ML19290E997
| ML19290E997 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 03/12/1980 |
| From: | Beers F Maine Yankee |
| To: | |
| Shared Package | |
| ML19290E986 | List: |
| References | |
| NUDOCS 8003170428 | |
| Download: ML19290E997 (16) | |
Text
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MAINE YANKEE NUCLEAR POWER STATIO!
MONTHLY STATISTICAL REPORT 80-02 FOR THE MONTH OF FEBRUARY, 1980 80031'10l{'l-(5
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OPERATING DATA REPORT DOCKET NO.
50-309,
DATE 800312 COh!PLETED BY F. C. Beers TELEPHONE A17-1AA-0011 X2215 OPERATING STATUS Maine Yankee Notes
- 1. Unit Name:
- 2. Reporting Period:
February, 1980 2630
- 3. Licensed Therms! Power ($1Wt):
864
- 4. Nameplate Rating (Gross 5!We):
825
- 5. Design Electrical Rsting (Net SIWE):.
850
- 6. 51sximum Dependable Ct.pscity (Gross alwe):
810
- 7. 51sximum Dependsble Capacity (Net 51We):
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:
- 9. Power Les e! To which Restricted. If Any (Net SIWE):
- 10. Ressons For Restrictions.If Any:
9
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i This Sionth Yr.to.Date Cumu!stive i
696 1,440 t
- 11. Hours In Reporting Period 0.0 263.33 51,473.33
- 12. Number Of Hours Reactor Was Critical
- 13. Reactor Reserve Shutdown Hours 0
0 0-14, Hours Generator On.Line 0.0 263.05 49*,780.86
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Cenerated (31WH) 0.0 474.499 105,684,582
- 17. Gross Electric::1 Ener;y Generated (5tWH) 0.0 139.660 34,712,840 0.0 131,040 32.958,227
- 18. Net Electrical Energy Generated (SIWH)
- 19. Unit Service Factor 0.0 18.3 77,7
- 20. Unit Avsibbility Factor 0.0 18.3 77.7
- 21. Unit Capacity Factor (Using alDC Net) 0.0 11.2 66.9
- 22. Unit Capacity Factor (Using DER Net) nn 11 64.6-
- 23. Unit Forced Outsge Rate 0.0 0.0
'6.9
- 24. Shutdowns Scheduled Over Next 6 Stonths(Type.Date.snd Duration of Esch):
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- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units In Test Status (Prior to Commercial Operstion):
Forecast Achieved eI INITIA L CRITICALITY INITIA L ELECTRICITY CONIStERCIAL OPERATION
'(9/77)
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-100 UNIT Maine Yankee DATE 800312 CO3tPLETED BY F. C.
Beers TELEPHONE 617-366-9011 X2215 510 NTH February, 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (31We-Net)
(Siwe-Net) 0 0-1 g7 0
0 2
gg 3
n 19 0
4 0
20 0
0 0
S 21 6
0 22 0
k,,
7 0
23 0
8 0
24 0
9 0
25 0
10 0
26 0
O 0<
II 27 0
12 0
23 13 0
29 0
14 0
30 0
15 3;
16 n
INS'IRUCTIONS On this format, list the average dsily unit power level in SIWE Net for essh day in the reporting month. Compute to the nearest whole megswatt.
V.
(9/77)
UNITS!!UTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-109 UNIT NAhlE M.,ine Yankee DATE A00112 REPORT al0NTil February, 1980 CO&fPLETED Hy F. C. Beers TELLPl!ONE 617-366-9011 X2215
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re No.
Date E.
k_E 3 $ "U h1 5*e Cause & Corrective By 53 nl So Action to
- C"8 yu Prevent itecurrence 3 Di y Repost #
v3 o 0-M 6
8-79-4 1-11-80 S
1176.95 C
1 N/A N/A N/A Cycle 4/5 refueling shutdown, plus N
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0 PE38 Eiel W
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F: Fort ed Iteason:
Eleiliud:
Extiibit G -Instructions S. Stlieduled A.Eiinipment Failure (Explain) 141anual foi Piepuation of Dais B klaintenance niTest 741anual Scram.
Entry Slicets fus 1.ieensee C.ltefueling 3 Antumatic Scram.
Event Itepunt (Llilt) File INUltl'.G-D.Itegulatiny Itcst iction
- 4. Oilier (Explain) 0161) li-Opeutor Training & License Examination F.Ailminiuolive 5
G Opeutiinut lasur (limplain)
Extiileit 1 Same Sousee
('8/ 77)
It Ollies (limplain)
DOCKET NO.
50-309 UNIT Maine Yankee DATE 800312 COMPLETED BY F. C. Beers TELEP110NE 617-366-9011 X2215 REPORT MONTli February, 1980 SlRDIARY OF OPERATING EXPERIENCES The plant remained shutdown for the Cycle 4/5 refueling outage for the entire month. Plant startup is expected early in March.
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Design Packages Completed During 1979 Plant Alterations PA 4-78 Computer Te=perature Bridge Change PA 7-78 Main Control Board Aux. Steam Pressure Indication PA 14-78 Generator Condition Monitor PA 16-78 MSR Scavanging Vent System PA 17-78 Security Perimeter / Protected Area Lighting Changea PA 9-79 Additional Breathing Air Co= pressor Plant Design Change Requests PDCR 13-79 Provide Throttling Controls for Cooling Water Outlet to RER Heat Exchangers Engineering Design Change Requests EDCR 75-23 Modification to Power Supplies of Emergency Shutdown Panels EDCR 79-5 Post Accident Transmitters Sealed Cable Splices EDCR 79-20 Modification to H-51 & H-53 Contata=ent Spray Piping O
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PA 4-78 ur7erature Bridge Replace =ent Computt' T Because of temperature range differences made necessary by operating conditions, -the " canned" computer RTD bridges were determined to be obsolete. They were replaced with printed cir-cuit card bridges.
Existing plant sensor wiring and computer input wiring was utilized.
This alteration did not involve an unreviewed Safety Question as specified in 10 CFR 50.59(a)(2).
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PA 7-78 Main Control Board Auxiliary Steam Pressure Indication To permit the control room operators to more accurately deter-mine secondary plant status and to provide advanced warning of auxiliary steam pressure and resulting loss of condenser air ejectors, a pressure transmitter was installed near the air ejectors and an indicator was mounted in section "A" of the Main Control Board.
This alteration did not invols e an unreviewed Safety Question as specified in 10 CFR 50.59(a)(2).
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PA 14-78 Generator Condition Monitor In order to receive control room indication of possible eddy current heating caused by =echanical damage to the stator core lamination insulation, a generator condition monitor / core monitor was installed. This system detects particles produced by insulation hot spots. The monitor includes an automatic sampling feature which, when in alarm, captures a sample for analysis.
In the control room, 2 Main Control Board mounted alarm and recorder provide indication.
This alteration did not involve an unreviewed Safety Question as specified in 10 CFR 50.59(a)(2).
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PA 16-78 Scavanging Steam Vent Condenser This alteration provided a means to reduce Moisture Separator Reheater (MSR) u-tube failures due to cyclic fatigue. A scavanging steam vent chamber was installed in the hemi-head of the MSR u-tube bundle. This chamber converts the u-tube bundle to a four pass heat exchanger with condensation drainage between the second and third pass to the reheater drain receiver. The outlet of the fourth pass is' directed through a control orifice to the MSR's crossunder drain piping.
This alteration did not involve an unreviewed Safety Question as specified in 10 CFR 50.59(a)(2).
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de PA 17-78 Security Perimeter / Protected Area Lighting Changes The Nuclear Regulatory Cc= mission requires in 10 CFR part 73.55 that area lighting in the security perimeter and protected area illum-inste the ares to a minimum of 0.2 foot candles for security observa-tion. The requirements also specify that security lighting must be restored within one minute upon loss of nor=41 power supply.
The requirements were met by moving the perimeter fence closer (thus decreasing th' size of the protected area) and by to the plant e
lighting changes. The lighting changes included adding lights in certain~ areas, changing types of lights in certain areas, and viring all " security lighting" to the security lighting panel.
(The security lighting panel was installed under EDCR 78-8 in 1978.)
This alteration did not affect areas evaluated by the safety analysis report. The interface between plant safety related systems and the security lighting has been evaluated by EDCR 78-8.
Therefore, this alteration did not involve an unreviewed Safety Question as specified in 10 CFR 50.. )(a)(2).
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PA 9-79 Breathing Air Compressor In order to assure that breathing air charging capatities are continuously available, a redundant breathing air compressor was purchased. It was installed on the second level of the turbine hall. During the installation the original compressor was relocated to the same area.
This alteration did not involve an unreviewed Safety Question as specified in 10 CFR 50.59(a)(2).
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PDCR 13-79 Provide Throttling Controls for Cooling Water Outlet to RER Heat Exchangers During shutdown operations it is necessary to throttle the cooling water outlet valves of the Residual Heat Removal (RHR) heat exchangers. Prior to implementation of this change it was necessary to send an auxiliary operator to the valve location to perform throttling operations.
Per PDCR 13-79, the seal-in contacts were removed from the open and close contactor circuit. By doing this the valves can now be throttled using the existing controls at the Main Control Board.
This does not interfere with the operation of Recirculation Actuation Signal (RAS), which opens the valve, since the RAS relay must be manually reset. The relays cannot be reset if the two of three level switch circuit calls for recirculation.
This change does not affect valve operation upon RAS; therefore, no unreviewed Safety Question as specified in 10 CFR 50.59(a)(2) was crenced by this change.
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EDCR 75-23 Modification to Power Supplies of Emergency Shutdown Panels In the event of a postulstad fire in the Main Control Room and a resulta'nt evacuation, certain plant systems would have to be controlled from the Steam Generator Emergec:y Panel (SGEP) and the Primary Auxiliary Building Emergency Panel (PABEP). Power to these panels is supplied by vital bus #4 in the Main Control Board.
Should teh fire involve vital bus #4, power to the SCEP and PABEP would be interrupted. This would leave certain plant syste=s with-out control.
Maine Yankee, per EDCR 75-23, provided an alternate power supply to the emergency shutdown panels froc emergency bus #7 by tying into a 120 VAC power supply which feeds panel DP/IAC in the Main Contrcl Room. A double pole double throw selector switch at each of the e=ergency shutdown panels provides the nor=al or alternate power supply selection.
The design change improves the availability of the SGEP and PABEP.
The change did not alter the plant Technical Specifications, nor did it present an unreviewed Safety Question as specified in 10 CFR 50.59 (a) (2).
EDCR 79-05 Post Accident Transmitters Sealed Cable Splices Prior to this change several of Maine Yankee's post accident transmitters had field splices consisting of a bolted terminal lug connection, wrapped with "Scotchfil" tape, then wrapped with friction tape, and then painted with glyptel. The suitability of these splices to withstand a Loss of Coolant Accident or Snall Line Break was unknown. Rather than perforning qualification tests to prove the environ = ental integrity of these splices a qualified method of conductor connection was employed.
The cables are now joined at a terminal block (LOCA qualified by General Electric) inside of an enclosure. The terminal box with the terminal hlock mounted has been seismically analyzed.
This change did not present an unreviewed Safety Question as specified in 10 CFR 50.59(a)(2).
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EDCR 79-20 Maine Yankee Modification to 3-51 and H-53 Containment Spray Piping During Seismic reanalysis perforned on supports H-51 and H-53 of Maine Yankee's containment spray piping, increased loads were discovered. The seismic reanalysis required that several angles be added to the support structure as well as several required welds.
The support is Seismic Category I and Safety Class I.
This change did not:present an unreviewed Safety' Question as specified in 10 CFR 50.59(a)(2).
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