ML20235A551
| ML20235A551 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 09/21/1987 |
| From: | Fisher W, Hackney C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20235A525 | List: |
| References | |
| 50-482-87-21, NUDOCS 8709230335 | |
| Download: ML20235A551 (8) | |
See also: IR 05000482/1987021
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APPENDIX
U.S. NUCLEAR REGULATORY' COMMISSION-
REGION'IV
NRC Inspection Report:
50-482/87-21
Licens'e:
Docket: . - 50-4'82
Licensee:
Wolf Creek Nuclear Operating Corporation
1
P.O. Box'411
Burlington,1 Kansas 66839.
Facility Name: Wolf Creek Generating Station
Inspection At:
Wolf Creek Site, Burlington, Kansas-
Inspection Conducted: . August 31 through September 4, 1987
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Inspector:
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s C. A. Hackney,. Emergency Preparedness-Analyst.
Dats
Accompanying
Personnel:
R. Vickrey, Region'IV, NRC
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E. Podolak,iNRR,'NRC Headquarters
D. Schultz, Comex Corporation
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Approved:
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W. L. Fisher, Chief, Nuclear Materials and
Date '
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Emergency Preparedness Branch
Inspection Summary
Inspection Conducted August 31 through September 4, 1987 (Report 50-482/87-21)
Areas Inspected:
Routine, announced inspection of the licensee's performance
and capabilities. during an annual exercise of the, emergency plan and
'
procedures.
Results:
Within the areas inspected, no violations or deviations were
identified.
One deficiency was identified by NRC inspector (paragraph 4).
8709230335 870921
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DETAILS
1.
Persons Contacted
Principal Licensee Personnel
- B. Withers, President and Chief Executive Officer
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- F. Rhodes, Vice President, Nuclear Operations
- J. Bailey, Vice President, Engineering and Technical Services
- G. Boyer, Plant Manager
- R. Hagan, Manager, Nuclear Services
- K. Moles, Manager, Emergency Planning
- 0. Maynard, Manager, Licensing
- R. Andrews, Emergency Planning Administrator
- M. Nichols, Superintendent, Plant Support
- J. Zell, Manager, Nuclear Training
- J. Goode, Licensing Engineer
- J. Dagenette, Instructor Coordinator
NRC
- J. Cummins, Senior Resident Inspector
- B. Bartlett, Resident Inspector
Federal Emergency Management Agency (FEMA)
R. Leonard, Program Manager
R. Bissell, Technological Hazards Specialist
The NRC inspector also held discussions with other station and corporate
personnel in the areas of security, health physics, operations, training,
and emergency response organization.
- Denotes those present at the exit interview.
2.
Followup on Previously Identified Items
(Closed) Deficiency (482/8704-01):
The primary offsite dose calculation
method used by the licensee was essentially a manual method, involving
data entry into a matrix and operating in it with a handheld calculator.
Although the method was reasonably timely, it had a high potential for
error (due to numerous arithmetic operations) and only addressed simple,
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straight-line Gaussian dispersion conditions.
The NRC inspector observed dose assessment personnel performing dose
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calculations utilizing the dose assessment computer.
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(Closed) Deficiency (482/8704-03):
The access code number for placing
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telephone calls to state and local agencies was not initially available to
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the Technical Support Center (TSC) communicator, thus causing confusion
and a slight delay in making the required initial notification from the
TSC.
The licensee had established a facility telephone directory.
The
,
telephone directory contained access codes for each facility and other
appropriate information.
(Closed) Deficiency (482/8704-04):
The Duty Emergency Manager (DEM)
delayed making protective action recommendations after plant conditions
(e.g., clad failure and core uncovering at 9:59 a.m.; 3.5 percent
concentration of hydrogen in the containment at 10:30 a.m.; continuous
pressure buildup in.the containment building; large LOCA and loss of
coolant inventory) warranted it. The DEM postponed making protective
action recommendations for the public at risk, even after the NRC
emergency response team informed him that in their opinion general
emergency conditions were present (10:23 a.m.).
The decision for
sheltering personnel within the center zone was not recommended by the DEM
until 11:10 a.m.
At that time, the county decided for evacuation of human
populations at the center zone.
The DEM made a timely classification at the general emergency.
The
accompanying protective action recommendations to the state and county
were timely.
(Closed) Deficiency (482/8704-05):
During the exercise, the EOF
experienced a temporary loss of the telephone system.
Communicators in
the EOF had not received hands-on training in the use of the radio.
That
lack of hands-on radio training prevented the communicators from using the
backup radio communications for making offsite notifications to the state.
The telephone service was restored in a matter of minutes and the offsite
notifications were made within the 15-minute requirement.
If the event
had been a lasting telephone system failure, notifications could have been
substantially delayed.
The NRC inspector observed during the exercise that E0F communicators did
establish radio contact with the county.
The communicators demonstrated
the capability to properly use the radio communication system. A review
of training records revealed that personnel were given hands-on training
in the use of the radios.
No violations or deviations were identified.
3.
Program Areas Inspected
The following program areas were inspected.
Unless otherwise noted, the
inspection was completed and revealed no violations, deviations,
deficiencies, unresolved items, or open items.
The inspection included
interviews with cognizant individuals, observations of activities, and
record reviews.
The depth and scope of these activities were consistent
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with past findings and with the current status of the facility.
Notations
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after a specific inspection item are used to identify the following:
I = item not inspected or only partially inspected; V = violation;
D = deviation; H = deficiency; U = unresolved item; O = open item.
Procedure
Program Area and Inspection Requirements
82201
Emergency Detection and Classification
021 - Adequacy of EALs in site emergency plan and
procedures.
(I)
022 - Initial offsite notification procedures based on EALs.
Procedures for recommending protective actions for
onsite nonessential personnel.
023 - State and local agency agreement with EALs.
(I)
024 - Emergency event classification.
025 - Use of post-TMI indicators for core and containment
status.
(I)
026 - One individual onsite at all times understands
authority and responsibility to classify events and
initiate emergency actions.
027 - Emergency Operating, Alarm, or Abnormal Occurrence
Procedures direct the user to classify emergencies.
(I)
028 - EALs consistent with appropriate control room
instrumentation.
Decisional aids readily available and consistent with
EALs.
029 - Shift supervisors and other responsible personnel
promptly and correctly classify events.
(I)
02202
Protection Action and Decision Making
021 - Authority and responsibility clearly and unambiguously
assigned.
02i
Authority and responsibility for making protective
action decisions are in procedures and understood by
licensee personnel.
023 - Emergency response facilities can implement onsite and
offsite protective measures.
024 - Understanding of relationships between plant
conditions, offsite consequences, and effectiveness of
protective measures.
025 - Offsite officials have the capability to make prompt
public notifications and protective action decisions
in 15 minutes.
(I)
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82301
Evaluation of Exercises for Power Reactors
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(1) Control Room (D)
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(3) Emergency Operations Facility
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(4) Operational Support Center
(5) Corporate Command Center (H0EC) (I)
(6) Offsite Monitoring Team (I)
(7) Corrective Action / Rescue Team
(8) Security / Accountability Team
(9) Press Center (I)
(10) Medical Team (1)
(11) Postaccident Sampling (I)
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4.
Control Room (Emergency Classification) 82301 (1)
The NRC inspector noted that several EALs relating to fuel breach were
exceeded, but the control room staff classified the event as an unusual
event.
EALs exceeded included:
CVCS letdown radiation monitor off scale high,
containment air monitor (s) increased significantly,
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area radiation monitors increased significantly, and
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sampling data verified existence of failed fuel (five times Technical
Specification limits).
Based on the observation above, the following is considered to be an
emergency preparedness deficiency:
Classification of the emergency was incorrect, considering the plant
parameters and radiological conditions given to the operators.
(482/8721-01)
5.
Exercise Critique
The NRC inspector attended the post-exercise critique by the licensee
staff on September 3, 1987, to evaluate the licensee's identification of
deficiencies and weaknesses as required by 10 CFR 50.54(q),
10 CFR 50.47(b)(14), and 10 CFR Part 50, Appendix E, paragraph IV.F.5.
The licensee staff identified the deficiencies listed below.
No violations or deviations were identified.
Licensee Identified Deficiencies
Reliability of dose assessment computer needs to be increased. '
Media representatives need additional training.
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Review news release information flow from Wichita to Topeka,
especially for fast occurring events.
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Review core damage methodology, need additional method.
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Correct cause of'telecopier. problems.in Wichita and the plant.
Corrective action for identified deficiencies-and-weaknesses will be
examined during a futu're NRC inspection.
No violations or. deviations were identified.
6.
Exit Interview
=The NRC inspector met with licensee representatives (denoted,in
paragraph 1) at the conclusion of the in'spection'on September.4,'1987.
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The. inspectors summarized the purpose and the scope of the inspection and
the findings.
The NRC team' leader. reviewed the' deficiency with
Mr. B. D. Withers and staff and stated that the findings.would be' reviewed
by NRC Region-IV management.
Any substantive changes to the findings
would be brought to the attention of appropriate licensee representatives..
- The licensee's actions during the' exercise were found to be acceptable to
protect the health and safety of the public.
No' violations or deviations were identified.
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