ML20101N088
| ML20101N088 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, Catawba, McGuire  |
| Issue date: | 04/04/1996 |
| From: | Tuckman M DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| IEB-96-001, IEB-96-1, NUDOCS 9604080230 | |
| Download: ML20101N088 (25) | |
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fo' ogg Se or President NuclearGeneration 0\arlotte,NC282014006 (704)M22200 OWice (704)382436CFax DUKEPOWER April 4, 1996 U. S. Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Duke Power Company McGuire Nuclear Station - Units 1 and 2 Docket Nos. 50-369 and 50-370 Catawba Nuclear Station - Units 1 and 2 Docket Mos. 50-413 and 50-414 Response to NRC Bulletin 96-01 NRC Bulletin 96-01, dated March 8, 1996, requested holders of operating licenses for Westinghouse-designed plants to
) take actions and supply information to the NRC regarding recent control rod insertion problems. The Duke Power response to NRC Bulletin 96-01 is itemized in the following i paragraphs.
l Required Response Item (1).
(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 Actions (3) and (4).
Requested Action (1)
(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 upon reactor trip (e.g., boration of a pre-specified amount).
G900M9 9604080230 960404 l PDR ADOCK 05000369 G PDR i y
U..S. NRC, Document Control Desk
April 4, 1996 Page 2 Response to Requested Action (1):
Operations management at McGuire and Catawba have advised the plants' licensed operators of the industry events described in NRC Bulletin 96-01. This advisement was made using the weekly Operations Team Notes at McGuire. Each McGuire licensed operator received the information directly through the electronic mail system. At Catawba, the advisement was made by including an operator update in a required reading package distributed to all licensed
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operators. The update process informed the licensed operators of the industry events referenced in the bulletin and detailed the expected procedural response.
The operator simulator training programs at McGuire and Catawba have been reviewed in response to the issuance of NRC Bulletin 96-01. At McGuire, it has been determined that the current training being given to the plant operators on a continuing basis adequately covers the control rod insertion problems addressed by the bulletin. This determination was made because the cyclic simulator training program in place at McGuire already contained stuck rod scenarios. The McGuire training is administered to the licensed operators during the biannual / annual evolutions on the simulator and during the normal requalification training cycles.
At Catawba, a special simulator training session has been developed to address the issues covered by NRC Bulletin 96-
- 01. This training covers the expected operator response in the event there is a failure of control rods to fully insert on a reactor trip. The training will be administered to the plant operators during the next cycle of requalification training. The simulator training at both plants includes the use of applicable station procedures.
Duke has ensured that the applicable station procedures at McGuire and Catawba adequately address the issues identified in NRC Bulletin 96-01. At McGuire and Catawba, Reactor Trip Response Procedure EP/1/A/5000/ES-0.1 contains the required action for the plants' licensed operators to tako (including appropriate boration) in the event that all control rods are not fully inserted.
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U..S. NRC, Document Control Desk
April 4, 1996 Page 3 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 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):
Duke has determined that the control rods at McGuire and Catawba are operable. The operability determinations were performed and documented using the normal Duke processes (NSD 208, Problem Investigation Process (PIP); and NSD 203, Operability). PIPS were used to document and track actions taken on the operability evaluation ascociated with this bulletin. McGuire PIP M96-0657 and Catawba PIP C96-0662 were initiated. Considerations used in the determination of operability are discussed in the following paragraphs.
Beginning-of-cycle rod drop times and drag testing results were reviewed for the last five years of operation. All acceptance criteria were met for this testing and no adverse trends were noted. All rod drop times were well within the Technical Specifications limits. Also, every control rod that has been measured has exhibited the rod recoil effect on the rod timing traces.
Results from reactor trip evaluations were also reviewed for the past five years of operation. There were no cases of slow or sticking Rod Cluster Control Assemblies (RCCA) for any of the reactor trips that were reviewed.
Control rod operability is also verified once every 31 days by movement of at least ten steps in any one direction. No '
anomalies indicating a stuck or slow rod have been observed during the performance of these tests.
In addition to the normal operability evaluations documented in the referenced PIPS, a separate analysis was conducted by l the Nuclear Design and Reactor Support Section which evaluated the impact on shutdown margin for the current ;
operating cycles, assuming that RCCAs in fuel assemblies g with >45,000 MWD /MTU burnup stick at the dashpot. This j analysis confirmed that the required shutdown margin is 1 maintained even if these RCCAs stick at the dashpot. The Duke calculation file number that documents this analysis is DPC-1553.05-00-0130.
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U..S. NRC, Document Control Desk April 4, 1996 Page 4 In response to a previous Westinghouse Owners Group (WOG) request, Duke conducted a review of data beyond five years.
Three occurrences of RCCA incidents were found that are deemed to merit some discussion. These three cases involved Westinghouse Optimized Fuel assemblies.
Trip information from this period identified two cases at Catawba, one in 1987 and one in 1989, where there were indications that a RCCA did not fully insert. In 1987, following a Unit 2 reactor trip, core location H-2, which had an approximate burnup of 4000 MWD /MTU, indicated 44 steps withdrawn on the Digital Rod Position Indication (DRPI). In 1989, following a reactor trip on Unit 1, core location D-8, with a burnup of approximately 20,880 MWD /MTU, indicated 6 steps withdrawn on DRPI. Both of these cases at Catawba were felt to be problems with the rod position indication electronics. No other problems with the RCCAs were experienced.
At McGuire in 1990, during the RCCA component shuffle at the -
end of McGuire 2 Cycle 6, it was observed that a RCCA would not insert the final 8 inches into assembly S18. This assembly was a Westinghouse Optimized Fuel Assembly which ,
had operated two fuel cycles and had a burnup of 24,500 0 MWD /MTU. B&W Fuel Company personnel were on site for this outage and an investigation was conducted. Fuel assembly bow was found to be approximately 1/4 inch, which was considered normal. Additionally, all guide tubes were probed individually and none were found to be blocked. The RCCA was placed into another fuel assembly without problem i and another RCCA was tried in S18 and it also stopped at the i same elevation. Since no definite cause or correction could be identified for this problem and no other damage was evident, the core was redesigned to. place this assembly into a non-rodded location for the next cycle. It was then discharged at the end of that cycle and now resides in the McGuire spent fuel pool.
During the last five years, Duke has converted to Mark BW fuel manufactured by Framatome Cogema Fuel (formerly B&W Nuclear). Currently, operating cores are composed of all Framatome Cogema Fuel (FCF) Mark BW fuel. No cases of sticking or slow RCCAs have ever been identified with the Mark BW fuel.
l U. 5. NRC, Document Control Desk
April 4, 1996 Page 5 Requested Action (3):
(3) Measure and evaluate at each outage of sufficient duration during calendar year 1996 (end of cycle, l maintenance, etc.), the control rod drop times and rod recoil data for all control rods. If appropriate plant I conditions exist where the vessel head is removed, measure and evaluate drag forces for all rodded fuel assemblies.
- a. Rods failing to meet the rod drop time in technical specifications shall be deemed inoperable.
- b. Rods failing 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). i Response to Requested Action (3):
Requested action 3 requests that licensees measure and evaluate at each outage of sufficient duration during calendar year 1996 the control rod drop times and recoil data for all RCCAs. Also, if appropriate conditions exist where the vessel head is removed, measure and evaluate drag forces for all control rod assemblies, etc.
Duke Power will comply with this requested action. The first scheduled outage of 1996 is McGuire 2 End-of-Cycle (EOC) 10, currently scheduled to begin April 5, 1996. McGuire 2 Cycle 10 also contains the lead (or highest) burnup fuel of any current core. The center fuel assembly (which is a rodded location) burnup at EOC is expected to be 52,600 MWD /MTU and several other assemblies will have burnup >45,000 MWD /MTU.
Current plans are to perform the rod drop timing / recoil ;
tests during shutdown, and drag tests prior to core offload.
These tests will also be repeated with the new core in accordance with routine surveillance testing. Recoil data will also be collected and reviewed. The only other currently scheduled outage for the Duke Westinghouse units in 1996 is Catawba 1 EOC 9, scheduled for June 13, 1996.
Duke will also perform the requested testing for this outage. The testing will be performed in accordance with the requirements of each station's Technical Specifications, and rods failing to meet the specified drop times will be deemed inoperable. Appropriate corrective actions will be taken for rods that fail the tests.
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U.'S. NRC, Document Control Desk April 4, 1996 Page 6 For nonscheduled outages occurring during 1996, Duke will perform the requested testing if the anticipated outage duration (return to Mode 2) is greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. This 72-hour period will allow time to make arrangements for vendors and test equipment to arrive on site if needed.
Also, Duke does not plan to repeat the testing if it has been previously performed on the same unit within the last 62 Effective Full Power Days. This time frame is considered to be conservatively within the guidance of 2500 MWD /MTU provided by the WOG, and accounts for a burnup increment of approximately 2,000 MND/MTU.
Requested Action (4):
(4) For each reactor trip during the calendar year 1996, verify that all control rods have promptly fully inserted (bottomed) and obtain other available information to assess the operability and any performance trend of the rods. In the event that all rods do not fully insert promptly, conduct tests to measure and evaluate rod drop times and rod recoil.
Response to Requested Action (4):
As stated in this requested action, for each reactor trip experienced at McGuire or Catawba during the remainder of
) the 1996 calendar year, Duke will verify that all control rods have promptly fully inserted (bottomed) and obtain other available information to assess the operability and performance trend of the rods. In the event that all rods do not fully insert promptly, Duke will conduct appropriate testing to measure and evaluate rod drop times and rod recoil.
4 Required Response Item (2):
(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 cycle; when available, provide the same information for the next cycle.
Response to Item (2):
Attachment 1 to this letter provides the requested information for McGuire 1, Cycle 11; McGuire 2, Cycles 10 and 11; Catawba 1, Cycles 9 and 10; and Catawba 2, Cycle 8.
Duke will also provide the requested information on McGuire 1, Cycle 12 and Catawba 2, Cycle 9. This information will
U..S. NRC, Document Control Desk
April 4, 1996 Page 7 be submitted to the NRC within 30 days of the completion of the design of these cycles. It should be noted that all fuel currently in the reactors is manufactured by FCF.
Additionally, all future fuel through 1999 is expected to be Mark BW fuel manufactured by FCF.
I Required Response Item (3):
(3) Within 30 days after completing Requested Action (3) l for each outage, a report that summarizes the data and that documents the results obtained; this is also applicable to Requested Action (4) when any abnormal rod behavior is observed.
Response to Item (3):
As requested in NRC Bulletin 96-01, a summary report of the data obtained for Requested Actions (3) and.(4) (EOC rod drop times, recoil data, and drag force data if appropriate) will be submitted within 30 days of completing the testing.
These reports will be submitted for outages of sufficient '
duration, and reactor trips when applicable, that occur at McGuire and Catawba during the remainder of calendar year 1996. During 1996 Duke experienced two reactor trips at these stations prior to the issuance of NRC Bulletin 96-01 (McGuire 1 on 2/3/96 and Catawba 2 with a Loss-of-Offsite Power (LOOP) event on 2/6/96). Duke does not plan to submit reports, as requested in Item 3, for these two reactor trips. For the 2/3/96 McGuire event, all post-trip plant indications were normal. For the 2/6/96 Catawba event, the rod position indicatica was lost due to the LOOP, which agrees with current de** . and regulatory requirements.
When power was restored to the DRPI system, all rods '
indicated fully inserted.
f Please direct questions on this matter to J. S. Warren at (704) 382-4986.
I declare, under penalty of perjury, that the statements set forth herein are true and correct to the best of my knowledge.
Very truly yours, ,
f pk l M. S. Tuckman ,
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1 U. S. NRC, Document Control Desk l April 4, 1996
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MST/JSW ,
ATTACHMENT 1: Information for NRC B 111etin 96-01 l Required Response Ite n 2 (17 Pages) xc: S. D. Ebneter, Regional Administrator U.S. Nuclear Regulatory Commission, Region II R. E. Martin, NRC Project Manager (CNS)
V. Nerses, NRC Project Manager (MNS)
ONRR R. J. Freudenberger, NRC Resident Inspector (CNS)
G F. Maxwell, NRC Resident Inspector (MNS)
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ATTACHMENT 1 i
,, Page 1 of 17 Fuel Description McGuire and Catawba Nuclear Stations presently utilize Mk-BW fuel fabricated by Framatome Cogema Fuels, FCF. The fuel assembly mechanical design features are described in Topical Report BAW-10172P," Mark-BW Mechanical Design Report", -
which was approved by the NRC on December 19,1989. The guide tubes, ferrules, and six intermediate spacer grids are made of annealed zircaloy-4. The upper and lower end grids are made of Inconel. The guide tube inner diameter is:
upper region of GT 0.450"ID nominal lower region of GT 0.397"ID nominal
%e Westinghouse fuel assembly structure is somewhat different from the FCF fuel. He Westinghouse fuel structure consists of welding the grids to the guide tubes, whereas, the FCF fuel structure allows the intermediate grids to move axially a small amount early in life as the fuel pins grow. Ferrules limit the axial movement of the grids. Later in life, the
! grip forces on the zircalloy grids relax and the fuel pins can slide through the grid contact areas. The inconel grids are rigidly attached to guide tubes in both fuel assembly designs.
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ATTACHMENT 1 Page 2 of 17 McGuire/ Catawba RCCA Placements H G F E D C B A eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen e e e . . . e e e 00
- Control *
- Control *
- Shutdown *
- Control * *
- D *
- A *
- E *
- c *
- e e e e e e e e e seeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee e e e e e e e e e 09 * * * * *
- Shutdown * * *
- * * * *
- B * *
- e e e e e e e e e seeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee e e e e e e e e e 10
- Control *
- Control * * *
- Control * *
- A *
- C * * *
- B * *
- e e e e e e e e eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee......eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen
. . e e e e e e e 11 * * * * *
- shutdown * * *
- * * * *
- C * *
- e e e e e e e e e ee........................................................... ...................
e e e e e e e e 12
- Shutdown * * *
- Control *
- shutdown *
- E * * *
- D *
- A
- e e e e e e e e eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee e e e e e e e e 13 *
- Dhutdown*
- shutdown * * *
- e e B *
- D * * *
- e e e e e e e e eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeseeeeeeeeeeeeeeeeeeeeene e e . . . . e 14
- Control *
- Control *
- Shutdown *
- RCCA Locations
- C *
- B *
- A *
- e e a e e e e eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee99eeeeeeeeeeeeeeeeeeee e e e e e 15 * -* * *-
- e e e e e ;
e e e e e eeeeeeeeeeeeeeeeeeee4eeeee99ee4eeeeeeeeee
, 1 ATTACHMENT 1 Page 3 of 17 1
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I Current Assembly Burnup Information for Current Cycles GWD/MTU l
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. ATTACHMEMT 1 ;
, . Pa@e 4 of 17 l l
McGuire 1 Cycle 11 Assembly Burnup Distribution 50 EFPD H G P E D C B A 8
- 40.8880
- 2.4660
- 35.6530
- 2.4720
- 26.5880
- 2.3860
- 14.5540
- 1.5230
- 9
- 2.4660
- 32.6120
- 2.5030
- 25.4870
- 2.4150
- 26.5580
- 2.3260
- 25.8320 **
10
- 35.6530
- 2.5040
- 26.5950
- 18.4580
- 25.0440
- 2.3870
- 19.2670
- 18.6840 **
11
- 2.4720
- 25.5020
- 18.4620
- 22.1030
- 2.4520
- 21.5800 = 2.:ri'0
- 20.4720
- 12
- 26.5880
- 2.3980
- 25.0990
- 2.4500
- 21.6570
- 2.1920
- 20.758 * .
13
- 2.3860
- 26.5300
- 2.3810
- 21.5810
- 2.1910
- 34.7370
- 20.4380 *.
14
- 14.5540
- 2.3230
- 19.2640
- 2.1060
- 20.7670
- 20.4470 **
...........................+.................................
15
- 1.5230
- 25.8540
- 18.6830
- 20.4740
- AVG ASSY EXPOSURE E
l AVG ASSY EXPMAXIMUM MAGNITUDE IS 40.8880 AT ASSEMBLY H-08 i
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ATTACHMENT 1 Rage 5 of 17 g McGuire 2 Cycle 10 Assembly Burnup Distribution 400 EFPD H G F E D C B A 8
- 51 8350
- 19.9750
- 47.1130
- 19.9650
- 43.1290
- 30.1370
- 40.0960
- 11.4310 **
9
- 19.9750
- 44.1620
- 20.1460
- 41.0320
- 20.0390
- 36.7040
- 17.1940
- 36.9050 **
10
- 47.1130
- 20.1010
- 47.0740
- 19.6840
- 38.0180
- 19.6190
- 32.1030
- 24.3960 .*
11
- 19.9650
- 40.9950
- 19.5870
- 44.3610
- 20.2070
- 36.5030
- 16.1250
- 26.3670 **
12
- 43.1290
- 20.0290
- 37.9680
- 20.1820
- 36.7650
- 17.5920
- 27.6610 ** ;
l l ***********...e***************..**..********.e..**..*** ..*****..*** .. ,
13
- 30.1370
- 36.6890
- 19.6060
- 36.4910
- 17.5950
- 31.5180
- 24.8130 **
14
- 40.0960
- 17.1720
- 32.1150
- 16.1210
- 27.7010
- 24.8200 **
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15
- 11.4310
- 36.9520
- 24.3690
- 26.2780
- AVG ASSY EXPOSURE
.*....e..**...********.......******** ....
AVG ASSY EXP MAX 1 MUM MAGNITUDE IS 51.8350 AT ASSZMBLY H-08
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ATTACHMENT 1 I
,Page 6 of 17 l 1
1 Catawba 1 Cycle 9 Assembly Burnup Distribution i 350 EPPD ;
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H G F E D C B A
........*** .**.............c.*** .....****......**..*******************.........
8
- 42.6380
- 27.1050
- 40.0540
- 27.8060
- 40.8840
- 17.4210
- 32.8240
- 34.6920 **
9
- 27.1050
- 34.8170
- 17.3E40
- 35.3670
- 17.4520
- 32.6370
- 15.6700
- 27.6110 **
10
- 40.0540
- 17.3710
- 36.0970
- 17.5490
- 35.6780
- 17.1170
- 29.8820
- 9.9740 **
- . ******.........**.......**.e..**.....*******. **. ********.. *** .....
11
- 27.8060
- 35.3450
- 17.5190
- 41.1510
- 17.6190
- 32.4010
- 14.1380
- 31.8690 **
12
- 40.8840
- 17.3750
- 35.6500
- 17.5930
- 35.1260
- 15.2340
- 31.3360 **
13
- 17.4210
- 32.6310
- 17.0840
- 32.3860
- 15.2230
- 29.0090
- 32.4700 ** .
14 = 32.8240
- 15.6450
- 29.8730
- 14.1170
- 31.4780
- 32.4690 **
15
- 34.6920
- 27.6020
- 9.9610
- 31.8990
- AVG ASSY EXPOSURE AVG ASSY EXP MAXIMUM MAGNITUDE IS 42.6380 AT ASSEMBLY H-08 i
ATTACHMENT 1
.Pege 7 of 17 Catawba 2 Cycle 8 Assembly Burnup Distribution 100 EFPD H G F E D C B A 8
- 37.1660
- 4.4860
- 24.1680
- 17.0210
- 25.0320
- 4.6850
- 24.9400
- 31.3110 **
9
- 4.4860
- 25.6200
- 4.6630
- 22.5370
- 4.8100
- 22.1920
- 4.2720
- 21.9570 **
- r 10
- 24.1680
- 4.6840
- 29.0190
- 4.7640
- 25.4800
- 4.7070
- 15.1540
- 2.9290 **
11
- 17.0210
- 22.5500
- 4.7820
- 25.0320
- 4.7930
- 20.2060
- 4.1470
- 27.9190 **
12
- 25.0320
- 4.8100
- 25.5950
- 4.7940
- 24.1530
- 4.30e3
- 23.5380 ** -
f ************************************************.********.*************
13
- 4.6850
- 22.1060
- 4.7070
- 20.2360
- 4.3880
- 24.0960
- 28.1570 **
14
- 24.9400
- 4.2720
- 15.1570
- 4.1470
- 23.5290
- 26.081)
- 15
- 31.3110
- 21.9910
- 2.9280
- 27.9750
- AVG ASSY EXPOSURE AVG ASSY EXP MAXIMUM MAGNITUDE IS 37.1660 AT ASSEMBLY H-08
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ATTACHMENT 1
. P5ge 8 of 17 EOC Assembly Burnup Information for Current Cycles GWD/MTU 1
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ATTACHMENT 1 Page 9 of 17 McGuire 1 Cycle 11 i EOC Assembly Burnup Distribution (GWD/MTU) 358 EFPD H 0 F E D C B A e...............................eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee....... eee e e e e e e e e .
08 *
- 51.8582
- 17.2360
- 47.3734
- 17.7956
- 39.5173
- 17.7144
- 28.2833
- 11.0386
- e e e e e e e e e eseeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeesseeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee
. e e e e . .
09 *
- 17.1912
- 44.8718
- 17.5165
- 38.2565
- 17.6907 *e 39.3924 *e 16.6523 *e 32.7944 *a e e e e e eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee e e e e e e e e e 10 * *
- 47.3348
- 17.5206
- 38.7758
- 31.9141 *e 38.0666 *e 17.5182 *e 31.2740 *e 25.4878 *e e e e e
............................... eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee e e e e e e e e
11 * *
- 17.7907
- 38.2445
- 31.9120
- 35.7637 *. 17.8947 *. 35.0403 *. 14.7672 *. 25.7068 *e e . . e neeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee
. . e e e e e e 12 *
- 39.5164
- 17.5907
- 38.0956
- 17.8828
- 35.4002 e* 15.7795 e* 28.5533 *e e e . . e eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee i
. . e e e e e e 13 *
- 17.7133
- 39.3336
- 17.4921
- 35.0323
- 15.7763 e* 42.0101 e* 24.8226 *e e . . + e
............ eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee i e e e e e e e e e e e e e 14 e
- 28.2840
- 16.6386
- 31.2639
- 14.7583
- 28.5548 e* 24.8291 *e e e . . e eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee e e e e e 15 *
- 11.0387
- 32.8127
- 25.4854
- 25.7051
- Avg Assy Exposure e e e e e eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee4eeeeeeee l
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, ATTACHMENT 1 Rage 10 of 17 McGuire 2 Cycle 10 )
l EOC Assembly Burnup Distribution (GWD/MTU) 1 425 EFPD H G F E D C B A eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee e e e e e e e e e i I
08
- 52.6111
- 21.1750
- 48.0112
- 21.1818
- 44.0690
- 31.0365
- 40.8819
- 12.1396
- e e e e e e e e .
. . . e e e e e e seeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee
. . e e e e e e .
09
- 21.1497
- 45.1194
- 21.3596
- 41.9765
- 21.2610
- 37.5000
- 18.2556 *., 37.3564 e e e e e e e e e e o e e e e e e
................................ee.....eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee
. . e e e e e e e 10
- 47.9964
- 21.3147
- 47.9569
- 20.8975
- 38.9061
- 20.8221 .* 32.8353 e* 24.7978 e*
e . . . . .
e e e e e e e e e
...........eeeeee....... ..........ee.........eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee e e e e e e e e e 11
- 21.1771
- 41.9402
- 20.8018
- 45.3401
- 21.4335
- 37.3254
- 17.1196
- 26.6021 *
. e e e e e e e .
e e . . e e e e e
................ .................................................eeeeeeeeeeeeeee e e e e e e . .
12
- 44.0007
- 21.2524
- 38.8576
- 21.4093
- 37.6147 *e 18.6875 *e 28.2208 *a e e e e e l e e e e
- e e e e eeeeeeeeee...............eeeeeee..............eeeeeeeeeeeeeeeeeeeeeeee. e e e e . . . e e l
13
- 31.0293
- 37.5356
- 20.8099
- 37.3133 *e 18.6889 *e 32.1264 *e 25.0850 *e e . . .
e e e e e e e e seeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee
. . . . e e e 14
- 40.8867
- 18.2324
- 32.8471
- 17.1160
- 28.2581
- 25.0915
- AVG e ASSY EXPOSURE e e e e e e e e e e e e e eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee e e e e e f 15
- 12.1397
- 37.4011
- 24.7713
- 26.5150
- I e e e e e e e e . .
l
......e..ee...e.ee.eeen.eeeeee....eeeeee.
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ATTACHPENT 1
. Pdge 11 of 17 Catawba 1 Cycle 9 EOC Assembly Burnup Distribution (GWD/MTU) 420 EFPD H G F E D C B A eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee.
. . e e . . . e .
08
- 44.7607
- 29.7700
- 42.5493
- 30.6864
- 43.5047
- 20.9004
- 35.2235 e* 36.0004 e*
e e e e e e e e e e e . . . . e eeeeeeeeeeeeeeeeeee...............................................eeeeeeeeeeeeeee e e e e e e e e e 09
- 29.7780
- 37.7935
- 20.7731
- 38.3105
- 20.9672
- 35.5847 e* 18.8098 e* 29.1002 e*
- e e e e e e e e e e e e e e eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee e e e e e e e e e 10
- 42.5494
- 20.7601
- 39.0838
- 21.0792
- 38.8484
- 20.5808 *e 32.3584 *e 12.0283 *e e e e e e e e * * . e e e e e eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeer-eeeeeeeeeeeeeeeeeeeeeeeeeeee e e e e e e e e e 11
- 30.6863
- 30.2629
- 21.0517
- 43.7969
- 21.1217
- 35.0845 *e 16.9076 *e 32.8165 *e e e . . e e
. . e . . e e e e eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee '
e e e e e e e e 12
- 43.5047
- 20.8951
- 38.8189
- 21.0972
- 37.9705
- 18.2348 *e 32.7603 *e e e e e e e l e e e e e e e e eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee ..
. e . . . . e e 13
- 20.9004
- 35.5001
- 20.5590
- 35.0842
- 18.2222
- 30.6986 *. 33.1337 *e e e e e e .
- *
- e e e e e eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeene
. . . . . . e 14
- 35.2235
- 18.7920
- 32.3520
- 16.8887
- 32. 9081
- 33.1194
- AVG e ASSY EXPOSURE e e e e e e e e . . . e e eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeseeeeeeeeeeeee e e e e e 15
- 36.0004
- 29.0898
- 12.0182
- 32.8406
- e e e e .
. e e e 9 eteeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee tte l
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ATTACHMENT 1
. Psge 12 of 17 Catawba 2 Cycle 8 EOC Assembly Burnup Distribution (GWD/MTU) 445 EFPD H G F E D C B A eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee e e e e e e e e e 08 * $0.5090
- 21.6314
- 39.2346
- 32.5349
- 40.4148
- 21.4389
- 37.2951
- 37.5143
- i
. . . . . . . -e e l e .ee...ees.eeee.eeeeeeeeeeeeeeeeee.....eeeeeeeeee.e.eeee...... ..ee...eee.teeeee i e e e e e e e e e 1 I
09
- 21.6253
- 41.0631
- 21.9235
- 37.7220
- 22.0697
- 37.0521
- 19.0000
- 29 4543
- e e e e e e e e e e e e e e e e e e eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen e e e e . . . e e 10
- 39.2368
- 21.9977
- 43.7340
- 22.2188
- 40.9910
- 21.4181
- 28.5734
- 12.7148
- e . . . . . . e e
. . . . e e e e e seeeeeeeeeeveneeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee e e e e e e e e e 11
- 32.5398
- 37.7622
- 22.2813
- 40.8085
- 21.9009
- 34.5607
- 17.7294
- 33.4649
- e e e e e e e e e e e e e e e e e e eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee e e e e e e e e 12
- 40.4144
- 22.0646
- 41.0991
- 21.9119
- 38.9014
- 19.0317
- 31.7684
- e e e e e e e e e e e e e e eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee....eeeeeeeeeeeeee.
. e . . e e e e 13
- 21.4387
- 36.9759
- 21.4139
- 34.5900
- 19.0369
- 33.3697
- 32.4716 *
- e e e e e e e e e e . . e e e eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeewee e e e e e e e 14
- 37.2968
- 19.0869
- 28.5784
- 17.7245
- 31.7772
- 32.3887
- e e e e e e e e e e e e e e seeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee e e e e e 15
- 37.5141
- 29.4861
- 12.7093
- 33.5182
- Assembly Average Exposure (GWD/MTU) i e e . e e j e . . . e eeeeeeee9eeeee99eeeeeeeee.Oeeeeeeeeeeeeee
ATTACHMENT 1
.. Page 13 of 17 1
Assembly Burnup Information for Future Cycles GWD/MTU McGuire 1 Cycle 12 and Catawba 2 Cycle 9 designs are not final.ized.
The following four pages provide the requested information for McGuire 2 Cycle 11 and Catawba 1 Cycle 10 o
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1 ATTACHMENT 1
- Page 14 of 17 McGuire 2 Cycle 11 HOC Assembly Burnup Distribution (GWD/MTU) 0EFPD G F E D C B A H
....e.e.ee.e........................ee ....ee. ............eeeece...eeeee...ee... j i
e e e . .
e e e e 08
- 36.4430 * .0000
- 31.1783 * .0000
- 28.3164 * .0000
- 28.3442
- 12.1599
- e e e e e e . e e
. e e e e e e e .
eeeeeeeeeeee......eeeeeeeeeeeeeeeeeeeeeeeeeeeee.eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeene.
e e e e e .
e e 09 * .0000
- 32.2650 * .0000
- 25.2489 * .0000
- 21.4365 * .0000
- 18.6945
- e i
e e e e e e I e e e e e . . e e e e )
i
..ee.....ee.......e.....................eee.e......... ................. ........ l e e e e e e e e e ]
10
- 31.1709 * .0000
- 24.9230 * .0000
- 26.7080 * .0000
- 17.1161
- 20.8300
- 1
. e e . e
. e . .
e e e . . .
e e e eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen e e e e e e
. . e 11 * .0000
- 25.2324 * .0000
- 24.9535 * .0000
- 20.9489 * .0000
- 21.2904
- e e e e e e e e e e e e e e e e e e seeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee j
. . e, e e e e .
12
- 28.3063 * .0000
- 26.7828 * .0000
- 21.2335 * .0000
- 18.2411
- e e e e e
- e e e e . . e e eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee ,
e . e e . .
e e ,
l 13 * .0000
- 21.4594 * .0000
- 20.8529 * .0000
- 21.2301
- 21.4274
- I e e e e e e e e
e e e e e e e e
..............................................eeeeeeeeeeeeeeeeeeeeeeene e e . e e e e 14
- 28.3555 * .0000
- 17.1199 * .0000
- 18.2657
- 21.3816
- e . . e e e e
e e e e e e e seeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee e e e e e 15
- 12.1607
- 18.6973
- 20.8168
- 21.2839
- Assembly Average Exposure (GWD/MTU)
. . . e e l
. . e e .
, Maximum Assembly Average Exposure - 36.4430 GWD/MTU at location H 08 l
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ATTACHMENT 1 Page 15 of 17 McGuire 2 Cycle 11 EOC Assembly Hurnup Distribution (GWD/MTU) 430 EFPD H G F E D C B A eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee e e e e e e e e e 08
- 52.0835
- 20.8054
- 47.4570
- 21.5494
- 45.5522
- 21.0409
- 42.8140
- 22.9549 *
. . . . . . e e e e e e e e e e e e seeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee e e e e e e e . .
09
- 20.8350
- 48.2354
- 21.3202
- 43.1347
- 21.6248
- 40.2706
- 19.3757
- 28.8314
- e e e e e e e e e e e e e e e e e e eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee.eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee e e . . e e e e e 10
- 47.4572
- 21.3227
- 42.7935
- 21.7252
- 44.4306
- 21.2728
- 33.8396
- 29.9187
- e e e e e e e e e e e e e e e e e e
.........................neeeeeeeeeeee...................eeeeeeeeeeeeeeeeeeeeeeee e e e e e e e e e 11
- 21.5532
- 43.1289
- 21.7299
- 43.0032
- 21.6653
- 39.4020
- 17.6119
- 28.4209
- e e e e . . e e e e . . . e e e e e i .......eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee e . . e e e e e 12
- 45.5452
- 21.6500
- 44.5006
- 21.6714
- 39.9345
- 18.9503
- 29.5434
- j e . . . . . . .
e . . . . e e .
l .ee.e... .......e ee..e.ee...ee.......ee..eee.eeen.eee.....ee ..e.eeeee e . . . . e e e l '
l 13
- 21.0412 ' 40.3067
- 21.2837
- 39.3307
- 18.9563
- 33.5918
- 27.8070
- e e e e e e e e l
1 e o e e e e e e l ee e e e e e..e e...ee eee e e eee e ee e e e e e e e e eeee eee e ee ee e e ee e e e e e e e e e e e e e e......
e e e . . e e 14
- 42.8231
- 19.4035
- 33.8533
- 17.6209
- 29.5677
- 27.7637
- e . . . . . e e e e e e e e eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee e e e e e 15
- 22.9551
- 28.8428
- 29.9128
- 28.4182
- Assembly Average Exposure (GWD/MTU)
. . . e e e e e e .
....................e....................
- Maximum Assembly Average Exposure - 52.0835 GWD/MTU at location H-08 i
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ATTACHMENT 1
. Pa*ge 16 of 17 Catawba 1 Cycle 10 HOC Assembly Burnup Distribution (MWD /MTU) 0EFPD E D C B A H G F eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee**e ***ee***ee***esee. e e e e e e e e e 08
- 30.1038 * .0000
- 30.0165 * .0000
- 21.1052
- 30.9040 e* 12.0359 *e 33.0023 *e
. e e e e .
. . . e e e !
......e..........ee.eeeee..ee..eeeeeeeeeeeeeeeeee.eeeeeeeeeeeeeeeeeeeeeeeeeeeeee. e e e e e e e
. e 09 * .0000
- 20.9061 * .0000
- 20.9223 * .0000
- 20.5739 * .0000
- 16.9237 *
. e e e e e e . .
e e e e e e e e e eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee e e e e e e e e 10
- 30.0165 * .0000
- 30.1992 * .0000
- 29.2913 * .0000
- 20.8273
- 18.7804 * ,
e e e e e e e e e e e e e e e e . .
eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee e e e e e e . .
.0000
- 21.0079 * .0000
- 21.1377 * .0000
- 21.1411 * .0000
- 32.4550
- 11
- e e e
- . e e e e e e e e e e e . .
........................................eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee e e . . e e e e
12
- 21.1052 * .0000
- 29.2812 * .0000
- 30.9473 * .0000
- 18.2426 *
. . e e e e .
e . . e e e e e eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee e e e e e e e e 13
- 30.9040
- 20.6082 * .0000
- 21.1688 * .0000
- 12.0224
- 32.6024
- e e e e e e e e e e e e e e e e eeeeeeeeeeeeeeeeeeeeeee...........e.ee........e ....................... e e e e e . .
14
- 12.0359 * .0000
- 20.8127 * .0000
- 18.2544
- 32.5929
- e e e e e e e e e e e e e
eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee eeeeeeeeeeeeeeeeeeeeeeeeeee e e e e e 15
- 33.0023
- 16.9024
- 18.8062
- 32.5610
- Assembly Average Exposure (GWD/MTU)
. . e . e e ee.eeeen..... ........ee....ee.........
Maximum Assembly Average Exposure - 33.0023 MWD /MTU at locations A-08 and H-15 i
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. Pige 17 of 17 Catawba 1 Cycle 10 l EOC Assembly Hurnup Distribution l 410 EFPD H G F E D C B A eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee e e e e e e e e e 08
- 46.5293
- 20.9087
- 46.8871
- 20.7699
- 39.4369
- 45.5910
- 28.1468 e* 40.1256 *e e e e e e e e l l
e e e e e e e e e eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee e e e e e e e e e 09
- 20.9087
- 40.1071
- 20.9940
- 40.2011
- 20.0754
- 38.2744
- 18.081n *e 26.1544 e e e e e e e e e e e . . e e e e e.eee.ee...ee..ee......ee...ee.eeeeeee.e..e. .ee.ee. ....e...eeeee.eee.eeee...... j e e e e e e e e e l
10
- 46.8871
- 21.0014
- 46.6101
- 20.9783
- 46.1288
- 20.3799
- 36.0799
- 27.2188 *e l e e e e e e e e l
e e e e e e e e e i eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee e e e e e e e e e 11
- 20.7699
- 40.2784
- 20.9943
- 40.3913
- 20.7868
- 38.8036
- 16.3231 *e 37.6590 *e e e e e e e e e e e e e e e e e neeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen e e . . e e e e 12
- 39.4369
- 20.0824
- 46.1303
- 20.0047
- 46.8128
- 18.5781
- 28.8038 *e
- e e e e e e e e e e e e e e eeeeeeeeeeeeeeeeeeeeee......eeee.........eeeeeeeeeeeeeeeeeeeeeeeeeeeeee i e . . . . . e e 13
- 45.5910'* 38.3203
- 20.3960
- 38.8549
- 18.6744
- 25.2623
- 37.7432 *e
- * *
- e e e
. . . . . e e e
.......................................eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee e e e e e e e 14
- 28.1468
- 18.1102
- 36.0824
- 16.3521
- 28.8851
- 37.8018 *e e e e e e e e e e e e e e seeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee e e e e e 15
- 40.1256
- 26.1481
- 27.2500
- 37.7657
- Assembly Average Exposure (GWD/MTU)
. e e e e e e e e e ee.eeee....Genetee ..eeeeeet.ee...e....ee Maximum Assembly Average Exposure -46.8871 MWD /MTU at krations F-08 and H-10 1 1
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