ML20062D157
| ML20062D157 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 11/15/1978 |
| From: | Barrett J FLORIDA POWER CORP. |
| To: | |
| Shared Package | |
| ML20062D155 | List: |
| References | |
| NUDOCS 7811200187 | |
| Download: ML20062D157 (5) | |
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Octobsr 1978 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-302 UNIT FICRP-3 DATE 11/6/78 COMPLETED BY 1
F. herect TELEPHONE Q04)795-6486 MONTH October. 1978 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net)
(MWe Net)
I 406 7
7 2
552 18 756 3
650 19 766
^
20 765' 5
776 21 761 6
760 763 22 7
754 23 761 8
0
.,4 759 9
755 25 762 10 N
26 763
{ ',
11 759 12 752 28 760 I3 29 783 I4 30 751 15 463 31 7c;n 16 662 INSTRUCTIONS On this format. list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.
(9/77) 7811200W7,
e OPERATING DATA REPORT DOCKET NO. 50-302 DATE 11/1/78 COMPLETED BY J. E. Barrett TELEPHONE (ona) 70s-6486' OPERATING S1 ATUS
- 1. Unit Name:
Crystal River #3 Notes
- 2. Reporting Period:
10/1/78 - 10/31/78 2452
- 3. Licenwd Thermal Power (MWit:
- 4. Nameplate Rating (Gross MWel:
890
- 5. Design Electrical Rating (Net MWe): 82,5 835
- 6. Manimum Dependable Capacity (Grom MWe):
7.' Maximum Dependable Capacity (Net MWe):
- 8. If Changes Occur in Capacity Ratings (items Number 3 Through 7) Since Last Report Give Reasons:
c N
None
- 9. Power Level To Which Restricted. lf Any (Net Mwel:
None
- 10. Renwns For Restrictions. lf Any:
This Month Yr. to-Date Cumulative
- 11. Hours In ReportinF eriod 745 e 7395,g 14352.0 P
- 12. Number Of Hours Reactor was Critical 745.0 2337.3 8393.o
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 383.'4
- 14. Hours Generator On.Line 744.8 2180.2 18095.0
- 15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
^-
./
- 16. Gross Thermal Energy Generated (MWHI 1656897.0 4626978.0 17255069.0
- 17. Gross Electrical Energy Generated (MWH) 567618.6 1576919.6 5845948.6 l
- 18. Net Electrical Energy Generated (MWHI 549802.0 1506839.0 5544558.0 19 Unit Service Factor.
100.0%
29.9%
56.4%
100.0%
29.9%
56.4%
- 20. Unit Availability Factor
- 21. Unit Capacity Factor (Using MDC Neti 92.6%
25.9%
48.5%
- 22. Unit Capacity Factor (Using DER Net) 89.5%
25.0%
46.8%
- 23. Uni Forced Outage Rate
.0%
69.7%
41.2%
- 24. Shutdowns Schedulcd Oser Nes 6 Months (T.spe. Date and Duration of Eacht:
Refuelinst-Scheduled 4/23/79. Pla:Inmi 6-8 Weekn
- 25. If Shut Down 4: End Of Report Period. Esiimated Date of Startup:
- 26. Units In Test Status (Prior io Commercial Opetath.ns:
Forecast Achieved INITIA L CRITICALITY
.1/14/77 INITML ELECT RICITY 1/30/77 CO\\1\\1ERCI AL OPER A TinN 3/13/,77 (9/77)
.. _ _ ~.
UNIT SilUIDOWNS AND POWER REDUCIlONS DOWE F NO.
50-302 UNII N AME FLCRP-3 DA1E 11/6/7R COMPI ETED HY T
REPORI MON 1lI Qctober_ 1978
- E_
heratt lEl.EPilONE (99/.) 795-6486 jg Y'
l.icensee
,Eg f't Cause & Conective Disc e-
- 7. E 4
~
.g[5
- E Event
- '2 o.
Auion to O
Repori 1*
N0 hU Presetit Recurrente
- ~ -
3 u
6 NA 781410 S
0 B
4 NA NA Power reduction to complete Power Reduction Physics Testing NA 781610 F
. 25 G
4 ED NA Turbine / Generator tripped.off line Power Reduction dtfring adjustment of main generator (Reactor Remainec fiald voltage. Operator mis-critical) understood operation of the control Info mation: Total Forced Out age Iburs this Mo...25 Year to Date 5016.9 Cum 5663.3 1
2 3
4 F: Forced a
Reason:
Method:
Exhibit G. Instructions S: Scheduled A-Equipment Failure (Explain) 1 Manual for Preparation of Data B Maintenance of Test 2 Manual Scram.
Entr> Sheets for Licensee C-Refueling 3 Automatic Scram.
Event Report (LERI Fde INURI.G.
D Regulatory Restriction i
4-Other ( Explain )
0161)
E-Operator Training & License Examination F Administrative 5
G Operational Error (Explain)
Eshibit I - Same Source
,(9/77) 11-0t her (Explain) a e
, flu f4 I li t.Y WI AlllS Hl;puH r - H,1j l tl C l.1 fig I N FO Hil A I I uti H ijyll M S T, l.
Name of Faellity:
Crystal H l ve r lin i e 1 2.
S c h e d ii l e d date of next refueling sholdown:
Apel1, 1979 3
Scheduled date for restart foflowlun retueIlug:
June, 19/9 4
WIi1 refueIlug or resumption of operatton the rea f Le r rc <lu i r e a technical specification change or other license amendment?
Yen.
In general, channen to the CR #3 Lechnical specift-cattunn wiiI ineiude:
a3 Hoile ra t o r Temperature Coefficient (3.1.1.3) b.
Control Mod insertion I.i m i t s (1.1.3.6) c.
Control Hud Group As.S i gn me n t s '( 3.1. 3. 7 )
d.
Axial imbalance 1,imits (3.2.1) e.
Refueling llo r o n Co n c e n t r..a t i o n (3.9.1)
These speciiica: i o n e.
wIII he re v le wed and changed as neces-sary based'on the teactivity of L li e netund cycle as compared to t h.i t of the itrst cycle.
5 Scheduled date(s) for submitting p r o ;io n e d liccusing action and supporting luformation:
March, 19/9 b.
Important licensing considerations a s s o c i a t.e d with re f ue l-
- Inn, e.g.,
n e t, or different fuel design or nupplier, un-reviewed deign or performance analysis methods, significant changes in ine1 design, or new operaLing procedures.
Florida Power Corporation is presently discussing with the NHC staff our intent to r c <l o e s t that the power level of CR
- 3 be ra i sed from the present level of 2452 HW (t) to the ultimate core power level of 2544 MW(t) as described in the CR #3 FSAR.
Additional information concerning o u r.
proposed p
power upgrade lor CH # 1 wi ll be supplied in forthcoming U
monthly ope ra t ing re po r t s.
9
/.
The number of fuel assemblies (a) In the core and (b) in the spent fpel storage pool, a) 177 assembiles b) 4 assemblies H.-
The present lleensed spent fuel pool s t o rage capacity and the s i f. e of any increase in Iicensed storage capacILy that has been re q u e s t eil or in planned, in number ot fuel assemblles.
i a.
.present s t o ra ge capacity - pool A 120 plus'M failed IneI assemblies Pool !! - 120 plus H !alled fueI assembiles t
e--,
c.
.--n..
,r
.8.
~(Centinued)
~
- 12.
Filed request on January 9. 1978 with NRC toncerning expansion of Pool A from 120 to 544 assemhiles plun 6 failed fuel assemblics and expansion of Pool it from 120 to 609 assemblies.
Expansion of Pool A in to occur after the refueling In' April, 1979.
The Pool il ex-pansion will occur at a.later refueling outage (approximately 198{i).
Add itional deta iled design information concerning our fuel pool expansion was submitted to the Commission on March 3 and March 22, 1978.
9.
The projected date of the lost refueling that can he dis '
charged to the spent fuel pool assuming the present licensed capacity.
1981-1482.
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