IR 05000329/1978001

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IE Insp Repts 50-329/78-01 & 50-330/78-01 on 780124 & 25.No Noncompliance Noted.Major Areas Inspected:Installation of Reactor Pressure Vessel,Steam Generator,Pressurizer & Coolant Pumps & Other safety-related Equipment
ML19329E261
Person / Time
Site: Midland
Issue date: 02/17/1978
From: Cook R, Hayes D, Vandel T
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML19329E255 List:
References
50-329-78-01, 50-329-78-1, 50-330-78-01, 50-330-78-1, NUDOCS 8006120555
Download: ML19329E261 (5)


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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT

REGION III

Report No. 50-320/78-01; 50-330/78-01 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, M1 i

Inspection conducted:

January 24 and 25, 1978

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Project Section Inspection Summary Inspection on January 24 and 25, 1978 (Report No. 50-329/78-01; 50-330/78-01)

Areas Inspected: Review of Procedures for installation of NSS equip-ment (RPV, steam generator, pressurizer and coolant pumps) and of other safety related equipment, and followup review of previously identified noncompliance and unresolved matters.

This inspection involved a total of 21 inspector-hours onsite by two NRC inspectors.

Results: No items of noncompliance or deviations were identified.

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D DETAILS Persons Contacted Consumers Power Company (CPCo)

  • T.

C. Cooke, Project Superintendent

  • J. L. Conley, Project QA Superintendent
  • D. R. Keating, Field QA Engineer
  • P.

R. Kyner, QA Engineer

  • B.

H. Peck, Construction Supervisor H. Stephens, NDE Group Supervisor Bechtel Power Corporation (Bechtel)

  • W. L. Barclay, Project Field QC Engineer
  • A. J. Boos, Project Field Engineer
  • R.

C. Hollan, QA Engineer G. L. Richardson, Lead QA Engineer During the course of the inspection, other CPCo and Bechtel personnel were contacted.

  • Denotes those present at the exit interview.

Licensee Action on Previous Inspection Findings (Closed) Noncompliance (Report No. '50-329/77-05, 50-330/77-08; 50-329/

77-08; 50-330/77-11; 50-329/77-11, 50-330/77-14). Unit 2 pipe support hanger bracket mounting clearance failed to meet specification require-ments.

NCR 813 issued for pipe support bracket 16-1HCB-2-H9 being nonconforming to the revised acceptance criteria.

In observing the installed bracket, grouting was observed to have been completed and the bracket replaced over the grout for an acceptable supporting surface.

Iso drawing 610 sheet 3 showed that a 16" x 16" wall bracket marked 18-1HCB-2-H9 is to be installed to provide the support wall brackee for the 18" decay heat removal suction line 1 HCB-2.

The inspector reviewed the completed NCR 813 and determined that the inspector had reinspected the installation and had signed the NCR as being acceptable and completed on November 29, 1977.

This item is considered to be closed.

(Closed) Noncompliance (Report No. 50-329/77-09, 50-330/77-12). US Testing failed to follow procedure UST-Audit-1. Audit finding reports OV-2-

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(AFR's) one through four of inkonal audit No. 11, due to be responded to by project supervision regarding corrective actions by June 3, 1977, were completed and approved by the Project Manager on August 31, 1977 with close out accomplished for all four AFR's by verification and sign of by the originating auditor. The inspector additionally learned that an Administrative Instruction was also issued (AI No.

PGI-425-1) requiring a twice monthly status reporting of all AFR's outstanding which is now implemented. The inspector reviewed the biweekly status reports for weeks of November 23, 1977, December 8, 1977, December 23, 1977, and January 6, 1978 regarding the status of the 12 AFR's from audit No. 12.

  • An additional Administrative Instruction, AI No. NCI-450-1, has now been issued and implemented for the close out and followup of internal corrective action requests (ICAR's). This to be a separate control mechanism to be used in conjunction with the AI for AFR's.

This item is considered to be closed.

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(0 pen) Two unresolved matters (Report No. 50-329/77-05, 50-330/77-08; 50-329/77-08, 50-330/77-11; and 50-329/77-10, 50-330/77-13):

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Consumers Power Company manual revisions, and (2) further review of NATCO audit. These items were not reviewed during the current j

inspection. Review will be conducted during future inspections.

7-g (Open) Unresolved matter (Report No. 50-329/77-11-01, 50-330/77-14-01):

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Records of qualifications of CPCo. QA auditors were not available

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at the site.

In discussions with the CPCo Training and Qualifications supervisor it was learned that some qualification records have been issued to the Midland site and that additionally further training

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activity has been and is taking place that will further update records of qualification. This item will be further reviewed during future inspections.

(Closed) Unresolved matter (Report No. 50-329/77-01, 50-330/77-01):

Derailment of railroad car carrying Unit 1 steam generator. A B&W site problem report was issued to B&W Component Engineering for review and sign off.

Mr. Demis F. Rice, Task Engineer indicated no damage had resulted and that no inspections of the steam generator was necessary. Signed on March 28, 1977. The details regarding the unit involved are - steam generator unit number 1 RC-S G1A being transported by railroad cars BAWX-101 (partly derailed) and BAWX-103 (not derailed). The two railroad cars together were transporting the steam generator unit into the site yard at approximately three miles per Lour when 22 of the 24 wheels of the one car became derailed at a frozen switch.

The car was placed back on the track the next day by the B&O without incident. This matter is considered closed.

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Licensee Action on Previous Inspection Findinos (Closed) Unresolved Item (Report 50-329/77-09; 50-330/77-12). Dis-crepancies noted in the vertical tendon gallery.

An examination of the vertical tendon galleries for both Units 1 and 2 revealed that:

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Access control had been established by locked gates.

Entry is permitted after the site safety department has performed a survey of the area. The entry to the galleries is posted for possible gas hazard.

  • 2.

Hot air circulation has been established in the galleries which has alleviated the excessive dampness condition.

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Some ingress of water still exists and some water was noted on the floor. The licensee has evaluated this situation and determined that if conditions do not progressively worsen some water ingress could be tolerated.

A routine inspection program for the galler!-s has been established to ensure conditions remain stable.

j Other Inspection Areas Reportable Deficiency (50.55(e))

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During the inspection the licensee discussed a reportable deficiency.

It was noted during a routine dimensional inspection that the reactor coolant pump motor mounting flange was less than specified on the motor drawing. This could result in a potential loosening and falling of the motor during a LOCA or seismic event. The licensee is presently evaluating proposed corrective action.

This item will be reviewed during subsequent inspections.

Functional or Program Areas Inspected

Procedures for Handling and Installing Components The inspector requested procedures for review regarding the instal-lation of the NSSS equipment.

It was learned that the Reliance Trucking Company (Reliance) procedures have been received on site and are currently under review for approval by Bechtel and CPCo.

The inspector indicated that he would prefer to review the procedures once they have been approved for use and so will defer such review until next inspection.

In response to questioning, the inspector j

was informed that it is currently planned to start moving and setting of NSSS equipment in April 1978 with the Unit 2 components planned to be set first.

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Regarding installation procedures for other safety related pumping units, the inspector was informed that the procedures are currently being revised to provide additional acceptance criteria and that the revised j

procedure will not be approved and available until some time next month.

It,was indicated that these procedures also would be reviewed

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during the next inspection.

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