View source for JPN-90-017, Safety/Relief Valve Challenges & Failures for 1989

{{Adams
| number = ML20055C300
| issue date = 12/31/1989
| title = Safety/Relief Valve Challenges & Failures for 1989
| author name = Brons J
| author affiliation = POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
| addressee name = 
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000333
| license number = 
| contact person = 
| case reference number = RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.3.03, TASK-TM
| document report number = JPN-90-017, JPN-90-17, NUDOCS 9003020015
| document type = ANNUAL OPERATING REPORT, TEXT-SAFETY REPORT
| page count = 4
}}

=Text=
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February 23, 1990 JPN-90-017 U.S. Nuclear Regulatory Commission Mall Station P1137 Washington, D.C. 20555
                - ATTENTIONi Document Control Desk

==SUBJECT:==
James. A. FitzPatrick Nuclear Power Plant Docket No. 50-333 NUREG 0737 Item II.K.3.3 Safety / Relief Valve Challenges and Failures

==Reference:==
NYPA letter, J. P. Bayne to T. E. Murley, dated October 22,1984 (JPN 84 069).

==Dear Sir:==

NUREG 0737 Item II.K.3.3 requires that challenges or failures to safety /rellet valves (SRVs) be reported annually.
Attachment I is a list of SRV challenges and tallures, as defined in Reference I, which occurred between January 1,1989 and December 31,1989 at the FitzPatrick plant.
Should you or your staff have any questions regarding this matter, please contact Ms. S. M.
Toth of my staff.
Very truly yours, LW p.[J     n .Brons h    ERec tive Vice President V    Nuclear Generation Enclosures cc:- Usted on following page M
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Lycoming, NY 13093                       l l
Mr. David LaBarge                        ,
Project DirectorateI 1 Division of Reactor Projects l/11      <
U.S. Nuclear Regulatory Commission Mall Stop 14 B2                        '
Washington, D.C. 20555                 ,
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        ..g. g e JPN 90 017 ATTACHMENT I SAFETY /REUEF VALVE CHALLENGES AND FAILURES FOR 1989
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I New York Power Authority James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 DPR 59

i 2
6 SERIAL DATE          VALVE     NUMBER     CHATTRNGE   FAILURE         REMARKS 03/06/89      02SRV-71K     1062    YES              NO        Inadvertent operator actuation -
100% power (1005 PSIG).
10/07/89      02SRV-71L. 1088       YES              NO        Replaced during Fall 1989 Maintenance outage.            Startup testing per ST-22B at 562 PSIG.
11/14/89      02SRV-71E     1080    YES             NO         Replaced during Fall 1989 Maintenance cutage. Startup testing per ST-22B at 941 PSIG.
11/14/89      02SRV-71F     1912    YES             NO         Replaced during Fall 1989 Maintenance outage. Startup testing per ST-2;B at 941 PSIG.
12/13/89      O2SRV-71E    1050     NO           YES           Tested at WYLE. Found setpoint drift
                                                                       = -l'.4% (1089 PSIG versus 1105 at setpoint). LER-89-026.
12/13/89      02SRV-71F    1087     NO           YES           Tested at WYLE.              Found setpoint drift
                                                                       = +4.7% (1194 PSIG versus 1140 at setpoint).            LER-89-026.
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