IR 05000329/1978021
| ML19282B312 | |
| Person / Time | |
|---|---|
| Site: | Midland |
| Issue date: | 01/30/1979 |
| From: | Cook R, Hayes D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19282B310 | List: |
| References | |
| 50-329-78-21, 50-330-78-21, NUDOCS 7903130056 | |
| Download: ML19282B312 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-329/78-21; 50-330/78-21 Docket No. 50-329; 50-330 License No. CPPR-81; CPPR-82 Licer.see:
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: Oct obc r 2-31, 1978 I
'Q Inspector:
R. J. Coo a
. bayes,
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-/~7 Ar. proved By:
D Projects Section
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Inspection Summary Inspection on October 2-31, 1978 (Report No. 50-329/78-21; 50-330/78-21)
Areas Inspected: Examination of the general site condition, settlem nt of the diesel generator foundations and structures, seismic qualification of Class 1E battery racks, scheduling analysis, information meetings with licensee personnel, location of core flood lines for Unit 2, installation of reactor coolant system piping restraints, potential for loose links on States Terminal Blocks, welding of reactor coolant system piping for Unit 2, sand blasting operations in Unit 1 containment, condition of temporary laydown areas, in place storage condition of electrical equipment, disposition of the nonconformance report (NCR)
issued pertaining to bump of Unit 1 pressurizer while upending, auxiliary piping systems field welding and fabrication, and status of auxiliary feed pump inplace storage maintenance, This inspection effort involved a total of 112 inspection-hours by one NRC inspector.
Results: No items of noncompliance or deviations were identified.
790313005(o
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DETAILS Persons Contacted
- D. Miller, Site Manager
- T.
Cooke, Project Superintendent
- J. Corley, QA Section Head, IE&TV
- B.
Peck, Construction Cupervisor
- R.
Whitaker, QA Engineer G, Keeley, Project Manager B. Marguglio, Manager, Quality Assurance W. Bird, Section Head, Quality Engineering L, Lowell, QA Engineer
- W.
Barclay, Bechtel Corporation Project Field QC Engineer
- L. Dreisbach, Bechtel Corporation Project QA Engineer
- E.
Smith, Bechtel Corporation QA Engineer J. Spence, Bechtel Corporation QC Inspector
- R.
Shope, B&W Project Engineer
- J. Ashworth, B&W QC Inspection Supervisor 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.
Inspection Areas 1.
Site Tours At periodic intervals generalized tours of the facility were per-formed 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 used in site construction; the potential for fire or other hazards which might have a deleterious affect on personnel and equipment and to witness construction activities in progress.
2.
50.55(e) Item Settlement of Diesel Generator Foundations and Structure Open (Item No. 329/78-13-03; 330/78-13-03) - The licensec has kept the Resident Inspector informed of evaluations being performed
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pertaining to the settling of the diesel generator building and foundations.
Information requested by the Regional Based Inspector for the review of this item has been supplied through the Resident Inspector. The Resident Inspector participated in a portion of the inspection activities of the Regional Inspector conducted on site during the period of October 24-27, 1978.
Class lE Battery Racks, Seismic Brace on October 20, 1978, the licensee informed the Resident Inspector that based on a Mailgram from the supplier of the battery racks, it had been identified that an additional isolation bar is required in Class 1E battery racks to isolate the buildup of horizontal momentum during a seismic event.
This item had been reported to the USNRC by the supplier of the battery rack (Exide Industrial Battery Division) under the provisions of 10 CFR Part 21.
3.
In Place Storage of Electrical Equipment During the reporting period, in place storage of electrical equip-ment in motor control centers, switchgear rcoms and in proximity to the control room were examined. This equipment appears to be properly protected from weather conditions.
4.
Unit 1 Pressurizer Bump During the placing of Unit 1 pressurizer, the pressurizer was bumped.
B&W generated NCR No. 421 which identified the damages. During this reporting period the status of the NCR No. 421 was examined.
Cor-rective action has not yet been completed.
5.
Scheduling Analysis During the reporting period the licensee explained a computerized technique for keeping abreast of the construction schedule and items which might impact on the schedule.
The computerized tech-nique allows visibility into the construction progress of those critical path areas which may require more emphasis to avert any major schedule slippage.
These analyses have indicated that the f uel load date for Unit 2 has not been altered.
6.
Management Meetings During the reporting period, the Resident Inspector met with the Corporate manager for the QA staff to discuss current enforcement items, and current status of Consumer Power's QA/QC overview inspections. Also 3_
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I during the reporting period, meetings were held with the Site Manager to discuss implementation of 10 CFR Part 19.
Letters encouraging workmen to identify items of safety significance to their supervisors and the means of contacting the NRC in confi-dentiality are posted in the Change House.
7.
Core Flood Lines During the reporting period J6W roncompliance reports (NCR) No.
436 and No. 441 were issued p utaining to an elevation mismatch between the B6W installed portion of the core flood system and the Bechtel Corporation portion of the installed core flood system.
These NCR's were reviewed and final disposition has not been completed.
It appears that the elevation mismatch has occurred by one portion of the system being installed to looser elevation tolerance requirements than the other portion of the system.
Corrective action will be reviewed (Item No. 330/78-21-01)
8.
Reactor Coolant System Pipe Restraints The installation of pipe whip restraints around the Unit 2 north steam generator reactor coolant system (RCS) hot leg piping was examined during the reporting period.
The RCS hot leg piping was used for a chain hoist pivot point for fitting the restraint.
The RCS hot leg piping was not fully welded but was fitted and tacked at this time.
The licensee agreed to reverify the RCS hot leg piping alignment.
This was accomplished on November 2, 1978.
9.
States Terminal Blocks During the reporting period the licensee informed the Resident Inspector that a Consumers operated fossil plant had tripped off the line as a result of loose links on States Terminal Blocks becoming open circuited.
Investigative efforts revealed that the loose links were caused by using nuts with an internal chamfer on a modified terminal which requires a standard hexagon nut.
The chamfered nuts were used on earlier styled terminal blocks that require this type of fastener. The licensee is performing inspec-tions of all safety related vendor installed control circuit terminations using States Terminal Blocks to determine if com-patible terminals and fastening hardware were used. Results of the licensee's inspections will be reviewed at a later time (Item No. 329/78-21-01; 330/78-21-02).
10.
Weiding of Reactor Coolant System (RCS) Piping - Unit 2 During the reporting period, B6W performed RCS pipe welding oper-ations on the Unit 2 hot leg to steam generator nozzles for both steam generators. The welds were examined at various times on-4-
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i procedural preheat requirements were both shifts to insure that controlled weld rod was being used; voltage and amperage were being controlled within the specifications for the size rod being met; being used; that presently calibrated instrumentation was being the welding used; that the fitup was within design limitations; that was being performed by previously qualified personnel and that NDE personnel were qualified in the type of examinations perf ormed.
leg nozzle for the south steam generator could not be The hot 444 was fitted to the drawing specifications and B&W NCR No.
A Field Change Authorization No. 04-3015-01 was generated.
issued to allow a wider root gap when a specified backing ring The original prints did not detail the fitup geometry is used.
The licensee stated that the Field when backing rings are used.
Change Request would become an integral part of the as built documentation.
Welder qualification records for welders No. 30, 83, 277 and 279 were reviewed.
Information radiographs for the north steam generator taken after 1" of material was added to the radius were examined.
NDE qualification records were examined for personnel being used in this capacity.
No deviations or items of noncompliance were observed.
11.
Sand Blasting of Unit 1 Containment 1 containment walls During the period extensive sand blasting of UnitEssentially all areas was performed.
Unit heaters were to verify protection of safety related equipment.
not covered during the initial stages of sand blasting operations.
However, the licensee took immediate steps to cover the heaters and sand would be cleaned from the heaters after termination stated that activities to preclude sand from being blown onto of sand blast other construction activities when the heaters are energized at a
Respirators were required for personnel in containment later time.
while sand blast operations are in progress.
12.
Temporary Laydown Areas During the reporting period temporary laydown areas for safety The piping appears to be adequately related piping were examined.
stored on dunage in well drained areas and relatively free from potential contamination.
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13.
Auxiliary Piping Systems Field Welding and Fabrication Field fabrication of piping being installed on the 568, 584 and 634 foot elevation levels of the Auxiliary Building was examined. This included witnessing weld preparation and fitup and welding of piping joints in the boric acid addition system, auxiliary feed system and containment spray system and other system joints welded in the auxiliary building. Purge gas flow appeared to be adequate and within procedural limitations. Welding rod appeared to be controlled and withdrawals were being made per procedural control.
14.
Auxiliary Feed Pump Inplace Storage Maintenance The inplace storage condition of the electric drive auxiliary feed pumps 1P05A and 2P05A was examined. Auxiliary feed pump 2P05A was found with the suction and discharge piping against the pump casing flange and out of alignment enough to allow open access to the pump casing without the opening being covered. A review of the maintenance information check forms F-10/20-119 and F1-436 indicated that periodic checks had been made to verify that all openings were closed.
It was difficult to establish when the suction and discharge connections had become open as maintenance records indicated the last examination had been made approximately three weeks earlier. During the review of the inplace storage maintenance documentation it appeared that routine maintenance had not been performed on the motor driver and long term maintenance had not been performed on the pump end.
Subsequently this was substantiated as a item of noncompliar.ce and will be documented in the November 1978 report.
Exit Interview The Resident Inspector attended the Exit Interview conducted by Mr. E. Gallagher, RIII Reactor Inspector on October 27, 1978.
The Resident Inspector met with licensee representatives (denoted under Persons Contacted) on October 3, 12, 19 and 26, 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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