ML20217F056
| ML20217F056 | |
| Person / Time | |
|---|---|
| Site: | 07000036 |
| Issue date: | 09/30/1999 |
| From: | ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY |
| To: | |
| Shared Package | |
| ML20217F042 | List: |
| References | |
| NUDOCS 9910200184 | |
| Download: ML20217F056 (4) | |
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i Enclosure I to RA99/138 CRITICALITY SAFETY PROGRAM UPDA FE -
EIGHTH STATUS REPORT April 1999 - September 1999 ABB COMBUSTION ENGINEERING NUCLEAR POWER, INC.
October 8,1999 9910200184 991008 PDR ADOCK 07000036; C
PDR h
I.
' INTRODUCTION This report is the eighth 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, the sixth on September 30,1998, and the seventh on April 7,1999. Since the milestones for the remainder of the program were less frequent, it was agreed that subsequent status reports be submitted semiannually.
II.
ADMINISTRATIVE UPDATE STATUS Status: Plan elements described under this heading are complete. Progress reports 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.
1 2.
Centralize Document Control Status: Complete. Additional documentation resulting from the CSPU will be added when generated and approved.
IV.
LICENSE UPDATE l.
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 responses to questions and a further revision of Chapter 4, was submitted on January 30,1998 and approved by the NRC on July 23,1998.
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On June 11, 1998 ABB CENP provided a letter committing to further revise definitions in Chapter 4 by the end of 1999. However, the pending promulgation of revisions tol0CFR Part 70 and the accompanying standard review plan will both have substa ntial impact on the terminology defined in this chapter. Additionally some type of conforming amendment will be required to make the currently approved license consistent with the new rule. Therefore, to allow for the most eflicient use of resources, we do not
- intend to make further revisions to chapter 4 until required by changes to the part 70 rule.
Status: Initial commitment complete.
I V.
TRAINING Continued training and retraining were provided to operators in the area of Nuclear Criticality Safety.
VI.
SELF ASSESSMENT PROGRAM Status: Plan elements described under th;; heading are complete.
1 VII.
ANALYSIS UPDATE j
1.
Recycle / Recovery At this time, the various systems design bases, criticality safety analyses, and system criticality safety evaluations are complete. The technical team assessment ponion of the Integrated Safety Analysis was completed using the HAZOP methodology, the initial report and risk ranking of the results
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has. also been completed with comments to the initial report being addressed.
In addition, the Process and Instrumentation Diagrams (P&ID's), component drawings and layout drawings have been verified in regard to criticality safety.
Status: Analytical assessment of the Recycle Recovery area and the documented results are complete. The comments on the initial report of the IS A are currently being addressed.
2.
Pellet Plant Front End 2
2 Focus is now shined to the front end of the pelletizing process. Similar to
-evaluations 1of previous ' areas.of the plant, this region of the plant is receiving review of the associated drawings, analysis of the components,
- and evaluation ~ of the criticality safety measures.
Unlike the previous areas addressed as pan of the CSPU program, the systems contained in the front end of the pellet plant are operated under moderr 4 control.
Therefore, explicit three dimensional KENO Va modehnb and calculational determination of the system behavior is not
'. considered necessary to demonstrate the. safety basis, rather in depth evaluation (s) of the methods and mechanisms ensuring robust moderation controls are more appropriate.
To date effort has focussed on the component drawings and evaluation of the necessary process flow information with the criticality safety evaluations expected to be completed in January 2000.
Statur.: At this point, progress on the pellet plant area is approximately
._15% complete. Focus has been on understanding the system, verification of the component drawings, and analysis of the bulk storage hoppers.
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SUMMARY
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The criticality safety analysis for. the Recycle Recovery areas of the plant has been completed and the Integrated Safety Analysis is complete with comments j
' on the initial report currently being addressed. As scheduled, the focus has now
' shined to the criticality analysis update of the front end of the pelletizing process.
The expected completion date for the front end of the pellet plant is January 2000.L j
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