ML19337A210
| ML19337A210 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 09/05/1980 |
| From: | Jackie Cook COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML19337A207 | List: |
| References | |
| NUDOCS 8009090298 | |
| Download: ML19337A210 (11) | |
Text
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- O OPERATING DATA REPORT DOCKET NO.
SO-29I DATE % 540 x
COMPLETED BY 6 M f oo A' TELEPHONE 3/U '1%-205V E'cr.,3(,3 OPERATING STATUS
- 1. Unit Name:
E Io ^ ll ' Y !
- 2. Reporting Period': anna 700 go / vo aYoo 800 TSf
- 3. Licensed Thermal Power (MWt):
A MO
- 4. Nameplate Rating (Grom MWe):
/ dM
- 5. Dengn Electrical Rating (Net MWe):
/OYO
- 6. Maximum Dependable Capacity (Gross MWe):
I O IS'
- 7. Maximum Dependable Capacity (Net MWe):
/ O YO
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give R:ssons AlA a
- 9. Power Level To Which Restricted If Any (Net hlWe):
A>/A
- 10. Reasons For Restrictions,if Any:
e)/A since. c.ommercoo L I
WCumula ife This Month Yr to Date
- 11. Hours in Reporting Period W
4 #56 A 8 Yl03
- 12. Number Of Hours Reactor Was Critical
'7/ 9 A 464/.5 41.'?V9.2
- 13. Reactor Reserve Shutdonn Hours O
'O
- d. 6A I -~ ?
- 14. Hours Generator On4.ine GGP.9 4 429.5
'/o 5 ?/o. R
- 15. Unit Reserve Shutdown Hours O
O
'O
- 16. Gross Thermal Energy Generated (MWH)
O O M T(o 5
/3 25S 09d 17AAD.M93
- 17. Gross Electrical Energy Generated (MWH) la 3 G ) O 459'7/ 160 M' S A9.E
- 18. Net Electrical Energy Generated (MWH)
/.02 TO P 4 og6l457 39'S-)6,],p,3
- 19. Unit Service Factor E9.9 7 6.' 'I
- 20. Unit Availability Factor N9 7 (o ~1
'0 9 /
6 9. '-/
- 21. Unit Capacity Factor (Using MDC Net)
T7 9 la 7 I 46 9
- 22. Unit Capacity Factor (Using DER Net) 77 9 69 1 SG 9
- 23. Unit Forced Outage Rate iO.I 23.3 8/. '/
- 24. Shutdowns Scheduled Over Next 6 Months (Type. Date.and Duration of Each):
Re n ano seAa.doies ce La, a i, int l
L-W pne;m a -tel y p
']
to e e r s l
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
Al lA
- 26. Units in Test Status (Prior to Commercial Operation):
Forecast Achieved INITIAL CRITICALITY l
INITIAL ELECTRICITY A)%
COMMERCIAL OPERATION (9/77) 8 009'O 9 04Z.N
' AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
00-D95 UNIT ' Zion On IT I W'80 DATE COMPLETED BY 6 /VI Cood TELEPHONE A/1-7 W-208V e nr.s o1 MONTH M t>o us-f /9TO DAY AVERAGE D IL POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
I 17 943 2
945 959 is 3
19 949 1
4 20 9 (cd 21 9(o3 i
22 4l2 l
7 23 303 8
24 54/
25 4b0 10 955
-3S 26 S@f 11 27
-3'$
28 fr(e 0 13 959 q5/
2, I#
hbO 30 954 939 IS 3,
9D 16 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)
+
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9 y
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50- MT UNIT NAME 2 i o n Urs ir i
.3 DATE 9 bb REPORTMONT11 Muctusf /g90 COMPLETED BY 6 M7 C oo M v
TELEPHONE 3#J-m -2af(/
Err.363 "t.
=
a
.! E 3
jM Licensee E r, Cause & Corrective k
No.
Date
{
gg g
,g g 5 Event
,#v?
ju?
ti Action to H
$5 5
j;5g
. Report #
Prevent Recurrence 5
llo
% 0 0 D 'X.'
F l'\\.1 6
3 AJ Ja Nla alA ReAcwR. rRr P Dus To 16 5 tean (.rene.caloe lo-l0 Wel.
17 200g15 F
44.3 A
i g/A e/A N/A (renera+o r o H-line dve.
+o vol4%e rg vla.+ios p ro bl e m.
l8 SOQ8A'1 F
1).']
A 3
4)^
4)A AllA
'SeaciOr fr flW P.
' ^ * *
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due40 I6 g i
1 1
2 3
4 F: Forced Reason:
Method:
Exhibit G - Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance of Test 2-Manual Scram.
Entry Sheets for Licensee C-Refueling 3 Automatic Scram.
Event ReporI(LER) File (NUREG-D-Regulatory Restriction 4-Other (Explain) 0161)
E-Operator Training & Ucense Examination F-Administrative 5
G-Operational Error (Explain)
Exhibit I - Same Source 19/77)
II4)ther (Explain) i d
rU1 7
OPERATING DATA REPORT DOCKET NO. 30 Y DATE 9-f-86.
l COMPLETED BY T. /M Cook
~
TELEPHONE 313 ~)Ws-.10d Y
'I OPEi1ATING STATUS
- 1. Unit Name:
EUA b "f
A
- 2. Reporting Period': o000 IOMO /
- 2VM IOOf3 /
- 3. Licensed Thermal Power (MWt):
Mf0
- 4. Nameplate Rating (Gross MWe):
/OEs
)
S. Design Electrical Rating (Net MWe):
/ O '/ O
- 6. Maximum Dependable Capacity (Gross MWe):
I 0 I6
- 7. Maximum Dependable Capacity (Net MWe):
/O 40
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
A) / A
- 9. Power Level To Which Restncted.If Any (Net MWe):
A3 / A
- 10. Reasons For Restrictions,if Any:
- /A l
s rou ce. c oinnter c ta l This Month Yr to Date Ob[OuIs$h$ 9'#v0Y i
!!. Hours In Reporting Period 9V4 IO M / 7lC
- 12. Number Of Hours Reactor Was Critical 73V. 5 4 36_9.9 36[9 M. G
'O N0/
- 13. Reactor Reserve Shutdown Hours 0 @lo lo
- 14. Hours Generator On-Line E
5199 1 37 0/3 O
!$. Unit Reserve Shutdown Hours O
'O
'O
- 16. Grom Thermal Energy Generated (MWH) 1.459 45*7
- 9. 5/,6. a V A
/02 a o 1. s% 0
~
- 17. Cross Electrical Energy Generstad (MWH)
G / 9'#3s S.t07.A8o
,3a. 22 g. s oo
- 18. Net Electncal Energy Generated (MWH) 5 Rle '/'/7 J 9 A7 229 3 i i AE 7</7
- 19. Unit Service Factor
- 9) S
'54I6
'7 O[9
- 20. Unit Availability Factor -
92.3
- 54. (A 70.9 i
)
- 22. Unit Capacity Factor (Using DER Net) 76 Y 9E A 57 V
- 23. Unit Forced Outage Rate '
- 7. 7 M/ 3
/ 7- (#
j
- 24. Shutdons Scheduled Over Next 6 Months (Type. Date.and Duration of Each):
A)/ A i
l
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
%A
- 26. Units In Test Status (Prior to Commercial Operation):
Forecast Achieved i
INITIAL CRITICALITY.
1
. INITIAL ELECTRICITY p
COMMERCIAL OPERATION 1
(4/77) j
+
_.. _,._ ~..._.. _.._._.._.- __.- _._-_. _. _ _... - - _,. -
r.
q AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
5 O-SOY UNIT Sin n Ur0T h hd'E DATE COMPLETED BY 8M doof, TELEPHONE 312 7V6 -V')8V Exv.363 MONTH f/4 fA67' /980 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 28N 824 17 2
9Ik 24[
gg 9dd 7 3 f,,
3 19 4
Ob 20 Shl 5
900 3SN 21 NN 73I 6
22 bAO 839 7
n 904
?IP 24 9
f 83b 25 10
'33 73a 26 II
'b!
83l 27 N33 70O 12 3
O bbb 13 29 I4 SI2 bb 30 15 S29 895 33 16 l
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)
,a
l UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50 30Y ~
UNIT NAME F inn Un ir -1 DATE-O'Ido REPORT MON 111 [} U 0 US T I980 COMPLETED BY
& /M f a o A' v
TELEPHONE - 31.2
~1 Y/# - 20Y/
G K 7~ 3&J s "=r
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c e
3 g
- , p g Licensee f*.
Cause & Corrective N"-
Da'#
E 2E
.E 3 oc Event u7 3
Action to
$3 E
j di y R' Port #
ih0 ju E revent Recurrence 6
IS 900809 F
15.9 a
i g /A N/A 4/A
-for binc., / (rwerA+or o 44 &
refAi R$ of STA7 oA. w Atev
- c. 0 0 L i h6-Puen 95
- t 4007iO F
5.1 A
3
^> / A J /^
e/^
Re ac-t o r reif) dv4 +o sltr u.
lo-le ve.1 in coinc.;A.en4 wi4%.S*'A%
-C lou; / fe e8 f lou m's s mA fcA c(o e 4tl 51ew s vite, w 16 le. ca.4 fe n,p 'eny -
y fe afar & E {t,e 4 to a-ter pump.
.i. o tootio i'
3(a.4 A
3 e)A 4)A 4 /A Re.* cior-te;e S)(r ac. Si'Aq Fl*/+ -
pee g plow.m ispia ecA. caince d e n wj4 k to-leVf] cm v$e.d by 9Er1EFC110h*
ct.ve.rs e. p ow e.r + rip clu t, to A.
pro b le m w i n. +ke. e HC-sys f eas.
Al 9009k.9 f
O A
b MIA dlA a)R L o no* re a o cef) -% L o c a le. p rlmery.
co ol et.nt St/ 5 +e m Le 4 M.
a 1
2 3
4 F: Forced Reason:
Method:
Exhibit G - Inst ructions S: Scheduled A-Equipment Failure (Explain) l-Manual for Preparation of Data B-Maintenance of Test 2-Manual Scram.
Entry Sheets for Licensee
- l C Refueling 3-Automatic Scram.
Event ReporI (LER) File (NUREG-D-Regulatory Restriction 4-Other (Explain) 0161)
E-Operator Training & License Examination F-Administrative 5
G-Operational Error (Explain)
Exhibit I - Same Source 19/77)
Il-Other(Explain) jd
_U
t
SUMMARY
OF OPERATING EXPERIENCE UNIT 1 The Unit entered the reporting period at a power level of 997 MWe (99% reactor power).
The Unit remained at, or near this power level until August 22nd, at 1045 hours0.0121 days <br />0.29 hours <br />0.00173 weeks <br />3.976225e-4 months <br /> when'the reactor tripped, due to 1B steam generator lo-lo level.
The Unit was made critical on August 23rd, at 0306 hours0.00354 days <br />0.085 hours <br />5.059524e-4 weeks <br />1.16433e-4 months <br />, and was synchronized to the grid at 0550 hours0.00637 days <br />0.153 hours <br />9.093915e-4 weeks <br />2.09275e-4 months <br />.
On August 25th, at 1845 hours0.0214 days <br />0.513 hours <br />0.00305 weeks <br />7.020225e-4 months <br /> the generator was taken down manually, due to voltage regulation problems and was synchron-ized to the grid on August 27th, at 1505 hours0.0174 days <br />0.418 hours <br />0.00249 weeks <br />5.726525e-4 months <br />.
On August 27th, at i
1535 hours0.0178 days <br />0.426 hours <br />0.00254 weeks <br />5.840675e-4 months <br /> a reactor trip / turbine trip occurred, due to 1B feedwater pump...The Unit was made critical on August 28th, at 0001 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and was synchronized to the grid at 0317 hours0.00367 days <br />0.0881 hours <br />5.241402e-4 weeks <br />1.206185e-4 months <br />.
Overall, the Unit per-formed very well, having an Availacility Factor of'89.9% and a Cap-j acity Factor of 78.1%.
The Unit ended the month on-line at a power 1
level of 1015 MWe (98% reactor power).
UNIT 2 i
The Unit entered the reporting period at a power level of 942 MWe (90% reactor potter).
On August 9th, at 2305 hours0.0267 days <br />0.64 hours <br />0.00381 weeks <br />8.770525e-4 months <br /> the turbine / gen-erator was manually shutdown for the repairs of stator water cooling
. On August 10th, at 1502 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.71511e-4 months <br /> the reactor tripped, due to pumps.
steam generator 2D lo-level in coincident with steam flow / feed flow mismatch, due to steam spike while attempting to start "B" feedwater pump.
The Unit was made critical at 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br />, and at 2010 hours0.0233 days <br />0.558 hours <br />0.00332 weeks <br />7.64805e-4 months <br /> the reactor tripped from steam generator 2C steam flow / feed flow mismatch. coincident with lo-level caused by generator reverse power trip, due to a problem with the EHC system.
On August lith, at t
0340 hours0.00394 days <br />0.0944 hours <br />5.621693e-4 weeks <br />1.2937e-4 months <br /> the Unit was made critical, and.was synchronized to the -
grid on August 12th, at 0830 hours0.00961 days <br />0.231 hours <br />0.00137 weeks <br />3.15815e-4 months <br />.
Overall, the Unit performed very well having an Availability Factor of 92.3% and a Capacity Factor of-76.7%.
The Unit ended the month on-line at a power level of 940 MWe (92% reactor powerl.
1 1
]
1
-AUGUST MAJOR SAFETY RELATED MAINTENANCE 1
Equipment Name Work Done 2B R.C. Pump Seals Replaced #4 seal, seal in-sert, runner.
Replaced motcr connected to pump.
2B Reactor Coolant Pump No. 3 seal replaced 2D Reactor Coolant Pump Complete seal inspection
~
for fluctuation #1 leakoff and high stand pipe alarm 2A Charging Pump Installed new inboard and outboard mech, seals, new shaft sleeves, new thrust shoes, new sleeve "O" rings and associated gaskets.
2A Auxiliary Feed Pump Installed new gov. end radial Turbine bearing, new thrust bearing, new carbon seal rings inboard and outboard and new gaskets-and oil seal.
2C Containment Spray Pump Installed new bearings i
i i
A M
Y l
4, -, _ _. _ _
~
Pega 1 of 3 REFUELING INFORMATION REQUEST Questions:
1.
Name of facility.
2.
Scheduied date for next refueling shutdown.
- 3.. Scheduled date-for restart following refueling.
4 Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
i If answer is yes, what, in general, will these be?
If. answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to determine whether any unreviewed safety questions are associated with the core reload (Ref.10 CFR Section 50.59) ?
i i
If no such review has taken place, when is it scheduled?
5.
Scheduled date (s) for submitting proposed licensing action and supporting _information.
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.
7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.
8.
The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies.
~
9.
The. projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.
l l
i t
l'
.. _ _.. - -, _. _ _.,. ~. _. _...,.
=-
Page 2 of 3 Unit 1 - Answers 1.
Zion Unit 1.
2.
January 1, 1981 is the scheduled date for the next refueling outage.
3.
February 18, 1981 is the scheduled date for initial criticality I
following refueling.
4.
The reload fuel design and core configuration has not under-gone On-Site and Off-Site Review.
However, no Technical Specification 4 :hanges or license amendments are anticipated.
)
The On-Site and Off-Site review of the Cycle VI fuel design and core configuration is enrrently scheduled for completion by November 1, 1980.
5.
If the need for Technical Specification changes or other license i
amendments arise from the review in 4 above, then November 1, 1980 will be the scheduled date for submitting the required information.
4 6.
No important licensing considerations are anticipated with this refueling.
7.
The number of fuel, ass'emblies a) in the core is 193, and b) in the spent fuel storage pool, which have been discharged urom Zion Unit 1, is 248.
1 4
8.
The present licensed spent fuel pool storage capacity (shared with Zion Unit 21 is 2112 fuel assemblies.
}
The installation of the new storage racks is scheduled to begin within the next two months.
9.
- October, i
1992 is the projected date of the last Zion Unit 1 refueling which can be discharged to the spent fuel pool assuming l
the presen.
licensed capacity.
i i
i i
,,,ec-e"-w.-
l Page 3 of 3 Unit 2 - Answers 1.
Zion Unit 2 2.
September 12, 1981 is the scheduled date for the next refueling outage.
3.
October 31, 1981 is the scheduled date for initial criticality following refueling.
4.
The reload fuel design and core configuration has not undergone On-Site and Off-Site Review.
However, no Technical ~ Specification changes or license amendments are anticipated.
The On-Site and Off-Site review of the cycle VI fuel design and core configuration is currently scheduled for completion by July 15, 1981.
5.
If the need for Technical Specification changes or other license amendments arise from the review in 4 above, then August 1, 1981 will be the scheduled date for submitting the required information.
I
.6 No important licensing considerations are anticipated with this refueling.
7.
The number of fuel assemblies al in the core,is 193, and b) in the spent fuel storage pool which have been discharged by Zion Unit 2 is 260 8.
The present licensed spent fuel pool storage capacity (shared with Zion Unit 1) is 2112 fuel assemblies.
The installation of the.new storage racks is scheduled to begin within the next two months.
9.
October, 1992 is the projected date of the last Zion Unit 2 refueling, which can be discharged to the spent fuel pool assuming the present licensed capacity.
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