ML20245D512
| ML20245D512 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 04/24/1989 |
| From: | Brons J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20245D516 | List: |
| References | |
| JPN-89-020, JPN-89-20, JPTS-86-024, JPTS-86-24, NUDOCS 8905010027 | |
| Download: ML20245D512 (2) | |
Text
_
i
'123 Main Street White Plains, Newbic10601 914 681.6240 NewYo&hwer aea c.aroe.
4# Authority lC%7"%"e"la*"'
o April 24, 1989 JPN-89-020 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station F1-137 Washington, D.C.
20555
' SUBJECT : '
James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Proposed Change to the Technical Specifications Regarding Pertubation of Reactor Water Level Following Instrument Functional Tests (JPTS-86-024)
Dear Sir:
This application for an amendment to the James A.
FitzPatrick Technical Specifications proposes to remove the requirement to perturb the reactor vessel water level as part of the monthly functional test for the reactor water level scram instruments.
Perturbing the reactor water level is considered an unnecessary operational inconvenience and it is superfluous to the existing channel check requirements.
The proposed changes are administrative in nature and promote consistency with the Standard Technical Specifications.
The proposed changes do not involve modification of any existing equipment, systems, or components; nor do they alter the conclusions of the plant's accident analyses or radiological release analyses.
An evaluation of the proposed change has determined that no j
significant hazards consideration exists.
A similar change was approved for Browns Ferry Units 1, 2 and 3 on September 19, 1984.
This change was Amendment 113, 107 and 81 for Units 1, 2 and 3 respectively.
The NRC safety evaluation for the Browns Ferry Technical Specification Amendments noted that the level' pertubation was not a regulatory requirement, was an operational inconvenience and was not' required by Standard Technical Specifications.
The proposed changes revise Technical Specification 4.1, Table 4.1-1 on pages 44 and 45a.
i 8905010027 890424 l
g PDR ADOCK 05000333 P
PDC N
g=
s
(, ;..
p o
a s.
s...
.. Enclosed for filing is the signed original of a document entitled " Application for Amendment to Operating er License," with Attachments I and'II thereto, comprising
- a'statementLof'the proposed changes to the Technical
. specifications and'the associated Safety Evaluation.
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 Mr. J. A. Gray, Jr. of my staff.
l' Very truly yours, N~
ohn C.
Brons fxecutive 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,.NY 13093 Mr.' David E. LaBarge Project Directorate I-1 Division of Reactor Projects - I/II U.S. Nuclear Regulatory Commission Mail Stop 14 B2 Washington, D.C.
20555 Ms. Donna Ross Division of Policy Analysis and Planning Empire State Plaza th Building Number 2 - 16 Floor Albany,-NY 12223
- _ _ _ _