ML20116F971
| ML20116F971 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 04/22/1985 |
| From: | Carey J DUQUESNE LIGHT CO. |
| To: | Starostecki R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| 2NRC-5-063, 2NRC-5-63, NUDOCS 8505010323 | |
| Download: ML20116F971 (4) | |
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'Af 412 787 5 1 (412) 923-1960 Nuclear Construction Division Telecopy (412) 787-2629 Robinson Plaza. Building 2, Suite 210 Pittsburgh, PA 15205 April 22, 1985 United States Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406 ATTENTION:
Mr. Richard W. Starostecki Division of Project and Resident Programs
SUBJECT:
Beaver Valley Power Station - Unit No. 2 Docket No. 50-412 USNRC IE Inspection Report No. 40-412/85-02
REFERENCE:
NRC Inspection Report 85-02 to Mr. E. J. Woolever dated March 22, 1985 Gentlemen:
This is in response to the Notice of Violations cited in Inspection No. 50-412/85-02 and listed in Appendix A (Notice of Violation) attached to your letter to Mr. E. J. Woolever, dated March 22, 1985.
A.
Notice of Violation 10CFR50, Appendix B,
Criterion V, requires that activities af fect ing quality shall be prescribed by procedures or drawings.
The Beave r Valley Power Station Unit 2 (BVPS-2) FSAR, Section 17.1, Quality Assurance during Design and Construction, which refers back to BVPS PSAR Section 17. 2.1. 5 A, Instructions, Procedures and Drawings, requires that activities af fecting quality shall be prescribed by documented procedures and drawings.
The BVPS-2 Field Cons truc t ion Procedure No. FCP-302 requires that an Assembly / Disassembly report be issued for authorized valve work.
Contrary to the above, on January 22, 1985, the installed valve VCW-150-x2 (V-115) on line 2-SIS-010-10-2 was found with loose nuts including one missing nut on the shaft seal plates.
The documentation fo r the valve has been signed of f by QC inspection as complete.
It was determined th at no Assembly / Disassembly Report was issued for the installation changes of shaft seal plate covera; thus, indicating unathorized or incomplete work had been accomplished.
Corrective Actions Nonconformance and Dispos ition (N&D) 7994 has been ge nerated for the subject valve and a replacement nut is now being obtained in accordance 8505010323 850422
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Unitcd Stctsa Nucisar Regulctory Commission Mr. Richcrd W. Stercatscki
~USNRC IE Inspection Report No. 50-412/85-02 Page 2 with ASME XI Code requirements.
Upon receipt, the nut will be installed and the tightness of all the shaf t seal nuts will be verified. This work
.is currently scheduled to be complete by July 1985.
In order to prevent any future occurrence of unauthorized rework the following has been done.
The mechanical and electrical contractors have been instructed to ensure that their personnel are thoroughly familiar and working' in compliance with the requirements of the site rework control program.
Failure to comply with the program will lead to disci-plinary action.
Duquesne Light Company's Architect Engineer, Stone and Webster, will provide manageme nt control to ensure adherence to the requirements of the rework control program.
5.
-10CFR50, Appendix B, criterion IX, requires nondestructive testing to be controlled and accomplished in accordance with applicable codes, stan-dards, specifications, criteria, and other special requirements.
~ The - drawing 883D683 for the Reactor Vessel Internals Energy Absorber Assembly requires penetrant inspection of the upper weld to quality level "B" defined in W PS 595139.
Quality Level "B" prohibits cracks or other linear indications. This component was fabricated and considered accept-able prior to shipment to the field for installation.
Contrary to the above, on January 24, 1985, the NRC initiated liquid penetrant inspection of this shop weld on component K468A02 disclosed linear indications exceeding the limits of Quality Level "B".
Corrective Actions Upon Notification of the Inspector's concern, a liquid penetrant examina-tion was performed in accordance with DLC's Procedure PT-10, revision date January 17, 1984.
The examination conducted according to this
-procedure was performed without acceptance or rejection criteria being applied since DLC's NDE Inspectors were not qualified for the W procedure quoted in the Inspector's report.
The results of this examTnation are shown on NDE Report #111465.
In summarf, within the 1-1/4" area of interest selected 'by the Ins pector, four (4) discontinuities were discovered, ranging in size from 1/32" to 3/16"; the 3/16" indication was g
blotched.
W, initiated Field Deficiency Report DMWM-Following this exmainat ion, l
10132 to document the event and to track any subsequent activities.
It was established that the equipment supplier was W Pensacola Division h
in Florida; and, following instructions, W researched their shop records and retrieved the original LP Inspection Instructions / Recording Form that identified the piece by serial number.
The report has evidence of the t,DE Inspector's stamp of acceptance, dated August 10, 1976.
a
U itcd Stctco Nuclect Rrgulctory Connaission Mr. Richcrd W..Stcrostccki USNRC IE Inspection Report No. 50-412/85-02 Page 3 During this investigation, it was further established that the procedure in use at the time was W Quality Inspection Procedure #8100, Revision 1.
A level III Examiner froIa the manufacturer attended the site and repeated the LP examination utilizing the referenced original procedure.
The examiner evaluated the results against ' that procedure and found them acceptable.
Following this examination, a light buffing was applied to the area of interest and the LP examination was repeated, with acceptable results.
The details of these inspections are described in W letters QE-85-030 and QE-85-031, respectively.
The associated documentation and the disposi-tioned W Field Deficiency Report are available - to the NRC Res ident Inspector for review at the site as required.
As noted in the Inspector's report, the original concern was obtained by -
. visual examination; and, in consequence, an informal visual exmalnation of the remaining three similar welds was performed by ~W personnel with no evidence of surf ace discontinuities.
Based - on this act ion, it is con-sidered that in addition to the LP examinations being evaluated as acceptable, this type of visual discontinuity was an isolated case.
DUQUESNE LIGHT COMPANY s
By
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J.J.
, rey
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Vice eside JS/wjs
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cc:
Mr. R. DeYoung, Director (3)
Mr. B. K. Singh, Project Manager Mr. G. Walton, NRC Resident Inspector INPO Records Center NRC Document Control Desk t
SUBSCRIBED AND S RN TO BEFORE ME THIS
<$438 DAY OF i[
, 1985.
$mA/O b
Notary Public ANITA ELAINE REITER, NOTARY P.UBLIC ROBINSON TOWNSHIP, ALLEGHENY COUNTY MY COMMISSION EXPIRES OCTOBER 20,1986 l
.:s Unitsd Stctc3 Nuciscr R2gulctcry Commissien Mr. Richcrd W. Stcrectscki USNRC IE Inspection Report No. 50-412/85-02
-Page 4 2
-COMMONWEALTH OF PENNSYLVANIA )
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SS:
COUNTY OF ALLEGHENY
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The Manage r, Regulatory Affairs, E.
F.
- Kurtz, Jr.,
being first duly sworn, deposes, and says:
that he is Manager, Regulatory Affairs, of Duquesne Light Company, with legal authority to sign of ficial correspondence on behalf of the Vice President, Nuclear Division, J. ~ J. Carey, in relation to licensing for Beaver Valley Power Station, Unit 2,
and is therefore authorized to submit the foregoing on behalf of the applicant, knowledge.
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Date
' Manage r,
~ ulatorpAfrfairs Sworn and subscJibed before me this
,7A J day of / fad
, 1985.
/
YA-LM Nolary Public ANITA ELAINE REITER, NOTARY PUBLIC ROBINSON TOWNSHIP, ALLEGHENY COUNTY MY COMMISSION EXPIRES OCTOBER 20,1986 3
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