ML20005B250
| ML20005B250 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 05/13/1981 |
| From: | Keimig R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20005B249 | List: |
| References | |
| 50-354-81-04, 50-354-81-4, NUDOCS 8107070015 | |
| Download: ML20005B250 (2) | |
Text
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, APPENDIX A IJTICE OF VIOLATION Public Service Electric and Gas Company Docket No. 50-354 Hope Creek Unit 1 License No. CPPR-120 As a result of the inspection conducted on March 2 - April 5,1981 and in accordance with Interim Enforcement Policy 45 FR 66754 (October 7,1980),
the following violations were identified:
I.
10 CFR 50, Appendix B, Criterion IX states, in part, that:
...special processes, including welding shall be controlled and accomplished...
using qualified procedures in accordance with applicable codes, standards, specifications, criteria, and other special requirements."
Section 16.2.9 of Chapter 16 of the PSAR states, in part, that:
"The NSSS Contractor and Architect-Engineer shall establish controls over special reocesses such as welding... These controls shall assure that the proceaures... are duly qualified in accordance with applicable codes, standards..."
Paragraph 10.2 of the Technical Specification for Reactor Pressure Vessel Internals Installation states, in part, that:
"All welding procedures and performance qualification tests shall be performed in accordance with Section IX of the ASME Code..."
Paragraph QW 201.1 of ASME Section IX requires that the weld procedure specification (WPS) list in detail for each process the essential and nonessential variables.
Contrary to the above, as of April 3,1981, GEI&SE WPS HC 5001D, Rev.1, t
which had been reviewed and approved by GEI&SE, GENED, and Bechtel, was in effect for in process production welding and failed to list in detail t
four nonessential variables and stated a thickness range qualification l
for the SMAW process that was in excess of that qualified by the pro-cedure qualification record.
This is a Severity Level VI Violation (Supplement II).
l II.
10 CFR 50, Appendix B, Criterion V, states, in part, that:
" Activities affecting quality shall be prescribed by documented instructions, pro-l cedures, or drawings... and shall be accomplished in accordance with these instructions, procedures, or drawings."
Section 16.4.5 of Chapter 16 of the PSAR states, in part, that:
... qual i ty l
related activities are documented and controlled by written procedures l
and instructions."
l Paragraph 13.2 of the Technical Specification for Reactor Vessel Internals Installation states, in part, that:
" Test and examination procedures and I
standards for acceptance shall be in accordance with these specifications l
and applicable codes and standards." Additionally, Paragraph 4.1 of this technical specification states, in part, that:
"All materials, fabrica-tion, examination, testing...shall be in accordance with the latest issue of the AS!!E Boiler and Pressure Vessel Code..."
8107070016 81051 PDR ADOCK 0:2000 4
O P,
Appendix A 2
GEI&SE radiography procedure 18XA9603, Rev. 2 states in Paragraph 6.6.2 that the penetrameter shall be placed on the weld metal when the weld metal is not radiographically similar to the base material.
ASME Section V Article 22, SE-142, Standard Method for Controlling Quality of Radiographic Testing, states in Appendix Al that carbon steel and inconel are not radiographically similar.
Contrary to the above, as of April 3,1981, penistrameter placement for radio-graphy of the welder mockup qualification for the jet pump adapter to shroud support plate weld (carbon steel base metal with inconel filler) was not in accordance with procedure 18XA9603 requirements.
This is a Severity Level V Violation (Supplement II).
Pursuant to the provisions of 10 CFR 2.201, Public Service Electric and Gas Company is hereby required to submit to this office within twenty-five days of the date of this Notice, a written statement or explanation in reply, including:
(1)thecor-rective steps which have been taken and the results achieved; (2) corrective steps which will be taken to avoid further violation; and, (3) the date when full compli-ance will be achieved. Under the authority of Section 182 of the Atomic Energy Act of 1954, as amended, this response shall be submitted under oath or affirmation.
h'AY 131981 Dated
'u:^f
- f. R. Keimi, Chi
/ProjectsBanch 2
Division f Resi nt and Project Inspection
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