ML20209E990

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Part 21 & Second Interim Deficiency Rept,Item 188 Re Natural Frequencies of ITT-Grimmell air-operated Diaphragm Valves. Initially Reported on 840926.Design & Installation of Addl Supports Continuing.Next Rept Expected by 850930
ML20209E990
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 06/27/1985
From: Watson R
CAROLINA POWER & LIGHT CO.
To: Grace J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
CON-NRC-374, REF-PT21-85, REF-PT21-85-310-000 188, PT21-85-310, PT21-85-310-000, NUDOCS 8507120367
Download: ML20209E990 (3)


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Carolina Power & Light Company P. O. Box 101, New Hill, NC 27562 June 27,1985 Dr. J. Nelson Grace NRC-374 United States Nuclear Regulatory Commission Region II 101 Marietta Street, Northwest (Suite 2900)

Atlanta, Georgia 30323 CAROLINA POWER & LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT 1986 - 900,000 KW - UNIT I AIR-OPERATED DIAPHRAGM 27:

VALVES-NATURAL FREQUENCIES, ITEM 188 c_

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Dear Dr. Grace:

Attached is our second interim report on the subject item, which was deemed repor3able per the provisions of 10CFR50.55(e) and 10CFR, Part 21 on September 26,1984. CP&L is pursuing this matter, and it is currently projected that corrective action and submission of the final report will be accomplished by September 30,1985.

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Thank you for your consideration in this matter.

Yours very truly, R. A. Watson Vice President Shearon Harris Nuclear Power Plant RAW:bs Attachment cc:

Messrs. G. Maxwell /R. Prevatte (NRC-SHNPP)

Mr. R. C. DeYoung (NRC) 8507120367 850627 PDR ADOCK 05000400 S

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- CAROLINA POWER & LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT I

UNIT NO. I SECOND INTERIM REPORT ITT-GRINNELL AIR OPERATED DIAPHRAGM VALVES NATURAL FREQUENCIES ITEM No.188 JUNE 27,1985 REPORTABLE UNDER 10CFR50.55(e) and 10CFR21 XEX-SMI/3-OSS

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SUBJECT:

10CFR50.55(e) and 10CFR21 Reportable item, Shearon Harris Nuclear Power' Plant Unit 1,ITT-Grinnell Air-Operated Diaphragm Valves Natural Frequencies.

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y ITEM:

Air-operated Diaphragm Valves for SHNPP Unit 1.

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.i SUPPLIED BY:

Westinghouse Water Reactor Division /ITT-Grinnell.

r' NATURE OF DEFICIENCY:

Westinghouse notified CP&L in September 1984 that a problem

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existed with a number of air-cperated diaphragm valves supplied byITT-Grinnell. The valves, designed to have frequencies greater than 33 hz, were found by test not to meet this requirement. Further investigation revealed valves of the same type supplied directly by ITT-Grinnell to CP&L. These

'q valves are supplied as ASME Class 2 and 3' components.

DATE PROBLEM W AS CONFIRMED 3 EXIST:

Westinghouse Letter CQL-8174 dated September 4,1984, and.

received September 11;1984.

-PROBLEM ni REPORTED:

N. J. Chiangi natified the NRC (Mr. A. Hardin) that this item was reportable under 10CFR50.55(e) and 10CFR21 on September 26, 1984.

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' SCOPE OF PROBLEM:

'. Twerify-seven (27) NSSS-supplied valves and nine (9) BOP-

' ' supplied valves.

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-SAFETY 1

s IMPLICATIONS:

Potential for increasing piping stresses and support loads in affected piping systems.

REASON PROBLEM 15 REPORTABLE:

Erroneous analysis / support of the valves (due to non-rigidity) could cause the design loads or stresses to be exceeded.

CORRECTIVE do

, CP&L and Ebascofreanalysis of the systems to include the

.- ACTION:

effects of the non-rigid valves has been completed. A review t

of the impact on the design of the existing supports, and design

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and installation of additional supports that are required is s

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continuing and should be complete by August-30,1985.

r FINAL REPORT:

A final report is anticipated to be submitted by September 30, 1985.

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