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=Text=
{{#Wiki_filter:REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
{{#Wiki_filter:REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
DISTRIBUTION FOR INCOMING MATERIAL                           50-315 REC: CASE E G                     ORG: T ILLINGHAST J               DQCDATE: 05/12/78 NRC                                'IN  5 MI PNR                      DATE RCVD: 05/23/7 DQCTYPE:   LETTER     NOTARIZED: NO                                       COPIES RECEIVED
DISTRIBUTION FOR INCOMING MATERIAL 50-315 REC:
CASE E G
NRC ORG:
TILLINGHAST J
'IN 5 MI PNR DQCDATE: 05/12/78 DATE RCVD: 05/23/7 DQCTYPE:
LETTER NOTARIZED:
NO COPIES RECEIVED


==SUBJECT:==
==SUBJECT:==
LTR 1               ENCL 1 RESPONSE   TO NRC LTR DTD     02/24/78... FORWARDING INFO RELATING TO CYCLE 3 OF SUBJECT   FACILITY CONSISTING OFi DESCRIPTION       OF PROPOSED REFUELING DETAILED CORE LOADING PATTERNS AND STARTUP TEST REPT PROVIDING SAME PLANS'NCLUDING INFO AS CYCLE 2 REPT SUBMITTED g/Qgt77 PLANT NAME: CQOK  UNIT                                        REVIEWER INITIAL: X JM DISTRIBUTOR   INITIAL:           ~
LTR 1
DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS NOTES:
ENCL 1
I 8c E 3 CYS ALL MATERIAL GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LICENSE.
 
===RESPONSE===
TO NRC LTR DTD 02/24/78...
FORWARDING INFO RELATING TO CYCLE 3 OF SUBJECT FACILITY CONSISTING OFi DESCRIPTION OF PROPOSED REFUELING PLANS'NCLUDING DETAILED CORE LOADING PATTERNS AND STARTUP TEST REPT PROVIDING SAME INFO AS CYCLE 2 REPT SUBMITTED g/Qgt77 REVIEWER INITIAL:
XJM DISTRIBUTOR INITIAL:~
DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS PLANT NAME: CQOK UNIT NOTES:
I 8c E 3 CYS ALL MATERIAL GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LICENSE.
(DISTRIBUTION CODE A001)
(DISTRIBUTION CODE A001)
FOR ACTION:       BR CHIEF SCHWENCER44W/7 ENCL INTERNAL:              F ILES~ W/ENCL                  NRC PDR++W/ENCL
FOR ACTION:
                                    ~C I.IANAUER++W/ENCL OELD~~LTR ONLY CHECK+4W/ENCL I
INTERNAL:
E SENHUT~~+W/ENCL                    SHAO~~W/ENCL BAER~~W/ENCL                          BUTLER+4W/ENCL EEB~~W/ENCL                          J COLLINS++W/ENCL J. MCGQUGH+4W/ENCL EXTERNAL:        LPDR S ST. JOSEPH'I +~W/ENCL TIC4~~W/ENCL NS I C+4W/ENCL ACRS     CAT B4+W/16 ENCL DISTRIBUTION:     LTR 40       ENCL 39                         CONTROL NBR:                781420040 SIZE: 3P+2P
EXTERNAL:
%%%%%%%4%%4%%%4%%4 4'%%%%%%%%%%%%%%%4         THE END
BR CHIEF SCHWENCER44W/7 ENCL FILES~W/ENCL
~C I.IANAUER++W/ENCL EISENHUT~~+W/ENCL BAER~~W/ENCL EEB~~W/ENCL J.
MCGQUGH+4W/ENCL LPDR S ST.
JOSEPH'I +~W/ENCL TIC4~~W/ENCL NS IC+4W/ENCL ACRS CAT B4+W/16 ENCL NRC PDR++W/ENCL OELD~~LTR ONLY CHECK+4W/ENCL SHAO~~W/ENCL BUTLER+4W/ENCL J COLLINS++W/ENCL DISTRIBUTION:
LTR 40 ENCL 39 SIZE:
3P+2P
%%%%%%%4%%4%%%4%%4 4'%%%%%%%%%%%%%%%4 THE END CONTROL NBR:
781420040


it 'I II
it
                                        'm                   I,'OPT II6CK7 ALE INDIANA     R Hl(%         N     OWER COMPANY P. O. BOX 18 BOILING GREEN STATION NEW YORK, N. Y. 10004 May 12, 1978 Donald C. Cook Nuclear Plant Unit           1 Docket No. 50-315 DPR No. 58 Mr. Edson G. Case,     Acting Director Office of Nuclear Reactor Regulation Nuclear Regulatory Commission Washington, D.C. 20555
'I II
 
'm II6CK7 ALE I,'OPT INDIANA R Hl(%
N OWER COMPANY P. O. BOX 18 BOILING GREEN STATION NEW YORK, N. Y. 10004 May 12, 1978 Donald C.
Cook Nuclear Plant Unit 1
Docket No.
50-315 DPR No.
58 Mr.
Edson G.
: Case, Acting Director Office of Nuclear Reactor Regulation Nuclear Regulatory Commission Washington, D.C.
20555


==Dear Mr. Case:==
==Dear Mr. Case:==
is given in response to request (1).
ng on April 6, 1978 and Cold Shutdown The reactor vessel head was lifted subsequently the reactor cavity and th borated water.
,The fuel shuffle completed on May 2, 1978.
Sixty-supplied, fuel assemblies were re-Company (ENC) supplied fuel assemblies nserted into the reactor.
The detailed 3 is shown in the attachment.
A key d in the core loading pattern is the attachment.
During the time of rradiated fuel elements supplied by levision camera.
The following information Unit 1
was shutdown for refueli was attained on April 7, 1978.
on the morning of April 21, and refueling canal were flooded wi began on April 26, 1978 and was four expended Westinghouse (W) moved and 64 new Exxon Nuclear with 2.92 w/o enrichment were core loading pattern for Cycle to the identification codes use included on a separate page of the fuel shuffle, a sample of i each vendor was inspected by te Following the fuel shuffle, inservice inspection of the reactor vessel
: welds, as required by Technical Specifications, was performed.
This effort required 4 days.
After reinstallation and securing of the reactor vessel head including reconne'ction of all instrumentation and equipment and reinstallation of the missile shield, the contain-ment integrated leak 'rate test will be performed.
This letter is in response to Mr.
AD Schwencer's {{letter dated|date=February 24, 1978|text=letter dated February 24, 1978}} which requested us to furnish for Cycle 3 of the Donald C.
Cook Nuclear Plant Unit 1 the following: (1) prior to startup for operation of Cycle 3, a brief description of the proposed refueling plans, including a detailed core loading pattern, and (2) following startup, a startup test report providing the same infor-mation as the Cycle 2 Startup Report we submitted on June 24, 1977.
>~L42oo4o


This letter is in response to Mr. AD Schwencer's letter dated February 24, 1978 which requested us to furnish for Cycle 3 of the Donald C. Cook Nuclear Plant Unit 1 the following: (1) prior to startup for operation of Cycle 3, a brief description of the proposed refueling plans, including a detailed core loading pattern, and (2) following startup, a startup test report providing the same infor-mation as the Cycle 2 Startup Report we submitted on June 24, 1977.
Mr.
The following information is given in response to request (1).
Edson G.
Unit 1 was shutdown for refueli ng on April 6, 1978 and Cold Shutdown was attained on April 7, 1978.            The reactor vessel head was      lifted on the morning of April 21, and subsequently the reactor cavity and refueling canal were flooded wi th borated water. ,The fuel shuffle began on April 26, 1978 and was completed on May 2, 1978.                  Sixty-four expended Westinghouse        (W) supplied, fuel assemblies were re-moved and 64 new Exxon      Nuclear    Company (ENC) supplied fuel assemblies with 2.92 w/o enrichment      were      nserted into the reactor. The detailed core loading pattern      for  Cycle    3 is shown in the attachment.        A key to the  identification    codes  use  d  in the  core  loading    pattern  is included on a separate page of the attachment.                During the time of the  fuel shuffle,    a  sample  of  i rradiated  fuel  elements    supplied by each vendor was inspected by te levision camera.
Case This requires three additional days.
Following the fuel shuffle, inservice inspection of the reactor vessel welds, as required by Technical Specifications, was performed.
The rod drop'-time tests are to be conducted shortly before initial criticality for Cycle 3, which is presently scheduled for May 26, 1978.
This effort required 4 days. After reinstallation and securing of the reactor vessel head including reconne'ction of all instrumentation and equipment and reinstallation of the missile shield, the contain-ment integrated leak 'rate test will be performed.
Zero power physics tests are scheduled for the next four days.
                                                  >~L42oo4o
The zero power physics tests include power distribution maps, measurement of control rod bank'orths, isothermal temperature coefficient at various control bank insertions, boron endpoints, and shutdown margin if required by significant deviation of control bank worths from the calculated values.
 
The generator is projected to be paralleled to the system on approximately May 30,
Mr. Edson G. Case This requires three additional days. The rod drop'-time tests are to be conducted shortly before initial criticality for Cycle 3, which is presently scheduled for May 26, 1978. Zero power physics tests are scheduled for the next four days.                           The zero power physics tests include power distribution maps, measurement of control rod bank'orths, isothermal temperature coefficient at various control                     bank insertions,   boron endpoints, and shutdown margin control bank worths if     required by significant deviation of from the calculated values. The generator is projected to be paralleled to the system on approximately May 30, 1978, ending the refueling outage.                         The power ascension physics tests will then be conducted, including power coefficient measurement, power distribution maps at various power levels and incore-excore instrument calibration.
: 1978, ending the refueling outage.
The power ascension physics tests will then be conducted, including power coefficient measurement, power distribution maps at various power levels and incore-excore instrument calibration.
Other major activtties not related to refueling of the reactor which are planned for this outage are:
Other major activtties not related to refueling of the reactor which are planned for this outage are:
Installation of "J-tubes" in the steam generator feedwater sparger rings, Weighing of the required sample of ice baskets in the containment ice condenser, Opening and inspection of low pressure turbine "C", and Removal and inspection of the electrical generator rotor, In response to request (,2), we are planni'ng to write p Startup Test Report for Cycle 3 whi'ch will be submitted within 90 dyys of startup of Unit 1, Cycle 3, following completion of'tartup testi'ng.
Installation of "J-tubes" in the steam generator feedwater sparger rings, Weighing of the required sample of ice baskets in the containment ice condenser, Opening and inspection of low pressure turbine "C", and Removal and inspection of the electrical generator
This report will contain si'mi-lar. information as the Cycle .2 Startup Report submitted on June 24, 1977 following the Unit 1 startup for Cycl e 2.
: rotor, In response to request
Very  truly yours, JT; em                                                                                   0~)
(,2),
i'ce Presi.dent Sworn and Subscribed to before me on this I z. day of May, 1978 in New York County, New   York ary Publi'c J,rtt'! 0. 6tt!tt't"CK HotcQr Pu'Xfc, Sta>o of ttc;y York Ho. ".t-d634"r6 Qualitt"d ln ttsvi Yore County Commtsstcn Expires March 60,   t98',
we are planni'ng to write p Startup Test Report for Cycle 3 whi'ch will be submitted within 90 dyys of startup of Unit 1, Cycle 3, following completion of'tartup testi'ng.
This report will contain si'mi-lar. information as the Cycle.2 Startup Report submitted on June 24, 1977 following the Unit 1 startup for Cycl e 2.
JT; em Sworn and Subscribed to before me on this I z. day of May, 1978 in New York County, New York Very truly yours, i'ce Presi.dent 0~)
ary Publi'c J,rtt'! 0. 6tt!tt't"CK HotcQr Pu'Xfc, Sta>o of ttc;y York Ho. ".t-d634"r6 Qualitt"d ln ttsvi Yore County Commtsstcn Expires March 60, t98',
cc: Attached
cc: Attached


Mr. Edson G. Cas cc: R. C. Callen G. Charnoff P. W. Steketee R. Walsh R. J. Vollen R. W. Jurgensen D. V. Shaller Bridgman
Mr. Edson G.
Cas cc:
R.
C. Callen G. Charnoff P.
W. Steketee R. Walsh R. J. Vollen R.
W. Jurgensen D. V. Shaller Bridgman
 
DONALD C.
COOK NUCLEAR PLANT UNIT 1 KEY TO THE IDENTIFICATION CODES USED IN THE CORE LOADING PATTERN The upper identification code in each square classifies a core insert according to the following scheme:
Initial Letter T
e of Core Insert None RS SPS Thimble Plug Control rod (full length)
Control rod (part length)
Secondary neutron source rod The number following the initial letter(s) identifies the insert within its type.
The lower identification code specifies the fuel assembly.
The first letter in each fuel assembly identification code classifies the fuel batch or region according to the following scheme:
First Letter Re ion Fuel Batch D
W fuel from initial core ENC fuel new in'ycle 2
ENC fuel new in Cycle 3
The two digit number following the initial letter uniquely identifies each assembly within its region.
The last letter is a Unit 1 Specific Dummy Index.
No burnable poison rods are to be used in the Cycle 3 core.'
 
1
 
DONAI D C.
CYCLE 3 COOK NUCLEAR PLANT UNIT 1
CORE FUEL LOADING PATTERN RPNMLKJHGFED t
)
/8 Eisa g+
E97ri R.53 037 EQD 101
/=4k'i
/oc/D-
/po'u el zC I
2 A,li
/03 Cf7 C'480 c$$
Cce R,33 C'0/7 PSZ 7.
R,Z4 COWB al D/)
Res
/3 7+
R,0'P ZO CAD F~
ling/
77
/=SD go g
RZO b
RZ3 ng l(@
33 ll CZ RS I p
l25 39 4l 8
y8 R5to 5
P 03 i4/
2S IlO CWD EA,iy FI,IS lz) 3E )
90 y2. RZ8 vj
/0.24 ZZ /ZZ'P62 3
c3OD C03D ra R3l log c/80 cmo
/0/
Co C2ID l72 7l pe 4/D tl8
+Z
/3D z-C/oD P5 BED
)zq pal MOCJSO ge (rs Cmy ufo l.a R.]b 220 D//0 RS7 gg R.Z)
/~3' 41 c2o3
/gj g,C'f /23 SOIO<~ Eri R,l 'f D
847 CiO
/Z El2 57 E09'.
gl7 EO6p ~
D
@8 Ro/ 7Q zi c5to JA l2.'l D5' 70 23 4
Z7 SZ.
Rob RZz 9'g AD RSV /o+ R<.o mn uzi 7
ESSE 8C Cp7 s~
es F'I+
gag EZ~g Cayg
/
~27
/7D
/'+ Rzg
<24 D RSC R08 07$
',3o 7/I
/oe EO R,37 Wl c'ozD R3~
SdD
/27 852 P32.
Igz gZ'Z9'D 35 Po2 C270 yg f~fZ z
~mo P (G 8
/9G END dC R(<
la' 8 E2/f)
/b 3o Os E37D


DONALD C. COOK NUCLEAR PLANT UNIT 1 KEY TO THE IDENTIFICATION CODES USED IN THE CORE LOADING PATTERN The upper  identification    code  in each square classifies    a  core insert according to the following scheme:
[2
Initial Letter          T  e of  Core Insert None                  Thimble Plug Control rod (full length)
RS                    Control rod (part length)
SPS                    Secondary neutron source rod The number  following the    initial letter(s) identifies the the  insert within its type.      The  lower  identification code specifies fuel assembly. The  first letter in each fuel assembly      identification to the following code classifies the fuel batch or region according scheme:
First Letter                      Re ion            Fuel Batch W fuel from initial core D                                                  ENC fuel new in'ycle 2 ENC fuel new in Cycle 3 The two  digit number    following the    initial letter  uniquely identifies each  assembly within its region.
The  last letter is    a  Unit  1  Specific Dummy Index.
No  burnable poison rods are to be used in the Cycle          3 core.'


1 DONAI D  C. COOK NUCLEAR PLANT UNIT          1 CYCLE 3 CORE FUEL LOADING PATTERN t
l3 G
                                                                                                          )
AEP J/Z M$5 ODE OO ZJ ENDED
RPNMLKJHGFED                              101    /oc
/'/j E53D
                                                /=4k'i    /D-                        ling/          I
                /8 g+          R.53                                          el  zC Eisa E97ri      037 EQD
                                                        /po'u 2
A,li Cf 7 c$ $            R,33    PSZ R,Z4        al  Res    7+  R,0'P  ZO
              /03 C'480 Cce            C'0/7    7. COWB D/)          /3 CAD F~
go RZ3          RS I                    y8 R5to            P  03 2S IlO g          ng      p                        5                  i4/ CWD EA,iy 77        RZO l(@      ll  l25      4l                                      FI,IS  lz)
  /=SD          b 33    CZ      39 8                                            3E )
y2. RZ8    vj              l72 7 tl8                )zq    pal        RS7    gg    R.Z)
      /0 .24                        l                  MOCJSO            /~3'      41 c2o3 ZZ /ZZ'P62 /0/
3 c3OD C03D z-C/oD Cmy ge (rs ufo j
                                                                            /g g,C'f /23 /Z SOIO<~ Eri El2 90  ra R3l                  Co  pe      +Z    P5        l.a R.]b                      R,l 'f 57 E09'.
log c/80 cmo          C2ID 4/D /3D BED 220 D//0                      D      847 CiO gl7  l2.'l                23              Z7 SZ. Rob              RZz 9'g        7 EO6p  ~        D D5'                    4                                              AD ESSE
    @8  Ro/ 7Q            70                                              RSV    /o+ R<.o 8C zi c5to JA                                                              mn uzi            Cp7 s~ es F'I+                                          /27                  yg  f~fZ gag EZ~g Cayg
          /                    RSC            R,37 852 35 z
P (G
                                                                                  ~mo 8    /9G    [2
        ~27    /7D
          /'+ Rzg
                          <24 D      ',3oI 7/
Wl P32. Igz Po2 c'ozD                C270 dC    R(< la' 8 E2/f)
END l3 R08    /oe R3~        gZ'Z9'D
                                                                            /b 3o 07$ EO        SdD                          Os  E37D J/Z                     ZJ /'/j G                        M$5      ODE          ENDED    E53D AEP                                          OO


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Latest revision as of 15:30, 5 January 2025

Response to Letter of 02/24/78, Forwarding Information for Cycle 3 with Description of Proposed Refueling Plans & Following Startup
ML18219D819
Person / Time
Site: Cook  
Issue date: 05/12/1978
From: Tillinghast J
Indiana Michigan Power Co, (Formerly Indiana & Michigan Power Co)
To: Case E
Office of Nuclear Reactor Regulation
References
Download: ML18219D819 (9)
v • d • e


Text

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

DISTRIBUTION FOR INCOMING MATERIAL 50-315 REC:

CASE E G

NRC ORG:

TILLINGHAST J

'IN 5 MI PNR DQCDATE: 05/12/78 DATE RCVD: 05/23/7 DQCTYPE:

LETTER NOTARIZED:

NO COPIES RECEIVED

SUBJECT:

LTR 1

ENCL 1

RESPONSE

TO NRC LTR DTD 02/24/78...

FORWARDING INFO RELATING TO CYCLE 3 OF SUBJECT FACILITY CONSISTING OFi DESCRIPTION OF PROPOSED REFUELING PLANS'NCLUDING DETAILED CORE LOADING PATTERNS AND STARTUP TEST REPT PROVIDING SAME INFO AS CYCLE 2 REPT SUBMITTED g/Qgt77 REVIEWER INITIAL:

XJM DISTRIBUTOR INITIAL:~

DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS PLANT NAME: CQOK UNIT NOTES:

I 8c E 3 CYS ALL MATERIAL GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LICENSE.

(DISTRIBUTION CODE A001)

FOR ACTION:

INTERNAL:

EXTERNAL:

BR CHIEF SCHWENCER44W/7 ENCL FILES~W/ENCL

~C I.IANAUER++W/ENCL EISENHUT~~+W/ENCL BAER~~W/ENCL EEB~~W/ENCL J.

MCGQUGH+4W/ENCL LPDR S ST.

JOSEPH'I +~W/ENCL TIC4~~W/ENCL NS IC+4W/ENCL ACRS CAT B4+W/16 ENCL NRC PDR++W/ENCL OELD~~LTR ONLY CHECK+4W/ENCL SHAO~~W/ENCL BUTLER+4W/ENCL J COLLINS++W/ENCL DISTRIBUTION:

LTR 40 ENCL 39 SIZE:

3P+2P

%%%%%%%4%%4%%%4%%4 4'%%%%%%%%%%%%%%%4 THE END CONTROL NBR:

781420040

it

'I II

'm II6CK7 ALE I,'OPT INDIANA R Hl(%

N OWER COMPANY P. O. BOX 18 BOILING GREEN STATION NEW YORK, N. Y. 10004 May 12, 1978 Donald C.

Cook Nuclear Plant Unit 1

Docket No.

50-315 DPR No.

58 Mr.

Edson G.

Case, Acting Director Office of Nuclear Reactor Regulation Nuclear Regulatory Commission Washington, D.C.

20555

Dear Mr. Case:

is given in response to request (1).

ng on April 6, 1978 and Cold Shutdown The reactor vessel head was lifted subsequently the reactor cavity and th borated water.

,The fuel shuffle completed on May 2, 1978.

Sixty-supplied, fuel assemblies were re-Company (ENC) supplied fuel assemblies nserted into the reactor.

The detailed 3 is shown in the attachment.

A key d in the core loading pattern is the attachment.

During the time of rradiated fuel elements supplied by levision camera.

The following information Unit 1

was shutdown for refueli was attained on April 7, 1978.

on the morning of April 21, and refueling canal were flooded wi began on April 26, 1978 and was four expended Westinghouse (W) moved and 64 new Exxon Nuclear with 2.92 w/o enrichment were core loading pattern for Cycle to the identification codes use included on a separate page of the fuel shuffle, a sample of i each vendor was inspected by te Following the fuel shuffle, inservice inspection of the reactor vessel

welds, as required by Technical Specifications, was performed.

This effort required 4 days.

After reinstallation and securing of the reactor vessel head including reconne'ction of all instrumentation and equipment and reinstallation of the missile shield, the contain-ment integrated leak 'rate test will be performed.

This letter is in response to Mr.

AD Schwencer's letter dated February 24, 1978 which requested us to furnish for Cycle 3 of the Donald C.

Cook Nuclear Plant Unit 1 the following: (1) prior to startup for operation of Cycle 3, a brief description of the proposed refueling plans, including a detailed core loading pattern, and (2) following startup, a startup test report providing the same infor-mation as the Cycle 2 Startup Report we submitted on June 24, 1977.

>~L42oo4o

Mr.

Edson G.

Case This requires three additional days.

The rod drop'-time tests are to be conducted shortly before initial criticality for Cycle 3, which is presently scheduled for May 26, 1978.

Zero power physics tests are scheduled for the next four days.

The zero power physics tests include power distribution maps, measurement of control rod bank'orths, isothermal temperature coefficient at various control bank insertions, boron endpoints, and shutdown margin if required by significant deviation of control bank worths from the calculated values.

The generator is projected to be paralleled to the system on approximately May 30,

1978, ending the refueling outage.

The power ascension physics tests will then be conducted, including power coefficient measurement, power distribution maps at various power levels and incore-excore instrument calibration.

Other major activtties not related to refueling of the reactor which are planned for this outage are:

Installation of "J-tubes" in the steam generator feedwater sparger rings, Weighing of the required sample of ice baskets in the containment ice condenser, Opening and inspection of low pressure turbine "C", and Removal and inspection of the electrical generator

rotor, In response to request

(,2),

we are planni'ng to write p Startup Test Report for Cycle 3 whi'ch will be submitted within 90 dyys of startup of Unit 1, Cycle 3, following completion of'tartup testi'ng.

This report will contain si'mi-lar. information as the Cycle.2 Startup Report submitted on June 24, 1977 following the Unit 1 startup for Cycl e 2.

JT; em Sworn and Subscribed to before me on this I z. day of May, 1978 in New York County, New York Very truly yours, i'ce Presi.dent 0~)

ary Publi'c J,rtt'! 0. 6tt!tt't"CK HotcQr Pu'Xfc, Sta>o of ttc;y York Ho. ".t-d634"r6 Qualitt"d ln ttsvi Yore County Commtsstcn Expires March 60, t98',

cc: Attached

Mr. Edson G.

Cas cc:

R.

C. Callen G. Charnoff P.

W. Steketee R. Walsh R. J. Vollen R.

W. Jurgensen D. V. Shaller Bridgman

DONALD C.

COOK NUCLEAR PLANT UNIT 1 KEY TO THE IDENTIFICATION CODES USED IN THE CORE LOADING PATTERN The upper identification code in each square classifies a core insert according to the following scheme:

Initial Letter T

e of Core Insert None RS SPS Thimble Plug Control rod (full length)

Control rod (part length)

Secondary neutron source rod The number following the initial letter(s) identifies the insert within its type.

The lower identification code specifies the fuel assembly.

The first letter in each fuel assembly identification code classifies the fuel batch or region according to the following scheme:

First Letter Re ion Fuel Batch D

W fuel from initial core ENC fuel new in'ycle 2

ENC fuel new in Cycle 3

The two digit number following the initial letter uniquely identifies each assembly within its region.

The last letter is a Unit 1 Specific Dummy Index.

No burnable poison rods are to be used in the Cycle 3 core.'

1

DONAI D C.

CYCLE 3 COOK NUCLEAR PLANT UNIT 1

CORE FUEL LOADING PATTERN RPNMLKJHGFED t

)

/8 Eisa g+

E97ri R.53 037 EQD 101

/=4k'i

/oc/D-

/po'u el zC I

2 A,li

/03 Cf7 C'480 c$$

Cce R,33 C'0/7 PSZ 7.

R,Z4 COWB al D/)

Res

/3 7+

R,0'P ZO CAD F~

ling/

77

/=SD go g

RZO b

RZ3 ng l(@

33 ll CZ RS I p

l25 39 4l 8

y8 R5to 5

P 03 i4/

2S IlO CWD EA,iy FI,IS lz) 3E )

90 y2. RZ8 vj

/0.24 ZZ /ZZ'P62 3

c3OD C03D ra R3l log c/80 cmo

/0/

Co C2ID l72 7l pe 4/D tl8

+Z

/3D z-C/oD P5 BED

)zq pal MOCJSO ge (rs Cmy ufo l.a R.]b 220 D//0 RS7 gg R.Z)

/~3' 41 c2o3

/gj g,C'f /23 SOIO<~ Eri R,l 'f D

847 CiO

/Z El2 57 E09'.

gl7 EO6p ~

D

@8 Ro/ 7Q zi c5to JA l2.'l D5' 70 23 4

Z7 SZ.

Rob RZz 9'g AD RSV /o+ R<.o mn uzi 7

ESSE 8C Cp7 s~

es F'I+

gag EZ~g Cayg

/

~27

/7D

/'+ Rzg

<24 D RSC R08 07$

',3o 7/I

/oe EO R,37 Wl c'ozD R3~

SdD

/27 852 P32.

Igz gZ'Z9'D 35 Po2 C270 yg f~fZ z

~mo P (G 8

/9G END dC R(<

la' 8 E2/f)

/b 3o Os E37D

[2

l3 G

AEP J/Z M$5 ODE OO ZJ ENDED

/'/j E53D

(t.

4 YvY ~ ~' ) -'

j~p

/

L

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