ML17331B282
| ML17331B282 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 12/31/1993 |
| From: | Lauren Gibson, Moran W, Will Smith INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | |
| Shared Package | |
| ML17331B281 | List: |
| References | |
| NUDOCS 9403040366 | |
| Download: ML17331B282 (21) | |
Text
DONALD C.
COOK NUCLEAR PLANT 1993 ANNUAL OPERATXNG REPORT February 28, 1994 COMPILED BY: C~
W. R. Moran Senior E
REVIEWED BY:
L. S.
Gi.bson Assi.stant Plant Manager APPROVED BYt W. G. Smith, Jr.
Chief Ope'rations Manager 94050403bb 940224 PDR ADOCK 05 PDR
ATTACHMENT TO AEP!NRC:1147D DONALD C.
COOK NUCLEAR PLANT 1993 ANNUAL OPERATING REPORT
TABLE OF CONTENTS SECTION SECTION TITLE PAGE NUMBER 1.0 Introduction 1.1 1.2 Plant Description Report Preparation 2.0 3.0 Personnel Radiation Exposure Summary Steam Generator Zn-Service Inspection 3.1 3 '
Unit 1 Inspection Summary Unit 2 Inspection Summary 4.0 5.0 4.1 Changes to Procedures Chemistry Procedures 4.1.1 Use of Ethanolamine Tests or Experiments Not Described in the FSAR 5.1 Tests 5.1.1 Valve Leak Rate Testing 5.1.2 Steam Dump Valve Test 6.0 Challenges to Pressurizer Power Operated Relief Valves and Safety Valves 7.0 8.0 9.0 9.1 Reactor Coolant Specific Activity Irradiated Fuel Examinations Changes to Facility Design Changes (RFCs) 10 10 9.1.1
- 9. 1.2 9.1.3 Radioactive waste System Modification New and Spent Fuel Pool Modification Unit 1 Steam Generator Chemical Addition System Modification 10 10 11
TABLE OF CONTENTS (Cont'd.)
SECTION SECTION TITLE PAGE NUMBER 9.2 Plant Modifications (PMs) 11 9.2.1 9.2.2 9.2 '
Makeup Water system Modifications Spent Resin Storage Tank Level Indication Circulating Water Discharge Points 11 11 12 9.3 9.4 Minor Modifications (MMs) 9.3.1 Sample Line Relocation Temporary Modifications (TMs) 12 12 12
1.0 INTRODUCTION
1.1 PLANT DESCRIPTION The Donald C.
Cook Nuclear Plant is owned by Zndiana Michigan Power Company and is located five miles north of Bridgman, Michigan.
The plant consists of two nuclear power
- units, each employing a
Westinghouse pressurized water reactor nuclear steam supply system.
Each reactor unit employs an ice condenser reactor containment system.
The American Electric Power Service Corporation was the architect-engineer and constructor.
Unit 1 and 2 reactor design power output (and licensed rating) are 3250 MWt and 3411 MWt, respectively.
Unit 1 approximate gross and net electrical outputs are 1056 MWe and 1020 MWe, respectively.
Unit 2 approximate gross and net electrical outputs are 1100 MWe and 1060 MWe, respectively.
The main condenser cooling method is open cycle using Lake Michigan water as the cooling source for each unit.
1.2 REPORT PREPARATION This report was compiled by W. R. Moran with the following individuals contributing information as follows:
Personnel Exposure Summary J.
R. Kambach Steam Generator ZSZ Summary C. A. Freer Changes to Procedures R. G. Vasey Tests or Experiments Not Described in the FSAR R.
G. Vasey Challenges to Pressurizer PORVs and Safety Valves R. S. Ptacek Reactor Coolant Specific Activity Results of Irradiated Fuel Inspections S.
W. McLea T. A. Georgantis Changes to Facility RFCs, MMs, PMs R.
G. Vasey Changes to Facility Temporary Modifications to Unit 1 6
2 R. G. Vasey
2.0 PERSONNEL RADIATION EXPOSURE
SUMMARY
Table 1 provides a summary of the number of station, utility, and contractor (and others) personnel receiving exposures greater than 100 millirem in 1993.
The total record dose for all personnel was 43.526 rem as measured by thermoluminescent dosimetry (TLD) and reported in accordance with Regulatory Guide 1.16.
TABLE ANNUAL OPERATING REPORT -
1.16 FOR 1993
¹ PERSONNEL >100 mR TOTAL MAN-REM STAT. UTIL. CONT.
STATION UTILITY CONTRACT veillance Reactor Operations 6 Sur Maintenance Personnel Operations Personnel Health Physics Personnel Supervisory Personnel Engineering Personnel Routine Maintenance Maintenance Personnel Operations Personnel Health Physics Personnel Supervisory Personnel Engineering Personnel 0000 0007 0020 0001 0000 0011 0000 0002 0000 0002 0000 0000 0000 0000 0000 0000 0000 0000 0000 0000 0002 0000 0004 0000 0000 0007 0001 0000 0000 0000 000.000 000.696 002.618 000.107 000.000 001.687 000.000 000.211 000.000 000.280 000.000 000.000 000.000 000.000 000.000 000.000 000.000 000.000 000.000 000.000 000.407 000.000 000.411 000.000 000.000 000.977 000.153 000.000 000.000 000.000 In-Service Inspection Maintenance Personnel Operations Personnel Health Physics Personnel Supervisory Personnel Engineering Personnel Special Maintenance Maintenance Personnel Operations Personnel Health Physics Personnel Supervisory Personnel Engineering Personnel Waste Processing Maintenance Personnel Operations Personnel Health Physics Personnel Supervisory Personnel Engineering Personnel Refueling Maintenance Personnel Operations Personnel Health Physics Personnel Supervisory Personnel Engineering Personnel TOTALS Maintenance Personnel Operations Personnel Health Physics Personnel Supervisory Personnel Engineering Personnel GRAND TOTALS 0000 0000 0000 0000 0000 0001 0000 0000 0000 0000 0000 0000 0002 0001 0000 0000 0000 0000 0000 0000 0012 0007 0024 0002 0002 0047 0000 0000 0000 0000 0000 0000 0000 0000 0000 0000 0000 0000 0000 0000 0000 0000 0000 0000 0000 0000 0000 0000 0000 0000 0000 0000 0000 0000 0000 0000 0000 0042 0004 0003 0000 0000 0002 0002 0007 0000 0000 0000 0000 0000 0000 0000 0053 0007 0014 0000 0000 0074 000.000 000.000 000.000 000.000 000.000 000.3.28 000.000 000.000 000.000 000.000 000.000 000.000 000.320 000.089 000.000 000.000 000.000 000.000 000.000 000.000 001.815 000.696 003.149 000.196 000.280 006.136 000.000 000.000 000.000 000.000 000.000 000.000 000.000 000.000 000.000 000.000 000.000 000.000 000.000 000.000 000.000 000.000 000.000 000.000 000.000 000.000 000.000 000.000 000.000 000.000 000.000 000.000 000.000 000.000 000.000 000.000 000.000 006.537 000.586 000.351 000.000 000.000 000.692 000.678 000.877 000.000 000.000 000.000 000.000 000.000 000.000 000.000 008.613 001.417 001.639 000.000 000.000 011.669 3.0 STEAM GENERATOR IN-SERVICE INSPECTION 3.1 UNIT 1 INSPECTIONS During 1993, there were no steam generator in-service inspections performed for Unit 1.
3.2 UNIT 2 INSPECTIONS During 1993, there were no steam generator in-service inspections performed for Unit 2.
4.0 CHANGES TO PROCEDURES This section contains a
brief description of the procedure changes implemented under the provisions of 10CFR50.59 and the associated safety evaluations.
4.1 CHEMISTRY PROCEDURES 4.1.1 Use of Ethanolamine Description of Change:
Plant procedures 12 THP 6020 LAB.041 and 1
THP 6020 LAB.061 were revised when a change was made to the Unit 1 secondary side chemistry.
The change in the chemistry was to use ethanolamine
'(ETA) for better pH and corrosion control.
Safety Evaluation Summary:
The use of ETA was reviewed, and it was determined that it did not constitute an unreviewed safety question.
This conclusion is based on the fact that the use of ETA is not expected to adversely impact the steam generator.
ETA is currently used in four U.S. nuclear plants, and the data from these plants indicate improved pH
- control, reduced flow-accelerated corrosion, and no adverse effects on plant materials or secondary side chemistry.
5 ~ 0 TESTS OR EXPERIMENTS NOT DESCRIBED IN THE FSAR This section describes procedures classified as "Test and Experiment",
implemented under the provisions of 10CFR50.59, including the associated safety evaluation.
5.5 TESTS 5.1.1 Valve Leak Rate Testin Description of Tests Non-essential water isolation valve 1-WCR-955, which serves as a containment service isolation valve, was tested with the pressure in the reverse direction from that which would occur under accident conditions.
This test was conducted using plant procedure 1 EHP SP.040.
Safety Evaluation Summary:
This test was reviewed, and it was determined that it did not constitute an unreviewed safety question.
This conclusion was based on the fact that 10CFR50, Appendix J allows valves to be tested in the reverse direction providing that it is demonstrated that the results are ecpivalent to applying the pressure in the forward direction.
An evaluation was performed, and it was determined that testing in the reverse direction would provide ecpxivalent results.
5.1.2 Steam Dum Valve Test Description of Test:
Performance testing of a refurbished steam dump valve was conducted utilizing a Unit 1 unused piping loop.
The valve was installed in the loop and was stroked while data were obtained.
This was performed under plant procedure 1 EHP SP.032.
Safety Evaluation Summary:
This test was reviewed, and it was determined.that it did not constitute an unreviewed safety question.
This conclusion is based on the fact that the conditions resulting from this test are within normal operating conditions.
Additionallyg this procedure was modeled on the simulator before it was performed.
6.0 CHALLENGES TO PRESSURIZER POWER OPERATED RELIEF VALVES AND SAFETY VALVES During 1993, there were no challenges on either Unit 1 or Unit 2 to the pressurizer power operated relief valves (PORVs) or the pressurizer safety valves as a result of the valves being called upon to mitigate an actual overpressure condition.
7.0 REACTOR COOLANT SPECZFZC ACTZVZTY During 1993, there were no instances on either Unit 1 or Unit 2 in which the reactor coolant Z-131 specific activity exceeded the limits of Technical Specification 3.4.8.
8.0 ZRRADZATED FUEL EXAMZNATZONS During 1993,, no irradiated fuel examinations were performed because there were no scheduled refueling outages.
9.0 CHANGES TO FACILITY This section contains a brief description of the design changes implemented under the provisions of 10CFR50.59 and the associated safety evaluations.
9.1 DESIGN CHANGES (RFCs) 9.1.1 Radioactive Waste S stem Modification Description of Change:
DC-12-4109 replaced a 2-gallon per minute radwaste evaporator with a Duratek-design ion exchanger r'csin system.
The Duratek system',
which processes liquid radioactive waste, consists of six 36-inch diameter demineralization
- tanks, a
60-inch diameter deep bed filter, and associated components.
Safety Evaluation Summary:
This change was reviewed and it was determined that it did not constitute an unreviewed safety question.
This conclusion is based on the fact that the system is designed to the requirements of Regulatory Guide 1.143, it is located in an area where any leakage is routed to the radwaste
- system, and no effluents are discharged directly from the system.
9.1.2 New and S ent Fuel Pool Modification Description of Change:
A revision to DC-12-3051 (spent fuel pool re-racking modification) added nine high pressure sodium lights/
temporarily defeated the auxiliary building crane interlocks, installed a
temporary power supply with a
stepdown transformer, and temporarily removed various obstructions on the new and spent fuel pool walls.
Safety Evaluation Summary:
These changes were reviewed, and it was determined that they did not constitute an unreviewed safety question.
This is based on the fact that all loads in excess of 2500 pounds passing over the new and spent fuel pool would be lifted in accordance with the requirements of NUREG 0612, the temporary power supply would be mounted in such a way that it would not damage fuel assemblies, and the new lights are of sufficiently light weight that the technical specification limitations on impact energy are met.
9.1.3 Unit 1 Steam Generator Chemical Addition S stem Modificatio Description of Change:
DC-01-3090 changed the status of a system that was originally installed to supply a boric acid solution to the Unit 1 steam generators from temporary to permanent and also made modifications to the existing system.
The system consists of an 850-gallon boric acid solution mixing tank, a
pump to transfer the solution from the mixing tank to the chemical feed tank, and new, upgraded feedwater chemical feed pumps.
Safety Evaluation Summary:
This change was reviewed, and it was determined that it did not constitute an unreviewed safety question.
This conclusion is based on the fact that the system does not perform a safety function and the modification does not adversely interact with a safety-related system.
9.2 PLANT MODIFICATIONS (PMs) 9.2.1 Makeu Water S stem Modification Description of Change:
Plant Modification 12-PM-1387 added a tee and a valve-isolated hose connection to the makeup water system discharge piping.
A hose is periodically connected to this connection in order to supply water to reverse osmosis units that are being evaluated for improvements in makeup plant effluent water chemistry.
safety Evaluation:
This change was reviewed, and it was determined that it did not constitute an unreviewed safety questi.on.
This conclusion is based on the fact that no safety-related equipment is adversely impacted by this change.
9.2.2 S ent Resin Stora e Tank Level Indication Description of Change:
Plant Modification 12-PM-1059 removed the spent resin storage tank high/low level alarm because it was not functioning properly and repairs were impractical because of its location in an extremely high radiation area.
Safety Evaluation Summary:
This change was reviewed, and it was determined that it did not constitute an unreviewed safety question.
This conclusion is based on the fact that the level alarm is not required for the safe shutdown and isolation of the reactor nor is its use assumed in the mitigation of design basis accidents.
11
9.2.3 Circulatin Water Dischar e Points Description of Change:
Plant Modification 12-PM-821 installed sample pumps and routed one-inch steel sampling piping between the sample pumps and each unit's discharge tunnel access manhole.
The modification was made for improved monitoring capability because of the increase in chemical additions to the circulating water for zebra mussel control.
Safety Evaluation Summary:
This modification was reviewed, and 'it was determined that it did not constitute an unreviewed safety question.
This conclusion is based on the fact that this system is not required to mitigate the consequences of an accident nor is any safety-related equipment adversely impacted.
9.3 MINOR MODIFICATIONS (MMs) 9.3.1 Sam le Line Relocation Description of Change:
Minor Modification Ol-MM-245 relocated a 1/2-inch sample line installed in the waste gas disposal system.
This change moved the sampling point upstream of an isolation valve, allowing samples to be taken whenever the waste gas compressor was running.
Safety Evaluation Summary:
This change was reviewed, and it was determined that it did not constitute an unreviewed safety question.
This conclusion is based on the fact that moving the sample did not alter the function of the system.
9.4 TEMPORARY MODIFICATIONS (TMs)
None.
12
Dr. T.
E. Murley AEP: NRC: 1147D bc:
S. J.
Brewer D. H. Malin/K. J. Toth/W. R. Moran M. L. Horvath - Bridgman J.
B. Shinnock J.
B. Hickman, NRC - Washington, D.C.
AEP:NRC 1147D DC-N-6015.1, w/o attachment