ML20045E641
| ML20045E641 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 06/24/1993 |
| From: | Horn G NEBRASKA PUBLIC POWER DISTRICT |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| IEB-93-002, IEB-93-2, NSD930770, NUDOCS 9307020264 | |
| Download: ML20045E641 (2) | |
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.,e-y GENERAL OFFICE c Na P.O. BOX 499 COLUMBUS. NEBRASKA 68602-0499 Nebraska' Public Power. District "T4d"S?AsW" L
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NSD930770l 6'
- June'24, 1993 U S. Nuclear Regulatory Commission
. Attention: Document Control Desk Washington, D.C. 20555 Gentlemen:
Subject:
Correction to Response-to NRC Bulletin 93 Cooper Nuclear _ Station NRC Docket 50-298, DPR 46
Reference:
Letter from G. R. Horn-(NPPD) to NRC dated' June 10, 1993',
" Response to NRC' Bulletin No. 93;02"'
a correction and.
The Nebraska Public Power District (District) hereby makes provides additional clarification to its earlier response to NRC Bulletin 93 (Reference), which addressed concerns regarding fibrous ' material's in' primary containment and their potential'effect on Emergency Core' Cooling. System-(ECCS) performance following postulated Loss-Of+ Coolant-Accidents (LOCAs), While this;
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~10, 1993. response, L the' District determined that '. this ~ information. should'. be
~
correction does not' alter any of the_ conclusions. stated in cne District's~ June:
conveyed to the NRC expeditiously.
The attached, revised page two
'o f the Reference submittal identifies the '
corrections and clarifications.
Revision-bars are. provided. to Lindicate~' the '
changes made. These changes correct the identification of the Main Steam Relief Valve (71B), and clarify the discussion of che District's plans to insulate that valve. This valve' was mis-identified during primary containment.walkdowns'as the component identification tags had not yet been replaced following relief' valve setpoint bench testing.
Please note that the changes discussed above are b'eing considered in the District's ovaluation, discussed in the Reference, that addresses ' the. LOCA effects'on the permanent insulation installed in the' Drywell.
If y u have any questions on'the above, or require any additional information; pie se contact my office.
Cw R. Horn Nuc car Power Group Manager Attachment cc:
NRC Regional Administrator Region IV Arlington, TX NRC. Resident' Inspector Cooper Nuclear' Station l ~
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.y U. S. Nuclear Regulatory Commission Attachment to NSD930770 June 10, 1993-(REVISED)
Page 2 of 3 the Kaowool blankets was completed June 3,1993. Except as discussed below, the l
District will fabricate and install new sections of. permanent reflective or-metal-jacketed fiberglass insulation in these locations before startup from the current refueling outage.
The amounts and locations of the Kaowool blankets identified were as follows:
Approximately 113 square feet. on 24 inch Residual Heat Removal P ping i
Approximately 80 square feet on 12 inch Reactor Feedwater piping Approximately 12 square feet on Core Spray check valves 18 and 19 Approximately 5 square feet on 6 inch Reactor Water Cleanup piping.
Approximately 25 square feet on Main Steam Relief Valve 71B
-l The District plans to install approximately 25_ square feet of nuclear grade fiberglass blanket insulation on Main Steam Relief Valve 71B prior to startup from the 1993 outage. This material is acceptable for use in a LOCA environment, and is considered in the evaluation discussed below.
The District will complete all actions requested in Bulletin 93-02 prior to plant startup from the ongoing refueling outage, currently scheduled for June 22, 1993.*
As directed by Bulletin 93-02, a report confirming completion of the requested actions will be submitted within 30 days of completion.
The District is also evaluating, in accordance with available NRC and industry guidance, LOCA effects on the permanent metal-jacketed fiberglass insulation installed in the drywell.
This evaluation is being pursued to further' ensure that ECCS pump performance will not be degraded due to accumulation of insulation material debris on ECCS suction strainers during such events.
In accordance with 10 CFR 50.54(f), this response is submitted under oath.
If you have any questions regarding this response, or require any additional information, please contact my office.
Sincerely, G. R. Horn Nuclear Power Croup Manager
/ dis cc:
NRC Regional Administrator Region IV Arlington, TX NRC Resident Inspector Cooper Nuclear Station
- Mete:
At the time of the original writing, this date was correct. The current scheduled startup date is July 3,1992.