ML20027D446
| ML20027D446 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/15/1981 |
| From: | Smyth C METROPOLITAN EDISON CO. |
| To: | |
| Shared Package | |
| ML20027D443 | List: |
| References | |
| NUDOCS 8211040310 | |
| Download: ML20027D446 (6) | |
Text
.
OPERATING DATA REPORT DOCKET NO.
50-289 DATE Sect. 15, 1981 COMPLETED BY C. W. Srnvth TELEPHONE i'li) si.E-8 5 51 OPERATING STATUS Three Mile Island Nuclear Station, Unit 1
- 1. Unit Name:
Aueust. 1981
- 2. Reporting Period:
2535
- 3. Licensed Thermal Power (MWt):
871
- 4. Nameplate Rating (Gross MWe):
019
- 5. Design Electrical Rating (Net MWe):
- 6. Maximum Dependable Capacity (Gross MWe): {0 e/6
- 7. Maximum Dependable Capacity (Net MWe):
- 8. If Changes Occur in Capacity Ratings (items Number 3 Through 7) Since bst Report.Give Reasons:
- 9. Power Leve! To Which Restricted,if Any (Net MWe): -
- 10. Reasons For Restrictions.If Any:
This Month Yr..to.Date Cumularise 744.
5831.
61344.
I1. Hours in Reporting Period 0.0 0.0 31731.8
- 12. Number Of Hours Reactor was Critical 0.0 839.5 0.0
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 31180.9
- 14. Hours Generator On-Line 0.0 0.0 0.0
- 15. Unit Reserve Shutdown Hours 0.0 0.0
- 76531071,
- 16. Gross Thermal Energv Generated (MWH)
O.
O.
254e4330.
- 17. Gross Electrical Energy Generated (MWH) u.
U.
zJb*uun.
- 18. Net Electrical Energy Generated (MWH) 0.0 0.0 50.8
- 19. Unit Service Factor 0.0 U.0 50.6
- 20. Unit Availability Factor 0.0 0.0 49.5
- 21. Unit Capacity Factor (Using MDC Net) 0.0 0.0 47.5
- 22. Unit Capacity Factor (Using DER Net) 100.0 100.0 42.3
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Over Next 6 Months (Type.Date.and Duration of Eachl:
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
Forecast Achieved
- 26. Units in Test Status (Prior to Commercial Operation!:
INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCI AL OPER ATION B211040310 810916 POR ADOCK 05000289
- gg7, R
AVER AGE D AILY UNIT POWER LEVEL DOCKET NO.
50-289 TMI-I W'IT September 15, 1981 DATE COMPLETED BY C. k'.
Smyth (717) 948-8551 TELEPHONE August, 1981 MONTH DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Net) g gwe.Neti I
O 17 0
0 2
0
- 3 0
3 0
g9 0
4 0
20 5
0 21 0
6 0
27 0
,7 0
3 0
0 8
21 0
0 9
25 0
10 26 0
1 0
1I 27 0
1 28 0
0 13 29 0
0 14 30 0
o 15 3,
0 16
- h.
PT l
l.
50-289 UNii SilU1 DOWNS AND POWER REDUCTIONS DOCKET NO.
UNIT N AME
'A lli-l DATE September 15, 1981 REPORT MONTil August, 1981 COMPLET EI) RY
_C. W. Smyth TELErilONE (7171 94R-8551 "k
hn,
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[h I.icensee E,
Cause & Corrective g
~E Event 7
o3 Action to No.
DJte Q
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H
$E cE j ;?, g Iteport sr in u o
Prevent Recurrence d
" I'" " #7 "" # "
1 8/1/81 F
744 0
1 1
2 1
4 F: Forced Reason:
Method:
Exhibit G -Instructhms S: Sclieduled A-Equipment Failure (Explain) 1 Manual for Preparation of Dits H Maintenance ci Test 2 Manual Scram.
Entry Sheets for I.r.ensee C ReIncling 0 Airtomatic Scram.
Even't ReporI (l.ER) File INilRI.G-D Regulatory Restriction 1 Other (Explain) 0161)
E Operator Training & l_icense Examination F Administrative 5
G-Operathmal Error (E= plain)
Exhibit I - Same Source Il Other I Explain)
OPERATIONS
SUMMARY
During the August report period the unit was in cold shutdown by order of the NRC until August 20, when Hot Functional Testing was commenced.
All testing was performed using RCP heat for the RCS and Auriliary Boilers to heat the secondary. Testing was performed for several
. reasons:
1.
To permit operator training with the plant hot.
2.
Perform testing to determine system and equipment integrity and ensure proper installation of restart modifications.
3.
Perform many Tech Spec Surveillances that could not be per-formed since the last refueling (Spring 1979).
The following is a sequence of events for the testing through the end of August.
8/20 - Performed Makeup and RCS systen valve lineups, filled RCS, drew bubble in pressurizer, pressurized to 50 pounds and performed 50 pound CRDm vent, performed various Tech Spec Surveillances and Testing.
8/21 - Established RCS "Daisey Chain" cleanup, changed seal injection filters, increased RCS pressure to 300 pounds, bumped RCPs and performed 300 pound CRDm vent, established RCP seals.
Per-formed various T.S. Surveillances and Testing.
8/23 - Drew vacuum in condenser and placed secondary on cleanup.
Performed T.S. Surveillances and Testing.
t 8/26 "B" Feedwater string cleaned and in service.
Performed T.S. Surveillances and Testing.
8/27 - RCS to 250 F, 400 pounds. Performed T. S. Surveillances and Testing.
8/28 - RCS to 530 F, 2155 pounds. Performed T.S. Surveillances and Testing.
8/29 - RCS to 530 F, 2285 pounds for RCS leak test. Performed T.S. Surveillances and Testing.
8/30 - RCS to 530 F, 2155 pounds.
Major tests performed were as follows.
l I
l Test new industrial cooler Ventilation balance of Aux / Control Building Leak test of various primary system check valves Intermediate closed cooling flow balance l
Non Nuclear instrumentation testing Tsat meter calibration check l
RCP Op/ Flow functional testing l
Source range instrument functional test RCS pipe thermal checks Diesel load test g
i PORV acoustic monitor test f
Main steam safety valve testing
't RCS leak rate testing CRDm movement and drop times Turbine roll and testing
Operations Summary l
Page 2 There were no major problems identified during the testing. Chemistry, both primary and secondary came into spec. with on1v minor problems.
There were no major system or equipment malfunctions. Worklists resulting from the heatup deal.primarily with expected findings such as adjustment or replacement of valve packing.
Specific problems, although minor in nature included:
- 1) Aux vacuum pump - damaged bearing
- 2) Poor new industrial cooler performance
- 3) Condensate booster pump seal repairs
- 4) Powdex vessel element replacement Most problems identified have been repaired; the remaining are scheduled for repair.
The testing was very effective in giving new operators training and in verifying system integrity and reliability in preparation for restart.
MAJOR SAFETY RELATED MAINTENANCE None performed during August.
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- l REFUELING INF0PJiATION REOUEST 1.
Name of Facility:
Three Mile Island Nuclear Station, Unit I 2.
Scheduled date for next refueling shutdown:
Unknown 3.
Scheduled date for restart following refueling:
Unknown 4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
If answer is yes, in general, what will these be?
If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to determine 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.
t 5.
Scheduled date (s) for submitting proposed licensing action and supporting information:
N/A 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 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 number of fuel assemblies:
The present licensed capacity is 752.
There are no planned increases at this time.
The projected date of the last refueling that can be dischahged to the spent 9.
fuel pool assuming the present licensed capacity:
1986 is the last refueling discharge which allows full core off-load capacity (177 fuel assemblies).
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