ML20043G523
| ML20043G523 | |
| Person / Time | |
|---|---|
| Site: | Seabrook |
| Issue date: | 05/31/1990 |
| From: | Feigenbaum T, Nardone P PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NYN-90-125, NUDOCS 9006200394 | |
| Download: ML20043G523 (6) | |
Text
'
,,y'
' s, s
-Q.
.,f-
_y H
INew; Hampshire-l Ted C, Feigenboom Senior Vice President and -
3""'
Chief Operating Officer NYN-90125
'~
June 13, 1990 United States Nuclear Regulatory Consnission
. Washington, DC.20555
. Attention: Document Control Desk l
References:
Facility Operating License NPF-86, Doc'.:et No. 50-443
Subject:
Monthly Operating Report m
Gentlemen Enclosed.please find Monthly Operating Report 90-05.
This report
' addresses the operating and shutdown experience relating to Seabrook Station y
Unit'1 for the month of May, 1990 and is submitted in accordance with the requirements of-Seabrook Station Technical Specification 6'.8.1.5.
mt Very truly yours, f'
t Ted C. Feif nbaum m
TCF:VJT/ssi s
Enclosure
- h
'cca Mr. Thomas T. Martin 1
Regional Administrator United States Nuclear Regulatory Conunission Region I.
475 Allendale Road
?
King of. Prussia, PA 19406 w ;; D
- Mr. Noel Dudley NRC Senior Resident Inspector
- P.O. Box 1149 4
Seabrook, NH 03874 4 ;c 1
.m 9006200394 900531 PDR ADOCK 05000443 AA/
f)
R PDC
/ f
/
New Hampshire Yankee Division of Public Service Company of New Hampshire
)t\\
'p.7 P.O. Box 300
- Seabrook, NH 03874
- Telephone (603) 474 9521
~ !w
- V I!M n
- .
(
i OPERATING DATA REPORT" I
DOCKET NO.
50-443 UNIT Sea'arook 1 l
DATE. 06/13/90 1
COMPLETED BY P. Nardone TELEPHONE (603) 474-9521 (Ext. 4074)
OPERATING STATUS 1.
Unit Name Seabrook Station Unit 1 2.
Reporting Period:
MAY 1990 1
3.
Licensed Thermal Power (HWt):
3411 4.
Nameplate Rating (Gross HWe):
1197 5..
Design: Electrical Rating (Net MWe):
1148 6.
Maximum Dependable Capacity (Gross MWe):
1197 (Initial design value) 7.
. Maximum Dependable Capacity (;;al ;-M6)*
1148 (Initial design value) 8.-
If Changes Occur in Capacity Ratings'(Items Number 3 Through 7)
Since Last-Report, Give Reasons:
Not Apolicable 9.
Power Level To Which Restricted, If Any:
None
- 10. Reasons For Restrictions, If Any Not Aeolicable This Month Yr.-to-Date Cumulative
- 11. Hours In Reporting Period 744.0 3623.0 31752.0
- 12. Number Of Hours Reactor Was Critical 138.5 1026.5 1220.9 i
- 13. Reactor Reserve Shutdown Hours 605.5 715.2 715.2 L
- 14. Hours: Generator On-Line 22.1
~22.1 22.1
- 15. Unit Reserve Shutdown Hours.
0.0 0.0 0.0
- 16. Gross Thermal Energy Generated (MWH) 36338 195339 196429
- 17. Gross Elec. Energy Generated (MWH) 2954-2954 2954
- 18. Net Electrical Energy Generated (MWH) 2081 2081 2081 l
!*19.' Unit Service Factor 3.0 1.2 1.2 l
?*20. Unit Availability Factor 3.0 1.2 1.2 L
- 21. Unit' Capacity Factor (Using MDC Net) 0.2 0.1 0.1
!*22. Unit Capacity. Factor (Using DER Net) 0.2 0.1 0.1'
- 23. Unit Forced Outage Rate 52.1 52.1 52.1 l-
- 24. Shutdowns Scheduled over Next 6 Months (Type, Date, and Duration of Each):
1 Maintenance / Snubber Insosction. 11/03/90. 14 l' ave
[25. If' Shut Down At End Of Report Period. Estimated Date Of Startup: Not Applicable A6.-Prior to Commercial Operetion:
Forecast Achieved l
?
INITIAL CRITICALITY 1989 06/13/89 INITIAL ELECTRICITY 1990 05/29/90 COMMERCIAL OPERATION 1990 Not Applicable l
- NOTE: Year-to-Date and Cummulative values based on accumulated hours starting 03/15/90, date the full power license was issued.
1 of 5 h
y.o k
t jl.1
- c. p AVERAGE DAILY UNIT POWER LEVEL u
DOCKET ~NO,-
50-443 UNIT Seabrook 1
.' 1 DATE-06/13/90 COMPLETED BY P. Nardone TELEPHONE (603)-474-9521 (Ext. 4074)
MONTH MAY 1990 r;
DAY AVERAGE DAILY POWER LEVEL DAY-AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 0
16 0
2 0
17 0
w
'3 0
16 0
1 4
-0 19 0
l5 -
0 20 0
6 0
21 0
J7 0
22 0
'8 0
23 0
i9' O
24 0
- 10 0
25 0
11 0
26 0
if
- L 12 0
27 0
r i:
0' 28 0
' 13 '
}'
14
'O 29-5
,o
' 15 ;
O 30 82 4 J '!-
ij ;.
31 0
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.
2 of 5 s-
~
. }^
.~
^
UNIT SHUIDOWS'AND F0WER REDUCTIGIS IXXTET NO. -
50-443 -
~
INIT Seabrook 1 1
DpaE 06/13/90-(
REECRP PDfIH MAY, 1990 EMPIEITD BY ' P. Nardone i
TEIEPIENE f 6031 474-9521 (Ext. 4074) l 2
Method of Licensee Cause & Corrective No.
Date Type Duration Reason (Hours)
Shutting Event Action to 3
Report #
Prevent Recurrence Down Reactor 90-03 05/01/90 S
605.5 B/F' 4
N/A Reector shutdown while turbine vazia is nodifying low pressure hwhina rotor blading as a result of hwhine torsional test data.
90-04 05/31/90 F
24 A
9 N/A Reactor power reduced to 2% RPP.
Generator breaker opened. Ttzrhine va du. remiring nechanical over-speed trip Inechanism.
1 2-3 F: Forced Reason:
Method:
S: Scheduled A-Equipnent Failure (Ruplai71) 1-Manual B-Maintenance or Test 2-Manual Scram C-Refueling 3-Autmatic Scram D-Regulatory Restriction.
4-Continued fran E-Operator Training & License Examination previous nonth F-A*ninistrative 5-Power Reductim G-Operational Error (Explain)
(Duration = 0)
H-Other (Explain) 9-Other (Explain) 3 of 5
. ~.
f
~
~
,.. 2 '
h 12 5
)
9 4
1 e
7 h
0 m
4 0
?
. 3 A
9 t
7 4
t
/
d 4
n f
u 3
r a
^
t F
1 a
)
s 0
/
N 3
x
, 5
=
6 0
E 0
6
(
o-P e
f r
E u
i T
E Y
N O
l
.O I
G B
O I
i H
P a
N M
PD D
P C
f I
T T
E A
I E
r G
E E
E e.
0 I
C t
E N
tr 0
a G
E D
i elM B
C ffN i-IA t
M a
.d u.
m=d T
e=i N
l A
%fa wy m
D!
mUER Y
1EF 0
2 yw 5
A 9
o m
S 9
4 l
f pF o
1 T
4 R
N 2
r 4
E 4
K
- e rm G
TA t
Y M
E P
Fa E
M n
w WiDd C
99 O
Fa e
rGe W
1TSF S
H I
E N
CN K
E T
D R
f O
N P
I E
r A
R M
e M
T t
h I
s S
v YS ir
-4 mu 1
0 f
9 o
E
/
T 9
1 A
1 D
/
e 5
g 0
aP
~
n lI l!(!!lllii ll>l ltll l
II<
1!l
!N ^,.,,
DOCKPT NO.
50-443 INIT hhnx* 1
+i'--
=
i:L DME 06/13/90 j
CXMPLE11!D BY P. Nardone i
TELEPtKNE 1603) 474-9521 (Ext. 4074)
REFUELING INFCEDATIN RBJUEST
- l. Nane of, facility: hhmok Unit 1
- 2. Schedule:1 date for next refueling shutdowns. 07/27/91 l
l A
- 3. Scheduled date for restart following refueling:
09/21/91 r
- 4. Will refueling or restaption of operation thereafter require a technical specification change or other license amendment?
Unknown at this time.
- 5. Scheduled date(s) for subnitting licesing action and supporting information:
Not Applicable
- 6. Inportant licensing considerations associated with refueling, e.g.,
. new or different fuel design or supplier, unreviewed design or perfonnance analysis methods, significant changes in fuel design, new operating g. d ures:
None t.
l-
- 7. The number of fuel assemblies (a) in the : ore and (b) in the spent fuel storage pools (a) In Core:
193
-(b) 0
- 8. 'Ihe present licensed spent fuel pool storage capacity an:1 the size of any increase in licensed storage capacity that has been requested or is planned,'in number of fuel assa blies:
Present licensed capacity: 1236 No increase in storage capacity requested or planned.
- 9. 'Ihe projectexi date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
Licensed capacity of 1236 fuel assablies based on sixteen refuelings and full core offload capability.
'1he current licensed capacity is adequate until at least the i
year 2010.
5 of 5 o
- - - - -