ML18219D819

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)

Text

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

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: ~

DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS NOTES:

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

(DISTRIBUTION CODE A001)

FOR ACTION: BR CHIEF SCHWENCER44W/7 ENCL INTERNAL: F ILES~ W/ENCL NRC PDR++W/ENCL

~C I.IANAUER++W/ENCL OELD~~LTR ONLY CHECK+4W/ENCL I

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

%%%%%%%4%%4%%%4%%4 4'%%%%%%%%%%%%%%%4 THE END

it 'I II

'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

Dear Mr. Case:

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.

The following information is given in response to request (1).

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.

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.

>~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 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.

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.

Very truly yours, JT; em 0~)

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',

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 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

)

RPNMLKJHGFED 101 /oc

/=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

(t.

4

~ ~' -'

YvY

)

j~p

/ L