ML19308E270
| ML19308E270 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 01/27/1972 |
| From: | Rodgers J FLORIDA POWER CORP. |
| To: | US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8003240818 | |
| Download: ML19308E270 (5) | |
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' DATE mICEIVID NO.s Ada Power CerForation Jam. 27, 1972 Feb. 1, 1972 578 Fetersburg, Fla.
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The Director Division of Reactor Licensing
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Dear Sir:
In re: Florida Power Corporation V-4W' Crystal River Unit 3 Nuclear Generating Plant Docket No 50-302 This letter is to respond to the AEC letter to Florida Power Corporation, dated January 14, 1972, signed by R.C. DeYoung, Assistant Director for Pressurized Water Reactors, Division of Reactor Licensing, requesting additionel information relating to AEC continuing review and evaluation of the Final Safety Analysis Report for Crystal River Unit 3 Nuclear Generating Plant. The specific information requirements were listed in an enclosure to the January 14 letter entitled Request for Addi.tional 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 14 letter.
On receipt of the January 14 letter, Florida Power Corporation proceeded immediately with assessment, planning, scheduling, and performance of work to be accomplished to respond to the specific information require-ments therein.
The schedule for submittal of this information to the AEC, as shown below, reflects a minimum practicable duration of time for work accomplishment, review, and internal approval prior to submittal.
The schedule is specifically dependent upon the very major commitment of our manpower resources for an extended period of time.
The follow-ing is the schedule for response to the AEC letter of January 14, 197.2.
To be Filed on'Approximately April 3, 1972.
1.
A general updating of the FSAR will be made on thi' ute to the fullest extent possible.
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The following portions (questions) of the et..!osurc, Regt.ast, s
for Additional Information will be answered un this dst.?:
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The Director January 27, 1972 2.0 Site and Environment.
2.2, 2.4, 2.5, 2.6, 2.8, 2.9, 2.10, 2.11, 2.12 and 2.13 3.0 Reactor.
3.1 4.0 Reactor Coolant System.
4.2, 4.3, 4.4, 4.5, 4.6, 4.8, 4.10, 4.12, 4.13, 4.14, 4.18, 4.19, 4.20, and 4.25 5.0 Containment 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, 5.20, 5.21, 5.22, 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 Systeam.
8.1, 8.4, 8.5, and 8.6 9.0 Auxiliary and Emergency Systems.
9.1, 9.6, and 9.9 11.0 Radioactive Waste and Radiation Protection.
11.3 and 11.3 14.0 Safety Analysis.
14.1, 14.4 and 14.5 To be Filed on Approximately May 8, 1972.
1.
Further general updating of the FSAR will be made on this date to include information not available on in preparation for the April 3 submittal.
2.
The following portions (questions) of the enclosure, Request for Additional Information will be answered on this date:
2.0 Site and Environment.
2.1,-2.3, and 2.7 578
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The Director January 27, 1972
.3.0 Reactor.
4.7, 4.9, 4.11, 4.15, 4.16, 4.17, 4.21, 4.22, 4.23, 4.24, 4.26, and 4.27 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, 7.11, 7.12, and 7.17 8.0 Electrical Systems.
8.2, 8.3, and 8.7 9.0 Auxiliary and Emergency Systems.
9.2, 9.3, 9.4, 9.5, 9.7, 9.8, 9.10, and 9.11 11.0 Radioactive Waste and Radiation Protection.
11.1, 11.2, 11.4, 11.6, 11.7, 11.8, 11.9, and 11.10 14.0 Safety Analysis.
14.2 and 14.3 To bc Filed on a date after May 8, 1972, to be determined Based on Ongoing Assessment and Analysis.
The following portions (questions) of the enclosure, Request for Additional Information require further assessment and analysis for projection of an accurate schedule for submittal and require possible developmental work for meaningful response and subsequent evaluation by the Company prior to submittal.
Company response dates for the following questions will be supplied to the AEC as soon as possible.
5.0 Containment Systems and Other Special Structures.
5.15, 5.15, 5.17, 5.18, 5.19, and 5.25 7.0 Instrumentation and Control Systems.
7.10
n The Director January 27, 1972 The above is representative of our complete coverage (in terms of schedule) uf the requirements stated in the AEC' letter (with enclosure) dated January 14, 1972.
Please contact us if you desire any discussion or clarification of the above information.
Very truly yours,
$ !f )a l., i t.
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J. T. Rodgers.
Assistant Vice President &
Nuclear Project Manager JTR/iw cc: Mr. Roy B. Snapp l
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