?11SSIO ' 0FFICF. OF INSPF.CT]O:: A::D E::FoltCEMF.NT
REGION III
Report of Countruction Innpection IE Inspection Report No. 050-346/75-21 Licensee: Toledo Edison Company Edison Plaza i 300 Madison Avenue Toledo, Ohio 43652 Davis-Besse Nuclear Power Station Licence No. CPPR-80 Oak.Ilarbor, Ohio Category: B Type of Licensee: BMJ PWR-871 MUe ) " Type of Inspection: Routine, Unannounced Dates of Inspection: November 19-21, 1975 ,1 .o . ' Y ?/ t ** f I ,f / /2[f ?I .h.W. Sutton Ptincipal Inspector (Date) ,, j.
/ ~. f'. , 7/ ,// ' Accompanying Inspector: U. Key /j! ff/f ) (pate) ) ' ) Other Accompanying Personnel: None {{}. __.@ ' ',.wn'., .- ^ Reviewed By: D. W. llayes, Sec on Leader [ 9/,71 Projects '(Date) , r,[ 'l,,/ a. A J $ r ' I go01150 [h . ' -- - - - . -. -
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _, __ I - l SIR 4 MARY OF FIN 1)INGS M pection Snmnary Inspection of November 19-21, (75-21): Reviewed licensee's corrective action relative to previously identified unresolved matters.
Reviewed records and observed liase-line inservice inspection activities.
Reviewed QA records and procedures pertainlug to installation of Reactor Vessel l I n te rna ls. Reviewed original vs repair radiographs for Reactor Coolant [ Pump (RCP) casings.
One item of noncompliance was identified relative Lo placement and failure to doct: ment removal of RT location marks on ' RCP suction welds.
i Enforcement Action Items of Noncompliance A.
Violations I j None.
l ' B.
Infraction . _.
Contrary to 10 CFR Part 50, Appendi>: B, Criterion V, a deviation
relative to improper placement of inservice inspection RT location marks on the suction welds of the Reactor Coolant pumps was not documented in accordance with Babcock and Wilco >: Construction Company Quality Control Procedures.
(Report Details, Paragraph 1) This infraction was identified by the IE inspector and had the potential for causing, or contributing to, an occurrence with safety significance.
Licensee Action on Previously Identified Enforcement Items No previously identified enforcement items were included within the scope of this inspection.
Other Significant 1indings t A.
Systems and Components i ! None identified.
H.
Facility Items (Plans and Procedures) .- 2 - O . - - - .. - - - - -- -. . - - - -, - -
_ _ _ _ _ _ _ _ _. . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _.. _ _ _ _ _ _. _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _.. - - - - - - _
I
1 - I t Current Status i 1.
The licensee indica ted that, as of November 1975,. Plant overall j construction was 92% complete, and Design and Engineering was f 98.8% complete.
2.
The special electrical inspection being conducted by the licensee is progressing on schedule.
i l C.
Managerial Items i l None.
} D.
Noncompliance Identified and Corrected by 1,1censee I j None.
E.
Deviations
None.
i F.
Status of Previously Reported Unresolved Items ,
1 { 1.
Ilydraulic Snubbers (Inspection Reports No. 050-3'.6/74-07,_ l No. 050-346/75-01, No. 050-346/75-03, No. 050-346/75-07.
No. 050-346 / 7 5-13, No. 050-346//5-16 and No. 050-346/75-20) i i 2.
Class TE Electrical Cable Trays (Inspection Reports No.
i 050-346/74-02, No. 050-346/74-04, No. 050-346/74-04, j E. 050-346 / 74-10, No. 050-346/75-03, No. 050-346/75-07, j No. 050- 346 / 75-13, No. 050-346/ 75-16 and No. 050-346/75-20) 3.
Bagwell Coating, Incorporated (Bameell) S top-work Order , I (Inspection Reports No. 050-346/74-07, No. 050-346/75-16 and No. 050-346/75-20) , ' 4.
Inappropriate Closure of Nonconformance Reports (NCR's) _IE Inspection Reports No. 050-346/75-03, No. 050-346/75-07.
( , No. 050-346/75-13, No. 050-346/ 75-16 and No. 050-346/75-20)
! ! i 5.
Incomplete Test Data (IE Inspection Reports No. 050-346/75-03 No. 050-346/75-07, No. 050-346/75-13, No. 050-346/75-16 and
No. 050-346/75-20) ! ! i 6.
Audits of the Installation Restraints (IF. Inspection Reports I ! No. 050-346/75-03, No. 050-346/ 75-13, No. 050-346/75-16 and . l "o. 050-346/75-20) , e i G-3-l I l l < r -
l i i , l l ' i !
' 7.
Cable Identifying and Pullinsttateri_al Certifications fIE Inspection Reports No. 050-346/75-04, No. 050-346/75-16 i and No. 050-346/75-20) 8.
Cable Material Certifications (IE Inspection Reports No.
, l 050-346/ 7 5-O'1, No. 050-346/75-16 and r:o. 050-346/75-2R
9.
Equipment Secured by "llilti-Kwik" Devices (IE Ing ection i Repor& No. 050-346/75-10, No.'050-346/75-15, No. 050-346/75-16, and No. 050-346/75-20) i 10.
Motor Operated Valves (IE Inspection Reports No. 050-346/75-15, No. 050-346/75-16 and No. 050-346/75-20) f 11.
Valve Design and Manufacturer (IE Inspection Reports No.
050-346/75-15, No. 050-346/75-16 and No. 050-346/75-20)_
12.
Reactor Main Coolant Pumps - Repairs (IE Inspection Reports No. 050-346/75-16 and No. 050-346/75-20) a ! a.
Original and Repair RT Film of RCP Casings l = l l The inspectors reviewed the original NDE documentation and RT film for the reactor coolant punp casings.
The , 9 inspectors found that in several areas of concern, the penetrameter placement had masked the discontinuity.
! The repair films reviewed were found to be clear of defects.
This item is considered as resolved.
(Report Details, Paragraph 2) , b.
Reactor Coolant Pumps Recertification i The licensee indicated that this matter is still under discussion with B&W and that they had requested a code committee interpretation for hydrostatic test requirements ' after a major repair.
This item remains open pending review of the code interpretation.
13.
Electrical Penetrations (IE Inspection Reports No. 050-346/75-18 and No. 050-346/75-20) 14.
Base-1.ine Inspection Procedure - Authorized Inspector Sign Off (IE Inspection Report No. 050-346/75-20) i
-4-i k O ' i
l
l j - .. . - - - - - - -
-__ _ _ _ _ _. _ _____ ___. _ _ ____ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ i l l f , i 15.
Non Code Fillet Weld Installed on Containm,it Personnel l Lock Expansion llellows Ring (IE Inspection h nort.
l No. 050-34f>/ 7 5 v, i l The inspector was inforned that the unauthorized non-code l weld installed on '.he containnent personnel lock would be removed by Chicago Bride,e and Iron Company (Cl &I) and rewelded using approved CB&I procedures and ASME Code qualifled welders.
The repair is to be performed prior to the leak rate test.
This item has bec.i documented on nechtel Nonconforraance Report No. 8-194 and is considered to be resolved.
Except as noted, the above items remain unresolved pending review of the corrective action taken by the licensee.
i Management Interview ' A.
The following persons attended the management interview at the conclusion of the inspection.
Toledo Edison Company (TECO) J. P. Williamson, President L. E. Roe, Vice President, Facilities Development
( E. C. Novak, General Superintendent, Power Engineering and l Construction J. D. Lenardson, Quality Assurance Manager i ' C.
T. Daft, Field Quality Assurance Engineer G. W.
Eicher.huer, Field Quality Assurance Engineer , l M. D.
Calcamuggio, Power Plant Electrical Engineer ! J.
E.
Orkino, Engineer Bechtel Corporation (Bechtcl) C. L. Houston, Field Construction Manager P. R.
Britncil, Project Quality Assurance Engineer J. D.
Heaton, Project Field Quality Control Engineer ., W. C. Lowery, Electrical Quality Assurance Engineer
' , ' l Babcock and Wilcox Company (B&W) W. R. Klingler, Project Manager F. Whytselo, NDE Examiner M. Weis, NDE Examiner l - -5-O . -en-. - - -. ---we .--.rn.e - - - -. - - - - - - - - .-
_ _ _ _ _ _. _ _ _ -
. O B.
Matters discusued and corments, on the part of management personnel, were as follows: 1.
The inspector stated that the current inspection covered: (1) a comparison of the original and repair RT film for the Reactor Coolant Pump Casings; (2) review of the Base-line inspection in progress, (3) a review of the QA/QC program f and procedures relating to the fit-up of the Reactor Vessel internals, and (4) a discussion of the Reactor Coolant P t cr.p Recertification Problem.
[ l i t
2.
In regard to previously identified unresolved matters, the I f inspector stated all items remain open except for two, the ' non-code fillet weld on the containment personnel lock and the review of the RCP original RT film.
Concerning the j later item the inspector stated that the original and repair j film of the RCP casings were examined.
The inspectors added j that the film speeds appeared conpatible but that the penetrameter in some cases had maskcd the areas of concern on the original film.
He further stated that the repair film examined appeared , j to be clear.
3.
The inspector stated that, during his examination of the weld areas of the Reactor Coolant Pumps it was noted and brought to the attention of the licensee that RT location j , rkers had been peened over.
lie further stated that this ! s ter was known by the contractor but that documentation hao nat been generated to control the matter as required by the contractors QA manual.
The inspector added that this j was considered as an item of noncompliance contrary to j Criterion V of 10 CFR Part 50, Appendix B.
4.
The inspector stated that he had reviewed the B&W 1etter to TECO dated November 7, 1975, pertaining to the recertification j of the RCP's and that he questioned the interpretation given I as to when the repaired areas would be reexamined, before or l after the hydrostatic test.
l The licensee indicated that this matter was being referred to the ASME code committee for resolution.
5.
The inspector stated that preliminary examination of available B6W records and procedures pertaining to the trail fit-up of the reactor vessel internals appeared to be in order.
lie added that a further review of this operation would be conducted during; subsequent inspections.
-6-
" i -
._ - _ - - - -. - - - _ - - _ _ - -. - - - - - - -. -- ,
l
REPORT DETAILS Persons Contacted The following persons, in addition to those listed in the M;magement ! Interview section were contacted during the inspection.
! Toledo Edison Company (TECO) E. M. Wilcox, Fir.ld Quality Assurance Engineer .J. C.
Buck, Field Quality Assurance Engineer Babcock and Uilcox Construction Ccmpany (B&W) R. E. Nelson, Quality Control Engineer ! i Results of Inspection l 1.
Reactor Coolant Pump Casings, RT Location Marks During the visual inspet!1.on of the Reactor Coolant pump casings , i the inspector noted that RT location marks were stamped in the welds of the suction clhow to the pumps and that these marks had been peened out with a hammer.
The inspector questioned this ' method of renoving location marks and was informed that the
marks had been stanped on the welds by mistake, by B&W Base-line , inservice inspection personnel.
The BSW ultrasonic inspection , l procedure ISI-102, Revision 6 states that the location marks will { be placed (2) two inches from the center of the welds.
The above j deviations had not been documented as required by BLW Construction j Company QA Procedure 9-QA-209, Report of Inspection of Inservice l Inspection activity.
The inspector informed the licensee that l cven though they were aware of the condition f ailure to follow l procedures was considered to be an item of noncompliance and
contrary to the requirements of 10 CFR Part 50, Appendix B, I Criterion V.
! t j 2.
Main Coolant Pumps - Casint; Field Repairs and RT Film i { The inspector reviewed radiographs of field repairs to the , I i following RT pump casings-Pump Casing Radiographs , 1-B-1 A-2-3 - A-4-5 1-A-1 E25 - 26 ! l-A-2 A-B28 - A-18-19-7- , l t
! -.--...-...-.... - -- .-.- - - - - - . . - -. -. .. -. - - -. - .
, . _. - _.
. , . The inspector reviewed the Base-line ISI radiographs that detected
the diucontinuities in the pump casings and the repair film I generated for those areas.
The inspector found that the field , i l repair ff]m were of good quality and the welds were cleat; of the ' previous!'/ recorded defects.
The ori;;inal shop radiographo and records of the same areas were also reviewed.
The inspector I found that with the exception of the penetrameter placement masking l part. of the area of concern that, the NDE technique used during
{ both the original and the current inspection was the same, also l ) that the film used during the current i.nspection although provided j j by another manufacture, was of the same speed as the film used ( { for the original radiographs.
! j 3.
Reactor Vessel Internals
j The inspector reviewed B&W procedure FS-Ill-le for the receipt
inspection, storage handling and installation of reactor vessel internals, and field construction procedure number 151, trial fit-up - of Reactor Internals.
Both procedures appe red to meet the require-ment of NRC and SAR commitments.
Ve.<sel nternal fit up was not in progress during the current inspection.
i 4.
Base-Line inspection Record Review and Observation of Work
p
I The inspector observed the B&W Examiners inspection of the pressurizer 0" weld.
The examiners were using B6W ISI procedures No. 102.
The
instruments being used had been properly calibrated and the results documented on B&W Calibration sheet, Forn No. 11.
The Base-line rough draft records of the inspection were ex" 'ned and found to be in order.
The Base-line inspection is approximately 65-707.
complete.
No major concerns have been identified to date.
, ! l l
! i ! ! -8-
\\
j ' I P ml 4..-e , -.,. - - - - - - - - -, - - - - . . . w -- - -. }}