ML19343B993
| ML19343B993 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/15/1981 |
| From: | Mitchell D METROPOLITAN EDISON CO. |
| To: | |
| Shared Package | |
| ML19343B991 | List: |
| References | |
| NUDOCS 8102180468 | |
| Download: ML19343B993 (6) | |
Text
O OPERATING DATA REPORT DOCKET NO.
50-289 DATE February 15, 1981 COMPLETED BY D-C. Vi*chell TELEPHONE
'7173 wes-8553 OPERATING STATUS Three Mile Island Nuclear Station, Unit I
- 1. Unit Name:
"""" U 1
- 2. Reporting Period:
2535
- 3. Licensed Thermal Power (MWt):
671
- 4. Nameplate Rating (Gross MWe):
019
- 5. Design Electrical Rating (Net MWe):
- 6. Maximum Dependable Capacity (Gross MWe): {0
- D
- 7. Maximum Dependable Capacity (Net MWe):
- 5. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report.Give Reasons:
- 9. Power Level To which Restricted. lf Any (Net MWe):
- 10. Reasons For Restrictions.If Any:
This Month Yr to-Date Cumulatise 744.
744.
56257.
- 11. Hours in Reporting Period
,0.0 0.0 31731.8
- 12. ' umber Of Hours Reactor Was Critical
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 839. 5 0.0 0.0 31180,9
- 14. Hours Generator On.Line 00 0.0 0.0
- 15. Unit Reserve Shutdown Hours 0.0 0.0 76531071.
- 16. Gross Thermal Energy Generated (MWH)
O.
O.
25464330.
- 17. Gross Electrical Energy Generated (MWH) u.
U.
4454vuaa.
- 18. Net Electrical Energy Generated (MWH) 0.0 0.0 55.4
- 19. Unit Service Factor 0.0 U.U 55.4
- 20. Unit Availability Factor 53.9 0.0 0.0
- 21. Unit Capacity Factor (Using MDC Net) 0.0 0.0 51.7
- 22. Unit Capacity Factor (Using DER Net) 100.0 100.0 36.3
- 23. Unit Forced Outage Rate
~
- 24. Shutdowns Scheduled Over Next 6 Months (Type.Date,and Duration of Each):
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units in Test Status (Prior to Commercial Operation):
Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCI AL OPERATION sioniso g (4/77i L,
i AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. _50-289 THI-I UNIT 1,
DATE February 15, 1981 l
COMPLETED BY D. G. Mitchell (717) 948-8553 TELEPHONE January 1981 MONTH DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe NetI (Mwe. Net )
I O
17 0
2 0
0 16 3
0 0
19 4
0 0
20 S
O 0
21 6
0 0
22 7
0 0
23 8
0 0
24 0
0 9
25 0
0 10 26 0
11 27 0
12 0
28 0
0 13 29 0
0 14 30 0
15 0
0 31 16 0
)
s 49
~
j
'e "
~
s 50-289 UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO.
UNIT NAME 'IMI-I DATE February 15, 1931 COMPLE1ED ay D. G. Pfitelm11 REPORT MONTil.Janunry 1981 TELFPflONE (717) 948-8553
'3 ea 2 y
5-ce I.icensee E4
- n Cause & cor,ccig,e No.
Date 8.
5$
5 7.E y
{d 4
4-yJ
.g 5 e Event g.g Adion to E
y di y Report a
- G Prevent Recurrence oO E
6 g
Reginintory Restraint Order 1
810101 F
744 9
1 Y
l G
Les9 WA)
C==D V2)
Ls?)
W JEED^
IJ l.
2 3
4 F: Forced Reason:
Method:
Exhibit G -Instructions S: Scheduled A Equiprnent Failure (Explain) l Manual for Preparation of Data B Maintenance of Test 2 ManualScram.
Entry Sheets for I.icensee C-Refueling 3 Automatic Scram.
Event Report 11.1 R1 File INtIRI G D-Regulatory Restriction 4-Oiher (Explain) 0161)
E-Operator Training & IJcense Examhiation F-Administrative 5
Exhibit I - S.nne Snorce G Operational Error (Explain)
Il-Other (Explain)
OPERATIONS
SUMMARY
j The Unit was in cold shutdown the entire conth by order of the Core cooling was provided by the Decay Heat System.
NRC.
l During the month a preplanned training / test program was conducted involving the primary plant systems and components. This program included heatup of the primary system to 185 F.
During the period between 1/16/81, and 1/30/81, the following evolutions were conducted.
January 16 - RCS filled (from partially drained)
- 45 psig CRDM vent completed January 17 - Make-up system in operation (ran all make-up pumps)
- RCS cleanup established (found acceptable crud levels)
- Ran all RC pumps
- Make-up system leak discovered (see LER-81-01 for i
detailed report)
January 18 - Plant depressurized MU system secured Between January 18, and 25, 1981, the make-up system leaks were repaired and the program continued as follows.
1 January 25 - MU system in operation
- Seal injection and cleanup chain established
- RCS at 300 psig January 26 - Ran RC pumps
- Vented CRDMs at 300 psig January 28 - Control rods withdrawn i
- Completed source range testing January 30 - Plant depressurized and nitrogen blanketing estab-lished on RCS In addition to enabling hands-on training for most operators, several y
other benefits were gained from the program:
i
- 1) A program was established which verified no loose parts in the Reactor Coolant-System.
- 2) The RCS was found to be leak tight.at 300 psi, verifying the soundness of several primary system check valves on which maintenance has been performed (see previous mcathly operating reports).
- 3) The ability to operate -all CRDMs was verified (no binding was -
l evident).
4)
Suberitical multiplication was produced verifying the operability of the source range detectors and instrumentation.
- 5) Acceptable crud levels were found in the Reactor Coolant System and existing levels were reduced.
As expected a significant number of work items were generated as a result of the program. There were no major areas of concern un-covered however.
It was concluded that, based on the training received and on the plant equipment performance,- the program was very successful.
i
MAJOR SAFETY RELATED MAINTENANCE During the month of January,1981, the following major maintenance items were performed.
Spent Fuel System Loop "B" was in operation while weld repairs were performed on the "A"
loop.
The following work uas performed as part of the on-going intergranular stress corroaion cracking repair program:
- Weld #195 (Discharge of Spent Fuel Pump "A")
- Weld #503 (Suction of Spent Fuel Pump "A")
- Weld #501 (Suction of Spent Fuel Pump "A")
- Weld # 300 (Spent Fuel Cask Loading Pit drain / full line)
Repairs included either installation of a new spool piece or removing indication / rewelding.
Functional test of the weld repairs is in progress.
Emergency Diesel Generator "B" annual inspection was performed with minor repairs performed. Balancing of the generator was performed to lower vibration readings.
Stop check valve work progressed with FW-V-12A/B being reassembled and valves torqued to final value. Various make-up system stop check valves, on which work was performed (see previous monthly operating reports), were retorqued.
Refueling Outage Surveillance Testing items were performed. Ten (10) snubbers were removed for functional testing and some were reinstalled af ter testing was performed satisf actorily. One snubber f ailed to lockup requiring an additional ten (10) more snubbers to be removed and tested. Work will continue into February.
4 9
PIFL"ZLING INF0FF.ATION FIOL'EST 1.
Na=e of Facility:
Three Mile Island Nuclear Station, Unit I 2.
Scheduled date for next refueling shutdown:
Unknown 3.
Scheduled date for restart following refueling:
Unknowr.
4.
k'ill refueling or resu=ption of operation thereaf ter require a technical specification change or other license amend =ent?
If answer ir yes, in general, what will these bs?
If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Co==ittee to deter =ine whether any unreviewed safety questions are associated with the core reload (Ref. 10 CFR Section 50.59)?
If no such review has taken place, when is it scheduled?
Amendment No. 50, Cycle 5 reload, was approved on 3-16-79.
5.
Scheduled date (s) for submitting proposed licensing action and supporting infor=ation:
N/A 6.
Important licensing considerations associated with refueling, e.g. new or different fuel design or supplier, unreviewed design or perfor=ance analysis methods, significant changes in fuel design, new operating procedures:
N/A 7.
The number of fuel assemblies (a) in the core, and (b) in the spent fuel storage pool:
(a) 177 (b) 208 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 nu=ber of fuel asse=blies:
The present licensed capacity is 752.
There are no planned increases at this time.
9.
The projected date of the last refueling that can be discharged to the spent fuel. pool assuming the present licensed capacity:
1986 is the last refueling discharge which allows full core off-load 2
capacity (177 fuel assemblies).
k
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