ML19281B437

From kanterella
Jump to navigation Jump to search
Responds to IE Bulletin 78-14, Deterioration of Buna-N Components. Replacement of Components During Outage Dependent Upon Plant Startup,In View of Pipe Stress Problems.Replacement within Seven Years of Packaging Date
ML19281B437
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 04/04/1979
From: Leonard J
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To: Grier B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
JAFP-79-163, NUDOCS 7905250162
Download: ML19281B437 (2)


Text

&

POWER AUTHORITY OF THE STATE OF NEW YORK J AMES A. FITzPATRICK NUCLEAR POWER PLANT Wll D; e, P.O. BOX 41 JOHN D. LEONARD, JR.

Resident Manager Lycoming, New York 13093 315-342 3840 April 4, 1979 JAFP-79-163 Boyce H. Grier, Director inspection and Enforcement Divisioa U.S. Nuclear Regulatory Commission Region i 631 Park Avenue King of Prussia, Pennsylvania 19406

SUBJECT:

I & E BULLETIN NO. 78-14 DETERIORATION OF BUNA-N COMPONENTS

REFERENCES:

1)

General Electric Company, SIL 128, Revision 1, Supplement 1, Dated August 28, 1978 2)

Letter from J. D. Leonard, Jr. to B. H. Grier Dated January 26,1979 (JAFP-79-055)

Dear Mr. Grier:

Bulletin No. 78-14 required that the James A. FitzPatrick Nuclear Power Plant review the application of certain Buna-N materials in the Control Rod Drive System and report the results of this review to the Commission.

In addition, the Bulletin required that the FitzPatrick facility describe their schedule for replacement and periodic mainten-ance including justification of any proposed periodic replacement in excess of three (3) years.

In Reference 2, the Authority indicated that all of the components of concern would be replaced no later than the scheduled 1980 refueling outage.

In view of the current outage at the FitzPatrick Plant related to the pipe stress analysis problem, replacement of these components will be undertaken in the following weeks. Whether or not all of the components can be replaced during this outage depends primarily on the uncertainty with respect to startup of the plant following the required analysis related to the pipe stress problems.

Those components which are not replaced in the followir weeks will be replaced during the 1980 Refueling Outage.

7905250l W

Boyce H. Grier, Director April 4, 1979 Inspection and Enforcement Division JAFP-79-163 U. S. Nuclear Regulatory Commission Page 2-

SUBJECT:

I r, E BULLETIN NO. 78-14 Periodic replacement of the components following the initial replacement will be conducted on a schedule that will replace components within seven (7) years of their packaging date.

This schedule of replacement is based on a study performed by the General Electric Company in which the failure frequency of 1252 valve diaphragms and 2574 solenoid valve plunger assemblies was reviewed.

The study indicated there are no known failures due to aging during several combinations of shelf and service life until at least seven (7) years from the packaging

date, if you should have any further question in this matter, please contact us.

Very tru h ours, y

j j

,(

)

i ll

~'

I bi

.,nd s

\\tO,,n,,,.

sv

.v JDL:VC:brp JOHN D. LEONARD, JR.'

j

/

i DISTRIBUTION:

/

)

G. T. Berry N

y P. W. Lyon G. A. Wilverding R. Ba S. Wells Document Control Center