IR 05000312/1974012
| ML19309A297 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 12/26/1974 |
| From: | Andrea Johnson, Malmros M, Spencer G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML19309A278 | List: |
| References | |
| 50-312-74-12, NUDOCS 8003270667 | |
| Download: ML19309A297 (8) | |
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. ATOMIC ENERGY. C010CSSION DIRECTORATE OF REGULATORY OPERATIONS
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REGION V
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RO Inspection Report No.
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Sacramento Municipal Utility District Docket No. 50-312
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l 6201S. Street,P.O. Box 15830 License No. DPR-54 Sacramento, California 95813-Prisrity B
Facility
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- ategory Rancho Seco
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Clay Station, California
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Location ( 1 PWR, B&W, 913 MWe (2772 MWt)
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Type of Facility
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Type of Inspection Routine, Unannounced i
Dates of Inspection December 2-4, 1974 Dates of Previous Ine/ection Oct. 10-11, Nov. 6, 7, 12, 1974
/2//v/77 Principal Inspector N khlr Q
e A. D. Johnson, Reactor Inspector /
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Accompanying Inspectors M D7 Mjhy[7f
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M. H. Malmros, Reactor Inspector Date
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Other Accompanying Personnel: None
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Reviewed by U"U" G.S.SpencerhChief,ReactorConstructionand Operations Branch
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8003270
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SIM4ARY OF FINDINGS
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Enforcement Actions Inspect'cr. planning using the Maintenance Inspection Data Report
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(MIDR) tc the performance of maintenance inspection on Class 1
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and selected Class 2 items had not been perfonned in accordance
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with the Quality Assurance Program.
(Paragraph 4^of Details)
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Stamps to indicate the acceptance status and to provide objective evidence that maintenance inspections were performed had not been issued to or used by the personnel performing maintenance inspection.
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(Paragraph 4 of Details)
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Maintenance QC inspections had been performed by personnel directly
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responsible for the work being inspected.
(Paragraph 4'of Details)
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Licensee Action on previously Identified Enforcement Items Enforcement items' identified in RO Inspection Report No. 50-312/74-09 related
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to Quality Assurance Program controls for the procurement and receipt
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of spare parts will be examined following receipt of the licensee's response to RO:V's description of violations sent to the licensee subsequent to the
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past inspection.
Abnormal Occurrences The circumstances and proposed corrective action for three abnormal occurrences with thirty' day reports still pending submission to the Comaission were examined. The occurrences involved the calibration of a primary system ressure transmitter and a speed switch on a diesel generator.
p(Paragraph 2 of Details)
In addition, the information submitted to the Commission in the licensee's reports nos. 74-7, 8 and 9 was confirmed.
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,O,ther Significant Findinos s
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Power ascension testing)had resumed at the 40% power plateau.
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(Paragraph-5ofDetails 2.
Administrative controls for plant operation have been satisfactorily implemented. (Paragraph 3ofDetails)
Management Interview The inspectors met with Messrs. J. Mattimoe, R. Rodriguez and L. Schweiger-
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.and other members of the licensee's staff at the conclusion of the inspection
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u on December 4, 1974. The results of the inspection, including items 1 n-s
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through 3 listed under Enforcement Action were discussed. The licensee stated that stamps had been issued to designated inspectors in response
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to Enforcement Action item 2.
No other specific comitments were made
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by the licensee.
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DETAILS _
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Persons Contacted
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Sacramento Municipal Utility District.
R. Rodriguez, Manager, Nuclear Operations P. Oubre', Assistant Plant. Superintendent, Operations J. McColligan, Assistant Plant Superintendent, Technical Support
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R. Colombo, Technical Assistant
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G. Al.biani, Administrative Assistant S. Anderson, Plant Nuclear Engineer
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G. Coward, Plant Mechanical Engineer D. Comstock, Shift Supervisor D. Martin, Health Physicist
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L. Bell, Senior Chemical & Radiation Assistant
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D. Cass, Maintenance Superintendent
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A. Locy, Electrical Foreman L. Schweiger, QA Director
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l J. Jewett, QA Engineer J. Sullivan, QA Engineer D
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Bechtel J. Kearns, Electrical Test Documment Control
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2.
Abnormal Occurrences Abnormal Occurrence Report Nos. 74-7, 8 and 9 submitted by the licensee as thirty day r'eports were reviewed and found consistent with the infomation previously documented in R0:V Inspection Report No. 50-312/74-09, paragraph 3.c(1) and (2). The licensee had re-evaluated the malfunction of a position indication readout of safety feature valve SFV 22009, and determined that the occurrence was not reportable to the Commission. The inspector concurred with the licensee.
(Reference R0:V Inspection Report No. 50-312/74-09, paragraph 3.c.(3).)
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The circumstances and proposed corrective action for abnormal occurrences with thirty day reports still pending submission to the Commission were raviewed and discussed with the licensee. The
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occurrences reviewed were as follows:
I Following a reactor trip on high reactor coolant system pressure a.
as a result of a loss of feedwater flow to the steam generators on 11/22/74, it was discovered that one of the high reactor
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coolant pressure trip channels'in the reactor protection system had failed to actuate.
Investigation revealed that.a pressure transmitter for the channel was.out of calibration by
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15 psig. The pressure transmitter was calibrated and the L-channel was tested to verify operation at the predetermined pressure trip setpoint.
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b.
During the inspection, the "A" diesel generator failed to start when tested on 12/3/74. The "B" diesel generator was j
immediately tested and satisfactory operation was verified.
Investigation revealed that a malfunction of-the. speed switch
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prevented the air start control circuit from actuating to provide startup air to the diesel. Repairs to correct this problem were estimated to take three days and the "B" diesel generator was to be tested daily until the "A" diesel was
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returned to service.
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c.
The results of the startup tests following major repairs to the motor driven auxiliary feed pump were reviewed. Two separate tests were conducted using Surveillance Procedure 210.01B, Rev. 6, with the resultant flows being 851.9 and 853.1 gallons per minute. The flow rate acceptance criterion is 840 gallons per minute.
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Plant Operations
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Station Logs Station logs, maintained in accordance with administrative procedure No. 23, Control Room Watchstanding, were found to be consistent with the requirements of ANSI N18.7, Administrative Control for Nuclear Power Plants. The Control Room Log, Shift Supervisor's Log and the Computer Hourly Data Log for October and November 1974 were examined and found to be consistent
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with Administrative Procedure No. 23. Minor discrepancies in log keeping, i.e., improper initialing and incomplete entrys, had been identified during a SMUD QA audit of plant operations
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on October 23-24, 1974. The inspector verified tnat the corrective action related to these deficiencies had been implemented. The log entriec following the date of the audit were without discrepancies.
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Special Orders Special Orders are prepared by the Assistant Plant Superintendent, Operations in accorde:ce with administrative procedure No. 24, Control of Special Orders. The Special Orders prepared during
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the period 9/11-11/22/74 (Nos. 26-41) were found to be consistent with the requirements of administrative procedure No. 23. The
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orders were consistent with the requirements of the technical
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specifications.
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Jumper (Bypass) Control
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Controls for the use of jumpers or bypasses are prescribed in administrative procedure No. 26, Abnormal Log Procedure. As of the date of the inspection, the use of abnormal tags and the abnormal tag log had not been implemented by SMUD personnel due to a delay in receiving the abnormal tags from the print'er.
Administrative control of jumpers and bypasses M s been retained by Bechtel for SMUD. An examination of the Be 3 tel system verified that the system used was a continuation of the jumper / bypass control system used during construction. A review of the
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issued abnormal tags indicated conformance with technical specification requirements.
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d.
Site Tour A tour of the plant, including controlled access areas in the auxiliary building, was conducted while the reactor was at 40%
power. No abnormal piping vibrations or fluid leaks were observed. General housekeeping was observed and found to be
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s consistent with safety and fire hazard considerations.
Proper position of safety feature valves in the high pressure infection system and the standby status of the diesel generators were Several clearance tags (danger verified by) direct observation.were examined on installed component and caution tour.and verified to.be properly installed through examination of control documentation maintained in the control room. The installation and approval signatures for clearance tags were consistent with administrative procedure No. 4, Tagging System.
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Discussions were held with the control room operator and the shift supervisor regarding safety related annunciators which indicated an alarm condith..
Both individuals were knowledgeable as to the cause and significance of the apparent alarm conditions.
4.
Maintenance Records of activities associated with maintenance af W following items'were examined by the inspector.
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Control rod drive mechanism vent Pressurizer code relief valve
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Auxiliary feedwater pump Seal water injection filter
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Vacuum relief valve in RWS
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Inverter circuitry Diesel generator control circuit High pressure injection pump Decay heat system check valve From the information in the records related to the ab6've maintenance items and through discussions with licensee representatives-the
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inspector verified the following.
Limiting conditions for operations of the reactor were met
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during the maintenance activities.
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The maintenance was performed in accordance with approved procedures.
Prior to returning the items to service, appropriate functional j
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tests were performed.
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Quality control records were available to appropriatelp show that the maintenance activities were properly performed, The maintenance work was performed by qualified personnel.
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During the examination of the maintenance activities the inspector found that the quality control inspections of the activities performed were conducted'by personnel using procedures other than those prescribed by the licensee's QA program as discussed'below.
The licensee's QA program provides that:
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The maintenance QC inspections are to be performed pursuant
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to inspection plans (MIDRs) prepared by the QA group in coordination with Nuclear Operations and Engineering and final approval by the QA Director (QAP No. 6).
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Inspectors are to stamp and date inspection and data reports in b.
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a partim I?r :aanner to provide uniform documentation of inspection
findings (QAP No. 16).
Inspectors are to be independent of any responsibility for c.
performing the work or action he will be insoccting (QAP No. 6).
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' At the time of the inspection the licensee's practices were:
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The maintenance personnel were formulating-and implementing inspection plans and procedures without the QA Director approvals.
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Qualified and approved inspectors were initialing and/or recording
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on the work procedures or on an inspection report form the activities verified by the inspectors.
c.
The electrical maintenance foreman directly responsible for work performed by the electrical maintenance crew was performing all of the eldctrical maintenance QC inspections. 'The mechanical maintenance inspections have been performed by a foreman other than the foreman assigned to accomplish a particular job. However, -
the organizational structure provides that both the foremen and journeymen administrative 1y work directly for the Maintenance Supervisor and therefore are all members of the same group.
The licensee representatives indicated that all future maintenance QC inspections will be performed in accordance with the requirements of the QA Program.
5.
Power Escalatien Program Power ascension tests at the 40% power p~ateau commenced on December 2, 1974. Preliminary tests at this level indicated'that the-power distribution, heat balance and NI calibration data corresponded -
with the acceptance criteria.
Testing with equilibrium xenon condition is scheduled for the next three weeks with a plant trip and transient tests scheduled to be performed at the end of this period.
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Nonconformance Reports
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Reports of nonconforming items dated between October 1 and December 3
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were examined by the inspector. 'The items were found to have been, or were in the process of being, dispositioned pursuant to the
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requirements of the licensee's QA program.
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7.
Primary Flow Coastdown Data The results of flow coastdown tests with three and four pump operation were slightly less than the B&W acceptance criteria. However. the values were shown to be consistent with those used in the Safety
Analysis Report.
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