ML21272A172
| ML21272A172 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 09/28/2021 |
| From: | Ameren Missouri, Union Electric Co |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML21272A167 | List: |
| References | |
| ULNRC-06636 | |
| Download: ML21272A172 (9) | |
Text
ULNRC06636 Page 1 of 9 Definitions 1.1 1.1 Definitions (continued)
CHANNEL OPERATIONAL TEST (COT)
A COT shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY of all devices in the channel required for channel OPERABILITY. The COT shall include adjustments, as necessary, of the required alarm, interlock, and trip setpoints required for channel OPERABILITY such that the setpoints are within the necessary range and accuracy. The COT may be performed by means of any series of sequential, overlapping, or total channel steps.
CORE ALTERATION CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components, within the reactor vessel with the vessel head removed and fuel in the vessel.
Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.
CORE OPERATING LIMITS REPORT (COLR)
The COLR is the unit specific document that 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 I-131 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcuries per gram) that alone would produce the same dose when inhaled as the combined activities of iodine isotopes I-131, I-132, I-133, I-134, and I-135 actually present.
The determination of DOSE EQUIVALENT I-131 shall be performed using thyroid dose conversion factors from:
- 1. Table 2.1 of EPA Federal Guidance Report No. 11, EPA-520/1-88-020, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion," 1988.
(continued)
CALLAWAY PLANT 1.1-2 Amendment xxx
ULNRC06636 Page 2 of 9 CREVS 3.7.10 CALLAWAY PLANT 3.7-28 Amendment No. xxx l 3.7 PLANT SYSTEMS 3.7.10 Control Room Emergency Ventilation System (CREVS)
LCO 3.7.10 Two CREVS trains shall be OPERABLE.
NOTE ---------------------------------------------
The control room envelope (CRE), control building envelope (CBE) and equipment room envelope (ERE) boundaries may be opened intermittently under administrative control.
APPLICABILITY:
MODES 1, 2, 3, and 4, During movement of irradiated fuel assemblies.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CREVS train inoperable for reasons other than Condition B.
A.1 Restore CREVS train to OPERABLE status.
7 days (continued)
ULNRC06636 Page 3 of 9 CREVS 3.7.10 CALLAWAY PLANT 3.7-29 Amendment No. xxx l ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B. One or more CREVS trains inoperable due to an inoperable CRE, ERE or CBE boundary in MODE 1, 2, 3, or 4.
B.1 Initiate action to implement mitigating actions.
AND B.2 Verify mitigating actions to ensure CRE occupant radiological exposure will not exceed limits and CRE occupants are protected from chemical and smoke hazards.
AND B.3 Restore the CRE, ERE and CBE boundaries to OPERABLE status.
Immediately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 90 days C. Required Action and C.1 Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A or B not met in MODE 1, 2, 3, or 4.
AND C.2 Be in MODE 5.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> (continued)
ULNRC06636 Page 4 of 9 CREVS 3.7.10 CALLAWAY PLANT 3.7-30 Amendment No. xxx l ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and associated Completion Time of Condition A not met during movement of irradiated fuel assemblies.
D.1 Place OPERABLE CREVS train in CRVIS mode.
OR D.2.1 Suspend CORE ALTERATIONS.
AND D.2.2 Suspend movement of irradiated fuel assemblies.
Immediately Immediately Immediately E. Two CREVS trains inoperable during movement of irradiated fuel assemblies.
OR One or more CREVS trains inoperable due to an inoperable CRE, CBE or ERE boundary during movement of irradiated fuel assemblies.
E.1 Suspend CORE ALTERATIONS.
AND E.2 Suspend movement of irradiated fuel assemblies.
Immediately Immediately F.
Two CREVS trains inoperable in MODE 1, 2, 3, or 4 for reasons other than Condition B.
F.1 Enter LCO 3.0.3.
Immediately
ULNRC06636 Page 5 of 9 CREVS 3.7.10 CALLAWAY PLANT 3.7-31 Amendment No. xxx SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.10.1 Operate each CREVS train pressurization filter unit for 15 continuous minutes and each CREVS train filtration filter unit for 15 continuous minutes.
In accordance with the Surveillance Frequency Control Program SR 3.7.10.2 Perform required CREVS filter testing in accordance with the Ventilation Filter Testing Program (VFTP).
In accordance with the VFTP SR 3.7.10.3 Verify each CREVS train actuates on an actual or simulated actuation signal.
In accordance with the Surveillance Frequency Control Program SR 3.7.10.4 Perform required unfiltered air inleakage testing of the CRE, CBE and ERE boundaries in accordance with the Control Room Envelope Habitability Program.
In accordance with the Control Room Envelope Habitability Program
ULNRC06636 Page 6 of 9 Programs and Manuals 5.5 5.5 Programs and Manuals (continued)
CALLAWAY PLANT 5.0-15 Amendment No. xxx l 5.5.11 Ventilation Filter Testing Program (VFTP) (continued)
- b.
Demonstrate for each of the ESF systems that an inplace test of the charcoal adsorber shows a penetration and system bypass < 1.0% when tested at the system flowrate specified below.
ESF Ventilation System Flowrate Control Room Filtration 2000 cfm, +/- 200 cfm Emergency Exhaust System 9000 cfm, +/- 900 cfm
- c.
Demonstrate for each of the ESF systems within 31 days after removal that a laboratory test of a sample of the charcoal adsorber, when obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, shows the methyl iodide penetration less than the value specified below when tested in accordance with ASTM D3803-1989 at a temperature of 30°C and the relative humidity specified below.
- d.
Demonstrate at least once per 18 months for each of the ESF systems that the pressure drop across the combined HEPA filters and the charcoal adsorbers (as applicable) is less than the value specified below when tested at the system flowrate specified below.
ESF Ventilation System Control Room Filtration Delta P 5.4" WG Flowrate 2000 cfm,
+/- 200 cfm Control Room Pressurization*
5.4" WG 500 cfm,
+500,- 50 cfm Emergency Exhaust System 5.4" WG 9000 cfm,
+/- 900 cfm
- A charcoal adsorber is not required to be installed or included in either control room pressurization train.
ESF Ventilation System Penetration RH Control Room Filtration 2.0%
70%
Emergency Exhaust System 2.0%
70%
ULNRC06636 Page 7 of 9 Programs and Manuals 5.5 5.5 Programs and Manuals (continued)
CALLAWAY PLANT 5.0-16 Amendment No. xxx l 5.5.11 Ventilation Filter Testing Program (VFTP) (continued)
- e.
Demonstrate at least once per 18 months that the heaters for each of the ESF systems dissipate the value specified below when tested in accordance with ANSI 510-1975 and corrected to design nameplate voltage settings.
ESF Ventilation System Wattage Emergency Exhaust System 37 +/- 3 KW The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the VFTP test frequencies.
5.5.12 Explosive Gas and Storage Tank Radioactivity Monitoring Program This program provides controls for potentially explosive gas mixtures contained in the Gaseous Radwaste System, the quantity of radioactivity contained in gas storage tanks and the quantity of radioactivity contained in unprotected outdoor liquid storage tanks. The gaseous radioactivity quantities shall be determined following the methodology in Branch Technical Position (BTP) ETSB 11-5, "Postulated Radioactive Release due to Waste Gas System Leak or Failure, Revision 0". The liquid radwaste quantities shall be determined in accordance with Standard Review Plan, Section 15.7.3, "Postulated Radioactive Release due to Tank Failures, Revision 2".
The program shall include:
- a.
The limits for concentrations of hydrogen and oxygen in the Gaseous Radwaste System and a surveillance program to ensure the limits are maintained. Such limits shall be appropriate to the system's design criteria (i.e., whether or not the system is designed to withstand a hydrogen explosion);
- b.
A surveillance program to ensure that the quantity of radioactivity contained in each gas storage tank is less than the amount that would result in a whole body exposure of 0.5 rem to any individual in an unrestricted area, in the event of an uncontrolled release of the tanks' contents; and
- c.
A surveillance program to ensure that the quantity of radioactivity contained in the outdoor liquid radwaste tanks listed below that are not
ULNRC06636 Page 8 of 9 Programs and Manuals 5.5 5.5 Programs and Manuals (continued)
CALLAWAY PLANT 5.0-21 Amendment No. xxx l 5.5.17 Control Room Envelope Habitability Program A Control Room Envelope (CRE) Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Control Room Emergency Ventilation System (CREVS), CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke challenge. The program shall ensure that adequate radiation protection is provided to permit access and occupancy of the CRE under design basis accident (DBA) conditions without personnel receiving radiation exposures in excess of 5 rem total effective dose equivalent (TEDE) for the duration of the accident. The program shall include the following elements:
- a.
The definition of the CRE, CRE boundary, control building envelope (CBE), CBE boundary, equipment room envelope (ERE) and the ERE boundary.
- b.
Requirements for maintaining the CRE, CBE and ERE boundaries in their design condition, including configuration control and preventive maintenance.
- c.
Requirements for (i) determining the unfiltered air inleakage past the CRE, CBE and ERE boundaries in accordance with the testing methods and at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, "Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors," Revision 0, May 2003, and (ii) assessing CRE habitability at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, Revision 0.
The following exception is taken to Sections C.1 and C.2 of Regulatory Guide 1.197, Revision 0:
- 1.
The Tracer Gas Test based on the Brookhaven National Laboratory Atmospheric Tracer Depletion (ATD) Method is used to determine the unfiltered air inleakage past the CRE, CBE and ERE boundaries. The ATD Method is described in AmerenUE letters dated December 15, 2004 (ULNRC-05104), June 6, 2006 (ULNRC-05298), July 16, 2007 (ULNRC-05427), and October 30, 2007 (ULNRC-05448).
- d.
Measurement, at designated locations, of the CRE pressure relative to the outside atmosphere during the pressurization mode of operation by one train of the CREVS, operating at the flow rate required by the VFTP, at a Frequency of 18 months on a STAGGERED TEST BASIS. The results shall be trended and used as part of the periodic assessment of the CRE boundary.
(continued)
CALLAWAY PLANT 5.0-22 Amendment No. xxx l ULNRC06636 Page 9 of 9 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.17 Control Room Envelope Habitability Program (continued)
- e.
The quantitative limits on unfiltered air inleakage into CRE, CBE and ERE. These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph c. The unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of DBA consequences. Unfiltered air leakage limits for hazardous chemicals must ensure that exposure of CRE occupants to these hazards will be within the assumptions in the licensing basis.
- f.
The provisions of SR 3.0.2 are applicable to the Frequencies for assessing CRE habitability, determining CRE, CBE and ERE unfiltered inleakage, and measuring CRE pressure and assessing the CRE, CBE and ERE as required by paragraphs c and d.
5.5.18 Surveillance Frequency Control Program This program provides controls for Surveillance Frequencies. The program shall ensure that Surveillance Requirements specified in the Technical Specifications are performed at intervals sufficient to assure the associated Limiting Conditions for Operation are met.
- a.
The Surveillance Frequency Control Program shall contain a list of Frequencies of those Surveillance Requirements for which the Frequency is controlled by the program.
- b.
Changes to the Frequencies listed in the Surveillance Frequency Control Program shall be made in accordance with NEI 04-10, Risk-Informed Method for Control of Surveillance Frequencies, Revision 1.
- c.
The provisions of Surveillance Requirements 3.0.2 and 3.0.3 are applicable to the Frequencies established in the Surveillance Frequency Control Program.