IR 05000312/1974001
| ML19309A409 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 02/14/1974 |
| From: | Andrea Johnson, Rook H, Spencer G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML19309A404 | List: |
| References | |
| 50-312-74-01, 50-312-74-1, NUDOCS 8003270855 | |
| Download: ML19309A409 (10) | |
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U. S. ATCMIC ENE?.GY CO:'MISS* ' '
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JIEICTOEATE CF EECU*eTORY OPEPAIONS
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REGION V
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'do Inspection Report No.
50-312/74-01
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' Licensee:
Sacramento Municipal Utility District Docket No. 50-312
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Sacramento. California License No.(s) CPPR-56
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Priority
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Facility:
Rancho Seco
Category B
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14 cation:
Clay Station, California
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Type of Facility:
PVR. B&W. 913 We (2772' Wt)
Type of Inspection:
unuHne. Unnnnnunced
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s Dates of. Inspection:
January 14-16 and February 1, 4-6, 1974
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Dates of Previous Inspection:
November 26-28 and December 6. 1973
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Principal Inspector:
- 2. M tw M Z 3 f/
A. D. Joh soh, Reactor Inspector
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Accompanying Inspectors:
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'2,[/ d/7 f-N L. J." Garvirf Reactor Inspector
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FA 2. - VfP7'
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1.F.Fisk,RadiationSpecialist (Date)
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Other Accompanying Personnel: None
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Reviewed by:
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G. S. Spencer, Chief, Reactor Construction (Date)
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Operations ranch
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R. E. Book, Chief, Radiological and (Date)
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Environmental Protection Branch
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8.c os 270 255
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SUMMARY OF FINDINGS
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' Enforcement Action
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None j
i Licensee Action on Previously Identified Enforcement Items
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None required Unusual occurrences
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None
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Design Changes A.
The approved vendor field change requiring installation of suitable overcurrent protection in each reactor protective undervoltage circuit of the control rod drive (CRD) trip breaker system has been delayed pending receipt of the fuse holders.
(R0 Report No. 50-312/73-03, paragraph 4)
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Other Significant Findings
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A.
The previously reported indication that the control rod position
instrumentation was drifting out of calibration was in error. The i
observed variation of voltage at the partictlar test point was erroneously thought to have a plus or minus three (3) millivolt acceptance criteria when in fact in that part of the circuitry, variations in voltage in the millivolt range were shown to have a
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minor effect on system performance. Appropriate limits for that part of the circuitry have been conservatively established at a
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value of 350 millivolts (R0 Report No. 50-312/73-07, paragraph 7).
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B.
The preoperational test procedures for the high pressure emergency core cooling system were being revised to incorporate items con-
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sidered necessary by Regulatory Operations to adequately demonstrate the performance of the system.
(Paragraph 5 of Details)
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C.
Construction was estimated to be approximately 96% complete. The
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scheduled fuel load date of May 1974 was considered likely barring
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unforeseen delays.
(Paragraph 2 of Details)
'D.
The information submitted to RO:V by letter dated January 7, 1974 related to valve minimum wall thickness requirements was confirmed.
(Paragraph 6 of Details)
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E.
Excessive vibration was observed during initial testing o'f the emergency diesel generators.
(Paragraph 8 of Details)
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F.
The testing of the high efficiency particulate air (HEPA) and
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charcoal filters will be performed by an organization under contract
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to the ventilation contractor. The testing procedures, however, have been avamined and approved by SMUD.
(Paragraph 12.c of Details)
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Strontium-90 concentrations in some environmental sample's have decreased from the initial values detected by the licensee over a year ago.
(Paragraph 12.d of Details)
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The structural and leakage rate tests of the containment vessel have been satisfactorily completed.
(Paragraph 11 of Details)
Management Interviev
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The inspectors met with the following personnel on January 16, 1974 to discuss the scope and findings of the inspection. In addition, the
inspector discussed with Mr. Raasch on February 12, 1974 the findings related to the performance of the containment tests.
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Sacramento Municipal Utility District
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D. Raasch, Manager, Generation Engineering
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R. Rodriquez, Manager, Nuclear Operations R. Colombo. Technical Assistant R. Miller, Chemical and Radiation Protection Supervisor
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J. Hiltz, Resident Engineer D. Whitney, Plant Nuclear Engineer L. Schwieger, QA Director
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J. Sullivan, QA Engineer J. Jewett, QA Engineer
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W. Stinchfield, Project Manager
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W. Miller, Project Field Engineer W. Chapla, Project QA Engineer The licensee made the following commitments:
A.
Energency Core Coolina - The procedures for testing the high pressure
injection system will be revised to include items considered by Regulatory Operations as being necessary to provide an adequate i
preoperational test of the system.
(Paragraph 4 of Details)
B.
Process Radiation Monitors - The need for inplace testing of
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process monitors will be evaluated.
(Paragraph 12.b)
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REPORT DETAILS 1.
Persons Contacted Sacramento Municipal Utility District (SMUD)
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1. Rodriquez, Manager, Nuclear Operations R. Colombo, Technical Assistant
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D. Whitney, Plant Nuclear Engineer L. Schwieger, QA Director R. Miller, Chemical and Radiation Protection Engineer D. Martin, Plant Health Physicist J. Hiltz, Resident Engineer G. Drew, Civil Engineer
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J. Sullivan, QA Engineer
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J. Jewett, QA Engineer G. Coward, Mechanical Engineer F. Kellie, Senior Chemical and Radiation Protection Assistant L. Bell, Senior Chemical and Radiation Protection Assistant Bechtel W. Chapla, Project QA Engineer P. Graham, QA Clerk 7.. Blackburn, QA Clerk R. Dundas. Integrated Leakage Rate Test Director W. Kooy, ILRT-Coordinator W. Enmon, Startup Engineer J. Williams, Senior Mechanical Engineer R. Daniels, Associate Electrical Engineer L. Moon, Project Civil Engineer
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Babcock and Wilcox Company (B&W)
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J. Kennedy, Site Operations Manager A. Brown, Electronics Engineer
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e Wiss Janney. Elstner and Associates
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W. Waddington, Test Engineer R. Krause, Test Engineer *
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Status of Construction
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i Construction activities appeared to be on schedule.
Project construc-tion was estimated to be approximately 96% complete.
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Status of Preoperational Test Program
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Informhtion contained in the licensee's test program status reports indicated that the test program was essentially on schedule. The containment leakage rate test was initiated on the scheduled date of February 1, 1974. Hoc functional testing was expected to begin on February 25, 1974. Barring unforeseen delays, fuel loading was anticipated to begin during May 1974.
4.
Riah Pressure Emergency Core cooling System
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The inspector found during the previous inspection that the proca-dures to be used to test the high pressure emergency core cooling system failed to include checks considered necessary by Regulatory Operations to provide for adequate testing of the systems. (See R0 Report No. 50-312/73-07, paragraph 5.)' During this inspection, the licensee representatives stated that as a result of their reevalua-tion, the procedures were being ravised to include provisions to:
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Determine movements of the high pressure injection system a.
piping and the adequacy of the supports under system startup
and steady state operating conditions.
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Determine response speed of all motor operated valves required
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to open within ten seconds for proper operation of the system.
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Demonstrate the ability to inject water through system lines c.
into the reactor vessel at normal reactor operating pressure and temperature. However, since the more conservative test of i
the system was considered to be dependant upon differential pressura at each valve and flow rate, the acceptance test for the high pressure injection system has been defined at the 600 psig and 500 spa conditions and will remain unchanged.
5.
Preoperational Test Procedures and Results e
The inspector armnined the procedures and results related to the
preoperational testing of the reactor coolant pumps and the decay
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heat removal system which also serves as the low pressure injection system for emergency core cooling.
a.
Reactor Coolant Pumps The reactor coolant pump initial operation test verified
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proper installation and monitoring of. the pumps and motors and
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demonstrated that the pumps were ready for cperation. The tests for each motor and pump included measurement of speed i
and vibration, starting current and voltage and the operability of the associated alarms, trips and interlocks Test data were obtained under both load and no load conditions. No deficiencies
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were observed by the inspector.
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Decay Heat Removal System
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The recorded data related to the operating performance of the decay heat removal system was incomplete pending hot func-
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tional testing. The data available was found to be consistent with the prescribed acceptance criteria.
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Status of Preoperational Test Procedures l
The preoperational test procedure files were examined to ascertain the status of approval of the tests. All the
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Category I procedures.and approximately 90% of th,e Category II and III procedures were examined. Six of the Category I, seven of the Category II and three of the Category III proce-
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dures had not undergone the complete process of review and approval. The procedures were found to have a status consis-tent with the development of the testing program.
6.
Valve Wall Thickness Measurements i
The information provided in the licensee's letter to RO:V in reply to Regulatory Operation's request to verify that important valves jest minimum wall thickness was confirmed. The records at the i
construction site were reviewed. They indicated that an valves
either met minimum wan requirements, had been reworked to meet minimum van requirements by depositing weld material or accepted
"as is" by the engineering review process.
One of the valves originally installed was replaced because it had been overtorqued during closing..The replacement valve was veri-fied to have met minimum van thickness values.
7.
Nonconforming Material Reports
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The nonconformance report (NCR) log for the period November 14
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written. NCRs that involved the primary system and other important components were examined. Both the log and the NCRs were being processed in accordance with the appropriate QA procedures.
8.
Emergency Diesel Generator The documentation for the instanation of the emergency engine
generators was examined.
It was noted that during the startup test, both the "A" and "B" generators experienced excess vibration.
The "A" generator experienced the most vibration. NCRs were initiated and the factory representative notified. The bearings and diaphragm plates were found defective and were replaced. The supports were i
also strengthened. The generators were again tested and the vibra-
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tions measured and found to be within acceptable levels (maximum 4.0 mils - acceptable 10.0 mils).
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9.
Cold Hydrostatic Test of the Primary System
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i The data package for the conduct of the primary system hydrostatic test was examined. The package was undergoing the review process for final acceptance. The documents included in the package were the procedure approvs1 record, procedure checklist, weld inspection (leakage) documentat).on, chemistry of water, piping diagrams of all systems involved, amounts of leakage during the test, valve line up and realign records, list of changes to the procedure and the associated approvals, nonconforming reports, calibration records for the pressure gauges, pressure charts, temperature and pressure logs, calibration of temperature gauges, log of events and the record for final approval.
It was noted that code inspectors approved the hydrotest af ter viewing all welds in the system during the leak rate part of the test.
10.
Inservice Inspection
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i Base line data ollection was 'being conducted during the inspection.
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Three ultrasonic test (UT) procedures were reviewed. These proca-dures were purported to be consistent with the other UT procedures used for the base line testing. The three procedures were found to
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j be consistent with ASME Section XI requirements.
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l The base line investigation was nearly completed. The report of the findings of the investigation will be published approximately April 1, 1974. At that time, RO:V will review the results.
11. Containment Testing
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The inspectors avamined, or observed, the following items related to the structural and integrated leakage ra.te testing of the contain-
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ment vessel.
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Detailed procedures and changes thereto
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Installed instrumentation
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e Calibration records of pressure, temperature, humidity,
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flow rate and deflection measuring devices d.
Records of concrete cracking
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Leakage rate data at 30 and 59 psig (Pt and Pa)
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Records of containment deflection data
Recording of deflection data at 30, 68 and 59 psig (data taken at 5 psig intervals up to 68 psig)
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Recording of leakage rate and verification test data at 30
psig and leakage rate data at 59 psig
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Selected locations of concrete and the related maps of cracking at pressure levels of 0, 30, 68 and 62 psig. Changes in
concrete cracks were mapped at pressure levels of 0,15, 30.. 45, 60 and 68 psig-
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Test coordinator's log i
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-1-The leakage rate test, structural deflection, and concrete cracking data were all found to be within the prescribed acceptance criteria.
No defects in the containment system were identified during the sequence of testing. The inspectors observed, however, that the contairment purge valves were manually closed for the test. Upon receipt of the valve operators, the licensee plans to demonstrate proper valve operation and integrity by performing approved local leakage rate tests.
In addition, several isolation valves were being modified to eliminate crud traps. Upon completion of the approved modifications, the effected valves were to be checked for leakage using the approved local leakage rate test procedures.
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12. Radiological and Environmental Protection
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Procedures
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The test procedure for the radiation monitoring systems was avamined. The procedure had received the required approvals on March 1, 1973. The procedare covered the following topics:
purpose, references, limitations and precautions, the required plant status, prerequisite system conditions, test method, l
data required, acceptance criteria and the detailed test procedure with provision for recording results or data. The
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i test coordinator had been assigned, however, only one instrument j
had been tested to date.
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A surveillance procedure for the routine operational testing and calibration of the radiation monitoring instruments (process monitors, area monitors and emergency portable radiation
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survey instruments) was also examined. The procedure received its final required approval on March 28, 1973. The procedure
~covers the weekly and monthly routine checks and the quarterly and annual calibrations to be performed after reactor startup.
The procedure consists of the following topical items: purpose,
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references, limits and precautions, surveillance procedures,
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and acceptance criteria. Forms for the data records have been i
made a part of the procedure. The licensee stated that the
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I area monitors have been declared operational and that part of the surveillance procedura pertaining to them has been placed in effect.
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b.
Radiation Monitoring Systems
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The radiation monitoring. systems have been purchased from
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Victorean Instrument Company. SMUD received a copy of the calibration procedures to be used for these systems on April 30,
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1971. During the week of May 10, 1971 three SMUD employees visited the Victoreen plant to observe the calibration of some of the instruments.. The SMUD employees randomly selected three liquid and three gas process monitors to be calibrated
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in their presence. A report of the SMUD trip to Victoreen was prepared and submitted to management. By letter dated August 17, 1971 Victoreen submitted the final test report for the radiation.
monitoring systems to SMUD. SMUD has received some of the calibration data and according to the licensee, the remainder will be received in the near future. The test report showed that the following calibrationa were performed.
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Gas detectors
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Krypton-85 and xenon-133 gases and cesium-137 point source
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Particulate detectors chlorine-36, strontium-yttrium-90, technetium-99 and iodine-129 filter paper sources Liquid detectors Cobalt-60 and cesium-137 solutions and cesium-137 point sources High energy liquid Cobsit-56 solution and radium detector point source According to the licensee, a decision has not been made regarding the need for inplant calibration of the process monitors prior
to initial loading of the fuel.
c.
Filter Testing The high efficiency particulate air (HEPA) and charcoal filters will be tested by Nuclear Containment Systems, Inc. under a contract with the ventilation systems contractor. A descrip-tion of the specifications for inplace testing of these filters and frames was presented to SMUD for review and comment. The EEPA filtera will be tested using an aerosol of dioctyl phtalate (DOP) and must have a minimum removal efficiency of 99.95 per cent. The charcoal filters shall be tested with Refrigerant II and in accordance with proposed standard ANSI N45-8.3, " Testing of Nuclear Air Cleaning Systems",
d.
Environmental Monitoring Program The inspection included an avamination of the analyses for
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milk and fish samples collected during the first three quarters
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of 1973. There was a drop in the concentration of strontium-
90 in the flesh of fish caught in the SMUD reservoir from 1767 picoeuries per kilogram in the first quarter to 405 picoeuries per kilogram in the second quarter. The licensee attributed this drop to the diluting effect cause by filling the reservoir.
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Fish flesh from catches at Comanche Reservoir, collected at
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the same time, showed 540-830 picoeuries per kilogram. The
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strontium-90 concentration in the milk from a cow pa',tured on
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the northeast corner of the site varied bet, en 2.0 and 6.3 picoeuries per gram of calcium. Earlier milk samp*es from this source had shown concentrations up to 10.6 picocuries per gram of calcium.
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