ML20043H960
| ML20043H960 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/15/1990 |
| From: | Wenzinger E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Hukill H GENERAL PUBLIC UTILITIES CORP. |
| Shared Package | |
| ML20043H961 | List: |
| References | |
| NUDOCS 9006270132 | |
| Download: ML20043H960 (3) | |
See also: IR 05000289/1990008
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NN251000
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Docket No. 50-289
GPU Nuclear Corporatior.-
ATTN: Mr. H. D. Hukill
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Vice President and Director, THI-1
P. O. Box 480
-Middletown, Pennsylvania 17057
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Gentlemen:
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Subject:
Inspection Report No. 50-289/90-08
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During the-period from April 4, 1990 to May 15, 1990, members of the NRC
Region I staff conducted routine safety inspections at your facility. We have
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documented the results of those inspection findings.in the enclosed report.
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We continue to observe good overall control over operational activities by
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your staff, At the conclusion 'of the-inspectlon period, Mr. F. Young, of my
staff, sommarized the inspection findings to you and other members of your
staff.
Your cooperation in these matters is appreciated.
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Sincerely,
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0.T;lf/LslenE0ny
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EDWARD C. WEtatiGER
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Edward C. Wenzinger, Chief
Projects Branch No. 4
Division of Reactor Projects-
Enclosures:
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1.
Exec tive Summary
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2. .Inspes .lon Report.50-289/90-08
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cc w/encis:
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E. L. Blake, Jr. , Esquire
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T. G. Broughton, Operations and Maintenance Director THI-1
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R. J. McGoey, Manager, PWR Licensing
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C. W. Smyth, TMI-1 Licensing Manager
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Commonwealth of Pennsylvania
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Local Public Document Room (LPDR)
NRC Resident Inspector
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Nuclear Safety Information Center (NSIC)
Public Document Room (PDR)
Susquehanna Valley Alliance
TMI Alert
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OFFICIAL RECORD COPY
IR TMll 90-08 - 0001.0.0
9006270132 900615
11/29/80
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GPU Nuclear Corporation
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bec w/ enc 1:
Region I Docket Room (with concurrences)
Management Assistant, DRMA (w/o enc 1)
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R. Bellamy, DRSS
DRP Section Chief
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K. Abraham,PA0(2)
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J. Caldwell, NRR
E. Wenzinger, DRP Branch Chief, RI
R. He.3an, PM, NRR/PD1-4
F. Young, SRI
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0.' Johnson, RI
L. Thonus, NRR/PD1-4
W. Kane, DRP, RI (cover letter and enclosure 1 only)
J. Wiggins, DRP, RI (cover letter and enclosure 1 only)
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M. Hodges, DRS (cover letter and enclosure 1 only)
M. Knapp, DRSS (cover letter and enclosure 1 only)
E. Jordan, AEOD
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0FFICIAL RECORD COPY
IR TMll 90-08 - 0002.0.0
11/29/80
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Executive Summary
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1.
PLANT OPERATIONS
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The plant ran at 95% power for the duration of the inspection period.
Problems with communications between. site chemistry and operations and log
keeping practices were demonstrated when a technical specification (TS)
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required sampler was removed from service without operations being made
aware. The main r:ondenser vent continuous iodine sampler was out of
service for 42 hours4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br />; the maximum allowed by TS is 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
Review of
the circumstances found the issue to be an isolated case. The licensee
adequately defined the problem and proposed and implemented adequate cor-
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rective actions. Overall, plant operations continue to be conducted in a
safe manner.
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II.
RADIOLOGICAL CONTROLS
Routine observations of radiological controls were conducted throughout
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the inspection period.
No significant weaknesses were noted.
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III. MAINTENANCE / SURVEILLANCE
The licensee continues to conduct maintenance and surveillance activities
in a safe and timely fashion. No deficiencies in the program or in speci-
fic activities were noted.-
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ENGINEERING AND TECHNICAL SUPPORT
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A review of the annual 10 CFR 50.59 report dated April 26, 1990, found the
document to fulfill the requirements of 10 CFR 50.59 for yearly reporting
of changes and modifications. A review of the nuclear engineers' 8R start-
up report verified that all core performance parameters were within their
acceptance criteria and that the-technical specification requirements were
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satisfied.
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V.
EMERGENCY PREPAr.CDinSS (EP)
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No weaknesses were identified,
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VI, SECURITY
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One reportable event caused by perannel error occurred during this
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inspection period.
The licensee took appropriate compensatory measures
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and adequate corrective action.
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VII. SAFETY ASSESSMENT AND QUALITY VERIFICATION
Licensee Event Reports (LER) 90-01 thru 90-05 were reviewed.
No
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deficiencies were noted,
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