ML20040H140
| ML20040H140 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 02/08/1982 |
| From: | Mardis D FLORIDA POWER CORP. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.2.13, TASK-TM 3F-0282-05, 3F-282-5, NUDOCS 8202170256 | |
| Download: ML20040H140 (3) | |
Text
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M Power C o m p o s a t o o se February 8,1982
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. Mr. John F. Stolz, Chief i
.lgI884 *[s Operating Reactor Branch #4 2-Division of Licensing U.S. Nuclear Regulatory Commission
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O Washington, D.C. 20555
Subject:
Crystal River Unit 3
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Docket No. 50-302 Operating License No. DPR-72 NUREG-0737, Item II.K.2.13 Thermal-Mechanical Report - Effect of High Pressure Injection on Vessel Integrity from Small Break Loss of Coolant Accident with No Auxiliary Feedwater
Dear Mr. Stolz:
Florida. Power. Corporation (FPC) has received 'your letter dated January 4,1982, requesting information on the above subject. Specifically, you requested (1) our plant operating procedures which instruct operators in'the feed and bleed operation and limit operations within the 1000F subcooling limits following any small break loss of coolant accident and any significant cooldown transient, and (2) the basis for demonstrating that operators can follow those procedures.
FPC contends that procedures are best utilized when they are. not -submitted and docketed. The contents of procedures are changed to reflect current plant operating configurations, and submittals are not maintained current to reflect these changes.
Therefore, to preclude confusion at a later date, our procedures will be available at the site for inspection and verification by your staff or members of the regional In'spection and Enforcement Office.
Crystal River Unit 3 Emergency Procedure EP-106, " Loss of Reactor Coolant or Reactor Coolant Pressure,". Revision 33, dated November 19, 1981, specifies in Step.
1.4.9.4 for the operator to maintain reactor coolant subcooling within a region on the enclosed graph. At less than 5000F reactor coolant temperature, the limit is n,1000F.
subcooling. At greater than 5000F reactor coolant temperature, the subcooling limit may be greater than 1000F.
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Mr. John F. Stolz -
February 8,1982 Page 2 The reactor coolant temperature used during the feed and bleed operation is an average of the five highest in-core thermocouple temperatures. Of the 5000F, 3500F is the temperature necessary to provide an adequate margin of safety to ensure that the material properties meet the requirements for adequate fracture toughness as required by 10 CFR 50, Appendix G. An additional 1500F margin allows for a 500F AT across the core and a margin of 1000F for mixing in the downcomer.
Secondly, this procedure is reviewed during each year's Licensed Operator Requalification Training Program which includes simulator training.
Florida Power Corporation's Crystal River Unit 3 procedures and training programs are available for inspection as required at our site.
Very truly yours, 3d 6.
a,A David G. Mardis Acting Manager Nuclear Licensing Enclosure RMB:mm -
cc:
Mr. 3. P. O'Reilly, Regional Administrator Office of Inspection & Enforcement U.S. Nuclear Regulatory Commission 101 Marietta Street, Suite 3100 Atlanta, GA 30303 a.
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