ML050620513
| ML050620513 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 03/03/2005 |
| From: | Brian Benney NRC/NRR/DLPM/LPD4 |
| To: | Parrish J Energy Northwest |
| Benney B, NRR/DLPM, 415-3764 | |
| Shared Package | |
| ML050620299 | List: |
| References | |
| TAC MC4444 | |
| Download: ML050620513 (8) | |
Text
TABLE OF CONTENTS 3.6 3.6.3.1 3.6.3.2 3.6.3.3 3.6.4.1 3.6.4.2 3.6.4.3 3.7 3.7.1 3.7.2 3.7.3 3.7.4 3.7.5 3.7.6 3.7.7 3.8 3.8.1 3.8.2 3.8.3 3.8.4 3.8.5 3.8.6 3.8.7 3.8.8 3.9 3.9.1 3.9.2 3.9.3 3.9.4 3.9.5 3.9.6 3.9.7 3.9.8 3.9.9 3.10 3.10.1 3.10.2 3.10.3 CONTAINMENT SYSTEMS (continued)
Deleted Primary Containment Atmosphere Mixing System Primary Containment Oxygen Concentration.
Secondary Containment Secondary Containment Isolation Valves (SCIVs).
Standby Gas Treatment (SGT) System.......
PLANT SYSTEMS Standby Service Water (SW) System and Ultimate Heat Sink (UHS)..........
High Pressure Core Spray (HPCS) Service Water (SW) System Control Room Emergency Filtration (CREF) System Control Room Air Conditioning (AC) System Main Condenser Offgas Main Turbine Bypass System...........
Spent Fuel Storage Pool Water Level ELECTRICAL POWER SYSTEMS AC Sources -Operating AC Sources -Shutdown..............
Diesel Fuel Oil, Lube Oil, and Starting Air DC Sources -Operating DC Sources -Shutdown..............
Battery Cell Parameters Distribution Systems-Operating Distribution Systems-Shutdown.........
REFUELING OPERATIONS Refueling Equipment Interlocks.........
Refuel Position One-Rod-Out Interlock Control Rod Position..............
Control Rod Position Indication Control Rod OPERABILITY-Refueling.......
Reactor Pressure Vessel (RPV) Water Level -Irradiated Fuel...........
Reactor Pressure Vessel (RPV) Water Level -New Fuel or Control Rods Residual Heat Removal (RHR)-High Water Level Residual Heat Removal (RHR)-Low Water Level SPECIAL OPERATIONS Inservice Leak and Hydrostatic Testing Operation Reactor Mode Switch Interlock Testing Single Control Rod Withdrawal -Hot Shutdown I
3.6.3.2-1 3.6.3.3-1 3.6.4.1-1 3.6.4.2-1 3.6.4.3-1 3.7.1-1 3.7.2-1 3.7.3-1 3.7.4-1 3.7.5-1 3.7.6-1 3.7.7-1 3.8.1-1 3.8.2-1 3.8.3-1 3.8.4-1 3.8.5-1 3.8.6-1 3.8.7-1 3.8.8-1 3.9.1-1 3.9.2-1 3.9.3-1 3.9.4-1 3.9.5-1 3.9.6-1 3.9.7-1 3.9.8-1 3.9.9-1 3.10.1-1 3.10.2-1 3.10.3-1 (continued)
Columbia Generation Station ii i Amendment No. 149,169i 189
TABLE OF CONTENTS 3.10 SPECIAL OPERATIONS (continued) 3.10.4 Single Control Rod Withdrawal -Cold Shutdown..
3.10.4-1 3.10.5 Single Control Rod Drive (CRD)
Removal-Refueling...............
3.10.5-1 3.10.6 Multiple Control Rod Withdrawal-Refueling.....
3.10.6-1 3.10.7 Control Rod Testing-Operating...........
3.10.7-1 3.10.8 SHUTDOWN MARGIN (SDM) Test -Refueling 3.10.8-1 4.0 DESIGN FEATURES 4.1 Site Location 4.0-1 4.2 Reactor Core....................
4.0-1 4.3 Fuel Storage....................
4.0-2 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility...................
5.1-1 5.2 Organization....................
5.2-1 5.3 Unit Staff Oualifications 5.3-1 5.4 Procedures..................
5.4-1 5.5 Programs and Manuals................
5.5-1 5.6 Reporting Requirements...............
5.6-1 5.7 High Radiation Area 5.7-1 Columbia Generating Station i v Amendment No. +4-9 1691
PAM Instrumentation 3.3.3.1 SURVEILLANCE REQUIREMENTS
-- ----------------------------- NOTES------------------------------------
- 1.
These SRs apply to each Function in Table 3.3.3.1-1.
- 2.
When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the other required channel(s) in the associated Function is OPERABLE.
SURVEILLANCE FREQUENCY SR 3.3.3.1.1 Perform CHANNEL CHECK.
31 days SR 3.3.3.1.2 Deleted SR 3.3.3.1.3 Perform CHANNEL CALIBRATION for 18 months Functions 1. 2. 4, 5, and 10.
SR 3.3.3.1.4 Perform CHANNEL CALIBRATION for 24 months Functions 3, 6, and 7.
I I
Columbia Generating Station
- 3. 3.3. 1-3 Amendment No. 149.169,179, 189
PAM Instrumentation 3.3.3.1 Table 3.3.3.1-1 (page 1 of 1)
Post Accident Monitoring Instrumentation CONDITIONS REFERENCED REQUIRED FROM REQUIRED FUNCTION CHANNELS ACTION D.1
- 1. Reactor Vessel Pressure 2
E
- 2.
- a. -150 inches to +60 inches 2
E
- b. -310 inches to -110 inches 2
E
- 3.
Suppression Pool Water Level
- a. -25 inches to +25 inches 2
E
- b. 2 ft to 52 ft 2
E
- 4.
Suppression Chamber Pressure 2
E
- 5.
Drywell Pressure
- a. -5 psig to +3 psig 2
E
- b. 0 psig to 25 psig 2
E
- c. 0 psig to 180 psig 2
E
- 6.
Primary Containment Area Radiation 2
F
- 7. PCIV Position 2 per penetration E
flow path (a)(b)
- 8. Deleted
- 9.
Deleted
- 10.
ECCS Pump Room Flood Level 5
E I
(a) Not required for isolation valves whose associated penetration flow path is isolated by at least one closed and de-activated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured.
(b) Only one position indication channel is required for penetration flow paths with only one installed control room indication channel.
Columbia Generating Station 3.3.3.1 -4 Amendment No. 149,169, 189
Primary Containment Hydrogen Recombiners 3.6.3.1 3.6 CONTAINMENT SYSTEMS 3.6.3.1 Deleted Columbia Generating Station 3.6.3. 1-1 Amendment No. 149.169,18-7 189
Primary Containment Hydrogen Recombiners 3.6.3.1 This Page Intentionally Left Blank Columbia Generating Station
- 3. 6.3. 1-2 Amendment No. 149,169,187, 189
Programs and Manuals 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Programs and Manuals The following programs shall be established, implemented, and maintained.
5.5.1 Offsite Dose Calculation Manual (OCM)
- a.
The ODCM shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the radiological environmental monitoring program; and
- b.
The ODCM shall also contain the radioactive effluent controls and radiological environmental monitoring activities, and descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release reports required by Specification 5.6.2 and Specification 5.6.3.
- c.
Licensee initiated changes to the ODCM:
- 1.
Shall be documented and records of reviews performed shall be retained.
This documentation shall contain:
(a) Sufficient information to support the change(s) together with the appropriate analyses or evaluations justifying the change(s), and (b) A determination that the change(s) maintain the levels of radioactive effluent control required pursuant to 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I. and do not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations;
- 2.
Shall become effective after review and acceptance by the Plant Operations Committee and the approval of the Plant General Manager; and (continued)
Columbia Generating Station Amendment No. 1494 1691
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.1 Offsite Dose Calculation Manual (ODCM)
(continued)
- 3.
Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as a part of, or concurrent with, the Radioactive Effluent Release Report for the period of the report in which any change in the ODCM was made.
Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e., month and year) the change was implemented.
5.5.2 Primary Coolant Sources Outside Containment This program provides controls to minimize leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to levels as low as practicable.
The systems include the Low Pressure Core Spray, High Pressure Core Spray, Residual Heat Removal, Reactor Core Isolation Cooling, process sampling, (the program requirements shall apply to the Post Accident Sampling System until such time as administrative controls provide for continuous isolation of the associated penetration(s) or a modification eliminates the potential leakage path(s)),
containment monitoring, and Standby Gas Treatment.
The program shall include the following:
- a.
Preventive maintenance and periodic visual inspection requirements; and
- b.
Integrated leak test requirements for each system at 24 month intervals or less.
The provisions of SR 3.0.2 are applicable to the 24 month Frequency for performing integrated system leak test activities.
5.5.3 Deleted (continued)
Columbia Generating Station
- 5. 5-2 Amendment No. 149,169,184, 189