ML19210A803
| ML19210A803 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/14/1978 |
| From: | Mitchell D METROPOLITAN EDISON CO. |
| To: | |
| Shared Package | |
| ML19210A781 | List: |
| References | |
| NUDOCS 7910310689 | |
| Download: ML19210A803 (7) | |
Text
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AVERAGE DAILY UNIT POWER LEVEL Docket No.
50-289 Unit TMI-1 Date b-lh-78 Completed By D. G. Mitchell Telephone 215-929-3601 Ext. 169
!.mm{ MARCH DAY AVERAGE DAILY PO'4ER LEVEL DAY AVERAGE DAILY POWER LEVEL (Kle-Net)
(Kle-Net) 628 17 Th0 1
600 16
-25 2
6h6 19
-13 3
h 782 2C
-9 780 21
-7 5
6 TTT 22
-T
-6 7
779 23
-6 TT6 2h 8
780 6
25 o
-783
- 26
~
10
-6 679 27 11 595 28
-5 12
-5 598 29 13
-6
-669-30 l'a.
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-._b Tne negative numbers indicate that more energy was supplied to the unit than ns produced during that day.
1Eo9 044 7910810
1PERATING DATA REPCRT 7ceket No. 50-289 Date April 14., 1976 Completed 3y D. C. 'fitchell Telephene 215 c?o '601 -e:.16 CPERATING STATUS 1.
Unit Nane:
Three Mile Island. Unit 1 2.
Reporting Pericd: March 1978 3
Licensed Thermal Power (.Wt):
ec,e k.
Nameplate Rating (Gress We):
8 ?'_
5 Design Electrical Rating (Net We):
819 6.
Max. Dependable Capacity (Gross We):da0 7
Max. Dependable Capacity (Net We):
woe 8.
If Changes Occur in Capacity Ratings (Ite=s No. 3 thrcush 7) Since Last Report, Give Reasons:
N/A 9
Fever level to which Restricted. If Any (Net.We):
ro N/A 10.
Reascns fer Restrictions, If Any:
Sis Menth Yr.-tc-Cate Cu=ulative 744 2160 31,369 11.
Ecurs in Reporting Period 12.
No. of Ecurs Reacter was Critical kC8 182h 2h.88 2.3 0
0 838.5 13 Reactor Reserve Shutdevn Ecurs h08 182k 24,h21.5 1k.
Hours Generator On-Line 15 Unit Reserve Shutdevn Ecurs o
o n
16.
Grcss Thermal Energy Generated (!f4H) 9h6,062 h,h69,915 59,863,h8C 17.
Gross Elect. Energy Go irsted (WH) 310cc5 1,491,977 19,985,77:
18.
Net Electrical Energy Geaerated (WH) cAng:h
, hon ch-
, o,, o n h.-
5k.8 Sh.h 77.9 19 Unit Service Factor 20.
Unit Availabilit/ Facter c:h 2 ah h
-e 21.
Unit Capacity Facter (Using MDC Net) h9.0 Si.c vs.i 22.
Unit Capacity Facter.(Using DER Net) 47.2 79.2 72.9 5.2 23 Unit Forced Outage Rate o
o 2h.
Shutdevns Scheduled Over Next 6 Months (Type, Date, and Daratien of Zach):
April 27, 1973 25 If Shut Devn at End cf Report Period, Estimated Date of Startup:
- 26. Units In Test Status (Frier to Cc nercial CT.aration):
FCRECAST ACH1 TIED INIT AL CRITICAL!1"'
INITIAL E1EC'"RICITY CC:0E?CIAl 0FERA!!CN
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Docket No. 50-289 I'
1RTIT SHUTDOWNS AND POWER REDUCTIONS Unit Name THI-1 RFPORT MONTil MAncH Date h-11s-78 Completed By D. G. Mitchell Telephone 215-929-3601 Mxt. 169 No.
Date Tyre 'h ;, y System Component Cause and Corrective l
Code I6 Code 5 Action to ej g /
g, o tgm gg ggo g
g Prevent Recurreice
. bmi e
dNS 8Ej s us!
3An 2
3/1/78 F
0 A
1:
Feedwater heater leaks 3
3/11/78 F
0 A
la Feedwater heater leaks 4
3/18/78 3
336 C
1 l
E I
i.
I.
l h
.s i
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2 'eason:
3
" Exhibit G - Instructions 1: Forc ed F
R Method:
'3: Scheduled A'-Equipment Failure (Explain)
- E"#"
1-Manu al n
s for Meensee L -]
B-Maintenance or Test 2-Manual Scram.
Event Report (LER) File C-Re fueling 3-Automatic' Scram.
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. C Regulatory Restriction 14-Other (Explain) i d-Operator Training & Licensee Examination g
F-Adriinistrative r
s 0
Cys C -Op<trational Error (Ex' plain)
Exhibit 1 - Same Source ll-Other (Explain)
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TMI-1 OPERATING
SUMMARY
~
UtlIT PERFORMANCE The Unit began the month at about 83" power as a result of feed water heater leak repair work which had ccmmenced lagt month. The Unit returned to 100%
power on 03/03/78 but at reduced load (s 15 MWe) due to the "B" high pressure string remaining isolated. On 03/11/78 Unit power was reduced to 75% to repair the gasket leak on the 1B feedpump discharge flow nozzle (FE-8).
The Unit returned to 100% power within 71.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> but still at reduced load due to the isolation of the "B" high pressure string. On 03/16/78 the Unit pcwer was reduced to approximately 98" due to the End of Life reactivity deficiency. This power reduction was the first of several planned step pcwer reductio 1s in order to extend Core Cycle 3 frem the original max. of 250 to 315 EFPD.
Because of the earlier power reductions to repair the feed..ater system problems, enly the first step cf the power coast down scheme was executed.
On 03/17/78, the Unit shutdcun to ccmmence the 1978 Refueling Outage.
Refueling Outage Milestenes which were ccmpleted this month are as follows:
03/22/78 - Incore Detectors Chopped 03/23/78 - Reactor Vessel Head Removed 03/29/78 - Turbine LPA and HP Rotor Removed 03/31/78.- Fuel Shuffle Ccmplete SIG:!!FICANT POUER REDUCTI0tlS 1.
03/01/78 to 03/03/78 (68.6 Hrs.) at 83" prwer due to "B" feedwater heater string (both HP & LP) being isolated.
The Unit returned to 100% Reactor Power on 03/03/78 with the "B" HP FW string isolated. This reduction in feedsater heating caused a loss of unit efficiency equivalent to about 15 Mie.
2.
03/11/78 to 03/14/78 (71.5 Hrs.) at 75% jewer due to a gasket leak on the 18 feed pump discharge ficw nozzle (FE-8).
3.
03/15/78 to 03/17/78 (39 Hrs.) at 98", pcwer due to End of Life Reactivity deficiency.
03/17/78 to 03/31/78 at 0", ocwer due to 1978 Refueling Outage.
N T b Q/
J 'E
--. ' JELING INFORMATION REQUEST 1.
- are of Facility: Three Mile Island Unit No. 1 2.
Scheduled date for next refueling shutdown: March 17, 1979 3
Scheduled date for restart following refueling:
May 15, 1978 for Reactor Criticality (tentative - present refueling) h.
Will refueling or resu=ption of operation thereafter require a technical specification change or other license amendment?
Yes If answer is yes, what in general, vill these be?
The Technical Specificatien change for Cycle h vill provide revised Operational limits for red withdraval index and Power I= balance.
Also the Core Protection Safety Li=its and the Protection System Maxi =us Allevable Setpoints for Reactor Pever Inbalan:e have been slightly revised. The quadrant power tilt li=it vill be changed from a maximu:
actual core tilt of 3.h15 to h.925 If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Cct=ittee to deter =ine whether any unreviewed safety questions are associated with the core reload (Re f. 10 CTE Section 50 59)?
U/A If no cuch review has taken place, when is it scheduled?
N/A 5
Scheduled'date(s) for submitting preposed licensing action and supporting-infor=ation.
Technical Specification Change Request #70 and #70 A vere submitted to the URC on 1-9-78, and k-3-78, respectively.
6.
Important licencing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new cperating procedures.
are holi portant. licensing considerations acsceisted %ith Cycle L.
"x a-a cperation~.
TMI-l vill change from a redded to a feel-bleed mode of
'~
cperation..for Cycle h.
.This change ic not regarded an a tsjor change in the operating =cde since TMI-1 was cperatel in essentially a rcIs-cut configura:len during the latter par: of Cycle 1 and Cycic 3 7
The numaer of fuel assemblies (a) in the core and (b) in the spent fuel stcrage poc_.
(2) 177 (b) 160 (after 1973 refueling outage)
C. ' q9b lr.., o )
t-SAFETY RELATED MAINTENANCE During the month of March the following maintenance was performed:
On March 17, 1978 at 2400 the turbine generator was taken off line to commence the refueling outage. The reactor coolant system was cooled down and depressurized in preparation for Reactor Vessel work.
The following work was performed in preparations for the fuel shuffle:
1.
Reactor Vessel head 'ans removed 2.
Reactor Vessel head cables disconnected 3.
Reactor Vessel APSR's and CROM's uncoupled and parked 4.
Reactor Vessel head detensioned and removed 5.
Vent valve inspection performed 6.
FTC filled to refueling level The Reactor refueling shuffle ccmmenced on March 27 and was completed and verified on March 31, 1978.
Reactor Coolant Pump 13, #2 and #3 and pump 1C, #1, #2 and #3 seals were rer.oved for periodic inspection. A blank flange was installed to allow the reactor refueling to continue while the seals were inspected.
Seals were inspected and worn parts replaced.
RC-RV-1A was removed for pop testing per technical specification.
A spare valve, tested prior to the refueling outage,was installed in its place. The old RC-RV-1A valve was pop tested to ensure the setpoint was within the specified limits. The valve tested satisfactorily. The valve will be sent out at a later date for overhaul.
RCS nitrogen overpressurization modification was performed as required to fulfill a prior NRC ccmmittment.
.Priot to. starting fuel : shuffle s 35 incore.detecto.rs.wer.e. pulled.for.
replacement. Remaining incares were pulled ta the parked position for f
fuel shuffle.
New inceres to be installed upon completion of' fuel shuffle.
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'8. ' The present licensed spent fuel pool storage capacity and the size of E -
increase in licensed storage capacity that has been requested or is pla.ned, in nu=ber of fuel assemblies.
Recently licensed for 752 fuel assemblies storage location: in the M3 spent fuel pools, h96 location B pool racks to be installed starting in Februa / 1978.
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