ML070400172
| ML070400172 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 03/08/2007 |
| From: | NRC/NRR/ADRO/DORL/LPLIV |
| To: | |
| Donohew J N, NRR/DORL/LP4, 415-1307 | |
| Shared Package | |
| ML070400165 | List: |
| References | |
| TAC MD1154 | |
| Download: ML070400172 (14) | |
Text
(4)
LUE, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source of special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5)
UE, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level UE is authorized to operate the facility at reactor core power levels not in excess of 3565 megawatts thermal (100% power) in accordance with the conditions specified herein.
(2)
Technical Specifications and Environmental Protection Plan*
The Technical Specifications contained in Appendix A, as revised through Amendment No. 181 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3)
Environmental Qualification (Section 3.11. SSER #3-M*
Deleted per Amendment No. 169 Amendments 133, 134, &1 35 were effective as of April 30, 2000 however these amendments were implemented on April 1, 2000.
- The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.
Amendment 181
TABLE OF CONTENTS 3.9 REFUELING O PERATIONS.................................................................
3.9-1 3.9.1 Boron Concentration........................................................................
3.9-1 3.9.2 Unborated W ater Source Isolation Valves.......................................
3.9-3 3.9.3 Nuclear Instrumentation...................................................................
3.9-5 3.9.4 Containment Penetrations...............................................................
3.9-7 3.9.5 Residual Heat Removal (RHR) and Coolant Circulation - High W ater Level...................................................
3.9-9 3.9.6 Residual Heat Removal (RHR) and Coolant Circulation - Low W ater Level....................................................
3.9-11 3.9.7 Refueling Pool W ater Level.............................................................
3.9-13 4.0 DESIGN FEATURES...............................................................................
4.0-1 4.1 Site Location....................................................................................
4.0-1 4.2 Reactor Core......... I........................................................................
4.0-1 4.3 Fuel Storage....................................................................................
4.0-1 5.0 ADMINISTRATIVE CONTROLS 5.0-1 5.1 Responsibility...................................................................................
5.0-1 5.2 Organization 5.0-2 5.3 Unit Staff Qualifications...................................................................
5.0-4 5.4 Procedures......................................................................................
5.0-5 5.5 Program s and Manuals............................................
........................ 5.0-6 5.6 Reporting Requirem ents................................................................
5.0-20 5.7 High Radiation Area.........................................................................
5.0-25 CALLAWAY PLANT 4
Amendment 181
BDMS 3.3.9 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.
(continued)
B.2 Perform SR 3.1.1.1.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> AMD_
Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter AND B.3.1 Close and secure 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> unborated water source isolation valves.
B.3.2 Verify unborated water Once per 31 days source isolation valves are dosed and secured.
C. No RCS loop in operation.
C. 1 Close and secure 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> unborated water source isolation valves.
AND C.2 Verify unborated water Once per 31 days source isolation valves are closed and secured.
CALLAWAY PLANT 3.3-72 Amendment 181
Unborated Water Source Isolation Valves 3.9.2 3.9 REFUELING OPERATIONS 3.9.2 Unborated Water Source Isolation Valves LCO 3.9.2 Each valve used to isolate unborated water sources shall be secured in the closed position.
NOTE-------------------------
Unborated water sources may be unisolated under administrative controls for planned boron dilution evolutions.
I I
APPLICABILITY:
MODE 6.
ACTIONS NOTE Separate Condition entry is allowed for each unborated water source isolation valve.
COMPLETION CONDITION REQUIRED ACTION TIME TIME A.
NOTE A.1 Suspend CORE Immediately Required Action A.3 must ALTERATIONS.
be completed whenever Condition A is entered.
AND One or more valves not A.2 Initiate actions to secure Immediately secured in closed position.
valve in closed position.
AND A.3 Perform SR 3.9.1.1.
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> CALLAWAY PLANT 3.9-3 Amendment No. 181
Unborated Water Source Isolation Valves 3.9.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.2.1 Verify each valve that isolates unborated water 31 days sources is secured in the closed position.
CALLAWAY PLANT 3.9-4 Amendment No. 181
Nuclear Instrumentation 3.9.3 3.9 REFUELING OPERATIONS 3.9.3 Nuclear Instrumentation LCO 3.9.3 APPLICABILITY:
Two source range neutron flux monitors shall be OPERABLE.
MODE 6.
ACTIONS COMPLETION CONDITION REQUIRED ACTION TIME TIME A.
One required source range A.1 Suspend CORE Immediately neutron flux monitor ALTERATIONS.
ANM A.2 Suspend operations that Immediately would cause introduction into the RCS, coolant with boron concentration less than required to meet the boron concentration of LCO 3.9.1.
B.
Two required source range B.1 Initiate action to restore Immediately neutron flux monitors one source range inoperable, neutron flux monitor to OPERABLE status.
B.2 Perform SR 3.9.1.1.
Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> CALLAWAY PLANT 3.9-5 Amendment No. 181 I
Nuclear Instrumentation 3.9.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.3.1 Perform CHANNEL CHECK.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.9.3.2 NOTE-----------------
-NOTE Neutron detectors are excluded from CHANNEL CALIBRATION.
Perform CHANNEL CALIBRATION.
18 months CALLAWAY PLANT 3.9-6 Amendment No. 181 I
Containment Penetrations 3.9.4 3.9 REFUELING OPERATIONS 3.9.4 Containment Penetrations LCO 3.9.4 The containment penetrations shall be in the following status:
- a.
The equipment hatch closed and held in place by four bolts, or if open, capable of being closed;
- b.
One door in the emergency air lock and one door in the personnel air lock capable of being closed; and
- c.
Each penetration providing direct access from the containment atmosphere to the outside atmosphere either:
- 1.
closed by a manual or automatic isolation valve, blind flange, or equivalent, or
- 2.
capable of being closed by an OPERABLE Containment Purge Isolation valve.
-- -- -- -- NOTE --- ------ ---
Penetration flow path(s) providing direct access from the containment atmosphere to the outside atmosphere may be unisolated under administrative controls.
APPLICABILITY:
During CORE ALTERATIONS, During movement of irradiated fuel assemblies within containment.
ACTIONS COMPLETION CONDITION REQUIRED ACTION TIME TIME A.
One or more containment A.1 Suspend CORE Immediately penetrations not in required ALTERATIONS.
status.
AND A.2 Suspend movement of Immediately irradiated fuel assemblies within containment.
CALLAWAY PLANT 3.9-7 Amendment No. 181 I
Containment Penetrations 3.9.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.4.1 Verify each required containment penetration is in the 7 days required status.
SR 3.9.4.2 NOTE-Only required for an open equipment hatch.
Verify the capability to install the equipment hatch.
7 days SR 3.9.4.3 Verify each required containment purge isolation 18 months valve actuates to the isolation position on a manual actuation signal.
CALLAWAY PLANT 3.9-8 Amendment No. 181 I
RHR and Coolant Circulation - High Water Level 3.9.5 3.9 REFUELING OPERATIONS 3.9.5 Residual Heat Removal (RHR) and Coolant Circulation - High Water Level LCO 3.9.5 One RHR loop shall be OPERABLE and in operation.
S-NOTE -----.-.--------.-----......-
The required RHR loop may be removed from operation for < 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period, provided no operations are permitted that would cause introduction into the Reactor Coolant System, coolant with boron concentration less than that required to meet the minimum required boron concentration of LCO 3.9.1.
-- --. =-
APPLICABILITY:
MODE 6 with the water level Ž_ 23 ft above the top of reactor vessel flange.
ACTIONS COMPLETION CONDITION REQUIRED ACTION TIME TIME A.
RHR loop requirements not A.1 Suspend operations that Immediately met.
would cause introduction into the RCS, coolant with boron concentration less than required to meet the boron concentration of LCO 3.9.1.
AND A.2 Suspend loading Immediately irradiated fuel assemblies in the core.
AND (continued)
CALLAWAY PLANT 3.9-9 Amendment No. 181 I
RHR and Coolant Circulation - High Water Level 3.9.5 ACTIONS COM PLETION CONDITION REQUIRED ACTION TIME A.
RHR loop requirements not A.3 Initiate action to satisfy Immediately met.
RHR loop requirements.
(continued)
AND A.4 Close all containment 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> penetrations providing direct access from containment atmosphere to outside atmosphere.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.5.1 Verify one RHR loop is in operation and circulating 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> reactor coolant at a flow rate of >- 1000 gpm.
CALLAWAY PLANT 3.9-10 Amendment 181 I
RHR and Coolant Circulation - Low Water Level 3.9.6 3.9 REFUELING OPERATIONS 3.9.6 Residual Heat Removal (RHR) and Coolant Circulation - Low Water Level LCO 3.9.6 APPLICABILITY:
Two RHR loops shallbe OPERABLE, and one RHR loop shall be in operation.
MODE 6 with the water level< 23 ft above the top of reactor vessel flange.
ACTIONS COMPLETION CONDITION REQUIRED ACTION TIME A.
Less than the required A.1 Initiate action to restore Immediately number of RHR loops required RHR loops to OPERABLE.
OPERABLE status.
OR A.2 Initiate action to Immediately establish Ž 23 ft of water above the top of reactor vessel flange.
(continued)
CALLAWAY PLANT 3.9-11 Amendment No. 181 I.
RHR and Coolant Circulation - Low Water Level 3.9.6 ACTIONS (continued)
COMPLETION CONDITION REQUIRED ACTION TIME B.
No RHR loop in operation.
8.1 Suspend operations that Immediately would cause introduction into the RCS, coolant with boron concentration less than required to meet the boron concentration of
AND B.2 Initiate action to restore Immediately one RHR loop to operation.
ANM B.3 Close all containment 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> penetrations providing direct access from containment atmosphere to outside atmosphere.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.6.1 Verify one RHR loop is in operation and circulating 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> reactor coolant at a flow rate of _ 1000 gpm.
SR 3.9.6.2 Verify correct breaker alignment and indicated power 7 days available to the required RHR pump that is not in operation.
CALLAWAY PLANT 3.9-12 Amendment No. 181 I
Refueling Pool Water Level 3.9.7 3.9 REFUELING OPERATIONS 3.9.7 Refueling Pool Water Level LCO 3.9.7 APPLICABILITY:
Refueling pool water level shall be maintained _>_
23 ft above the top of reactor vessel flange.
During movement of irradiated fuel assemblies within containment.
ACTIONS COMPLETION CONDITION REQUIRED ACTION TIME TIME A.
Refueling pool water level A.1 Suspend movement of Immediately not within limit.
irradiated fuel assemblies within containment.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.7.1 Verify refueling pool water level is > 23 ft above the 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> top of reactor vessel flange.
CALLAWAY PLANT 3.9-13 Amendment No. 181 I