ML20235E869
| ML20235E869 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 09/21/1987 |
| From: | Baer R, Murray B, Scott H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20235E760 | List: |
| References | |
| 50-482-87-17, IEB-79-20, NUDOCS 8709280301 | |
| Download: ML20235E869 (7) | |
See also: IR 05000482/1987017
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= APPENDIX B
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U.S. NUCLEAR REGULATORY COMMISSION
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REGION-IV
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NRC Inspection Report:
50-482/87-17
License:
Docket:
50-482
Licensee: . Wolf Creek Nuclear Operations Corporation (WCN00)
P. O. Box 411
Burlington, Kansas
66839
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Facility Name: Wolf Creek Generating' Station (WC35)
~ Inspection At:
Inspection Conducted:
August 17-21, 1987-
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Inspectors:
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T/O/[7
R. E. Baer, Madiation Specialist, Facilities
Date
Radiological Protection Section
W&1W Y
W/7N7
I[ L. Scott (/ Radiation Specialist, facilities
Date
Radiological Protection Section
Approved:
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5711Grray, Chicif, Facil %ies Radiological
D'irte
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Protection Section /
Inspection Summary
Inspection Conducted August 17-21, 1987 (Report 50-482/87-17)
Areas Inspected:
Rectine, unannounced inspection of the radiation protection
program including organization and management controls, training and
qualifications, and the ALARA program.
Results: Within the areas inspected, two violations (failure to provide
retraining, paragraph 7; and failure to maintain training records, paragraph 8)
were identified.
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DETAILS
1.
Persons Contacted
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- G. D. Boyer, Plant' Manager
- H. M. Davis, Health Physics (HP) Supervisor
- T. F. Deddens Jr. , Manager, Outage
- A. A. Freitag, Manager, Nuclear Plant Engineering
- E. C. Holman, HP Supervisor
J. M. Isom, HP Technician
- C. F. Kesinger, Training Program Coordinator (HP)
- W. M. Lindsay, Supervisor, Quality Systems
'*0. L. Maynard, Manager, Licensing
G. A. McClelland, Quality Assurance (QA) Auditor
- J. F. McMahon, Supervisor, Technical Training
- C. M. Medenciy, Supervisor, Radioactive Waste
T. S. Morrill, Site Health Physicist
T. G. Moreau, Radiation Protection Training Instructor-
- W. L. Mutz, Manager, Nuclear Plant Engineering Services
- M. M. Nichols, Superintendent, Plant Support
- D. K. Parks, Training Program Coordinator, General Employee / Radiation
Protection Training
- G. J. Pendergrass, Licensing Engineer
- W. J. Rudolph II, Manager, QA
- M. G. Williams, Superintendent, Regulatory, Quality and Administration
- J. A. Zell, Manager, Nuclear Training
NRC
- B. L. Bartlett, Resident Inspector
J. E. Cummins, Senior Resident Inspector
- Denotes those individuals present during the exit interview conducted on
August 21, 1987.
The NRC inspectors also interviewed several other licensee employees
including administrative, HP, and chemistry personnel.
2.
Inspector Observations
The following are observations the NRC inspectors discussed with the
licensee during the exit interview on August 21, 1987.
These observations
are not violations, deviations, unresolved items, or open items.
These
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observations were identified for licensee consideration for program
improvement, but the observations have no specific regulatory requirement.
The licensee stated that the observations would be reviewed.
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I A Auditor Trainin'a.
Q
a.:
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QA auditors conducting'au'dits of HP activities have not received.
HP technical training in the areas:they are responsible,for auditing.
b.
QA Technical Reference File
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'Apnlicable HP. technical reference material'is not maintained by QA.
atdit personnel responsible for auditi.ng HP activities,
c.
Dos'imetry Clerk Training
Afformal; training program has not been' established for dosimetry
clerks responsible for issuance of thermoluminescent dosimeters (TLD)
and performing whole body counts.
.d .
Dosimetry Records Quality Control Program
'A quality control program has not been established,for dosimetry data
being entered into the dosimetry computer records system,
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e.
Preventative Maintenance Request (PMR) ALARA Review
The ALARA group.had not received the PMR work packages for the
' October 1987 refueling outage in order to allow adequate time.for
proper ALARA reviews.
f.
Mockup' Training
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Training department radiation protection instructors. had not been
considt. red for attendance in.the steam generator jumper training
Course,
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Training of Instructors
Training department instructors responsible for conducting radiation
protection training had not received HP technical training in order
to maintain proficiency in their assigned discipline.
3.
Open Items
The NRC inspector discussed the following open item with the licensee
during the exit interview on August 21, 1987.
Open items are matters that
require. turther review and. evaluation by the NRC inspector or licensee.
Open: items are used to docimient, track, and ensure adequate followup on
matters of concern to the NRC inspector.
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.(0 pen) Open Item (482/8717 03):
Health Physics Staff Trai..ing - The NRC
inspectors-determined that there is no formal, organized training program
for health physics supervisors and professionals that addresses goals,
objectives, and training frequency.
This is consider (d an gpen item
pending. licensee action (482/8717-03)
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4.
P_regram Areas Inspected
The following program areas were inspected.
Unless otherwise noted, the
inspection was completed and revealed no violations, deviations, unresolved
items, or open items.
Notations after a specific inspection item are used
to identify the following:
I = item not inspected or only partially
inspected; V = violation; D = deviation; U = unresolved item; and 0 = open
item.
Procedure
, Inspection Requirements
83522
Organization and Management Controls (Radiation Protection)
02.01 - Organization, Responsibilities, and Authorities
02.02 - Staffing
02.03 - Identification and Correction of Weaknesses
02.04 - Audits and Appraisals
02.05 - Communication to Employees
02.06 - Documentation and Implementation
83722
Organization and Management Controls (Radiation Protection)
02.01 - Organization
02.02 - Staffing
02.03 - Radiation Protection Manager
02.04 - Identification and Correction of Program Weaknesses
02.05 - Audits and Appraisals
83523
Training and Qualifications (Radiation Protection)
02.01 - Training and Qualification Program - 0 (see
paragraph 3)
02.02 - Education and Experience
02.03 - Adequacy and Quality of Training - V (see
paragraph 8)
83723
Training And Qualifications (Radiation Protection)
02.01 - Adequacy of Training
02.02 - Employee Knowledge
02.03 - Transportation /Radwaste Training - V (see
paragraph 7)
02.04 - Qualification Requirements
02.05 - New Employees
02.06
INP0 Accreditation
02.07 - Audits and Appraisais
02.C3 - Training not Covered by INP0
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83528
02.01 - Managcment Policy
02.02 - Assignment of Responsibilities and Authorities
02.03 - Procedures and Standards
02.04 - Indoctrination and Instruction
02.05 - Reviews of Design and Equipment Selection
83728
-ALARA-
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02.01 - Audits and Appraisals
02.02 - Program Changes
02.03 - Worker Awareness and Involvement
02.04 - Goals and Objectives
02.05
-Results and Effectiveness
5.
Occupational Ext'sure Expenditures
Table 1 (attached) shows the licensee's person-rem expended versus the
national average for pressurized water reactors for 1984-1986.
Table 2 (attached) identifies the jobs that involved more than 5 person-rem
for the period June 1986 through July 1987.
6.
. Disposal of Sewage Sludge
The NRC inspectors reviewed the licensee's procedures for the removal of
sewage sludge from the ensite waste treatment plant.
The NRC inspectors
determined that the licensee transfers the sewage sludge to a holding tank
truck where a gamma isotope analysis is performed of a representative
sample prior to offsite disposal.
7.
Radioactive Waste Supervisor Retraining
The NRC inspectors reviewed the training and retrainir.g of the individual
recently assigned to the position of HP Ry;ioactive Waste Supervisor.
Inspection and Enforcement Bulletin (IEB) No. 79-20 requires that licensees
who generate low-level waste for burial provide training and periodic
retraining in the DOT and NRC regulatory requirements, the waste burial
license requirements, and licensee instructions and operating procedures
for all personnel involved in the transfer, packaging, and transport of
radioactive material.
The licensee is also required to maintain a record
of training dates, attendees, and subject material for future inspections
by NRC personnel.
The NRC inspectors reviewed the training / retraining records of the HP
Radioactive Waste Supervisor.
The NRC inspectors determined the individual
had not received the periodic retraining specified in IEB No. 79-20 in that
the previous retraining was last conducted in March 1984.
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The failure to provide periodic, retraining ~is considered an apparent
violation ' f IEB No. ' 79-20 (482/8717-01).
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8.
Training Records
The NRC inspectors,rev.iewed-training records of licensee employees'.
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- Technical Specification 6.10.2 states, in part, that records'of. training
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.and qualification for current members of the unit staff.shall be' retrained
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for the duration of the unit operating license.
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The NRC inspectors reviewed the training department' training records.for
'10 current licensee radiation protection' staff. employees.
The-NRC:
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inspectors-determined that records for two. employees were not complete.
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-The ALARA coordinator records did not include a vendor ALARA training
program' completed in September 1986, and the HP Radioactive Waste
~ Supervisor training records did not include any training completed prior to
. January'1986.-
The failure to maintain: complete training records-for current staff is
considered an apparent.. violation of Technical Specification 6.10.2
<(482/8717-02). .
9.
Exit Interview-
lThe NRC' inspectors met with the personnel identified in paragraph 1 at the
conclusion of the inspection ~on August 22, 1987. The NRC inspectors
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summarized the scope.and findings of the inspection.
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- ATTACHMENT NO. 1
Table 1
' Person-Rem Expended
Year.
1984
1985'
1986
-1987
'PWR Average
552.0.
416.0
392.0
Not Available
Wolf Creek
Under Construction
7.2
142.0
6.0 (1/1 -
8/19/87)
. Table 2
Jobs That Exceeded 5 Person-Rem For 1986-87
Job Description
Person-Rem
a.
Health Physics Containment Access at Shutdown
17.110
b.
Reactor Vessel Head Removal / Replacement
14.406
c.
General Access to Non-Specific RWP Areas of the RCA
9.232
d.
Routine Access / Maintenance Inside Containment at Shutdown
6.199
e.
Testing of Mechanical Snubbers
5.320
f.
Removal and Reinsta11ation of Reactor Head Components
5.311
g.
Repack Isolation Valves
5.138
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