View source for JPN-89-029, Forwards Application for Amend to Tech Specs Revising Tech Spec 4.7.A.3, Continuous Leak Rate Monitoring, to Remove Misleading Ref to Continuous Leak Rate Monitoring Sys

{{Adams
| number = ML20247H489
| issue date = 05/19/1989
| title = Forwards Application for Amend to Tech Specs Revising Tech Spec 4.7.A.3, Continuous Leak Rate Monitoring, to Remove Misleading Ref to Continuous Leak Rate Monitoring Sys
| 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 = 
| document report number = JPN-89-029, JPN-89-29, NUDOCS 8905310250
| package number = ML20247H494
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 2
| project = 
| stage = Request
}}

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                                       'U.S. Nuclear Regulatory Commission                                                                                               i ATTN: Document Control Denk                                                                                                      j Mail Station P1-137                                                                                                              i Washington, D.C. 20555

==SUBJECT:==
James A. FitzPatrick Nuclear Power Plant
              \                                                Docket No. 50-333 2                                             Proposed Change to the Technical Specifications Regarding Containment Atmosphere Continuous Leak Rate Monitorina (JPTB-89-005)

==REFERENCE:==
1.'NYPA letter, W. Fernandez to NRC, dated
                                                         .         March 20,.1989, (JAFP-89-0214), responds to Inspection Report 50-333/88-29.
  +.

==Dear Sir:==
l This application for an amendment to the James A.
* FitzPatrick Technical Specifications revises Technical                                                                         3 Specification 4.7.A.3, " Continuous Leak Rate Monitoring,"                                                                     l on pages 176 and 177. The' change removes a misleading reference to a continuous leak rate monitoring system.
There is no dedicated monitoring system. Containment leakage is determined by periodically calculating the Containment Air Dilution system makeup requirements and by review of the drywell to suppression chamber differential                                                                       l pressure instrumentation.                                                                                                        i This amendment is one of the Technical Specification corrections committed to by the Authority in Reference 1.
Enclosed for filing is the signed original of a document entitled " Application for Amendment to Operating License," with Attachments I and II thereto, comprising a statement of the proposed changes to the Technical Specifications and the associat(.d Safety Evaluation,                                                                           j In accordance with 10 CFR 50.91, a copy of this                                                                      I application and the associated attachments are being provided to the designated New York State official.
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Should you or your staff have any questions regarding the. proposed changes, please contact Mr. J. A. Gray, Jr., of my staff.
Very truly yours, l
J       w JcEn C. Brons Executive Vice President Nuclear Generation cc:   U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 office of the Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 136 Lycoming, Ni' 13093 Mr. David E. La Barge Project Directorate I-1 Division of Reactor Projects - I/II U.S. Nuclear Regulatory Commission Mail Stop 14 B2 Washington, DC 20555 Ms. Donna Ross New York State Energy Office 2 Empire State Plaza 16th Floor Albany, NY 12223 i
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