ML20236D066: Difference between revisions

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| number = ML20236D066
| number = ML20236D066
| issue date = 03/15/1989
| issue date = 03/15/1989
| title = Forwards Addl Info on Raw Water Pump Facility License Change,Per 890209 Telcon Re Util 881231 Ltr Including Application for Amend to License DPR-40,correcting Inconsistency Between Section 2.4 & Updated SAR
| title = Forwards Addl Info on Raw Water Pump Facility License Change,Per 890209 Telcon Re Util Including Application for Amend to License DPR-40,correcting Inconsistency Between Section 2.4 & Updated SAR
| author name = Morris K
| author name = Morris K
| author affiliation = OMAHA PUBLIC POWER DISTRICT
| author affiliation = OMAHA PUBLIC POWER DISTRICT

Latest revision as of 09:16, 20 March 2021

Forwards Addl Info on Raw Water Pump Facility License Change,Per 890209 Telcon Re Util Including Application for Amend to License DPR-40,correcting Inconsistency Between Section 2.4 & Updated SAR
ML20236D066
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 03/15/1989
From: Morris K
OMAHA PUBLIC POWER DISTRICT
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20236D071 List:
References
LIC-89-266, NUDOCS 8903220443
Download: ML20236D066 (2)


Text

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l Omatia Public Power District 1623 Harney Omaha, Nebraska 68102 2247 402/536 4000 March 15, 1989 LIC-89-266 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station P1-137 Washington, DC 20555

References:

1. Docket No. 50-285
2. Letter to NRC (Document control Desk) from OPPD (K. J.

Morris) dated December 31, 1988 (LIC-88-1137)

Gentlemen:

SUBJECT:

Additional Information on Raw Water Pump Facility License Change As requested in our telephone conversation of February 9, 1989 between P.D.

Milano of the NRC and members of the OPPD staff, additional information is attached to assist you in your review of Reference 2. Attachment 1 contains the calculation performed by Combustion Engineering regarding the limiting temperature vs. raw water flow. Also included is the internal cover sheet for calculation review and the independent review that was done on the calcul ation . Attachments 2 through 5 are the procedures that were utilized in performing the independent review.

Copies of letters to Byron Jackson pump and KETEMA are found in Attachment 6 requesting the equipment manufacturers indicate the operating assumptions contained in the calculation are correct. We have requested their responses by March 31, 1989, however, Byron Jackson has indicated it may take slightly longer for their response.

The testing of the raw water pumps is anticipated to be resolved by the response to Generic letter 88-11 on service water systems. This is due to the difficulty of the existing raw water system not having any dedicated flow instrumentation for the pumps. The surveillance tests (ST-ISI-RW-1 and ST-ISI-RW-3) are currently under review as part of the procedure upgrade program under Project 1991. It is not known at this time what changes may be incorporated into the test procedures.

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U. S. Nuclear Regulatory Commission LIC-89-266 Page 2 Revised Technical Specification pages are included in Attachment 7 to define the LC0 condition requirements for entry and exit. Attachment 7 supercedes revised Technical Specifications pages previously submitted by Reference 2. A No Significant Hazard evaluation is included.

If you have any questions, please contact us.

Sincerely, K&Morr s

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Division Manager Nuclear Operations KJM/jak c: LeBoeuf, Lamb, Leiby & MacRae R. D. Martin, NRC Regional Administrator P. D. Milano, NRC Project Manager P. H. Harrell, NRC Senior Resident Inspector Harold Borchert, Director - Division of Radiological Health State of Nebraska

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