ML072830343
| ML072830343 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 10/04/2007 |
| From: | NRC/NRR/ADRO/DORL/LPLIII-2 |
| To: | |
| Kuntz, Robert F, NRR/DORL, 415-3733 | |
| References | |
| TAC MD3079, TAC MD3080 | |
| Download: ML072830343 (7) | |
Text
SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs In MODES 1 and 2, the combination of THERMAL POWER, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the limits specified in the COLR; and the following SLs shall not be exceeded.
2.1.1.1 In MODE 1, the Departure from Nucleate Boiling Ratio (DNBR) shall be maintained _> 1.24 for the WRB-2 DNB correlation for a thimble cell and _> 1.25 for the WRB-2 DNB correlation for a typical cell.
2.1.1.2 In MODE 2, the DNBR shall be maintained >
WRB-2 DNB correlation, and Ž 1.30 for the correlation.
1.17 for the W-3 DNB 2.1.1.3 In MODES 1 and 2, the peak fuel centerline temperature shall be maintained as follows:
- a. < 5080°F decreasing by 58OF per 10,000 MWD/MTU burnup for Westinghouse fuel,
- b. < 5173°F decreasing by.65°F per 10,000 for AREVA NP fuel (Unit 1 only), and
- c. < 5189°F decreasing by 65°F per 10,000 for AREVA NP fuel containing Gadolinia MWD/MTU burnup MWD/MTU burnup (Unit 1 only).
2.1.2 RCS Pressure SL In MODES 1, 2, 3, 4, and
! 2735 psig.
5, the RCS pressure shall be maintained 2.2 SL Violations 2.2.1 If SL 2.1.1 is violated, restore compliance and within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
be in MODE 3 2.2.2 If SL 2.1.2 is violated:
2.2.2.1 In MODE 1 or 2, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
restore compliance and be in MODE 3 2.2.2.2 In MODE 3, 4, or 5, restore compliance within 5 minutes.
BRAIDWOOD - UNITS 1 & 2 2.0-1 Amendmentl45/145
Spent Fuel Pool Boron Concentration 3.7.15 3.7 PLANT SYSTEMS 3.7.15 Spent Fuel Pool Boron Concentration LCO 3..15 APPLICABILITY:
The spent fuel pool boron concentration shall be Ž 300 ppm.
Whenever fuel assemblies are stored in the spent fuel pool.
i ACTIONS ACTIONS
- - -- - -- - -- - -- - -NOTE - - -----
LCO 3.0.3 is not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. Spent fuel pool boron A.1 Suspend movement of Immediately concentration not fuel assemblies in within limit, the spent fuel pool.
AND A.2 Initiate action to Immediately restore spent fuel pool boron concentration to within limit.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.15.1 Verify the spent fuel pool boron 7 days concentration is within limit.
BRAIDWOOD - UNITS 1 & 2 3.7.15 - 1 Amendment 145/145
Spent Fuel Assembly Storage 3.7.16 3.7 PLANT SYSTEMS 3.7.16 Spent Fuel Assembly Storage LCO 3.7.16 Each spent fuel assembly stored in the spent fuel pool shall, as applicable:
- a.
Region 1 of Holtec spent fuel pool storage racks Have an initial nominal enrichment of
- 5.0 weight percent U-235 to permit storage in any cell location.
- b.
Region 2 of Holtec spent fuel pool storage racks Have a combination of initial enrichment and burnup within the Acceptable Burnup Domain of Figure 3.7.16-1.
Whenever fuel assemblies are stored in the spent fuel pool.
APPLICABILITY:
ACTIONS
NOTE LCO 3.0.3 is hot applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the A.1 Initiate action to Immediately LCO not met.
move the noncomplying fuel assembly into a location which restores compliance.
I BRAIDWOOD - UNITS 1 & 2 3.7.16 -
1 Amendmentl45/145.
Spent Fuel Assembly Storage 3.7.16 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY NP
'1 7 1 f' 1
'prifv hy Adminic'i1-Hun Menc the f-ial D I-4 J/ r-nominal enrichment of the fuel assembly is storing the
< 5.0 weight percent U-235.
fuel assembly in Region I SR 3.7.16.2 Verify by administrative means the Prior to combination of initial enrichment, burnup, storing the and decay time, as applicable, of the fuel fuel assembly assembly is within the Acceptable Burnup in Region 2 Domain of Figure 3.7.16-1.
BRAIDWOOD -
UNITS 1 & 2 3.7.16 - 2 Amendment 145/145
Spent Fuel Assembly Storage 3.7.16 45000 40000 S35000 30000 z 25000
> 20000 15000 10000 5000 7 7,
I
- ACCEPTABLE IBURNUP D OMAN[
A I N I
I
-I
,.-p-I
~--t-:
I T
I
[vI1 7
~~
I T
9 I
C A---
UNACCEPTABLE UR
-IBURNUP DOMAIN I
7 -
7/K E I' 0
2 2.5 3
3.5 4
INITIAL U-235 ENRICHMENT (w/o) 4.5 5
Figure 3.7.16-1 (page I of 1)
Region 2 Fuel Assembly Burnup Requirements (Holtec Spent Fuel Pool Storage Racks)
I BRAIDWOOD -
UNITS I & 2 3.7.16 - 3 Amendment 145/145
Design Features 4.0 4.0 DESIGN FEATURES 4:1 Site 4.1.1 Site Location The site is located in Reed Township, approximately 20 mi (32 km) south-southwest of the city of Joliet in northern Illinois.
4.1.2 Exclusion Area Boundary (EAB)
The EAB shall not be less than 1591 ft (485 meters) fromthe outer containment wall.
4.1.3 Low Population Zone (LPZ)
The LPZ shall be a 1.125 mi (1811 meter) radius measured from the midpoint between the two reactors.
4.2 Reactor Core 4.2.1 Fuel Assemblies The reactor shall contain 193 fuel assemblies.
Each assembly, with exceptions as noted below, shall consist of a matrix of Zircaloy or ZIRLO clad fuel rods with an initial composition of natural or slightly enriched uranium dioxide (UO) as fuel material.
Limited substitutions of zirconium alioy or stainless steel filler rods or vacancies for fuel rods, in accordance with approved applications of fuel rod configurations, may be used.
Fuel assemb lies shall be limited to those fuel designs that have been analyzed with applicable NRC staff approved codes and methods and shown by tests pr 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 nonlimiting core regions.
Up to 8 AREVA NP Advanced Mark-BW(A) fuel assemblies containing M5 alloy may be placed in nonlimiting Unit 1 core regions for evaluation during Cycles 14, 15, and 16.
4.2.2 Control Rod Assemblies The reactor core shall contain 53 control rod assemblies.
The control material shall be silver indium cadmium, hafnium, or a mixture of both types.
BRAIDWOOD - UNITS I & 2 4.0-1I Amendment 145/145
Design Features 4.0 DESIGN FEATURES (continued) 4.3 Fuel Storage 4.3.1 Criticality The spent fuel storage racks are designed and shall be maintained, as applicable, with:
- a.
Fuel assemblies having a maximum U-235 enrichment of 5.0 weight percent;
- b.
For Holtec spent fuel pool storage racks, kff
- 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Holtec International Report HI-982094, "Criticality Analysis for Byron/Braidwood Rack Installation Project," Project No. 80944, 1998;
- c.
For Holtec spent fuel pool storage racks, a nominal 10.888 inch north-south and 10.574 inch east-west center to center distance between fuel assemblies placed in Region 1 racks; and
- d.
For Holtec spent fuel pool storage racks, a nominal 8.97 inch center to center distance between fuel assemblies placed in Region 2 racks.
4.3.2 Drainaqe The spent fuel pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 410 ft, 0 inches.
4.3.3 Capacity The spent fuel pool is designed and shall be maintained with a storage capacity limited to no more than 2984 fuel assemblies.
BRAIDWOOD -
UNITS 1 & 2 4.0-2 Amendment 145/145