ML19319D607
| ML19319D607 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 03/13/1969 |
| From: | Morris P US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Rodgers J FLORIDA POWER CORP. |
| References | |
| NUDOCS 8003170775 | |
| Download: ML19319D607 (4) | |
Text
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e, UNITED STATES
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ATOMIC ENERGY COMMISSION d
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WASHING 10N. D.C. 20545
'g, "#g March 13, 1969 Docket No. 50-302 Florida Power Corporation 101 Fifth Street South St. Petersburg, Florida 33701 Attention:
Mr. J. T. Rodgers Nuclear Project Manager Gentlemen:
We met with you and your contractors on February 27, 1969 to discuss the issues that were not fully resolved during the construction permit review of the Crystal River Unit 3 station. Our review of your Pro-visional Operating License application, to be filed at a later date, can be expedited by the filing of selected information as it becomes available. We discussed the topics, including the anticipated avail-ability dates, in our meeting. Further details are contained in Part I of the Attachment to this letter.
We have also included in Part II of the Attachment several items for which information is required as soon as available. Please supply this information in the form of a supplement to your application.
Sincerely yours, J
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i Peter A. Morris, Director Division of Reactor Licensing-
Enclosure:
Attachment ec:
Roy B. Snapp 1725 K Street, N.W.
Washington, D. C.
20006 8003170 % f g
1 ATTACHMENT DISPOSITION OF TOPICS DISCUSSED AT MEETING WITH FLORIDA POWER CORPORATION ON CRYSTAL RIVER UNIT 3 FEBRUARY 27, 1969 I. Topics for which Information is Desirable, but not Mandatory, prior to POL A.
Research and Development Items We understand from our meeting that the topical reports on the following subjects will be issued by your nuclear steam system supplier, the B&W Company.
a.
Once-Through Steam Generator.
Second Quarter 1969 b.
In-Core Detectors.
Second Quarter 1969 c.
Core-Barrel Check Valve.
Mid-1969 d.
Xenon Oscillation.
Early 1970 e.
Iodine Removal..
Second Quarter 1969 f.
Fuel Rod Failures During LOCA.
Early 1970 The submission of this information in the form of topical reports is acceptable, and no further action is required by Florida Power Corporation at this time.
The R&D on the Control Rod Drives is discussed separately in this attachment. We have no availability date on the Thermal-Hydraulics topic as mentioned in our Safety Evaluation, in reference to the pressure-vessel scale-model flow tests. Please provide us with the manner and timing for submission of that information.
B.
Combined Seismic and Blowdown Forces We were notified in the meeting that a topical report will be submitted by B&W in the second quarter of 1969. No action by Florida Power Cor-poration is indicated at this time.
C.
Pressure-Vessel Thermal Shock We understand that B&W will submit a topical report on pressure vessel thermal shock in May 1969.
In our safety evaluation (pages 26, 55) and at the public hearing (Transcript pp 449-459), we stated that the appli-cant should continue his work on thermal shock analysis as expeditiously as possible, and that the ' applicant should explore possible changes to the facility to eliminate the need to consider potential vessel failure due to thermal shock. It is our understanding, based on our meeting,
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that the forthcoming topical report will not be responsive to the sub-ject of facility changes. We therefore request that Florida Power Cor-poration continue to review this subject and provide a suitable and timely response.
II.
Topics for Which Information Should be Supplied as Soon as Available A.
tiurricane Ef fects From our meeting we are aware of your intentions to modify your design.
Provide the calculations on storm tide and wave runup, and minimum water levels, and the plant design features asacciated with these calculations.
B.
Control Rod Drives Please provide a description of your proposed modification to the control rod drive system. You may reference material provided in connection with other applications if you d: sire.
C.
Reactor Building Fan Coolers We stated in our safety evaluation (page 22) that we would review the final design of these coolers when available. Please provide the final design.
If you refer to another application in your answer, provide a list of any design or construction differences.
D.
Quality Assurance We discussed quality assurance at our meeting and had the benefit of a presentation from Florida Power Corporation. Please submit a summary of your QA plans for Crystal River Unit 3, including an expanded de-scription of the duties and qualifications of the person or persons performing what you refer to as guality Surveillance functions.
E.
Dynamic Analysis of Class I Structures, Equipment,and Piping We noted in our safety evaluation (page 87) tLe need for such analyses, and Florida Power Corporation agreed to provide them (Amendment 2).
Please submit complete and detailed reports covering the dynamic analyses of Class I structures, equipment, and piping.
. 1 F.
Cadweld Splices Provide the testing frequency for testing Cadweld splices, and the change in frequency that may be dictated by a below-standard test result.
-G.
Containment Redesign We discussed in our meeting your plans to change the design of the con-tainment prestress tendons. Provide a description of the design changes, and supporting evidence that justifies the adequacy of the new design.
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