JPN-88-024, Forwards Application for Amend to License DPR-59,revising Tech Spec Table 3.7-1, Process Pipeline Penetrating Primary Containment to Reflect Two Facility Mods Re RWCU Sys Containment Isolation Valves.Fee Paid
| ML20154S512 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 05/27/1988 |
| From: | Brons J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML20154S517 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.E.4.2, TASK-TM JPN-88-024, JPN-88-24, NUDOCS 8806090082 | |
| Download: ML20154S512 (3) | |
Text
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May 27, 1988 JPN-88-024 U.
S.
Nuclear Regulatory Commission Attention: Document Control Desk Mail Stop 01-137 Washington, D.
C.
20555
Subject:
James A.
FitzPatrick Nuclear Power Plant Docket No. 50-333 Proposed Change to the Technical Specifications Regarding Reactor Water Cleanup Containment Isolation Valves (J PTS-88 -00 5 )
References:
1.
PASNY letter, J.
P.
Bayne to T. A.
Ippolitto, dated January 7, 1982 (JPN-82-005), regarding containment isolation dependability.
Dear Sir:
This application proposes to revise Table 3.7-1 ("Process Pipeline Penetrating Primary Containment") of the Jamed A.
FitzPatrick Nuclear Power Plant Technical Specifications to reflect two plant modifications associated with the Reactor Water Cleanup (RWCU) system containment isolation valves.
Both modifications will be completed during the 1988 refueling outage which is currently scheduled to begin in August 1988.
The Authority completed a comprehensive review of containment isolation dependability in response to NUREG-0737, Containment Isolation Dependability.
The results Item II.E.4.2 of this review were transmitted to the NRC as part of Reference 1.
In that report, the Authority committed to install the modifications associated with these proposed changes to the Technical Specifications.
The first of these two modifications involves the addition of an isolation signal (high drywell pressure) to three existing containment isolation valves.
When this modification is complete, these valves will be actuated using diverse isolation signals as recommended in Section 6.2.4 of the Standard Review A pg l Plan (the criteria referenced in NUREG-0737).
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r The second modification adds a motor-operated containment isolation valve outside containment in the RWCU return line (12MOV-069).
This modification will bring the RWCU system into compliance with General Design Criteria 55 of Appendix A to 10 CFR 50.
This new valve will actuate on diverse isolation signals, including high drywell pressure.
The proposal also revises Table 3.7-1 to update and correct RWCU entries.
These revisions are not directly associated with tha modifications described above.
An isolation signal, included as part of the original FitzPatrick design, is added to one RWCU valve table entry.
Valve closure times for two RWCU valves are reduced from thirty to twenty seconds to reflect the assumptions in the FitzPatrick environmental qualification analyses.
Page 200 of Table 3.7-1 is revised to reflect these changes.
Isolation signal "F"
(high drywell pressure) is added to the three existing RWCU system entries.
A table entry is revised to reflect the replacement isolation valve.
Associated "Bases" sections do not require revision and are not altered by this proposal.
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 associated Safety Evaluation.
In accordance with 10 CFR 170.12, a check in the amount of
$150.00 is enclosed as payment of the application fee for the review of the proposed changes to the Technical Specifications.
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.
Very truly yours, t
- tem w-
/,To an C.
Brons Executive Vice President Huclear Generation
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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. Harvey Abelson Project Directorate I-1 Division of Reactor Projects - I/II U.S. Nuclear Regulatory Commission Mail Stop 14 B2 Washington, D.C.
20555 Mr. J.
D.
Dunkelberger, Director Technology Development Programs New York State Energy Office Two Rockefeller Plaza Albany, New York 12223 f