IR 05000320/1988006
| ML20195B964 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/10/1988 |
| From: | Cowgill C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20195B961 | List: |
| References | |
| 50-320-88-06, 50-320-88-6, NUDOCS 8806220061 | |
| Download: ML20195B964 (47) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
50-320/88-06 Docket No.
50-320 License No.
OPR-73 Priority Category C
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Licensee:
GPU Nuclear Corporation
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p-O.-Box 480
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- Middletown, Pennsylvania 17057 Facility Name: Three Mile Island Nuclear Station, Unit 2 Inspection At: Middletown, Pennsylvania Inspection Conducted: ' April 1 - May 7 and May 11, 1988 Inspectors:
R.- Conte, Senior Resident Inspector D. Johnson, Resident Inspector (Reporting Inspector)
T. Mos ak, Resident Inspector Approved by:
J1L h /0 C. Cowhill,(Ghjef, Reactor Projects Section 1A Date h
Inspection Summary:
Areas Inspected: Routine safety inspection by site inspectors of defueling and decontamination activities, including operations to cut the uppermost plate of the Lower Core Support Assembly into sections; off-normal event follow-up; implementa-tion of radiological controls; and, assessment of the overall progress for decon-taminating plant areas and defueling plant system.
Specifically, the inspectors reviewed a number of licensee-identified items and followed licensee actions in responding to off-normal plant events, including a precautionary reactor building evacuation; a hose rupture in a liquid radwaste flowpath; an inadvertent transfer from the Borated Water Storage Tank to the "B" Reactor Coolant Bleed Tank; and, a failure of the handrails on the core drilling platform.
Results: In general, procedures were properly implemented.
Housekeeping and fire protection conditions improved.
The root causes of the above noted events appear to be personnel weaknesses in clearly communicating (between operations and support departments) and in providing attention to detail in the area of procedural implementation.
None of these event had a major impact on site radiological safety. However, because of unique condi-tions at TMI-2, such weaknesses, if permitted, could result in serious consequences.
The effectiveness of the licensee's corrective actions for off-normal events will continue to be routinely reviewed by the NRC resident office.
The licensee discussed the status of their decontamination efforts at the meeting in Region I on April 28, 1988.
One licensee identified violation was identified (Paragraph 2.3.5).
No Notice of Violation was issued in accordance with the provision of 10 CFR Part 2, Appendix C,
8806220061 880610 PDR ADOCK 05000320
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SUMMARY OF MAKEUP SYSTEM FLUSH RESULTS ALL SURVEY DATA GIVEN IN mRIhr GAMMA AREA PREFLUSH SURVEY DATA POSTFLUSH SURVEY DATA AVG.DECON RLENUMBER GENERAL CONTACT GENERAL CONTACT FACTOR COMMENTS AX005 46o 8-1000 20 80 7-250 0.93 HIGH READMGS NOT RESURVEYED SEAL INLIECTION EQUIPMENT N AREA AX006 15-600 50400 18-2 m 60-400 1.60 UNISTRUT HOTSPOT AND VICINITY NOT RESURVEYED AX007 4-500 50-3000 2-150 20-3000 6.4o MAXEUP TANK RELEF LINE RUSH AND KELLY VACIMPROVED GA RATES AX026 3-50 2-iso 2-16
<2 t 10 1.99 COMPLETED ROSH; GENERAL AREA f>A) RATE NDUCTION EVIDENT AX111
>1m 8-6 m 1s 40-50 s.17 RUSH CONNECTION CONTACT LOWER WITH LitTcD REDISTRIBUTION 2s-3so sa2mo ta2m 10-1800 6 S4 Fit.TER HOUSING CLEAN OUT.DRAN AX112 WORK ANDSCABBLNGLOWEREDGA 20-10 75-150 o 10-60-1000 20.4 TANK NLEF LNE RUSH REDUCED AX116 GA SIGNIFICANTLY 200-900 toc 4000 600-2000 50-5000 DATA NSUFFICENT DUE TO ENTRY AX117 PROBLEMS. SOME WORK REMANS FH001 50-200 60-1000 50-500 30-2c'.,o 3.1 HIGH EXTERNALCONTAMINATION ON VALVES tmMTED EFFECT OF RUSH FH002 2-50 INSUFFICIENT 2-10 s-8 NSUFFICENT PRE-RUSH DATA FH003a 200-1000
<1m-toom 500-800 400-2000 UMRED DATA N THIS AREA NSULTS NCONCLUSIVE FH003b do-som 2 w -s m o NSUrFICENT 2so-24w V
FH101 100-480 200-3000
<100-300 100-900 3.2s LARGEST REDUCTION DUE TO BLOCK ORIFICE NMOVAL RESULTS AS OF 31 OCTCCCR 1987
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