ML20235F804
| ML20235F804 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 09/18/1987 |
| From: | Hunsader S COMMONWEALTH EDISON CO. |
| To: | Murley T Office of Nuclear Reactor Regulation |
| References | |
| 3592K, NUDOCS 8709290322 | |
| Download: ML20235F804 (4) | |
Text
. -_ - _____ _ _ _ _ _ _ _
CN Commonwealth Edloon -
I s} Ora First Nitional Plaza, Chicago, Illincie C#
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. Address Reply to: Fost Offica Box 767 n,
Chicago, Illinois 60690 0767 September 18, 1987 i
Mr. Thcaas E. Murley, Director office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission g
Washington, DC 20555
--s M [C Attn: Document Control Desk N
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Subject:
Braidwood Station Unit 1 Preservice Inspection'(PSI) Program y
3-NRC Docket No. 50-456 e
N Reference (a): September 10 1986 A.D. Miosi letter to
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H.R. Denton (b): NUREG-1002, Safety Evaluation Report, l
Supplement #2, dated October, 1986
Dear Mr. Murley:
Reference (a) provided Revision 1 of the Braidwood Unit 1 PSI Program Relief Request INR-ll. Relief had been requested for weld ELHXC-03 on the Excess Letdown Heat Exchanger (lCV-1AA) of the Chemical and Volume control System because a limited volumetric (ultrasonic) examination had been performed. Access to weld ELHXC-03 was restricted, due to four (4) branch connections welded to the vessel in close proximity.1 This relief request was evaluated by the NRC Staff and accepted, as noted in reference (b). The purpose of this letter is to correct the applicable component included in the relief request.
Per ASME Section XI, Section IWC-2500-1, Examination Category C-A, in the case of multiple vessels of a similar design, size, and service,.the examinations may be conducted on only one vessel or may be distributed among the total vessel population. Braidwood Station had chosen to examine only one vessel (heat exchanger ICV 01AB) as the subject coraponent.
Inadvertently, equipment number ICV 01AA was listed on Relief Request INR-ll.
Therefore, Revision'2 of the relief request provides the correct equipment number.
(see Attachment "A").
8709290322 870918 PDR ADDCK 05000456 PDR
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- T.E. Murley -
September 18, 1987.
I This change is administrative in nature and does not affect any ASME Section XI Code requirements or the justification for the' relief-request.
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This is being' submitted for NRC review. Please address any questions concerning this matter to this office.
Very truly yours,
'(
S. C. Hunsader Nuclear. Licensing Administrator i
cc:
S. Sands Braidwood Resident Inspector Region III Regional Administrator 1
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RELIEF REQUEST 1NR-11 1.
SYSTEM:
Chemical and Volume Control, Excess Letdown Heat Exchanger 2.
NUMBER OF ITEMS:
1 4
4 Component Number Weld Number ICV 01AB ELHXC-03 3.
ASME CODE SECTION XI REQUIREMENTS:
Table IWC-2500-1, i
Examination Category C-A, Item C1.10 requires volumetric examination of the regions described in Figure IWC-2520-1 for shell circumferential welds.
(
Mandatory Appendix III, Article III - 4000 requires examination for:
a.
Ref_ lectors parallel to the weld seam.
The angle beam examination for reflectors parallel to the weld seam shall be performed by a full V path from one side or a one-half V path from two sides of the weld, where practicable.
b.
Reflectors transverse to the weld seam.
1)
The angle beam examination for reflectors transverse to the wold seam shall be performed on the weld crown on a single seam path to examine the weld root by one-half V path in two directions along the weld.
2)
For inservice examination, only those welds showing reportable preservice indications need be examined for transverse reflectors.
5.
BASIS FOR RELIEF: Weld ELRXC-03 received radiographic examination to meet the requirements of ASME Section III.
These examinations could be used to meet the requirements of ASME Section II.
However, we do not intend to use radiography as our inservice test method.
0322m(091086) 0885A
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Ultrasonic examination of weld EtJDC-03 was limited for approximately 70% of the weld length due to four branch connections welded to the vessel.
6.
AE. TERNATE TEST METIOD:
In lieu of the required ultrasonic inspection a surface examination utilising the.11guld penetrant test will be performed on the above welds.
7.
JUSTIFICATION: The ASME Section III radiograph and hydrostatic test along with the limited ultrasonic examination and alternate surface examination will provide an adequate level of structural integrity for plant operation.
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4 0322m(040986) 0885A
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