ML20050B235
| ML20050B235 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 03/31/1982 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20050B233 | List: |
| References | |
| 0069T, 0097A, 69T, 97A, NUDOCS 8204050125 | |
| Download: ML20050B235 (17) | |
Text
0 ZION GENERATING STATION ANtUAL OPERATING REPORT 1981 DOCKETS 50-295 AND 50-304 COMMONWEALTH EDISON COMPANY f
8204050125 820331 PDR ADOCK 05000295 R
, g.
0069t 0097A
TABLE OF CONTENTS I.
Environmental Reports A.
Intake and Discharge Data B.
Rates of Change of Circulating Water Temperature C.
De-icing D.
Violations of Environmental Technical Specifications E.
Malfunction of Environmental Monitoring Equipment F.
Hypochlorite Usage G.
Shoreline Erosion Status H.
Summary of Chemicals Used at Zion Station and Discharged to Lake Michigan II.
Waukegan Memorial Airport Expansion Plans III.
Modifications, Tests and Experiments IV.
Annual Occupational Exposure Data V.
Challenges to Primary System PORV and Safety Valves 0069t 0097A
INTRODUCTION This Annual Report by Commonwealth Edison Company, Zion Station transmits environmental data, near-site airport expansion plans, facility modifications, tests, experiments, occupational exposures, and challenges to the primary systems PORV or safety valves. AlUlough the Annual Report is no longer required by Zion Technical Specifications, the annual reporting of certain items is required.
The following areas are addressed in this report:
I.
Environmental Report Regarding Chemical and Temperature Discharges II. Expansion Plans for Waukegan Memorial Airport III. Modifications, Tests and Experiments Conducted at Ule Plant IV.
Occupational Exposure Report V.
Challerges to Primary System PORV or Safety Valves l
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ENVIR0f# ENTAL REPORT I
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0069t 0097A
A.
UNIT 1 INTAKE Ato DISCHARGE TEMPERATURE DATA i
MDNTH AToF INLET TEMP oF DISCHARGE TEMP 0F 1981 (AVG)
(AVG)
(AVG)
JAM Outage Outage Outage FEB Outage Outage Outage MAR Outage Outage Outage APR 15.7 (21 days down) 47.8 (21 days down) 63.5 (21 days down)
MAY 22.2 (4 days down) 47.9 (4 days down) 70.1 (4 days down)
JUNE 24.3 51.1 75.4 JULY 25.0 63.0 88.0 AUG 25.6 66.7 92.3 SEPT 24.5 J6.4 90.9 l
OCT 23.3 54.0 77.3 1
NOV 24.4 48.1 72.5 i
DEC 23.5 39.2 62.7 THE I W ORMATION IN THIS THE INFORMATION IN THIS THE IWORMATION IN THIS l
COLtNN WAS DERIVED FROM COLUMN WAS DERIVED FROM COLUMN WAS DERIVED FROM THE TECH STAFF DAILY LOG SUBTRACTING THE AT AVG THE TECH STAFF OAILY LOG WHICH IS TAKEN FROM THE FROM THE DISCHARGE TEMP WHICH IS TAKEN FROM THE i
STRIP CHART.
AVG.
STRIP CHARTS.
0069t 0097A
A.
UNIT 2 INTAKE AND DISCHARGE TEMPERATURE DATA MONTH t.T oF INLET TEMP oF DISCHARGE TEMP of 1981 (AVG)
(AVG)
(AVG) 3AN 27.5 36.0 63.5 FEB
- 29. '
35.8 64.8 MAR 28.4 38.6 67.0 APR 28.6 46.8 75.4 MAY 29.7 46.9 76.6 JUNE 30.7 50.1 80.8 JULY 33.4 62.2 95.6 AUG 26.1 66.4 92.5 SEPT 21.8 (20 days down) 68.1 (20 days down) 89.9 (20 days down)
OCT Outage Outage Outage NOV Outage Outage Outage DEC 25.4 (15 days down) 39.5 (15 days down) 64.9 (15 days doan)
THE INFORMATION IN THIS THE INFORMATION IN THIS THE INFORMATION IN THIS COLUMN WAS DERIVED FROM COLUMN WAS DERIVED FROM COLUMN WAS DERIVED FROM THE TECH STAFF DAILY LOG SUBTRACTING THE AT AVG THE TECH STAFF DAILY LOG WHICH IS TAKEN FROM THE FROM THE DISCHARGE TEMP WHICH IS TAKEN FROM THE STRIP CHART.
AVG.
STRIP CHARTS.
0069t 0097A
B.
UNIT 1 RATES OF CIRCULATING WATER AT CHANGE UNDER NORMAL ST ARIUP AND 5tUTDOWN (1981)
DATE RATE OF CHANGE OF/ifl 4-23-81
+.8 4-27-81
+ 9.0 4-28-81
- 10.5 5-01-81
- 3.1 5-05-81
+ 2.9 5-09-81
- 3.7 5-09-81
+ 3.3 5-29-81
+ 2.1 NOTE:
The rate of change for AT was calculated by noting aT at the beginning and end of normal startup and shutdown.
The difference in AT was then divided by the number of elasped minutes giving an average rate per minute.
This was multiplied by 60 giving an average rate per hour.
0069t 0097A 1
B.
UNIT 2 RATE 3 OF CIRCULATING WATER AT CHANGE UNDER NORMAL STARTUP AND SHUTDOWN (1981)
DATE RATE OF CHANGE OF/HR 5-08-81
+ 3.8 7-31-81
+ 2.3 8-09-81
+ 3.0 9-10-81
- 4.9 12-01-81
+ 1.7 12-01-81
+ 3.0 12-07-81
+ 2.7 12-23-81
+ 1. 9-12-23-81
+ 6.0 12-26-81
- 7.2 12-27-81
+ 3.6 NOTE: The rate of change for AT was calculated by noting AT at the beginning and end of normal startup and shutdown. The difference in AT was then divided by the number of elasped minutes giving an average rate per minute. This was multiplied by 60 giving an average rate per hour.
0069t 0097A
C.
DC-ICIriG Zion Station operated in the Oe-icing Mode during the first three months and the last two months of 1981.
D.
VIOLATIONS OF TFE EtNIR0ffENTAL TECHNICAL SPECIFICATIONS There were no violations of the Environmental Technical Specifications during 1981 E.
MALFUNCTION OF ENVIR0rNENTAL MONITORING EQUIPMENT There were no malfunctions of the environmental equipment in 1981.
F.
HYPOCFt.0 RIDE USAGE There was no sodium hypochlorite used at the Station in 1981.
G.
SHORELINE EROSION STATUS Commonwealth Edison Company is continuing to monitor ble status of shoreline erosion at the Zion Station Environs via monthly photographic surveys as oescribed in the 1980 submittal. Removal of concrete blocks from the north end of the property has effected improvement on the erosion conditions previously cited.
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0069t 0097A
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H.
SUMMARY
OF CHEMICALS USED At IION STATION Tech. Spec. Ref.
App. B, Sec. 2.3.B.1 AND DISCHAPCED TO LAKE MICHIGAN Years 1881 CHEMICALS
._ aste_Neut d ank Waste Neut. Tank
_C_orTonen_t _qmilne f_g ent coolino Lake Dis. Tank Lake Di, Tank SYSTEMr w
Sulfurie Acid Sodium flydroxide Potassium Hydroxide Potassium Dichromate Borfe M d Detergents (Gal.)
[Ca l. )
[LEs-)
(Lbs.)
(Lbs.)
(Lbs.)
January 10.0 13.0 271.0 14.0 29.0 492.1 February March gg,o 20,0 40s.9 6.0 11.0 3558.3 April May 1.0 3.0 2399.3 June 2.0 4.0 1394.1 0.0 1.0 1148.2 July 2.0 6.0 1622.3 August 11.0 21.0 2326.7 September October 14.0 28.0 2575.1 November 30.0 70.0 4366.8 December 38.0 62.0 3200.4 4892 7440
- 139.0
- 269.0 23,763.7
- % 100 Yearly Total Monthly totals not available, yearly totals below.
Comments:
Normal clothing dry cleaned, rubber goods washed with detergents, amounts to 4.100 lbs/ year.
1his amount reflects the chemicals 9dded to this system. This amount is not neceusarily what is discharged.
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II WAUKEGAN MEMORIAL AIRPORT EXPANSION PLANS The Airport Master Record (Form 5010-1) has been updated as of May 22, 1981 and has been attached.
The airport's Environmental Impact Assessment Report, submitted in 1978, has been approved.
The airport expansion project has not been completed, but acquisition of land is in progress.
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III MODIFICATIONS, TESTS AND EXRRIENTS MODIFICATIONS There were four modifications and two reactor fuel reloads completed in 1981 which involved a change to the facility as described in the FSAR.
These modifications did not raise an unreviewed safety question as defined in 10CFR50.59(a)(2). One modification required a Technical Specification change. Brief descriptions of the four modifications follow:
Turbine Building Drain Oil Separator (M22-1/2-77-14):
The addition of an oil separator changes the facility as described in the FSAR. The oil separator treats turbine building drains prior to treatment in the mixed bed demineralizer.
The new filter unit and tank do not increase the probability of an occurrence or the consequence of an accident.
The equipment does not degrade safety related systeras. The possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR is not increased because the equipment for the water treatment is similiar to other equipment discussed in the FSAR. The margin of safety is not reduced.
Replace SVAG Valve Key Lock Switches (M22-1,2-80-2): Certain valve operators (Spurious valve Acutation Group - SVAG) have been modified to provide control circuit functional requirements. Three position key operators have been replaced with 1) three position spring return right to center operators for normally closed valves or 2) three position spring return left to center operators for normally open valves. This modification resolves IE Inspection Reports No. 50-295/80-17 and 50-304/80-17, page 5, item 6.
The modification changes the response to Question 6.19 of the FSAR.
Question 6.19: Describe the design and operation of the key locked switch to be installed on motor-operated valves 90llA and B to prevent possible hot leg injection or of an alternate design means providing an equivalent degree of protection.
Revised Answer: Key locked switches will not be installed because valve cycling would occur if a switch was in open position during time of safety injection signal. A three position switch operator will be installed with maintained contacts for normal position and spring return from Non SI l
position to center position. Therefore when a switch is mis-positioned it j
self-returns to the intermediate position and arms itself for returning i
l the valve to the normally closed position upon SI Actucation.
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The replacement of the control switch operator assures valve cycling will not occur when there is a safety injection and therefore, decreases the probability of an occurrence or the consequences of an accident and decreases the probability of equipment malfunction. The improved control circuit logic does not create a possibility of an accident or malfunction i
of a different type than any previously evaluated in the FSAR. The margin i
l of safety is not reduced.
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0069t 0097A 1
Charging Pump Miniflow Isolation Valves (M22-1,2-80-46): The safety injection isolation signai has been removed from the circuitry of the charging pump miniflow isolation valves. This ensures adequate coolant flow through the pumps under all applicable reactor coolant system pressures.
The probability of an occurrence or the consequence of an accident, or safety equipment malfunction has not been increased as previously evaluated in the FSAR because Westinghouse sensitivity studies have shown that accidents are relatively insensitive to miniflow isolations as long as miniflow is unisolated when the RCS pressure reaches the RCP trip setpoint. The possibility for an accident or malfunction of a different type than previously evaluated in the FSAR is not created because the modification increases the reliability of the pumps. The pumps provide adequate flow to the RCS and the margin of safety is not reduced.
Spent Fuel Pool Racks: The Spent Fuel Racks as described in the FSAR have been replaced by high density racks. These racks now provide storage for 2112 fuel assemblies. The Facility Operating License [2.C.(7)] has been changed by Ammendment 61, dated 1-15-81.
TESTS AND EXPERIWNTS There were no testing or experiments performed during 1981 that involved a change in the technical specifications or an unreviewed safety question.
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IV ANNUAL OCCUPATIONAL EXPOSURE DATA This data for 1981 was submitted to the Nuclear Regulatory Commission by a letter from J.S. Bitel, Tech Services Department, to Mr. James G. Keppler, Regional Director dated February 25, 1982.
0069t 0097A
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V CHALLENGES TO PRIMARY SYSTEM PORV AND SAFETY VALVES On 12-6-81, Unit 2 reactor tripped from approximately 88% power while core physics testing was being performed. The reactor trip occurred at about 0355, and a lift of both PORVs (ZPCV-455C, 456) took place almost immediately. Pressurizer pressure was approximately 2335 psig at the time j
the PORVs lifted, and decayed to approximately 2120 psig at which time, I
pressure increased to = 2235 psig (normal RC pressure).
l The PORVs reseated normally after lift, with minimal leakage observed to the Pressurizer Relief Tank (PRT). No abnormal occurrences were observed.
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