ML19296C897
| ML19296C897 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 01/25/1980 |
| From: | Barker J, Spessard R, Tongue T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19296C892 | List: |
| References | |
| 50-010-79-25, 50-10-79-25, 50-237-79-29, 50-249-79-27, NUDOCS 8002290035 | |
| Download: ML19296C897 (11) | |
See also: IR 05000010/1979025
Text
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U.S. NUCLEAR REGULATORY COMMISSION
.
OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-010/79-25; 50-237/79-29; 50-249/79-27
Docket No.50-010; 50-237; 50-2 9
License No. DPR-02; DPR-19; DPR-25
Licensee:
Commonwealth Edison Company
Post Office Box 767
Chicago, IL 60690
Facility Name:
Dresden Nuclear Power Station, Units 1, 2 and 3
Inspection At:
Dresden Site, Morris, Illinois
Inspection Conducted: December 3, 1979 - January 4, 1980
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Inspectors:
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T. M. To gue p
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Approved By:
R. L. Sp ssard, Chief
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Reactor Projects Section 1-1
Inspection Summary
Inspection on December 3, 1979 - January 4, 1980 (Report No. 50-010/79-25;
50-237/79-29; 50-249/79-27)
Areas Ins ected:
Routine, unannounce ' resident inspection of maintenance
i
activities; plant operations; physical protection-security organization,
physical barriers, access control (identification, authorization, badging,
search, and escorting), and communications; licensee event reports; sur-
velliance of safety related systems / components required by technical
specifications; calibration of safety related components required by
technical specifictions; radioactive waste system-operations; surveillance
of core power distribution limits; thermal power evaluation; radiation
protection-operations; calibration of LPRM system; APRM calibration; cal-
ibration of safety related components not required by technical specifi-
cations; critical fire protection area inspections; and, design, design
changes, and modifications. The inspection involved lit inspector-hours
onsite by two Nlic inspectors.
Results: Of the eighteen areas inspected, there were nt items of noncom-
pliance identified in seventeen areas. There was one.iten. of noncompliance
(Inf raction-failure to follow procec'ures-Paragraph 3) iderJ.ified in one area.
8 0022g0 &
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DETAILS
1.
Persons Contacted
a.
Commonwealth Edison Personnel
- B. Stephenson, Station Superintendent
- R. Ragan, Opertions Assistant Superintendent
- J. Eeingenburg, Maintenance Assistant Superintendent
- B. Shelton, Administrative Services and Support Assistant
Superintendent
- E. Budzichowski, Unit Support Operating Engineer
- C. Sargent, Unit 1 Operating Engineer
J. Wujeiga, Unit 2 Operating Engineer
kM. Wright, Unit 3 Operating Engineer
D. Farrar, Technical Staff Supervisor
D. Adam, Waste Systems Engineer
- J. Parry, Rad-Chem Supervisor
- B.
Saunders, Station Security Administrator
- J. Mayer, Staff Assistant
- R.
Rybak, Technical Staff
- B.
Tanonge, Technical Staff
- D.
Wheeler, Station Construction
- R.
Werder, Station Construction
- R.
Redinger, Station Construction
- D.
Nohr, Station Construction
- J. Ahlman, Quality Assurance
b.
Contractor Personnel
- E. Rodgers, Burns Security
- D. Jackson, Universal Power and Pipe
- C.
Steiner, Chicago Bridge and Iron
- W. DeYoung, United Engineering and Construction
The inspector also talked with and interviewed several other licensee
employees, including members of the technical and engineering staffs,
reacter and auxiliary operators, shift engineers and foremen, elec-
trical, mechanical and instrument perronnel, and contract security
personnel.
- Denotes those attending one or more exit interviews conducted on
December 7, 14, 21, 1979 and January 4,1980.
2.
Maintenance
Station maintenance activities of safety related systems and compon-
ents were reviewed to ascertain that they are conducted in accordance
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with approved procedures, regulatory guides and industry codes or
standards and in conformance with Technical Specification requirements.
The following items were considered during this review:
the limiting
conditions for operations were met while components or systems were
removed from service; approvals were obtained prior to initiating the
work; maintenance activities were accomplished using approved proce-
dures; maintenance activities were inspected as applicable; functional
testing and/or calibrations were performed prior to returning compon-
ents or systems to an operating status; quality control records were
maintained for maintenance activities; and maintenance activities
were accomplished by qualified personnel.
The inspector observed maintenance in progress concerning the fol-
lowing Unit 3 work requests: WR 2036, HPCI Valve 2301-7; Isolation
Condenser Valve 1302-501; WR 3377, Diesel Generator Semiannual In-
spection; and, WR 3436, Reactor Building Interlock Door to Outside.
The inspector reviewed the following completed work packages:
(1)
Unit 2, WR 3039, Core Spray (0 pen for Inspection); (2) Unit 2, WR 3026, A SBGT System and WR 3526, Reactor High Pressure Scram Switch;
(3) Unit 3, WR 3119, MSIV 2D (Add Oil and Check Packing); and, (4)
Unit 2/3, WR 3689, Unit 2/3 Diesel Generator.
No items of noncompliance were identified.
3.
Plant Operations
The inspector reviewed the plant operations including examinations of
control room log books, routine patrol sheets, shift engineer log
book, equipment outage logs, special operating orders, and jumper and
tagout logs for the month of December, 1979. The inspector observed
plant operations during 5 offshifts during the month of December,
1979.
The inspector also made visual observations of the routine
surveillance and functional tests in progress during the period.
This review was conducted to verify that facility operations were in
conformance with the requirements established under Technical Spec-
ifications, 10 CFR, and Administrative Procedures.
A review of the
licensee's deviation reports for the period was conducted to verify
that no violations of the licensee's Technical Specifications were
made. The inspector conducted a tour of Units 1, 2 and 3 rcactor
builuings and turbine buildings throughout the period and noted that
the monitoring instrumentation was recorded as required, radiation
controls were properly established, fluid leaks and pipe vibrations
were minimal, seismic restraint oil levels appeared adequate, equipment--
caution and hold cards agreed with contral room records, plant house-
keeping conditions / cleanliness were adequate, and fire hazards were
minimal. The inspector observed shift turnovers to verify that plant
and component status and problem areas were being turned over to
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relieving shift pers' .nel.
The inspector observed sampling and
chemical analysis of water chemistry samples to verify that water
chemistry was being maintained in accordance with Technical Spec-
ifications.
During a routine tour of Unit 1 Turbine Building on December 20,
1979, the inspector observed evidence of eating, drinking, smoking,
and chewing (i.e., the presence of numerous cigarette butts, empty
soft drink cans, empty candy wrappers, and empty chewing gum wrappers)
in this posted radiation area.
There actions are specifically pro-
hibited by the licensee's Radiation Control Standards Procedure
37-1-E-3, " Work in Controlled Areas (Radiation and High Radiation
Areas)." This failure to follow procedures is contrary to Technical Specifications, Section 6.2.B and is considered an item of noncom-
pliance. (10/79-25-01)
This item is a recurrent item of noncompliance as delineanted in
Inspection Report Number 50-010/79-19. During a management meeting
on December 21, 1979, with the station superintendent, station con-
struction management, and contractor management, the NRC inspector
emphasized the importance of proper management controls and supervi-
sion to er?ure the health and safety of all personnel who may be
working in radiation and high radiation areas, and stated that the
management policies and procedures in effect were apparently inade-
quate to ensure compliance with NRC requirements.
No additional items of noncompliance were identified.
4.
Physical Protection - Security Organization
The inspector verified by observation and personnel interview (once
during each operating shift) that at least one full time member of
the security organization who has the authority to direct the phy-
sical security activities of the security organization was onsite
at all times; verified by observation that the security organization
was properly manned for all shif ts; and verified by observation that
members of the security organization were capable of performing their
assigned tasks. There were no weapons qualifications conducted dur-
ing this monthly inspection.
No items of noncompliance were identified.
5.
Physical Protection - Physical Barriers
The inspector verified that certain aspects of~the physical barriers
and isolation zones conformed to regulatory requirements and commit-
ments in the physical security plan (PSP); that gates in the protected
area were closed and locked if not attended; that doors in vital area
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barriers were closed and locked if not attended; and that isolation
zones were free of visual obstructions and objects that could aid an
intruder in penetrating the protected area.
No items of noncompliance were identified.
6.
Physical Protection - Access Control (Identification, Authorization,
Badging, Search, and Escorting)
The inspector verified that all persons and packages were identified
and authorization checked prior to entry into the protected area (PA),
all vehicles were properly authorized prior to entry into a PA, all
persons authorized in the PA were issued and displayed identifica-
tion badges, records of access authorized conformed to the PSP, and
all personnel in vital areas were authorized access; verified that
all persons, packages, and vehicles were searched in accordance to
regulatory requirements, the PSP, and security procedures; verified
that persons authorized escorted access were accompar.ied by an escort
when within a PA or vital area; verified that vehicles authorized
escorted access were accompanied by an escort when within the PA; and
verified by review of the licensee's authorization document that the
escort observed above was authorized to perform the escort function.
No items of noncompliance were identified.
7.
Physical Protection - Communications
The inspector verified by observation (during each operating shif t)
that communications checks were conducted satisfactorily at the be-
ginning of and at other prescribed time (s) during the security per-
sonnel work shift and that all fixed and roving posts, and each
member of the response team successfully communicate from their
remote location; and verified that equipment was operated consistent
with requirements in the PSP and security procedures.
No items of noncompliance were identified.
8.
Review and Followup on Licensee Event Reports
Through direct observations, discussions with licensee personnel, and
review of records, the following event reports were reviewed to deter-
mine that reportability requirements were fulfilled, immediate correc-
tive action was accomplished, and corrective action to prevent recur-
r(nce had been accomplished in accordance with Technical Specifications.
Unit 2
LER 79-58, Isolation condenser condensate high flow switch (DPIS 1349-A)
tripped in excess of Technical Specification limits.
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LER 79-59, 2A Core Spray line declared inoperable as a result of IEB 79-14 inspections.
LER 79-60, Failure to perform surveillance on testable valves in fire
supp ?ssion water flow path as specified in Technical
Spe,ification.
LER 79-61, Cardox storage tank preisure less than Technical Specifica-
tion limits.
LER 79-62, Failure of A SBGT system.
LER 79-63, SRM channel 23 rod block trip in excess of Technical Spec-
ification limits.
LER 79-64, Torus to drywell vacuum breaker 2-1601-32F inoperable.
LER 79-65, Failure of B SBGT system.
Regarding LER 79-59, the deficiencies identified during inspections
required by IEB 79-14 will be inspected to ensure procedure adherence
and adequate corrective action completion when all such inspections
have been completed. (Outstanding Inspection Item 237/79-29-01)
Regarding LER 79-60, the NRC inspector determined that the licensee
failed to perform an annual surveillance requirement, as specified in
Technical Specifications, Section 4.12.B.1.C, on the testable valvec
in the fire suppression flow path. This failure was identified and
corrected through adequate management controls and is considered a
licensee identified item.
Regarding LER 79-64, the NRC inspector will follow the results of the
licensee's investigation regarding the applicability of teflon as a
bushing material. (Outstanding Inspection Item 237/79-29-02)
Unit 3
LER 79-29, IRM channel 11 tripped in excess of Technical Specification
limits.
LER 79-31, MSIV 3-203-2D closure time less than specified in Techni-
cal Specifications.
LER 79-32, Pinhole leak found on 3B reactor feed pump.
No items of noncompliance were identified.
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.
9.
Surveillance of Safety Related Systems / Components Required by Technical
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Specifications
The inspector observed Technical Specifications required surveillance
testing (other than calibrations and checks) on the control drive
system and the LPCI syster curing the week of December 10, 1979 and
verified that testing was performed in accordance with technically
adequate procedures, that test results were in conformance with
Technical Specifications and procedure requirements and were reviewed
by personnel other than the individual directing the test, and that
any deficiencies identified during testing were properly reviewed and
resolved by appropriate management personnel.
No items of noncompliance were identified.
10.
Calibration of Safety Related Components Required by Technical
Specificati'.s
The inspector observed calibration of IRM's, SRM's and area radiation
monitors during the week of December 24, 1979 ar verified conformance
with Technical Specifications and use of a technically adequate proce-
dure. He also selected 3 instrument testing devices (DF-5, Tektronic
Oscilloscope-SC 502; DY-13, Pulse Generator-PG-501; and DW-14, Tek-
tronic Digital Multimeter-DM-501) used as a standard and verified that
calibration frequency was met, that accuracy was verified as prescrib-
ed by internal procedures or specifications, that accuracy was traceable
to National Bureau of Standards or other independent testing organiza-
tions, and that storage and control of the selected devices were in
accordance with internal procedures or specifications.
No items of noncompliance were identified.
11.
Radioactive Waste Systems - Operations
The inspector verified through record review that all effluent re-
leases which occurred during the month of December, 1979 were pro-
perly documented, that timely approvals of the releases were obtained,
and that required sampling had been accomplished.
No items of noncompliance were identified.
12.
Surveillance of Core Power Distribution Limits
The inspector verified through examination of P-1 print outs obtained
on December 12, 1979 that linear heat generation rates (LHGR) were
within Technical Specifications limits and that if core maximum
peaking factors were above design value total peaking factors for
that class of fuel, APRM setpoint adjustments would be made by the
amount specified in Technical Specification; and verified by examina-
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.
tion of the OD-6, " Thermal Data in a Specified Bundle," associated
with the P-1 selected above that minimum critical power ratio (MCPR)
and average planar linear heat generation rate (APLHGR) were with
Technical Specifications limits.
No items of uoncompliance were identified.
13.
Thermal Power Evaluation
The inspector reviewed the results of the licensee's core thermal
power evaluation for Units 2 and 3 which were obtained on December 13,
1979 and verified the technical adequacy of the evaluations and re-
sults and that the frequency of evaluationa was as prescribed by the
':cility's Technical Specifications.
.4o items of n acompliance were identified.
14.
Radiation Protection- Operations
On December 11, 1979, the inspector examined all radiation protection
instruments in use and verified operability and currency of calibra-
tion, examined 3 SWP's and verified operations conducted under the
SWP's were in accordance with licensee procedures and verified that
high radiation area posting and control and 10 CFR 19 posting re-
quirements were met.
No items of noncompliance were identified.
15.
Calibration of Local Power Range Monitor (LPRM) System
On December 12, 1979, the inspector observed a LPRM calibration on
Unit 2 and verified that the calibration was performed in accordance
with approved procedures and at required Technical Specification
frequency, verified that the following LPRM calibration APRM settings
were reviewed to assure they were within Technical Specification
limits, and verified that post gain adjustment P-1 calculations and
gain adjustment factors were with established limits.
No items of noncompliance were identified.
16.
Average Power Range Monit.r (APRM) Calibration
On December 13, 1979, the ir.7pector c5 served APRM calibrations on
Unit 2 and verified that the calibrations were performed in accord-
ance with technically adequate procedures and required Technical
Specification frequency.
No items of noncompliance were identified.
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17.
Calibration of Safety Related Components Not R;quj. red by Technical
Specifications
The inspector, through record and procedure review verified for the
components listed below that specific requirements have been estab-
lished for calibration of components associated with safety related
systems or functions but not specified in the Technical Specifications
as requiring calibration; that the operating range / accuracy of the
components were consistant with the applicable Technical Specifica-
tion /FSAL specified range and accuracy criteria; that procedures used
to calibrate the components were reviewed and approved as required by
Technical Specifications, contained acceptance criterie consistant
with Technical Specifications /FSAR criteria, and contained detailed
instructions commensurate with the complexity of the calibration; and
that the technical content of the procedures was adequate to perform
a satisfactory calibration of related components.
Components
Procedure
Reactor Building Crane Radiation Monitor
DIS 1800-2
Chimney Flow-Monitor
DIS 5700-2
Hydrogen Storage Tank
DIS 8500-1
TIP Purge Monitor
DIS 700-29
Condensate Pit High Level Alarm
DIS 4400-1
HPCI Turbine Trip High Reactor Level Isolation
DIS 500-3
Drywell Nitrogen Purge and Vent Valve Pressure
Switch
DIS 1600-11
Reactor Pressure (Feed Water Control)
DIS 600-1
No items of noncompliance were identified.
18.
Critical Fire Protection Area Inspections
During the review of administrative procedures, shift logs and operat-
ing records, the inspector verified that whenever installed fire
detection or suppression systems in the critical areas were out-of-ser-
vice, fire watches were established as required by the Technical
Specifications; that surveillance tests on systems serving critical
fire areas were accomplished as required by Technical Specifications;
that watches were stationed when work requiring an open flame was
performed in the critical area; and that administrative controls were
established to control combustible material and ignition sources in
the critical fire areas.
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During a tour of the facility on January 3,1980, the inspector
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observed that combustible material was not being stored in a critical
area, that fire watches were established when work was in progress
requiring open flames or ignition sources, that fire extinguishers
were unobstructed and contained the proper pressure, and that the
Cardox System contained adequate pressure and the general conditions
of the system were adequate.
No items of noncompliance were identified.
19.
Design, Design Changes, and Modifications
Through record review that inspector verified for the design changes
listed below that design changes were made in accordance with 10 CFR 50.59; that design changes were reviewed in accordance with Technical
Specifications and the established Quality Assurance program; that
design changes were conducted in accordance with written procedures
which included identification of specifications and codes governing
work, identification of inspections required by codes or standards,
and acceptance test procedures which defined acceptance values or
acceptance standards; that test records verified performance of
equipment modified to Technical Specifications /FSAR requirements
and performance of modified equipment was reviewed and approved;
that operating procedures modifications were made and approved in
accordance with Technical Specifications; that installation proce-
dures were adequate for the identified function; that as-built
drawings were changed to reflect the modifications; and that records
of design changes were maintained as described in 10 CFR 50.59b and
the established QA program.
Unit 2
M 12-2-79-09, Remove A & B SJAE rupture disk and blind flange
M 12-2-79-16, Replace latch proximity switch on fuel grapple with
modified microswitch
M 12-2-79-22, Reactor building drain tank level transmitter; elimin-
ate magnetrol level switch; add dual alarm trip unit
to supply pump start and stop
Unit 3
M 12-3-79-04, Temporary protection bypass for crossaround piping on
high pressure trip for turbine
M 12-3-79-10, Temporary closure for Unit 3 reactor building blowout
panel
M 12-3-79-35, Revise diesel generator multiple start circuitry
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Unit 2/3
.
M 12-2/3-79-05, Diesel fire pump; replace existing magnetic switch,
DC contactor, and wiring harness
M 12-2/3-79-10, Provide isolation valve on Unit 2/3 torus-hotwell/ rad-
waste tranfer line to auto close on Group II isolation.
20.
Exit Interview
The inspector met with licensee representatives (denoted in Para-
graph 1) throughout the month and at the conclusion of the inspec-
tion on January 4, 1980 and summarized the scope and findings of
the inspection activities. The licensee acknowledged the item of
noncompliance identified in Paragraph 3.
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