ML19210A784
| ML19210A784 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/13/1978 |
| From: | Herbein J METROPOLITAN EDISON CO. |
| To: | Volgenau E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| Shared Package | |
| ML19210A785 | List: |
| References | |
| GQL-0416, GQL-416, NUDOCS 7910310675 | |
| Download: ML19210A784 (2) | |
Text
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YY REGULATORY INi OReiATION DISTRIBUTION SYSTEM (RIDS)
DISTRIEUTIOil FOR INCOMING MATERIAL 50 JP' REO: VOLGENAU E ORG-HEREEIN J G DOCDM E' 2 '1: ':
NRC t1ETROPOL EDISON DATE FC'd-
' I '20 ~'s DOCTYPE: LETTER NOTARIZED: NO COPIES CZIEIVED SUBJECT-LTA 1 ENCL 1 MONTHLY OPERATING REPT FOR THE NONTH OF FEERUARY, 1979.
PLANT NAME: THREE MILE ISLAND - UNIT 1 FEVIEUER INITI L:
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NONTHLY OPERATING REPORT FOR ORAY EOOK FFEPAPATION.
(DISTRIEUTION CODE A003)
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j $s- 0.s, Mr. E. Volgenau, Director H
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U. S. Nuclear Regulatory Conmission s
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Dear Sir:
Three Mile Island Nuclear Station Unit 1 (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Enclosed please find two (2) copies of the February Operating Report for Three Mile Island Nuclear Station Unit 1.
"*1cerely J.
. Herbein Vice President-Generation JGH:DGM:ej g Enclosure ec:
Mr. 3. H. Grier, Director Office of Inspecticn & Enforcement, Regicn I U. S. Nuclear Regulatory Cec =issicn 631 Park Avenue King of Prussia, Pennsylvania 19h06 Director (2 ccpies)
Office of Management Information & Program Centrol c/o Distribution Services Branch DPC, AEM U. C. Nuclear Regulatory Cec =issicn
'4ashingten, D. C.
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AVERAGE DAILY UNIT POWER LEVEL 50-289 Decket No. IhT'1 Unit 3-10-73 Date D. G. Mitchell Completed By Telephone 020 1601 Fe. 169 MONTH February, 1978 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (M*4e-Net ) 1 789 17 vo7 2 789 18 801 3 788 19 801 h 78h 20 707 5 747 21 786 6 782 22 783 7 789 23 785 8 79h 2h tS6 9 792 25 785 10 793 26 790 11 795 27 715 12 796 28 611 13 798 29 1h 796 30 15 797 31 16 797 c,-,/ 059 su 7910810{
ket No. 50-289 vPERATING DATA REPCRT Date 3-10-73 Completed By D. G. Mitchell OPERATING STA"1'US Telephone 920-3001 Ext. lo9 1. Unit Name: Three Mile Island Unit 1 2. Reporting Period: February 1978 3 Licensed Thermal Power (T4t) 2535 h. Nameplate Rating (Gross M4e): Oil 5 Design Electrical Rating (Net M4e): 810 6. Max. Dependable Capacity (Gross W4e): 8h0 7 Max. Dependable Capacity (Net M'de): 792 8. If Changes Occur in Capacity Ratings (Items No. 3 through 7) Since Last Report, Give Reasons: N/A 9 Power Level to which Restricted. If Any (Net M'Je): N/A 10. Reasons for Restrictions, If Any: N/A This Month Yr.-to-Date Cumulative 672 1h16 on com 11. Hours in Reporting Period 672 1h16 2h,h7h.3 12. No. of Hours Reactor was Critical 13. Reactor Reserve Shutdown Hours 0 0 878.5 lb. Hours Generator On-Line 672 1h16 2h.013.5 0 0 0 15 Unit Reserve Shutdown Hours 16. Gross Thermal Energy Generated (MWH) 1,672,h92 3,523,853 58.017.h13 17 Gross Elect. Energy Generated (K45) 557,129 1,181.112 lo.67h.olh
- 18. Net Electrical Energy Generated (MWH) 524,h03 1,112,107 18,h30,506 19 Unit Service Factor 1005 1005 73.h5 100%
100% 78.h4 20. Unit Availability Factor 21. Unit Capacity Factor (Using MDC Net) 90.53 99.2% 70.0% 22. Unit Capacity Factor (Using DER Net) 95.3% c5.05 77." 0 0 5.3% 23. Unit Forced Outage Rate 2h. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): Refueline March 17.1Q78 - 6 veeks 25 If Shut Down at End of Report Period, Estimated Date of Startup; N/A
- 26. Units In Test Status (Prior to Cocmercial Operation):
FORECAST ACHIEVED INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A COMMERCIAL OPERATION \\b G
9 6 1 l e l t s e e x n*se e h E o nl c ei r c u*eF t 1 u e i 0 o m M) 8 M 6 v S i e 9 7 3 R t c 8 1 t rE e c n 2 0 G 9 s"oL m e e I 1 2 n f( a ror 0 M 9 5 T 3 D rt r S e o u st e e n C c r o o mt yo ne s p 1 d oR k E e N a aB h N D p ni a R ~ t att t e e i cn L t b e d l k t e e eA e n i s v r ci t T e h
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SUMMARY
OF OPERATING EXPERIENCE With the exception of the following reductions, the unit operated at essentially 100% full power until 2/27/78. On 2/5/78, t'oth penetration cooling fans (AH-E-9A/B) failed causing high temperatures at the Reactor Building penetrations for the four main steam lines. Reactor Power / Unit load was reduced to 80% for 7 hours in order to reduce the penetration temperatures while temporary cooling fans could be installed. On 2/8/78, while conducting FW temperature calitiration checks, a technician lifted the ICS selected FW temperature lead in arror causing the ICS to sense a Reactor-Feedwater~ demand mismatch and an automatic Reactor Power runback. The power reduction was to 80% and lasted approximately 6 minutes. On 2/25/78, a 6 hour planned power reduction to 95% was made to conduct surveillance testing of the 5 main steam safety valve setpoints. On 2/27/78, the unit reduced power in order to isolate the "B" low pressure feed-water heater string and locate leaking feedwater heater tubes. While isolating the low pressure heater string, tube leaks developed in the "B" high pressure feedwater heaters forcing the isolation of the "B" high pressure feedwater heater string. While maintaining about 83% power, the 88 low pressure heater was opened and 18 leaking tubes were plugged. Isolation of the "B" high pressure FW heater string was inadequate to permit leak checking and tube plugging. As a result of the above FW heater maintenance, Reactor power remained at 83% for the remainder of tne month. MAINTENANCE
SUMMARY
DH-P-1B was inspected during February upon reaching 1 hour of running operation. The following work was performed: (1) IRD reading was taken. (2) Pump to motor coupling removed. (3) Alignment check between motor and pump. (4) Ultrasonic test of pump shaft. (5) Analysis of UT results. (6) Coupling of pump to motor. (7) Testing of pump (IRD and operational) and declaring pump operable. (8) Return pump to service. Results of UT and IRD readings were satisfactory. Anverkvas performed within the time limits set forth in the technical specifications. 1509 002
RERJELING INTORMATICH RECUEST 1. Name of Facility: Three Mile Island Unit No. 1 2. Scheduled date for next refueling shutdown: " arch 17,1978 3. Scheduled date for restart folleving refueling: Pay 15, 1978 for Reacter Criticality (tentative) h. Will refueling or resumption of operatien thereafter require a technical specification change or other license amendment? Yes If answer is yes, what, in general, will these be? The Technical Specification change for Cycle h vill provide revised operational limits for rod withdrawal index and Power Inbalance. Also the Core Protection Safety Limits and the Protection System Maximum A11ovable Setpoints for Reactor Power Inbalance have been slightly revised. The quadrant power tilt limit vill be changed from a maximum 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 Conmittee to determine whether any unreviewed safety questions are associated with the core reload (Ref.10 CFR Section 50.59)? U/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 design, new operating procedures. There are no important licensing consideraticns associated with Cycle h cperation. TLC-1 vill change from a rodded to a feed-bleed mode of operation 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 assemblies (a) in the core and (b) in the spent fuel storage pool. (a) 177 (b) loh (start of 1973 refueling outage) 8. The present licensed spent fuel pool storage capacity and the site of any increase in licensed storage capacity that has been rec.uested or is planned, in number of fuel assemblies. Recently licensed for 752 'uel assemb[ies storage locations in the A&3 spent fuel pools. h90 locatien 3 pool racks to be installed starting in February 1978. n m 7 d
heftwling Information, Eequest 9 T e projected date of the last refueling that can be discharged to the spen +~ . el,co? assuming the present licensed capacity. 1986 is last refueling discharge which allows full core off-load capacity (177 fuel assemblies). UA O r ' n, Juy r .}}