ML19290E121

Forwards Corrected Pages 23a & 19 & Sections 5.2.4,5.4 & 5.5 to 800214 Safety Evaluation Re Control Bldg Mods.Fourth Line on Page 19 Should Ref Section 4 Instead of Section 5. Certificate of Svc Encl

ML19290E121
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	02/15/1980
From:	Schwencer A Office of Nuclear Reactor Regulation
To:	Goodwin C PORTLAND GENERAL ELECTRIC CO.
References
TAC-11299, NUDOCS 8003040302
Download: ML19290E121 (7)

Text

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% 'A EEBRUARY. a E3 Docket No. 50-344 Mr. Charles Goodwin, Jr.

Assistant Vice President Portland General Electric Company 121 SW Salmon Street Portland, Oregon 97204

Dear Mr. Goodwin:

The Safety Evaluation Report related to the Control Building modifications transmitted to you yesterday should be corrected as follows:

1. Insert new page 23a (enclosed) which was inadvertently omitted.

2. On page 19, fourth line from the top of the page, the reference to Section 5 should be to Section 4.

3. Enclosed are SEP, Sections 5.2.4, 5.4, and 5.5, which were inadvert-ently omitted.

We regret the errors.

Sincerely, p

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f A. Schwencer, Chief Operating Reactors Branch No.1 Division of Operating Reactors Enclosu res:

1. SER page 23a

2. SER Sections 5.2.4, 5.4 and 5.5 8008040 3 02,

Mr. Charles Goodwin, Jr.

Portland General Electric Company cc:

Mr. Ronald W. Johnson, Esquire Mr. John A. Kullberg Corporate Attorney Route One Portland General Electric Company Box 250Q 121 S.W. Salmon Street Sauvie Island, Oregon 97231 Portland, Oregon 97204 Maurice Axelrad, Esquire Robert M. Hunt, Chairman Lowenstein, Newman, Reis, Board of County Comissioners Axelrad and Toll Columbia County Suite 1214 St. Helens, Oregon 97051 1025 Connecticut Avenue, N.W.

Washington, D. C.

20036 Columbia County Courthouse Law Library, Circuit Coud Room Richard M. Sandvik, Esquire St. Helens, Oregon 97051 Frank W. Ostrar. der, Jr.

Counsel for Oregon Dept. of Director, Oregon Department of Energy Energy Labor and Industries Building, Room 111 500 Pacific Building Salem, Oregon 97310 520 S.W. Yamhill Portland, Oregon 97204 Dr. Hugh D. Paxton 1229 41st Street Mr. David B. McCoy Los Alamos, New Mexico 87544 348 Hussey Lane Grants Pass, Oregon 97526 Michael Malmros U. S. Nuclear Regulatory Commission William Kinsey, Esquire Trojan Nuclear Plant 1002 N.E. Holladay P. O. Box 0 Portland, Oregon 97232 Painier, Oregon 97048 Ms. Nina Bell Dr. Kenneth A. McCollom, Dean 728 S.E. 26th Street Division of Engineering, Portland, Oregon 97214 Architecture and Technology Oklahoma State University Mr. Eugene R. Rosolie Stillwater, Oklahoma 74074 Coalition for Safe Power 215 S.E. 9th Avenue Portland, Oregon 97214

Mr. Charles Goodwin, Jr.

Portland General Electric Company cc:

Marshall E. Miller, Esquire, Chairman Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Atomic Safety and Licensing Board Panel V. S. Nuclear Regulatory Commission Washington, D. C.

20555 Docketing and Service Branch (7)

Office of the Secretary U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Alan S. Rosenthal, Esquire Atomic Safety and Licensing App,eal Board U. S. Nuclear Regulatory Concission Washington, D. C.

20555 Dr. John H. Buck Atomic Safety and Licensing Appeal Board U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Dr. W. Reed Johnson Atomic Saf ety and Licensing Appeal Board U. S. Nuclear Ra Jlatory Commission Washi ngton, D.

20555 Atomic Safety and Licensing Appeal Panel (5)

U. S. Nuclear Regulatory Commission Washington, D. C.

20555

- 23a -

protection to the cables contained inside.

The drill operator should recog-nize the difference when the drill contacts the conduit and withdraw the drill.

Should the operator fail to notice the difference and continue to drill through damaging the cables within, depending on which conduit was impacted, some of the nuclear instrumentation would be lost.

However, redun-dant instrumentation from three other channels would be available.

In the unlikely event that cables from both conduits were damaged, an inadvertent scram could occur.

Safe shutdown of the plant would be unaffected since the plant is designed to handle such occurrences and redundant instrumentation for neutron monitoring would be available.

4.2 Bolt Assembly Installation Bolts, washers and nuts will be installed at each drilling location in areas identified above.

Safety-related cables in open cable trays are present in certain of these areas and could be damaged if tools or the large steel washers were inadvertently dropped onto the cables.

The licensee has committed to install solid steel cable tray covers to prevent damage to cables from the dropping of tools, nuts or washers.

A supervisor will be in attendance during these operations to assure that the cable tray covers are in-place and that care is taken in the installation of the bolts, nuts and washers.

An analysis of the drop of one of these large steel washers, using the conservative assumption that the corner of the washer strikes the cable tray cover and that the impact energy is concentrated in the corner, demonstrates that the cable tray cover will not be punctured for washer drops from slightly greater than 3 feet above a tray.

In addition, the licensee has proposed to construct scaffolding with timber planking against the R line wall at each location where a plate washer will be installed.

Coverage of the planking will be such that the maximum height a washer could drop to the scaffold planking is 3 feet.

A test will be performed by dropping one of the large steel washers onto the planking.

If the planking cannot withstand the drop, an additional layer of planking will be added. During installation of the plate washer, the washers will not be lifted over the trays unless the planking is in place.

The planking coverage will be such that in the unlikely event a washer drops onto a steel tray the drop height will be no more than 3 feet.

5.2.4 Building Resistance to Overturning Moments and Sliding The factors of safety against gross overturning and sliding for the Control Building are given in the PGE 2/13/80 submittal.

For gross overturning, the factor of safety is so large that this cannot be significantly impacted by the previous discussions.

However, the impacts of the previous discussions on those for sliding must be presented.

5.4 Adeouacy of Testing Program to Establish Capacities and Stiffnesses of the Complex Walls As discussed previously, the testing program described in Appendix A provided much useful information.

However, it still lef t uncertainties which must be considered.

Two major areas not covered in this program were the effects of the interaction on an assemblage of panels encased in a steel frame with similar characteristics of the in-situ conditions at Trojan, and the effects of induced net tensions in the s peci mens.

5.5 _ Cyclic Effects The approach taken for deriving the stiffness degradation effects f rom the test specimens seems reasonable.

The bases for and the acceptability of the consideration of 5 OBEs, each producing 10 effective full cycles of stress, was discussed in Section 3.2.1.2.18 o' this SER.

The impacts of the previous discussions must be considered and the impacts on the analyses perforned to estimate this effect considered.

UNITED STATES OF AMERICA NUCLEAR REGULATORY CO'01ISSION BEFORE THE ATOMIC SAFETY AND LICESSING BOARD la the Matter of

)

)

PORTLAND GENERAL ELECTRIC COMPANY, ET AL. )

Docket No..

50-344

)

(Control Building)

(Trojan Nuclear Plant)

)

CERTIFICATE OF SERVICE I hereby certify that copies of a letter from NRC's A. Schwencer to PGE's C.

Goodwin, dated February 15, 1980, transmitting corrections to inadvertant clerical errors in the " Safety Evaluation by the Office of Nuclear Reactor Regulation Relating to Design Modifications to the Control Building, Trojan Nuclear Plant," dated February 14, 1980 were served on the following by deposit in the United States mail, first class, or, as indicated by an asterisk, through deposit in the Nuclear Regulatory Commission's internal mail system, this 15th day of February,1980:

Marshall E. Miller, Esq., Chairman

• Richard M. Sandvik, Esq.

Atomic Safety and Licensing Board Frank W.

Ostrander, Jr.

U.S. Nuclear Regulatory Commission Counsel for' Oregon Dept. of Washington, DC 20555 Energy 500 Pacific Building Dr. Kenneth A. McCollom, Dean 520 S.W. Yamhill Division of Engineering, Portland, OR 97204 Architecture & Technology Oklahoma State University Maurice Axelrad, Esq.

Stillwater, OK 74074 Lowenstein, Newman, Reis, Axelrad 6 Toll Dr. Hugh C.

Paxton Suite 1214 1229 41st Street 1025 Connecticut Avenue, N.W.

Los Alamos, NM 87544 Washington, DC 20036 Mr. John A. Kullberg Mr. David B. McCoy Route One 348 Hussey Lane Box 250Q Grants Pass, OR 97526 Sauvie Island, OR 97231 William W. Kinsey Mr. Eugene Rosolie 1002 N.E. Holladay Coalition for Safe Power Portland, OR 97232 215 SE 9th Avenue Portland, OR 97214 Ms. Nina Bell 728 S.E.

26th Ronald W. Johnson, Esq.

Portland, OR 97214 Corporate Attorney Portland General Electric Co pany 121 S.W. Salmon Street Portland, OR 97204

,. Dr. W.

Reed Johnson

• Atomic Safety and Licensing Board Atomic Safety and Licensing Appeal Panel

• Soard U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Washington, DC 20555 Washington, DC 20555 Atomic Safety and Licensing Appeal Alan S.

Ecsenthal, Esq.*

Panel (5)*

Atemic Safety and Licensing Appeal U.S. Nuclear Regulatory Commission Board Washington, DC 20555 U.S. Nuclear Regulatory Commission Washington, DC 20555 Docketing and Service Section ( 7)*

Office of the Secretary Dr. Jchn H.

Buck

• U.S. Nuclear Regulatory Commission Atomic Safety and Licensing Appeal Washington, DC 20555 Board U.S. ':uclear Regulatory Commission Washington, DC 20555

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