ML20203F928
| ML20203F928 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 04/30/1986 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20203F921 | List: |
| References | |
| 1907B, NUDOCS 8604280183 | |
| Download: ML20203F928 (12) | |
Text
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Inservice inspection Report ,
INlERVAL - 2 PERIOD - 1 OUI AGE .-l l-or lhe Commonwealth Edison Company Zion Unit #2 Nuclear Power Station 101 Shiloh Boulevard Zion, illinois 60099 i
!, O Report Date: April 1986 Commercial Service Date- 3eptember 19 M 1
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. Index (Excerpted from Report)
TAB ISI Certificate - Owner Certificate and 0wner's Data Report ............................................A Summary ............................................................B E xami n a t i o n P r og ram . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C
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. FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules
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- 1. Owner Commonwealth Edison Co., P.O. Box 767, Chicago. IL 6n69n (Name and Address of Owner)
- 2. Plant Zion Genernt ing At atinn, ini Rhilnh n.Ltyg_, Zion, IL 60099 (Name and Address of Plant)
- 3. Plant Unit #7 4. Owner Certificate of Authorization (if required) N/A
- 5. CommercialService Date _9/17/7 6 4 . National Board Number for Unit See list below fot
- 7. Components Inspected Manufacturer Component or Manufacturer or installer State or National Appurtenance or Installer Serial No. Province No. Board No.
CLASS I Reactor 610-0152 Vessel Welds B&W 51-51 74880 N-185 RV Nozzle 610-0152 Safe-End B&W 51-52 74880 N-185 RV Flange 610-0152 Ligaments B&W 51-52 74880 N-185 S/G 1,2,3,4 Manway Bolti ng Westinghouse N/A N/A N/A PZr. Relief l Vlv. Bolting 1,2,3 Kellogg N/A N/A N/A
{d Various Supports ITT Grinnell N,'A N/A N/A RCP 1,3 Flywheels Westinghouse N/A N/A N/A CLASS II Various Supports ITT Grinnell N/A N/A N/A REPAIRS / REPLACEMENTS CLASS I B,C Pres, re l.
vlvs. Crosby N/A N/A N/A RTD flow ind ,
u 137 Kerotest N/A N/A N/A Note: Supplemental sheets in form of lists, sketches, or drawings may be used provided (1) size is 8% in. x 11 in.,
(2) information in items I through 6 on this data report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
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This form (E00029) may be obtained from the Order Dept., ASME,345 E. 47th St., New York, N.Y. 10017
FORM NIS 1 (back)
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- 8. lixamination Dates to 9. Inspection Interval from to
- 10. bstract of Examinations, include a list of examinations and a statement concerning status of wor ired to urrent interval.
- 11. Abstract Conditions Noted.
- 12. Abstract of Co crive Measures Rwmmended and Taken
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We certify that r'.ie stat ents made in this report are correct and the examinations and corrective mes-sures taken conform to t'.e rules of t. ASME Code,Section XI.
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r Date 19 ed By Owner
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Certificate of Authorization No.(if applicsble) / Expiratior Date N
CERTIFICATE OF INS VICE INSPECTION 1, the undersigned, holding a valid commi'ssion issued by th National Board of Boiler and Pressure Vessel inspectors and/or the State or Province of an mployed by of have inspected,de components described in Owners' Data Report during the period n to / . and state that to the best f my knowledge and belief, the Owner has performed examinatioris a,pdraken cerrective measures described in th Owners' Data Report in accordance with the requirements of tly'ASME Code,Section XI.
By signink this certifichte neither the inspector nor his employer makes any rranty, expressed or implied, concerning the exami[ations and corrective measures described in this Owners' sta Report. Furthermore, neither the Inspepc[nor his employer shall be liable in any manner for any personal i ry or property damage or a loss of any fnd arising from or connected with this inspection.
Date 19 Commissions
[ Inspector's Signature National Board, State, Province and No.\
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Page 2 of 2
. FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules
[ 1. Owner Commonwealth Edison Co., P.O. Box 767, Chicago, IL 60690 (Name and Address of Owner)
- 2. Plant Zion Generating Station, 101 Shiloh Blvd., Zion, IL 60099 (Name and Address of Plant)
- 3. Plant Unit __l 2 4. Owner Certificate of Authorization (if required) N/A
- 5. Commercial Service Date _2/_11/_7_4 6. National Board Number for Unit .See 1ist be l nW__for_
- 7. Components inspected Manufacturer Component or Manufacturer or installer State or National Appurtenance or Installer Serial No. Province No. Board No.
S/G sample vlv. _
Mason-Neil N/A N/A N/A 2,4 S/G rech .
tube pl ugriin ti Westinghouse N/A N/A N/A CLASS II Chrg, pump case drain viv. Hancock N/A N/A N/A 3,4 daieLy relief vlvs. Crosby N/A N/A N/A L.)
3" relief v1 v. Crosby N/A N/A N/A Support remov.
and instal. ITT Grinnell N/A N/A N/A 2,4 S/G aux.
FW check vlvs. Crane-Chapman N/A N/A N/A 2B manifold flow indic. Kerotest N/A N/A N/A 2B Seal wtr. inj. Rockwell-filter outlet, inlet v1vs. Edwaril s N/A N/A N/A 2A Flow transmit.
innlat. viv. Anderson-Greenwood N/A N/A N/A 2D MS drain viv. Hancock N/A N/A N/A
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Note: Supplemental sheets in form of lists, sketches, or drawings may be used provided (1) sisc is 8% in. x 11 in.,
(2) information in items I through 6 on this data report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
U This form (E00029) rnay be otitained frc m the Order Dept., ASME, 345 E. 47th St., Nb York, N.Y. 10017
FORM NIS-1 (brek)
- 8. Examination Dates _9/5/8 5 to 1/22/86 -
- 9. Inspection Interval from 9/17/R 4 to 4/11/ria
- 10. Abstract of Examinations. Include a list of examinations and a statement concerning status of work required for current interval. Reference Tab C
- 11. Abstract of Conditions Noted. Reference Tab B
- 12. Abstract of Corrective Measures Recommended and Taken Reference Tab B We certify that the statements made in this report are correct and the examinations a corre tive men-sures taken conform to the rules of the ASME Code,Section XI.
Commonwealth
'g g 'C 1986 Signed EdiSQn_ Company By T. A. Rieck Date 4[1_5 Superintendent, Services Owner Cer:ificate of Authorization No. (if applicable) N/A Expiration Date. N/A CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned. holding a valid commission issued by the National Board of Boiler and Pressure Vessel inspectors and/or the State or Province of I 1 l inoiS and employed by IISBI6I Co. of lia rt fo rd , CT have inspected the components desciibed in this Owners' Data Report during the period 9/5/85 to . ]/22/J6 , and state that to the best of my knowledge and belief, the Owner
,3 Q has performed examinations and taken corrective measures described in this Owners' Data Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examination: and correceive measures described in this Owners' Data Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
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% - Commissions [0( hM Inspector's Signature National floard, State, Province and No.
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) COMMONWEALTH EDIS0N COMPANY ZION NUCLEAR POWER STATION UNIT 2 INSERVICE INSPECTION INTERVAL-2 PERIOD-1 OUTAGE-1 EXAMINATION
SUMMARY
INTRODUCTION An inservice examination of Class 1 and Class 2 components and piping was conducted at the Zion Station Unit 2 from September 5,1985 to January 22, 1986. The examinations were performed in accordance with an approved Examination Program Plan located under Tab C of the Final Report.
Also during this outage, multifrequency eddy current examination was
- onducted on the 4 steam generators in accordance with Plant Technical Specification 4.3.1.B.S.B. This' program included essentially 100% U-Bend examination ir each generator from the hot legs, with full le.tgth exami-nation of approximately 900 tubes in each generator.
Examination procedures were approved prior to the examinations, and certification documents relative to personnel, equipment and materials were reviewed and determined to be satisfactory.
Additionally, as noted in the Owners' Data Report, several repairs /-
replacements were accomplished during this outage.
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Inspections, witnessing and surveillance of the examinations and related t
k activities were conducted by personnel from: Hartford Steam Boller Inspection and Insurance Company; the United States Nuclear Regulatory Commission; and Zion Station Quality Assurance and Technical Staff.
RESULTS Eddy current examination resulted in the plugging of 3 tubes, in steam generator B and 1 tube in steam generator C.
Other examinations resulted in a total of 12 recordable indicatica areas being not>!d on the basis of procedure recording criteria which, gener-ally, are more critical than specified Section XI acceptance criteria.
Two (2) ultrasonic indications in outlet nozzle to shell weld 11 and, one indication in outlet nozzle to s' hell weld 18 were subjected to additional investigations. These investigations, using refined methods, and the review of results were based on approved alternative methods in accordance with IHA-2240.
The nozzle indications are due to fabrication reflectors (porosity / slag) located in the embedded root area of these modified double J joints.
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Invest'igation of recorded indications resulted in all of them being judged acceptable.
Specific data relative to all of the above are located under Tabs E and F of the FINAL REPORT.
EXAMINATIONS Examinations were conducted to review as much of the specified surface / volume as reasonably practicable. For a few items, examl-nations were limited by geometric, metallurgical or design access restrictions, as explained under LIMITATIONS.
Mostly, the limitations relate to examinations by ultrasonic methods and
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(~J the effect is that a small volume of base metal, on the restricting side only, may be missed. The resulting coverage in such cases is that the sound beam passes through all of the specified volume of weld metal and
, adjacent heat affected zones that are within the volume specified for examination; through all of the base metal on the unrestricted side and; through all but a small mid-wall portion of base metal on the restricted side.
The occurrence and cause of various limitations have been noted.
LIMITATIONS
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v Some of the arrangements and details of the piping system and components were designed and fabricated before the access and examination ID:3060r/40786:49
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requirements of Section XI of the 1971 Code could be applied; consequently some examinations are limited or not practical due to geometric configuration and/or design accessibility. Generally these limitations exist at all fitting-to-fitting joints such as elbow to tee, elbow to valve, reducer to valve, etc., where geometry precludes optimum ulltrasonic search unit contact or scanning distance from both sides of i 1
the weld. The limitations exist tc 1 lesser degree at pipe to fitting assemblies, such as pipe to valve or pipe to flange. At these joints, search unit contact and scan distance is usually adequate to achieve a minimum acceptable.converage from the pipe side.
In many cases scanning is accomplished from both sides of a weld in an attempt to cover as much of the specified volume from as many directions q as practical, however, the extent of additional coverage from the N,J restricted side cannot be specifically quantified.
The resulting coverage is the maximum that is reasonably practical.
i j Specific limitations and restrictions for all examinations are indicated on the examiners' data sheets, under Tab-0 of Outage Report.
ID:3060r/40786:49
COMMONWEALTH EDISON COMPANY
- h. ZION NUCLEAR POWER STATION UNIT 2
' INSERVICE INSPECTION INTERVAL-2 PERIOD-1 OUTAGE-1 EXAMINATION
SUMMARY
All items and areas listed below were examined as indicated, in ,
accordance with the requirements of the plant Technical Specifications Section 4.3, based on the 1980 Edition,Section XI of the ASME Boller and Pressure Vessel Code up to and including winter, 1981 Addenda to the extent practical with the access provided and the limitations of component geometry.
- Reference APPENDIX A (Tab I - Final Raport) for specific details of Reactor Vessel Remote examinations.
COM LINE IWB-2500-1 SKETCH EXAMINATION EXAMINATION NUMBER REFERENCE REFERENCE ITEM / AREA PROCEDURE REAC10R VESSEL Vol. Sur. Vis.
1 81.30 1-1100 Held 1 154 2 83.90 1-1100 Welds 11,14,15 and 18 154 3 B6.40 1-1100 Ligaments L14 thru L21, 154 L28 thru L37 and L46 thru L54
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.COM-LINE IWB-2500-1 SKETCH EXAMINATION EXAMINATION [
NUMBER REFERENCE REFERENCE ITEM / AREA PROCEDURE -
,Vol. Sur. Vis.
4 84.10 1-1100 Instrumentation Nozzle V/T 2 (1) 5 B5.10 1-4100 Weld 1 154 6 B5.10 1-4200 Held 1 154 7 85.10 1-4400 Weld 1 154
'8 B5.10 1-4400 Weld 1 154 FLYWHEELS 9 RGI.14 1-1500 1-1 Fly and 3-1 Fly 41 -
11 LEAK TEST O 10 815.XX General '
V/T 2 SUPPORTS / HANGERS 11 F3.40 1-4800 Items 21, 159, 220, 257, (1) 278, 296, 312 and 355
.12 F3.40 2-2700 Items 5, 15, 26, 39 '(1) 40, 65, 66, 203 and 204
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(1) Done by station personnel
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