ML18219D819
| 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
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
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'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.
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