ML20134G433
| ML20134G433 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 08/20/1985 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20134G436 | List: |
| References | |
| NUDOCS 8508260224 | |
| Download: ML20134G433 (3) | |
Text
{{#Wiki_filter:. REACTIVITY CONTROL SYSTEMS 3/4.1.3 MOVABLE CONTROL ASSEMBLIES GROUP HEIGHT LIMITING CONDITION FOR OPERATION 3.1.3.1 All full-length shutdown and control rods shall be OPERABLE and positioned within i 12 steps (indicated position) of their group step counter demand position. APPLICABILITY: MODES 1* and 2*. ACTION: a. With one or more full-length rods inoperable due to being immovable as a result of excessive friction or mechanical interference or known to be untrippable, determine that the SHUTDOWN MARGIN require-ment of Specification 3.1.1.1 is satisfied within 1 hour and be in HOT STANDBY within 6 hours. b. With more than one full-length rod inoperable or misaligned from the group step counter demand position by more than i 12 steps (indicated position), be in HOT STANDBY within 6 hours. c. With one full-length rod trippable but inoperable due to causes other than addressed by ACTION a., above, or misaligned from its group step counter demand height by more than i 12 steps (indicated position), POWER OPERATION may continue provided that within 1 hour: 1. The rod is restored to OPERABLE status within the above alignment requirements, or 2. The rod is declared inoperable and the remainder of the rods in the group with the inoperable rod are aligned to within i 12 steps of the inoperable rod while maintaining the rod sequence and insertion limits of Figure 3.1-1. The THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.6 during subsequent operation, or 3. The rod is declared inoperable and the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied. POWER OPERATION may then continue provided that: a) A reevaluation of each accident analysis of Table 3.1-1 is performed within 5 days; this reevaluation shall confirm that the previously analyzed results of these accidents remain valid for the duration of operation under these conditions; b) The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is determined at least once per 12 hours; "See Special Test Exceptions Specifications 3.10.2 and 3.10.3. 8508260224 h h kB3 DR ADOCK p PDR CALLAWAY - UNIT 1 3/4 1-14 AUG 2 01985
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REACTOR COOLANT SYSTEM OVERPRESSURE PROTECTION SYSTEMS LIMITING CCNDITION FOR OPERATION 3.4.9.3 At least one of the following Overpressure Protection Systems shall be OPERABLE: a. Two residual heat removal (RHR) suction relief valves each with a Setpoint of 450 psig i 3%, or b. Two power operated relief valves (PORVs) with Setpoints which do not exceed the limit established in Figure 3.4-4, or c. The Reactor Coolant System (RCS) depressurized with an RCS vent of greater than or equal to 2 square inches. APPLICABILITY: MODE 3 when the temperature of any RCS cold leg is less than or equal to 368 F, MODES 4 and 5, and MODE 6 with the reactor vessel head on. ACTION: With less than two PORVs or two RHR suction relief valves operable, a. either restore two PORVs or two RHR suction relief valves to OPERABLE status within 7 days or depressurize and vent the RCS through at least a 2 square inch vent within the next 8 hours. b. With both PORVs and both RHR suction relief valves inoperable, depressurize and vent the RCS through at least a 2 square inch vent within 8 hours. In the event the PORVs, or the RHR suction relief valves, or the c. RCS vent (s) are used to mitigate an RCS pressure transient, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 30 days. The report shall describe the circumstances initiating the transient, the effect of the PORVs, or the RHR suction relief valves, or RCS vent (s) on the transient, and any corrective action necessary to prevent recurrence. 4 d. The provisions of Specification 3.0.4 are not applicable. i ) CALLAWAY - UNIT 1 3/4 4-34 m20 W =-}}