ML20077P991
| ML20077P991 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 08/15/1991 |
| From: | Fuller C PUBLIC SERVICE CO. OF COLORADO |
| To: | Weiss S NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| P-91270, NUDOCS 9108200170 | |
| Download: ML20077P991 (2) | |
Text
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@ Public Sery ce' ML"A.-
August 15, 1991 i
Fort St. Vrain Unit No. 1 P-91270 l
U. S. Nuclear Regulatory Commission ATTN: Document Control Desk l
Washington, D.C.
20555 t
ATTN: Dr.-Seymour H. Weiss, Director l
Non-Power Reactor, Decommissioning and f
Environmental Project Directorate j
Docket No. 50-267
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SUBJECT:
FIRE PROTECTION C00LDOWN EQUIPMENT INOPERABILITY l
Dear Dr. Weiss:
.l This letter provides a report describing the inoperability of j
firewater pump P-4501, which is required for one of the two fire protection cooldown trains at Fort St Vrain (FSV).
Public Service i
Company of Colorado (PSC) is providing this report in accordance with
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the requirements of the FSV Fire Protection Program Plan (FPPP).
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The FSV Fire Protection Operability Requirements (FPORs) contained in l
the FPPP require two fire protection cooldown trains.
These trains
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ensure adequate cooling water flow to the prestressed concrete reactor vessel (PCRV) -liner in the event of a
- fire, FPOR-16 specifies that firewater pump P-4501 is used to supply cooling water in Train 1.
P-4501 has been inoperable for more than 7 days.
Therefore, in accordance with FPOR-16, Action a.3, this report is provided to outline the cause of the inoperability, the actions taken, and the schedule for restoring the pump to an operable status, j
Cause of Inoperability l
1 In June 1991, during the annual fire suppression water system flush I
in accordance with FPOR-11, system flow rates were observed to be slightly below expected values.
FPOR-11 does not specify minimum flow rates, so no equipment was declared inoperable at that time.
PSC initiated an investigation to determine whether the low flow i
condition was due to a plugged inlet screen to P-4501 or degradation of the pump. On July 9, 1991 PSC personnel disassembled firewater pump P-4501, and determined that certain parts of the pump required
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replacement.
These parts were not readily available, however, and i
they could not be obtained within the 7 days allowed by FPOR-16.
910s200170 910815
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P-91270 Page 2 August 15, 1991 It is noted that at all times during the inoperability of firewater pump P-4501, an equivalent firewater pump, P-4501S, was available.
P-4501 and P-4501S are identical in capacity and are capable of supplying firewater to the same equipment. P-4501 is electric motor driven and P-45015 is diesel engine driven.
Therefore, the availability of a water source for fire protection cooldown Train 1
was never in jeopardy.
It addition, the redundant fire protection cooldown train, Train 2 has remained operable throughout the inoperability of P-4501.
Actions Taken PSC has prepared an engineering evaluation to qualify the use of the diesel engine driven firewater pump, P-45015, in fire protection cooldown Trair 1.
This evaluation was documented in an Engineering Evaluation, EE-FP-025, with an approved Safety Evaluation in accordance with the provisions of 10 CFR 50.59.
FPOR-16 allows the qualification of alternate compensatory reasures under the authority of 10 CFR 50.59.
- Also, in accordance with FPOR-16, a fire watch was established on fire protection cooldown Train 2 when firewater pump P-4501 was taken out of service.
Schedule for Restoration PSC is planning to complete the repairs and restore P-4501 to operable status by August 30, 1991.
If you have any questions regarding the inoperability of firewater pump P-4501, please contact Mr. M. H. Holmes at (303) 480-6960.
Sincerely, bl ?.
LLJflhG k, C. H. Fuller Manager, Nuclear Production and Station Manager CHF/SWC/img cc:
Regional Administrator, Region IV Mr. J. B. Baird Senior Resident inspector Fort St. Vrain
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