ML062690054
| ML062690054 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 09/21/2006 |
| From: | NRC/NRR/ADRO/DORL/LPLI-1 |
| To: | Spina J Calvert Cliffs |
| References | |
| Download: ML062690054 (23) | |
Text
rules, regulations, and orders of the Commission, now or hereafter applicable; and is subject to the additional conditions specified and incorporated below:
(1) Maximum Power Level The licensee is authorized to operate the facility at steady-state reactor core power levels not in excess of 2700 megawatts-thermal in accordance with the conditions specified herein.
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 279, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications.
(a) For Surveillance Requirements (SRs) that are new, in Amendment 227 to Facility Operating License No. DPR-53, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 227. For SRs that existed prior to Amendment 227, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the Surveillance was last performed prior to implementation of Amendment 227.
(3) Additional Conditions The Additional Conditions contained in Appendix C as revised through Amendment No. 267 are hereby incorporated into this license. Calvert Cliffs Nuclear Power Plant, Inc. shall operate the facility in accordance with the Additional Conditions.
(4) Secondary Water Chemistry Monitoring Pro-gram The Calvert Cliffs Nuclear Power Plant, Inc.,' shall implement a secondary water chemistry monitoring program to inhibit steam generator tube degradation. This program shall include:
- a. Identification of a sampling schedule for the critical parameters a*lpoi"n'*+- or, these parami "ters;
- b. Identification of the procedures Used to quantify parameters that are critical to control points; Amendment No. 279
C. This license is deemed to contain and is subject to the conditions set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act, and the rules, regulations, and orders of the Commission, now and hereafter applicable; and is subject to the additional conditions specified and incorporated below:
(1) Maximum Power Level The licensee is authorized to operate the facility at reactor steady-state core power levels not in excess of 2700 megawatts-thermal in accordance with the conditions specified herein.
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 256 are hereby incorporated into this license.
The licensee shall operate the facility in accordnace with the Technical Specifications.
(a) For Surveillance Requirements (SRs) that are new, in Amendment 201 to Facility Operating License No. DPR-69, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 201. For SRs that existed prior to Amendment 201, including SRs with modified acceptance criteri and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the Surveillance was last performed prior to implementation of Amendment 201.
(3) Less Than Four Pump Operation The Licensee shall not operate the reactor at power levels in excess of five (5) percent of rated thermal power with less than four (4) reactor coolant pumps in operation. This condition shall remain in effect until the licensee has submitted safety analyses for less than four pump operation, and approval for such operation has been granted by the Commission by amendment of this license.
(4) Environmental Monitoring Program If harmful effects or evidence of irreversible damage are detected by the biological mon.toring program, hydrological monitnring program, and the radiological monitoring program specified in the Appendix B Technical Specifications, the licensee will provide to the staff a detailed analysis of the problem and a program of remedial action to be taken to eliminate or significantly reduce the detrimental effects or damage.
Amendment No. 256
Definitions 1.1 1.1 Definitions include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.
CHANNEL FUNCTIONAL TEST A CHANNEL FUNCTIONAL TEST shall be:
Analog Channels - the injection of a simulated signal into the channel as close to the primary sensor as practicable to verify OPERABILITY, including alarm and/or trip functions.
Bistable Channels - the injection of a simulated signal into the channel sensor to verify OPERABILITY including alarm and/or trip functions.
I CORE OPERATING LIMITS The COLR is the unit specific document that REPORT (COLR) provides cycle specific parameter limits for the current reload cycle. These cycle specific parameter limits shall be determined for each reload cycle in accordance with Specification 5.6.5. Plant operation within these limits is addressed in individual Specifications.
DOSE EQUIVALENT 1-131 DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microcuries/gram) that alone would produce the same thyroid dose as the quantity and isotopic mixture of 1-131, 1-132, 1-133, 1-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, AEC, 1962, "Calculation of Distance Factors for Power and Test Reactor Sites."
E shall be the average I 11LU in ....
r"-- to E -AVERAGE DISINTEGRATION ENERGY the concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and gammra energies per CALVERT CLIFFS - UNIT 1 1.1-2 Amendment No. 279 CALVERT CLIFFS - UNIT 2 Amendment No. 256
Definitions 1.1 1.1 Definitions disintegration (in MeV) for isotopes, other than iodines, with half lives > 15 minutes, making up at least 95% of the total non-iodine activity in the coolant.
ENGINEERED SAFETY FEATURE The ESF RESPONSE TIME shall be that time interval (ESF) RESPONSE TIME from when the monitored parameter exceeds its ESF actuation setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays, where applicable. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components and methodology for verification have been previously reviewed and approved by the NRC.
La The maximum allowable containment leakage rate, La, shall be 0.20% of containment air weight per day at the calculated peak containment pressure (P,).
LEAKAGE LEAKAGE shall be:
- a. Identified LEAKAGE
- 1. LEAKAGE, such as that from pump seals or valve packing (except reactor coolant pump (RCP) seal leakoff), that is captured and conducted to collection systems or a sump or collecting tank;
- 2. LEAKAGE into the containment atmosphere from sources that are both specifically located and known either not to CALVERT CLIFFS - UNIT I 1.1-3 Amendment No. 279 CALVERT CLIFFS - UNIT 2 Amendment No. 256
Definitions 1.1 1.1 Definitions interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE; or
- 3. Reactor Coolant System (RCS) LEAKAGE through a steam generator to the Secondary System (primary to secondary LEAKAGE).
- b. Unidentified LEAKAGE All LEAKAGE (except RCP seal leakoff) that is not identified LEAKAGE;
- c. Pressure Boundary LEAKAGE LEAKAGE (except primary to secondary LEAKAGE) through a nonisolable fault in an RCS component body, pipe wall, or vessel wall.
MODE A MODE shall correspond to any one inclusive combination of core reactivity condition, power level, average reactor coolant temperature, and reactor vessel head closure bolts specified in Table 1.1-1 with fuel in the reactor vessel.
OPERABLE-OPERABILITY A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controis, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that arý required for the system, subsystem, train, component, or device to perform its specified safety function(s) are also capable of performing their related sunport functinn(c)
CALVERT CLIFFS - UNIT 1 1.1-4 Amendment No. 279 CALVERT CLIFFS - UNIT 2 Amendment No. 256
Definitions 1.1 1.1 Definitions PHYSICS TESTS PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation.
These tests are:
- a. Described in Chapter 13, Initial Tests and Operation of the Updated Final Safety Analysis Report;
- b. Authorized under the provisions of 10 CFR 50.59; or
- c. Otherwise approved by the Nuclear Regulatory Commission.
RATED THERMAL POWER (RTP) RTP shall be a total reactor core heat transfer rate to the reactor coolant of 2700 MWt.
REACTOR PROTECTIVE SYSTEM The RPS RESPONSE TIME shall be that time interval (RPS) RESPONSE TIME from when the monitored parameter exceeds its RPS trip setpoint at the channel sensor until electrical power to the CEAs drive mechanism is interrupted. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components and methodology for verification have been previously reviewed and approved by the NRC.
SHUTDOWN MARGIN (SDM) SDM shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming all full length control element assemblies (CEAs) (shutdown and regulating) are fully insertedU except 1o1 tIhfI LLM O highest reactivity worth, which is assumed to be fully withdrawn. However, with all CEAs verified fully inserted by two independent means, it is not CALVERT CLIFFS - UNIT 1 1.1-5 Amendment No. 279 CALVERT CLIFFS - UNIT 2 Amendment No. 256
Definitions 1.1 1.1 Definitions necessary to account for a stuck CEA in the SDM calculation. With any CEAs not capable of being fully inserted, the reactivity worth of these CEAs must be accounted for in the determination of SDM.
STAGGERED TEST BASIS A STAGGERED TEST BASIS shall consist of the testing of one of the systems, subsystems, channels, or other designated components during the interval specified by the Surveillance Frequency, so that all systems, subsystems, channels, or other designated components are tested during n Surveillance Frequency intervals, where n is the total number of systems, subsystems, channels, or other designated components in the associated function.
THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
CALVERT CLIFFS - UNIT I 1.1-6 Amendment No. 279 CALVERT CLIFFS - UNIT 2 Amendment No. 256
CRS 3.3.7 3.3 INSTRUMENTATION 3.3.7 Containment Radiation Signal (CRS)
LCO 3.3.7 Four CRS containment radiation monitor sensor modules, associated measurement channels, one CRS Actuation Logic channel, and one Manual Actuation channel shall be OPERABLE.
APPLICABILITY: During movement of irradiated fuel assemblies within containment with containment purge valves open.
I ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One radiation monitor A.1 Place the affected 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> sensor module or sensor module in associated trip.
measurement channel inoperable. OR A.2 Suspend movement of Immediately irradiated fuel assemblies within containment.
CALVERT CLIFFS - UNIT 1 3.3.7-1 Amendment No. 279 CALVERT CLIFFS - UNIT 2 Amendment No. 256
AC Sources-Shutdown 3.8.2 ACTIONS
NOTES ---------------------------
- 1. LCO 3.0.3 is not applicable.
- 2. Performance of Required Actions shall not preclude completion of actions to establish a safe conservative position.
CONDITION j REQUIRED ACTION I COMPLETION TIME A. One required offsite - ----------- NOTE--------
circuit inoperable. Enter applicable Conditions and Required Actions of LCO 3.8.10, with one required train de-energized as a result of Condition A.
A.1 Declare affected Immediately required feature(s) with no offsite power available inoperable.
OR A.2.1 Suspend movement of irradiated fuel Immedi ately I assemblies.
AND A.2.2 Suspend operations Immediately I involving positive reactivity additions that could result in loss of required SDM or boron concentration.
AND CALVERT CLIFFS- UNIT 1 3.8.2-2 Amendment No. 279 CALVERT CLIFFS - UNIT 2 Amendment No. 256
AC Sources-Shutdown 3.8.2 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME A. (Continued) A.2.3 Initiate action to Immediately I restore required offsite power circuit to OPERABLE status.
B. One required DG inoperable. B.1 Suspend movement of Immediately irradiated fuel assemblies.
AND B.2 Suspend operations Immediately I involving positive reactivity additions that could result in loss of required SDM or boron.
concentration.
AND B.3 Initiate action to Immediately restore required DG to OPERABLE status.
CALVERT CLIFFS - UNIT I 3.8.2-3 Amendment No. 279 CALVERT CLIFFS - UNIT 2 Amendment No. 256
AC Sources-Shutdown 3.8.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.2.1 --------------------NOTE--------------
The following Surveillance Requirements (SRs) are not required to be performed:
SR 3.8.1.11, SR 3.8.1.12, and SR 3.8.1.14.
For the LCO 3.8.2.a and LCO 3.8.2.b AC In accordance sources required to be OPERABLE, the SRs of with applicable Specification 3.8.1, "AC Sources-Operating," SRs except SR 3.8.1.4, SR 3.8.1.8, SR 3.8.1.10, SR 3.8.1.13, 3.8.1.15, and SR 3.8.1.16, are applicable.
SR 3.8.2.2 For the LCO 3.8.2.c and LCO 3.8.2.d AC In accordance sources required to be OPERABLE, the SRs with applicable required by SR 3.8.1.16, are applicable. SRs CALVERT CLIFFS - UNIT 1 3.8.2-4 Amendment No. 279 CALVERT CLIFFS - UNIT 2 Amendment No. 256
DC Sources-Shutdown 3.8.5 3.8 ELECTRICAL POWER SYSTEMS 3.8.5 DC Sources-Shutdown LCO 3.8.5 The required channels of DC electrical sources shall be OPERABLE to support the DC electrical power distribution subsystem(s) required by LCO 3.8.10, "Distribution Systems Shutdown."
APPLICABILITY: MODES 5 and 6, During movement of irradiated fuel assemblies.
ACTIONS
NOTES ---------------------------
- 1. LCO 3.0.3 is not applicable.
- 2. Performance of Required Actions shall not preclude completion of actions to establish a safe conservative position.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Declare affected Immediately DC channels required feature(s) inoperable. inoperable.
OR A.2.1 Suspend movement of Immediately irradiated fuel assemblies.
AND CALVERT CLIFFS - UNIT 1 3.8.5-1 Amendment No. 279 CALVERT CLIFFS - UNIT 2 Amendment No. 256
DC Sources-Shutdown 3.8.5 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.2 Suspend operations Immediately involving positive reactivity additions that could result in loss of required SDM or boron concentration.
AND A.2.3 Initiate action to Immediately restore required DC electrical power subsystems to OPERABLE status.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.5.1 ------------------ NOTE--------------
The following Surveillance Requirements are not required to be performed: SR 3.8.4.6, SR 3.8.4.7, and SR 3.8.4.8.
For DC sources required to be OPERABLE, the In accordance following Surveillance Requirements are with applicable applicable: Surveillance Requirements SR 3.8.4.1 SR 3.8.4.4 SR 3.8.4.7 SR 3.8.4.2 SR 3.8.4.5 SR 3.8.4.8 SR 3.8.4.3 SR 3.8.4.6 CALVERT CLIFFS - UNIT I 3.8.5-2 Amendment No. 279 CALVERT CLIFFS - UNIT 2 Amendment No. 256
Inverters-Shutdown 3.8.8 3.8 ELECTRICAL POWER SYSTEMS 3.8.8 Inverters-Shutdown LCO 3.8.8 Inverter(s) shall be OPERABLE to support the onsite Class 1E AC vital bus electrical power distribution subsystem(s) required by LCO 3.8.10, "Distribution Systems-Shutdown."
APPLICABILITY: MODES 5 and 6, During movement of irradiated fuel assemblies.
ACTIONS
NOTE-------------------------------
LCO 3.0.3 is not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Declare affected Immediately inverters inoperable. required feature(s) i noperabl e.
OR A.2.1 Suspend movement of Immediately irradiated fuel assemblies.
AND CALVERT CLIFFS - UNIT 1 3.8.8-1 Amendment No. 279 CALVERT CLIFFS - UNIT 2 Amendment No. 256
Inverters-Shutdown 3.8.8 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.2 Suspend operations Immediately involving positive reactivity additions that could result in loss of required SDM or boron concentration.
AND A.2.3 Initiate action .to Immediately restore required inverters to OPERABLE status.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.8.1 Verify correct inverter voltage and 7 days alignment to required AC vital buses.
CALVERT CLIFFS - UNIT I 3.8.8-2 Amendment No. 279 CALVERT CLIFFS - UNIT 2 Amendment No. 256
Distribution Systems-Shutdown 3.8.10 3.8 ELECTRICAL POWER SYSTEMS 3.8.10 Distribution Systems-Shutdown LCO 3.8.10 The necessary portion of AC, DC, and AC vital bus electrical power distribution subsystems shall be OPERABLE to support equipment required to be OPERABLE.
APPLICABILITY: MODES 5 and 6, During movement of irradiated fuel assemblies.
ACTIONS
NOTES ---------------------------
- 1. LCO 3.0.3 is not applicable.
- 2. Performance of Required Actions shall not preclude completion of actions to establish a safe conservative position.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Declare associated Immediately AC, DC, or AC vital supported required bus electrical power feature(s) distribution inoperable.
subsystems
,inoperable. OR A.2.1 Suspend movement of Immediately irradiated fuel assemblies.
AND CALVERT CLIFFS - UNIT 1 3.8.10-1 Amendment No. 279 CALVERT CLIFFS - UNIT 2 Amendment No. 256
Distribution Systems-Shutdown 3.8.10 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.2 Suspend operations Immediately involving positive reactivity additions that could result in loss of required SDM or boron concentration.
AND A.2.3 Initiate actions to Immediately I restore required AC, DC, and AC vital bus electrical power distribution subsystems to OPERABLE status.
AND A.2.4 Declare associated Immediately required shutdown cooling subsystem(s) inoperable and not in operation.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.10.1 Verify correct breaker alignments and 7 days voltage to required AC, DC, and AC vital bus electrical power distribution subsystems.
CALVERT CLIFFS - UNIT I 3.8.10-2 Amendment No. 279 CALVERT CLIFFS - UNIT 2 Amendment No. 256
Boron Concentration 3.9.1 3.9 REFUELING OPERATIONS 3.9.1 Boron Concentration LCO 3.9.1 Boron concentrations of the Reactor Coolant System and the refueling pool shall be maintained within the limit specified in the COLR.
APPLICABILITY: MODE 6.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Boron concentration not within limit. A.1 Suspend positive Immediately reactivity additions.
AND A.2 Initiate action to Immediately I restore boron concentration to within limit.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.1.1 Verify boron concentration is within the 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> limit specified in the COLR.
CALVERT CLIFFS - UNIT 1 3.9.1-1 Amendment No. 279 CALVERT CLIFFS -UNIT 2 Amendment No. 256
Nuclear Instrumentation 3.9.2 3.9 REFUELING OPERATIONS 3.9.2 Nuclear Instrumentation LCO 3.9.2 Two source range monitors (SRMs) shall be OPERABLE.
APPLICABILITY: MODE 6.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required SRM A.1 Suspend positive Immediately inoperable, reactivity additions.
AND A.2 Suspend operations Immediately that would cause introduction of coolant into the RCS with boron concentration less than required to meet the boron concentration of LCO 3.9.1.
two required SRMs B.1 Initiate action to Immediately inoperable. restore one SRM to OPERABLE status.
AND B.2 Perform SR 3.9.1.1. Once per 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> CALVERT CLIFFS - UNIT I 3.9.2-1 Amendment No. 279 CALVERT CLIFFS - UNIT 2 Amendment No. 256
Containment Penetrations 3.9.3 3.9 REFUELING OPERATIONS 3.9.3 Containment Penetrations LCO 3.9.3 The containment penetrations shall be in the following status:
- a. 1. The equipment hatch closed and held in place by a minimum of four bolts, or
- 2. The containment outage door is capable of being closed under administrative control;
- b. One door in the emergency air lock is closed;
NOTE ---------------------
The emergency air lock temporary closure device can be used in place of an emergency air lock door.
- c. The personnel air lock shall be either:
- 1. closed by one personnel air lock door, or
- 2. capable of being closed by 4n OPERABLE personnel air lock door under administrative control.
- d. 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 Valve Isolation System.
APPLICABILITY: During movement of irradiated fuel assemblies within I containment.
CALVERT CLIFFS - UNIT 1 3.9.31-1 Amendment No. 279 CALVERT CLIFFS - UNIT 2 Amendment No. 256
Containment Penetrations 3.9.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more containment A.1 Suspend movement of Immediately penetrations not in irradiated fuel required status, assemblies within containment.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.3.1 Verify each required containment penetration 7 days is in the required status.
SR 3.9.3.2 Verify each required containment purge and 24 months exhaust valve actuates to the isolation position on an actual or simulated actuation signal.
CALVERT CLIFFS - UNIT 1 3.9.3-2 Amendment No. 279 CALVERT CLIFFS - UNIT 2 Amendment No. 256
SDC and Coolant Circulation-High Water Level 3.9.4 3.9 REFUELING OPERATIONS 3.9.4 Shutdown Cooling (SDC) and Coolant Circulation-High Water Level LCO 3.9.4 One SDC loop shall be OPERABLE and in operation.
:-----------NOTES -------------
- 1. The required SDC loop may be not in 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 of coolant into the Reactor Coolant System with boron concentration less than that required to meet the minimum boron concentration of LCO 3.9.1.
- 2. The shutdown cooling pumps may be removed from operation during the time required for local leak rate testing of containment penetration number 41 pursuant to the requirements of SR 3.6.1.1 or to permit maintenance on valves located in the common SDC suction line, provided:
- a. no operations are permitted that would cause introduction of coolant into Reactor Coolant System with boron concentration less than that required to meet the minimum boron concentration of LCO 3.9.1,
- b. Movement of fuel assemblies within Containment is I suspended, and
- c. all containment penetrations are in the status described in LCO 3.9.3.
APPLICABILITY: MODE 6 with the water level Ž 23 ft above the top of the irradiated fuel assemblies seated in the reactor vessel.
CALVERT CLIFFS - UNIT I 3.9.4-1 Amendment No. 279 CALVERT CLIFFS - UNIT 2 Amendment No. 256
Refueling Pool Water Level 3.9.6 3.9 REFUELING OPERATIONS 3.9.6 Refueling Pool Water Level LCO 3.9.6 Refueling pool water level shall be maintained Ž 23 ft above the top of the irradiated fuel assemblies seated in the reactor vessel.
APPLICABILITY: During movement of irradiated fuel assemblies within I containment.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Refueling pool water level not within A.1 Suspend movement of Immediately limit, irradiated fuel assemblies within containment.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.6.1 Verify refueling pool water level is Ž 23 ft 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> above the top of the irradiated fuel assemblies seated in the reactor vessel.
CALVERT CLIFFS - UNIT I 3.9.6-1 Amendment No. 279 CALVERT CLIFFS - UNIT 2 Amendment No. 256