ML20212F734: Difference between revisions

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{{Adams
#REDIRECT [[3F0287-14, Forwards Semiannual Radioactive Effluent Release Rept, Jul-Dec 1986. Future Repts Will Include Statement Re Reported Site Boundary Doses to Individual Members of Public]]
| number = ML20212F734
| issue date = 02/27/1987
| title = Forwards Semiannual Radioactive Effluent Release Rept, Jul-Dec 1986. Future Repts Will Include Statement Re Reported Site Boundary Doses to Individual Members of Public
| author name = Simpson E
| author affiliation = FLORIDA POWER CORP.
| addressee name =
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000302
| license number =
| contact person =
| document report number = 3F0287-14, 3F287-14, NUDOCS 8703050148
| package number = ML20212F739
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 2
}}
 
=Text=
{{#Wiki_filter:l h
Power COQPOR AT ION February 27, 1987 3F0287-14 Document Control Desk U.S. Nuclear Regulatory Comission Washington, DC 20555
 
==Subject:==
Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 Semiannual Radioactive Effluent Release Report
 
==Dear Sir:==
 
Pursuant to Title 10, Code of Federal Regulations, Part 50.36a(a)(2) and Crystal River Unit 3 Technical Specification 6.9.1.5(d), Florida Power Corporation (FPC) hereby submits the Crystal River Uni t 3 Semiannual Radioactive Effluent Release Report for the period July 1, 1986 through December 31, 1986.
Previous Semiannual Reports have not explicitly stated the reported site boundary doses to individual members of the public are more conservative than the individual doses to the worst case individual member of the public inside the site boundary and, therefore, represent the worst case individual doses to any member of the public.                      This report, and future reports, will include a statement to this effect.
Crystal River Unit 3 Technical Specification 3.3.3.9(b) requires the reporting of any radioactive gaseous effluent monitoring instrumentation being inoperable for more than thirty (30) days in the next Semiannual Radioactive Effluent Release Report.              The Semiannual Report for the second half of 1985 f ailed to contain information concerning the inoperability of the RM-A2 mid and high range post accident sampling instrumentation as requi red . The inoperability of these monitors was reported by Florida Power Corporation in Special Report 85-03 dated August 21, 1985, as required by Technical Specification 6.9.2(p). The Special Report provided 0      0    02 PDR k
GENERAL OFFICE: 3201 Thirty-fourth Street South
* P.O. Box 14042
* St. Petersburg, Florida 33733 * (813) 866-5151 A Florida Progress Company
 
Fcbruary 27, 1987
          !3F0287-14 Page.2 the required information of Technical, Specification 3.3.3.9(b) concerning _
          'the ~ reason' for; monitor 1 1noperability and -corrective actions. Any - further -
radioactive gaseous effluent monitoring instrumentation inoperability will .
be reported as required.
Sincerely,
{
E. C. Simpson Director, Nuclear Operations Engineering and Licensing GMF/feb-                                                                            j Enclosure xc: Dr. J. Nelson Grace (1)
Regional Administrator, Region II-Mr,- T. F.~ Stetka -(1)-
Senior Resident Inspector l
l G
l.
L_}}

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