ML20215B097
| ML20215B097 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 05/31/1987 |
| From: | Dean C, Miller D CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8706170220 | |
| Download: ML20215B097 (10) | |
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MONTHLY OPERATING REPORT NO. 87-05 FOR THE MONTH OF 1
MAY 1987
.8706170220 870531
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- PDR.-. ADOCK 05000213I i
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PLANT OPERATIONS
SUMMARY
- MAY 1987 The following is a summary of plant operations for May 1987.
On May 5 at 1105 hours0.0128 days <br />0.307 hours <br />0.00183 weeks <br />4.204525e-4 months <br />, we reduced load to 530 MWE to adjust the number three governor valve position. At 1121 hours0.013 days <br />0.311 hours <br />0.00185 weeks <br />4.265405e-4 months <br />, the governor valve was reset and we commenced increasing the load. At 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br />, 100 percent power was attained.
On May 9 at 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br />, we reduced load to 300 MWE to allow entry into containment to add oil to number 4 Reactor Coolant Pump. At 1644 hours0.019 days <br />0.457 hours <br />0.00272 weeks <br />6.25542e-4 months <br />, we commenced increasing load. At 2228 hours0.0258 days <br />0.619 hours <br />0.00368 weeks <br />8.47754e-4 months <br />, 100 percent power was attained.
On May 22 at 0935 hours0.0108 days <br />0.26 hours <br />0.00155 weeks <br />3.557675e-4 months <br />, we reduced load by 25 MWE to replace the number one feed water regulating valve positioner. At 1037 hours0.012 days <br />0.288 hours <br />0.00171 weeks <br />3.945785e-4 months <br />, 100 percent power was attained.
The plant was operated at 100 percent power for the remainder of the month of May 1987.~
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AVERAGE DAILY UNIT POWER LEVEL
. DOCKET NO.
50-213 Conn. Yankee UNIT Haddam Neck DATE 6-1-87 COMPLETED BY C. B. Dean TELEPHONE (203) 267-2556 MONTH:. May 1987 DAY AVERAGE DAILY. POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) l 1
534-17 551 2
534 18 548 1
3 333 19 548 4-534.
20 548 5-545 21 548 6'
557 22 547 7
557 23.
546 557 546 8
24 482 544 9
25 554 544
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4 553 545 11 27 547 12 552 28 544 13 552 29
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11 4 552 30
.15 552 31 16 552 I
INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month.
Complete the nearest whole megawatt.
(9/77)
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CONNECTICUT YANKEE:
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REACTOR COOLANT DATA E'
1 MONTH: MAY 1987 i
REACTOR ^ COOLANT
- ANALYSIS
. MINIMUM AVERAGE MAXIMUM L :.'....................................................................
lPH @ 25 DEGREES C-6.87E+00-:
6 97E+00 7.14E+00.
. CONDUCTIVITY.(UMHOS/CM) 6.90E+00 8.81E+00 1.22E+01 :
- <5.00E-02 : <5.00E-02': <5.00E-02+
DISSOLVED' OXYGEN (PPB).
- <5.00E+00 : <5.00E+00 : <5.00E+00':
1 1.56E+02.3.2.04E+02 :
2.69E+02 :
4.54E-01
. 5.97E-01 8.85E-01 2 cTOTAL GAMMA ACT. (UC/ML) 1.94E-01 2 3.13E-01 l-3.62E-01 IODINE-131~ - ACT. t (UC/ML)
4.0 3E-031
6.81E-03E:
1.10E-02 :
I-131/I-1'33 RATIO
.L 1.37E+00':
1.87E+00 2.83E+00.
CRUD (MG/ LITER)-
- <1.00E-02': <1.00E-02:
<1.00E-02.
1 TRITIUM-(UC/ML) i 1.15E+00
- 1.36E+00 1 1.50E+00 :
! HYDROGEN.(CC/KG) 2.00E+01 2.24E+01-2.'66E+01 :
AERATED LIQUID WASTE PROCESSED (GALLONS):
1.38E+05 1 WASTE LIQUID PROCESSED'THROUGH BORON' RECOVERY (GALLONS):
9.31E+04 AVERAGE PRIMARY LEAK RATE (GALLONS PER MINUTE):
4.88E-01 PRIMARYLTO SECONDARY. LEAK-RATE (GALLONS PER MINUTE):
0.00E+00.
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'NRC Oporcting Ototuo Ropert Haddam' Neck
- 1. Docket: 50-213
- 2. Reporting Period: 05/87 Datage + On-line Hours:
0.0 + 744.0 = 744.0
- 3. Utility
Contact:
J. Stanford (203) 267-2556 ext 325
- 4. Licensed Thermal Power (Mt): 1825
- 5. Naseplate Rating (Bross Me): 667 x 0.9 =. 600.3
- 6. Design Electrical' Rating (Net Me): 582
- 7. Maxieue Dependable Capacity (Bross Meli 595.8
- 8. Maxieue Dependable Capacity.(Net Me): 569
- 9. If changes occur above since last report, reasons are: NONE
- 10. Power level to which restricted, if any (Net Me): N/A
'.!!. Reasons for restriction, if any: N/A MONTH YEAR-TO-DATE CUMULAT!VE
- 12. Report period hours:
744.0 3,623.0.
170,103.0
- 13. Hours reactor' critical:
744,0 3,589.1 145,049.3
- 14. Reatter reserve shutdown hours:,
0.0
. 0. 0 1,285.0 15; Hours generator on-lines 744.0 3,568.7 139,056.3
- 16. Unit reserve shutdown hours::
0.0 '
O.0 398.0
- 17.' Bross thermal energy generated (MtH):
1,339,821.0 6,349,524.0 240,729,985.0 t
- 18. Bross electrital energy generated (MeH):
425,336.0 2,038,448.0
~70,851,370.0 t
'19. Net electrical energy generated (MeH):
405,235.8 J,941,287.3 74,972,775.3 8
- 20. Unit service factor 100.0 98.5 81.7
- 21. Unit availability f actor:
100.0 98.5 81.9
- 22. Unit capacity fattor using MDC net 95.7 94.2 80.6 1
- 23. Unit capacity factor,using DER nets 93.6 92.1 75.7 l
- 24. Unit forced outage rate:
0.0 1.5 6.1
- 25. Forced outage hours:
0.0 54.4 8,975.6 l
- 26. Shutdowns scheduled over next 6 sonths (type,date, duration): REFUELIN8 07/18/87 14 WEEKS
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. 27. If currently shutdown, estiaated startup date: N/A l
I I Cumulative values from the first criticality (07/24/67). (The remaining cumulative values are from the first date of consercial operation, 01/01/68).
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, {p REFUELING INFORMATION REQUEST W
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. hut. Yankee Atomic' Power Company 2.
. Scheduled klate for next cafueling shutdown.'
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Jul 17,1987 (last day at full power) 3.
Scheduleddateforrestartfollowingref,ueling.
,+b 9etober 30',1987. (first day at full poudr) d(
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(3) Will'refue ing or resumption of operation thereafter require a technical speci-E
'. 'i. ff eation' change,or other license. unendment?
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J YES (b) If answer'is yes, what, in general, will'these be?
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( Technical Specifications related to revised physics reload methodology and transient M. analyses design basis.
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(c) If answer is no, has'the' reload fuel design and core configuration been reviewed i
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by your Plant Safety Reirdgw Committee to determine whether any unrevietved safety
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questions are associatod with the core reload (Ref. 10 CFR Section 50.59)?
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a yNpt applicable.
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, j (d) If no such revie has taken place, when is it scheduled?
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f Nth applicable.
.hheduleddate(s)for'submittingproposedlicensingactionandsupportinginformation.
5.
. i. 6/)l/87 j
6.
'Important licensing considerations asecciated with refueling, e.g., new or different fuel design or supplier, unrevievod design or performance analysis methods, significant changes in fuel design, new opedacing procedures, j
NO
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The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.
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li-(a) 157 (b) 597 rol?.:
56 new fuel ascenblies in New Fuel Storage.
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The present licenred spett fuel pool storage capacity and the size of any increase in N
licensed storage capreity that has been dequested or is planned, in number of fuel assemblies.
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71 7 9.
The' ptt;jected date of the last refueling that can be discharged to the spent fuel g\\a }J pool' assuming the present licensed capacity.
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g_i CONNECTICUT YANKEE ATO MIC POWER COMPANY HADDAM NECK PLANT RR#1
- BOX 127E
- EAST HAMPTON, CONN. 06424 June 15, 1987 RE: Technical Specification 6.9.1d Docket No. 50-213 U. S. Nuclear Regulatory Commission j
Document Control Desk Washington, D. C. 20555
Dear."ir:
f In accordance with reporting requirements of Technical Specification 6.9.1d, the Connecticut Yankee lladdam Neck Plant Monthly Operating Report 87-05, covering operations for the period May 1, 1987 to May 31, 1987, is hereby forwarded.
Very truly yours, Donald B. Miller, Jr.
Station Superintendent DBM/mdw Enclosures cc:
(1) Regional Administrator, Region 1 U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 (2)
-P. Swetland Sr. Resident Inspector Connecticut Yankee 1
4"44
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