ML20203F934
| ML20203F934 | |
| 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 8604280184 | |
| Download: ML20203F934 (13) | |
Text
-
r' 1
,O Inservice inspection Report INlERVAL - I PERIOD - 3 OUI AGE - Final For The Commonwealth Edison Company Zion Unit #2 Nuclear Power Station 101 Shiloh Boulevard Zion, Illinois 60099 COMMONWEAllH EDISON Post Office Box 161 Chicago, Illinois 60690
- O '
Report Date: April 1986 f
Commercial Service Date: September 1914 4
a I
i l
e6o4asois4 e60417 i
^" N '-
t O P ;
i 1901B
. - , . - - - , - - - - . ~ . . , - - - - - . . . . - - . , - - . - . - , -
, . _ . _ . _ . _ . . . . ~ .. . . . . _ , _... _ . _ . . ._~ _ ._...._ ___.___- _.-____ _ _.. . ._. _ ._.
F
- f. 6
., s
.)
1 O
Index (Excerpted from Report) I TAB r
! ISI Certificate - Owner Certificate and ,
- 0wner's Data Report ............................................A
[
Summary'............. ..............................................B Examination Program ................................................C ;
1 9
4 ie i
t
- - 0: s t
4 e
T b 0
A
> s
~
4 i
).
, l t,
s v
l' 1.
l
!O i
l i
{. ,
i ,
.i 1
19078 4
+-+-e E--.-ocee..-ww--.,,,-m-., -, _. . ---wew.ww------.ee, ws-e m -w r -e, .w ww ._ - - y -ve- - sw r-- -'
s Page 1 of 2 s
FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules
[")
V
- 1. Owaer 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 i (Name and Address of Plant)
- 3. Plant Unit #2 4. Owner Certificate of Authorization (if required) N/A
- 5. Commercial Service Date 9/17 /7 4 6. National Board Number for Unit See list below for component or appurtenance
- 7. Components Inspected Manufacturer Component or Manufacturer or Installer State or National Appurtenance or Installer Serial No. Province No. Board No.
CLASS I ,
Reactor 61()'-0152 Vessel Welde B&W Slf52 74880 N-185 RV Nozzle 6)D-0152 Safe-End B&W 51-52 74880 N-185 RV Internals Westinghouse N/A N/A N/A Various Supports ITT Grinnell N/A N/A N/A gCPSeal O BOS$fhh Kelloqq N/A N/A N/A
%./
l t
i Note: Suppicmental 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.
[u This form (E00029) nay be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017
s
.' {
FORM NIS 1 (back)
+ .
O U 8. Examination Dates to 9. Inspection Interval from to
- 10. bstract of Examinations. Include a list of examinations and a statement concerning status of wor equired f current interval.
- 11. Abstrac ( Conditions Noted.
- 12. Abstract of C ective Measures Recommended and Taken We certify that the sta ments made in this report are correct an he examinations and corrective mea-sures taken conform to the rules o e ASME Code,Section XI.
< Date 19 igned By O er Certificate of Authorization No. (if applicable) Expiration Date CERTIFICATE OF VICE INSPECTION 1, the undersigned, holding a valid commi on issued by t National Board of Boiler and Pressure Vessel inspectors and/or the State or Frovince of an mployed by of have inspected t components described in : Owners' Data Report during the period r p to -
. and state that to the bes f my knowledge and belief, the Owner
, V has performed examinations and en corrective measures described in th Owners' Data Report in accordance with the requirements of the A . E Code,Section XI.
By signing this certifica neither the Inspector nor his employer makes any rranty, expressed or implied, concerning the examina ' ns and corrective measures described in this Owners' ata Report. Furthermore, neither the inspector r his employer shall be liable in any manner for any personal i 'ury or property damage or a loss of any kin rising from or connected with this inspection.
l Commissions National Board, State. Province and No
[ ' Inspector's Signature V
, Pago 2 of 2
. FORM NIS 1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules n
Id 1. owner Commonwealth Edison Co., P.O. Box 7t37. 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 #2 4. Owner Certificate of Authorization (if required) N/A
- 5. Commercial Service Date 9/17/74 6. National Board Number for Unit N/A
- 7. Components inspected : Hydrostatic testing of the following to complete 10 year ISI hydro tests. l l
Manufacturer !
Component or Manufacturer or Installer State or National Appurtenance or Installer Serial No. Province No. Board No.
-Systems-Reactor Coolant M.W. Kellogg N/A N/A N/A Containment Snrav M.W. Kelloqq N/A N/A N/A Silfety Tniectinn M.W. Kelloqq N/A N/A N/A e5 dual ea Removal M.W. Kelloco N/A N/A N/A Volume control M.W. Kelloco N/A N/A N/A Feedwater M.W. Kelloca N/A N/A N/A Blowdown M.W. Kelloco N/A N/A N/A Component l Cooling M.W. Kelloca N/A N/A N/A l Service Water M.W. Kelloqq N/A N/A N/A Is Nglatg*on f-X@
^l M.W. Kellogg N/A N/A N/A l i
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 1 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) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017
+
s FORM NIS 1 (back) p 4 6
- 8. Examination Dates 9/5/R 5 to 1/? 2 /R 6 9. Inspection interval from 9/17 /74 to 9/17 /R 4 plus extension from 9/17/84 to 1/22/86
- 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 nd '
c rective mes-sures taken conform to the rules of the ASME Code,Section XI. g Commonwealth M &
Date 4/19 19 H6 Signed _ Erli nnn enmnany By T . A . Rieck Owner Superintendent, Services Certificate of Authorization No. (if applicabic) N/A Expiration Date N /A CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessed Inspectors and/or the State or Province of T11innie and employed by n Anr.T ty ; of Hartford, CT have inspected the components described in this Owners' Data Report during the period
/3 _9/5/R5 to 1/?S/R6 and state that to the best of my knowledge and belief, the Owner b has performed examinations and taken corrective measures described in this Owners' Data Repott in acco dance 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 examinations and corrective measures described in this Owners' Data Report. Furthermore, neither the inspector nor his employer shall be liabic in any manner for any personalinjery or property damage or a loss of any kind arising from or connected with this inspection.
te b / 6 19 86 Ub -
Comruissions _ __ hb 1 Inspector's Signature National Board, State, Province and No.
O .
/
V_
COMMONHEALTH EDISON COMPANY ZION NUCLEAR POWER STATION UNIT 2 INSERVICE INSPECTION INTERVAL 1 - FINAL EXAMINATION
SUMMARY
INTRODUCTION An inservice examination of Class 1 and Class 2 components and piping tias 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.
b Also during this outage, multifrequency eddy current examination was conducted on the 4 steam generators in accordance with Plant Technical Specification 4.3.1.B.5.B. This program included essentially 100% U-Bend examination in each generator from the hot legs', with full length 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.
ID:3059r/32186:49
-~
I i
I .
Inspections, witnessing and surveillance of the examinations and related 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.
The remaining examinations resulted in a total of 53 recordable O indicatioa areas bein9 acted oa the basis of procedure recordia9 criteria which, generally, are more critical than specified ASME Section XI Acceptance standards. None of the recorded indications exceeded specified Section XI acceptance criteria.
Investigation and disposition of these recorded indications resulted in 1 (one) of them being corrected and 52 that were judged to be acceptable as is.
Specific data relative to all of the above are located under Tabs E and F of the FINAL REPORT.
ID:3059r/32186:49
EXAMINATIONS O
Examinations were conducted to review as much of the examination zone as was practical within geometric, metallurgical and physical limitations.
When the required ultrasonic examination volume or area could not be examined 1007., the examination was considered to be partial (PAR) and so noted. Generally PAR's are noted as fitting-to-fitting assemblies (as explained under LIMITATIONS) and in areas where integrally welded supports, lugs, or hangers, etc., preclude access to some part of the examination area.
Ultrasonic examinations that produced greater than reference level sensitivity, from reflectors that are characteristic of metallurgical structure or the I.D. and or 0.D. surfaces of an item were acknowledged O oniy. Exempies of ereas thet senereiiy produce such 9eometric indications are as follows:
(1) I.D. weld prep or root and or the crown overlay or toe. l l
(2) The I.D. radius of the tube shhet on the channel head to tube l l
sheet weld of steam generators, when examining from tube sheet I side. l (3) The metallurgical structure of the cast materials.
(4) Responses from the thread areas of bolting. j
\
NJ ID:3059r/32186:49 j
_ __ _ _. j
Areas where complete examination of 100% of the required volume of area 1([ ) could not be achieved are indicated by a PAR (partial) notation on the examiners' data sheet, and the limiting cause is noted.
The principal basis for PAR's is to identify the inability to examine '
100% of the required base metal volume for the 1 T distance beyond the edge of the weld on a fitting or component. Examples are (1) ultrasonic examination of a pipe to elbow assembly where scanning on the intrados of the elbow causes de-coupling of the sound beam and (2) a pipe to flange or valve assembly, where scanning the entire volume on the fitting or component side is limited by configuration.
The resulting coverage is such that examination of the weld, heat affected zone and base metal for 1 "T" on the pipe side can be achieved O'
k/ by scanning from the pipe side of the weld. An indeterminate coverage of the base metal on the fitting or component side may be achieved during this pipe side scan depending on the calibrated sweep length, attenuation, joint configuration, etc. However, the volume on the fitting or component side additionally cannot be scanned completely for transverse indicat'lons as required by Code. In either case, 100% of this 1 "T" volume cannot be assured, thus a PAR is required as a disclaimer to having satisfied code requirements, albeit the intent is satisfied to the extent practical.
Specific limitations and restrictions for all examinations are as indicated on the raw data sheets - Section D and E of the Final P.eport.
O ID:30s9r/32186:49
O LIMITATIONS id Some of the arrangements and details of piping systems and components were designed and fabricated before the access and examination requirements of Section XI of the 1971 Code could be applied; consequently some examinations are limited or not practical due to geometric configuration or 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 and sometimes surface condition preclude u'ltrasonic coupling or access for the required scan length.
The limitations exist to a lesser degree at pipe to fitting assemblies, particularly where the weld is not ground flush with the pipe 0.D.
(})
surface. At these joints, examinations can be conducted from the pipe side; however, the fitting again limits or precludes examination for the opposite side. When the weld surface is flat, the fitting side examination is replaced by a calibrated straight beam examination on the weld.
In most cases, examinations in these areas were accomplished as a best effort attempt to cover as much of the code requred area or volume (generally, the weld and base metal for 1 "T' on each side) as is possible, however, the extent of examination coverage in the base metal of the fitting or component cannot be specifically quantified as being 100%.
mx_
COMMONWEALTH EDISON COMPANY ZION NUCLEAR POWER STATION UNIT #2 INSERVICE INSPECTION INTERVAL - 1 FINAL y 1985 kJ 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 1974 Edition,Section XI of the ASME Boller and Pressure Vessel Code up to and including Summer, 1975 Addenda to the extent practical with the access provided and the limitations of component geometry.
Reference APPENDIX A (Tab I - Final Report) for specific details of Reactor Vessel examinations.
- COM PROGRAM IWB-2600 ITEM / AREA SUBJECT EXAMINATION SKETCH ITEM REFERENCE TO EXAMINATION U/T SURF V/T REFERENCE REACTOR VESSEL
- 1. 1.1 Welds #3,4,7,8,9 and 10 154 -- - --
1-1100
- 2. 1.2 Welds #2 and #5 154 -- --
1-1100
- 3. 1.3 Weld #1 154 -- --
1-1100
({}
- 4. 1.4 Welds #12,13,16 and 17 154 -- --
1-1100
- 5. 1.5 Vessel Penetrations -- --
V/T.(1) General
- 6. 1.6 Weld #16 154 -- --
1-4100
- 7. 1.6 Weld #16. 154 -- --
1-4200
- 8. 1.6 Weld #16 154 -- --
1-4300'
- 9. 1.6 Weld #16 154 -- --
1-4400
- 10. 1.15 Vetesl Interior -- --
88 1-1200
- 11. 1.17 core - Support Structures -- --
88 1-1200
- 12. 1.19 Exempt Components -- --
V/T (1) General I)
_ - - , _ , , . _ . - . . . .,,m. , , , . ._ - , - _ . . - - - _ , . - _ . , . .,._m,,.,_.-.r-.-_. -. --
s t -
COM PROGRAM IWB-2600 ITEM / AREA SUBJECT EXAMINATION SKETCH ITEM REFERENCE TO EXAMINATION U/T SURF V/T REFERENCE PIPING
- 13. 4.10 Items 530 and 531 -- -- 8 1-4800 PUMPS i
- 14. 5.2 Seal Housing Bolting 2-B1 U/T (1) M/T (1) u l-5100 t
Thru 2-B12; 4-B1 thru 4-B12 i() 15. 5.3 Seti Housing Bolting, 2-B1 V/T (1) 1-5100 Thru 2-B12; 3-81 thru 3-B12; 4-B1 thru 4-812 (1) Done by Station Personnel. - -
r i-4 4
I O
If)
- i ns S e #111 B C
- A O