ML20205A009

Notice of Violation from Insp on 880829-0902.Violation Noted:Electrical Equipment Files Did Not Adequately Address Instrument Accuracy

ML20205A009
Person / Time
Site:	Crystal River
Issue date:	10/13/1988
From:	Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20204K133	List: IR 05000302/1988027 ML20204K131 ML20205A009
References
50-302-88-27, NUDOCS 8810250355
Download: ML20205A009 (2)

Text

. _ _ - - -

ENCLOSURE 1 NOTICE OF VIOLATION Florida Power Corporation Docket No. 50-302 Crystal River License No. DRP-72 !

During the Nuclear Regulatory Comission (hRC) inspection conducted on August 29 - September 2, 1988, 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 (1987), the v1olations are  !

listed below:

A. 10 CFR 50.49(d),(f) and (j), respectively, require in part that: (1)a j list of electric equipment important to safety be prepared, and infonna- j tion concerning performance specifications, electrical characteristics and postulated environmental conditions for this equipment be maintained in a qualification file, (2) each item of electric equipment important to safety shall be qualified by testing of, or experience with identical or >

similar equipment, and qualifications shall include a supporting analysis  !

4 to show that the equipment to be qualified is acceptable, and (3) a record '

of the qualification of the electric equipment shall be maintained in a

qualification file in an auditable form to permit verification that the '

j required equipment is qualified and that the equipment meets the specified performance requirements under postulated environmental conditions. '

Contrary to the above, at the time of inspection the licensee did not have: (1) components associated with the Main Feedwater Startup Block  !

I Valves (tag number FWY-33 and FWV-36) on the list of electric equipment 4

important to safety (Master List of qualified electrical equipment),

(2) the components tested in the installed configuration, and (3) documen- t 1 tation to verify qualification of the components in an auditable form. The i unqualified components are the motor operator, motor starters, valve  !

t control stations, and terminal boxes, i l

This is a Severity Level IV violation (Supplement !).

B. 10 CFR 50.49(f) and (k) respectively require that: (1) each time of l electric equipment important to safety shall be qualified by testing of, t or experience with, identical or similar equipment, and the qualification '

j shall include a supporting analysis to show that the equipment to be qualified is acceptable, and (2) electric equipment important to safety  :

j which was previously required to be qualified in accordance with 00R  ;

1 Guldelines need not be requalified to 10 CFR 50.49. 00R Guidelines,  ;

, Section 5.2.5, requires that operational modes tested must be representa-  !

tive of the cctual application requirements and that failure criteria j should include indrument accuracy requirements based on the maximum error i assumed in the plant safety analyses. [

~

0010250355 881013  !

PDR ADOCK 05000302 G PNU ,

- e. ,

Fiorida Power Corporation 4 Docket No. 50-302 Crystal River License No. ORP-72 Contrary to the above, at the time of the inspection FPC EQ files did not adequately address instrument accuracy in that the files did not contain documentation specifying requi red accuracies for actual application requirements (i.e., all contributions of error in an instrument loop) and comparisons of those accuracies with instrument errors from LOCA type tests.

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

Pursuant to the provisions of 10 CFR 2.201, Florida Power Corporation is hereby required to submit a written statement or explanation to the Nuclear Regulatory Comission, ATTN: Document Control Dask. Washington, DC 20555, with a ccpy to the Regional Administrator, Regior. !!, and a copy to the NRC Resident Inspector, Crystal River, 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) admission or den'al of the violation, (2) the reason for the violation if admitted (3) the cor"ective steps which have been taken and the results achieved. (4) the correctO<e steps which will be taken to avoid further violations, an6 (5) the date wnen full compliance will be achieved. Where good cause is shown, consideration will be given to extending the response time. If an adequate reply is not 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 he taken.

Security or safeguards information should be submitted as an enclosre to facilitate withholding it from public disclosure as required by 10 CFR 2.790(d) or 10 CFR 73.21.

FOR T E NUCLEAR REGULATORY COMMISSION 1

b 4

i Alan R. Herdt, Chief Engineering Branch <

Division of Reactor Safety )

Dated at Atlanta, Georgia I this j[dayof gg 1988 i

l 1

__