ML19319D723
| ML19319D723 | |
| Person / Time | |
|---|---|
| Site: | Crystal River, 05000303  |
| Issue date: | 08/10/1967 |
| From: | FLORIDA POWER CORP. |
| To: | |
| Shared Package | |
| ML19319D724 | List: |
| References | |
| NUDOCS 8003240747 | |
| Download: ML19319D723 (4) | |
Text
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Docket No. 302 Supplement No. k July 15, 1969 SUPPLEMENT h RESPONSE TO PART II 0F ATTACHMENT TO LETTER b
FROM PETER A. MORRIS, DIRECTOR, DIVISION OF REACTOR LICENSING, FLORIDA POWER CORPORATION TO MR. J. T. RODGERS, DATED MARCH 13,19o9 "A.
Hurricane Effects From our meeting, we are aware of your intentions to modify your design. Provide the calculations on storm tide and wave run-up, and minimum water levels, and the plant design features associated with these calculations."
Appendix 2C, " Flood Studies and Hurricane Effects," has been revised to show the modified plcat design and associated features. It is Florida Power Corporation's opinion that this design satisfies the new ESSA criteria,
".B.
Control Rod Drives Cm
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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 desire."
The application is amended to describe the roller nut and lead screw design which Florida Power Corporation has selected for Crystal River Unit 3; applicable PSAR text revisions in Sections 3, 7, 9, and ik are included herewith.
(This control rod system has been previously submitted, refer to Three Mile Island Nuclear Station Units 1 and 2, Dockets 50-289 and 50-320).
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The design changes result in small changes to reactivity M
insertion rates and core reactivity balances which are not
'O included in this amendment since they are well within the range of-paraceters examined previously in the safety analysis, and do not involve significant safety related considerations.
Thus Section lh presents analysis based on a 25" per minute rod speed and a maximum rod group reactivity addition rate of 5.8 x 10-5 ok/k-sec. Although Sections 3 and 7 show that a higher rod speed and reactivity addition rate are now em-ployed in the design, the safety analysis has been performed over a range of values including the new value showing adequate safety. These details will be presented in the final safety analysis report.
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"C.
Reactor Building Fan Coolers We stated in our safety evaluation (page 22) that we vould 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."
The final design of the Reactor Building Fan Coolers is not available as of this date for Crystal River Plant Unit 3.
"D.
Quality Assurance We discussed quality assurance at our meeting and had the benefit of a presentation from Florida Power Corporation. Please submit a su= mary of your QA plans for Crystal River Unit 3, including an expanded description of the duties and qualifications of the person or persons performing what you refer to as Quality Surveillance functions."
A summary of the Florida Power Corporation's Quality Program is included as Attachment I to this Supplement h.
"E.
Dynamic Analysis of Class I Structures, Equipment, and Piping A
We noted in our safety evaluation (page 87) the 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."
The proposed methods of dynamic analyses of Class I structures, conponents, and systems being used for Crystal River tlnit 3 vill be documented to the DRL Staff as a Gilbert Associates Topical Report.
(Refer to Section 6 of Appendix 5A and
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CD Question 9 12, Supplement No. 1) eq CD "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."
Information relating to the testing frequency for testing Cadweld splices is presented in revised Section 2.h "Cadweld Splices," of Appendix 5D.
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"G.
Containment Redesigg We discussed in our meeting your plans to change the design of the contain=ent prestress tendons. Provide a description of the design changes, and supporting evidence that justifies the adequacy of the new design."
We are submitting the change in the prestress system. This change is from a 901/h-in. wire BBRV system to a 163 7-mm low relaxation wire system supplied by the Prescon Corp. of Corpus Christi, Texas. The new prestress system is currently being developed and tested to demonstrate the adequacy of the new design. The type of tests and information being develcped are included in this submittal in the form of revised text pages in Section 5 and Appendix SB of the PSAR.
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