ML20004C417
| ML20004C417 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 04/28/1981 |
| From: | Reyes L, Rogers W, Warnick R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20004C412 | List: |
| References | |
| 50-346-81-04, 50-346-81-4, NUDOCS 8106040031 | |
| Download: ML20004C417 (9) | |
See also: IR 05000346/1981004
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U.S. NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENF0FCEMENT-
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. REGION III
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Report No. 50-346/81-04
-Docket No. 50-346
License No. NPF-3
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Licensee: Toledo Edison Company
Edison-Plaza, 300 Madison Avenue
Toledo,JOH 43652
Facility Name: Davis-Besse 1
Inspection At: Oak Harbor, OH
Inspection Conducted: March 2-31, 1981
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Inspectors:
L. A. Reyes-
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W. G. Rogers
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Approved By:
R. F. Warnick, Chief,
4/-2/- J'/
Reactor Projects Section 2B
Inspection Summary
Inspection on March 2-31, 1981 (Report No. 50-346/81-04
Areas Inspected: Routine Resident Inspection of Followup on previous
inspection findings, Operational Safety Verification, Monthly Maintenance
Observation, Review of Plant Operations, Licensee Event' Reports Followup,
Plant trip on March 11, 1981, and increase primary to. secondary leakage.
The inspection involved 239 inspector 'iours onsite by two NRC inspectors
including 49 inspector-hours onsite during off-shifts.
Results: Of the six areas inspected no items of noncompliance or deviation
were identified in four: areas; two items of apparent noncompliance were
identified in the other two areas.
(Failure to log the evntainment purge
time and failure to notify the shift supervisor prior to initiate trouble-
shooting on a safety related system.)
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DETAILS
1.
Persons Contacted :
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- T. Murray,! Station Superintendent .
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B. ~Beyer, Assistant Station Superintendent
P. Carr,_ Maintenance Engineer
S. Quennoz, Technical Engineer
- D.~Huffman, Administrative-Coordinator
'D. . Miller, Operations Engineer
D.'Briden, Chemist'and Health Physicist-
J. Hickey, Training Supervisor
L. Simon,. Operations Supervisor
- C. Daft, Operations QA Manager-
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- J. Byrne, QA Engineer-
~*E. Caba, Senior Assistant _ Engineer
- T. Powers, Lead-Instrument and Control Engineer
- Denotes _those present at the exit interview on~ March 13, 1981.
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' ** Denotes those present at 'the exit interview on March 27, 1981.
- Denotes those present at both exit-interviews.
The inspectors also interviewed other licensee' employees, including
- members of the technical, operations, maintenance, I&C, training and
health-physics. staff.
2.
-Followup on Previous Inspection Findings
(Closed) Followup _ Item (50-346/80-34-01): Amendment 36 to the license
was issued on January 24, 1981. All modifications and personnel train-
ing on the Facility Change were completed prior to the unit startup
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from'the January, 1981 outage.
.(Closed) Unresolved Item (50-346/79-13-01):
Bulletin 79-27 and
Confirmatory Order on the Crystal River Incident. Procedures EP
1202.63 " Loss of NNI Power" and EP 1202.62 " Integrated _ Control System
Loss of Power" have been issued. Operator training in the use of
these procedures has been completed. Modification of the NNI power
supply systems-have been completed by Facility Changes80-058 and
80-096.
(Closed) Unresolved Item (50-346/79-13-03):
BulletinI79-24 was
issued. The licensee implemented Facility Change 79-168 to provide
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freeze protection to the HPI recirculation line. Revision 2 to LER
79-34 dated June 1, 1979, documents the analysis for the operation of
the High Pressure Injection Pumps with a frozen recirculation line.
(Closed) Unresolved Item (50-346/79-13-02): Revision 2 to LER 79-29
dated June 22, 1979, documents the analysis performed on the opera-
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tion of the High PressureLInjection' Pumpand Containment Spray Pumps
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- with-valves DH-7A!and DH-7B closed.
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- (Closed) Followup' Item (50-346/79-14, Paragraph 14)'
- The inspector-
? witnessed'the conduct of PT 5199.14 conducted on March 31, 1981. The
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- lechnical Support Center has's set of' control drawings,zstation pro-
- cedures and technical' specifications.
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'(Closed)' Followup Ites'(License Condition 2.c(3)(f)): . Facility
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Shange 79-077 installed DC motors on the motor operated valves on:
' Auxiliary Feedwater System Train.No.1. j Applicable procedures were :
revised.~: Witnessed. portions of operator training on this facility.
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change..
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f(Closed) Fol'lowup Item (License Con'dition-2.c(3)(g)): Facility:
- Change 79-078-installed;notor operator p on valves DH-63.and DH-64.
. Applicable. procedures were' revised. Witnessed portions'of operator
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-training on this facility- change.
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(Closed). Followup Item-(Section 9.4.1.3 FSAR Revision 24): -Standing
Order No. 17 requires a station shutdown if control' room temperature
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reaches' 110*F. .
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(Closed) Followup Item:(NCR 203-76): Nonconformance Report 203-76-
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was. closed out :on April 19,"1977, after the documentatien on:the High
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Pressure Injection Pump DC oil pump was received.
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(Closed) Followup Item -(50-346/76-23): All' special process procedures
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(welding, NDE) have been reviewed subsequent to the issuance of Quality
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Assurance Procedure 2090 " Control of Special Processes."'
(Closed) Noncompliance (50-346/79-30, Paragraph 10): CNRB not review-
ing violations of Technical Specifacations and regulations identified
in NRC Inspection Reports. The inspector verified by review of CNRB
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minutes that the specific inspection' report violations cited in the
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infraction were reviewed by the CNRB in meeting No. 56. Additionally,
CNRB meeting ciinutes 72 through 81'and 65 were reviewed to determine
4.
if the CNRB was continuing to review violations in NRC Inspection
Reports. 'As evidenced in CNRB meeting minutes No. 65 (Inspection
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-Report 80-24), No. 72 (Inspection Report 80-25), No. 73~(Inspection
Reports 80-23 and 80-26) and No.~ 81 (Inspection Reports 80-29 and
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80-30), the CNRB is' continuing to review violations of Technical
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Specifications and regulations identified in NRC Inspection Reports.
-(Closed) Followup Item (50-346/79-05-06): The inspector verified by
re"lew;of records that a periodic testing program has been implemented
it
to check the instrument ground cable to instrument. ground bus for
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each channel. The test is conducted per procedure PT 5165.01, which
is to be done after each refueling. The teat results of April 22,
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p
n1980 were' reviewed and found satisfactory.
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L 3c : Operational Safety:Verificat' ion' '
LThe' inspector observed control room operations, reviewed applicable
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~1oss;and' conducted discussions'with control' room operators during.
thel month of March :1981. The inspector verified the' operability of
Eselected~ emergency systems, reviewed tagout records'and verified
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_ proper . return ;to' service of affected components. Tours of the: aux-
- iliary building and turbine-building were: conducted to observe plant
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- equipment conditions,Lincluding potential' fire hazards, fluid leaks,
and excessive' vibrations.and to verify that maintenance requests hsd
been' initiated.for equipment:in need_of:maintecanc'e. The inspector'
by observation and direct.: interview verified. that the' physical'
security plan:was being implemented in accordanceLwith the station:
security plan.
.The. inspector observed-plant housekeeping / cleanliness conditions and
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verified ' implementation of: radiation protection controls. During.the
month of March;1981).the. inspector _ walked down'the, accessible portions
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lof the essential power supply syste
to verify operability. The
inspector'also witnessed portions c. the radioactive waste, system
' controls associated with radwaste shipments and barreling.
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-These' reviews and observations were conducted to verify that facility.
operations-were in conformance with the requirements established
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.under technical specifications, 10 CFR, and administrative procedures.
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During the. review of the Containment Purge Log on March 10, 1981, the.
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inspector noticed that'the accumulated time for cot.tainment purge was
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not determined for:the date of March'7,~1981. .This is contrary to -
Technical Specification 4.6.1.7 which requires that the accumulated
time any containment purge supplyJand/or exhaust-valve is' open and
provides access to the outside atmosphere shall be determined at
least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. This is an item of noncompliance.
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No additional items of noncompliance or deviations were identified.
4.
Monthly 'Ma intenance - Obse rvation
-Station maintenance activities of safety related systems and com-
ponents listed below were observed / reviewed to ascertain that they
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were conducted in accordance with approved procedures, regulatory
guides and industry codes or standards -and in conformance with E
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technical specifications.
-The following~ items were considered during this review:
the limiting
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conditions-for operation were met while components or systems were
removed from service; approvals were obtained prior to initiating-the
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work; activities were accomplished using approved procedures and were
inspected as applicable; functional testing and/or calibrations were
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performed' prior to returning components or syste9s to service; quality 1
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control records were maintained; activities were accomplished'by
qualified personnel; parts and materials used were properly certified;
radiological controls were implemented; and, fire prevention controls
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were implemented.
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Work requests were reviewed to' determine status of outstanding jobs
and to assure that priority is. assigned to safety related equipment
maictenance which may affect system performance.
The following maintenance activities were observed / reviewed:
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Inspection of emergeeny diesel generator 1-1 brushes and measurement
of generator field resistance.
Follcwing completion of maintenance on the emergency diese1' generator,
the-inspector verified that the applicable systems had been returned
to. service properly.
On March 18, 1981, during the conduct of maintenance on Emergency
Diesel Generator No. 1, maintenance personnel'took resistance read-
ings on the Generator Roter Windings. These readings were being-
taken because of reports that during the conduct of surveillance
test the previous date the operator noticed what appeared to be
o erheating of the Generator Brush Holders. .Since the readings
taken could not be correlated to the vendor specifications, main-
tenance personnel decided ~to take the same resistance readiags on
Diesel Generator No. 2.
Although several discussions were held between maintenance and
operations management personnel prior to taking the resistance
readings, the Shift Supervisor was not notified of the activities
planned to be performed on Diesel Generator No. 2.
The Assistant
Shift Supervisor noticed that maintenance personnel had removed
Generator No. 2 inspection covers when a scheduled start of Diesel
Generator No. 2 was being initiated. The Assistant Shift Supervisor
then remained at the Emergency Diesel Generator Room for the conduct
of the resistance readings.
This appears to be contrary to Section 4.1.10 of Procedure 1844.00
" Maintenance" which states that " Initial trouble shooting of equip-
ment / component for purposes of identifying equipment / component prob-
lems can be done without a MWO if Maintenance /I&C personnel work with
operations department under the cognizance of the Shift Supervisor.
After the problem has been ide.tified; a MWO will be issued te correct
the problem."
It also appears to be contrary to enclosures 8 and 9 of the same
procedure which indicates the maintenance activity to be initiated
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subsequent to the Shift Supervisor's approval to commence work. This
is an item of noncompliance.
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No additional items'of noncompliance or., deviations 1were identified.
5:
Monthly Surveillance Observation
The inspector observed technical-specifications required surveillance
testing on the Diesel Generator 1-1-(ST 5081-01) and verified that
testing was performed in accordance with adequate procedures, that
test instrumentation was calibrated, that limiting conditions for.
operation were met, that; removal and restoration'of the affected
components were accomplished, that test results conformed with
technical specifications and procedure requirements and were reviewed
by personnel other than the individua1' directing the test, and that
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any deficiencies identified during the' testing were properly revi2wed'
and resolved by appropriate management. personnel.
The inspector also witnessed portions of the following test activ-
ities: ~RPS Monthly Functional Test (ST 5030.02) for channel 3 and
Component Coding Water System Monthly. Surveillance Test (ST 5074.01)
for pump 1-1.
-No items of noncompliance er deviations were identified.
6.
Licensee Event Reports Followup
Through direct observations, discussions with licensee personnel, and
review of records, the following event' reports were reviewed to
determine that reportability requirements were fulfilled, immediate
cor ective action was accomplished, and corrective action to prevent
recurrence had been accomplished in accordance with technical speci-
fications.
80-28
RCP Trip Reguirement Results in Delay of RCS Depressuriza-
tion during a SG Tube Failure Accident.
80-52
Seismic Supports for Emergency Diesel Generator Exhaust;
Lines Overstressed during Seismic Efent.
80-55
Loss of Position Indication for ECCS Room Ventilation
80-58
Closure of Valve DH-12 Resulting in Loss of Decay Heat
Removal System Flow.
80-57
Reduction of Decay Heat Removal System Flow Below T. S.
Requirements.
80-60
Closure of Valve DH-11 Resulting in Loss of Decay Heat
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Removal System Flow.
80-92
Failure of Valve MS-136 to Close During the Performance of
Surveillance Testing.
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Failure of Transformer 01 and 02 Lightning Arrestors.
'81-09
EDG Left Side Air _ Motors lWoul'd_Not Start.
.81-11
' Failure of'HP1' Flow 1ndicator.
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81-13:
. Loss of Power to Chlorine. Detector No. I and Closure of
Control Room Emergency. Ventilation System.
-81-15
Negative Pressure Boundary Door 107 was Found Open.
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No_ items of noncompliance or deviations were identified.
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Review.of Plant Operations
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During_the month of March 1981 the inspector reviewed the'following-
activities:
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a.
Review and Audits
OnMarch13;1981, the inspector-sat in on a safety review
committee meeting. The inspector verified that provisions of
technical 1 specifications dealing with membership, review pro-
cess, frequency, and qualifications were met. .The inspector
also verified that decisions made were reflected in the. meeting
minutes and that corrective actions proposed were taken.
b.
Environmental Protection
1The inspector verified the installation and operability of-
environmental air and water sampling (monitoring) station (s)
and associated equipment and reviewed records for completeness
and accuracy.
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c.
Security
On March 25, 1981, the inspector attended a training lecture
given to physical security personnel and verified the lesson
plan objectives and lecture schedule were met.
d.
The inspector reviewed the lesson plans and attendance records of'
training conducted for Carroll Township EMS, Carroll Township Fire
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and H. B. Magruder Memorial Hospital personnel to ensure these
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agencies are familiar with their role in the emergency plan. The
inspector also observed an emergency drill on November 15, 1980,
and verified that the licensee has a program for correcting
identified discrepancies and that equipment disrupted was returned
to its proper location after the drill.
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-No' items.of' noncompliance or deviations were identified.,
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8.
Plant Trip
'Following the plant' trip 'on March II, 1981,'the'inspectorsas'certained
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.the' status of the reactor and safety systems by observation of control
room. indicators and discussions with licensee personnel concerning..
- plant parameters, emergency system status and reactor coolant chemistr';.
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The inspector verified the. establishment of proper communications and
reviewed the corrective actions taken by the licensee;
All systems responded as expect.ed,' .'and the plant was returned to..
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operation on March 13, 1981.
No: items.of noncompliance or deviations'were. identified.
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IE' Bulletin Followup For Bulletin 80-09 "Hydramotor Actuator.
' Deficiencies
The inspector 4 reviewed the. licensee's response in letter Serial _No.11-152'dat.ed July 11,'1980. The licensee identified a total of six
systems that used AH-90 or NH-90 series Hydramotor Actuators manu-
factured by ITT General Controls.
During the review of the licensee's records, the inspector noticed
that there was'no documentation available tn document the functional
. testing of the Containment Post Accident Radiation Monitor Isolation
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The-inspector also noticed that with the exception of the Emergency
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Ventilation System, all the other systems were-not periodically tested.
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This is considered an open item until'the above-mentioned bulletin
~ requirements are completed (50-346/81-04-01).
No items of noncompliance or deviations were identified.
10.
Primary to Secondary Leakage
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On March 23, 1981, the radiation monitor on the steam jet air ejector
increased indicating a primary to secondary leak in the steam genera-
tors. Surveys of the steam lines indicate that the leak is from Steam
Generator No. 2.
Due to the increase in activity.on the secondary side all the drains
have been routed t) the settling basins to provide a monitored and
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controlled release. The primary to secondary leakage has remained
oclow' technical specification requirements.
No items of noncompliance or deviations were identified.
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Exit Interview'-
The inspector-met with licensee representatives '(denoted'in . Paragraph
-1) throughout the month ~and at the conclusion of the, inspect. ion on:
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March 27, 1981-and summarized the scope and findings of the inspection
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