ML20011F308
| ML20011F308 | |
| Person / Time | |
|---|---|
| Site: | 07001113 |
| Issue date: | 02/13/1990 |
| From: | Kasnicki D, Mcalpine E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20011F305 | List: |
| References | |
| 70-1113-90-01, 70-1113-90-1, NUDOCS 9003050090 | |
| Download: ML20011F308 (4) | |
Text
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I f
e a 88o UNITED STATES NUCLEAR REGULATORY COMMISSION og i/'
REOlONll q'
gg; 101 MARIETTA STREET.N.W.
y ATLANTA, GEORGI A 30323
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FEB-131990
' Report No.:
70-1113/90-01
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Licensee: General Electric Company Wilmington, NC 28401 Docket No.:
70-1113 License No.:
Facility Name: General Electric Company Y
Inspection Conducted:' January 8-12, 1990 Inspector:
M hh 2[l3!90 D. Kasnickl, Fuel Facil%ty Inspector Date Signed
' Approved by:
M3/90 -
E. J. McAlpfne, Section Clpief Date Signed Radiation Safety Projects Section Nuclear Materials safety and Safeguards Branch Division of Radiation Safety and Safeguards
SUMMARY
Scope:
This-routine',- unannounced' inspection was conducted in the areas of' Management
--Organization. and Controls. Training, Nuclear Criticality Safety. Operations
~ Review, Maintenance and Surveillance Testing, and 10 CFR 21 reportable' items.
.Results:
In. the areas inspected, violations or deviations were _not identified.
~Wilimington had not identified-any 10 CrR 21 reportable items, had initiated action.in response to an NRC Infomation Notice regarding packing nuts on UF6
- cylinder valves, and has -initiated an operations self-audit program to improve
~ safety and enhance employee awareness of safety requirements, i
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REPORT DETAILS
.I 1.
Persons Contacted Licensee Employees G. Barclay, Developnent & Training l
- B. Beane, Manager, FM0 Maintenance i
- G. Bowman, Senicr Program Manager, Nuclear Safety Engineering-ll R. Foleck, Senior Specialist, Licensing Engineering
- D. Hassler, HVAC Supervisor R. Keenan, Senior Nuclear Safety Engineer 4
- R. McIver, Mana5er.. Plant Engineering & Maintenance
- S. Murray, Senicr Nuclear Safety Engineer
- R. Torres, Manacer, Radiation Protection
- C. Vaughan, Manager, Regulatory Compliance
- T. Winslow, Manager, Licensing and Nuclear Materials Management
- Attended exit interview 2.
Wilmington Safety Review Committee (88005, 88015, 88020)
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~Section 2.3.1 of the~1icense application establishes the Wilmington Safety Review Committee (WSRC) and defines specific requirements regarding the committee's scope of responsibility, membership, documentation, and meeting frequency.
This license condition is implemented by GE procedure
.P/P 40-1, "Wilmington ' Safety Review Committee," Rev.
9.
dated December 7, 1989.
The inspector reviewed - WSRC meeting minutes for meetings held-on September 21, 1989, November 9, 1989, and
' December 7, 1989.
- No violations or deviations were identified.
3.
Operational Radiation Safety Review Committee (88005, 88020)J Section-2.3.2 of the license application establishes the Operational Radiation Safety Committee (0RSC) and defines specific -requirements regarding the conuni ttee's scope of responsibility,. membership, 4
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documentation, and meeting frequency.
This license condition is-p implemented by GE procedure P/P 40-31, " Operational Radiation Safety Committee," Rev. 2, dated April 22, 1988.
The inspector reviewed ORSC m
meeting minutes dated from August 3,1989 to December 6,1989.
.No violations or deviations were identified.
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Nuclear Safety Reviews of Changes (88005, 88015, 88020) j Sections 2.7.2, 2.7.3, and 4.1.2 of the license application establishes requirements regarding Nuclear Safety reviews of-changes to procedures,
' facilities, or equipment prior to-implementing the changes. This license i
condition is implemented by GE procedures:
P/P 40-5, " Nuclear Safety Review System," Rev. 6, dated October 3,1989; NSIE-3.0, " Nuclear Safety Review Request," Rev. 14, daced December 19, 1989; and NSIE-7.0,
" Radiological Safety Review for Process and Equipment Change Requests,"
Rev.-11, dated October 12, 1989.
The inspector reviewed Facility Change Request (FCR) packages for pellet cabinet, a procedure for removing' fuel cans from a drum in a work area, and repair. work on an incinerator.'
3 Nc violations or deviations were identified, t
5.
QuarterlyNuclearSafetyAudits(88005,~88015,88020)
Section 2.8.1 establishes internal quarterly nuclear safety audits and requirements associated therewith.
The inspector reviewed audit findings-from the fourth quarter 1989.
1 No violations or deviations were identified.
6.'
10 CFR 21 Reporting of Defects and Noncompliance (36100) i 10 CFR 21 ~ requins the reporting to the NRC of defects and noncompliance which could create a substantial safety hazard.- The inspector discussed this requirement with GE representatives who indicated that they had-not identified.any reportable items.
No violations or= deviations were identified.
7.-
Followup on NRC Information Notice 89-78:
Failure of: Packing Nuts on One-Inch Uranium.Hexafluoride Cylinder Valves (88005, 88020, 88025, 92701) r This information notice advised licensees about incidents in which packing nuts were found to be cracked.
Discussion with GE representatives 1
indicated that they had received the information notice and have intitiated actions recommended by the information notice.
No violations or deviations were identified.
8.
Training'(88010)
Section 2.6 of the license application establishes nuclear safety training and requirements associated therewith.
This license condition is implemented by GE procedure P/P 40-17, " Nuclear Safety Training", Rev. 6, dated December 14, 1989.
The inspector discussed training with GE representatives, reviewed training records, and viewed the most recent re-training video-tape.
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No violations or deviations were identified.
9.
~ Air Flow Diiection Checks; Air Flow Rate Checks; Differential Pressure Checks (88020), 88025)
Sections 3.2.2.1 and 3.2.2.2 of the license application establish the requirements for monthly air flow direction checks, monthly air flow rate checks, and monthly differential pressure checks across filters.
The inspector examined records of these monthly checks.
t No violations or deviations were identified.
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- 10. Plant Walk' Through and Operations Review (88015, 88020)
^
The inspector toured uranium handling areas with a GE representative.
Observed operations appeared to be being conducted in accordance with l
, safety requirements, observed anti-c head coverings were being properly worn and housekeeping, including visible uranium contamination, appeared good.
l Discussions with GE representatives indicated that they have instituted a 1
self auditing program within all production groups. A primary purpose of 1
these ' audits is to enhance operator awareness of safety. rules via employee l
involvement in the. audit process.
l No~ violations or deviations were identified.
- 11. Exit Interview The. inspection scope and results were sumarized on January 12,100, with i
those persons indicated in paragraph 1.
The inspector described the areas
-l inspected and discussed in detail the inspection results described above.
1 Although reviewed during this inspection, proprietary information is not contained in this report.
Dissenting comments were not received from the
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licensee.
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