ML20077C402
| ML20077C402 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 11/18/1994 |
| From: | Gates W OMAHA PUBLIC POWER DISTRICT |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| REF-GTECI-A-47, REF-GTECI-SC, TASK-A-47, TASK-OR GL-89-19, TAC-M74944, NUDOCS 9412010355 | |
| Download: ML20077C402 (2) | |
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Ornaha Public Power District 444 South 16th Street Mall Omaha. Nebraska 68102-2247 402/636-2000 November 18, 1994 LIC-94-0233 U. S. Nuclear Regulatory Commission Attn:
Document Control Desk Mail Station P1-137 Washington, DC 20555
References:
1.
Docket No. 50-285 2.
Letter from NRC (J. G. Partlow) dated September 20, 1989 (Generic Letter 89-19) 3.
Letter from OPPD (W. G. Gates) to NRC (Document Control Desk) dated March 19, 1990 (LIC-90-0205) 4.
Letter from OPPD (W. G. Gates) to NRC (Document Control Desk) dated December 10, 1990 (LIC-90-0941) 5.
Letter from CE0G (J. J. Hutchinson) to NRC (S. Newberry) dated October 31, 1990 (CE0G-90-736) 6.
Letter from NRC (C. O. Thomas) to CEOG (J. J. Hutchinson) dated September 13, 1994
SUBJECT:
Fort Calhoun Station (FCS) Response to Generic Letter (GL) 89-19 Regarding Unresolved Safety Issue (USI) A-47 " Safety Implication of Control Systems in LWR Nuclear Power Plants" (TAC No. M74944)
As requested by Mr. S. D. Bloom (NRC) on September 9, 1994, the Omaha Public Power District (OPPD) submits this update to OPPD's response to GL 89-19 regarding USI A-47, " Safety Implication of Control Systems in LWR Nuclear Power Plants."
In Reference 4, OPPD extended its response date pending further NRC notification and subsequent analyses from the Coabustion Engineering Owners Group (CE0G).
The CE0G presented an analysis in Reference 5, which concluded from a risk perspective that the cost to retrofit existing plants with additional overfill protection did not result in comparable safety benefits.
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U."S. Nuclear Regulatory Commission LIC-94-0233 Page 2 In Reference 6, the NRC approved the CE0G analysis with the following provisions:
1)
The plants must have procedures in place for overfill events, 2)
Any necessary training on such events must be provided to operators, and 3)
The plant specific design features must fall within the CEOG generic analysis.
OPPD has conducted the appropriate operator training and verified implementation of the procedures necessary to address steam generator overfill events and small break Loss of Coolant Accidents at FCS.
Also, OPPD has confinned that the FCS design is bounded by the Reference 5 CE0G generic analysis for steam generator overfill events.
Therefore, OPPD concludes that FCS meets the NRC's requirements for providing steam generator overfill protection and no further actions are necessary.
If you should have any questions, please contact me.
Sincerely,
/&. h h by W. G. Gates Vice President WGG/dll c:
LeBoeuf, Lamb, Greene & MacRae L. J. Callan, NRC Regional Administrator, Region IV S. D. Bloom, NRC Project Manager R. P. Mullikin, NRC Senior Resident Inspector I
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