IR 05000361/1978011

From kanterella
Jump to navigation Jump to search
Insp Repts 50-361/78-11 & 50-362/78-08 on 780906-08.No Noncompliance Noted.Major Areas Inspected:Open Items from Fastener Investigation,Mirror Image Problems & Code Interpretations
ML13309A582
Person / Time
Site: San Onofre  
Issue date: 09/21/1978
From: Albert W, Elin J, Haynes R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML13309A581 List:
References
05-362-78-08, 5-362-78-8, 50-361-78-11, NUDOCS 7811010037
Download: ML13309A582 (5)


Text

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

REGION V

50-361/78-11 Report N /78-08 50-361 CPPR-97 Docket N License No. CPPR-98 Safeguards Group Licensee:

Southern California Edison Company 2244 Walnut Grove Avenue Rosemead, California 91770 Facility Name:

San Onofre Units 2 & 3 Inspection at: Corporate Office and Construction Site Inspection Cond d:

September 6:-8, 197$

Inspectors

//

/1 2/

Ta o

  • ne or at-g9 A. 0.El i, ea tor Inspetor Dat Signed Approved By: (. Q-197S R. C. Haynesch-iEhf, Projects Section, Reactor Date Signed Construction and Engineering Support Branch Summary:

Inspection on September 6-8, 1978 (Report Nos. 50-361/78-11 and 50-362/78-08)

Areas Inspected:

Special announced inspection of construction activities, including open items from fastener investigation; open items regarding mirror image design problems and code interpretation; and NRC circular and bulletin follow-u Results: In the three areas inspected, no items of noncompliance or deviations were identifie o037 IE:V Form 219 (2)

DETAILS 1. Individuals Contacted a. Southern California Edison Company (SCE)

  • P. A. Croy, Site Quality Assurance Supervisor
  • L. L. Seyler, Project Quality Assurance Supervisor
  • A. E. Talley, Quality Assurance/Quality Control Superviso R. P. Frick, Quality Assurance Engineer
  • H. B. Ray, Manager, Quality Assurance K. L. Baldwin, Quality Assurance Engineer C. K. Balog, Systems Engineer B. Katz, Nuclear Engineer b. Bechtel Power Corporation (Bechtel)

C. A. Blum, Quality Control Manager

  • J. R. Caldwell, Project Quality Assurance Supervisor J. Mattimoe, Lead Quality Control Engineer L. French, Inspector L. G. Hersh, Assistant Project Engineer
  • Denotes those attending exit intervie. Licensee Action on Previous Inspection Findings a. (Closed) Open Item 50-361/78-05: Disposition of Nonconformance Reports Generated from User Test Programs for Fastener All nonconformance reports generated to date were examined to assure disposition in accordance with provisions of licensee's and Bechtel 's QA programs. No items of noncompliance or deviations were foun b. (Open) Open Item 50-361/78-05: Routine Receiving Test Progra Implementation of the user test program as defined by Bechtel memo of 2/6/78, "Bolt Testing Program," was further examine The inspector found that the program was being implemented as described in the program, however, the program did not specify any technique for sample selection, nor were inspectors utiliz ing any specific technique. See exit intervie *

-2 c. (Closed) Open Item 50-361/78-05: Installation Inspection Criteri Modification of Bechtel QCI No. 107 to assure bolt thread projection in accordance with AISC practices was confirme The licensee reported that reinspection of several hundred bolted connections revealed only two cases of questionable thread projectio d. (Closed) Open Item 50-361/77-10. In Paragraph 9 of the reference report, the nonconformances discussed represented a third party inspector question regarding the interpretation of ASME Section III, NB-520 The question was whether or not the code required the full removal of internal cladding for a distance of 1/2 inch on each side of a weld. Letters from Weber and Millman of ASME, dated August 19, 1977 and May 1, 1978, respectively, stated that roll bond cladding does not require complete removal on the internal surface within 1/2 inch of the weld root and that indications at the clad-base material interface are

"...considered to be non-relevant mechanical discontinuities..."

The inspector examined the various communications on the sub ject and had no further question e. (Open) Open Item 50-361/77-10: Documentation of Special Mirror Image Design Revie A report on the completion of this review for mechanical components showed only a minor finding regarding the mounting of the regenerative heat exchanger. The electrical review remains to be completed, therefore, the item will remain ope The inspector had no questions on the review activity completed thus fa. Bulletin and Circular Follow-up Action of the licensee regarding bulletins and circulars issued by the NRC during the past twelve months was examined at the SCE cor porate office in Rosemead, Californi The methods of routing bulletins and circulars was discussed with emphasis on the methods of receipt, review and forwarding to appro priate management. Additionally, records were examined to ascertain that information discussed in the response to bulletins was accurate and represented actions taken by the license In all the instances examined, the inspector found prompt response, adequate review and appropriate action by the licensee. However, in some cases, corrective actions identified in the licensee's responses to the NRC remained to be complete Although, as noted above, all bulletins and circulars issued during the past 12 months were audited, the action of the licensee regard ing the following construction oriented bulletins and circulars was examined in detail:

a. Circular 78-06; Common Mode Flooding of ECCS Equipment Room b. Circular 78-04; Installation Errors That Could Prevent Closing of Fire Door c. Circular 78-03; Packaging Greater.Than Type "A" Quantities of Low Specific Activity Radioactive Materials for Transpor d.Bulletin 78-06; Defective Cutler-Hammer, Type "M" Relay e.Bulletin 78-05; Malfunctioning of Circuit Breaker Auxiliary Contact Mechanis f.Bulletin 78-04; Environmental Qualification of Certain Stem Mounted Limit Switche g.Bulletin 78-02; Terminal Block Qualificatio h.Bulletin 78-01; Flammable Contact - Arm Retainers in CR120A Relay i.Bulletin 77-08; Assurance of Safety and Safeguards During an Emergenc j.Bulletin 77-07; Containment Electrical Penetration Assemblies at Nuclear Power Plants Under Constructio k.Bulletin 77-06; Potential Problems with Containment Electrical Penetration Assemblie. Bulletin 77-05A; Supplement to 77-0 m.Bulletin 77-05; Electrical Connector Assemblie n.Bulletin 77-04; Calculational Error Affecting the Design Performance of a System for Controlling pH of Containment Sump Water Following a LOC o.Bulletin 77-02; Potential Failure Mechanism in Certain W AR Relay. Management Interview The scope and findings of the inspection were discussed with Messr H. B. Ray, Jr., J. R. Caldwell and others at the close of the inspec tion. The licensee indicated that the inspector's concern regarding sampling techniques would be addressed. The NRC resident inspector was advised and will provide follow-up action.