ML20125D762
| ML20125D762 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 12/04/1992 |
| From: | Durr J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Opeka J NORTHEAST NUCLEAR ENERGY CO. |
| Shared Package | |
| ML20125D766 | List: |
| References | |
| NUDOCS 9212160021 | |
| Download: ML20125D762 (3) | |
See also: IR 05000336/1992026
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DEC 04 B32
Docket No. 50-336
Mr. John F. Opeka
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Executive Vice President - Nuclear
Northeast Nuclear Energy Company
P. O. Box 270
Hartford, Connecticut 06141-0270
Dear Mr. Opeka:
SUBJECT:
NRC INSPECTION OF UNIT 2 STEAM GENERATOR REPLACEMENT,
NRC REGION I INSPECTION REPORT NO. 50-336/92-26
This letter refers to several inspections conducted by Mr. Herbert Kaplan,
Mr. Suresh Chaudhary, Mr. Joseph Carrasco and other members of our staff between
August 30 and November 6,1992, at the Millstone Nuclear Power Station - Unit 2, in
Waterford, Connecticut. These inspections focused on activities related to the replacement of
the steam generators at Millstone Unit 2. At the conclusion of each inspection, our findings
were discussed with members of your staff. The objective of these inspections was to verify
that the replacement of the Unit 2 steam generators was conducted in a thorough, technically
sound manner, and in accordance with applicable industry codes 'and standards.
Areas examined during the inspections are described in the enclosed inspection report.
Within these areas, the inspections consisted of selected examinations of procedures,
representative records, interviews with personnel, and observations by the inspectors. The
steam generator replacement project is important to safety because the steam generator tubes
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and the connected reactor coolant system piping are one of the principal fission product
barriers. In general, the replacement steam generators welding met applicable industry code
and standard requirements. However, the initial analysis and evaluation of the reactor
coolant system piping movement appeared to be deficient. The preliminary results of the
improved stress analysis appear to be acceptable and indicate that the reactor coolant system
piping stresses are within code allowable limits. This item remains unresolved pending the
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review of the final reactor coolant system pipe stress analysis.
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9212160021 921204
DR
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DEC 041392
Mr. John F. Opeka
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Based on the results of this inspection, it appears that two of your activities were not
conducted in full compliance with NRC requirements, as set forth in the Notice of Violation,
enclosed herewith as Appendix A. Two violations were identified regarding the
nondestructive examination performed using radiography. The first violation is the failure to
identify and disposition a linear indication on the radiographic evaluation report. The second
violation is the failure to follow the radiography procedure regarding back scatter of radiation
during radiography. Your response to this notice should follow the instructions provided in
the Appendix.
Your cooperation with us in this matter is appreciated.
Sincerely,
origimi ste,c3 en
Jacque P. Detrn
Jacque P. Durr, Chief
Engineering Branch
Division of Reactor Safety
Enclosure: NRC Region I Inspection Report No. 50-336/92-26
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cc vi/ encl:
W. D. Romberg, Vice President - Nuclear, Operations Services
S. E. Scace, Nuclear Station Director
J. S. Keenan, Nuclear Unit Director
R, M. Kacich, Director, Nuclear Licensing
D. O. Nordquist, Director of Quality Services
Gerald Garfield, Esquire
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Nicholas Reynolds, Esquire
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K. Abraham, PAO (2)
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Public Document Room (PDR)
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Local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
State of Connecticut SLO Designee
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DEC0413E
Mr. John F. Opeka
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bec w/ encl:
Region I Docket Room ( vith concurrences)
DRS/EB SALP Coordinator
R. Blaugh, DRP
L. Doerflein, DRP
P. Swetland, SRI, Millstone
J. Raymond, SRI, Haddam Neck
R. Lobel, OEDO
R. Ihrkley, DRP
A. Lee, NRR/EMED
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OFFICIAL RECORD COPY
A:M1LL9226.JT
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