ML17037B736
| ML17037B736 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 03/07/1978 |
| From: | Lempges T, Schneider R Niagara Mohawk Power Corp |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML17037B736 (13) | |
Text
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I REGULATORY INFORMATION DISTRIBUTION SYSTEM DISTRIBUTION FOR INCOMING ARTERIAL Fp REC:
ORG:
LEMPGES T E NRC NIAGARA MOHAWK PWR r
DOCTYPE:
LETTER NOTARIZED:
NO
SUBJECT:
MONTHLY OPERATING REPT FOR THE MONTH OF FEBRUARY'978.
(RIDS)50-220 DOCDATE: 03/07/78 DATE RCVD: 03/09/78 COPIES RECEIVED LTR 1
ENCL 1
PLANT NAME: NINE MILE PT UNIT 1
MONTHLY OPERATING REPORT FOR GRAY BOOK PREPARATION.
< DISTRIBUTION CODE A003)
REVIEWER INITIAL:
XJM DISTRIBUTOR INITIAL:P Q
++++~+++++++4++++ DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS FOR ACTION:
INTERNAL:
REG '
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/2 ENCL BR CHIEF LEAR~~+W/2 ENCL NRC PDR4+W/ENCL EXTERNAL:
LPDRiS OSWEGO NY++W/ENCL TIC~~W/ENCL NS IC++W/ENCL BNL(NATLAB>++W/ENCL ACRS CAT B+4W/0 ENCL DISTRIBUTION:
LTR 10 ENCL 10 SIZE:
iP+bP THE END CONTROL NBR 80690044
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Nh(P-0193 NIAGARAMOHAWKPOWER CORPORATION/300 ERIE BOULEVARDWEST, SYRACUSE, N,Y. 13202/TELEPHONE (315) 474-1511 Ha7tch 7, 1978
'0~ecto/L O(g,ce o( lHanagement In)otun~n and Plug/Lam Cont/LoL 0~ed S~e5 NucLea7L ReguLato/Lg Comehehkon (I/aehkngkon,
'D.C.
20555 RE:
Socket No.
50-220 OPR-69
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GentLemen:
Submits'ed he7Leeith Le Che Repo/Lt o( Ope/ca~g S~&cs and Shut-down Expe7u.ence (o/L Feb/u1a7Ig 1978 (o/L Che N~ne NLe Po~ NucLea/L
~on UnLC <1.
AQo LncLuded Le
- a. na/I/Iative /Lepo/Lt of ope7Iatu1g expe7u.ence (o/L Che month.
ALeo, pLea5e pnd encLoaed Re)using In)o/Im~on Reque54, wtu,ch eiXL be sub~ed tu pa7Lt o( She monthLy /LepoM.
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T.E.
empgeh Gene/cd Supe7u,ntendent NueLea/L Gene7LatLon FOR R.R. Schneide/L V~ce P/Leskdent-ELect/u'.c P/Lodu~on EncLoau/Le5
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Smmto/L, 0$ )Lee o( ISE (10 copiee)
NRC Region I 0$ tILe,e (1 copy)
AVERAGE DAILYUNITPOWER LEVEL DOCKET NO.
50-220 UNIT 9
DATE COMPLETED BY T. J. Perkins
/
MONTH February 1978 DAY AVERAGEDAILYPOWER LEVEL (MWe-Net) 598 DAY AVERAGE DAILYPOWER LEVEL (MWe-Net) 608 17 599 564 594 593 161 552 18 19 20 21 22 23 609 610 610 610 609 609 610 10 12 13 14 15 16 584 604 607 605 604 606 25 26 27 28 29 30 31 609 607 608 INSTRUCTIONS On this format, list the average daily unit power level in Mme-Net for each day in the reporting month. Compute to the nearest whole megawatt.
(9/77)
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UNITSHUTDO)VNS AND PO>VER REDUCTIONS DOCKET NO.
50-220 DATE REPORT MONTH 78 Date PP, a,o Liccnsec Event Rcport =
Cl~
O CP
~o io Cause 8(, Corrective Actlolt to Prevent Rccurrcnce 0
0 2/3/78 2/6/78 2/25/78 S
20.5 4.4 H
H Reduced load to change condensate demineralizers.
Trying to latch up T.S.V. Bypass Valve.
All T.S.V.'s closed causing turbine trip and reactor scram.
Reduced load to change condensate
'emineralizers.
F: Forced S: Scheduled (o/77)
Reason:
A-Equipmcnt Failure (Explain)
B.IIiaintcnancc or Test C-Refueling D-Regulatory Restriction E-Operator Training k. Liccnsc Examination F-Administrative G-Operational Error (Lxplain)
I I.Other (Explain)
Method:
! -Manual 2-Manual Sera in.
3-Autotnatic Scram.
4-Other (Explain)
(l Exhibit G - Instructions for Preparation of Data Entry Shc ts for Licensee Event Report (LER) File (NUREG-0161)
Exltibit I
~ Sainc Source
OPERATING DATAREPORT DOCKET NO 50-220 DATE COilPLBTED BY ~J.
Perkins
~j'ELEPHONE
~~110 I
2 3
4 5
6 7
8 OPERATING STATUS Notes Unit Name Reporting Pcr;od.
02-01 02-28-78 Licensed Thermal Power (MWt):
Nameplate Rating (Gross MWe):
Design Electrical Rating (Net hf'lVc):
hfaximum Dependable Capacity (Gross MIVe):
Maximum Dependable Capacity (Net hfWe):
630 610 IfChanges Occur in Capacity Ratings (Items Number 3 Through 7} Since Last Report, Give Reasons:
- 9. Power Level To Which Restricted, IfAny (Nct hflVe):
- 10. Reasons For Restrictions, If'ny:
This Month Yr.-to.Date 1 416 672 1,367. 1 1 343.3 1 169 266 2,327,886 98
- 11. Hours In Reporting Period
- 12. Number Of Hours Reactor Was Critical 657.4
- 13. Reactor Reserve Shutdown Hours
- 14. Hours Generator On.Line
- 15. Unit Reserve Shutdown Hours
- 16. Gross Thermal Energy Generated (MWH)
~selt-:~
- 18. Net Electrical Energy Generated (MIVH)
- 19. Unit Service Factor 98 95
- 20. Unit AvailabilityFactor
- 22. Unit Capacity Factor (Using DER Net) 99 87
- 23. Unit Forced Outage Rate 3
5
- 24. Shutdowns Scheduled Over Next 6 hfonths (Type. Date, and Duration of Each):
24 A ril 1978 Snubber Inspection Cumulative 73,008 52,43.0 50 033.5
- 20. 2 80,781,895 26 573 579 25,742,108 58
- 25. IfShut Down At End Of Report Period, Estimated Date of Startup:
- 26. Units ln Test Status (Prior to Commercial Operation):
Forecast Achieved INITIALCRITICALITY INITIAL ELECTRICITY COhfMERCIALOPERATION
('>/77 )
NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT NUCLEAR STATION UNIT 81 NARRATIVE~OPERATING REPORT FEBRUARY 1978
,The Station operated at 98/ availability and 94/ capacity factor for the month.
The daily operating history follows:
Feb.
1-Feb.
4 Feb.
5 Feb.
6 Feb.
7 Feb.
8 Feb.
9 Feb.
10-Feb.
24 Feb.
25 Feb.
26-Feb.
28 Operated at 97.5X thermal power 615 MWe.
Reduced load to 500 MWe for condensate demineralizer resin change and control rod pattern adjustment.
Load increased to 608 MWe, pre-conditioning power level increases after rod pattern adjustment.
Full load reached at 0500 623 MWe.
At 2230, a reactor scram occurred while attempting to relatch gl3 TSV Bypass valve mechanism.
Failure of a pneumatic operated valve caused all stop valves to shut.
Reactor critical at 1400 and unit synchronized to the line at 1900.
Continued load increases to reach 500 MWe.
Held at this level until 2100 for Xe production; reduced load via recirc flow to 400 MWe for rod withdrawals to obtain 100/ control rod pattern.
Continued load increases to 600 MWe by 2200.
Operated continuously at approximately 1840 MWth 623 MWe.
Reduced load to 500 MWe for change of condensate demineralizer.
Load returned to 623 MWe after 6th condensate demineralizer was placed in service.
Steady state power operation at approximately 99Ã.
~'EFUELING INFORMATION RE UEST 1.
Name of Facility Nine Mile Point Unit 81 2.
Scheduled Date for Next Refueling Shutdown The next refueling at Nine Mile Point Unit bl is tentatively scheduled for the Spring of 1979.
However, evaluations to be performed during the Spring of 1978 may reveal a Fall 1978 refueling to be more desirable.
If a Fall 1978 refueling is
- utilized, a September 2, 1978 shutdown date is assumed.
I 3.
Scheduled Date for Restart Following Refueling The refueling outage is scheduled to take approximately eight weeks.
4.
Will refueling or resumption of operation thereafter require a
Technical Specification change or other license amendment?
If answer is yes, what, in general will these be?
It is anticipated that prior, to resumption of operation following the'ext refueling outage,;a chnage will be required to the Nine Mile, Point Unit Pl Technical Specifications.
The next reload at Unit O'I will contain redesigned fuel assemblies which will be incorporated into, the Technical Specifications (i.e. fuel thermal
" limits)."
5.
Schedule Date(s) for submitting proposed licensing action and supporting information.
In anticipation of a Fall 1978 refuleing, Niagara Mohawk is scheduled to submit a reload licensing document to NRC around June 1, 1978.
Should the cycle be extended to the Spring 1979
- period, Niagara Mohawk is scheduled to submit a reload licensing document to NRC around November 15, 1978.
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.
The next reload at Nine Mile Point bl will contain redesigned fuel assemblies as summarized in General Electric's Generic Reload Fuel Application Licensing Topical Report NEDE 24011-P Revision 2.
7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.
The Nine Mile Point Unit 5'1 core contains 532 fuel assemblies.
The spent fuel pool contains 660 fuel assemblies.
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8.
The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or planned in number of fuel assemblies.
The Nine Nile Point Unit j/1 spent fuel pool is licensed to contain 1,984 fuel assemblies.
9.
The projected date of the last refueling that can be discharged to the present fuel pool assuming the present licensed capacity.
Under normal operating conditions, it is estimated the spent fuel pool can contain all fuel assemblies scheduled to be dis-charged from Unit 81 until approximately 1990.
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