ML20054E752

Responds to NRC Re Violations Noted in IE Insp Rept 50-382/82-07.Corrective Actions:Insp of Cables 32366J- SB,32366G-SB & 32366F-SB Revealed No Cable Damage.Memo Issued Cautioning Personnel Re Potential for Damage

ML20054E752
Person / Time
Site:	Waterford
Issue date:	05/21/1982
From:	Mclendon G LOUISIANA POWER & LIGHT CO.
To:	Madsen G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20054E744	List: IR 05000382/1982007 ML20054E752
References
Q-3-A35.02.01, W3K-82-0294, W3K-82-294, NUDOCS 8206140141
Download: ML20054E752 (4)

Text

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .

D Louisiana POWER & LIGHT

,42 o<<AmoNoe s,ees, P O BOX 6008

• NEW ORLEANS. LOUISIANA 70174 * (S04) 366-2345

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t May 21, 1982 G. D. McLENDON Senior Vice President W3K-82-0294 Q-3-A35.02.01 Mr. G. L. Madsen, Chief, Reactor Prajects Branch, Region IV U. S. Nuclear Regulatory Commission 611 Ryan Plaza Dri;e Suite 1000 Arlington, Teras 76012

SUBJECT:

Waterford SES Unit 3 USNRC Inspection Report 50-382/Rpt. 82-07

Dear Mr. Madsen:

The following information regarding the violations cited by the USNRC Inspectors in IE Inspection Report No. 50-382/Rpt. 82-07 dated April 13, 1982, is herewith submitted:

Criterion V of 10 CFR 50, Appendix B, states that, " activities affecting ,

quality shall be prescribed by instructions, procedures or drawings of a type appropriate to the circumstances and that these activities shall be accomplished in accordance with these instructions, procedures, or drawings."

Ebasco Care and Maintenar.ce Instruction CMI #150, " Emergency Diesel Generator and Control Panels," requires that equipment be protected from damage.

Contrary to the above, the NRC inspector observed on March 14, 1982, that the following conditions existed:

1. The following cables entering Emergency Diesel Generator, 3B-S, Generator Control and Relay Panel through a vertical conduit run in the floor of the cabinet appear to have been stepped on, in that, the insulation on the cables was flattened where they exit the conduit.

The cables are unprotected f rom the conduit to the terminal board area on the side of the panel.

32366J-SB 32366G-SB 32366F-SB (2 cables) l -.

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This is a Severity Level V Violation j's my 251982  ;

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PDR ADOCK 05000382 G PDR

. _ _ _ _ _____ __________ _____ ____ __ ____________ _j

. o Mr. G. L. Madsen Page 2 The following information is submitted:

Corrective Action Taken and the Results Achieved:

A review of quality control inspection records reveal that at the time of the Fischbach & Moore Quality Control inspection, the cables exiting the vertical conduit were acceptable as per design drawing requirements.

Cables 32366J-SB, 32366G-SB and -32366F-SB have been inspected by LP&L for 2xcessive bend radius, damage to jacketing,-and visible damage.

There is none. Additionally, a continuity check was made from conductor to ground and conductor-to-conductor. These tests indicate that there is no damage to cables.

Corrective Action Taken to Preclude _ Repetition:

A visual examination was made in Emergency Diesel Generator 3A-S with no damage being found. LP&L has issued a memorandum cr ' 'oning personnel about

~

the potential for damage which could be done when' :ning within control panels.

Date When Corrective Action Will Be Achieved:

Corrective action complete as of this date.

2. Junction box covers were not installed on -Emergency Diesel. Generator 3B-S Junction Boxes JB-1.and JB-2. , 4 _

i J y, This is a Severity Level V Violation (Supplement?II.E.).

4- :P 7 ,

The following information is submitted:

I Corrective Action Taken and the Re'sultd Achieved: [

Junction box covers are insta? 'ed on all junction boxes on Emergency Diesel Generator 3B-5.

Emergency Diesel Generator 3A-5 was inspected and covers have been installed.

Corrective Action Taken to Preclude Repetition Surveillance activities are in effect to identify and correct this type of problem.

Date When Corrective Action Will Be Achieved Corrective action complete as of this date.

Mr. G. L. Madsen Page 3 If you have any questions concerning this response, please advise.

Very truly yours, G. D. McLendon Senior Vice President GDMcL:LLB:grf 1

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, , UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of ).

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Louisiana Power & Light Company ) D(eket No.~50-382.

Waterford 3 Steam Electric Station- )

AFFIDAVIT G. D. McLendon being duly sworn, hereby deposes and says that he is Senior Vice President of Louisiana Power & Light Company; that he is duly authorized to sign and file with the Nuclear Regulatory Commission the attached response (W3K82-0294) to the Notice of Violation identified in NRC Inspection Report 82-07; that he is familiar with the content thereof; and that the matters set forth therein are true and correct to the best of his knowledge, information and belief.

e h G. D. McLendon "

x Senior Vice President STATE OF LOUISIANA)

) se PARISH OF ORLEANS )

Subscribed and s a Publicdu and for the arish and State above named this rn/to before

/tf' day of me, /v)'oJayy

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/ uw My Commission expires MM