IR 05000341/1981003
| ML19352B081 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 04/24/1981 |
| From: | Byron P, Konklin J, Little B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19352B078 | List: |
| References | |
| 50-341-81-03, 50-341-81-3, NUDOCS 8106030041 | |
| Download: ML19352B081 (5) | |
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NUCLEAR REGUI.ATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT.
REGION III
Report No. 50-341/81-03 Docket No. 50-341 License No. CPPR-87 Licensee: Detroit Edis on Company 2000 Second Avenue Detroit, MI 48226 Facility Name: Enrico Fermi Nuclear Power Station, Unit 2 Inspectico At: Fermi Site, Monroe, MI Inspection Conducted: February 16 through March 31, 1981 < f, . Inspectors: B. H ittle Y/29 [[ ifa Y/Ef/g/ P.
. Byro A
r Approved By: J.
'onklin, Acting Chief meg /[[. 'l ' ' R ctor Projects Section 2A
Inspection Sunnary Inspection on Febr uary 16 through March 31, 1981 (Report No. 50-341/81-03) Areas Inspected: Routine resident inspector preoperational inspection consisting of licensee action on previous inspection findings, IE Bulletin and Circular followup, licensee event followup, independent inspection effort and plant tours. The inspection involved a total of 136 inspector-hours'onsite by two NRC inspectors including 16 inspector-hours onsite dur-ing of f-shif ts.
Results: No items of noncompliance or deviations were identified.
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g - - - - .. - DETAILS ' ~1.
Persons Contacted
- T.'Alessi, Director Project QA
. . -*W. Fahrner, Manager Fermi 2 Project ~ *E. Griffing, Assistant Plant Superintendent J. Gessner, Assistant Project QA Director S. Noetzel,' Assistant Project Manager
- A. Walker, Project QA'Section Supervisor
- Denotes those attending weekly management' meetings.
2.
Licensee Action on Previous Inspection Findings .(Open) Unresolved Item (341/80-23-01): "QA Level I Cable Pulling Prob lems."
The licenace performed an operational audit of the electrical area in December, 1980.,The. audit identified concerns in material control, field installation, and engineering. The inspector met with licensee's Project and Quality Assurance manage-ment to review and evaluate licensee's disposition of the identified concerns. The inspector verified'that concerns having safety signifi-cance had been adequately resolved, or under management controls pending engineering, quality assurance resolution.
The licensee has issued an interim 10 CFR 50.55(e)~ report on. apparent cable damage.
Close out of this matter is pending inspector's' review of licensee's final 10 CFR 50.55(e) report.
, - No items of noncompliance or-deviations were identified.
3.
IE Bulletin and Circular Followup IE Bulletin issued during this period: IE Bulletin 81-01, Revision 1 " Surveillance of Mechanical Snubbers."
IE Circulars issued during this period: IE Circular No. 81-03 " Inoperable Seismic Monitoring Instrumentation."
, IE Circular Nc. 81-05 "Self-Aligning Rod End Bushings for Pipe Supports."
The inspector verified the above bulletin and circulars have been received and undergoing licensee review.
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, - v.. Licensee action on previous IE Bulletins include: p' t[ fi , L'~*, lE Bulletin 80-23 (Open): " Failure of Solenoid = Valves Manufactured ~ ~ . by' Valcor Engineering Corporation."_ - - .t i-. , - lE. Bulletin 80-25:(Open):." Operating Problem with Target Rock - Safety-Relief Valves at.BWR's."' " ' Licensee reports on these bulletins 'are Jpending. inspector's review.
Followup and close out of these items will be documented in subsequent.
inspection reports.
- No' items of noncompliance or deviations were identifidd.
l 4.- Licensee Event Followup-a.- . Removal of; Pipe Supports af ter Inspection.
,The licensee 11ssued an-interim 10 CFR 50.55(e). report on. removal ! of Q._-A. level I pipe _ supports in the Reactor Building.
A l - licensee' review of approximately seventy-five pipe supports.. L ' revealed that twelve pipe supports had'apparently been removed r . and' reinstalled. ~This work was apparently done by sit'e contractor (s)- l .on previously inspected and accepted pipe supports without ! proper aathorization/ documentation.
~ Followup and close out of this matter will' be documented in a - subsequent. inspection ' report. This matter is assigned open . item number 341/81-03-01, ' t ' b.
. Terminations To Receptacles on GE Panels.-
i The licensee reissued a 10 CFR 50.55(c) report which concerned I loose ' receptacle pins in the main control room panels, when sub--
l: sequentvinvestigation' revealed that the problem also exists in
[ the GE supplied relay room panels.
Followup and close out of this item will be documented in a sub-sequent inspection report. This matter is assigned open item number 341/81-03-02.
. t-l No items of noncompliance or deviations were identified.
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. Independent Inspection Effort I-a.
Calibration and Control of Torque Wrenches . The inspector reviewed the work activities of seven site contractors
' relating-to calibration and control of torque wrenches. This re- - view identified the following deficient practices: l I ~ (1). One contractor's torque wrenches exceeded the calibration
due-dates.
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~ Ti _ .,. T, (2)l Another contractor had not documented torque wrenches use as required' by contractor's own procedure.1 Also the docu-- nent review process did not detect or correct this deficiency.
- (3) :Three contractors had issued purchase orders' to a. calibra-tion laboratory without specifying tolerance or calibration ., requirements, had received "out of tolerance" wrenches - from the 1aboratory and had issued these wrenches to the ~ field for use. The inspector noted that tolerance and calibration frequency requirements varied between contractors.
' A QA audit by.the licensee of -one contractor identified simi-lar deficient practices in this area. The licensee plans additional audits of other contractors.
Followup and close out of this matter will be documented in a subsequent inspection report. This matter is assigned
open item number.341/81-03-03.
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Supervision and Control of Safety-Related Activities-Quality: assurance inspections performed by the licensee during this period identified deficient safety-related activities by a ' site contractor. Deficiencies identified include removal of QA Level I pipe supports,'(See Paragraph 4a. above),.and. changing heat numbers'and welder identification numbers on QA Level 1-piping systems.
The inspector reviewed these deficient practices 'for safety significance and causal factors.
Reinspection of pipe support would verify proper installation.
Initial licensee review of changed heat and welder ID numbers indicate traceability 'does exist. and that original numbers were acceptable numbers.
These. licensee inspections highlighted the following concerns: (1) Inadequate procedures (2) Procedure noncompliance (3) Lack of management controls Licensee review of this matter has not been completed. Followup . and close out of this matter will be' documented in a subsequent inspection report. This matter is assigned open item number 341/81-03-04.
No items of noncompliance or deviations were identified.
6.
Plant Tours The inspectors conducted tours of the RHR Couplex and the Reactor,
Auxiliary and Turbine Buildings. The inspe'. tors observed the conduct of routine business in the control room including work control, shif t' turnover and review of control room logs.
The inspectors also observed the ' performance of a fire drill by the onsite fire brigade.
, No items of noncompliance or deviations were identified.
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. Exit Interview ' The inspectors' met with licensee representatives (Denoted in l Paragraph 1) weekly' and at the conclusion of this inspection - pe riod. The inspectors summarized the scope.of the inspection ~ findings. With regard to work controls and practices (Paragraph 5(a).
. and (b)),the licensee acknowledged the findings.and was responsive , to the need for corrective action in those areas.
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