ML17355A139: Difference between revisions
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| issue date = 12/05/2017 | | issue date = 12/05/2017 | ||
| title = Potentially Degraded Snubber SF1154 Hydraulic Fluid Batch 14ELVS145 Final Report Per 10 CFR Part 21 | | title = Potentially Degraded Snubber SF1154 Hydraulic Fluid Batch 14ELVS145 Final Report Per 10 CFR Part 21 | ||
| author name = Brown D | | author name = Brown D | ||
| author affiliation = Lake Engineering Co | | author affiliation = Lake Engineering Co | ||
| addressee name = | | addressee name = | ||
| Line 15: | Line 15: | ||
=Text= | =Text= | ||
{{#Wiki_filter:LAKE ENGINEERING CO. P.O. Box296 10 Austin Avenue Greenville, RI 02828 Tel: 401-949-4733 Fax: 401-949-0220 December 5, 2017 U S Nuclear Regulatory Commission Attn: Document Control Room Washington, DC 20555-0001 | {{#Wiki_filter:LAKE ENGINEERING CO. | ||
P.O. Box296 10 Austin Avenue Greenville, RI 02828 Tel: 401-949-4733 Fax: 401-949-0220 December 5, 2017 U S Nuclear Regulatory Commission Attn: Document Control Room Washington, DC 20555-0001 | |||
==Subject:== | ==Subject:== | ||
Potentially Degraded Snubber SF1154 Hydraulic Fluid Batch 14ELVS145 Final Report per 10 CFR Part 21 This letter reflects new information available since our interim ~eport dated November 3, 2017. Three Mile Island We have concluded that a substantial safety hazard does not exist at this plant as a result of the subject fluid. _ Millstone**, . . We have concluded that a substantial safety hazard does not exist at this plarit as a result oMhe | Potentially Degraded Snubber SF1154 Hydraulic Fluid Batch 14ELVS145 Final Report per 10 CFR Part 21 This letter reflects new information available since our interim ~eport dated November 3, 2017. | ||
* subject fluid. * | Three Mile Island We have concluded that a substantial safety hazard does not exist at this plant as a result of the subject fluid. _ | ||
* The status of the subject issue as it applies to US nuclear plants to which SF1154 fluid from Batch 14ELVS145 was shipped by Lake Engineering Company is summarized in the following table. Millstone Fluid used in some installed snubbers No substantial safety hazards exist. Nine Mile Point , Fluid not used No substantial safety hazards exist. Duane Arnold Fluid not used No substantial safety hazards exist. Monticello Fluid not used No substantial safety hazards exist. Pilgrim Fluid not used No substantial safety hazards exist. Three Mile Island Fluid used in some installed snubbers No substantial safety hazards exist. Grand Gulf Fluid used in some installed snubbers No substantial safety hazards exist. Peach Bottom Fluid used in some installed snubbers No substantial safety hazards exist. | Millstone**, | ||
U S Nuclear Regulatory Commission Potentially Degraded Snubber SF1154 Hydraulic Fluid Batch 14ELVS145 Final Report per | . . We have concluded that a substantial safety hazard does not exist at this plarit as a result oMhe | ||
}} | * subject fluid. * | ||
* The status of the subject issue as it applies to US nuclear plants to which SF1154 fluid from Batch 14ELVS145 was shipped by Lake Engineering Company is summarized in the following table. | |||
Millstone Fluid used in some installed snubbers No substantial safety hazards exist. | |||
Nine Mile Point , Fluid not used No substantial safety hazards exist. | |||
Duane Arnold Fluid not used No substantial safety hazards exist. | |||
Monticello Fluid not used No substantial safety hazards exist. | |||
Pilgrim Fluid not used No substantial safety hazards exist. | |||
Three Mile Island Fluid used in some installed snubbers No substantial safety hazards exist. | |||
Grand Gulf Fluid used in some installed snubbers No substantial safety hazards exist. | |||
Peach Bottom Fluid used in some installed snubbers No substantial safety hazards exist. | |||
U S Nuclear Regulatory Commission December 5, 2017 Potentially Degraded Snubber SF1154 Hydraulic Fluid Batch 14ELVS145 Page2 Final Report per 10 CFR Part 21 If there are any questions or if additional information is required, please contact the writer by mail or by phone using the contact information provided above or by email at dbrown@lakeengineeringri.com. | |||
Very truly yours, LAKE ENGINEERING COMPANY D. P. Brown, P.E. | |||
President DPB/d/let120517.nrc cc: P. Guay- QA Mgr.}} | |||
Latest revision as of 02:19, 10 November 2019
| ML17355A139 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Peach Bottom, Grand Gulf, Three Mile Island  |
| Issue date: | 12/05/2017 |
| From: | David Brown Lake Engineering Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML17355A139 (2) | |
Text
LAKE ENGINEERING CO.
P.O. Box296 10 Austin Avenue Greenville, RI 02828 Tel: 401-949-4733 Fax: 401-949-0220 December 5, 2017 U S Nuclear Regulatory Commission Attn: Document Control Room Washington, DC 20555-0001
Subject:
Potentially Degraded Snubber SF1154 Hydraulic Fluid Batch 14ELVS145 Final Report per 10 CFR Part 21 This letter reflects new information available since our interim ~eport dated November 3, 2017.
Three Mile Island We have concluded that a substantial safety hazard does not exist at this plant as a result of the subject fluid. _
Millstone**,
. . We have concluded that a substantial safety hazard does not exist at this plarit as a result oMhe
- subject fluid. *
- The status of the subject issue as it applies to US nuclear plants to which SF1154 fluid from Batch 14ELVS145 was shipped by Lake Engineering Company is summarized in the following table.
Millstone Fluid used in some installed snubbers No substantial safety hazards exist.
Nine Mile Point , Fluid not used No substantial safety hazards exist.
Duane Arnold Fluid not used No substantial safety hazards exist.
Monticello Fluid not used No substantial safety hazards exist.
Pilgrim Fluid not used No substantial safety hazards exist.
Three Mile Island Fluid used in some installed snubbers No substantial safety hazards exist.
Grand Gulf Fluid used in some installed snubbers No substantial safety hazards exist.
Peach Bottom Fluid used in some installed snubbers No substantial safety hazards exist.
U S Nuclear Regulatory Commission December 5, 2017 Potentially Degraded Snubber SF1154 Hydraulic Fluid Batch 14ELVS145 Page2 Final Report per 10 CFR Part 21 If there are any questions or if additional information is required, please contact the writer by mail or by phone using the contact information provided above or by email at dbrown@lakeengineeringri.com.
Very truly yours, LAKE ENGINEERING COMPANY D. P. Brown, P.E.
President DPB/d/let120517.nrc cc: P. Guay- QA Mgr.