ML20106J817
| ML20106J817 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 04/08/1996 |
| From: | Wadley M NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| IEB-96-001, IEB-96-1, NUDOCS 9604110295 | |
| Download: ML20106J817 (14) | |
Text
i t
l Northern States Power Company l
Prairie Island Nuclear Generating Plant 1717 Wakonade Dr. East l
Welch, Minnesota 55089 l
April 8,1996 NRC Bulletin 96-01 l
U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos.50-282 License Nos. DPR-42 50-306 DPR-60 Response to NRC Bulletin 96-01: Control Rod Insertion Problems This letter provides our response to Bulletin 96-01, Control Rod Insertion Problems.
The bulletin requests two responses within 30 days of the date of the bulletin:
I (1)
Within 30 days of the date of this bulletin, a report certifying that control rods are determined to be operable: actions taken for Requested Actions (1) and (2) above; and the plans for implementing Requested Action (3) and (4).
(2)
Within 30 days of the date of this bulletin, a core map of rodded fuel assemblies indicating fuel type (materials, grids, spacers, guide tube inner diameter) and current and projected end of cycle burnup of each rodded assembly for the current cycl; when available, provide the same information for the next cycle.
The response to (1) is included in Attachment 2 and the core maps for the current cycles for both units as requested by (2) are included in Attachment (3). In addition, we commit to provide the requested core maps for the next cycle for each unit when available. New NRC commitments contained in Attachment 2 are those statements which are italicized.
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m USNRC NORTHERN STATES POWER COMPANY April 8,1996 Page 2 Please contact Jack Leveille (612-388-1121, Ext. 4662) if you have any questions related to this letter.
b hY Michael D Wadley Plant Manager Prairie Island Nuclear Generating Plant c:
Regional Administrator - Region Ill, NRC Senior Resident inspector, NRC NRR Project Manager, NRC J E Silberg Attachments:
1.
Affidavit 2.
Response to Bulletin 96-01, Control Rod Insertion Problems 3.
Core Maps of Rodded Fuel Assemblies l
l l
l B96-01 0. DOC
l UNITED STATES NUCLEAR REGULATORY COMMISSION l
NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT DOCKET NO. 50-282 50-306 BULLETIN 96-01: CONTROL ROD INSERTION PROBLEMS Northem States Power Company, a Minnesota corporation, with this letter is submitting information requested by NRC Bulletin 96-01.
This letter contains no restricted or other defense information.
NORTHERN STATES POWER COMPANY BY #lE sdbN Michael D Wadley g*
Plant Manager v
Prairie Island Nuclear Generating Plant h
On this day of NN before me a notary public in and for said County, personally appearep Michael D Wadley, Flant Manager, Prairie Island Nuclear Generating Plant; and being first duty sworn acknowledged that he is authorized to execute this document on behalf of Northem States Power Company, that he knows the contents thereof, and that to the best of his knowledge, information, and belief statements ma e in it are true and that it is not interposed for delay.
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MARCIA K. LaCORE NOTARY PUBUC WINNt90TA i}
HENNEPIN COUNTY 4% Commission EreesJan.31,t000 e::.: " :::::::::::::::::::::::::::
I r
i RESPONSE TO BULLETIN 96-01, CONTROL ROD INSERTION PROBLEMS i
Requested Action (1):
l (1)
Promptly inform operators of recent events (reactor trips and testing) in which control rods did not fully insert and subsequently provide necessary training, including simulator drills, utilizing the required procedures for responding to an event in which the control rods do not fully insert upcn reactor trip (e.g., boration of a pre-specified amount).
I l
Response to Requested Action (1):
}
Northern States Power, Prairie Island is meeting the intent of Requested Action (1) from NRC Bulletin 96-01as follows:
i i
Northern States Power, Prairie Island operators and management were promptly
)
notified of the Wolf Creek event on 2/12/96 using information from the NRC press release concerning the event. The procedural requirements to borate should two or more rods fail to fully insert was emphasized.Bulletin 96-01 was issued 3/8/96. Follow-4 j
up communication with the additional information contained in this bulletin was j
transmitted to the operators on 3/15/96.
Simulator training of Operations crews began on 3/12/96. The simulator scenario is designed to require the operators to enter the procedure having the requirements to i
borate should two or more rods fail to fully insert. Critiques will be held after the I
simulator training. The crews will receive the simulator training during their regular
~
training cycle. This training will be complete by 5/24/96.
l Requested Action (2):
(2)
Promptly determine the continued operability of control rods based on current information. As new information becomes available from plant rod drop tests and trips, licensees should consider this new information 1
together with data already available from Wolf Creek, South Texas, North Anna, and other industry experience, and make a prompt determination of control rod operability.
Response to Requested Action (2):
Northern States Power, Prairie Island is meeting the intent of Requested Action (2) from NRC Bulletin 96-01as follows.
On March 15,1996 the Prairia Island Operations Committee determined that control rods for Units 1 and 2 were operable. The operabilitiy determination was based on the following information:
s Attichment 2 Page 2 of 4
- 1) Prairie Island standard practice is to trip rods in and verify that they trip in during a shutdown for refueling. A review of rod trip information from 1990 to 3/15/96, from both planned and unplanned trips from both units combined, shows that a total of 52 rod-trips into fuel elements having a burnup of greater than 40,000 MWD /MTU have occurred. Two of these rod-trips were in fuel elements having
}
greater than 50,000 MWD /MTU. According to control board instrumentation, all of these rod-trips were normal. The control rod insertion problems observed in the industry to date have only occurred in rodded fuel assemblies having l
burnups of greater that 42,000 MWD /MTU.
- 2) Results of drag tests on RCCAs after latching following refuelings from 1990 to 3/15/96 have met their acceptance criteria.
l
- 3) Rod drop timing traces at beginning of core life show normal rod recoil and acceptable rod drop times for all rods for the current cycles for both units.
l
- 4) The periodic surveillance procedures SP1047 and SP2047, " Control Rod l
ExerciseTest", have been performed satisfactorily.
- 5) Westinghouse has performed safety assessments on a large number of plants that show that the amount of uninserted worth associated with observed control rod insertion problems to date is small compared to the design basis assumption of the most reactive rod stuck out.
l On April 8,1996 the Prairie Island Operations Committee again determined that the control rods for Units 1 and 2 were operable. This operabilitiy determination included all of the items considered for the operability determination of March 15,1996 as well as i
the following additionalitems:
- 1) Information obtained from the Prairie Island Unit 2 trip of 3/19/96 was assessed on 3/19/96. This asessment showed that rods inserted normally.
- 2) Rod drop timing tests were performed after the 3/19/96 Unit 2 reactor trip.
This testing showed that all rods had acceptable rod drop times and normal l
recoil. Only one rod was in a fuel element having an exposure of greater l
than 40,000 MDW/MTU. This rod drop timing information will be submitted to the NRC in accordance with reporting requirements of Bulletin 96-01in a separate report to be submitted by 4/18/96.
l
- 3) At the end of the current Unit 1 core cycle (18), Unit 1 will have five rodded fuel elements with burnups greater than 50,000 MWD /MTU and no other l
rodded elements with burnup greater than 40,000 MWD /MT. At the end of the current Unit 2 core cycle (17), Unit 2 will have thirteen rodded fuel i
I
Page 3 of 4 elements with burnups between 47,000 and 51,000 WD/MTU and no other rodded elements with burnup greater than 40,000 MWD /MTU.
Shutdown margin analysis for Unit 2 end of life burnups show that even with 11 of the rods in elements having greater than 40,000 MWD /MT burnup stuck at 20 steps withdrawn and 2 rods stuck at 30 steps withdrawn, that the amount of uninserted worth associated with the postulated control rod insertion problem is small compared to the design basis assumption of the most reactive rod stuck out.
Northem States Power, Prairie Island will continue to monitor the industry for additional information related to this issue thmugh the Westinghouse Owners Group and other generic communications. Our determinations that controlrods are operable will be assessed as such applicable additionalinformation is received.
l Requested Actions (3) and (4):
(3)
Measure and evaluate at each outage of sufficient duration during calendar year 1996 (and of cycle, maintenance, etc.), the control rod drop times and rod recoil data for all control rods. If appropriate plant conditions exist l
where the vessel head is removed, measure and evaluate drag forces for l
all rodded fuel assemblies.
i a.
Rods failing to meet the rod drop time in the technical specifications shall be deemed inoperable.
l l
b.
Rods falling to bottom or exhibiting high drag forces shall require prompt corrective action in accordance with Appendix B to Part 50 of Title 10 of the Code of Federal Regulations (10 CFR Part 50).
(4)
For each reactor trip during calendar year 1996, verify that all control rods have promptly fully inserted (bottomed) and obtain other available l
Information to assess the operability and any performance trend of the i
rods. In the event that all rods do not fully insert promptly, conduct tests to measure and evaluate rod drop times and rod recoil, i
Response to Requested Actions (3) and (4):
Northem States Power, Prairie Island plans to meet the intent of Requested Actions (3) and (4) from NRC Bulletin 96-01. This will be accomplished by following the actions described in Requested Actions (3) and (4) until such time as Westinghouse and the Westinghouse Owners Group have identified the appropriate data required to support a root cause determination. Northem States Power, Prairie Island willprovide an update of our Bulletin 96-01 response if ourplans forimplementing Requested Actions (3) and l
l
Atttchment 2 Page 4 of 4 1
(4) are modified to support the collection of appropriate data for the root cause
\\
determination. An outage of sufficient duration is an outage that allows time to properly set up and test the rods by established plant procedures without restraining a plant restart.
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Core Maps of Rodded Fuel Assemblies I
Prairie Island Nuclear Generating Plant April 8,1996 1
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3 1
0 3
2 1
1 1
V V
4 6
7 1
3 2
3 1
V U
V 0
9 n
0 3
2 s
e 1
n e
V V
o t
it h
a ig c
8 3
o E
3 3
L 9
e V
V e
lc r
y o
C 4
6 5
9 C
1 2
2 0
d e
8 V
V V
V e
n d
O d
t o
in 7
3 5
R 2
2 2
U 7
t d
U P
U a
n s
a e
ls 1
7 8
6 i
lb I
6 1
2 2
1 m
e V
V V
V e
ir s
ia s
rP 5
0 A
5 3-4-
V V
1 2
3 3
V 9
8 6
3 3
2 3
V U
V 5
2 1
1 2
V V
1 A
B C
D E
F G
H i
J K
L M
!llll!llI1
Unit One Cycle Eighteen Guide Tube Inner Number of
- Diameter, Grid Grid Average Number of Initial Instrument Guide Guide Upper Number of
- Material, Material, initial Fuel Gad Pins Gadolne Fuel Tube Tubes per Tube Region Grids per End Two Middle 5 Enrichment Pellet per Gad Pelet Ew Jsst Clad Assemby Fuel Type Material Assemby Material (Inches)
Assemby Grids Grids (w/o23sU)
Material Assembly Material (w/o Gd 0 )
Material 23 P-23 W OFA Zr-4 16 Zr-4 0.490 7
inconel Zr-4 3.49 UO 8
Gd 0rUO2 4.0 Zr-4 2
2 U-25 W VANTAGE +
ZlRLO 16 ZlRLO 0.492 7
inconel Zr-4 4.87 UO 8
Gd 0rUO2 6.0 ZlRLO 2
2 U-26 W VANTAGE +
ZlRLO 16 ZlRLO 0.492 7
inconel Zr-4 4.87 UO 8
Gd 0rUO2 6.0 2.lRLO 2
2 U-27 W VANTAGE +
ZlRLO 16 Z!RLO 0.492 7
inconel Zr-4 4.87 U0 8
Gd 0rU02 6.0 ZlRLO 2
2 U-28 W VANTAGE +
ZlRLO 16 ZIRLO 0.492 7
inconel Zr-4 4.87 UO 8
Gd 0rUO2 6.0 ZlRLO 2
2 V-09 W VANTAGE +
ZlRLO 16 ZlRLO 0.492 7
inconel Zr-4 4.91 00 4
8.0 ZlRLO Gd 0rU02 2
2 V-10 W VANTAGE +
ZlRLO 16 ZlRLO 0.492 7
inconel Zr-4 4.91 UO2 4
Gd 0rUO2 8.0 ZlRLO 2
V-11 W VANTAGE +
ZlRLO 16 ZlRLO 0.492 7
inconel Zr-4 4.91 UO2 4
Gd0rUO2 8.0 ZlRLO 2
V-12 W VANTAGE +
ZlRLO 16 ZlRLO 0.492 7
inconel Zr-4 4.91 UO2 4
Gd 0rUO2 8.0 ZlRLO 2
V-13 W VANTAGE +
ZlRLO 16 ZlRLO 0.492 7
inconel Zr-4 4.91 UO2 4
Gd 0rUO2 8.0 ZlRLO 2
V-14 W VANTAGE +
ZlRLO 16 ZlRLO 0.492 7
inconel Zr-4 4.91 UO2 4
Gd 0rV02 8.0 ZlRLO 2
V-15 W VANTAGE +
ZlRLO 16 ZlRLO 0.492 7
inconel Zr-4 4.91 UO 4
Gd 0rUO2 8.0 ZlRLO 2
2 V-16 W VANTAGE +
ZlRLO 16 ZlRLO 0.492 7
inconel Zr-4 4.91 UO2 4
Gd 0rUO2 8.0 ZlRLO 2
V-25 W VANTAGE +
ZlRLO 16 ZlRLO 0.492 7
inconel Zr-4 4.83 UO 2
12 Gd 0rUO2 8.0 ZlRLO 2
V-26 W VANTAGE +
ZlRLO 16 ZlRLO 0.492 7
inconel Zr4 4.83 U0 12 Gd 0rUO2 8.0 ZIRLO 2
2 V-27 W VANTAGE +
ZlRLO 16 ZIRLO 0.492 7
Inconel Zr-4 4.83 UO 12 Gd 0rUO2 8.0 ZlRLO 2
2 V-28 W VANTAGE +. ZlRLO 16 ZlRLO 0.492 7
inconel Zr-4 4.83 UO2 12 Gd 0rV02 8.0 ZlRLO 2
V-29 W VANTAGE +
ZlRLO 16 ZlRLO 0.492 7
inconel Zr-4 4.79 UO2 16 Gd 0rUO2 8.0 ZlRLO 2
V-30 W VANTAGE +
ZlRLO is ZlRLO 0.492 7
inconel Zr-4 4.79 UO2 16 8.0 ZlRLO Gd 0rUO2 2
V-31 W VANTAGE +
ZlRLO 16 ZlRLO 0.492 7
inconel Zr-4 4.79 UO2 16 Gd 0rUO2 8.0 ZlRLO 2
V-32 W VANTAGE +
ZlRLO 16 ZlRLO 0.492 7
inconel Zr-4 4.79 UO 16 Gd 0rUO2 8.0 ZlRLO 2
2 V-33 W VANTAGE +
ZlRLO 16 ZlRLO 0.492 7
inconel Zr-4 4.79 UO2 16 Gd 0rUO2 8.0 ZlRLO 2
V-34 W VANTAGE +
ZlRLO 16 ZlRLO 0.492 7
inconel Zr-4 4.79 UO2 16 Gd 0rUO2 8.0 ZlRLO 2
V-35 W VANTAGE +
ZlRLO 16 ZlRLO 0.492 7
nconel Zr-4 4.79 UO Gd 0rUO2 8.0 ZlRLO 2
16 2
V-36 W VANTAGE +
ZlRLO 16 ZlRLO 0.492 7
inconel Zr-4 4.79 UO 16 Gd0rUO2 8.0 ZlRLO 2
2 V-37 W VANTAGE +
ZlRLO 16 ZlRLO 0.492 7
inconel Zr-4 4.79 UO2 16 Gd 0rUO2 8.0 ZlRLO 2
V-38 W VANTAGE +
ZlRLO 16 ZlRLO 0.492 7
inconel Zr-4 4.79 UO 16 Gd 0rV02 8.0 ZlRLO 2
2 V-39 W VANTAGE +
ZlRLO 16 ZlRLO 0.492 7
inconel Zr-4 4.79 UO2 16 Gd 0rUO2 8.0 ZIRLO 2
V-40 W VANTAGE +
ZlRLO 16 ZlRLO 0.492 7
inconel Zr-4 4.79 UO 16 8.0 ZlRLO Gd 0rV02 2
2 Fuel Asserrby Data
- - ~
1 i
j i
Unit Ons Cyclo Eighteen Burnup At Projected Control BOC Timing EOC Fuel Rod Bank Test Exposure Assembly Core Location Control Rod Group (MWD /MTU)
(MWD /MTU)
P-23 G07 R-119 C2 36215 52660 U-25 K07 R-105 D1 26757 50260 U-26 G11 R-106 D1 26724 50260 U-27 C07 R-112 D1 25836 50260 i
U-28 G03 R-126 D1 25969 50260 V-09
-LO8 R-104 A2 0
25240 V-10 F12 R-110 A2 0
25240 V-11 B06 R-101 A2 0
25240 V-12 H02 R-102 A2 0
25240 V-13 H12 R-124 A1 0
25240 V-14 B08 R-111 A1 0
25240 V-15 F02 R-108 A1 0
25240 V-16 LO6~
R-115 A1 0
25240 V-25 H08 R-113 B1 0
30560 V-26 F08 R-103 B1 0
30560 V-27 F06 R-114 B1 0
30560 V-28 H06 R-107 B1 0
30560 V-29 J10 R-109 C2 0
28630 V-30 D10 R-125 C1 0
28630 V-31 D04 R-117 C2 0
28630 V-32 J04 R-122 C1 0
28630 V-33 K09 R-128 S.B1 0
28630 V-34 E11 R-129 S.81 0
28630 i
V-35 C05 R-123 S.81 0
28630 V-36
_ 10 3 R-127 S.81 0
28630 V-37 11 1 R-121 S.A1 0
28630 V-38 C09 R-120 S.A2 0
28630 V-39 E03 R-116 S.A1 0
28630 V-40 K05 R-118 S.A2 0
28630 Fuel Burnup Data
rt' l
,iti 3
1 7
0 2
6 7-1
-U U
1 9
4 1
9 6
9 1
U T-U n
3 4
e 0
5 5
sn T-T-
e 1
n i
o t
t e
a v
5 0
c e
S 9
9 9
o L
e U
U e
r l
o c
y C
1 2
5 6
C 8
7 8
8 4
d o
w U
T T-U e
d T
do t
i 7
2 6
R nU 7
6 2
6 t
T-P T-a d
n sie a
8 3
4 3
b l
ls I
6 6
8 8
7-m i
U T-T U
e e
r s
i s
a P
2 7
A r
5 9
9 U
U 1
6 4
5 5
T-T 6
8 3
9 6
9 3
U T-U 2
9 2
7 6
U U
1 y
B C
D E
F G
H i
J K
L M
Unit Two Cycle Seventeen Guide Tube inner Number of
- Diameter, Grid -
Grid Average Number of inlumi instrument Guide Guide Upper Number of
- Motonal, Motonal, inilial God Pir's thdnerum Fuel Tube Tubes por Tube Region Grida per End Two Mides 5 Ennchment Fuel PeHet per God Petet C..J. a Clad
]
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Fuel Type Motonal Assembly Metenal (inches)
Assomt%
Grids Gnds (vdeam )
Motonal Aseemth Motonal (wdb Gd 0 )
Motonal U
22 Gd 0rU02 4.0 Zr-4 P-22 W OFA Zr-4 16 Zr-4 0.490 7
incW Zr-4 3.49 UOr 8
2 T-51 W VANTAGE +
ZlRLO 16 ZlRLO 0.492 7
incanal Zr-4 4.88 U02 4
Gd 0 UOr 6.0 ZRLO 22 T-53 W VANTAGE +
ZlRLO 16 ZlRLO 0.492 7
incenel Zr-4 4.88 UOr 4
Gd 0rU02 6.0 ZRLO 2
Gd OrU02 6.0 -
ZlRLO T-54 W VANTAGE +
ZRLO 16 ZlRLO 0.492 7
inconal Zr-4 4.88 UOr 4
2 ZlRLO 16 ZlRLO 0.492 7
inconel Zr-4 4.88 UOr 4
Gd 0rUOr 6.0 ZlRLO T-56 W VANTAGE +
2 T-66 W VANTAGE +
ZlRLO 16 ZlRLO 0.492 7
inconel Zr-4 4.84 UOr 8
Gd 0rU02 6.0 ZlRLO 2
T-67 W VANTAGE +
ZlRLO 16 ZlRLO 0.492 7
inconal Zr-4 4.84 UOr 8
Gd 0rUOr 6.0 ZlRLO 2
T-68 W VANTAGE +
ZlRLO 16 ZlRLO 0.492 7
inconal Zr-4 4.84 UOr 8
Gd 0rV02 6.0 ZlRLO 2
T-69 W VANTAGE +
ZlRLO 16 ZlRLO 0.492 7
inconal Zr-4 4.84 UOr 8
Gd 0rU02 6.0 ZRLO 2
T-82 W VANTAGE +
ZlRLO 16 ZlRLO 0.492 7
inconal Zr-4 4.80 U0 12 Gd 0rUOr 6.0 ZRLO 2
6.0 ZRLO T-83 W VANTAGE +
ZRLO 16 ZlRLO 0.492 7
inconal Zr-4 4.80 U02 12 Gd OrUor 2
Gd 0rUOr 6.0 ZRLO T-s4 W VANTAGE +
ZlRLO 16 ZlRLO 0.492 7
inconal Zr-4 4.80 UOr 12 2
Gd OrUOr 6.0 ZlRLO T-85 W VANTAGE +
ZRLO 16 ZlRLO 0.492 7
inconal Zr-4 4.80 U02 12 2
U-86 W VANTAGE +
ZlRLO 16 ZlRLO 0.492 7
inconal Zr-4 4.87 U02 8
Gd 0rUOr 8.0 ZRLO 2
U-67 W VANTAGE +
ZRLO 16 ZlRLO 0.492 7
incanal Zr-4 4.87 UOr 8'
Gd 0 -UOr 8.0 ZlRLO 22 8.0 ZRLO 4
U-e8 W VANTAGE +
ZlRLO 16 ZlRLO 0.492 7
inconal Zr-4 4.87 UOr 8
Gd 0rV02 2
U-69 W VANTAGE +
ZlRLO 16 ZlRLO 0.492 7
inconal Zr-4 4.87 U0 Gd 0rU02 8.0 ZRLO 2
8 2
U-70 W VANTAGE +
ZlRLO 16 ZlRLO 0.492 7
inconal Zr-4 4.87 UOr 8
Gd OrU02 8.0 ZIRLO 2
U-71 W VANTAGE +
ZlRLO 16 ZlRLO 0.492 7
inconal Zr-4 4.87 UOr 8
Gd 0r002 8.0 ZRLO 2
Gd 0 UOr 8.0 ZlRLO U-72 W VANTAGE +
ZlRLO 16 ZlRLO 0.492 7
inconel Zr-4 4.87 U0r 8
27 Gd 0rU02 8.0 ZIRLO U-73 W VANTAGE +
ZlRLO 16 ZlRLO 0.492 7
Inconal Zr-4 4.87 U02 8
2 Gd 0rUOr 8.0 ZlRLO i
U-90 W VANTAGE +
ZlRLO 16 ZlRLO 0.492 7
inconal Zr-4 4.76 U02 20 2
U-91 W VANTAGE +
ZlRLO 16 ZlRLO 0.492 7
inconel Zr-4 4.76 UOr 20 Gd 0rV02 8.0 ZlRLO 2
8.0 ZlRLO U-92 W VANTAGE +
ZlRLO 16 ZlRLO 0.492 7
inconal Zr-4 4.76 UOr 20 Gd 0rU02 2
U-93 W VANTAGE +
ZlRLO 16 ZlRLO 0.492 7
inconel Zr-4 4.76 U02 20 Gd 0rU02 8.0 ZlRLO 2
U-94 W VANTAGE +
ZlRLO 1S ZlRLO 0.492 7
incenal Zr-4 4.76 U0 20 Gd 0rUOr 8.0 Z!RLO 2
2 U-95 W VANTAGE +
ZIRLO 16 ZlRLO 0.492 7
inconal Zr-4 4.76 UOr 20 Gd 0rU02 8.0 ZlRLO 2
U-96 W VANTAGE +
ZlRLO 16 ZlRLO 0.492 7
inconal Zr-4 4.76 U02 20 Gd 0r002 8.0 ZlRLO 2
Gd Or002 8.0 ZlRLO U-97 W VANTAGE +
ZlRLO 16 ZlRLO 0.492 7
inconal Zr-4 4.76 UOr 20 2
t Fuel Aseembly Date
.~
Unit Two Cycle Ssvantun l
l l
I Control Burnup At Projected L
Rod BOC Timing Burnup on EOC l
. Fuel Core Control Bank Test 2/29/95 Exposure i
Assembly Location Rod Group (MWD /MTU) (MWD /MTU) (MWD /MTU)
P-22 G07 R-148 C2 35775 41776 50490 T-51 D04 R-132 C2 23749 34301 47340 l
T-53 D10 R-147 C1 24097 34762 47340 l
T-54 J10 R-138 C2 24222 34899 47340 l
T-56 J04 R-141 C1 24020 34788 47340 l
T46 K07 R-158 D1 24381 35656 49020 T-67 C07 R-152 D1 24453 35677 49020 T-68 G03 R-151 D1 24387 35642 49020 l
T-69 G11 R-150 D1 25120 36395 49020 T-82 F08 R-145 B1 27669 37392 50100 T-83 F06 R-157 B1 27895 37828 50100 T-84 H06 R-134 B1 27960 37763 50100 l
T-85 H08 R-142 B1 27611 37372 50100 U46 LO8 R-131 A2 0
11243 25720 l
U-67 F12 R-154 A2 0
11501 25720 U48 B06 R-136 A2 0
11091 25720 U-69 H02 R-139 A2 0
11013 25720 i
U-70 H12 R-143 A1 0
11443 25720 l
U-71 B08 R-135 A1 0
10943 25720 U-72 F02 R-156 A1 0
11084 25720 U-73 LO6 R-153 A1 0
11292 25720 U-90 K09 R-144 S.B1 0
11829 28070 U-91 E11 R-137 S.B1 0
11924 28070 U-92 C05 R-140 S.B1 0
11788 28070 U-93 10 3 R-133 S.B1 0
11820 28070 U-94 11 1 R-155 S.A1 0
11991 28070 U-95 C09 R-146 S.A2 0
11876 28070 l
U-96 E03 R-149 S.A1 0
11655 28070 l
U-97 K05 R-159 S.A2 0
11828 28070 I
l l
l Fuel Burnup Data l
l
--.-.