JPN-92-076, Forwards Safety Evaluations in Accordance w/10CFR50.59 to Cable Separation Issues.Evaluations Address Cable Configurations,Alternate Electrical Separation Criteria & Apparent Electrical Separation Anomalies

Forwards Safety Evaluations in Accordance w/10CFR50.59 to Cable Separation Issues.Evaluations Address Cable Configurations,Alternate Electrical Separation Criteria & Apparent Electrical Separation Anomalies

ML20126H458
Person / Time
Site:	FitzPatrick
Issue date:	12/24/1992
From:	Ralph Beedle POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20126H461	List: JPN-92-076, Forwards Safety Evaluations in Accordance w/10CFR50.59 to Cable Separation Issues.Evaluations Address Cable Configurations,Alternate Electrical Separation Criteria & Apparent Electrical Separation Anomalies ML20126H472 ML20126H475 ML20126H490
References
JPN-92-076, JPN-92-76, NUDOCS 9301050214
Download: ML20126H458 (2)

Text

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twear cenmaton December 24,1992 JPN 92-076 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-137 Washington, D.C. 20555

SUBJECT:

James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Qp_bl.g Separation Safety Evaluation 1

Dear Sir:

Three safety evaluations were prepared in accordance with 10 CFR 50.59 to address FitzPatrick cable separation issues. Two of these safety evaluations were performed for cable configurations which may not meet the separation criteria contained in the FitzPatrick FSAR. These evaluations assess operability using the guidance contained in 1 NRC Generic Letter 91 18. The FSAR requires cabling of redundant circuits to he separated by sp7cified distances, The Authority has identified instances were cabling of different color code designations aie not separated by the distances described in the FSAR for redundant circuits. Further work is necessary to determine whether these configurations actually involve redundant circuits. Until this work is completed, these configurations are being considered apparent deviations from the FSAR. The safety evaluations assess them as though they were actual deviations involving redundant circuits. These safety evaluations are being provided to the NRC as attachments to this 4 letter.

The first safety evaluation, titled " Alternate Electrical Separation Criteria, (JAF-SE-92-238, Rev. O)." addresses using a cable separation distance of 1 foot horizontal or 1 foot vertical and a conduit separation distance of 1 inch horizontal or 1 inch vertical as altomate separation criteria. These alternate separation criteria are being used by the Authority to determine operability for these cable configurations on an interim basis in lieu of the separation criteria described in the FitzPatrick FSAR.

The second safety evaluation, titled " Evaluation of Apparent Electrical Separation Anomalies, (JAF-SE-92-236, Rev. O)," addresses potential operability issues associated with 81 additional apparent deviations from the FSAR electrical separation criteria. These ,

apparent deviations involve configurations where cables, conduits, or cable trays of different color code designations are separated by less than 1 foot horizontal or 1 foot vort i cal. This safety evaluation is being used by the Authority to determine operability on an interim basis in lieu of the separation criteria described in the FitzPatrick FSAR.

These safety evaluations reference tests conducted by Wyle Laboratories and provided to the NRC by other utilities. The test report numbers and the associated NRC Public Document Room (PDR) accession numbers are listed below:

9301050214 921224 k PDR ADOCK 05000333 g(

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Wyle Test Report No. 47879-06 8609190299 860527-ADOC 05000400 Wyle Test Report No. 48422-01 8701020118 861219 ADOC 05000445 Wyle Test Report No. 17769 01 8510280349 851022:

ADOC 05000455 The Authority does not have the PDR accession number for the fourth report, Wyle - $

Test Report No. 47906-02, which is also publicly available. The Authority has reviewed these test reports for applicability to the FitzPatrick plant. Cabling used at FitzPatrick is .

either.lEEE-383 or equivalent based upon review of cable specifications and procurement:

documentation. .

These reports are certified and contain affirmations in Soction 8.0 that-they_were -

performed _t y Wyle Laboratories under their 10 CFR 50 Appendix B, Nuclear Quality:

Assurance Program. Also attached is a letter from Mr. J. F. Gloason of Wyle Laborator'es to Mr. K. J. Vehstedt of the New York Power Authority dated December 23,-1992, which -

certifies that the tests were conducted under the Wyle Quality Assurance program. Wyle - ,

Laboratories is an approved vendor to the New York Power Authority with an approved and audited 10 CFR 50 Appendix B Quality Assurance program, if you have any questions, please contact Mr. J. A. Gray, Jr.

Very truly yours,

\- 30 Ralph E. Beedle t

Attachments: - As stated .

1 cc: Regional Administrator U.S. Nuclear-Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Office of the Resident inspector U.S. Nuclear Regulatory Commission -

P.O. Box 136 Lycoming, NY 13093' Mr. Brian C. McCabe Project Directorate 11-Division of Reactor Projects - 1/11 U.S. Nuclear Regulatory Commission Mail Stop 14 B2 Washington, DC 20555