ML19341C448

Annual Operating Rept,1980.

ML19341C448
Person / Time
Site:	Cooper
Issue date:	03/01/1981
From:	NEBRASKA PUBLIC POWER DISTRICT
To:
Shared Package
ML19341C444	List: ML19341C443 ML19341C448
References
NUDOCS 8103030500
Download: ML19341C448 (12)

Text

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COOPER NUCLEAR STATION BROWNVILLE, NEBR/SKA ANNUAL OPERATING REPORT JANUARY 1,1980 TIIROUGII DECEMBER 31, 1980 USNRC DOCKET 50-298 l

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i I TABLE OF CONTENTS SECTION PAGE NUMBER i

' 1 I. PERFORMANCE CllARACTERISTICS AND TESTS Fuel Performance 2 1

! Vessel Transient Condition Events 3 MSV and MSRV Failures and Challenges 5 II. FACILITY CllANGES REPORTABLE UNDER 10CFR50.59 6 4

. IIf. PERSONNEL AND MAN-REM BY WORK AND JOB FUNCTION 9

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1. PERFORESNCE CHARACTERISTICS AND TESTS 1

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FUEL PERFORMANCE off-gas activity in the January 1 through March 1, 1980 operational period shewed no increases indicative of additional fuel failures beyond that reported in the 1979 Annual Report. The off-gas activity level continued at essentially steady state levels from January 1 to March 1, 1980 with the release rates being well within the limits specified in the CNS TecSnical Specifications.

During the period from March 1 through May 29, 1980, the reactor was shut down and the reactor vessel disassembled for the scheduled re-fueling and maintenance outage. The core was unloaded as per the spiral unloading plan developed by CNS for Cycle VI; 152 spent fuel assemblies were removed and replaced with 112 new fuel assemblies and 40 used fuel a sse mbl ics . These 40 used fuel assemblies were previously used in the reactor during Cycle II and Cycle III. In concurrence with General Electric, sipping for leaking fuel assemblies was not warranted due to the low off-gas activity. A spiral reload plan was used by CNS to reload the fuel into the reactor. Af ter the reactor core loading was completed, the fuel loading was verified as correct in accordance with the General Electric loading plan for Cycle VI and the results recorded on video tape.

On May 30, 1980, following completion of the NRC review and approval of the Cycle VI licensing submittal, the reactor was started up and the startup physics test program was initiated. One hundred percent thermal power was initially achieved for Cycle VI on June 26, 1980. From May 30 through December 31, 1980, an essentially steady state of f gas activity was monitored. This activity, however, was less than one half of the off gas activity at the beginning of 1980 and indicates a very small number (or severity) of leaking fuel pins in the reactor.

Comparisons of the actual control rod density durj ng the period Jan-uary 1 to December 31, 1980, to the control rod density predicted by computer programs at various core average exposures indicated reactivity anomalies less than 1% AK/K.

The startup physics test program was completed on August 17, 1980.

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VESSE1 TRANSIENT CONDITION EVENTS l

No operational transients nore severe than the transients evaluated in the fatigue usage calculations as described in CNS Calculation Book 8.40-21 are identified during'this report period. There were nine (9) thermal-pressure cycles on the Reactor Coolant Pressure Boundary during 1980. Of these nine (9), four (4) were full cycle (from rated pressure and temperature to vessel vented). Reactor Coolant Pressure Boundary thermal and pressure cycles are summarized as follows:

NOTE: All transients started from approximately rated pressure and temperature except the second scram on 8-4-80 which occurred at a reactor pressure of 230 psig.

MINIMUM TEMPERATURE DATE OF THE MODERATOR (OF) 1 1-19-80 260 2 3-1-80 70 3 5-31-80 135 4 6-4-80 260 l 5 7-26-80 (a) 380 6 7-26-80 (a) 280 7 8-4-80 320 8 8-4-80 125 9 11-15-80 90 (a) NRC required testing of Scram Discharge Volume l

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I VESSEL TRANSIENT CONDITION EVENTS-1980 (DESIGN FATIGUE USAGE)

REPORT PERIOD TOTAL EVENTS DESIGN l EVENTS TO DATE EVENTS Normal Startup (100 F/hr) 9 102 120 l

50% Power Operation 3 60 14,600 (reduction to)

Rod Worth Tests 0 3 400 Loss FW 11 eaters 25% Turbine Trip 0 6 10 FW Heater Bypass 0 1 70 Loss FW Pumps (Scrams) 1 6 10 Turbine Generator Trip 2 19 40 Reactor Overpressure 0 0 1 Safety Valve Blowdown 1(a) 1(a) 2 All Other Sc.ams 5 48 147 Imprope- Start Cold RR Loop 0 0 5 Sudden Start Cold RR Loop 0 0 5 Normal Shutdown 4 32 118 0 3 Hydrostatic Pressure Tests 1 (1563 psig)

< Hydrostatic Pressure Tests 1 0 1025 9 0 1025 130 (1250 psig)

(a) Main Steam Eypass Valves remained open resulting in rapid blowdown from 1000# to 210#. Transient is similar to safety / relief valve l'

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i MSV AND MSRV FAILURES AND CHALLENGES (Ref: NUREG 0737, Action Item II.K.3.3) 4 I There were no MSV or MSRV failures in 1980.

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Two-stage Target Rock MSRVs were installed at all eight (8) main steam

line locations in the Spring 1980 outage. There was a single challenge to the new valves during the first 8-4-80 scram. Four (4) MSRVs opened on the pressure transient and two (2) MSRVs were operated pneumatically.

All valve actuations were satisf actory.

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l II. FACILITY Cl!ANGES REPORTABLE UNDER 10CFR50.59 ,

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REPORTABLE MINOR DESIGN CRANGES (MDC) COMPLETED IN 1980 MDC 78-32 Component: Reactor Building Equipment Drain Sump (IE) Pumps l

Description:

This MDC authorized replacement of the two 1E sump pumps l with pumps of larger capacity. With both of the old pumps running, the capacity was 100 gpm. The capacity of one of the new pumps is approximately 200 gpm. Reli-ability of the system was increased since one of the pumps could be operated in ST.*,i!DBY. A seismic analysis of the system, as modified, was performed and the ability of the system to withstand a seismic event was demon-strated.

MDC 79-12 Component: Automatic Wet Sprinkler System

Description:

This MDC authorized inr.ta11ation of automatic wet sprinkler systems to the following areas:

a. MG Set Oil Heat Exchangers in Reactor Buildiag

b. Cable Expansion Room in Control Building

c. Laundry Room and Adjacent Cotridor in Control Building

d. Instrument Storago Room in Control Building Plant safety is enhanced by this change since fires in these areas can be extinguished thereby protecting safety-related equipment and electrical circuits.

MDC 79-13 Component: Fire Protection For Diesel-Driven Fire Pump

Description:

This MDC authorized installation of automatic fixed foam and wet sprinkler fire protection equipment for the

' diesel-driven fire pump in the intake structure. Safety and availability of the fire pump is increased since a fire in er near the pump can be extinguished.

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4 MDC 80-09 i

Component: Main Steam Safety / Relief Valves (S/RVs) i

Description:

This MDC authorized replacement of all eight (8) S/RVs 7 i

with new two-stage Target Rock relief valves. The safety of the plant is enhanced since the two-stage valves

]L reduce or climinate recurring problems in the old three-stage S/RVs. The effect of the new valves on plant operation was analyzed by G.E. and Target Rock. The consequences of the new valves on all transients and 3

accidents was found to be less severe than those used in the original safety analysis.

i MDC 80-10 4

Component: Main Steam Safety / Relief Valve (S/RV) Position Indication

Description:

Pressure switches were installed in the discharge piping f rom each S/RV to provide open/ closed indication. This

! change was done to fulfill our commitments to the NRC per NUREG 0578 recommendations. The switches provide indi-1 cation only (i.e., no control function).

MDC 80-30 Component: Feedwater Spargers I

Description:

This MDC authorized modification of the feedwater nozzles

! and installation of dual-scal interference fit feedwater spargers. The work was performed as described in General

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Electric Document NEDE-218-02, " Boiling Water Reactor Feedwater Nozzle /Sparger Final Report (Supplement 2)". 1

The new spargers were designed to reduce or eliminate I nozzle cracks which occurred in the old spargers. NUREG 0312 contains the NRC's safety evaluation of the new spargers.

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J III. PERSONNEL AND MANREM BY WORK AND JOB FUNCTION 1

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^ O PERSONNEL AND MAN-REM BY WORK AND JOB FUNCTION 1980 Number of Personnel Total Man-Rem I

( >100 mrem)

Station Utility Contractor Station Utility Contractor Work and Job Function Employees Employees & Others Employees Employees & Others REACTOR OPERATIONS & SURV.

Maintenance Personnel 2 --- ---

.826 --- ---

Operating Personnel 41 --- ---

35.764 --- - -

Health Physics Personnel 11 ---

2 10.595 --- . '; 4 9 Supervisory Personnel 8 1 1 6.844 .576 .153 Engineering Personnel 13 --- 3 11.612 ---

.614 ROUTINE MAINTENANCE Maintenance Personnel 52 ---

127 91.549 ---

109.161 Operating Personnel 2 --- ---

.241 --- ---

Health Physics Personnel 11 ---

3 1.959 ---

1.324 Supervisory Personnel 4 ---

1 1.810 ---

.134 Engineering Personnel 4 --- ---

1.433 --- ---

SPECIAL MAINTENANCE Maintenance Personnel 13 ---

316 3.057 ---

469.697 Operating Personnel 6 --- ---

1.425 --- ---

Health Physics Personnel 5 --

9 1.614 ---

6.766 Supervisory Personnel 5 --- ---

1.516 --- ---

Engineering Personnel 2 12 4 .285 13.682 4.012 WASTE PROCESSING Maintenance Personnel 1 --- ---

.031 --- ---

Operating Personnel 15 --- ---

4.182 --- ---

Health Physics Personnel 8 --- ---

1.499 --- ---

Supervisory Personnel 1 --- ---

.010 --- ---

Engineering Personnel --- --- --- --- --- ---

REFUELING Maintenance Personnel --- ---

2 --- ---

.806 Operating Personnel 31 --- ---

8.462 --- ---

Health Physics Personnel 8 ---

3 .081 ---

.154 Supervisory Personnel 3 --- ---

.299 --- ---

Engineering Personnel 5 --- ---

.644 --- ---

INSERVICE INSPECTION Maintenance Personnel --- ---

17 --- ---

20.361 Operating Personnel --- --- --- --- --- ---

Health Physicr Personnel 11 ---

3 .586 ---

.160 Supervisory Personnel --- ---

1 --- ---

.886 Engineerint; Personnr.1 6 --- ---

5.000 --- ---

TOTAIS Maintenance Personnel 57 ---

356 95.463 ---

600.025 Operating Personnel 42 --- ---

50.074 --- ---

llealth Physics Personnel 11 ---

9 16.334 ---

8.753 Supervisory Personnel 9 1 3 10.479 .576 1.173 Lngineering Personnel 13 12 7 18.974 13.682 4.626 l

375 191.324 14.258 614.577 CRAND TOTALS 132 13