ML20150D375

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Responds to Violation Noted in Insp Repts 50-259/88-10, 50-260/88-10 & 50-296/88-10.Violation Denied.Procedure Adequately Ensures Proper Mgt Approval & Technical Accuracy of Info Provided to NRC
ML20150D375
Person / Time
Site: Browns Ferry  
Issue date: 07/06/1988
From: Gridley R
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8807130445
Download: ML20150D375 (4)


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TENNESSEE VALL.EY AUTHORITY CH ATTANOOG A. TENNESSEE 37401 SN 1578 Lookout Place JUL.061988 U.S. Nuclear Regulatory Commission ATTN:

Document Control Desk Washington, D.C.

20555 Gentlemen:

In the Matter of

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Docket Nos. 50-259 Tennessee Valley Authority

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50-260

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50-296 BR0HNS FERRY NUCLEAR PLANT (BFN) UNITS 1, 2. AND 3 - NRC INSPECTION REPORT NOS. 50-259/88-10, 50-260/88-10, AND 50-296/88-10, - RESPONSE TO NOTICE OF VIOLATION This letter provides TVA's response to the letter from K. P. Barr to S. A. White dated June 3, 1988, which transmitted the subject report citing TVA with a violation in the area of procedural guidance for the preparation of licensing submittals.

As described in the enclosure to this letter, TVA dentes the violation on the basis that TVA's procedures provide sufficient guidance to ensure proper authorization for releasing licensing information to NRC.

If you have any questions, please telephone Carroll McFall at (205) 729-2046.

l Very truly yours, TENNES EE VALLEY AUTHORITY r

R.

ridley, Otr4 r

Nuclear Licensing and Regulatory Affairs Enclosure I

cc:

See page 2 f

8807130445 880706 gDR ADOCK 05000259 PNU t

An Equal Opportumty Employer

U.S. Nuclear Regulatory Commission JUL 061988 cc (Enclosure):

Mr. F. R. McCoy, Assistant Director for Inspection Programs TVA Projects Division U.S. Nuclear Regulatory Commission Region 11 101 Marietta Street, NH, Suite 2900 Atlanta, Georgia 30323 Hs. S. C. Black, Assistant Director for Projects TVA Projects Division U.S. Nuclear Regulatory Commission One White Flint, North 1:555 Rockville Pike Rockville, Maryland 20852 Browns Ferry Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637 Athens, Alabama 35611

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. ENCLOSURE RESPONSE TO NRC INSPECTION REPORT NOS. 50-259/88-10, 50-260/88-10, AND 50-296/88-10 LETTER FROM K. P. BARR TO S. A. WHITE DATED JUNE 3, 1988 Violation

' Technical specifications 6.8.1.1.a and 6.8.1.1.j reautre the licensee to establish, implement, and maintain administrative procedures which control technical and cross-disciplinary review.

Impilcit in this requirement is that the procedures be adequate for the activity involved.

Administrative procedure PMP 0602.01, Management of TVA's Interface with the Nuclear Regulatory Commission, addresses the licensee's responsibilities and requirements for the preparation of licensing submittals.

Contrary to the above, administrative procedure PHP 0602.01 was found to be inadequate in that it lacked any requirement or guidance on the use of tentative.or draft information in preparation of licensing submittals.

This deficiency contributed to the licensee's submittal of draft information for NRC review on March 23, 1988.

The licensee's calculations used to evaluate the effects of a postulated fuel drop accident did not receive full independent verification nor approval for issuance untti two days af ter issuance of the submittal.

.TVA Response 1

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Admission or Dental of the Violation TVA denies the violation as stated.

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Reasons for the Dental of the Violation PMP 0602.01 establishes the review and approval process for communications with NRC.

The procedure requires that information submitted to the NRC be technically correct and approved by management for release.

The calculations which supported the March 23, 1988 submittal had been prepared more than a week before the transmittal to NRC.

Sufficient checking and design verification had been done to ensure technical 1

adequacy.

The signatures which had not been obtained as of the submitial i

date were thase associated with minor verification checks and final administrative review.

The calculation results were released through a i

Quality Information Release (QIR), which provides for an appropriate technical and management review.

Formal issuance of the calculations was completed on March 25.

Thus, by virtue of the technical information being released in accordance with TVA procedures and its having appropriate technical and management review before being submitted to NRC, TVA considers that the requirements of PMP 0602.01 were tre t.

Furthermore, this procedure adequately ensures the proper management approval and technical accuracy of informativo provideo to NRC.

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TVhalsotakesexceptiontotheviolationwith'respecttothe-quoted technical specification provisions. Technical specification 6.8.1.1.a is the implementing clause for procedures referenced-in Appendix A to Regulatory Guide 1.33, Revision 2, which applies'to procedures for typical safety-related activities associated with an operating nuclear power plant. PMP-0602.01, which provides guidelines for TVA's interface with NRC, is clearly outside the scope of activities that must be covered by written procedures under this regulatory guide.

Technical specification 6.8.1.1.j was approved as part of a recent general revision to the administrative section of the technical specificutions and requires that administrative procedures be maintained which control the technical and cross-disciplinary review of other plant procedures. Our review indicates PHP 0602.01 does not fit into this category of procedures.

Rather, PHP 0602.01 implements TVA Office of Nuclear Power policy with respect to the interface of TVA and NRC on nuclear licensing matters.

This distinction is substantiated by the NRC Safety Evaluation R6 port (SER) for the subject technical specification change dated September 11, 1987.

In secticn 2.9 of the SER, NRC recognized the role the Plant Operations Review Committee would have in reviewing administrative procedures for the control of the technical and cross-disciplinary review of plant specific written procedures.

Based on the above, TVA does not consider that either technical specification 6.8.1.1.a or 6.8.1.1.j was violated, 1

I In summary, the calculation results submitted to the NRC were accurate and received an appropriate level of technical and management review.

PHP 0602.01 provides sufficient guidance to ensure proper authorization for release of licensing information. Additionally, the referenced technical specifications were not violated.

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