ML19274D383
| ML19274D383 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 01/19/1979 |
| From: | Goodwin C PORTLAND GENERAL ELECTRIC CO. |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| TAC-07713, TAC-7713, NUDOCS 7901230281 | |
| Download: ML19274D383 (2) | |
Text
.
s
,r
- ~
[.(O { PortlandGenemlElectricCompany Cha es Goad.n. 3 etyt Vce Prt i ent January 19, 1979 Trojan Nuclear Plant Docket 50-344 License NPF-1 License Change Application 33 Director of Nuclear Reactor Regulation ATTN:
Mr. A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Dear Sir:
Pursuant to telephone conversations with members of your staff, we are forwarding three signed and 40 copies of this letter providing additional information on our License Change Application 33 regarding Technical Specifications for hydraulic snubbers.
The additional inf ormation requested is as follows:
1.
Sixteen (16) steam generator hydraulic snubbers iden-tified on Page 1 of Attachment B of our letter of September 1, 1978 as SG A-1, A-7, A-10, A-13, B-5, B-12, B-14, B-15, C-2, C-4, C-ll, C-16, D-3, D-6, D-8 and D-9 eontain a seal material known as Viton A.
The conser-vatively estimated dose to be received by this seal material on these 16 snubbers over a 40 yr lifetime 7 rads.
The exposure is expected to be less than 10 temperature environment of these hydraulic snubbers is approximately 120-140*F during normal Plant operation and f rom 70-100*F when the Plant is shut down in Mode 5 or 6.
2.
The remaining four hydraulic pipe snubbers on the main steam lines from the steam generators identified on Page 1 of Attachment B of our letter of September 1, 1978 as SS-81, SS-86, SS-88 and SS-92 contain an ethylene propylene seal material. Radiation measurements ts. ken adjacent to snubber SS-81 indicate 16 mrem /hr due to gamma and 5 mrem /hr due to neutrons at rated reactor power.
Radiation measurements taken in the proximity of the other 7 9 012 3 0 2 F/
, ~wa n au
~
PortlandGeneralBectricCor aiy v
Mr. A. Schwencer January 19, 1979 Page two three snubbers indicates levels between 10-20 mrem /hr due to gamma and 10-25 mrem /hr due to neutrons at rated reactor power. The temperature environment of these snubbers is between 70-90*F.
3.
We f eel justified in requesting an 18 month initial sur-veillance interval due to the f act that our prior inspec-tions conducted in 1976 and 1978 satisfied the proposed Technical Specifications for hydraulic snubbers.
The results of both surveillance inspections indicated that the remaining 20 safety-related hydraulic snubbers were operable.
Some of the snubbers were fouw, with minor deficiencies such as small amounts of oil ieakage, a lower than normal hydraulic oil level or a looser than normal adaptor. Maintenance-related work was performed on several snubbers during these inspections such as add-ing oil to return the level to the proper point, tighten-ing the adaptor, checking alignment, adjusting the clamp positioner, adjusting the pipe clamp for alignment, replacing cotter pins, and removal and inspection of the gland seal and housing. However, none of these items are of such significance as to render any of these 20 remain-ing hydraulic snubbers inoperable.
This additional information should provide you with the data necessary to issue the Standard Technical Specifications on hydraulic snubbers.
- However, if additional questions arise, please do not hesitate to contact us.
Sincerely, C. Goodwin, Jr.
Assistant Vice President Thermal Plant Operation and Maintenance CG/GAZ/4crw2A7 c:
Dr. W. Kelly Woods, Acting Director State of Oregon Department of Energy