ML20211F256
| ML20211F256 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 10/20/1986 |
| From: | Brons J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | Muller D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20211F259 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.A.1.3, TASK-2.B.3, TASK-2.F.1, TASK-2.K.3.03, TASK-TM GL-83-36, GL-83-86, JPN-86-47, NUDOCS 8610310111 | |
| Download: ML20211F256 (3) | |
Text
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123 Main Street Whte Plains, New brk 10601 914 681.6240
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October 20, 1986 JPN-86-47 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 Rega rding NUREG-07 37 Items
References:
1.
NRC Generic Letter 83-36, dated November 1, 1983.
2.
NYPA letter, C.
A.
McNeill to D.
B.
- Vassallo, dated December 6, 1984, (JPN-84-80) proposed changes to the Technical Specifications.
3.
NYPA letter, J.
C.
Brons to D.
B.
Vassallo, dated October 18, 1985, (JPN-85-75) responded to NRC questions.
Dear Mr. Muller:
The purpose of this letter is to request an amendment to several sections of the James A.
FitzPatrick Technical Specifications related to NUREG-0737 items.
Technical Specifications related to NUREG-0737 - Item II.F.1.1, Noble Gas Effluent Monitors The sample technical specification provided in Referance 1 required that one channel be provided and one channel be operable.
Guidance provided in Reference 1 suggested that, in case of failure of the one channel, a preplanned alternate method for monitoring the effluent should be initiated within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
Reference 1 further stated, that if the channel were not restored within seven days, a special report should be submitted to the Nuclear Regulatory Commission (NRC).
In Reference 2, the New York Power Authority specified that two channels be provided, and that at least one channel be operable.
8610310111 861020 PDR ADOCK 05000333 l
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t-9, Following NRC review of Reference 3 and furtner conversations with the NRC Staff, the.New York Power Authority is submitting revised technical specification pages for this NUREG-0737 item.
These pages replace and supersede in their entirety those originally submitted in Reference 2.
Unlike the guideline which requires one channel and one alternate method, the enclosed specification states that there are two channels provided, and one is required to be operable.
The second channel will serve as an installed alternate method for monitoring.
In the event of failure of the required monitor, the second channel will be placed in operation as the preplanned alternate within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
If one channel is not restored within seven days, a special report will be submitted to the NRC.
The Authority considers the FitzPatrick design and Technical Specification to be more conservative than the sample specification.
Technical Specifications related to NUREG-0737, Item II.F.1.2, Sampling and Analysis of Plant Effluents Reference 1 suggested an administrative program to ensure the capability for post accident sampling for radioactive iodines and particulates in plant gaseous effluents.
Reference 1 further states that this program should be referenced in the administrative controls section of the Technical Specifications.
In Reference 2, the New York Power Authority had prepared proposed technical specifications for iodines and particulates wnich provided specific limits for continued operation and specific action statements.
Following discussions with NRC Staff, those proposed technical specifications are replaced and superseded in their entirety by this application which conforms to the guidance provided in Reference 1.
Technical Specifications.related to NUREG-0737, Item II.B.3, Post Accident Sampling In accordance with discussions with NRC Staff, proposed Technical Specifications are provided in this submittal which replace and supersede in their entirety those originally submitted in Reference 2.
The proposed Technical Specifications are the same as those suggested in Reference 1.
Technical Specifications, Table of Contents A typographical correction is made on page iii of the Table of Contents.
Technical Specifications related to NUREG-0737, Item I.A.l.3.1 Overtime Limits Proposed changes to page 248 relating to overtime are provided in this submittal replacing and superseding in its entirety the page originally proposed in Reference 2.
1
Technical Specification related to NUREG-0737, Item II.K.3.3, Reporting Safety Valve and Relief Valve Failures and Cnallenges Proposed cnanges provided in this submittal agree with the sample specifications and replace and supersede in their entirety thcae originally proposed in Reference 2.
Although tne specification originally proposed was more definitive, this change is being made at the request of the NRC Staff.
Technical Specification related to Reactor Core Isolation Cooling The proposed change adds a logic system function test to the list of required tests.
The requirement to perform this test was originally omitted from the Technical Specifications.
Additional proposed changes related to this system remain the same as originally submitted in Reference 2.
An update of Table 3.7-1 will be addressed in a separate letter.
Enclosed for filing are tnree (3) signed originals and nineteen 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 the Technical Specifications and the associated Safety Evaluation.
In accordance witn 10 CFR 50.91, a copy of this application, with attachments, is being provided to the designated New York State official.
In accordance with 10 CFR 170.12, a check in the amount of
$150.00 was enclosed as the application fee with our original submittal.
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, bE C.
rons Senior Vice President Nuclear Generation Encs.
cc:
Office of the Resident Inspector U.S.
Nuclear Regulatory Commission Post Office Box 136 Lycoming, New York 13093 Mr.
J.
D.
Dunkleberger Division of Policy Analysis and planning New York State Energy Office Agency Building 2, Empire State Plaza Albany, New York 12223