ML19332C072
| ML19332C072 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 10/31/1989 |
| From: | Joyce T, John Thomas COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8911220284 | |
| Download: ML19332C072 (15) | |
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.' Zion Gintrating Station c, ?
101 Shiloh Blvd.
- Zion,'lilinois 60099 Telephone 3121746 2084 -
November.2,.1989 o
r U.>S.
Nuclear Regulatory Commission Document Control Desk Washington,.DC 20555
Dear Sir:
Enclosed please: find the Operating Status Report for.
the~ month of.0ctober, 1989 for Zion Generating Station.
Sincerely,
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T. P. Joycp.
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Station Mahager Zion Station I
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Enclosure
'cc :
T. Maiman L
A. B. Davis (NRC)
L. D. Butterfield H.'E.
Bliss M. Finn L.
J. Ananstasia INPO L
Div.' of Eng. Health State of IL
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Tech Staff File Director, Office of Inspection and Enforcement Master File 1
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4-OPERATING DATA REPORT DOCKET No. 50-29 5 DATE 11/02/89 COMPLETED SY
>. Thomas TELEPHONE (706)/46-2084 OPERATING STATUS
- 1. Uaft Name:
Zion Unit 1 Nota
- 2. Reporting Peilod:
0000 891001 to 2400 891031
- 3. Liesmeed Thennelroww (MW:):.39sn
- 4. Namepiste Rating (Grom MWe): 1085
- 5. Design Electrical Rating (Net MWe)
1040
]
- 6. hulmum De;endable Capacity (Gross MWe)-
1OR5
- 7. Maakaum Dependable Capacity (Not MWe):
1040
' 8. If Cheesse Ocew in Capacity Ratings Gtems Nussber 3 Thre agh 7) Since last Report, Give Reasons:
NIK 9.' Power Level To Which Restricted,11 Any (Net MWe):
N/A
' 10. Reasons For Restrictions,if Any:
N/A Thb Weath Yr t&Dete Cumuletter
- 11. Moure la Reporting Period 745.0
- 7.296.0 138,816.0
' 12. Number Of Hours Reactor Was Critical 0.0 5,268.3 98.101.4-
- 13. Reactor Reserve 5' utdows Hows 0.0 0.0 2,621.8 a
- 14. Hours Gensator On Line 0.0 5,152.0 95.301.4
- 18. Unit R+eerve Shutdown Houn 0.0 0.0 0.0 16, Grom Thermel Energy Generated (MWH) 0.0 15,620,439 273,461,029
- 17. Gross Electrical Energy Generetad (MWH) 0.0 5,224,,653 89,062.609
- 18. Net Elecerten! Energy Cemeseted (MWH) 0.0 4.999.460 88',110.54'9'
- 19. Unit Servies Factor nn 78.6 69.0
- 30. Unit Avallabuity Factor 0.0 78.6 69.O i
- 21. Uelt Capacity Factor (Using MDC Net) _
0.0 73.4 61.4-
- 22. Unit Capacity Factor (Uelag DER Net) 0.0 7 t/A 61.4
- 23. Unit Forced Outage Rate 00 20.7 12.8
- 34. 3betdowns Scheduled Over Next 6 Months (Type. Dete.and Duration of Each):
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-Refuellna Unit 1 Shutdown date:
9/7/89 for approximately 10 uLs.
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- 28. If Shut Down At End Of Report Period. Estimated Date of Startup:
11/26/89 l
- 26. Units in Test Status (Prior to Commercial Operation):
Forecent Achkved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION
- 744 hours0.00861 days <br />0.207 hours <br />0.00123 weeks <br />2.83092e-4 months <br /> in month plus 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> daylight savings time.
(9/77)
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OPERATING DATA REPORT DOCKET NO. 50-304 DATE 11/09/89 COMPLETED 8Y 1
Thnmas TELEPHONE (708)746-2084 OPERATING STATUS L
- 1. Unit Naam: - 7 inn Unit 2 Notes
- 2. % Period: 0000 891001 to 2400 891031
- 3. Lloonsed ThennalPower (MWt): 3250 c.
- 4. Nemwpiste Rating (Gross WWe):
1085 L
- s. Design Electrical Reting (%t MWe):
1040 L
- 6. Maxhnum Dependable Capacity (Grom MWe):
1085
- 7. Maximums Dependekle Capacity (Net MWe).
1040 l
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Tluough 7) Since Last Report, Give Reasons:
M/A
- 9. Power Level To Which Restricted,if Any (Net MWe):
O
- 10. Reasons For Restrictions,If Any:
N/A This Month Yr. to Dete -
Cumuistive
!!. Hours In Reporting Perlod 745.0
- 7,296.0 1q9_s99 o 3
.12. Nussber Of Hours Reactor Was Celtical 7A5 0 6.869.9 94.024.7
- 13. Reactor Resern Shutdown Hour, DJ 0.O
??6.1
- 14. Hours Generator On Lhw 745.0 6 R74.8 96.036.1
- 15. Unit'Aosam Shutdown Heure 0.0 0.0 0.0
' 16. Geens Thenmal Emessy Generated (MWH)
_2.352.951 1o A16 s61 9ao 110.705 i
17.- Gsee; Eisctrical Enagy Generetad (MWH) 788,959 6.579 323 87.654.220
~
- 18. Nt Enscer6 sal Easrgy Genented (MWH) 761.454 6.302.729 86,065,617 i
- 19. Unit Servies Factor 100.0 93.5 72.5 1
- 20. Unit Aveasbuity Facto, 100.0 93.5 72.5
- 21. Unit Capocky Factor (Using MDC Mt) 98.5 83.1 62.4
- 22. Unit Capacity Factor (Using DER Nt) 98.5 g1.1 62.4
- 23. Unit Forood Outage Rate 0.0 6.7 14.4
- 24. Sheldowns Scheduled Over Nat 6 Months (Type. Dete, sad Duration of Eachl:
- 25. If Shut Down At End Of Report Period Estbneted Date of Startup:
- 24. Units in Test Status (Prior eo Comnwecial Operation):
Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION
- 744 hours0.00861 days <br />0.207 hours <br />0.00123 weeks <br />2.83092e-4 months <br /> in month plus 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> daylight savings time (4/77)
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- AVERAGE DAILY UNIT POWER LEVEL
..c DOCKET NO.
50-295
. UNIT Zion Unit'1-
'pA13 11/2/89' 4 '
COMPLE1ED BY -
J. Thomas 11LEPHONE -
(708)746-2084 MONiy October-1
, DAY AVERAGE DAILY POWER LEVEL DAY
- AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-NC) 1-
-10 17
-10 2
' Ig.
-10 i
-10
-10 39 3
, l; 4
1n 20 3
-10 5:
' -10 ~
21 '-
-10
-10 22
'6 L
-10
-10 7 --
23 -
-10
-10.
s.
34 !
-10 25
-10:
'-10
-10 26
-10
-10 27
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12' 28
-10
-10 13 -
29 -
-11
-10 30 1n-
-14
-10 15 31
-10
-10 16-
!NSTRUC110NS On this format list the average daily unf t power level in MWe. Net for each day in the reporting month. Compute to
.the nearest whole megawatt.
(9/77)
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, AVERAGE DAILY UNIT POWER LEVEL -
DOCKET NO. 50-304 UNIT Zion Unit 2 e<-
DAT3 11-02-89 COMPLETED BYEJ. Thomas TTLEPHONE - (708)746-2084 -
MONTH ncenbac
-l DAY' AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL
-- (MWe-NeO (MWe Net)-
l 1047 948
-1 37 1047 2_
la 1nio-3-
1046 1,-
1045
.' 4 1050 20-1046
'2
- 5 1049-21 1045 6
1047 22 1046-961
'7 1049' 23 1049 1046 s.
y 1044 1045 25 1045-10 1047 26 11 1048 27 1042 12 1048 28 1037 816 13 1029 2,
988 14 1043 30 W2 15 1nAA 3
16 950 i
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-J INSTRUCTIONS
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On this format, list the mrage daily unit power level in MWe Net for each day in the reporting rnonth. Compute to L
the nearest whole rnegawatt.
(9/77) l 1
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4 anrarsylogy, 50-795~
INTERffD00nW AISPUIUR RWWT9015 INSTIImW 74aa'"=ie '
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890907 S.
745.C C
1 Unit'l Shutdown for; refueling,.
i Cycle j
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Enlett G-Instrecitans S: Scheduled A-Egalpensee Pseuse(EmpIsin)
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~ I8'T $heets for Licensee
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J3-Maneet seras-Emery C. Refueling 3-avte seram
~ Event Iteport (LER)Far(NUltEG-
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e
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Hoder(EmpInts)
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tsetTWRffBOIIIS AfDFOIfER RWUCHOIS
.mg 11-01 -
m gy.cJ_ Thnmaa REPORT 80W8N Oc' ahar 1gg 3 ge 3 3 (708)746-2084^
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i There were no shutdowns or powe reductions'for the month of October-t
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FaGuse(Espisin)
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-n a seras EmeryIInses for Lkensee C-Refesung 3-Aete seram Ewer Repers(LER)FueUEUREG,
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G4pseselemal Essur(Eglein)
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OCTOBER
SUMMARY
OF OPERATING EXPERIENCE UNIT 1
'The Unit entered the reporting period in cold shutdown for the continuation of the scheduled refueling outage.. The unit remained offline the entire month.
UNIT 2 The Unit entered the report period at a power level of 1078 MHe (99%-
reactor power).
The unit remained on line the entire report. period ending at a port?r level of 1070 MHe (99% reactor power) and having an availability factor of 100.0%.
3397t 0934A-
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'f OCTOBER MAJOR SAFETY RELATED MAINTENANCE
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Equinment Name.
Work Performed
. (UNIT 1)
}
None Unit in Refueling 0utage
- (UNIT:2)
"0" D/G went through"5 year. major overhaul and surveillance.
The'
- Generator'was found~ faulty and replaced.
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t REFUELING INFORMATION RE00EST-Questions:
1.
Name of facility.
2.
Scheduled date for next refueling shutdown.
3.
Scheduled date for restart following refueling.
4..
Hill refueling or resumption of operation thereafter require a technical specification change or other license amendment?
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)?
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.
H 7.
The number of. fuel assemblies (a) in the core and (b) in.tne spent fuel storage pool.
8.-
The present licensed spent fuel pool storage capacity and the size of 4
any increase in licensed storage capacity that has been requested or is planned,-in number of fuel assembliec.
9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.
Page 1 of 3 1397t 0934A
Unit 1 - Antweri 1.
Zion Unit 1 2.
1he current refueling outage began on September 7, 1989.
3.
Cycle 12 is scheduled to go on-line November 17, 1989.
4.- One Technical Specification change was made for the next cycle (Amendment No. 114).
The completed change involves line and valve assignment changes associated with the recently approved Tech Spec change for the Boron i
Injection Tank (BIT) removal. A revised section 14.2.5.1 of the Zion U.f.S.A.R. was submitted in support of this Tech Spec change.
The reload safety evaluation was held on June 1, 1989.
The On-site Review for the Z1C12 reload design is being prepared.
5.
None 6.
None 7.
The number of fuel assemblies a) in the core is 193, and b) in the spent fuel storage pool from Zion Unit 1 is 708.
~
8.
The present licensed spent fuel pool storage capacity (shared k.th Zion Unit 2) is 2112 fuel assemblies.
9.' Zion Station will lose full core discharge capability (for both units) in May 1993, at the end of Unit 2 Cycle 13, based on the latest Nuclear Stations Refueling Schedule.
Full core discharge capability for a single core will be lost in November, 1994, at the end of Unit 2 Cycle 14.
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URLt_2__. Answers 1.
Zion Unit 2 i
2.
Cycle 11 is scheduled to shut down for refueling on March 22, 1990.
3.
Cycle 12 is scheduled to start up May 31, 1990.
4.
The reload safety evaluation meeting for Cycle 12 is scheduled for December 6, 1989. The on-site review will be held after this meeting.
S.
None 6.
None 7.
The number of fuel assemblies a) in the core is 193, and b) in the s;.ent fuel storage pool from Zion Unit 2 is 664.
8.
The present licensed spent fuel pool storage capacity (shared with Zion Unit 1) is 2112 fuel assemblies.
9.
Zion Station will lose full core discharge capability (for both units) in May 1993, at the end of Unit 2 Cycle 13, based on the late:it Nuclear Stations Refueling Schedule.
Full cere discharge capability for a single core will be lost in November, 1994, at the end of Unit 2 Cycle 14, i
t Page 3 of 3 1397t 0934A
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DDCM REVISION The following pages are an addendum to the previous Monthly Operating Report.
The prior report contained a section describing revisions (Revision 11A) made in the ODCM.
However, the revised pages were not included in that-report.
The ensuing pages are the aforementioned.
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'1397t 0934A l
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e Revisions to the Offsite Dose Calculation Manual (ODCH) are reportable to the NRC in accordance with stations' technical specifications.
The document contains the models for the public dose assessment from gaseous effluents, liquid discharges, and direct radiation.
In 1988, in response to the NRC's request to make the ODCM a more readable document as well as to incorporate certain changes, Commonwealth Edison rewrote its ODCM. This document renumbered to Revision 0, March, 1989, will be submitted under separate cover.
This-summary describes the principal.non-edited changes.
f MMOILCHallGE The NRC, in NuReg 0472. Rev. 3, Draf t 7, has identified the child's thyroid and not in infant's as W most sensitive organ from the inhalation of airborne effluents. Dresden, LaSalle, and Quad Cities Stations' 10CFR20 instantaneous release rate limits have been revised to restrict the dose rate i
to the child's thyroid to less or equal to 1500 mrem /yr.
l Hydrogen addition to the primary coolant increases the boiling water reactors' turbine N-16 skyshine by a magnitude of 5.
This phenomenon is now included in the ODCH formulation.
In addition the sky shine calculation is written for LaSalle County Station as well as revised in Dresden and Quad Cities.
MIR0lLCHAllGES Most of the ODCM documentation has been either clarified, corrected or deleted. Plume depletion, terrain factors and heat content were not accounted for in the original for D/0, X/Q and plume rise calculations.
They are described in the revised document.
It was implied that the X/0 dose factors were calculated assuming a monoenergetic gamma energy having an average gamma ray energy per disintegration for each radionuclide. Also, it was assumed that the corrected tissue absorptions were made using a tissue energy absorption coefficient equivalent to this same average gamma ray energy for cach radianuclide.
Actually, the dose t:ctors and the tissue energy absorption coefficients referenced were calculated using the photon energy spectra for each radionuclide. The tissue energy absorptions coefficients are negligible and have been deleted from the text.
Formulas and parameters for determining the maximum permissible concentrations p
(MPC's) have been eliminated from the section on radioactivity in storage tanks.
The maximum limits, in curies, are found in the site specific sections.
l The potential direct radiation dose from stations' interim radwaste storage facilities is discussed.
The radwaste containers will have a contact dose rate of 5 R/hr and the expected radiation levels will be minimal at the site boundary.
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1397t 0934A
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The distance dependent parameters were adjusted to the values reported in the
'88 census for nearest residents and/or nearest milk animal. This also affected the D/0 tables and BHR turbine N-16 skyshine calculation.
The time of travel from the station liquid discharge to the nearest community water supply was reevaluated for Braidwood and Quad Cities.
It-has been determined that the change will not reduce the accuracy or reliability of dose calculations or set point determinations.
i ODCM Revision 0, March 1989 has received approvals by all six on-site review committees and the CECO offsite review per the Technical Specifications.
Chenges to the ODCM computer program required by this document are in the process of being implemented now and should be fully available by November 1, 1989.
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