ML19338C956
| ML19338C956 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 12/14/1976 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19338C953 | List: |
| References | |
| NUDOCS 8009100931 | |
| Download: ML19338C956 (3) | |
Text
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ATTACHMENT TO-LICENSE AMENDMENT NO. 19 1
FACILITY OPERATING LICENSE NO.'DPR-2 DOCKET N0. 50-10 1
Replace the existing pages 48 and 49 of the Technical Specifications with the attached revised pages. Changed areas on revised pages are i
shown by a marginal line.
3 1
d 1
1 1
J 8009100.pgg i
9 t.I 1,1hlTIt!G COilDITION FOR Ol'ERATION 4.3 SURVEILI.ANCE REQUIREMENT h.
The control rod dIrectlona1 control valves for inoperable control rods shall be disarmed electrically and the control rods shall be in such positions that Specification 3.3.A.1 is met except as specified in 3.3.2.d.
c.
Control rod drives which are fully inserted and electrically disarmed shall not be considered inoperable, d.
Control rods with scram times greater than those permitted by Specification 3.3.C are inoperable, but if they can be moved with control rod drive pressure they need not be disarmed electrically if Specification 3.3.A.1 is ret for each position of these rods.
c.
During reactor power operation the number of inoperable control rods shall not exceed four.
H.
Control Rods B.
Contr-+1 Rods 1.
Each control rod shall be coupled to its 1.
The coupling integrity shall be drive or completely inserted and the con-verified for each control rod trol rod directional or control valves following a refuel outage or If disarmed electrically. This requirement a control rod is uncoupled from does not apply in the refuel condition its drive (for maintenance) by:
t.' hen the reactor is vented, a.
Performing a control rod pull test.
The control rod pull test shall consist of withdrawing the control rod one notch and then pulling the control rod to the fully inserted position. The control rod Amendment flo. 19 48
- 1. t 1,I rll T l!D : COND LTLON. Folt Oi'EIMTI.ON 4.3 SUltVEILI.ANCE ItEQUlitEMENT 2.
The control rod drive housing support shall be considered coupled if the system shall be in place during reactor control rod driv'e position indicator power operation and when the reactor located in the control room returns coolant system in pressurized above to the fully inserted position. The atuonpheric pressure wit h fuel in the force used to conduct the pull. test shall reactor vessel, unicas all control, rods be-less than or' equal to 250 pounds are fully inserted and Specification to prevent control rod drive damage.
3.3.A.1 is met.
b.
Observing discernible response of 3.
Control rod patterns shall be established the nuclear instrumentation when the so that the maximum reactivity that rod is withdrawn. For rods withdrawn could be added by dropout of any incre-carly in startup when response is not ment of any one control blade would not discernibic, subsequent-exercising of make the core more than 0.015 delta k these rods after the reactor is supercritical'.
critical shall be performed to verify coupling by inattumentation response.
a.
Whenever the reactor is in the startup/ hot standby or run mode 2.
The control rod drive ho'using support below 10% rated thermal power, a system shall be inspected after reassembly second independent operator or and the results of the inspection recorded.
engineer shall verify that the operator at the reactor console is 3.
Prior to control rod withdrawal for following the control rod program.
startup, the control red withdrawal sequence shall be verified.
4.
Control rods shall not be withdrawn for startup or refueling unless at least two 4.
Prior to control rod withdrawal for source range channels have an observed startup or during refueling verify that count rate equal to or greater than 100 at least two source range channels have counts per minute, except as specified an observed count rate of at least 100 in Section 3.10.B.
counts per minute.
C.
Sc ram Insertion Times C.
Scram Insertion Times l.
The maximum scram insertion time, based 1.
After each refueling outage and' prior to on the de-energization of the scram power operation, and at intervals of not pilot valve solenoids as time zero, of more than six months, all control rods shall all operable control rods in the reactor be subject to scram-time tc.sts from the fully power operation shall be no greater withdrawn position. The scram times shall be than:
measured without reliance on the feedwater pumps.
s 49' Amendment No. 19
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