ML20059A125
| ML20059A125 | |
| Person / Time | |
|---|---|
| Site: | 07000824 |
| Issue date: | 10/14/1993 |
| From: | Kasnicki D, Mcalpine E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20059A112 | List: |
| References | |
| 70-0824-93-04, 70-824-93-4, NUDOCS 9310260226 | |
| Download: ML20059A125 (5) | |
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UNITED STATES
- p n;%~J NUCLEAR REGULATORY COMMISSION
,j REGloN ll Q;
9 101 MARIETTA STREET, N.W., SUfTE 2300 15 j
ATLANTA, GEORGIA 30323-0199
^ Report No.: 70-824/93-04 Licensee: Babcock and Wilcox Company
- n Lynchburg Research Center Lynchburg, VA 24505 Docket No.: 70-824 License Nos.:
SNM-778 Y
- Facility Name:
Lynchburg Technology Center Inspe:: tion Conducted: September 13-17,IJ97
' Inspector: %
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QS D. Kasnickperfaci ties Inspector Ddte Sighed Approved by:
bM ab
/0[IV[93 E. McAlpine, ' Chief -
1 Date Signed
' Radiation Safety Projects Section Nuclear Materials Safety and Safeguards Branch Division of Radiation Safety and Safegu'ards E
SUMMARY
Scope:
This routine, announced inspection.was conducted in the areas of Nuclear
' Criticality Safety 'and Fire Protection. The inspection focused on the
' programmatic aspects of Lynchburg Technology Center's Nuclear Criticality Safety and Fire Protection programs as well as addressing previously l
identified Nuclear Criticality-Safety issues.
Results:
In the areas inspected, violations or deviations were not identified.
Currently, the. Lynchburg Technology Center has no. license conditions which
' address Fire Protection or are otherwise related to the NRC's Branch Technical D
Position on fire Protection. The Lynchburg Technology Center Nuclear
-Criticality Safety and Fire Protection programs appeared to be adequately implemented and the previously identified Nuclear Criticality Safety issues had.been partially addressed with the remainder remaining open.
No
-observations were made of any circumstances or conditions which would preclude or.otherwise hinder safety.
i 9310260226 931014-PDR-ADOCK 07000824'
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REPORT DETAILS r
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- 1.
Persons Contacted Licensee Employees
- C, Boyd, Jr.,' Licensing and Compliance Officer
- P. Rosenthal, Environment, Safety and Health Manager T. Whitaker, Health Physicist 5
- Attended exit interview on September 17, 1993 2.
. Unusual Nuclear Criticality Safety (NCS) Incidents-(88005, 88015, 88020)
Discussion with an Lynchburg Technology Center (LTC) representative indicated that there had been no unusual incidents of a criticality safety nature during.the past year.
.There were no violations of regulatory requirements noted in this area.
3.
Safety Review Committee Meetings (88005)
Section 2.3 of the' license application _ establishes the Safety Review Committee (SRC) and specific. requirements associated therewith.
The
. inspector reviewed the minutes of SRC meetings dated March'27, 1992, June 15, 1992, September 10, 191'2, November 3, 1992, February 4, 1993, April 6, 1993, May 24, 1993, anc August 20, 1993 and determined that the meetings were held at the required frequency with the required quorum present, and that the agenda for items reviewed were in accordance with the charter.. The minutes were informative and indicative of meeting the intent of the corresponding license condition.
There were.no violations of regulatory requirements noted in this area.
4.
Quarterly NCS Audits (88005, 88015, 88020, 88025)
I Section 2.8.1 of the license application establishes the requirement for quarterly NCS audits. The inspector reviewed the Nuclear Safety t-Officer's quarterly' audit reports for all_ four quarters of 1992 and the
~
first and second quarters of 1993.
These quarterly audits reports revealed that no significant NCS problems;or concerns had been observed.-
The audit reports appeared to adequately meet the intent of the license condition.
There were no violations of regulatory requirements noted in this area.
t-2 5.
Criticality Alarm System Calibration (88025)
Section 3.2.3.4 of the license application establishes requirements associated with LTC's Criticality Monitoring System.
The inspector reviewed the calibration records for the NMC criticality alarm monitors i
and the NMC neutron criticality detectors and verified that the units were calibrated semi-annually meeting the license condition requirement.
There were no violations of regulatory requirements noted in this area.
6.
Training (88010) j Section 2.6 of the license application establishes safety training and specific requirements associated therewith. The inspector was given i
Radiation Protection Training Level 1 to obtain escorted access to controlled areas and unescorted access to restricted areas. The content of this training and the other level training programs were discussed 1
with the trainer and the programs appeared to be adequate.
There were no violations of regulatory requirements noted in this area.
7.
Action of Previous NCS Inspection Findings During a previous inspection documented in NRC Inspection Report No. 70-824/91-03, the following items were identified as NCS issues which LTC management agreed to address:
IFI 91-03-01:
LTC management to initiate Double Contingency Analyses for fuel handling operations.
IFI 91-03-02:
CHA Pool:
LTC to evaluate strength of administrative control to maintain 12-inch spacing.
IFI 91-03-03: CHA Pool: LTC to evaluate reactivity of 2 assemblies at various enrichments.
IFI 91-03-04: CHA Pool:
LTC to evaluate accident scenario involving end-dropped assembly.
During a subsequent inspection documented in NRC Inspection Report No.
70-824/92-01, the inspector learned that LTC management had initiated these Double Contingency Analyses through the use of the NNFD NCS Engineering department; accordingly, IFI 91-03-01 is closed as this project had been initiated.
During this inspection, discussions and related documentation revealed that action on IFI 91-03-03 had been completed as NNFD NCS Engineering had employed a contractor to conduct the related reactivity calculations. The calculational results indicated that 2 assemblies at 4.05% enrichment have a k-eff of less than 0.95 with a spacing of 5 inches (in water), and that the same 2 assemblies at 5%
enrichment require 10 inches of separation to have a k-eff of less than 0.95.
This calculational result is documented in a letter and attachment from the contractor to the NNFD NCS Engineering manager dated July 29,
n 3
.1993. Accordingly, IFI 91-03-03 is closed. An LTC representative stated
-that. actions required to address IFIs 91-03-02 and 91-03-04 were in
. progress but'not yet completed, therefore these items remain open and will be followed up on during a subsequent inspection, 8.
Fire Protection (88055) a.
B&W NES/LTC had no license conditions or other commitments related to Fire Protection at the time of this inspection.
Discussions with
)
an LTC representative and a review of related documentation indicated that the LTC's Fire Protection program'was not formalized (i.e. proceduralized); efforts to formalize the program had been initiated but were not yet completed.
The facility that is now 3
known as.the LTC has undergone a few major organizational changes in the last several years: The B&W LTC was previously the B&W NNFD-RL, and-before that it was the B&W LRC. An LTC representative explained that the B&W Naval Nuclear Fuel Division (NNFD) had assumed the programmatic aspects of the Fire Protection program for the NNFD-RL.
Prior to that, the LRC had Fire Protection procedures, but they are now obsolete.
Since the last reorganization in which the NNFD-RL became the LTC, they have recognized the need to resume the programmatic aspects of their Fire Protection program by creating appropriate procedures. While LTC presently had no regulatory requirements related to a Fire Protection program, discussions with j
the cognizant LTC representative and a review of implementation j
records for their informal program indicated adequate implementation i
of essential programmatic elements.
j b.
The manager responsible or LTC's Fire Protection program is the Manager of Environment, Safety and Health. The individual responsible' for implementing the program is the Licensing and Compliance Officer.
LTC's Safety Review Committee (SRC) also serves the function of a Fire Safety Review Committee, and audit / corrective i
action programs'are served by LTC's Safety Audit Subcommittee (SAS) l and Insurer's audits.
LTC uses Hot Work Permits, and equipment 4
maintenance and testing checklists for sprinkler systems, water supply valves, fire extinguishers, and automatic sprinkler alarms.
The B&W NNFD Emergency Response Team (ERT) still serves as the Fire Brigade for LTC.
LTC has a Pre-Fire Plan which was created when i
they were still organizationally part of NNFD as NNFD-RL; this plan is still functional for LTC. The inspector did not detect deficiencies in the Pre-Fire Plan. The inspector reviewed the equipment maintenance and testing checklist records and the most recent Insurer's audit report with LTC responses, all of which appeared adequate. A tour of the facility with an LTC 3
representative revealed no observed Fire Protection deficiencies.
There were no violations of regulatory requirements noted in this area.
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9.
Exit Interview The inspection scope and findings were summarized on September 17, 1993 with those persons indicated in Section 1.
The inspector described the areas inspected and discussed in detail the inspection results. Although reviewed.during this inspection, proprietary information is not contained in this report. Dissenting comments were not received from the licensee.