ML20029B107

From kanterella
Jump to navigation Jump to search
Notice of Violation from Insp on 901210.Violation Noted: Design Review Performed to Verify Adequacy of Design Failed to Identify That Proper Coordination Not Achieved Between Newly Installed Fuse & Feeder Circuit Breakers
ML20029B107
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 02/19/1991
From: Julian C
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20029B095 List:
References
50-416-90-24, NUDOCS 9103050430
Download: ML20029B107 (2)


Text

-

a -+ _. -..~. >

..aa w..

.~=.s ns u

...an..

ENCLOSURE NOTICE OF VIOLATION System Energy Resources, Inc.

Docket No. 50 416 Grand Gulf License No.-

NPF-29 During an NRC inspection conducted on December 10, 1990, a violation of NRC requirements was identified.

in acccrdance with the " General Statement of Policy and Precedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1990), the violation is listed below:

10 CFR 50 Appendix B, Criterion III, and the accepted QA Program require establishing measures to assure that applicable regulatory requirements and the design bases are correctly translated into specifications, drawings, procedures, and instructions.

These measures shall i nclude design controls which provide for verifying or checking the adequacy of design, such as by the performance of design reviews; by the use of alternate or simplified calculational methods; or the performance of a suitable testing program.

Section 3.5.9 of the Operational Quality Assurance Program requires the use of procedures which shall include requirements to verify that the design is adequate and that it meets the specified design inputs.

The QA Program endorses Regulatory Guide 1.64 and ANSI N45.2.ll-1974 Section 6.0 of this standard requires that designs be verified.

Contrary to the above, on May 12, 1988, Design Change Pat.tage 87/0034 Revision 0, was issued for construction and resulted in the installation

.of a 1200 Ampere fuse in series with the battery-to-bus feeder circuit breaker for both Divisions I and TI of the 125 VDC Main Distribution

_ Systems. The design review perfonled to verify the adequacy of the design failed to identify that proper cocrdihation was not achieved between the newly installed fuse and existing feeder circuit breakers for the cattery chargers (2 per bus); and the static inverter (1 per bus), in that the short time characteristic of these fuses precluded proper coordination.

This failure to verify tha technical adequacy of the design resulted in the system as modified beir.g deficient in that a single fault at either one of the three existing feeders could result in operation of the 1200 Ampere fuse and disabling of a complete 125 VDC Division.

This is a Severity level IV violation (Supplement I ).

Pursuant to the provisions of 10 CFR 2.201, System Energy Resources, Inc. is hereby required to submit a written statement or explanation to the U.S.

i Nuclear Regulatory Conn.ission, ATTN:

Document Control Desk, Washington, D.C.

20555 with a copy to the Regional Administrator, Region 11, and if applicable, a copy to the NRC Resident inspector, Grand Gulf within 30 days of the date of 1

the letter transmitting this Notice of Violation (Notice),

This reply should be clearly marked as a " Reply to a Notice of Violation" and should include [for 9103050430 910219 PDR

/sDOCK 05000416 O

PDR

,., - _. ~

System Energy Resources, Inc, 2

Docket No. 50-416 Grand Gulf License No, NPF-29 each violation]:

(1) the reason for the violation, or, if contested, the basis for disputing the violation, (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 acnieved.

If an adequate reply is not receiveJ 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. Where good cause is shown, consideration will be given to extending the response time.

FOR THE NUCLEAR REGULATORY COMMISSION ht

-/

T q

Caudle A Julian, Chief Engineering Branch Division of Reactor Safety Dated at Atlanta, Georgia this19thday of February 1991 r-,

. _. -