ML20211P960
| ML20211P960 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 02/20/1987 |
| From: | Bailey J WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20211P965 | List: |
| References | |
| ET-87-0064, ET-87-64, NUDOCS 8703020460 | |
| Download: ML20211P960 (15) | |
Text
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NUCLEAR OPERATING CORPORATION U. S. Nuclear Regulatory Comission February 20, 1987 ATTN: Document Control Desk washington, D. C.
20555
[etter: ET 87-0064 Re:
Docket No. 50-482 Subj:
Inservice Inspection Progr.cun for Wolf Creek Generating Station Ref:
1)
Letter KMLNRC 85-268 dated 12/11/85 from GLKoester, KG&E to HRDenton, lEC 2)
[etter dated 8/15/86 from PW0'Connor, NRC, to GLKoester, KG&E Gentlemen:
We attachments to this letter are being provided per discussions with the staff in January 1987.
Provided in attachment 1 are relief requests to the Wolf Creek Generating Station Inservice Inspection Program which have been revised to provide additional clarifying information.
Wese relief requests were previously supplied as enclosures C, F,
G, H and L to Referenc.e 1.
Relief Requests provided in enclosures D and E to Reference 1 are being withdrawn at this time for further evaluation.
A copy of the supplemental examination program for the Refueling Water Storage System and Containment Spray System is provided in attachment 2.
A copy of this letter is being provided to Mr. Boyd Brown of EG&G, Idaho per the staff's request.
If you have any questions concerning this subnittal, please contact me or Mr. O. L. Maynard of my staff.
Very truly yours,
% fo g y $[hh 2
John A. Bailey o
Vice-President Engineering and Technical Services JAB:jad Attachments cc: P0'Connor (2)
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PO Dox 411/ Buritngton, KS M839 ' Phone:(310) 3M 8831 An Equal OppermMy Emptoyer M F HC VET l
- to Er 87-0064 February 20, 1987 RELIEF REGJESTS 9
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- to ET 87-0064-
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..l February 20, 1987 DiCLOSURE C Systen: Reactor Coolant Category: C-F Camponent
Description:
4 Component Description Reactor Coolant Pump D Seal Canponent Identification Water Injection Line Welds 1-BG-09-W790 2" x 1 1/2" Reducer to 1 1/2" pipe 1-BG-09-PW879 1 1/2" Pipe to Valve 1-BG-09-PW880 Valve to 1 1/2" Pipe 1-BG-09-W859 1 1/2" Pipe to 2" x 1 1/2" Reducer 4
Reactor Coolant Pump A Seal Water Injection Line Welds 1-BG49-W686 2" x 1 1/2" Reducer to 1 1/2" Pipe 1-BG-09-PW881 1 1/2" Pipe to Valve 1-BG49-PW882 Valve to 1 1/2" Pipe 1-BG-09-W779 1 1/2" Pipe to 2" X 1 1/2" Reducer Reactor Coolant P R C
+
Seal Water Injection Line Welds 1-BG-09-W806 2" x 1 1/2" Reducer to 1 1/2" Pipe 1-N A 9-PW877 1 1/2" Pipe to Valve 1-BG-09-PW878 Valve to 1 1/2" Pipe 1-BG49-W807 1 1/2" Pipe to 2" X 1 1/2" Reducer Reactor Coolant Puttp B Seal Water Injection Line Welds I
l-BG49-W814 2" X 1 1/2" Reducer to 1 1/2" Pipe i
1-BG-09-PW875 1 1/2" Pipe to Valve 1-BG49-PW876 Valve to 1 1/2" Pipe 1-BG-09-W696 1 1/2" Pipe to 2" X 1 1/2" Reducer -
Code Requirenents: Voltanetric examination of these welds not required by Code.
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Examination Requirenent: Voltanetric examination of these welds is required by adoption of the augmented,exanination requirenents of NUREG 0800. 100% of the pressure retaining welds in piping i
greater than 1" NPS, designated for augmented inspection, as reflected by Figure 3.6-1, Sheet 1 of the FSAR shall be subject to voltanetric (buttwelds) or surface (socket welds) exanination.
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_ to ET 87-0064 February 20, 1987~
ENCLOSURE C Areas _for Relief:.Voltanetric exanination of piping welds.
Basis for Relief: Canbination of anall pipe diameter and minim'Jn wall thickness cause voltanetric exanination to be meaningless.
Alternate Testing: Penetrant Testing.
ASME Code Section III Examinations: Voltanetric and surface exaninations as well as pressure tests in accordance with Section III.(and Section XI).
Evaluation of Plant Safety: No impact to plant safety is expected. The surface exaninations proposed, as alternate testing, cambined with the required pressure testing and the capability to makeup for any losses due to a break in one of these lines assures an adequate level of safety.
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Attachment I to ET 87-0064 February 20. 1987 ENCIDSURE F Systan: Pressurizer Description Code Requirenent Basis for Relief Conponent I.D.
Category 1-TBB83-4-W B-F Relief Nozzle to Volumetric examination Component undulations restricting search Safe-end Weld by scanning both sides unit movement and metal structure of of weld, inconell buttering inhibiting shear wave transmission. 20% loss of volume I
coverage with a 60' axial scan and a 45 loss of volume coverage with a 4f axial' scan.
1 'IBB03-3-A-W B-F Safety Nozzle to Volumetric examination Congonent undulations restricting search Safe-end Weld by scanning both sides unit movement and metal structure of.
of weld.
inconell buttering inhibiting shear wave-transmission. 50% loss of volume coverage with a 60 axial scan and a 35%
loss of voltane coverage with a 45 axial scan.
1-TBB03-1-W B-F Surge Nozzle to Volumetric exanination Conponent undulations restricting search Safe-end Weld by scanning both sides unit movement and metal structure of of weld.
inconell buttering inhibiting shear wave transmission. 15% loss of voltane coverage with a 60 axial scan and a 40%
loss of volume coverage with a 45' axial scan.
1 'IBB03-3-B-W B-F Safety Nozzle to Voltanetric examination Component undulations restricting search Safe-end Weld by scanning both sides unit movement and metal structure of of weld.
inconell buttering inhibiting shear wave transmission. 55% loss of volume coverage with a 69 axial scan ang a 49%
loss of volume coverage with a 45 axial scan.
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Attachment I to ET 87-0064 I
Februaryl20. 1987 1 "IBB03-2-W B-F Spray Nozzlo to Voltanei.ric examination Canponent undul;tiona restricting search Safe-end Weld by scanning both sides unit m.o..ent and metal structure of of weld.
inconell buttering inhibiting shear wave transmission. 10% loss of volume coverage with a 60* axial scan and a 40%.
loss of volume coverage with a 45* axial scan.
1-TBB-03-3-C-W B-F Safety Nozzle Volumetric eraination Component undulations restricting search to Safe-end Weld by scanning both sides unit movenent and metal structure of of weld.
inconell buttering inhibiting shear wave transmission. 20% loss of volume coverage with a 60* axial scan and a 40%
loss of volume coverage with a 45* axial scan.
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l ET to 87-0064 February 20. 1987 ENCLOSURE F Alternative Examinations: No alternate exams proposed.
ASME CodesSection III Examinations: Volumetric and surface examinations as well as pressure tests in accordance with Section III (and Section XI).
Evaluation of Plant Safety: Sufficient examinable volume remains combined with the ASME Code Section XI surface examinations and pressure testing to assure adequate safety.
Note 1: Conponent undulations are defined as skips in the Ultrasonic Examination signal transmitted versus received resulting from: 1) an uneven surface condition,
- 2) a bimetallic (carbon to stainless steel) weld joint with Inconel weld buttering, and 3) transitioning pipe wall thicknesses from one side of the weld to the other.
Exanple sketch for 1-TBB03-3-B-W is provided.
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o Attachment I to ET 87-0064 W.1d No:
1-TBB03-3-B-V F,ebruar.y 20, 1987 ENCLO5URE F
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/f to ET 87-0064 February 20, 1987 T
ENCLOSURE G RELIEF REQUSST POR 'INE VOLUMETRIC SERVICE INSPECTION WOLF CREEK REACIOR COOLANT SYSTEM BRANCH C0tt4BCTIONS I.
ASME CODE SECTION XI REQUIREMENFS In Section XI,1980 EditionAfintel 1981 Addenda, Table im 2500-1, exanination Category BJ, item B9.31 requires a surface and volunetric examination of regions described in Figure IW2500-ll, for branch connection piping 4" naninal pipe size and greater. However, the above code does not define the specific weld volane required to be exanined. To address this lack of definition, Figure IW2500-8 was used as a guideline to define the exanination volane of the branch connection welds.
Figure 01 corresponds to Figure IW2500-8 of the Code and Figure 03 corresponds to Figure Ih2500-11 with the modifications as stated above. The inservice inspection exaninations will be performed to ultrasonically examine the defined volunes in Figure 03.
II.
SPECIFIC RELIEF REQUE9F Relief is requested fram performing the Category BJ (Note (1)(d)) volumetric exaninations of 2 branch connection welds on the primary loops of the Reactor Coolant Systen. 'the l
welds are identified in Table I along with identification of l
the type of weld (referring to the weld configuration in the i
attached figures). Branch connections for the accum21ator j
discharge lines are butt welded to the reactor coolant loop piping and are not included in this relief request. All eight (8) branch connections to the reactor coolant loop i
piping are covered by this relief request, with the exception of the accumulator discharge lines as noted above.
I III. BASIS FOR RELIEF j.
Due to thematerials of construction (austenitic) and the design and fabrication geanetry of corner type branch i
l connections depicted in attached Figure 03, it is concluded i
that meaningful exanination by ultrasonic methods is not feasible and that no other practical volumetric method is
- available.
IV.
ALTERNATE TEST ME'! HOD As an alternative, 42 examinations for leakage will be con $ucted in accordance with IW5240. These will be carried out during the leakage test specified under Im 5221. The combination of exaninable volune, surface examination and proposed visual exanination for leakage will establish the continued integrity of the pressure boundary.
Attachment I to ET 87-0064 February 20, 1987 ENCLOSURE G (contd)
TABt,E 1 BRANCH CONNBCTION WELDS i
VOLUME Itan W Weld 3 KGE Weld 3 Size UNEXAMINABLE TYPE OF WEID 1
15 IBB-41 S302-3 6"
55%
Figure 03 2
15 1BB-01 S402-3 14" 10%
Figure 03 V.
ASME Code Section III Examinations Voltznetric and surface examinations as well as pressure
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tests in accordance with Section III (and Section XI).
VI.
Evaluation of Plant Safety Given the Alternate Test Methods no impact to plant safety is anticipated.
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. to ET 87-0064 February 20, 1987 I
ENCLOSUREG(contd)
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WEFT 1NGHOUSE ELYCTRIC CORPOR ATION F I G U R E O.1 zu.ummn om nrzum-wu i i
SIMILAR AND DISSIMILAR METAL I
WELDS. IN PIPING
A-4 Up PROFILE OF VALVE BODY,
[ PUMP CONNECTION
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VESSEL NO22LE OR A,,
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INNER SURFACE k
NDM. PIPE SIZE LESS THAN 4 IN.
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St.RF. EXAM. AREA _
A-B PROFILE OF VALVE 80DY, f VE5SEL N022LE. OR 8.l. gp PUMP CONNECTION s-1 p/,
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Attachment I to ET 87-0064 February 20, 1987 ENCLOSURE G (contd)
WESTINGHOUSE ELECTRIC CORPOR ATION t
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PIPE BRANCH CONNECTION t
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AttachmentI 1 to ET 87 d(554 a
1 February 20, 1987
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Ef3 CLOSURE G (contd)
WESilNGHOUSE ELECTRIC CORPOR ATION
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Attachment '1 to ET 87-0064 February 20, 1987 ENCLOSURE H System: Reactor Pressure Vessel Category:
B-A Ccanponent
Description:
Flange to Vessel Weld, (I.D. #1-RV-101-121)
Code Requirement: 100% Voltanetric Examination Areas for Relief: 25% of Weld Voltano Basis for Relief: Parallel scan portion of exanination can only be done from lower side due to presence of flange taper above the weld.
Alternate Testing: None ASME Code Section III Examinations: Volunetric and surface examinations as well as pressure tests in accordance with Section III (and Section XI).
Evaluation of Plant Safety: Sufficient voltane renains examinable to provide assurance of plant safety.
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Att'achment 1 to ET 87-0064 February 20,'.1987 DKIDSURE L Systen: Reactor Pressure Vessel Category:
B-A Canponent
Description:
Meridional Welds in Lower Head (I.D. 91-W-101-154A)
(I.D. #1-RV-101-154B)
(I.D. #1-W-101-154C)
(I.D. 41-RV-101-154D)
Code Requirenent: 100% Voltanetric Examination Areas for Relief: Weld Number Percentage Requesting Relief 1-RV-101-154-A 22%
l-RV-101-154-B 27%
l-W-101-154-C 12%
l-RV-101-154-D 14%
Basis for Relief: Weld geanutry and O.D. surface condition limit ultrasonic head contact.
Alternate Testing: None ASME Code Section III Examinations: Voltanetric and surface exaninations as well as pressure tests in accordance with Section r
III (and Section XI).
Evaluation of Plant Safety: Sufficient voltane renains examinable.
to provide assurance of plant safety.
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