ML19283B663
| ML19283B663 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 03/01/1979 |
| From: | NEBRASKA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML19283B662 | List: |
| References | |
| NUDOCS 7903060173 | |
| Download: ML19283B663 (9) | |
Text
.
a s COOPER NUCLEAR STATION BROWNVILLE, NEBRASKA ANNUAL OPERATING REPORT JANUARY 1, 1978 THROUGH DECEMBER 31, 1978 USNRC DOCKET 50-298 7903060\13
TABLE OF CONTENTS SECTION PAGE NUMBER 1
I. PERFORMANCE CHARACTERISTICS AND TESTS 2
Fuel Performance 3
Vessel Transient Condition Events II. FACILITY CliANGES REPORTABLE UNDER 10CFR50.59 5 8
III. PERSONNEL AND MAN-REM BY WORK AND JOB FUNCTION i
I. PERFORMANCE CHARACTERISTICS AND TESTS 1
FUEL PERFORMANCE Off-gas activity in the January 1 through April 1, 1978 operat4'nal period showed no increases indicative of additional fuel failures beyond those reported in the Cooper Nuclear Station (CNS) Annual Operating Report for 1977. The off-gas activity level continued to decrease from January 1 to April 1, 1978 with the release rates being well within the limits specified in the CNS Technical Specifications.
During the period from April 2 through April 30, 1978, the reactor was shutdown and the reactor vessel disassembled for the scheduled refueling and maintenance outage. The core was rearranged as per the fuel loading plan developed by General Electric for Cycle IV; 100 spent fuel assemblies were removed and replaced with new fuel. Twenty (20) fuel assemblies were sipped in an attempt to locate and remove the leaking fuel assemblies.
The leakers were not located and after consultation with General Electric, it was concluded that the off-gas activity level did not warrant further sipping. Af ter the reactor core loading was completed, the fuel loading was verified as correct, per the General Electric supplied loading arrangement for Cycle IV operation, and the results were recorded on video tape.
Prior to obtaining the CNS Power Operating Litanse, training criticals were performed (April 30, 1978 to May 2, 1978) no neet the reactivity change requirements for the licensed operators; the low power startup physics tests were also completed at this time. On May 3, 1978, following NRC review and approval of the Cycle IV Licensing Submittal, the reactor was started up and the remainder of the startup physics test program initiated. The maximum power achieved during the period of May 3 through December 31, 1978 was 100%. On November 25, 1978, there was a srall increase in off-gas activity; the activity level suggests possible leaks in one additional assembly or further deterioration of a previously existing leaking fuel assembly that was not found during the April 1978 refueling outage.
Comparisons of the actual control rod inventory during the period January 1 to December 31, 1978 to the control rod inventory predicted by normalized computer programs at various core average exposures indicated reactivity anomalies less than 1% AK/K.
The startup physics test program was completed on June 22, 1978 with the results of the last test being mailed to the NRC on September 11, 1978.
2
VESSEL TRANSIENT CONDITION EVENTS No operational transients more severe than the transients evaluated in fatigue usage calculations as described in CNS Calculation Book 8.40-21 are identified during this report period.
Reactor Coolant Pressure Boundary thermal and pressure cycles are sum-marized as follows:
NOTE: All transients started from approximately rated pressure and temperature.
MINIMUM TEMPERATURE DATE OF THE MODERATOR 1 4-2-78 120 F 2 6-1-78 2310F There were two (2) thermal-pressure cycles on the Reactor Coolant Pres-sure Boundary, one (1) was full cycle (from rated pressure and temper-ature to vessel vented), during the other cycle the vessel temperature did not go below 231 F as indicated above.
3
VESSEL TRANSIENT CONDITION EVENTS (DESIGN FATIGUE USAGE)
REPORT PER10D TOTAL EVENTS DESIGN EVENTS TO DATE EVENTS Normal Startup (100 F/hr) 2 86 120 50% Power Operation 8 43 14,600 (reduction to)
Rod Worth Tests 0 3 400 Loss FW Heaters 25% Turbine Trip 0 6 10 FW Heater Bypass 0 1 70 Loss FW Pumps (Sct. .ts) 0 4 10 Turbine Generator Trip 1 16 40 Reactor Overpressure 0 0 1 Safety Valve Blowdown 0 0 2 All Other Scrams 1 38 147 Improper Start Cold RR Loop 0 0 5 Sudden Start Cold RR Loop 0 0 5 Normal Shutdown 1 28 118 Hydrostatic Pressure Tests 0 1* 3 (1563 psig) llydrostatic Pressure Tests 2 0 1025 7 @ 1025 130 (1250 psig)
- Correct number of events prior to 1978 is 1.
4
0 II. FACILITY CHANGES REPORTABLE UNDER 10CFR50.59 5
REPORTABLE MINOR DESIGN CHANGES (MDC) COMPLETED IN 1978 MDC 76-2 Component: Pump, Fire Protection
==
Description:==
This FDC authorized the addition of a third fire pump to the Fire Protection System. The pump is electrically operated and similar in design and capacity to the two pumps presently installed. The new pump will differ in that the impeller will be of stainless steel and the assembly will utilize hardened stainless steel wear rings. Also included is a 250 HP, UL listed, F.M. - approved motor.
MDC 77-100 Component: CRD Return Line Nozzle
==
Description:==
This MDC provided for the cutting of the CRD nozzle safe end, removal of the thermal sleeve, inspection of nozzle and reactor vessel wall in the area of the nozzle, ferrite measurement of nozzle cladding, and capping of the nozzle with an inconel cap. The open return line was capped both inside and outside of the Drywell.
MDC 77-101 Component: MSIV Pressure Control Manifold
Description:
This FDC authorized the rebuilding of the FGIV control manifold components to a new upgraded control manifold as per General Electric FDI 117/10100. The parts which were modified were the three solenoid valves and the air operated pilot valves.
MDC 77-108 Component: Peak Accelerographs
Description:
This FDC authorized the removal of the six peak accelerographs which were located in the following places:
Core Spray lA Pump Motor Housing Core Spray lA Suction Line RHR Heat Exchanger 1B RHR Heat Exchanger lA Inlet Line RHR Heat Exchanger 1B Inlet Line REC Curge Tank 6
hEPORTABLE MINOR DESIGN CHANGES (MDC) COMPLETED IN 1973 (Cont'd)
MDC 77-108 (Cont'd)
Three new accelerographs were added te, raplace the above instruments. One accelerograph was located on the support skirt for the reactor vessel. Another was located on the Core Spray 1A Line entering the Drywell, and the last was located on the ACAD Isolation Relay Panel in the Cable Spreading Room. These instruments are for retrieval and analysis of data following a seismic event.
MDC 77-110 Component: No Break Power Panel
Description:
This MDC authorized the isolation of inverter 1B to eliminate the possibility of a ':ailure which could disable both 250V DC buses. This modification was also necessary for compliance with NRC Regulatory Guide 1.6.
MDC 77-122 Component: Floor Drain Filter Cooler
Description:
This MDC authorized the removal of the floor drain filter cooler in the Radwaste System. The cooler is located on the 903 level of the Radwaste Building down-stream of the floor drain filter holding pump. When pressure is lost, as in a leak, the precoat is lost and n;ust be reapplied. The cooler was originally installed to provide cooling to prevent high temperatures from breaking down the precoat. However, since operation high temperatures have not been encountered and cooler operation has not been required.
MDC 77-138 Component: GE/ PAC 4020 Computer
Description:
The purpose of this design change was to add a magnetic tape subsystem to the GE/ PAC 4020 Computer. This magnetic tape subsystem is a plug-compatible replacement for the paper tape system. A peripheral switch permits the utilization of either the magnetic tape system or the paper tape system.
7
J III. PERSONNEL AND MAN-RDI BY WORK AND JOB FUNCTION 8
?! * ;)
.-: .i.i '
- i. n "!MCTIO:;
Nun.ber of Pc m nnel '
Total M:ni-Ee-( >100 eEen) l Station Utility Contractor Station Utility Contractor Uork a..d Job Function Employees Employees & Others Employees Employees & Other Er. ACTOR OPERATIO:;S & SURV. ~
Maintenance Personnel 2 ---
2 .080 Operating Personnel
.739 38 --- ---
22.302 --- ---
Health Physics Personnel 12 ---
4.710 --- ---
Supervisory Personnel 7 ---
3.902 --- ---
Engineering Personnel 12 1 ---
4.599 .320 ---
ROUTINE MAINTENANCE Maintenance Personnel 46 ---
49 41.106 ---
22.646 Operating Personnel 6 --- ---
.332 --- ---
Health Physics Personnel 10 --- ---
1.804 --- ---
Supervisory Personnel 3 ---
1 .133 ---
.570 Engineering Personnel 1 --
.015 --- ---
SPECIAL MAINTENANCE Maintenance Personnel 8 ---
13 2.305 ---
8.175 Operating Personnel 4 ---
.689 --- ---
Health Physics Personnel 5 ---
.511 --- ---
Supervisory Personnel 2 ---
1 ,058 ---
.120 Engineering Personnel 3 ---
.349 --- ---
WASTE PROCESSING Maintenance Personnel 3 ---
,541 _-- ---
Operating Personnel 9 ---
2.815 --- ---
Health Physics Personnel 9 --- ---
1.202 --- ---
Supervisory Personnel 1 --- ---
.010 --- ---
Engineering Personnel 1 ---
.010 --- ---
REFUELING Maintenance Personnel 4 ---
7 .475 ---
1.648 Operating Personnel 27 ---
2.028 --- ---
Health Physics Personnel 3 ---
.102 --- ---
Supervisory Personnel 3 ---
.082 --- ---
Engineering Personnel 3 --- ---
.569 --- ---
INSERVICE INSPECTION Maintenance Personnel ---
21 -- ---
17.472 Operating Personnel 1 ---
.036 --- ---
Health Physics Personnel 5 --- ---
.548 --- ---
Supervisory Personnel 3 ---
2 .185 ---
2.140 Engineering Personnel 1 ---
1.068 --- ---
TOTALS Maintenance Personnel 46 ---
72 44.507 ---
50.680 Operating Personnel 39 ---
28.202 --- ---
Health Physics Personnel 12 ---
8.877 --- ---
Supervisory Personnel 9 ---
4 4.370 ---
2.830 Engineering Personnel 12 1 ---
6.610 .320 ---
GRAND TOTALS 118 1 76 92.566 .320 53.510 i I 9