ML20151K887

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Provides Results of Review as Supplemental Response to Generic Ltr 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants
ML20151K887
Person / Time
Site: Sequoyah  
Issue date: 07/29/1988
From: Gridley R
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
GL-88-05, GL-88-5, NUDOCS 8808030310
Download: ML20151K887 (4)


Text

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-e TENNESSEE VALLEY AUTHORITY CHATTANOOGA TENNESSEE 374ot SN 157B Lookout Place

<dllL 291988 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.

20555 Gentlemen:

In the Matter of

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Docket Nos. 50-327 Tennessee Valley Authority

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50-328 SEQUOYAH NUCLEAR PLANT (SQN) - SUPPLEMENTAL RESPONSE TO CENERIC LETTER 88-05, "BORIC ACID CORROSION OF CARBON STEEL REACTOR PRESSURE BOUNDARY COMPONENTS IN PWR PLANTS"

. By our letter dated June 1,1988 TVA indicated that a detailed review was being performed of the SQN procedures to determine if enhancements were required to address the new NRC Staff position on boric acid corrosion provided in Generic Letter 88-05.

Pursuant to the requirements of 10 CFR 50.54(f), this letter provides the results of our review as a supplemental response to the generic letter.

- TVA has reviewed applicable site procedures, practices, and instructions pertaining to borated water leakage, including monitoring and inspec'lon.

There are several procedures pertaining to inspecting, evaluating, identifying, reporting, and locating small leaks in systems containing boric acid; however, the combination of these does not address the full scope of the new Staff requirements. The elements that are currently not covered by SQN site procedures are:

(1) determination of principal locations where reactor coolant leaks smaller than technical specification limits may cause degradation of the reactor coolant pressure boundary, (2) engineering evaluations of the effects of leakage on the reactor coolant pressure boundary, and (3) determination of corrective actions to prevent recurrence.

Based on these findings, it was determined that procedural enhancements will be required to address the program elements defined in Generic Letter 88-05.

In order to establish the required programmatic approach to control boric acid degradation. TVA is developing an Engineering Requirements Specification (ERS) that identifies upper-tier engineering requirements for boric acid corrosion control and damage evaluation.

Included in this specification are requirements for identification of susceptible components, monitoring and surveillance, awareness training, leak path determination, prevention of corrosion, and trending analysis.

Extensive use is being made of industry experience and recommendations from industry working groups on boric acid 8808030310 880729 PDR ADOCK 05000327 P

PDC An Equal Opportunity Employer

. U.S. Nuclear Regulatory Commission corrosion during the development of the ERS.

The ERS is scheduled to be issued by September 30, 1988.

Subsequent to the issuance of the ERS, existing plant procedures will be revised and a new plant procedure will be written to incorporate the ERS requirements, as applicable. These procedural enhancements will require an engineering evaluation and determination of corrective actions to prevent recurrence of reported leakage.

SQN's program for boric acid corrosion to comply with the NRC Staff's requirements in Generic Letter 88-05 will be implemented through the above actions by March 1, 1989.

The enclosure provides a summary list of commitments made by TVA in this response.

If you have any questions, please telephone D. L. Williams at (615) 632-7170.

Very truly yours, TENNESSEE VALLEY AUTHORITY

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R. G dley,' Dire tor Nuclear Licensi g and Regulatory fairs Subscribed a en to bgforp I

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... WUL 291986 U.S. Nuclear Regulatory Commission Enclosure cc (Enclosure):

Ms. S. C. Black, Assistant' Director for Projects TVA Projects Division

' U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Mr. P. R. McCoy, Assistant Director for Inspection Programs TVA Projects Division U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Sequoyah Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy Daisy, Tennessee 37379

ENCLOSURE GENERIC LETTER 88-05 SUPPLEMENTAL RESPONSE FOR SEQUOYAH NUCLEAR PLANT (SQN) d

SUMMARY

LIST OF COMMITMENTS 1.

The Enginecting Requirements Specification (ERS) for boric acid corrosion-contesl will be issued by September 39, 1988.

2.

SQN's pectram for boric acid corrosion to comply with the NRC Staff's requirements in Generic Letter 88-05 will be implemented through existing plant procedure revisions and development of a new plant procedure, as applicable, by March 1, 1989.

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