IR 05000312/1975001
| ML19319D828 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 02/07/1975 |
| From: | Book H, Malmros M, Spencer G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML19319D819 | List: |
| References | |
| 50-312-75-01, 50-312-75-1, NUDOCS 8003250818 | |
| Download: ML19319D828 (7) | |
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U. S. NUCLEAR REGULATORY COMMISSION
'. *0FFIt. OF INSPECTION AND ENFORCEMENT
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REGION V
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(IE Inspection Report No.
050-0312/75-01 l
Licensee sacramento Municipal Utility District Docket No. 050-0312
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6201 S. Street, P. O. Box 15830 License No.nPR 54
Sacramento, California 94813'
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i Facility Rancho Seco Category B
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Location Clay Station, California Type of Facility PWR, B&W, 913 MWe (2772 MWt)
Routine, Announced and Unannounced Type of Inspection
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Dates of Inspection December 27. 1974 and January 14-17, 24, 1975 Dates of Previous Inspection December 2-4, 1974 c2[g/Jf Principal Inspector fN
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M. H. Malmros, Reactor Inspector (1/15-17,
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24/75)
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Accompanying Inspectors,'/' l' !
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A. D. Johnson, Reactor Inspl ecto Q /15-1 f
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,Manctor Inspector (12/Z///4) / D/te
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Other Accompanying Personnel:
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Rei ved by A
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Date G. S. Spencir, Chief, Reactor Testing and Operations Bra 9ch
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G-Rf 7f 7I Reviewed b_y e
H. E. Book, Chief, Radiological and Date Environmental Protection. Branch
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SUMMARY OF FINDINGS
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Enforcement Action None Licensee Action on Previously Identified Enforcement Items The corrective action described in the licensee's letter of December 30, 1974, in response to the enforcement action items identified in R0 Inspection Report No. 50-312/74-09, was verified to have been implemented.
Enforcement items identified in R0:V Inspection Report No. 50-312/74-12 related to Quality Assurance Program control for the performance of maintenance inspection will be examined following receipt of the licensee's response to R0:V's description of violations sent to the licensee subsequent to the past inspection.
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Unusual Occurrences The circumstances and corrective action described in abnormal occurrence reports Nos. 74-10,11,12, and 13 submitted by the licensee to Licensing
g were confirmed.
(Paragraph 2 of Details.)
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Other Significant Findings 1.
Power ascension testing was in progress at the 92.6% power plateau.
(Paragraph 6 of Details.)
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The review and audit program for plant operations has been implemented.
(Paragraph 4 of Details.)
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The program for the establishment of permanent storage facilities for plant operating records was being developed by the licensee.
(Paragraph 3ofDetails.)
Management Interview Messrs. M. Malmros and A. Johnson met with Messrs. J. Mattimoe,
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R. Rodriguez and L. Schweiger and other members of the licensee's staff at the conclusion of the inspection on January 17, 1975. The results of the inspection were discussed with the following comments noted.
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The inspection findings verified the implementation of the licensee's corrective action related to the enforcement items in R0 Inspection-Report 50-312/74-09..
2.
The licensee described the program for the development of permanent record storage facilities consistent with their QA program requirements.
(Paragraph 3ofDetails.)
3.
The licensee stated that observed differences between test results and p(redicted values were being resolved with the NSSS supplier.
Paragraph 6 of Details.)
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REPORT DETAILS
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Persons Contacted Sacramento Municioal Utility District R. Rodriguez, Manager, Nuclear Operations P. Oubre', Assistant Plant Superintendent, Operations
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J. McColligan, Assistant Plant Superintendent, Technical Support R. Colombo, Technical Assistant
D. Whitney, Plant Nuclear Engineer J. Neyman, Nuclear Engineering Assistant R. Knierim, Engineering Aide G. Albiani, Administrative Assistant N. Brock, Instrumentation and Controls Supervisor R. Ozment, Mechanical Foreman F. Lopez, Warehouse Supervisor L. Schweiger, Quality Assurance Director J. Sullivan, Quality Assurance Engineer J.'Jewett, Quality Assurance Engineer R. Miller, Health Physics and Chemistry Supervisor D. Martin, Health Physicist D. Gardiner, Senior Chemical h M Radiation Assistant Bechtel J. Tosh, Technical Assistant M. Kearns, Field Engineering Aide t
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b-3-V 2.. Abnormal Occurrences
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Abnormal Occurrence Report Nos. 74-10, Auxiliary Feedwater Pump Failure; 74-11, Motor Operated Valve Failure; 74-12, Motor Operated Valve Failure; and 74-13, Diesel Generator "A" Failure to Start, were submitted by the licensee as thirty day reports since the previous inspection. Based on an examination of the records and discussions with licensee representatives the inspector verified the following:
a.
The cause of each abnormal occurrence was identified and the details were clearly reported to facility management.
b.
The corrective actions described in the reports to prevent recurrence of the events were implemented by the licensee.
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The abnormal occurrences had been reviewed by the Plant Review
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Committee and the Management Safety Review Committee as required by the technical specifications.
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The limiting conditions for operation were met in all occurrences reported.
System and component failures have been reviewed by the Plant
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Staff and properly identified as abnormal occurrences, when applicable.
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Record and Document Control
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The record copies of the documents retained by the licensee as required by Technical Specifications 6.11.2 (item A, C, D and H) and 6.11.3 (item A, B, D and H) were examined by the inspector with the following observation noted.
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a.
Record copies of all documents examined were located in prescribed file locations under the responsibility of a designated strff member.
b.
Documents were appropriately bound or contained within a file folder.
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Documents removed from the file were identified by the use of "out"
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cards containing the signature of the individual removing the document.
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The file records, at a minimum, consisted of specific records required by the technical specifications.
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O-4-V Record storage was consistent with the preservation and protection e.
requirements of ANSI N45.2.9. for the operating plant QA records generated to date.
Plans for a documentation control center to include storage facilities for construction records (presently in the construction records vault), operating records, and future needs, were being evaluated by the licensee.
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Record copies of as-built drawings were maintained in accordance with SMUD QA Procedure No. 7, Configuration Control.
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The drawing files maintained by maintenance and operations personnel were found to contain the most recently issued revision to system and equipment drawings consistent with configuration control records.
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Review and Audit The inspector examined the minutes of both Plant and the Management Safety Review Committees, along with the QA audit reports for the period
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August 16, 1974 through January 10, 1975.
Certain minutes of the Plant-Review Committee had been previously examined. Based on the information in the records and discussions with licensee representatives, the ()
inspector verified the following.
s-m a.
Both the Plant and Management Safety Review Committees held meetings with a quorum present at the frequency required by
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the facility technical specifications.
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Facility testing, plant mcdifications, abnormal occurrences, and proposed changes to the technical specifications had been evaluated by the committees as required by the facility technical specifica-tions.
c.
Audits had been performed by the on-site QA personnel pursuant to the written procedure in the QA manual.
During the period August 16, 1974 through January 10, 1975, approximately 2] audits had been performed, d.
Audit findings were documented 'and submitted to the appropriate plant and corporate management for review and action.
Followup action related to resolution of discrepancies identified in the audit reports had been taken er was in progress.
Reaudits had been performed of areas where corrective action had been
implemented.
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An audit team of the Management Safety Review Committee was in e.
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the process of performing an audit of the QA program to evaluate ('~;'N the program effectiveness.
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Radiation Surveys-The surveys of the biological shield and other areas of the containment
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The' procedure format was as described in paragraph 7.a. of Regulatory
Operations Report No. 50-312/74-02..To date, survey data for the reactor
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The procedure also requires data for.100 percent.of full-power.
The data showed that radiation levels just inside the entry to the
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containment building :(40-foot level) were less than 0.5 mR/hr gamma
-plus less than 0.5 mrem /hr neutrons at 40 percent of full power.
The licensee stated that additional surveys had been made in' the
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containment and auxiliary building; however, these results were not
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examined during -this inspection. Projecting the survey data at.
.40 percent of full power to results expected at full power, it appears-
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Lthat the radiation zones will be as described in Section 11.2.1.1 of the FSAR.
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Power Ascension Program
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Program Status
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The reactor power level was increased in accordance'with the power
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ascension program to 75% power on January 9, 1975~and to-92.6% on
January 23, 1975. Test results from tests performed at 40% and 75%
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have been reviewed by the licensee.. Testing was in progress at 92.6%
as of January 24,1975 and was scheduled to continue for the next
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several weeks.
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Test Performance
On December 27, 1974, the inspector observed the performance.of
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the trip of.the generator main breaker test conducted in -
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accordance with SMUD procedure iTP 800-42, Unit Loss of Electric Load.. This procedure had been previously reviewed by the inspector.
The. test results'obtained were consistent with the acceptance criteria of.the procedure. The following observations were made.
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(1) The effective revision of TP 809-42 was available and used
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by the personnel ~ performing the test.
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The personnel participating in the test consisted of the (2)' normal' shift of licensed operators consistent with the
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i technical specification requirements.
In addition, a shift-l test engineer and personnel -to record 'and evaluate test data.
were available.
(3) The prerequisites for initial-_ plant conditions, installation of special test equipment, and required procedure sign-offs by'
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prior to the-performance of the-test.
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n O-6-J (4) Throughout the test, the shift test engineer coordinated the
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modification.
(5) The raw test data were consistent with the inspector's independent observations of turbine overspeed (102%), reactor power (runback-to15%),andreliefvalveperformance(atmosphericdumpvalve sequence). All test data was assembled an; a summary analysis made by the shift test engineer. Formal reviews by the Test Working Group and the Pant Review Committee were to be performed to verify that the test results meet the acceptance criteria i
of the test procedure.
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Test Results The test data gathered at 40% and 75% of full power were reviewed by the inspector for the following power ascension tests:
TP 800-2 NI Calibration TP 800-5 Reactivity Coefficients at Power TP 800-11 Core Power Distribution TP 800-22 NSS Heat Balance TP 800-28 Pseudo CRA Ejection Through an examination of the test results and discussions with licensee representatives, the following items were verified.
_i (1) Test results data sheets were available and complete.
(2) Test deficiencies were noted and appropriate retesting was accomplished to resolve data deficiencies.
i (3) The licensee verified that requisite tests were completed
and results approved prior to escalation' of power to a new testing plateau.
_(4) Variations in test results from predicted values were o
identified by the licensee and formal resolutions with Babcock and Wilcox were being-pursued. The basis for these variations-has been attributed to differences in computational methods (computer calculations and hand calculations) used by SMUD and~ Babcock and Wilcox.
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