View source for 3F0884-16, Revises Schedule for Installing Portion of RCS Water Level Instrumentation,Per NUREG-0737,Item II.F.2, Instrumentation for Detection of Inadequate Core Cooling, to Refuel VI

{{Adams
| number = ML20096E321
| issue date = 08/31/1984
| title = Revises Schedule for Installing Portion of RCS Water Level Instrumentation,Per NUREG-0737,Item II.F.2, Instrumentation for Detection of Inadequate Core Cooling, to Refuel VI
| author name = Westafer G
| author affiliation = FLORIDA POWER CORP.
| addressee name = Stolz J
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| docket = 05000302
| license number = 
| contact person = 
| case reference number = RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.2, TASK-TM
| document report number = 3F0884-16, 3F884-16, NUDOCS 8409070014
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 2
}}

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August 31,1984 3F0884-16 Directar of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch #4 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 NUREG-0737, Item II.F.2 Instrumentation for Detection of Inadequate Core Cooling

==Dear Sir:==

In reference to your order dated September 6,1983, on the above subject, Florida Power Corporation is hereby informing the NRC that the schedule for installation of the portion of the reactor coolant system water level instrumentation which connects to the reactor vessel head is being revised to Refuel VI. The remainder of the reactor coolant system water level instrumentation will still be installed in Refuel V. The portion of the modification which will be installed in Refuel V includes the instrumentation from the hot leg lower tap to the top of the hot leg which will provide reactor coolant system hot leg level indication to the operator.
The reason for this revision is to permit manpower, funds, and space utilization to be directed toward the corrpletion of other required high priority projects; namely the Emergency Feedwater System Program improvements including EFIC, the Remote Shutdown System installation, the " Appendix R" modifications, and the Engineered Safety Features Actuation System testing modification. FPC also will be performing major turbine work during Refuel V.                       The refueling outage is presently planned for twenty weeks and the portion of the reactor coolant system water level system which connects to the reactor vessel head is the most difficult and costly portion of the system to install from the manpower and time aspects.
By postponing this portion of the project to Refuel VI, an estimated 3,700 manhours can be saved.
840907001' 840831 PDR ADOCK 05000302 P                           PDR A00 A GEN ER AL OFFICE 3201 Thirty-fourth street south e P.O. Box 14042, st. Petersburg, Florida 33733 e 813-868-5151

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August 31,1984 3F0884-16 Page 2 FPC requests a response to this letter by September 28,1984 in order to adequately schedule and plan the refueling outage work.
Sincere  ,
  -r-            I.
G. R. Westafer Manager, Nuclear Operations Licensing and Fuel Management EMG/feb L}}