IR 05000329/1978023
| ML19289F210 | |
| Person / Time | |
|---|---|
| Site: | Midland |
| Issue date: | 03/22/1979 |
| From: | Cook R, Knop R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19289F204 | List: |
| References | |
| 50-329-78-23, 50-330-78-23, NUDOCS 7906040411 | |
| Download: ML19289F210 (5) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report Nos. 50-329/78-23; 50-330/78-23 Docket Nos.
50-329; 50-330 License Nos.
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, MI Inspection Conducted: December 1-28, 1978
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Inspector.
. Cook
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Approved By:
R. C. Knop, Chief 3 /82 [77
Projects Section Inspection Su= mary Inspection on December 1-28. 1978 (Recort Nos. 50-329/78-23; 50-330/78-23 Areas Inspected:
Examination of the site conditions, assembly of States Terminal Blocks in Q-listed equipment, elevation mismatch in
the core flood system, settlement of the diesel generator building, inadequate crimping and wire termination in electrical penetrations, undersized wire being used in the control room makeup filter drain heater, installation activities pertinent to the makeup feed pumps, lifting of reactor coolant pump motors into Unit 2 containment, lifting and placing of Unit 1 primary coolant piping, welding of reactor coolant system piping in Unit 2, review of B&W generated noncompliance reports, and information meetings with licensee personnel.
This inspection effort involved a total of 66 inspection hours by one NRC inspector.
Results: No items of noncompliance or deviations were identified.
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DETAILS Persons Contacted
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- D.
Miller, Site Manager
- T.
Cooke, Project Superintendent
- J.
Corley, QA Section Head IE&TV B. Marguglio, Manager, Quality Assurance W. Bird, Section Head, Quality Engineering M. Shaeffer, QA Engineer D. Vokal, Lead Mechanical Engineer
- L. Dreisbach, Bechtel Corportation Project QA Engin?eer
- E.
Smith, Bechtel Corporation QA Engineer
- R. Shope, B&W Project Engineer Numerous other principal staff and personnel were contacted during the reporting period.
- Denotes those present during at least one of the four exit interviews conducted during the report period.
Licensee Action on Previous Inspection Findings (Closed) (329/78-21-01; 330/78-21-02): During the reporting period, the licensee completed their inspection of all safety related (Q-listed)
equipments on site using States Terminal Blocks. This involved inspecting 53 equipment items. No loose links were found and all links examined used standard hexagon nuts in conjunction with compatible modified terminals.
(0 pen) (330/78-21-01) During the reporting period the status of B&W noncompliance reports (NCR's) No. 436 and 441 were reviewed.
These NCR's pertain to an elevation mismatch between the B&W installed portion of the core flood system and the Bechtel Corporation installed portions.
Final disposition has not been completed.
Reportable Deficiencies - 50.55(e) Items Settlement of Diesel Generator Foundations and Structures Open (Item No. 329/78-13-03; 330/78-13-03)
The licensee has kept the Resident Inspector informed of activities being performed during the reporting period which are pertinent to the settlement of the diesel generator building.
During the reporting period, the licensee placed approximately five feet of initial base sand in the motor boys. However, actual preloading of the building
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has not occurred.
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As a result of transfer of responsibility for evaluation and final resolution to the settlement of the diesel generator building to
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NRR, NRR reviewers were present onsite on Dece=ber 3-4, 1978, to discuss the situation with the licensee and examine the site. The Resident Inspector attended these meetings and discussions.
Inadequate Crimping in Vendor Supplied Electrical Penetrations On December 21, 1978, the licensee informed the Resident Inspector that a physical examination of five of the 26 Q-listed electrical penetration assemblies in Unit 2 revealed that three of the penetrations had discrepancies in the crimping of numerous terminations. The penetrations were assembled and the terminations were made by the vendor. The discrepancies noted in crimping were in the three general categories of wire not fully penetrating the lug barrel; crimping was not tightly made, and the barrel seams being collapsed preventing full wire compression. This item has been considered reportable to the NRC under the provisions of 10 CFR 50.55(e)
and constitutes a breakdown in vendor QA programs.
Undersized Wire Used in Control Room Makeup Filter Drain Heater On December 27, 1978, the licensee informed the Resident Inspector that they had been informed that undersized wire was used in the Control Room Makeup Air Filters Drain Heaters which could cause an undetected loss of heaters. The licensee was informed that a loss of heaters during high relative humidity conditions could result in decreasing the ef ficiency of the carbon air filters and subsequent increase in thyroid dose to control room personnel during
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postulated accident conditions. This item has been considered reportable to the NRC under the provisions of 10 CFR 50.55(c).
Functional 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 to assess the cleanliness of the site, storage condition of equipment and piping being used in site construction; the potential for fire or other hazards which might have a dilatorius affect on personnel and equipment and to witness construction activities in progress. During one of these tours, it was noted that the inplace storage condition for
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Radwaste Gas Air Compresscrs OK-99B and OK-99C did not meet the standards for the site. These compressors are considered non-safety related (non-Q listed). The source of the dirt and debris around these compressors was primarily from cutting and fitting concrete block in walls adjacent to the compressors.
It was also noted on these tours that the electric driven auxiliary feed pump motors were covered and that storage maintenance had been performed.
The diesel generator building, setvice water pump house, tank farm, fuel oil storage area and solid radwaste building were examined during a tour established to assist the NRR reviewers interested in settlement of the diesel generator building while they attended meetings at the site.
2.
Installation of Makeup Feed Pumps During the reporting period lifting of Makeup Feed Pumps was observed. The slings were used around the pump casing.
Preliminary alignment activitias were also observed on these pumps. The pump bases are not "true" and additional shimming under the bases is required. The factory representative from B&W Canada, Lmt. is available onsite to monitor all Makeup Feed Pump installation and align =ent activities.
3.
Lifting of Reactor Coolant Pump Motor - Unit 2 Rigging to lift a Reactor Coolant Pump Motor from a truck to storage inside Unit 2 containment was witnessed. The operation
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appeared to be controlled and monitored by Consumers Power Company QA personnel.
Heavy equipments are being moved to temporary storage within containment to accomodate closing of the containment access portal in preparation for tensioning.
4.
Lifting of Unit 1 Primary Coolant Piping During the reporting period, the lifting and initial positioning of the reactor coolant system cold leg for Unit 1 south steam generator was witnessed.
5.
Welding of Reactor Coolant System (RCS) Piping Unit 2 During the reporting period B&W performed RCS pipe welding operations on Unit 2 which were examined by the Resident Inspector.
Two joints of particular interest because of being a P-1 to P-3 material weld and designates WJ-1-1 and WJ-1-2 were witnessed during welding.
It was noted that these joints were being welded within the requirements of the procedure and control were being naintained. The preliminary radiographs of these designated joints were examined. No discrepancies contrary to requirements were noted.
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B&W Noncompliance Peports (NCR's)
A review of B&W active noncompliance reports was made. Many of the NCR's generated by B&W have not received final disposition.
However, no deficiencies were noted in the administrative control of these NCR's.
7.
Specialized Meetings with Licensee Staff During the reporting period the Resident Inspector met with licensee staff members to discuss the number of 10 CFR Part 50.55(e)
items and timeliness of reporting, operational QA and cleanliness requirements for non-Q items. These meetings were in the interest of exchanging information.
8.
Exit Interview The Resident Inspector attended the Exit Interview conducted by I. Yin, RIII, Reactor Inspector conducted on December 13, 1978.
The Resident Inspector met with licensee representatives (denoted under Persons Contacted) on December 15 and December 21, 1978.
The inspector summarized the scope and findings of the inspection effort to date. The licensee acknowledged the findings reported herein.
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