ML20024F106
| ML20024F106 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 08/14/1983 |
| From: | Elms A, Graves R CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| NUDOCS 8309080235 | |
| Download: ML20024F106 (9) | |
Text
T CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT HADDAM, CONNECTICUT l
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MONTHLY OPERATING REPORT No. 83-7 FOR THE MONTH OF JULY 1983 b
9 4'b 9309080235 830731 1{
PDR ADOCK 05000 R
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PLANT OPERATIONS The unit operated at 100% power until July 7 at 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br />. A load decrease was commenced to 400 MWE to conduct a routine turbine control valve test. The plant continued a load decrease to 360 MWE and then idled loop 3 in order to repair a leak on the steam generator wide range level instrumentation root stop valve. Loop 3 was returned to service at 1528 hours0.0177 days <br />0.424 hours <br />0.00253 weeks <br />5.81404e-4 months <br /> and a load increase was started l
at 1607. The unit reached full power on July 7 at 1859 hours0.0215 days <br />0.516 hours <br />0.00307 weeks <br />7.073495e-4 months <br />.
A load reduction was commenced at 0400 on July 16 to 60% power.
Loop I was idled to investigate a low oil level alarm on the #1 1
reactor coolant pump. The alarm was repaired and loop I was returned to service at 1033 hours0.012 days <br />0.287 hours <br />0.00171 weeks <br />3.930565e-4 months <br />. The unit reached 100% power at 1340 on July 16.
Another load reduction was commenced on July 27 at 0500 to idle i
loop 3.
The steam generator wide range level instrumentation root stop valve was found to require additional repairs and loop 3 was subsequently returned to service. At 1256 hours0.0145 days <br />0.349 hours <br />0.00208 weeks <br />4.77908e-4 months <br /> the unit commenced a 4
load increase and at 1530 on July 27 the plant reached full power.
l The unit remained at 100% power for the duration of July.
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EFFECT SPECIAL PRECAUTIONS.
SYSTEM I&C R p3rt for July 1983 ON CORRECTIVE ACTION TAKEN TO PROVIDE OR MALFUNCTION SAFE TAKEN TO PPR ENT FOR REACTOR SAFETY COMPONENT CAUSE RESULT OPERATION REPF*'ITION DURING REPAIR
- 1 Reactor Coolant Vibration Low level None Readjusted and Reduced power Pump 011 reservior caused loose alarm actuated tightened connections Low Level Alarm connection e
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seeeeos NRC OPER AllNG ST ATUS REPORT COMPLE VED BY R E ACIOR E NGINE E R I NG * * * * * *
- 1.
DOCKE T.... 50-213 0P ER A TING STA TUS 2.
RE POR T ING PER IOO...JUL Y 1983 OuiAGE. ONLINE HOURS..
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UI ! L i f f C ON T A C T............ A. L. ELMS 82039 267-2556 EIT 258 esseeeeeeeeeeeesessees 4.
LICENSE 0 THE R M A L P 0WE R................................... 18 2 5
- CONNECTICUT YANKEE e S.
NAME PL ATE R AT I NG I GROS $ MWE l................ 66 7 X 0.9 = 600.3 e HADOAM NfCR PLANT e 6.
DESIGN ELECTRICAL RATING (NET MWER.......................
582
- esseesseeeeeeeeeees 7.
MARIMUM DEPENOABLE CAPACITV (GROSS PWEl.................
595.8 8.
MAX tMUM DEPENDABLE CAP AClif (NET MWEl....................
569 9.
IF CHANGES 00C04 ABOVE SINCE LA$i REPORio REA50NS ARE......N/A t o. P OWE R LE V E L 70 WHICH RESTRICTEO. IF ANY INET MWEl..........N/A
- 11. PEASON FOR RESTRICil0N. IF ANY.............................N/A
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MONTH TR. 10 DaiE CUMUL ATIVE TO D ATE j
- 12. HOUR $ IN REPORTING pep!OO 744.0 5087.0 136583 0 e
- 13. NUMBER OF HofR$ THE RFACTOR WAS CRlitCAL 744.0 3276.0 187528.4 e
- 84. REACTOR RESERVE SHUIDOWN HOURS 0.0 0.0 8264.0 e
- 15. HOURS CENERATOR ONLl1E 744.0 3145.3 182235.4 e
- 16. UNIT RESERVE SHUIDOWN HOURS 0.0 00 373.7
- 17. GROSS THERM AR. ENE RGY GENER ATEP (MWH3 1337082 0 5535913.0 194T01403.0
- 18. GROSS ELFCTRIC AL ENERGY GENER ATED IMWHI 421863.0 1801258.0 63940159.c
- 19. NET ELECTRICAL ENERGY GENERATEO IMWH3 401701.0 1706770.8 608255R2.R
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- 20. UNIT SERVICE FACEJR 100.0 61.8 82 2 e
- 21. UNIT AVAILABILITY FACIOR 100.0 61 8 82.4 e
- 22. UNII CAPACITY FACTOR tuS'NG MOC NETI 94.9 59.0
- 1.9 e 2 3. UNI T CAPACITf FACIOR EUSING DER NEil 92.8 57.6 75.9 e
- 24. UNIT FORCED OUTAGE RAIE 0.0 0.9 6.4 e 9
- 25. UNIT EORCEO OUTAGE HOUMS 0.0 27.0 7619.0
- eSINCE EOMMERCIAL OPERATION I/t/68 SHUIDOWNS SCHE 0tE ED DVE R NEXT SIM MONTHS tiYPE, DATE ANO DURATION OF EACHl.............
N/A IF CURRENTLY SHUTDOWN, ESitMATEO STARTUP DATE....................
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CONNECTICUT YANKEE REACTOR COOLANT DATA MONTH: JULY 1983 REACTOR COOLANT ANALYSIS MINIMUM AVERAGE MAXIMUM PH 0 25 DEGREES C 5.55E+00 5.77E+00 5.92E+00 :
CONDUCTIVITY (UMHOS/CM) 1.65E+01 :
1.98E+01 :
2.45E+01 :
- <5.00E-02 : <5.00E-02 :
5.30E-02 :
DISSOLVED OXYGEN (PPB)
- <5.00E+00 : <5.00E+00 : <5.00E+00 :
8.59E+02 :
9.16E+02 :
1.59E+00 :
2.03E+00 :
TOTAL GAMMA ACT. (UC/ML) 6.08E-01 :
8.00E-01 :
9.90E-01 :
IODINE-131 ACT. (UC/ML) 4.62E-03 :
5.82E-03 :
6.66E-03 :
I-131/I-133 RATIO 8.76E-01 :
1.00E+00 1.17E+00 :
CRUD (MG/ LITER)
- <1.00E-02 : <1.00E-02 : <1.00E-02 :
TRITIUM (UC/ML) 1.95E+00 2.24E+00 1 2.45E+00 :
HYDROGEN (CC/KG) 2.79E+01 :
3.33E+01 :
3.96E+01 :
AERATED LIQUID WASTE PROCESSED (GALLONS):
1,70E+05 WASTE LIQUID PROCESSED THROUGH BORON RECOVERY (GALLONS):
3.41E+04 AVERAGE PRIMARY LEAK RATE (GALLONS PER MINUTE):
4.11E-01 PRIMARY TO SECONDARY LEAK RATE (GALLONS PER MINUTE):
3.47E-04
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-213 Conn. Yankee UNIT Haddam Neck DATE July, 1983 A. Elms COMPLETED BY TELEPHONE (203) 267-2556 uly 1983 MONTH:
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 560 17 544 2
555 18 543 553 543 3
19 551 543 4
20 550 542 5
21 551 545 6
g 7
546 416 550 549 8
24 553 551 9
25 554 550 10 26 554 466 l
11 27 553 550 12 28 551 550 13 29 550 3
30 549 547 g
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l INSTRUCTIONS l
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.
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I 50-213 DOCKET NO.
UNITSilUTDOWNS AND POWER REDUCTIONS UNIT NAME Conn..ankee q
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1
REFUELING INFORMATION REQUEST 1.
Name of facility Connecticut Yankee Atomic Power Company 2.
Scheduled date for next refueling shutdown.
July 21, 1984 3.
Scheduled date for restart following refueling.
September 8, 1984 4.
(a) Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
No technical specification changes are anticipated at this time.
(b)
If answer is yes, what, in general, will these be?
N/A (c)
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)?
When the above stated documents are received from the fuel vendor, they will be reviewed in accordance with 10CFR50.59 to determine if any unreviewed safety questions are associated with the core r
reload.
(d)
If no such review has taken place, when is it scheduled?
N/A 5.
Scheduled date(s) for submitting proposed licensing action and supporting information.
There are no scheduled dates because of question 4 above.
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.
None 7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.
(a) 157 (b) 493 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.
1168 9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.
1994 to 1995
CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT RR # 1, BOX 127E. EAST H AMPTON CONN. 06424 August 14, 1983 Docket No. 50-213 Director, Office of Management Information and Program Control U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Dear Sir:
In accordance with reporting requirements, the Connecticut Yankee Haddam Neck Monthly Operating Report 83-7, covering operations for the period July 1, 1983 to July 31, 1983 is hereby forwarded.
Very truly yours, Richard II. Graves Station Superintendant
!!HG/mb Enclosures cc:
(1) Director, Region I Division of Inspection and Enforcement U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 (2) Director, Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention:
Mr. Victor Stello v
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