ML19260B986
| ML19260B986 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 11/27/1979 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19260B983 | List: |
| References | |
| NUDOCS 7912180077 | |
| Download: ML19260B986 (4) | |
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SUPPLEMENTAL ATTACHMENT TO LICENSE AMENDMENT NO. 52 FACILITY OPERATING LICENSE NO. DPR-49 DOCKET NO. 50-331 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove
- Replace, vi vi 3.6-9 3.6-9 3.6-10a 3.6-10a O
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l6J}<f 109 7 91218 0 C))
DAEC-1 Table Number Page 4.2-D '
Minimum Test and Calibration Frequency for Radiation 3.2-29 Monitoring Systems 4.2-E Minimum Test and Calibration Frequency for Drywell 3.2-30 Leak Detection 4.2-F Minimum Test and Calibration Frequency for Surveillt.nce 3.2-31 Instrumentation 4.2-G Minimum Test and Calibration Frequency for Recircula-3.2-34 tion Pump Trip 3.6-1 Number of Specimens by Source 3.6-33 4.6-3 Snubbers Accessible During Normal Operation 3.6-41 4.6-4 Snubbers Inaccessible During Normal Operation 3.6-43 4.6-5 Snubbers in High Radiation Area During Shutdown and/or 3.6-44 Especially Difficult to Remove 3.7-1 Containment Penetrations Subject to Type "B" Test 3.7-20 Requirements 3.7-2 Containment Isolation Valves Subject to Type "C" Test 3.7-22 Requiremer,ts 3.7-3 Primary Containment Power Operated Isolation Valves 3.7-25 3.12-1 Significant Input Parameters to the Duane Arnold 3.12-9 Loss-of-Coolant Accident Analysis 3.12-2 MCPR Limits 3.12-9a 3.13-1 Fire Detection Instruments 3.13-11 3.13-2 Required Fire Hose Stations 3.13-12 6.2-1 Minimum Shift Crew Personnel and License Requirements 6.2-3 6.9-1 Protection Factors for Respirators 6.9-8 6.11-1 Reporting Summary - Routine Reports 6.11-12 6.11-2 Reporting Summary - Non-routine Reports 6.11-14 O
Amendment No. 52 vi 16 W 110
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 4.
Starting with the next refueling out-age (scheduled for 1980) the inspections required in Table 4.6-1 under Items 1.7, 4.1 and 4.4 are augmented with respect to the three pressure boundary welds identified as weld Nos. 2, 6 and 7 in Figure 4.6-1 on the eight recircu-lating system inlet safe-ends. Each of the three welds on four of the safe-ends shall be ultrasonically examined during the next refueling outage. The three welds on the other four safe-ends shall be ultrasonically examined during the subsequent refuel-ing outage. This cycle of inspections shall continue in the same sequence in subsequea' refueling periods.
Amendment No. 52 3.6-9 g\\
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INTENTIONALLY LEFT BLANK Amendnent No. 52 3.5-10a
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