ML20005E403
| ML20005E403 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 12/21/1989 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20005E400 | List: |
| References | |
| NUDOCS 9001050184 | |
| Download: ML20005E403 (3) | |
Text
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Seent-Fuel Pool Soecial Ventilation Svatam 1.:Except as specified in Specification 3.8.D 3 below, both trains of-the Spent Fuel Pool Special Ventilation System and the diesel generators required for their operation shall be operable at all times.-
- 2. a.. The results of in place DOP and halogenated hydrocarbon tests at design flows on HEPA filters and charcoal adsorber banks respec-tively shall show 2 994 DOP removal for particles having a mean diameter of 0.7 microns and g 994 halogenated hydrocarbon removal, b.
The results of laboratory carbon sample analysis shall show 2 904 radioactive methyl iodide removal efficioney (130*C, 95% RH).
The Spent Fuel Pool Special Ventilation System fans shall cperate
.c.
within i 10% of 5200 cfm per train.
- 3. From and after the date that one train'of the Spent Fuel Fool Special Ventilation System is made or found inoperable for any reason, fuel handling operations are permissible only during the succeeding seven days (unless such train is made operable) provided that the redundant train is verified to be operable daily.
- 4. If the conditions for operability of the Spent Fuel Pool Special Ventilation System cannot be met, fuel handling operations in the Auxiliary Building shall be terminated immediately.
E.
Storare of Low Burnuo Fuel
- 1. The following restrictions shall apply whenever fuel with an average assembly burnup less than 5,000 MVD/MTU is stored in the spent fuel pool (except as specified in 3.8.E.2 and 3.8.E.3 below):
a.
The boron concentration in the spent fuel pool shall be maintained greater than or equal to 500 ppa, and b.
Fuel with an average assembly burnup less than 5,000 MWD /MTU shall not be stored in more than three storage locations of every two by two storage rack array.
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- 2. If the conditions in 3.8.E.1.a above are not met, verify that the spent fuel pool storage configuration meets the requirements of specification L
3.8.E.1.b and suspend all actions involving the movement of fuel in the spent fuel pool until the boron concentration is increased to 500 ppm or greater.
- 3. If the conditions in 3.8.E.1.b above are not met, suspend all actions involving movement of fuel in'the spent fuel pool, verify the spent fuel pool boron concentration to be greater than or equal to 500 ppm and initiate corrective actions. Mis positioned fuel assemblies shall be moved to acceptable locations prior to the resumption of other fuel movement in the spent fuel pool.
Prairie Island Unit 1 - Amendment No. J7, 26, 73, 7#,90 Prairie Island Unit 2 - Amendment No. JJ, 19, 66, 67, 83 90010so1s4 99122,
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- 5. 3 RFACTOR.
A, Reactor Core 1.
The reactor core contains uranium in the form of slightly l
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- enriched uranium dioxide pellets. b pellets are encapsulated in Eircaloy 4 tubing to form fuel rods, the reactor core is made up of 121 fuel assemblies. Each fuel assembly contains-179. fuel rods (Reference 1).
2.
h maximum enrichment will be 4.25 we1 ht percent U 235.
8 2.
In the reactor core,'there are 29 full length RCC assemblies that contain a 142 inch length of silver indium. cadmium alloy clad with stainless steel (Reference 2).
B.
Reactor Coolant Evatam l
'1.' The design of the reactor coolant system complies with all appl-cable code requirements (Reference 3).
2.
All high pressure piping, components of the reactor coolant system and their supporting structures are designed to Class I L
requirements, and have been designed to withstand:
The design seismic ground acceleration, 0.063 acting in the s.
horizontal and 0.04g acting in the vertical planes simultane-ously, with stresses maintained within code allowable working
- stresses, i
b.
The maximum potential seismic ground acceleration, 0.12,
3 acting in the horizontal and 0.08g acting in the vertical planes simultaneously with no loss of function.
3.
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The nominal liquid volume of the reactor coolant system, at rated operating condia: ions, is 6100 cubic feet.
C. Protection Systems The protection systems for the reactor and engineered safety features are designed to applicable codes, including IEEE 279, dated 1968. The design includes a reactor trip for a high negative rate of change of t:
p neutron flux as measured by the excore nuclear instruments (Reference 4).
The system is intended to trip the reactor upon the abnormal l:
dropping of more than one control rod (Reference 4).
If only one control rod is dropped, the core can be operated at full power for a short time, as permitted by Specification 3.10.
References l;
1.
USAR, Section 3.4.2 3.
USAR, Table 4.1 11 L
2.
USAR, Section 3.5.2 4.
USAR, Section 7.1 Prairie Island Unit 1 - Amendment No. 35. AB, 80,90 1
Prairie Island Unit 2 - Amendment No. 29, #2, 73, 83 lq-
TS.5.6 3 l-The spent fuel cask will be lowered 66 feet from the auxiliary building to the railroad car for offsite transportation, specification 3.8 will limit this leading operation-so that if the cask drops 66 feet, there
d' will not be a significant release of fission products from the fuel in the cask.
D.
Soent Puel Storane Canacity
-The spent fuel storage facility is a two compartment pool that, if completely filled with fuel storage racks, providas.up to 1582 storage locations. The southeast corner of the small pool (pool no.1) also serves as the cask lay down area. During times when the cask is being
.used, four racks are removed from the small pool.. With the four storage racks in the southeast corner of pool 1 removed, a total of 1386 storage locations are provided.
To allow insertion of a shipping cask, total storage is limited to 1386 assemblies, not including those assemblies which can be returned to the reactor.
Reference 1.
USAR. Section 10.2 l.
Prairie Island Unit 1 - Amendment No.90 Prairie Island Unit 2 - Amendment No.83
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