IR 05000312/1972005
| ML19319E147 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 12/19/1972 |
| From: | Albert W, Andrea Johnson, Spencer G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML19319E140 | List: |
| References | |
| 50-312-72-05, 50-312-72-5, NUDOCS 8003310666 | |
| Download: ML19319E147 (9) | |
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U. S. ATOMIC ENERGY COMMISSION DIRECTORATE OF REGtru\\ TORY OPERATIONS
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REGION V
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RO Inspection Report No.
050-0312/72-05 e
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- Licensee:
Sacramento Municipal Utility District Docket No. 050-0312 License No.(s) CPPR-56 Priority Facility:
Rancho Seco Category B
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Location:
Sacramento County, California
Type of Facility:
963 Mwe, PWR, B&W Type of Inspection:
Test and Startup, Routine-Unannounced O
Dates of Inspection: _ November 15-17, 1972 Dates of Previous Inspection:
September 13-15, 1972
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Principal Inspector:
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A. D. Johns 6n, Reactor Inspector
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Accocipanying Inspecto
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/4 /f 2-W. G. Albert, Reac' tor Inspector
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R. F. Fish, Radia tion Spec.
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Other Accompanying Personnel:
None
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l Reviewed by:
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G. S. SpeMer, Chief, Reactor Construction (Date)
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~'N and Operations Branch
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SUMMARY OF FINDINGS
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Enforcement Action
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No safety problems or violations'of Regulatory requirements were-
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Licensee Action on Previously Identified Enforetment Items None required for activities related to the licensee's preoperational
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test program.
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Unusual Occurre ies No unusual occurrences were identified during the course of the inspection.
Design Channes Design changes were not reviewed during this inspection.
Other Significant Findings 1.
The status of development and approval of test procedures appeared to be' consistent with the status of construction activities (Item 3 of
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. details).
2.
The selected procedures examined were found to contain the required provisions to demonstrate proper functioning of the particular systems as. described'in the Final Safety Analysis Report (Item 4 of details).
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Completed preoperational test results were being evaluated and docuraented in accordance with the licensee's program (Item 3 of details).
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4.
The licensee was continuing to obtain environmental samples to establish background ~ data (Item 5 o'f details).
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Management Interview
p The inspectors met with the following personnel at the conclusion of the
. inspection and discussed the scope and findings of the inspection as recorded in the details section of this report.
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D. Raasch.
Project Engineer
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R. Rodriguez Plant Superintendent
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V. McMahon'
Quality Assurance Director
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P..Oubre'
.-- Asst. Superintendent Nuclear Plant Operations
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'J..McColligan-Asst. Superintendent Technical Support
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R. Miller Chemical and Radiation Protection Engineer
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W.:Friedrich
-' Quality Assurance Engineer
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The licensee's comments were as follows:
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Test Procedure Changes ~-_ The licensee indicated that all plant or test changes affecting a given approved test procedure are incorporated into the. final' test procedure when the " working" copy is prepared by the Test Coordinator immediately prior to conducting a particular
' test (Item 4 of details).
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Environmental' Samples - The licensce~said they would continue to-
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evaluate the significance of the onsite samples tha'c showed higher.
strontium-90 concentrations than those from the surrounding areas (Item 5 -
of details).
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DETAILS i
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Persons Contacted R. Rodriguez Plant Superintendent
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R. Oubre'
Asst. Superintendent Nuclear Plant Operations
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J. McColligan Asst. Superintendent Technical Support
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e R. Colombo Technical Assistant
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f P. Spencer Shift Supervisor
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H. Runk-
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' Senior Control Room Operator
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S. C. Farrington - Instrument and Control Engineer V. McMahon
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Quality Assurance Director
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W. Friedrich-Quality Assurance Engineer-
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R. Miller Chemical and Radiation Protection Engineer
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D. Martin Plant Health Physicist
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L. Bell Senior Chemical and Radiation Protection Assistant
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D. Whitney Plant Engineer, Nuclear
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G. Kennedy.
Startup Test Engineer, B&W
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J. Brewer Cons'ultant, Westinghouse
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Status'of Construction and Preoperational Test Program Construction activities were estimated to be approximately 80%
complete.
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Based on1 discussions with the licensee representatives and an examination of schedules for performing the preoperational tests,
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the inspectors found the status of the program to be'as follows.
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Total Tests Scheduled
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Procedures Prepared and Approved-
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- Tests Performed-
Test Results Evaluated and Approved
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In addition to'the above, the licensee has requested the'A-E and the NSSS supplier to provide the scope of vibration, expansion and restraint
. tests to be performed on both the primary and secondary systems.
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The'preoperational' test program statistics do not. currently include
=the' tests to be conducted'on the ventilation' systems. These systems
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are to be tested-by'an independent: contractor whose procedures will
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be avamined and approved by the licensee.
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Preoperational' Test-Results The records.of test approvals, changes and completion of the preoperational
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tests for the startup transformers l'and 2, and the 4.16 kv and 480 volt i
switchgear interlocks were examined.by the. inspectors. The results of the
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tests'demoncerated that the systems satisfied the approved acceptance j
t criteria.; All results had been evaluated and approved by the responsible engineering personnel; however, not all of the results-had been approved
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-by all of the necessary' parties. Changes to the originally approved test procedures were examined and-found to have been evaluated and approved by the Plant Review Committee and the Plant Superintendent as
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required by the licensee's change procedures.. According to the licensee i-L representative, no discrepant items. were identified during the tests.
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~ Preoperational Test Procedures-
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i The selected preoperational test procedures listed below were examined
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in detail. The examinatior. included a comparison of the system drawings l'
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test'would be accomplished by the procedural steps. On tests
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for the Decay. Heat Removal, Reactor Building Spray, and Boric Acid.
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. Mixing.and Storage Systems, a visual examination of the physical plant was performed.to.the extent permitted by construction status. 'Also,
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~ he procedures were evaluated to determine whether the recorded test t
L results would demonstrate that the systems would p'erform as described.in j'
the pertinent *section of the Final Safety Analysis Report.
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'a.
' Boric' Acid Mixing and Storage System' Functional Test - Purpose:
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'(1) Verify the capability of the boric acid pumps -P-705A and, B
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to' supply'100 gym totalsflow to the makeup tank V-235.
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(2) Verify the capability of pumps P-705A and B'to supply flow
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to the high pressure injection pumps P-238A and B, the decay l
' heat removal pumps P-261A and B and the borated water storage tank T-250.-
(3) Verify the capability of the boric acid addition pump P-712
.i to. supply flow to-the core flooding tanks V'265A and B.
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(4) Verify the level alarm indication on concentrated boric acid
. storage tank T-704 and functional operation of the temperature p
instrumentation and controls on the boric acid mix tank T-703.
(5) Verify the capability to add chemicals to the makeup tank
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through the' tank primary chemical addition tank.
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b.
Makeup and Purification System Safety Features Actuation Test -
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Purpose:
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(1) Demonstrate emergency makeup injection flow to the reactor coolant system through each makeup pump.
(2)
y Verify that operating times of B & W supplied safety j
features actuation equipment are within the values
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given in the SNUD Rancho Seco Unit 1 FSAR, Section 6.
Reactor Building Spray System Dry Pipe Gas Flow Test - Purpose:
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(1) Determine that reactor building spray nozzles are free from obstruction.
,(2) Provide basis for periodic tests.
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Decay Heat Removal System Safety Features Actuation Test - Purpose:
(1) Demonstrate emergency injection flow capability to the reactor coolant system from 'the decay heat system.
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Reactor Internals Vent Valve Inspection Test - Purpose:
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(1). Demonstrate use of internals vent valve handling tool.
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l I-(2) Demonstrate ability to remove and replace internals vent
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valve remotely and to verify.the B&W evaluation related to the reactor internals vent valve removal and replacement.
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- 1 (3) Demonstrate use of internals vent valve exercise tool.
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(4) Demonstrate and determine accessibility requirements for
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l inspection of each. vent valve.
(5) Demonstrate and determine visibility requirements for i
inspection of each vent valve.
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(6) Determine the opening force and full open force for each
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valve.
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Reactor Coolant System Chemictry Test - Purpose:
(1) Establish proper water chemistry for the reactor coolant
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j system during initial system fill, pre-operational, and g
hot functional testing.
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(2) Establish necessary sampling frequency during these periods.
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I The inspectors observed during the examination of the above listed
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j procedures that, in several instances, prerequisite tests and drawings
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referenced in the procedures had been revised after approval of the
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-testa procedures. The licensee stated that the Test Coordinator has
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the specific responsibility to confirm that current documents are used when the " working" copy of the approved test procedure is prepared shortly before conducting a particular test. At that time, according
to the licensee, any changes to the systems noted on the drawings or interfacing systems will'be evaluated and appropriate procedural changes initiated and approved prior to performing the test.
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5.
Environmental Monitoring Program
'I An examination was made of the modifications to the environmental -
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monitoring program since the May 1971' inspection. The results of the analyses of'the samples collected through the second quarter of 1972 were also examined. The following is a summary of the findings
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of these' examinations.
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Particulate Air Sampling An onsite sampling station has been located near.the warehouse building.- Also new stations have been located at Camanche Reservoir and near Carbondale.
Sampling is now on a full time basis.- A licensee representative stated they were considering
. making the onsite air sample, shown in Tabic 2.8-1 of the FSAR, a movable loc.: tie:n rather than one specific station. Through June
_1972 the background beta-gaga conegnerations have been in the range of-506 tog.41X10 uC1/cm. Alpha concentrations up to
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0.7 x 10 uCi/cm have been detected.
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Water Samples-
- A new'well sampling station has been established at a corral site south of-the SMUD property. Also a second on11te well sample is
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now being obtained from the well near the reservoir. Through
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l, June 1972 the lake and reservoir samples hg e shown beta-gamma concentrations in the range 0.6 to 13 x 10 fi/mlandtritium concentrationsintherange0.22to1.gx10 uCi/ml. The ground wat.or results hge shown 1 to 22 x 10 uCi/ml for beta-gamma and 0.2 to 0.7 x 10- uCi/ml for tritium.
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Mud and Silt A routine sample is now being taken at Camanche Reservoir. The.
gross beta-gamma _gesults through June 1972, have been in the range
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of 18 to 74 x 10 uCi/g.,9 The strontium 90 results have been in the range 11 to 24 x 10 uCi/g.-
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Vegetation An additional dairy'(one family cow) feed sample has been added.
The location is near the SMUD property boundary adjacent to the onsite reservoir..A licensee's representative stated they were exper.iencing some difficulty in obtaining edible vegetation i
samples.
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Milk
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.A sa'mple from a one family cow has been includ'ed in the program.
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The location is adjacent to the onsite reservoir and near the SMUD property boundary. The analyses of the preserved milk samples, through June 1972,,pve shown tritium and strogtium-90 concentrations
. f 0.2 to 0.7-x 10 uci/mi and 1 to 10.6 x 10 o
uC1/g calcium, respectivaly.
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Fish
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Samples are now being ebtained quarterly from the onsite reservoir.
Samples of bottom and top feeding fish have been obtained from the Mokelumne River. A sample of top feeding fish has been obtained-from Pa==nche Reservoir and a bottom feeding sample will be obtained. The strongium 90 concentrations have been in the range of 230 to 4600 x 10 uCi/g'.
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Rabbits Quarterly samples are now being obtained from locations representing the north and south directions from the SMUD property.
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Soil The initial samples were obtained on 10/13/71. Samples have been collected semi-annually. The initial samples have been analyzed as well as a second sample from the southwest boundary fence. These analyges showed beta-gamma concentrations in the range of 34 to 45 x 10 uci/g and strontium 90 concentrations between 9 and 265 x 10~9uci/g.
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Background Radiation Dose
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An additional data collection site has been established at Carbondale. Also data is being collected at the farm near the
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onsite reservoir. According to a licensee representative this latter site will be changed to the building at the onsite reservoir in the future.
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Miscellaneous Samples Some algae samples have been obtained from the edge of the property where the plant _gffluent.and site run-off waters pass. The samples showed 130 x 10 uci/g of strontium-90. These samples were also analyzed for potassium-40 and scanned with a gamma spectrometer.
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Some thyroid samples have been obtained from cattle that were grazed on the SMUD property.
The licensee representative said the
. continued collection of these types of samples would depend upon
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whether the land was still being used for grazing cattle and the ability to schedule collections from the slaughterhouse.
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Tour of Facilities
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Tours of the site were made to obtain familiarization with the location and present construction status of the following systems: ' ventilation, i
l liqu1C sses treatment, gaseous waste treatment, solid waste treatment.
and other reactor Class I auxiliaries, l
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