Text

Annual Operating Rept
	ML19317G697
Person / Time
Site:	Rancho Seco
Issue date:	03/31/1975
From:	Mattimoe J, Reinaldo Rodriguez; SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:	;
References
	NUDOCS 8003260828
	Download: ML19317G697 (97)
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>M O nuclear generating station RANCHO SECO UNIT ONE l UNITED STATES NUCLEAR REGULATORY COMMISSION DOCKET NUMBER 50-317 OPERATING LICENSE DPR-54 C 3 ANN A_ PCR k J MARCH 1975 APPROVED: MM 1 R. J. RodriqJez, PIant Su rintendent 9 APPROVED: J. J. Mattim66% Assistant General Manager, Chief Engineer gsuun i SACRAMENTO MUNICIPAL UTILITY DISTRICT .---------..---i

1 gW. PART I OPERATIONS

SUMMARY

introduction This report has been prepared.for submittal to the Nuclear Regulatory Commission in'accordance with Proposed Appendix A, Section 6.9, and Appendix' B, Section-5.6 to Operating License DPR-54 for the Ranch Seco Nuclear Power Station. The Operating License for the Rancho Seco Nuclear Station was granted to the Sacramento Municipal Utility District.on August 16, 1974. This report is intended to summarize all significant activities from the date of obtaining the Operating License to the end of the annual reporting period on December 31, 1974. During the reporting period, the major plant activities involved the completion of the preoperational' testing, fuel loading, startup j testing and power escalation. f l j i i L I l.

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-/ INDEX-SECTION I OPERATIONS

SUMMARY

PAGE 1.0- ~ Chronological' History 1-1 1.1 Report for July 1-2 1.2 Report for August 1-9 1.3 . Report for September - 1-16 1.4 . Report for October 1-25 'I.5 Report for November 1-32 l.6-. Report for December 1-39 1.7. Tabulation of Personnel Exposures 1-48

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Fuel Examinations 1-50 I SECTION 11 ENVIRONMENTAL REPORT i 2.0 Table of Contents, Section ll 2-1 i- -2.1 Introduction and Summary 2-4 ~ 2.2 Environmental Protection 2-6 2.3 'Non-Radiological Environmental Surveillance Programs 2-17 t. 1 2.4 Radiological Environmental Moni toring 2-20 2.5 - Estimation of Errors 2-39 m '[. .s-. =. 1. .r*, w

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a -,w p 'CHRON0 LOGICAL' HISTORY -I.0 ' August ~ 16,;1974 - Operating License issued - August 19. 1974 - Commenced Fuel. Loading August 23,'1974 - Completed Fuel Loading - September 16,~1974 - Initial Criticality October: 3, 1974- --Completed Zero Pos.. Physics Test October 11, 1974 Initial Turbine fksil ' Oc tobe r-- 13, 1974 - - Synchronized to Grid November 18,~1974 - Completed 15% Testing ~ January-4,-1975 - Completed 40% Testing 4 4 - l' a . -g b Dl - -X -- c zu z

0 eo l' + 4 9 L I. L. 1.1 REPORT FOR JULY 4 l r E l t,_ s l % ;a 1 1 be i I 4 j 1-2 I w. d 9

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' OPERATIONS

SUMMARY

'~ ~ e 1.1.' l.1 Changes in Design ~ There were no significant' safety. related changes in plant design during July. m l'.l.l.2 Performance Characteristics The primary' effort this month was completion of the hot functional test program. 1.1.1.3 Changes in Operating Methods ~ ~ The following significant safety related chan'ges were made to Rancho Seco Unit I h opert ting procedures in' July, 1974: 1. Procedure B-4, " Plant Shutdown and Cooldown". Revision 1 - Revised system limits and precautions and rewrote Plant Shutdown section;- rewrote Plant Cooldown section to provide more detail. 1.1.1.4 Surveillance Tests n All equipment successfully passed the scheduled surveillance testing during July. i 1.1.'I. 5 -Periodic Containment. Leak Rate Tests -r .a There were no periodic containment leak rate tests performed in July. l.1.1.6-Changes,' Tests, and Experiments Authorized by NRC &) changes, tests, or experiments. requiring authorization from Nuclear Regulatory Commission,' pursuant to 10 CFR 50.59a, were performed during July, 1974. me f M I-3 l-l F W

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. MAINTENANCE OF SAFETY.RELATED EQUIPMENT 1 a

== Description:== Date - 1.1.4.1 !nadvertent Operation and Damage to High Pressure Injection Pump. 7-8-74 High Pressure injection pump started inadvertently.when a short strand of wire j fell across terminals, accidentally jumpering the control -switches in the con- - trol' room. The pump started and ran dead-headed for 15 minutes prior to trip-Ing on overcurrent.- The lack of flow recirculation heated the pump internals which :resulted. in~ complete seizure of the shaf t to the casing. This incident ~ occurred during performance-of 'the integrated Safety Features Actuation System q No fuel was loaded and the coolant ' system was at ambient temperature. Test. ; and dep.ressurized. The failed pump was sent to the vendor, Byron-Jackson, whe re.i t is-undergoing repai r in the Los Angeles shop. The pump was dissasembled-and inspected for damage. One Impeller was found ruined and replaced. The new impeller _ meets all-the original design specifications. All new wear rings and 'shaf t seals have' been ins talled. Shaft bearings were rebabbitted and fitted to the new shaft sleeves. The shaft was checked for straightness and rebalanced ~ with the'new impeller. installed. The pump casing was hydrostatically tested I satisfactorliy. The pump was reasserc. bled and is expected to be returned to the site in early March, 1975 A surveillance test will be performed on-the pump

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o . I.l.5 CHANGES IN PLANT OPERATING ORGANIZATION - JULY, 1974 r- ,1-The re were. no changes l i n the p l an t ope ra t i ng s ta f f for those pos i t ions ~wh i ch - are designated asikey supervisory personnel on Figure 6.2-1 of the Technical Specifications. 1 i i: - l 4 t 4 . f l I , ( + i. is. ^ l Y ! 4

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SUMMARY

.a 1.2.1.1 Changes in Design There were no significant safety related changes in plant design during August. l.2.1.1 Performance Characteristics The primary ef fort this month was completion of the initial fuel loading. 1.2.1.3 Changes in Operating Methods The following significant safety related changes were made to Rancho Seco Unit i operating procedures in August, 1974: 1. Procedure A.8,'" Decay Heat System". Revision 1 - Added pertinent system limits and precautions and rewrote " Decay Heat Removal During RCS Cooldown" section to include detailed steps as recommended by B&W; also included Decay Heat section valve /RCS pressure interlock modification and revised valve lineups per latest P&lD revisions. 2. Procedure A.23 " waste Gas System". Revision I - Updated system limits and precautions; r.ewrote normal operations.section to provide more operator information and revised valve lineups per latest Ps!D revisions. 1.2.1.4 Surveillance Tests Diesel Generator B failed to start on August 29, 1974 during Surveillance Test -h 206.03B. An Abnormal Occurrence Report No. 74-1 was filed with NRC. 1.2.1.5 Periodic Containment Leak Rate Tests There were no periodic containment leak rate tests peformed in August, 1974. .l.2.1.6 Changes, -Tests, and Experiments Authorized by NRC - No changes, tests, or experiments reouiring authorization from Nuclear Regulatory Commission, pursuant to 10 CFR 50 59a, were performed during August, 1974. [ 1-10 i J J

, 7 d 1.2.2 POWER GENERATION 1. ..t Nuclear August, 1974 Cumulative- ? l 1. Number of hours the reactor was. critical 0 0 2. Number of times the reactor was made critical 0 0 '3. . Gross thermal power generated (MWH)'- 0 0 4. Ef fective full power hours 0 .0 l I Electrical I. Gross electrical power generated (MWH) 0 0 t [ '2. Net electrical power generate'd (HWH) 0 0 r. 3. Number of hours the generator was on line 0 0 f i i I L ( -L ' l L. I L t-l-11 f. 'a s . l ,_{~ .u

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SUMMARY

l.2.1.1 Changes in Design There were no significant safety related changes in plant design during August. 1.2.1.1 Performance Characteristics The primary ef fort this month was completion of the initial fuel loading. 1.2.1.3 Changes in Operating Methods The following significant safety related changes were made to Rancho Seco Unit i operating procedures in August, 1974: l. Procedure A.8, " Decay' Heat System". Revision 1 - Added pert 1nent system limits and precautions and rewrote " Decay Heat Removal During RCS Cooldown" section to include detailed steps as recommended by B&W; also included Decay Heat section valve /RCS pressure interlock modification and revised valve lineups per latest P&lD revisions. _2 2. Procedure A.23, " Waste Gas System". Revision I - Updated system limits and precautions; rewrote ~ normal operations section to provide more operator infornation and revised valve lineups per latest e-P&lD revisions. 1.2.1.4 Surveillance Tests i Diesel Generator B failed to start on August 29, 1974 during Surveillance Test 206.038. An Abnormal Occurrence Report No. 74-1 was filed with NRC. 1.2.1.5 . Periodic Containment Leak Rate Tests There were no periodic containment leak rate tests peformed in August, 1974. 1.2.1.6 Changes, Tests, and Experiments Authorized by NRC No changes, tests, or experiments requiring authorization from Nuclear Regulatory Commission, pursuant to 10 CFR 50.59a, were performed during August, 1974. I a 1-10 b

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-e . f;. .y 'ff-i l.2.5 CHANGES _IN PLANT OPERATING ORGANIZATION - AUGUST, 1974 ~. {- There were no changes in-the plant operating staf f for those positions which are designated as key supervisory personnel on Figure 6.2-1 -of the' Technical C Speci fica t ions. i. (* o i + ?! r f 4 'i 1 I

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== Description:== Date-1.2.4.I Diesel' Generator "B" did not start as required by the t surveillance test procedure. 8-29-74 i^ ' During the performance of the monthly sur, vel,llance test procedure, it was found that-the "B"' Diesel Generator would not start manually in three successive . attempts. On the fourth attempt the diesel started, but did not reach operating r speed and the. field.did not flash. No indication of voltage nor spee'd onL the tachometer were observed. The diesel was then shut down and the problem ana-lyzed. A loose-connection inside the relay tachometer was found and resoldered. During'a bench test of the relay tachometer it was found that an internal high L. . temperature resistor was affecting the proper operation of other components L inside the relay tachometer which are temperature sensitive. The high tempera-ture. resistor was removed from the uni t' and mounted externally where the temper- 'f ature would not affect the tachometer. The tachometer was reinstalled in the r . control circuitry and functioned properly during successive starts of the Diesel Generator on August 31,-1974, September 1, 2, and 3,1974. Reactor. fuel was loaded in the1 reactor vessel and reactor head installation was in progress. f m O

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r. .i / 7. 1.3.1.5 Periodic Containment Leak Rate Test (Continued) t 3 The North Fuel Transfer Tube was tested on September 8,1974. No leakage was found. p 4. The Equipment Hatch was tested on September 9, 1974. No leakage 4,. was found. 5 The Personnel Hatch Outer Door was tested on September 10, 1974. .[ No leakage was found. 6. Emergency Sump Valves HV-26105 and HV-26106 were tested on I. September 12, 1974. No leakage was found. 'k 1.3.1.6 Changes, Tests, and Experiments Authorized by NRC -l No changes, tests, or experiments requiring authorization from Nuclear Regulatory Commission, pursuant to 10 CFR 50.59a, were performed during September,1974. ,t 1 -1 l i l l I

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OPERATIONS

SUMMARY

= 1 3.1.I . Changes in Design There were no significant safety related changes in plant design during September,-1974. ~ 1 3.1.2 Performance Characteristics The primary ef fort this month was completion of the Zero Power Physics Test -] Program. I.3.1.3 Changes in Opertting Methods t The following signill cant safety related changes were made to Rancho Seco Unit 1 operating procedures in September, 1974. ~ l. Procedure A.69, " Reactor Protection System". Revision 1 - Added system limits and precautions and made detailed h changes to the entire procedure to incorporate B&W comments. 2. Procedure B.1, " Plant Precritical Check". Revision 1 - Corrected specifications and verification frequencies and added applicable surveillance procedure. numbers L to reflect latest Technical Specification ~ requiressnts. .l.3.1.4. Surveillance Tests 1. -The isolation valve HV-26106 to the Reactor Building Emergency Sump failed to open on September 7,~1974 during performance of Surveillance Procedure 203.06B. An Abnormal Occurrence Report No. 74-2 was filed with NRC. u 2. Reactor Protection System Channel A was found out of calibration on the " Imbalance. function generator" when Surveillance Procedure 1-108 was1 performed September 19, 1974. An Abnormal Occurrence Report No. 74-4 was ~ filed with NRC. .4 1.3.1.5 Periodic Containment Leak Rate Tests The following Local Leak Rate Testing was performed during September, 1974: I. The Emergency Hatch Outer Seal was tested on September 4, 1974. No leakage was found.

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y-1 .e-:nicx w '1 9 1.3 2 PO'4ER GENERATION Nuclear Sept., 1974 Cumulative 1. Number of hours the reactor was critical 59 59 2. Number of times the reactor was made critical 26 26 3. Gross thermal power generated (MWH) 0 0 4. Effective full power days 0 0 Electrical J Gross electrical power generated (MWH) 0 0 1. 2. Net electrical power generated (MWH) 0 0 f 3 Number of nours the generator was on line 0 0 n I D 1 J I r. l-19 b

I, September, 1974 l.3.4 MAINTENANCE OF SAFETY RELATED EQUIPMENT

== Description:== Date r i 1.3.4.1 Emergency Sump Valve would not open. 9-7-74 Two unsuccessful attempts were made to cycle open one of the two Emergency Sump Valves during performance of a quarterly surveillance te<t procedure. An operator observed that during the test that stem travel was only 1/4 inch when complete travel should have been 20 inches. The valve was removed and I inspected. Inspection showed the motor and drive gears to be in excellent 'l condition. With the motor operator off, the valve stem was manually pulled to open the valve. The stem did not move, Indicating the gate was binding to the [ seat. Af ter further valve disassembly, a hydraulic Jack was attached to the i stem and with a moderate force the stem started out. Once loose, the stem was easily removed. The gate and seat were carefully inspected and all components were found in perfect condition. The valve was reassembled and the motor oper-r- ator attached. The torque limi t switches were adjusted and the valve tested. Numerous open and close cycles were performed without signs of binding. The valve successfully passes its surveillance test on September 14, 1974. It is assumed that since the valve had not been operated in 9 months, bond had formed i between the seat and gate seal surfaces. The valve is dry and lacks lubrication which would be provided by water under actual operating conditions. Valve cycling ~j frequency was increased to ensure valve operates freely. The plant was at cold L shutdown completing final testing prior to initial criticality. 1.3.4.2 High Pressure injection Pump Lube Oil Piping Failure. 9-8-74 High pressure injection pump was started and taking suction from the Borated Water Storage Tank in order to increase makeup tank level by use of pump recir-cula t ion. One minute after the pump started a Lo Lube Oil Pressure Alarm was received in the Control Roon. The pump was immediately shut down. Upon inves-tigation a bearing oil pipe Joint was found to have separated. The pipe Joint was repai red, the Lube Oil Reservoir refilled and the pump was started and bearing temperatures moni tored. Pump performance was determined satisfactory and the pump was placed back in service. The plant was in cold shutdown con-dition with preparations underway for initial criticality. 1.3.4.3 Reactor Coolant System overpressure during heatup due to 9-10-74 de-energized vital AC inverter and subsequent loss of l vital instrumentation. i Heatup of the Reactor Coolant System was in progress when an unusual sound was discovered coming from the internals of the SID inverter cabinet. Upon inves-i tigation, a loose inductor lug was found to be sparking to a grounding bar. To i' prevent electrical transients and further degradation of the inductor lug, it was decided that the SID inverter be de-energized and repair started immediately. Twelve minutes af ter the inverter was secured, the High Reactor Coolant Pressure w 1-22 e_

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n n 1.3.4.3 (Continued) Alarm sounded. The operator inspected his pressure indicators and noted the wide and narrow range pressure recorders for "B" loop were reading 1950 psig and the narrow range pressure indicator for "A" loop was reading 2400 psig and rising sharply. The operator decided the latter reading was correct and shut down the high pressure injection pump. The pressure began to drop quickly and at 2l00 psig the operator energized the pressurizer heaters to assure that the "A" loop pressure was responding correctl*; and that there was still a ~ steam bubble in the pressurizer. The RCS pressure subsequently decreased to 1900 psig by natural decay and then was reduced to 1600 psig until a complete analysis of the sie.uation could be made. One of the systems that the SID in- ~ verter supplies is the reactor non-nuclear instrumentation "X" power. This bus feeds numerous signal converters, transmitters, indicators, controllers, recorders, and selector stations. The Reactor Coolant Narrow and Wide Range Recorders for Loop "B" stopped at the pressure indicated at the time "D" in- ~ verter was de-energized (1950' psig). The Seal injection Flow Transmitter and Valve Controller went to zero signal and 50% open. The makeup control valve and letdown control valve also went to 50% open (zero signal). As a result of i this problem an alternate power supply has been assigned to the NNI X power with a temporary manual transfer switch, to be replaced by an automatic trans- ~ fer system. All inverters were checked for loose inddctor ground connections. A thorough analysis of the transient revealed no adverse effects to the Reactor l Coolant System. The reactor was subcri tical and stabilized at 355 F and 1950 8 psig at the time the inverter was de-energized. = ( i _j I -w .J 1 1-23 'A

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1.4.2 POWER GENERATION 1 Nuclear Oct., 1974 Cumulative r-l. Number of hours the reactor was critical 326 326* 2. Number of times the reactor was made critical 3 3* 3. Gross thermal power generated (MWH) 123,006 123,006 4. Ef fective full power 0.81 0.81 Electrical 1. Gross electrical power generated (MWH) 18,456 18,456 2. Net electrical power generated (MWH) -230 -230 .r 3. Number of hours the generator was on line 146 146

Numbers from month of September, 1974 during Zero Power Physics Test no-r' included.

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1.4.1 OPERATIONS SUt1 MARY 1.4.1.1 Changes in Design The following change in design of Rancho Seco Unit I were made ciuring October, 1974: 1. The upper level sensing line for CRD cooling water surge tank level transmitter was relocated to the surge tank nitrogen space. This modifi-cation was necessary to eliminate erroneou: Indications that occurred J when the low pressure connection on the level transmitter was vented to the atmosphere. 1.4.1.2 Performance Characteristics The primary effort this month was completion of tlee initial power operation and electrical synchroniza. ion tests. 1.4.1.3 Changes in Operating Methods l No significant safety releated changes were made to the Rancho Seco Unit I oper-ating procedures in October, 1974. l.4.1.4 Surveillance Tests ~ 1. The Nuclear Service Cooling Water System A was found to have low flow during performance of Surveillance Procedure 203.07C on October 6,1974. An Abnormal Occurrence Report 74-7 was filed with NRC. 2. Diesel Generator "B" tripped during performance of Surveillance Procedure i 206.03B on October 23, 1974. An Abnormal Occurrence Report 74-8 was filed with NRC. l.4.1.5 Perirdic Containment Leak Rate Tests -There were no pariodic contair. ment leak rate tests performed in October, 1974. 1.4.1.6 Changes, Tests, and Experiments Authorized by AEC ] l No changes, tests, or experiments requiring authorization from Nuclear Regulatory Commission, pursuant to 10 CFR 20 50.59a, were performed during October, 1974. 1 'e= W l-26 w

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A .t' i ' ' l.4.5 CHANGES IN PLANT OPERATING ORGANIZATION - OCTOBER, 1974 p . There were no changes in the plant operating staff for those positions which j-are designated as key supervisory personnel on Figure 6.2-1 of the Technical Specifications. r~ +% i i .t 'f ? lf^

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October, 1974 1.4.4 MAINTENANCE OF SAFETY RELATED EQUlPMENT

== Description:== Date ~7 } 1.4.4.1 Diesel Generator "B" Electrical Breaker Trip 10-23-74 The Diesel Generator "B" Synchronization Surveillance Test is performed monthly j as required by the Technical Specifications. During the test on October 23, 1974, the output breaker opened af ter operating the generator on line for Si minutes. The first indication of trouble was both the green (stop) and white (run) lights for the diesel control panel in the Control Room came on. The diesel generator -s breaker was checked and found open with no faults and normal indication on the back lighted push buttons. Approximately 10 minutes later, the green (stop) 7 light for the diesel started flashing. Normally this indicator is either on or i off. Five minutes later the green light went out indicating proper operation of the controls. The diesel remained at 900 RPM the entire time with correct volt-age and control. Later the diesel was re-paralleled and ran satisfactorily for ] two hosrs and fifteen minutes, at which time the generator was shut down using normal procedures. The problem was traced directly to the tachometer speed swltch due to the dual indication of both "stop" and "run" lights in the Control The relay tachometer was removed from the Diesel Generator "B" control l Room. panel. A new unit was installed and tested successfully on October 29, 1974. The failed relay tachometer was returned to the manufacturer for repair. The manufacturer reported that a dropping resistor was intermittently open and was ]y the cause of the failure. The resistor was replaced at the factory and returned. The sa:ne component failed on August 29, 1974. (See Abnormal Occurrence Report 74-1.) At that time the contacts were resold'ered inside the tachometer and a i retest proved the component operable. It is believed that the failure experienced J at that time was not corrected and can be traced to this occurrence. Replacement of the dropping resistor which was found to be intermittent at the factory should l the problem and return the tachometer to its operable condition. The _j correct reactor had completed 15% power testing during the initial escalation program and was at cold shutdown conditions to perform maintenance. m 1.4.4.2 Overheating of Auxiliary Feedwater Pump. 10-30-74 An Auxiliary Feedwater Pump overheated while attempting to transfer water from i the Condensate _ c,torage Tank to the steam generators during a feed and bleed operatioa to improve the water chemistry in the steam generators. The overheating occurred due to failure to open a discharge valve. The pump was inspected and the lead packing was found melted and leaking out of the glands. ,J The coupling to the motor was removed and manual rotation of the pump shaf t was unsuccessful. When dismantled in the plant shop, the casing wear rings were distored and frozen to the impellers, the seal rings were frozen to the I bushings, and the bushings were frozen to the drive shaft.~ New wear rings, bushings, and a new shaft were fabricated at the shop,.the seveh impellers i were inspected and reused and the completed pump was reassembled to factory l specifications. The pump was installed and tested on November 11, 1974, and a met all the Technical Specification requirements. The plant was at cold shut-down conditions and no transient was associated with this occurrence. 1-30 m

.r-1 t 1 i 1: - i i 4 [ 1,5 REPORT FOR Ek)V9tBER l .t I .l i i 1-32 4 f! l

, mm.,,. p ;.- e .1.5.1 OPERATIONS

SUMMARY

l. 5.1.'l Changes in Declgn The following changes in design of Rancho Seco Unit I were made during November, 1974. l. Ihnv Silicon Control Rectifiers were installed in Inverter SIC. This modification was necessary to make the inverter less vulnerable to noise spikes which had caused the inverter to trip. 2. The Bailey -positioner on Turbine Bypass Valve PV-20564 was replaced with

a. Fisher positioner. The Bailey positioner had broken due to vibration and valve shock from fast cpening.

The change was made to determine which positioner works best for this type of valve and service. 3 Repeater relays were installed in the Seismic Monitoring System to isolate seismic sensor relays from the Annunciator System. This modif-ication was necessary because 480 volt AC from an annunciator failure shorted'out the relay in a seismic sensor, causing high voltage on the m .+12 volt DC supply to the seismic system. This resulted in a burnout of the electronics in the system. i 1.5.1.2 Performance Characteristics The primary ef fort this month was completion of the 15% power operation test 3, plateau. J 1.5.1.3 Changes in Operating Methods No significant safety related changes were made to the Rancho Seco Unit 1 operating procedures in November,1974. 1.5.1.4 Surveillance Tests i 1. - Nuclear Service Cooling Water System "B" was found to have low flow during performance of Surveillance Procedure 203 07D on November 1,1974. An Abnormal Occurrence Report 74-9 was filed with NRC. -2. High. Pressure injection System Valve SFV-23645 failed to close during per-t formance of Surveillance Procedure 203.02A on November 8, 1974. An Abnormal Occurrence Report 74-12 was filed with NRC. -1.5.1.5 Periodic Containment Leak Rate Tests 'There were no periodic containment leak rate tests performed in November, 1974. i J 12 5.1.6 L Changes, Tests, and Experiments Authorized by AEC No changes, tests, or. experiments requiring authorization from Nuclear Regulatory Commission,. pursuant to 10 CFR 50.59a, were performed during November, 1974. 1-33 S

. r t V.5.2 POWER GENERATION

. 7_

i Nuclear Nov., 1974 Cumulative 1. Number of hours the reactor was critical 333 659 2.. Number of times the reactor was made critical 3 6 3. Gross thermal power generated (MWH) 227,728 350,734 k-4. Effective full' power days 3.56 4.37 Electrical i I. Gross electrical power generated (MWH) 68,568 87,024 2. Het electrical power generated (MWH) 44,394 44,164 i 3 Number of hours ' the generator was on line 289 435 6 f 4 -be 4.. t F p 1-34 L {l .o

} _, ,. ~. _, ~_ _4 ~~ c_ l.5.3 UNIT 1 SHUTDOWNS - NOVEMBER 1974 Status . ^ i During Corrective' Action Duration I Date Type Outage . Raason 11/19 Manual Hot Shutdown Feedwater Flpw Oscillation The ICS feedwater during ICS tuning at power dynamics was adjusted to decrease the re-resulting in manual reactor . sponse time to trip simultaneous with high coolant system pressurd trip. transients 14.5 hours .l { 11/22 Trip Hot Shutdown Temporary Reduction of Loop A-Backup Power Supply g 7 feedwater flow and subsequent to "J" inverter to be ? ig reactor trip on high coolant installed af ter de-pressure caused by. momentary sign review. ' 16.5 hours loss of "J" Inverter. I ~

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7-q ;; _e ,po amw i November, 1974 ~) 1 5.4' .' MAINTENANCE OF SAFETY RELATED EQblPMENT Description Date 1.5.4.1 Nuclear Service Cooling Water System Low Flow-11-1-74 Plant personnel performing routine rurveillance testir:g of the nuclear service y cooling water "B". system discovered the flow to be below the minimum flow re-i quirements of.the Technical Specifications. Valve positions of all components j -cooled by the NSCW system were inspected. A Nuclear Service Cooling Water Supply Valve for Reactor Building Emergency Cooling Unit "B" was found in a more closed position than when it:was -initially throttled during the initial flow balance test. A careful-inspection revealed that the worm gear on the position ~ adjustment handle had worn due-to flow induced vibration. A new worm gear was installed on the operator and an inspection of the other throttle valves showed them to be satisfactory with no apparent wear. In addition, positive locking pins have been. Installed on all throttle valves for the emergency cooling units. The plant was at cold shutdown conditions and all components in the nuclear service cooling water "A" system were operable. _i l.5.4.2 Failure cf Decay Heat Exchanger Discharge Valve (SFV-23039). 11-2-74 .j 4 The Decay Heat System was being filled and vented following the replacement of a decay heat exchanger bypass vent valve. During the fill and vent procedure,.the decay heat exchanger discharge valve (SFV-26039) was throttled from 3200 gpm to 2800 Later attempts to throttle the discharge valve were unsuccessful, gpm. inspec-tion of the valve operator revealed that a tooth had broken from the main drive gear and the object Jammed between two adjacent drive gears. The object was removed and the main ~ gear drive was replaced. The valve was, retested success-fully'and returned to service. The reactor. was at cold shutdown conditions and ~ no' transient was associated with this occurrence. The redundant decay heat sys-tem was fully operational and in service during the repair of this valve. 1.5.4.3 cailure of High Pressure injection System Recirculation 11-8-74 Isolation Valve to fully close. ~ s During a routine surveillance test, .Jection system did not stop as-required. recirculation flow of the high pressure in-is' stopped'by one of two valves in series.The' recirculation of the HPI System w and during this test SFV-23645 did not completely close.Each valve is tested Individually This permitted a 'small amount of water' to recirculate back' to the makeup tank, rathcr 'than flow

to the reactor coolant system. -The'other series. valve was tested and operated

- correc t l y.'. Both ' valves are designed ~ to operate at a maximum differential pressure of 2500 psi'..However, the maximum differential pressure across-the

valve whentit failed to close.was approximately 2900 psl.

Therefore, the torque switch setting'had to be: Increased to allow the valve to close at a higher- ~ differ ~ential. pressure.than~the initial design condition. 'After the torque switch setting was incriased~on SFV-23645, the valve was stroked five times and operated correctly each time. The reactor was at cold shutdown condition - and there was no transient associated with this occurrence. i 1-37 ~ h 4-

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,c il'l- ~ l.5. 5. CHANGES lN PLANT OPERATING ~0RGANIZATION - N0'JEMBER,1974 ~ ,p There were no changes'in the plant operating staff for those positions which are designated as : key supervisory personnel on Figure 6.2-1 of the Technical Specifications.

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SUMMARY

'l.6.1.1 Changes in Design The following changes in design of Rancho Seco Unit I were made during December, 1974:

1..

The Bailey positioners on Turbine Bypass Valves PV-20561, PV-20563 and .PV-20566 were replaced with Fisher positioners. The Bailey positioners had previously broken due to vibration and valve shock from opening too fast. The Fisher positioners seem to be less susce'ptible to vibration for this type of valve than the Bailey positioners. 1.6.1.2 Performance Characteristics The primary effort this month was completion of the 40% power operation test plateau. 1.6.1.3 Changes in Operating Methods The following significant safety.related changes were made to Rancho Seco Unit I operating procedures in December,1974: 1. Procedure A.66, " Radiation Detection for Liquid System". Revision.1 - Added additional system limits and precautions and rewrote abnormal operation section on radiation L monitor system failure alarm to clarify system design functions. 2. Procedure A 67, " Area Radiation Monitoring Sys tem". ~1 Revision 1 - Revised abnormal operation section to provide oper-ator response to a radiation monitor alarm and to provide operator response to a failure alarm. 3 Procedure B-2, Plant Heatup and Startup". s Revision 2 - Changed recommended control rod configurations for criticality and added B&W recommended maneuvering restrictions. ~ 1.6.l.4 Surveillance Tests 1. Diesel Generator System "A" failed to start on December 3,1974 during performance of Surveillance Procedure 206.03A. An Abnormal Occurrence i . Report 74-13 was filed with NRC. e m e. l.6.1.5 ' Periodic Containment Leak Rate Tests. -There were no. periodic containment leak rate tests performed in December, 1974. 1-40' ~

(S.-

l.6.1.6 Changes, Tests,-and Experiments Authorized by AEC- ' No changes, tests, or. experiments requiring authorization from Nuclear Regulatory - Commission, pursuant to 10 CFR 50.59a, were performed during December, 1974. j-mJr -. p

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7:4.;; ;;-- c> I 1.6.2 POWER GENERATION Nuclear Dec., 1974 Cumulative 1. Number of hours the reactor was critical 626 1,285 2. Number of times the reactor was made critical 6 12 3. Gross thermal power generated (MWH) 595,528 946,262 4. Effective full power days 8.95 13.32 Electrical l. Gross electrical power geaerated (HWH) 184,536 271,560 2. Net electrical power generated (MWH) 152,968 197,132 3 Number of hours the generator was on line 582 1,017 M_ S a> e* M. Sw m-j i.m q

i gggi 7 3 4 e. / M 9 in II 17 11 14 l '. i r. 1J 12 14 20 21 ?? 21 74 ?i 26 ?7 28 79 30 31110 y 105 th l Ino 100 V v5 "5 ) 1 . 90 'to

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l.6.3' UNIT 1 SHUTDOWNS - DECEMBER-1974 7 Status T During Date Type-Outage -Reason Corrective Action Duration 12/l: Trip Hot Shutdown Instrument technician tripped OPC transducer a,nd turbine durin'g instrument feedwater prespure check switches recalibratud 42 hours } 12/10 Manual Hot Shutdown Leaking weld on "l ?' fitting lFitting rewelded 7.75 hours for-EH fluid suppl.y line to intercept valve hydraulic operator 3 ' 7-12/15 Trip Hot Shutdown Power f. allure in Control Rod Added cooling: fans to $5 Drive System CRs panei 34 hours 12Il7 Trip Hot Shutdown Power failure in Control RorJ Control Rod Group 6/7 1 Drivs System p rog rame r. as semb ly readj us ted 17 hours 12/19, Manual Hot Shutdown Main Turbine,0PC Controller Pressure sensing line not functioning due to con-blown down 4 hourp tcminants in pressure sensing line. 12/26 Trip Hot Shutdown Failure of Vital Power Bu.s Replaced'two Silicon Inverter "C" Control Rectifiers in "C"' inverter 16 hours 12/28 Trip Hot Shutdown Failure of. Vital Power Bus Failed componen.ts [ Inverter "C" replaced. Load Trans-S fer Switch to "J" inverter installed 20 hours

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....- i _-[ ~ p - ;. 3 c..- 7-e 1.6.3 UNIT l' SHUTDOWNS - DECEMBER 1974 (continued) Status During Date' Type Outage - Reason Corrective Action Duration 12/31 Trip Hot-Shutdown ' Operator. tripped electrical blown fuses replaced 12 hours' bus during transfer 'to alternate power supply 6 a e M I J:* U1 e ,d 9 0 1 e e e e e O j 4 e ) 4 O e e 9 e

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+ a December, 1974 ~} 1.6.4 MAINTENANCE OF' SAFETY RELATED EQUIPMENT (

== Description:== Date 1.6.4.1 Failure of "A" Diesel Generator to Start. 12-3-74 I Starting of Diesel Generator "A" was attempted unsuccessfully from the Control ~f Room. The Diesel Room fans and engine fuel, oil pumps started, the engine run light on the local control panel came on, went off and stayed off. The starting air motors did not run and therefore the diesel did not start. The manual air 7 valves were checked open and starting air pressure was at 250 psig. The "A" f[ diesel "stop" button in the Control Room was pushed and the engine auxiliaries ~ went-through their shutdown sequences as if the engine had been running. An inspection of the diesel generator. control circuit revealed the Dynalco Relay { Tachometer had malfunctioned in such a manner that it blocked the energizing of the diesel air start solenoid which prevented the diesel from starting. The defective relay was removed and a new one was calibrated, installed, and tested "} success ful ly. An inspection of the original relay tachometer indicated that three ~Zener diodes had overheated and failed. This in turn caused the, relay tachometer to malfunction. Based on extensive testing by Dynalco, it has been determined that the Zener diodes had overheated, which caused them to fail, due to the close _f proximity of the Zeners to each other, the fact that the Zeners were not connected to a heat sink and the lack of air circulation through the relay tachometer. To .y correct this problem, the manufacturer made the following modifications: (1) The Zener diodes that are overheating are three 5-watt 7.5 volt connected in series to give a control voltage of i approximately 22.5 volts. They have been replaced with one J 50-watt 24 volt Zener mounted to a heat sink to dissipate the heat more efficiently. (2) Air vents have been cut in the side of the relay tachometer to allow air circulation through the tachometer. i To ensure that the new relays will operate as required, the relays were electrically I tested daily for a month. The reactor was operating at 40% full power. No transient occurred as a result of this problem. {J t ~' .J 1-46 I ' n

i, -. i . l.6'~5 CHANGES IN PLANT OPERATING ORGANIZATION - DECEMBER, 1974 There were no changes in the plant operating staff for those positions which -are-designated as key supervisory personnel.on Figure 6.2-1 of the Technical ~ Specifications, t~ i-t- . p 8,4 .I 4 4 4 ) k a 4 - 4 l, 1 e T f s . t ( - ) i I = l i i = t r. + t L 47 't i. L, t... t- , ~,

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-d A a PERSONNEL WHOLE BODY EXPOSURES FOR CALENDAR YEAR 1974 . Licensee' Reporting (Name & Address) License'No. Rancho Seco, Unit 1 DPR-54 Clay Station, California Annual Dose Ranges Number of Individuals (rem) in Each Range I. No Measurable Exposure 1405 i Measurable Exposure Less Than 0.10 121 t. 0.10 -- 0.25 5 t 0.25 -- 0.50 1 0.50 -- 0.75 0 l. 0.75 -- 1 0 1 l 0 1 -- 2

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'i . L 5' -- 6 0 . f-6 -- 7 0 i 7 -- 8 0 f 8 -- 9 0 9 --10 0 tr fI 10 --Il 0 It-11 --12 0 (' 12 +- 0 i l i. Total number of Individuals reported 1532 t l!L l The above information is submitted for the total number of individuals for whom l, personnel monitoring was (check one) 1:L -l l : required under -10CFR20.202(a) or 10CFR34.33(a) during the im-calendar year. ( .l / l-prov'ided during the calendar year. lrm l-49 t.

r 4 -,r-- . s.y 4 ,c --;- 3;; yy ; ;-- .,,,,.__,.35,- 1 .w .**1 1.8 FUEL EXAMINATIONS There~were no irradiated fuel examinations by eddy current tests, ultrasonic tests, or visual examinations performed during 1974. During the power escalation sequence the following data was accumulated: Month 5 Gross B Activity 1-131 1-133 October 1.74 2.18 x 10-2 < MDA < MDA November 0.45 2.97 x 10-2 < MDA < MDA December 0.245 .. 4 x 10-2 < HDA 4.09 x 10-5 Note: MDA is Minimum Detectable Activity The activity increase was expected due to the power escalation during the report period. These activities indicate that there are no fuel cladding failures during October, November, and December, when the power escalation and startup testing were in process. VV es. GnM S j l t ed o, ; l l-l.-50 e ,,,y ..,,y. ,e te A'

O h ao 4 4 V SECTION 11 L h OPERATING REPORT .i k c. f I

c. PAGES -~ '2.0 TABLE OF CONTENTS 2-1 -2.0.1-L*st of Tables 2-3 - 2.1

lNTRODUCTION 'AND

SUMMARY

2-4

k-2.2 ENVIRONMENTAL PROTECTION 2-6 i,.

c 2. 2 '. I Plant Water Discharge Temperature 2.6 2.2.2 Chlorine 2-6 I 2.213 Dissolved Solids 2-6 lit 2.2.4 pH 2-7 t i d-_ 2.2'5 Other Chemicals 2-7 2.2.6 Radioactive Discharges and Shipments 2-7 2.2.6.1 Liquid Releases 2-7 2.2.6.2 Gaseous Releases 2-8 -2.2.6.3 Solid Wastes 2-8 2.2.6.4 Offsite Liquid Shipments 2-9 2.3-NON-RADIOLOGICAL ~ ENVIRONMENTAL SURVEILLANCE PROGRAMS 2-17

p 2.3.1

. Erosion 2-17 i} 2.3 2 Orift Contaminants 2-17 il 2.3 3 Liquid Effluent Contaminants 2-17 - 2 3.4. Noise 2-19 1 2.3.5 Fogging 2-19 2.3.6 Reservoir Drawdown 2-19 2.4 -RADIOLOGICAL ENVIRONMENTAL MONITORING 2-20

2.4.1 Fish' 2-20 2.4.2.

Algae and Other Aquatic Plants 2-20 su 2.4.3 -Surface and Runoff Water-2-20 a: 2-1

e. -

- I'b

.. ~ - -. 9 s TABLE'0F CONTENTS (Cont.) PAGES / 2.4.4 Mud and Siit 2-21 2.4.5 Fresh Milk Sampling 2-21 2.4.6 Rabbits. 2-22 2.4.7 -Edible Vegetation 2-22 2.4.8 Well Water 2-23 2.4.9 Airborne Particulates and lodine 2-23 ~ 2.4.10 Di rect Radiation 2-23 -2.5 ESTIMAT10N OF. ERRORS 2-39 = 3 m .) .J T F u v a s 1 g we G 3 H L

)' L -. 4 2.0.1 LIST OF TABLES PAGES Table 1 Radioactive Liquid Effluents - -Sommation of All Releases 2-10 '~ Table 2. Liquid Effluents Batch Mode 2-11 r l Table 3 Airborne Effluents Summation of All Releases (3rd and 4th Quarter) 2-12 Table 4 Gaseous Effluents - Ground-level Releases, Batch Mode 2-13 Table 5 Gaseous Effluents --Ground-level Releases, Continuous Mode 2-14 Table 6 Liquid Waste Trucked Offsite for Disposal 2-15 Table 7 Reporting of Radioactivi ty in the Envi rons (Flora, Fauna and Water, 3rd Quarter) 2-24 Table 8 Reporting of Radioactivity in the Environs (Airborne, 3rd Quarter) 2-30 Table 9 Reporting of Radioactivity in the Environs (TLD, 3rd Quarter) 2-31 Table 10 Reporting of Radioactivity in he Environs (Flora, Fauna, and Water, 4th Quarter) 2-32 t Table 11 Reporting of Radioactivi ty in the Environs (Ai rborne, 4th Quarter) 2-37 g Table 12 Reporting of Radioactivity in the Envirans I TLD, 4th Quarter) 2-38 6 9 4 4 2-3 4J. ! ~.h. - L 1..

i~

2.1 INTRODUCTION

AND

SUMMARY

I k This report has been prepared for submittal to the U. S. Nuclear Regulatory Commission in accordance with Appendix B to the Operating License for Rancho Seco Unit 1. This report is intended to summarize / the significant environmental aspects during the period from initial criticality to the end of 1974. The report period was from September 16,

i 1974 through December 31, 1974.

Initial criticality was achieved on this pressurized water reactor on September 16, 1974. The highest power level attained through December rf 31,1974 was 42% '(384HW' -net); the power levels were varied to perform l e startup tests. f !{ ij The effects of tne plant upon the environment were minimal. Several short periods of higher than desirable chlorine levels in plant effluent .I were experienced without any appreciable effect on the receiving waters. There was one occurrence of discharge of effluent water containing 853 mg/l 1 dissolved solid (850 mg/l limit). Very minor amounts of plant related radioactivity were realeased to the environs. The environmental survelilance programs were effective in evaluating j{ the effect of the olant on the environs. There was no evidence of deleteri- .L l ous ' effects due to effluents from the facility. Measurements of radioacti-i; vity in the air, water, soll, vegetation and animal life Indicated that there was no sigr.ificant contribution from the operation of Rancho Seco. 2-4 lf I. L

~ a-. ggg;., 9 . i 9 An estimate of the errors associated with the determination of air-7 borne and liquid radioactive releases is included in Section 2.5 R S M U ..) lJ a I a ' }, I a Il 0 sl 1 Ji i* !i 4 1 2-5 J 1;

) 2.2 ENVIRONMENTAL PROTECTION 2.2.1 PLANT WATER DISCHARGE TEMPERATURE Technical Specification Appendix B limit - 900F. The plant water discharge temperature during the report period of September 16 through December 31 varied from 55 to 82oF., well under the specification re-0 ' qui rement of 90 F, Since seasonal temperatures were low enough, addi-tion of' dilution water for reducing water effluent temperatures was not required. l 2.2.2 CHLORINE Technical Specification Appendix B limit - 0.2mg/1.- Three brief periods exceeding the specified limit occurred during the reporting per-I lod. Chlorine concentrations to 0.35 mg/1. were experienced due to con-trol problems in the sewage plant. (I) Chlorination injection rates - were adjusted to bring the concentrations down to acqeptable values. r ( Work is in progress to prevent reoccurrence of overchlorination. 2.2.3 DISSOLVED SOLIDS Technical Specification Appendix B limit - 850 mg/1. or 34,000 c .lbs. for a single day - The total dissolved solids, TDS, were kept below the specification requirement with the exception of one occurrence in t which the concentration exceeded the specification for 2 hours.(2) { inaccurate measurement of effluent flow was encountered due to obstruction l-of the flow path at the outfall; high flow was indicated with consequent I-[. high TOS calculated discharges; the flow measurement error was diagnosed and corrected. t_. '(1) Unusual. Occurrence Reports, September 21, 1974 and November 26, 1974. -(2) _ Un' usual Occurrence Report, November 22, 1974. 2 5; '. m

-2.2.4-pH Technical Specification Appendix B limit - 6.5 to 8.5 - The pH of the site effluent during the. report period was within the range of 6.5 to 8.5 It should be noted that the-Folsom Canal had high pH values (9.0 to 9 2) in the months of September, October, and November, indicating leaching of the Canal surfaces. The pH of the Canal dropped ~ below 8.5 in the month of December. These pH changes of the Folsom Canal were not connected to the operation of Rancho Seco. 2.2.5 .OTHER CHEMICALS Technical Speci fication Appendix B Limi t - Dissolved Oxygen 5.0 -mg/1; B, 1.2 mg/1; Zn 1.0 mg/1. The dissolved Oxygen concentration ,l measured.100 yards downstream of the discharge point was maintained above _[ the limi t of 5.0 mg/1. During the months of September, October, and Nov-d ember the dissolved Oxygen in Hadselville Creek was below 5.0 mg/l pri- ~ marily due to local damming of the creek and seasonal related heavy _4 growths of water flora. The dissolved Oxygen content of Rancho Seco Effluent was always above the 5.0 mg/l level. - Composite samples analyzed during the report period indicated that the average Boron content of the effluent was less than 0.1 mg/1. and the average Zinc content was 0.3 mg/1. These values were we!1 under the-technical. specification limits. 2.2.6 RADIDACTIVE DISCHARGES AND SHIPMENTS 2.2.6.1 LIQUID RELEASES A small-quantity of radioactive tritiated water was 2-7 L

i [- released in October. An improperly routed drain sump in a con-t' rolled area caused some floor drains to be processed through the ion exchange regeneration system. The radioactivity was heldup, sampled and measured in retention basins. Since the [ concentration amounted to only 0.01% of the applicable 7-day l' average limit for discharge, the liquid was released. The - rathway by which this discharge occurred has been physically removed. The total activity released contained 0.002 Ci of 'l fission and activation products and 0.0197 Ci of Tritium. The low level of activity precluded identification of specific ~ isotopes. The summary of the liquid released is given in Tables I and 2. 2.2.6.2 GASEOUS RELEASES Since Rancho Seco is a pressurized water reactor the gaseous releases are composed of batch releases from the waste gas decay tanks, batch releases from the containment building purges, and continuous releases from the auxiliary building stacks and the gland' steam exhaust. The total gaseous releases for this reporting period were 0.00298 Ci of fission gases, primarily Xenons 133 and 135 and Krypton 85; 0.00606 CI of Tritium, 0.00000956 Ci of particulates and_0.000000809 Ci gross alpha activity. The low l' levels of the gaseous releases is presented in Tables 3, 4, and 5 j. 2.2.6.3 SOLID WASTES There were no solid wastes shipped from the Rancho Seco 'l ~ reactor facility during. the report pericd. i 2-8 c !O

--.... n. _,. .A 2.2.6.4 0FFSITE LIQUID SHIPMENTS ~ Four shipments.of radioactive IIquid wastes were trucked - to-Nuclear Engineering Co., Beatty, Nevada. A total of 0.1523 Ci, I primarily' H-3, wi th some Co-58 were shipped for disposal. The details of each shipment are included in Table 6. 1 (: M 'a e w i _J E 'k i 4 .J en .c' F +r 99 ~A

' TABLE I .p P EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FACILITY: RANCHO SECO (UNIT 1) ' DOCKET NO. 312 REPORTING PERIOD: 3RD AND 4TH QUARTER, 1974 'r .i . RADIOACTIVE LIQUID. EFFLUENTS - SUMMATION OF ALL RELEASES * '1 t 3RD QTR.* 4TH QTR.* EST. TOTAL UNITS.

SUMMARY

ERROR, % A. FISSION &' ACTIVATION PRODUCTS l. Total Release (not 'CI 0.00E0 2.28E-03 +2.6E+01 Including tritium, gases, alpha)

2.. Average' diluted con-pCi/ml 0.00E0 1.00 E-06 centration during period-f f3.

Percent of appli-0.00E0 9.12E-02 i cable limit B TRITIUM l. Total Release Cf. 0.00E0 1.97-02 1,5 5E+01 i ~ Average diluted con-p C I/ml - 0.00E0 8.68E-06 2. centration during period 3 Percent of appli-t 0.00E0 2.89E-01 . cable' limit C. DISSOLVED & ENTRAINED GASES ![ 1.- Total Release Ci 0.00E0 0.00E0 2. Average diluted con-pCi/mi 0.00E0 0.00E0 l{ centration during - t[: . period 3. Percent of:appli-0.00E0 0.00E0 [ cable limit .i D. GROSS ALPHA-RA010 ACTIVITY q- 'l. Total Release CI 0.00E0 0.00E0

(

E. VOLUME OF WASTE RELEASED liters 0.00E0 2.27E+06' +1.0E +01 F. VOLUME OF DILUTION WATER' i! USED DURING PERIOD-OF l RADIDACTIVE LIQUID-RELEASES liters 0.00E0 1.47E+07 10.2E+01 i-- r

Monthly summahles not / included-since only two releases occurred during

[ Lthe reporting' period; both'during thetperiod of October 14'through October ~ i f.18,1974. ~ 2-10 a I~. + -

E 0 k!$>Q>Rf/ ///// 5 ?$Z$> %fp% \\\\ IMAGE EVALUATION NN TEST TARGET (MT-3) 1.0 E!RM Ela 5[E ! ';2f El l EM l.1 m l l 1.8 1.25 I l.4 "l 1.6 1-- l i i 4 6" MICROCOPY RESOLUTION TEST CHART i I/

i!s'$/

'4

i!

i, s.

<$' N N/ Q \\\\\\/ // IMAGE EVALUATION N TEST TARGET (MT-3) l.0 5 m 1111 g m gin su = a l,l D bb I.8 l 1.25 1.4 1.6 -. ~. MICROCOPY Ri1SJ J T!ON TEST CHART r 4% + 4 >,N// $A{hf v

TABLE 2 EFFLUENT AND WA5TE DISPOSAL SEMIANNUAL REPORT FACILITY: RANCHO SECO (UNIT 1) DOCKET N0. 50-312 l AVERAGE QUARTERLY RESULTS REPORTING PERIOD: 3RD AND 4TH QUARTER, 1974 LIQUID EFFLUENTS BATCH MODE NUCLIDES. RELEASED UNIT QUARTER 3 QUARTER 4 .Strontlum-89 CI 0.00E0 0.00E0 ] Strontium-90 Cl 0.00E0 0.00E0 Cesium-134 Cl 0.00E0 0.00E0 Cesium-137 Ci 0.00E0 0.00E0 lodine-131 Cl 0.00E0 0.00E0 i Cobalt-58 Ci 0.00E0 0.00E0 Cobalt CI 0.00E0 0.00E0 Iron-59 CI 0.00E0 0.00E0 Zinc-65 Ci 0.00E0 0.00E0 Manganese-54 Ci 0.00E0 0.00E0 Chromium-51' Cl 0.00E0 0.00E0 Zfrconium-lllobium-95 C1 .,. ;0E0 0.00E0 Mol bdenum-99 Ci 0.00E0 0.00E0-i Technetlum-99m Ci 0.00E0 .0.00E0 Barium-Lanthanum-14C Ci 0.00E0 0.00E0 I Cerlum-141 C1 -0.00E0 0.00E0 Other (specify) ~ 1.- Tritium (H-3) CI 0.00E0 1.97E-02

2. Xenon-133 Cl 0.00E0 0.00E0

3. Xenon-135 Ci 0.00E0 0.00E0 Unidentitled Cl 0.00E0 2.002-03

~ Total for period (above). Ci 0.00E0 2.17E-02 .a _J lJ r 11 ]

w

.w

a p.=
=.: W.- -

=-w = ~.: : Lf %; i TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FACILITY: RANCH 0 SECO (UNIT 1). DOCKET NO. 50-372 AIRBORNE EFFLUENTS SUMMATION OF ALL RELEASES REPORTING PERIOD: ~3RD and 4TH QUARTER,' 1974 3RD.-QTR. MONTHLY

SUMMARY

4TH QTR. 4TH QTR. EST. TOTAL 7 UNITS

SUMMARY

OCTOBER NOVEMBER DECEMBER-

SUMMARY

% ERROR (1) A. FISSION & ACTIVATION GASES

1. ' Total Release Ci 0.00E0 (2) 0.00E0 (2) 1.66E-03 1.32E-03 2.98E-03 13.4E+01

.2. Average Release Rate uCi/sec 0.00E0 (2) ~ 0.00E0 (2) 6. 40 E-04 4.93E-04 3.75E-04 3. % of Technical Specifi-cation Limit 0.00E0 (2) (3) (3) (3) 1.17E-05 t B. IODINES Y 1. Total 1-131 Ci 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) 2. Average Release Rate u C i/sec 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) 3 % of Technical Specifi-cation Limit 0.00E0 (2) (3) (3) (3) 0.00E0 (2) C. PARTICULATES 1. Particulates (t> 8 days) 0+1.00E+02 (5) Ci 0.00E-0 (2) 4.68-06 4.35E-06 5.26E-07 9.56E-06 -1.3E+02 2. . Average Release Rate pCi/sec 0.00E0 (2) 1.75E-06 1.68E-06 1.96E-07 1.20E-06 3 % of Technical Specifi-cation Limit t 0.00E0 (2) (3) (3) (3) 8.09E-07 i 4. Gross' alpha radioactivity Ci 0.00E0 (2) 1.40E-08 6.59E-07 1.36E-07 8.09E-07 D. TRITIUM /+1.5E+01' 1. Total Releast. Ci 0.00E0 2.04E-03 2.19E-03 1.83E-03 6.06E-03 -2.8E+01 2. Average Release Rate pCI/se.c 0.00E0 7.64E-04 8.47E-04 6.81E-04 7.62E-04 3 % of Technical Specifi-cation Limit (4) (4) (4) (4) (4)

TABLE 4 9 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT- , :1 FACILITY: RANCHO SECO (UNIT.1) DOCKET NO. 50-312 REPORTING PERIOD-3RD AND 4Tn QU/'TER, 1974 GASEOUS EFFLUENTS-GROUND-LdVEL T.ELEASES BATCH MODE 3RD. QUARTER MONTHLY

SUMMARY

, 4TH QTR 4TH QUARTER . UNITS

SUMMARY

OCTOBER NOVEMBER DECEMBER

SUMMARY

.1. FISSION GASES 9 Krypton-85 Ci 0.00E0 0.00E0 (2) 8.72E-04 0.00E0 (2) 8.72E-04 -i Krypton-85m Cl' O.00E0 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) Krypton-87 Ci 0.00E0 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) Krypton-88 Ci

0. 00E0' O.00E0 (2). 0.00F0 (2) 0.00E0 (2) 0.00E0 (2)

Xenon-133 CI 0.00E0 0.00E0 (2) 7.90E-04 1.24E 2.03E-03 .j ~ Xenon-135 Ci 0.00E0 0.00E0 (2) 3.05E-05 7.90E-05 1.10E-04 Xenon-135m Ci 0.00E0 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) LXenon-138 CI 0.00E0 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) Others Ci 0.00E0-0.00E0 0.00E0 0.00E0 0.00E0 Unidentified Ci 0.00E0 l.00E0 0.00E0 0.00E0 0.00E0 Total for Perlod Ci 0.00E0 0.00E0 (2) 1.66E 1.32E-03 2.98E-03 2. 10 DINE lodine-131 'Ci 0.00E0 '0.00E0 (2) 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) lodine-133 Ci 0.00E0 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) lodine-135 'Ci

0.00E0 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) 0.00E0 (2)

~ Total for Period Ci 0.00E0 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) 3. PARTICULATES Strontium-89 Ci 0.00E0 (5) (5) (5) (5) Strontlum-90__ _C I 0.00E0 (5) (5) (5) (5) Ceslum-134 Ci 0.00E0 (5)~ (5) (5) (5) Ceslum-137 .C1 0.00E0' (5) '(5) (5) (5) j Barium-- i, Lanthium 140 _CI 0.00E0 (5) (5) (5) (5) a Others Cl 0.00E0' (_ 5) (5) (5) (5) ~ i Unidentified CI 'O.00E0 2.35E-07 9.53E-07 3.22E-10 1.19E-06 ,j l J j' 2-13 ] a

TABLE 5 .f EFFLUENT AND k%STE DISPOSAL SEMIANNUAL REPORT FACILITY: RANCHO SECO (UNIT 1) DOCKET NO. ' 50-312 REPORTING PERIOD: 3RD AND 4TH QUARTER, 1974 l GASEOUS EFFLUENTS-GROUND-LEVEL RELEASES CONTINUOUS MODE 3RD. QUARTER MONTHLY

SUMMARY

, 4TH QTR 4TH QUARTER UNITS,

SUMMARY

OCT03ER NOVEMBER DECEMBER

SUMMARY

1. FISSION GASES Krypton-85 Cl 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) Krypton-85m Ci 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) Krypton-87 Ci 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) Krypton-88 Ci 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) Xenon-133 CI 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) . Xenon-135 Ci 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) 0.00E0 s2) 0.00E0 (2) Xenon-135m Cl 0.00E0(2) 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) Xenon-138 Ci 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) Others Ci Unidentified Ci =t'l Total for I Period CI 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) 2. 10 DINE todine-131 Cl 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) lodine-133 CI 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) d lodine-135 C' O.00E0 (2) 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) Total for T Period Ci 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) 0.00E0 (2) 3. PARTICULATES j Strontium-89 CI (5) (5) (5). (5) (5) Strontlum-90 Ci -(5) (5) (5) (5) (5) Cesium-134 CI (5) (5) (5) (5) (5) Cesium-137-C1 (5) (5) (5) (5) (5) Barium-tanthium-140 'CI (5) (5) (5) (5) (5) Others. .CI (5) (5) (5) (5) (5) l Unidentified CI 0,00E0 (2) 4.44E-06 3.40E-06 5.26E-07 8.37E-06 ft l[ 2-14 f

TABLE 6 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FACILITY: RANCHO SECO (UNIT 1) DOCKET NO. 50-312 REPORTING PERIOD: 3RD AND 4TH QUARTER, 1974 LIQUID WASTE TRUCKED OFFSITE FOR DISPOSAL VOLUME TOTAL ACTIVI'TY MAJOR NUCLlDES

DATE (gal)

(Cl) AND % COMPOSITION , DESTINATION Nov. 14, 2785 2.25E-02 H-3 62% Nuclear Engineering 1974 Co-58 34% Co. Beatty, Nevada 7 G; 4 Dec. 12, 2300 2.28E-02 H-3 75% 1974 Co-58 24% (Same) Dec. 19, 2420 5.00E-02 H-3 98% (Same) 1974 t 1/ Dec. 23, 2740 5.70E-02 H-3 94% (Same) 1974 Co-58 2.6% e 4'$ i

A 7-L _,--- L.
---_ 1 1 _

rz : t c' t. .. L 1 !.o I:': r .a t x_ -. J "1 'J i o Ed ~

l ;' EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FACILITY: RANCHO SECO (UNIT 1) DOCKET NO. 50-312 REPORTING PERIOD: 3RD AND 4TH QUARTER, 1974 'p I NOTES . r* !f. (1) Third quarter monthly summary not included since all operation during the third quarter occurred in September. .j (2) No measurable activity in samples collected during this period. Measure-ment sensitivity and volumes of air released during the reporting period .are as follows: L. MINIMUM DETECTABLE BATCH RELEASE CONTINUOUS RELEASE '[' ISOTOPE ACTIVITY (uCI/ml) VOLUME VOLUME

i Kr-85 4.65E-06 1.13E+11 cc 1.81E+14 cc Kr-85m 1.48E-08 Kr-87 3.08E-08 Kr-88 1.16E-07 r

Xe-135 1.10E-08 Xe-135m 4.46E-08 Xe-138 3.94E-08 Xe-133 1.00E-07 l-131 =S.0E-14 j, 1-133 - 22.5E-13 j{ =l.0E-10 H-3 = 4.0E-12 (3) Technical Specification release Ilmits are given in terms of quarterly ] average release rates. L (4) No Technical Specification limit for release of Tritium in gaseous effluents. i (5) Particulates identified by gross beta activity. Insufficient activity for identification of specific isotopes present. All particulate activity released is assumed to have a half-life > 8 days. 6 2 i f

L.,.

i

f. -

s 2.3 NON-RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE PROGRAMS r I' 2.3.1 EROSION Each quarter a visual inspection of the waste water effluent course was made and channel dimensions were compared to the baseline channel. Photo-graphs were taken to document the characteristics of the effluent stream bed and banks. Examination and comparison with the reference photographs indi-cated no erosion of the strisam bed or degradation of the soil banks due to { plant effluent discharges at Rancho Seco. l. 2. '). 2 DRIFT CONTAMINANTS Soil samples were taken each quarter from three locations approximately L 0.25. miles from the base of the cooling towers. These sample points were about 120 apart to provide adequate coverage. The samples were analyzed for teachable sulfates. The leachable sulfates concentration Indicated by f analyses of the soil samples remained at preoperational levels and well under the 1500 ppm allowable level. This was substantiated by no evident degradation of agricultural land around the cooling towers. s t 1 i 2.3.3 LIQUID EFFLUENT CONTAMINANTS Three downstream locations were sampled to monitor the possible effects of effluent streams from the plant on irrigated lands. The effect on the I L agricultural land was assessed by monitoring leachable sulfates. u l 2-17 L F.L

sw _.c ~ P A Again the analyses of the samoles showed no evidence of degradation of the agricultural land. The samples of effluent water analyzed for oxygen, boron, and zinc also showed that the effluent water from Rancho Seco was maintained at a satisfactory environmental quality. A check was made to determine the quantities.of chemical used or T released by the plant.. The quantities were compared to the Technical Speci fication requirements, Table 5.1, Appendix B. Quantities of chemicals ~ released were within the stated limits with the following exceptions: ACTUAL USE ESTIMATED USE CHEMICAL lbs. conc. mg/l lbs. conc. mg/l Sodium (Na) 2.86 x 10s 33 1.45 x los 39 Alum 5.0 x 104 0 90 4.0 x 104 1.7 Al The use of NaOH has exceeded the design limit by approximately a l.( factor of two due primarily to a very high frequency of regeneration of lon exchange bec for the steam generator feedwater cycle. The ultimate i cause of this high rate of regeneration reflects back to corrosion and scaling problems with the feedwater heaters and the inability to properly ^ . protect these units during construction and testing. The frequency of regeneration is still greater than design as the system continues to be I cleaned up during power ascension, but should come down to design levels .I af ter reaching steady state operation in April,1975 It should be noted. that although the total quantity of consumed caustic exceeded the limit, i the effluent concentration of Na Ion was within the limit. ai The use of alum exceeded the design' level because it was found .i necessary to operate the makeup water clarification system continuously, j 2-18 ) m

s [II ~t' whereas design use w'as only during a portion of the year when high' solids were occurring. The clarifier is still being operated continuously, but .I alternative techniques for removal of problem solids are under study; these { may permi t removing the clarifier from service. It should be noted that although~ the total amount of alum released slightly exceeded the limit, the concentration of Al ion in effluent was below the projected limit.

2. 3. 4 -

NOISE Noise measurements within the site boundary taken during the initial startup indicated higher than desirable levels near the parking lot area ,p of the plant. Another set of noise measurements will be made wi th the plant

j at full power. An evaluation will be made at that time.

1l-l 1.3.5 FOGG I NG I I .l - No evidence of ground level fogging due to operation of Rancho Seco was observed during the reporting period. 2 3.6 RESERVOIR DRAWDOWN t i ! t The reservoir was maintained at required levels (237-240 feet) during i the reporting period. The County Parks Department in consonance with the

(

State requested that water level be lowered from 240 to 237 feet during the perlo'd of November and early December to aid in weed control. The reser-voir was then returned to its normal operating level of 240 feet, fI. u t t 8 2-19 I 6 I k.- l lU

.I t ( ~ 2.4' RADIOLOGICAL ENVIRONMENTAL MONITORING 2.4.1 FISH 3 Samples of fish were collected from the Rancho Seco Reservoir and the l~ Comanche Reservoir during the reporting period. The samples were analyzed .} for Gross Beta minus K-40, K-40 and Sr-90 activities. The activities are i low and correspond with preoperationally determined analyses. The data is shown-in Tables 7 and 10. There was no indication of any effect due to the operation of Rancho Seco. i 2.4.2 ALGAE AND OTHER AQUATIC PLANTS An algae sample was collected from the mixed effluent stream at the site boundary on November 16, 1974. The sample was analyzed for Gross Beta minus K-40, K-40 and Sr-90. A Gamma spectrometric analysis was also pe rformed. The data are shown in Tables 7 and 10. The analyses showed that l the activity was within previous base data and that there has been no indica-

l tion of contributton by the effluents of the plant.

t i 'f i 2.4.3 -SURFACE AND RUN0FF WATER j g ( Surface and runoff water samples were taken in both reportable quarters. The samples were analyzed for Tritium and Gross Beta,and Gamma spectra were obtained. The data are shown in Tables 7 and 10. The Gross Beta data-In t general showed no significant variations when compared with preoperational levels. The Tritium values in all cases were below the detection limit

[_

2-20 e _y

(0 + 160 pCi/l). In the analyses of the Gammas spectra only Cs-137 was detected (in the suspended solids), but the activity (9.0 pCi/l) was just above the deteccable limi t of R pCi/1. This could he attributed to fall-out. There was no indication that the activity was attributable to the station. -~ 2.4.4 MUD AND SILT Samples were collected from the Site Reservoir and the Mixed Runoff Effluent at the Site Boundary. Although the 4th quarter samples were slightly higher in Gross Beta than the 3rd quarter samples, all samples ~ were nonetheless within preoperational measured values. The data is~given ~ In Tables 7 and 10. These changes in concentrations do not appear to be a result of the startup of the reactor or any effluents from the plant. 2.4.5 FRESH MILK SAMPLING Fresh milk samples were collected on a weekly basis from four dairles during the report period. The I-131 levels were below the detection limit of 0 5 pCi/1. The average Sr-90 levels which ranged from 1.4 to 2.8 pCl/l were consistent with preoperational baseline data. The data are pre-sented in Tables 7 and 10. A review of the data Indicated no specific correlation of activity in the milk with animal vegetation samples collected during this period. There was no indication of contribution of the activity by the reactor facility. 2-21 ---,r

m-2.4.6 RABBITS. ( Four rabbit samples were collected. The flesh was analyzed for t. Gross Beta minus K-40 and K-40; the femurs for Sr-90 and stable Calcium, and the thyroids for 1-131. The Gross Beta minus K-40 and K-40 levels 'f compared we,. .ith preoperational data. The Sr-90 activi ty fluctuated b between the two reportable quarters but was well within acceptable levels. The Calcium data also varied but were within previously measured values. There was evidence of low l-131 activi ty (0.24 + 0.16 p Ci/g). The data are included in Tables 7 and 10. In summary the measured values were wi thin normal variations. 2.4.7 EDIBLE VEGETATION Four human vegetation samples (tomatoes and hops) were collected and analyzed. Naturally occurring K-40 activity appeared to be slightly higher than previous samples for no apparent reason. The Gross Beta 'I [ minus K-40 activity continued to be at levels measured during preopera-tional moni toring. See Tables 7 and 10 for the specific data Twenty-four anaimal vegetation samples were obtained and analyzed for Gross Beta minus K-40, K-40 and Sr-90. No signi ficant variations ~ were observed although one s pie indicated a Sr-90 activi ty of 0.75 pCi/g. There is no apparent corielation of the Sr-90 activity with the powe r_ pl an t ope ra t ion. Further, these values were similiar to others measured throughout the country. The data is summarized in Tables 7 l and 10. (l. i l' !$lll i.. 2-22 lL

i-TABLE 7 REPORTING OF RADICACTIVITY IN THE ENVIRdNS DOCKET NO. 50-312 FACILITY: RANCHO SECO (UNIT 1) REPORTING PERIOD: 3RD QUARTER, 1974 [ AVERAGE QUARTERLY RESULTS <~ j' FISH pCi/g (DRY) Q/G Beta less K-40 K-40 Sr-90 Location 0.02* .00l* 0.03* Site Reservoir 0.00 10.84 0.42 r Comanche Reservoir 0.00 9 57' O.26 ALGAE No Samples Available This Quarter. I [ SURFACE WATER pCi/l - M/G a H-3 Beta (Sus.) Beta (Dis.) Location 160* 0.5* 0.5* I i Comanche Reservoir 0 0.5 33 Folsom Canal 0 1.4 11.0 [ Site Reservoir 0 0.9 5.3 Site Drinking Fountain 0 1.5 4.2 Folsom South Canal 0 2.0 2.0 Natome Lake 0 0.0 2.5

Detection Limit FREQUENCY: W-Weekly, F-Fortnightly, M-Monthly, q-Quarterly, S-Semi-Annually TYPE:

G-Grab, C-Cont inuous, C'-Compos i te L 2-24 r. v-. c-.- -n

4 TABLE 7 (Cont) REPORTING OF RADI0 ACTIVITY IN THE ENVIRONS DOCKET NO. 50-312 FACILITY: RANCHO SECO (UNIT 1) REPORTING PERIOD: 3RD QUARTER, 1974 AVERAGE QUARTERLY RESULTS RUNOFF WATER pCI/1 - F/G H-3 Beta (Sus.) Beta (Dis.) Location 160* 0.5* 0 5* Mixed Effluent 0 6.48 9.07 (Site Boundary)- Gamma Spectrometry Ba-140 Co-60 Cs-137 l-131 Mn-54 Ru-106 Zn-65 Zr-95 33* 17* 8* 5* 10* 5* 23* 13* All six samples (suspended and dissolved) collected this quarter were analyzed for the isotopes listed above. All were below the detection ilmits listed. MUD AND SILT pCl/g (DRY) - Q/G j i Gross Beta Locatlon 0.05* l Site Reservoir 0.41+ 0.02 Mixed Runoff Effluent. I.37+ 0.31 ~ -(Site Boundary) I

Detection Limit' FREQUENCY: W-Weekly, F-Fortnightly, M-Monthly, Q-Quarterly, S-Semi-Annually

-TYPE: G-Grab, C-Continuous, C'-Compostte ~ I 2-25

9 TABLE 7 (Cont) l lL REPORTING OF RADIDACTIVITY IN THE ENVIRONS I' DOCKET NO. 50-312 i FACillTY: RANCHO SECO (UNIT 1) REPORTING PERIOD: 3RD QUARTER, 1974 t. AVERAGE QUARTERLY RESULTS .I FRESH MILK pCi/l - W/G l-131 Location 0.5* Sturmer Dairy 0.0 Borges Dairy 0.0 '~ Marciel Ranch 0.0 Warmerdam Dalry 0.0 .I it.

I

i

Detection Limit i

I !- FREQUENCY: W-Weekly, F-Fortnightly, M-Monthly, Q-Quarterly, S-Semi-Annually TYPE: G-Grab, C-Continuous, C'-Composite 'L 2-26

TABLE 7.(Cont) REPORTING OF RA010 ACTIVITY IN THE ENVIRONS DOCKET NO. 50-312 ~ FACILITY: RANCHO SECO (UNIT 1) REPORTING PERIOD: 3RD QUARTER, 197 4 AVERAGE QUARTERLY RESULTS RABdlT FLESH pCl/g (DRY) - Q/G Beta less K-40 K-40 Location 0.02* _.00l* Rancho Seco Site 0.00 9 960 North of Site 0.00 9.960 RABBIT FEMUR pCl/g (WET)- Q/G Sr-90 Ca ~ Location 0.03* .00l* Rancho Seco Site 0.56 + 0.05 37.0 North of Site 3.63 + 0.15 6.1 RABBIT THYROID pCl/g (WET) - Q/G j I-131 l Location 0.05* Rancho Seco Site 0.00 l North e' <lte 0.00

Detection '.imit E

l FREQUENCY: W-Weekly,~F-Fortnightly, M-Monthly,. q-Quarterly, S-Semi-Annually ~ TYPE: G-Grab, C-Continuous, C'-Composite 2-27

TABLE 7-(Cont) REPORTING OF RADIDACTIVITY IN THE ENVIRONS 7.. DOCKET NO. 50-312 i FACILITY: RANCHO SECO (UNIT 1) REPORTING PERIOD: 3RD QUARTER,1974 f AVERAGE QUARTERLY RESULTS l' I" ANIMAL VEGETATION pCI/g (DRY) - M/G Beta less K-40 K-40 Sr-90 Location 0.02* .001* 0.03* Sturmer Dairy 0.00 26.93 0.08 Broges Dairy 0.00 17.87 0.04 Marclei Ranch 0.00 7.15 0.09 Warmerdam Dairy 0.00 39.06 0.15 HUMAN VEGETATION pCl/g (DRY) - S/G Type of Beta less K-40 K-40

l'

' Loca t io.1 Vegetation 0.02* .001* 1 Sloughhouse Area Hops 0.00 23.24 Clay Station Area Tomatoes 0.00 58.10 tone Area Tomatoes' O.00 49.80 Clements Area Tomatoes 0.00 44.82 l. i

Detection Limit FREQUENCY: W-Weekly, F-Fortnightly, M-Monthly, Q-Quarterly, S-Semi-Annually TYPE:

G-Grab, C-Continuous, C'-Composite 2-28 m .~. .. ~,

TABLE 7 (Cont) _1 REPORTING OF RADIOACTIVITY IN THE ENVIRONS DOCKET NO.- 50-312 7 1 FAC!LITY: RANCHO SECO (UNIT 1) REPORTING PERIOD: 3RD QUARTER, 1974 AVERAGE QUARTERLY RESULTS l WELL WATER pCI/l - Q/G H-3 Beta ] Location 160* 0.5* q l Site Well 0 3.4 + 1.4 ( Clay Station Well 0 2.7 + 1.4 l l Reservoir Area Well 0 2.8 _+ 1.4 l Clay Cattle Co. Well 0 1.9.+ 1.3 h l l l l I l m..

Detection Limit FREQUENCY: W-Weekly, F-Fortnightly, M-Monthly, Q-Quarterly, S-Semi-Annually TYPE:

G-Grab, C-Continuous, C'-Composite 'lJ 2-29 1

[' 't TABLE 8 j REPORTING OF RADIDACTIVITY-IN THE ENVIRONS DOCKET NO. 50-312 r FACILITY: RANCHO SECO (UNIT 1) REPORTING PERIOD: 3RD QUARTER, 1974 I AVERAGE QUARTERLY RESULTS L AIRBORNE pCl/m r Air Particulates(W/C) Air Particulates(Q/C') Charcoal Filters (W/C) Gross Beta Alpha 1-131 Location .002* .005* .004* i S ite A .053 .000 .000 Site B .042 .000 .000 Site C .046 .000 .000 Site D .042 .000 .000 Site E .049 .000 .000 Site F .068 .000 .001 l Site G .068 .000 .000 [ Site H .047 .000 .000 Air Particulate Gamma Spectrometry (Q/C') ) Ba-140 Co-60 Ce-144 Cs-137 l-131 hn-54 Ru-106 Fe-59 Zn-65 Zr-95 Location .00l* .004* .00l* .002* .001* .002* .00l* .00l* .004* .002* l Site A .004 Si te B .004 .005 Site C .006 Site 0 .005 Si te E .008 Site F .010

(

Site G .003 Site N .002 O Detection Limit 00 Below Detection Limit FREQUENCY: W-Weekly, F-Fortnightly, M-Honthly, Q-quarterly, S-Semi-Annually TYPE: G-Grab, C-Continuous, C'-Composite L. 2-30

~~ = TABLE 9 REPORTING OF RADIOACTIVITY IN THE ENVIRONS DOCKET NO. 50-312 FACILITY: RANCHO SECO (UNIT I) REPORTING-PERIOD: 3RD QUARTER, 1974 AVERAGE QUARTERLY RESULTS DIRECT RADIATION - mrem / QUARTER - Q/l ~ Location TLD Reading ~ N. Perimeter Fence 16.1 + 1.2 ~ E. Perimeter Fence 13.81 0.5 W. Perimeter Fence 15.41 1.5 S. W. Perimeter Fence 14.9+ 0.8 S. E. Perimeter Fence 17.51 1.4 Visitors' Center 17.51 0.5 Rt. 104 Entrance

20. 6.+ 0. 8 N. W. of Site (6 miles) 23.81 7.2 N. W. of Site, Sacramento (22 miles) 18.71.1.5 S. W. of Site, Lodi (17 miles) 20 51 0.7

~ S. of Si te (0.25) miles 19.01 0.6 E. of Site, lone (11 miles) 22.0+ 4.4 W. Milk Station (10 miles) 21.8+ 1.1 ~ S. W. of Site, Galt (11 niles) 23.7+ 0.8 S. E. of Site, Comanche Res. (11 miles) 23.2+ 0.6 W. of Site, Clay (1.5 mIIes) 22.9+ 2.1 ,j S. W. Milk Station (9 miles) 25 71 2.9 N. E. of Site (8 miles) 24.9+ 0.2 S. E. of Site (1 mile) 25.5+ 1.1 .J l FREQUENCY: W-Weekly, F-Fortnightly, M-Monthly, Q-Quarterly, S-Semi-Annually TYPE: G-Grab, C-Continuous, C'-Composite, I-Integrating c i 2-31 l

.m TABLE 10 REPORTING OF RADICACTIVITY IN THE ENVIRONS DOCKET.NO. 50-312 FACILITY: RANCHO SECO (UNIT-1) REPORTING PERIOD: 4TH QUARTER, 1974 !f-AVERAGE QUARTERLY RESULTS li'!I f FISH pCl/g (DRY) - Q/G Beta less K-40 K-40 Sr-90 Location 0.02* .00l* 0.03* Site Reservoir 0.00 12.282 0.00 ~ l ALGAE pCI/g (DRY)- Q/G Beta less K-40 K-40 Sr-90 Location 0.02* .00l* 0.03* Mixed Effluent 0.35+ 0.07 1 33 0.00 (Site Boundary) Gamma Spectrometry i Ba-140 Co-60 1-131 Mn-54 Ru-106 Zn-65 Zr-95 Cs-137 ]l .010* .033* .010* .020* .010* .0 47* .025* .016* .124 .081

{': L

]

Detection Limit
- Below Detection Limit if i

' FREQUENCY: W-Weekly, F-Fortnightly, M-Monthly, q-Quarterly, S-Semi-Annually TYPE: G-Grab, C-Continuous, C'-Composite !L 2-32 - -~

b i TABLE 10 (Cont) 7 REPORTING OF RADIOACTIVITY IN THE ENVIRONS DOCKET NO.~50-312 FACILITY: RNHCHOSECO(UNIT 1) REPORTING PERIOD: 4TH QUARTER, 1974 _ AVERAGE QUARTERLY RESULTS ~? i SURFACE WATER pCl/l - M/G i H-3 Beta (Sus.) Beta (Dis.) location 160* 0.5* 0 5* 7 J Comanche Reservoir 0 1.6 0.7 Folsom Canal 0 07 1.2 l Site Reservoir 0 0.4 23 Site Drinking Fountain 0 05 09 'l -1 i RUNOFF WATER pCl/l - F/G H-3 Beta (Sus.) Beta (Dis.) Location 160* 0.5* 0 5* 1 Mixed Effluent 0 1.1 32

J (Site Boundary)

Gamma Spectrometry j I Ba-140 Co-60 Cs-137 1-131 Mn-54 Ru-106 zn-65 zr-95 33* 17* 8* 5* 10* 5* 23* 13* a All seven samples (suspended and dissolved) collected this quarter were analyzed for the isotopes listed above. All were below the detection ilmits listed except j l .the sample collected on112/31/74. This sample'p, suspended fraction had an Cs-137 value of 9. FREQUENCYs W-Weekly, F-Fortnightly, M-Monthly, Q-Quarterly, S-Semi-Annually TYPE: G-Grab, C-Continuous, C'-Composite

Detection Limit'

-33 e e r e R-&va-e 7 m g -awe. yen 1-we e e-'-

TABLE 10 (Cont) REPORTING OF RADI0 ACTIVITY IN THE ENVIRONS DOCKET NO. 50-312 I' FACILITY: RANCHO SECO (UNIT I) REPORTING PERIOD: 4TH QUARTER, 1974 i AVERAGE QUARTERLY RESULTS 1 T l MUD AND SILT pCI/g (DRY) - Q/G Gross Beta Location 0.05* Site Reservoir 2.96 + 0.45 Mixed Runoff Effluent 3.91 + 0.50 (Site Boundary) I 'l. FRESH MILK pCI/1 - W/G l-131 Sr-90 Location 0.5* 1.0* Sturmer Dairy 0.0 1.4 i Borges Dairy 0.0 2.8 Marciel Ranch 0.0 2.4** Warmerdam Dairy 0.0 1.4 ~ !!:t

Detection Limit
- Includes'one sample-with 3 3 + 1.1 pCi/1

~{- FREQUENCY: W-Weekly,'F-Fortnightly, M-Monthly, Q-Quarterly, S-Semi-Annually j . TYPE : 'G-Grab, C-Continuous, C'-Composite - Lj 2-34 We

s TABLE 10 (Cont) REPORTING OF RADI0 ACTIVITY IN THE ENVIRONS ~ DOCKET NO. 50-312 FACILITY: RANCHO SECO (UNIT 1) REPORTING PERIOD: 4TH QUARTER, 1974 AVERAGE QUARTERLY RESULTS RABBIT FLESH pCl/G (DRY) - Q/G Beta less K-40 K-40 Location 0.02* .001* Rancho Seco Site 0.04 4.192 RABBIT FEMUR pCl/g (WET) - Q/G ~ Sr-90 Ca Location 0.03* .001* Rancho Seco Site 1.11 30.05 RABBIT THYR 010 pCl/ 9 (WET) - Q/G l-131 JocatIon 0.05* I l Rancho Seco Site 0.12

Detection Limit
- Includes one sample with 0.24 + 0.16 p Ci/g FREQUENCY: W-Weekly, F-Fortnightly, M-Monthly, Q-Quarterly, S-Semi-Annually TYPE:

G-Grab, C-Continuous, C'-Composite i J 2-35

. TABLE 10 (Cont) REPORTING OF RADIOACTIVITY IN THE ENVIRONS DOCKET NO. 50-312 f. I. FACILITY: RANCHO SECO (UNIT 1) REPORTING PERIOD: 4TH QUARTER, 1974 AVERAGE QUARTERLY RESULTS 7 i. , l" ANIMAL VEGETATION pC1/g (DRY) - M/G ,1 Beta less K-40 K-40 Sr-90 Location 0.02* .00l* 0.03* Sturmer Dairy 0.00 26.25 0.23 Borges Dairy 0.00 17 01 0.17 Marciel Ranch 1.58 6.70 0.40 Warmerdam Dairy 0.00 21.03 0.26 ~ HUMAN VEGETATION No samples collected this quarter. WELL WATER pCl/l - Q/G . [' H-3 Beta Location 160* 0.5* Site Well 0 3.84;1.6 Clay Station Well 0 2.33;0.4 il Reservoir Area W' ll 0 2.1 ; 0.4 3 e Clay Cattle Co..W'll 0 2.9 + 0.5 e

Detection' Limit I

i FREQUENCY: W-Weekly, F-Fortnightly, M-Monthly, Q-Quarterly, S-Semi-Annually TYPE: G-Grab, C-Continuous, C'-Composite il..u 2-36 v + w

TABLE 11 REPORTING OF RADIDACTIVITY IN THE ENVIRONS DOCKET NO. 50-312 ~ FACILITY: RANCHO SECO (UNIT 1) REPORTING PERIOD: 4TH QUARTER, 197 4 AVERAGE QUARTERLY RESULTS AIRBORNE pCi/m Air Particulates(W/C) Air Particulates(Q/C ') Charcoal Filters (W/C) Gross Beta Alpha 1-131 Location .002* .005* .004* Site A .034 .000 .000 Site B .162 .000 .001 Site C .038 .000 .000 Site D .031 .000 .001 Site E .040 .000 .000 Site F .046 .000 .000 5Ite G .019 .000 .001 Site H .036 .000 .000 Air Particulate Gamma Spectrometry (Q/C') Ba-140 Co-60 Ce-144 Cs-137 l-131 Mn-54 Ru-106 Fe-59 zn-65 Zr-95 .001* .004* .00l* .002* .001* .002* .001* .001* .004* .002* All samples, composited b/ sampling location, were analyzed for the isotopes listed above. All were below the detection ilmits IIsted except the sample from Site H. i This composite had a Ce-144 value of.004.

Detection Limit t

FREQUENCY: W-Weekly, F-Fortnightly, M-Monthly, Q-quarterly, S-Semi-Annually TYPE: G-Grab, C-Continuous, C'-Composite i l 2-37

f' I TABLE 12 REPORTING 0F RADIDACTIVITY IN THE ENVIRONS DOCKET NO. 50-312 L. FACILITY: RANCHO SECO (UNIT 1) REPORTING PERIOD: 4TH QUARTER, 1974 AVERAGE QUARTERLY RESULTS I' lI DIRECT RADIATION - mrem / QUARTER - Q/l Location TLD Reading N. Perimeter Fence 18.9 1 1.7 E. Perimeter Fence 18.5 + 1.1 W. Perimeter Fence 18.6 + 0.33 S. W. Perimeter Fence 17 1 1 0.84 S. E. Perimeter Fence Dosimeter Lost Visitors' Center 16.5 1 0.63 Rt. 104 Entrance 20.7 1 7 5 N. W. of Site (6 miles) 28.4 + l.3 7 N. W. of Site, Sacramento (22 miles) 20.1 + 0.28 S..W. of Site, Lodi (17 miles) 22.1 + 0.51 S. of Site (0.25 miles) 20.1 + 1.25 E. of Site, lone (11 miles) 21.4 + 1.2 W. Milk Station (10 miles) 14.2 + 4.4 S. W. of' Site, Galt (11 miles) 22.9 1 0.78 S. E. of Site, Comanche Res. (ll miles) 22.1 1 0.6 W. of Site, Clay (1.5 mIIes)- 16.9 1 0.92 S. W. Milk Station (9 miles) 20.0 + 0.15 N. E. of Site (8 miles) 18.8 1 0.33 S. E. of Site (1 mile) 21.1 + 3.2 FREQUENCY: W-Weekly, F-Fortnightly, M-Monthly, Q-Quarterly, S-Semi-Annually TYPE: G-Grab, C-Continuous, C'-Composite, I-Integrating l_ 2-38 l

) Y 5k 2.5 ESTIMATION OF ERRORS 't An estimate of th'e errors associated with determining the airborne and . liquid radioactive releases was made for the Rancho Seco Unit 1 Plant. The airborne releases included the continuous releases and decay tank releases from the Auxiliary Building Stack, the Reactor Building Purges, and the Gland Steam Exhaust. The liquids consisted of Radwaste Shipments and con-7 .y trolled liquid effluents from the plant. - The considerations used in estimating the errors of the airborne re-leases included the following items: (1) anisokinetic sampling, (2) des- . position of sample in lines, (3) losses on particulate filters, (4) in- .t. efficiencies of the charcoal cartridge, (5) losses'due to handling, (6) flow rate uncertainties, (7) decay tank pressure changes, and (8) counting sta-tistics. The items included in the liquid release error analysis were: (1) sampling, (2) volume measurements, and (3) counting statistics. A compilation of the error analysis is given in the subsequent summary. _T l-i i

f. '

4.-

2-39 3q. M. =

SUMMARY

0F ERRORS IN THE DETERMINATION OF 1 AIRBORNE AND LIQUID RADICACTIVE RELEASES AT RANCHO SECO (All Errors in Percent) 1. Airborne Releases A. Auxiliary BuildI'ng Stack 1. Continuous Releases +(o +7 ) l/2 2 2 Fission and Activation Gases = +(o +9 ) I/2 or -[6+(o +g2)I/2) 2 2 2 lodines = +(o +g2)1/2 or.[5+(o,9 )l/2) 2 2 2 Particulates = +(o +g2)1/2 or -[10+(o +9 )I/2) Trliilum 2 2 2 2. Decay Tank Releases Fission and Activation Gases = +[o +42)l/2 2 = +(o +9 )1/2 or -[6+(o +9 )1/2) 2 2 2 2 lodines = +(o +9 )I/2 or -[5+(o +9 )1/2) 2 2 2 2 Particulates = +[o +5 +42) I/2 - 2 2 Tritium' gr -(10+[o +5 +42]l/2) 2 2 -8.- Reactor Building Purges Fission and Activation Gases = +(o +5 )l/2 or -[5+(o +5 )l/2). 2 2 2 2 = +(o +9 ) I/2 or -[6+(o +3 )I/2) 2 2 2 2 lodines = +(o +g2)l/2 or -[5+(o +g2)l/2) 2 2 Particulate = +(o +5 )1/2 or -[15+(o +5 )1/2) 2 2 2 2 Tritium m. M =2-40 i

i C. Gland Seal Exhaust Fission andl Activation Gases = +(o +]o2)l/2 2 = g(o +10 )i/2 2 2 lodines = +(o +10 )I/2 or -[542+io2)1/2) 2 2 Particulates- =.+(o +jo2)l/2 or -[10+(o +;o2)l/2) 2 2 ~, Tritium

.{-
I.

II. Liquid Releases A. Radwaste Shipments 1: Error in activity = +(o +;)U2 2 8. Liquid Effluents = +(o +;o2)l/2 2 Fission and Activation Products i .= +(o +;o2}1/2 2 Tritium = +(o +10 ) 1/2 2 2 Dissolved and Entrained Gases = +(o +10 )I/2 2 2 Gross Alpha Activity Volume of Water = +10 Volume of Dilution Water = +2 o f t r 2-41 1. =... w- ,}}

ML19317G697

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2.1 INTRODUCTION

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