ML19309B026
| ML19309B026 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 05/08/1975 |
| From: | SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| Shared Package | |
| ML19309B021 | List: |
| References | |
| NUDOCS 8004020503 | |
| Download: ML19309B026 (9) | |
Text
.
(,.
O O
.. e 1.3 REPORT FOR flARCH e
E 8004020
v-
-?
- 3
~
k_)
7
(.
1.3.1 OPERATIONS
SUMMARY
1 3.1.1 Changes in Design There were no-significant changes in design of-Rancho Seco Unit 1 made during March,~1975.
1.3.1.2 Performance Characteristics Prima'ry effort this month was the completion of the 100 hour0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> run at 92.5%
Reactor Power. Other tests successfully completed were 75% and 92.5% load rejection tests. The unit was shutdown on March 22nd for bearing inspection and steam screen removal.
1.3.1.3 Changes in Operating Methous The following significant safety related changes were made to Rancho Seco Unit i operating procedures in March, 1975:
1.
Procedure A.51, " Auxiliary Feedwater System" Revision 3 - Added new procedure section.for feeding the OTSG's from the Auxiliary Feedwater System during a shutdown to provide makeup water for chemistry control.
1.3.1.4 Surveillance Tests All equipment successfully passed the scheduled survelliance testing during March, 1975 1.3.1.5 Periodic Containment Leak Rate Tests There were no periodic containment leak rate tests performed in March, 1975 1.3.1.6 Changes, Tests or Experiments Authorized by NRC No changes, tests or experiments requiring authorization from Nuclear Regulatory Commission, pursuant to_10 CFR 50 59a were performed during March, 1975
_y.
a
E
q) 1 q-1.3 2 POWER GENERATION Nuclear r
March, 1975 cumulative Y.
540 3,200 Number of hours the reactor g'as critical 1.
2 18 Number of times the reactor';ias made critical 2.
3 Gross thermal power generated (MWH) 1,159,993 4,692,237
?
17.43 70.65 4.
Effective full power days Electrical 1.
Gross electrical power generated (MWH) 394,200 1,536,191 l
2.
Net electrical power generated (MWH) 369,497 1,373,081 3
Number of hours the generator was on the line 490 2,822 O
s
.c 3
- I
/
R l
/4
\\
1101 '2
'3 4 5 6 7 8 4 10 11 17 13 to 19 16 17 18 19 20 21 22 24 25 26 27 25 79 30 31110 m
I*
.<g O
r i
f4 c3 m
\\
.]
.~ l
/
O fc3.
a )l 85 l
j 80 t_
f 80 i
j.
p.
T.
. _ ~ ' '
~~
~
p.
15 15
.h
..j
...g r-t
)
65 b_
65 Q
_e N
..q
__s j
i j
.j Q
.i
'_ _j Q
i OJ 45
.c i' _ _
45 M.
I lL No l
N 2 l
~
~
gg
\\
4
.o U
n 35 py#
35 p%.,a j
>4 33 30 2 >,6 l
_~ _-
~..
> 0 a.
z of x a-25 25 x
l_
i l-W
~.
L-20 1
20
.a l
j 15 15
(
i i
j 5
)
l j
O_
\\
0 1 2 3 4 5 6 2 8 9 to !! 12 13 14 15 16 Il 13 j9 *20 28 72 23 24 2b 26 21 28 23 30 31 1
1 Month
_M.CM 19 I
5-7 1
r 1.3 3 UtilT I SHUTDOWNS - March,1975 Status Date Type huta Reason Corrective Action Duration i,
(_/
3-5 Forced Reactor Anti-rotation pin in, Turbine New anti-rotation pin 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> &
Outage maintained Governor valve stem sheered.
Installed.
20 minutes Turbine-at 15% FP.
i Generator Tripped manually
)
3-6 Forced Reactor Anti-rotation pliniin Tiubbine New anti-rotation pin 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> &
j Outage maintained Governor valve stem sheered, installed.
13 minutes Turbine at 15% FP Generator tripped i
nanual ly 3-7 Forced Reactor Low lube oil in reservoir for Added lube oil to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and Outage critical reactor coolant pump P-210C.
reservoir 41 minutes Turbine at zero Generator power i
tripped manually Reactor runback C
to zero power.
- s 3-8 Reac. tor Hot Shutdown Reactor tripped on power im-Slow response in add-6 hours Trip balance while increasing power boron and Control rod to 84% FP after shutdown for management schedule reactor coolant pump repair..
changed.
O M I l
)
133 HUNIT I SHUTDOWNS - March, 1975 / Continued)
Status Durinq Corrective Action.
Duration Reason Date Type Outage 3-13 Turbine /
Reactor ran Turbine / Generator tripped by SCOTS system was 46 minutes n
Generator back from 40% SCOTS overspeed contr'ol. system.
placed in test until trip FP to 20% FP Actual cause was from failure scheduled outage on in SCOTS system.
3-22-75 Upon inves-tigation, SCOTS sys-tem power supply was l
found to have failed and was replaced.
g 3-13 Reactor Hot ~ Shutdown Reactor tripped on power im-Boron addition start 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and balance while increasing to 83%
sooner and control 38 minutes Trip FP during performance of Pseudo rod management pro-
's Design transient test.
gram changed.
3-17 Hanual Reactor ran Generator OCB's~ tripped for None required - test 18 minutes 1
Gener-back from 75% performance of 75% load rejec-completed successfully
(,)
tion test.
d Turbine still on line.
3-18 Hanual Reactor ran Generatnr OCB's tripped for None required test 15 minutes Gener-back from pciformance of 92% load rejec-completed successfully ator Trip 92% FP to tion test.
19% FP.
Tur-
,(3 -
bine still on line.
1 j
s 5
-I.
,, 9
[!
j
,I1i f
g?
e no s
i r
t u
a o
r h
u D
42 2
-de
,n h
o c
S i
tc A
d e
e.
v re ig i
ua
)
t d
c qteu e
e u
r ro n
r ed i
o ne t
C n
ol o
Nu C
(
5 5
es 7
9 y-d ar o i w o e. )n 1
l rs f
lapt t io h
u unn(i c
ntOaw t
r as l oec a
memPd ge M
t o t ap d
r ut s ehF. hun soi n "m pt n
pi S
o iwwodt g N
s r
ool nn W
a t edRoai OD e
ct cl r R
snui pa TU aahoo e
H wdS rtdb r
t e
ro" ntl e S
1 oceohun t crc gdi T
cau ueb I
a d eohr N
enehrcu U
RictbsT 3
s ge t
3 unn u
1 tia h
art s
t uu SDO d n l w oo Cd r
e l o p
at y
ucp T
nai aer MRT e
t 2
a 2
D 3
e U
i' t
E 4
e
p NL/
March, 1975 1.3.4 MAINTENANCE OF SAFETY RELATED EQUIPMENT Description 1 3.4.1 Reactor Protection Pressure Transmitter Out of Calibration During calibration verification of RPS pressure transmitters, three of the four units were found outside the Reactor Protection System Trip Setting Trip Limits, of Technical Specifications Table 2.3-1.
The transmitters had drif ted greater than the original prediction of + 4 psig.
Bistable trips were set to 1904 psig for low pressure trip and 2351 psig for the high pressure trip. One unit was indicating eight (8) psig low and one unit was indicating twelve (12) psi high. The third unit was slightly above the maximim 4 psi tolerance. All four units, plus a spare unit were removed and returned to the manufacturer to determine the cause of the excessive drift. The units were checked at the factory and were reported to be within the purchase specifications.
Drift was stated to be 0.1% of span per month. The units have an 800 psi span which Indicates that the drift could be 0.8 psi per month. The units were returned end reinstalled in the reactor protection system.
To resolve this problem, a program has been developed to assure correct calibration and limit the drift of the RPS pressure transmitters.
A reference gauge will be set up to measure the reactor coolant pressure within 2 psi. At two week intervals both the gauge and the output of the pressure transmitters will be moni'tored and recorded on a digital voltmeter. The reference value will be compared with each of the pressure transultter values and the drift will be followed.
If the drift indicates that the Technical Specification limit may be exceeded on any unit, a recalibration will be performed on the transmitter. This pro-cedure will be followed until a final resolution is determined concerning the transmitter drift. There was no reactor transient associated with this occurrence.
- 3. -
~
7 s.
j 1.>3.'5" CHANGES IN PLANT OPERAT!NG ORGANIZATION - MARCH, 1975 There were no changes in the plant operating staff for those positions which
-are designated as key supervisory personnel on Fig. 6.2-1 of the Technical Specifications.
4 l
l
' l i
j i
e e
._A 6