ML052290254
| ML052290254 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 08/16/2005 |
| From: | Macon W NRC/NRR/DLPM |
| To: | Bezilla M FirstEnergy Nuclear Operating Co |
| Macon W, NRR/DLPM,415-3965 | |
| Shared Package | |
| ML051800079 | List: |
| References | |
| TAC MC6812 | |
| Download: ML052290254 (9) | |
Text
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 314.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION.......................................
3/49-1 3/4.9.2 INSTRUMENTATION...............
............................. 314 9-2 314.9.3 DECAY TIME.
3/4 9-3 314.9.4 CONTAINMENT PENETRATIONS........
......................... 3149-4 3/4.9.5 DELETED..................
4 34 9-5 314.9.6 FUEL HANDLING BRIDGE OPERABILITY..........................
3/4 9-6 314.9.7 DELETED....................................................
314 9-7 314.9.8 DECAY HEAT REMOVAL AND COOLANT CIRCULATION All Water Levels...........
314 9-8 Low Water Levels.............................................. 314 9-8a 3/4.9.9 DELETED.................
3/4 9-9 314.9.10 WVATER LEVEL-REACTOR VESSEL.......
...................... 314 9-10 314.9.11 STORAGE POOL WATER LEVEL........
314 9-11 314.9.12 STORAGE POOL VENTILATION.........
......................... 3/4 9-12 314.9.13 SPENT FUEL ASSEMBLY STORAGE.......
...................... 3/4 9-13 3/4.10 SPECIAL TEST EXCEPTIONS 314.1 0.1 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS......................................
3/4 10-1 3/4.10.2 PHYSICS TESTS.
3/4 10-2 314.10.3 REACTOR COOLANT LOOPS..........
.......................... 3/4 10-;
314.10A SHUTDOWN MARGIN.............
............................. 314 10-4 DAVIS-BESSE, UNIT I Villl AmendmentNo.38, 130,186,224,237 266
DELETED DAVIS-BESSE, UNIT I 3/4 9-7 Amendment No. 237, 247, 266
REFUELING OPERATIONS STORAGE POOL WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.11 As a minimum, 23 feet of water shall be maintained over the top of irradiated fuel assemblies seated in the storage racks in the spent fuel pool.
APPLICABILMTY: Whenever irradiated fuel assemblies are in the spent fuel pool.
ACTION:
With the requirement of the specification not satisfied, suspend all movement of fuel and crane operations with loads in the fuel storage area and restore the water level to within its limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.11 The water level in the spent fuel pool shall be determined to be at least its minimum required depth at least once per 7 days when irradiated fuel assemblies are in the spent fuel pool.
DAVIS-BESSE, UNIT I 3/4 9-11 Amendmient No. 237, 247, 266
REFUELING OPERATIONS STORAGE POOL VENTILATION LIMITING CONDITION FOR OPERATION 3.9.12 Two independent emergency ventilation systems servicing the storage pool area shall be OPERABLE. When an emergency ventilation system servicing the storage pool is incapable of meeting the acceptance criteria of Surveillance Re4uirement 4.9.12.1 solely because the containment equipment hatch is open and both doors of the containment personnel air lock arc open, it may be considered OPERABLE provided that at least one personnel air lock door is capable of being closed and a designated individual is available immediately outside the personnel air lock to close the door.
APPLICABILITY:
Whenever irradiated fuel is in the spent fuel pool or during CORE ALTERATIONS or movement of irradiated fuel within the containment with the containment equipment hatch open.
ACTION:
- a. With one emergency ventilation system servicing the storage pool area inoperable, fuel movement within the spent fuel pool or crane operation with loads over the spent fuel pool may proceed provided the OPERABLE emergency ventilation system servicing the storage pool area is in operation and discharging through at least one train of HEPA filters and charcoal adsorbers.
- b. WVith one emergency ventilation system servicing the storage pool area inoperable, CORE ALTERATIONS and fuel movement within containment may proceed provided either the OPERABLE emergency ventilation system servicing the storage pool area is in operation and discharging through at least one train of HEPA filters and charcoal adsorbers or the containment equipment hatch cover is closed and held in place by a minimum of four bolts.
- c. With no emergency ventilation system servicing the storage pool area OPERABLE, suspend CORE ALTERATIONS and all operations involving movement of fuel within the containment or spent fuel pool, or crane operation with loads over the spent fuel pool, until at least one system is restored to OPERABLE status. CORE ALTERATONS and fuel movement within containment may proceed provided the containment equipment hatch cover is closed and held in place by a minimum of four bolts.
- d. The provisions of Specifications 3.0.3 and 3.0A are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.12.1 The above required emergency ventilation system servicing the storage pool area shall be demonstrated OPERABLE per the applicable Surveillance Requirements of4.6.5.1, and at least once each REFUELING INTERVAL by verifying that the emergency ventilation system servicing the storage pool area maintains the storage pool area at a negative pressure of > 1/8 inches Water Gauge relative to the outside atmosphere during system operation.
4.9.12.2 The normal storage pool ventilation system shall be demonstrated OPERABLE at least once each REFUELING INTERVAL by verifying that the system fans stop automatically and that dampers automatically divert flow into the emergency ventilation system on a fuel storage area high radiation test signal.
DAVIS-BESSE, UJNIT I 3/4 9-12 Amendment No. 135,217,237,247,251 266
REFUELING OPERATIONS SPENT FUEL ASSEMBLY STORAGE LIMITING CONDITION FOR OPERATION 3.9.13 Fuel assemblies stored in the spent fuel pool shall be placed in the spent fuel storage racks in accordance with the criteria shown in Figure 3.9-1.
APPLICABILITY: Whenever fuel assemblies are in the spent fuel pool.
ACTION:
With the requirements of the above specification not satisfied, suspend all other fuel movement within the spent fuel pool and move the non-complying fuel assemblies to allowable locations in accordance with Figure 3.9-1. The provisions of Specifications 3.0.3 and 3.0A are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.13.1 Prior to storing a fuel assembly in the spent fuel pool, verify by administrative means that the initial enrichment and burnup of the fuel assembly are in accordance with Figure 3.9-1.
DAVIS-BESSE, UJNIT I 3/4 9-13 Amendment No. 130, 181, 237,247, 266
Figure 3.9-1 Bumup vs Enrichment Curves For the Davis-Besse High Density Spent Fuel Pool Storage Racks I
75 70 65 60 55 50 5
cE 45 rz S 40
_ 35 CZ E 30 25 20 15 10 5
0 2.00 2.50 3.00 3.50 4.00 4.50 5.00 Initial Enrichment (wt% U-235) 5.50 Notes:
Fuel assemblies with initial enrichments less than 2 wt% U-235 will conservatively be required to meet the burnup requirements of 2.0 wt% U-235 assemblies.
Loading pattern considerations applicable to Category "A", "B", and "C" assemblies are described in the Bases DAVI S-B ES SE, UNIT I 314 9-14 Amendment No. 247, 266
Design Features 5.0 5.0 DESIGN FEATURES 5.1 Site Location The Davis-Besse Nuclear Power Station, Unit Number 1, site is located on Lake Erie in Ottawa County, Ohio, approximately six miles northeast from Oak Harbor, Ohio and 21 miles east from Toledo, Ohio. The exclusion area boundary has a minimum radius of 2400 feet from the center of the plant.
5.2 (Deleted) 53 Reactor Core 5.3.1 Fuel Assemblies The reactor core shall contain 177 fuel assemblies. Each assembly shall consist of a matrix ofzircaloy M5, or ZIRLO clid fuel rods with an initial composition of natural or slightly enriched uranium dioxide (UO) as fuel material. Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with approved applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff approved codes and methods and shown by tests or analyses to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in non-limiting core regions.
5.3.2 Control Rods The reactor core shall contain 53 safety and regulating control rod assemblies and 8 axial power shaping rod (APSR) assemblies. The nominal values of absorber material for the safety and regulating control rods shall be 80 percent silver, 15 percent indium and 5 percent cadmium. The absorber material for the APSRs shall be 100 percent Inconel.
5A (Deleted) 5.5 (Deleted) 5.6 Fuel Storage 5.6.1 Criticality 5.6.1.1 The new fuel storage racks are designed and shall be maintained with:
- a. A Keff equivalent to less than or equal to 0.95 when flooded with unborated water, *which includes a conservative allowance of 1% delta k/k for uncertainties as described in Section 9.1 of the USAR.
DAVIS-BESSE, UNIT 1 5-1 AmendmentNo. 170,179,204, 237,239, 247, 266
Design Features 5.0 5.0 DESIGN FEATURES 5.6 Fuel Storage (continued)
- b. A Kcfr equivalent to less than or equal to 0.98 when immersed in a hydrogenous "mist" of such a density that provides optimum moderation (i.e., highest value of KIp3), which includes a conservative allowance of 1% delta k/k for uncertainties
- as described in Section 9.1 of the USAR.
- c. A nominal 21'inch center-to-center distance between fuel assemblies placed in the storage racks.
- d. Fuel assemblies having a maximum initial enrichment of 5.0 weight percent uranium-235.
5.6.1.2 The high density spent fuel pool storage racks are designed and shall be maintained with:
- a.
A Kerr equivalent to less than or equal to 0.95 when flooded with unborated water, which includes a conservative allowance for manufacturing tolerances and calculation uncertainty.
- b.
A rectangular array ofstainless steel cells with walls of 0.075 inches nominal thickness, spaced a nominal 9.22 inches on center in both directions. Boral neutron absorber material is utilized between each cell for criticality considerations.
- c.
Fuel assemblies stored in the spent fuel pool in accordance with Technical Specification 3.9.13.
DAVlS-BESSE, UNIT I 5-2 Amendment No. 237,247, 266
Design Features 5.0 DESIGN FEATURES 5.6 Fuel Storage (continued) 5.6.2 Drainane The spent fuel storage pool, cask pit, and transfer pit are designed and shall be tmaintained to prevent inadvertent draining below 9 feet above the top of the fuel storage racks.
5.63 Cagacitv The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1624 fuel assemblies.
5.7 (Deleted)
DAVIS-BESSE, UNIT I 5.3 Amendment No. 204, 237, 247, 266 DAVIS-BESSE,UNIT I 5-3 Amendment No. 204, 237, 247, 266