ML19341A053

Monthly Operating Rept for Dec 1980

ML19341A053
Person / Time
Site:	Farley
Issue date:	01/01/1981
From:	Hairston W ALABAMA POWER CO.
To:
Shared Package
ML19341A052	List: ML19341A051 ML19341A053
References
NUDOCS 8101210521
Download: ML19341A053 (7)

Text

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l ATTACHMENT,1 JOSEPH M. FARLEY NUCLEAR PLANT

' UNIT 1 NARRATIVE SLMfARY OF OPERATIONS DECEMBER, 1980 In December, 1980, the unit remained shutdown for Cycle II-III re-fueling.

The following safety-related maintenance was performed in December *

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1. Repacked 1B service water pump.

2. Continued modification of Service Water Lube & Cooling piping.

3. Performed miscellaneous maintenance on Diesel Generators.

4. Replaced fiber optic lamp on a control room chlorine detector.

5. Continued implementation of main control board modifications re-commended as a result of human factors evaluation'.

6. Continued implementation of NUREG-0578 requirements.

a. Reactor vessel head venting. system,

b. High range containrent radiation monitor.

c. On-site Technical Support Center.

d. Wide range containment pressure monitor,

e. Backup air supply for Turbine Driven AFW pump steam admission valve.

f. Plant shielding review.

g. Power Operated Relief Valves backup air supply.

h. High range effluent monitor.

1. Containment level indicator.

J. Core subcooling monitor (modification).

k. Overvoltage on Auxiliary Feedwater Flow control solenoid valves.

7. Replaced Chem-Nuclear mobile solidification system with Hittman mobile solidification system (see attached report submitted for information only).

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l ATTACHMINT 2 MAJOR CHANGES TO RADI0 ACTIVE WASTE TREATMENT SYSTEMS Licensee initiated major changes to the radioactive waste systems (Liquid, gaseous and solid):

1. Shall be reported to the Commission in the Monthly Operating Report for the period in which the evaluation was reviewed by the Plant Operations Review Committee. The discussion of each change shall contain:

a. A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59; Discussion:

Offsite Gaseous Releases - Ne change.

Offsite Liquid Releases - No change.

Cffect of Shipped Volume - No change.

Operator Radiation Exposure - No change.

Radiation Exposure to Public from Shipments - No change.

Shipping Accident - Probability reduced due to smaller liner size.

Spent Liner Handling Accident - Probability reduced.

b. Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information; Discussion: The Hittman Cement Solidification System meets South Carolina's January 1, 1981 free standing water criteria.

The Chem-Nuclear Urea-formaldehyde So,lidification System which was replaced did not meet the January 1, 1981 criteria.

c. A detailed description of the equipment, components and processes involved and the interfaces with other plant systems; Discussion: The Hittman Cement Solidification System interfaces with the FNP bulk waste loading facility exactly as the Chem-Nuclear Urea-formaldehyde Solidification Unit did. The system consists of waste disposal liners with agitation blades, a fill head with motor driven agitator, a cement hopper, interconnecting hoses and valves and a control panel. ,

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d. An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid weste that differ from those previously predicted in the license application and amendments thereto; Discussion: There is no change from the Chem-Nuclear Urea-formaldehyde System which was replaced.

e. An evaluation of the change which shows the expected maximum exposures to individuals in the unrestricted area and to the general population that differ from those previously estimated in the license application and ,

amendments thereto; Discussion: There is no change from the Chem-Nuclear Urea-formaldehyde System which was replaced.

f. A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made; Dis' maion: There is no change from the Chem-Nuclear Urea-formaldehyde System which was replaced.

g. An estimate of the exposure to plant operating personnel as a result of the change; and Discussion: To date FNP has filled and solidified six 149 cubic foot Hittmaa Liners, about 50% from evaporator concentrates and 50% from chemical /decon drainage. Total exposure has averaged less than 15 mrem per liner with no liner exceeding 50 mrem. Total shipping exposure is expected to be less than 10 mrem. These figures are approximately equal to the exposures from the Chem-Nuclear Urea Formaldehyde Solidification System.

h. Documentation of the fact that the change was reviewed and found acceptable by the PORC.

Discussion: Safety Evaluation Checklist for PCN 80-893 approved by the PORC 12/22/80.

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STEAM GFNERATOR TUBE INSERVICE INSPECTION Date of Inspection: 12/20/80 - 12/23/80

References:

Technical Specification 4.4.5.5.b Technical Specification 4.4.5.5.b requires that the complete results of the Steam Generator tube inservice inspection be included in the Annual Operating Report for the period in which this inspection is completed. This report shall include:

1. Number and extent of tubes inspected.

Response

Type and Extent Number of Tubes Inspected of Inspection S/G B Hot / Cold Multi-Frequency through U-bend 507/0 Channel 1 - 400 KHZ (Dirf.)

Channel 2 - 100 KHZ (Diff.)

Channel 3 - 10 KHZ (Diff.)

Channel 4 - 100 KHZ (ABS.)

2. Location and percent of wall-thickness penetration for each indication of an imperfection. ,

Response

Percent Wall-Thickness S/G B Penetration Indication of Imperfection 90-100% 0/0 80-89% 0/0 70-79% 0/0 60-69% 0/0 50-59% 0/0 40-49% 0/0 30-39% 0/0 21-29% 0/0

, Subtotal 0/0

< 20% 0/0 Total 0/0

3. Identification of tubes plugged.

Response

None in S/G B. However, a leak test was performed on S/G C and one (1) tube was found to leak. This tube (location - row 1, column

27) was plugged.

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ATTACHMENT 3 OPERATING DATA REPORT DOCKET NO. 50-348 DATE 1/1/81 COMPLETED BY W. G. Hairston, I:

TELEPHONE (205)899-5156 OPERATING STATUS J seph M. Farley - Unit 1 Notes

1. Unit Name: 1) Cumulative data

2. Reporting Period: December 1980 since 12/1/77, date of

3. Licensed Thermal Power (MWt):

2652 commercial operation.

4. Nameplate Rating (Gross MWe):

860

5. Design Electrical Rating (Net MWe)

6. Maximum Dependable Capacity (Gross MWe): 844.6

7. Maximum Dependable Capacity (Net MWe): 803.6

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:

NA

' NA

9. Power Level To Which Restricted. If Anv (Net MWe):

10. Reasons For Restrictions,if Any: NA

. i s This' Month Yr..to.Date Cumulative

11. Hours in Reporting Period 744 8,784 27,048 0 6.246.8 17,182.3

. 12. Number Of Hours Reactor Was Critical

13. Reactor Reserve Shutdown Hours 0 1,041.5 2,446.8

14. Hours Generator On.Line 0 6,112.9 16,703.4

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 0 ,,,,,

15,391,877.4 41,989,891.8

17. Gross Electrical Energy Generated (MWH) d 4,895,370 13,419,408

18. Net Electrical Energy Generated (MWH) -4,402 4.603.742 12.607.750

19. Unit Service Factor 00.0 69.6 61.7

20. Unit Availability Factor 00.0 69.6 61.7

21. Unit Capacity Factor (Using MDC Net) -00.7 65.2 58.0

22. Unit Capacity Factor (Using DER Net) -00.7 63.2 56.2

23. Unit Forced Outage Race 00.0 06.1 06.9

24. Shutdowns Scheduled Over Next 6 Months (Type. Date, and. Duration of Each 3:

NA

25. If Shut Down At End Of Report Period. Estimated Date of Startup: Februarv. 1981

26. Units in Test Status tPrior to Commercial Operation): Forecast Achieved INITIAL CRITICALITY 8/6/77 8/4/77 INITIAL ELECTRICITY 8/20/77 8/18/77 COMMERCIAL OPERATION 12/1/77 12/1/77 19/77) t

AVERAGE DAILY UNIT FOWER LEVEL .

'. ATTACHMENT 4 ,

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.,, DOCXIT NO. 50-348

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.. DATE 1/1/81 l

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COMPLETED BY If.G. Hairston, III l M MONE (205)899-5156 Deceraber , 1980 .

MO DAY AVERAGE DAILY POWER LEVEL ' DAY AVERAGE DAILY POWER LEVEL '-

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0 0' 39 4 0 -

3 0 0 0 5 21 6 " 22 0 .-

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INSTRUCTIONS On this format. list the sversge dsily unit power Invet in MWe-Net for each day in the reporung month. Compute to  ;

the nearest whole megswatt. '

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