ML20058A089

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Revised Monthly Operating Rept for Aug 1990 for Haddam Neck Plant Unit 1
ML20058A089
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 09/30/1990
From: Emmons K
CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20058A092 List:
References
NUDOCS 9010250269
Download: ML20058A089 (10)


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Haddam Neck Plant -

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Haddam, Connecticut -

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Monthly Operating' Report No.90 09

,a For The Month'of September 1990 '

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. Plant Onerations Summarv - Sentember 1990

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4 The following is a summary of Plant Operations for September 1990.

e On September 1,1990 at 00:00 hours, the plant was in Mode 1 at 30% power for Chemistry hold. At

07
02 hours, power ascension resumed.- By 22:55 hours, the plant was at 80% power and conducting
flux mapping.

On September 3,1990 at 04:57 hours, the plant was manually tripped due to a low suction pressure on the Main Feed Pumps. At 18:10 hours, a primary plant startup was commenced. By 19:11 hours, the plant was in Mode 2, Startup.

On September 8,1000 at 22:55 hours, the plant was phased to the grid. Power was held at 9% because i

of a Chemistry hold.

On September 9,1990 at 04:29 hours, a load increase was commenced. By 06:35 hours, the plant was -

at 30% power on another Chemistry hold. At 22:43 hours, a load increase was commenced.

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~ On September 10,1990 at 04:05 hours, the plant was at 80% and conducting flux mapping. At 12:30 hours, the plant reduced load due to Pressurizer level channels 1 and 2 being declared moperable. By t

14:36 hours, the load decrease was stop been declared operable. At 14:59 hours, ped at 70% power because the Pr:ssurizer level a load increase was commenced. By 16:37 hours, the plant was at 80%_ power conducting flux mapping.

On September 14,1990 at 00:24, the plant commenced increasing load. At 02:03 hours, the load o

increase was halted at 83% power due to condensate pump motor current oscillations. At 19:36 hours, a load increase was commenced. At 22:00 hours, the plant was at 90% and holding for completion of steam line break Estrument calibration. By 23:02 hours, a load increase was resumed. At 23:30 hours, the plant was at 92% and power was reduced due to low discharge pressure on the "IB" condensate i

pump. Plant load was then stabilized at 88% power.

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' On September 15,1990 at 12:30 hours, the plant commenced a load increase. At 12:50 hours, the load was stabilized at 89% power.

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. On September 16,1990 at 23:03 hours, plant load was reduced due to current oscillations on the condensate pumps.' Load was stabilized at 87 % power.

On Se}itember 19,1990 at 13:10 hours, a load increase was commenced. By 14:00 hours, the plant-was at 92% power and began a load reduction to 88% power due to condensate pump oscillations.

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On Septetaber 20,1990 at 00:01 hours, the plant commenced a load reduction to troublesh'oot and.

repair the condensate pumps. At 06:28 hours, the load was at 50% power. At 07:15 hours, the Reactor

= was manua.ly tripped due to low feed pump suction caused by the isolation of the "lB" condensate 1

pump. The plant was returned to Mode 3, (Hot Standby).

. On Septemt er 21,1990 at 14:40 hours, the plant entered Mode 4 (Hot Shutdown) to permit working on pressurizer level instrumentation.

On September 24,1990 at 11:40 hours, a plant heatup was commenced. By 12:26 hours, the plant was in Mode 3 (Hot Standby.)

On September 25,1990 at 03:31 hours, the plant reached Mode 2 (Startup).

On September 26,1990 at 03:22 hours, the plant was phased to the grid and in Mode 1,'(Power Operation) at 5%. At 13:28 hours, a load increase was commenced. By 19:45 hours, the plant was at -

30% power and holding for Chemistry. At 21:33 hours, a load increase was commenced.

On September 27,1990 at 20:12 hours, the plant reached at 10Po power.

The plant continued to operate at 100% power for the remainder of the month.

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AVERACE DAILY UNIT POWER LEVEL I

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n-4 DOCKET NO.

_50-213' Conn. Yankee UNIT Haddam Neck

- DATE 9/90

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COMPLETED BY K. C. Emons TELEPHONE (203) 267 3654 MONTH:

SEPTEMBER I

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.-DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL.

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(MWe-Net)

(MWe-Net)-

1 232 17 497

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' 31 18 501 l

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3-n 19 499 4-0 20 106 I

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13 468 29 571-14' 30 568

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INSTRUCTIONS

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'On this format, list the average' daily unit power level in MWe-Net for each' day

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..in the. reporting month. ' Complete the nearest whole megawatt.

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(9/77) 4 4 k.f, m

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MAINTENANCE-

'9/90 I.

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.EFFECT klII CORRECTIVE ACTICII SPECIAL PRECairt100iS -

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MALFUBICTICII SAFE TAKERI TO PREVEIIT-TAKEll-f0 PROVIDE' I

C00ettBEllT CAIISE RESULT OPERATIQM REPETIT10bl FOR REACTOR SAFETY I

Dum w. EEFAIR.

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Feedwater-Sten Plug-Loss of Caused Shutdown All valve stem / plug-assemblie
Regulating Failure Feedwater

' Plant Shutdown s

Valve in stock were inspected and Control xerayed for defects, Stem /plui, assemblies were welded in addition to being pinned, T-2-1B

~ Aux. Feed Pums Water in Found before none Replaced bearing and oil, None

~ Turbine Bearing Oil failure h

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t-i CONNECTICUT YANKEE REACT 6R COOLANT DATA MONTH: SEPTEMBER 1990 4

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" I<CACTOR COOLANT ANALYSIS MINIfiUM AVERAGE MAXIMUM

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L PH-e 25-DEGREES C 5.95E+00 :

6.18E+00

- 6.36E+00-

"! CONDUCTIVITY (UMHOS/CM) 1.33E+01

- 1.75E+01 2.19E+01 CHLORIDES.(PPM)

<5.00E-02 : <5 00E-02 : <5.00E-02 :
DISSOLVED OXYGEN (PPB)
-<5.00E+00 : <5.00E+00 : <5.00E+00 l BORON-(PPM)
- 1.03E+03 :

1.30E+03 :

1.59E+03 :

1.: LITHIUM (PPM) 1.27E+00 :

1.71E+00 2.09E+00 :

" TOTAL. GAMMA ACT.-(UC/ML) 2.75E-02 :- 3.69E-01 8.82E-01't i

'. IODINE-131 ACT.-(UC/ML) 5.10E-05 4.60E-03 :

2.82E-02 :

I-131/I-133 RATIO 0.00E-01 :

8.30E+00 8.93E+01L:

I CRUD (MG/ LITER)

<1.00E-02 :

1.04E-01 :

1.60E+00- '

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! TRITIUM-(UC/ML)'

4.08E-02.:

2.91E-01 :

5.16E-01 :

' HYDROGEN-(CC/KG) 2.45E+01 :

2.90E+01 3.60E+01 l'

AERATED LIOUID WASTE PROCESSED (GALLONS):

1.25E+05 WASTE LIOUID-PROCESSED THROUGH-BORON RECOVERY (GALLONS):

4.20E+04

- AVERAGE PRIMARY LEAK RATE (GALLONS PER MINUTE):

5.10E-01 PRIMARY TO SECONDARY: LEAK RATE (GALLONS PER MINUTE):

1.01E-02 f

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NRC OPERATING STATU$ REPORT

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Maddam Neck I

1. Docket: 50 213
2. Reporting Period: 09/90 Outage + on-line Mourst' 278.1 + 441.9 = 720.0
3. Utility

Contact:

J. Stanford (203) 267 3635 t

4. Licensed Thermal Power (MWt): 1825-
5. Nameplete Reting (Gross MWe):. 667 x 0.9 = 600.3
6. Design Electrical Rating (Not MWe): 582 i'
7. Maximum Dependable Capacity (Gross MWe): 591.8
8. Maalaum Dependebte Capacity (Net MWe): 565
9. If changes occur above since test report, reasons are: NONE

.10. Power levet to which restricted, if any (Net MWe): N/A

11. Reasons for restriction, !f any: N/A MONTH YEAR TD-DATE CUMULATIVE 12, Report period hours:

720.0 6,551.0.

199,415.0

'13. Mours reactor criticet:

589.5 1,055.5 159,304.7

14. Reactor reserve shutdown hours:

0.0

0.C 1,285.0
15. Nours generator on line 441.9 836.2 152,923.9
16. Unit reserve shutdown hours '

O.0 0.0 398.0 17, cross thernet energy generated (MWtH):.

631,715.0 711,527.0 263,578,845.0

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18. Groes electricot energy generated (MWeH):

201,159.0 212,258.0-86,305,304.0 *

19. Net electrical energy generated (MWeH):

185,327.2 166,803.8 81,989,783.8 *

20. Unit service factors 61.4 12.8 76.7
21. Unit-evellability factor.

61.4 12.8 76.9

22. Unit capacity factor using MDC net:

45.6-4.5 74.8

23. Unit cepecity factor using DER net 44.2 4.4 70.7
24. Unit forced outoge rate:

38.6 25.0 5.7

25. Forced outage hours:

2 78.1 279.4 9,255.0 i

26. Shutdowns scheduled over next 6 months (type,dete, duration): NONE-

'27. If currently shutdown, estimated startup date: N/A t

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  • Cumulative values frem the first criticality (07/24/67). (The remaining cumulative values are from the first date of commercist operatloc, 01/01/68).

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1811T SMUTD064tS AND POWER REDUCT10blS DOCKET tiA 50-213 1911T NAME Conn. Yankee 3

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. DATE 9/90 COMPLETED BY _K. W. Emmons i

REPORT HORITil SEPTEMBER TELEPMotlE : 203-267-3654 i-

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  1. 1 Feedwater regulating

'90-03 9/03/90

.F 137.97 A

2 90-01f SJ

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valve plug separated fro a; stem.-Stem plug-assemblie a

' modified with welded joi it where plug attached to st :m.

90-04 9/20/90 S

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n/a SD PP Reduced load to 50% power due to cavitation and lo,r discharge pressure on the IB condensate pump 90-05 9/20/90 F

140.12 C/A 2

90-02(

SD PP Premature shutdown of 1

Condensate pump as well a s i

degradation of. flexible ci rubber: coupling on conder sate' pump suction piping. Repl aced ;

rubber coupling with stai alest steel coupling ~

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3.

4 F Forced Ke.ason: -

~Hethod:

Exhibit C-Instructiona.

LS Scheduled A-Equipment Failure (Explaia)

H-Other(Explain 1-Manual

for Preparation of Das:a B-Maintenance or Test
2-Manual Scram C-Refueltag Entry Sheets for Licesses; '

3-Automatic Scram

-Evust Report (LER) Fila D-Regulatory Bestrictica 4-Other(Explain)~

(IInmareOl61).

.E-Operator Training & License Examination F-Administrative 15-C-Operational. Error.(Explaia)

Exhibit 1 Same Source: ~ _ g ;

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- Refueline Informatinn Reauest is '

  • Name of facility.

Haddam Neck-t 12.

' Scheduled date for next refueling shutdown.

October 5,1991 3.

Scheduled date for restart following refueling.

1 November 26,1991 4.

(a)

Will refueling or resumption of operatior thereafter require a technical specification change or other license amendment?

3 Yes (b)-

If answer is yes, what, in general, will these be?

Revise Section 5 of Technical Specifications to allow use of zircaloy clad fuel. Obtain an exemption fmm 10CFR50 Appendix K Sections I.D.3, I.D.4 and I.D.5.

(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) n/a

-(d)

If no such review has tahn place, when is it t.::heduled?,

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Scheduled date(s) for submitting proposed licensing action and supporting information.

~ The exemption request will be submitted to the NRC in October 1990. The request will be submitted in March 1991:

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.

Conversion to zircaloy cladding.

7.

The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pcol.

(a) 157 (b)

~709 8.

The prese nt licensed spent fuel pool storage capacity and the size of any increase in licensed storage.

j capacity. hat has been requested or is planned, in number of fuel assemblies.

I168 9..

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.

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i REVISION lR p

8, NRC OPERATING $TATUS REPORT Haddam Neck

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1. Docket: 50 213.
2. Reporting Period: 08/90 Outage + on-line Hours: 349.7 + 394.3 = 744.0
3. Utility contact: J. $tanford (203) 267 3635
4. Licensed Thermal Power (Wt): 1825-
5. Nameptete Rating (0ross We): 667 x 0.9 = 600.3
6. Desten Electrical Rating (Wet We): 582
7. Maxiaun Dependable Capacity (Gross We): 591.8
8. Maxlaun Dependable Capacity (Net We): 565
9. If changes occur above since test report, reasons are: NONE
10. Power levet to which restricted, if any (Net W e): N/A
11. Reasons for restriction, if any: N/A r

MON 1H YEAR TO DATE CUMULATIVE

12. Report period hours:

744.0 5,831.0 198,695.0

13. Hours reactor critical:

466.0 466.0 158,715.2

.14. Reactor reserve shutdown hours:

0.0 0.0 1,285.0

- 15. Hours generator on line 394.3 394.3 152,482.0

16. Unit reserve shutdown hours:

0.0 0.0 398.0

17. Gross thernet energy generated (WtH):

79,812.0 79,812.0 262,947,130.0 *

18. Gross electrical energy generated (WeH):

11,099.0 11,099.0 86,104,145.0

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19. Net electrical energy generated (WeH):

1,348.3' 18,523.4 81,804,456.6 *

20. Unit ser' ice factors 53.0 6.8 76.7
21. Unit availability factor 53.0' 6.8 76.9
22. Unit capacity factor using MDC net:

0.0 0.0 74.9 l

23' Unit capacity factor using DER net:

0.0 0.0 70.8

' 24. Unit forced outage rate:

0.3 0.3 5.6 A

l, 25.. forced outage hours:

1.3 1.3

'8,976.9 l?

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- 26. Shutdowns scheduled over next 6 months (type,date, duration): NONE i

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27 :lf currently shutdown, estientt'd startup date N/A l.

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  • Cuautative values from.the first criticality (07/24/67) (The remaining cunulative values are f rom the first date of comercial operation, 01/01 co).

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