IR 05000312/1977011
| ML19309A232 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 07/22/1977 |
| From: | Crews J, Dodds R, Malmros M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML19309A226 | List: |
| References | |
| 50-312-77-11, NUDOCS 8003260931 | |
| Download: ML19309A232 (4) | |
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U. S. N'ICLEAR REGULATORY COMMISSION OFFICE OF INSFECTION AND ENFORCEMENT
REGION V
Report No. 50-312/77-11-Safeguards Group License No.
OPR-5a Docket No.
An_117 Sacramento founicical Utility District ucensee:
P.
0.- Box 15830 45813
__ Sacramento. California Facility Name:
Rancho seco lospection at:
Rancho Seco
Inspertion conducted:
July 12-13. 1977 Y2./77
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' Date S1gnec Inspectors:
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"R. T. Dodds, Reactor Inspector 7/) + l~)2
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M. H. Malmros, Reactor Inspector Dat,e Signed 7[g,q,/ 7 j
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Approved by:
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J' L.# trews /, Chief, Reactor Ope ~ rations
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[ndNuclearSupportBranch
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Summary:
Inspection on July 12-13, 1977 (Recort No. 50-312/77-11)
Routine, unannounced inspection of preparation for Areas Insoected:
l ting to refueling; calibration; followup on a deviation; procedures re a transportation of heavy loads over spent fuel pool and This and observation of surveillance testing and plant operations.
inspection involved 24 regular on-site inspection hours by two NRC
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inspecters.
No items of noncompliance or significant deviations were Results:
TdestiTTed during the inspection.
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. DETAILS
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Persons Contacted
- R. Rodriguez, Plant Superintendent
- R. Columbo, Technical Assistant
- W. Ford, Acting Assistant Superintendent, Operations
- J. McColligan, Assistant Superintendent, Technical Support J. Wright, Shift Supervisor D. Gouker, Shift Supervisor
- A. Swieger, Quality Assurance Director N. Brock, I&C Supervisor The inspectors also talked with and interviewed several other licensee employees, including members of the technical and
engineering staff, technicians, reactor operators and craft personnel.
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- Denotes those present at the exit interview.
2.
Followup on Deviation Discussions were held with licensee representives regarding the previously identified deviation pertaining to the operation of the reactor building gaseous and particulate air monitors (Report No.
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77-09). The represenatives stated that they would examine ways
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of reducing instrument sensitivity of the air monitors and/or analyze the sensitivity and response time of building radiation monitors for the detection of reactor coolant system leakage.
This item was discussed in the exit interview.
3.
Preperations for Refueling Procedures AP.16, A.13, B.8, Special Test Procedure Cycle 1 Refueling (Draft), and Fresh Fuel Assembly Receiving Inspection data sheets.for 6 of 56 assemblies were examined to ascertain whether approved procedures will be available for in-core and ex-core fuel handling activities. The licensee represenative stated that the Cycle 1 Refueling Procedure (schedule of core moves) will be reviewed and approved in August 1977 prior to the refueling outage.
No items of noncompliance or deviations were identified.
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Calibration Based on discussions with licensee representatives and an exami-nation of facility records, the calibration of components and equipment associated with safety related system and/or functions was found in conformance with the requirements of the Technical Specifications. The frequency of calibration was verified to have been met for the following:
a.
Control rod position indication instrumentation b.
Turbine overspeed trip instrumentation
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c.
Reactor coolant pressure instrumentation d.
Reactor building spray analog channels e.
Reactor building pressure instrumentation f.
Pressurizer relief tank pressure instrumentation g.
Reactor building spray flow instrumentation
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During the calibration of the above items, service status of the affected systems was in conformance with the applicable limiting
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condition for operations. The voltage set points for instruments providing a reactor trip signal were verified to be correctly set to conform with limiting safety system settings.
procedures used to perform the c'al+ibration of the above components were found to have been reviewed and approved and to contain acceptance values and detailed stepwise instructions. The qualifications of indi-vidual performing calibrations were found to be in conformance with licensee requirements.
The records of three measuring / testing devices used as primary standa'rds during the performance of the above calibrations were examined with the following results observed:
a.
Calibration frequency was met and accuracy verified as prescribed by licensee procedures.
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Accuracy vas traceable to an independent testing organization.
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Storage and control of the test equipment was proper.
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-3-of a portion of the The inspector directly observed the performancelear instrumentat periodic surveillance / calibration of the nucTest equipment use the licensee's 13, 1977.
d personnel was verified to have been calibratet with approved system on July and the actual work was performed consisten identified.
No items of noncompliance or deviations were pool and Reactor Transport of Heavy Loads Over the Spent Fuel were examined i
Procedures B.8 and M.31 for refueling and operat onort of h 5.
and found to specifically prohibit the transpd upper internals have over spent fuel once the reactor head an been removed and stored.
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Independent Inspection Effort.
l rvei,llance The inspectors observed portions of the quarter y sud raw 6.
ral jumper and testing of the nuclear service component an systems and control room operations; examined seve d portions of the lifted lead tags and nonconformance reports; toure nel on miscel-n.
facility; and held discussions with facility pe f eling outacle.
V identified. However, No items of noncompliance or deviations were i
d were unaware of the significance of the bypassing of the i y circuit in circuit for control rod 3 in group 6 due to a no sLicen inter-view that the operators will be kept alerted to November 1976.
ing information in the future.
Manacement Exit Interview discussed with 7.
tion. The li-The scope and findings of the inspection were licensee management at the conclusion of the inspecact tioned in para-censee representatives stated that the areas men i
graphs 2 and 6 would be examined and correct ve as appropriate.
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