ML19310A242
| ML19310A242 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 05/19/1980 |
| From: | Broehl D PORTLAND GENERAL ELECTRIC CO. |
| To: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| Shared Package | |
| ML19310A241 | List: |
| References | |
| NUDOCS 8006060350 | |
| Download: ML19310A242 (4) | |
Text
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O T.~. y M PortlandGeneralEecideCoupmy i
Isiiis Otra'da Bred Asscart Vcc Rett.ert May 19, 1950 Trojan Nuclear Plant Docket 50-344 License NPF-1 Y
tCCKETED 6
Hr. R. H. Engelke1, Director U. S. Nuclear Regulatory Co:2 mission MNI 2 2 G80 >
-11 Region v cffice of taa Secrets Suite 202, Walnut Creek Plaza 1990 N. Californir, Blvd.
$ Od:tM 3 SufCS
\\A Walnut Creek, CA 94596 V *,
Dear Mr. Engelken:
This is a follow-ep to the report made by se to Mr.sD. M. Sternberg of your office at approx 5=ately 6:30 p.m. on May 16, 1980 regarding discovery of a wall which is not adequately connected at its top to interfacing structural ele =ents.
The subject wall consists of a single wythe of 12-in.-thick reinforced grcuted nasonry, approximately 80 f t. wide spanning frca Elevation 61 fc.
to Elevation 93 ft.
It is the south wall of the Auxiliary Building The wall is adjacent to column line 55 between column lines F and N.
adequately connected by reinforcing steel to the wall below Elevation 61 ft. and the ficor slabs at Elevaticus 61 ft and 77 ft.; hwwever, the top of the wall is not connected to the floor slab at Elevation 93 ft.
The actual condition of this interface was determined during an inspection to verify bcundary conditions for use in current evaluations related to 1.icensee Event Report (LER) 79-15.
This vall was evaluated in November 1979 relative to out-of-plane reac-tion forces during review of, valls pursuant to I.ER 79-15.
Since typical j
details and construction notes on design drawings would indicate that a positive connection should have been made, that evaluation assumed a
-l pin-ended condition at the tcp of the wall which is now known not to exist.
Analysing the wall as an effective cantilever indicates that' it cannot adequately resint cut-of-plane loads.
Corrective action will be taken to provide apprepriate end connections for this wall.
Although the original Plant design did not rely on this vall to serve as a shear wall, it was asse: ed to be connected and participate as a niner structural shearmenisting element in the STARDYNE finite element analyses l
of the Control-Auxiliary-Fuel Building Cocplex (Complex) for the Control l
Building proceedings, Phase 1 (Interim Operation - As-Et.11t) and Phase 2 j
Since this wall is in close proximity to a parallel (Modified Complex).
l 4-ft.-thick shield vall and its relative strength and stiffness are low, j
removal of this vall from the STARDYNE model or reduction of ita l
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tir. R. H. Engelken l
May 19.1980 l
Page 2
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j shear capacity to zero will not reduce the capability of the as-built structure below that required to resist the Safe Shutdown Earthquake.
l In any event, prenpt corrective action is being taken to connect the wall such that it will participate as assu=ed in the STARDYNE analyses.
An initial review has been performed to assess the potential effects of degradation of the subject wall. The wall provides partial lateral restraint for cable trays vertically supported from structural steel beneath the Elevation 93 ft. floor slab.
The cable trays contain cables serving eeveral train B safety systems, but they contain no train A cables. Portions of safety train 3 are currently out of service for installation of decouple switches, and equipsent operabild.ty requirenents are being met with train A equipment. The Plant is in a refueling shutdown with transfer of fuel assemblies from the Spent Fuel Pool to the reactor vessel in progress.
In this condition, there is no i= mediate concern for Plant safety while this occurrence is being evaluated furthe and corrective action is being taken.
other nasonry walls at the Plant are being reviewed to determine if similar conditions exist elsewhere. The results of this review will be provided in the detailed report.
This occurrence vill be reported to the Nuclear Regulatory Commission in accordance with the Technical Specifications. "Ihat report will provide a more detailed description and analysis of the occurrence, the cause of the occurrence, a description of and basis for the corrective action being taken, and a schedule for coc pletion of documentacion and corrective action.
In addition, a safety evaluation for transition from operational Mode 6 to Mode 5 will be provided prior to bolting on the reactor vessel head.
Sincerely, W
c: Mr. I.ynn Frank, Sire tor State of Oregon Departnent of Energy Mr. Robert A. Clark, Chief Operating Reactors Branch No. 3 Division of Operating Reactore U. S. Nuclear Regulatory Commission 4
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S DOCMUU3 UNITED STATES OF AMERICA csNBC I_'
g $80 P NUCLEAR REGULATORY COMMISSION 1.S g
- BEFORE THE ATOMIC SAFETY AND LICENSING BOARD C6 g
In the Matter of
)
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PORTLAND GENERAL ELECTRIC COMPANY, et al.
)
Docket No. 50-344
)
(Trojan Nuclear Plant)
)
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(Control Building Procceding)
)
)
CERTIFICATE OF SERVICE from Maurice Axelrad co the members of the Atomic Safet
, 1980, censing Board, including the enclosure thereto, was served on the and Li-following by deposit in the United States mail postage prepaid, first class and this 20th day of May, 1980:
Marshall E. Miller, Esq., Chairman Atomic Safety and Licensing Board Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission Panel Washington, D.
U. S.
C.
20555 Nuclear Regulatory Commission Washington, D. C.
20555 Dr. Kenneth A. McCollom, Dean Division of Engineering, Docketing and Service Section Architecture & Technology Office of the Secretary Oklahoma Scate University Nuclear Regulatory Commission U. S.
Stillwater, OK 97074 Washington, D.
C.
20555 (Original & 20 copies)
Dr. Hugh C. Paxton 1229 - 41st Street Columbia County Courthouse Los Alamos, NM 87544 Law Library, Circuit Court Room i
St. Helens, OR 97051 Joseph R. Gray, Esq.
Counsel for NRC Staff Atomic Safety and Licensing U. S. Nuclear Regulatery Commission Appeal Board Washington, D. C.
U. S.
i 20555 Nuclear Regulatory Commission Washington, D. C.
20555
o Ms. Nina Bell Ronald W. Johnson, Esq.
728 S. E.
26th Street Corporate Attorney Portland, OR 97214 Portland General Electric Company 121 S. W.
Salmon Street Mr. Eugene Rosolie Portland, OR 97204 Coalition for Safe Power 3926 N. E.
12th Frank W.
Ostrander, Jr.,
Esq.
~
Portland, OR 97212 Assistant Attorney General State of Oregon Mr. David B. McCoy Departinent of Justice 348 Hussey Lane 500 Pacific Building Grants Pass, OR 97526 520 S.
W.
Yamhill Portland, OR 97204 Mr. John A. Kullberg 15523 S. E. River Forest Drive William W. Kinsey, Esq.
Portland, OR 97222 Bonneville Power Administration P.O.
Box 3621 Ms. C. Gail Parson Portland, OR 97208 P.O.
Box 2992 Kodiak, AK 99615 s/
/
/
i v
r g Lowenstein, Newman, R
's, Axelrad & Toll 1025 Connecticut A nue, NW Washington, D. C.
20036 (202)862-8400 Dated:
May 20, 1980 d
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