IR 05000445/1989080
| ML19332F041 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 11/24/1989 |
| From: | Murray B, Ricketson L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19332F025 | List: |
| References | |
| 50-445-89-80, 50-446-89-80, NUDOCS 8912130311 | |
| Download: ML19332F041 (6) | |
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' APPENDIX j
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- U.S. NUCLEAR REGULATORY COMMISSION
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REGION IV
b NRC: Inspection Report:
50-445/89-80 Construction Permit:
CPPR-126-50-446/89-80 CPPR-127
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50-445.
Docket:
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50-446-Licensee: -TU Electric-h-Skyway Tower.
400 North Olive, L.B. 81
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Dallas, Texas :75201 p
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- Facility.Name:. Comanche Peak Steam Electric Station (CPSES)
m s-Inspection'At:
CPSES, Glen Rose, Somerville County, Texas r-Inspection Conductedi October 23-27, 1989 f
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' Inspector:
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/& TD-PP L. T.
'ckption,\\P.E.,- Radiation Specialist Date Facili i{Mdiolhical~ Protection Section H
Approved:'
T h Murray, Chief,-Facil(ties Radiological Date
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Protection Section'
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Inspection Summary
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Inspection Conducted October 23-27, 1989 (Report 50-445/89-80; 50-446/89-80)
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Areas Inspected:
Routine, unannounced inspection of the applicant's radiation j
protection-(RP.) program including organization and management controls,
.i training and qualifications, external exposure controls, internal exposure
controls, control of radioactive materials and contamination, and facilities
. and equipment.
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Results: Within the areas inspected, no violations or deviations were
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- identified. The applicant's RP program was fully staffed and appeared to be ready for operations.
The RP management possessed sufficient operational experience and technicians have been adequately trained.
This coupled with the
- applicant's commitment to bolster the operational e;perience of the technicians with contract personnel should be adequate for startup operations.
Management appeared attentive to NRC concerns, addressing them in a timely manner.
8912130311 091201 PDR ADOCK 05000445 PNV
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- -Technical: issues l appeared to be understood and dealt with likewise.
Due.in
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part-to the-generous development time, adequate RP procedures were in place _for all expected operations.
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DETAILS
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1.
Persons Contacted
- A. B. Scott, Vice President Nuclear Operations
- E.'J. Schmitt, Radiation Protection Manager
- J. C. Hicks, Licensing Compliance Manager
- D. M. McAfee,. Quality Assurance Manager
- D. E. Deviney, Deputy Director, QA
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R. J. Prince, Assistant RP Manager
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J. R. Curtis, RP Supervisor R. E. Fishencord, RP Supervisor A. H. Redlow, RP supervisor G. D. Jones, RP Supervisor S. E. Bradley, Engineering Senior-C. L. Mansfield, Engineer D. C. Kay, Senior Engineer (Corporate RP)
- J. R. Waters, Licensing Engineer NRC R. F..Warnick, Assistant Director for Inspection Programs, CPPD, NRR
- S. D. Bitter, Resident Inspector, Operations I
s-Other-
- E. F. Ottney, Program Manager, Citizens Association for Sound Energy (CASE)
- 0. L. Thero, CASE
- Denotes those present during the exit meeting on October 27, 1989.
2.
Action on Previous Inspection Findings r
(Closed) Open Item 445/8333-07; 446/8317-57:
Iodine Monitors - This item was most recently discussed in NRC Inspection Report 50-445/89-77; 50-446/89-77-and involved several items to improve the operation of the portable iodine monitors..The inspector verified that iodine monitors, specially codified with a beacon and a stripchart recorder were available in the Technical Support Center (TSC), the Operations Support Center (OSC), and.the Logistical Support Center (LSC).
Applicant representatives stated that there was also a fourth unit which is used as Em a substitute whenever an instrument is returned from the field for calibration.
During the applicant's demonstration of the use of the instrument in the TSC, the inspector noted that the counting instrument, the sampling pump, and the stripchart drive mechanism all had separate power cords.
A copying machine was in use next to the iodine monitor leaving only one electrical outlet for the three items needing electrical power.
A multiple outlet extension cord was secured and the iodine monitor functioned properly.
The applicant's representatives stated that i
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the extension cord would_be permanently mounted to the cart supporting the
- iodine monitor and that similar remedies would be effected in the OSC and the LSC.
The inspector also noted that the applicant had made provisions
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for adding the alarm setpoint on the monitor data sheets RPI-920-1 and
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RPI-920-2, for the reference.
The applicant's actions appear adequate to
address the NRC's concerns in regard to this item.
e (Closed) Open Item 445/8929-04; 446/8929-04:
Solid Radwaste System - This item was discussed in NRC Inspection Report 50-445/89-29; 50-446/89-29 and-involved:
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The need for modi 1ying the resin transfer system to maintain the resins in a slurry.during transfers, b.
the lack of means of collecting a sample of the resins being transferred for testing, c.
NRC approval.of the radwaste process control program (PCP).
l The inspector verified that the resin transfer system has been modified by li making cross connections to the sluice supply headers, thereby keeping the resins intrained in a slurry and preventing their settlement in the manifolds.
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The inspector also verified that a sampling tube has been installed-to
. take a sample ~ from the. flow.
Testing demonstrated that the technique delivered a representative sample throughout the transferring process.
Chemistry will be responsible for the sampling, working under a radiation work permit.
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The applicant's PCP has been approved by the Office of Nuclear Reactor
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l Regulation (NRR). The-inspector noted that the current program includes ll provisions for dewatering of waste, but not (cement) solidification.
(0 pen) Open Item 445/8929-06; 446/8929-06:
Radiation Monitoring - This item was discussed in NRC Inspection Report 50-445/89-29; 50-446/89-29 and involved the steps necessary to ready the Digital Radiation Monitoring System (DRMS) for use.
Specifically, they were:
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Completion of all calibrations L
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Completion of functional testing of all instruments s
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Finalizing of DRMS setpoints and establishment of administrative
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controls of the DRMS i
The' inspector verified that all instruments were calibrated and functional testing was completed in October 1989.
The system was turned over to Operations following functional testing.
The applicant discovered that the high voltage setting on the liquid monitors affected the lower limit of detection more than originally thought, so that these monitors wern recalibrated.
All monitors were calibrated by October 27, 1989.
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-5-Final-selection of setpoints can not be completed unti1= engineering
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finishes.it operational calculations, In all other regards, the
applicant's' actions appear to be adequate.to address the NRC's' concerns.
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' However, this item will remain open, pending the final selection of the i
setpoints prior to initial criticality.
(Closed) Open Item 445/8942-01; 446/8942-01:
Hot Particle Identification and~ Control Program - This item was previously discussed in NRC inspection Report 50-445/89-42; 50-446/89-42 and involved the lack of such a program
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by the applicant.
This item has been addressed in Procedures RPI-613,
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" Hot Particle Contamination Control," and STA-654, " Personnel and Hot l
Particle Contamination' Control." The inspector reviewed both procedures and found them adequate to address-the NRC's concerns.
(0 pen) Open Item 445/8942-03; 446/8942-03:
Instrumentation and
Operability - This item was discussed in NRC Inspection Report 50-445/89-42; 50-446/89-42 and involved the applicant's need to calibrate-l and' place high sensitivity contamination monitors and portal contamination-i monitors at the appropriate locations.
The inspector noted that the applicant had six high sensitivity personnel
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. contamination monitors immediately available.
All were in current
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calibration.
Three were in access control, two were in the laundry room
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awaiting placement, and a sixth was in the hot tool room.
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number ~of the units used at the exit to the radiological controlled area will depend on the traffic flow.
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Portal monitors have not yet been calibrated and the applicant's-plan
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remains that these are-to be calibrated and put in use at least 2 weeks l
prior to initial criticality.
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L The applicant's actions with respect to the high sensitivity personnel J
contamination. monitors appears adequate to address the NRC's concerns; j
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however, this item will remain open with respect to the calibration and
. placement of the portal monitors at the primary and alternate access points.
(Closed) Open Item 445/8942-04; 446/8942-04:
ALARA Personnel Involvement in the Work Control Organization - This item was previously discussed in NRC Inspection Report 50-445/89-42; 50/446/89-42 and involved the lack of involvement of ALARA personnel in the early stage of work planning and -
scheduling.
The applicant responded to this item by assigning an ALARA
representative to work in the maintenance planning area.
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reviews incoming work requests from the various organizations and, if
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appropriate, drafts an RWP to accompany the work order.
When the work is scheduled by the work control group, another individual, assigned on a rotating basis from RP's surveillance and control group, reviews the draft RWP and updates the survey information, if necessary.
The inspector i
reviewed Procedures RPI-606, " Radiation Work and General Access Permits,"
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STA-656, " Radiation Work Control," and STA-657, ALARA Job t
Planning / Debriefing," related to-this item.
The applicant's_ actions-
appear to be adequate to address the NRC's concerns with regard to this
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item.
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(Closed) Open Item 445/8950-01; 446/0950-01:
Skin Dose Calculations -
This item was previously discussed in NRC Inspection Report 50-445/89-50;
'50-446/89-50, and involved the lack of a proceduralized method to calculate skin doses to individuals immersed in noble gas atmosphere.
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response, the-applicant has revised (Revision 3) RPI-506, which is now titled, '! Calculation and Tracking of Personnel Exposure to Airborne Radioactive Material, to include such a method.
The inspector reviewed
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the procedure and found that it adequately addressed the NRC's concerns in
regard to this item.
3.
Radwaste Storage Section 11.4 of the Final Safety Analysis Report (FSAR), states that there j
will be storage capacity for at least 144'- 55 gallon drums.
Applicant-representatives confirmed that there was space in the fuel i)uilding, but
that it was not planned that this space would be utilized for drums.
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is currently the applicant'.s plan to survey bags of trash and place
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contaminated waste into one container and clean trash in another.
The contaminated trash will be shipped to a vendor's facility for segregation-
and/or compaction, before ultimate deposal by burial.
The clean trash
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will be taken to an onsite landfill.
Larger containers of dewatered waste
'will be stored outdoors in temporary, transportable concrete structures.
No violations or deviations were identified.
4.
Transportation
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Most of the applicant's transportation activities will be handled by
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The applicant will employ vendors to package and ship l
contaminated items which will become waste (se paragraph 3) and dewatered l>
waste. _The applicant (radwaste personnel) will handle the preparation for
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. transportation of contaminated items such as reactor components.
QA will perform surveillances of all radioactive materials shipments.
No plans have been made for the eventual ~ shipment of spent fuel.
The inspector verified that the applicant has an approved QA program for transportation activities, current copies of applicable transportation regulations, and' procedures for transportation of radioactive materials.
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No violations or deviations were identified.
5.
Exit Meeting The inspector met with the NRC resident inspector and applicant i
representatives denoted in paragraph 1 on October 27, 1989, and summarized
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i the scope and findings of the inspection as presented in this report.
The applicant did not identify as proprietary, any of the materials provided to or reviewed by the inspector during the inspection.
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