ML19354D870

Forwards Application for Amend to License DPR-59,revising Note 16 to Table 3.1-1 & Note 9 to Table 3.2-1 to Increase Main Steam Line High Radiation Monitor Trip Level Setpoint During Operating Cycle 10

ML19354D870
Person / Time
Site:	FitzPatrick
Issue date:	01/12/1990
From:	Brons J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML19354D871	List: ML19354D870 ML19354D872 ML19354D873
References
JPN-90-004, JPN-90-4, NUDOCS 9001230063
Download: ML19354D870 (2)

Text

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I 1 a ewYork 1DG31

. 914 WI fJ40 hk [ John C. Brons

& MUth0fity Dr~c5r"ItII" January 12, 1990 J m-90-004 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mall Station P1137 Washington, D.C. 20555

SUBJECT:

James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Proposed Changes to the Technical Specifications Regarding Main Steam Line High Radiation Monitor Trip Level Setpoint (JPTS-89 023)

REFERENCE:

1. NRC letter, H. l. Abelson, dated May 16,1985, transmitted Technical Specification Amendment 90.

Dear Sir:

This application for an amendment to the James A. FitzPatrick Technical Specifications revises Note 16 to Table 3.1 1, " Reactor Protection System (SCRAM) instrumentation Requirement," and Note 9 to Table 3.21, " Instrumentation That initiates Primary Containment Isolation,' to allow the main steam line high radiation monitor trip level setpoint to be increased during Operating Cycle 10 to accommodate testing of the in core stress corrosion monitoring system.

The test involves incremontally increasing the hydrogen flow rates while monitoring the electrochemical potential and crack growth rate from modified low power range monitors in the core. The data collected from the test will provide the basis for ,

establishing the amount of hydrogen needed to suppress crack growth of IGSCC susceptible materialin the core. The addition of hydrogen reduces the concentration of oxygen in the coolant water and increases the Nitrogen-16 carryover in the steam. This results in a higher background radiation level seen by the main steam line radiation monitors. At this time, the test is scheduled to be conducted approximately 12 months after the 1990 refueling outage and is expected to last 3 4 weeks.

The Authority conducted a related test (HWC mini test) during operating Cycle 7. A similar change to the main steam line radiation monitor trip setpoint was incorporated for that test. That change was reviewed and approved by the NRC as Amendment 90 to the Technical Specifications (sco Reference 1),

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t Enclosed for filing is the signed original of a document entitled " Application for i Amendment to Operating Ucense,' with Attachments I and ll thereto, comprising a t statement of the proposed change to the Technical Specifications and the associated Safety Evaluation, j In accordance with 10 CFR 50.91, a copy of this application and the associated ,

attachments are being provided to the designated New York State official.

Should you or your staff have any questions regarding the proposed changes, please contact Ms. S. M. Toth of my staff. ,

f truly yours, I (VeB3-En 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 i Lycoming, NY 13093 ,

Mr. David E. LaBarge Project Directorate 11 Division of Reactor Projects 1/11 U.S. Nuclear Regulatory Commission l' Mail Stop 14 B2 Washington, DC 20555 -

Ms. Donna Ross New York State Energy Office 2 Empire State Plaza 16th Floor  :

Albani, NY 12223 l

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