ML20207D100

Forwards Application to Amend License DPR-59,deleting Tech Spec Table 3.7-1, Process Piping Penetrating Primary Containment & Adding Nine Reactor Bldg Closed Loop Cooling Water Sys Containment Isolation Valves.Fee Paid

ML20207D100
Person / Time
Site:	FitzPatrick
Issue date:	12/19/1986
From:	Brons J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	Muller D Office of Nuclear Reactor Regulation
Shared Package
ML20207D106	List: ML20207D100 ML20207D202 ML20207D264
References
JPN-86-60, NUDOCS 8612300327
Download: ML20207D100 (4)

Text

m

. s 123 Main Street D

, WNte Plains, New brk 10601 014 681.6240

1. > NewWrkPbwer s' % 2 T eent

& Authority "-'e ' e"e't*"

December 19 , 1986 JPN-8 6-60 Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Mr. Daniel R. Muller, Director BWR Project Directorate No. 2 Division of BWR Licensing

Subject:

James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Proposed Changes to the Technical Specifications Regarding the Deletion of Table 3.7-1 Process Pinina Penetratina Primary Containment

References:

1. NYPA letter, J. C. Brons to H. R. Denton, dated July 22, 1986 (JPN-86-032) regarding 1986 annual FSAR update.

Dear Sir:

This application proposes to delete Table 3.7-1,

" Containment Isolation Valves" and any reference to this table from the FitzPatrick Technical Specifications.

l References to a similar table in the updated FitzPatrick Final Safety Analysis Report (.3AR) will replace the table. This application also pr7 poses to revise the limiting conditions for operation, surveillance requirements and bases to reflect the addition of nine Reactor Building Closed Loop Cooling Water System (RBCLCWS) containment isolation valves 8612300327 B61219 PDR ADOCK 05000333 P PDR I

ce , ,..,,

i g yf9d46

. e a

Table of Containment Isolation Valves The relocation of the table of containment isolation valves will reduce the amount of administrative resources required for both the NRC and the Authority to maintain an up-to-date table of containment isolation valves. Rather than preparing and submitting a technical specification amendment request for each change, the Authority will maintain the table of containment isolation valves in the FSAR. 10 CFR 50.71(e) already requires that the FSAR be updated and submitted once each year.

A more up-to-date table, similar to Table 3.7-1, has already been added to the updated FitzPatrick FSAR. Table 7.3-1, also entitled " Process Piping Penetrating Primary Containment," was included in the FSAR update issued in July 1986 (Reference 1.)

This change does not alter any operability or surveillance requirements currently in the FitzPatrick Technical Specifications. The deletion of this table is purely administrative in nature and will not have any effect on safety.

Over one year ago, both the NRC's Technical Specification Improvement Project Final Report and the Atomic Industrial Forum endorsed the idea of using the FSAR as an appropriate place for this type of information.

RBCLCWS Isolation Valves This application includes changes to reflect the addition of new containment isolation valves in the RBCLCWS and the exclusion of these valves from certain limiting conditions for operation and quarterly surveillance requirements. These valves were added to comply with the requirements of General Design Criteria 57 and to bring the plant into conformance with the FSAR.

Enclosed for filing are three (3) signed originals and nineteen (19) copies of a document entitled " Application for Amendment to Operating License" together with forty (40) copies of Attachments I and II thereto, comprising a statement of the proposed changes to Appendix A of the Technical Specifications and the associated Safety Evaluation.

l,

. l The proposed changes are Attachment I to the Application for Amendment to the Operating License enclosed with this letter. The Safety Evaluation for the proposed changes to the Technical Specifications is Attachment II to the Application for Amendment.

In accordance with 10 CFR 170.12, a check in the amount of $150.00 is enclosed as the application fee.

In accordance with 10 CFR 50.91, a copy of this application with attachments, is being provided to the designated New York State official.

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, s thn C. Brons fienior Vice President luclear Generation cc: Office of the Resident Inspector U. S. Nuclear Regulatory Commission P. O. Box 136 Lycoming, New York 13093 Mr. J. D. Dunkelberger l Division of Policy Analysis and Planning l New York State Energy Office Agency Building 2, Empire State Plaza Albany, New York 12223 l

c _-

. o The proposed changes are Attachment I to the l Application for Amendment to the Operating License enclosed I with this letter. The Safety Evaluation for the proposed changes to the Technical Specifications is Attachment II to the Application for Amendment.

In accordance with 10 CFR 170.12, a check in the amount of $150.00 is enclosed as the application fee.

In accordance with 10 CFR 50.91, a copy of this application with attachments, is being provided to the designated New York State official.

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, t

28-o n C. Brons Senior Vice President Tuclear Generation cc: Office of the Resident Inspector U. S. Nuclear Regulatory Commission P. O. Box 136 Lycoming, New York 13093 Mr. J. D. Dunkelberger Division of Policy Analysis and Planning New York State Energy Office Agency Building 2, Empire State Plaza Albany, New York 12223

__ . _ _ . . _ _