ML20125E179

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Monthly Operating Rept for Nov 1992 for Zion Generating Station,Unit 1
ML20125E179
Person / Time
Site: Zion File:ZionSolutions icon.png
Issue date: 11/30/1992
From: Cygan J, Joyce T
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
ZAD-92-014, ZAD-92-14, NUDOCS 9212160231
Download: ML20125E179 (14)


Text

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.$ Commonwealth Edison Zon Generating Station 101 Shiloh Dfvd.

Zon. Illinois 60099 Telephone !?4 / 746-2084 December 09, 1992 ZAD-92-014 Nuclear Regulatory Commission Document Control Desk Hashington, DC 20555

Dear Sir:

Attached is the November 1992 Operating Status Report, ww yc/

T.P.J[nManager Statio Zion Station TPJ/jlc Enclosure i

cc: Regualtory Assurance USNRC Document Control M. Hallace A. B. Davis (NRC)

J. Leider T. Rieck T. J. Kovach D. R. Eggett INPO Div. of Eng. Health State of Illinois F. Yost B. Gallo H. Granjean NRC Inspector, Zion P. Graessle Operating Engrs.

C. Patel - Fax Master File

$ 00]$ l, ZCLERK-5(1) l

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OPERATING DATA 0FPORT DOCKET NO._50:295.

DATE_12LO9192 COMPLETED BY_L _Cygan TELEPHONE _170BL746-20B4 13169 QPERAlltlG_SIAIUS

1. Unit Name: _llon_ Volt.I
2. Reporting Per1od: 0000_92110Lto_2400_921130_ Notes
3. Licensed Thermal Power (MHt): 3250
4. Nameplate Rating (Gross MHe): _ _ _1.035
5. Design Electrical Rating (Het MHe):_1010
6. Maximum Dependable Capacity (Gross MHe):_1085 _
7. Maximum Dependable Capacity (Net MHe):__] 010_
8. If Changes Occur in Capactty Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons: 11/&
9. Power Level Td Which Restricted If Any (Net MHe):_ _J{lA
10. Reasons for Restrictions, If Any: JilA Th.. Month Yr-to-Date Cumulative
11. Ilours In Reporting Period __]20A B Q40 Q_ 16L&40A
12. Number Of Hours Reactor Has Critical 720 1 _ __3.8 fill llbhBB 1
13. Reactor Reserve Shutdown Hours OA Om0_ 242LL
14. Hours Generator On-Line . 720 A 3,56L2_ II)B 2121
15. Unit Reserve Shutdown Hours OA 0 ,.0_ _Q A
16. Gross Thermal Energy benerated WH!;L_L20L632_ IL3EL62h_ _311.391d&L D. Gross Electrical Energy Generated (MHH) 742_J153_ 32 500,823_ _10L11L 5]L
18. Het Elcariccl Energy Generated (MHH)__ l L5mS39_ __3.34L 562_ __9Ll6L32L
19. Uni t ' .. n ce f actor 1Q0 1 442L 65 1 _
20. Untt Availability Factor 10Q10_ 44.4 65.3_
21. Unit Capacity Factor (Using MDC Net) 95 1 40.0_ 56 1
22. Unit Capactty Factor (Using DER Net)__ _95 1 40 1 56J_
23. Unit Forced Outage Rate 0.10_ lQ,i_ JLL
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
25. If Shut Down At End Of Report Period, Estimated Date of Startup:
26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved INITIAL CRITICALITY .

INITIAL ELECTRICITY COMMERCIAL OPERATION ZCLERK-5(2)

OPERATING DATA REPORT DOCKET NO._50-304 DATE_12109/92 COMPLETED BY_L _Cygan TELEPHONE _1108) 746-293.4_

x3169 OEEJMUtiGJJAIUS

1. Unit Name: _ZjorLUnit _2
2. Reporting Period: 0000_92110Lio 2400 921J30 Notes 3, Licensed Thermal Power (MHt): 3250
4. Nameplate Rating (Gross MHe): LQ85
5. Design Electrical Rating (Net MHe):_].010
6. Maximum Dependable Capacity (Gross MHe): 10BL
7. Maximum Dependable Capacity (Net HHe):. 104Q_
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasoas: NLA
9. Power Level To Hhich Restricted, If Any (Net MHe): -N/A
10. Reasons for Restrictions, If Any: N/A This Month Yr-to-Date Cumulative
11. Hours In Reporting Period 720,0_. 8.040A __15L553.0_.
12. Number _0f Hours Reactor Has Critical 265.3_ 5.758.7 114.532 L -
13. Reactor Reserve Shutdown-Hours 0.0- 0.0- 226.1
14. Hours Generator On-Line - 26LJ_ 5,11L.0_ -- 111.519A :

.5. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal' Energy-Generated-(MHH) 49L2af 16.703JJL _330.692.340 -
17. Gross Electrical Energy Generated (MHH) 162.128 5.627.978_ . -106.167 .93L -
10. Het Electrical Energy Generated (MHH)- _L4L571 5.365.05L _l01.110.664
19. Unit Service Fattor 3LL 71mL 6LL -
20. Unit Availablilty Factor 3E1 : 71.5_ 69.9
21. Unit Capactty Factor (Using MDC Net) 19 L -- 64.2 60 1 -
22. Unit Capacity Factor (Using DER Net) 19.7 -64 1 - 6QJ_ _

.". Unit Forced Outage-Rate 0. 0__ -25.L.

15.6

<. 4 Shutdowns-Scheduled Over Next 5 Months (Type, Date, and' Duration of Each):

Z2RR - Refaling 11/12/92 - Q2/25/93

25. If Shut Down At End Of Report Period', Estimated Date of Startup: 02/25/RU
26. Units In Test Status (Prior to Commercial Operation): Forecast _ Achieved INITIAL CRITICALITY i

INITIAL ELECTRICITY i COMMERCIAL OPERATION y

ZCLERK-5(3) l

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UNIT SHUTDOHNS AND POWER REDUCTIONS DOCKET NO. EQ=295 UNIT NAME Zion Unit 1 DATE 12/09/92 COMPLETED BY L_Cyg3n TELEPHONE (708) 746-2084 x3169 REPORT MONTH Novemoer 1992 I Duration I Method of Licensee Systgm Compocen l Cause & Corrective 3 Action to No. Date Type l (Hours) Reason", Shutting Event Code Code Down Report # Prevent Recurre:ee Reactor 3 2

720.0 F 5 Unit was on line the l 011192 F ent'.re month. Power was limited to 961 l due to Delta T (

fluctuation.

3 4 2

1 F: Forced Reast Method Exhibit G - Instructions A-Eqt . aent Failure (Explain) 1-Manual for Preparation of Data S: Scheduled 2-Manual Trip Entry Sheets for Licensee B-Maintenance of Test Event Report (LER) Flie C-Refueling 3-Auto Trip D-Regulatory Restriction 4-Continued (NUREG-0161) e E-Operator Training & Licensee Examination 5-Reduced Load 5

F-Administrative G-Operational Error (Explain) Exhibit 1 - Same Source H-Other (Explain)

ZCLERK-5(4) 9

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UNIT SHUTDOWNS AND POWER REDUCTIONS .

DOCKET NO.50-304 _ i UNIT NAME Zion Unit 2 ^

DATE 12/0r/92 i COMPLETED.BY L_Cygan TELEPHONE 1194) 746-2084 x3169 REPORT HONTH November 1992 Duration Method of Licensee Systgm Compogent Cause &' Corrective No. Date Type l (Hours) Reason 2 Shutting Event Code Code Action to Down Report-# Prevent Recurrence Reactor 3 12/11/92 S 454.45 C Reactor came down on 11/12/92 for Refueling Outage.

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'l '2. 3- 4 F: Forced Reason: Method Exhibit G . Instructions 't 15 : Scheduled .A-Equipment' Failure.(Explain) 1-Manual for Preparation of Data .

B-Maintenance of Test' 2-Manual Trip Entry Sheets for Licensee C-Refueling 3-Auto Trip Event Report (LER) File D-Regulatory Restriction . .

4-Continued (NUREG-0161) .

E-Operator Training & Licenvee Examination 5-Reduced Load

'F-Administrative 5 G-Operational Error (Explain) Exhibit 1 - Same Source H-Other (Explain) t ZCLERK-5(5)' ,

.9 AVERAGE DAILY UNIT-P0HER' LEVEL- ,

DOCKET ' N0.' 50.-J95 '

UNITllonXM.L]

DATE_12/09/92 COMPLETED BY_A_Cygan TELEPHONE _(lDBLlA6-2031, _

t31b9 liONTH_tloyember 1932 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL:

(HWe-Net) (HWe-Net)-

1 _963 17 1.022 2 997 18 1.022 o

-3 LD08 19 1.022 4 1.003 20 1.022-5 1M3 21 1.908 6 LO11 22 99.5 7 939 23- 1.Q21.

8 _ 941 24 1.023-'

9 986 25 1.02.2 10 1 D01 26 918-l-

11 -953 27 93 9 12 987 28- 914-13 994 29 913 +

I4 _,

1,Q034. 30 -996 15 _ 1.013 16 1 020 i

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.

ZCLERK-5(6) 1 .

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"4-AVERAGE DAILY UNIT P0HER LEVEL DOCKET N0._50-304 UNIT _ Zion _.tinLL 2 DATE_]2/09192 __

COMPLETED BY_ A Cygtq _

TELEPHONE _(108) )16-2014_.

.33162 MONTil_ NovembeL_1992 _ _

DAY AVERAGE DAILY P0HER LEVEL DAY AVERAGE DAILY POWER LEVEL (MHe-Het) (MWe-Net)

I ___ Ell 17 -l2 e 2 60 2___._ 18 -12 3 _.- ___600 19 -12 4 592 20 -1 5 587 21 _12c 6 _ 58L 22 -1L 7 _ _ _ _57.5__ 23 -12 8 _ 513 24 -12 9 .. 510 25 -12 10 ___ 558 26 -12 1 6 11 _ 524 27 -12 12 -8 28 -12 13 -13 29 --12_

14 -13_ _ 30 _ -12 15 ___ -12__ _ _ _

i6 _ _ ___ -12 _ _

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.

ZCLERr-5(7)

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t!oresher-.1932 SuliMARY OU'ERATIllGlXEERIEllCE UNLL1  :

Unit 1, beg'n NovembJr at 96% Power. The unit has been limited to 96%-

power based sn delte T fluctuation due to Eagle 21.

UlllLZ x

Unit 2, began November at 643 MWe power level (62,0% reactor power),

remained online through 0115 on 11/12/92. . Reactor went into cold shutdown, Hode 5, on 11/13/92. On 11/30/92 Mode changed to 6 for ,

Refueling Outage.

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htelnbar.J292 tR10fLSAEfJY REL&lER_lMIR[EHitiCf l EquipmenLEame hik Perfor_tDad (UNIT 1)

OA fire Pump Sensing Line Broke:-liite Repaired'

& PCV Repaired .

005: 11/01/92 - 11/05/92 1A HDR Pump Seal Hork: Parts 09 Site - Hork Restarted 00S: Continue OA CC Pump Breaker Inspection: Brkr Repaired - 4 New H. R. Issued Z26097 005: Continue - 11/02/92 .

  1. 1 Pp Air Comp Tech Staff Troubleshooting: Head Repair Required 005: Continue ID CD Purp Strainer P High: . Strainer Cleaned 00S: 11/05/92 - 11/06/92 0 0/G Scheduled Work: Hork Completed, PT-11 Completed.

005: 11/16/92 - 11/23/92 1A IA Ccmp Breaker Problem:'Hork Completed.

005: 11/20/92 -11/22/92 CChiMENT:

Should complete work by 12/06/92 Should complete work by 12/07/92 l

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'RQyamber_1932 ,

fB10UAf1LY_RELAIE0JiMMiffiatlCE-EquipmenUdame Hortlerlorad (UN'T 2) 2B llDR Pump Cooler / Seals Leak 005: Continue 2C fH Pump Seal Leak ,

00S: Continue 2A CD/CDB Pp Check Valve Work 005: Continue 2A SH Pump Dreaker Inspection: Scheduled-Outage Hork 005: 11/05/92 - 11/20/92 REFUELING OUTAGE OOS: 11-12-92 COMMENTS:

  • Hork Hi11 De Completed During The Refueling Outage.

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REfMELUlGlHEORtMIl0R3EQUESI Dutillons:

1. Name of facii' ty.
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 fue'l 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 Ilcensed 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.. s

9. the projected date of the last refueling that can be dischargedLto-the spent fuel pool assuming the present licensed capacity.

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UnLt 1 - AnsweII

1. Zion Unit 1
2. Cycle 13 is scheduled to shutdown September 9, 1993 for refueling; ,
3. Cycle 14 is scheduled to start up January 7, 1994.
4. No Technical Specification changes are planned for Z1C14 so far.
5. Not applicable or none proposed.
6. Not applicable.

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 784.

8. The present licensed spent fuel pool storage capacity (shared with Zion Unit 2) is 2112 fuel assemblies. Plans are being developed to' rerack the Spent Fuel Pool to increase storage capacity to 3012 assemblies.
9. Zion Station will lose dual full core _ discharge capability in January 1994, at the beginning of Unit 1 Cycle-14, based on:the latest Nuclear Stations-Refueling Schedule, full core discharge capability.

for a single core will be lost in January 1996, at the beginning of_

Unit 2 Cycle 15.

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. W il 2_ _ Answers : ,

1. Zion Unit 2-
2. Cycle 12 was November 12, 1992 for refueling.
3. Cycle 13 is scheduled to start up February 20, 1993.
4. Yes. Technical _ Specification changes have been made to include the-Hestinghouse VANTAGE fuel design being. loaded for 22C13, and effects of the vessel fluency reduction program beginning with Z2C13.

A Tech Spec change has also been made that will allow CECO to use a CORE OPERATING LIMITS REPORT (COLR) in-place of some existing Tech-Spec Limits.

5 License amendments for the Z2C13 reload were submitted in Summer.

1991, and were approved July 26, 1992 Amendment 128,

6. License considerations associated with the Z2C13 reload include-the new VANTAGE fuel design, and the new LOCA analysis with-higher core power peaking factors required for the low-low-leakage loading pattern used in 22C13.
7. The number of fuel assemblies a) in the core is 0, and b) in the_ spent fuel storage pool from Zion Unit 2 is 933. .
8. The present-licensed spent-fuel pool storage capacity (shared with Zion _ Unit 1) is 2112-fusi assemblies. -Plans-are being developed lto' rerack the Spent fuel Pool to increase storage capacity'to_3012 assemblies.
9. Zion Station will lose dual fu11: core discharge capability in January _

1994, at.the beginning of Unit 1 Cycle 14, basedson the latest Nuclear Stations Refueling Schedule. Full core-discharge capability l

for.a single core will be lost.in January 1996, at the beginning ofL l- Unit-2 Cycle 15, F

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ZCLERK-5(13)

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-.i ADDENDUM TO ZION STATION MONTHLY REPORT-Special Report submitted in accordance with Zion Tech Spec. Surv. 4.14.B. 5-This report' addresses two invalid failures of the 0 EDG. The. criteria to determine valid tests and failures is in accordance with section C. 2.e of Reg. Guide 1.108.

On November. 20, 1992 the 0 EDG tripped during a maintenance run for-maintenance verification. .The-engine had been Out Of Service (O. O. S.), for preventative maintenance (including the replacement of 4 cylinders), for approximately six days. The engine was started, in the maintenance mode and tripped prior to reaching rated speed. It is currently believed that this trip was caused by the work performed. The EDG was returned to service on November 22, 1992 following the successful completion of PT-II. This failure was determined to be invalid per Reg.' Guide 1.108 C. 2.e.

On November 20, 1992-the O EDG was secured, during a maintenance'run, in response to an unusual noise near the 2L cylinder. Investigation revealed.an improperly installed fuel cam key for the 2L cylinder. The key had been improperly installed during the maintenance immediately preceding this?run.

The EDG was returned to service, following the repositioning of the fuel cam key, on November 22, 1992 following the successful completion of PT-11. This

-fallure was determined to be invalid per Reg. Guide 1.108 C. 2.e.

As of November 30, 1992 the test frequency for 0 EDG remains at 31 days.

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