ML20151F994

Monthly Operating Rept for Mar 1988

ML20151F994
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	03/31/1988
From:	Miller D, Wall K CONNECTICUT YANKEE ATOMIC POWER CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8804190130
Download: ML20151F994 (10)

Text

s CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECX PLANT HADDAM, CONNECTICUT

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l MONTHLY OPERATING REPORT N0. 88-03 FOR THE MONTH OF MARCH 1988

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PDR ADOCK 05000233 R DCD

5 April 11,1988 ODM 88 81 PLANT OPERATIONS .

De following is a summary of Plant Operations for March 1988:

The unit continued with its 14th Refueling and Maintenance Outage. On March 19 at 0055, the reactor achieved criticality; however at 0530 hours0.00613 days <br />0.147 hours <br />8.763227e-4 weeks <br />2.01665e-4 months <br />, the reactor tripped due to Nucler Instrumentation Channel 21 high stanup rate, ne reactor achieved criticality on March 20 at 1938 hours0.0224 days <br />0.538 hours <br />0.0032 weeks <br />7.37409e-4 months <br />. De reactor was manually tripoed on March 21 at 1025 hours0.0119 days <br />0.285 hours <br />0.00169 weeks <br />3.900125e-4 months <br /> per Reactor Engineering 3rocedurer. The reactor went entical again at 1206 hours0.014 days <br />0.335 hours <br />0.00199 weeks <br />4.58883e-4 months <br />. However a reactor trip occurrec on March 22 at 0623 hours0.00721 days <br />0.173 hours <br />0.00103 weeks <br />2.370515e-4 months <br /> due to Nuclear Instrumentation Channel 22 high startup rate.

The reactor achieved criticality on March 22 at 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> and, after completing Startu )

Physics testing, the plant phased on line on March 26 at 1454 hours0.0168 days <br />0.404 hours <br />0.0024 weeks <br />5.53247e-4 months <br />. At 1545 hours0.0179 days <br />0.429 hours <br />0.00255 weeks <br />5.878725e-4 months <br />, tie umt reached 5% for a Chemistry hold.

On March 27 at 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> a power reduction was initiated and at 0318 the plant was taken off line for a Turbine Overspeed Trip Test. De test was completed at 0348 and the plant phased back on line at 0412 hours0.00477 days <br />0.114 hours <br />6.812169e-4 weeks <br />1.56766e-4 months <br />. De unit reached 5% at 0425 hours0.00492 days <br />0.118 hours <br />7.027116e-4 weeks <br />1.617125e-4 months <br /> and remained there for a Chemistry Hold. At 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br />, a load increase to 15% was started. At 15% power, Internal Vibranon Monitor Testing was performed and the unit increased load to 30% and remained at that power level for a Chemistry Hold.

De unit commenced a load increase to 80% on March 30 at 0940 and reached 80% at 0542 hours0.00627 days <br />0.151 hours <br />8.96164e-4 weeks <br />2.06231e-4 months <br /> on Man:h 31.

De plant stayed at 80% power for the remainder of March.

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l AVERAGE DAILY UNIT POWER LEVEL 9

DOCKET No. 50-213 Conn. Yankee UNIT Haddam Neck DATE 4/15/88

. . Wall COMPLETED BY TELEPHONE (203)'267-2556 MONTH: March 1988 DAY- AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0 17 0 2 0 18 0 3 n 19 0 4 0 20 0 5 0 21 0 6 0 _

22 0 7 0 23 0 0

8 0 24 9 n 25 0 10 0 26 0 11 n 27 27 12 0 28 123 13 0 ?9 128 14 0 30 203 15 0 31 448 16 u 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.

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o CONNECTICUT YANKEE REACTOR COOLANT DATA MONTH! MARCH 1988 REACTOR COOLANT ANALYSIS MINIMUM A'/ERAGE MAXIMUM PH 9 25 DEGREES C  ! 4.51E+00 t 5.37E+00 ! 6.19E+00 t CONDUCTIVITY (UNHOS/CM)  ! 5.40E+00 1 1.22E+01 ! 2.10E+01 !

CHLORIDES (PPM)  ! <5.00E-02 8 <5.00E-02 i <5.00E-02 !

DISSOLVED OXYGEN (PPB)  ! <5.00E+00 1 3.56E+02 ! 4.00E+03 !

BORON (PPM) i 1.46E+03 1 2.21E+03 1 2.69E+03 !

LITHIUM (PPM)  ! 0 00E-01 ! 4.77E-01 ! 1.70E+00 t TOTAL GAMMA ACT. (UC/ML)  ! 2.08E-04

• 2.48E-02 2 2.45E-01 !

IODINE-131 ACT. (UC/ML) 1 0.00E-01 ! 9.70E-05 3 1.84E-03 !

I-131/I-133 RATIO  ! 0.00E-01 ! 1.35E-01 ! 9.40E-01 !

CRUD (MG/ LITER)  ! 6 00E-02 1 9.44E-02 ! 1.00E+00 t TRITIUM (UC/ML)  ! 2.03E-03 ! 1.84E-02 8 3.43E-02 I HYDROGEN (CC/KG)  ! 2.56E+01 ! 2.61E+01 ! 2 67E+01 1 AERATED LIQUID WASTE PROCESSED (GALLONS)! 7.96E+04 WASTE LIQUID PROCESSED THROUGH BORON RECOVERY (GALLONS)! 2.66E+05 AVERAGE PRIMARY LEAK RATE (GALLONS PER MINUTE)! 3.16E+00 PRIMARY TO SECONDARY LEAK RATE (GALLONS PER MINUTE)! 0.00E+00 l

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. NRC-Oporcting Statuo Roport

.E Haddam Neck

1. Cocket: 50 213

2. Reporting Period 03/88 Outage + On-line Hours: 615.0 + 129.0 = 744.0

3. Uttlity Centact: J. Stanford (203) 267-2556 est. 452

4. Licensed Thereal Peeer (Mti 1925

5. Naseplate Rating (6ross Mel 667 0.9 = 600.3

6. Design Electrical Rating (Net Me): 592

7. Ma,seva Cependable Capacity (6ross Me): 595.9

8. Masieve Cependable Capacity (Net Me): .569 9 _!f changes occur above since last report, reasons are N0h!

10. Peaer level to ehich restricted. if any (Net Me): N!A

!!. Keatens for restraction, if anyt N/A

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12. Peport period hours: 744.U 4,194.V 177,504.0

13. Hours reacter critical 257.7 257.7 146,446.7

14. Reactor reserve statdcen hours: 0.0 0.0 1,285.0

15. Hours generator on line: 129.0 129.0 140,316.9 4

16. Unit reserve shutdcen hours: 0.0 0.0 398.0

17. Broes thereal energy generated (MtH) 22,124.0 $2,124.0 242,052,128.0 8

19. Gross electrical energy generated (MeH): 25,330.1 25,330.1 79,506,137.1 8

19. Net electrical energy generated (M eH): 14,371.5 9,151.6 75,567,846.2 8

20. Unit service factor: 17.3 5.9 79.0

21. Unit availability factor: 17.3 5.9 79.3

22. Unit capacity factor using MDC net: 3.4 0.7 77.9

23. Unit capacity factor using DER net: 3.3 0.7 73.2

24. Unit forced outage rate: 0.0 0.0 6.0

25. Forced outage hours: 0.0 0.0 8,975.6

26. Shutdoens scheduled over nest 6 eenths (type,date, duratten): Replate RCP 13 Seal 04/19189, 5.5 days

27. If currently stutdcen, estteated startup date N/A 8 Cueulattie values free the first criticality (07/24/67). (The reestning cueulattie value, are frce the first date et ccesercial operation, 01/01/68).

UNIT SIIUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-213 UNIT NAME Conn, Yankee.

DATE 4/15/88 COMPLETED BY K. C. Wall REPORT MONT11 March 1988 TELEP110NE (203) 267-2556 ~__

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No. Date b7 e4

.o 3 g LER 4 $e Cause & Corrective "e U$ $ RPT. $'8 h 8:O 8 j"k"g "j

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O'U Action to Prevent Recurrence 5" 5  ?"OM m0 0 87-03 7/18/87 S 614.9 C 1 N/A RC Fuel XX Continuation of Refueling Outage 88-01 3/27/83 S 0.9 B N/A N/A liA ZZZZZZ Turbine Overspeed Trip Test 1 2 3 4 F Forced Reason: Method: Exhibit C-Instructions S Scheduled A-Equipment Failure (Explain) Il-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 D-Regulatory Restriction 4-Other(Explain) (NUREG-0161)

E-Operator Training 6 License Examination F-Administrative 5 G-Operational Error (Explain) Exhibit 1 Same Source

REFUELING INFORMATION REQUEST

1. Name of facility Connecticut Yankee Atomic Power Company

2. Scheduled date for next refueling shutdown.

. August 5, 1989

3. Scheduled date for restart following refueling.

September 30, 1989

4. (a) Will refueling or resumption of operation thereafter require a technical speci-fication change or other license amendment?

NO (b) If answer is yes, what, in general, will these be?

(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)?

NO (d) If no such review has taken place, when is it scheduled?

July, 1989

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

N/A

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.

NO

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

(a) 157 (b) 653

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 L , c-

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c YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT C CONNECTICUT

-r RRs1 e Box 127E e EAST HAMPToN, CT 06424-9341 April 15,1988 RE: Technical Specification 6.9.1d Docket No. 50-213 U. S. Nuclear Regulatory Commi,sion Document Control Desk Washington, D. C. ?0555

Dear Sir:

In accordance with reporting requirements of Technical Specification 6.9.1d, the Connecticut Yankee Haddam Neck Plant Monthly Operating Report 88-03, covering operations for the period March 1, 1988 to March 31, 1988, is hereby forwarded.

Very truly yours, h ,

Donald E. Miller, Jr.

Station Superintendent DBM/mdw Enclosures cc: (1) Regional Administrator, Region 1 U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 (2) J. T. Shediosky Sr. Resident Inspector Connecticut Yankee I

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1968 Twenty Years of Service

• 80 Billion Kilowatt Hours Generated 1988 x-as or l