ML20070L781
| ML20070L781 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 03/13/1991 |
| From: | NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20070L778 | List: |
| References | |
| NUDOCS 9103200241 | |
| Download: ML20070L781 (4) | |
Text
_ _
TS.$.3 1
--REV-90 0/20/09
$.3 REACTOR A.
Reneter Core 1.
The reactor core contains uranium in the form of slightly enriched uranium dioxide pellets.
The pellets are encapsulated in Zircaloy.4 tubing to form fuel rods. The reactor core is made up of 121 fuel assemblies.
Each fuel assembly qontains 179 fuel rods (Reference 14 2.
The maximum enrichment vi).1 be 4.25 weight percent U 23D'~
3.
In the reactor core, there are 29 full length RCC assemblies that contain a 142. inch length of silver indium. cadmium alloy ciud with stainless steel (Reference 2).
B.
Reacter Coolant System 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 coM anc system and their supporting structures are designed to Class I requirements, and have been designed to withstand:
The design seismic ground acceleration, 0.06g acting in the a.
horizontal and 0.04g acting in the vertical planes simultane.
ously, with stresses maintained within code allowable working
- stresses, b.
The maximum potential seismic ground acceleration, 0.12g, acting in the horizontal and 0.08g acting in the vertical planes simultaneously with no loss of function.
3.
The nominal liquid volume of the reactor coolant system, at rated operating conditions, is 6100 cubic feet.
C. Protection Systems The protection systems for the reactM. and engineered safety features are designed to applicable ecdes including IEEE.279, dated 1968.
The design includes a reactor trip for a high negative rate of change of l
neutron flux as measured by the excore nuclear instruments (Reference l
4).
The system is intended to trip the reactor upon the abnormal 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 1.
USAR, Section 3.4.2 3.
USAR, Table 4.1 11 2.
USAR. Section 3.5.2 4
USAR, Section 7.1 h
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, except that substitution of Zircoloy 4 or stainless steel filler
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rods or open w:.ter channels for fuel rods may be made in fuel
- i assemblies if justified by cycle specific reload analyses usin6 an i
1 NRC. approved methodology.
Should more than 30 rods in the core, or N
10 rods in any assembly, be replaced per refueling, a special report _
describing the number of rods replaced shall be submitted to the
. i Commission pursuant to Specificatior 6.7.D within 30 days after j
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cycle startup.
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Exhibit C l
Prairie Island Nuclear Generating Plant License Amendment Request Dated March 13, 1991 Revised Technical Specification Pages Exhibit C consists of the revised page for the Prairie Island Nuclear Generating Plant Technical Specification with the proposed changes L
incorporated.
The revised page is listed below:
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TS.5.3 1 5.3 REACTOR A.
Reactor Core I
1.
The reactor core contains uranium in the form of slightly enriched uranium dioxide pellets.
The pellets are encapsulated
[
in Zircaloy 4 tubing to form fuel rods.
The reactor core is made up of 121 fuel assemblies.
Each fuel assembly nominally contains j
179 fuel rods (Reference 1), except that substitution of Zircoloy*4 i
or stainless steel filler rods or open water channels for fuel rods may be made in fuel assemblies if justified by cycle specific reload j
analyses using an NRC approved methodology.
Should more than 30 rods in the core, or 10 rods in any assembly, be replaced per refueling, a i
special report describing the number of rods replaced shall be subinitted to the Cominission pursuant to Specification 6.7.D within 30 days after cycle startup.
2.
The maxiinum enrichment will be 4.25 weight percent U 235.
3.
In the reactor core, there ate 29 full length RCC assemblics that l
contain a 142 inch length of silver indium cadinium alloy clad with stainless steel (Reference 2).
i B.
[
1.
The design of the reactor coolant system coinplies with all appli-cable code requirerwents (Rcference 3).
I 2.
All high pressure piping, components of the reactor coolant system and their supporting structures are designed to Class I requirements, and have been designed to withstand:
I a.
The design scisinic ground ac,eleration, 0.06g acting in the horizontal and 0.04g acting in the vertical planes simultano-ously, with stresses maintained within code allowable working a
stresses.
b.
The maximum potential seismic ground acceleration, 0.12g, acting in the horizontal and 0.08g acting in the vertical j
planes simultaneously with no loss of function.
=
t' 3.
The nominal liquid volume:of the reactor coolant system, at rated operating conditions, is 6100 cubic feet.
C.
Protection Systems-i The protection systems for the reactor and engineored safety features are designed to applicable codes, including IEEE 279, dated 1968. The j
design includes a reactor trip for a hi h DeSative rate of change of S
neutron flux as measured by the excore nuclear instruments (Reference 4).
The system is intended to trip the reactor upon the abnormal dropping of more than one control rod (Reference 4).
If only one i
control rod is dropped, the core can be operated at full-power for a short time, as permitted by Specification 3.10.
References 1.
USAR, Section 3.4.2 3.
USAR, Table 4.1 11 2.
USAR, Section 3.5.2 4.
USAR, Section 7.1
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