ML20072Q759
| ML20072Q759 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 03/31/1983 |
| From: | Westafer G FLORIDA POWER CORP. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| 3F-0383-32, 3F-383-32, TAC-51300, NUDOCS 8304050312 | |
| Download: ML20072Q759 (1) | |
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Power C O R F O R & T e O ss March 31,1983 3F-0383-32 Director 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 Integrated Leak Rate Testing
Dear Mr. Stolz:
Florida Power Corporation hereby requests NRC approval to perform a short duration integrated leakage rate test (Type A) at Crystal River Unit 3 (CR-3). The short duration test will be performed to meet the criteria of Bechtel Topical Report NB-TOP-1, Revision 1, dated November 1,1972,
" Testing Criteria for Integrated Leakage Rate Testing of Primary Containment Structures for Nuclear Power Plants". The test will also be in conformance with CR-3 Technical Specifications,10 CFR 50 Appendix 3 and ANSI N45.4-1972, " Leakage-Rate Testing of Containment Structures for Nuclear Reactors".
In addition to meeting the above criteria, the mass point technique will be used to calculate the leakage rate. This technique is recommended in ANSI N56.8 - 1981, " Containment System Leakage -
Testing Requirements" for short duration leak rate tests.
The measured overall integrated containment leakage rate of less than or equal to 0.75 La (where La equals 0.25 percent by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 49.6 psig) will be used as the acceptance criteria as required by -
10 CFR 50, Appendix 3 and CR-3 Technical Specification 3.6.1.2.a.
Florida Power Corporation understands that the Bechtel Topical Report has been approve'd by the NRC. The use of this technique will not require technical specification changes; however, it.will require a change to the CR-3 FSAR. This change will be included in the 1984 FSAR update.
Please provide your response to this request as soon as possible so that planning for this test can be :
completed as the test is scheduled to be performed at the end of our current refueling outage (July,-
1983).
, Sincerely, t
. R. Westafer loOI
~ Manger j
Nuclear Licensing and Fuel Management 8304050312 83033'1
~
PDR'ADOCK DP/ mig P
05000302
.PDR i cc: Mr. 3. P. O'Reilly s/
General Office 320i Tretyentn street souin. P.O. Box 14042. St. Petersburg. Florda 33733 813--866-5151