IR 05000341/1979022
| ML19257A105 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 11/13/1979 |
| From: | Jablonski F, Knop R, Phillips H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19257A100 | List: |
| References | |
| 50-341-79-22, NUDOCS 8001020103 | |
| Download: ML19257A105 (4) | |
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U.S. NUCLEAR REGULATORY COMMISSION
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OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-341/79-22 Docket No. 50-341 License No. CPPR-87 Licensee:
Detroit Edison Company 2000 Second Avenue Detroit, MI 48226 Facility Name:
Enrico Fermi Nuclear Station, Unit 2 Inspection At:
Fermi Site, Monroe, MI Inspection Conducted: October 23 and 24, 1979 db b 6L
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Inspectors:
F.' J. -Jablonski h//3/79 kh:lfV"
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Approved By:
R. C.
no, Chief
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Projects Section 1 Inspection Summary Inspection on October 23 and 24, 1979 (Report No. 50-341/79-22)
Areas Inspected:
Plant tour and resolution of open items. The inspection involved a total oi 16 inspector-hours on site by two inspectors.
Results: No items of noncompliance were identified.
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DETAILS Persons Contacted Principal Licensee Employees
- E. Hines, Assistant Vice President and Manager of QA
- W. Everett, Project Superintendent
- H. Walker, Project QA Engineer
- R.
Barr, Project QA Director Other Personnel
- J. F. Bolt, Project QA Manager, DIC
- Denotes those attending the exit interview.
Licensee Action on Previous Inspection Findings (0 pen) Noncompliance (541/78-10-02): Nonseismic fire main pipe installed across redundant Class 1E cable tray systems.
During the inspection, observations were made of nonseismically supported duct work installed above Class 1E raceway. Based on the neicompliance above, Detroit Edison Company formed a task force to review non-seismic equipment over seismic equipment.
(RE: memorandum EF2-45, 665-B) The review is continuing.
For information and possible reporting under requirements of 10 CFR 50.55(e), the following information is presented:
General Design Criterion 2 of Appendix A, " Design Bases for Protection
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Against Natural Phenomeona" requires nuclear power plant structures, systems and components important to safety be designed to withstard the effects of earthquakes without loss of capablility to perform their safety functions.
Regulatory Guide 1.29 delineates the structures, systems and components
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required to meet seismic requirements.
FSAR Section 3.2.1 states that the Fermi 2 design fully conforms to
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the requirements of Regulatory Guide 1.29.
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Regulatory Guide 1.29 requires those portions of structures, systems or components whose continued function is not required but whose failure could reduce the functioning of any plant feature required to rc nain functional during a Safe Shutdown Earthquake (SSE) should be designed and constructed so the SSE would not cause such failure.
The review should include how the requirements of FSAR paragraph
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3.9.2.2.4.1 (supports and structures) and 3.9.2.2.4.2 (anchor bolts)
have been factored into the installation of non-safety related air 1665 231-2-
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handling equipment (HVAC) and non-safety related piping which pass over or otherwise provide potential hazards to safety related equipment.
(0 pen) Noncompliance (341/79-13-01): Wismer & Becker procedure for indoctrination, training and qualification of personnel was unclear.
Also, effective scheduling / rescheduling of training had not been accomplished.
The inspector determined the corrective action was incomplete. Testing-training coordinators have been replaced twice since the noncompliance was identified in NRC Report No. 50-341/79-13.
(Closed) Unresolved Matter (341/79-14-01):
An allegation was made concerning embeds which pulled out of concrete. The NRC inspector followed up and determined the deformation to the embeds used to support non-safety related piping had been damaged by welding on attachments which were subsequently used to hoist unknown loads.
Deco letter dated August 15, 1979, EF2-45813, documented a review to assure that safety related embeds were not used and damaged. The letter stated that as a result of engineering analysis Nelson studs, plates and straps were selected from Nelson design aid and tabbs.
A guideline was also issued per EF2-45242, (June 7, 1979) to avoid overloading embeds.
(Closed) Unresolved Matter (341/79-04-02):
A fire occurred in Building 45A and destroyed a limited number of records which were in the process of being reviewed. The records destroyed were generally limited to those left in "in baskets."
Wismer & Becker letter dated April 20, 1979 documented a review of files damaged in the fire. Two weld process control sheets were destroyed beyond reconstruction. These were placed on W&A Deviation Disposition Requests #275 and #376.
Daniel DDRW2550 and W2703 closed the matter after assuring a copy of the records was restored. W&B letter dated October 22, 1979, was issued to formally this item.
Functional or Program Areas Inspected 1.
Review of 10 CFR 50.55(e) Deficiency Report (79-XX-02)
Detroit Edison Company DECO reported that RHR Heat Exchange Relief Valves (V22-2038 and 2039) were undersized.
The NRC inspector found that Deco had placed a requisition P15045 to replace the undersized valves.
Since the undersized valves have not been replaced, it is only a matter of using the proper valves.
DECO Engineering is still in the process of reviewing other systems to assure similar problems do not exist in other areas. This review 16u65 232-3-
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is about 90% complete and no other problems were found. This review
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will be documented when complete; results will be forwarded to Region III. This matter is considered closed.
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Verification of ASME Certification Requiremer,ts Detroit Edison has an ASME "N" Certificate of Authorization which expires February 13, 1981.
Exit Interview The inspector met with site staff representatives (denoted under Persons Contacted) at the conclusion of each portion of.he inspections. The
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inspector summarized the purpose and findings of the inspection. The licensee acknowledged the findings reported herein.
Region III has a new telephone number:
312-932-2500.
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