ML20133J107
| ML20133J107 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 10/15/1985 |
| From: | Copeland V COMMONWEALTH EDISON CO., ISHAM, LINCOLN & BEALE |
| To: | Brenner L, Callihan A, Cole R, Grossman H Atomic Safety and Licensing Board Panel |
| References | |
| CON-#485-815 ALAB-143, OL, NUDOCS 8510180268 | |
| Download: ML20133J107 (7) | |
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ISHAM, LINCOLN & BEALE COUNSELORS AT LAW 00[MEI[O USMC l
THRE E FIRST NATONAL PLA Z A
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=3 =2 C^N Msww? m October 15, 1985 Herbert Grossman, Esq., Chairman Lawrence Brenner, Esquire Administrative Law Judge Administrative Law Judge Atomic Safety and Licensing Atomic Safety and Licensing Board Board U.S. Nuclear Regulatory U.S. Nuclear Regulatory L
Commission Commission Washington, D.C.
20555 Washington, D.C.
20555 Dr. A. Dixon Callihan Dr. Richard F. Cole Administrative Law Judge Administrative Law Judge 102 Oak Lane Atomic Safety and Licensing Oak Ridge, TN 37830 Board U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Re:
In the Matter of Commonwealth Edison Company (Braidwood Station, Units 1 and 2, Docket Nos. 50-456 and 50-457) D / _
Dear Administrative Judges:
In accordance with the disclosure requirements of the McGuire decision, Duke Power Co. (William B. McGuire Nuclear Station, Units 1 & 2) ALAB-143, 6 AEC 623 (1973), Commonwealth Edison company hereby serves on the Licensing Board and the parties the following enclosed documents:
1.
Letter dated September 9, 1985 from A. D. Miosi to James G. Keppler, with attachment, regarding disposition of Nonconformance Reports concerning deficiencies in the residual heat removal and containment spray pump base installations at Braidwood Station.
This information may be relevant to the QA Contention, item 6.D.
2.
Letter dated September 25, 1985 from L. O. DelGeorge to James G. Keppler, with attach-i ment, regarding Commonwealth Edison's supplemental 8510180268 851015 PDR ADOCK 05000456 3So3
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Administrative Judges
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October-15, 1985 Page 2 response to an' inspection report concerning random inspections of dimensions of piping components.
This information may be relevant-to the QA Contention, item 6.B.
Very truly yours, YW
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Victor G. Copeland One of the Attorneys for Commonwealth Edison Company VGC/mg cc:
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Addrsss RIply to P:st Othee Box 767 j
CNeago. Illinois 60690 s
September 9, 1985 Mr. James G. Keppler Regional Administrator Region III U. S. Nuclear Regulatory Commission 799 Roosevelt Road
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Glen Ellyn, Il 60137 e
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SUBJECT:
Braidwood Station Units 1 and 2 Supplemental Response to Inspection Reports Nos.
50-456/85-007 and 50-457/85-007 NRC Docket Nos. 50-456 and 50-457
REFERENCE:
(a) R. F. Warnick letter to C. Reed dated April 4, 1985 (b) D. L. Farrar letter to J. G. Keppler dated May 3, 1985
Dear Mr. Keppler:
The Reference (a) Inspection Report cited a deficiency in the containment spray pump base installation at Braidwood Station.
Commonwealth Edison's response, Reference (b), stated that upon disposition of the Nonconformance Reports issued on this deficiency, a supplemental report would be issued.
The enclosure to this, letter supplements our Reference (b) response.
If you have any further questions on this matter, please direct them to this office.
t Very truly yours, hkhNh]
A. D. Miosi' Nuclear Licensing Administrator Commonwealth Edison
/klj Enclosure Braidwood cc:
NRC Resident' Inspector 0620K l
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o Supplemental Response to Inspection Report 456/85-007 and 457/85-007 Item 456/85-007-02 and 457/85-007-02 Response - violation Part b Phillips-Getschow Nonconformance Reports 3961 and 3963 were issued to document deficiencies in the residual heat removal and containment spray pumps base installations.
These Nonconformance Reports have been reviewed and dispositioned.
These installations will De reworked to conform with design documents.
The Unit 1 pumps are expected to be reworked by January, 1986 and the Unit 2 pumps prior to the Unit 2 fuel load.
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e September 25, 1985 Mr. James G. Keppler Regional Administrator Region III U. S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Il 60137
SUBJECT:
Braidwood Station Units 1 and 2 Supplemental Response to Inspection Reports Nos.
50-456/83-09 and 50-457/84-83-09 NRC Docket Nos. 50-456 and 50-457
REFERENCE:
a.
J. G. Keppler letter to J. J. O'Connor dated May 7, 1984 b.
L. O. DelGeorge letter to J. G. Keppler dated July 6, 1984 c.
E. D. Swartz letter to J. G. Keppler dated July 20, 1984 d.
D. H. Smith letter to J. G. Keppler dated September 18, 1984 e.
D. H. Smith letter to J. G. Keppler dated November 2, 1984 f.
D. H. Smith letter to J. G. Keppler dated December 13, 1984 g.
D. H. Smith letter to J. G. Keppler dated February 27, 1985 h.
A. D. Miosi letter to J. G. Keppler dated May 2, 1985
Dear Mr. Keppler:
This letter supplements our Reference (b) response to the Reference (a)
Inspection Report. A re-review of data relevant to Notice of Violation Item 2.b disclosed new information. The enclosure to this letter provides a supplemental response to Violation Item 2.b and explains this new information.
i If you have any further questions on this matter, please direct them to this office.
Very truly yours, 6i L. O. DelGeorge Assistant Vice President l
l Enclosure cc: NRC Resident Inspector - Braidwood (03241)
ENCLOSURE COPmONWEALTH EDISON COMPANY SUPPLEMENTAL RESPONSE TO INSPECTION REPORT 456/83-09 and 457/83-09 ITEM 456/83-09-02B and 457/83-09-02B VIOLATION 2.b 2.
10 CPR 50 Appendix, B, Criterion V, as implemented by the rn==nnwealth Edison Company Quality Assurance Manual, QR No. 5.0, requires, in part, that activities affecting quality be prescribed by documented
- instructions, procedures or drawings, and shall be accomplished in accordance with these instructions, procedures, or drawings.
b.
Commonwealth Edison Quality Assurance Manual, Revision 77, Q.P. No.
7-1 " Control of Procured Material and Equipment Receiving and Inspection," Section 5.2.1.5.7, " Dimensional," requires visual checks be performed on a random bacis to assure that interface dimensions conform to drawings and/or specifications.
Contrary to the above, random visual checks of interface dimensions of piping components were not being done.
SUPPLEMENTAL RESPONSE In response to the Reference (a) Inspection Report Commonwealth Edison committed to perform a wall thickness inspection of 10% of the pipe material in stock. This inspection was performed by Phillips-Getschow company. Phillips-Getschow QC inspectors performed and documented the
' inspections and results, reviewed the inspection results and compared them to wall thickness requirements. This review showed that all items appeared to be acceptable. Since the inspection performed by Phillips-Getschow was not a standard QC inspection, with specific forms l
and signoffs, the review of the inspection results was not documented.
l Coaunonwealth Edison, in its Reference (b) response reported that all items checked were found to meet minimum wall thickness acceptance criteria.
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In August 1985, during preparations for upcoming licensing hearings, Phillips-Cetschow personnel again reviewed this issue. Since no documented evidence of the QC review of the 1983 10% wall thickness inspections was available, a re-evaluation of the sample inspection results was necessary. Phillips-Getschow undertook a re-review of these inspection results. As indicated on page 2 of Ceaumonwealth Edison's Response to Specific Interrogatory 45 included in Applicant's Fourth Partial Response to Rorea's First Set of Quality Assurance Interrogatories, two pieces of pipe from the sample were determined to have measured wall thicknesses less than the manufacturer's specification.
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(1) 2-inch Schedule 160 SA106 Gr B Heat 273088 Manufacured by ARMCO Tubular Commonwealth Edison Purchase Order 207003 Five pieces of this heat were measured with one piece found less than minimum wall.
Nominal Wall
.344 inch Minimum Wall (87.5%)
.301 inch Measured Wall (1 pc.)
.291 to.360 inch (2) 2-inch Schedule 40 SA313 type 304 Heat 462773 Manufactured by Sandvick r' w alth Edison Purchase Order 207003 Thirteen pieces of this heat were measured with one piece found less than minimum wall.
Nominal Wall
.154 inch Minimum Wall (87.5%)
.135 inch Measured Wall (1 pc.)
.128 to.137 inch Both items were supplied to Commonwealth Edison by Guyon Alloys.
Item 1 above was documented on Phillips-Getschow NCR 5317 usted August 9, 1985. Additionally, this item is included under the scope of r
Commonwealth Edison NCR 633 Rev. I and 10CFR 50.55(e) Report 84-10.
Disposition of this item will be in accordance with actions identified in l
10 CFR 50.55(e) Report 84-10 (Reference c through h).
' Item 2 above was documented on Phillips-Getschow NCR 5318 dated August 8, 1985. Commonwealth Edison and Phillips-Getschow are evaluating the available material to verify the 1983 measurements. Further actions will be determined based on this verification.
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Commonwealth Edison received the Phillips-Getschow NCR's 5317 and 5318 on Friday, September 13, 1985 and notified Guyon Alloys of the potential i
problem on Tuesday, September 17, 1985.
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