ML20071B317
| ML20071B317 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 02/21/1983 |
| From: | Westafer G FLORIDA POWER CORP. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| 3F-0283-25, 3F-283-25, NUDOCS 8302280148 | |
| Download: ML20071B317 (2) | |
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Power C On POR ATION February 21,1983 3F-0283-25 i
Director of Nuclear Reactor Regulation Attention: Mr. Darrell G. Eisenhut, Director Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 Status of Outstanding Commitments
Dear Sir:
In a letter to you dated July 16, 1980, Florida Power Corporation (FPC) documented the status of 51 actions which were committed to following the February 26,1980, transient at Crystal River. At that time eight of the 51 items were identified as being incomplete.
This letter provides an updated status of those remaining eight items.
Six of the eight items involved the final verification testing of plant modifications. This The seventh item involved testing was completed shortly after restart in July,1980.
removal of two emergency feedwater valves from the steam line rupture matrix. At the time of our July,1980, letter the safety justification for this action was still being prepared. This justification has since been completed and approved by the NRC; however, the change is still under in-house FPC review.
The last item involved addition of redundant instrumentation displays for five plant parameters. These parameters were:
1.
Decay Heat Suction Temperature 2.
Startup Feedwater Flow 3.
Emergency Feedwater Flow 4.
Decay Heat Flow 5.
High Pressure Injection (HPI) Flow Our July,1980 letter indicated that the first two parameters were erroneously included on the original list of parameters and that the remainder of this instrumentation would be The installed at the first outage of sufficient duration following receipt of equip.nent.
third parameter (Emergency Feedwater Flow) is still awaiting delivery of equipment a is presently scheduled for installation concurrent with the Emergency Feedwater Initiation and Control System Upgrade during Refuel V.
8302280148 830221 PDR ADOCK 05000 General Office 320 Tmrty-fourin street soutn. P O. Box 14042, St. Petersburg Florida 33733 e 813-8 U
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c c-4 Mr. Darrell G. Eisenhut' 3F-0283-25 Page 2 The remaining.two parameters (Decay Heat Flow and HPI Flow) were scheduled for installation during the last refueling outage which began in September,1981. During that outage all of the indicated instrumentation was installed. However, it was recently -
discovered that due to. inadequate review and processing of one of the Modification
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Approval Records (MAR's) associated with this instrumentation, half of the committed indicators were never made operational. As a result of this error, redundant indication of Decay Heat Flow and HPI Flow, fed from independent power supplies, is still not available
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to the operator.
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The required final calibration and checkout of these instruments has been added to our RefuelIV outage schedule and will be completed prior to restart from that outage which is currently scheduled to begin March 19, 1983.
Sincerely, f
G.~ R. Westafer Manager Nuclear Licensing and Fuel Management AEF:mm 1
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