ML20237G434
| ML20237G434 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 08/10/1987 |
| From: | FLORIDA POWER CORP. |
| To: | |
| Shared Package | |
| ML20237G433 | List: |
| References | |
| NUDOCS 8708140067 | |
| Download: ML20237G434 (2) | |
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ATTACHHENT 1 P ga 1 of'2 PROPOSED REGULATORY DESIGN FEATuns'n RFfACATION CONTROLS
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SECTION 5.1 SITE i
5.1.1 Exclusion Area FSAR 10 CFR 50.59 Figure:5.1-1, Exclusion Area FSAR 10.CFR 50.59 5.1.2 Low Population Zone FSAP./E Plan 10 CFR 50.59/-
10 CFR 50.54 Figure 5.1-2, Low Population Zone FSAR/E Plan 10 CFR 50.59/
10 CFR 50.54 5.1.3 Maps Defining Unrestricted Areas and Site FSAR 10 CFR 50.59 Boundary for' radioactive gaseous and liquid effluents.
i Figure 5.1-3, Site Boundary for Gaseous and Liquid FSAR 10 CFR 50.59 Effluents 5.2 CONTAINMENT 5.2.1 Configuration FSAR 10 CFR 50.59 5.2.2 Design pressure and Temperature FSAR 10 CFR 50.59 5.3 REACTOR COEg 5.3.1 Fuel Assenslies Technical 10 CFR 50'.90' Specifications 5.3.2 Control Rods FSAR/ Cycle Rpt.
5.4 REACTOR COOLANT SYSTEM i
5.4.1 Design pressure and Temperature FSAR 10 CFR 50.59 S
5.4.2 Volume FSAR 10 CFR 50.59
-5.5 METEOROLOGICAL TOWER LOCATION 5.6 FUEL STORAGE 5.6.1 Criticality Technical 10 CFR 50.90 Specifications 5.6.2 Drainage FSAR 10 CFR 50.59 5.6 3 Capacity
't FSAR 10 CFR 50.59 1
i 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIl l
l 5.7.1 Limits FSAR 10 CFR-50.59 5.7-1 Cyclic Transient Limit
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ATTACHMENT 1 Page 2 of 2
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PROPOSED REGULATORY SECTION i
1.1 P. RESPONSIBILITY QA Plan 10 CFR 50.54 (a) 6.2 ORGANIZATION QA Plan 10 CFR 50.54 (a) 6.2.1 Offsite QA Plan 10 CFR 50.54 (a) 6.2.2 Facility QA Plan 10 CFR 50.54 (a)
Figure 6.2.1 Offsite Organization QA Plan 10 CFR 50.54 (a)
Figure 6.2-2 Facility Organization QA Plan 10 CFR 50.54 (a)
Table 6.2-1 Minimum Shift Crew Composition QA Plan 10 CFR 50.54 (a) 6.3 FACILITY STAFF QUALIFICATIONS QA Plar 10 CFR 55/50.54 (a) 6.4 TRAINING FSAR/ Training /
10 CFR 55/50.54 (1-1)
Requal. Prog.
6.5 REVIEW AND AMR.II 6.5.1 Plant Review Committee (PRC)
QA Plan 10 CFR 50.54 ('a) 6.5.2 Nuclear General Review Committee (NGRc)
QA Plan 10 CFR 50.54 (a) 6.6 REPORTABLE EVENT ACTION FSAR 10 CFR 50.59 10 CFR 50.71e 10 CFR 50.73, and 6.7 SAFETY LIMIT VIOLATION Technical 10 CFR 50.90 Specifications 6.8 PROCEDURES QA Plan 10 CFR 50.54 (a) 1,9 REPORTING REQUIREMENTS 6.9.1 Routine Reports FSAR 10 CFR 50.59 10 CFR 50.71e 10 CFR 50.73, and 6.9.2 Special Reports Technical 10 CFR 50.90 Specifications 6.10 RECORD RETENTION QA Plan 10 CFR 50.54 (a) j.11 RADIATION PROTECTION PROGRAM FSAR 10 CFR 50.59 6.12 HIGH RADIATION AREA FSAR 10 CFR 50.59 6.13 ENVIRONMENTAL QUALIFICATION FSAR 10 CFR 50.59 6.14 PROCESS CONTROL PROGRAM (PCP)
PSAR 10 CFR 50.59 1,15 0FFSITE DOSE CALCULATION MANUAL (ODCM)
FSAR 10 CFR 50.59 6.16 MAJOR CHANGES TO LIOUID. GASEOUS. AND FSAR 10 CFR 50.59, SOLID RADWASTE TREATMENT SYSTEMS 10 CFR 50.71e, and
" decrease in effectiveness" test
,6.17 POST ACCIDENT SAMPLING AND AUTOMATED FSAR 10CFR50.59 ISOTOPIC MONITORING SYSTEMS
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