ML17303B149

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Responds to Generic Ltr 88-05 Re Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants
ML17303B149
Person / Time
Site: Palo Verde  Arizona Public Service icon.png
Issue date: 05/27/1988
From: Van Brunt E
ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
GL-88-05, GL-88-5, NUDOCS 8806010278
Download: ML17303B149 (8)


Text

.bCCELZRATED DISTRIBUTION DEMONST1410N SYSTEM REGULATORY INFORMATXON DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:8806010278 DOC.DATE: 88/05/27 NOTARIZED: YES DOCKET SI FACIL:STN-50-528 Palo Verde Nuclear Station, Unit 1, Arizona Publi 05000528'TN-50-529 Palo Verde Nuclear Station, Unit 2, Arizona Publi 05000529 STN-50-530 Palo Verde Nuclear Station, Unit 3, Arizona Publi 05000530 AUTH.NAME AUTHOR. AFFILIATION VAN BRUNT,E.E.

Arizona Nuclear Power Project (formerly Arizona Public Serv RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Responds to Generic Ltr 88-05 re boric acid corrosion of carbon steel reactor pressure boundary components in PNRs.

DISTRIBUTION CODE:

AOOID COPIES RECEIVED:LTR I

ENCL L SIZE: 3 TITLE: OR Submittal:

General Distribution NOTES:Standardized plant.

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Standardized plant.

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05000528'8 05000529 05000530/

RECIPIENT XD CODE/NAME PD5 LA LICITRA,E INTERNAL: ACRS NRR/DEST/ADS 7E NRR/DEST/ESB 8D NRR/DEST/RSB 8E NRR/PMAS/ILRB12 OGC 15-B-18 RES/DE/EIB EXTERNAL: LPDR NSIC NOTES COPIES LTTR ENCL 1

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Arizona Nuclear Power Project P.O. BOX 52034

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PHOENIX, ARIZONA85072-2034 161-01058-EEVB/ACR/JMQ May 27, 1988 Docket Nos.

STN 50-528/529/530 Document Control Desk U.S. Nuclear Regulatory Commission Mail Station Pl-137 Washington, D.C.

20555

Reference:

Letter from F. Miraglia, NRR, to All Licensees of Operating PWRs an'd Holders of Construction Permits for PWRs, dated March 17, 1988

Subject:

Generic Letter 88-05

Dear Sirs:

Subject:

Palo Verde Nuclear Generating Station Units 1, 2 and 3

Generic Letter 88-05 Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components In PWR Plants File: 88-005-026;< 88-010-026 The referenced letter requested a response to provide assurances that a Boric Acid Corrosion Program is in place or a schedule for implementing such a program if one is not in place.

The referenced letter further describes what the program should entail.

ANPP is addressing Generic Letter 88-05 in the following manner:

(1)

A determination of the principal locations where leaks that are smaller than the allowable technical specification, limit can cause degra'dation of the primary pressure boundary by boric acid corrosion.

Particular consideration should be given to identifying those locations where conditions exist that could cause high concentrations of boric acid on pressure boundary surfaces.

ANPP RESPONSE:

ANPP will determine principal locations where a small leak can cause degradation of primary pressure boundaries by boric acid corrosion.

(2)

Procedures for locating small coolant than technical specification limits).

potential path of the leaking coolant components it is likely to contact.

determining the interaction between the pressure boundary materials.

leaks (i.e.,

leakage rates at less It is important to establish the and'he reactor pressure boundary This information is important in leaking coolant and reactor coolant I

8806010278 880527 PDR ADOCK 05000528 P

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Document Control Desk U.S. Nuclear Regulatory Commission

Subject:

Generic Letter 88-05 Page 2

161-01058-EEVB/ACR/JMQ May 27, 1988 ANPP RESPONSE:

Procedures will be revised or written to in'corporate the list of potential leak locations as determined'y item 1, for visual inspections on a routine basis.

It will also. state the need to determine not only the source of the leakage but also the path taken by the leaking fluid.

3)

Methods for conducting examinations and performing engineering evaluations to establish the impact on the reactor coolant pressure boundary when leakage is located.

This should include procedures to promptly gather the necessary information for an engineering evaluation before the removal of evidence of leakage,.

such as boric acid crystal buildup.

ANPP RESPONSE:,

The appropriate procedures will be revised to include provisions for conducting examinations and performing engineering evaluations to establish the impact on the reactor coolant pressure boundary when a leak is located.

(4)

Corrective actions to prevent recurrences of this type of corrosion.

This should include any modifications to be introduced in the present design or operating procedure's of the plant that (a) reduce the probability of primary coolant leaks at the locations where they may cause corrosion damage and (b) entail the use of suitable corrosion resistant materials or the application of protective coatings/claddings.

ANPP RESPONSE:

The corrective actions will be determined upon the results of the engineering evaluations performed in part 1 and may entail the use of suitable corrosion resistant materials, the application of protective coatings/claddings, or modifications to designs or operating procedures.

The program is scheduled to be implemented by September 30, 1988. If you have any questions, please contact Mr. Carter Rogers of my staff.

Very truly yours,

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Q cLS E. E.

Van Brunt, Jr.

Executive Vice President Prospect Director EEVB/ACR/JMQ/pvk cc:

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B. Martin E. A. Licitra A. C. Gehr T. J. Polich

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STATE OF ARIZONA

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COUNTY OF MARICOPA)

I, Edwin E.

Van

Brunt, Jr.,

represent that I am Executive Vice President Project Director of Arizona Nuclear Power

Project, that the foregoing document has been signed by me on behalf of Arizona Public Service

-Company with full authority to do so, that I have read such document and know its

contents, and that to the best of my knowledge and'elief, the statements made therein are true.

Edwin 'E. Van Brunt, Jr.

Sworn to before me this~j day of 1988.

Notary Public My Commission Expires:

t My Commission Expires Mov. 12. fAA8

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