ML19308D274
| ML19308D274 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 04/21/1977 |
| From: | Stewart W FLORIDA POWER CORP. |
| To: | |
| Shared Package | |
| ML19308D270 | List: |
| References | |
| NUDOCS 8002270721 | |
| Download: ML19308D274 (3) | |
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@l During the performance of Reactor shutdown remote from the Control Center, an excessive l
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This was pri-l
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First occurrence of high level in steam generators. Thih is second occurrence of l
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$ l excessive cooldown rate. Fed Reactor Coolant System from borated water storage tank. (77-29)l
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[o] l The cause of this occurrence was,the overfilling of the OTSG due to out-of-calibration l,
1 09 00 Qjl pressure transmitter not causing start-up feedwater' valves WV-39 and 40 to fully close.
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/ 09 80 f' Calibrated pressure transmitter and revised procedure to trip feed pump when appropriate.
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SUPPLENENTARY INFORMATION I
l 1.
Report No.
50-302/77-29
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2.
Facility:
Crystal River Unit #3 3.
Report Date:
21 April 1977 4.
Occurrence Date:
16 April 1977 i
l S.
Identification of occurrence:
During the process of performing Reactor shutdown remote from the Con-
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trol Center, an excessive cooldown rate contrary to Technical Specifi-cation 3.4.9.1 was experienced in that the cooldown rate was approximately 101 F. in 20 minutes. This was primarily caused by overfilling of the i
steam generators contrary to Technical Specification,3.4.5 to a level above 360 inches.
f.
6.
Conditions Prior to Occurrence:
Plant was in Mode 3 during test of shutdown from outside the Control Room.
Reactor had tripped.
J 7.
Description of Occurrence:
At approximately 0815, during remote shutdown test, overfilling of the OTSG's past the high level limits was experienced.
It was determined that start-up feedwater valves FWV-39 and 40 were not fully seated causing j
the overfill. An attempt wat made to throttle the FWP discharge to no avail. The steam generator drains and atmospheric dump valves were opened i
and excessive cooldown rate was experienced.
Reactor coolant temperature i
. decreased 1010 F. in 20 minutes.
l 8.
Designation of Apparent Cause of Occurrence:
The cause of this occurrence was the overfilling of the OTSG due to out-of-calibration pressure transmitter not causing start-up feedwater valves' FWV-39 and 40 to fully close.
?
9.
Analysis of Occurrence:
I At all times, the Reactor coolant temperature / pressure parameters remained within the region of acceptable operation set forth in Technical Specifica-tion 3.4.9.1, Figure 3.4.3.
Prior to start-up and power operation, an engineering evaluation was performed to determine the effects of the cool-down on the fracture toughness properties of the R coolant system.
It x
was determined that the RCS remained acceptable for continued operation.
We have been informed by Babcock & Wilcox that the cooldown transient
. which occurred on 2 March 1977 (LER-77-20) "was found to cause no derroga-tory effects". That transient was more severe than the one occurring on 16 April 1977. Therefore, it is determined that this transient did not endanger the safety of the plant.'
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.Sup'plementary Information (Cont'd.)
10.
Corrective Action:
i The pressure transmitter has been recalibrated to assure closure of the start-up feedwater valves.
In addition, the test and operating procedures have been revised to incorporate tripping of the main 4
feedwater pump at the appropriate time to prevent overfilling of' the steam generators.
^
11.
Failure Data:
This is the second occurrence of cooldown in excess of 100 F. in one hour (LER-77-20).
It is the first occurrence from these causes.
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