ML19317G705
| ML19317G705 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 04/07/1972 |
| From: | Rodgers J FLORIDA POWER CORP. |
| To: | US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8003270522 | |
| Download: ML19317G705 (3) | |
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Dear Sir:
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In Re: Florida Power Corporation
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50-302 This letter provides an update of the Florida Power Corporation letter to the Atomic Energy Commission dated January 27, 1972 concerning response to the A.E.C. letter of January 14 entitled Request for Additional Information Florida Power Corporation Crystal River Unit 3 Docket No.
50-302.
In addition, the requirement of a general updating of the FSAR was stated in the January 14th letter.
Amendment #17 to the Application for Licenses for Crystal River Unit 3 Nuclear Generating Plant to be filed with the Atomic Energy Commission on April 10,1972 will contain update information for Sections 2, 4, 5, 7, 8, 9, and 10 of the Final Safety Analysis Report. In addition, responses to the following questions included in the A.E.C's Request for Additional In-formation will be provided in Amendment #17.
2.0 Site and Environment 2.2, 2.4, 2.5, 2.6, 2.7, 2.8, 2.9, 2.11, 2.12 and 2.13.
4.0 Reactor Coolant System 4.3, 4.4, 4.5, 4.6, 4.8, 4.9, '. 10, 4.12, 4.13, 4.14, 4.15, 4.18, 4.19, 4.20, 4.25, 4.26 and 4.27.
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The Director April 7,1972 5.0 Contaiament Systems and Other Special Structures 5.1, 5.2, 5.3, 5.4, 5.5, 5.6, 5.7, 5.9, 5.10, 5.11, 5.12, 5.13, 5.14, 5.15, 5.16, 5.17, 5.18, 5.19, 5.20, 5.21, 5.22, 5.25, and 5.27.
7.0 Instrumentation and Control Systems 7.2, 7. 4, 7.5, 7. 8, 7.13, 7.14, 7.15, 7.16, and 7.18.
8.0 Electrical Systems 8.1, 8.2, 8.3, 8.4, 8.5, 8.6, and 8. 7.
9.0 Auxiliary and Emergency Systems 9.1, 9,2, 9.3, 9.6, 9.7, and 9.9.
11.0 Radioactive Waste and Radiation Protection 11.5 14.0 Safety Analysis 14.3, 14.4, and 14.5.
In addition to the responses provided, Supplement #1 will be added to the FSAR which contains a cross-reference of the FSAR with the Request for Additional Information responses.
Amendment #18 to the Application will be filed with the A.E.C. on or about May 8,1972 and will include the remainder of the responses to the Request for Additional Information and general update information as found necessary.
The specific question responses will be:
2.0 Site and Environment 2.1, 2. 3, and 2.10 3.0 Reactor 3.1 i
4.0 Reactor Coolant System 4.1, 4.2, 4. 7, 4.11, 4.16, 4.17, 4.21, 4.22, 4.23, and 4.24.
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I The Director April 7,1972 5.0 Containment Systems and Other Special Structures 5.8, 5.23, 5.24, and 5.26 7.0 Instrumentation and Control Systems 7.1, 7. 3, 7.6, 7. 7, 7.9, 7.10, 7.11, 7.12, and 7.17.
9.0 Auxiliary and Emergency Systems 9. 4, 9.5, 9. 8, 9.10, an d 9.11.
11.0 Radioactive Waste and Radiation Protection 11.1, 11. 2, 11. 3, 11. 4, 11. 6, 11. 7, 11. 8, 11. 9, an d 11.10.
14.0 Sale *y Analysis 14.1 and 14.2.
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The above is representative of our complete coverage of the requirements stated in the A.E.C. letter (with enclosure) dated January 14, 1972.
Please contact us if you desire any discussion or clarification of the above information.
Very truly yours,
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J. T. Rodgers Assistant Vice President &
Nuclear Project Manager JTR/kdd cc: Roy B. Snapp i.[)d1E$
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