ML17037C231
| ML17037C231 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point |
| Issue date: | 09/14/1973 |
| From: | Schneider R Niagara Mohawk Power Corp |
| To: | O'Leary J US Atomic Energy Commission (AEC) |
| References | |
| Download: ML17037C231 (14) | |
Text
AEC DISTRIBUTION FOR PART 50 DOCKET MATERIALt (TEMPORARY FORM)
CONTROL NO:,7213 FILE:
FROM:
Niagara Mohawk Power Corporation
- Syracuse, New York 13202 Rudol h R. Schneider 9-14-73 9-27-73 DATE OF DOC DATE REC'D LTR MEMO RPT OTHER TO:
John F. O'eary ORIG 1 signed CC 39 OTHER SENT AEC PDR SENT LOCAL PDR CLASS UNCLASS PROP INFO INPUT NO C
S REC'D 40 DOCKET NO:
50-220 DESCRIPTION:
Ltr 'trans the following:
PLANT NAME: Nine Mile Point Unit 8 1
ENCLOSURES:
ADDENDUM No.
1 to Semi-Annual Report of Operations for <<~the Nine Mile Point Unit 8 1 covering period 1-1-73 thru 6-30-73.
ACKNOWLEDGED DO NOT REMOVE (40 cys rec'd)
FOR ACTION/INFORMATION
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Copies GOLLER(L)
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Copies KNIEL(L)
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Copies SCHWENCER(L)
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Copies STOLZ(L)
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Copies VASSALLO(L)
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Copies SCHEMEL(L)
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Copies NIEMANN(L)
W/ 7 Copies DICKER(E)
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Copies KNIGHTON(E) "
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Copies INTERNAL DXSTRIBUTXON REGAN(E)
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A/P XND DRAXSMAN S ALLAN PLANS MCDONALD DUBE INFO C. MILES EXTERNAL DISTRIBUTION LOCAL PDR Oswe o
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NIAGARA MOHAWK POWER CORPORATION
~IIllM NIAGARA~
MOHAWK 30D ERIE BOULEVARDWEST SYRACUSE, H.Y. I3202 Fifo 0 September 14, 1973 I
Mr. John F. O'eary Director of Licensing United States Atomic Energy Commission llfashington, D.
C.
20545 CP C@
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'4'>ipn QQIQfpgy Soctipn lP Re:
Nine Mile Point Nuclear Station, Unit ¹1 Provisional Operating License:
DPR-17 Docket No.:
50-220 Enclosed is Addendum dated September 13, 1973 to the Semiannual Report of Operation for the Nine Mile Point Nuclear 5
Station, Unit ¹1 covering the period January 1,
1973 through June 30, 1973.
This addendum includes an:iaddition to the Instrument and Control Summary and typographical corrections.
Very"truly yours, RRS:cm dolph' Sc ez.der Vice President Electric Operations Cl DDCKEKD usAEC lt,sEp2V 1973 5
EGuulTORY euI. SeCrI0N fsCuT <ge
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NIAGARA MOHA1'IK POWER CORPORATION NINE MILE POINT NUCLEAR STATION UNIT 1 SEMIANNUAL REPORT OF OPERATION JANUARY 1, 1973 THROUGH JUNE 30, 1973 ADDENDUM 1 Please substitute the attached pages 14, 24, 25 and 41 marked Addendum 9/13/73 for the corresponding pages in y'our copy of the Eighth Semiannual Report of Operation, Nine Mile Point Nuclear Station Unit l.
Thomas J.
rkins Station Superintendent
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NINE MILL'OINTNUCLEAR STATION UNIT NO.
1 INSTRUMENT AND CONTROL SURfARY JANUARY THROUGH JUNE 1973 l>ATE Apr.
20 Apr.
24 May 2
I May 6
May 7
- May 7
May 10 May 14 SYSTEM Containment Leakage L.P.R.M.
Aux.
Power Turbine Turbine R.PCS.
Control Rod Drive P. R.M.
COMPONET Drywell Equipment Drain Lines Detectors N167 M-G Set Moog Valve E.P.R.
RE18A Lo-Lo-Lo Rx.
ll Pump Thermo-cou le Main Steam Rad.
Monitors NATURE OF MAINTENANCE Revision New Installation Correct ive Revision Annual Calibration Functional Test Corrective Calibration EFFECT ON SAFE OPERATION OF THE REACTOR None More complete picture of Reactor Flux Rx. Protection System Bus Manual Auto Control of turbin Controls Turbine None (Outage)
Loss of CD R.DE Press on Pump Burnout Faulty Steam Line Rad.
Reading CAUSE OF MALFUNCTION None.
Age 6 Mo'ture Defective Contacts None None Drift Broken Thermocouple Instrument Drift RESULTS OF MALFUNCTION None Bad Detectors Trip out on time delay Vibration Succeptable Improper Turbine Control None No indication of bearing Tem erature Faulty Reading ACTION TAKEN TO PRECLUDE RECURRENCE Added thermocoupl to all drain line to indicate leaka e
Install New Detectors New Relay Added two set screws to stop sli age Annual Calibration Rechecked calibration on 5-10-73 Replace T C Quarterly Calibrations TIME FOR COMPLET s
2 Wks.
3 Wks.
3 Hr.
I/2 Day 1 Day 2 Hr.
1 Hr 2 Days May 20 May 26 Rx.
Vessel Main Steam Electromati Relief Valves I ~ V. Limit Switches Calibration Check Revision Pressure Relief Cap abi1it y Causes isolation of Main Stm.lines Instrument Drift Poor Mounting Lower Press Relief Setting Erratic operation of switches Annual Calibrations Repositioned switches 3 Days II 2 Days
- Addendum 9-13-73
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TABLE 1 SU MARY OF STATION OPERATIONS JANUARY 1, 1973 THROUGH JUNE 30, 1973 PERIOD GENERATION IN hm HOURS HOURS Gross Thermal Gross Net On Electrical Electrical Load Total Hr.this Period Reactor Number Equiv.Full of Power Hrs(a) Criticals Number of Scrams RATES Availability Factor Capacity Factor (d)
Load Fact January 1, 300, 937 February March April May I
June 6 hSNTH TOTAL 1969 1970 1971 1972 442, 780 430, 156 744.0 744 257,733 2499277 467.8 672 441,782 429>418 744.0 744 1399852 135,268 247.7 720 771, 137 1, 304, 479 4239566 392,683 4, 192, 802 743 126, 869 122,604 345. 2 720 1,409,016 1,366,864 2548.7 4343 63,505 473.3 1464 294,997 70, 967 5,940,025 1,917,708 1,857,134 4079.6 8760 9,145,980 3,032,972 2,937,369 5962.6 8760 10,010,627 3,344,721 3,242,306 6167.4 8784 703. 2 416. 8 705. 1 228.9 212. 2 2266.2
. 126.8 3832.2 5360.1 5410.6 15 (b) 19 32 88 49 17 17 13 69.6 60.8 100.0 94.6 34.4
- 30. 8 47.9 58.7 100.0 27.9 51.5 35.2 48.9 42.4
- 68. 1 63.4 70.2 60.5 100.0 (c) 94.8 96.3 63.4 96.8 32.0 35.7 54.0 69+
- 41. 7 66.1 60.0 TOTALS THRU JUNE/73(e)29,584,431 9,775,384 9,467,178 19231.6 32111 15991.5 (a)
Based on 1538 Ml<t prior to July 1971 and 1850 Wt from July 1971 (c)
From December 14, 1969 - Commercial Operation (e)
Cumulative rates are based on total Unit ¹1 Operating Hours, 610 We net capacity rating, 615 hwe net max. hr. generation, and 299 57 59.9 48.3 (b)
Includes criticals for training (d) 500 Mlle Prior to July 1971 610 We from December 1971 1850 hwt.
Addendum 9-13-73 47.9
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V TABLE II REACTOR SHUTDOWNS AND SCRAMS PERIOD JANUARY 1, 1973 THRU JUNE 30, 1973 DATE OPERATION
SUMMARY
OF OUTAGE CAUSE HOURS GENERATOR REACTOR OFF LOAD SUBCRITICAL
- 1. Feb.
9 Scram Generator trip on loss of excitation.
Generator available 2/12/73 8 08:00 Remainder of outage to complete replacement of control rod drives 5 SRM's.
Reactor start-up Feb.15 (Rx.critical 8 0120)
Generator on line 2/15/73 8 17:13 151. 2 135 '
- 2. Feb.
23 Shutdown
- 3. Apr.
8 Scram
- 4. Apr.
11 Shutdown 5
~ Apr.
14 Scram
- 6. June 12 Shutdown A.E.C. Examination for Operator Licensing Turbine trip by Emergency Governor Repack ¹12 Recirc.
Pump Ins'trument Valve 5 Union On ¹13 Reactor Recirc.
Cooling Water Piping.
Annual Re fue ling. Turbine was tripped to complete full power plant testing.
Shutdown to repair ¹113 Electromatic Relicf Valve
- 53. 0 17.1 47.8 1517.9 32.9 6.8 24.0 1394.8 46.0
- 7. June 15
- 8. June 16 Scram Turbine-Generator Shutdown Only Low Vacuum Generator off line.
Reactor remained super-critical. Turbine was removed from service to adjust an oil deflector that was rubbing.
8.3 4,4 25 Addendum 9-13-73
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TABLE XVI RADIATION EXPOSURE ACCORDING TO DUTY FUNCTION JANUARY THROUGII JUNE 1973 DUTY FUNCTION Regular Station Employees:
Routine Operation 6 Surveillance MAN REM 16.97 NUMBER OF MEN INCLUDED 26 Shutdown Operation 6 Surveillance 33.25 26 Routine Maintenance Shutdown Maintenance Routine Radiation Protection Coverage Shutdown Radiation Protection Coverage Supervision 19.92 58.04 4.02 8.79 22.12 30 30 15 NMPC Personnel on Temp. Duty:
Shutdown Maintenance 118. 28
'6 Contractor Personnel:
Shutdown Maintenance 97.82 94 NOTE:
Only individuals with exposure
>500 mrem for 6 month period included.
41 Addendum 9-13-73
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