ML20235R034

Notice of Violation from Insp on 870530-0710.Violations Noted:Heat Treating of Yoke of Safety Feature Valve SFV-25004 Not Controlled Using Qualified Procedure & Cable Trays A57E1 & A57015 Had No Cable Tray Edge Bumpers

ML20235R034
Person / Time
Site:	Rancho Seco
Issue date:	09/21/1987
From:	Chaffee A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML20235R007	List: ML20235R004 ML20235R034 ML20235R060
References
50-312-87-20, NUDOCS 8710070772
Download: ML20235R034 (2)

Text

l i .

m NOTICE OF VIOLATION Sacramento Municipal. Utility District Docket No. 50-312 P. O. Box 15830 License No. DPR-54 During an NRC inspection conducted on May 30, 1987 through July 10, 1987, two violations of NRC requirements were identified. In accordance with the

" General Statement of Policy and Procedure for NRC Enforcement Actions,"

10 CFR Part 2, Appendix C, the violations are listed below:

A. 10 CFR 50, Appendix B, Criterion IX, " Control of Special Processes,"

states, in part:

" Measures shall be established to assure that special processes, including ... heat treating, are controlled and accomplished by qualified personnel using qualified procedures in accordance with applicable codes, standards, specifications, criteria and other special requirements."

Quality Assurance Policy Section IX, Revision 0, " Control of Special Processes," Paragraph 3.0, states:

" Appropriate procedure and methods shall be prescribed and implemented to assure that special processes, equipment and personnel are controlled and accomplished by qualified personnel and procedures".

Contrary to these requirements, on June 24, 1987, heat treating of the yoke of safety features valve SFV-25004 was not controlled or accomplished using a qualified procedure. This work was performed under Work Request #1133657 with no specific provisions for heat treating. j 1

This is a severity level IV violation (Supplement 1). l l

B. 10 CFR 50, Appendix B, Criterion X, " Inspection," states, in part: )

"A program for inspection of activities affecting quality shall be established and executed by or for the organization performing the -i activity to verify conformance with the documented instructions, l procedures and drawings for accomplishing the activity ...." l Quality Assurance Policy Section X, Revision 0, " Inspection," states, in paragraph 4.8:

"A construction inspection program will be performed on Class I and '

Environmental Qualified (EQ) equipment to assure construction and installation activities are in conformance to design drawings and specifications ...."

Licensee construction procedure NPEM 8304.8C section 5.1.27 requires that j the minimum bend radius for 4 AWG triplex cable be 1.6 inches. I B710070772 B70921 2 l DR ADOCK 0500

o 1

I ~2-i

/

.i Licensee construction procedure NPEM 5304.7.C section 5.2 requires the  ;

installation of. cable tray bumpers and installation of separation group  ;

color markings.- j

' Contrary to =these requirements, an electrical cable for essential HVAC I air handling unit AH-DG-18 had an electrical cable bend radius of 3/4" in (

the motor terminal. box. In cable trays A57El and A57015 no cable tray i edge. bumpers existed. Electrical pull box H7J2995, which contained an "A" channel safety related cable, was color marked black rather than red, as required..

' This -is a Severity Level IV violation (Supplement 1).

Pursuant to.the provisions of 10 CFR 2.201, The Sacramento Municipal Utility District. is hereby required to submit a written statement or explanation to the U.S.' Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555 with a copy to the NRC Resident Inspector, Anthony D'Angelo, within 30 days of the date of the letter transmitting this Notice. This reply should be clearly marked as a " Reply to a Notice of.

Violation" and should include. for each violation: (1) the reason for the violation if admitted, (2) the corrective steps that have been taken and the results. achieved, (3) the corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved. If an -

adequate reply is n'ot received within the time specified in this Notice, an order may be issued to show cause why the license should not be modified, suspended, or revoked or why such other action as may be proper should not be taken. Consideration may be given to extending the response time for good cause shown.

FOR THE NUCLEAR REGULATORY COMMISSION B . F_ h A A. E. ChaffgJ7, Deputy Directhr Division orReactor Safety and Projects DatedatgainutCreek, California day of Seo f.1987 this 9:

j l'

_ _ - - _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ -