ML20214J166
| ML20214J166 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 11/21/1986 |
| From: | Tucker H DUKE POWER CO. |
| To: | Harold Denton, Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8612010182 | |
| Download: ML20214J166 (3) | |
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-6 DuxE POWER GOMP.WY P.O. Box 33189 CHAmLorTE, N.C. 98249
'HALH. TUCKER Tzternosrr.
vna rammionwr PO4) 3M834 wims.nas emonocreon November 21, 1986-Mr. Harold R. Dentan, Director Office of Nuclear Reactor Regulation U.S.' Nuclear Regulatory Commission Washington, D.C.
20555
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'ATTEhTION:
.Mr. B.J. Youngblood, Director PWR Directorate No. 4
Subject:
McGuire Nuclear Station f
Docket No. 50-369, 50-370 L
Technical Specification Proposals
Dear Mr. Denton:
The purpose of this letter is to provide additional information relative to a Technical Specification proposal relative to containment isolation valves and to request an approval timetable for Technical Specification proposals that are
. needed by the upcoming (1987) refueling outages at McGuire. The additional information regarding the containment isolation valve proposal was requested in telephone discussions between Mr. D. Hood of your staff and Mr. J.B. Day of my staff.
By letter dated May 14, 1986 and, supplemented July 14, 1986, Duke proposed changes to the McGuire Nuclear Station Technical Specifications for containment penetra-tions. One'of the changes addressed redesignation of penetration M348 from " Upper Head Injection Test Line" to." PALS Discharge" in Table 3.6-1 with a footnote to redesignate the penetration effective upon completion of the modifications in-volved. These modifications are planned for the 1 17 refueling outages.on each unit,'therefore approval is requested prior to the refuelint outages, the first of which is presently scheduled to begin approximately April 1,1987. We would also like to confirm telephone discussions between Mr. D. Hood of your staff end Mr.
J.B. Day of my utaff thtt would change the wording of the previously referenced footnote from "This penetration is for the UHI test line and will be for PALS discharge following the implementation of NSM 1-1761, 1-1768, 2-593, and 2-598."
to "Upon the deactivation of the UHI System by removal of related components and piping and modifications to the Cold Leg Accumulators, this penetration is uti-lized for PALS discharge". The two statements have the same meaning, with the k
latter statement not referencing NSM (modification) numbers. A similar footnote to Table 3.6-2 to insert the PALS discharge containment isolation valves is also r gd changed.
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8612010182 861121 PDR ADOCK 05000369:
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Its Harold R. Denton, Director November 21, 1986 Page 2 Another part of the proposal was to relocate these tables to the Bases. Most of the information contained in these tables is also maintained in the FSAR. Table 6.2.4-1 of the McGuire FSAR lists Containment Piping Penetrations and Isolation Valve Data; Table 6.2.4-2 lists Containment Isolation Valves Subject to Type C Leakrate Tests, and Table 6.2.4-3 lists Containment Penetrations Not Subject to Type C Leakrate Tests. Based upon the information given in these FSAR tables.
Duke will be required to evaluate changes to any containment penetration according to the standards of 10CFR50.59, maintain the records of such an evaluation, and to report these changes to the NRC in the annual 50.59 report. The net effect of transferring Technical Specifications Tables 3.6-1 and 3.6-2 to the Bases would be to remove an administrative burden from Duke and NRC by no longer requiring that a license amendment be sought to change information in either of the tables, while ensuring that a full review is performed and documented.
Another Technical Specification proposal was submitted by letter dated October 13, 1986 seeking to allow the use of higher enrichment fuel (up to 4.0 w/o U-235) for future core reloads on both units. Duke plans to use this higher enrichment level in the McGuire Unit 1 Cycle 5 reload, therefore it is requested that the change be granted in time for the receipt of this fuel onsite, presently scheduled for April 1, 1987.
A third change (which has not yet been submitted) will be needed on this same schedule. This change will address the surveillance requirements for the cold leg injection accumulator isolation valves (4.5.1.1.1c and 4.5.1.2.le).
The proposal will be forthcoming and is due to a Human Engineering Deficiency (HED) modification planned for the upcoming outages.
If there are any questions, please contact us through normal Licensing channels.
Very truly yours, Hal B. Tucker JBD/126/j gm i
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Mr. Harold R. Denton, Director November 21, 1986 Page 3~
xc: Darl Hood Office of Nuclear Regulation l
U.S. Nuclear Regulatory Commission
' Washington, D.C.
20555 Dr. J. Nelson Grace Regional Administrator U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW Suite 2900 Atlanta, GA 30323 Mr. W.T. Orders NRC Resident Inspector McGuire Nuclear Station L
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