IR 05000302/1990016
| ML20043D286 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 05/15/1990 |
| From: | Blake J, Economos N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20043D284 | List: |
| References | |
| 50-302-90-16, NUDOCS 9006070330 | |
| Download: ML20043D286 (11) | |
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, , . ' ? D [ 's- . . b >* Recoy'o - UNITED STATES , , - . . W .! NUCLEAR REGULATORY COMMIS$10N Yv . [ REGION il ' ' , .j' 101 MARIETTA STRE'ET,N.W.
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D iI E ATLANTA, GEORGI A 30323
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, , m N" y, , ,. Report No.t 50-302/90-16 , ' ' Licensee: Florida' Power Corporation 3201 34th Street. South ' ' St'. Petersburg,-FL 33733 ' . , Docket No.: 50-302 License No.: OPR-72 i ' " t... .; ~ Facility Name: Crystal River 3 j Inspection nd .ed jApril.10-20,1990 . , ThL &&_ [ Inspecto : l .I -. t _.
Date Signed
Approv 'by:. * ~ [ /, v h , -0./J. BlaKe, Chief Date Signed-4te ials and Processes Section ! 'o ng neering Branch , e Division of Reactor Safety
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' .o SUMMARY- , Scope - j , . This routine, unannounced inspection was performed onsite, in. the areas of c .. I _ observation of inservice activities and welding and a review of applicable
' procedures, related' records, personnel certification and material-certification.- p ' . 'Re sul t s t ' ' In. that ~ the current inservice inspection is the first of the second ten year c.
[ interval _ since. commercial operation, nondestruction. examinations required by.
p plant Technical Specifications (TS). and regulatoryL requirements.are being L Leonducted in accordance with ASME Section XI 1983 Edition and Summer 1983 i
Addenda.
As' such, observation of volumetric and surface examination conducted' n with procedures written in accordance with subject code requirement. was found l l' . to be sati sf actory.. Welding performed as part of corrective maintenance ] activities was. observed'6nd related work packages were' reviewed and-found that~ i l: consistent with work procedures and code requirements. The inspector found the- . ~ inspection' effort for this outage was well organized,' examinations were being l . conducted by qualified personnel in -accordance with approved procedures.
' Inspection results'and findings were documented and evaluated as required.
h _In the areas inspected,- violations or deviations were. not identified.
q s i 9006070330 900518 ~ ' $DR ADOCK 05000302 PDC , ' , . , ,
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Persori Contacted h Licensee Employees [ H . G. A. Becker, Manager, Site Nuclear Engineering Services 'G. L. Boldt, Vice President, Nuclear Production '*J. CooperLJr., Nuclear Technical Support , n 'D. Galling,-ISI Specialist ' L
- J. 0.-Holton, Nuclear Technical Support L
P..F. McKee, Director,= Nuclear Plant Operations '
- S. G. Johnson, Manager, Site Nuclear Services
- J. J. Warren, Site Welding Engineer
' M. S. Williams, Nuclear-Regulatory Special Other licensee employees contacted during this inspection ' included craftsmen, engineers and administrative personnel.
Other Organizations Babcock & Wilcox, Nuclear Services Company (B&W NSC) 'J. Burton,-ISI Coordinator l S.~M. Herman, Task Leader ' ' NRC Resident Inspectors
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- P._ Holmes-Ray, Senior Resident Inspector
- W. H. Bradford, Resident Inspector ! e '
- Attended exit interview
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Inservice Inspection > The inspector. reviewed documents and' records and observed activities, as indicated - below, to determine whether ISI-was= being conducted -in .' accordance with applicable procedures, regulatory requirements, and' licensee commitments. The applicable code for ISI is the American Society - of Mechanical Engineers Boiler and Pressure Vessel ( ASME' B&PV) Code,- Section XI, edition with addenda through Summer 1983.
, B&Wfis responsible for the eddy current (EC) examination of the once ! through Esteam-generator (OTSG) tubing and will utilize the automated evaluation equipment for the primary data evaluation. Westinghouse _has , , the responsibility for the automated ultrasonic examination of the reactor - vessel welds.
This will be done with the Ultrasonic Data Recording and Processing System- (UDRPS), B&W -has the remainder / balance of plant ISI examination. activities.
Independent third party inspection service , L' i , . _ . I
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, < (ANII/ANI), was provided by Factory Mutual Co. under contract with the f-licensee.
At_the' time of this inspection, visual, surface and volumetric examination were in< progress end were being performed on primary, secondary and , L balance of plant' piping.
The reactor vessel. examination and ' st eam b generator tube eddy current (EC), examinations had not-begun.
The NRC inspector. elected to observe a representative sample of the on going examinations and reviewed 0A-documentation relative to procedures.
> personnel qualifications, and certifications of materials and equirment used in these examinations.
a.
ISI Program Review (73051) The inspector reviewed the following documents relating to the ISI L' program to determine whether the plan had been approved by the licensee and to assure that procedures and plans had been established (written._ reviewed, approved and issued). to control and accomplish the following applicable activities:- organizational structure including qualifications, training, responsibilities,' and duties of-- personnel responsible for ISI; audits including procedures, frequency, and qualification of personnel; general Quality Assurance requirements-including examination reports, deviations from previously established program, material certifications, and ideritification of components to be covered; work and inspection _.
procedures; control of processes including suitably controlled work conditions, special methods, and.use of qualified ~ personnel; - corrective action; document control; control of-examination . equipment; quality records including documentation of indications and NDE-. findings, review of documentation, provisions to assure-n legibility and retrievability and corrective action; scope of the ' inspection including description of areas to be examined, examination category,. method of. inspection, extent of.- examinations,- and.
,, justification for any exception; definition of inspection interval and extent of examination; qualification of NDE personnel; 'and, controls of generation, approval, custody, storage and maintenance of 'NDE records.
- Inservice Examination Manual.
3/29/90 g Reactor Vessel Examination Westinghouse, Nuclear Service Division , l
Ten year Inservice Inspection Program 2/1/88 ,," General' Electric, Nuclear Plant Services
' Inservice Examination Manual,1990, Babcock 3/20/90 X & Wilcox Nuclear Services Company
AI-701 Conduct of Inservice Inspection 8/29/89 \\ . . E'
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Review of NDE Procedures (73052)' (1) The inspector reviewed the procedures listed below to determine whether they were consistent with regulatory requirements and licensee commitments. The procedures were also. reviewed-in,the , ,! ~ areas of procedures approval, requirements for qualification of .NDE personnel, and compilation of required records; and, if applicable, division of responsibility between the licensee and-contractor personnel if contractor personnel were ' involved in the ISI effort.
ISI-120 Rev. 29 Ultrasonic : Examination of Piping - Welds Joining Similar Metals 151-130 Rev. 25 Ultrasonic Examination of Vessel Welds and Nozzles-Inside Radius Sections 151-240 Rev. 24 Penetrant Examination of Welds and Base Metal Including Studs and Nuts 151-270 Rev. 24 Wet..and Dry Methods of. Magnetic Particle Examination of. Welds Studs, Bolts and Primary Motor Fly Wheel 151-418 Rev, 6 Technical Procedure-for Multifrequency Eddy Current . Examination of OTSG Tubing in 177 Steam Generators using Miz-18 151-425 Rev. 11 Eddy Current Examination of Tubing-by Absolute Multicoil .(8x1) Techniques BCRY-ISI-88 Rev. 0-Underwater Remote Visual-Examination for CR-3 BCRY-151-54 Rev. O Manual Ultrasonic Examination of Reactor Vessel Upper Shell to Flange' Weld BCRY-ISI-153 Rev. O General-Requirements for the Ultrasonic Examination of Reactor-Vessel Using UDRPS BCRY-ISI-154 Rev. O Ultrasonic Examination Requirement for Outlet Nozzles and Piping Welds from Nozzle Bores Using.
UDRPS .
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(2) The inspector reviewed the. Ultrasonic procedures to ascertain i , whether they had been reviewed and approved in accordance with ! the licensee's established QA procedures.
The procedures were also reviewed for technical adequacy and conformance with ASME - , l.
Section V, Article 5, and other licensee commitments / requirements i 'l-in the following areas: type of apparatus used; extend of [L coverage of weldment; calibration ' requirements; search units; j , ' beam angels; DAC curves; reference level for monitoring " - discontinuities; method for demonstrating penetration; limits for evaluating and recording indications;. recording significant
indications; and, acceptance limits.
[ E (3) The inspector reviewed the Liquid Penetrant procedure to
L ascertain whether it had been reviewed. and approved in ! accordance with the licensee's established QA procedures.
The i procedure was also reviewed for technical adequacy and ' conformance with ASME, Section V, Article 6, and other licensee l commitments / requirements in the following areas:- specified.
method; penetrant material identification; penetrant materials t analyzed for sulfur, penetrant materials analy:ed for total ' halogens; surface temperature; acceptable pre-examination surface conditioning; method used for pre-examination surface cleaning; surface drying time prior to penetrant application; ', f method of penetrant application;c penetrant dwell time; method - used 'for excess penetrant removal; surf ace drying prior to ' developer application, if applicable; type of developer; .' examination technique; evaluation techniques; and, procedures requalification.
, ! (4) The inspector reviewed the Magnetic Particle procedure to ascertain whether it had been reviewed and approved in .' accordance with the licensee's established QA procedures.
The procedure was reviewed for technical adequacy and-for. , conformance with the ASME Code Section V Article 7, and other ! licensee commitments / requirements in the following areas: , . examination methods; contrast of dry powder particle color with.
background; surf ace temperature; suspension medium and surf ace temperature requirement for wet particles; viewing conditions; examination overlap and directions; pole or prod spacing; current or lif ting power (yoke); and, acceptance criteria.
t (5) The ' inspector reviewed the Visual examination procedures to determine whether they contained sufficient instructions to ' assure that the following parameters were specified and controlled within the limits permitted by the applicable code, standard, or any other specification requirement: method - direct visual, remote visual or translucent visual; application - hydrostatic testing, fabrication procedure, visual examination of welds, leak testing, etc.; how visual examination is to be' performed; type of surface condition available; method or implement used for surface preparation, if any; whether direct
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t [ L e or remote viewing is used;. sequence of performing examination, i r when applicable; data to be tabul?ted, if any;- acceptance i criteria is specified and censistent with the applicable; code - section or controlling specification; and, report form > completion.
. .! (6) The inspector reviewed the Eddy Current procedures for technical - W content relative to: multichannel examination-unit, multichanne1~ examination indication equipment is specified, examination sensitivity, method of examination, method of i , ' -calibretion and calibration sequence,>and acceptance criteria.
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[. All procedures reviewed appeared to contain -the necessary elements i y for conductir.g the specific examination.
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Observation of-Work and Work Activities Unit 1 (73753) l The - inspector observed work activities, reviewed certification . , , records of NDE equipment and materials, and reviewed NDE personnel-qualifications for personnel that had been utilized during ~ the ' required ISI examinations during this outage. The observations and , reviews conducted by the inspector are documented below.
! (1) Ultrasonic Examination ] a ' Loop A-1, cold leg cross over to S/G A" i MK65 to , B4.5.206 MK67 =Noz to Pipe O, 45' Dwg. -SK.27.1 Rev. O
g . ^ MK67 to - B4.5.216 MK45 Pipe to Elbow 0', -45' Dwg. SK 17.1 Rev. 0 .; < . m . - The -observations were compared with the. applicable procedures [ '
and the ASME B&PV Code in the following areas: availability of ~ , and compliance with approved NDE procedures; use of knowledge-able.NDE personnel; use of NDE personnel qualified to the. proper ! m levelt type of apparatus used; calibration requirements; search-units; beam angles; DAC curves; reference. level for monitoring l ,,, ' ciscontinuities; method of demonstrating penetration; extent of
A weld / component examination coverage; limits of evaluating and j recording indications; recording significant indications; and,-
acceptance limits.
' ' e The' following listed ultrasonic equipment and materials-
, O certification records were reviewed.
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, , ' Ultrasonic Instruments ts i Manufacturers /Model-Serial No.
j KB/USIPa12 29321-1082- - r " ' KB/USIP-12 29321-1275 Sonic / Mark-1 08683E-Sonic / Mark-1 11225E ' Sonic / Mark-I 14561F ' - Sonic / Mark-! 14554F Spectrum analysis data was reviewed for the foll'owing ultrasonic transducers: i , . KT 100-2-X 123601-06 2.25 MHz h",",- 1.0 KT-50-2-X-123607-18 2.25 MHz .: KT 50-1-X 123728 2.25 MHz h", ' ! KT 50-1-X 12731 2.25 MHz h"e , ' GAMMA C26682 2.25 MHz 1.0"$ l ' Ultrasonic Couplant Ultragel 11, Batch #62043 < i t Ultrasonic Calibration blocks " ' , , S/N, Si:e i l 40757 S.8 x 18 x 45.188 t J =40763 3.97 x 6 x 14.005
U 40753 3.1 x 12 k 7- -(2) Liquid' Penetrant Examination , K 1 ,
In process'11guid penetrant (PT) examination was observed on the
S9 following main loop cross-over drain line weld:- , r k' MK64 to L B4.1.43 MK63-Nozzle to P1pe Dwg. #SK17.1~ ~ m< , E< The observation was compared with0 the applicable procedure and i " the ASME B&PV Code in the 'following areas: specified method,-
W penetrant materials identified; penetrant materials analyzed for i Kf, halogens and sulfur; acceptable pre-examination. surface;. surface W temperature; surface drying time prior to penetrant application;- , ' method of penetrant application; penetrant ' dwell. time; method
(p% used for excess penetrantm removal; surface ~ drying prior to- , developing, if applicable; type of deve'oper;.- examination W. y' technique; evaluation technique; and,- reporting of examination , ( results.
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' c 5%, ~ i: The NRC inspector re-evaluated the drain line weld following the; f PT examiners evaluation, but prior to the developer. being L '.. received from the weld surfaces. The re-evaluation was removed.
' in order to determine if.the evaluation performed by the PT examiner was in accordance with; the applicable procedure-g , acceptance criteria and to determitie if the examination results ' were being. reported as required. The re-evaluation conducted by-
the NRC inspector indicated that the proper evaluation was made by the PT examiners and that the examination results were being [ reported as required.. A review -of 'the below listed liquid penetrant materials certification records indicated that the sulfur and halogen-I content of the material was within acceptable content limits.
Materials Data / Base Batch / Type - ' Cleaner - 63104 89K05S/SKC-NF Penetrant - 64067 89K01F/SKL-HF/S. Developer - 65066 89LO3P/SKD-NF-(3) Magnetic Particle Inspection In ' process magnetic particle (MT) examination was observed on - the following Loop A-1 cold leg cross-over to S/G A welds.
MK.65 to B.4.5.206 MK67 Noz. to Pipe Dwg. SK17.1 Rev.0 MK 67 to B4.5.216 MK45 Pipe to Elbow Dwg. SK17.1 Rev.0 . , Observations were compared witn the - applicable. procedures and : the. Code in the following areas: examination methods; contrast it of. ~ dry powder particle color with background;. surface.
I temperature; suspension medium for wet particles, if applicable;. ' viewing conditions; examination overlap and directions; pole or prod spacing; current or lifting power (yoke); and, acceptance
criteria.
A review of certification records for magnetic particle
alternating current yoke S/N 18003 and magnetic powder batch
- 66028 indicated confirmed the subject items met applicable-specification requirements, ji (4) Qualification records of B&W personnel performing nondestructive examination were reviewed to verify -compliance with applicable ASNT-TC-1A requirements.
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b R. Tomienson 11-II II II
- k V.:P. Montalbano: II.
II-II II
J. E. Scoates-II-II II.
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-- ,, R. K. Moore- ~II II II-
-- G. E. Szubature-I I ~ I
-- 't J. A. Burton 11-II II
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-- '* A. Richne 4 II II II' II II: II I i S. M. He
.G. L. But ier - I-T I-T I-T I-T- .i , ' R. L. Richardson I-T I-T I-T
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I-T-I-T-u. . .,3 More specifically, these personnel qualifications were reviewed: [ in. the following-areas: employer's name;- person certified; ,l
.. activity qualified to perform; current period of-certification;
- j signature _ ofiemployer's designated representative; basis used--
' for certification; and, annual visual acuity, color vision - -! examination. and, period recertification.
! $ ?~ 'd.; Data-Review and Evaluation (73755) - Records of' completed-ISI nondestructive examinations.for 2 UT,' 2 PT, ! - 15 MT, and 2 VT examinations were selected and reviewed'te ascertain _ 1whether; :thef method (s), technique, and extent of the examination.
> . complied with' the ISI plan and applicable-NDE procedures; findings g ' were properly recorded and evaluated ~by qualified; personnel;
programmatic deviations were recorded as required; personnel,. instruments, calibration - blocks. and= NDE - materials (penetrants, D , 9-couplants).were designated.
All of. the. examination reports reviewed appeared 'to contain the " ' . required -examination information including disposition of:
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- indications, if 'any.
-Within the areas inspected, violations or deviations were not y , identified.
, ' 3; Corrective Maintenance - Welding (55050) a.
Valve RCV-21 Replacement.
The subiect valve was replaced because of , unrepairable seat. leakage. LThe valve provides the: second isolation boundary between - reactor coolant class 1 and the waste : disposal j class 3 systems.
The 'line provides : a vent path when ' filling the ~ - C' loop and "A" generator.
The valve-appears on CR3-P-8020-RC-I ' drawing' andiis described 'as a 1" 2500lb Globe -isolation valve.
-Because dnstallation had-been completed at the time of the inspection-the inspector elected to' review the work package and thereby ~ ascertain whether procurement,, installation and testing were . consistent with ANSI B31.7-69, the controlling standard for the , o
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ReplacementL was performed under ' " .' modification approval = record '(MAR), #90-01-13-01 and work package '(WR), - #NVQ 26285.. Administrative control 5 - were - provided through - ',. L maintenance procedure MP-132 Erection.of -Piping., Replacement.
p . materials / components were identified as follows: . ?! Pipe - 1 inch diam schedule ~160- > - Heat #464319 stainless ' steel PO:#A473580 p 0C1 #139848
.Nalve-1" 2500lb Globe nonsafety related - .S/N 891096-1-PO #FS404630 ,, QCI #140449 ' Records indicated the. completed welds' had been examined - per e . applicable code requirements and found acceptable.
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= Modification' of Reactor Coolant and Makeup Piping to~ Reactor Coolant- ! , Pump Seals.
t-In ' an - effort.. to-- improve the service life of reactor coolant pump ; - ,! j seals, the licensee is replacing existing iseal assemblies with' a i inewly' designed Byron Jackson N-9000 sealed cartridge.
The. licensee expects.a minimum of 50,000 opet iting -hours before -servicing ~ these g
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- replacements. installation require t that some of the existing; small i
k diameter nim'c 'and flanges be modified, which. involved: welding Land - p flange.. , e-The: work was - perf ormed under /MARJ #87091302 and . , ys work.re te-N764 which invoked ANSI 31.7-69 as the code'ofirecord.
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'Tne ir ex+o; oF - .1 completed field welds, RC-85-313, -315; +319. , -321 a,' 1'5 ' ..., e.ps "C" to verify that workmanship quality:and- '] weld ape ". ^ < + onsistent with applicable code requirements.- $lh In'adt
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% pector reviewed the work package which included t W weld-t- . m, waterials quality records and 'no-destructive ,
G examination ieports.
Other work related maintenance-procedures ' .- j w{, . g . reviewed for technical content and adequacy included: ' '{ gggg ' * f( MP-137 Hydrostttic Testing d'5i MP-122 ' Assembly 'and Disassembly of Flanged Connections ihh MP-132 Erection of Piping g, ce j6 t, A, Within the areas. inspected, violations or deviations were :not pQ' identified, i P' rj
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