ML20237K404
| ML20237K404 | |
| Person / Time | |
|---|---|
| Site: | Ginna |
| Issue date: | 05/31/1987 |
| From: | Kober R, Mcnamara A ROCHESTER GAS & ELECTRIC CORP. |
| To: | NRC |
| References | |
| NUDOCS 8708190238 | |
| Download: ML20237K404 (6) | |
Text
ua R
DM P
m.
U R
at N
A Nxn e(
EL 7 cEo e e C8 i
s sl e
6t na n i c
U 9 N ot e F
r 1
4 a ia u
N c)
,Y E4t e
e t DiR o
wS i
c c
4 v
L S
A uf E
0 -
n t
r o e
4 N1b m4 a c
e t
roL 4
m r
sn N
2 n eo e f (
2 v
no a
r t 0 G n '; i 5 n I
e r
t I i s r S
r - i on e x
t o
t 5
e
. ukA5G Co a ep r
iR Ga e e I
E. J 1
t
&c ph R t
3 R
eA n ieS i
t t
e br ytn )1 ib EY I
s v
iP i
{
. l r
l w
e h
t e6 h
OMTI N
o r
xr n v 1 E
x NA A D
al C
P EfoEE0 O
T ND E P
4 5
ET T
E I
K N E
L cl L
E t
o P
T D
M O
C S
N O
X I
X T
- 80 C
E P
m)
U 7-
- gg!u I
a n ri D
8 P
mc a
aSl E
9 r
p R
1 c c x
- Si E
t R
a(
l l
mr E
Y a a J
- u u oe d
A g.
H onnt h W
M h a a ut O
eM M A O t
P H
M1 234 D
TN 3
N e
O e
A M
s t n nt n
N T
e e o o
r W
R c v p i
t iE e a
O O
L R
n D
P i
T E
m U
R ax H
E S
n' i
- $go
)
e T
[2$
A n
s
)
n n
I
/
a e
i N
- Ii2 N
p ic lp l
a U
x n
E oL x
t
(
ic&
E s
t A
e e
(
- c3I, uT n
o r
ig r
t r
si r) l n e r n i o e
a ivEi Rai lap F e yT a l
a qEE r t c
tn n 7
gr r nx e a n or t E 7, f:
5 os ioE ni t
m i
(
el at t
- pt el a n a r ni nu ur i r e ouif gemeh sqa e e pd pt aEMRROAOO e-F s.
RABCDEFGl l
2 n
7 o
i 8
i w
e
/
t ta 9
c D
0 u
/
d
.a le d
5 e
0 du R
ed ce e
h s
r
l i i
l l-NARRATIVE
SUMMARY
OF OPERATING EXPERIENCE DOCKET No.
50-244 UNIT R.E.
Ginna Nuclear Power Plant DATE June 10. 1987 COMPLETED BY
/2 As 6 %Mr ~C Andrew E. McNasara TELEPHONE 1 (315) 524-4446 EXT. 301 at Ginna MONTH May, 1987 The reactor power level was maintained at 100% for the majority of the report period, with the following two exceptions:
On May 1, 1987 the reactor power level was reduced to - 97% for a short period to perform a Periodic Test on the Auxiliary Feedwater System.
On May 9, 1987 the reactor power level was reduced to - 61% to effect repairs on a valve associated with one of the' reheaters.
The reactor power level was further reduced to - 38% to facili-tate the repairs.
The power level was restored to 100% on May 11, 1987 and remained there for the remainder of the report period.
I i
j l
i l
GINNA STATION I
MAINTENANCE REPORT
SUMMARY
JUNE, 1987 During the month of May, routine maintenance and inspections were completed.
Major safety related work included:
a.
Replace Flow Meter #FI-929A b.
Repair Cooler For "C" Stand-by Aux. Feed Water Pump c.
Monthly Snubber Inspection per M-40 d.
Replace RV-284 on "B" Charging Pump e.
"A" Reactor Coolant Drain Tank Pump Maint. Inspection f.
"A" SI Pump Maint. Inspection & Replace Mech. Seal Cooler Piping & Fittings g.
"C" Service Water Pump - Minor Maint. Inspection j
l 1
1 i
l i
i, l
l m
i OPERATING DATA REPORT DOCKET NO.
50 244 DATE June 10. 1987 COMPLETED BY SM8 M l
Andrew E. McNamara TELEPif0NE 315-524-4446 Ext. 301 OPERATING STATUS Ginna Station
- 1. Unit Name:
R.E. GINNA NUCl. EAR POWER PLANT Notes May, 1987
'Ihe reactor power level was i
- 2. Reporting Period:
1520 maintained at 100% for the
- 3. Licensed Thermal Power (MWt):
490 majority of the report period
- 4. Nameplate Rating (Gross MWe):
with two exceptions, detailed 470
- 5. Design Electrical Rating (Net WWe):
on page 4.
490
- 6. Maximum Dependable Capacity (Gross WWe):
470
- 7. Maximum Dependable Capacity (Net MWe):
- 8. If Changes Occur in Capacity Ratings (Icess Number 3 Through 7) Since Last Report, Give Reasons:
- 9. Power Level to Which Restricted, if Any (Net MWe):
- 10. Reasons For Restrictions, if Any:
This Month Yr. to Date Cumulative 744 3,623 153,503.00
- 11. Ilours in Reporting Period 744 2,877.5 118,881.47
- 12. Number of flours Reactor Was Critical 0
0 1.687.55*
- 13. Reactor Reserve Shutdown flours 744 2,857 116,541.38
- 14. Ilours Generator On.Line 0
0 8.5 *
- 15. Unit Reserve Shutdown flours 1,088,112 4,144,565 163,194,614
- 16. Gross Thermal Energy Generated (MWil) 368,434 1,399,846 53,488,458
- 17. Gross Electrical Energy Generated (MWil) 350,357 1,330,594 50,744,177 j
- 18. Net Electrical Energy Generated (MWil)
- 19. Unit Service Factor 100%
78.86%
75.92%
I 100%
78.86%
75.93%
i
- 20. Unit Availability Factor 100.2%
78.14%
71.84%
f
- 21. Unit Capacity Factor (Using MDC Net) 100.2%
78.14%
71.84%
- 22. Unit Capacity Factor (Using DER Net) 0%
0%
6.78%
- 23. Unic Forced Outage Rate
- 24. Shutdowns Scheduled Over Next 6 Months (Type Date and Duration of Each):
3 1'
')
- 25. If Shut Down At End Of Report Period, Estia.ated Date of Startup:
- 26. Units in Test Status (Prior to Commercial Operation):
Forecast Achieved i
INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION
- Cumulative total carmiencing January 1,1975 su au..
I E
t
l k
- i
?-
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-244 UNIT R.E. Ginna Nuclear Power Plant DATE June _10, 1987 COMPLETED BY h 2 Mh Andrew E. McNamara TELEPHONE 1 (315) 524-4446 Ext. 301 at Ginna MONTH May, 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1.
490 17.
489 2.
492 18.
489 3.
492 19.
488 4.
491 20.
490 5.
491 21.
490 6.
490 22.
490 7.
490 23.
488 8.
491 24.
488 9.
403 25.
489 10.
229 26.
489 11.
266 27.
489 12.
489 28.
489 13.
488 29.
489 14.
488 30.
488 15 490 31.
488 16.
489 i
INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting nonth.
Compute to the nearest whole megawatt..
1 I
_-_______A
r
~
DCS j
LA L
I' i.
.o
~
59 EAST AVENUE, ROCHESTER, N Y I4549 0001 ROCHESTER GAS AttD EllCTRIC CO%dn-liOtt e
MOGER W HODER
^ ~
t c H r.
> x t
,*n GINNA STATION June 10, 1987 l
Director, Office of Management Information and Program Analysis U.S. NUCLEAR REGULATORY COMMISSION Washington, DC 20555
Subject:
Monthly Report for May, 1987 Operating Status Information R. E. Ginna Nuclear Power Plant Docket No. 50-244 V
Dear Sir:
Pursuant to our Technical Specification 6.9.1, attached herewith is the monthly operating status report for Ginna Station for the month of May, 1987.
V truly yours, (p he m
Roger W. Kober RWK/eeh Attachments cc:
Dr. Thomas E. Murley NRC (1)
I d
se e
Co*,
h 7
T i
_