IR 05000312/1973006
| ML19317G001 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 11/01/1973 |
| From: | Albert W, Andrea Johnson, Spencer G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML19317F957 | List: |
| References | |
| 50-312-73-06, 50-312-73-6, NUDOCS 8002210702 | |
| Download: ML19317G001 (9) | |
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U. S. ATC.'d.IC ENERGY CO:OtISSluN DIFICTOP.m 0F REGUIATORY OPERATIONS
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REGION V
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30 Inspection Report No.
50-312/73-06
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' Licensee:
Sacramento Municipal Utility District Docket No.
50-312 5acramento, California License No.(s).cppn_ce,
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Priority
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Pacility:
Rancho Seco Unit No. 1 Category B
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Imcition:
Clay Station, California
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Type of Facility:
913 Mwe (2772 Mwt)
Type of Inspection:
Routine, Unannounced Dates of Inspection:
October 16-18, 1973 Dates of Previous Inspection:
August 27-29. 1973 P
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Principa1 Inspector:
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v A. D. Joldtso6 Reactor Inspector
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Accompanying Inspectors:
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3-W. G. '- bert, Reactor Inspector'
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L. J. Garvin, Reactor Inspector
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g Other Accompanying Personnel: R. F. fish, Specialist Radiation
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None
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Eaviewed by,:
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G.S.:Speher, Chief,ReactorConstruction (Date)
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and Operations Branch
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SUMMARY OF FINDINGS
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Enforcement Action
None
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Licensee Action on Previously Identified Enforcement Items
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~Information contained in the licensee's records confirmed that the corrective actions taken on the enforcement items identified during the previous construction inspection-were as described in the licensee's letter to the Director of Region V, Directorate of Regulatory Operations, dated August 28, 1973.
- Unusual occurrences None Design Changes None armniried.
Other Significant Findings Current Findings
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m A.
ITT, Barton Process Instrument and Controls, notified the licensee by letter dated October 9, 1973 that all D/P transmitters supplied for the Rancho Seco plant were from prodt.ction groups after June 1971, and therefore not subject to the identified generic problem of the inadequate epoxy mixture used for bonding the strain gauge to the cantilever beam.
(R0 Report No. 50-312/73-05, paragraph 4)
B.
The SMUD Quality Assurance Director position was filled on October 2, 1973, by Mr. L. G. Schwieger, formerly a Supervisory Engineer of Quality Assurance for the Northern States Power Company.
(Paragraph
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12 of.Datails)
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C.
The primary coolant system hydrostatic test has been scheduled to begin ou December 7,1973.
D.
The proc:.se and area radiation monitors have been installed and the testing of the units had been initiated.
(Paragraph 6 of Details)
E.
Construction activities were estimated to be 93% complete.
F.
The action taken by the licensee concerning items of uaderstanding identified in RO Report No. 50-312/73-04 were verified.
(Paragraph 9 of Details)
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Management Interview The inspectors met with the following personnel at the conclusion of the inspection on October 18, 1973.
Sacramento Municipal Utility District e
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'J. Mattimoe, Chief Engineer D. Raasch, Project Engineer R. Rodriquez, Plant Superintendent L. Schwieger, QA Director
R. Miller, Chemical and Radiation Protection Supervisor R. Colombo, Technical Assistant
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J. Hilz, Resident Engineer Bechtel i
W. Stinchfield, Project Manager L. Brown, Project Engineer T. Greer, Manager of Power Projects J. Bashosa, Assistant Project Manager After a discussion of the 1, cope and findings of the inspection, the licensee was informed that no violations of Regulatory requirements were identified within the areas of activity examined by the inspectors. The licensee stated that the instructions governing use of the nonconformance report to assure completion of construction items before turnover to the startup s
. group will be examined and clarified as necessary. (Paragraph 10 of Details)
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REPORT DETAILS 1.
Persons Contacted
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Sacramento Municipal Utility District
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R. Rodriguez, Plant Superintendent R. Oubre', Asst. Superintendent, Nuclear Plant Operations J. McColligan, Asst. Superintendent, Technical Support.
R. Colombo, Technical Assistant L. Schwieger, QA Director J. Jewett, QA Engineer R. Dietrich, Nuclear Engineer
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D. Whitney, Plant Nuclear Engineer J. Haratyk, Plant Electrical Engineer J. Kearns, Electrical Technician G. Coward, Mechanical Engineer R. Miller, Chemical and Radiation Protection Engineer D. Martin, Plant Health Physicist F. Kellie, Senior Chemical and Radiation Protection Assistant Bechtel
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W. Chapla, Project QA Engineer
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M. Jones, Electrical Inspector
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D. Madden, Electrical Field Engineer A. Stenersen, QA Engineer R. Andresen, QA Engineer
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2.
Status of Preoperational Test Program From discussions with the licensee and the examination of records and schedules, the statue of the preoperatianal test program was determined to be as follows:
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May 1973 October 1973
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Total tests scheduled 114 114 Procedures approved
92 Tests underway
22 Test results approved
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Significant Tests Underway
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-Core Flooding System Functional Test The major portion of this test will now be conducted in the " hot functional" phase of testing because of a major change in test procedure. This change resulted from the decision by the NSSS supplier (B&W) to use the pressurizer in a steam mode for the test rather than pressurizing the system with nitrogen. Changes in this Clacs I test were examined and discussed with*the licensee's representatives. No exceptions were noted by the inspectors.
b.
Nuclear Service Cooling Water System Functional Test Tast has been held up by a delay in the delivery of two valves required to complete construction.
c.
,0ther Class I System Test
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No significant problems have been encountered with the following tests in progress.-
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Makeup and purification system functional test.
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. ERD control system pre-op calibration.
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Safety Features Actuation System (3FAS) pre-op calibration.
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Decay heat system functional test.
4.
Test Results and Procedures a.
Reactor Coolant System Hydrostatic Test The procedure to be used during the performance of the reactor coolant system hydro test had been reviewed and approved in
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accordance with the licensee's QA program. The inspector verified fr'on an evamination of the pro'cedure that appropriate reference materials were listed; prerequisite tests were identified; test equipment was prescribed; limitations and precautions were defined; the plant status and system conditions were delineated; the test
. method, data required and acceptance criteria were stipulated.
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The. test procedure also provided a detailed stepwise sequence to
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folitar during performance of the test to assure that the test results would demonstrate that the system test and examination conformed to the applicable code requirements. No deficiencies
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.were identified by the inspector.
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Compressed Air System Functional Test The procedure and test data of the compressed air system functional test were examined by the inspector. The test data verified proper functioning of the system controls and operating characteristics with the exception of capacity. The purchase specifications prescribed a 300 SCFM compressor capacity. The capacities of the three units were recorded to be as follows:
Unit Capacity - SCFM -
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A 275 B
280 C
278
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The less-than-rated capacities had been evaluated in accordance with the QA program nonconformance procedure.
Since the unit capacities involve no safety implications and the economic penalty was considered minor, the lower-than-specified capacity was dis-positioned by " accept as is".
The test results had been reviewed and approved pursuant to the licensee's QA program requirements.
No deficiencies were identified by the inspector.
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Flash Tank System
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The procedure and results of the flash tank sys' tem functional
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is the automatic mode was acceptable and in conformance with the design acceptance criteria. The system pressure, temperature and level controls were found to operate as designed and the system-performance under maximum-flow was demonstrated. The test results had been reviewed and approved in accordance with the licensee!s QA program requirements.
No deficiencies were identified by the inspector.
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d.
Reactor Coolant System Drain Tank and Pump Functional Test The procedure and results of the reactor coolant system drain tank and pump functional test were examined by the inspector. The test
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. purpose was to verify the system instrumentation control and alarm functions, system flow rates and operating currents of the pumps.
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l The test data confirmed that-the system performed in conformance
with the established acceptance criteria. The test results had been approved in accordance withythe licensee's QA program require-j
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Control of Electrical Jumpers and Lifts
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i The system for controlling jumpers and lif ts during tests of electrical i
components was ayamined. The log, files and drawing records of these i
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" abnormalities" were evamined. The audit was performed by comparing i
los to drawings, log to file, drawings to file, field tags to file and field tags to log. No deviations vers noted. The system appeared to be effective in controlling the use of jumpers and lif ts required for the conduct of testing of electrical components.
6.
Radiation Process and Area Monitors i
i The inspector confirmed that the process and area monitors, identified in Section 11.3 of the FSAR, had been installed. The stack sampling i
locations for the auxiliary building and reactor building purge exhausts were in the process of being changed from near the bottom of the stack
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to a higher position. The test procedures for the radiation monitoring system had been approved and the testing initiated.,
7.
Radiation and Emergency Procedures
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The Site Emergency Procedures and Radiation Safety Manuals were almost complete. The last few additions to these manuals were ex-pected to be finalized in the next 4-6 weeks. Copies of these manuals will be supplied to Region V, Directorate of Regulatory Operations, when they have been completed. The licensee stated that the Rancho
Seco site would be. involved in a November 1973 test of the AEC
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radiological assistance program. The test will include the visit of a. radiological assistance team to the site and telephone contacts with the State of California and local agencies involved in an.
emergency radiological situation. The licensee also stated that they were planning a test of the site emergency procedures prior to (late April:or early May 1974) the loading of nuclear fuel into the reactor.
'8.
'Possible Unmonitored Releases Off Site By letter dated September 17, 1973, the licensee informed the Directorate of Licensing.that an evaluation of the possible overflow of tanks containing radioactive liquids with a subsequent release offsite
.had been made.. The licensee concluded there was a low probability
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'of overflow and no offsite contamination would occur. This inspection
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disclosed that only one of the tanks in the yard that will contain radioactive-liquids had any real potential for overflowing into the yard. All drains within the fenced '(aontrolled) area flow to the discharge structure. All waste leaving the discharge structure is monitored for gross-radioactive content.
Since this monitor does not measure tritium, the licensee stated that regular grab samples of the site affluent will be obtained and analyzed.
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9.
Licensee ktion on Previous Items of Understanding Related to Construction a.
Primary Coolant Pumps The assembly records for the reactor coolant pumps were examined.
The installation records had beca updated and all unfinished items had been referenced on the " punch list" NCR.
(R0 Report No.
50-312/73-04)
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Control Rod Drive Pressure Tubes
' cumentation relating to the rerating of the contrcl rod drive
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fressure tubes was examined. No anomalies were noted.
(R0 Aaport No. 50-312/73-04)
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10.
Electrical Equipment The records for the installation of the emergency engine generators were avamined. These records included the Construction Inspection Data Reports (CIDR), and Non Conformance Reports (UCR). The CIDR's had been-stamped as. completed, but the last steps in the construction sequence (lubricating, aligning, etc.) had NCR numbers referenced
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in the remarks column. The referenced NCR's stated that these steps
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had not been completed.
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Af ter discussion with Bechtel startup and QA personnel and examination of the Quality Control Instructions'(QCI), the inspector learned that j
the method of turning systems over to the startup group involved using an NCR as a means of assuring that all construction activities had been completed ~ before testing occurred.
One NCR for each system docu-ments all activities needed to be completed at the time of turnover.
These NCR's are in practice used as a " punch list".
The QCI's governing use of the CIDR's and NCR's were unclear as to whether reference to an NCR closed a CIDR or whether the CIDR should
be stamped as complete 'after ' completion of the referented NCR's.
The licensee stated the instructions would be changed to assure consistency in.the use of the control forms.
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Instrumentation a.
Record Review The records for the installa'io'~of the instrumentation associated t n with the reactor coolant flow trip, pressurizer level. control and the'high pressure injection system were examined. These records included receiving reports, cable pulled and termination
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reports for all circuits, welding reports on tubing, isometric drawings, weld electrode issue records, panel installation re-ports and instrument calibration reports. No anomalies were noted,
b.
Observation of Work The instrument systems involved in the record review were in-spected. No anomalies were noted in the field installation of these systems.
12. Personnel Changes Effective October 2, 1973, Mr. Leander G. Schwieger assumed the Quality Assurance Director position. Prior to joinin5 the SMUD-organization, Mr. Schwieger held the position of Supervisory Engineer of Quality Assurance with the Northern States Power Company. From
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1950 to the present time, Mr. Schwieger's experience has included:
1) quality assurance activities related to construction and opera-tion of nuclear power plants, 2) design and research as a specialist in the areas of nondestructive testing and 3) design and development of instrument and control systems.
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