ML20126C777
| ML20126C777 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 03/18/1980 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | Goodwin C PORTLAND GENERAL ELECTRIC CO. |
| References | |
| NUDOCS 8004090322 | |
| Download: ML20126C777 (5) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION e
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MARCH 1 8 1980 Docket No. 50-344 Mr. Charles Goodwin, Jr.
Assistant Vice President Portland General Electric Company 121 S. W. Salmon Street Portland, Oregon 97204
Dear Mr. Goodwin:
In conducting our review of your December 28, 1979 letter relating to the inservice inspection program at Trojan Nuclear Plant, we have determined that we will need the additional information identified in the enclosure to continue our review.
In order for us to maintain our review schedule, your response is requested within 45 days of your receipt of this letter.
Please contact us if you have any questions concerning this request.
Sincerely,
/
H(WWOL A. 3chwencer, Chief Operatng Reactors Branch #1 Division of Operating Reactors
Enclosure:
Request for Additional Information cc w/ enclosure:
See next page 8094090 ir
MARCH 2IN
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Mr. Charles Goodwin, Jr.
Portland General Electric Co@any cc: Mr. J. W. Durham, Esquire Robert M. Hunt, Chairman Vice President and Corporate Counsel Board of County Comissioners Portland General Electric Company Columbia County 121 S.W. Salmon Street St. Helens, Oregon 97501 Portland, Oregon 97204 Warren Hastings, Esquire Counsel for Portland General Electric Co@any 121 S.W. Salmon Street Portland, Oregon 97204 Mr. Jack W. Lentsch, Manager Generation Licensing and Analysis Portland General Electric Company 121 S.W. Salmon Street Portland, Oregon 97204 Columbia County Courthouse Law Library, Circuit Court Room St. Helens, Oregon 97501 Director, Oregon Department of Energy Labor and Industries Building, Room 111 Salem, Oregon 97310 Richard M. Sandvik, Esquire Counsel for Oregon Energy Facility Siting Counsel and Oregon Department of Energy 500 Pacific Building 520 S.W. Yamhill Portland, Oregon 97204 Michael Malmros, Resident Inspec:or U. S. Nuclear Regulatory Comission Trojan Nuclear Plant P. O. Box 0 Rainier, Oregon 97048 Mr. Donald W. Godard, Supervisor Siting and Regulation Oregon Department of Energy Labor and Industries Building, Room 111 Salem, Oregon 97310
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..s PORTLAND GENERAL ELECTRIC LOMPANY b
INSERVICE INSPECTION PROGRAM FOR THE i-SECOND FORTY MONTHS O' THE FIRST TEN YEAR INTERVAL 4
Requests for Additional Information A.
General p
I.
Table 1 1.
Please explain the absence of the following categories in Table 1:
Re,a,etor Vessel Pressurizer 81.1 B-A B2.3 B-E Bl.12 B-H B2.5 B-G-1 B2.6 B-G-1 B2.7 B-G-1 B2.9 B-I-2 Steam Generators Pipino PressureLB_oundag
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B3.2 B-D B4.2 B-G-1 B3.4 B-G-1 B4.3 B-G-1 B3.5 B-G-1 B4.4 B-G-1 B3.6 B-G-1 B4.6 8-J P3.7 B-9 B3.8 B-1-2 Pumps Valves B5.4 B-K-1 B6.1 6-G-1 D5. 6 B-L-1 B6.2 B-G-1 B 5. 7 B-L-2 B6. 3 B-G-1 BS. 9 B6.4 B-K-1
'06.6 B-M-1 66.7 B-M-2 II. Tabl.e 2 1.
Please explain the absence of the following categories in Table 2:
Letdown Excess Letdown Heat Heat Exchanger Exchanotr C1.2 C-B C1.2 0-B C1.3 C-C C1.3 C-C C1.4 C'-D 1
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. II. Table 2 - Continued i s. d.i.
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s.y Recenerative Heat Exchancer Seal Water Meat ExchanMr' 9 C1.2 C-B C1.2 C-B C1.3 C-C C1.3 C-C C1.4 C-D C1.4 C-D j
Reactor Co'olant Filter and Steam Genretor Seat Hater Return Filter C1.3 C-C C1.4 C-D Volume Co,n,tyl Tank Charoing Pump Stabilizer Separator C1.2 C-B
.u-C1.2 C-B C1.3 C-C C1.4 C-D Pipine Systems Pumps C2.3 C-F. C-G C3.3 C-E-1 C3.4 C-E-2 Valves C4.1 C-F. C-G C4.3 C-E-1
!!I. ASME Section XI Exemptions
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1.
Paragraph IWC-1220(c) of the 1974 Edition permits the exemption from examination of ECCS components provided that the control of fluid ch'emistry is verified through periodic sampling.
The control of fluid chemistry is intended to minimize corrosive effects, particularly stress corrosion. The " chemistry control" provision was deleted from the 1977 Edition of Section XI becast.. practical evaluation, review and acceptance standards were not defined.
It is the position of the staff that the exemption described in
!WC-1220(c) is not an acceptable basis for exempting ECCS components from inservice examination.
Therefore, the inservice program should be revised to include components exempted under IWC-1220(c).
2.
What criteria was used by Portland General Electric to determine maximum permissible line breaks for exemption of components under IWB-1220(b)(1) 7 IV.
Requests for Relief 1.
Relief 4.1.1.
The staff has taken the following position concerning the adoption of Appendix III:
Indication 50" of DAC or greater shall be recorded.
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IV.
Requests for Relief - Continued
'An indication 100% of DAC or greater shall be evaluated by a level II or Level III examiner to the extent necessary to determine the siza, shape, identity and location of the reflector, e
Any non-geometric indication, 20% of DAC or greater, discovered during the ultrasonic (UT) examination shall bc recorded and investigated by a Level II or Level III examiner to the extent necessary to determine the shape, identity and location of the reflector.
The licensee's request for the use of Appendix III should be modified to include the guidelines outlined abovc.
2.
Relief 4.2.4.
What is the maximum permissible line break with normal reactor make-up?
If this weld cannot be examined, will another weld be examined in its place?
3.
Relief 4.2.5.
If the three inch weld on line RC-2501-10-1 cannot be examined. will another weld be examined in its place ?
4.
Relief 4.2.7.
Is there a scheduled or routine maintenance on reactor coolant pumps?
5.
Relief 4.2.8.
Has a dual beam refracted L-wave technique been attempted or considered as an examination for the regenerative beat
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exchanger.?
j 6.
Relief 4.2.9.
Have higher beam angles (>45') been attempted or considered in the examiratior. rf the trir vailtf vess?it ?
7.
Relief 4.2.11.
Please furnish drawings and/or details to show the inaccessibility of these welds.
8.
Relief 4.2.12.
Please furnish drawings and/or details on the location of pump casing welds.
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