TXX-6158, Interim Deficiency Rept CP-86-22 Re Capacity of Present Fan Cooler Design in Safeguards Area to Adequately Handle Heat Load.Initially Reported on 860402.Engineering Evaluation Determined That Fans Adequately Sized.Next Rept by 870520
| ML20212B114 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 12/12/1986 |
| From: | Counsil W, Keeley G TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | Johnson E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| CP-86-22, TXX-6158, NUDOCS 8612290173 | |
| Download: ML20212B114 (2) | |
Text
A Log # TXX-6158 File # 10110 909.4 TEXAS UTILITIES GENERATING COMPANY 7 NAY TOWER. 400 MORTIE OLIVE STREET.1.FL el. I)ALLAS. TEXAS 753D8 December 12, 1986 M@S0Wg y
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i Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects d
'J U. S. Nuclear Regulatory Commission L
611 Ryan Plaza Drive, Suite 1000 u
Arlington, Texas 6011
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 SAFEGUARDS AREA FAN COOLERS SDAR: CP-86-22 (INTERIM REPORT)
Dear Mr. Johnson:
On April 2,1986, we verbally notified your Mr. T. F. Westerman of a deficiency involving the capacity of the present fan cooler design in the Safeguards area to adequately handle the heat load in several rooms. This is an interim report of a potentially reportable item under the provision of 10CFR50.55(e). We have submitted interim reports logged TXX-4780, TXX-4894, and TXX-5008, dated April 30, 1986, July 3, 1986, and September 12, 1986, respectively.
During a review of Unit 2 preoperational test procedures, a comparison of fan cooler specifications and drawings identified cooling capacities below the calculated heat loads in the design basis calculation. Test performance data for Unit I coolers may have been accepted at values below both the design heat loads and equipment capacities.
In order to assess the impact of this condition on the safety of plant operations, an engineering evaluation was undertaken to determine if failure of equipment cooling capacities to meet required design criteria could result in an inability of associated safety-related systems to perform as required following LOCA with loss of offsite power.
The completed calculations for Unit 1 have determined that the emergency fan coolers (served by the safety chilled water system) are adequately sized to l
maintain the room temperatures, within the FSAR requirements, following a LOCA coincidental with loss of offsite power. However, we have determined that the chilled water flow rates require rebalancing.
We are continuing with our evaluation which includes revising the design documents as indicated above. Unit 2 calculations are scheduled for completion by April 30, 1987.
Upon completion of the engineering evaluations, an assessment of this issue can be completed.
8612290173 861212 PDR ADOCK 05000445 S
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December 12, 1986 Page 2 We anticipate submitting our next report no later than May 20, 1987.
Very truly yours, hY
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W. G. Counsil By:[
4 G. S. Keeley Manager, N ensing GLB/gj c - Region IV (0 + 1 copy)
Director, Inspection and Enforcement (15 copies)
U. S. Nuclear Regulatory Commission Washington, D. C.
20555
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