ML20205M112
| ML20205M112 | |
| Person / Time | |
|---|---|
| Site: | 07000036 |
| Issue date: | 03/31/1999 |
| From: | ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY |
| To: | |
| Shared Package | |
| ML20205M110 | List: |
| References | |
| NUDOCS 9904150111 | |
| Download: ML20205M112 (8) | |
Text
.
1 Enclo'sure 1 to RA99/070 CRITICALITY SAFETY PROGRAM UPDATE SEVENTH STATUS REPORT October 1998-March 1999 COMBUSTION ENGINEERING,INC.
1 April 7,1999 4
99041501,1 990407 7 PDR ADOCK 07000036 C
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I.
INTRODUCTION This report is the seventh periodic status report on the progress made in implementation of the CSPU plan. The first quarterly progress report was submitted on December 20,1996, the second on March 27,1997, the third on June 27,1997, the fourth on September 30,1997, the fifth on March 31,1998, and the sixth on September 30,1998. Since the milestones for the remainder of the program were less frequent, it was agreed that subsequent status reports be submitted umiannually.
II.
ADMINISTRATIVE UPDATE STATUS Status: Plan elements described under this heading r.e complete. Progress repotts will continue to be submitted semi-annually.
III.
CONFIGURATION CONTROL STATUS 1.
Revise Change Management Process Status: Plan elements described under this heading are complete.
2.
Centralize Document Control Status: Complete. Additional documentation resulting from the CSPU will be added when generated and approved.
IV.
LICENSE UPDATE 1.
Revise chapter 4 of SNM-33 Chapter 4 of SNM-33, Nuclear Criticality Safety was revised to incorporate applicable portions of the CSPU.- Typographical errors were corrected and license conditions reworded to clarify their meaning. An amended Chapter 4 was submitted to NRC Licensing on April 17,1997.
NRC responded with a request for additional information on November 3, 1997. The additional information, including recponses to questions and a further revised version of Chapter 4, was submitted on January 30,1998 and approved by the NRC on July 23,1998. CE committed to further revise definitions in Chapter 4 by the end of 1999.
Status: Initial commitment complete.
I
l V.
TRAINING Continued training and retraining was provided to operators in the area of
' Nuclear Critiality Safety. The training included safe movement and storage of material, the requirements of the NRC license, and internal procedures. The program of short, topical criticality safety training on a weekly or biweekly schedule has continued, however the regularity has been reduced from weekly or bi-weekly to an as needed basis. The training subject is generally chosen from in-plant observations by regslatory affairs personnel.
VI.
SELF ASSESSMENT PROGRAM Statm: Plan elemen.s described under his heading are complete.
VII.
ANALYSIS UPDATE i.
1.
Recycle / Recovery As stated in the preceding semi-annual report, the progress of the CSPU pmgram concerning the Recycle Recovery area was behind schedule.
Increased attention and the addition of resources have significantly advanced the analytical safety assessment of this area of the plant.
At this time, the various systems design bases, criticality safety analyses, and system criticality safety evaluat:ons have been complete and are receiving independent review. The technical team assessment portion of the Integrated Safety Analysis has been completed using the IIAZOP methodology with the final report and risk ranking of the results still in process.
The Process and Instrumentation Diagrams (P&lD's), component drawings and layout drawings have been verified in regard to criticality safety and a2 a result of the recently completed Integrated Safety Analysis are undergoing minor revision.
Status: Analytical assessment of the Recycle Recovery area is complete and undergoing in lependent review of the data and documentation.
The independent review process is expected to be completed in May 1999.
2 L
w.
2.
Pellet Plant Front End Focus is now shifted to the front end of the pelletizing process. - Similar to the previous areas of the plant evaluated, this region of the plant is
. expected to receive review of the associated. drawings, analysis of the components, and evaluation of the criticality safety measures.
To date effort has focussed on the' component drawings and evaluation of:
the necessary process flow information with the criticality safety analyses -
and evaluations expected to be completed in September 1999.
1.
Status: At this point, prog s on the pellet plant area is approximately 15% complete and has been h. :ted to the component drawings.
VIII.
SUMMARY
Significant advancement was made in the area of Recycle Recovery with final results pending independent review and satisfactory closure of items raised by such review. Frequent on-shift training of operators continues. As scheduled, the focus has now shifted to the criticality analysis update of the front end of the c
pelletizing process. Consistent with the attached Gantt chart, and NRC approved schedule, the expected completion date for the front end of the pellet plant is October 8,1999.
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