IR 05000329/1979016
| ML19249B277 | |
| Person / Time | |
|---|---|
| Site: | Midland |
| Issue date: | 07/06/1979 |
| From: | Cook R, Knop R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19249B270 | List: |
| References | |
| 50-329-79-16, 50-330-79-16, NUDOCS 7909040225 | |
| Download: ML19249B277 (7) | |
Text
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-329/79-16; 50-330/79-16 Docket No. 50-329; 50-330 License No. CPPR-81; CPPR-82 Licensee:
Consumers Power Company 1945 West Parnall Road Jackson, MI 49201 Facility Name: Midland Nuclear Power Plant, Units 1 and 2 Inspection At:
Midland Site, Midland, Michigan Inspection Conducted: May 1-31, 1979
~7 I /f Inspector: R. J.' oo Rc&-
Approved By:
R. C. Knop, Chie
//
Projects Section 1 Inspection Summary
.
Inspection on May 1-31, 1979 (Report No. 50-329/79-16; 50-330/79-16)
Areas Inspected:
Examination of site conditions, settlement of diesel generator foundations and structures, strength capabilities of reactor building spray piping supports, inadequate soldered terminations in control panel status modules, information meeting with Congressman D. Albosta and aides, acts of malicious vandalism (cut wires in the control room and nails driven into three conductor power cable), hydro-static testing of Unit 2 Incore Instrument Tank 2T-87, ASME Section III qualification of auxiliary feedwater pump seal and lube oil coolers, audit of QA management functions. This inspectan effcet involved a total of 83 inspector-hours by one NRC inspector.
Lesults: No items of noncompliance or deviations were identified.
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DETAILS Persons Contacted D. Miller, Site Manager, Consumers Power Company (CPCO)
- T. Cooke, Project Superintendent (CPCO)
M. Shaeffer, QA Engineer (CPCO)
R. Wollney, Field QA Engineer (CPCO)
D. Horn, QA Engineer (CPCO)
- D. Vokal, Lead Mechanical Engineer (CPCO)
E. Jones, QA Inspector (CPCO)
- L. Dreisbach, Project QA Engineer, Bechtel Power Corporation (BPC)
- E. Smith, QA Engineer (BPC)
R. Siple, Lead Mechanical QC (BPC)
H. Smith, QC Inspector (BPC)
- R. Shope, Project Engineer (B&W)
W. McDougall, Authorized Inspector, Kemper Insurance Numerous other principal staff and personnel were contacted during the reporting period.
- Denotes those during at least one of the two exit interviews conducted during the report period.
Licensee Action on Previous Inspection Findings Reportable Deficiencies - 50.55(e) Items Settlement of Diesel Generator Foundations and Structures (Open) Item No. (329/78-13-03; 330/78-13-03):
During the report period the licensee has kept the Resident Inspector informed of activities being performed pertinent to the settlement of the diesel generator building.
The licensee has started digging of some selected test pits for furtner evaluations for the site settlement monitoring program. The licensee informed the Resident Inspector of these plans for digging test pits and the information was relayed to NRR and the Regional Office.
On May 14-15, 1979, a Regional Based Inspector was onsite and reviewed the status of the settlement monitoring program.
The results of his inspection efforts are documented in a separate NRC Inspection Report No. 50-329/79-10; 50-330/79-10.
Reactor Building Spray Piping Supports On May 15, 1979, the licensee informed the Resident Inspes 'or that the 50.55(e) item pertaining to the load carrying capability of the-2-d U.1 *T m, c.q e
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r! actor building spray piping support would require additional
,
.eview as the installed hangers are not compatible with the design arswings used in the reanalysis. The licensee had submitted a final report to the NRC on May 1, 1979. Therefore, this item is considered as remaining open and reportable to NRC under the provisions of 10 CFR 50.55(e).
Inadequate Solder Terminations in Control Panel Status Display Modules On May 29, 1979, the licensee informed the Resident Inspector that numerous inadequate soldered terminations on status display modules installed in control panels IC-14, 2C-14, and OC-10 were found. The disposition for the inadequate terminations is being " tracked" by nonconformance rej ort No. NCR-2176 and management corrective action request No. MCAR-28. This item has been considered reportable to the NRC under the provisions of 10 CFR 50.55(e) and appears to be a break down in vendor QA program.
Fr.ictional or Program Areas Inspected 1.
Site Tours At periodic intervals, generalized tours of the facility were performed by the Resident Inspector. During the reporting period, these tours covered essentially every area of the site.
These tours were intended tc assess the cleanliness of this site, storage condition of equipment and piping being used in site construction; the potential for fire or other hazards which might have a deliterious effect on personnel and to witness construction activities in progress.
During one of these tours, chains were noted being used to support valves and/or piping spools in the decay heat removal system located in Room 27 of the 568' elevation cf the Auxiliary Building. The current revision to Technical Specification for Field Fabrication and Installation of Piping does not explicitly prohibit use of chains against stainless steel piping but does state that nylon straps (or equivalent) should be used.
The licensee took immediate steps to remove unprotected chains f rom stainless steel piping and informed personnel to use discretion whenever chains are used in contact with stainless steel.
2.
Specialized Site Meeting and Tour On May 5, 1979, Congressman D. Albosta and aides visited Midland Site to discuss comparisons between the Midland Site and the March 28, 1979, Three Mile Island, Unit 2, event. This meeting was attended by Consumers Power Company corporate and site personnel, the NRC Region III Director, the NRC Region III Construction Branch Chief and the Resident inspector.
Congressman Albosta's visit to the site terminated wita a tour through the turbine building ground level,
~
upper level of the Unit 2 containment building and surrounding site ground o.
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3.
Cut Wires in Control Room On May 3, 1979, the licensee informed the Resident Inspector that wires had been discovered cut in four control room panels and cover glasses were broken on electrical relays located in another control room panel. This information was relayed to the regional of fice and an investigation was performed by a Regional Based Investigator on May 7-8, 1979. The results of this investigation clarsified the damage as malicious vandalism.
These results are documented in NRC Investigation Report No. 50-329/79-11; 50-330/79-11.
4.
Damaged Power Cable The licensee informed the Resident Inspector on May 25, 1979, that Bechtel Corporation electrician had found two nominal 6 penny nails driven into a three connector 350 MCM-600 volt power cable. The cable was a nominal 160' length and was located on the roof of the Auxiliary Building to facilitate cable installation.
The nails were located in a central section of the cable and were spaced approximately 17 feet apart.
The length of cable being installed has been replaced.
The event is considered an act of malicious vandalism.
5.
Hydrostatic Test of Unit 2 Incore Instrument Tank to T-87 During the reporting period a successful hydrostatic test of the Unit 2 Incore Instrument Tank 2T-87 was performed.
The hydrostatic test was witnessed and/or examined by the Hartford Boiler Authorized Inspector, Bechtel Corporation Authorized Inspector, Consumers Power Company QA and the Resident Inspector.
The 2 foot vertical welds penetrating the floor anulus (referenced in NRC Inspection Report No. 50-329/79-13; 50-330/79-13) were inspected using a borescope.
Vertical weld No. 1-A (east) at the floor location requires exami-nation from both top and bottom as no access existed where the horizontal support is welded across the vertical seam. Welding across the vertical seam is being evaluated by the licensee.
6.
Auxiliary Feedwater Pump Seal and Oil Coolers During the reporting period the Resident Inspector was informed by a Vendor Inspector from Region IV that some confusion appeared to exist in the Bechtel Corporation Quality Assurance Report associated with the auxiliary feedwater pumps supplied by Bingham '.'illamette Company.
This confusion pertained to the ASME Code Section III qualification of seal and lube oil coolers.
A cursory review of the status of the auxiliary feedwater pump seal and oil coolers revealed that it could not be concretely established that the installed oil coolers were qualified to ASME Section III criteria at this time.
Additional review into this matter has continued into the scnth of June, 1979, and the results of this review will be documented in the next Resident Inspection Report.
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7.
Management QA Audit
.
On May 8-9, 1979, a team of four Regional Based Inspectors performed an indepth audit of Consumers Power Company, Bechtel Power Corporation, and B&W QA management functions onsite. The Resident Inspector offered first-hand insight into the NRC inspection team's areas of interest and attended the exit interview conducted on May 11, 1979.
The results of this inspection effort are documented in NRC Inspection Report No. 50-329/79-12; 50-330/79-12.
Management Interviews The Resident Inspector attended the Exit Interviews conducted by J. Creed, W. Hansen, E. Gallagher, and E. Lee, RIII Investigator and Reactor Inspectors on May 8, May 11, and May 17, 1979, respectively.
The Resident Inspector met with licensee representatives (denoted under Persons Contacted) on May 16, and May 31, 1979. The inspector summarized the scope and findings of the inspection effort to date.
The licensee acknowledged the findings reported herein.
Attachment:
Preliminary Inspection Findings-5-c. r c mzm *
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