ML19210A100
| ML19210A100 | |
| Person / Time | |
|---|---|
| Site: | Crane |
| Issue date: | 03/14/1978 |
| From: | Herbein J METROPOLITAN EDISON CO. |
| To: | Hartfield R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| GQL-0429, GQL-429, NUDOCS 7910240820 | |
| Download: ML19210A100 (4) | |
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. Y REOULATOR'r u 4, GP!1ATION DISTRIEUTION SYSTEM (RIDS)
DISTRIBUTION FOh INCCMING MATERIAL 50-25#
REC: HARTFIELD R A JRG-HEREEIN J G DOCD W 00 14'75 NRC t1ETROPOL EDISON DATE RLJD-O? 'l : N OCCTYFE: LETTER NOTARIZED. tJO COPIEE RECEIVED S UE._:EC T -
LTR 1 E*:CL 10 CCt1FLETED REFUELING INFORMATION REOUEST FOR SUB. JECT FACILITY LIC. NO DFP-50 PLANT NANE: THFEE MILE ISLAND - UNIT 1 REVIEWER INITIAL.
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METROPOL! FAN EDISON COMPANY POST OFFICE BOX 542 REACING. PENNSYLVANI A 19603 TELEPHONE 215 - 919-0601 March 1k, 1978 GQL 0429 4 'g,
[C[h O-I1 Mr. R. A. Hartfield, Acting Director U
Office of Management Information & Prog an Control lM 44 g* ISA '[O' U. S. Nuclear Regulatory Cc= mission G
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Dear Sir:
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Three Mile Island. Nuclear Statien, Unit 1 (TE-1)
GI Operating License No. DPR-50 Docket No. 50-289 Enclosed please find ten (10) copies of the completed Refueling Inforraticn Request for Three Mile Island Nuclear Station, Unit 1.
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v J. G. Herbein Vice President-Generatica JGH:DGM:ej g Enclcsure 1489 127 Goof g M mom
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RETUELING INTOPMATION PSUEST 1.
Name of Facility: Three Mile Island Unit No. 1 2.
Scheduled date for next refueling shutdevn: March 17,1978 3.
Scheduled date fo* restart following refueling:
May 15, 1978 for Reactor Criticality (tentative) h.
Will refueling or resumption of cperation thereafter require a technical specification change or other license nendment?
Yes If answer is yes, what, in general, vill these be?
The Technical Specification change for Cycle h will provide revised operational limits for red withdrawal index and Power Idbalance. Also the Core Protection Safety Limits and the Protection System Maximum Allevable Setpoints for Reactor Power Imbalance have been slightly revised.
The quadrant power tilt limit vill be changed from a maxi =um actual core tilt of 3.hl% to h.925.
If answer is no, has the reload fuel design and core ecnfiguraticn been reviewed by your Plant Safety Review Conmittee to determine whether any unreviewed safety questions are associated with the core reload (Ref.10 CFR Section 50 59)?
N/A If no such review has taken place, when is it scheduled?
N/A 5
Scheduled date(s) for submitting propcsed licensing action and supporting information.
Technical Specification Change Request #70 was submitted to the NRC on 1/9/78.
6.
Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel nesign, new operating procedures.
There are no important licensing considerations associated with Cycle h operation. TMI-l vill change frem a redded to a feed-bleed mode of cperation for Cycle k.
This change is not regarded as a major change in the operating mode since TMI-1 was operated in essentially a rods-cut con-figuration during the latter part of Cycle 1 and Cycle 3 7
The number of fuel assedblies (a) in the core and (b) in the spent fuel storage pool.
(a) 177
( b,' 10h (start of 1978 refueling cutage) 8.
The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in nudber of fuel assemblies.
Recently licensed for 752 fuel assembies storage locations in the A&3 spent fuel pools. h96 location 3 pool racks to be installed starting in February 1978.
1489 128
O 2-Refueling Infor:ation Request u1" 1 ss r.g the preser+ 11 rs capaci+-
1986 is nst refueling discharge which allows '~ull 2'a
-l ad capacity er (177 fuel assemclies).
1489 129