ML19209A395
| ML19209A395 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 08/20/1979 |
| From: | Bagaglio M, Canter H, Faulkenberry B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML19209A393 | List: |
| References | |
| 50-312-79-11, NUDOCS 7910030784 | |
| Download: ML19209A395 (6) | |
See also: IR 05000312/1979011
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U.S. fiUCLEAR REGULATORY COMMISSION
OFFICE OF If1SPECTION AND ENFORCEliEfiT
Region V
Report No.
50-312/79-11
Docket flo.
50-312
License fla.
Safeguards Group
Licensee:
Sacramento Municipal Utility District
P. O. Box 15830
Sacramento, California 95813
Facility Name:
Rancho Seco
Inspection at:
Clay Station, California
Inspection Conducted:
, June 12 - July 12,1979
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Inspectors:
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A. D. Jo nso (, Reactor Inspector
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P. H. Joh son, Reactor Inspector
Date Signed
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J. D. Carlson, Reactor InspEtor
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G.'W. J
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. B. 76etziW, Reacto Inspector
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f. J. Morrill, Reactor Inspector
Date Signed
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Approved By:
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B. H.iFaplkenberry, Chief, Reactor Projects Section 2
'Date Signed
Keactor Operations and fluclear Support Branch
Summary:
Areas Inspected: Operator training pertaining to "Three Mile Island" incident,
IE Bulletins, Licensee Event Reports, tpecial tests, design changes, procurement
and reactor operations. The inspection involved 252 inspector hours onsite by
nine NRC inspectors.
Resul ts :
fio items of noncompliance or deviations were identified.
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e
DETAILS
1.
Persons Contacted
- R. Rodriguez, Manager, Nuclear Operations
- F. Oubre, Plant Superintendent
- G. Coward, Maintenance Supervisor
- R. Colombo, Technical Assistant
- R. Miller
W. Ford, Operations Supervisor
R. Wichert, Plant Mechanical Engineer
J. Mau, Training Supervisor
H. Heckert, Engineering Technician
J. McColligan, Supervisor, Engineering and Quality Control
2.
Auxiliary Feedwater System Tests
The inspectors examined the approved test procedures and results of
the auxiliary feedwater system tests to verify system performance
STP-070, Auxiliary Feedwater Flow verification test,
capabilities.
verified:
that using either auxiliary feedwater pump, adequate flow
a.
would be supplied to each steam generator;
that with the ICS overridden, auxiliary feedwater flow was
b.
capable of being manually controlled;
that upon loss of both main feedwater pumps, auxiliary feedwater
c.
flow would be initiated; and
that upon loss of air pressure, the auxiliary feedwater control
d.
valves can be manually closed.
STP-071, Auxiliary Feedwater Pump Endurance Test, verified the
endurance capability of the auxiliary feedwater pumps by continuous
operation of each for forty hours.
In addition to performing the above examinations the inspectors witnessed
those portions of the tests described in STP-070 a. and b. and a
portion test described in STP-071.
No items of noncompliance or deviations were identified.
- Denotes those attending exit interview.
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3.
IE Bulletins
The inspector confirmed the information submitted by the licensee in
response to IE Bulletins 79-03, 79-04, 79-07, 79-09 and 79-10 thru
discussion with licensee representatives and by examination of
pertinent documents.
4.
Licensee Event Reports
The inspector confirmed the information contained in Licensee Event
Reports (LER's) f40s 79-03 and 79-04.
5.
Operator Retraining (Inspection Report _ 50-312/79-10)
A representative of General Physics Corporation provided training
to licensed operators at Rancho Seco durIng the weak of June ll, 1979.
This training emphasized small break procedures, the sequence of
events at and lessons learned from Three Mile Island, and other
changes in plant design and procedures made during the recent
shutdown period.
Portions of this training were audited by the
inspectors.
Following the training a General Physics auditor
conducted oral interviews with the operators to verify that they
understood the materials presented and discussed.
An f1RC inspector
also interviewed approximately 50% of the licensed operators
on June 17-18, 1979. These interviews confirmed the effectiveness
of the training and audit program provided by the licensee.
6.
A reactor trip occurred on July 12, 1979 while an inspector was at
the site.
Erratic operation of the turbine intercept valves led
to a turbine trip, which tripped the reactor by means of the direct
trip function installed during the recent shutdown. All safety-
related equipment operated as required.
Following evaluation and
trouble-shooting of the turbine control system the plant returned to
power with a brush recorder connected to system parameters of interest.
These parameters showed further instability at a power output of
approximately 200 MWe, and portions of the "D" reheater pressure
transmitter were replaced. Further intercept valve instability
was experienced on July 14, 1979, although a plant trip did not
occur. The licensee replaced the complete "D" reheater pressure
transmitter following this transient, and further difficulties were
not observed.
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7.
Procurement
The inspector examined the following Quality Assurance Procedures
(QAP's) to verify that administrative controls exist relating to
the procurement of safety-related equipment:
QAP-4
Procurement Document Control
QAP-5
Supplier Quality Assurance
QAP-10
Receiving Inspection
QAP-15
Handling, Storage, Shipping and Preservation
QAP-17
Nonconforming Material Control
For selected components in the following listed systems the inspector
verified that procurement specifications contained proper approval
signatures, quality control inspection requirements, and quality
record requirements. The inspector also verified that the items
were inspected upon delivery, handled and stored in accordance with
the plant procedures, and purchased from approved venders. The
inspector toured the warehouse areas and examined the storage
conditions.
Reactivity Control and Power Distribution
Instrumentation
Containment System
Plant and Electrical Power Systems
No items of noncompliance or deviations were identified.
8.
Design, Design Changes, and Modifications
The inspector reviewed the licensee's program for handling design
changes and modifications.
In addition to the program review,
the inspector examined the documentation for the NRC required
modifications resulting from the Three Mile Island incident.
The
modifications examined were:
Keyswitch cutout of the loss of feedwater and turbine trip
a.
(used for startup and shutdown of the unit.)
b.
Loss of feedwater and turbine trip - reactor trip.
c.
Auxiliary feedwater flow indication.
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d.
Condensate storage tank low level alarm.
No items of noncompliance or deviations were identified.
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9.
Management Interview
The inspectors met with licensee representatives at the conclusion of
the inspection and reviewed the scope and findings of the inspection.
The inspectors inforr.ed the licensee that no items of noncompliance
or deviations were identified during the course of the inspection.
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