ML20235K679
| ML20235K679 | |
| Person / Time | |
|---|---|
| Site: | River Bend |
| Issue date: | 09/28/1987 |
| From: | Paulson W Office of Nuclear Reactor Regulation |
| To: | Deddens J GULF STATES UTILITIES CO. |
| Shared Package | |
| ML20235K682 | List: |
| References | |
| NUDOCS 8710050194 | |
| Download: ML20235K679 (1) | |
Text
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l September I28,1987.
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'D'oc'ket No.' 50-458 Mr. James C. Deddens-Senior Vice Presidenti(RBNG)
Gulf-States Utilities P. 0.L Box 220
, St. Francisville, LA; 70775 y
ATTN:
Nuclear Licensing
Dear Mr. Deddens:
SUBJECT:
ADEQUACY OF ULTIMATE HEAT SINK TEMPERATURE.
MONITORING SYSTEM The staff has completed its review of your letter dated June 29,'1987.which provided a description of a proposed temperature monitoring system'for the L
River Bend Station (RBS) ultimate heat sink.
Your letter was in response to License Condition 2(C)(9) of Facility Operating License NPF-47 and Supplement 3' of the Safety Eva'luation Report related to the operation of River Bend Station
-(NUREG-0989).
This license condition requires that prior to startup following the first refueling outage, Gulf States Utilities (GSU): shall have installed and operational'~in the ultimate heat sink a permanent temperature monitoring system acceptable to the NRC staff and Technical Specification modifications as required.
-Based on our review, we find that the design as proposed by GSU to be acceptable and sufficient to satisfy.the requirements for a' temperature' monitoring system i
for the RBS ultimate heat' sink. -The bases for this conclusion are contained in the enclosed safety evaluation.
Your June 29, 1987 letter indicated that GSU was currently reviewing the RBS technical specifications regarding the temperature. monitoring system to deter-mine the need for revisions.
As stated in the enclosed safety evaluation, please provide proposed technical specifications for staff review and approval.
The reporting and/or recordkeeping requirements' contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.
Sincerely, l
Walter A. Paulson, Project Manager Project Directorate - IV j
Division of Reactor Projects - III,
{
j.
IV, V and Special Projects
Enclosure:
8710050194 870928 DR p
ADOCK 05000458 As stated PDR cc w/ enclosure:
See next page DISTRIBUTION 3 Docket;Eile-NRC PDR Local PDR PD4 Reading F. Schroeder-J. Calvo P. Noonan W. Paulson 1
OGC-Bethesda E. Jordan J. Partlow ACRS (10) 1 PD4 Plant File PD4/L P
PD4/D / N f
PNogn WPaulson:sr JCalvo S/)7' /87 9p/87 9/2t/87
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