IR 05000312/1973003
| ML19317F997 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 06/15/1973 |
| From: | Albert W, Andrea Johnson, Spencer G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML19317F950 | List: |
| References | |
| 50-312-73-03, 50-312-73-3, NUDOCS 8002210698 | |
| Download: ML19317F997 (8) | |
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U. S. ATC".!C ENE?.GY CO:SiI
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DIFICTOEATE OF FIGULATORY OPERATIONS
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REGION V
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R0 Inspection Report No.
050-0312/73-03
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[ Licensee:
Sacramento Municipal Utility District Docket No. 050-0312
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l Sacramento, California License No.(s) CPPR-5'
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Facility:
Rancho Seco Unie No.1 Category n
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14 cation:
Clay Station. Sacrarento County. Calif.
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Type of Facility:
PUR, E&W 913 Mwe (2772) Mut
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Type of Inspection: Routine, unannounced
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Dates of Inspection:
riay 30-31,1973 Dates of Previous Inspection:
March 15,'16, 19 and 20, 1973
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Principal Inspector:
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A. D. Johnson, f.e. actor inspector
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(Date)
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J Accompanying Inspectors:
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W. G.
ert, Reacto/ Inspector (Date)
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(Date)
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Other Accompanying Personnel: None J
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Reviewed by:
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S', SpencM, Chief, Reactor Constructiod (Date)'
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and Ope::ations Branch
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SUMMARY OF Fir. DINGS
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Enforcement Action
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Licensee Action on Previousiv Identified Enforcement Itees None required for activities related to preoperational test program.
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Unusual Occurrences
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None
t Design Changes
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f None examined
/j Other Significant Findines
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Current Findings A.
The containment leakage rate test procedure was found to be consistent with the previsions of the Final Safety. Analysis Report (FSAR) and 10CFR50 Appendix J.
(Item 6 of Details)
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B.
Procedures available for combating emergency conditions or significant events appear to be generally consistent with the recommendations provided in ANS 3.2 and AEC Safety Guide No. 33.
(Item 8 of Details)
C.
The status of development and approval of test procedures appeared to
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be consistent with the status of construction activities.
(Item 2 i
of Details)
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Corrective measures have been initiated to increase the reliability of the meteorological data collection system.
(Item 7 of Details)
E.
Corrective measures have been initiated as suggested by the vendor to assure proper performance of the scram breakers.
(Item 4 of Details)
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F.
Several personnel changes have occurred within the licensee's QA group.
(Item 5 of Details)
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Status of Previousiv Reported Unresolved Items
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A.
The QA group serves as the final check to assure all sections of a
procedure have been appropriately reviewed and approved by other required parties prior to release of the procedure for implementation.
(Item 3 of Details)
thnagement Interview
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The inspectors met with the following personnel at the conclusion of the inspection and discussed the scope and findings of the inspection contained
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in this report.
D. Raasch
- Project Engineer R. Rodriguez
- Plant Superintendent R. Colombo
- Technical Assistant P. Dubre J. McColligan
- Assistant Superintendent, Nuclear Plant Operations
- Assistant Superintendent, Technical Support W. Friedrich
- QA Engineer J. Jewett
- QA Engineer The licensee's comments were as follows:
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A.,
Containment Leakace Rate Test - the licensee indicated that the prescribed minimum time duration would be reflected in the test procedure.
In addition the test sequence was considered by the licensee to be the most appropriate.
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The inspector indicated that the technical support personnel in the Directorate of Regulatory Operations, H;2dquarters would examine the proposed sequence to determine its acceptatility.
(Icem 6 of Details)
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Meteorological Data Collection Svstem - the proposed changes to the system.
were believed by the licensee to be adequate to assure the desired reliability factor.
(Item 7 of Details)
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REPORT DETAILS
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Persons Contacted
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D. Raasch
- Project Engineer" 1. Rodriguez
- Plant Superintendent W. Friedrich
- Quality Assurance Engineer
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J. Jewett
- Quality Assurance Engineer R. Colombo
- Technical Assistant j
1. Oubre
- Assistant Superinten. dent, Nuclear Plant Operations 5. Farrington
- Plant Instrument and Control Engineer-J. McColligan
- Assistant Superintendent, Technical Support L. Keilman
- Mechanical Engineer D. Whitney
- Plant Nuclear Engineer V. Pritchett
- Nuclear Service Engineer, B&W 2.
Stat'us 'of Preoperational Test Program s.
Summary
From discussions with the. licensee and examination of records and schedules, the status of the preoperational test program was determined to be as follows.
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March 1973 May 1973
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Total Tests Scheduled 114 114 Procedures Prepared & Approved
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Tests Underway
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Tests Performed
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Test Results Evaluated & Approved
4 The above listing does not include low power or power ascension tests nor does it include all tests of the ventilati'on system or system vibration which are still to be fully defined.
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(See d. below)
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Tests Underway The following tests were in progress at the time of the inspection.
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255-1 Compressed Air System Functional
277-1 Acid & Caustic _ System Functional 350-1 Plant Computer Field Verification
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350-7 Conputer Input - Output Verification
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360-1 Radiation Monitoring System
400-5 Station Battery & Chargers,
400-8 Heat Tracing Systems Functional
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Tests Performed
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According to the licensee, the test 400-2 Interlock Test of 6-9 KV i
Switchgear and the 204-2 RB Spray System Dry Pipe Test have been completed. However, the evaluation of the test results had not
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been completed.
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Test Procedure Development
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The licensee's representatives stated that criteria had been prepared for ventilation system tests and that draft procedures were under review. Criteria for testing vibration characteristics of major
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piping systems have been draf ted by the A-E in conjunction with
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the NSSS supplier. The tests to be performed included measurements of vibration and ther=al motion during hot functional testing and
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3.
Action on Previous Item of Understanding
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The licensee's representative stated that procedures were no longer being
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submitted for approval by the Quality Assurance organization unless all sections of the procedure are complete.
4.
Special Items
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Scram Breakers
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Experience at other similar nuclear power plants related to failure of under-voltage trip coils in breaketa required to function to trip the reactor was discussed with the licensee representatives.
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The inspector examined documents that indicated the coils in
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question (both AC and DC) were scheduled for replacement with better
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' quality coils.
In addition the circuitry was scheduled to be modified by the addition of appropriately sized fuzes to provide
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additional protection..As an additional precaution, the licensee
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indicated the spring tension valves of the new undervoltage devices will be checked to assure that the vendor sectings nave remained within the prescribed values.
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Personnel Changes
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According to the licensee representative, the Quality Assurance Director.
Mr. V. McMahon terminated his e= ploy =ent with SMUD during April 1973.
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In addition Mr. W. Friedrich had tendered his resignation and planned to leave SMUD on June 8, 1973.
Mr. J J. Jewett joined the SMUD QA group during April. Mr. Jewett indicated that he had approxi=ately 10 years related experience from his previous positions within the QA Department at Aerojet.
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Containment Leakage Rate Test Procedure Examination of the licensee's proposed procedure to measure the leakage rate of the containment building indicated that the procedure was consistent with the provisions of 10CFR50 Appendix J and the requirement contained' in the FSAR. However it was noted that the six hour minimum time duration specified in tre test criteria was not written into the detailed test procedure and th2refore could be overlooked and negate some test results. The licensee stated that the minimum time period had purposely been omitted pending agreement by all parties that six hours would be an appropriate period. Now that it has been accepted by the Directorate of Reactor Licensing the time period requirement will be added to the detailed procedure, according to the licensee.
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The inspector also noted that the following proposed structural integrity and leakage rate test sequence differed from the sequence recently
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determined to be acceptable to Regulatory Operations.
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Integrated leakage rate test at the reduced pressure (30 psig) level.
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Structural test at 115% design (68 psig).
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An integrated leakage rate determination at the accident design pressure of 59 psig.
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The licensee was informed that the test sequence would be examined further by the technical support group in the Directorate of Regulatory Operations.
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Meteorological Data collection System
e In their response to a Directorate of Licensing letter dated May 9,1973, concerning erratic dats obtained from the meteorological dcta collection program in use at the site, the licensee outlined the past deficiencies of the program and steps being taken to improve the reliability. The
. inspector confirmed the information provided in the licensee's letter a
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-6-dated May 30, 1973 through discussions with licensee representatives responsible for =aintenance of the data collection equipment,
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examination of records showing results of routine surveillance and a recently issued (tiny 11, 1973) detailed surveillance procedure.
The new surveillance procedure provides for a daily check of equipment and evaluation of data being collected.
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Emergency Operation Procedures
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The procedures developed to provide guidance to operations personnel
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examined and discussed with the licensee representatives. The
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inspector found from a reading of several of the procedures that the
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scope, content and format of the procedures were consistent with the
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recommendations of ANS 3.2.
However. several procedures suggested l/
. by AEC Safety Guide No. 33 were absent. The licensee representative explained that the subjects of the missing individual procedures were
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considered to be adequately covered either by training, in the nor=al operating procedures, or site emergency plan. The subjects suggested by AEC Safety Guide No. 33 which were not covered by separate individual procedures, and the licens'ee's comments were as follows:
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Loss of Flux Indication - covered by operating procedures, training and
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limiting conditions of technical spec 1.fications.
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Condition Recuiring Use of Emergency Bor tion or Standby-Liouid Control System - Safety features operations procedures cover.this subject.
Expected Transients - Covered. by individual emergency procedures such
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as loss of primary coolant pump, reactor trip, turbine trip, etc.
Malfunction of Autematic Reactifity Control Systen - guidance given by training and operating procedures. The control system is switched to manual whenever malfunctions occur.
Malfunction of Pressure Control System - Covered by norral operating procedures.
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Emergency Shutdown - Actions would be the same as that covered by the
. reactor trip procedure.
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Plant Fires - Detailed actions included in site emergency plan.
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Acts of Nature - A procedure was under development to combat results of
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seismic events. However, due to the plant location, separate procedures have not been scheduled for development to cover tornadoes or flooding.
The site emergency plan provides general directions.
Abnormal Release of Radioactivity - Covered by emergency plan and procedures contained in the radiation control manual.
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