ML20086A760
| ML20086A760 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 11/09/1983 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| GL-83-28, NUDOCS 8311160103 | |
| Download: ML20086A760 (2) | |
Text
r-o TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 374ot 400 Chestnut Street Tower II November 9, 1983 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Denton:
In the Matter of the
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Docket Nos. 50-259 Tennessee Valley Authority
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50-260 50-296 By my letter to you dated November 7,1983 we submitted the response to Generic Letter 83-28 for the Browns Ferry Nuclear Plant. It has been discovered that because of an error in document reproduction that the first page of the response to generic letter item No. 2.1 was not included. Enclosed is that missing page.
Very truly yours, i
TENNESSEE VALLEY AUTHORITY 7i L. M. Mills, anager Nuclear Licensing
' Subscribe d sworn tA,before raetigis day effflb f 64/1983 g/-
M Notary Public
/
My Commission Expires Enclosure oc (Enclosureis U.S. luclear Regulatcry Commission Region II ATTN: James P. O'Reilly, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia ~ 30303 Mr. R. J.-Clark Browns Ferry Project Manager U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda,; Maryland 20814 gl.
l 8311160103 831109 P
gDRADOCK 05000259 1 I
PDR An Equal Opportunity Employer w
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a 2.1 EQUIPMENT CLASSIFICATION AND VENDOR INTERFACE (REACTOR TRIP SYSTEM i
COMPONENTS)
-q Position Licensees and applicants shall confirm that all components whose function-
. ing is required to trip the reactor are identified as safety-related on documents, procedures, and information handling systems used in the pla'nt to control safety-related activities, including maintenance, work orders, and parts replacement.
In addition, for these components, licensees and applicants shall establish, implement and maintain a continuing program to ensure that vendor information is complete, current and controlled throughout the life of '
the plant, and appropriately referenced or incorporated in plant instructions I
and procedures. Vendors of these components should b_e contacted and an inter-face established.
Where vendors can not be identified, have gone out of i
business, or will not supply the information, the licensee or applicant shall assure that sufficient attention is paid to equipment maintenance, replacement,.and repair, to compensate for the lack of vendor backup, to assure reactor trip system reliability. The vendor interface program shall include periodic communication with vendors to assure that all applicable i
information has been received. The program should use a system of positive feedback with vendors for mailings containing technical information. This could be accomplished by licensee acknowledgement for receipt of technical mailings. The program shall also define the interface and division of responsibilities among the licensees and the nuclear and nonnuclear divisions of their vendors that provide service on reactor trip _ system components to assure that requisite control of and applicable instructions for maintenance work are provided.
Response
Presently TVA's Division of Nuclear Power (NUC PR), identifies all i
components whose functioning is require 0 to trip the reactor as safety-related. These components which include t'te reactor protection system,'the solid state protection system, and all other components whose function is. defined as safety-related cM now o2tlined in TVA's '
~l Operational Quality Assurance manual as critical syste'na, structures, or components (CSSC) which is a corporate document.' Each individual
'i Plant has incorporated the applicable portions of this document into their procedures. In addition, TVA's corporate procedures require all.
maintenance or modification activities to be documented prior to' performing the work. This documentation is then reviewed.by the appropriate plant organizations to ensure that it is properly identi-I fled as CSSC or non-CSSC and to ensure that the applicable procedures and quality requirements for the idenitified work will be Ladhered to.
!e Furthermore, NUC PR requires that cll procurement documents be identi-'
fled as pertaining to CSSC or-non-CSSC equipment. These procurement documents are reviewed by plant organizations or division central
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office organizations (depending'on their point of origination) to i
t ensure they'are properly identified and contain the appropriate'and required quality controls and specifications. Depending on the quality. grouping, as outlined in division procedures'that the procure-a ment documents come under, many of them are also reviewed by'other.
division central office organizations to further ensure that they meet l
all requirements.
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