ML20148C143
| ML20148C143 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 05/07/1997 |
| From: | Keimig R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Danni Smith PECO CONTROLS CORP. |
| Shared Package | |
| ML20148C149 | List: |
| References | |
| 50-352-97-01, 50-352-97-1, 50-353-97-01, 50-353-97-1, NUDOCS 9705150124 | |
| Download: ML20148C143 (3) | |
See also: IR 05000352/1997001
Text
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May 7, 1997
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Mr. D. M. Smith, President
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PECO Nuclear
Nuclear Group Headquarters
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Correspondence Control Desk
P. O. Box 195
Wayne, PA 19087-0195
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SUBJECT:
NRC INTEGRATED INSPECTION REPORT 50-352/97-01, 50-353/97-01;
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Dear Mr. Smith:
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On February 4,1997 through March 29,1997 the NRC completed inspections at your
Limerick 1 & 2 reactor facilities. The enclosed report presents the results of those
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. inspections.
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During the 8-week period covered by this inspection, the conduct of activities at the
Limerick 1 & 2 facilities was generally characterized by safe and conservative operations
and decision making. Several conservative decisions associated with the Unit 2 refueling
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outage were made, which appropriately resulted in the expansion of the scope of the
outage. The bases for those decisions were to ensure component reliability and quality,
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and demonstrated that there was no unreasonable schedule pressure. Maintenance
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performed at both units appeared to be of high quality.
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. Several region-based reviews of your programs occurred during the period, including the
applied radiological controls program for the Unit 2 outage and the Inservice Inspection
(ISI) program and fire protection. The inspectors concluded that effective applied
radiological controls were established and implemented for the Unit 2 outage. The ALARA-
controls for ongoing work activities were also found to be effective. However, some
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indications of lax worker attention to radiation protection procedures were noted.
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The implementation of the ISI program at the Limerick Generating Station was found to
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meet the requirements of the American Society of Mechanical Engineers (ASME) Boiler and
Pressure Vessel Code,1986 Edition. Currently, the ISI program is on schedule and all
examinations are scheduled to be completed by the end of the first ten-year interval.
Two instances of poor management oversight of vendor activities were noted during the /
Unit 2 refueling outage. The inspector expressed concern to PECO management after
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observing several poorly controlled nondestructive examination activities. The inspectors
witnessed surface exams being performed with weak controls and under unfavorable
conditions. Upon further investigation, it was discovered that there was no requirement or
' formal program in place for PECO personnel to oversee the vendor Nondestructive
Examination (NDE) activities as performed in the field or to perform over-checks (re-
performance of the examinations) of the field exams. While the PECO Level lli NDE .
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9705150124 970507
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Mr. D. M. Smith
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inspector does review ten percent of data from the field, this may not preclude identifying
poorly performed exams in the field. As a result of the inspector's concerns, PECO is
evaluating the effectiveness of its NDE oversight program.
The second occurrence involved vendor inspection of spent reactor fuel and resulted in a
violation. The violation ic cited in the enclosed Notice of Violation (Notice) and the
circumstances surrounding it are described in detail in the subject inspection report. The
violation concerns an instance where a modification was made to the Unit 2 fuel
preparation machines that made the information in the Updated Final Safety Analysis
Report (UFSAR) incomplete in that a test fixture was added, causing two spent fuel
assemblies to be raised closer to the water surface pool than allowed by the UFSAR. The
modification was not evaluated to determine if it would make information in the SAR
inaccurate or incomplete. The violation is of concern because this was another example of
inadequate oversight and review of a vendor activity. You are required to respond to this
letter and should follow the instructions specified in the enclosed Notice when preparing
your response.
The fire protection program was found to be satisfactory. We noted a lack of good fire
protection program oversight. Weaknesses were noted in the control of hotwork activities
However, some good initiatives have been taken recently to improve the effectiveness of
this program.
In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter,
its enclosure (s), and your response will be placed in the NRC Public Document Room
(PDR).
Sincerely,
ORIGINAL' SIGNED BY:
Richard R. Keimig, Chief
Projects Branch 4
Division of Reactor Projects
Docket Nos.: 50-352, 50-353
Enclosures:
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2.
Inspection Report 50-352/97-01, 50-353/97-01
cc w/ encl:
G. A. Hunger, Jr., Chairman, Nuclear Review Board and Director - Licensing
W. MacFarland, Vice President - Limerick Generating Station
J. L. Kantner, Regulatory Engineer - Limerick Generating Station
Secretary, Nuclear Committee of the Board
Nuclear Safety Information Center (NSIC)
Commonwealth of Pennsylvania
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Mr. D. M. Smith
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Distribution w/ encl:
Region ! Docket Room (with concurrences)
K. Gallagher, DRP
D. Screnci, PAO (1)
NRC Resident inspector
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PUBLIC
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Distribution w/ encl: (Via E-Mail)
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W. Dean, OEDO
F. Rinaldi, NRR
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J. Stolz, PDl-2, NRR
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inspection Program Branch, NRR (IPAS)
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DOCUMENT NAME: g:\\ branch 4\\9701. lim
To receive e copy of this document. Indicate in the boa: "C" = Copy without ottachment/ enclosure
"E" = Copy with attachment / enclosure
"N" = No copy
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