View source for JPN-96-026, Forwards Application for Amend to License DPR-59,revising ATWS Recirculation Pump Trip Reactor Pressure for High Setpoint,Either Zero or Safety Relief Valves Out of Svc

{{Adams
| number = ML20112D256
| issue date = 05/30/1996
| title = Forwards Application for Amend to License DPR-59,revising ATWS Recirculation Pump Trip Reactor Pressure for High Setpoint,Either Zero or Safety Relief Valves Out of Svc
| author name = Salmon H
| 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 = 
| document report number = JPN-96-026, JPN-96-26, NUDOCS 9606040175
| package number = ML20112D262
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| page count = 2
| project = 
| stage = Request
}}

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123 Main Street White Plains. New York 10601
#                  914 6dt-6840
               ' 914-287-3309 (FAX)
William J. Cahill, Jr.
4# Authon.ty                                                                                        c" ~ e< = -
May 30,1996 JPN 026 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-137 Washington, DC 20555

==SUBJECT:==
James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Proposed Change to the Technical Specifications                                                         j Regarding ATWS Recirculation                                                                            '
P_ ump Trio instrumentation Requirements (JPTS-96-009)
Dear Sir.
This application for an amendment to the James A. FitzPatrick Technical Specifications proposes a revised ATWS Recirculation Pump Trip Reactor Pressure - High setpoint when either zero or one Safety Relief Valves are out of sennce.                                                                  ;
i The signed original of the Application for Amendment to the Operating Ucense is enclosed for filing. Attachment I contains the proposed new Technical Specification pages, and Attachment ll is the Safety Evaluation for the proposed changes. A markup of the affected Technical Specification pages is included as Attachment lil.
There are no commitments contained in this submittal.
A copy of this applicw on and the associated attachments are being provided to the 8
designated New York State official in accordance with 10 CFR 50.91.
If you have any questions, please contact Ms. C. D. Faison.
Very tru y yours,                                .
1 Hany P. Salmon, Jr.,16(r William J. Cahill, Jr.
Chief Nuclear Officer att: As stated cc: Next page                                                                                                               4 040010 9606040175 960530 PDR        ADOCK 05000333
                                                                                                                            . 00t'  ,

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