IR 05000369/1979003

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IE Insp Repts 50-369/79-03 & 50-370/79-02 on 790109-11.No Noncompliance Noted.Major Areas Inspected:Category 1 Structures & Supports Outside Containments,Containment Penetrations,Main Steam Line Relief Valve Assembly & Dam
ML19289D829
Person / Time
Site: McGuire, Mcguire  
Issue date: 02/05/1979
From: Bryant J, Swan W
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML19289D822 List:
References
50-369-79-03, 50-369-79-3, NUDOCS 7903140569
Download: ML19289D829 (6)


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tAnarou UNITED STATES

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NUCLEAR REGULATORY COMMISSION

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9 E 101 M ARIETTA STREET, N.W.

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ATLANTA, GEORGI A 30303

es,,e Report Nos.: 50-369/79-3, 50-370/79-2 Licensee: Duke Power Company P. O. Box 33189 422 South Church Street Charlotte, North Carolina 28242 Facility Name: McGuire Nuclear Station, Units 1 and 2 Docket Nos.: 50-369, 50-370 License Nos.: CPPR-83, CPPR-84 Inspection at McGuire Site, Lake Norman, North Carolina J

Inspector:

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[ # M /* M 8 W. B. Swan Date Signed

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Approved by:

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g/ f, /9 ) 9 J.g'. Bryant, Se'ction Chief, RCES Branch Date Signed

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SUMMARY

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Inspection on January 9-11, 1979 Areas Inspected This routine unannounced inspection involved 17 inspector-hours onsite in the areas of Category I structures and supports outside the containments; containment penetrations; main steam line relief valve assembly for Unit 1; and the standby nuclear service water dam.

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Results Of the four areas inspected, no apparent items of noncompliance or deviations were identified.

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DETAILS 1.

Persons Contacted Licensee Employees

  • J. C. Rogers, Construction Project Manager
  • G.

W. Grier, Construction Project Engineer

  • W. O. Henry, Manager, Construction Quality Assurance
  • E. B. Miller, Senior QA Engineer
  • K. A. Kisida, QA Engineer T. E. Touchstone, Senior Construction Engineer E. B. Abrams, Assistant General Superintendent R. L. Payne, Supervising Technician, Civil QC W. R. Lovingood, Civil Engineer R. D. Hall, Civil Engineer B. F. Owens, Electrical QC Inspector
  • Attended exit interview.

2.

Exit Interview The inspection scope and findings were summarized on January 11, 1979 with those persons indicated by an asterisk in Paragraph I above.

3.

Licensee Action on Previous Inspection Findings Not inspected.

4.

Unresolved Items Unresolved items were not identified during this inspection.

  • 5.

Independent Inspection Effort (a) A follow on inspection of the standby nuclear service water dam was made in company with the essigned civil engineer.

Erosion control on the downstream face of the dam was found to be adequate.

Effluent water from seepage draws was clear and appeared to be flowing at a steady rate of about 15 gallons per minute.

No settlement or realignment of the embankment had been recorded.

(b) The main steam line relief valve assembly for Unit 1, outside the containment, was examined for measures designed to resist reactive forces from steam discharge.

It was determined that adequate restraints had been installed to protect the assembl..

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-2-Inspection of the dam and the relief valve assembly disclosed no noncompliance or deviation from requirements.

6.

Safety Related Structures (Structural Steel and Supports II) - Observation of Work and Work Activities Units 1 and 2 McGuire structures in this category are limited and have been completed.

The inspector chose to inspect for both units the reinforced concrete base of the reactor refueling water storage tank, the concrete base of the reactor makeup water storage tank, and the structural steel supports for the main steam lines adjacent to the containment and those on the roof of the auxiliary building. A visual inspection was made, controlling documents were reviewed and quality records were reviewed for the completed work.

The controlling documents included:

a.

Drawing No. MC-1385-01, Revision 15, " Misc. Yard Structures, Reactor Refueling Water Storage Tank Foundation, Reactor Makeup Water Storage Tank Foundation, Concrete and Reinforcement".

b.

PSAR Section 3.0; PSAR figures 3.6.5-3.6.5-4 and 3.8.2-5 c.

Regulatory Guides 1.26; 1.38; 1.55; 1.58; 1.94; 1.127 and 1.142 d.

Construction Procedure 57; Revisica 11, " Welding of Structural Steel, Miscellaneous Steel, and other Steel Construction for Nuclear Structures and Certain Non-Nuclear Structures".

e.

Concrete Mixes from Specification MCS-1101.00-1 f.

Drawings MC-1220-9, Revision 1; MC-1220-10, Revision 2; and MC-1220-11, Revision 2, which direct the construction of main steam and feedwater pipe supports.

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Construction Procedure 18-A, Revision 2, " Inspection of Structural Steel Erection" h.

Structural Steel Erection Inspection Report M-18A i.

QA Procedure M-2, " Inspection of Design Concrete" In the visual inspections of completed structures and pertinent document review, no evidence of noncompliance with requirements or deviation from commitments was foun. _.... _ _ _ _.. ~.. _..

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-3-7.

Safety Related Structures (Structural Steel and Supports 1) - Review of Quality Records for Unit I and Safety Related Structures (Structural Steel and Supports II) - Review of Quality Records for Units 1 and 2 After referring to the documentation requirerents of the controlling documents listed in paragraph 6, the inspector reviewed quality records including:

a.

Prepour site inspection reports for the reactor refueling water storage tanks and the makeup water storage tank.; for Units 1 and 2, for inspections made in April, August and September of 1974.

b.

Structural Steel Erection Inspection Report Form 18A, dated March 25, 1977, for two Supports, Mark

"G",

at elevation 783'

+8" for main steam lines at exits from containment and two supports, Mark

"E",

and five supports, Mark "F", at elevation 784

'+0" on roofs of auxiliary buildings for Units 1 and 2.

The records review identified no nonconformances or deviations.

8.

Containment (Penetrations) - Observation of Work and Work Activities (Unit 1)

Unit 1 control was transferred from Duke Construction to Duke Power Production (Operations) Control in 1976. Unit I was under systems hot fuctional test during this inspection.

Inspections of containment penetrations were made by AEC-NRC inspectors and reported in 1974 and 1976.

During this follow-on inspection the inspector made a visual inspection of the main steam line penetrations and the completed equipment hatch which was installed after the construction block out of the liner was closed.

Design and quality requirements for the liner and its penetrations were stipulated in Section 3 and 17 of the PSAR. These were supplemented by

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requirements shown on the procurement specifications and drawings, the fabricator's detail drawings and the electrical penetration supplier's documents. These documents included:

a.

Construction Procedure (C.P.) 381, " Installation Procedure for Electric Penetration Types B, C, D, E, F, G, H, J, K, L and M" b.

Procedure M-7, " Containment and Tank Erection Inspection" c.

Specification MCS-1390.01-00-0046, dated May 23, 1977, " Procedure for Installation of Type A (6900 volt) Electric Penetration Assemblies."

d.

Drawing MC-1042-8, Revision 5, " Containment Vessel - Units 1 and 2, Equipment Hatch and Personnel Locks."

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Specification HCS-1132.00-1, " Containment Vessel Access Openings" f.

Drawing MC-1042-2, Revision 29, " Reactor Building Units 1 and 2, Containment Vessel Penetration Details". This sheet tabulates all penetrations by type.

g.

Drawing MC-1042-1, Revision 29, " Reactor Building Units 1 and 2, Containment Vessel, Cylindrical Plate Layout and Penetration Location."

h.

Procedure M-41 " Installation of Electrical Conduit and Components",

Form M-41B i.

D. G. O'Brien, Incorporated, " Manual for Electric Penetrations" j.

Regulatory Guide 1.63, Revision 2, " Electric Penetration Assemblies in Containment Structures for Light-Water-Cooled Nuclear Power Plants".

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5.2, " Receiving, Handling and the Issuing of Mechanical Penetrations" 1.

C. P. 53, " Erection of Personnel Air Locks MK C152 and MK C392" m.

C. P. 71, "The Installation of Cold and Spare Mechanical Penetrations" C. P. 84, '"The Installation of Hot Mechanical Penetrations Type I n.

Main Steam and Type II Feedwater" o.

C. P.105, " Repair of Stainless Bellows of Mechanical Penetrations" p.

C. P.114, "The installation of Electrical Penetration Flanges" q.

C. P. 380, " Equipment Hatch Assembly and Installation'

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From observation of completed work and review of NRC and Duke documents the inspector cor.cluded that adequate controls had been imposed on installation of penetrations.

No noncompliances or deviations were identified during this follow on inspection.

9.

Containment (Penetrations) - Observation of Work and Work Activities Unit 2 Two inspections of penetration installation work were made by NRC (AEC)

in 1974. Activity on this unit has been resumed after long interruption.

This follow on inspection involved observation of the work of installation of containment liner plates, with circular cut out, in the construction

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