ML19345G880
| ML19345G880 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 04/06/1981 |
| From: | Withers B PORTLAND GENERAL ELECTRIC CO. |
| To: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| NUDOCS 8104220611 | |
| Download: ML19345G880 (7) | |
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April 6, 1981 Cr-.,
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p Docket 50-344 License NPF-1 Mr. R. H. Engelken, Director U. S. Nuclear Regulatory Coe=ission Region V Suite 202, Walnut Creek Plaza 1990 N. California Blvd.
Walnut Creek, CA 94596
Dear Mr. Engelken:
In accordance with Amendment 55 to the Trojan Operating License dsted the attached co=mitment clarifications are forwarded 15, 1981, These clarifications represent changes from state =ents caea in January the Control Building Proceeding. A copy of these clarifications is to you.
to the Office of Nuclear Reacter Regulation.
being sent to use flanged cable trays as refer-L Contrary to Licensee's co==itment1, unflanged covers have been in use since constr enced in Attachment situation had been considered acceptable tion coe enced in 1980. That since Licensee's testi=eny had not specified flanged covers; however, a a clarification was review of responses to f3C questions indicated that required.
Sincerely, l
Bart D. Withers Vice President Nuclear l
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Mr. R. H. Engelksn April 6, 1981 CLARIFICATION REGARDING CABLE TRAY COVERS Backs'round in response to an NRC question (Q. 9 dated 7/20/79) cable tray covers protecting against a potential plate washer drop was described as flanged, 12-gauge, solid steel. In the Broehl, et al testimony, the covers were described as 12-gauge solid steel.
Commitment Modification The commitment is modified as follows:
Cable tray covers will be 12-gauge solid steel. The tray covers may be flanged or unflanged and will be secured by either standard cover clips t
or belts completely surrounding the tray and cover so as to prevent dislodging the cover from the tray.
Evaluation The flanges on the 12-gauge metal covers are to keep them from sliding
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off the trays and do not contribute to the cover's ability to resist the washer drop described in Q. 9 (7/20/79)*. In general, the cable tray covers for straight runs are flanged and attached to the trays with
'6 cover clips. The 12 gauge metal covers for curved sections of the c.able trays do not have flanges but are attached to the trays with cover clips which hold the covers securely in place. The unflanged covers secured with cover clips or belts are therefore considered equivalent to flenged Covers.
This change in commitment does not:
(1) increase the occurrence probabil-ity of an accident or malfunction of safety-related equipment previously analyzed; (2) increase the consequences of an accident or malfunction l
l of safety-related equipment previously analyzed; (3) represent the l
possibility of a different type of accident or malfunction of safety-related equipment from those previously analyzed; (4) reduce the margin of safety; nor (5) require a change to the Technical Specifications or
- Operating License.
- Cable trays exposed to potential drops of plate washers fr'om greater than 3 f t are further protected by timber planking in accordance with License Condition 2.c.(12)(e).
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Mr. R. H. Engsikea April 6, 1981 COMMITMENT CLARIFICATION REGARDING CUTTING TENDONS IN PRECAST PANELS
Background
In " Licensee's Testimony on Matters Other Than Structural Adequacy of the Modified Complex", Licensee testified that during the modification work tendons in the precast panels of the floor slab at elevation 65 ft. will not be affected.
In the process of the modification work, in order to provide continuity between rebar below and above the above-mentioned slab in wall line 41, it may be necessary to cut some of the tendons or slab rebar in the first precast panel adjacent to line R.
Commitment Clarification The commitment is changed to allow some tendons or rebar to be cut in the precast panel next to the wall on line R.
Evaluation The precast panel next to wall line R is now supported by the new wall R constructed to the bottom of the slab at elevation 65 ft.; therefore the tendons or rebar in this particular panel are no longer required as a t
l reinforcing element.
This change in commitment does not:
(1) increase the occurrence probability of an accident or malfunction of safety-related equipment previously analyzed; (2) increase the consequences of an accident or malfunction of safety-related equipment previously analyzed; (3) represent the possibility of a different type of accident or malfunction of safety-related equipment from those previously analyzed; (4) reduce the margin of safety, nor (5) require a change to the Technical Specifications or Operating License.
Mr. R. H. Eng31 ken April 6, 1981 COMMITMENT CLARIFICATION REGARDING LIFTING PLATE NO. 2
Background
in " Licensee's Testimony On Matters Other Than Structural Adequacy of the Modified
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Complex", Q84 stated that Plates 1-6 will be lifted one at a time from the incoming truck by the auxiliary hook of the Turbine Building crane, and 0105 stated that plates 7 and 8 will be hoisted from the truck at elevation 45 ft. to the Turbine Building floor at elevation 93 ft. using the 25-ton capacity hoist of the Turbine Building crane. Furthermore, Licensee's response, dated September 17, 1979 to State of Oregon Interrogatory No. 3 stated, in part, that the l
overhead crane will be tested at 110 percent of the rated hist caoacity prior to beginning the lifting operation.
l Due to the auxiliary hoist being out of service for a period of a week to ten days, in order to maintain the schedule it is necessary to use the main hoist of the Turbine Building to lift Plate No. 2.
Commitment Clartfication The commitment is changed to allow the main hoist of the Turbine Building crane to be used for lifting the plates.
r-Evaluation The rated capacity of the main hoist is 200 tons, while the weight of the heaviest plate is approximately 24 tons.
Since the capacity of the rain hook exceeds the lifted load by a large margin, the use of the main hook is acceptable. In addition, the Turbine Building crane main hoist was used during the April - June 1980 Turbine overhaul for several lifts in excess of 50 tons which qualifies the rain hoist for loads greater than the 110 percent of the 25 ton auxiliary hoist capacity.
This change in cormitment does not:
(1) increase the occurrence probability or an accident of malfunction of safety-related equipment previously analyzed; l
(2) increase the consequences of an accident or malfunction of safety-related equipment previously analyzed; (3) represent the possibility.of a different type of accident or malfunction of safety-related equipment from the previously analyzed; (4) reduce the margin of safety, nor (5) require a change to the Technical Specifications or Operating License.
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Mr. R. H. Engalkan April 6, 1981 COW.IDET CLARIFICATION REGARDING NONDESTRUCTIVE EKAMINATION OF PLATE VELDS Backa-ound In Licensee's response to NRC Question 9 dated Mey 18, 1979,and in Licensee's response to State of Oregon interrogatory 7 dated August 27, 1979, it was stated that nondestructive exar.instion of plate velds vi11 be perfor=ed by the smgnetic partical exar.ina+. ion method using a-e yoke and dry powder in accordance with AWS D T.1-79.
Use of tne a-c yoke did not prove effective in e= ' nation of initial plate veld passes. This is believed to be due to the fixsd distance between the yoke probes being too large with respect to the initial l
veld pass and parent metal configuration. Use of supplenental veld inspection methods,. which are also in accordance with AVS D 1.1-79, viIl per=it effective==4 nation of the veld pass and parent metal configura-tions.
Co--itre-t Cla-ification f
Tne co::=itment is modified and clm$1ried to per=it supple = ental plate veld nondestructive exa=ination methods which are in accordance with
'AVS D 1 1 79 These methods are magnetic partical e: car.ination by d-e probes and dry powder, dye penetrant exnr.ination,. and ultrasenic eWu-tion.
l 1N9tination l
Tnis modification and clarificatien of the co=itment permits use of supple = ental veld inspection methods which are in accordance with AWS D 1.1-79 and, pursuant to the original intent of the conitment, vill provide for effective nondestructive er.anination of plate veld::. All velds which have been inspected by use of an em'ntion method not de=onstrated to ha effective vill be rejected.
l Tcis change in ec=itnent does not: 1) increase the occurrence proba-bility of an accident or malfunction of safety-related equip =ent previonsly analyzed; 2) increase the consequences of an accident or =alfunction of I
safety-related equip =ent previously analyzed; 3) represent the possibil-ity of a different type of accident or r.alfunction of safety-related equip =ent frc= that previously analyzed; 1.) reduce the margin of safety; nor 5) require a change to the Technical Specifications or Operetion License.
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UNITED STATES OF AMERICA ggg;g, ef.<, g7gg.j NUCLEAR REGULATORY COMMISSION 1,
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BEFORE THE ATOMIC SAFETY AND LICENSING APPEAL BOARD Cn In the Matter of
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Docket 50-344 PORTLAND GENERAL ELECTRIC COMPANY,
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(Control Building Proceed (Trojan Nuclear Plant)
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CERTIFICATE OF SERVICE f //
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I hereby certify that on April 8, 1981 Licensee's letter dated
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April 6, 1981 to the NRC, Region V, with attachments, has been
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served upon the persons listed below by depositing copies thereof g5 in the United States mail with proper postage affixed for first class mail.
C.
Alan S. Rosenthal, Esq., Chairman Dr. Kenneth A. McCollom, Dean Atomic Safety and Licensing Appeal Division of Engineering, l
Board Architecture and Technology U. S. Nuclear Regulatory Commission Oklahoma State University Washington, D. C.
20555 Stillwater, Oklahoma 74074 Dr. John H. Buck, Member Dr. Hugh C. Paxton 1
Atomic Safety and Licensing Appeal 1229 - 41st Street l
Board Los Alamos, New Mexico 87544 l
U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Atomic Safety and Licensing Board Panel Dr. W. Reed Johnson, Member U. S. Nuclear Regulatory Commission Atomic Safety and Licensing Appeal Washington, D. C.
20555 l
Board I
U. S. Nuclear Regulatory Commission Atomic Safety and Licensing Appeal Washington, D. C.
20555 Panel (5)
U. S. Nuclear Regulatory Commission Marshall E. Miller, Esq., Chairman Washington, D. C.
20555 Atomic Safety and Licensing Board.
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~U. S. Nuclear Regulatory Commission i
Wash'ington, D. C.
20555 5
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i CERTIFICATE OF SERVICE Docketing and Service Section (4)
Ms. Nina Bell Office of the Secretary 3926 N. E. 12th Avenue U. S. Nuclear Regulatory Commission Portland, Oregon 97212 Washington, DC 20555 Mr. John A. Kullberg Joseph R. Gray, Esq.
15523 S. E. River Forest Drive Counsel for NRC Staff Portland, Oregon 97222 U. S. Nuclear Regulatory Commission Washington, DC 20555 Mr. David B. McCoy 348 Hussey Lane Lowenstein, Newman, Reis, Axelrad &
Grants Pass, Oregon 97526 Toll 1025 Connecticut Ave., N. W.
Ms. C. Gail Parson Suite 1214 P. O. Box 2992 Washington, DC 20036 Kodiak, Alaska 99615 Frank W. Ostrander, Jr., Esq.
Mr. Eugene Rosolie Assistant Attorney General Coalition for Safe Power State of Oregon Suite 527, Governor Bldg.
Department of Justice 408 S. W. 2nd 500 Pacific Building Portland, Oregon 97204 520 S. W. Yamhill Portland, Oregon 97204 Multnomah County Library F
Social Science and Science Dept.
William Kins'ey, Esq.
801 S. W. 10th Ave.
Bonneville Power Administration Portland, Oregon 97205 P. O. Box 3621 Portland, Oregon 97208
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Ronald W. Johnson Assistant GeneraldDounsel Portland General Electric Company Dated:
April 8, 1981 4-66.27B13 4