ML20212M896

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Summary of 860801 Meeting W/Util & Westinghouse in Bethesda, MD Re Failed Fuel Due to Baffle Jetting Discovered During Unit 1,Cycle 4 Refueling Outage & Licensee Proposed Corrective Actions
ML20212M896
Person / Time
Site: McGuire, Mcguire  
Issue date: 08/21/1986
From: Hood D
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 8608270430
Download: ML20212M896 (38)
v • d • e


Text

[( "" "*%g UNITED STATES g

NUCLEAR REGULATORY COMMISSION rn

j WASHINGTON, D. C. 20555

....J August 21, 1986 Docket Nos.: 50-369 and 50-370 3

LICENSEE:

Duke Power Company FACILITY:

McGuire Nuclear Station, Units 1 and 2

SUBJECT:

SUMMARY

OF AUGUST 1, 1986, MEETING REGARDING FUEL DAMAGE DUE TO BAFFLE JETTING On August 1,1986, the NRC met in Bethesda, Maryland with Duke Power Company (the licensee) and Westinghouse to discuss the failed fuel due to baffle jetting discovered during the Unit 1 - Cycle 4 refueling outage and the licensee's proposed corrective actions. Meeting attendees are listed in Enclosure 1.

On June 26, 1986, while performing core verification using an underwater video camera, the licensee observed several small cylindrical objects lying on the upper core baffle.

One June 27, additional cylindrical objects were found in the vicinity of the upender. One June 29, these cylindrical objects were con-firmed to be spent fuel pellets and were later vacuumed from the core and up-ender and other areas were inspected for debris.

Subsequent video inspection revealed that three fuel rods at the outer face of one fuel assembly, and several spacer grids in that assembly, had been damaged. Video inspection of all other fuel assemblies at baffle joint locations revealed no further damage, but gap measurements at baffle joints revealed a potential for future jetting at an additional fuel assembly location.

Tapes from the video inspection were played during the meeting.

The licensee's corrective action included a decision to remove eight fuel rods from the outer face of two assemblies (one to be located in the damaged area, and the other next to the gap) and to replace these eight rods with eight and six solid stainless steel (SS) rods. Therefore, water jetting across the

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baffle at these joints in the future would impinge on the'SS rods and not lead to fuel rod failure. The assembly to be modified with eight SS rods and located where damage occurred during Cycle 3, is the demonstration assembly; it will provide greater resistance to baffle jetting damage than the other assemblies (Westinghouse 17 X 17 Optimized Fuel Assemblies) Decause it has three additional intermediate grids in its upper region.

Beginning in 1972, use of SS rods in fuel assemblies to mitigate the effects of baffle jetting has been applied to several operating nuclear power plants, both foreign and domestic. A sumary of this experience was presented by Westinghouse.

8638270430 860821 PDR ADOCK 05000369 P

PDR L

l August 21, 1986 c

~To provide improved performance with these changes for Cycle 4, a new fuel cycle loading pattern (including changes in burnable poison configurations) was performed such that no significant change in core reactivity occurred. The s

licensee stated that a revised Reload Safety Evaluation (RSE) for the redesigned Unit 1 - Cycle 4 core would be submitted to the NRC about August 8,1986.

The revised RSE is to support licensee's application for amendments to change Technical Specification 5.3.1 to allow substitution of some of the required 264 fuel rods per assembly with SS rods or open water channels.

[Accordingly,the reader is referred to licensee's letter of August 4,1986 wi'.h its attached RSE for additional technical details of the meeting].

Copies of the viewgraph slides used during the non-propries.ory portion of the meeting are shown in Enclosure 2.

Darl Hood, Project Manager PWR Project Directorate #4 Division of PWR Licensing-A

Enclosures:

As stated DISTRIBUTI0il:

Docket File Local PDR llRC PDR PWR#4 Reading BJYoungblood Reading D. Hood

'DJ d W

PWR#4/DPWR-A PWR#4/DPWR-A DHood/ rad

.(nBJYoungblood 08/ /86 08/g /86 3f

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Mr. H.,B. Tucker Duke Pbwer Company McGuire Nuclear Station 3

cc:

l Mr. A. Carr Dr. John M. Barry Duke Power Company Department of Environmental Health P. O. Box 33189 Mecklenburg County i

422 South Church Street 1200 Blythe Boulevard Charlotte, North Carolina 28242 Charlotte, North Carolina 28203 Mr. F. J. Twogood County Manager of Mecklenburg County i'ower Systems Division 720 East Fourth Street Westinghouse Electric Corp.

Charlotte, North Carolina 28202 P. O. Box 355 i

Pittsburgh, Pennsylvania 15230 Chainnan, North Carolina Utilities i

Commission Mr. Robert Gill Dobbs Building Duke Power Company 430 North Salisbury Street Nuclear Production Department Raleigh, North Carolina 27602 P. O. Box 33189 Charlotte, North Carolina 28242 Mr. Dayne H. Brown, Chief 1

Radiation Protection Branch 1

J. Michael McGarry, III, Esq.

Division of Facility Services Bishop, Liberman, Cook, Purcell Department of Human Resources and Reynolds P.O. Box 12200 1

1200 Seventeenth Street, N.W.

Raleigh, North Carolina 27605 l

Washington, D. C.

20036 j

Senior Resident Inspector c/o U.S. Nuclear Regulatory Commission j

Route 4, Box 529 j

Hunterville, North Carolina 28078 i

Regional Administrator, Region II U.S. Nuclear Regulatory Commission, 2

j 101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 30323 L. L. Williams Operating Plants Projects i

Regional Manager j

Westinghouse Electric Corporation - R&D 701 P. O. Box 2728

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Pittsburgh, Pennsylvania 15230 i

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P l

s Attendees k

i August 1, 1986 i

l Name Organization Darl S. Hood PAD 4/PWR-A/NRR l

Richt.rd Lobel NRC/RSB-A Carl H. Berlinger NRC/NRR/DPLA/RSB 4

Marvin Dunenfeld NRC/DPLA/RSB l

Richard H. Clark Duke / Nuclear Design Jerry' Day Duke / Licensing i

Michael S. Kitlan, Jr.

Duke / Nuclear Production /McGuire Robert J. Tomonto Duke / Design / Nuclear Engineering i

William T. Orders NRCSRI/McGuire l

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  • Robert B. Borsum Babcock & Wilcox - Bethesda
  • Lynn Connor Doc-Search Associates j

David R. Forsyth Westinghouse /GTSD e

William R. Jones NRC/IT/ Events Analysis Bob Pierson NRC/IE/ Pat /SSFI i

Rebecca Long NRC/ Region II j

Mark Beaumont Westinghouse - Bethesda l

Ken Casady Duke Power Company / Nuclear Engineer l

M.G. Arlotti Westinghot.se Fuel Support Operations I

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DlEE F0WER/NRC ItGUIRE NUCtIAR STATION 9

DN%GED FUEL AGENDA AUGUST L 1986 e INTRODUCTION I

I e CHRONOLOGY OF EVENTS e ASSESSENT OF TE FUEL DN%GE i

e '.ESTINGHOUSE EXPERIENCE f

e BAFFLE GAP WASURBINTS i

i e PLANNED COURSE OF ACTICN i

e F0NITORING AND SURVEILIANCE e Sift %RY 1

Chronology of Events McGuire Unit 1 Date Event 6/26/86 Fuel pellets observed on core baffle and at Reactor Building upender following core loading' Initial site NRC notification of problem.

6/29/86 Fuel pellets vacuumed from core and upendcr area.

Spent fuel pool racks checked for fuel pellets.

None found.

D03 confirmed to be damaged assembly by inspection.

7/1/86 003 moved to Spent Fuel Pool.

7/4/86 Core unloaded.

7/6/86 All 16 corner injection baffles have been measured.

Three show readings >.003 inches.

The 23 other assemblies that resided in baffle locations last cycle have been inspected.

No damage found.

7/8/86 Decision made to place stainless steel rods in two assemblies.

7/9/86 Site NRC notified of decision.

7/25/86 Assemblies have been reconstituted.

Two stainless steel pins fall out of one assembly.

Site NRC notified.

7/31/86 Core reloaded.

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i MCGUIRE UNIT 1 AND 2 BAFFLES o

THE MCGUIRE UNITS HAVE:

e 16 CORNER INJECTION JOINTS e

12 CENTER INJECTION JOINTS 0

FOR A TOTAL OF 28 EAFFLE JOINTS.

AS A RESULT OF A FIELD CHANGE NOTICE (FCN) PERFORMED BY WESTINGHOUSE - ALL CENTER INJECTION JOINTS WERE BOLTED THE FULL LENGTH.

KNIFE EDGE PEENING USING A (SHARP POINTED CHISEL) WAS PERFORMED ON ALL INTERIOR JOINTS > 3 MILS.

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FIGURE 1 : BAFFLE WATER - JET IMPlNGEMENT I

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SUMMARY

OF DAMAGE TO FA D03 IN CORE LOCATION P-03 DAMAGE WAS LIMITED TO THREE FUEL RODS ON FACE-1 0F THIS ASSEMBLY.

A REVIEW 0F THE HIGH MAGNIFICATION (5 RODS PER PASS) VIDEO INSPECTION PROVIDES THE FOLLOWING OBSERVATIONS OF FUEL i

ASSEMBLYDd3.

i FUEL ROD #17 THIS ROD WAS LIMITED TO DAMAGE AT ONLY ONE LOCATION, SELOW GRID #3 (SECOND ZIRCALOY GRID FROM THE BOTTOM).

I IHIS DAMAGE WAS OBSERVED TO BE A THRU-WALL DEFECT l

CAUSED BY FRETTING.

FUEL ROD #16 JHISRODEXPERIENCEDTHELARGESTDEGREEOFDEGRADATION.

A REVIEW OF THE VIDE 0 TAPE IDENTIFIES A LOSS OF CLADDING GORRESPONDING TO APPROXIMATELY THE TOP EIGHT INCHES.

lHE FUEL ROD SPRING WAS FOUND LODGED BETWEEN THE HOLDDOWN SPRING AND THE UPPER GRILLAGE.

IHE REMAINING PORTION OF THE ROD ( ~12.5 INCHES)

BETWEEN THE TOP INCONE GRID N

MEDIATE ZIRCALOY GRID GRID # )D THE FIRST INTER-1 WAS FOUNp BE(T OUT FROM THE ASSEMBLY TOWARDS FUEL ROD #1.

IHE TUBING WAS SPLIT LONGITUDINALLY AND SHEERED OFF TO A POINT PORTIO 3S OF T BEHINDkOW1ON-ACE 1.HECLADDINGWEREIDENTIFIED THE DISPLACEMENT QF JHE ROD FROM FACE 1 WAS FOUND TO BE LESS THAN 4.5.

IHRU-WALL CRACKS WERE OBSEBVED AI GRIDS 6, 5 AND 4, WITH THE ROD AT BOTH GRID 5 AND b COMPLETELY TORN.

l BELOW GRID #3, THE FUEL ROD WAS DBSERVED TO HAVE A FLAT SURFACE ALONG THE CLADDING OD.

THIS DAMAGE IS EXPECTED l

TO HAVE CORRESPONDED TO CONTACT WITH THE BAFFLE WALL.

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i FUEL ROD #16 IS SEATED ON TOP OF THE GRILLAGE ON THE LOWER N0ZZLE. THE EilDCAP IS THE HEAT AFFECTED ZONE (HAZ) WORN, UP TO THE POIllT OF ON THE WELD SURFACE.

BELOW GRID #2, SWIRLING LINES ARE OBSERVED ALONG THE j

CLAD.

FUEL ROD #15 ll FUEL ROD #15 WAS MISSING APPROXIMATELY THE TOP 1.5" 0F THE CLADDING (SUCH THAT THE TOP OF AVAI(ABLE ROD 2

MATERIAL WAS SEATED BELOW THE INCONEL GRID).

lHE EUEL RQD SPRING WAS NOT VISIBLE.

DETWEEN SPACER GRID i

/ AND 0, THE CLAQQJ,NG WAS DISPLACER AND (OCA"5D i

ADJACENT TO ROD #19 IN ROWS 1 AND 4 AND MOD #15 IN i

R0W 2.

BELOW GRID #/,-CIRCUMFERENTIAL WEAR WAS l

OBSERVED.

J FUEL ROD #15 IS SEATED ON BOTTOM OF THE GRILLAGE ON THj LOWER N0ZZLE.

THIS n0D IS WORN APPROXIf1ATELY t

1/0" TO THE CHAMFER.

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WITH THE EXCEPTION OF SPACER GRIDS #1 AND 8 i

OCCURRED ON ALL GRIDS BETWEEN RODS : 6ANDIf. DAMAGED I

SPECIFICALLY GRIDS 4-7 WERE J,QRN COMPLETELY THROUGH Igg OUTER GRID STRAP.

GRID F3 WAS TORNED APPROXIMATELY 1

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/D4 THROUGH AND GRID #2 WAS MISSING ONLY THE DIMPLE l

SPRING.

i DEBRIS i

FUEL PELLET QEBR[S WAS IDEN"!FIED ABOVE SPACER GRIDS 1

1, D, b AND /

ALONG FACE...

A REVIEW OF FACE 4 1DEJTIFIEQ LODGED FUEL PELLETS ABOY SPAGER GRID #1, t

i D, b AND / BETWEEN FUEL RODS 1 AND (50M THIS DEBRIS WAS OBSERVED FROM BOTH FACE AND 4.5 0:

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30RIIONS 0F THE FUEL CLADDING WERE FOUND BEHIND FUEL RODS b ON FACE #1.

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i FURTHER VIDEO ASSESSMENT WESTINGHOUSE PERFORMED A COMPLETE HIGH MAGNIFICATION VIDEO INSPECTION (10 RODS / PASS) 0F ALL FUEL ASSEMBLIES SITTING IN CENTER AND CORNER INJECTION JOINT LOCATIONS.

OntY FUEL ASSEMBLY D-03 IDENTIFIED ANY FUEL FAILURES.

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BAFFLE GAP MEASUREMENT 1

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PURPOSE OF INSPECTION:

4 BASED UPON THE RECENT FAILURES IN MCGUIRE UNIT 1, THESE INSPEC-TIONS WERE PERFORMED TO DETERMINE THE CONDITION OF EACH CORNER i

INJECTION JOINT.

i THIS INSPECTION COULD PROVIDE INFORMATION CONCERNING THE i

CAUSE OF FUEL FAILURE AND THE CONDITION OF THE BAFFLE j

RELATIVE TO ADJACENT FUEL ASSEMBLIES.

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a METHOD OF INSPECTION

[ASEDUPONSEVERALDISCUSSIONSBgTWEENDUKEANDWESTINGHOUSE, UUKE FABRICATED A FEELER GAGE.

lHESE GAGES WOULD TYPICALLY PROVIDE A "GO - NO G0" TYPE OF RESPONSE.

4 THE GAGES FABRICATED AND USED WERE QUILT TO THICKNESSES OF

.003,.005,.007 AND.010 INCHES.

TACH REACH POLE WAS INCREMENTALLY MARKED EVERY 6 INCHES AND HAD ATTACHED A TOOL WITH TWO FEELER GAGES.

AS A MEANS TO DETERMINE A DEPTH OF PENETRATION A WHITE SCROLL WAS PLAC D ON THE FEELER GAGE j

CORRESPONDING TO APPROXIMATELY A 1/[2 INCH DEPTH.

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I ACCURACY OF MEASUREMENT IN ORDER TO DETERMINE THE ACCURACY AND FEASIBILITY OF THIS METHOD, l

MCGUIRE SET-UP A MOCK-UP OF THE BAFFLE CONFIGURATION.

USING AN ADJUSTABLE BAFFLE PLATE CONFIGURATION FOR THE CORNER l

INJECTION JOINTS AND A VIDEO CAMERA EACH OF THE TWO CREWS TRAINED FOR THE DURATION OF EACH SHIFT.

REPEATIBILITY AND ACCURACY WERE READILY OBSERVED FOR MANY GAP OPENING COMBINATIONS.

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CORE LOCATION MEASUREMENT LOCATION

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<.003 ALL REMAINING CORNER INJECTION LOCATIONS MEASURED BAFFLE GAPS OF LESS THAN.003".

" NOTE:

ALL MEASUREMENTS MADE FROM THE TOP OF THE BAFFLE AND MOVE DOWN.

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MONITORING AND SURVEILLANCE f

o COOLANT ACTIv!TY TYPICALLY THE FOLLOWING ISOTOPES HAVE BEEN MONITORED AND TRENDED MONTHLY, DURING EACH CYCLE.

THESE INCLUDE:

4 IODINE - 131 0

IODINE - 133 9

IODINE - 131/10 DINE -133 RATIO DURING MCGUIRE 1 CYCLE 3 THE AVERAGE STEADY-STATE VALUE FOR EACH ISOTOPE WAS 1131 =.008 MICR0 CURIE /llL 1133 =.0584 MICR0 CURIE /ML 1131/1133 = 0.137 BASED UPON THE LOW MAGNITUDE OF THESE VAL!lES - 10 DINE-134 DID NOT WARRANT BEING TRENDED.

AS A RESULT OF THE KNOWN FUEL FAILURES AT MCGUIRE, 10 DINE-134 SHALL BE TRENDED FOR ALL OF DUKE'S UNITS.

DUKE HAS ESTABLISHED AN EIGHT POINT ACTION PLAN TO BE UTILIZED IN THE EVENT THE STEADY-STATE VALUE OF DOSE EQUIVALENT IODINE EXCEEDS 0.04 MICR0 CURIES / GRAM.

a

t JVIDb0INSPECTIONANDBAFFLEGAPMEASUREMENT DURING THE NEXT OUTAGE OF BOTH MCGUIRE UNITS, DUKE SHALL e PERFORM A COMPLETE INSPECTION OF THE APPROPRIATE FACE OF EACH FUEL ASSEMBLY PRESENTLY OPERATING IN A CORNER INJECTION JOINT CORE LOCATION.

8 MEASURE THE BAFFLE GAP ON ALL 16 CORNER INJECTION JOINTS.

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SlH%RY OF DEBRIS REMNAL ACTIVITIES itGUIE UNIT 1 EACTOR BUILDIE UPENDER #0 VESSEL AREA VACUllE (INCLUDING lt0ER COE PLAlD ALL DEBRIS REID&D, EACTOR EUILDING CAVITY (INClllDING DEEP END) DRAIED #0 ALL DEBRIS PB1NED SPENT REL POOL RACKS (AND UNDER RAGG) EXAMIED FOR DEBRIS -f0E FOUiG SPENT FUEL POOL REL TRANSFER AREA EXN1!fE #0 SURVEYED FOR EllETS OR DEBRIS. NO PELLETS NOTED BUT OTER DEERIS PRESENT. AREA SCHEDulfD FOR VACulfilm EXT EEK HEALTH PHYSICS SUPNEY OF F0l10 WING AREAS:

i A. REACTOR C00lRfT SYSTB1 PIPING #0 FILTERS B. ESIDUAL EAT RERNAL SYSTBi PIPING #0 C0F0ENTS C. SPENT FUEL POOL LETDOH1 LIES INCll' DING FILTERS D. EFUELItE WATER STORAGE TANK PIPING E. REACTOR BUILDING LEIDOWN LIES s.

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INSERTION OF SOLID SS RODS IN TWO FUEL ASSEMBLIES I

CORE REDESIGN l

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LICENSING SCHEDULE I

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O COURSE OF ACTION CORE LOCATIONS P03 AND A05 ARE THE ONLY CORE LOCATIONS OF CONCERN BECAUSE:

1.

CORE LOCATION P03 OBSERVED FUEL DAMAGE OF FA D03 DURING THE LAST CYCLE.

2.

P03 AND A05 WERE THE ONLY LOCATIONS WHERE 5-7 MIL BAFFLE GAPS WERE MEASURED OVER ANY SIGNIFICANT LENGTH.

3.

P03 AND A05 WERE THE ONLY LOCATIONS WHERE A GAP 0F GREATER THAN 3 MILS WAS OBSERVED NEAR OR AB0VE THE MIDDLE OF THE FUEL ASSEMBLIES (WHERE THE AP ACROSS THE BAFFLE IS HIGHEST).

THE IFM DEMONSTRATION ASSEMBLY HAS BEEN MOVED TO P03.

SINCE IT HAS THREE ADDITIONAL INTERMEDIATE GRIDS IN THE UPPER PART OF THE ASSEMBLY, THIS ASSEMBLY WILL PROVIDE SIGNIFICANTLY MORE RESISTENCE TO BAFFLE JETTING DAMAGE THAN A REGULAR FUEL ASSEMBLY.

AS AN ADDED PRECAUTION, THE ASSEMBLIES G0ING INTO CORE LOCATIONS P03 AND A05 HAVE HAD EIGHT FUEL RODS REMOVED AND EIGHT AND SIX STAINLESS STEEL RODS INSERTED.

SHOULD BAFFLE JETTING OCCUR IN THESE LOCATIONS, THE WATER WILL IMPINGE ON THE SS RODS AND NOT LEAD TO FUEL R0D FAILURE.

SS Rod Configuration for Assembly in Core Location P03 CENTER INJECTION JOINT

  • p1 CORNER INJECT ON JOl,NT OO-00 00 O00@@1 00@@

O@@

P

>P j

2 P-P2 2 29 PSI AT TOP j

OF THE BAFFLE FIGURE BAFFLE WATER - JET IMPINGEMENT l

s r a i a t. e s s s r c e c.

l~

Roos t a. x 4 Aamy)

' [

SS Rod Configuration for Assembly in Core Location A05 1

1 CENTER INJECTION JOINT O

' pI CORNER INJECTION JOINT

/

Y 3

OO

~

00 OO@@f 000 O@@

P

>P j

2 P --P 3

2

l-26 PSI AT TOP OF THE BAFFLE FIGURE : BAFFLE WATER - JET IMPINGEMENT I

i

'3 TAI N L_E ss S TCE L_

f' Rods

( A 'x 3 AR.RAv )

o v

,-,-----m a

+---n

'r DESCRIPTION OF NEW FUEL CYCLE DESIGN

SUMMARY

OF FUEL ASSEMBLIES BEING DISC,HARGED, REINSERTED, AND BURNABLE ABSORBER CHANGES.

FUEL CYCLE SHUFFLE

.. BOC RADIAL POWER DISTRIBUTION (HFP, eg. Xe)

MAXIMUM PIN PEAK VERSUS BURNUP NO.SIGNIFICANT CHANGE IN CYCLE LENGTH OR CORE REACTIVITY l

i 1

l

. x, MCGUIRE 1 CYCLE 4 REDESIGNED LDADING PATTERN CHANGES Assemblies Leaving the Core 4

Region 4 assemblies (3.2 w/o U-235 optimized fuel - twice-burned) i r

Assemblies Entering the Core 4

Region 1 assemblies (2.1 w/o U-235 standard fuel once-burned) i Assemblies Changing Burnable Poison (BP) Configurations l

4 Region 6A assemblies reducing number of BP pins from 8 pins each to 4 pins each.

(Region 6A 3.2 w/o U-235 optimized fuel - fresh) r 4

6 L

MCGUIRE 1 CYCLE 4

)

REDESIGNED LOADING PATTERN CHANGES H

G F

E D

C B

A 1

                • *************+++++

.+++****s***++++.********************

+ 4 EPs *

+ Reg 5 *

+

+

8 4

  • 2 bps *
  • Reg 4 *

+

                                                                                                        • ++++ ********

4 EPs

  • Reg 1 +

+

9*

+

8 bps

  • Reg 4 *
                                                      • s*************************************

13

  • Reg 5 *
  • Reg 5 *
  • Reg 4
  • 11 *

+

  • Reg 4 *
  • Reg 4 *
  • Reg 5 +'
                                                                                    • .****************+* ***
  • Reg 5
  • 12 *
  • Reg 4 *
                                                                                        • +++++++...***
  • Reg 4
  • Redesig>1 13 *
  • Reg 5
  • Orig. Design
  • Reg 4
  • 14 *
  • Reg 5
  • 15
  • McGuire 1 Cycle 4 Fuel Types l

Region 1 2.1 w/o U-235 standard fuel

- once-burned Region 4 - 3.2 w/o U-235 optimized fuel

- twice-burned Region 5 3.2 w/o U-235 optimized fuel once-burned Region 6A - 3.2 w/o U-235 optimized fuel

- fresh Region 6B -

3.4 w/o U-235 optimi:ed f uel

- fresh.

e

MCGUIRE 1 CYCLE 4 ASSEMBLY AVERAGE POWER DISTRIBUTIONS REDES GN VS. CRIGINAL DESIGN

KO. MFF, EC XE, 1000 FPME. 150 MWD /MTU H

G F

E D

C 8

A e.*****ese+e,*****************.***

eeee+.

    • e...+++4***+.**...e+++++
      • +++4.**++

1.03 +

1.31 1.06

+

1.17

  • 1.19
  • 1.0E 4

.E?

.22 8

1.C2 +

1.28.

1.07 +

1.13

  • 1.19.

1.09 +

.69

.80

+

+

.98 2.34 *

.93 e

3.54

  • 0.20

.72

+

3.00 +

2.50

  • 4.+ee***e

.**. 43 4..***+++************..

    • ... 44

+.4.++.

+4.+++++,..

44 4.....

+

1.31

.98 1.14

  • 1.14
  • 1.26

+

1.00

  • 1.19

.65 9

+

1.28

  • 1.13 e 1.17 e 1.14 e 1.25 +

1.00

  • 1.19

.67 e

2.34 * -13.27

-2.56 2.00 *

.80

+

0.00 +

0.00

  • 1.4?

+

  • .. ******.**+****...***************************

e****+++e+++++++

    • +.e.******...

1.25

  • 1.14 +

1.11

1. 2.1

.94 1.25

  • 1.00

.78 10 e

1.07

  • 1.17 e

1.12 e 1.2t e

.93

+

1.24

.?9

.77

-1.57

-2.56

.89

.61 1.08 *

.81

+

1.01

+

1.30 +

+

...e********

        • eeen eeeeee*************************************+.***

++

+++++e e

1.17 +

1.14 1.25

  • 1.19
  • 1.13
  • 1.03
  • 1.15 +

47

  • 11 e

1.13

  • 1.14 e 1.24 +

1.15

  • 1.12 e

1.01 e

1.13 *

.47 3.54

  • 0.20 +

.81

+

3.48 *

.89 e

1.98 e

1.77 3.20 e

ee**************e*+eien**eese,

                          • +,e,*eeeeee*****ee**++++++++++

.++,..

1.18 +

1.26 *

.94 e

1,13

  • 1.17
  • 1.21

.67 12 e 1.19

  • 1.26 *

.94 1.13

  • 1.15
  • 1.22 *

.67

.84 0.02

  • 2.00 +

0.0C

  • 1.74 e

.83

+

0.20

+

    • e,****e 1***e
                  • e.....**,.***e e***

eeeeeee,*eeese...+

4....

1.07 *

.99

+

1.25 +

1.02

  • 1.21

.79

+

.!6

+

13 +

1.29

  • 1.00 +

1.25

  • 1.02
  • 1.21 +

.81

.37

+

+

-1.53

-1.00

+

0.02

  • 2.00
  • 0.00 *

-2.47

+

2.70

+

      • 4ee.es***e**********+..*******.,*e.,******,,*****e***,.........

.88 1.19 *

.99 1.14

.67

.37 e

14 e

.89 1.19 +

.99 1.14.

.67

.37 e

-1.12 0.00

  • 0.20 +

0.00

  • 0.00
  • 8.00
  • e,*evee*****+ee**++

..ee****...,*e,**e..,*e.eeee......#,

.. e e

.81 e

.68

.77 e

.47

  • REDESIGN 15 *

.80

.67 e

.77

.47 e ORIG. DESIGN e

1.25 e 1.49 e

0.00

  • 0.00 * % DIFFERENCE es*****e,*e++++++**,......,***ese*,ee,,,,

a

\\

_i MCGUIRE 1 CYCLE 4 PEAK PIN POWERS REDESIGN VS. ORIGINAL DESIGN I

f REDESIGN ORIG. DESIGN CYCLE BURNUP PEAK PIN PEAK PIN MWD /MTU POWERS POWERS

% DIFFERENCE O

1.420 1.408 0.85 150 1.399 1.388 0.79 500 1.393 1,3g0 g,94 1000 1.385 1.374 0.80 2000 1.372 1.363 0.66 4000 1.361 1.350 0.81 6000 1.361 1.340 1.57 8000 1.363 1.345 1.34 10000 1.364 1.345 1,41 12400 1.355 1.335 1.50 t-I f

,----,e.

, --n,-

... - ~,, - - - - - - -, -. ~ - - - - - - - -, - - - - - - ~ - - -

LICENSING IMPACT ITEM DUE T0-NRC 1.'

REVISED TECHNICAL SPECIFICATIONS TO 01 AUG 86 ALLOW LESS THAN 264 FUEL RODS PER ASSEMBLY 2.

REVISED RSE 08 AUG 86 3.

REVISED PEAKING FACTOR LIMIT REPORT 12 AUG 85 NOTE EXPECTED CRITICALITY DATE 08/26/86

..--.e.--

.. -..., =.m

---,--m-

--<-,m--

---+--e---

y y

y g

v-4,.-'

_m r_a m

+

~

~

PLANT "B" EXPERIENCE - F/A WITH SST RODS CYCLE 2

3 4

5 6

7 8

9 APPROX B/D PLANT B

  • UF GWD/T 0 EOC 3SSR 2P 2I 2I 2I 34 6

12P 12P 12I 12I 4I 29 8

SSSR-2x8 MG 8P 8P 8P 8P 8P 18 8

PLANT 0

  • UF 2SSR 2P 2I 2I 30 4

4SSR 8P 7P 7I 27 6

4SSR-2x5 MG 12P 12P llI 4P 28 7

8SSR+2x5 MG 8P 8P BI 4P 28 7

7SSR+2x5 MG IP II 21 6

KEY:

SSR-SST. Ron P - PERIMETER LOCATION MG - MINI-GRID I - INTERIOR LOCATION l

t

..v DOMESTIC PLANT TiPE EOC YEAR F/A DAMAGED FUEL MODIFICATIONS A

2 LOOP 2

73 1

3 75 1*

12 85 1

13 86 1*

CONVERTING TO U/F EQE B

4 LOOP 2

80 1+1 2 F/A (3SSR) 3 81 4

82 7+1 8 F/A (SSSR+MG) 12 F/A (2SSR) 5 83 CONVERTED TO U/F C

3 LOOP 2

80 1

3 83 4

84 11 CONVERTED TO U/F D

3 LOOP 5

85 1

l E

2 LOOP 11 85 2

CONVERTING TO U/F ESE__

j F

3 LOOP 6

86 1

1 F/A (7 SSR)

G 4 LOOP 3

86 1

1 F/A (8 SSR) 1 F/A (6 SSR)

  • SAME LOCATION AS PREVIOUS CYCLF

i NON DOMESTIC (NOT COMPLETE LIST)*

YEAR TYPE E0C YEAR F/A DAMAGED FUEL MODIFICATIONS 4

H 1 LOOP 2

72 2

h 2 LOOP 1

73 1

0 2 LOOP 1

79 2

2 F/A (3SSR) 2 81 4

3 22 3+2 20 F/A (4SSR+MG) 8 F/A (4SSR) 4.

83 1 (MODIFIED F/A) 5 85 CONVERTED TO U/F

  • EXCLUDES PLANTS BEING FUELED BY OTHERS i

4 f

4 9

i

_

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