ML20059J130

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Monthly Operating Rept for Aug 1990 for Haddam Neck Plant.W/
ML20059J130
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 08/31/1990
From: Emmons K, Stetz J
CONNECTICUT YANKEE ATOMIC POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9009190184
Download: ML20059J130 (10)


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September 15,1990 Re: Technical Specification 6.9.ld 1

- Docket No. 50-213 o

x U.' S. Nuclear Regulatory Commission

. Document Control Desk Washingtm, D. C. 20555 ~

Dear bir:

In accordance with reportmg requirements of Technical Specification 6.9.ld, the Connecticut Yankee F.addam Neck Plant Monthly Operating Report 90-08, covering operations for the period '

. August 1,1990 to August 31,1990 is hereby forwarded.

Very truly yours,

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John P. Stetz Station Director 4

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Regional Administrator, Region 1 U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 (2)

. John T. Shediosky Sr. Resident Inspector Connecticut Yankee s

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Monthly Opemting Repon No. 90-08 i

For The Month of August 1990 l

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Plant Onerations Summarv - August.1990 go mge, The following is a summary of Plant Operations for August,1990.

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The 15th refueling and maintenance outage continued for the month of August with the unit in Hot Standby, Mode 3.

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F On Au;;ust 2,1990 at 1221 hours0.0141 days <br />0.339 hours <br />0.00202 weeks <br />4.645905e-4 months <br />, a~ cool down and depressurization was initiated to facilitate repair of a va ve on the Pressurizer. By 1932 hours0.0224 days <br />0.537 hours <br />0.00319 weeks <br />7.35126e-4 months <br />, the plant had been cooled down to llot Shutdown,-

Mode 4.

On August 3,1990 at 0623 hours0.00721 days <br />0.173 hours <br />0.00103 weeks <br />2.370515e-4 months <br />, the plant was in Cold Shutdown, Mode 5.

' On August 7,1990 at 0230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br />, the plant heat up commenced. Repairs were complete and the

. valve was ready for testing.

On August 8,1990 at 0230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br />, plant heat up commenced. At 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br />, the plant was in Hot Shutdown, Mode 4. At 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br />, the pressurizer vent pot, channel 2, sample line valve was leaking. At 2157 hours0.025 days <br />0.599 hours <br />0.00357 weeks <br />8.207385e-4 months <br />, the plant commenced a cool down and depressurization to initiate repairs.

On August 9,1990 at 0321 hours0.00372 days <br />0.0892 hours <br />5.30754e-4 weeks <br />1.221405e-4 months <br />, the plant reached Cold Shutdown, Mode 5.

On August 10,1990 at 0053 hours6.134259e-4 days <br />0.0147 hours <br />8.763227e-5 weeks <br />2.01665e-5 months <br />, repairs were complete and the valve was ready for testing. At 0320 hours0.0037 days <br />0.0889 hours <br />5.291005e-4 weeks <br />1.2176e-4 months <br />, the plant heat up commenced. At 0646 hours0.00748 days <br />0.179 hours <br />0.00107 weeks <br />2.45803e-4 months <br /> the plant retumed to Hot Shutdown, Mode 4'.

On August 11,1990 at 0335 hours0.00388 days <br />0.0931 hours <br />5.539021e-4 weeks <br />1.274675e-4 months <br />, the plant was at Hot Standby, Mode 3.

On August 12,1990 at 0853 hours0.00987 days <br />0.237 hours <br />0.00141 weeks <br />3.245665e-4 months <br />, the plant reached Startup, Mode 2. At 2213 hours0.0256 days <br />0.615 hours <br />0.00366 weeks <br />8.420465e-4 months <br />, the Reactor i

' was manually tripped, as per the Low Power Physics Test procedure. By 2308 hours0.0267 days <br />0.641 hours <br />0.00382 weeks <br />8.78194e-4 months <br />, the Plant -

l commenced heatmg back up to Startup, Mode 2.

K On August 13,1990 at 0020 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />, the Reactor was manually tripped due to mechanical failure of a 120 volt DC rod control relay. By 0316 hours0.00366 days <br />0.0878 hours <br />5.224868e-4 weeks <br />1.20238e-4 months <br /> the plant commenced heating up. At 0433 hours0.00501 days <br />0.12 hours <br />7.159392e-4 weeks <br />1.647565e-4 months <br /> the plant was at Startup, Mode 2.

9 On August 15,1990 at 0723 hours0.00837 days <br />0.201 hours <br />0.0012 weeks <br />2.751015e-4 months <br />, the plant phased to the grid and attained Power Operation, Mode-y, I at 5% power. At 1740 hours0.0201 days <br />0.483 hours <br />0.00288 weeks <br />6.6207e-4 months <br />, the plant was removed from the grid to investigate a voltage L

regulator ground. At 1858 hours0.0215 days <br />0.516 hours <br />0.00307 weeks <br />7.06969e-4 months <br />, the problem was corrected and the plant phased to the grid. At i

2045 hours0.0237 days <br />0.568 hours <br />0.00338 weeks <br />7.781225e-4 months <br /> the plant resumed Power Operations, Mode 1 at 8% power.

On August 16,1990 at 1350 hours0.0156 days <br />0.375 hours <br />0.00223 weeks <br />5.13675e-4 months <br />, the plant was removed from the grid, for the Turbine Overspeed '

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Trip. At 1415 hours0.0164 days <br />0.393 hours <br />0.00234 weeks <br />5.384075e-4 months <br />, the test was successfully completed. ' At 1850 hours0.0214 days <br />0.514 hours <br />0.00306 weeks <br />7.03925e-4 months <br /> the plant phased on to the grid..By 1920 hours0.0222 days <br />0.533 hours <br />0.00317 weeks <br />7.3056e-4 months <br />, the plant resumed Power Operations, Mode 1 at 10% power and on Chemistry j

hold, i

On August 30,1990 at'1630 hours0.0189 days <br />0.453 hours <br />0.0027 weeks <br />6.20215e-4 months <br />, Chemistry was within specifications required for Power l

Ascension. By 1940 hours0.0225 days <br />0.539 hours <br />0.00321 weeks <br />7.3817e-4 months <br />, the plant reached 30% Power and holding for Chemistry and j

perfonnance of the flux map.

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DOCKET.NO.-

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COMPLETED BY K. W. Emmons TELEPHONE (203) 267 3634 =

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DAY' AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL'

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~ INSTRUCTIONS 4

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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EFFECT ON CORRECTIVE ACTION.

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CGIrGNENT CAUSE RESULT.

OPERATION.

REFETITION~

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MONTHi' AUGUST 1990

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MINIMUM AVERAGE MAXIMUM.

1 REACTOR'. COOLANT. ANALYSIS

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5.09E+00.!

5.70E+00;t.6.17E+00 tL n

"i CONDUCTIVITY:(UMHOS/CM) 5 59E+00 !

1.20E+01 1-2 01E+01-1 1

< CHLORIDES (PPM)-

1'<5 00E-02't-<5.00E-02 t <5.00E-02 1

' DISSOLVED OXYGEN (PPB)-

11 <5 00E+0011 <5 00E+00

<5.00E+00 !

(BORONE(PPM) 1.28E+03 1 1.74E+03.1 2.34E+03 !

ELITHIUM (PPM);

1 3.87E-01-!

9.99E-01 1

~1.86E+00 _ t 9TOTALD GAMMA ACT. ~ (UC/ML).

t 1 97E-04 t'

4.47E-02 1..

37E-01Et

? IODINE-131'ACT.- (UC/ML):

0.00E-01

,2.93E-04 l'

'1 34E-03't.

,jI-131/I-133 RATIO.

t 0.00E-01 t '- 5.98E-01' !

1.63E+00 !'

' CRUD-(MG/ LITER)-

!t'<1.00E-02 1 3.27E-01 1 3 40E+00 t 4

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(UC/ML) 4.96E-03 t-1.69E-02 !

3 38E-02 !

/A, TRITIUM HYDROGENi(CC/KG) 1.91E+01.! '2.45E+01 !

3.29E+01.'t

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AERATED: LIQUID' WASTE PROCESSED (GALLONS)!

-1.76Ef05 ifc; V..

i t MWASTEoLIQUID' PROCESSED THROUGH' BORON RECOVERY (GALLONS)1 1.23E+05: i 4 AVERAGE' PRIMARY LEAK-RATE (GALLONS PER MINUTE)t. 2.08E-04 l lE 'PRIMARYSTO. SECONDARY-LEAK RATE (GALLONS PER MINUTE) -2.10E-03 I Ye i

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~. ~ .g. =., s WRC OPERATING STATU$ REPORT Haddam Neck.

1. Docket: 50 213
2. Reporting Period 08/90.

Outage + on-line Hours: 349.7 + 394.3 744,0-

3. Utility contact: J. Stenford (203) 267-3635
4. Licensed Thermal Power (MWt): 1825

- 5. Nameplate Rating (Gross MWe): 667 x 0.9 600.3

6. Design tiectrical Rating (Net MWe): 582
7. Maximum Dependable capacity (Gross MWe) 591.8
8. Maximun Dependable Capacity (Net MWe): - 565
9. If changes occur above since test report, reasons are: NONE

- 10. .e tevet to which restricted,.lf any (Net MWe)s N/A A 115 Reestns for restriction, if any: N/A MONTH YEAR TO-DA)E 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 thermal energy generated (MWtN): 79,812.0 79,812.0 262,947,130.0 *-

18. Gross electrical energy generated (MWeN):

11,099.0 11,099.0 86,104,145.0

  • 19' Net electrical energy generated (MWeH):

1,348.3 10,523.4 81,804,456.6 *

20. Unit service factor 53.0 6.8 76.7 L21. Unit availability factor:

53.0 6.8 76.9 22'. Unit capacity factor using MDC net 0.0 0.0 74.9

23. Unit capacity factor using DER net:

0.0 0.0 70.8

24. Unit forced outage rate:

0.0 0.0 5.6

25. Forced outage hours:

0.0 0.0 8,975.6

26. Shutdowns scheduled over next 6 months (type,date, duration): NONE
27. If currently shutdown, estimated startup date: N/A
  • Cumulative values from the first criticality (07/24/67). (The remolning cumulative values are f rom the first date of comnerclat operation, 01/01/68).

_,_.~.__.s . _~ $12ilT SHUTD0laiS AND POWER REDUCTIONS DOCKET NO. 50-213 UNIT NAME Conn. Yankee DATE August 1Wu COMPLETED BY K. M. Emmons REPORT MONTg August 1990 TELEPHONE 203-267-3654 w e an o ae es y No. Date .a $ g LER .e o Cause & Corrective .og .n 'g RPT. E15 Action to [,*8 g uo o h Oh l J,E 3 ~ $E (" Prevent Recurrence "A" No. m o .89-03 8/1/90 s 343.4 C -1 N/A RC Fuel XX Continuation of Core XV-XVI Refueling. 90-01 - 8/15/90. F 1.3 A N/A .N/A TL EXC i? hen testing voltage regulator, power supply module caused ground. 90-02' 8/16/90 -S 5.0 B N/A N/A HA ZZZZZZ Turbine Overspeed Trip Test = ~ ' I .1' 2

3 4

F Forced. Re.ason: Method:- Exhibit G-Instructions -S Scheduled ^. A-Equipment Failure;(Explain) H-Other(Explain 1-Manual for. Preparation of Data.

B-Maintenance or Test

'2-Manual Scram Entry Sheets for Licensee C-Refueling' 3-Automatic Scram Event Report (LER)' File-i

D-Regulatory Restriction 4-Other(Explain).

(NUREG-0161) E-Operator Training & License Examination-F-Administrative. -5 C-Operational Error (Explala) Exhibit 1'Same Source: y> m v -_. %,C ) ~ e

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t k, y*. .,,REfueline Information Reauest : F ' 3.,, $ ~ .) yg. C 4 , Name of facility 4 m. Haddam Neck Iy l 22 [ Scheduled date for next refueling shutdown. September 13,1991-l 2 $. Schululed date for restart following refueling. { November 9,1991 y 4 4l (a) Will refueling or resumption of operation thereafter require a technical 'l xN_ ' specification change or other lleense amendment? i es (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 from ICCFR50 Appendix K Sections I.D 3, I.D.4 and I.D.5. l -(c) If answrr is no, has the reload fuel design and core configura ion been reviewed by your Plant Safety Review Committee to determine whether any unreviewed safety, J questions are associated with the com reload? (Ref,10 CFR section 50.59) i-n/a ( n L(d). If no such review has taken place, when is it scheduled? n/a g ' 5.i Scheduled date(s) for submitting proposed licensing action and supporting information. m 'I'he exemption request will be submitted to the NRC in JOctober 1990. The TSCR will be L ' 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 } l design, new operating procedun:s. l', LConversion to zirealoy cladding. j, 7 '. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool. 1, p (a) ~157 (b) 701 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. 1996 y l' 1,}}